ML20024A196
| ML20024A196 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 05/16/1983 |
| From: | LONG ISLAND LIGHTING CO. |
| To: | |
| Shared Package | |
| ML20024A188 | List: |
| References | |
| PROC-830516-01, NUDOCS 8306160091 | |
| Download: ML20024A196 (1000) | |
Text
{{#Wiki_filter:____.__a._..-~m_.~..'...._...... O EMERGENCY PREPAREDNESS SIGNOFF FORM To: Holder, Manual No. Shoreham Wclear Power Station Emergency Plans an ementation Procedures From: Emergency Planning Coordinator
Subject:
REVISION TRANSMITTAL t Attached is Revision No. A o the Shoreham Wclear Power Station Emergency Plan and Implementation Procedures for insertion into your Controlled Copy No./o# . Two copies of this memorandum have been provided. Once you have complied with the instructions presented below, sign one copy and place it in front of your controlled copy of the Manual. Sign the se:ond copy of the memorandum and return it within seven (7) working days to: Emergency Preparedness Coordinator G LILCO 175 East 01d Country Road Hicksville, NY 11801 The undersigned acknowledges completion of the following actions: 1
- 1. The receipt and incorporation of Revision No.
dated in Controlled Copy No. of the Shoreham Nuclear Power Station Emergency Plan and Implementation Procedures.
- 2. Destruction of all pages which have been superseded by the revision.
i Signature Date 1 O 8306160091 830609 Rev. O PDR ADOCK 05000322 3/6/83 F PDR
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EPIP 1-0 CLASSIFICATION OF EMERGENCY ACTION LEVELS EPIP 1-1 UNUSUAL EVENT EPIP 1-2 ALERT , EPIP 1-3 SITE AREA EMERGENCY EPIP 1-4 GENEPAL EMERGENCY EPIP 1-5 , NOTIFICATIONS , EPIP 1-6 EVACUATIONS
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EPIP 1-7 PERSONNEL ACCOUNTABILITY EPIP 1-8 SEARCH FOR MISSING PERSONS EPIP 1-9 TECHNICAL SUPPORT CENTER (TSC) ACTIVATION EPIP 1-10I OPELATIOhALFUPPORTCENTER(OSC) ACTIVATION EPIP 1-11 OPERAT{0NALASSESSMENT f _ EPIP 1-12 ' EMERGENCYREPNIRANDCORRECTIVEACTIONS J EPIP 1-13 EMERGENCY RADWASTE OPERATIONS . c EPIP 1-14 CORE DAMAGE ESTIMATE P EPIP 1-15 SECURITY DURING EMERGENCIES EPIP 1-16 , OPERATIONAL SUPPORT CENTER (OSC) COORDINATION EPI? 2-1 RADIOLOGICAL ASSESSMENT EPIP 2-2 DOSE PROJECTIONS EPIP 2-3 PROTECTIVE ACTION RECOMMENDATIGHS~ a , EPl?s2-4 INPLANT SURVE','S 1 F. PIP,2-S s ONSJTE4 SURVEYS i '. s 1 ,
',JP P 1-6 ' -
0FFSITE SURVEYS' EPIP 2-7 POST-ACCIDENT GAS EFFLUENT SAMPLING EPIP 2-8 POST-ACCIDENT GAS EFFLUENT SAMPLE ANALYSIS EPIP 2-9 POST-ACCIDENT PRIMARY COOLANT SAMPLING EPIP 2-10 POST-ACCIDENT PRIMARY COOLANT SAMPLE ANALYSIS O Rev. 0
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a EPIP 2-11 POST-ACCIDENT CONTAINMENT AIR SAMPLING j EPIP 2-12 POST-ACCIDENT CONTAINMENT AIR SAMPLE ANALYSIS EPIP 2-13 POST-ACCIDENT LIQUID EFFLUENT SAMPLING EPIP 2-14 POST-ACCIDENT EFFLUENT SAMPLE ANALYSIS EPIP 2-15 ENVIRONMENTAL ASSESSMENT EPIP 2-16 RADIATION PROTECTION DURING EMERGENCIES 5 PIP 2-17 THYROID BLOCKING EPIP 2-18 VEHICLE MONITORING s EPIP 2-19 VEHICLE DECONTAMINATION I EPIP 2-10 PERSONNEL MONITORING / PERSONNEL DECONTAMINATION EPIP 2-23 PLANNED CONTAINHENT RELEASE DURING EMERGENCIES EI EPIP 2-24 THYROID DOSE COMMITMENT USING TSC AIR SAMPLER l EPIP 2-25 DETERMINATION OF PASS SAMPLE LOCATION k L EPIP 2-26 NATIONAL LAB SAMPLE CASK TRANSPORTATION
, EPIP 3- EMERGENCY OPERATIONS FACILITY ACTIVATION a
it 5 EPIP 3-2 SUPPORT CORPORATE HEADQUARTERS EPIP 3-3 RE-ENTRY EPIP 3-4 RECOVERY EPIP 3-5 DOCUMENTATION AND RECORDKEEPING EPIP 3-6 CORPORATE NOTIFICATIONS EPIP 4-1 PUBLIC INFORMATION FOR UNUSUAL EVENT f, EPIP 4-2 PUBLIC INFORMATION FOR ALERT [ EPIP 4-3 PUBLIC INFORMATION FOR SITE AREA / GENERAL EMERGENCY
- EPIP 4-4 RUMOR CONTROL i
- EPIP 4-5 PUBLIC AFFAIRS NOTIFICATIONS 4 EPIP 4-6 EMERGENCY NEWS CENTER ACTIVATION EPIP 4-7 PUBLIC AFFAIRS EMERGENCY ORGANIZATION 4
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4 ; EPIP 5-1 EMERGENCY PREPAREDNESS IMPLEMENTING PROCEDURE DEVELOPMENT EPIP 5-2 EMERGENCY PREPAREDNESS PLAN AND EMERGENCY PREPAREDNESS l IMPLEMENTING PROCEDURE REVIEW, REVISION, AND DISTRIBUTION EPIP 5-3 EMERGENCY FACILITIES AND EQUIPMENT INVENTORY OPERATIONAL CHECKS 4 EPIP 5-4 EMERGENCY PREPAREDNESS PROGRAM TRAINING EPIP 5-5 CONDUCT OF EMERGENCY DRILLS AND EXERCISES EPIP 5-7 EMERGENCY ORGANIZATION EPIP 5-8 COMMUNICATIONS TESTS d 4 ?'
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I I l I i t I I t F e i lO L ( Rev. O I 3/6/83
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EPC dr EPIP l-1 Approved: Page 1 of 7 Plant Manager / O Effective Date[5/16/83 COBiTROLLO COPY # of l l EPIP l-1 UNUSUAL EVEllT 1.0 PURPOSE To provide instructions for implementing a response to an Unusual Event. ~ 2.0 RESPONSIBILITY The Emergency Director is responsible for implementing this procedure. 3.0 PRECAUTIONS 3.1 The following actions may not be delegated: 3.1.1 Classification of Emergency 3.1. 2 Directing the notification of offsite officials 4.0 PREREQUISITES 4.1 An Unusual Event has been determined in accordance with EPIP l-0, Event Classification. l l l Rev. 0 3/4/83
EPIP l-1 Page 2 of 7 O 5.0 ACTIONS 5.1 Inform Control Roou personnel that you have assumed duties as the Emergency Director ano have declared an Unusual Event. 1 I l CAUTION I I I I ONCE AN EERGENCY HAS BEEN DECLARED, YOU i l MUST NOTIFY STATE AND COUNTY OFFICIALS, VIA l ' l THE NEW YORK STATE RADIOLOGICAL EMERGENCY l I COMUNICATIONS SYSTEM, WITHIN 15 MINUTES. I i I I
- 5.2 Log your actions in the Watch En3 neer/
1 Emergency Director l Log Book and file completed Event Classification record sheets in tne tabbea section. 5.3 Direct a Plant Operator to make the following announcement l over the page/porty system:
" Attention all personnel. Attention all personnel. An Unusual Event has been declared.
All members of the on-shift emergency response crew report to the Control Room. All other j personnel remain at your present location and await further instructions." 5.4 Direct the Shift Technical Advisor (STA) to implement EPIP l-11, Operational Assessment in consultation with a licensed operator. O Rev. 0 3/4/83 i
EPIP l-1
- Page 3 of 7 .D\
V 5.5 Contact the Shift Security Supervisor and direct him to implement EPIP l-15, Security During Emergencies. 5.6 Direct a communicator to implement EPIP l-5, Notifications
- (plant personnel).
5.7 Direct the on-shif t Health Pnysics Technic 1. n to act as the Radiological Assessment Coordinator (RAC), and direct him to implement EPIP Z-1, Radiological Assessiaent. i 5.8 Complete a Radiological Emergency Data Form Part I . ( Attachment 1). 5.9 Give the completed Radiological Emergency Data Fona Part I to the Communicator and instruct him to notify offsite dyencies in accordance with EPIP l-6, Notifications. 5.10 Confer with the Watch Supervisor, RAC, and STA, and: 5.10.1 Review the Operational Assessment and Radiological Assessment Data sheets in EPIPs 1-5, Notifica-tions, and 2-1, Radiological Assessment, respectively. 5.10.2 Detennine wnether any plant conoitions have changed or may potentially change. If so, reclassity event in accordance with EPIP 1-D, Event Classification. 5.10,3 Determine wnether any repairs and/or corrective actions are necessary. If so, implement EPIC 1-12, Emergency Repair and Corrective Actions. D U Rev. 0 3/4/83
EPIP l-1 Page 4 of 7 f3 L) - 5.10.4 Direct a Itcensed operator to contact the NRC using tiie Emergency Notification System (ENS) (NRC red phone) and relay information using the Operational Assessment Data Sheet as a guide. I l l CAUTION l l l l ONCE A LICENSED OPERATOR HAS ESTAB- l l LISHED CONTACT WITH THE NRC VIA THE l l ENS, HE WILL BE EXPECTED TO MAINTAIN 1 l CONTINUOUS CONT?.CT. IF THE ASSIS- 1 l TANCE OF THE LICENSED OPERATOR IS l l NECESSARY FOR THE SAFE OPERATION OF 1 l THE PLANT, HE MAY REQUEST TO DROP 1 1 0FF THE ENS LINE PROVIDED A CALL l l BACK SCHEDULE HAS BEEN ESTABLISHED l l WITH THE NRC DUTY OFFICER. l . l l 5.11 Verify that the communicator has completed all required initial notifications. 5.12 Verify that the NRC has been notified via ENS. j 5.13 Verify triat the HAC has completed Part II Raoiolo91 cal i Assessment Data Sheet in EPIP 2-1, Radiological Assessment. 5.14 Review Part Il Raaiologicdl Assessment Data Sheet, approve, and give completed Data Sheet to communicator and instruct him to relay information to offsite agencies as a followup to the initial notifications. O-Rev. 0 3/4/03
EPIP l-1 Page 5 of 7 O 5.15 As emergency conditions stabilize, consider re-entry in accordance with EPIP 3-3, Re-Entry, as a preliminary to ; recovery operations. 5.16 When re-entry has been performed or is near completion, evaluate ability to enter recovery moda per EPIP 3-4, Recovery.
6.0 REFERENCES
6.1 EPIP l-0, Event Classification 6.2 EPIP l-5, Notifications 6.3 EPIP l-ll, Operational Assessment 6.4 EPIP l-12, Emergency Repair and Corrective Actions 6.5 EPIP l-15, Security During Emergencies 6.6 EPIP 2-1, Radiological Assessment u 6.7 EPIP 2-2, Dose Projections 6.8 EPIP 2-3, Protective Action Recommendations 6.9 EPIP 3-3, Re-Entry 6.10 EPIP 3-4, Recovery 7.0 ATTACHMENTS
- 1. New York State Radiological Dnergency Data Form Part I - General Information Part II - Radiological Assessment Data i
I l V Rev. 0 3/4/83 l 1 - - _
EPIP 1,1 Page 6 of 7 Attachment 1 A Page 1 of 2 (.) New York State Radiological Emergency Data Form PART I - GENERAL INFORMATION l
- 1. Message transmitted at: 8. There has:
Time A NOT been a release of radio-Date activity. Via h been a release of radio-
- 2. Facility providing informations activity to the ATMCSPHEPI.
t-l"A Indian Point Unit No. 2 been a release of redio-l I
=
B Indian Point Unit No. 3 activity to a BODY OF WATER.
=
C Ginna Station 0 been a GRO*JND SPII.I. release
=
D Nine Mile Point Unit No. 1 of radioactivity. lMl E Fit 2 Patrick Plant l 9 Ihe release is [ Shoreham Station i continuing.
@ Other * - terminated.
i
- 3. Reported by: C l intermittent.
Name D NOT applicable. Title
- 10. Protective Actions:
Phone lif given) h There is NO need for Protective Actions outside the site bound-
- 4. This ... A is ... an exercise.
[j] ary.
'\ .@isNOT * * ** * "" *
$. Emergency Classification # ^*
Unusual Event '# " *" * # '# ** ^* ' ""* g Alert Shelter within miles /or g Site Area Emergency dj General Emergency sectors /or ERPA's. d) Transportation Incident Evacuate within miles /or F Other
- 6. This classification declared at sectors /or ERPA's.
Date Time
- 11. Weather:
- 7. e D scription/Initiat- A Wind speed miles per hour or meters per second.
degrees. h Direction (from)
@ Stability class unstable, (A-G/or stable, neutral)
D General Weather condition fif available), f Message received by Rev. 0 3/4/83
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, EPIP l-1 i Page 7 of 7 Attachment 1 Pace 2 of 2 4 , \s ,<
PART II - RADIOLOGICAL ASSESSME:IT DATA
. 12. Prognosis for Worsening or. Termination of the Emergency: ,1 -
- 13. In~ Plant Emergency Response Actions Underway:
l 14. ' Utility off-site Emergency Response Action Underway I 15. Release Information A ATMOSPHERIC RELEASE Actual P roj ected 1 Date and Time Release Started Duration of Release hrs hrs Noble Gas Release Rete Ci/sec C1/sec Radiciodine Release Rate Ci/sec Ci/sec Elevated or Ground Release Inplant Monitors 4 8 ~ WATERBORNE REI. EASE - Date and Time Release Started Duration of Release hrs hrs .; Volume of Release gal gal Radioactivity Concentration (gross) uCi/ml uCi/ml Total Radioactivity Released Ci Ci Radionuclides in Release uCi/ml uCi/ml uCi/mi uCi/ml p '/'. Basis for release data e.g. effluent monitors, grab sample, 7 2 ( composite sample and sample location: i 16. Dose and Measurements and Pro $ections A - SITE BOUNDARY Actual l Proieeted f Whole Body Dose Rate mR mR/hr 3 Whole Body Commitment (for duration t above) Rem
-Thyroid Dose Commitment (1 hour exposure) mrem mrem Thyroid Dose (total commitment) Rem B PROJECTED OFFSITE
. 2 Miles 5 Miles 10 Miles Whole Body Dose Rate (mR/hr) Whole Body Dose (Rem)
- Thyroid Dose Commitment (1 hr Exposure - mrem)
Thyroid Dose l, (Total Commitment - Rem)
- 17. Protective Action Recommendations and the Basis for the Recommenda-tions:
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EPC A: EPIP l-2 Appr ved: , Page 1 of 8 fect ae 5/16/83 CONIi10lLE] COPY #_,,p EPIP l-2 ALERT 1.0 PURPOSE To provide instructions for implementing the response to an Al ert. 2.0 RESPONSIBILITY The Emergency Director is responsible for implementing this procedure. 3.0 PRECAUTIONS
~J 3.1 Although certain of the steps in this procedure will have been implemented previously, the steps shall be repeated.
3.2 The following actions may not be delegated: 3.2.1 Classification of the emergency l l 3.2.2 Directing the notification of offsite officials l l l 3.2.3 Making protective action recommendations to offsite emergency management agencies 4.0 PREREQUISITES 4.1 An Alert has been determined in accordance with EPIP 1-0, Event Classification. Rev. 0 3/4/83 m
EPIP l-2 Page 2 of 8 V 5.0 ACTIONS J 5.1 Infonn Control Room personnel that you have assumed duties as the Emergency Director and have declared an Al e rt. l l l CAUTION I I i l ONCE AN EERGENCY HAS BEEN DECLARED, YOU i l MUST NOTIFY STATE AND COUNTY OFFICIALS, VIA l l THE NEW YORK STATE RADIOLOGICAL EMERGENCY l l COMUNICATIONS SYSTEM, WITHIN 15 MINUTES. I I I 5.2 Los your actions in the Waten En ineer/ u Emergency Director Log Book and file completed Event Classification record sneets in the tabbed section. 5.3 Direct a Plant Operator to make the following announcement over the page/ party system:
" Attention all personnel. Attention all personnel. An Alert has been declared. All members of the on-shif t emergency response crew report to the Control Room. All other personnel remain at your present location and await further instructions."
5.4 Direct the Shif t Technical Advisor (STA)/ Core Evaluation Coordinator to implement EPIP l-11, Operational Assessment in consultation with a licensed operator. Rev. 0 3/4/83
EPIP l-2 Page 3 of 8 5.5 Contact the Shif t Security Supervisor and direct him to
~
implement EPIP 1-15, Security During Emergencies. 5.6 Direct a communicator to implement EFIP l-5, Notifications (plant personnel). 5.7 Direct the on-shift Health Physics Technician to act as the Radiological Assessment Coordinator (RAC), and direct him to implement EPIP 2-1, Radiological Assessment. 5.8 Complete a Radiological Emergency Data Form Part I ( Attachment 1). 5.9 Give the corapleted Radiological Emergency Data Form Part I to the Communicator and instruct him to notify offsite
. /7 agencies in accordance with EPIP l-5, Notifications.
() 5.10 Confer with the Watch Supervisor, RAC, and STA, and: 5.10.1 Review the Operational Assessment and Radiological Assessment Data sheets in EPIPs 1-5, Notifica-tions, and 2-1, Radiological Assessment, respectively. 5.10.2 Determine whether any plant conditions have changed or may potentially change. If so, reclassify event in accordance with EPIP l-0, I Event Classification. 5.10.3 Determine whether any repairs and/or corrective actions are necessary. If so, implement EPIP l-12, Emergency Repair and Corrective Actions. A U Rev. 0 3/4/83
EPIP l-2 Page 4 of 8 O 5.10.4 Direct a licensed operator to contact the NRC using trie Emergency Notification System (ENS) (NkC red phone) and relay infonnation using the Operational Assessment Data Sheet as a guide. I I l CAUTION 1 I l l ONCE A LICENSED OPERATOR HAS ESTAB- 1 l LISHED CONTACT WITH THE NRC VIA THE I l ENS, HE WILL BE EXPECTED TO MAINTAIN 1 l CONTINUOUS CONTACT. IF THE ASSIS- l l TANCE OF THE LICENSED OPERATOR IS I i NECESSARY FOR THE SAFE OPERATION OF l l THE PLANT HE MAY REQUEST TO DROP l 1 0FF THE ENS LINE PROVIDED A CALL I i BACK SCHEDULE HAS BEEN ESTABLISHED l l WITH THE NRC DUTY OFFICER. l l l O 5.11 Verify that the communicator has completed all required initial notifications. 5.12 Verify that the NRC has been notified via ENS. 5.13 Verify that the RAC has completed Part II Radiological Assessment Data Sheet in EPIP 2-1. 5.14 Review Part II Radiological Assessment Data Sneet, approve, and give completed Data Sheet to communicator and instruct him to relay information to offsite agencies as a followup to the initial notifications. 5.15 Verify that the Technical Support Center (TSC) is Deing activated in accordance with EPIP l-9, TSC Activation. a Rev. 0 3/4/83
EPIP l-2 Page 5 of 8 5.16 Verify that the Operations Support Center (OSC) is being activated in accordance with EPIP l-10, OSC Activation. 5.17 Evaluate the need for evacuation of personnel from onsite areas by reviewing the Prerequisites contained in EPIP l-6, Evacuations. 5.18 Continually evaluate the need to recommend offsite protective actions based on plant and/or radiological conditions in accordance with EPIP 2-3, Protective Action Recommendations. 5.19 As emergency conditions stabilize, consider re-entry in accordance with EPIP 3-3, Re-Entry, as a preliminary to recovery operations. 5.20 When re-entry has been performed or is near completion, evaluate ability to enter recovery mode per EPIP 3-4, Recovery.
6.0 REFERENCES
6.1 EPIP l-0, Event Classification 6.2 EPIP l-5, Notifications 6.3 EPIP l-6, Evacuations 6.4 EPIP l-ll, Operational Assessment , 6.5 EPIP l-12, Emergency Repair and Corrective Actions 6.6 EPIP l-15, Security During Emergencies 6.7 EPIP 2-1, Radiological Assessment 6.8 EPIP 2-2, Dose Projections 6.9 EPIP 2-3, Protective Action Recommendations 6.10 EPIP 3-3, Re-Entry 6.11 EPIP 3-4, Recovery C Rev. 0 3/4/83
_ -- ._ .. - .. .. . =. . - _ . EPIP l-2 1 Page 6 of 8 7.0 ATTACHENTS
- 1. New York State Radiological Emergency Data Fona Part I - General Infonnation Part II - Radiological Assessment i
r i lO 1 f a Rev. 0 l 3/4/83
EPIP 1-2 Page 7 of 8 i Attachment 1 Page 1 of 2 p New York State
- Radiological Emergency Data Form PART I - GENERAL INFO *UG. TION I
- 1. Message transmitted at: 8. There has Date Time A NOT been a release of radio-via activity. -
B been a release of radio-
- 2. - Facility providing informations activity to the ATMOSPHERE.
.l Indian Point Unit No. 2 O C been a release of radio-i B Indian Point Unit No. 3 activity to a BODY OF "ATER.
b "*
- D been a GROUND SPILL release
! D l - Nine Mile Point Unit No.1
== of radioactivity.
4 E l FitzPatrick Plant lh Shoreham Station 9 1.h.e release is: continuing. [ Other s&m g' terminated. 3
- 3. Reported by.
IL intermittent. I D NOT applicable. Title
, Phone 10. Protective Acticns:
(if given) A There is NO need for Protective
- 4. This.... A is ... an exercise. Actions outside the site bound-7 ary.
B is NOT B Protective Actions are under f v/ $. - Emergency Classification consideration. g Unusual Event C Recommended Protective Actions: g Alert Shelter within miles /or j g Site Area Emergency (g General Emergency 1l Transportation Incident sectors /or ERPA's. Evacuate wit.hin miles /or I
@ Other
- 6. This classification declared at sectors /or ERPA's.
i Date Time I 11. Weathers
- 7. Brief Event Description /Initiat-A Wind speed miles per hour ing Condition:
or meters per second. degrees. [
@ Direction (from) c Stability class (A-G/or stable, unstable, neutral)
- D General Weather Condition (if available),
Message received by ( Rev. 0 l O- -. *- 3/4/83
EPIP 1-2 Page 8 of 8 Attachment 1 Page 2 of 2 s PART II - RADIOLCGICAL ASSESSMENT DAPA 12. Prognosis for Worsening or Termination of the Emergency:
- 13. In Plant Emergency' Response Actions Underway:
- 14. Utility Off-Site Emergency Response Action Urderway:
- 15. Release Information A ATMOSPHERIC RELEASE Actual Proieeted Date and Time Release Started Duration of Release- hrs hrs Noble Gas Release Rete Ci/see Ci/sec Radiciodine Release Rate Ci/sec Ci/sec Elevated or Ground Release Inplant Monitors
@ WATERBORNE RELEASE -
Date and Time Release-Started Duration of Release hrs hrs Volume of Release gal gal Radioactivity Concentration (gross) uCi/mi uCi/ml Total Radioactivity Released C1 Ci Radionuclides in Release uCi/ml uCi/ml
-s uCi/ml uCi/ml Basis for release data e.g. effluent monitors, grab sample, (v j 16.
composite sample and sample locations oose and Measurements and Projections A SITE BOUNDARY Actual Proiected Uhole Body Dose Rate mR mR/hr whole Body Commitment (for duration above) Rem Thyroid Cose Commitment (1 hour exposure) mrem mrem Thyroid Dose (total commitment) Rem
@ PROJECTID OFFSITE 2 Miles 5 Miles 10 Miles Whole Body Dose Rate (mR/hr)
Whole Body Dose (Rem) Thyroid Dose Commitment (1 hr Exposure - mrem) Thyroid Dose (Total Commitment - Rem) 17. Protective tions: Action Recommendations and the Basis for the Recommenda-x Rev. 0 3/4/83
EPC A . M~ EPIP l-3 Approved: , Page 1 of 8 Plant Manager / O Effective Date 5/16/83 i 0 t 0 {Qf}' *4(= te EPIP l-3 SITE AREA EMERGENCY 1.0 PURPOSE To provide instructions for implementing the response to a Site Area Emergency. 2.0 RESPONSIBILITY The Emergency Director or the Response Manager is responsible for implementing this procedure. 3.0 PRECAUTIONS 3.1 Although certain of tne steps in tnis procedure will have been implemented previously, the steps shall be repeated. 3.2 The following actions may not De delegated: 3.2.1 Classification of the emergency 3.2.2 Directing the' notification of offsite officials 3.2.3 Making protective action recomr.dations to offsite emergency mar 3ement agencies 4.0 PREREQUISITES i 4.1 A Site Area Emergency nas been deterrained in accordance with EPIP l-0, Event Classification. V Rev. 0 3/4/83
EPIP l-3 Page 2 of 8 O 5.0 ACTIONS , 5.1 Inform Control Roou personnel that you have assumed duties as the Emergency Director and have declared a Site Area Emergency. 4 I I l CAUTION I I i i ONCE AN EE RGENCY HAS BEEN DECLARED, YOU l 1 MUST NOTIFY STATE AND COUNTY OFFICIALS, VIA i 1 THE NEW YORK STATE RADIOLOGICAL EMERGENCY I I C0lG4UNICATIONS SYSTEM, WITHIN 15 MINUTES. l l 1 5.2 Log your actions in the Emergency Director Log Book and file completed Event Classification record sheets in the tabbed section. 5.3 Check prerequisites of EPIP l-6, Evacuations, and implement EPIP l-7, Personnel Accountability, if necessary. I I l CAUTION l l l l IF EVACUATION IS NOT NECESSARY, MAKE THE l l FOLLOWING ANNOUNCEMENT: l 1 1 I " Attention all personnel. Attention all l l personnel. An Alert has been declared. All l l members of the on-shift emergency response l l crew report to the Control Room. All other 1 i personnel remain at your present location l I and await further instructions." l I l O o : Rev. 0 3/4/83
EPIP l-3 Page 3 of 8 5.4 Utrect the Shift Technical Advisor (STA)/ Core Evaluation Coordinator to implement EPIP l-11, Operational Assess-ment, in consultation with a licensed operator. 5.5 Contact the Shif t Security Supervisor n'id' direct him to implement EPIP l-15, Security During Emergencies. 5.6 Direct a communicator to implement EPIP l-o, Notifications (plant personnel). 5.7 Direct the on-shif t Healtn Physics Technician to act as the Radiological Assessment Coordinator (RAC), and direct him to implement EPIP 2-1, Radiological Assessment. 1 5.8 Complete a Radiological Emergency Data Form Part I (Attachment 1). O 5.9 Give the completed Radiological Emergency Data Forir Part i I to the Communicator and instruct him to notify offsite agencies in accordance with EPIP l-6, Notifications, 5.10 Confer with the Watch Supervisor, RAC, and STA, and: 5.10.1 Review the Operational Assessuent and Radiological Assessment Data sheets in EPIPs 1-5, Notifica-tions, and 2-1, Radiological Assessment, respectively. 5.10.2 Determine whether any plant conditions have changed or may potentially change. If so, reclassity event in accordance with EPIP l-0 Event Classification. O Rev. 0 3/4/83
EPIP l-3 Page 4 of 8 O 5.10.3 Determine whether any repairs and/cr corrective actions are necessary. If so, implement EPIP 1-12, Emergency Repair and Corrective Actions. 5.10.4 Direct a licensed operdtor to contact the NRC using the Emergency Notification System (ENS) (NRC red phone) and relay information using the Operational Assessment Data Sheet as a guide. I I l CAUTION l 1 l l ONCE A LICENSED OPERATOR HAS ESTAB- l l LISHED CONTACT WITH THE NRC VIA THE 1 l ENS, HE WILL BE EXPECTED TO MAINTAIN l l CONTINU0US CONTACT. IF THE ASSIS- l l TANCE OF THE LICENSED OPERATOR IS I l NECESSARY FOR THE SAFE OPERATION OF l 3 l THE PLANT HE MAY REQUEST TO DROP l J l OFF THE ENS LINE PROVIDED A CALL 1 i BACK SCHEDULE HAS BEEN ESTABLISHED l l WITH THE NRC DUTY OFFICER. l l 1 5.11 Verify that tne communicator has completed all required l initial notifications. l 5.12 Verify that the kKC has been notified via ENS. 5.13 Verify that the RAC has completed Part II Radiological l Assessment Dato Sheet in EPIPs 2-1. [ l 5.14 Review Part II Radiological Assessment Data Sheet, approve, and give completeo Data Sheet to communicator and instruct him to relay infonnation to offsite agencies as a followup to the initial notifications. Rev. 0 3/4/83
EPIP l-3 Page 5 of 8 4 O 5.15 Verify that all personnel have been accounted for. If not, initiate EPIP l-8, Search for Missing Parsons. 5.16 Verify that the Technical Support Center (TSC) is being activated in accordance with EPIP l-9, TSC Activation. 5.17 Verify that the Operations Support Center (OSC) is being activated in accordance with EPIP l-10, OSC Activation. 5.18 Verify that the EOF is being activated in accordance with EPIP 3-1, EOF Activation. 5.19 Continually evaluate the need to recommend offsite protective actions based on plant and/or radiological conditions in accordance with EPIP 2-3, Protective Action Recommendations. O 5.20 As emergency conditions stabilize, consider re-entry in accordance with EPIP 3-3, Re-Entry, as a preliminary to recovery operations. ! 5. 21 When re-entry has been performeo or is near completion, evaluate ability to enter recovery mode per EPIP 3-4, Recove ry.
6.0 REFERENCES
6.1 EPIP l-0, Event Classification 6.2 EPIP l-5, Notifications 6.3 EPIP l-6, Evacuations l 6.4 EPIP 1-7, Accountability 6.5 EPIP l-8, Search for Missing Persons l p 6.6 EPIP 1-9, TSC Activation l V l Rev. 0 3/4/83 l . -. .. . . . - - - . . . . - . . . _ - - - -. - -. -.
^
l EPIP l-3 ; Page 6 of 8 l
! 6.7 EPIP 1-10, OSC Activation 6.8 EPIP 1-11, Operational Assessment 6.9 EPIP l-12, Emergency Repair and Corrective Actions 6.10 EPIP l-15, Security During Emergencies 6.11 EPIP 2-1, Radiological Assessment 6.12 EPIP. 2-3, Protective Action Recoimeendattoris 6.13 EPIP 3-3, Re-Entry 6.14 EPIP 3-4, Recovery 7.0 ATTACHENTS
- 1. New York State Radiological Emergency Data Fonn Part I - General Information Part II - Radiological Assessment Data O
l l i l i tO Re v. 0 3/4/83 i .__ _ .. _ _ _ _ _ _ _ .-
EPIP 1-3 Page 7 of 8 Attachment 1 Page 1 of 2.
/m\ \v] New York State Radiological Emergency Data Form PART I - GENERAL INFOPJ4ATION l'
- 1. Message transmitted at: 8. There has Date Time A NOT been a release of radio-activity.
Via
~
- 2. Facility providing informations l Indian Point Unit No. 2 l
** * **'* * ~
Indian Point Unit No. 3 activity t a B DY OF "ATER. Y Ginna Station "" ** i Nine Mile Point Unit No. 1
- FitzPatrick Plant
@ Shoreham Station 9 .The release ist
@ Other A continuing.
- 3. Reported by: k
- Name NOT applicable.
h Phone 10. Protective Actions: (11 given) A There is No need for Protective
- 4. This ... A is ... an exercise.
Actions outside the site bound-ary. (%, B is NOT B Protective Actions are under (v ) .
- 5. Emergency Classification # "" *#* "*
4 h Unusual Event C Recommended Protective Actions: g *
- 1 Site Area Emergency h General Emergency h Transportation Incident sectors /or ERPA's.
Evacuate-witnin miles /or
@ Other
- 6. This classification declared at sec ers/or ERPA's.
Date Time I
- 7. rie '
scription/Initiat- ) 11. Weather: l A Wind speed miles per hour I or meters per second. B Direction (from) degrees. i C Stability class j (A-G/or stable, unstable, i neutral) i i D General weather Condition fif available), Message received by V Rev. 0 3/4/83
EPIP 1-3 Page 8 of 8 Attachment 1 O Page 2 of 2 V PART II - RADIOLCCICAL ASSESSME !T DATA 12. Prognosis for Worsening or Termination of the Emergency:
- 13. In Plant Emergency Response Actions Underway:
- 14. Utility off-Site Emergency Resoonse Action Underway
- 15. Releasa Information A ATMOSPHERIC RELEASE Actual Proiseted Date and Time Release Started Duration of Release hrs hrs Noble Gas Release Rete Ci/Sec Ci/sec Radiciodine Release Rate Ci/sec Ci/sec Elevated or Ground Release Inplant Monitors B WATERBORNE RELEASE -
Date and Time Release Started Duration of Release hrs hrs volume of Release gal gal Radioactivity Concentration (gross) uC1/ml uCi/ml Tctal Radioactivity Released C1 Ci Radionuclides in Release uCi/ml uCi/ml n, uci/ml Basis for release data e.g. effluent monitors, grab sample, composite sample and sample location: uci/mi
- 16. Dose and Measurements and Projections A SITE BOUNDARY Actual Proieeted Whole Body Dose Rate mR Whole Body Commitment (for duration mR/hr above) Rem Thyroid Dose Commitment (1 hour exposure) mrem mrem Thyroid Dose (total commitment) Rem a PROJECTED OFFSITE 2 Miles 5 Miles 10 Miles Whole Body Dose Rate (mR/hr)
Whole Body Dose (Rem) Thyroid Dose Commitment (1 hr Exposure - mrem) Thyroid Dose (Total Commitment - Rem) 17 Protective tions: Action Recommendations and the Basis for the Recommenda-1 4 4 4 n-s_ Rev. 0 3/4/83
EPC -C - EPIP l-4 nt 59er Effective Date[ 5/16/83 CMIR0llE0 ccpy *e n EPIP 1-4 GENERAL EMERGENCY , 1.0 PURPOSE To provide instructions for implementing the response to a General Emergency. 2.0 RESPONSIBILITY The Emergency Director or the Response Manager is responsiole for implementing this procedure. 3.0 PRECAUTIONS j 3.1 Although certain of tne steps in this procedure will have been implemented previously, the steps shall be repeated. 3.2 The following actions may not be delegated: i 3.2.1 Classification of the emergency 3.2.2 Directing the notification of offsite officials 1 3.2.3 Making protective action recommendations to offsite emergency management agencies 3.3 A General Emergency requires the irFnediate consideration of predetermined protective action reconnaendations. !(
%)
Rev. 0 3/4/83
= . _ - . . _ _ . _ . ._. . _ . _ - - . . - .. _-. - - . - _ _ _ .
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EPIP l-4 Page 2 of 11 , 4 4 - g 1 4.0 PREREQUISITES > 41 A General Emergency hds been detennined in accordance with EPIP l-0, Event Classification. 1 i l ' PJ $ g 4 .g t( .. , ! 4 '/ j
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t EPIP l-4 3 - Page 3 of 11 [O 5.0 ACTIONS 5.1 Infona to Control Room personnel that you have assumed i ' duties as the Emergency Director and have declared a Gen'eral Energency. 7 l~ 1 i~, i CAUTION I I I I ONCE AN EE RGENCY HAS BEEN DECLARED, YOU l i MU5T NOTIFY STATE AND COUNTY OFFICIALS, VIA I I THE NEW YORK STATE RADIOLOGICAL EMERGENCY l l COMUNICATIONS SYSTEM, WITHIN 15 MINUTES. I I I 5.2 Log your actions in the Emergency Director Log Book and Os file completed Event Classification record sheets in the tabbed section. 5.3 Implement EPIP l-6, Evacuations, Section 5.3. Site Evacuation and EPIP l-7, Section 5.3, Accountability for Site Evacuations, iranediately. 5.4 Direct the Shift Technical Advisor (STA)/ Core Evaluation Coordinatur to implement EPIP 1-11, Operational Asst ,'? ^ in consultation with a licensed operator. 5.5 Contact the Shift Security Supervisor and direct him to implement EPIP l-15, Security During Emergencies. 5.6 Direct a coimaunicator to implement EPIP l-5, Notifications (plant personnel). b a ' p Rev. 0 3/4/83
EPIP 1-4 Page 4 of 11 5.7 Direct the on-shift Health Physics Technician to act as the Radiological Assessment Coordin0 tor (RAC), and direct him to implement EPIP 2-1, Radiological Assessment. l l l CAUTION l l 1 i FOR GENERAL EERGENCIES, THERE ARE PREDETER- l l MINED PROTECTIVE ACTION RECo mENDATIONS TO I l BE CONSIDERED BASED ON PLANT CONDITIONS. l l l 5.8 Refer to Attachment 2 and consider the need to recommend the predetennined protective actions described. 5.9 Complete a Radiological Emergency Data Form Part I (Attachment 1). 5.10 Give the completed Radiological Emergency Data Fonn Part I to the Communicator and instruct him to notify offsite agencies in accordance with EPIP l-5, Notifications. 5.11 Confer with the Watch Supervisor, RAC, and STA, and: 5.11.1 Review the operational Assessment and Radiological Assessment Data sheets in EPIPs 1-5, Notifica-tions, ano 2-1, Radiological Assessment, respectively. 5.11.2 Detenaine wnether any plant conaitions have changed or may potentially change. If so, reclassify event in accordance witn EPIP l-0, , Event Classification. Rev. 0 3/4/83
EPIP l-4 Page 5 of 11 5.11.3 Detennine whether any repairs and/or corrective actions are necessary. If so, implement EPIP 1-12. Emergency Repair and Corrective Actions. 5.11.4 Direct a licensed operator to co.itact the NRC using the Emergency Notification System (ENS) (NRC red phone) and reldy infonaation using the Operational Assessment Data Sheet as a guide. l l l CAUTION l
- ' I I I ONCE A LICENSED OPERATOR HAS ESTAB- l l LISHED CONTACT WITH THE NRC VIA THE l l ENS, HE WILL BE EXPECTED TO MAINTAIN l l CONTINUOUS CONTACT. IF THE ASSIS- l I TANCE OF THE LICENSED OPERATOR IS O
l I NECESSARY FOR THE SAFE OPERATION OF l l THE PLANT, HE MAY REQUEST TO DROP l l OFF THE ENS LINE PROVIDED A CALL l l BACK SCHEDULE HAS BEEN ESTABLISHED l l WITH THE NRC DUTY OFFICER. l I l 5.12 Verify that the communicator has completed all required initial notifications. 5.13 Verify that the NRC has been notified via ENS. 5.14 Verify that the RAC has completed Part II Radiological Assessment Data Sheet in EPIPs 2-1. 5.15 Review Part II Radiological Assessment Data Sheet, approve, and give completed Data Sheet to communicator and instruct him to relay information to offsite agencies as a followup to tne initial notifications. Rev. 0 3/4/83
4 , EPIP l-4 Page 6 of 11 5.16 Verify that all personnel have been accounted for. If not, initiate EPIP l-8, Searcn for Missing Persons. 5.17 Verify that the Technical Support Center (TSC) is being activated in accordance witn EPIP l-9, TIC Activation. 5.18 Verify that the Operations Support Center (OSC) is being activated in accordance with EPIP l-10, OSC Activation. ~ 5.19 Verify that the EOF is being activated in accordance with EPIP 3-1. EUF Activation. 5.20 Continually evaluate the need to recommend offsite ! protective actions based on plant and/or radiological conditions in accordance with EPIP 2-3, Protective Action O Reconnendations.
- 5. 21 As emergency conditions stabilize, consider re-entry in accordance with EPIP 3-3, Re-Entry, as a preliminary to recovery operations.
5.22 When re-entry has been performed or is near completion, evaluate ability to enter recovery mode per EPIP 3-4, Recovery.
6.0 REFERENCES
6.1 EPIP l-0, Event Classification 6.2 EPIP l-5, Notifications 6.3 EPIP l-6, Evacuations 6.4 EPIP l-7, Accountability p 6.5 EPIP l-8, Search for Missing Persons . d Rev. O i 3/4/83
l l' E EPIP 1-4 4 - Page 7 of 11 6.6 EPIP l-9, TSC Activation 6.7 EPIP l-10, OSC Activation 6.8 EPIP 1-11, Operational Assessment 6.9 EPIP l-12, Emergency Repair and Corrective Actions
; 6.10 EPIP l-15, Security During Emergencies
. 6.11 EPIP.2-1, Radiological Assessment 6.12 EPIP 2-3, Protective Action Recommendations 6.13 EPIP 3-3', Re-Entry 6.14 EPIP 3-4, Recovery - 7.0 ATTACINENTS )
- 1. New York State Radiological Emergency Data Form Part I - General Information Part II - Radiological Assessment Data
- 2. Predetermined Protective Action Recommendations for General Emergency Classifications
- 3. Evacuation Areas by Zones l
O Rev. 0 l 3/4/83
_,. m _. _ _ . _ _ __ . _ . ...& . EDIP 1-4 Page 8 of 11 w Attachment 1 1 , Page 1 of 2 i New York State i Radiological Emergency Data Form PART I - GENERAL INFOpy.ATION l
- l. Message transmitted at: 8. There hass j Date Time A NOT been a release of radio-Via activity.
~
- 2. Facility providing information:
Indian Point Unit No. 2
** * ** ~
g Indian Point Unit No. 3 activity to a BODY OF WATER. C , Ginna Station
**^ * ****
D Nine Mile Point Unit No. 1 I* l Fit 2 Patrick Plant l Shoreham Station 9 .T_he release is:
@ Other 'A continuing.
- 3. Reported by: I 11 intermittent.
h NOT applicable. Phone 10. Protective Actions: (if given) A There is NO need for Protective
- 4. This ... A is ... an exercise. Actions outside the site' bound-B is NOT ary.
B Protective Actions are under
- 5. - Emergency Classification consideration.
A l Unusual Event C Recormnended Protective Actions: gi Alert Shelter within miles /or I . Site Area Emergency l l General' Emergency U Transportation Incident sectors /or ERPA's. F Other Evacuate wit.hin miles /or
- 6. This classification declared at i
sectors /or ERPA's. Date Time
- 11. Weather:
- 7. Brief Event Description /Initiat-ing Condition: A Wind speed miles per hour l
j or meters per second. ! B Direction (from) degrees. C Stability class l (A-G/or stable, unstable, neutral) D General Weather Condition fit available), Message received by b V Rev. O
- 3/4/83
EPIP 1-4 Page 9 of 11 O ' Attactment 1 V Page 2 of 2 PART II - RADIOLOGICAL ASSESSMENT DATA 12. Prognosis for Worsening or Termination of the Emergency:
- 13. In Plant Emergency Response Actions Underway: ,
- 14. Utility Off-Site Emergency Response Action Underway:
- 15. Release Information A AT:20 SPHERIC RELEASE Actual Proiected Date and Time Release Started Duration of Release hrs hrs Noble Gas Release Rete Ci/sec Ci/sec Radioiodine Release Rate Ci/sec Ci/sec Elevated or Ground Release Inplant Monitors B WATERSCRNE RELEASE Date and Time Release Started Duration of Release hrs hrs volume of Release gal gal Radioactivity Concentration (gross) uCi/ml uCi/ml gg Total Radioactivity Released C1 Ci r i Radionuclides in Release uCi/ml uCi/mi
\s_,/ uCi/ml uci/ml Basis for release data e.g. effluent monitors, grab sample, composite sample and sample location:
- 16. Dose and Measurements and Proiections
( } SITE BOUNDARY Actual Proiected Whole Body Dose Rate mR Whole Body Commitment (for duration mR/hr above) Rem Thyroid Dose Commitment (1 hour exposure) m9em mrem Thyroid Dose (total commitment) Rem B PROJECTED OFFSITE I 2 Miles 5 Miles 10 Miles Whole Body Dose Rate (mR/hr)
- Whole Body Dose (Rem)
Thyroid Dose Commitment (1 hr Exposure - mrem) Thyroid Dose (Total Commitment - Rem) 17. Protective tions: Action Recommendations and the Basis for the Recommenda-l i i i l
- Rev. O 3/4/83 l
EPIP 1-4 Page 10 of 11 Attachment 2 Pa ge 1 of 1 PREDETERMINED PROTECTIVE ACTION O RECOMMENDATIONS FOR GENERAL EMERGENCY CLASSIFICATIONS 1 2 CORE CONTAINMENT PAR TO BE FAILURE FAILURE CONSIDERED COND. NO NO I 2 MILES WIND DIRECTION COND. YES NO y1 ' I n U/ 5 MILES ,,go D'*% g DIRECTION A, x LIKELY BUT f WJ R COND. YES NOT WITHIN [f ' 5 ! III 3 HOURS (% .. / [j 5 10 MILES WIND DIRECTION YES OR COND. YES WITHIN
/)
E 3 HOURS 5 10 MILES NOTE:
- 1. CORE F AILURE-RELE ASE OF FISSION PRODUCTS INTO CONT AINMENT
- 2. CONT AINMENT FAILURE-RELE ASE OF FISSION PRODUCTS INTO ATMOSPHERE EV ACU ATION y SHELTERING WIND O :gi, ,,,;;;
'!!'; AREA ,/ AREA DIRECTION TOWARD Rev. 0 3/4/83
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PROTECTIVE ACTION RECOnnENDATIONS BY ERPA FOR GENERAL CLASS!FICATION , CONDITION I CONDITION !! CONDI!!ON 111 ON0! TION IV
$ IDEGREESI 348 TO EVACUATE: ABCDEFGHI EVACUATE: ABCDEFGHIJ SHELIER: ABCDEFGHIJ H NWAR AB N KLMNORS g3 SHELTER: J KLMNORS
- 11 TO ' EVACUATE: ABCDEFGHI EVACUATE: ABCDEFGHIJ SitEiiER : ABCDEFGHIJ NNE 34 SHELTER: J .tLnN00R KLnN00R 34 TO EVACUATE: ABCDEFGH EVACUATE: ABCDEFGHIJ SHELiEE:'ABCDEFGHIJ NE EVACUATE: ABCDE KLnNQR KLMNOR 56 SHELTER: IJ
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56 TO EVACUATE: ABCDEFGH EVACUATE: ABCDEFGHIJ SHELTER: ABCDEFGHIJ ENE EVACUATE: ABCDE KLn0R
. 79 SHELTER: IJ KLMQR 79 TO ^ ' " " "'
E 101 EVACUATE: ABCDE SHELTER: HIJ ' kok ' kok > 101 TO EVACUATE: ABCDEFG EVACUATE: ABCDEFGHIJ SHE U[5$ ABCDEFGHIJ ESE *^ KQ 124 SHELTER: HIJ KQ 124 TO EVACUATE: ABCDEF EVACUATE: ABCDEFGHIJ SHE'LiEk ABCDEFGHIJ O SE ' MG MO 146 SHELTER: GHIJ 146 TO EVACUATE: ABCDEF EVACUATE: ABCDEFGHIJ sit U[R ABCDEFGHIJ " SSE '# 169 SHELTER: GHIJ > 169 TO EVACUATE: ABCDEF EVACUATE: ABCDEFGHIJ SHELiER: ABCDEFGHIJ S ggg MUAM: AB N SHELTER: GHIJ -< 191 TO EVACUATE: ABCDE
^ ^ ' " ' "
SSH 214 SHELTER: GHIJ g EVACUATE: ABCDEFJ EVACUATE: ABCDEFGHIJ SHEL1ER: ABCD& GHIJ M 214 TO '^ SW 236 SHELTER: GHI P P 236 TO EVACUATE: ABCDEFlJ EVACUATE: ABCDEFGHIJ SHEUfii'ABCDEFGHIJ g3g EVACUATE: ABCDE OS OS 258 SHELTER: GH 58 TO EVACUATE: ABCDEFlJ EVACUATE: ABCDEFGHIJ SHE'L T E R : ABCDEFGHIJ W EVACUATE: ABCDE OS OS 281 SHELTER: GH 281 TO EVACUATE: ABCDEFHIJ EVACUATE: ABCDEFGHIJ SHELYER: ABCDEFGHIJ WNW EVACUATE: ABCDE NOS NOS 303 SHELTER: G 303 TO ' " H H m>mm
' ho EVACUATE: ABCDE g ,u NW 326 SHELTER DS k .# 326 TO EVACUATE: ABCDE
' " " ' " " ' "I NNW 348 SHELTER: *-* g ~ y o <n 4 uses.cus.se
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EPC A w_ ' EPIP 1-5 an ager Effective Date .V 5/16/83 [h QOjr 44 <
'tr' EPIP l-5 NOTIFICATIONS 1.0 PURPOSE To specify the means by which notifications are to be made to station personnel for all emergency levels and to expedite the notification of selected LILC0 personnel to augment the emergency response oc?anization.
2.0 RESPONSIBILITY
; 2.1 An Equipment Operator, as assigned by the Emergency Director, is responsible for implementing this procedere. He will be assisted by one person from Security for Alert or higher classifications.
2.2 The Emergency Callers, as enlisted by the Control Room Communicator, are responsible for implementing the appropriate Caller Procedure in Attachment 11. 2.3 A licensed operator, as assigned by the Emergency Director, is responsible for notifications to the NRC. 3.0 PRECAUTIONS 3.1 Implementation of this procedure requires the specific approval of the Emergency Director. Rev. 0 4/23/83
. := .= : := = : .= == =:: . ==.= ::= :=:: - -
. . ... := :: . ::u : .:_ -
EPIP 1-5
- Page 2 of 43 3.2 Full or partial implementation of this procedure may be perfomed for lower level responses at the discretion of the Emergency Director.
3.3 The EPC will update the phone numbers in this procedure on a quarterly basis. 4.0 PREREQUISITES 4.1 An emergency has been classified in accordance with EPIP 1-0, Classification of Emergency Action Levels. 1'
; 4,2 Approval of the Emergency Director.
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l
! EPIP 1-5 Page 3 of 43 f}
p.- 5.0 ACTIONS 4 5.1 Initial Notifications I I l NOTE I I i l DURING NORMAL WORKING HOURS, ONSITE EMER- l l GENCY RESPONSE PERSONNEL ARE NOTIFIED BY l l "PA" ANNOUNCEMENT. BEEPERS / TELEPHONES WILL l l BE USED AS A BACKUP. l I l
;l 5.1.1 Communicator #1, obtain the Onsite Emergency Call
[, Checklist, Attachment 1, and the Emergency Caller k; List, Attachment 2.
;:.p/( '3 p 5.1. 2 Set up the conference bridge using the L instructions posted near the phone.
p h 5.1. 3 Referring to Onsite Emergency Call Checklist, h; Attachment 1, for ALL classes of emergency, l *< activate the Group Tone I pagers for the: ,j 1e Response Manager ] Emergency Director [ Operations Assessment Coordinator j- Radiological Assessment Coordinator
- l. k j'j Emergency Comunications Liaison l f-lI As individuals call in, infonn respondees of g a.
y . I j; current emergency classification and time declared. li: l! Rev. 0 4/23/83
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EPIP 1-5 Page 4 of 43 (b..i wu
, b. Get the names of the respondees and next to L-those names record the date, time of call, and your initials.
- c. Remain on the conference bridge until one individual has responded for each designated emergency position or 5 minutes have elapsed, whichever is shorter.
- d. If acknowledgement of a designee for an emergency position is not received within 5 minutes of paging, attempt to contact the individuals using the card dialer phone.
- e. If a designee cannot be reached by phone, i
~
contact one of the designated alternates on t the list by card dialer phone. I I
- s. CAUTION l
;* 1 I I
? 1 l FOR AN UNUSUAL EVENT, GO l } l l DIRECTLY TO STEP 5.1.8. I l i T: 5.1.4 For an ALERT, SITE AREA, or GENERAL EMERGENCY l 3 classification, activate the Group Tone II pagers 4
-j for the:
3 f Site Support Coordinator I Emergency Planning Advisor #2 Corrective Actions Coordinator 3
'y p Environmental Assessment Coordinator b Rev. O 4/23/83
; - - ._ _ _.. _ 7 , = = = .;. , _ ., . . = , . .;
EPIP 1-5
- Page 5 of 43
/ and repeat directions in Steps 5.1.3a through j
. 5.1.3e. .
5.1. 5 Refer to the Emergency Caller List, Attachment
- 2. Using the card dialer phone, contact the Gas Systems Operator (GS0). Infom him of the current emergency classification, time declared, and tell him to implement EPIP 3-6, Corporate Notifications.
5.1. 6 Af ter call back verification from the Gas Systems Operator, record the time and your initials on
; the Emergency Caller List.
L r 5.1.7 Referring to Part II of the Emergency Caller List, call from the top name down and enlist f THREE (3) individuals to act as callers.
- a. Use the following text for your notifications:
lF ): - "This is the Shoreham Nuclear Power Station. This is (your name) at phone number or (line being lV j used). A(n) (state
~
emergency class) has been declared at the f[ j site. You are emergency caller ( ) 1. ( ) 2, Ll or ( ) 3. Please initiate the appropriate 'k call out list. Upon completion of this task, j report to the TSC to act as a TSC n ' jj Communicator." R 'ti U b. Repeat the message a second time. T iffk m. Rev. O i 4/23/83 I t
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Page 6 of 43 qq l
, U l l I '
I CAUTION . -l '
, I l ; I EMERGENCY CALLERS: FOLLOW I I EMERGENCY CALLER PROCEDURE, I i
l ATTACMENT 11. l i l 1 l I4 f
- c. Record on the Emergency Caller List the time i contacted, the caller number assigned, and
- your initials next to the name of the callers
- enlisted.
- d. After call back verification from the j Faergency Callers, record the time and your initials on the Emergency Caller List.
1 I l CAUTION l I l 1 l STATE AND COUNTY NOTIFICATIONS I l ARE TO BE MADE WITHIN 15 MINUTES l
- 1 0F EMERGENCY DECLARATION. I ; I l 4
4 5.1.8 Obtain and implement the New York State /Suffolk ) County Notification Call Checklist, Attachment 6, H and the Supplementary Notification Call j Checklist, Attachment 7. } i 5.1.9 When contact is establisited, follow directions as }1 j outlined in Communications Guidelines, Attachment lf 7. 1 ,-' CT , 1, t Rev. 0 4/23/83 i l\ h ___ _ ____ _ __ _ ._ _ __
- ::::= r . n=:.===== =:T:== z= = =""'::: =' -- - . --- :N:h:t --- -.
EPIP 1-5 Page 7 of 43 1 l l CAUTION 1 I I l CALLS MADE TO OFFSITE AGENCIES BY I l USE OF COMERCIAL LINES REQUIRE I l CALL-BACK VERIFICATION SY THE AGENCY l l RECEIVING THE NOTIFICATION. l I I i NOTIFICATIONS MADE BY DEDICATED I l LINES REQUIRE NO VERIFICATID C ~ l
- I I 5.2 Message Verification by Station Personnel Emergency Response Personnel with Pagers, on being paged ,
by the connunicator: 5.2.1 Call the conference line in the Main Control Room Cy at to receive verification that an [; emergency has been declared. I'
; 5.2.2 Give your name to the communicator after i verification is received.
3 i - 5.3 NRC Notifications ]b l d i I l CAUTION l J l I } l THE CALL TO THE NRC MUST BE MADE WITHIN ONE I g}, l l (1) HOUR OF EMERGENCY DECLARATION. I I I L t. li. s ie h r 6 I l _. Rev. 0 4/23/83 i . l\
, = = -i =w ::==.=.: .u=- - - -- - :-.= .= ==.=:. := r .........==: -- EPIP 1-5 Page 8 of 43 i 5.3.1 Licensed Operator, obtain the NRC Notification Call List, Attachment 9. !
. 5.3.2 Use the ENS Hotline as the primary mode of
- communications.
5.3.3 When the NRC Duty Officer answers the ENS phone, , he will ask for infomation from the Operational Assessment Sheet. A copy of this fom is provided as Attachment 10. Use this form for guidance,.and be prepared to answer any questions asked by the NRC. 5.3.4 Record all infomation required on the NRC ', Notification Call List. l l I CAUTION l l 1
- 1 ONCE THE LICENSED OPERATOR HAS ESTAB-l
- l LISHED CONTACT WITH THE NRC, HE WILL l l BE EXPECTED TO MAINTAIN CONTINUOUS l l CONTACT. IF THE ASSISTANCE OF THE I s
l LICENSED OPERATOR IS NECESSARY FOR l
- 1 THE SAFE OPERATION OF THE PLANT HE l l MAY REQUEST TO DROP OFF THE ENS LINE l e l PROVIDED A CALL BACK SCHEDULE HAS l c, i BEEN ESTABLISHED WITH THE NRC DUTY l 1 1 0FFICER. I l I l li f
! 5.4 Follow-up Notifications 1
'f 3 Rev. 0 4/23/83
^
.m . , . . , . . .: . . . ~ a .
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.. . . . 2 =i = & - -
4
~
EPIP 1-5 Page 9 of 43 i l i l NOTE I 1 I . I UPON ACTIVATION OF THE TSC, THE NOTIFICATION I , I RESPONSIBILITIES SHIFT FROM THE CONTROL RCOM i
; 1 TO THE TSC. I I I l UPON ACTIVATION OF THE EOF, THE NOTIFICATION I
, i RESPONSIBILITIES SHIFT FROM THE TSC TO THE l l l EOF. l
- I I T
5.4.1 Emergency Director (Control Room), EPA #2 (TSC), I or EPA #1 (EUF): If the emergency is reclassified or if there are significant changes in the Radiological Emergency Data Fom and/or ) Part II - Radiological Assessment Data Fom, Ii Attachment 4, and/or Part III - Plant Parameters,
.j Attachment 5, complete a new form and hand to the Communicator for appropriate notifications.
1 i
- I,
- I l l t l CAUTION l
'l I I ll l THESE FORMS MUST BE APPROVED BY THE I t
; I EMERGENCY DIRECTOR / RESPONSE MANAGER I ii l BEFORE TRANSMISSIONS. I i! I I ?.
If ll ! !. 5.4.2 Connunicator #1/TSC Communicator / EOF Communicator: l:1 '. i If augmentation of the emergency organization is
- y f required, obtain and implement the Onsite
~
q Emergency Call Checklist and the Emergency Caller 9, List AS. NEEDED, based on the emergency classification. Follow Steps 5.1.3 to 5.1.6. f. Rev. O
- 4/23/83 r
.I i
- - - ' ~-'
, ., . .a .. ~., .,w.-a-.w%. r =.
, .K:iwsw+. u wa x ..~ =..-~~
EPIP 1-5 Page 10 of 43 G l l l CAUTION -1 I I l WHEN DECLASSIFICATION OCCURS, NOTI- l
~
l FICATIONS MUST BE DIRECTED.TO ALL i ~ l AGENCIES NUTIFIED PREVIOUSLY. I l ^ l I 5.4.3 Comunicator #1/TSC Comunicator/ EOF Communicator: Obtain and implement the New York State /Suffolk County Notification Call Checklist and the Supplementary Call Checklist. Follow Steps 5.1.7 and 5.1.8. I
- 5.5 Securing from Emergencies
}
l
! . 5.5.1 Comunicator #1/TSC Comunicator/E0F Communicator:
If an emergency has been declassified in j, accordance with EPIP l-0 Emergency I Classification, such that an UNUSUAL EVENT or NO emergency exists, notify the site response j organization and offsite agencies as directed by j the Emergency Director to secure activation. lj 5.5.2 When long-tenn recovery actions have been 3 initiated in accordance with EPIP 3-4, Recovery, a j notify offsite agencies that recovery has begun. \l n !b
6.0 REFERENCES
11
- f; 6.1 EPIP l-0, Emergency Classification i! 6.2 EPIP l-1, Unusual Event
!3 6.3 EPIP l-2, Alert 2, Rev. O i: 4/23/83 1* l \ t
; =. :a u. = = = :N::. .= == : =w. ==. = .: . T G ..l.D- a --....~ .... 1 - .
EPIP 1-5 Page 11 of 43 X Q) EPIP l-3, Site Area Emergency 6.4 6.5 EPIP l-4, General Emergency . a 6.6 EPIP 3-4, Recovery 4 4 7.0 ATTACMENTS j
- l. Onsite Emergency Call Checklist
- 2. Emergency Caller List
- 3. New York State Radiological Emergency Data Fom Part I - General Infomation i
c 4. Part II - Radiological Assessment Data
. 5. Part III - Plant Parameters
)
i .
- 6. New York State /Suffolk County Notification Call Checklist i 7. Supplementary Notification Call Checklist 5 8. Comunications Guidelines l'
( P l'
- 9. NRC Notification Call List 1.,
i 10. Operational Assessment Sheet 1, lh ((j 11. Emergency Caller Procedure d,.
'e 2
lh
+
N 3; J Rev. 0 4/23/83
^
.:.= u= =.. .:==.=;2rth: :.:.u :=. ='.= :: :. : :. ....:........ _.. : : : n i: EPIP 1-5
. Page 12 of 43
- Attachment 1 Page 1 of 1 OIISITE EERGENCY CALL DIECKLIST l . GROUP TONE #1 l TO BE ACTIVATED FOR ALL EERGENCY CLASSIFICATIONS I l
l EMERGENCY TITLE /NAME lHOME PHONE l PLANT EXT. I BEEPER lDATE/ TIME / INITIAL 51 lRESPON5E MANAGER I I I i 1 IPrimary: 1 I I I / / I I I l i I / / I ( Al ternate: l l l l / / l l 1 I I / / I l I I I I I / / l IEMERGENCY DIRECTOR l l l l l IPrimary: l l l l / / l I IAlternate: 1 I I I / / I I I I / / I I I I I 10PERATIONS A55T. C00R. I I IPrimary: 1 I I l / / l I l Alternate: l l l l / / l l l l l / / I 1 RAD. A55T. COORDINATOR I I l l l IPrimary: l l l l / / l
+, I Alternate: l l l l / / l j l l l l l / / I
,' l lEMER. CDPFl. LIAI5ON I l l l IPrimary: l l 1 I / / l l l 1 I / / I l
GROUP TONE #2 l I l ACTIVATE AT ALERT, SITE AREA, AND GENERAL EMERGENCY LEVELS l IEMERGENCY TITLE /NAME lHOME PHONElPLANT EXT.I BEEPER lDATE/ TIME / INITIAL 51 l l l l 15ITE SUPPORI COORDINATOR l l Primary: I i 1 I / / I I I Alternate: 1 I I I / / I I I I / / I I l l l l
- IEPA #2 I l IPrimary: 1 l l l / / l l
} IAlternate: I l l l / / ) l I I I l / / l l l l l l
{ ICORRECTIVE ACTIONS C00R. 1 IPrimary: l l l l / / I i I I I / / I [ l I l l l 15ITE RAD. A55T. C00R. 1 l' IPrimary: I I I I / / I I I 1 I Alternate: l l 1 / / l I I I / / 1 { l I i
- ( O) -
.- Rev. O j
- t 4/23/83 a
- i
- . 7 - . ::'. . _ .~ z: .:. ..:. =: .r. =.= . . . . . :. . . . . . . . ... ... . . .
. :: : =. .:.
EPIP l-5 Page 13 of 43 Attachment 2 Page 1 of 1 s EMERGENCY CALLER LIST I l
, I THIS. LIST TO BE IMPLEMENTED AT THE ALERT, SITE I l AREA, OR GENERAL EMERGENCY STAGES. I I I I.
l l l IVERIFICATION I ^ IGAS SYSTEMSICOMMUNICATIONS MODE:lDATE TIME INITIALSITIME/INITIALSI l OPERATOR I CARD DIALER PHONE I / / l / I l I I I I 5 . S II* $ Pr . ;
-a x5 y/ ENLIST THREE (3). cal.LERS. FILL IN REQUIREU INFORMATION ONLY ! FOR SUCCESSFULLY COMPLETED CALLS.
r i i l l l PLANT l CALLER NO.I I I WAME lHOME PHONEl EXT.lASSIGNMENTIDATE/ TIME /INITIALSI
! I i l l ! l
) I I I I l / / I ) l I I I I / / I I I I I I / / l l} l l l 1 I / / I N I I I I I / / I i) I i i I 'l I / / I l} l i I I I I
- .\
ll 1-u ll - l!: Rev. 0 4/23/83 l! lt 'I
._...= ..,,,m.._. ._. _.
y =~u--=. . . I EPIP 1-5 l l Page 14 of 43 Attachment 3 Page 1 of 1 New York State - g Radiological Emergency Data Form f PART I - CENERAL INFORMATION !
! 1. Message transmitted at: 8. There has:
Date Time h NOT been a release of radio-activity. . via
- 2. eFacility providing informations h been a release of radio-activity to the ATMOSPHEPI.
W Indian Point Unit No. 2
* ! Indian Point Unit No. 3 9 activity to a BODY OF WATER.
C Ginna Station - been a GROUND SPII.L release D Nine Mile Point Unit No. 1 of radioactivity. i FitzPatrick Plant r Shoreham Station 9* Ih.,e release is: l
,@ Other A continuing.
- 3. Reported by:
E * ****
- y,,, l Al intermittent. .
NOT applicable. Title l D Phone (10. Protective Actions: lif 91V*A) ) h There is NO need for Protective S c, Actions outside the site bound-
~) 4.This...his...anexercise. .
ary. f @isNOT '# "" * ** "* "#* "" *# i S. Emergency Classification * "" "#* ** Unusual Event amended Protective Actions: k[ g Alert C ' Site Area Emergency [ [.
@ General Emergency sectors /or ERPA's.
@ Transportation Incident miles /or 7,
r Other Evacuate within I 5 *
- 6. This classification declared at sectors /or ERPA's.
f Date Time g.
- 11. weathers
( 7. Brief Event Description /Initiat-ing Conditions b Wind speed miles per hour gj or meters per second. y degrees. f h Direction (from) h
@.Stabilityclass (A-G/or stable, unstabie, 6: neutral)
O; @ General weather Condition fit available), i
?
t Message received by
?
.['8 i ) ?
.(w.A *
,f' i
Rev. O F W
_ . , . n.-.,, .. _ .... . , ....... .... ~ .... ..-. . ... ,.,_, - , .. . l l l EPIP 1-5 Page 15 of 43 AttacNnent 4
- Page 1 of 1 l
I PART II - RADI0t0CICAL ASSESSMENT DATA
- 12. Prognosis for Worsening or Termination of the Emergency:
- 13. In Plant Emergency-Response Actions Underways.
- 14. Utility off-site Emergency Respcase Action Underway:
- 15. Release Information A ATMOSPHERIC RELEASE Actual Preiseted Date and Time Release Started .
Duration of Release hrs hrs i Noble Gas Release Rete Ci/tec Ci/sec
' Radiciodine Release Rate Ci/sec Ci/sec f
Elevated or Ground Release Inplant Monitors i i B WATERBORNE RELEASE - i g Date and Time Release bearted Duration of Release hrs hrs Volume of Release gal gal Radioactivity Concentration (gross) uC1/ml uCi/ml [,_,i. '. Total Radioactivity Released C1 Ci
. (/ ,/
Radionuclides in Release uCi/ml uCJ/ml 4 uCi/ml uCi/ml Basis for release data e.g. effluent monitors, grab sample, { composite sample and sample location: P
- 16. Dose and Measurements and Proiections A SITE BOUNDARY Actual Proieeted
'T Whole Body Dose Rate mR mR/hr [ Whole Body Commitment (for duration above) Rem R Thyroid Dose Commitment (1 hour exposure) mrem mrem i Thyroid Dose (total commitment)
- t Rem B PROJECTED OFFSITE
. z. 2 Miles 5 Miles 10 Miles ). Whole Body Dose Rate (mR/hr) } Whole Body Dose (Rem) 4 Thyroid Dose Commitment 3 (1 hr Exposure = mrem) 3 Thyroid Dose L , (Total Commitment - Rem) 6 !$ 17. Protective Action Recommendations and the Basis for the Recommenda-
- ! tions:
.$c h+ .p 'Y iY iU f.f% i [ s = lI i , 5 Rev. 0 N
= . = ::::.=..~.=:=.= :. :=. =~ - - = = = . . = . . . = . = = - . = : = u.. . . .. ......x =..~ - ~ -- )
I I I l EPIP 1-5 I Page 16 of 43 i Attachment 5 Page 1 of 1 PART III - PLMT PARMETERS , TO BE DEVELOPED ; i i G L f ?s A l, *
),
s'
'O.T l
h i r 3 I' l: . h G f l h. I, I A, u 9* ~$
- a. b.
4. e i 3 , a Rev. 0 4/23/83
- o. ~ - -, .- - .- .. - . -._
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.m ?
.;)
EPIP 1-5 ! Page 17 of 43
. Attachment 6 i
?
NEW YORK STATE /SUFFOLK COUNTY NOTIFICATION CALL CHECKLIST
- Page 1 of 1 l t l CAUTION I
i 1 AT THE ONSET OF AN EMERGENCY, NOTIFICATIONS ARE COMPLETE AS LONG AS THE N.Y. STATE AND I l i l SUFFOLK COUNTY WARNING POINTS HAVE RESPONDED. THE E0Cs WILL NOT IMMEDIATELY RESPOND. i i l l ! i THE E0Cs ACTIVATE AT THE ALERT STAGE OR HIGHER. AFTER THEY ACTIVATE. THE WARNING I } l POINTS MAY DROP OFF THE LINE. i I l I l THE N.Y. STATE SOUTHERN DISTRICT OFFICE AND N.Y. STATE RADIOLOGICAL EMERGENCY PREPARED- l I l NESS GROUP SHOULD ANSWER ONLY DURING NORMAL WORKING HOURS. C0le4UNICATIONS MODE NAME OF PERSON VERIFICATION l N.Y. STATE /SUFFOLK TIME / INITIALS PRIMARY ALTERNATE 1 ALTERNATE 2 ACCEPTING CALL TIME / INITIALS ; COUNTY ORGANIZATION i t New York State RECS Card Dialer Card Dialer
/ /
, Warning Point (s) Hotline Phone Phone ; i Suffolk County RECS
/ /
Warning Point Hotline New York State RECS Card Dialer Card Dialer Phone / / Southern District Hotline Phone Office . New York State RECS Card Dialer Card Dialer : Phone / / Radiological Emer. Hotline Phone
,i Prepa mdness Group * ;
New York State EOC RECS NAWAS Card Dialer ' Phone / / Hotline Suffolk County EOC RECS NAWAS
/
/
Hotline Rev. 0 4/23/83
n' _,,m. , , ,,_,_ , . , _ __ , , , ^
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?
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l: it e EPIP 1-5 Page 18 of 43 [ Attachment 7 t Page 1 of 5 j; SUPPLENTARY NOTIFICATIONS CALL CHECKLIST f. j: l CAUTION ! l 1 1 FOLLOW THE GUIDELINES PROVIDED. I , l CALL, AS APPROPRIATE, ANY OR ALL OF THE FOLLOWING. [, VERIFICATION TELEPHONE NUMBER L NAME OF PERSON AGENCY / MESSAGE
' ACCEPTING CALL TIME / INITIALS _ TIME / INITIALS _ .i l
IT07E: NOTIFY FOR ALL INCIDENTS Artt.CTING I !! l LONG ISLAND SOUND. b e j
/ UNITED STATES COAST GUARD
~/ i.
p Message: "This is the Shoreham Nuclear Power 4 Station. We are in a(n) (state class of emergency). ' This is (your name) at ,i phone number (516) (one
- l l being used). Please ensure that boats !!
are cleared from Long Island Sound ? within a one (1) mile radius of the g plant." i g l l l NOTE: NOTIFT FOR ALERT OR HIGHER ~ l } l CLASSIFICATIONS. it INSTITUTE OF NUCLEAR POWER OPERATIONS (INPO), 1
/ / !!
Atlanta, Georgia ' Message: "This is the Shoreham Nuclear Power Station. We are in a(n) " i (state class of emergency). This is (your name) at phone number (516) (one being used)." Give a sunenary of the situation and request assistance if necessary. Rev. O A191/01
- == '= . . - - c.. m :. . =-----------__c . , . . .
. .:.=:= : .: :nv "" 7 : c:-- ~ ~
y ,h G ;j h) t . u - _ ~j fd. v
- 4 w - .
[^ EPIP 1-5
-~ : - . -
Page 19 of 43 [
~
- -1 -' Attachment 7 SUPPLMENTARY'WOTIFICATIONS CALL CHECKLIST Page 2 of 5 (r (ceptinued)
~
r
* \
NAME OF PER3ON VERIFICATION AGENCY / MESSAGE _ TELEPHONE NUMBER [- ACCEPTING CALL- TIME / INITIALS _ TIME / INITIALS . , 1 NOTE: NDTIFY FOR ALL INCIDENTS INVD M !eGM l ! I SEVERELY CONTAMINATED /0VEREXPOSED ~ l .i l INDIVIDUALS. 'l l
),
--RA_0_IATION MANAGEMENT CORPORATION, Philadelphia, PA !,
/ /
4
.w .
t Messagei."This is the Shoreham Nuclear Power l Station. This is (your [
- ~name) at phone twmber (516) / c
-m S ' (9ne being used). 'We hate had in 4
(
~
^ accident ~on site resulting in severe . :_ ^
i 4
~
contamination / overexposure."
-~
s Request assistance as directed. Give inforn stion : s l
., as available. 1 i
l NOTE: NOTIFY FOR ALERT OR HIGHER l i l CLASSIFICATIONS. l l j - i STONE & WEBSTER EMERGE.:CY RESP 0ilSE ORGANIZATION, ; i /_ / (24-hr. Hotline) i
- Boston, Massachusetts !
s s' v ~ Telex i x -- Message: "This is the Shorehem Nuclear Power- !
~~
" t
! ~- ,' Station. ' We are in a(n) -
~
(state class of emergency)..
, c (your name) at This is ' .>
- phone nuiiber (516) (one
~ being used)."
Give a summary of the situation and request assistance if necessary.
~
j g Rev. 0 4/23/83 I
- : ;,.... ; ..~,en,~..>---~---....--.
- ~w-+~~~ -- - - - -
l I
.... s. .c ;g ? EPIP 1-5 [l Page 20 of 43 ;!
xs ", Attachment 7 SUPPLENTARY NOTIFICATIONS CALL CHECKLIST , Page 3 of 5 le i (continued) r i. 3 n. NAME OF PERSON VERIFICATION ;[ ; ACCEPTING CALL TIME / INITIALS TIME / INITIALS AGENCY / MESSAGE TELEPHONE NUMBER j'; j .; : ! ! NOTE: CALL FOR ALERT OR HIGHER CLASSIFICA- l U! != l TIONS. , j t: l I l CALLS NEED TO BE MADE ONLY DURING THE I l [! l MONTHS OF JUNE THROUGH SEPTEMBER. I !! I
/ SAINT JOSEPH'S VILLA, Shoreham, NY p-
- / .,
gt 1 ALERT Message: "This is the Shoreham Nuclear d, Power Station. This is D: (your name) at phone number i ( 51 6) ( (one being used). We are in on ALERT il Classification. Please prepare for a i possible evacuation. Standby for h further information." h SITE AREA / GENERAL EERGENCY Message: "This is the Shoreham Nuclear Power Station. ' This is (your name) at .; phone number (516) ! (one being used). We are in a SI.TE .;
~
AREA / GENERAL EMERGENCY. Please implement your evacuation plan." , i t Rev. 0 4/23/83 i
. w . % . s...... _ ,. _ . , _ _ . _ _ , . _ _ , .
f
~s c0 () ~
EPiP 1-5 g s.J - Page 21 of 43 j Attachment 7 !. Page 4 of 5 SUPPLENTARY NOTIFICATIONS CALL CHECKLIST $ (continued) f i i VERIFICATION TELEPHONE NUMBER ; NAME OF PERSON AGENCY / MESSAGE . TIME / INITIALS _ TIME / INITIALS _ ACCEPTING CALL _ l l NOTE: NOTIFT FOR ALERI OR HIGHER CLA551F1- l l CATIONS.
/ / GENERAL ELECTRIC BWR EMERGENCY SUPPORT PROGRAM (24-hr. Hotline) .
t i Message: "This is the Shoreham Nuclear Power 4 Station. We are in a(n) l (state class of emergency).
- This is (your name) at
- '
l phone number (516) (one 'j , i being.used)." .
\ Give a summary of the situation and n! quest ,
l assistance if necessary. I NOTE: NOTIFY FOR ALL INCIDENTS INYOLVING THE l l I ENVIRONMENT. b s
/ / FEDERAL EMERGENCY MANAGEMENT AGENCY (FEMA) (24-hr. Hotline) l Message: "This is the Shoreham Nuclear Power '
Station. We are in a(n) : (state class or emergency). , I This is (your name) at ' (one
; phone number (516) -
f being used)." Give details as presented on the initial and follow-up foms. Request assistance if needed and as directed by the Emergency Director / Response Manager. Rev. 0 4/23/83
_ - .- wwm =.mnw-n-~.-.. . . -, ,:, . w-~~~ - - - - - - - -
; v '...: .... s
- t.
EPIP 1-5 [ Page 22 of 43
- Attachment 7 Page 5 of 5 I
8 SUPPLENTARY NOTIFICATIONS CALL CHECKLIST i (continued) -} NAME OF PERSON VERIFICATION TELEPHONE NLMBER E ACCEPTING CALL TIME / INITIALS TIME / INITIALS AGENCY / MESSAGE t 4 l i; l NOTE: NOTIFY ONLY WHEN DIRECTEU BY THE .
~
4 l RESPONSE MANAGER / EMERGENCY DIRECTOR. l
/ / U.S. DEPARTMENT OF ENERGY: FRMAP, Brookhaven, NY {
f Message: "This is the Shoreham Nuclear Power j Station. We are in a(n) k l j (state class of emergency). l
- This is _ (your name) at h j phone number (516) (one ;
being used)." : j I ! Give details as presented on the initial and - l follow-up forms. Request assistance if needed , l and as directed by the Response Manager / Emergency Director. I i I k
- i
, 1 h
- r a .1 l
Rev. 0 4/23/83
d
- .... ...- . . . . . a ... . - .
a .= = w = = . , w :.-i. - - ,- ~ n .... . - , f EPIP 1-5
~
Page 23 of 43 4
) Attachment 8 Page 1 of 2 C0W4VNICATIONS CUIDELINES J
For notification of individuals / organizations listed on the various Offsite Call Lists (Attachments 6 or 7) using the Radiological Emergency Data Fom and/or Part II - Radiological Assessment Data Fom and/or Part III - Plant Parameters.
- 1. Call each individual / organization using the primary rcode of
[ communication. If the party cannot be contacted using the primary method, use the alternate method. i 2. If a party cannot.be contacted, bypass that party and proceed to E the next one on the list. Af ter all notifications have been completed, attempt to contact the bypassed parties. If a party ((~ '. still cannot be contact.ed, r,0nsider other methods such as { [ relaying infomatt)n through a third party. y
- 3. When the party answers, identify yourself and infom the If individual to obtain the Radiological Emergency Data Form /Part j II - Radiological Assessment Data Fom/ Pert III - Plant j Parameters Fom on which to record the notification. If the
-,f party does not have the form (s), ask them to get a piece of
- (.l paper. Pause to pemit the individuc1 time to obtain the f: fom(s).
go
- 4. Read the notification, annunciating the infomation which is to I be entered on the form (s).
4 ' 3'E 5. Speak SLOWLY and CLEARLY. Remember, the party at the other end
.e . :. is writing down information.
inF)
; U \. . .- .t p.
- 5;.
Rev. O 7 4/23/83 I ,
"': 2 : ~~ = 22. :=.z:::: .2r' ~ ' L::: ::."~ : ':.. . ,... .
. .:.r.: . ' :
9 EPIP l-5 o g Page 24 of 43
- s Attachment 8 Page 2 of 2 CON 4UNICATIONS GUIDELINES
, (continued)
- 6. After the notification has been completed, ask the individual to read back the notification and, if necessary, correct any errors.
- 7. Record the name of the individual, the time of contact, and your
, initials on the Notification Call Lists.
- 8. Proceed to the next agency on the Call List until all organizations have been notified.
- 9. If call back verification is required, record verification time and your initials on the Notification Call List.
e f ? 4 k 0 ) 0 05.1 =-
- Rev. 0 4/23/83
~ . _ _ . . ._ - _ __. .-. __ - _ - . . _ - _
- ==:= .w. : =. ==: . . ==:= =: . .:==--::=: : -
. e : ~~ . = . . ._ . . . . :. - = = . --
L
. EPIP 1-5
')
p(k/ iu Page 25 of 43 Attachment 9 , Page 1 of 1 3 NRC NOTIFICATION CALL LIST I l l CAUTION l 1 l l NRC NOTIFICATIONS TO BE PERFORMED BY A l l LICENSED OPERATOR ONLY. I l I ! l l t l CAUTION l
- l l 5 l NRC NOTIFICATIONS TO BE MADE WITHIN ONE (1) l
? l HOUR OF EMERGENCY DECLARATION. I ! l l
'I l l . I I MESSAGE l 'i l l COMMUNICATIONS MODE l l VERIFIED l { l NRC OFFICE l PRIMARY / ALTERNATE ITIME/INITIALSITIME/INITIALSI
' I I I I I
$ 11 . Washington l Primary: Emergency I / I I i l Office, INotification Systems l l l
] l Bethesda, l(ENS) i l l 7 l HD l i l l T l l l l I j l l Alternate: Card I / l / l
- l l Dialer i l l
{ l l Phone to NRC Duty l l l 6 l 10fficer I I l A I I I I I I I I i 1 1 1 l 1 l I
$:p i i l l I 4 l l l l l
\ . ~ .I ty Rev. O l 4/23/83
=: -
--"~==:.=-,. . l
= = = : = = u.= x. ::= -r u.n: -= : - =.-- = ==== l l
EPIP 1-5 I I - Page 26 of 43 l } Attachment 10 t Page 1 of 7 OPERATIONAL ASSESSMENT SHEET
- 1. Time of Report: Date:
- 2. Facility: Shoreham Nuclear Power Station
- 3. Caller's Name:
- 4. Event Classification: 50.72 (Non-emergency)
Unusual Event Alert f.j Site Area Emergency i General Emergency i t Transportation Physical Security
]s E '- '
Other Category i ( 5. Event
Description:
- a i:
l I: 1 n. lb' ~t 1
- a-b 4'.l
,]i
- 6. . Event Time:
bi 'f 7. Cause: li R F p. W Rev. 0
- . 4/23/83 1
a
- r. ;; _ =; ::;::; :::: :- y-~_ ;;z u.7 .. .-
- p. ;w: _ - - - =. -- -- _-;;:. ;.r:- ;; ~;~;2 7.~;~.. .
l l 1 ' EPIP 1-5 ! #'\ Page 27 of 43 l Attachment 10 Page 2 of 7 OPERATIONAL ASSESSMENT SHEET (continued)
- 8. Power Prior to Event:
9 Power how:
- 10. Any Safety Injection or ECCS:
e I 11. Cooling Mode ~:
! 12. Any Contamination (Quantify):
)
I 1
!Q')
l
- 13. Any Releases (Quantify):
i, i
- 1
- (
l
! 14. Containment Status (if applicable):
4
- -i 15. Any Other Problems:
'I d
t
-l t
- i a
i D
~( Rev. 0 4/23/83- _ . __ .
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. . . . . , . . =
EPIP 1-5
- Page 28 of 43 Attachment 10 f'v).!'
Page 3 of 7 OPERATIONAL ASSESSMENT SHEET (continued) i l
- 16. Anything Unusual or Not Understood: .
- 17. Plans:
f. [ i
} 18. Any Outside Agency or Personnel Notified:
2 g ..,
~ .5 4.- .
t k a k 1
- i
-)
.) if l '- '+ 1 l a O!
.s -
l:f 9 d I h Rev. O 4/23/83 J. a
. n u .u. . . .... .. . . - : w a s =_ . - . a. . . .= =. = =. n u EPIP l-5
- Page 29 of 43
-g Attachment 10 Page 4 of 7 l
OPERATIONAL ASSESSMENT SHEET (continued) I 1 I ACTIONS l
, Taken:
Planned: Property Damage: RADI0 ACTIVITY RELEASED (OR INCREASED RELEASE) 5
, Liquid / Gas?: Location / Source of Release: ,i ; Elevation: Release Rate: Duration:
rt Stopped?: Release Monitored?: b:O ~. Amount of Release: N(/ [- s.
.)
! INCREASED RADIATION LEVELS IN PLANT
?
'r
! Location (s):
,f Radiation Level (s): Areas Evacuated: Maximum offsite dose rates: ' i: Integrated dose: Location: lg !E q, I i. METEOROLOGY i: j: Wind direction FROM: c [. 1 Wind Speed: meters /sec or miles /hr.
~! Sigma Theta: Temperature: ("C or *F)
I j Stability Class: ABCDEF Raining?
$i L
i l : s .. !h \ s Rev. 0 f '? 4/23/83
^
=.-- = a=~=--=- ~ ~ ~' ' ' ^""~~~~ ""'"'**' '"
_,.:. . . . ::._ w w... l EPIP l-5 1
. Page 30 of 43 g} Attachment 10 Page 5 of 7 r
e
! ; OPERATIONAL ASSESSMENT SHEET q (continued)
PROJECTED DOSES Dose Rates Integrated Dose . 2 mi 5 mi 10 mi d Sectors Contamination '(Surface): Inplant Onsite Offsite s v ,, REACTOR OPERATIONS
}
! Reactor System Status: Power Level:
e Pressure: Temp.: Flow (pumps on): '{ [ Cooling Mode: ECCS Operating /0perable?: 15 lLY Containment Status: li Containment Isolated?: Containment Temp.: [;. Containment Pressure: Containment Radiation: R/hr. ,e Standby Gas Treatment System Operable?: i i Reactivity Controls: di t Control Rods Inserted?: [j Status of Emer. Boration System:
'b i
, .I t
[ Rev. O j 4/23/83
- =-.w---=__.u==,=.=.-.=---====.:==.=:..._ - .. - --.. ..:.. = -: = ~ - = .-
l i EPIP 1-5
't "
Page 31 of 43 d Attachment 10 Page 6 of 7 OPERATIONAL ASSESSMENT SHEET (continued) STEAM PLANT STATUS f Equipment Failures?: l Feedwater Source / Flow: MSIVs Closed: s Electrical Dist. Status: I Nomal Offsite' Power Available?: Major Busses / Loads Lost?: Safeguards Busses Power Source: D/G Running?: Loaded?:
]
Security / Safeguards: 0 Bomb Threat: Search Conducted?:
- i
) Search Results: Site Evacuated?
O l !! Extortion: Source (phone, letter, etc.)?: lt* Location of Letter?: 1
? Intrusion: Insider?: Outsider?:
s i Furthest Point of Intrusion?: (
) Fire Ams Related?:
0 t Stolen / Missing Material?: i ' 4 Rx Oper./ Demonstration: Size of Group?: \j Demands?
! Fire Arms Related?:
Violence?: i i l Sabotage / Vandalism: Radiological?: Arson Involved?: 3 l l Stolen / Missing Material?: Y lii Rev. O 4/23/83
EPIP l-5
' Page 32 of 43
) Attachment 10 Page 7 of 7 OPERATIONAL ASSESSMENT SHEET (continued)
TRANSPORTATION . Mode (Road / Rail / Air /etc.): Carrier: Exact Location: Type of Haterial (HEU/ Spent Fuel / Cat. III/0ther): Description of Shipment: Labels: (On Material Package) (On Vehicle) Spillage?: Surveys: 1 Physical Damage to Container? _ i. Fire / Smoke: Missing Material?: [ y I -
', n..
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lI i '8 u. t i: I i s l.- t Lt !. f . lt , i i i s Rev. 0 4/23/83
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_ _ . _ . . . -.. _ _ . . ~ . . _ _ , , - . . . . . . -
. _ - . . _ _ _ _ . - . . . ~ - . - ~ _ . _ -
EPIP l-5
,X ") ~
Page 33 of 43 ( y Attachment 11 i Page 1 of 11 EMERGENCY CALLER PROCEDURE Emergency Caller 1, 2, or 3 - When notified by the Control Room Communicator, pe-fonn the
- following:
- 1. Take out the appropriate call list based on the caller number you have been assigned.
- 2. At the top of the call list, note the following items:
- a. Name of the Control Room Communicator
( 'S - ' ' ' b. Emergency C1assification 4
- c. Time the call was received i
- 3. Call the Communicator in the Control Room at or to verify that an emergency exists. State the
! following: "This is (your name). I am calling to verify that a (state emergency class) exists and that I have been assigned as Caller # _ (assigned number)." i 4 I I j l . CAUTION l 1 I a l FOR EMERGENCY POSITIONS THAT 00 NOT LIST A PRIMARY I i l DESIGNEE, SIMPLY ENLIST THE NUMBER OF INDIVIDUALS l ' I REQUIRED BY CALLING DOWN THAT LIST IN ORDER. l I I 9 i 1 Rev. 0 4/23/83
.._._.m __ - ~... _ _ _ _.__ _ _._. .._ ._. --.......~..._.. _ ._..___,_.._ .. . _
q EPIP 1-5 l Page 34 of 43 ; Attachment 11 Ii Page 2 of 11 g EMERGENCY CALLER PROCEDURE (continued) l
- i. 4. Attempt to notify the primary designee or the proper number of 3 -
individuals for each emergency position. - S. k' hen contact is made:
- a. Identify yourself.
- b. State: "An ALERT / SITE AREA / GENERAL EMERGENCY (choose appropriate one) has been declared at the site. The emergency organization is being activated. Pl' ease proceed to your emergency duty station immediately."
- 6. For each successfully completed call, log the time of the call
{ and initial the entry. j , 7. Proceed down the call list in order.
- 8. Upon completing the call list, go back and attempt to contact
- any primary designee who could not be reached.
- 9. If the line is still busy, or contact cannot be made, notify one of the designated alternates.
f
- 10. After completing your call list, contact either the EPA #2 in
,T the TSC at or Ext. , or the Communicator
#1 in the Main Control Room at or . Inform him of difficulties encountered in your callout procedure I,.
( (e.g., inability to contact an individual, delay in normal response time, etc.).
- 11. Report to the TSC to fill your position as TSC Communi.cator.
10 Rev. 0 4/23/83 r - _ _ . - _ .
- .- a..a.. ..
...a.............-.-. . . . _ . - . . . ~ . . . . . ..:.
EPIP l-5
~
Page 35 of 43 - (%l Attachment 11 Page 3 of 11
. Os EMERGENCY CALLER PROCEDURE (continued)
CALLER #1: EMERGENCY CALLOUT LIST
- 1. Control Room Comunicator:
- 2. Emergency Classification: ALERT SITE AREA GENERAL EMERCENCY (circle one)
- 3. Time Call Received: a.m./p.m. (circle)
EMERGENCY POSITION /NAME HOME PHONE WORK TIME INITIALS OPERATIONS COORDINATOR Primary: Alternate: CORE DAMAGE COORDINATOR
}
j . Primary: " Alternate: L i i OSC COORDINATOR r.; L L Primary: i Alternate: i ASSISTANT OSC COORDINATOR f i
?
Primary: 3 1 -5 X I&C TECHNICIANS For ALERT enlist ( )
.)
i}l For SITE AREA or GENERAL EMERGENCY enlist ( il: e ;' If. i !!O iI;
;, Rev. 0 4/23/83
.j'
- . ;.=.- .:.e .-- ..._......+v.-.,n. -
l .-- .:.== == ::.=-.= :.::= :..: = = - - - . EPIP 1-5 ('C'j Page 36 of 43 (__L/ Attachment 11 Page 4 of 11 EMERGENCY CALLER PROCEDURE '. , (continued) CALLER #1: EMERGENCY CALLOUT LIST (continued) - , EMERGENCYPOSITIOS/NAME HOME PHONE WORK TIME INITIALS b t L i 5
- i. -
[( ' Y ELECTRICIANS For ALERT enlist ( ) i For SITE AREA or GENERAL EMERGEkCY enlist ( ) b e 5, - s U MECHANICS I' For ALERT enlist ( ) l For SITE AREA or GENERAL EMERGENCY enlist ( ) h
'd -
h J 4 n
-3 2
)
I I Rev. O i 4/23/83
- w. a _. _ .u - _ . _ a = :_== = : = _- -
.w._.=.- : .= -- ~
. .-:. :.:= v EPIP l-5
~
Page 37 of 43
'i.*
Attachment 11 Page 5 of 11 EMERGENCY CALLER PROCEDURE (continued) CALLER #1: EMERGENCY CALLOUT LIST (continued) . HOME PHONE WORK TIME INITIALS EMERGENCY POSITION /NAME ADMINISTRATIVE SUPERVISOR Primary: Alternate: ENGINEERING COORDINATOR Primary: , Alternate: 1 1 iy 1 I, L t 1 i I c c_ t Rev. 0 l' 4/23/83 i, -
~ ~ ~ ~ ~ ~ ~
..._.-_.--.~a~~---
-~ **~~~~~"
l i ,e s EPIP 1-5 7 Page 38 of 43 3 Attachment 11
- Page 6 of 11
~ EMERGENCY CALLER PROCEDURE (continued)
CALLER #2: EMERGENCY CALLOUT LIST 4
- 1. .
i Control Room Communicator:
- 2. Emergency Classification: ALERT SITE AREA GENERAL EMERGENCY
^ (circle one)
- 3. Time Call Received: a.m./p.m.
i (circle) EMERGENCY POSITION /NAME HOME PHONE WORK TIME INITIALS gj ELECTRICAL ENGINEER (:
- . Primary:
ijSi . , . Alternate:
) QA ENGINEER !? Primary:
j
'i Alternate:
s 3 MECHANICAL ENGINEER
- v. . .
W Primary: i Alternate: , / { SITE RAD. ASSESSMENT ASSIST.
- Primary:
[0 Alternate: I i DISPATCHER I Primary: d Alternate: Li RADIATION PROTECTION COORDINATOR
}i Lj Primary.
'f i Alternate: [.. - 8 t. F I
;5 Rev. 0 4/23/83 i
. . - - . . . . . . . . . . . ~ . ~ . . . . - - - . ~ . . ~ . . . . . . . . . . . . ~ . , . . - .: - . .. -
EPIP l-5 Page 39 of 43 Attachment 11 Page 7 of 11 (\ ,w
) .
EMERGENCY CALLER PROCEDURE (continued) - I CALLER #2: EMERGENCY CALLOUT LIST. (continued)
. 1 HOME PHONE WORK TIME INITIALS EMERGENCY POSITI'ON/NAME _
I CHEMISTRY COORDINATOR l Primary: j Alternate: t FIRE BRIGADE Enlist ONE (1) Shift A i Shift B Shift C .' Shift D i '
. Shift E
($ U. ~! Shift F Enlist ANY THREE (3) l E Shift A l $ Shift B I Shift C kl t Shift U {! I s; S't
!! t "(~ _? Rev. 0
!i. l 4/23/83 l? > :t
EPIP 1-5
.- Page 40 of 43 L, Attachment 11 Page 8 of 11 EMERGENCY CALLER PROCEDURE (continued) .
CALLER #2: EMERGENCY CALLOUT LIST (continued) . o EMERGENCY POSITION /NAME HOME PHONE WORK TIME INITIALS Shift E , Shift F 1 "P
- I L
s ls s 1 l t Rev. 0
', 4/23/83 f
I..-- _ _ - _ . - _ _ . . _ _ _ . . _ . _ , , _. . . . _ _ _ . _ _ _ _ _ _ _ . . ______ ..____ _. ____ _ _ _
. - . . . - . . . . - . . . . . . - . . . - - ~ . . - . . ~ . ~ . . . - - . - . . . . - . - . - - . - - -
EPIP l-5 Page 41 of 43 Attachment 11 Page 9 of 11 EMERGENCY CALLER PROCEDURE h (continued) . CALLER #3: EMERGENCY CALLOUT LIST 1
\
[ 1. Control Room Communicator: l
- SITE AREA GENERAL EMERGENCY
- 2. Emergency Classification: ALERT (circle one)
- 3. Time Call Received: a.m./p.m. (circle)
EMERGENCY POSITION /NAME HOME PHONE WORK TIME INITIALS HEALTH PHYSICS TECHS. ! For ALEkT call FIVE (5) For SITE AREA or GENERAL ENERGENCY call EIGHT (8) i 5 # e 2 6 h F, s k, 1 s. lh ? e e iI. + . yd. ! . 3 Rev. 0 il 4/23/83 t Ir
jz = -.-a a w.:.z..-a =-=:.r.. n .._~ . ~. . . . - . .. . _ . _ _ _ . , , , , , . . . , , , , EPIP 1-5 Page 42 of 43 Attachment 11 Page 10 of 11
- EMERGENCY CALLER PROCEDURE (continued) .
8 CALLER f3: EMERGENCY CALLOUT LIST (continued) . EMERGENCY POSITION /NAME HOME PHONE WORK TIME INITIALS RADI0 CHEMISTRY TECHS. Enlist TWO (2) I, r#: , ()) 0FFSITE RAD. MON. ASST. [ Enlist ONE (1) i le
?
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EPIP 1-5 Page 43 of 43 Attachment 11 Page 11 of 11 T)/ EMERGENCY CALLER PROCEDURE (continued) . CALLER #3: EMERGENCY CALLOUT LIST
. (continued) -
EMERGENCY POSITION /NAME HOME PHONE WORK TIME INITIALS ADMINISTRATIVE SUPPORT For ALERT enlist ( ) For SITE AREA or GUEkAL EMERGENCY enlist ( ) i 1 5_ J 4 h i e I ' I 6 k i ~5 t O, 1 Rev. O i 4/23/83 1 5
EPC 4 - M '- EPIP l-6 Page 1 of 13 Approved: // Plant Manager W / - O' Effective Date[ 5/16/83 00ff $} x 1 EPIP l-6 EVACUATIONS 1.0 PURPOSE To provide instructions for tne emergency evacuatiori of areas within the Site Boundary of the Shoreham Nuclear Power Station. 2.0 RESPONSIBILITY The Emergency Director is responsible for implementing this procedure. 3.0 PRECAUTI0i4S 3.1 Initiate site evacuations before or after tne passage of the release and choose evacuation routes which lead personnel away from the path of tne plume. 3.2 If OSC is to be evacuated, all occupants shall report to the TSC lower level. l l 4.0 PREREQUISITES 1 l 4.1 Local Evacuation Ary of the following: 4.1.1 Valid alarm of single area radiation monitor (greater than 5 mr/hr). O Rev. 0 3/4/83
EPIP 1-6
.Page 2 of 13 O
4.1. 2 Alarra c/ a single continuous air monitor (CAM). 4.1.3 Surveys with portable survey equipment detect unexpected increases in or a presence of radia-tion levels. s 4.1.4 Fire, toxic or flammable gases, or heavy smoke in any occupied area.
" , , s ',. _
x 4.2 Restricted Area Evacuation ', t~ ' s s s, Any of the following:,
'- t , ' .
s ..
/ ..
- 4. 2.1 Building airborne nonitor ,17; dica +as 31rborne ( ,.- ,
\
s activity in excesi of 1 x 108uci/cc
~
,t
.' s unidentified' mix or in excass of l Naximum j s: ," cv Permissible Concentration' 096) folNieqti,fied s.[y x' \ ,'s#
mixes in areas not p'osted'as an Airborri," a Radioactivity Area. '
~
,[\ ' $~; ';
"]C s,
K, ,N ,.,s - 4.2.2 Multiple area radiation monitorglarms in s\' widespread areas. s -
~
4 ,- , h~ V. gg 4.2.3 Toxic gases, fire, flamable ' gases, uncontrollea
$ j
;w 3 live steam, ep., affecting widespread areas.
/
- s s1 4.3 Site Evacuation $, t\ '
; \, s\-
\
'~
Any of the
'l 1611owig: ,
s x ,; ( . ; 'l
' X 4 3.1 De;iaration of a General Emergency.
s w t Rev. O
~
3/4/83 m Y 8 m *t
a EPIP l-6 Page 3 of 13 s4.3.2 The" Criteria for Mandatory Evacuation (Attach-ment 1) are projected to be received by personnel. 4.3.3 Radiological conditions in any previously
'.,.t unrestricted ared. (including areas onsite but
~ ,
24 h' outside of plant buildings) and the protected q area, which will result in whole boqy dose rates
^
/.
*' in excess of 5 mres/hr, or a projected dose in t -
' dx' cess or 100 mrem wnole boqy, and/or airborne M <%
radioactivity in excess of 1 HPC or 40 MPC-hrs / week from uncontrolled sources of f t M , s radiation. s {n ,e,, ; ' k g - 4.3;4 An atmospheric release has occurred or is
. bt projected to occubthich results in projected d '
dose of'5 rem phole body or 25. rem thyroid. J ', -
. 3, . ,3 i
4.3.5 Safety hatards,5uch as . toxic.5ases, flamable l gases, and/pr' fire'affe'ct widespread areas onsite. 4 . <
> w..
4.3.6 Adverse westbd7 conditions s'uch as floods,
. v, m,.
l ., I byrica@s, or torgadoes -are expected to occur. i
~_ . n l
o- - In suchccases, advance; wee,ther warnings will ( - usually provide a@gdate time for an orderly
~
l , di'sgissal of statiodgersonnel without the ~need l~ \ Y s t for ezacuation ast de"scfibed in this procedure. e
)
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l ", EPIP l-6 O,' ,1 e Page 4 of 13 s !
/f 5.0 ACTIONS- /
.i . 3
'{,\
~
) i 5.1 Local Area Evacuation -
i f, i . ' s 5.1.1 Direct Control Room personnel to rinake the 4 following announcement over the page-party. system: /
. e a
j " Attention all station pertonnel.) p'
, s There is a (specify hazard) in the '
f, (psecify area). Personmis in she trea should evacuate to (specifflocatiori)
+ and await further instiwctio:L.",
r
- 5. l . 2 Notify the Respcnse Manager (if applicable) of the evacuation.
O 5.2 Restricted Area Evacuation
- i 5.2.1 Direct Control Room personnel to sound the
" PULSE" evacuation tone using the multitone generator asid announce the following over the page-party system: .
8 I " Attention all station personnel. A (specify hazard) exists in the Restricted Area. Evacuate the Restricted Area and all personnel without emergency assignments proceed to your designated assembly area and l await instructions." Repeat tre alann and announcement three times at approximately one-minute intervals. . Rev. 0 3/4/83
,_- g ,
- ,l' 1f '
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EPIP l-6 Page 5 of 13 0 5.2.2 Notify the Response Manager of the evacuation. 5.2.3 Direct Shift Security Supervisor to implement EPIP l-15, Section 5 4.1 5.3 Site Evacuation ' I I l CAUTION l l l l THE DECISION TO EVALUATE PERSONNEL AS A l l PROTECTIVE ACTION SHOLLD BE BASED ON THE I l DETERMINATION THAT IT WILL RESULT IN THE I l LOWEST PERSONNEL EXPOSURL~IN COMPARISON WITH I i OTHER PROTECTIVE ACTION. l I I l CONSIDER THE DOSE RATES AT THE PERSONNEL l l ASSEMBLY AREA, ONSITEg AND ALONG EVACUATION I I ROUTES, NIMIER OF PERSONNEL ONSITE AND THE l O l POTENTIAL FOR MITIGATING OR TERMINATING THE I l EERGENCY PRIOR TO FERSONNEL RECEIVING EX- l l POSURES IN EXCESS OF THE PROTECTIVE ACTION I i GUIDES. l l l 5.3.1 Confer with the Radiological Assessment Coor-dinator to determine radiological conditions including potential plume path. 5.3.2 Implement Site Evacuation Plan A, 8, C, or D ( Attachments 2 through 5) based on determination i n 5. 3.1. i
- a. Contact tne Shift Security Supervisor and inform him of the impending evacuation and to l make preparations in accordance with Sections 5.4 and 5.5 of EPIP l-15, Security During i
O Emergencies. Rev. 0 3/4/83
EPIP l-6 Page 6 of 13
- b. Direct Control Room personnel to sound the
" Warble" evacuation tone for 1 minute, using the multitone generator and announce the following vver the page-pdrty system (includ-ing all buildings within the exclusion area).
" Attention personnel. Attention personnel. A (Emergency Class) has been declared.
All personnel except those with emergency assignments shall evacu-ate the site promptly and orderly through (specify assembly area). All members of the onsite emer-gency organization report to your ( stations. "
- c. Assign Assembly Ared leaders to the North Parking Lot and/or the South Warehouse to coordinate the transportation of all evacuees.
- Direct the Assembly Area leaders to instruct evacuees to either 90 home or report to the Port Jefferson or Riverhead District Office, depending on accident conditions.
! 5.3.3 Contact the Response Manager and inforu him of the Site Evacuation. 'O Rev. 0 3/4/83
t EPIP l-6 Page 7 of 13 j i 5.3.4 Contact St. Joseph's Villa by calling and inform them of the site evacuation. f 5.3.5 Contact LILCO's Visitors Education Center.
6.0 REFERENCES
l 6.1 EPIP l-7. Personnel Accountability ! 6.2 EPIP 1-15 Security During Emergencies 70 ATTAC MENTS
- 1. Criteria for Mandatory Evacuations ;
2 Evacuation Plan A Route Map
- 3. Evacuation Plan B Route Map
- 4. Evacuation Plan C Route Map
- 5. Evacuation Plan D Route Map l
l I I l i O . Rev. 0 3/4/83
EPIP l-6 p Page 8 of 13 ( Attachment 1 Page 1 of 2 CRITERIA FOR MANDATORY EVACUATIONS Whole Body 2 Implement Radiofodine3 Dose Rate Evacuation Concentration (arem/ hour) Within (uCi/cc) Up to 600 8 hours Up to 1E-5 601 to 1,000 4 hours IE-5 to 2E-5 1,001 to 2,500 2 hours 2E-5 to 4E-5 2,501 to 5,000 1 hour 4E-5 to 7E-5 5,001 to 10,000 30 rainutes 7E-5 to 1E-4 10,001 to 20,000 15 minutes lE-4 to 3E-4 Over 20,000 IMMEulATELY 3E-4 CAUTION , 1. There is no direct correlation between the whole body dose > rates and the radiofodine concentrations; and the measurements or projectons of each must be performed independently. In the event that only a direct radiation determination is available, j with no corresponding knowledge of the concentration or frac-tion of the total which is attributable to radiofodine, the most conservative assumptions specified in the USEPA Manual for l Protective Action Guides would be required. Such assumptions, based only on direct radiation determinations, would likely result in gross overestimation of thyroid dose commitment. l \ O Rev. 0 3/4/83 l _ _ _ - . . . _ . __ _ _ _ , _ _ ----- - - -- - - - -
l EPIP l-6 Page 9 of 13 n i Attachment i v Page 2 of 2 CRITERIA FOR MANDATORY EVACUATIONS (continued)
- 2. Whole body dose to non-emergency personnel should not exceed 5,000 mrem from the event. The whole body dose rates specified above are based on 5,000 mrem. This value is based onthe USEPA PAG Manual specified mandatory evacuation times, in the absence of a significant constraints evacuations should be implemented to maintain personnel exposure as low as reasonably achievable and within specified quarterly exposure limits.
- 3. Maximum concentrations for specified time corresponds to approximately 25,000 mrem adult thyroid dose connitment.
Radiciodine concentrations vs. adult thyroid dose connitment based on Appendix D (January 1979) to USEPA Manual of Protec-tive Action Guides. Radioiodine nuclide distribution corres-ponds to 4 hours following reactor shutdown. l l O Rev. 0 3/4/83
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-REACTOR BUILDING Page 12 of 13 Attachment 4 Page 1 of I s
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4 ;7 EPC A r2 EPIP 1-7 App ved: g Page 1 of 11 O Plant Manager .v / Effective Dat ~5/16/83 b(V' S0!!:90*rt~QO}' 4r EPIP l-7 PERSONNEL ACCOUNTABILITY 1.0 PURPOSE To provide instructions for accounting for personnel onsite in case of an emergency. 2.0 RESPONSIBILITY The Emergency Director, Assembly Area Leaders, and Shift Security Supervisor are responsible for implementing this procedure. 3.0 PRECAUTIONS None 4.0 PREREQUISITES 4.1 Evacuation of a portion or all of the Shoreham Nuclear Power Station site is in process per EPIP l-6, Evacuations. O Rev. 0 3/4/83
h EPIP l-7 Page 2 of 11 5.0 ACTIONS 5.1 Accountaoility for Local Evacuations 5.1.1 Lead Person in Evacuated Area
- a. Ensure that those personnel who have evacu-ated the designated local area remain at the designated local Assembly Area.
- b. Obtain a list of the names of evacuees.
- c. Ask the evacuees if they know of anyone else that had been working in tne area that is not at the local Assembly Area.
O d. If an individual is identified as having been in the area but is not at 'the local Assembly Area, report that individual (s) name to the Emergency Director. 5.1. 2 Emergency Director i
- a. If a person is reported missing, direct formation of a Search Team and have them l stano by and await further instructions.
- b. Contact the individual's supervisor to j determine his presumed whereabouts.
i .O Rev. 0 3/4/83
l EPIP l-7 i Page 3 of 11 l 1 , c. If the individual's supervisor verifies that the person should have been in the area, page the individual. !
- d. If the individual does not respond to page, contact the Shift Security Supervisor to ensure that individual is still onsite.
- e. If the individual is onsite, initiate Search for Missing Persons in accordance with EPIP l -8.
5.2 Accountability for Restricted Area Evacuation 5.2.1 Shift Security Supervisor or Designee ;
- a. Direct Island Guard to execute Security Post Orders for a Restricted Area Evacuation.
- b. Report the names and badge numbers of missing individuals to the Emergency Director.
5.2.2 Assembly Area Leaders ( Attachment 1)
- a. Account for eacn individual by comparing the names on the designated Assembly Area accountability roster with individuals present (Attachments 2 and 3).
- b. Cneck off names of an/ individuals present and record names of any individuals present whose names DO NOT appear on the roster.
O Rev. 0 3/4/83
EPIP l-7 Page 4 of 11 O
- c. Once accountability has been completed, use the telephone numbers listed on the accounta-bility roster to call Security (phone no.)
and report names of missing individuals and non-roster personnel. 5.2.3 Emergency Director
- a. Consider missing naraes reported by the Shif t Security Supervisor and have the individuals paged.
- b. If any individuals do not respond, initiate Search for Missing Persons in accordance with EPIP 1-8 as necessary.
O c. If EOF is activated, notify the Response Manager of missing individuals. 5.3 Accountability for Site Evacuations 5.3.1 Site Support Coordinator / Emergency U1 rector
- a. Direct the Shift Security Supervisor to implement Section 5.4.1 of EPIP l-15, Security During Emergencies, and obtain final roll call results.
- b. Obtain accountability results from Security Officers in the Control Room and the TSC.
- c. Obtain accouaitability results from the OSC D
Q Coordinator. Rev. 0 3/4/83
i EPIP l-7 Page 5 of 11 O
- d. Identify all individuals who have not exited the Site and compare names witn those persons at emergency stations.
- e. Report the names of missing individuals to the Emergency Director.
i
- f. If any individual (s) are missing, direct the s Corrective Actions Coordinator to implement EPIP l-8, Search for Missing Persons.
5.3.2 Assembly Area Leaders
- a. When directed by the Site Support Coordinator, report to assigned Assembly Area.
- b. Assist all evacuees without transportation by
. finding them a ride with other evacuees or in a company vehicle.
- c. Direct any personnel in protective clothing to the Personnel Monitoring and Decontamina-tion Station at the Wildwood Substation.
I I l CAUTION I I I I IF POSSIBLE, PERSONNEL WEARING l l PROTECTIVE CLOTHING SHOULD BE I I GROUPED TOGETHER. l l l O Rev. 0 3/4/83
l l l EPIP l-7 Page 6 of 11
- d. If Assembly Area B only is being used, sepa- '
rate those personnel with cars in Assembly Area A and assign them to other evacuees for ride snaring before they leave the Assembly Area.
6.0 REFERENCES
6.1 EPIP l-8, Search for Missing Persons 6.2 EPIP l-6, Evacuations 6.3 EPIP l-15, Security During Emergencies 7.0 ATTACHMENTS
- 1. Restricted Area Evacuation Assembly Areas and Assemoly Area Leaders
- 2. ' Assembly Area Accountability Roster - Sample
- 3. Contractor Accountability Roster - Sample l
l lO Rev. 0 3/4/83 l
EPIP 1-7 Page 7 of 11 Attachment 1 O' Page 1 of 1 RESTRICTED AREA EVACUATION ASSEMBLY AREAS AND ASSEMBLY AREA LEADERS ASSEMBLY JOB FUNCTION ASSEMBLY AREA AREA LEADER 0QA Maintenance Shop Maintenance Foreman Radiochemistry Maintenance Health Physics I&C Shop I&C Forennen I&C Reactor Engineering OAS Mezzanine Classroom Nuclear Engineer Operations Technical Support Security Bldy., 2nd Floor Plant Engineer / Tech Training Classroom Support Group Administration 0&S Large Conference Room Plant Administra-tive Coordinator Visitors Security Bldg., Lower On-shift Security Classroom Personnel I Contractors To each individuals (less than 20) assigned section l l Contractors To assigned contractor Assigned (20 or more) assembly area I l !O Rev. 0 3/4/83
EPIP l-7 fm, Page 8 of 11 (s~) Attachment 2 Page 1 of 2 ASSEMBLY AREA ROSTER Assembly Area Section Note to Leader:
- 1. Accountability raust be reported to the Primary Guard Island within 10 minutes of leader's arrival.
- 2. If inaividual is not present, request his last known location from supervisor or whoever may know.
- 3. Report the names and badge slot numbers of individuals not present to the Primary Guard Island (ext. 557).
- 4. Where possible, also report last known location of missing individuals.
I NAME I BADGE SLOT NUhBER l PRESENT l 1 i i l i l I l i l i i l l I I I I I I I I I l l l l l 1 I I l l l l l l l l l 1 1 I I I I I I I I I I I I I l l l l l 1 1 I I I I I l i l l l l l l l 1 1 I l l l l l l l l l l l o 1 I l l l l 1 1 I I Rev. 0 3/4/83
. . - ~ . _ - . - - . - - - . . - _ - .
I i EPIP l-7 l Page 9 of 11 l O , Attachment 2 Page 2 of 2 ASSDSLY AltEA It0 STER ' 4 (continued) f i NMIL l BAIAsE SLUT NUMBER I PRE 5ENT I
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d EPIP l-7 gw Page 10 of 11 l] Attachment 3 Page 1 of 2 CONTRACTOR ASSEM LY .\REA ROSTER Assembly Area Leader Al ternate Note to Leader:
- 1. Accountability must be reported to the Primary Guard Island within 10 minutes of leader's arrival.
- 2. If individual is not present, request his last known location from supervisor or whoever may know.
- 3. Report the names and badge slot numbers of individuals not present to the Primary Guard Island (929-8300, ext. 557).
- 4. Where possible, also report last known location of missing individuals.
Ci V I l l LAST KNOWN LOCATION I I NAME I BADGE SLOT NUMBER I (check if present) l I I I I I I l l I I I I I I I I I l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l i i l l l I I I I l l l l l l 1 I I l l I I I I I I l l l l l l l l l l q l l I I V Rev. 0 3/4/83
EPIP 1-7 Page 11 of 11 O Attachment 3 Page 2 of 2 CONTRACTOR ASSEMBLY AREA ROSTER (continued) I l l LAST KNOWN LOCATION l l WAME I BAuGE SLUT NUMBER l (check if present) I l I I I l l l l 1 i i l i l l l l l l . I I I I I I I I I I I I l l l 1 l l 1 l i I l I l l l l 1 I l l l I I I I I I I I I I l l l l l 1 I i l l I I I l l l l l l l l l l I I I I I I l l l l l l l l' I l l l l l l 1 l~ l l I i 1 l I I i i ! I I l I I I I I I I I I I I I I I l l l 1 I I I I l l l l l l 1 1 I l Rev. 0 3/4/84
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*tr' A T Ir EPIP l-8 SEARCH FOR MISSING PERSONS
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- o iTo desribe actions to locate, rescue, and/or treat persons who ' '- " .
are missing and/or injured and contaminated. '
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2.0 RESFUIdSIBILITY
.s 2.1 If the OSC is activated, the OdC Coordinator is responsi-
; ble for assigning the team.
s ,3 e 2.2 11pf'ba TSC is activated, the Corrective Actions Coordina-4or (CAC) is responsible for directing the team. 3 , 2.3 If the TSC is not activ,:ted, the Emergency Director is responsibIsJor assigning and directing the team. I ( , 3.0 PRECAUTIONS N.
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3.1 For severe cr: life tnreatening injuries, immediate medical treatment is of tt'e highest priority.
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4.1 An indiviaual(s) is reported to be missing. , I t 7
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. .s S.2.1 At the hrdeJfng, ensure the briefer , s fills out a Search Team Briefing Fonn ( Attachment 1) and that
.\ i the following items are coveru jas a minimum): '
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l l i EPIP l-8 l Page 3 of 7 l O :
- a. Team identification
- b. Communications equipment and channel
- c. Search equipment
- d. Protective equipment, including Potassium Iodide (KI)
- e. Authorized doses
- f. Individuals' last known location 5.2.2 Receive Search Team Briefing Form ( Attaciment 1).
5.2.3 Log Predeployment personnel dosimeter reading onto the Search Team Briefing Form ( Attachment 1). 5.2.4 If K! administration is required, insure all team members take one KI tablet at this time. Inform the RPC/RAC when this is done. 5.2.5 Return to the OSC and assemble all required protective and search equipment as listed on the briefing fom. 5.2.6 Perform communications check with the CAC/ED. Maintain proper communications practices and , always identify both parties, e.g., Search Team
#1 to TSC.
i 5.2.7 Dress in appropriate protective clothing. 5.3 Search 5.3.1 Proceed to the last known location of the individual (s) and, if necessary, expand the search to adjacent areas. Rev. 0 3/4/83
EPIP l-8 Page 4 of 7
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O l l l CAUTION l 1 I l MAINTAIN VISUAL OR VOICE CONTACT l l WITH EACH OTHER. I I I 5.3.2 Inform the CAC or. ED immediately upon locating any personnel. 5.3.3 If the individual is not injured, direct the individual (s) to evacuate the area. 5.3.4 If a rescue operation is necessary and the search team does not have the necessary resources, con-tact the CAC/ED and request that a rescue team be dispatched to tne location. Provide the following infonnation:
- a. Location - give directions.
- b. Victims' predicament.
- c. Equipment wnich may be needea.
5.3.5 If radiological conditions permit, remain with victim until rescue team arrives. i 5.4 Decontamination / Return i 5.4.1 Follow normal Station Health Physics procedures when exiting radiation areas (SP62.026.03, l l 62.004.21, 62.040.01)). 5.4.2 Return t3 the TSC with the team. O Rev. 0 3/4/83
EPIP l-8 Page 5 of 7 O 5.4.3 Debrief with the CAC/ED.
6.0 REFERENCES
6.1 EPIP l-6, Evacuations
. 6.2 EPIP l-7, Personnel Accountability 6.3 EPIP l-15, Security uuring Emergencies 6.4 SP62.004. 21, Use of Direct Reading Dosimeters 6.5 SP62.026.03, Use of Protective Clothing 6.6 SP62.040. 01, Personnel Decontamination 7.0 ATTACHMENTS
- 1. Search Team Briefing Form O
-l t O Rev. 0 3/4/83
EPIP 1-8 Page 6 of 7 Attachment 1 O Page 1 of 2 SEARCH TEAM BRIEFING FORM
- 1. Date: Time: Briefing at: Team ID:
- 2. Briefing by: (CAC)
(RPC)
- 3. Unusual Area /Env. Conditions:
- 4. Communications Extensions:
CAC-TSC: OdC: CONTROL RM:
- 5. Required Equipment:
' Search light Rope Other
- 6. Team member names and authorized doses (rem):
Lead Dose rem Asst. Dose rem
- 7. Protective Equipment (check applicable):
(1) DRDs (200 mR & SR) (2) TLD (WB/ Extremity) (3) Respirator w I/P Canister (4) SCBA (5) High Range Survey Equipment (6) Glove (7) Bootie (8) Coverall 1
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(9) Hood (10) KI (11) (12) (13) Rev. 0 3/4/83 - S.. ,, e e,-m,4 - , - - . , , , . , - . - *,,,.,_m_._. - m.- ,_.,._,..,__-_7 -- ,, ,....e.p.,-,.
EPIP l-8 Page 7 of 7 Attachment 1 O Page 2 of 2 SEARCH TEAM BRIEFING FORM (continued)
- 8. Team dosimeter readings (Before/After Mission):
Lead (200 mR Scale) / ; (SR Scale) / Asst. (200 mR Scale) / ; (SR Scale) /
- 9. Special Instructions:
O l O Rev. O 3/4/83
EPC A1 EPIP l-9 Approved: Plant Managerfy/ Page 1 of 12 p Effective Date 5/16/83 C I ((h h0[ 9[- l EPIP l-9 TECHNICAL SUPPORT CENTER (TSC) ACTIVATION 1.0 PURPOSE To describe the method to be used in the activation of the Technical Support Center and subsequent shift changes in the TSC. 2.0 RESPONSIBILITY 2.1 The first person to arrive is responsible for implementing this procedure. The Emergency Planning
, Advisor #2 (EPA #2) assumes responsibility upon arrival.
3.0 PRECAUTIONS None l l 4.0 PREREQUISITES i Any of the following apply: l 4.1 An Alert, Site Area Emergency, or General Emergency has l been declared in accordance with EPIP l-0, Event Classification. i ? 4.2 The Emergency Director has ordered the activation of the TSC. O Rev. 0 3/4/83
i EPIP 1-9 Page 2 of 12 G i 5.0 ACTIONS 5.1 Turn on lights and proceed to Mechanical Equipment Room located on the lower level of the TSC. . 5.2 Switch ventilation system to the filtered intake mode. Control panel is located on rear wall on the left-hand side as you enter. Follow instructions located on panel. 5.3 Set up tables as shown on Attachment 1. i 5.4 Remove emergency cartons contained in the TSC emergency closets and place on the appropriate emergency position desks as shown on Attachment 1. 5.5 Remove communication equipment from the emergency O carton. If possible, set up the equipment in numerical order by position location. 5.6 Using Attachment 2, deten.iine the appropriate Communication Tenninal Box. Find its room location on Attachment 1. 5.7 Match the communication instrument's designation with that in the cable from the Terminal Box and plug in. J 5.8 Repeat Steps 5.4 through 5.7 until all conmiunications equipment is set up. 5.9 Test dedicated conmiunication circuits by contacting the party on the other end of the line. Rev. 0 3/4/83
EPIP l-9 Page 3 of 12 5.10 Direct the personnel who fill the positions of Emergency Director, Radiological Assessment Coordinator, Operational Assessment Coordinator, Site Support Coordinator, and the Maintenance Coordinator to fill out the attached checklists and return them to you upon completion (see Attachments 4 thru 8). 5.11 Ensure that the two Area Radiation Monitors shown on Attachment 1 are in their proper places. 5.12 Verify that status boards are in place. 5.13 Advise the relief Emergency Director that the TSC is set up, checklists are completed, and recomend activation. 5.14 Emergency Of rector snall have announced over the page party system that the TSC is activated. 5.15 As subsequent relief personnel fill the positions identified in paragraph 5.10, direct them to complete checklists for their respective position.
6.0 REFERENCES
6.1 EPIP l-0, Event Classification 7.0 ATTACHMENTS
- 1. TSC Layout
- 2. Technical Support Center Comunications
- 3. Emergency Position Locations
- 4. Emergency Director Checklist Rev. 0 3/4/83
EPIP l-9 Page 4 of 12 O . 5. Radiological Assessment Coordinator (RAC) Checklist
- 6. Operational Assessment Coordinator (0AC) 7 Site Support Coordinator (SSC)
- 8. Corrective Actions Coordinator (MC) Checklist
- O 1
f 4 e 't 4 O Rev. 0 3/4/83
F Also Available On e Asiertiira Card 1 PROTECTIVE ACTION CUIDES U
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@ TELEPHONE TERMINALS EPIP 1-9 Page 5 of 12 (YOUT @ RA I PH NE TERMINALS Attachment 1 g6 GAI-TRONICS - RECEIVE Page 1 of 1 4 TRANSMIT q GAI-TRONICS - RECEIVER 3 8 3
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EPIP 1-9 Page 6 of 12 () Attachment 2 , () Page 1 of 1 TECHNICAL SUPPORT CENTER C(BO4UNICATIONS l Communication Line Communication Position Number Designation (s) . Terminal Box 1 G-1, G-2 T 4 2 H-1, H-2 T 8 3 C-1, C-2, C-4, D-1 T) , Rj 4 M-1, M-2, E-1 T,R 3 2 5 A-1, A-2, A-3 T 6 6 J-2, H-3 T,T 8 9 7 F-1, F-2 T 5 8 --- -- 9 L-1, L-2, L-3 T,R 2 3 10 --- -- 11 --- -- 12 C-5 Tj 13 C-3 Tj 14 B-1 T 7 15 --- -- 16 B-3 T 7 17 --- -- 18 B-2 T 7 19 B-1 T 7 20 H-4 T 8 21 J-1 Tg 22 J-3, J-4 T 9 23 K-1, K-2, K-3 T 10 24 J-5, J -6, J -7 Tg 25 P-1 T 12 26 N-1 T 13 27 R-2, R-3 T jj O
; Rev. 0 3/4/83
EPIP 1-9 Page 7 of 12 Attachment 3 L Page 1 of 1 EERGENCY POSITION LOCATIONS
- 1. Emergency Director
- 2. Emergency Planning Advisor #2
- 3. Operations Assessment Coordinator
- 4. Radiological Assessment Coordinator
- 5. Site Support Coordinator
- 6. Emergency Coinnunications Liaison
- 7. Environmental Assessment Coordinator (Onsite Radiation Assessment Coordinator)
- 8. Dose Assessment Staff (Onsite Radiation Assessment Assistant)
- 9. Dispatcher
- 10. Radiation Protection Coordinator ,
- 11. Chemistry Coordinator
- 12. Maintenance Coordinator
- 13. Operations Coordinator
- 14. Core Assessment Coordinator
- 15. Engineering Coordinator
- 16. Electrical Engineer i 17. Chemical Engineer
- 18. Quality Assurance Engineer
- 19. Mechanical Engineer
- 20. Administrative Supervisor
- 21. Administrative Support
- 22. Communicator #2
- 23. Communicator #3
- 24. Communicator #4
- 25. Conference Room
- 26. Telecopy Machine O
Rev. 0 - 3/4/83
EPIP l-9 Page 8 of 12 Attachment 4 O Page 1 of 1 EE RGENCY DIRECTOR CHECKLIST Date/ Time Initial s Action Items
/ 1. Relief Emergency Director, contact the Onshirt Emergency Director and discuss:
/ a. Status of plant conditions including emergency classification and corrective actions underway.
/ b. Which Emergency Action Level (EAL) was exceeded to cause the emergency condition.
/ c. Reconnended protective actions made to data and his knowledge of the implementation of these CI actions.
/ 2. Confer with the EPA #2 on the status of activation.
/ 3. Relief Emergency Director, cetennine if adequate staff is on hand to support complete activation of TSC, if so activate.
/ 4. Notify the Onshift Emergency Director that you have relieved him of the Emergency Director Posi tion.
Rev. 0 3/4/83
EPIP l-9 Page 9 of 12 (gy Attachment 5 Page 1 of 1 RADI0 LOGICAL ASSESSMENT COORDINATOR (RAC) CHECKLIST Date/ Time Initials Action Items
/ 1. Perform survey of TSC. First arrival check that all materials needed to perform assessments are available.
/ a. Procedure and forms.
/ b. Walkie-talkie for field team communications.
/ c. Check all monitoring equipment. Turn on continuous Air Monitor.
/ 2. The relief RAC contact the Onshift RAC and determine:
C ( / a. Extent of radiological releases and plant conditions.
/ b. Meteorology.
l
/ c. Status of inplant surveys (if any)
/ d. Location and extent of any contaminated areas.
/ e. Projected offsite doses and Protective Action.
, Recommendations made to date. l l / 3. Once the relief RAC has l determined that adequate staff is on hand, he may relieve the l Onshift RAC. Notify the Emergency Director of this relief j action. Re v. 0 3/4/83
EPIP l-9 Page 10 of 12 Attachment 6 Page 1 of 1 OPERATIONAL ASSESSMENT COORDINATOR (0AC) Date/ Time Initials Action Items
/ 1. Determine plant status from the Shift Technical Advisor and the Onshift Operational Assessment
, Coordinator. ! / 2. Obtain infomation on plant status as it relates to core parameters in order to detemine current core conditions.
/ 3. Determine if any repairs or fire fignting activities are progressing.
/ 4. Once the relief 0AC has determined that acequate staff is on hand, he may relieve the
' Onshift 0AC. Notify the Emergency Director of this relief action.
O Rev. 0 3/4/83
. _ _ _ _ . ~ _ _ . . . _ . _ . - . - . _ _ _ . _ , . - . _ _ . . . . , _ _ _ _ _ _
l EPIP l-9 l Page 11 of 12 l O Attachment 7 Page 1 of 1 SITE SUPPORT COORDINATOR (SSC) Date/ Time Initials Action Items
/ 1. Determine if adequate administrative and logistics personnel are present to carry out duties.
/ 2. Ensure proper engineering support is available.
/ 3. Once the relief SSC has determined that adequate staff in on hand, he may relieve the onshift SSC. Notify the Emergency Director of this relief action.
O J O Rev. 0 3/4/83
EPIP l-9 Page 12 of 12 O Attachment 8 Page 1 of 1 l CORRECTIVE ACTIONS COORDINATOR (MC) CHECKLIST Date/ Time Initials Action Items
/ 1. Contact Operational Assessment Coordinator and determine:
/ a. Plant status as it affects maintenance or fire fighting.
, / b. Status of repairs or fire (if any) in progress.
/ 2. Determine how many support personnel are available at the OSC to support maintenance or fire fighting operations.
/ 3. Recommend that offsite fire fighting support be requested by l O the Emergency Director if conditions warrant.
/ 4. Once the relief MC has detennined that adequate staff is on hand, he may relieve the onshift MC.
[ Notify the Emergency Director of l this relief action. l l O Rev. 0 3/4/83
EPC em i EPIP l-10 Approved: g , Page 1 of 6 O, Plant Manager M Effective Datef 5/16/83
/ Onn h h9}f 44 wy EPIP l-10 OPERATIONAL SUPPORT CENTER (OSC) ACTIVATION 1.0 PURPOSE To describe the method to be used in the activation of the Operational Support Center.
2.0 RESPONSIBILITY The first person to arrive is responsible for implementing this procedure. The OSC Coordinator assumes responsibility upon arrival. O 3.0 PRECAUTIONS None 4.0 PMEREQUISITES Any of the following apply: 4.1 An Alert, Site Area Emergency, or General Emergency has been declared in accordance with EPIP l-0, Event Classi-fication. 4.2 The Emergency Director has ordered the activation of the TSC. f t O Rev. 0 3/4/83 _ . _ _ _ _ . _ _ _ . _ . _ _ _ _ _ ~ _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . . - _ _ . . _ _ _ _ . _ _ _ _ . _ - . --
l EPIP l-10 Page 2 of 6 5.0 ACTIONS 5.1 Set up tables as shown in Attachment 1. 5.2 Remove phones from the OSC Emergency Closet, plug them , into jack's bearing their numbers (see Attachment 2 for the location of these jacks), and test to insure opera-bility by contacting person at the other end. i 5.3 Ensure that all monitoring equipment is in its proper place and that a qualified Health Physics person is checking operations on cach piece of equipment. 5.4 Position status board in place. 5.5 Place signs, located in the OSC Emergency Closet, on table by joo classification as shown in Attachment 1. l 5.6 As personnel arrive, instruct them to sit in the appro-priate location by job classification. 5.7 Determine if manpower support available at the OSC is adequate. If not, request additional manpower through a Control Room or TSC communicator. 5.8 Notify the Corrective Actions Coordinator that the OSC is activated and report the number of personnel available.
6.0 REFERENCES
; None O
4 Rev. 0 3/4/83
EPIP l-10 Page 3 of 6 7.0 ATTACHENTS
- 7.1 OSC Layout 7.2 OSC Phone Diagram O
O Rev. 0 l 3/4/83
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EPIP 1-10 STORAGE CLOSET Page 5 of 6 Attachment 2 O DSC PHONE DIAGRAN Page 1 of 2 Og s e . m m m m o C ( ) C
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EPIP l-10 Page 6 of 6 O- Attachment 2 Page 2 of 2 OSC PHONE DIAGRAM (continued) TELEPHONE COM4UNICATION LIST
- 1. OSC Supervisor
- a. Direct Line to Control Room (DL-05) 4
- b. Direct Line to Technical Support Center (Dl-04)
- c. Internal Extension (IE-11)
- d. Direct Dial (DD-30)
O 2. Radiation Protection Technician Internal Extension ~ (IE-13)
- 3. Electrician /I&C Technician Internal Extension (IE-12) i t
]
i O Rev. 0 3/4/83
EPC -T-- EPIP l-11 ant M ager Effective Date 75/16/83
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EPIP l-11 OPERATIONAL ASSESSMENT _x w/. 1.0 PURPOSE To provide instructions for assessing the operational aspects of an emergency as a basis for recommending and implementing corrective and/or protective actions. 2.0 RESPONSIBILITY This procedure is the responsibility of the Shift Technical Advisor until the TSC has been activated, at which time the O Core Evaluation Coordinator will implement this procedure. 3.0 PRECAUTIONS None 4.0 PREREQUISITES ! None l I I V Rev. 0 I 3/4/83
EPIP l-11 O v Page 2 of 7 5.0 ACTIONS 5.1 Perform a quick verification of the classification of the event using EPIP l-0, Event Classification. 5.2 Verify that operator actions have been initiated and are adequate to terminate and/or mitigate the consequences of the event. 6.3 To determine if the containment has been breached, perform the following: 5.3.1 Check control room isolation panel. 5.3.2 Check to see if containment pressure exceeds O . design basis (41.9 psig). 5.3.3 Using Radiation Monitoring System (RMS), check - the Area Radiation Monitors in the secondary containment. 5.4 To determine if containment will be breached, perform the following: l 5.4.1 Trend containment pressure. 5.4.2 Determine the time when the pressure is going to l l exceed design basis pressure (41.9 psig). 5.5 Check water level in the reactor vessel. If decreasing, trend decrease and make core uncovery projection. Report your findings to the Emergency Director. Rev. 0 3/4/83 l - - - - , . . _ . - _ _ _ _ _ _ ___ _ _ _ _ _ __ _ _ _ _ _ _ . _ _ _ , _ __ ,
EPIP l-11 Page 3 of 7 5.6 For a pipe break inside primary containment, obtain the time after scrom and the reading of the drywell radiation monitor; if not pipe break, proceed to Step S.9. Time after scram Drywell Radiation Monitor 5.7 Locate tne appropriate point on the attached graphs. See Attachment 1 through 3. I I l CAUTION l 1 l l CHECK ALL THREE GRAPHS SINCE CURVES OVERLAP. I I i v i 5.8 Report to the Emergency Director (ED) and the Radiological Assessment Coordinator (RAC) if any core damage has occurred. 5.9 If you do not have a pipe break inside primary containment, evaluate the Emergency Action Level (EAL)
- used in classification to see if it is one that potentially could lead to core failure.
5.10 If core failure is possible, inform the EU and RAC of your conclusions. i 5.11 Request tne RAC to assess core damage by implementing EPIP 2-25, Detemination of PASS Sample Location. !O Rev. 0 3/4/83
EPIP l-11 Page 4 of 7 5.12 Request the RAC evaluate plant conditions using the following: EPIP 2-7, Post-Accident Gaseous Effluent Sampling EPIP 2-13, Post-Accident Liquid Effluent Sampling 5.13 Meet with the ED cnd discuss: 5.10.1 Present and projected plant operating conditions, 5.10.2 Necessary repair / corrective actions. 5.14 Continue monitoring operational aspects of the emergency and provide updated information to the ED if any change in condition occurs. C
6.0 REFERENCES
6.1 EPIP l-0, Event Classification 6.2 EPIP l-14, Core Evaluation 6.3 EPIP 2-7, Post-Accident Gaseous Effluent Sampling 6.4 EPIP 2-9, Post-Accident Primary Coolant Sampling 6.5 EPIP 2-11, Post-Accident Containment Air Sampling 6.6 EPIP 2-13, Post-Accident Liquid Effluent Sampling 7.0 ATTACHMENTS
- 1. Drywell High-Range Monitor Response - DBA LOCA Without Core Damage
- 2. Drywell High-Range Monitor Response - DBA LOCA With Core Inventory - Noble Gas Release
- 3. Drywell High-Range Monitor Response - DBA LOCA Witn Core Inventory - Noble Gas and Halogen Release Rev. 0 3/4/83
w- % 5-S N g, >3 D SHOREHAM NUCLEAR POWER STATION l $. es DRYWELL HIGH-RANGE MONITOR RESPONSE UNDER VARIOUS LOCA SCENARIOS p "E N io s (2 -.j@q 5 5 0 M WT - N O DRY WE LL,L,E?,A,h *,K A, G.E , G, A M M A, M'*N E.R.vGY RESPONSE) E Io. m, o E t..> io m 7m t;' n. '**.y'"' -v' W
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EPC 4e M '- EPIP l-12 Page 1 cf 9 Approved: 77 O Plant Manager y / Effective Date 5/16/83 CouT!!eumem'a e t/< EPIP 1-12 EMERGENCY REPAIR AND CORRECTIVE ACTIONS 1.0 PURPOSE To provide instructions for emergency repair and corrective actions. 2.0 RESPONSIBILITY 2.1 The Watch Supervisor / Operational Assessment Coordinator i (OAC) is responsible for determining the need for Repair and Corrective Actions. 2.2 Tne Emergency Director (tu) is responsible for making the final decision relative to the need for and timing of Repair and Corrective Actions operations. 2.3 If the TSC is operational, the Corrective Action Coorainator is responsible for preplanning ana coordinating manpower and equipment needs. If the TSC is not operational, then tnis is the responsibility of the Watch Supervisor. i 2.4 The Repair anu Corrective Action Team is responsible for perfonning the actual repair / corrective action task. l Rev. 0 3/4/83 l
EPIP l-12 Page 1 of 9 3.0 PRECAUTIONS 3.1 The actual / potential radiological impact of corrective actions on personnel and the environment must be consicered in comparison with the benefits to be derived from the performance of the action. 3.2 Repair operations requiring design or configuration alteration shall follow LILCO's normal design change procedures. 4.0 PREREQUJSITES 4.1 A repair / corrective action has been deeued necessary by the Operational Assessment Coordinator (0AC)/ Watch () Supervisor. 4.2 Any design changes reflected in a repair have been i properly approved and documented. 4.3 Use Radiation Work Permits (RWPs), Maintenance Work Requests (MWRs) Station Equipment Clearance Permit ! (SECP) whenever time allows. l i 4 4 O Rev. O ' i 3/4/83 1
l l l EPIP l-12 ; Page 2 of 9 l 5.0 ACTIONS 5.1 Corrective Action Coordinator (CAC)/ Watch Supervisor l l l CAUTION I I I I IF OSC IS~NOT ACTIVATED, WATCH SUPEP. VISOR l l FORM A CORRECTIVE ACTION TEAM. I I I 5.1.1 Contact the Operational Support Center (OSC) Coordinator by intraplant telephone. 5.1.2 Inform tne OSC Coordinator of your need for a Corrective Action Team and specify the
' composition of that team (e.g., electricians, mechanics, etc.), depending on skills required.
I 1 l CAUTION I I I I IF ENTRY INTO A HIGH RADIATION AREA i 1 IS REQUIRED, INSURE THAT A HEALTH I l PHYSICS TECHNICIAN IS PART OF THE l l TEAM. l l l 5.1. 3 Instruct the OSC Coordinator to:
- a. Assemble a Corrective Action Team.
- b. Assign a Team Leader.
O Rev. 0 3/4/83
EPIP l-12 Page 3 of 9 . O-
- c. Direct team to report to the TSC/ Control Room for a briefing with the CAC/ Watch Supervisor and Radiation Protection Coordinator (MPC)/ Radiological Assessment Coordinator (RAC).
5.1. 4 Briet the Corrective Action Team and fill out the Corrective Action Team Briefing Form ( Attachment 1). The briefing should cover the following (as
.a minimum):
- a. Team identification.
- b. Nature of corrective actions.
() c. Communications equipment and channel.
- d. Required equipment (including keys for tool / store room).
5.1.5 Request the RPC/RAC to brief the team on required radiation protection. 5.2 Team Leader
- 5. 2.1 Ensure that the RPL/RAC covers the following items (as a minimum) in his briefing:
- a. Protective equipment (including use of KI).
- b. Authorized doses.
() 5.2.2 Receive Corrective Action Team Briefing Form (Attachment 1). Rev. 0 3/4/83 r*- pw- -- . . -
EPIP l-12 Page 4 of 9 jO
. 5.2.3 If Potassium Iodide (KI) administration is necessary, insure all team members take one table ; at this time and place, and inform the RPC/RAC. ]
5.2.3 Log predep1oyment personnel self-reading dosimeter readings on the Briefing Form. 5.2.4 Return to the OSC and assemble required protective and corrective action equipment and verify the following:
- a. Availability and accessability of all required corrective action equipment.
! b. High-range survey equipment operability (if
- required) .
- c. Personnel self-reading dosimetry for each team member:
i (0-200 mR) l
- (0-5 R) l l
- d. Protective clothing for each team member (if required).
- e. Team composition.
I 5.2.5 Perform a communications check with the CAC. ! Maintain proper communications practices and I always identify both parties, e.g., Corrective Action Team #1 to Corrective Action Coordinator.
'O ,
Rev. 0 f 3/4/83 i
i , l EPIP l-12 Page 5 of 9 5.2.6 Dress in appropriate protective clothing. 5.2.7 Implement one of the following if necessary:
- a. Section 5.3 of EPIP 2-4, Inplant Surveys
- b. Section 5.3 of EPIP 2-5, Unsite Surveys 5.2.8 Instruct team members to stay in visual contact i
i at all times. 5.2.9 Maintain communications with the CAC/ Watch Supervisor at all times. l 5.3 Decontamination / Return to OSC l 5.3.1 Follow normal Station Health Physics procedures when exiting radiation areas (SP62.026.03, 62.004.21, 62.040.01). 5.3.2 Return to the OSC with the Team. i 5.3.3 Inform the OSC Coordinator and the CAC that you I have returned and are available for further duty. }
6.0 REFERENCES
6.1 EPIP 2-4. Inplant Surveys 6.2 EPIP 2-5, Onsite Surveys 6.3 EPIP 2-16, Radiation Protection During Emergencies 6.4 SP62.004.21, Use of Direct Reading Dosimeters j 6.5 SP62.026.03, Use of Protective Clothing 6.6 SP62.040.01, Personnel Decontamination i Rev. 0 3/4/83
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EPIP l-12 Page 6 of 9 O 7.0 ATTACHENTS
- 1. Corrective Action Team Briefing Fonn O
O Rev. 0 3/4/83
. EPIP l-12 Page 8 of 9 Attachment 1 m) Page 1 of 2 l
CORRECTIVE ACTION TEAM SkIEFING FORM
- 1. Date: Time: Briefing at: Team ID:
- 2. Briefing by: (CAC)
(RPL)
- 3. Unusual Area /Env. Conditions:
- 4. Communications Extensions:
CAC-TSc: OSC: CONTROL RM:
- 5. Required Equipment:
Keys Other
- 6. Team member names and authorized doses (rem):
Lead Dose rem Asst. Dose rem
- 7. Protective Equipment (check applicable):
(1) DRus (200 mK & 5R) (2) TLD (WB/ Extremity) (3) Respirator w I/P Canister (4) SCBA (b) High Range Survey Equipment (6) Glove i (7) Bootie i (8) Coverall l (9) Hood (10) KI ! (11 ) ! (12) (13) i 1O l Rev. 0 3/4/83
i l EPIP l-12 Page 9 of 9 Attactment 1 Page 2 of 2 CORRECTIVE ACTION TEAM BRIEFING FORM (continued)
- 8. Team dosimeter readings (Before/After Mission):.
Lead (200 mR Scale) / ; (SR Scale) / Asst. (200 mR Scale) / ; (SR Scale) /
- 9. Special Instructions:
J t 1 O 9 l l l l O ! Rev. O ! 3/4/83 l l
EPC & ^ 'EPIP l-13 Approved: g[ Page 1 of 6 Plant Manager .V tffective Date 75/16/83 CWiT!!P~nmggpf.n,,.
-m u EPIP l-13 EMERGEkCY RADI0 CHEMISTRY OPEkAlIOkS 1.0 PURPUSL lo describe the procedure to be followed for the conduct of radwaste operations during emergency conditions.
2.0 ktSPut<SIBILIllES Ine l,hemistry Coordinator is responsible for implementation of this procedure. O 3.0 PktCAulIUleS 3.1 Reduce liquid waste tankage to minimum content during the immediate post-accident plant operations. 3.2 Operating personnel must anticipate and report liquid waste generation and rates due to limited radwaste storage capacity. 4.0 PkLRLQUIS11 LS 4.1 lhe on-shift response organization has been augmented and the 150 and USC are operational. O Rev. 0 3/25/83
EPIP l-13 Page 2 of 5 , 5.0 AtlIONS 5.1 Lhemistry Coordinator 5.1.1 tstablish and maintain a log to track liquid and solid waste accumulation and generation. 5.1. 2 1 rend storage capacity vs. weste generation to ensure adequate reserve capacity is maintained. 5.1.3 Lonfer with the Radiological Assessment Coordinator (RAC) on Post-Accident Sampling I requirements for Operational Assessment and Radwaste Operations. 5.1. 4 when directed by the RAL, contact the Operational ((-) _/ Support Center (USC) Coordinator and request that a Radiochemistry lechnician be sent to the TSC for a briefing. Upon arrival intond the Radiochemistry Technician
~
5.1. 6 to (if necessary):
- d. Obtain samples per:
LPIP 2-7, Post-Accident baseous Effluent Sampling LPlP 2-9, Post-Accident Primary Coolant Sampling
- LPIP 2-11, Post-Accident Containment Air Sampling Rev. 0 3/25/83
i EPIP l-13 Page 3 of 5
' LPIP 2-13, Post-Accident Liquid Ef tluer.t Sampling I I I CAUTION l l l l ADVISE RADI0 CHEMISTRY TECHNICIAN l l TO TAKE SUFFICIENT SAMPLES TO l l SATISFY ThE REQUIREMENTS OF l l SP71.020.02, LIQUID WASTE RE- l l LEASE ANALYSIS AND DISCHARGE l l AUTh0RIZAlION. l l l l l l CAUTION l l l 1 AbVISE RADIOCHEMISTRY TECHNICIAN l O
l ON ROUTE TO APPROPRIATE SAMPLE O l LOCATION WHICH WILL NOT SUBJECT l I l hlM TO EXPOSURES IN EXCESS OF l l GUIDELINES PROVIDED IN EPIP 2-161 l l
- b. Report to the kadiation Protection Coordinator for a briefing.
5.1.6 Provide the Radiochemistry Technician with a completed briefing Forta (attachment from appropriate procedure above). i 1 5.1. ~/ af ter sampling is accomplished, perforin radiochemistry analysis in accordance with the following procedures: LPIP 2-8, Post-Accident baseous tffluent Sample Analysis Rev. 0 3/25/83
EPIP l-13 Page 4 of 5 EPIP 2-10, Post-Accident Primary Coolant Sample Analysis
- LPlP 2-12, Post-accident Lontainment Air Sample Analysis EPlP 2-14, Post-Accident Liquid Effluent Sample Analysis 5.1. 6 Provice sample analysis results from LPIPs 2-10 and 2-12 above to the RAC and the Core Lyaluation Loordinator for core evaluation and operational assessment.
5.1.9 btilize the results of LPIPs 2-8 and 2-14 n
'd above to establish the need for and prediction of gaseous and liquid releases.
5.1.10 Advise Radiological Assessment Loordinator of impending need for_ gaseous or liquid releases and, upon his direction, implement LPlP 2-22, Plannea Liquid Keleases During tmergencies and/or LPIP 2-23, Planned Containment Releases uuring tmergencies.
- I l I CAUTION l I I I Il4PLLl1ENTATION OF LPIPs 2-22 AND l l 2-23 WILL NECESSITATE A REEVALUATION l
. 1 0F PROJECTEU DOSES IN ACCORDANCE i I l WITh EPIP 2-2, DOSE PROJEC110NS. l 1 l O Rev. 0 3/25/83
EPIP 1-13 Page 5 of 6 u
6.0 REFERENCES
6.1 LPIP 2-2, Dose Projections 6.2 LPIP 2-7, Post-Accident Gaseous Effluent Sampling 6.3 LPIP 2-8, Post Accident taaseous Effluent Analysis 6.4 EPIP 2-7, Post-Accident Gaseous Effluent Sampling 6.5 LPIP 2-9, Post-Accident Primary Coolant Sampling 6.6 EPIP 2-11, Post-Accident Containment Air Sampling 6.7 LPIP Z-11, Post-Accident Containment Air Sampling 6.8 LPIP 2-13, Post-Accident Liquid tffluent Sampling 6.9 tPIP 2-14, Post Accident Liquid Effluent Sample Analysis 6.10 LPlP 2-22, Planned Liquid Releases buring Emergencies 6.11 LPIP 2-23, Planned Containment Keleases During Emergencies b.12 SP71.020.02, Liquid Waste Release Analysis and bischarge authorization 7.0 AllAChhENlb None l O Rev. 0 3/25/83
/
EPC . EPIP 1-14 Approved: 77 / Page 1 of 44 Plant Manager M k&,v/n/'.',/' D Effective Date //5/16/83 f.h jf 'tGe EPIP 1-14 CORE DAMAGE ESTIMATION b 1.0 PURPOSE To estimate the degree of core damage based on fission product concentration in gaseous or liquid samples taken from the 1 Post-Accident Sampling Facility under accident conditions. 2.0 RESPONSIBILITY t Implementation of this procedure is the responsibility of the Core Evaluation Coordinator in the TSC. 3.0 PRECAUTIONS N/A f 4.0 PREREQUISITES \ - 4.1 The TSC is activated. 4.2 Core damage is suspected based upon results of EPIP 1-11, Operational Accident Assessment. AND l 1 i !O i Rev. O I 4/23/83 i
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EPIP l-14 Page 2 of 44 Either/both of the following apply: 4.3 A post-accident sample has been taken in accordance with EPIP 2-9, Post-Accident Primary Coolant Sampling and analyzed in accordance with EPIP 2-10, Post-Accident Primary Coolant Sampie Analysis. 4.4 A post-accident sample has been taken in accordance with EPIP 2-11, Post-Accident Containment Air Sampling and analyzed in accordance with EPIP 2-12, Post-Accident Containment Air Sampie Analysis. O O Rev. 0 4/23/83
EPIP 1-14 Page 3 of 44 O 5.0 ACTIONS I . l l CORE DAMAGE EVALUATION FROM GASE0US SAMPLES - SECTION 5.1 l 1- l l CORE DAMAGE EVALUATION FROM LIQUID SAMPLES - SECTION 5.2 l l l 5.1 Core Damage Evaluation from Gaseous Samples 5.1.1 Complete the Containment Atmosphere Sample Worksheet ( Attachment 1) as follows:
- a. Record the following items from the PASS Atmosphere Data Sheet (EPIP 2-11):
Sample # (item 1) Date (item 1) Time (item 1) Sample location (item 2) RM-013 initial monitor reading (item 3) RM-013 monitor reading after final dilution l (item 4) Sample vial parameters (items 10a and 10b) l l b. Calculate the sample dilution factor (item 5) i
- c. Record the following items from the PASS Atmosphere Sample Analysis Data Sheet (EPIP j
2-12) : Date/ time counting began (item 6a) i Date/ time counting ended (item 6b) f O. Rev. O i 4/23/83
EPIP l-14 l Page 4 of 44 O
- d. Calculate the spectrometer counting time (item 6c).
I I I CAUTION I I l l WHEN TAKING TIME AVERAGE USING l l DATES AND TIMES, BE CAREFUL I I ABOUT TAKING AVERAGES FOR I l DIFFERENT DAYS. I I I
- e. Using infonnation from Plant Status Data Sheet (EPIP 2-25), record the following items:
Date/ time of reactor scram (item 7) Drywell or Suppression Chamber temperatures O v and pressure (items 9a and 9b) i l l CAUTION I I I I IF SAMPLE LOCATION IS THE l l DRYWELL, USE DRYWELL TEMPERATURE I l AND PRESSURE. 1 I I I IF SAMPLE LOCATION IS THE SUP- l l PRESSION POOL, USE SUPPRESSION l l P0OL AIR TEMPERATURE AND I l PRESSURE. I I I Energy generated (items 12a, b, and c). O Rev. 0 4/23/83
l EPIP l-14 Page 5 of 44 O
- f. Calculate the decay time (item 8), sample location parameters (item 9 - in proper units), sample vial parameters (item 10 - in proper units), pressure temperature correction (item 11), and power level correction (item 12).
- g. Choose three isotopes (item 13) from the following list:
Kr-85m Kr-87 Kr-88 Xe-133 Xe-135 O Use a second worksheet if additional isotopes are chosen. I I l CAUTION l l 1 i THE ISOTOPES CHOSEN MUST HAVE I I MEASUPED SAMPLE VIAL CONCENTRA- l l TIONS (uC1/ml) FROM THE PASS l l ATMOSHPERE SAMPLE ANALYSIS DATA I I SHEET (EPIP 2-12). I I I ' h. Record half-lives from Half-life Tabic ( Attachment 2) in item 14. ( Rev. 0 4/23/83
. - , . _a-n,.,.- s --, . . -.- ,, ,,,, _ . , .,,, ,n ,. , , , _ _ , , , , , , , , , , _ , , , , , , - - - - - - . , ,mm,,- , m,_en, _,_, ,,,,_._,, , ,,,,,__ ,-- ,,.,___ ,,. ,,, ,
EPIP l-14 Page 6 of 44 I I l CAUTION I I I l ENSURE HALF-LIVES ARE CONVERTED l l TO UNITS OF HOURS, IF NECESSARY. I I i
- 1. Calculate decay constant (item 15) and decay correction (itea 16).
- j. Record uncorrected measured concentration in sample vial (from EPIP 2-12) in item 17.
- k. Calculate corrected concentration to scram time and full power (item 18) and total i activity released (items 19a, b, and c).
I 1. Detemine continuous power irradiation period (item 20a), look up core isotope inventory (item 20b), and convert to proper units (item 20c).
- m. Complete items 21 through 23 of the worksheet.
5.1.2 For each isotope, look at the clad failure ratio (item 23). l l a. If the clad failure ratio is less than or equal to 1, then core damage may have occurred for that fraction of the core (e.g., Clad failure ratio = 0.5, then core damage may have occurred for up to 50% of the core). Do not perform Steps 5.1.3 and 5.1 4. Rev. 0 4/23/83
EPIP l-14 Page 7 of 44
- b. If the clad failure ratio is greater than 1, clad failure has occurred and proceed to Step 5.1.3 for estimate of fuel overheating.
5.1. 3 For each isotope, look at the fuel overheat ratio (item 25).
- a. If the fuel overheat ratio is less than or equal to 1, fuel overheating may have occurred for that fraction of the core (e.g.,
Fuel overheat ratio = 0.2, then fuel overheating may have occurred for up to 20% of the core). Do not perform Step 5.1.4.
- b. If the fuel overheat ratio is greater than 1, fuel overheating has occurred and proceed to l
Step 5.1.4 for estimate of melting / fragmentation. 5.1. 4 For each isotope, look at the melt / fragment ratio (item 26). This ratio indicates that melting or fragmentation may have occurred for that fraction l of the core (e.g., Melt / fragment ratio = 0.3, then melting or fragmentation may have occurred for up to 30% of the core). l ! 5.1. 5 Enter conclusion (item 27) on worksheet and ' submit to the Operations Assessment Coordinator. T 3
+
5 h % l i O '
- Rev. 0 .
N 4/23/83 ' l , l q j
; s N -
. . __ .- - _. . - .. .~ _ - - _ - - - - . -. --
EPIP l-14 ' Page 8 of 44 O 5.2 Core Damage Evaluation from Liquid Samples
- 5.2.1 Complete the Liquid Sample Worksheet ( Attachment
- 6) as follows: -
- a. Record thC following items from the PASS Coolant Data Sheet (EPIP 2-9):
Sample # (item 1) Date (item 1) i Time (item 1) ! Sample location (item 2) lO i RM-Oll initial monitor reading (item 3) RM-011 monitor reading after final dilntion
-(item 4)
- b. Calculate the sample dilution factor (item 5).
- c. Record the following items from the PASS Coolant Sample Analysis Data Sheet (EPIP l\ 2-10):
Date/ time counting began (item 6a) Date/ time counting ended (item 6b) ? 4 Rev. 0
' 4/23/83 1m N
1 _ _.a -
EPIP l-14 Page 9 of 44 O
- d. Calculate spectrometer counting time (f tem 6c ) .
I i l CAUTION I I I l WHEN TAKING TIME AVERAGE USING l i DATES AND TIME, BE CAREFUL l l ABOUT TAKING AVERAGES FOR I I DIFFERENT DAYS. I I I
- e. Using information from the Plant Status Data Sheet (EPIP 2-25), record the following items:
Date/ time of reactor scram (item 7) () Energy generated (items 9a, b, and c)
- f. Calculate the decay time (item 8) and power l
level correction (item 9)
- g. Choose three isotopes (item 10) from the following list:
I-1 31 I-132 I-133 I-134 I-135 i Use a second worksheet if additional isotopes dre chosen.
- O Rev. 0 4/23/83
EPIP l-14 Page 10 of 44 I I l CAUTION l l l l THE ISOTOPES CHOSEN MUST HAVE l l MEASURED SAMPLE VIAL CONCENTRA- l l TIONS (uC1/ml) FROM THE PASS I l COOLANT SAMPLE ANALYSIS DATA l l SHEET (EPIP 2-10). I I l
.h. Record half-lives from Half-life Table
( Attachment 2) in item 11. I i l CAUTION I I I I ENSURE HALF-LIVES ARE CONVERTED l l TO UNITS OF HOURS, IF NECESSARY. I
- 1. Calculate decay constant (item 12) and decay correction (item 13).
- j. Record uncorrected measured concentration in sample vial (from EPIP 2-10) in item 14.
- k. Calculate corrected concentration to scram time and full power (item 15).
- 1. Check sample location recorded on PASS Coolant Sample Data Sheet (EPIP 2-9) in item 16.
- m. Complete items 17 through 22 of the worksheet.
Rev. 0 4/23/83
EPIP l-14 Page 11 of 44 5.2.2 For each isotope, look at the clad failure ratio (item 22). f
- a. If the clad failure ratio is less than or equal to 1, then core damage may have occurred for that fraction of the core (e.g.,
Clad failure ratio = 0.5, then core damage may have occurred for up to 50% of the core). Do not perfonn Steps 5.2.3 and 5.2.4
- b. If the clad failure ratio is greater than 1, clad failure has occurred and proceed to Step 5.2.3.
5.2.3 Complete items 23 through 25 of the worksheet. O 5.2.4 For each isotope, look at the melt / fragment ratio (item 25).
- a. If the melt / fragment ratio is less than or equal to 1, then melting or fragmentation may have occurred for that fraction of the core (e.g., melt / fragment ratio of 0.3 is equivalent of up to 30% core melt or fragmentation).
- b. If the melt / fragment ratio is greater than 1, melting or fragmentation may have occurred for the entire core.
O Rev. 0 4/23/83
EPIP 1-14 Page 12 of 44 O 1 I l CAUTION I I I I IF IMPROVED ESTIMATES OF MELTING l l OR FRAGMENTATION FRACTIONS ARE I I DESIRED, CONTINUE WITH STEP l l 5.2.6. I I I 5.2.5 Enter conclusions (item 41) on the worksheet and submit to the Operations Assessment Coordinator. 5.2.6 Complete the remainder of the worksheet as follows:
- a. Select three non-volatile isotopes and enter on line 26.
I I 1 CAUTION I I I I GIVE PREFERENCE TO CS-134, l I Cs-137, Sr-92, AND La-140. FOR I l OTHER ISOTOPES, CHOOSE LONG l l l HALF-LIVES (SEE ATTAC}9 TENT 2). I I I i i ISOTOPES CHOSEN MUST HAVE l l l MEASURED SAMPLE VIAL CONCENTRA- l l l TIONS (uCf/ml) FROM THE PASS l I COOLANT SAMPLE ANALYSIS DATA I l l SHEET (EPIP 2-10). l I I
- b. Detennine half-life (item 27), decay constant (item 28), and decay correction (item 29).
Rev. 0 4/23/83
EPIP 1-14 Page 13 of 44 V l I l CAUTION I I I l ENSURE HALF-LIFE OBTAINED FROM l l ATTACMENT 2 IS CONVERTED TO l I HOURS. l I I
- c. Record uncorrected neasured concentration in sample vial (from EPIP 2-10) in item 30.
- d. Complete items 31 through 37 on the worksheet.
5.2.7 For each isotope, look at the melt / fragment ratio (item 37).
- a. If the clad failure ratio is less than or
. equal to 1, then core damage may have occurred for that fraction of the core (e.g.,
clad failure ratio = 0.5, then core damage may have occurred for up to 50% of the core). Do not perfonn Steps 5.2.8 and 5.2.9. i b. If the clad failure ratio is greater than 1, clad failure has occurred and proceed to Step 5.2.9. 5.2.8 Complete items 38 through 40 of the worksheet. 5.2.9 For each isotope, look at the melt / fragment ratio l (item 40). l iO Rev. 0 4/23/83 l
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EPIP l-14 Page 14 of 44
- a. If the melt / fragment ratio is less than or equal to 1, then melting or fragmentation may have occurred for that fraction of the core (e.g., melt / fragment ratio of 0.3 is equivalent of up to 30% core melt or fragmententation).
- b. If melt / fragment ratio is greater than 1, melting or fragmentation may have occurred for the entire core.
5.2.10 Enter conclusions (item 41) on the worksheet and submit to the Operations Assessment Coordinator.
6.0 REFERENCES
O 6.1 EPIP 1-11, 0perational Accident Assessment 6.2 EPIP 2-9, Post-Accident Primary Coolant Sampling 6.3 EPIP 2-10, Post-Accident Primary Coolant Sample Analysis 6.4 EPIP 2-11, Post-Accident Containment Air Sampling i 6.5 EPIP 2-12, Post-Accident Containment Air Sample Analysis l 6.6 EPIP 2-25, Detemination of PASS Sample Location 6.7 LILCO Calculation # (later) 7.0 ATTACHENTS
- 1. Containment Atmosphere Sample Worksheet
- 2. Half-Life Table
- 3. Xe-135 Correction Factor Graph
- 4. Core Isotope Inventory
- 5. Fractional Release Ratios
- 6. Liquid Sample Worksheet (V 7. Fission Product Release Fractions Rev. 0 4/23/83 l
EPIP 1-14 Page 15 of 44 Attachment 1 Page 1 of 8 CONTAINMENT ATMOSPHERE SAMPLE WORKSHEET
- 1. Sample # Date Time (u'se 24-hr. clock)
- 2. Sample location
- 3. RM-013 gamma radiation monitor initial reading mr/hr
- 4. RM-013 gamma radiation monitor mading after final dilution mr/br
- 6. Sample dilution factor (choose a or b):
- a. If item 3 is equal to or less than 2 mr/hr, Sample dilution factor = 1
- b. If item 3 is greater than 2 mr/hr,
(
\'
Sample dilution factor = item 3/ item 4 =
- 6. Spectrometer counting time (use 24 hour clock)
- a. Date/ time counting began
- b. Date/ time counting ended
- c. Spectrometer counting time =
l item 6a + item 6b = 2 l l l CAUTION I I l l WHEN TAKING TIME AVERAGE USING DATES AND TIMES,I I BE CAREFUL ABOUT TAKING AVERAGES FOR DIFFERENT l l DAYS. l I I
- 7. Date/ time of reactor scram (use 24 hour clock)
Rev. 0 4/23/83
e EPIP 1-14 Page 16 of 44 O Attachment 1 U Page 2 of 8 CONTAINE NT ATMOSPHERE SAMPLE WORKSHEET (continued)
- 8. Decay time = item 6c - item 7 = hrs
- 9. Sample location parameters (units in atm and *R):
- a. Pressure = psig = atm i
(atm = (1 + psig)/14.7)
- b. Temperature = *F= *R
(*R = 460 + *F)
- 10. Sample vial parameters (units in atm and *R):
- a. Pressure = psig = atm (atm = (1 + psig)/14.7)
- b. Temperature = *F = *R
(*R = 460 + *F)
- 11. Pressure temperature correction
= (item 9a) (item .10b) = ( )( )=
= (item 10a) (item 9b) = ( )( )
i l CAUTION l l l l l l PRESSURES AND TEMPERATURES IN UNITS OF ATMOSPHERES I l AND DEGREES RANKINE, RESPECTIVELY. I I _l
- 12. Power level correction (complete a, b, and c):
- a. For isotopes with half-lives equal to or less than 24 hours:
W= 813 MWe x 24 hours = 813 x 24 = EPIP 2-25, Attachment 1, item 15a ( ) e t i G Rev. 0 4/23/83
EPIP 1-14 Page 17 of 44 Attachment 1 Page 3 of 8 CONTAINMENT ATMOSPHERE SAMPLE WORKSHEET (continued)
- b. For isotopes with half-lives greater than 24 hours and equal to or less than 72 hours W= 813 MWe x 14 days _ = 813 x 14 =
EPIP 2-25, Attachment 1, item 15b ( )
- c. For isotopes with half-lives greater than 72 hours:
W= 813 MWe x 30 days = 813 x 30 = EPIP 2-25, Attachment 1, item 15c ( )
- 13. Isotope (choose from the following list):
Kr-85m Kr-87 Kr-88 Xe-133 Xe-135 O l If more than three isotopes are chosen, use a second worksheet. l l i l CAUTION I ' I l ! l THE ISOTOPES CHOSEN MUST HAVE MEASURED SAMPLE VIAL i l CONCENTRATIONS (uC1/ml) FROM THE PASS ATM0 SPHEREI I I SAMPLE ANALYSIS DATA SHEET (EPIP 2-12). i I
- 14. Half-life (from Attachment 2) hrs I
i CAUTION I l l I l i l ENSURE HALF-LIVES ARE CONVERTED TO UNITS OF HOURS I I l IF NECESSARY. I I
- O Rev. 0 4/23/83
EPIP 1-14 Page 18 of 44 Attachment 1 O Page 4 of 8 CONTAINMENT ATM0 SPHERE SAMPLE WORKSHEET (continued) Isotope
- 15. Decay constant = .693/ item 14 hrs-I
- 16. Decay correction
= e(item 15 x item 8) l I
CAUTION I l I I 1 I FOR Xe-135 USE THE FOLLOWING: I I l A. IF ITEM 8 IS LESS THAN 70 HOURS, ENTER THE I CORRECTION FACTOR GRAPH (ATTACHMENT 3) AND 1 l RECORD DECAY CORRECTION. l i l B. IF ITEM 8 IS EQUAL TO OR GREATER THAN 70 1 HOURS, USE THE FOLLOWING FORMULA: 1 1 I l I DC = 22.52 e(.0756 (item 8-70)) l 1 l
- 17. Uncorrected measured concentration in sample vial (from EPIP 2-12) uCi/ml I
Rev. 0 l l 4/23/83 f
EPIP l-14 Page 19 of 44 O Attachment 1 Page 5 of 8 CONTAllMENT ATMOSPHERE SAMPLE WORKSHEET (continued) Isotope
- 18. Corrected concentration to scram time and full power:
= item 5 x item 16 x item 11 x item 12 x item 17 uCi/ml l I l CAUTION I I I l FOR ITEM 14 EQUAL TO OR LESS THAN 24 HOURS, USE I I ITEM 12a IN THE AB0VE EQUATION. l l l 1 FOR ITEM 14 GREATER THAN 24 HOURS BUT EQUAL TO OR l l LESS THAN 72 HOURS, USE ITEM 12b IN THE ABOVE l l EQUATION.
I FOR ITEM 14 GREATER THAN 72 HOURS, USE ITEM 12c l l IN THE AB0VE EQUATION. l l l
- 19. Total activity released (complete a, b, and c):
- a. Drywell activity =
(item 18 x 5.437 x 109) uCi
- b. Wetwell activity =
(item 18 x 3.858 x 109) uCi
- c. Total activity =
(item 19a + item 19b) uCi 'O 1 Rev. 0 4/23/83 i
i EPIP 1-14 Page 20 of 44 Attachment 1 J Page 6 of 8 CONTAIl#0ENT ATMOSPHERE SAMPLE WORKSHEET (continued) Isotope _
- 20. Total Core Isotope Inventory Listed below are the possible continuous power irradiation periods for establishin a core inventory:
1 day, 3 days, 7 days,14 days,1 month, 6 months,1 year, 1.5 years, 3 years l I l CAUTION I I I I IF THE CORE HAS BEEN OPERATING FOR LESS THAN 30 l l DAYS AFTER THE MOST RECENT EXTENDED OUTAGE, THEN I I SELECT AN OPERATING TIME LESS THAN 1 MONTH. I I EXTEIBED OUTAGE IS DEFINED AS AN OUTAGE LASTING l l LONGER THAN 6 HALF-LIVES OF THE ISOTOPE.
- a. Continuous power irradiation period
- b. Core isotope inventory (from Attachment.4) Ci
- c. Total core isotope inventory
= (item 20)(1 x 106) uCi
- 21. Gap Ratio Factor l = Release Ratio (Attachment 5)
! x 0.015 l t l l C Rev. 0 4/23/83
1 1 EPlP 1-14 Page 21 of 44 O Attaciment 1 Page 7 of 8 CONTAINMENT ATMOSPHERE SAMPLE WORKSHEET l (continued) Isotope
- 22. Rated power total gap
' activity
= (item 20c x item 21) uCi
- 23. Clad failure ratio
= item 19c/ item 22 l CAUTION l l l l IF CLAD FAILURE RATIO IS LESS THAN OR EQUAL TO 1, I l THEN CLAD FAILURE MAY HAVE OCCURRED FOR THAT l l FRACTION OF THE CORE-(e.g., CLAD FAILURE RATIO OF l l 0.5 IS EQUIVALENT OF UP TO 50% CLAD FAILURE). l l PROCEED TO ITEM 27. l I I l IF CLAD FAILURE RATIO IS GREATER THAN 1 CLAD l l FAILURE HAS OCCURRED. CALCULATE ITEMS 24 AND 25 l l FOR ESTIMATE OF FUEL OVERHEATING.
l c 24. Overheat inventory = l item 20c/2 _ uCi
- 25. Fuel overheat ratio =
(item 19c - item 22)/ item 24 l CAUTION l l l l CALCULATE FUEL OVERHEAT RATIO ONLY IF CLAD FAILURE l l RATIO (ITEM 23) IS GREATER THAN 1. l l l l l IF FUEL OVERHEAT RATIO IS LESS THAN OR EQUAL TO 1, I l l THEN FUEL OVERHEATING MAY HAVE OCCURRED FOR THAT l l FRACTION OF THE CORE (e.g., FUEL OVERHEAT RATIO 0F l l 0.2 IS EQUIVALENT OF UP TO 20% FUEL OVERHEATING). l l DO NOT CALCULATE ITEM 26. PROCEED TO ITEM 27. I I l 1 IF FUEL OVERHEAT RATIO IS GREATER THAN 1, FUEL l l OVERHEATING HAS OCCURRED AND PROCEED TO ITEM 26 l l FOR ESTIMATE OF MELTING / FRAGMENTATION. l l 1 Rev. 0 4/23/83
EPIP l-14 Page 22 of 44 O Attachment 1 Page 8 of 8 CONTAI MENT ATMOSPHERE SAMPLE WORKSHEET (continued) Isotope
- 26. Melt / fragment ratio =
(ite,n 19c - item 24)/ item 24 I I CAUTION 1 l l I . l CALCULATE MELT / FRAGMENT RATIO ONLY IF FUELl OVERHEATI l RATIO (ITEM 25) IS GREATER THAN 1 (e.g., MELT / l l FRAGMENT RATIO OF 0.6 IS EQUIVALENT OF UP TO 60% I l CORE MELT OR FRAGMENTATION). PROCEED TO ITEM l 27. l l 27.
Conclusions:
l f O Rev. 0 4/23/83 l
EPIP 1-14 4 Page 23 of 44 O Attachment 2 Page 1 of 4 HALF-LIFE TABLE 4 ISOTOPE HALF-LIFE ISOTOPE HALF-LIFE Se-79m 3.90 m Sr-92 2.71 h Se-81 18.5 m Y-92 3.54 h Se-83 22.5 m Kr-93 1.29 s Se-83m '70 s Rb-93 5.85 s Br-83 2.39 h Sr-93 7.4 m Kr-83m 1.83 h Y-93 10.2 h Br-84 31.8 m Kr-94 0.20 s Se-84 3.3 m Rb-94 2.72 s Se-85 31 s Sr-94 75 s
- Se-85m 19 s Y-94 18.7 m Br-85 2.9 m Rb-95 0.38 s Kr-85m 4.40 h Sr-95 24.4 s i Se-86 16 s Y-95 10.3 m Br-86 56 s Zr-95 64.0 d Br-86m 4.5 s Nb-95 35.0 d Se-87 5.8 s Rb-96 .2 01 s O Br-87 Kr-87 55.6 76 s
m Sr-96 Y-96 Sr-97 1.1 6 0.40 s s s j Se-88 1.- 5 s B r-88 16.6 s Y-97 1 .21 s Kr-88 2.84 h Zr-97 16.9 h Rb-88 17.8 m Nb-97 72 m Se-89 0.41 s Nb-97m 1.0 m i Br-89 4.4 s Sr-98 0.7 s Kr-89 3.18 m Y-98 0.6 s Rb-89 15.2 m Zr-98 31 s Sr-89 50.5 d Nb-98 2.9 s Br-90 1.9 s Nb-98n 51 m Kr-90 32.3 s Sr-99 0.6 s Rb-90 153 s Y-99 1.4 s Rb-90m 258 s Zr-99 2.1 s Sr-90 28.8 y Nb-99 15.0 s Y-90 64.1 h Nb-99m 2.6 m i Br-91 0.54 s Mo-99 66.02 h Kr-91 8.6 s Tc-99m 6.02 h Rb-91 58 s Y-100 0.8 s l Sr-91 9.50 h Zr-100 7.1 s Y-91 58.5 d Nb-100 3.1 s Y-91m 49.7 m Nb-100m 1.5 s i Kr-92 1.84 s Tc-100 15.8 s i Rb-92 4.52 s Y-101 0.98 s O Rev. 0 4 4/23/83 1
-- - _ _ _ , . . . . - - . . . _ _ _ . . - _ - - . , _ . . - _ . . _ _ _ _ . - _ . _ _ _ _ - _ _ _ _ _ _ . _ _ . . _ _ - ~ _ _ . _
EPIP l-14 Page 24 of 44 Attachment 2 4 O_ Page 2 of 4 HALF-LIFE TABLE (continued) ISOTOPE HALF-LIFE IS0 TOPE HALF-LIFE Zr-101 2 s Tc-109 1.4 s Nb-101 7.0 s Ru-109 34 s Mo-101 14.6 m Rh-109 80 s Tc-101 14.3 m Rh-109m 50 s Y-102 0.9 s Pd-109 13.43 h i Zr-102 2.9 s Pd-109m 4.69 m Nb-102 4.3 s Tc-110 0.82 s Mo-102 11.0 m Ru-110 16 s Tc-102 5.3 s Rh-110 28 s Zr-103 1.77 s Ru-111 1.5 s Nb-103 1.5 s Rh-111 11 s j Mo-103 60 s Pd-111 22 m
- ~ Tc-103 50 s Ru-112 0.7 s Ru-103 39.4 d- Rh-112 4.6 s Rh-103m 56.1 m Pd-112 21.1 h
, Zr-104 3.78 s Rh-113 0.9 s O Nb-104 Mo-104 Tc-104 4.8 1.0 18.1 s m m Pd-113 Pd-114 Pd-115 1.5 2.4 37 m m s Rh-104 42.3 s Sn-121 27.1 h Rh-104m 4.34 m Sn-125m 9.5 m Nb-105 2 s Sb-125 2.7 y i Mo-105 36 s Sn-127 2.1 h Tc-105 7. 6 m Sn-127m 4.1 m Ru-105 4.44 h Sb-127 3.9 d l Rh-105 35.4 h Te-127 9.4 h ! Rh-105m 45 s Sn-128 59.3 m Nb-106 1 s Sb-128 9.1 h Mo-106 9.5 s Sb-128m 10.0 m i Tc-106 36 s Sn-129 2.2 m i Ru-106 367 d Sn-129m 7.5 m Rh-106 29.8 s Sb-129 4.4 h Rh-106m 130 m Te-129 69 m Mo-107 5 s Te-129m 33.5 d , Tc-107 21 .2 s Sn-130 3.7 m Ru-107 4.2 m Sb-130 40 m ! Rb-107 21 .7 m Sb-130m 6.5 m Mo-108 1.1 s I-130 12.36 h Tc-108 5.1 s Sn-131 63 s Ru-108 4.5 m Sb-131 23.03 m i Rh-108 16.8 s Te-131 25.0 m i Rev. 0 4 4/23/83
EPIP 1-14 Page 25 of 44 Attachment 2 Os rage 3 of 4 i HALF-LIFE TABLE (continued) HALF-LIFE ISOTOPE HALF-LIFE ISOTOPE Te-131m 30 h Cs-138 32.2 m I-1 31 8.040 d Cs-138m 2.9 m 40 s I-139 2.3 s Sn-132 4.2 m Xe-139 39.7 s Sb-132 2.8 m Cs-139 9.5 m Sb-132m Te-132 78 h Ba-139 82.9 m 2.28 h I-140 0.8 s I-132 14 s Sn-133 1.47 s Xe-140 2.7 m Cs-140 65 s Sb-133 Te-133 12.4 m Ba-140 12.79 d Te-133m 55.4 m La-140 40.3 h 20.9 h Xe-141 1.73 s I-133 24.9 s I-133m 9 s Cs-141 Xe-133 5.25 d Ba-141 18.2 m 2.19 d La-141 3.90 h l Xe-133m ' 10.4 s Ce-141 32.5 d Sb-134 Sb-134m 0.8 s Xe-142 12 s l 42 m Cs-142 1.69 s
- Te-134 52.6 m Ba-142 10.6 m L
I-134 93 m I-134m 3.5 m La-142 0.29 s Pr-142 19.2 h Xe-134m Cs-134 2.062 y Xe-143 0.96 s Cs-134m 2.90 h Cs-143 1.78 s 1.70 s Ba-143 13.5 s Sb-135 19.2 s La-143 14.0 m Te-135 33.0 h l I-135 6.61 h Ce-143 Xe-135 9.10 h Pr-143 13.58 d Xe-135m 15.6 m Cs-144 1.00 s 53 m Ba-144 11.9 s Cs-135m l 17.5 s La-144 40 s Te-136 Ce-144 284 d I-136 46 s 83 s Pr-144 17.3 m I-136m 0.58 s Cs-136 13.1 d Cs-145 4 s Ba-145 5 s Te-137 30 s I-137 24.5 s La-145 3.82 m Ce-145 3.0 m Xe-137 5.98 h Cs-137 30.17 y Pr-145 2.551 m Ba-146 1.7 s Ba-137m 11 s Te-138 1.4 s La-146 Ce-146 14 m I-138 6.5 s 14.1 m Pr-146 24.0 m Xe-138 i O Rev. 0 4/23/83
EPIP 1-14 l' Page 26 of 44 Attachment 2 Page 4 of 4 HALF-LIFE TABLE (continued)
~
ISOTOPE HALF-LIFE ISOTOPE HALF-LIFE Ba-147 2.23 s Ce-151 1.0 s La-147 13 s Pr-151 4 s Ce-147 56 s Nd-151 12.4 m Pr-147 13 m Pm-151 28.4 h Nd-147 11 d Pr-152 8.32 s Pm-147 2.6234y Nd-152 11.4 m La-147 1.3 s Pm-152 4.1 m Ce-148 48 s Pr-153 7.74 s Pr-148 2.30 m Nd-153 67.6 s Pm-148 5.37 d Pm-153 5.4 m Pm-148m 41.3 d Sm-153 46.8 h La-149 2.86 s Nd-154 40 s Ce-149 5.0 s Pm-154 2.7 m Pr-149 2.3 m Nd-155 26 s Nd-149 1.73 h Pm-155 36.6 s Pm-149 53.1 h Sm-155 22.4 m , O Ce-150 Pr-150 4 6.2 s s Pm-156 Sm-156 13.1 9.4 s h l O Rev. 0 4/23/83
EPIP 1-14 . Page 27 of 44 Attachment 3 Page 1 of 1 i i
?
V Xe-135 CORRECTION FACTOR GRAPH 10 L M y13.D=':- E - r {-T T ' T'P - i 'JI'- '4--;3 j 2- . -2. p 21 ' 3 - p-- 4H g iE J--E;E 3.h 5 T SEE ' --
-34 7 J s .m J 2
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r "I2-NN.M ~~I D 54' -
;-5NrNa$-$$ 5.5NI!N5~N2- -- - _N :: :.$ -
.2 5-
_- =_=.r22
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Rev. 0 4/23/83
EPIP 1-14 Page 28 of 44 Attachment 4 Page 1 of 6 s s CORE ISOTOPE INVENTORY I OUTPUT UNIT
- 6 FISSION PR00 INVENTDRY VS. IRRADIATION TIME FISSION PRDOL POWER
- 2.43600E*03t'W. BURNUP: 2.66925E+06 MWD
- FLUX 2.32E+14N/CMut.SEC
SUMMARY
TABLE: RADI0 ACTIVITY. CURIES CORE FUEL LOA 0s:56.000 LB a 116 MTIHM 1.88% ENRICH.. POWER 2436 MW 1.00 3.00 7.00 14.00 30.00 100.00 1.01R 1.51R 3.0VR
~
.SE 79N 1.125E*06 1.125E+06 1.125E+06 1.1 5E+06 1.123E*06 1.117E+06 1.046E+06 9.981E*05 8.963E+05 SE 81 4.37:E*06 4.37:E*06 4.369E+06 4.361E+06 4.341E*06 4.227E*06 3.891E+06 3.667E*06 3.190E*06 SE 83 4.076E*06 4.074E*06 4.069E+06 4.054E+06 4.018E+04 3.810E*06 3.451E+06 3.2 5E+06 2.770E*06 SE 83N 6.78SE*06 6.782E*06 6.764E*06 6.721E*06 6.623E+06 6.030E*06 5.295E*06 4.849E*06 3.974E+06 r BR 83 1. 093E + 07 1. 093 E + 07 1. 091E
- 07 1. 085 E
- 07 1. 073E + 07 9. 930 E + 06 8. 911 E
- 06 8. 249E
- 06 6. 933E + 06 KR 83N 1.093E*07 1.092E+07 1.090E+07 1.085E*07 1.072E+07 9.978E+06 8.911E+06 8.251E+06 6.945E*06
'/ SE 84 2.005E+07 2.00 3E+07 1.'997E*07 1.983E*07 1.950E+07 1.749E+07 1.517E*07 1.377E+07 1.104E* 07 f \s ,, BR 84 2.C('.2+0 7 2.038E+ 07 2.03:E +07 2.018E*07 1.987E+07 1.796E*07 1.567E+07 1.428E +07 1.154E*07
! SE 85 1.co6E+07 1.265E+07 1.260E+07 1.249E+07 1.223E*07 1.055E+07 9.006E+06 8.027E*06 6.129E+06 SE 85M 9.060E*06 9.051E+06 9.019E+06 8.947E+06 8.783E+06 7.773E*06 6.651E*06 5.970E*06 4.621E+06 BR 85 2.496E*07 2.494E+07 2.486E+07 2.469E+07 2.430E+07 2.192E+071.904E+071.727E+071.374E+07 KR 85M 2.453E*07 2.5:1E*07 2.51:E+07 2.495E*07 2.456E+07 2.217E*071.927E+071.749E*071.393E+07 SE 86 2.648E*07 2.645E+07 2.633E*07 2.605E*07 2.54:E+07 2.160E*071.789E*071.571E+071.156E*07 ER 86 1.890E+07 1.888E+07 1.881E+07 1.865E+07 1.830E +07 1.613E*07 1.377E
- 07 1.2 35E*07 9.561E* 06 ER 86N 1.905E *07 1.903E* 07 1.896E+07 1.880E*07 1.844E+07 1.624E*07 1.386E+07 1.242E*07 9.591E+06
~
SE 87 1.994E+07 1.992E +07 1.984E+07 1.966E+07 1.925E+07 1.673E*07 1.414E *07 1.260E+07 9.638E*06 BR 87 4.307E*07 4.303E*07 4.287E+07 4.25 E+07 4.171E+07 3.677E*07 3.139E+07 2.814E*07 2.177E+07 KR 87 5.087E+07 5.081E+07 5.063E*07 5.023E+07 4.930E*07 4.360E*07 3.729E*07 3.347E*07 2.591E+07 SE 88 7.865E*06 7.854E*06 7.816E*06 7.730E+06 7.533E+06 6.354E*06 5.268E+06 4.652E*06 3.538E+06 BR 88 4.974E*07 4.967E+07 4.946E+07 4.897E+07 4.786E+07 4.103E+07 3.416E+07 3.007E*07 2.209E+07 KR 88 7.171E*07 7.185E+07 7.160E*07 7.102E+07 6.971E*07 6.163E+07 5.266E*07 4.720E+07 3.634E+07 R8 88 7.032E*07 7.245E*07 7.220E*07 7.164E+07 7.034E*07 6.235E+07 5.339E*07 4.790E+07 3.705E*07 , SE 89 2.212E*06 2.209E*06 2.199E*06 2.174E+06 2.117E*06 1.730E*06 1.47eE*06 1.311E*06 1.019E*06 j BR 89 3.805E*07 3.799E*07 3.779E+07 3.735E+07 3.634E+07 3.017E+07 2.441E*07 2.103E*071.453E+07 l KR 89 9.130E*07 9.119E*07 9.034E*07 9.003E+07 8.819E+07 7.683E+07 6.480E*07 5.753E+07 4.315E*07 R8 89 9.457E*07 9.447E+07 9.413E*07 9.337E*07 9.161E+07 8.083E+07 6.88SE+07 6.160E+07 4.707E+07 SR 89 1.267E*06 3.794E+06 8.628E*061.641E+07 3.131E*07 7.659E*07 7.172E+07 6.451E*07 4.722E+07 BR 90 2.553E+07 2.549E+07 2.535E*07 2.503E+07 2.431E*07 1.985E*07 1.579E +07 1.341E*07 8.834E+06 KR 90 9.101E*07 9.090E+07 9.053E*07 8.969E*07 8.778E+07 7.602E*07 6.3SSE*07 5.660E*07 4.237E+07 i R8 90 9.358E*07 9.347E*07 9.311E*07 9.231E+07 9.046E*07 7.911E+07 6.695E*07 5.959E*07 4.502E+07 R8 90N 1. 906 E
- 07 1.905 E + 0 7 1. 900 E
- 07 1. 910 E
- 07 1. 887E
- 07 1. 74:E+07 1.53SE+07 1.409E*07 1.140E+07 SR 90 7.315E*03 2.198E*04 5.121E*04 1.000E*05 2.160E+05 1.191E*06 2. 1E+06 3.119F400 5.304E*06 Y 90 1.907E*03 9.180E*03 3.149E+04 7.990E*04 1.943E*05 1.023E+06 2.237E+06 3.217E+06 5.511E+06 BR 91 8.429E+06 8.415E*06 6.369E*06 8.066E+06 8.030E+06 6.SoSE*06 5.299E*06 4.54SE+06 3.13SE+06 KR 91 6.247E*07 6.83CE +07 6.808E+07 6.741E+07 6.587E*07 5.650E+ 07 4.720E +07 4.175E+07 3.131E*07 R8 91 1.115E*08 1.114E*08 1.110E*0S 1.101E*06 1.031E*06 9.595E+07 8.234E*07 7.410E+07 5.785E+07 SR 91 9.564E* 0 7 1.151E*08 1.154E+ 08 1.145E+08 1.127E
- 08 1.013E*08 8.776E*0 7 7.*SIE *07 6.310E* 07 Y 91 7.128E+05 3.306E*06 8.4SOE+061.691E+07 3.344E+07 9.165E+07 9.050E*07 8.303E+07 6.564E+07 l
O Rev. U 4/23/83
1 EPIP 1-14 Page 29 of 44 - 4 Attachment 4 T Page 2 of 6 CORE ISOTOPE INVENTORY '. CONT'D) FISSION PROD INVENTORY VS. IRRADIATION TIME FISSION PRODI POWERS 2.43600E+03t94 SURteJPs 2.66925E+06telDe FLUXe 2.3tE+14N/CMeet-SEC i
~ ~ ~ ' ~ ~ ~
SUMMARY
TABLE RADI0 ACTIVITY. CURIES CORE FUEL LOA 0:256.000 L8 = 116 MTIHN.1.88X EMIICH., POWERS 2434 PSI 1.00 3.00 7.00 14.00 30.00 180.00 1.0YR 1.5YR 3.0VR l Y 91M ~"S.547E*07 6.691E*07 6497E+07 6.643E*07 6.535E+07 5.875E$07 5.093E+07 4.615E+07 3.664E+07 i
- kN 92 3.160E+07 3.156E*07 3.143E+07 3.11tt+07 3.042E*07 2.624E+07 2.225E+07 2.000E*071.600E*07 R8 92 9.505E+07 9.495E+07 9.464E+07 9.391E*07 9.ttBE+07 8.218E*07 7.099E*07 6.430E+07 5.143E+07 SR 92 1.186E+08 1.188E+08 1 185E+08 1.178E+08 1.162E+06 1.065E*06 9.387E*07 8.612E*07 7.071E*07 Y 92 1.153E+08 1.190E*06 1.187E*08 1.180E*08 1.164E*08 1.068E+08 9.425E+07 8.651E*07 7.112E*07 kR 93 1.133E+07 1.132E*07 1.126E+07 1.115E607 1.088E*07 9.314E+06 7.917E+06 7.171E*06 5.966E*06 R8 93 7.184E*07 7.176E*07 7.151E+07 7.092E*07 6.959E*07 6.158E*07 5.317E*07 4.830E*07 3.935E*07 SR 93 1.271E*08 1.270E*06 1.268E+08 1.262E+08 1.249E*06 1.168E*08 1.049E*08 9.748E*07 8.290E*07 I. Y 93 - 1.034E*08 1.276E*06 1.284E+08 1.281E*08 1.269E+08 1.192E+08 1.074E*08 1.000E*08 8.541E*07 MR 94 4.761E+06 4.754E*06 4.728E*06 4.671E*06 4.541E*06 3.756E*06 3.058E+06 2.664E*06 1.951E*06
- j. ,RS 94 3.675E+07 3.671E+07 3.658E+07 3.628E+07 3.560E*07 3.156t+07 2.742E*07 2.508E+07 2.099E+07 SR 94 1.171E+08 1.171E*08 1.169E+08 1.164E*08 1.153E+08 1.088E*06 9.842E*07 9.199E*07 7.939E*07 Y 94 1. 238E
- 08 1.238E
- 08 1. 236E
- 08 1. 233E + 08 1. 224E
- 08 1.174E+ 08 1.074E + 08 1. 010 E + 08 8.829E + 07
< R8 95 1. 968E + 07 1. 965E
- 07 1. 957E + 07 1. 937E
- 07 1. 892 E
- 07 1. 625E
- 07 1. 378E + 07 1. 241 E
- 07 1. 006 E
- 07
! SR 95 1.100E+08 1.100E+08 1.097E*08 1.092E*08 1.080E+08 1.007E+08 9.062E*07 8.461E*07 7.337E*07 Y 95 . __1 282E+04 1.282E+08 1.281E+06 1.278E*06 1.271E+06 1.233E*06 1.140E*06 1.081E*08 9.669E+07 ZR 95 1.373E*06 4.103E+06 9.382E+06 1.806E*07 3.545E+07 1.067E+08 1.152E+08 1.120E+08 1.007E+08 HS 95 1. 340E + 04 1.190E + 05 6. 239E + 05 2. 328E + 06 9.115E + 06 8. 946E + 07 1.138E
- 08 1.130 E + 08 1. 010E + 04 i R8 96 4.999E+06 4.995E+06 4.976E+06 4.931E+06 4.828E+06 4.248E*06 3.718E+06 3.448E*06 3.062E*06 SR 96 7.756E+07 7.750E+07 7.731E+07 7.685E*07 7.580E+07 6.971E*07 6.234E+07 5.814E*07 5.076E+07
- Y 96 1.208E*08 1.208E+08 1.207E+08 1.204E*08 1.197E*08 1.161E*08 1.076E+08 1.023E+08 9.233E*07 SR 97 4.150E+07 4.147E+67 4.134E+07 4.105E*07 4.038E+07 3.651E+07 3.242E+07 3.021E+07 2.666E+07 Y 97 1.032E*06 1.031E+08 1.031E+08 1.028E*08 1.021E*08 9.878E*07 9.161E*07 8.737E*07 7.985E*07 ZR 97 7.4365+07 1.1245*04 1,184E*06 1,146E*06 1,167E+06 1.196E*06 1.142E+06 1.105E+08 1.036E+08 _
' H6 97 7.470E+07 1.129E*08 1.189E+08 1.190E*08 1.193E+08 1.207E+08 1.151E*08 1.115E+08 1.047E+08 j HB 97M 7.040E+07 1.065E+08 1.122E+08 1.123E*08 1.125E+08 1.136E+08 1.082E+08 1.048E*08 9.832E+07 SR 98 1.655E+07 1.654E+07 1.648E+07 1.634E*07 1.602E+07 1.424E+07 1.256E*07 1.169E+07 1.044E*07 l Y 98 7.552E+07 7.548E+07 7.536E+07 7.506E*07 7.435E*07 7.049E*07 6.473E+07 6.152E+07 5.626E+07 ZR 98 1.172E+08 1.172E*06 1.173E*08 1.174E*08 1.176E*06 1.196E*06 1.147E*06 1.116E*08 1.059E*08 NB 98 8.466E+05 8.527E*05 8.735E*05 9.173E+05 1.015E*06 1.618E*06 1.883E*06 2.000E*06 2.148E+c6 N8 98N 1.177E*08 1.177E*08 1.178E*08 1.180E*08 1.183E+08 1.206E*08 1.158E+08 1.127E*08 1.071E+08
,SR 99 ._4.326E*06 4.322E*06.4.307E+06,4.269E*06 4.182E*06 3 710E*06 3.300E*06 3.108E*06 2.89eE*C6
. Y 99 4.421E+07 4.418E+07 4.408E+07 4.382E*07 4.324E+07 4.002E+07 3.638E+07 3.451E*07 3.192E+07 ZR 99 1.163E+08 1.164E*08 1.164E+08 1.165E*06 1.165E+08 1.177E+08 1.128E+08 1.098E+08 1.049E*08 NS 99 1.190E+08 1.190E+08 1.191E+08 1.192E+08 1.194E+08 1.217E*08 1.172E*06 1.144E*08 1.098E*08 N8 99M 2.832E+06 2.842E+06 2.879E+06 2.955E+06 3.124E*06 4.180E+06 4.583E+06 4.753E*06 4.964E*06 NO 99 2.715E*07 6.466E
- 07 1.010E+08 1.183E*08 1.222E*08 1.265E* 08 1.229E*08 1.203E* 08 1.179E* 08 TC 99M 1.612E+07 5.158E* 07 9.050E+07 1.051E*06 1.072E *08 1.108E* 0& 1.076E+ 08 1.057E *08 1.032E*08 Y100 2.022E*07 2.020E*07 2.014E*0 7 2.001E+07 1.969E+07 1.796E+07 1.621E+07 1.534E
- 07 1.42 3E+07 ZR100 1.090E*08 1.090E* 08 1.090E *06 1.090E +08 1.089E*08 1.092E+ 08 1,041E* 06 1.011E *06 9.623E + 07 H8100 6.348t+07 6.351E*07 6.361E+07 6.378E+07 6.415E*07 6.681E+07 6.510E+07 6.393E*07 6.185E+07
;NB100M 4.348t+07 6.351E+07 6.361E+07 6.378E+07 6.415E+07 6.681E+07 6.510E*07 6.393E+07 6.185E*07 TC100. 2.124E+03 1.886E+04 8.894E*04 2.508E*05 6.401E*05 4.083E+06 7.826E+06 1.143E*07 2.263E*07 Y101 6.772E+06 6.766E*06 6.742E*06 6.684E+06 6.552E*06 5.825E+06 5.185E+06 4.885E+06 4.549E*06 ZR101 7.369E+07 7.367E*07 7.359E+07 7.338E*07 7.286E+07 7.037E*07 6.590E*07 6.362E+07 6.072E*07 NB101 1.03.1E+08 1.031E+08 1.033E+08 1.035E+08 1.040E+08 1.081E*08 1.057E*08 1.043E*08 1.026E*08 M0101 1.052E*08 1.053E*06 1.055E+08 1.059E*08 1.068E+08 1.133E*06 1.121E+08 1.113E+08 1.108E+08 TC101 __ _1.052E*08.1.053E*08 1.055E*08 1.059E*06 1.068E+08 1.133E*QS 1.122E*06 1.114E+06 1.108E*06 Y102 1.542E+06 1.541E*06 1.536E*06 1.523E*06 1.494E*06 1.342E*06 1.217E+06 1.168E*06 1.147E+06
-ER102 4.022E+07 4.020E*07 4.015E+07 4.001E+07 3.967E*07 3.809E+07 3.590E*07 3.500E+07 3.463E+07 H8102 8.145E+07 8.150E+07 8.167E*07 8.196E*07 8.258E*07 8.735E+07 8.692E*07 8.691E+07 8.849E*07 N010t _, . 8.946t+07 4.956E*07 8.990E+07 9.056E*07 9.201E+07 1.019E*06 1.019E+08 1.050E+08 1.084E+08 Rev. 0 4/23/83
EPIP 1-14 Page 30 of 44 Attachment 4 Page 3 of 6 b c0RE ISOTOPE INVENTORY (CONT'D) OUTPUT UNIT s 6 FISSIDH PR00 INVENTORY VS. IRRADIATIDH TIME FISSIDH PROD POWERS 2.4360tE*03MW. BURNUP 2.66925E+06 MWD. FLUXs 2.32E+14N/CNeut-SEC
~ ~ ~ ~
~
SUMMARY
TABLE: RADI0 ACTIVITY, CURIES CORE FUEL LOAD =256.000 LB s 116 MTIHM. 1.88% ENRICH., POWER:2436 MW 1.00 3.00 7.00 14.00 30.0D 180.00 1.0YR 1.51R 3.0YR TC102 8.948E+07 8.959E+07 8.993E+07 9.060E+07 9.205E+07 1.020E*08 1.040E*08 1.052E*08 1.085E*08 ZR103 1.338E*07 1.338E*07 1.337E+07 1.333E+07 1.323E*07 1.287E*07 1.244E*07 1.242E+07 1.310E+07 NB103 4.919E* 07 4.924E+07 4.943E*07 4.978E*07 5.054E+07 5.604E+07 5.775E*07 5.90SE+07 6.308E*07 tN0103 6.796Et07 6.765E*07 6.623E*07 6.940E+07 7.200E*07 6.902E*07 9.619E*071.002E*081.087E+08 TC103 6.782E*07 6.800E*07 6.860E+07 6.982E*07 7.252E*07 9.018E*07 9.768E*07 1.018E*08 1.106E*08 RU103 1.184E+06 3.498E*06 7.908E*06 1.501E+07 2.873E407 8.092E+07 9.445E+07 1.004E*08 1.109E+08 RH103M 1.056E*06 3.151E*06 1.125E+06 1.352E*07 2.588E+07 7.288E*07 8.507E+07 9.047E+07 9.991E+07
,ZR104 2 604Et96.2.604E+06.2.600Et06 2.590E*06 2.565Et96 2.537Et06 2.543E+06 2.665E*06 3.20eE*06 NB104 2.043E+07 2.046E*07 2.053E*07 2.067E*07 2.098E*07 2.350E*07 2.511E+07 2.656E+07 3.110E+07 N0104 4.207E+07 4.224E+07 4.278E+07,4.389E*07 4.636E+07 6.276E*07 7.170E+07 7.724E*07 8.984E*07 TC104 4.321E407 4.340E+07 4.402E*07 4.529E+07 4.812E*07 6.675E*07 7.685E+07 8.296E*07 9.650E*07 JH199. 4 6264Et02.4.569Et03 2.453E+04 9.43EE+04 3.950E+05 7.536t+061.819E+07 2.852E*07 5.919E*07 RH104M 3.753E*01 3.404E*02 1.824E+03 7.014E403 2.937E*04 5.603E+05 1.352E*06 2.121E+06 4.400E*06 NB105 6.024E*06 6.033E*06 6.059E+C6 6.106E+06 6.211E*06 7.116E+06 7.885E*06 8.585E*06 1.073E*07 N01G5 2.340E*07 2.354E+07 2.398E*07 2.489E+07 2.691E+07 4.036E*07 4.849E*07 5.364E+07 6.544E*07 TC105 2.553E*0Z 2.572E+07 2.634E+07 2.763Et07 3 050E+07.4.929E+07 6.034E*07 6.700E*07 8.144E+07 RU105 2.475E+07 2.578E*07 2.640E+07 2.772E*07 3.065E+07 4.981E*07 6.110E*07 6.792E*07 8.278E407 f RH105 7.267E*061.719E*07 2.259E+07 2.468E*07 2.875E+07 4.677E*07 5.750E*07 6.395E*07 7.773E+07 f IRH105M 6.929E*06 7.219E*06 7.392E*06 7.761E*06 8.582E406 1.395E*07 1.711E+07 1.902E+07 2.318E*07 C iNB106 _ ._1.842E*06 1.662f+06 1,661E*06 1.858E+06 1.850E*06 1.886E*06 2.012E+06 2.185E+06 2.814E*06 N0106 1.026E+07 1.032E*07 1.052E*07 1.094E*07 1.188E+07 1.842E+07 2.335E*07 2.688E+ 07 3.592E+07 TC106 1.190E+07 1.204E*071.248E*07 1.342E+07 1.551E+07 2.944E*07 3.880E*07 4.486E+07 5.889E+07 20106 2.244E+04 6.756E*04 1.599E+05 3.308E*05 7.685E*05 6.973E+06 1.644E+07 2.567E*07 4.912E* 07 EH106 3.654Et05 6.795E+05 1.226Et06 1.490E+06 2.103E+06.9.053Et06 1.88SE+07 2.834E*07 5.251E*07 l
RH106M 1.728E+05 4.159E*05 5.418E+05 5.853E+05 6.723E+05 1.048E*06 1.229E*06 1.350E+06 1.706E+06 N0107 3.954E+06 3.967E*06 4.008E+06 4.088E*06 4.269E*06 5.792E*06 7.494E+06 8.967E+06 1.325E+07
.TC107 5.857E+06 5.918E+06 6.116E+06 6.530E+06 7.455E*C6 1.396E+07 1.926E+07 2.311E+07 3.299E+07 RU107_____6.033E+06 6.162E+06 6.5PSt+06 7.463E*06 9.486E*06 2.271E+07 3.174E+07 3.751E+07 5.063E+07 RH107 6.034E*06 6.163E+06 6.593E+06 7.496E+06 9.516E+06 2.284E*07 3.193E+07 3.773E+07 5.CS9E*07 N0108 1.637E*06 1.641E+06 1.653E+06 1.675E+06 1.725E*06 2.124E+06 2.465E+06 2.750E+06 3.575E+06 TC108 3.020E*06 3.061E+06 3.196E*06 3.477E+06 4.104E+06 8.384E+06 1.158E+07 1.378E*07 1.914E+07
! 10106 3.267Et06 3.376E*06 3.672E*06 4.295E+06 5.66SE+C61.492E*07.2.139E+07 2.558E*07 3.521E+07 l RH108 3.288E+06 3.379E*06 3.678E+06 4.309E*06 5.721E+06 1.507E407 2.161E+07 2.584E+07 3.555E+07 . l TC109 1.542E*06 1.565E*06 1.638E*06 1.790E+06 2.129E+06 4.360E*06 5.800E*06 6.694E+06 8.678E+06 RU109 2.024E*06 2.082E+06 2.271E*06 2.669E+06 3.560E+06 9.423E+06 1.341E+07 1.594E*07 2.162E+07 RH109 2 037E*06 2.097E*06 2.294E+06 2.709E+06 3.636E+06 9.745E+06 1.392E+07 1.657E+07 2.255E*07 RH109M 1.019E*06 1.049E+06 1.147E+06 1.354E*06 1.818E*06 4.873E*06 6.959E+06 8.284E*06 1.127E*07 i P0109 1.434E*06 2.019E+06 2.250E*06 2.718E*06 3.658E*06 1.002E*071.467E*071.744E+07 2.652E+07 l P0109M 1.019E*06 1.049E+06 1.147E*06 1.355E+06 1.819E*06 4.878E*06 6.974E*06 8.310E*06 1.134E+07 l TC110 8.552E*05 8.588E*05 8.689E+05 8.885E*05 9.317E*05 1.245E+06 1.461E+06 1.617E+06 2.025E*06 1.517E*06 1.539E*06 1.609E+06 1.754E*06 2.079E+06 4.269E+06 5.821E*06 6.853E*06 9.298E+06 RU110 RH110 1.538E*06 1.562E+06 1.639E*06 1.799E+06 2.156E*06 4.556E*06 6.257E+06 7.334E*06 1.005E+07 RU111 1.244E+06 1.252E*06 1.275E+06 1.321E+06 1.422E+06 2.137E*06 2.645E+06 3.001E+06 3.898E*06 l RH111 1.370E*06 1.381E*06 1.41eE*06 1.488E*06 1.648E+06 2.751E*06 3.539E+06 4.080E+06 5.410E+06 l P0111 1.372E*06 1.384E+06 1.420E+06 1.494E*06 1.658E+06 2.791E*06 3.603E*06 4.162E*06 5.549E+06 lRU112 9.265E+05 9.286E*05 9.330E*05 9.405E+05 9.568E+05 1.098E+06 1.200E+06 1.288E+06 1.556t+06 1.142E*06 1.146E*06 1.158E*C6 1.180E*06 1.230E*06 1.598E+06 1.860E+06 2.056E*06 2.581E+06
}RH112 LP0112 (2526Ef05_1 065E+06_1.170E+06 1.199E*06 1.263E+06.1.653E+06 1.987E+06 2.205E+06 2.780E+06 /h
, b Rev. O l 4/23/83
EPIP 1 14 Page 31 of 44 Attachment 4 Page 4 of 6
% CORE ISOTOPE INVENTORY (CONT'D)
O DUTPUT UNIT
- 6 j FISSIDH PROOL FISSION PROD INVENTDRY VS. IRWADIATIDH TIME POWER: 2.43600E+03MW. SURNUPs 2.66925E+06 MWD. FLUXs 2.32E+14N/CMes2.SEC
SUMMARY
TABLE: RADI0 ACTIVITY. CURIES CORE FUEL LOA 0 256.000 L8 s 116 MTIHN. 1.88% ENRICH., POWER:2436 MW 3.00 7.00 14.00 30.00 180.0D 1.0VR 1.SYR 3.0YR 1.00 RH113 1.031E*06 1.034E*06 1.039E*06 1.048E*06 1.069E*06 1.238E*06 1.353E*06 1.450E*06 1.739E*06 PD113 1.097E*06 1.100E*06 1.109E*06 1.125E*06 1.162E*06 1.437E*06 1.620E+06 1.757E*06 2.134E*06 P0114 9.229E*05 9.248E*05 9.293E*05 9.371E*05 9.541E*05 1.090E*06 1.167E+06 1.229E*06 1.414E*06 P0115 1.013E+06 1.015E*06 1.018E*06 1.021E+06 1.029E*06 1.107E*06 1.139E*06 1.173E*06 1.297E*06 SN121 4.253E*05 7.781E+05 9.113E*05 9.269E+05 9.382E+05 1.015E+06 1.031E*06 1.046E+06 1.106E+06 SN125M. 9.965E*05 9.994E*05 1.007E*06 1.022E+06 1.056E*06 1.283E*06 1.375E+06 1.427E+06 1.542E*06 58125 6.921E+02 2.172E*03 5.416E*03 1.179E*04 2.827E*04 2.091E*05 4.379E*05 6.528E*05 1.216E+06
.SN127 2.979E*06 2.988E+06 3.015E+06 3.067E+06 3.183E+06 3.957E+06 4.192E+06 4.402E*06 4.893E+06 0 SN127M S8127 iTE127 1.232E*06 1.238E*06 1.256E+06 1.292E*06 1.374E+06 1.892E*06 2.112E+06 2.215E+06 2.376E*06 6.568E+05 1.773E+06 3.110E+06 4.074E+06 4.625E*06 6.210E*06 E.842E*06 7.170E.06 7.788E+06 3.089E*05 1.295E+06 2.778E*00 3.629E+06 4.094E*06 5.846E*06 6.654E*06 7.065E*06 7.752E+06 SN128 8.837E+06 8.851E*06 8.897E*06 8.985E*06 9.179E*06 1.047E*07 1.076E+07 1.028E+07 1.111E+07 SP128 3.114E+05 3.709E*05 3.851E*05 4.085E+05 4.612E*05 7.889E*05 9.423E*05 1.013E+06 1.114E606 SS128M 9.133E*06 ?.152E,06 9.209E+06 9.322E*06 9.570E*06 1 12C3+07 1,166E+07 1.186E*07 1.220E*07 SN129 5.418E*06 5.429E*06 5.464E*06 5.531E*06 5.680E*06 6.678E*06 7.026E*06 7.217E+06 7.647E+06 SN129M. 7.7572906 7.763E+06 7.782E*06 7.817E*06 7.891E+06 8.420E+06 8.34SE*06 8.284E+06 8.205E*06
$8129 1.510E*07 1.553E*07 1.564E*07 1.588E*07 1.641E*07 1.981E*07 2.096E*07 2.150E*07 2.245E+07 TE129 1.343E
- 07 1.386E* 07 1.407E+ 07 1.446 E+07 1.525E+ 07 1.935E*07 2.05SE
- 07 2.114E
- 07 2.208E + 07
- TE129M 3.544E*04 1.248E*05 2.939E*05 5.616E+05 1.061E+06 2.702E*06 3.030E*06 3.153E*06 3.315E*06
,5N130 ' __t.108E+07 2.110E+07 2.116E*07 3 126E*07 2.150E*07 2.316E+07 2.31eE*07 2.317E+07 2 .
58130 4.434E*06 4.449E*06 4.499E*06 4.602E*06 4.829E*06 6.270E*06 6.828E+06 7.082E*06 7.469E*06 S8130M t.709E+07 2.712E*07 2.722E+07 2.741E+07 2.782E*07 3.061E+07 3.090E*07 3.098E*07 3.126E+07 I130 3.605E*03 7.534E*031.432E+04 2.802E*04 5.715E+04 3.540E*05 7.161E*051.085E+06 2.329E+06 SN131 2.185E+07 2.185E*07 2.184E+07 2.181E*07 2.173E+07 2.150E*07 2.051E+07 2.005E*071.964E*07 55131 5.367E+07 5.370E*07 7 379E*07 5.395E*07 5.428E+07 5.674E+07 5.560E*07 5.48eE+07 5.388E*07 TE131 5.307E+07 5.376E e07 3.419E*07 5.449E*07 5.509E*07 5.913E*07 5.882E*07 5.850E *07 5.812E*07 TE131M 3.157E*06 6.060E *06 7.366E*06 7.608E*06 7.878E*06 9.228E*06 9.579E*06 9.710E*06 9.859E *06 I131 4.272E*06 1.267E *07 2.630E+07 4.161E*07 5.555E*07 6.643E+07 6.641E+07 6.619E*07 6.594E
- 07 i SN132 1. 385E
- 07 1. 384E
- 07 1.380E + 07 1.371E + 07 1.351E
- 07 1.239E
- 07 1.123E + 07 1. 067E + 07 9.979E
- 06 l~ '58132 3.596E*07 3.595E*07 3.593E+07 3.587E+07 3.571E*07 3.503E*07 3.311E*07 3.210E+07 3.078E*07
! 58132M 2.192E+07 2.192E*07 2.194E+07 2.197E*07 2.702E*07 2.251E+07 2.177E*07 2.135E*07 2.076E*07 TE132 1.687E+07 4.160E*07 6.836E+07 8.397E*07 8.902E+07 9.557E*07 9.456E+07 9 374E+07 9.228E+07 1132 1.7J8E*07 4.245E*07 6.944E+07 8.501E+07 8.975E+07 9.672E+07 9.596E*07 9.527E*07 9.402E*07
$N133 4.437E*06 4.434E+06 4.417E+06 4.378E+06 4.287E+06 3.790E*06 3.358E*06 3.153E*06 2.916E*06 58133 4.797E*07 4.794E*07 4.782E+07 4.754E*07 4.689E+07 4.330E+07 3.924E+07 3.713E+07 3.409E*07 TE133 ~~
8.119E+07 8.121E*07 8.125E+07 8.130E+07 8.136E*07 8.246E+07 7.949E+07 7.787E*07 7.585E+07 TE133M 5.716E+07 5.715E*07 5.712E+07 5.704E*07 5.683E*07 5.571E*07 5.189E+07 4.947E*07 4.470E*07 2133 7.289E+ 07 1. 228E + 08 1. 353E +08 1. 363E+ 08 1. 376E + 08 1.418E
- 06 1. 373E + 08 1. 344t + 08 1. 294E
- 08 e 1133M t.520E+06 2.530E+06 2.562E+06 2.629E+06 2.778E+06 3.708E*06 4.068E+06 4.223E+06 4.427E+06
/ !XE133.___ 5.874E+06 2.816E*07_7,071E+07 1.100E*08 1.272E*08 1 416E+08 1.373E*06 1.345E* 03 1.297E+08 Rev. 0 4/23/83
EPIP 1-14 Page 32 of 44 Attachment 4 Page 5 of 6 c0RE ISOTOPE INVENTORY (CONT'D) O 4 OUTPUT UNIT = 6 . FISSION PROD INVENTORY VS. IRRADIATION TIME FISSION PR00' POWERS 2.43400E*03MW. SURNUPs 2.66925E+06fSee FLUX 8 2.32E+14N/CNe*2-SEC
SUMMARY
TABLEI RADI0 ACTIVITY. CURIES CORE FUEL LOA 0*256.000 L8 a 116 NTIHN. 1.88% ENRICH., POWER =2436 MW 1.00 3.00 7.00 14.00 30.00 180.00 1.0YR 1.5YR 3.0YR " XE133M 58134 3.540E*05 1.675E*06 3.283E*06 3.923E+06 3.754E*06 4.323E*06 4.264E*06 4.215E*06 4.123E+06 58134N ' 6.820E+06 6.817t+06 6.806E*06 6.775E+06 6.702E*06 6.372E+06 6.019E*06 5.907E*06 6.006E*0 TE134 6.30$E+06 6.303E+06 6.293E*06 6.265E+06 6.201E*06 5.911E*06 5.592E*06 5.491E*06 5.582E406 1134 1. 364E+08 1. 364E + 08 1. 361E+08 1.355E + 08 1. 340E
- 08 1.260E+08 1.151E+ 08 1.092E
- 08 9. 965E+ 07 1134M 1.543E*06 1.543E+08 1.544E*08 1.545E*06 1.547E*08 1.568E*06'1.506E*08 1.469E*08 1.409E*06 XE134N 8.942E*06 8.972E*06 9.075E*06 9.288E*06 9.761E*06 1.276E*071.399E*07 1.459E*07 1.559E*07 CS134 4.566E*05 4.597E+05 4.700E+05 4.917E*05 5.401E+05 8.406E+05 9.754E*05 1.037E*06 1.125E+06 CS134M 7.345E-01 8.923E*00 1 292E*0E 1.043Ee03 8.365E*03 4.355E+05 1.625E*06 3.326E*06 1.058E*07 58135 5.367E*021.359E*03 6.393E+03 2.240E+04 7.255E*04 5.370E*051.039E*061.517E*06 2.957E*06 4.844E+06 4.839E*06 4.820E*06,4.776E*06 4.676E*06 4.112E+06 3.616E+06 3.373E*06 3.058E+06 TE135 1135 6.898E*07 6.895E*07 6.882E*07 6.850E*07 6.776E+07 6.382E*07 5.885E*07 5.637E*07 5.323E+07 XE135 1 172E*08 1.274E*08 1 277E*08 1.279E+08 1.283E+06 1.318E*06 1.277E*08 1.252E*08 1.214E+08 XE135M 3.153E+07 3.425E*07 3.428E*07 3.453E*07 3.510E*07 3.819E*07 3.890E+07 3.676E*07 3.696E*07 1 CS135M 2.139E*07 2.299E*07 2.310E*07 2.328E*07 2.368E*07 2.632E+07 2.661E+07 2.665E*07 2.665E*07 4
TE136 1.186E*04 1.199E*04 1.243E*04 1.347E*04 1.656E*04 9.031E*04 2.561E*05 4.864E+05 1.529E*06 1156 4.013E*07 4.010E*07 3.998E+07 3.969E+07 3.905E+07 3.539E*07 3.166E*07 2.974E+07 2.697E*07 I136M 6.414E+07 6.413E*07 6.411E*07 6.401E*07 6.376E+07 6.284E*07 5.971E*07 5.816E*07 5.647E*07 CS136 3.842E*07 3.842E*07 3.842E+07 3.840E+07 3.835E*07 3.825E+07 3.629E+07 3.512E*07 3.313E+07 TE137 7.947E+03 2.314E+04 5.206E+04 1.005E+05 2.058E*05 1.042E*06 1.608E*06 2.062E*06 3.338E+06 1137 1.055E+07 1.054E*07 1.051E*07 1.044E*07 1.027E*07 9.370E+06 8.505E*06 8.107E*06 7.706E+06 (* XE137 6.804E*07 6.802E*07 6.792E+07 6.768E*07 6.710E*07 6.412E+07 5.948E+07 5.704E*07 5.355E*07 CS137 1.209E+08 1.210E*08 1.211E*08 1.212E+08 1.214E+08 1.238E*08 1.194E*08 1.167E*08 1.125E*08 BA137M 7.790E+03 2.343E*04 5.471E+04 1.094E*05 2.345E*05 1.420E*06 2.866E+06 4.275E*06 8.404E+06 j 'TE138 1.224E+04 2.709E*04 5.685E*04 1.090E*05 2.282E*05 1.354E*06 E.725E*06 4.059E*06 7.967E*06 1138 2.676E+06 2.674E*C6 2.665E*06 2.644E*06 2.593E*06 2.326E+06 2.088E*06 1.978E+06 1.86SE+06 XE138 3.603E*07 3.601E+07 3.593E*07 3.572E*07 3.525E*07 3.264E+07 2.964E*07 2.809E+07 2.587E+07
, CS138 1.256E*08 1.255E+08 1.255E+08 1.252E+08 1.247E+08 1.221E+08 1.144E*06 1.100E+08 1.025E+08
[ CS138N 1.352E+08 1.352E*08 1.352E+08 1.351E*06 1.348E+08 1.339E+08 1.266E+08 1.223E+08 1.148E*08 1139 4.760E+06 4.768E*06 4.795E+06 4.851E*06 4.975E*06 5.754E+06 5.908E*06 5.940E*06 5.917E+06 XE139 1. 672 E + 07 1. 670 E
- 07 1. 666 E + 07 1. 6552 + 07 1. 630 E
- 07 1. 487E
- 07 1. 333 E
- 07 1. 250 E
- 07 1.122 E + 07 1.027E+08 1.026E*08 1.025E+08 1.022E408 1.014E+08 9.701E*07 8.966E+07 8.553E*07 7.878E+07 CS139._ _,1.287E+08 1.286E*08 1.286E408 1.285E*08 1.282E*06 1.269E+06 1.199E+08 1.157E+08 1.086E+08 BA139
! 1140 1.301E+08 1.301E*08 1.301E+08 1.301E+08 1.300E+08 1.299E+08 1.234E+08 1.195E*06 1.128E+08 ! XE140 5 183E+06 5.178E*06 5.158E*06 5.111E*06 5.004E*06 4.388E+06 3.809E+06 3.500E*06 3.012E+06 CS140 7.279E+07 7.274E*07 7.257E+07 7.217E*07 7.123E+07 6.588E+07 5.937E+07 5.576E*07 4.974E*07 BA140 1.166E*08 1.166E*08 1.166E+08 1.164E*08 1.161E*08 1.147E*06 1.081E*08 1.042E*08 9.764E*07 LA140 6.582E+06 1.873E*07 3.940E*07 6.629E*07 9.986E*07 1.253E*08 1.192E*08 1.154E*08 1.086E*06 XE141 1.242E*06 8.264E*06 2.769E+07 5.769E*07 9.634E*071.260E+081.203E*08 1.171E+061.117E+08 CS141 2.569E*07 2.567E*07 2.559E+07 2.541E*07 2.500E+07 2.270E*07 2.034E*071.913E*071.740E+07 __,9.000E*07 8.998E+07 8.991E+07 8.972E+07 8.925E+07 8.688E*07 8.100E+07 7.753E+07 7.146E+07 84141 LA141 1.182E*08 1.182E+08 1.182E*08 1.183E*06 1.183E+08 1.190E+08 1.131E*08 1.093E+08 1.022E+08 CE141 1.147E+08 1.186E+08 1.186E*08 1.187E*08 1.187E*08 1.195E+08 1.136E+08 1.099E*08 1.028E*06 XE142 1.887E*06 6.729E*06 1.584E*07 3.001E*07 5.533E+07 1.155E+08 1.135E+08 1.104E*08 1.026E+08 CS142 9.244E*06 9.235E+06 9.200E+06 9.119E+06 8.932E+06 7.879E+06 6.929E+06 6.455E+06 5.809E*06 BA142 5.886E+07 5.883E+07 5.871E*07 5.842E*07 5.775E+07 5.401E+07 4.913E*07 4.642E*07 4.201E+07 { 1.159E+08 1.159E+08 1.159E*06 1.158E+08 1.155E*08 1.144E*08 1.076E+08 1.034E*08 9.565E*07 LA142 1.179E + 08 1.178 E + 08 1.178 E + 08 1.178E + 08 1.176 E + 08 1.168E + 08 1.101 E
- 08 1. 060 E + 08 9. 819E
- 07 FR142 ,,_ 7.581E*00 2.131E*02 1.750E*03 7.948E+03 3.829E*04 6,224E*051.389E*06 2.129E*06 4.545E+06 XE143 CS143 1.419E*06 1.418E*06 1.413E*06 1.402E*06 1.375E*06 1.232E+06 1.108E*06 1.053E+06 1.006E+06 j
i 84143 3.166E*07 3.163E*07 3.153E+07 3.131E+07 3.079E+07 2.778E+07 2.456E*07 2.278E+071.979E+07 l LA143 1.059E*08 1.059E+08 1.058E+08 1.056E+08 1.050E+08 1.021E+08 9.482E+07 9.044E+07 8.240E+07 1.174E+08 1.174E+08 1.173E408 1.171E*08 1.166E+08 1.138E+08 1.060E+08 1.011E+08 9.207E+07
\
Rev. 0 l 4/23/83
i e EPIP 1-14 ! Page 33 of 44 l Attachment 4 j Page 6 of 6 CORE ISOTOPE INVENTORY (CONT'D) i
' -._.a. __ ..
OUTPUT UNIT = 6 , FISSION P900 FISSION PROD INVENTORY VS. IRRADIATION TIME POWERS 2.43600E+03MW. SURNUPs 2.64925E*0HedO, FLUXs 2.3tt+14N/Cnent-SEC g-
SUMMARY
TABLES RADIOACTIVITY.' CURIES
. CORE FUEL LOAO*256.000 L8 a 116 MTIMM. 1.88% ENRICH.e POWERS 2436 NW 1.00 3.00 7.00 14.00 30.00 180.00 1.0YR 1.SYR 3.0YR r CE143 4.605E+07 9.148E*07 1.140E+08 1.172E+08 1.171E+08 1.143E*08 1.065E*08 1.016E+04 9.259E+07
,PR143 1.253E*06 8.245E+06 2.647E*07 5.350E+07 8.638E+071.138E*08 1.060E*08 1.012E+08 9.215E*07
.CS144 7.703E+D6 7.700E*06 7.683E*06 7.641E*06 7.543E+06 7.041E*06 6.495E*06 6.249E*06 6.025E*06 l BA144 _ 8.585E+07 8.580E*07 8.565E+07 8.527E*07 8.440E*07 7.943E+07 7.221E*07 6.802E+07 6.055E*07 j LA144 1.072E*08 1.072E+08 1.071E+08 1.068E*06 1.060E*08 1.019E+08 9.391E*07 8.912E+07 8.029E*07 ,
- CE144 f.639E*05 7.899E*05 1.833E+06 3.626E*06 7.579E+06 3.690E+07 5.859E+07 7.075E+07 8.195E+07 l
PR144 2.726E*05 8.354E*051.974E*06 3.907E*06 8.026E*06 3.746Ee07 5.909E*07 7.122E+07 8.239E*07 1 i lCS145..._1.917E*061.916E*061.912E+061.902E+061.479E*061.762E 8A145 LA145 4.171E*07 4.169E*07 4.164E+07 4.149E*07 4115E+07 3.930E*07 3.624E*07 3.450E*07 3.162E+07 7.464E+07 7.46tE*07 7.457E+07 7.441E+07 7.403E+07 7.205t*07 6.709E*07 6.413E+07 5.882E+07 I
'CE145 7.904E+07 7.902E*07 7.899E*07 7.886t+07 7.855E+07 7.704E*07 7.207E+07 6.905E*07 6.354E*07 kPR145 . _.7.39tt+07 7.449E*07 7.901E*07 7.466E+07 7.457E+07 7.706E+07 7.209E*07 6.908E+07 6.357E+07 BA146 1. 538E *07 1.538E
- 07 1.535E
- 07 1.528E
- 07 1. 511E + 07 1.422E* 07 1. 309E
- 07 1. 250E
- 07 1.170 E + 07 l LA146 4.780E*07 4.779E*07 4.776E*07 4.765E+07 4.739E+07 4.614E+07 4.315E*07 4.144E*07 3.867E*07 CE146 6.077E*07 6.077E+07 6.077E+07 6.072E*07 6.059E*07 6.018E*07 5.690E+07 5.494E*07 5.154E+07
. PR146 . . 6 094E*07 6.093E*07 6.093E*07 6.069E*07 6 077E*07 6.039E*07 5.712E*07 5.516E*07 5.176E*07
;84147 3.481E+06 3.480E*06 3.473E+06 3.455E*06 3.412E*06 3.194E+06 2.944E+06 2.824E*06 2.697E+06 LA147 2.298E+07 2.298E*07 2.196E+07 2.290E*07 2.276E+07 2.21tE*07 2.074E*07 2.000E*071.895E*07
( CE147 4.560E*07 4.560E*07 4.562E*07 4.561E*07 4.558E+07 4.573E*07 4.359E+07 4.232E*07 4.023E+07 4 PR147 4,663E+07 4.663E*07 4.665E+07 4.665E+07 4.665E+07 4.692E+07 4.480E*07 4.353E*07 4.141E+07 ND147 2.796E*06 7.955E*06 1.650E+07 2.711E*07 3.918E*07 4.667E+07 4.462E *07 4.342E+07 4.142E*07 . s PM147 1.021E+03 8.880E+03 4.455E*04 1.551E*05 5.350E*05 4.367E*06 7.428E*06 9.247E+06 1.108E+07
- LA148 8.361E*06 8.360E*06 8.354E*06 8.332E*06 4.281E+06 8.061E*06 7.610E*06 7.391E+06 7.163E406
! CE148 _ _ 3.164E*07 3.164E+07 3.167E+07 3.189E*07 3.194E+07 3.240E*07 3.134E+07 3.070E*07 2.965E+07
! lPR144 3.495E+07 3.496E+07 3.500E*07 3.505E*07 3.514E+07 3.604E+07 3.493E+07 3.429E+07 3.340E*07 l 'PM148 9.230E+01 2.007E+03 2.054E*04 1.171E*05 5.936E+05 6.618E*06 1.085E*07 1.340E+07 1.649E*07 ' PN1494 5.911E+00 1.447E*02 1.593E+03 1.002E+04 5.950E*04 9.182E+05 1.559E*06 1.945E+06 2.322E406 LA149 1. 964E +06 1. 964E
- 06 1.963E
- 06 1. 958E
- 06 1.946E +06 1.903E +06 1.819E
- 06 1.789E
- 06 1. 802E + 06 CE149 1.690E
- 07 1.691 E + 07 1.692 E
- 07 1.694 E + 07 1.698E
- 07 1. 740 E
- 07 1.698 E + 07 1. 679E
- 07 1.677E
- 07 i PR149 2.tS8E+07 2.260E*07 2.264E+07 2.272E+07 2.289E+07 2.416E+07 2.391E*07 2.379E+07 2.386E+07
- NO149 2.293E+07 2.295E+07 2.300E*07 2.309E*07 2.328E+07 2.470E*07 2.458E+07 2.457E+07 2.499E+07 l Pn149 . 5.509E+06 1 344E*07 1.992E*07 2.231E+07 2.310E+07 2.895E*07 3.153E+07 3.316E*07 3.579E*07
'CE150 6.981E+06 6.986E*06 7.000E*06 7.023E+06 7.073E*06 7.490E*06 7.522E*06 7.592E*06 7.956E*06 ,
- PR150 1. 313E+07 1. 315E +07 1. 320E
- 07 1. 329E + 07 1. 350E+ 07 1.497E* 07 1. 536 E + 07 1. 563E + 07 1. 647E
- 07,
- CE151 2.019E*06 2.021E+06 2.024E+06 2.030E+06 2.041E*06 t.154E+06 2.180E*06 2.221E*06 2.397E+06 1 i PR151 6.828E*06 6.838E*06 6.869E+06 6.929E*06 7.061E+06 7.993E*06 8.340E+06 8.587E+06 9.288E*06 l NO151 9.251E+06 9.269E*06 9.328E*06 9.446E+06 9.705E*06 1.147E*07 1.220E+07 1.267E*07 1.305E*07 PN151' 4.063E+06 7.639E*06 9.124E*06 9.388E+06 9.710E*06 1.149E+07.1.223E+07 1.271E*07 1.389E+07 PR152 2.926E+06 2.930E*06 2.943E+06 2.968E+06 3.022E+06 3.418E*06 3.597E+06 3.737E+06 4.149E*06 NO152 5.892E*06 5.907E*06 5.955E+06 6.053E*06 6.270E*06 7.725E*06 8.411E*06 8.835E+C6 9.843E*06 -
Pn152 5.980E+06 6.009E*06 6.065E+06 6.167E+06 6.393E+06 7.904E+06 8.616E+06 9.056E*06 1.009E*07 PR153 9.369E*05 9.380E*05 9.409E+05 9.461E*05 9.571E+05 1.052E*06 1.104E*06 1.154E*06 1.316E*06 ) ND153 3.435E*06 3.444E*06 3.470E+06 3.522E*06 3.639E*06 4.439E+06 4.852E*06 5.131E*06 5.839E+06 - PM153 3.766E+06 3.777E*06 3.809E+06 3.875E*06 4.022E+06 5.015E+06 5.526E+06 5.858E*06 6.666E*06 ) 5H153 1.124E*D6 2.480E*06 3.510E+06 3.926E*06 4.316E+06 8.499E+06 1.308E+071.729E*07 2.937E+07 i' ND154 1.400E+06 1.405E*06 1.423E+06 1.458E*06 1.537E*06 2.074E*06 2.399E*06 2.616E*06 3.148E*06 PN154 1.61bE+06 1. 622E+06 1.646E*06 1.695E*06 1.804E+06 2.534E+06 2.967E*06 3.245E+06 3.897E*06 ND155 _ __5.119t+05 5.140E*05 5.204E+05 5.335E*05 5.625E+05 7.647E+05 8.981E+05 9.915E*051.229E*06 - PM155 8.542E+05 8.594E+05 8.765E+05 9.119E+05 9.908E+05 1.515E*06 1.838E+06 2.043E*06 2.513E*06 i lSM155 9.063E+05 9.126E+05 9.332E+05 9.759E+051.071E+061.704E*06 2.097E*06 2.350E*06 2.949E+06 PM156 3.St9E+05 3.561E+05 3.665E+05 3.879E+05 4.359E+05 7.567E*05 9.709E+05 1.111E+06 1.43eE*06
',SM158_ __ _ 3.Sitt+05_4.260E+05 4.454E+05 4.770E+05 5.484E+05 1.018E+06 1.319E*06 1.507E+06 1.927E+06 L
e Rev. 0 4/23/83
1 EPIP 1-14 4 Page 34 of 44 Attachment 5 Page 1 of 1 FRACTIO 11AL RELEASE RATIOS ISOTOPE HALF-LIFE (HRS.) RELEASE RATIO
- i I -1 31 193. 1.000 I-132 2.28 0.109 I-133 20.8 0.328 I-134 .877 .0674 t I-135 6.59 0.185 Kr-85m 4.48 0.189 Kr-87 1.27 0.100 Kr-88 2.84 0.150 Xe-133 126. 1.000 Xe-135 9.09 0.269y-t ham Mfe of isotope IU
- Ratio = 1 I for noble gases -
g Half life of Xe-133 ; ' ' l' ! l
- ll l
I I/2
, ; Half life of isotope for icdines, .
g Half life of I-131 g , c
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e
~ ^j, ,A i , - ,-
a p=' f , l r { / l
.s Rev. 0 >'
4/23/83' ,
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