ML033300355
| ML033300355 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 11/12/2003 |
| From: | Inzirillo F, Weaver D Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| -RFPFR | |
| Download: ML033300355 (87) | |
Text
12-NOV-03 Page: 16 DISTRIBUTION CONTROL LIST Do ument Name: EMER PLAN CCNAME NAME DEPT LOCATION 2 EP/TRAINING ADMINISTRATOR TRAINING (ALL EP'S) #48 3 RES DEPARTMENT MANAGER RES (UNIT 3/IPEC ONLY) 45-4-A 4 REFERENCE LIBRARY REC/TRN(UNT 3/IPEC ONLY) BLDG/17 9 JOINT NEWS CENTER EMER PLN (ALL EP'S) EOF 10 SHIFT MGR.(LUB-001-GEN) OPS (UNIT 3/IPEC ONLY) IP3 11 CONTROL ROOM & MASTER OPS(3PT-D001/6(U3/IPEC) IP3(ONLY) 14 EOF E-PLAN (ALL EP'S) EOF 16 AEOF/A.GROSJEAN(ALL EP'S) E-PLAN (EOP'S ONLY) WPO-12D 19 NUC ENGINEERING LIBRARY DOC (UNIT 3/IPEC ONLY) WPO/7A 21 TSC RECORDS 45-3-F 22 RESIDENT INSPECTOR US NRC 88' ELEVATION IP2 23 SILK DAVID NRC (ALL EP'S) OFFSITE 24 SILK DAVID NRC (ALL EP'S) OFFSITE f25 DOCUMENT.CONTROL..DESK NRC (ALL EP'S) OFFSITE 28 AVRAKOTOS N J A(UNIT 3/IPEC ONLY) OFFSITE 29 E-PLAN STAFF E-PLAN (ALL EP'S) EOF 30 E-PLAN STAFF E-PLAN (ALL EP'S) EOF 31 BARANSKI J(VOLUME I ONLY) ST. EMERG. MGMT. OFFICE OFFSITE 32 SUTTON A -(VOLUME I ONLY) DISASTER & EMERGENCY WESTCHESTR 33 LONGO N (VOLUME I ONLY) EMERGENCY SERVICES ROCKLAND 34 GREENE D (VOLUME I ONLY) DISASTER & CIVIL DEFENSE ORANGE 35 RAMPOLLA M(VOLUME I ONLY) OFFICE OF EMERG MANAGE PUTNAM 41 SIMULATOR TRAIN(UNIT 3/IPEC ONLY) 48-2-A 107 QA MANAGER QA (UNIT 3/IPEC) K-IP2-4302 319 L.GRANT (LRQ-OPS TRAIN) LRQ (UNIT 3/IPEC ONLY) #48 354 L.GRANT(LRQ-OPS/TRAIN) LRQ (UNIT 3/IPEC ONLY) #48 376 E-PLAN STAFF E-PLAN (ALL EP'S) EOF 424 HULBERT TRACY(7COPIES) (UNIT 3/IPEC ONLY) #48 510 L.GRANT(LRQ-OPS/TRAIN) LRQ (UNIT 3/IPEC ONLY) #48 511 L.GRANT(LRQ-OPS/TRAIN) LRQ (UNIT 3/IPEC ONLY) #48 512 L.GRANT (LRQ-OPS TRAIN) LRQ (UNIT 3/IPEC ONLY) #48 513 L.GRANT (LRQ-OPS TRAIN) LRQ (UNIT 3/IPEC ONLY) #48 517 PLANT MANAGER'S OFFICE ADMIN/(UNIT 2/IPEC ONLY) IP2 518 LAZAZZARO MIKE UNIT 2(UNIT 2/IPEC ONLY) IP2 520 CONTROL ROOM (UNIT 2) OPS (UNIT 2 & IPEC ONLY) IP2 521 SIMULATOR TRAIN (UNIT 2/IPEC ONLY) IP2 522 NRC RESIDENT US NRC(UNIT 2/IPEC ONLY) 88'ELV IP2 523 DIGIOVANNI TINA (UNIT 2) REFERENCE LIBRARY 48-2-ALLE 524 JOHN MCCANN (UNIT 2) NUC SAFETY/LIC(ALL EP'S) IP2 558 TORRES DAMARIS R&D EEC BUILDING 2ND FL. IP2
_1OLA _5
IPEC SITE QUALITY RELATED IP-SMM-AD-103 Revision 0 Ent& y MANAGEMENT ADMINISTRATIVE PROCEDURE MANUAL INFORMATIONAL USE Page 13 of 21 ATTACHMENT 10.1 SMM CONTROLLED DOCUMENT TRANSMITTAL FORM SITE MANAGEMENT MANUAL CONTROLLED DOCUMENT TRANSMITTAL FORM - PROCEDURES Page 1 of I JiEnlergv lCONTROLLED DOCUMENT TRANSMITTAL FORM - PROCEDURES TO: DISTRIBUTION DATE: 11/14/2003 TRANSMITTAL NO: 28803 (Cirde one)
FROM: IPEC DOCUMENT CONTROL: EEC or P2 53'EL PHONE NUMBER: 271-7057 The Document(s) identified below are forwarded for use. In accordance with IP-SMM-AD-103, please review to verify receipt, incorporate the document(s) into your controlled document file, properly disposition superseded, void, or inactive document(s). Sign and return the receipt acknowledgement below within fifteen (15) working days.
AFFECTED DOCUMENT: EMERGENCY PLANNING IMPLEMENTATION PROCEDURES DOC# REV# TITLE INSTRUCTIONS NOTE: REPLACE CURRENT INDEX WITH ATTACHED REVISED INDEX.
- FOLLOWVATITACHED INSTRUCTIONS *****************************
- PLEASE NOTE EFFECTIVE DATE***********
RECEIPT OF THE ABOVE LISTED DOCUMENT(S) IS HEREBY ACKNOWLEDGED. I CERTIFY THAT ALL SUPERSEDED, VOID, OR INACTIVE COPIES OF THE ABOVE LISTED DOCUMENT(S) IN MY POSSESSION HAVE BEEN REMOVED FROM USE AND ALL UPDATES HAVE BEEN PERFORMED INACCORDANCE WITH EFFECTIVE DATE(S) (IF APPLICABLE) AS SHOWN ON THE DOCUMENT(S).
NAME (PRINT) SIGNATURE DATE CC#
NAME (PRINT) SIGNATURE DATE CC#
TO: Nuclear Regulatory Commission FROM: IPEC Emergency Planning
SUBJECT:
Emergency Planning Document Update Date: 11/06/03 Please update your controlled copy of the documents listed below as specified with the copy(s) attached.
- Docu-ment Document NAme New Rev.: #1 Old.Rc Instruictions IPEC ~Emergency P~laniplemeniting Procedures :i. : -
TOC IPEC 11/06/03 10/28/03 Replace old with new IP-EP- 15 Emergency Plan Forms Rev. 5 Rev. 4 Replace old with new 11/06/03 07/14103 Rpaeodwt e IP-EP-120 Emergency Classification Rev. 0 Add new procedure to IP-EP-120 Emergency Classification 11/06103 book
Indian Point Energy Center Emergency Plan Implementing Procedures Table of Contents o>-.' d~~~~~~~~~".po 'u-v:,eTil'j Procedure t IP-EP-115 Emergency Plan Forms 5 11/06/03 IP-EP-120 Emergency Classification 0 11/06/03 IP-EP-130 Emergency Notifications and Mobilization 0 05/05/03 IP-EP-250 Emergency Operations Facility 0 03/06/03 IP-EP-251 Alternate Emergency Operations Facility 1 03/06/03 IP-EP-255 Emergency Operations Facility Management and Liaisons N/A VOIDED IP-EP-260 Joint News Center 0 03/06/03 IP-EP-310 Dose Assessment 2 10/28/03 IP-EP410 Protective Action Recommendations 2 06/06/03 IP-EP-430 Personnel Accountability 0 07/09/03 IP-EP-510 Meteorological, Radiological & Plant Data Acquisition System 1 03/06/03 IP-EP-520 Modular Emergency Assessment & Notification System (MEANS) 1 03/06/03 IP-EP-610 Emergency Termination and Recovery 1 03/06/03 IP-EP-620 Estimating Total Population Exposure 1 03/06/03 Page 1 of 1 As of 11/4/03
IPECPNON-QUALITY RELATED IP.EP-115 Revision 5 k EMERGENCY PLANPROCEDURE IMPLEMENTING Energy
.==--Enter PROCEDURES REFERENCE USE Page I of 6 CONTROLLED COPY # - AT Emergency Plan Forms Prepared by: Daria Weaver PrFnt Name
- I11 o1Q Signature LVate Approval: Frank Inzirillo no V ,#Zf I/q/
cj/a Print Name Date Effective Date: 1/ Wo3 This poc-edure xcluded from further ENN-L- 00 reviews EP-IP-EP- 115 (Forms) R5.doc
IPEC NON-QUALITY RELATED SD. EMERGENCY PLAN PROCEDURE IP-EP-1I5 Revision 5
-- . IMPLEMENTING I ==rergy PROCEDURES REFERENCE USE Page 2 of 6 Table of Contents Section Page 1.0 PURPOSE ...................................... 3
2.0 REFERENCES
...................................... 3 3.0 DEFINITIONS ...................................... 3 4.0 RESPONSIBILITIES ...................................... 3 5.0 DETAILS ...................................... 3 5.1 Use of Forms ...................................... 3 5.2 Control of Forms ...................................... 3 5.3 Method of Placing Forms in this Procedure ...................................... 3 6.0 INTERFACES ...................................... 4 7.0 RECORDS ...................................... 4 8.0 REQUIREMENTS AND COMMITMENTS .................................. .. 4 9.0 ATTACHMENTS 9.1 Current List of Effective Forms .. 5
IPEC NON-QUALITY RELATED IP-EP-1 15 Revision 5 Aft EMERGENCY PLAN PROCEDURE
- L-- IMPLEMENTING J2~EnfeIgy PROCEDURES REFERENCE USE Page 3 of 6 Emergency Plan Forms 1.0 PURPOSE This procedure controls Forms used by the Emergency Response Organization during emergencies.
2.0 REFERENCES
NONE 3.0 DEFINITIONS NONE 4.0 RESPONSIBILITIES 5.1 The Emergency Planning Department is responsible for maintaining forms used by the Emergency Response Organization in accordance with this procedure.
5.0 DETAILS 5.1 Use of Forms 5.1.1 The Implementing Procedure that calls for a form to be completed controls the actual use of forms.
5.1.2 Any needed instructions for form completion will either be on the form itself or in the procedure calling for its use.
5.2 Control of Forms 5.2.1 Forms are numbered sequentially as the need for them is defined by other implementing procedures.
5.2.2 Form numbers will be formatted as "Form EP-n Rev x", where n is the sequential number of the form and x is the current revision of the form.
5.3 Method of Placing Forms in this Procedure 5.3.1 Forms are attached as addendums to this procedure. They will appear formatted in the end use format. There will be no annotation on the addendums or actual forms showing addendum number or procedure page number.
IPEC NON-QUALITY RELATED IP-EP-115 Revision 5 Aft EMERGENCY PLAN PROCEDUREP -1 RVSO5 i- - 7 IMPLEMENTING Ltntegy PROCEDURES REFERENCE USE Page 4 of 6 6.0 INTERFACES Attachment 1, Current List of Effective Forms contains interfacing documents to each form.
7.0 RECORDS Forms become official records when completed during a declared emergency.
8.0 REQUIREMENTS AND COMMITMENT CROSS-REFERENCE None 9.0 ATTACHMENTS Attachment 9.1 Current List of Effective Forms
IPEC NON-QUALITY RELATED I-P15 Rvso EMERGENCY PLAN PROCEDURE l l l E IMPLEMENTING D gnte
)'I PROCEDURES REFERENCE USE Page 5 of 6 Attachment 9.1 Current List of Effective Forms Sheet 1 of 2 Form Current Form Title Interfacing Number Revision (number of pages) Procedures EP-1 Rev. 2 NYS Radiological Emergency Data Form, Part 1 IP-EP-130 (1 page) IP-EP-250 IP-1010 (Unit 2)
IP-2001 (Unit 3)
EP-2 Rev. 2 NYS Radiological Emergency Data Form, Part 2 IP-EP-130 (1 page) IP-EP-250 IP-1010 (Unit 2)
EP-3 Rev. 1 CCR NUE Notification Checklist IP-EP-130 (2 pages, used back to back) IP-EP-250 IP-1010 (Unit 2)
IP-2001 (Unit 3)
EP-4 Rev. CCR Initial Notification Checklist-AIertSAElGE IP-EP-130 (2 pages, used back to back) IP-EP-250 IP-1010 (Unit 2)
IP-2001 (Unit 3)
EP-5 Rev. 1 Upgrade / Update Notification AlerVSAE/GE Checklist IP-EP-130 (2 pages, used back to back) IP-EP-250 IP-1010 (Unit 2)
IP-2001 (Unit 3)
EP-6 Rev. 0 Emergency Exposure Authorizations IP-1023 (Unit 2)
EP-7 Rev. 0 EOF Staffing IP-EP-250 EP-8 Rev. 0 Recovery Issues Strategies Form IP-EP-610 IP-EP-250 EP-9 Rev. 1 Essential Information Checklist IP-1010 (Unit 2)
IP-2001 (Unit 3)
EP-10 Rev. 0 ERO Log Sheet IP-EP-250 EP 1 Rev 1 IPEC Manual Dose Assessment Worksheet IP-EP-310 EP- ev. Estimating Containment Activity via R-25 /26 EP-12 Rev. 0 Estimated Total Population Dose (8 pages) IP-EP-620 IPEC Manual Dose Assessment Worksheet TEDE Whole EP-13 Rev. 1 Body Exposure Calculations and TODE Thyroid Exposure IP-EP-310 Calculations (2 pages)
EP-14 Rev. 0 EOF Check Point Sign-In Log (2 pages, used back to back) IP-EP-250 EP-15 Rev. 0 (un-assigned)
EP-16 Rev. 0 (un-assigned)
EP-17 Rev. 0 IP-2 Manual Determination of Release Rate IP-EP-310
IPEC NON-QUALITY RELATED EMERGENCY PLAN PROCEDURE IP-EP-115 Revision 5 IMPLEMENTING Enteg - PROCEDURES REFERENCE USE Page 6 of 6 Attachment 9.1 Current List of Effective Forms Sheet 2 of 2 Form Current Form Title Interfacing Number Revision (number of pages) Procedures EP-18 Rev. 0 IP-3 Manual Determination of Release Rate IP-EP-310 EP-19 Rev. 0 IPEC Manual Dose Assessment Worksheet/Back IP-EP-310
______ __Calculating Release Rate from Field Data EP-20 Rev. Emergency Director Turnover Sheet IP-EP-250 EP-21 Rev. 0 Media Briefing Worksheet IP-EP-260 EP-22 Rev. 0 Media Briefing Issues Form IP-EP-260 EP-23 Rev. 0 JNC Staffing Form IP-EP-260 EP-24 Rev. 0 Emergency Summary Sheet IP-EP-260 EP-25 Rev. Written Statement Distribution Checklist IP-EP-260 EP-26 Rev. 2 Information Distribution Guide IP-EP-260 EP-27 Rev. 0 Public Inquiry - Media Referral and Media Monitoring Form IP-EP-260 EP-28 Rev. 0 Joint News Center Fax Cover Sheet IP-EP-260 EP-29 Rev. 0 Individual Exposure Tracking Log IP-EP-250 EP-30 Rev. 0 Monitoring Team Radiation Field Survey Data IP-EP-250 EP-31 Rev. 0 Monitoring Team Sample Data IP-EP-250 EP-32 Rev. 0 Determination of Radioactive Airborne Concentrations IP-EP-250 EP-33 Rev. 0 Media Inquiry Log IP-EP-260 EP-34 Rev. 0 Courtesy Call Guide IP-EP-260 EP-35 Rev. 0 JNC Talking Points IP-EP-260 EP-36 Rev. 0 Primary - ERO Activation Checklist IP-EP-130 EP-37 Rev. 1 Backup - ERO Activation Checklist IP-EP-130 NRC 361 12-2000 Reactor Plant Event Notification Worksheet (NRC Form) IP-EP-130 IP-EP-1023 Unit 2 EP-38 Rev. 0 Emergency Team Briefing Form IP-2204 Unit 3
New York State Radiological Emergency Data Fon Notification #
Indian Point Energy Center Part I - General Information Instructions
- 2. This is... A. NOT an Exercise B. An Exercise
- 3. The Facility Affected is: A. Unit 2 B. Unit 3 C. Both
- 4. The Emergency A. Unusual Event C. Site Area Emergency E. Emergency F. Recovery B. Alert D. General Emergency Terminated G. Other
- 6. Release of A. No Release Radioactive Materials B. Release BELOW federally approved operating limits (Technical Specifications) due to the Classified Event: E To Atmosphere 0 To Water C. Release ABOVE federally approved operating limits (Technical Specifications) 0 To Atmosphere 0 To Water D. Unmonitored Release - requiring evaluation
- 7. Protective Action Recommendations are recommended to be implemented as soon as practical:
A. No need for Protective Actions outside the site boundary.
B. EVACUATE and implement the KI plan for the following ERPAs and SHELTER all remaining ERPAs:
1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51
- 8. EAL Number: l il Brief Event Description
- 9. The Plant status is: A. Stable C. Degrading E. Cold Shutdown B. Improving D. Hot Shutdown
- 11. Wind Speed: Meters/Second at elevation 10 meters.
- 12. Wind Direction: (From) Degrees at elevation 10 meters.
- 13. Stability Class: A B C D E F G
- 14. Report By: at Telephone Number (914)
(Communicators Name)
Message Received by: l Message Ended at:
Emergency Director Review and Approval:
PartI Effective 11/3103 Page 1 of 1 Form EP-1, Rev 2
New York State Radiological Emergency Data Form Indian Point Energy Center Part II - Radiological Assessment Data This is: A. NOT an Exercise B. An Exercise
- 15. Message transmitted at: Date: Time: Location / Facility transmitted from:
- 16. General release Information:
A. Event Release started Date Time:
B. Event Release expected to end Date: Time:
C. Event Release ended: Date: Time:
D. Reactor Shutdown: N/A OR Date: Time:
Meteorological Data As of Date: Time:
E. Wind Speed meters/second At elevation: meters F. Wind Direction: degrees At elevation: meters G. Stability class (Pasquill):A B C D E F G
- 17. Atmospheric release Information: As of Date Time_
A. Release from: Ground 0 Elevated D. Noble gas release rate: _Csec B. Iodine/Noble gas ratio: E. Iodine release rate Cilsec (Assumed OR Actual)
C. Total release rate: Cl/sec F. Particulate release rate Ci/sec
- 18. Waterborne release Information: As of Date Time_
A. Volume of release gallons C. Radiolnuclides in release:
B. Total concentration: pCi/ml D. Total activity released _ _ C
- 19. Dose calculations (based on a release duration of hours)
Calculation is based on (circle one):
A. Inplant measurements B. Field Measurements C. Assumed source term Table below applies to (circle one) A. At ospheric release B. Waterborne release DOSE DISTANCE Xp/Q TEDE (Rem) TODE (Rem)
Site Boundary = _ __ __
2 Miles 5 Miles 10 Miles
___ Miles
- 20. Field measurement of dose rates or surface contamination/deposition:
Mile/Sector OR Time of Dose Rate (mRlhr) OR Mile/Degrees Location OR Sampling Point Reading Contamination (pCi/m 2 )
Emergency Director Review and Approval:
Part II Page 1 of 1 Form EP-2, Rev 2
INDIVIDUAL EMERGENCY EXPOSURES AUTHORIZATION NAME: SOCIAL SECURITY NO.:
AGE:
Reason for exposure in excess of 5 Rem: (include tasks to be performed)
ESTIMATE OF PLANNED DOSE AUTHORIZED EMERGENCY DOSE WHOLE BODY REM REM EXTREMITY REM REM THYROID REM REM I have volunteered to perform the task(s) during which I will receive the emergency Exposure, and I understand the potential consequences of the proposed emergency from the attached summary.
Individual to Receive Exposure: Date:
(Signature)
EPM/POM Or Emergency Director Approval: Date:
(Signature)
WARNING Emergency worker exposure limits are NOT TO BE APPLIED to minors or Fertile women Emergency Exposure Guidelines:
- 1. All Emergency Exposures shall be authorized by the Emergency Director or Emergency Plant Manager.
- 2. All individuals may be authorized up to 5 Rem emergency exposure for a given emergency event. Historical occupational exposure is not totaled into this limit.
- 3. Procedures allow for the Emergency Director or Emergency Plant Manager to give a blanket authorization of up to 5 Rem emergency exposure for Alert or higher classifications.
- 4. Any emergency exposure greater than 5 Rem Whole Body, 50 Rem Extremities or 50 Rem Skin of Whole Body, shall be authorized on a individual basis for a specific task.
- 5. All emergency exposures are voluntary. - For higher doses individuals over the age of 45 are preferable.
- 6. Individuals shall be briefed that these exposures may increase their chances of cancer during their lifetime.
- 7. Volunteers may be authorized up to 10 Rem to protect valuable property.
- 8. Volunteers may be authorized up to 25 Rem for life saving or the protection of large populations.
- 9. Individuals may volunteer to receive greater than 25 Rem to save a life.
- 10. For any expected or actual Thyroid Exposure > 25 Rem CDE, the issuance of KI should be considered.
Page 1 of 2 Form EP-6 Rev 0
EFFECTS FROM HIGH LEVELS OF RADIATION EXPOSURE Radiation injury depends on numerous factors such as the type of radiation, the parts of the body exposed, the rate and duration of exposure, the number of exposures, and the age and sex of the irradiated person. There are short and long
' v term effects from high levels of radiation exposure.
Short Term Effects:
Whole Body Effects:
15 to 50 Rem - No symptoms, blood test may show some slight changes.
50 to 200 Rem - Some nausea, vomiting, and slight decrease in blood count, no deaths expected.
200 to 450 Rem - Most have nausea, vomiting, and feel flu symptoms. Most have hair loss, infection likely, 10-50% deaths.
450 to 600 Rem - Flu, bleeding from mouth and throat, infections likely, 50-90% deaths.
600 to 1000 Rem- Symptoms worse than above, 90-100% deaths.
Radiation Injury to the Skin:
Less than 1000 Rem - First degree thermal burn (similar to sunburn) to 5000 Rem - Blisters form and break open to 5000 Rem - Similar to scalding or chemical burn Over 5000 Rem - Ulceration and major skin damage x~v Potential LonQ Term Effects: Based on information from the National Research Council (BEIR V).
Cancer Probability: The normal chance of contracting fatal cancer for a group of people with no radiation exposure in the United States is 20%.lf this group of people were exposed to 100 Rem, the chance of any person contracting fatal cancer would increase to 28%.
Genetic Effects: A 100 Rem exposure to radiation is estimated to increase the chance of a genetic effect from 0.25% for the average person with no radiation exposure to 0.5%
Fertility Effects: An exposure to the gonads of 250 Rem may cause reduced fertility, and an exposure of 600 Rem may cause permanent sterility.
Cateracts: (Cloudiness or darkening in the lens of the eyes.) 200 Rem to the eyes may cause cataracts (ICRP 41).
Page 2of 2 Form EP-6 Rev 0
EOF Staffing No. Positions 15'SHIFT 2nd SHIFT 1* Emergency Director 1* ED Technical Advisor 1* Offsite Radiological Manager 1* Offsite Communicator 1 EOF Manager 2** Dose Assessor 1 Radiological Communicator 1 Field Team Coordinator _
6 Field Monitoring Team Members 1 Admin & Logistics Manager _
3 EOF Clerical Staff 1 Lead Offsite Liaison 1 State Liaison 1 Westchester County Liaison 1 Rockland County Liaison I Orange County Liaison 1 Putnam County Liaison 1 Equipment Operator 1 Information Liaison
- Minimum Staffing for facility activation
- Only one Dose Assessor required if determination is made there is limited offsite radiological concerns for event.
Form EP-7 Rev 0
Recovery Issue / Strategies Form Area Owner Safet Rel. Priorit Duration Man-hours Description of Issue Resources Needed Use this form to document major items to be addressed during Recovery.
Area: Onsite / Offsite I Public Information Owner: Responsible individual or organization Safety Related: Yes or No Priority: 1 = Immediate (24 hr.) 2 = Short Term (1Week) 3 = Intermediate (1Month) 4 = Long Term (> 1 Month)
Duration: Estimated Calendar Duration Man-hours: Estimated Total Project Hours Form EP-8 Rev 0
Essential Information Checklist Affected Unit: 0 Unit 2 0 Unit 3 0 Both Status of Unaffected Unit:
Emergency Classification: Reactor: At Power 0 Tripped Time: EAL#:
o Unusual Event RCS:
o Alert - Temp: 'IF Pressure: PSIG o Site Area Emergency RVLIS / Pressurizer Level:
O General Emergency Last Offsite Notification Completed Subcooling:
Method of Core Cooling: 0 S/G 0 Safety Injection 0 RHR Electrical Power Supply: 0 138KV 0 13.8KV 0 # Diesel Generators Event
Description:
Major Equipment Problems:
Current Priorities: High Med Low IJ No Release ID Release Fission Product Barrier Status E Liquid 0 Gaseous Barrier Intact Challenged Lost Release Status: Fuel Clad I 0 0 0 InProgress 0 Expected RCS L 0 0 O Filtered 0 Unfiltered 0 Monitored 0 Unmonitored Containment 0 0 0 0 Controlled 0 Uncontrolled Wind Speed: Wind Direction From:
Date / Time This Checklist was Other:
Completed: / .-
Form EP-9 Rev 1
Emergency Response Organization Log Sheet ERO Position: Date:
Name:
Time Significant Events, Information or Communications 4
4 4
4 4
4 4
4 Signature:
Form EP-1O Rev 0
IPEC Manual Dose Assessment Worksheet Estimating Containment Activity via R-25 / 26 Radiological Data R-25 /26 Reading Rem/hr Dose Conversion Factor (pCucc) / (R/hr)
(from table below) l Time after Shutdown (hrs.) Dose Conversion Factor (Ci/cc) / (R/hr)
< 1000 Rem/hr > 1000 Rem/hr (Gap Release) (Fuel Overheat I Melt Release) 0 0.04 0.03 4 0.12 0.07 8 0.17 0.1 12 0.2 0.13 16 0.22 0.14 20 0.25 0.17 24 0.27 0.18 Vapor Containment Activity Calculation X X 7.4E+10cc l R-25 /26 Dose Containment Total VC Activity (pCi)
Reading (R/hr) Conversion Volume Factor Sheet 1 of 2 Form EP-11 Rev. 1
IPEC Manual Dose Assessment Worksheet Estimating Containment Activity via R-25 / 26 Containment Data Containment Pressure psig Estimated Leak Rate 2 (see table below) (cclsec) - cm Estimated Leak Area Cm2 (leak area =7 Leak Rate per Cm2 VC Pressure Leak Rate (cc/sec) VC Pressure Leak Rate (cc/sec) 1.0 8.34E+03 18.0 1.93E+04 1.5 9.96E+03 20.0 1.95E+04 2.0 1.12E+04 22.5 1.97E+04 2.5 1.22E+04 25.0 1.99E+04 3.0 1.31 E+04 27.5 2.01 E+04 4.0 1.44E+04 30.0 2.03E+04 5.0 1.55E+04 32.5 2.04E+04 6.0 1.63E+04 35.0 2.06E+04 7.0 1.69E+04 37.5 2.07E+04 8.0 1.74E+04 40.0 2.08E+04 9.0 1.78E+04 42.5 2.10E+04 10.0 1.81 E+04 45.5 2. 1E+04 12.0 1.86E+04 47.5 2.12E+04 14.0 1.89E+04 50.0 2.13E+04 16.0 1.91 E+04 Vapor Containment Release Rate Calculation lxl l x Xi 1.OE-06 =
VC Activity Leak Rate Leak Area Conversion VC Release Rate 2
(pCvcc) (from Table) (Cm ) Factor (CUsec)
Sheet 2 of 2 Forrn EP-1 1 Rev. 1
( C. (
ESTIMATED TOTAL POPULATION DOSE Sheet of 8 Sector/Zone Ref. TlD mrem Zone Con. Factor (1) Interpreted mrem (2) Modifier (3) Population (4) Est. WB Rem 1-1 0 1-2 55 1-3 5,90 1-4 20 1 -5 _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 3 35 1 -6 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 35 0 _ _ _ _ _ _ _ _ _ _
1 -7 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 5,4 25 _ _ _ _ _ _ _ _ _ _
1 -8 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _5 ,935_ _ _ _ _ _ _ _ _ _ _
1 .9 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 2 ,345 _ _ _ _ _ _ _ _ _ _
1-10 990
' N B y ~ SECTOR TOTALS:
2-1 0 2-2 _ 40 2-3 _ _ _ _ _ _ _ _ _ _ _1 35 _ _ _ _ _ _ _ _ _ _
2-4 I I __l E140 _
2-5 1,450 2-6 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ 1 ,0 65 _ _ _ _ _ _ _ _ _
2-7 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ 8 25 _ _ _ _ _ _ _ _ _ _
2-8 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _6 95 _ _ _ _ _ _ _ _ _ _
2-9 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 2,2 80 _ _ _ _ _ _ _ _ _ _
2-10 1,370 7 ~~ ;I~ j. . .<'$i~$< ~ ~ ~ ~ ~ SECTOR TOTALS:
(1) Zone In question correction factor (Attachment 2 procedure IP-EP-620 or calculated from formula at bottom of Attachment2 and XuIQ values)
(2) Multiply TLD mrem by Zone Correction Factor (3) If no evacuation, modifier Is 1.0 (4) 1990 Census Form EP-12 Rev 0
(7 ( (
ESTIMATED TOTAL POPULATION DOSE Sheet 2 of 8 Sector/Zone TI-D mrem Zone Corr. Factor (I) Interpreted rnrem (2) Modifier (3) Population (4) Est. WB Rem 3 -1 0 _ _ _ _ _ _ _ _ _ _
3-2 _ _ _ _ _ _ _ _ _ _ 4 .480 _ _ _ _ _ _ _ _ _ _
3-3 _ _ _ _ _ _ _ _ _ _ _8,945 3-4 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _3 ,520 _ _ _ _ _ _ _ _ _ _
3.5 5,315 _ _ _ _ _ _ _ _ _
3-6 _ _ _ _ _ _ _ _ _ _ 3,6 60 _ _ _ _ _ _ _ _ _ _
3-7 4,020 _ _ _ _ _ _ _ _ _ _
3 -8 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _1 ,1 75 _ _ _ _ _ _ _ _ _
3.9 635 3-10 1,455
-,i .'~~~~~~~~~x;
~,, *. ~ ~'~~-~3* , ~SECTOR TOTALS:
4-1 __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _4 0 4 .2 __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _2 ,7 1 5 _ _ _ _ _ _ _ _ _ _
4-3 3,035 _ _ _ _ _ _ _ _ _ _
4 -4 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _1 ,990 4 -5 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _2 ,0 95 4 -6 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _2 ,72 5 4 -7 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _2 ,7 1 5 4 -8 _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _5 ,1 40 4 -9 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _5 ,9 20 4-10 4.475
........~~~ ~~rA~ SECTOR TOTALS:
(1) Zone In question correction factor (Attachment 2 procedure IP-EP-620 or calculated from formula at bottom of Attachment2 and Xu1Q values)
(2) Multiply TLD mnrem by Zone Correction Factor (3) If no evacuation, modifier Is 1.0 (4) 1990 Census Form EP-12 Rev 0
( ( (
ESTIMATED TOTAL POPULATION DOSE Sheet 3 of 8 Sector/Zone TLD mrem Zone Corr. Factor (1) Interpreted mrem (2) Modifier (3) Population (4) Est WB Rem 5-1 65 5-2 505 5 -3 _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _0 5-4 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 2 30 _ _ _ _ _ _ _ _ _ _
5 -5 _ _ _ _ _ _ _ _ _ _ _14 0 5-6 __ _ _ _ _ _ _ _ _ _ _235 5 -7 _ _ _ _ _ _ _ _ _ _1 ,5 90 _ _ _ _ _ _ _ _ _
5-8 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 1 .1 55 5-9 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 4,1 65 5-10 3,450
~~~ "~r.J. Ž~4~~ix;~AI ~ SECTOR TOTALS:
6 -1 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 1 70 _ _ _ _ _ _ _ _ _ _
6-2I=~~ _ _ _ _ _ _ _ _ _ _ 375_ e:-'..~~_____________
6 -3 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 2 60 _ _ _ _ _ _ _ _ _ _
6-4 _ _ _ _ _ _ _ _ _ _ 7 30 _ _ _ _ _ _ _ _ _ _
6 -5 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _2 60 _ _ _ _ _ _ _ _ _ _
6 -6 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 67 5 _ _ _ _ _ _ _ _ _ _
6-7 _ _ _ _ _ _ _ _ _ 1 ,1 4 5 _ _ _ _ _ _ _ _ _
6 -8 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 4 1 5_ _ _ _ _ _ _ _ _
6-9 1,040 _ _ _ _ _ _ _ _ _
6-10 1,740 e, ~~~~~~~~~~~TRTOTALS:
(1) Zone In question correction factor (Attachment 2 procedure IP-EP-620 or calculated from formula at bottom of Attachment2 and Xu/Q values)
(2) Multiply TLD mrem by Zone Correction Factor (3) If no evacuation, modifier Is 1.0 (4) 1990 Census Form EP-12 Rev 0
( (. (
ESTIMATED TOTAL POPULATION DOSE Sheet 4 of 8 Sector/Zone TLD mrem Ratio Corr. Factor (1) Interpreted mrem (2) Modifier (3) Population (4) Est. WB Rem 7-1 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _5 55 7-2 2,100 7-3 980 7-4 l L L _ __ _705 7-5 _ _ _ _ _ _ _ _ _ _ _4 20 _ _ _ _ _ _ _ _ _ _
7-6 _ _ _ _ _ _ _ _ _ _ _5 ,1 50 _ _ _ _ _ _ _ _ _ _
7-7 _ 3,340 7-8 2,505 7-9 __ _ _ _ _ _ _ _ _ _2.010 7-10 6,945
- 0 Th<.-;'v~~ ~ ~ SECTOR TOTALS:
8-1 105 8-2 . 1,835 8-3 ______ _SCTOR _OT A L S1,295 8-4 _ _ _ _ _ _ _ _ _ _ 635 8-5 85 8-6 0 8-7 0 8-8 95 8-9 5,020 8 10 5,955 r~~
~~ ~~ ~ ~
SECTOR TOTALS:
~~~~~~~~~~~~~~~~~
(1) Zone In question correction factor (Attachment 2 procedure IP-EP-620 or calculated from formula at bottom of Attachment2 and XuIQ values)
(2) Multiply TLD mrem by Zone Correction Factor (3) If no evacuation, modifier Is 1.0 (4) 1990 Census Form EP-12 Rev 0
( ( (
ESTIMATED TOTAL POPULATION DOSE Sheet5of8 SectorlZone TLD mrem Zone Corr. Factor (1) Interpreted mrem (2) Modifier (3) Population (4) Est. WB Rem 9-1 465 9 -2 _ _ _ _ _ _ _ _ _ _ 695 _ _ _ _ _ _ _ _ _ _
9-3 _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ 25 _ _ _ _ _ _ _ _ _ _
9 -4 _ _ _ _ _ _ _ _ _ _1 10 _ _ _ _ _ _ _ _ _
9-5 1,110 9-6 3,535 9-7 3.090 9-8 3,710 9-9 5,235 9-10 5,545
- 6 kt l M S S 1 l W W l ~~~SECTOR TOTALS:
1 0-1 _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ 1 50 10-2 _ 1,210 10-3 1,145 10-4 1,845 10-5 8260 10-6 4,440 10-7 2,345 10-8 2,690 10-9 6,320 10-10 9,115
-.. - J SECTOR E TOTALS:
(1) Zone In question correction factor (Attachment 2 procedure IP-EP.620 or calculated from formula at bottom of Attachment2 and XuIQ values)
(2) Multiply TLD mrem by Zone Correction Factor (3) If no evacuation, modifier Is 1.0 (4) 1990 Census Form EP-12 Rev 0
( I (
ESTIMATED TOTAL POPULATION DOSE Sheet 6 of 8 Sector/Zone TLD mrem Zone Corr. Factor (1) Interpreted mrem (2) Modifier (3) Population (4) Est. WB Rem 11-1 0 1 1 -2 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _2 5 11-3 1,505 11-4 2.485 11-5 2,220 11-6 _ _ _ _ _ _ _ _ _ 3,785 11-7 2,830 11-8 1,010 11-9 _ _ _ _ _ _ _ _ _ _ 3,045 11-10 3,705
.* ,. . SECTOR TOTALS:
121 10 12-2 345 12-3 __ _ _ _ _ _ _ _ _ _125 12-4 _ _ _ _ _ _ _ _ _ 295 12 .5 __ _ _ _ _ _ _ _ _ _160 1 2-6 __ _ _ _ _ _ _ _ _ _1 85 _ _ _ _ _ _ _ _ _ _
12-7 80 128 _ _ _ _ _ _ _ _ _ _ _2 0 _ _ _ _ _ _ _ _ _
12 9 __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _1 55 _ _ _ _ _ _ _ _ _ _
12-10 565
~~ ~ ~ *~~~~~** ~~~ SECTOR TOTALS:
(1) Zone In question correction factor (Attachment 2 procedure IP-EP-620 or calculated from formula at bottom of Attachment2 and XuIQ values)
(2) Multiply TLD mrem by Zone Correction Factor (3) If no evacuation, modifier Is 1.0 (4) 1990 Census Form EP-12 Rev 0
( ( (
ESTIMATED TOTAL POPULATION DOSE Sheet 7 of 8 Sector/Zone TLD mrem Zone Corr. Factor (1) Interpreted mrem (2) Modifier (3) Population (4) Est. WB Rem 13-1 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 0 13-2 280 13-3 . . 200 13-4 0 13-5 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 0 13-6 _ _ _ _ _ _ _ _ _ 0 13.7 . 70 13.8 _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ 70 13-9 . 440 13-10 55 li~..$.. s J t -= TOTALS:
'^PT~v¢SECTOR 14-1 __ _ _ _ _ _ _ _ _ _0 14-2 _ _ _ _ _ _ _ _80 14-3 ; ; ;__ _____ _65 14-4 __ _ _ _ _ _ _ _ _ _0 14-5 25 14-6 45 __________
14-7 __ _ _ _ _ _ _ _ _ _20 14-8 __ _ _ _ _ _ _ _ _ _620 14-9 ________________________________ 320 14-10 ___________________________ _____________2,045
~~~~ ~ ~ ~ ~~ ~~ ~~SECTOR TOTALS:
(1) Zone In question correction factor (Attachment 2 procedure IP-EP-620 or calculated from formula at bottom of Attachment2 and XutQ values)
(2) Multiply TLD mrem by Zone Correction Factor (3) If no evacuation, modifier Is 1.0 (4) 1990 Census Form EP-12 Rev 0
( ( (
ESTIMATED TOTAL POPULATION DOSE Sheet 8 of 8 Sector/Zone TLD mrem Zone Corr. Factor (1) Interpreted mrem (2) Modifier (3) Population (4) Est. WB Rem 15-1 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 0 _ _ _ _ _ _ _ _ _ _
15-2 20 15-3 . 105 15-4 180 15-5 __ 45 15-6 0 15-7 20 15-8 305 15-9 25 15-10 1,055
_______,_,,____!____ii-__ ,fl',,t SECTOR TOTALS:
16-1 0 16-2 70 16-3 0 16-4 95 16-5 1,635 16-6 235 16-7 . 0 16-8 35 16-9 25 16-10 0 L:'-"~'
L~ r-*.~'y' l ; *-, J. zt ~ ' SECTOR TOTALS:
(1) Zone In question correction factor (Attachment 2 procedure IP-EP-620 or calculated from formula at botom of Attachment2 and Xu/Q values)
(2) Multiply TLD mrem by Zone Correction Factor (3) If no evacuation, modifier Is 1.0 (4) 1990 Census Form EP-12 Rev 0
Manual Dose Assessment Worksheet TEDE Whole Body Exposure Calculations Date: Time lName:
Meteorology Wind Direction (from): Downwind Sectorl WS = Wind Speed (m/sec):
PasquillCategory: A O B C O D OE O F OG TEDE - Whole Body Exp sure Release Duraton (RD): hrs NGRR XUIQ K1 (1) + Dose Rate(DR) Dose Distance N (Cilsec) (from tables) WS ConstnP Dose RteDr) (mrem)
(Ml'secntnt)(re/ (DR x RD)
Site Boundary X X [ ] X( +
2 Mile X X jj X( +
5Mile X X X +
10OMile X X L ~X +
(1)Obtain K1 value from table below.
(2)Constant for MSL & SGBD is 3.3E+05, for all others use 3.3E+03 (Constant includes Iodine CEDE)
KI Whole Body @ Time After Shutdown K2 Thyroid for Noble Gas DDE For Iodine CDE TAS= hours.
4.7E+5 0- 1.5 Hours Iodine Mix 8.0E+8 2.8E+5 1.5-2.5 Hours 1-131 2.6E+9 2.3E+5 2.5-3.5 Hours 1-132 1.5E+7 2.OE+5 3.5 -4.5 Hours 1-133 4.4E+8 1.7E+5 4.5 - 6.5 Hours 1-134 2.6E+6 1.2E+5 6.5- 12.5 Hours 1-135 7.6E+7 5.8E+4 > 12.5 Hours _________________________-__-_.____________
NOTE:
Particulate Dose Conversion Factor (DCF) for TEDE is 2.7E+07. This DCF should be used applied during dose assessments performed in the EOF or AEOF only if significant particulates are identified in the release (E.G., FSB Accident). Control Room Staff need not consider particulates.
Form EP-13 Rev.1 Page 1 of 2
IPEC Manual Dose Assessment Worksheet TODE Thyroid Exposure Calculations Date: Time Name:
Meteorology Wnd Direction Downwind Sector: WS =Wind Speed (m/sec):
(from):
PasquillCategory: O A B O C D [ E O F 1 G NOTES:
For Less Than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> use Iodine Mix K2 (8.0 E+8)
For Greater Than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, only use 1-131 K2 value when using isotopic analysis. (2.6 E+9)
Isotope 1-131 (or Total Mix) TODE-Thyroid Exposure Release Duration (RD)=
NGRR X K1 A l RR(I. 13 orTotal) X K2 =B XU/ 1teDose A13Dos Distance XuQA+BDs (from tables) l WS l (above) ae(mrem) (DR X RD)
(mrem/hr)
_ __ __ __ _ __ _ _ _ _ _ _ __ _ __ __ _ (m lsec ) _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _
Site Boundary X X( + ) =
2Mile X X(+)= =-
5 Mile X X( + )=
10 Mile X X( + )=
Form EP-13 Rev. 1 Page 2 of 2
EOF Check Point Sign In Log
[ EOF Registration Assistant:
(print name)
Date:
Print Name In / Out In me t Organization Indian Pt. FFD* Yes: O No: I Other I Indian Pt. FFD* Yes: OI No: OI O Other O Indian Pt. FFD* Yes: l No: O O Other O Indian Pt. FFD* Yes: LI No: O O Other O Indian Pt. FFD* Yes: l No: O O Other O Indian Pt. FFD* Yes: LI No: O OI Other OI Indian Pt. FFD* Yes: LI No: O LOther O Indian Pt. FFD* Yes: O No: O O Other O Indian Pt. FFD* Yes: O No: O O Other OIndian Pt. FFD* Yes: O No: O O Other L Indian Pt. FFD* Yes: l No: O OI Other LI Indian Pt. FFD* Yes: LI No: l LOther O Indian Pt. FFD* Yes: L No: O Other If NO, THEN report to EOF Manager for further evaluation.
Page of 2 Form EP-14 Rev 0
EOF Check Point Sign In Log EOF Check Point Instructions:
1.0 Set up a EOF Checkpoint at the entrance to the EOF.
NOTES:
IF there is any question if an individual should be allowed to enter the EOF THEN request clearance from the Emergency Director or the EOF Manager.
Individuals entering the EOF during emergencies must be screened in accordance IPEC Fitness for Duty procedures. The Emergency Director may authorize individuals not meeting these requirements into the EOF.
1.1 Have all individuals entering EOF complete sign in log.
1.2 Request the Admin & Logistics Manager draft someone to take sign in log around to individuals who may have entered facility before check point was set up.
2.0 Allow only the following personnel into the EOF:
A. Indian Point Emergency Response Organization Personnel, as listed in the Emergency Telephone Directory, B. Indian Point Corporate Officers, C. State and County Officials, D. Federal Officials from the Nuclear Regulatory Commission and Federal Emergency Management Agency; E. Individuals authorized by the Emergency Director or the EOF Manager.
NOTE:
IF individuals are only going to another room within the Buchanan Service Center (offices across the hall or men's rest room) THEN it is not necessary to log them in and out each time they leave the EOF.
3.0 Maintain a "EOF Check Point Sign in Log" complete with names of all personnel within the EOF.
Page 2 of 2 Form EP-14 Rev
IP-2 Manual Determination of Release Rate Determine Noble Gas & Radioiodine Release Rates Date: Time: Name:
Plant Vent Release Rate Calculations (use only one vent monitoring method)
R-27 X X 4.7E-04 =
Wide Range Pc'/cc) (Plant Vent CFM)- (Constant) (NGRRCUsec)
R-44 X X 4.7E-04 =
Low I Mid Range (pcUcc) (Plant Vent CFM)- (Constant) (NGRRCai/sec)
Vent Contact X X X 4.7E-04 =
Reading (mRfb) (Conv. Factor) (Plant Vent CFM)l (Constant) (NGRRCi/sec)
Time After TAS (hr) Factor TAS (hr) Factor Shutdown 0 -2 2.8E-04 6 -8 4.9E-04 Conversion 2-4 3.4E-04 8 - 12 6.1 E-04 F actor s f or _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
Contact Reading 4-6 4.1 E-04 12 - 24 7.6E-04 Plant Vent x X 4.7E-04 =
Chemistry (picc) Plant VentCFM)- (Constant) (NGRRCi/sec)
SampleII Air Ejector (AE)
Air Ejector X X 4.7E-04 =
R-45 (PUcc) I (AE CFM)- (Constant) (NGRR CUsec)
R-28, R-29 X 2.7E-03 X X 4.9 E-06 =
R-30, R-31 (CPM) (MSL Conv. Factor) (Ibmbr)" (Constant) j (NGRRCiisec)
Steam Generator Blowdown (SGBD)
Chemistry X X 6.3E-05 =
Sample (ACI/cc) (GPM)" (Costaint) (NGRR C/sec)
Total Noble Gas Release Rate: Total NGRR Add Plant Vent + AE + MSL + SGBD Ci/sec Determine Radioiodine Release Rate (RR) In Curies/Second
2.PlantVentNGRR + AENGRR = X 1.OE-04 =
Total Radioiodine Release Rate (Add 1+ 2to Obtain) Total IRR (Ci/sec) =
- If actual flow rate is unavailable, use 70.000 cfm
- If actual flow rate is unavailable, use 20 cfm
- Steam Generator Atmospheric Flowrate 3.50 E+5 Ibm I hr / atmospheric Steam Generator Safety Flowrate 7.60 E+5 Ibm I hr I safety
IP-3 Manual Determination of Release Rate Determine Noble Gas & Radioiodine Release Rates Date: Time: I Name:
Plant Vent Release Rate Calculations (use only one vent monitoring method)
R-27 X 1.OE-06 Wide Range (pCi/sec) (CUpCi)- (NGRR Ci/sec)
R-14 X X 4.7E-04 =
Low/ Mid Range (pcucc) (Plant Vent CFM)- (Constant) (NGRR C/sec)
Vent Contact x x X 4.7E-04 =
Reading (mRf) (Conv. Factor) (Plant Vcnt CFM)* (Cons anl l (NGRR Ci/sec)
(Contact I 6 Ft)
Time After TAS (hr) Contact Factor 6t TAS (hr) Contact Factor 61t Shutdown 0- 2 6.OE-04 2.5E-03 6- 12 2.8E-03 9.5E-03 Conversion 2-4 1.2E-03 3.8E-03 12 - 24 5.5E-03 1.6E-02 Factors for _ _ _ _ __ _ _ _ _
Contact Reading 4 -6 1.6E-03 5.5E-03 24-2 Wk 6.5E-03 2.0E-02 Plant Vent x X 4.7E-04 _
Chemistry Sample (pcc) (Plant ent CFM)- (constant) Csec) s(NGRR Air Ejector (AE)
Air Ejector X X 4.7E-04 -
R-15 (pcucc) (AE CFM)' (constant) CUsec)
I/(NGRR Main Steam Line (MSL)
R-62A, R-62B X X 3.2 E-06 -
R-62C, R-62D (pCI/cc) (Ib)"' (Constant) (NGRR C/sec)
Total Noble Gas Release Rate: Total NGRR Add Plant Vent + AE + MSL + SGBD Ci/sec Determine Radioiodine Release Rate (RR) In Curies/Second
- 1. MSLNG RR = X 1.OE-02 =
- 2. Plant Vent NG RR + AENGRR = X 1.OE-04 =
Total Radioiodine Release Rate (Add 1 + 2 to Obtain) Total IRR (Ci/sec) =
^ If actual flow rate is unavailable, use 70,000 cfm If actual flow rate is unavailable, use 20 cfm Steam Generator Atmospheric Flowrate 6.30 E+5 Ibm 1hr I atmospheric Steam Generator Safety Flowrate 5.50 E+5 Ibm 1hr I safety Page 1 of 1 Form EP-18 Rev O
IPEC Manual Dose Assessment Worksheet Back Calculating Release Rate from Field Data Administrative Data Field Reading Location Field Reading Mileage Miles Field Reading Sector 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 Meteorology l Wind Speed (at time of release) meters/sec XPIQ ___
Radiological Data Field Reading (sd window or Reuter Stokes) mrem / hr Noble Gas DCF (from table below) (mr/hr) / (Ci/cc)
Time after Shutdown (hrs.) Dose Conversion Factor (mr/hr) / (pCi/cc) 0-1.5 4.70 E+5 1.5 - 2.5 2.80 E+5 2.5 - 3.5 2.30 E+5 3.5 - 4.5 2.00 E+5 4.5 - 6.5 1.70 E+5 6.5-12.5 1.20 E+5
> 12.5 5.80 E+4 Release Rate Calculation
( x ) _ ( x ) =
Field Wind X /Q Noble Gas NGRR (Ci/sec)
Reading Speed DCF (mr/hr) (mlsec)
Sheet of 1 Formn EP-1 9 Rev 0
Turnover Sheet Date: Time:
Outgoing: Relieving:
Discuss the following items:
- 2. Initiating Event:
- 3. Current Status of:
A. Personnel Safety:
B. Plant Safety:
C. Release of Non-Essential Personnel:
D. Accountability:
Missing Persons:
Search and Rescue:
E: Radiological Conditions:
F. WPO/JNC Actions:
G. OSC/TSC Status:
H. Offsite Actions (ie: schools, facility activation, PARs, etc.)
- 5. Status of Offsite Notifications: C None (D NYS / Counties 0 NRC (headquarters and Residents QINPO LIANI
- 6. Corrective Actions:
Teams Out:
- 7. Actions Underway:
Priorities:
- 8. Actions that need to be Initiated:
- 9. Prognosis:
Form EP-20, Rev 1
Media Briefing Worksheet Date: Briefing #:
Time: Briefing Announced: O Yes ONo Reason for Briefing: Li Initial Briefing Li Emergency Classification Change Li EAS Broadcast E3 Periodic Update Other Points to be Covered Order Entergy Westchester County Rockland County Putnam County Orange County (confirm if via PictureTel or teleconference)
State of NY Public Inquiry Feedback Media Monitoring Feedback Graphic Changes Needed:
Graphics I Visual Requests:
Form EP-21 Rev. 0
Media Briefing Issues Form Time Noted: INoted By:
Type of Issue: l Incorrect Information l Additional Information Needed l Clarification Requested l Unanswered Question Issue:
Type of Resolution: I Provide Information to Media Rep. LI Include in Written Statement LI Include in Next Media Briefing L Brief Spokesperson(s) Other Resolution Details:
Page 1 or 1 Form EP-22, Rev 0
( C. (:
,54 Ai 11. -V4., V N-, list, z re 1 s Shift Time Time 2nd Shift Time Time Position Name (print) Arrived Departed Name (print) Arrived Departed JNC Director Company Spokesperson'-,
-JNCTechnical Advisor.
Technical Briefer
- .Agency Liason.....', ,.
SuportServics Manager Media Room Manager.
Media Room Liaison JNC Writer JNC Documenter Audiovisual Coordinator AV I Gra'phics'Staff ;'-.,.
,(2 minimum for activation; :-
may incuiLde Audiovisual,___
Coordinator). '
Date: Page 1 of 3 Form EP-23 Rev. 0 Shaded positions entail functions that are required for activation
( C (
- ~*iSN7*F.
.v; NC *0* t -$ ' i
~~~'~-
- $v~~~~;4;t> JNC- OHMSTAFF1N,'FO 'j~vi.
Is' Shift Time Time 2nd Shift Time Time Position Name (print) Arrived Departed Name (print) Arrived Departed Public Inquiry Coordinator.
Media Monitoring Staff Media Referral Staff Member(s)
Public Inquiry Staff (as required)
Date: Page 2 of 3 Form EP-23 Rev. 0 Shaded positions entail functions that are required for activation
( Shf Tm Tm 2 dShf Tm(Tm (
NC-'ST
. . 1St~~I" Shift Time Time 2nd Shift Time Time Position Name (print) Arrived Departed Name (print) Arrived Departed Support Services Staff Registration Coordinatoir.
Registration Coordinator IT Representative Radiological Advisor jNC Access Control IP Communications Representative Government Liaison Rep Government Liaison Rep Government Liaison Rep Date: Page 2 of 3 Form EP-23 Rev. 0 Shaded positions entail functions that are required for activation
Emergency Summary Sheet Indian Point Enery Center 0
Time: 0 Date:
- 1. This is a Drill i This is an Actual Event Ij I
/ Putnam County
- 2. Emergency Classification: \_Westchester
> County Unusual Event I 270- 900 Alert I Site Area Emergency Li General Emergency Ij
- 3. Event
Description:
180
- 4. Radiological Conditions:
Release of E Radioactive Materials No Release due to the classified Q Release BELOW federally approved operating limits event. (Technical Specifications) 0 To Atmosphere 0 To Water El Release ABOVE federally approved operating limits (Technical Specifications) 0 To Atmosphere 0 To Water Li Unmonitored Release - Being Evaluated
- 5. Meteorological Conditions:
Wind Speed: MPH Wind Direction (from):
General Weather Conditions:
(To convert Meters I see to Miles / Hr divide by .46) Form EP-24 Rev.
Written Statement Distribution Checklist
'Follow each step below as assigned. Some steps are concurrent, as noted by the numbering. Support Services Manager isto confirm all steps are completed at conclusion.
Statement Number: II I Step JNC Position Completed By (Print)
- Responsible Detail Description and Time 1 Support Obtain "APPROVED WRITTEN STATEMENT/NEWS Services RELEASE" from JNC Writer and start distribution Manager process:
E Have Company Spokesperson initial, notify Documenter of approval time o Start a Written Statement Distribution Checklist and Fax Distribution Sheet (in Position Binder and file cabinet)
E Record Statement Number above O Give Original statement with Distribution Checklist and Fax Distribution sheet to Support Services Staff to make initial copies.
2 Assigned 03 Make 2 copies of statement Support El Provide Support Services Staff in fax/copy room Services Staff with 2 copies (one for further copying and one Person for fax distribution described below)
E Provide original initialed copy back to Support Services Manager 3a Support Make 48+ copies of final written statement/news Services Staff releases and coordinate distribution with other Support assigned to Services Staff as follows:
Copy area U 16 Copies to Public Inquiry Coordinator o 12+ Copies to the Media Room Liaison for media (Coordinate number needed with Media Room Liaison. Copies to Media may take priority depending on timing.)
o 4 Copies to Media Monitoring Room Personnel 0 8 Copies to Entergy Rooms A/B O Post I Copy on Bulletin Board near JNC Writer E 7 (or 14-2 each) copies to each work room (State, Westchester, Rockland, Putnam, Orange, NRC and FEMA) 0 Upon completion, provide this Distribution Checklist to Support Services Manager Page 1 of 2 Form EP-25 Rev. 1
Written Statement Distribution Checklist v . . . I . ., X . ,I I ..71 1 i Follow each step below as assigned. Support Services Manager is to I confirm all steps are completed.
Statement Number:
I.........1. . 1 -. . . ... 4. .- II 3b Support Concurrently, ensure statement is faxed to locations Service Staff indicated on the Fax Distribution Form. DO NOT SEND in Fax/Copy FAX DISTRIBUTION FORM IN OUT-GOING FAX Room TRANSMISSION, Include Fax Cover Sheet o Complete fax distribution to media on one fax machine o Complete fax distribution to other emergency facilities and other Entergy locations on another fax machine (follow Fax Distribution Form) o Review Fax Confirmation sheets to ensure they state that all transmissions were successfully completed (the text of the confirmation will read OK)
Upon completion, provide fax confirmation sheet(s) to Support Services Manager 4 Support Provide original (initialed) statement; fax confirmation(s);
Services and this Distribution Checklist to JNC Documenter for log Manager keeping L L__J ___
Page 2 of 2 Form EP-25 Rev. 1
Information Distribution Guide T
(Follow the priority ordernoted) I Recipient (follow order for distribution, if possible) Distribution
'-lType of Information Completed By (Print)
I 4 Plant Status, including Utility Room A & B PICS or EDDS data O JNC Technical Advisor (& Radiological sheets, Forms and Advisor) plant parameters (received via fax or o Company Spokesperson from/via JNC Technical O JNC Director Advisor)
O Agency Liaison o JNC Documenter O State/County PlOs (Radiological Data Forms, Part 1 and 2 ONLY)
EAS Statements ALL Locations/All positions (provided by State or 0 Public Inquiry Room & Media Monitoring via Agency Liaison) Room (20+ copies) 0 Entergy Rooms A & B (9+ copies) o State, County and Federal Work Rooms o Media Briefing Room (at assigned time provided by State or Agency Liaison)
Written Statements, Follow Written Statement Distribution Checklist including news releases form 1 All Other Information Request distribution instructions from the Received (via fax or Support Services Manager and/or JNC Director otherwise)
Page 1 of 1 Form EP-26 Rev. 2
PUBLIC INQUIRY - MEDIA REFERRAL -
MEDIA MONITORING FORM Type of call: (Public Inquiry) (Professional Inquiry) (Media Inquiry) (Media Monitor Report)
Date of call/broadcast: Time of call/broadcast:
Name of responder/monitor:
Media Name/Location:
Caller's/Reporter's name: Phone: ( -
Question(s) asked/inaccurate Information:
Response given/Correct Information and Source:
Is call back required: () Yes () No Call Back Number (___
If yes, call back completed at: By:
Was the call referred: (_* Yes () No If yes, to whom?
Further action required: ( Yes () No Was this action completed? (_) Yes (_) No By:
Reported to Public Inquiry Coordinator at:
Public Inquiry Coordinator Notes:
Return completed form to Public Inquiry Coordinator:
Page 1 of 1 Form EP-27 Rev. 0
Joint News Center Fax Cover Sheet FROM:
DATE: TIME:
Number of Pages (including cover):_
U WIRE SERVICES AP/NYC AP/WESTCH ESTER CNN REUTERS AMERICA GANNET SUBURBAN NEWS/WHITE PLAINS BLOOMBERG NEWSWIRE NEW YORK TIMES NEWS SERVICE I U IP EOF OR 13 IP AEOF LI ENTERGY MEDIA RELATIONS U LOCAL OFFICIALS U Other Page 1 of 1 Form EP-28 Rev. 0
Individual Exposure Tracking Log Name: TLD#
__ _ _ _ _ _ _ __ __ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ Em p lo ee # _ _ _ _ _
Available Time Emergency Location / Team / Times Exposure of Dosimeter Exposure
[ (mrem) Reading Reading (mrem)
Team:
Time Out:
Time In:
Team:
Time Out: .
Time In:__ _ _ _ _
Team:
Tim e O ut: __ _ _ _ _ _ ___ _ _ _ _ __ _ _ _ _
Time In:
Team:
Tim e O ut: __ _ _ _ _ _ _ __ _ _ _ _
Time In: _ _ _ _ _
Team:
Time Out:
Time In:
NOTES:
- 1. Use this form to track individual's exposure of ERO members dispatched from EOF/OSCITSC and
- 2. Initial Exposure Limit will be 1000 mrem for duration of emergency. ED or EPM may authorize more exposure.
- 3. If Form is filled transfer Name, TLD # and remaining available exposure to new form and staple this completed form to it.
Form EP-29 Rev 0
MONITORING TEAM RADIATION FIELD SURVEY DATA Team Name: Date:_
Team Member Names:
Count Rate Meter, Model#: Serial#: Ion Chamber, Model#: R-02 Serial#:_
SURVEY LOCATION TIME OW CW (OW-CW)X2 (Sector/Mile, (HH:MM) (CPM) (mR/hr) (mR/hr) (mrad/hr) REMARK StreetlIntersection/ml. to Int.) ___31 _ 31 _ 3_ #I Rma I I Remarks:
NOTES: [1] 24-hr clock 121 Count Rate Meter data or conversion from Dose Rate Meter 1000 CPM = 0.1 mR/hr (OW).
[3] RO-2, Ion Chamber data.
Form EP-30, Rev.0
MONITORING TEAM SAMPLE DATA Team Name: Date:
Sample Location:
Radiation Field Measurements (may be recorded on separate form):
ton Chamber, Model #: __Serial #: Time:
@ 3 in. above ground: @ 3 ft. above ground:
Opened Window (OW) (mR/hr): Opened Window (OW) (mR/hr):_
Closed Window (CW) (mR/hr): -Closed Window (CW) (mRlhr):_
I (OW-CW) X 2 (mrad/hr):
Air Samplina:
Air Sampler, Model #: Serial #:
Particulate Filter: Iodine (C): Iodine (AgZ):
Sampling Start: Time (HH:MM): Flow (CFM): _
Sampling Stop: Time (HH:MM): Flow (CFM): _
Duration (MM)
Average Flow (CFM):
Sample Volume (CF):
Air Sample Counting:
Count Rate Meter, Model #: Serial #: Time:
Part Filter, Bkgd (CPM): Gross (CPM): Net (CPM): _
Iodine (C), Bkgd (CPM): Gross (CPM): Net (CPM): _
Iodine (AgZ), Bkgd (CPM): Gross (CPM): Net (CPM): _
Form EP-31, Rev 0
Determination of Radioactive Airborne Concentrations Where: Volt' isin liters (Liters=2.832xFT3 )
A= Net CPM x 1.OE-09 2 ) Is Efficiency 0.1 for particulate, 0.2 for iodine pci/cc =
B= 2.2xVolxEff.xCCF CCF"3 is .95 for Charcoal, 1.0 for AgZ I Paper Sample Location: O Particulate O Iodine Sample Time: Team:
Sample Net CPM Constant A 4 l, '
X 1 .QE-09 =
Sample Volume Efficiency Constant CCF B in Liters('I (2) (3) B X X 2.2 X pCi/cc A/B pCi/Cc Calculated by: Time:
Sample Location: 0 Particulate IIodine Sample Time: Team:
Sample Net CPM Constant A 4 X 1.OE-09 Sample Volume Efficiency Constant CCF in Liters 1) (2) (3)
X X 2.2 X pCi/cc = A /B = pCi/cc : ' <
Calculated by: Time:
Sample Location: 0 Particulate Iodine Sample Time: Team:
Sample Net CPM Constant A 43 l s,.
X 1.01E-09 = .r -
Sample Volume Efficiency Constant CCF in Liters(') (2) (3) B G X X 2.2 X pCi/cc= A /B = pCi/cc v*
Calculated by: Time:m Form EP-32, Rev 0
MEDIA INQUIRY LOG DATE: TIME:
NAME OF REPORTER:
AFFILIATED WITH:
PHONE NUMBER:
INQUIRY:
RESPONSE
RESPONSE PROVIDED BY:
COMMENTS:
Form EP-33 Rev. 0
Courtesy Call Guide
- 1. EVENT
SUMMARY
(from P Communications Representative)
Indicate Emergency Classification Level (ECL), EALITime Unusual Event Alert Site Area Emergency General Emergency Plant Status/lnformation/Radiological Conditions (notes):
- 2. Script for Courtesy Calls "Hi, my name is I'm representing the Indian Point Energy Center as a Government Liaison Representative.
I'm calling to inform you that....(provide the event information obtained from the IP Communications Representative)....
This is all the information that I have at this point. Entergy will be issuing a news release regarding the event (give timeframe, e.g. within the next 30 minutes).
Should I continue to call you at this number if I need to contact you again?"
Name of GLR:
Time Calls Completed:
Form EP-34 Rev. 0
JNC BRIEFING
SUMMARY
ITALKING POINTS BRIEFING # DATE:
TIME: Start: End:
Indian Point Energy Center declared a at (time). The event was declared as a result of PLANT STATUS/EVENT INFORMATION: :- RESPONSE (SITE, CORPORATE):
I..L RADIOLOGICAL CONDITIONS: EMPATHY:
1-QUESTIONS REQUIRING FOLLOW-UP:
RUMORS TO ADDRESS:
Form EP-35 Rev. 0
PAGE10F2 FACSIMILE of NRC FORM 361 U.S. NUCLEAR REGULATORY COMMISSION (12-2000) OPERATIONS CENTER REACTOR PLANT EVENT NOTIFICATION WORKSHEET EN#
NRC OPERATION TELEPHONE NUMBER: PRIMARY - 301-816-5100 or 800-532-3469, BACKUPS - [1st] 301-951-0550 or 800-449-3694-,
f2'I 301415-0550 and T3 301415 0553 *Llcensees who maintain teir own ETS are provided these telephone numbers.
NOTIFICATION TIME FACILITY OR ORGANIZATION I UNT NAME OF CALLER CALL BACK I EVENT TIME &Zone EVENT DATE POWERIMODE BEFORE POWERIMODE AFTER EVENT CLASSIFICATIONS 1-Hr. Non-Emergency 10 CFR 50.72(b)(1) (v)(A) Safe SID Capability AINA GENERAL EMERGENCY GEN/MEC TS Deviation ADEV (v)(B) RHR Capability AINB SITE AREA EMERGENCY SITIAAEC 4-Hr. Non-Emergency 10 CFR 50.72(b)(2) (v)(C) ControlofRad Release AINC ALERT ALE/MEC () TS Required SID ASHU (v)(D) Accident Mitigation AIND UNUSUAL EVENT UNUIMEC (iv)(A) ECCS Discharge to RCS ACCS (xii) Offslte Medical AMED 50.72 NON-EMERGENCY (see next columns) _ (iv)(B) RPS Actuation (scram) ARPS (xiii) Loss Comm/AsmtlResp ACOM PHYSICAL SECURITY (73.71) DDDD (xi) Offsite Notification APRE 60-Day Optional 10 CFR
.50.73(a)(1) _
MATERLAUEXPOSURE B7?? 8-Hr. Non-Emergency 10 CFR 50.72(b)(3) Invalid Specified System Actuation
_ __ __ __ _ __ __ __ _ __ _ _ _ _ _ _ _ _ _ _ _ _IA IN V FITNESS FOR DUTY HFIT (ii)(A) Degraded Condition ADEG Other Unspecified Requirement OTHER UNSPECIFIED REQMT. (see last column) j i(B) Unanalyzed Condition AUNA (Identify NONR INFORMATION ONLY NNF (iv)(A) Specified System Actuation AESF = NONR DESCRIPTION Include: Systems affected. actuations and their Initiating signals, causes, effect of event on plant, actions taken or planned, etc. (Continued on back)
NOTIFICATIONS YES NO WILL BE ANYTHING UNUSUAL OR 0 YES (Explain above) NO NRC RESI______ENT- - . NOT UNDERSTOOD? UYS(xli bv)0N STATE(s) DID ALL SYSTEMS O YES 0 NO (Explain above)
LOCAL ____FUNCTION AS REQUIRED? 0YS0N Epanaoe OTHER GOV AGENCIES MODE OF OPERATION ESTIMATED MEDIA/-RESS RELEASE UNTIL CORRECTED: RESTART DATE: ADDITIONAL INFO ON BACK MEDIAIPRESSRELEASE I 0 YES NO FAUIMILE O N IL)KM (1W-2uu)0
ADDITlONAL INFORMATION PAGE20F2 RRADIOLOGICAL RELEASES: CHECK OR FILL IN APPLICABLE ITEMS (specfic deta laexplanatlon should be covered In the event description)
LIQUID RELEASE GASEOUS RELEASE UNPLANNED RELEASE PLANNED RELEASE ONGOING TERMINATED MONITORED UNMONITORED OFFSITE RELEASE T.S. EXCEEDED RM ALARMS _ AREAS
- - - - --- - - -- - - -I II IEVACUATED I PERSONNEL EXPOSED OR CONTAMINATED OFFSITE PROTECTIVE ACTIONS RECOMMENDED *Stale release path Indesciption
%... -5..
Release Rate (CUsec) %T. S. Limit HOO GUIDE Total ActIvity (CI) %T. S. Limit HOO GUIDE Noble Gas 0.1 Cl/sec 1000 Ci Iodine uClIsec D10 0.01 Ci Particulate I uCisec I mCi Uquld (excluding tritium 10 uCimin 0.1 Cl and dissolved noble gases)
Uquld (tritium) 0.2 CI/min 5Ci Total Activity PLANT STACK CONDENSERIAIR EJECTOR MAIN STEAM LINE SG ELOWDOWN OTHER RAD MONITOR READINGS ALARM SETPOINTS
%T. S. UMIT hfapplIcable)
RCS OR SG TUBE LEAKS: CHECK OR FILL IN APPLICABLE ITEMS: (specific detalls/explanations should be covered In event description)
LOCATION OFTHELEAK(e.g, So , var, ppo. otcJ LEAK Rate UNITS: gpmlgpd T. S. LIMITS SUDDEN OR LONG-TERM DEVELOPMENT LEAK START DATE TIME COOLANT ACTMTY PRIMARY SECONDARY AND UNITS:
LIST OF SAFETY RELATED EQUIPMENT NOT OPERATIONAL EVENT DESCRIPTION (Continued from front)
Emergency Team Briefing Form
'Team #:.^. l I Lead Briefer:_ Date: Location of Work:
K O I&C Rad Maint Time:
" 0 Ops 0 Chem 0 Sec Task (description/understanding/comprehension):
Attach any additional supporting documentation (diagrams,maps,visual aids,procedures,drawings,etc)
Tools, Keys,Equipment and Supplies:
Name I Avail Dose Name I Avail Dose Team Members:
Designate one member as the Team Leader Rad. Brief: L Complete O N/A Estimated Dose: Contact Numbers: -
ERWP: l NIA or #_ _
Method(s) of Communications: U Radio U Phone LI Other:
Recommended Route to Work:
Time released to field: Expected duration in field:
Status / Debrief Items: U Completed Debriefer:
Page 1 of 2 Form EP-38 Rev
Emergency Team Briefing Form Team Dispatch Guidelines:
KA* Technical Briefing, including scope of job, held, description on form. 0
- Radiological Briefing held, available dose on form 0
- Is their Team Number on the form O
- Is the Location of Job and Route on the form 0
- Approximate Duration on form O
- Required Tools on form 0
- Review Safety issues (ie electrical; confined space; lighting; environmental; 0 chemical; fall and fire protection; available/applicable OE; other work in vicinity)
- Do they have HP Coverage if needed 0
- Are the correct Team Members Assigned with names on form 0
- Put contact Phone Numbers on form 0
- Tell them to Report Back Every 20 - 30 Minutes 0
- Have them perform a Radio Check 0
- Give copy of briefing form to Emergency Team Leader 0 Team Check-In Guidelines:
- Ensure All Team Members Returned o
- Record Dose Received 0
- Ask about Job Status 0
- Have them Return Radio to Charger o
- Tell them to Report to Lead Briefer for Debriefing 0 Team Debriefing Guidelines:
- Are there any outstanding safety issues to address? 0
- Were any Non-Quality or Non-Standard Parts used? 0
- Were any Temporary Facility Changes made? O
- Was any excess torque or force applied to components? 0
- Was any valve position or equipment status changed? 0
- Was any work performed which would normally require follow-up Testing? 0 Attach further details as needed to ensure outstanding issues can be addressed during Recovery Phase.
Page 2 of 2 Form EP-38 Rev.O
ENN IPEC NON-QUALITY RELATED IP-EP-120 Revision 0 Aft EMERGENCY PLAN PROCEDURE
- Enter . IMPLEMENTING ON PROCEDURES REFERENCE USE Page 1 of 29 CONTROLLED coPY# '.
Emergency Classification Prepared by: Kelly Walker
&;t N!n 39!
E / E //- 1-6 z Print Name Sig ture Date Approval: Frank nzirillo i7/44 7 Print Name 4.- gnature Date Effective Date: II/L)s This proceJur eexcluded from further ENN-L(-1OUG reviews.
IP-EP-1 10 (Class) RO.doc
ENN IPEC NON-QUALTY RELATED IP-EP-120 Revision 0 a EMERGENCY PLAN PROCEDURE EntergyOR IMPLEMENTING PROCEDURES R
REFERENCE USE Page 2 of 29 Table of Contents Section Page 1.0 PURPOSE ............................................. 3
2.0 REFERENCES
............................................. 3 3.0 DEFINITIONS ............................................. 3 4.0 RESPONSIBILITIES ............................................. 3 5.0 DETAILS ............................................. 5 5.1 Recognizing an Emergency ............................................. 5 5.2 Initial Emergency Declaration from the Control Room ............................................. 5 5.3 While In a Classified Emergency ............................................. 6 5.4 Transitory Events, Spikes and Spurious Indications ............................................ 6 6.0 INTERFACES ............................................. 7 7.0 RECORDS ............................................. 7 8.0 REQUIREMENTS AND COMMITMENTS ............................................. 7 9.0 ATTACHMENTS Attachment 1:Emergency Action Levels .. 8 Attachment 2:Fission Product Barrier Thresholds .. 28
ENN IPEC NON-QUALITY RELATED IP-EP-120 Revision 0 EMERGENCY PLAN PROCEDURE
"_~Ei nte IMPLEMENTING Irg
- PROCEDURES I REFERENCE USE Page 3 of 29 Emergency Classification 1.0 PURPOSE To describe the method for classification of emergencies at IPEC as a Notification of Unusual Event (NUE), Alert, Site Area Emergency (SAE) or General Emergency (GE)
2.0 REFERENCES
2.1 Indian Point Energy Center Emergency Plan 2.2 IP-EP-1 10, Conduct of Operations 2.3 NUMARC/NESP-007, Revision 2, Methodology for Development of Emergency Action Levels 2.3 IP-EP-AD13 IPEC Emergency Action Level Technical Bases 3.0 DEFINITIONS Refer to Reference 2.3 4.0 RESPONSIBILITIES 4.1 The Shift Manager (Control Room Supervisor if the Shift Manager is unavailable or incapacitated) of the affected unit shall implement this procedure for the initial emergency classification. For classifiable events that potentially impact both units (security, natural or man-made events), the Shift Managers for each unit shall confer about the need to classify the event. If it is determined that emergency classification is warranted, the Unit 2 Shift Manager shall declare the event in accordance with this procedure. Once an initial emergency classification has been made, the unit Shift Manager making the initial declaration shall be responsible for any subsequent emergency classifications, regardless of which unit is affected, until such time as relieved by the on-call Emergency Director.
4.2 The Shift Manager, upon initial emergency classification, shall assume the role of Emergency Director and shall act as the Emergency Director until relieved by the On-Call Emergency Director or other qualified Emergency Director (Emergency Plant Manager/ Plant Operations Manager).
4.3 The Emergency Director is responsible for overall command and control of the emergency response, including classifications; notifications, PARs and ensuring all resources are available to mitigate emergency conditions. The Emergency Director is the final authority for determining the emergency classification level (initial classification, upgrading, or terminating to recovery). This authority may not be delegated.
ENN IPEC NON-QUALITY RELATED IP-EP-120 Revision 0 EMERGENCY PLAN PROCEDURE
-Entergy Io IMPLEMENTING PROCEDURES I REFERENCE USE Page 4 of 29 4.4 Initial and subsequent emergency classification shall be made within 15 minutes following the identification of a classifiable event to ensure that prompt notification, mobilization, protective and corrective actions are taken.
4.5 Upon becoming aware of any condition or event that they believe may warrant an upgrade in emergency classification, Emergency Response Organization members shall promptly inform the Emergency Director via their chain of command.
4.6 A broad spectrum of discretion in classifying events is provided under Category 9.0 "Other". In using the Category 9.0 "Other" and in classifying emergencies under circumstances which are not a straight-forward use of the EALs, ERO members should be mindful than an approach is needed which is conservative with respect to public, plant, and personnel safety and with respect to ensuring the adequacy of personnel and technical support. Conservative decisions must be made if the Emergency Director has any doubt regarding the health and safety of the public.
ENN IPEC NON-QUALITY RELATED IP-EP-120 Revision 0 EMERGENCY PLAN PROCEDURE lEntergy. IMPLEMENTING I~ ~~O PROCEDURES I REFERENCE USE IPage 5 of 29 5.0 DETAILS 5.1 Recognizing an Emergency NOTE All classifications are to be based upon VALID indications, reports or conditions.
Indications, reports or conditions are considered VALID when they are verified by (1) an instrument channel check, or (2) indications on related or redundant indicators, or (3) by direct observation by plant personnel, such that doubt related to the indicator's operability, the condition's existence, or the report's accuracy is removed. Implicit in this definition is the need for timely assessment.
5.1.1 When indications of abnormal conditions or events are received, personnel will verify the symptoms/indications and then compare with the Emergency Action Levels (Attachment 1) and Fission Product Barrier Thresholds (Attachment 2).
5.1.2 Identify the highest applicable emergency classification level (if multiple EALs are exceeded) for which an EAL has been met or exceeded considering the following:
(a) The plant condition existing at the time the abnormal condition exists:
. Average reactor coolant temperature > 200OF Average reactor coolant temperature < 200OF
- Defueled (no irradiated fuel in the reactor vessel)
(b) IF conditions warrant the issuance of offsite Protective Action Recommendations (PARs), THEN the classification of General Emergency is required.
(c) IF plant conditions indicate a possible radiological release or a release is in progress or suspected, THEN evaluate the applicability of offsite dose-based EALs (IP-EP-310, Dose Assessment).
(d) IF a classification level was met or exceeded but the classifiable condition no longer exists (a lesser classification level may or may not still be appropriate), THEN refer to Section 5.4, Transitory Events, Spikes and Spurious Indications.
ENN IPEC NON-QUALTy RELATED l-P1o Rvso
_ EMERGENCY PLAN PROCEDURE IP-EP-120 Revision Enterg .
-~~ IMPLEMENTING I/ PROCEDURES I REFERENCE USE Page 6 of 29 5.2 Initial Emergency Declaration from the Control Room NOTE IF the condition or event requiring initial classification potentially affects both units (security, natural or man-made events), THEN the Unit Shift Managers shall contact each other and confer on the need to declare. Upon concurrence, the Unit 2 Shift Manager shall make the appropriate emergency classification and assume the role of Emergency Director.
5.2.1 The Shift Manager (Control Room Supervisor if the Shift Manager is unavailable or incapacitated) shall announce to the Control Room operating staff:
(a) That an emergency has been declared.
(b) The emergency classification level.
(c) That the (Unit 2 or Unit 3) Shift Manager (Control Room Supervisor if the Shift Manager is unavailable or incapacitated) has assumed the role of Emergency Director.
5.2.2 For an emergency declared by the Unit 2 Shift Manager, implement procedure IP-EP-212 "Unit 2 Control Room".
5.2.3 For an emergency declared by the Unit 3 Shift Manager, implement procedure IP-EP-213 "Unit 3 Control Room".
5.3 While In a Classified Emergency 5.3.1 Emergency response personnel shall continuously review the Emergency Action Levels (Attachment 1) and Fission Product Barrier Thresholds (Attachment 2) to ensure appropriate event classification.
5.3.2 If an Emergency Action Level threshold is exceeded for an emergency classification higher than currently declared, the Emergency Director shall re-classify the event to the appropriate level and initiate all required notifications.
5.4 Transitory Events, Spikes and Spurious Indications 5.4.1 Transitory events that result in exceeding the Emergency Action Level criteria for event declaration, but which are terminated before they are declared, should still be identified, documented and reported (10CFR50.72), but not declared to implement the Emergency Plan.
ENN IPEC NON-QUALITY RELATED IP-EP-120 Revision 0
___ EMERGENCY PLAN PROCEDURE
=Entergy IMPLEMENTINGG I ~ E PROCEDURES I REFERENCE USE IPage 7 of 29 5.4.2 In the case of a "spike" in a plant indication or event which rapidly exceeds and then decreases below an Emergency Action Level threshold, entry into the Emergency Plan or escalation to a higher classification "in retrospect" is not appropriate unless the "spike' is indicative of continuing degrading conditions which will lead to an escalated emergency classification level.
Examples include momentary steam generator level shrink following reactor trip or brief wind gusts in excess of classifiable levels.
5.4.3 Spurious alarms or parameters, which are known to be invalid indicators of actual plant conditions or of the emergency classification, should not be used to declare emergency classifications.
6.0 INTERFACES 6.1 IP-EP-130, Emergency Notification & Mobilization 6.2 IP-EP-212, Unit 2 Control Room 6.3 IP-EP-213, Unit 3 Control Room 6.4 IP-EP-222, Unit 2, Technical Support Center 6.5 IP-EP-310, Dose Assessment 6.6 IP-EP-410, Protective Action Recommendations 6.7 IP-EP-510, Meteorological, Radiological & Plant Data Acquisition 6.8 IP-EP-520, Modular Emergency Assessment & Notification System (MEANS) 7.0 RECORDS Any logs or forms completed by members of the ERO during an actual declared emergency are permanent quality records.
8.0 REQUIREMENTS AND COMMITMENTS NONE 9.0 ATTACHMENTS 9.1 Attachment 1, Emergency Action Levels 9.2 Attachment 2, Fission Product Barrier Thresholds
( ( (
ENN IPEC NON-QUALITY RELATED PROCEDURE IP-EP-120 Revision 0 Enterg. PROCEDURESN REFERENCE USE Page 8 of 29 Attachment 1 - Emergency Action Levels CATEGORY 1.0 CSFST STATUS Category General Site Area Alert Unusual Event 0
1.1 1.1.3 {> 2001F) 1.1.2 {> 2000F} 1.1.1 {> 200 F}
Subcriticality RED path in F-0.1, Subcriticality RED path in F-0.1 Subcriticality Any Failure of an automatic trip signal to AND AND reduce power range < 5%
Actual or imminent entry into either: ALL manual attempts at tripping AND the reactor from the Control RED Path in F-0.2, Core Cooling Room have failed to reduce Manual trip is successful OR power range < 5%
Red Path in F-0.3, Heat Sink 1.2.2 > 2000 F} 1.2.1 {> 200F}
1.2 RED path in F-0.2,Core Cooling ORANGE or RED path in F-0.2, Core Cooling Core Cooling AND Functional restoration actions taken and procedures not effective within 15 min.
1.3.1 {> 200°F}
1.3 RED path in F-0.3, HEAT SINK Heat Sink AND Feed & Bleed is required 1.4 1.4.1 {> 2001F}
Integrity RED Path on F-0.4, Integrity 1.5 1.5.1 {> 2001F}
Containment RED Path F-0.5, Containment resulting from loss of coolant.
( ( (
ENN PEC NON-QUALITY RELATED PROCEDURE IP-EP-120 Revision 0 r ~IMPLEMENTING ntergy. PROCEDURES REFERENCE USE Page 9 of 29 Attachment 1 - Emergency Action Levels CATEGORY 2.0 REACTOR FUEL Category General Site Area Alert Unusual Event 2.1 2.1.3 {> 200 0F} 2.1.2 {> 2000 F1 2.1.1 {All)
Coolant Activity Coolant activity > 300 pCilcc 1-131 Coolant Activity> 300 tiClcc 1-131 Coolant sample equivalent and any of the following: equivalent activity in excess of
- RED path on F-0.4, INTEGRITY Technical
. limits
~~~~~~~~~~~~~~~~~~Specific
- Primary system leakage exceeding capacity (> 75 gpm) of a single charging pump
- [Unit 2] Rise in R-41 or R-42 offscale due to RCS leakage
- [Unit 3] > 0.06 gClcc on R-1 1 or R-1 2 due to RCS leakage 2.2 2.2.3 {> 2000 F} 2.2.2 {> 2001F} 2.2.1 {> 200 0F)
Containment Containment Containment Radiation monitor [Unit 2] Rise on R-41 or R-42 offscale Radiation Radiation monitor R-25 or R-26 > 17 R1HR due to RCS leakage R-25 or R-26 OR
> 68 RHR
[Unit 3] > 0.06 ,iCllcc on R-1 1 or R-1 2 due to RCS leakage
( (I. (
EMERGENCY PLAN NON-QUALITY RELATED PROCEDURE IP-EP-120 Revision 0 IMPLEMENTING "Enterg . PROCEDURES REFERENCE USE Page 10 of 29 Attachment I - Emergency Action Levels CATEGORY 2.0 REACTOR FUEL Category General Site Area Alert Unusual Event 2.3 2.3.2 {All) 2.3.1 {All)
Refueling Confirmed sustained alarm on any of the [Unit 2] or [Unit 3]
Accidents or following radiation monitors resulting spent fuel pool Other Radiation from fuel damage caused by an (reactor cavity during Monitors uncontrolled fuel handling process: refueling) water level cannot be restored
- R-2/R-7 Vapor Containment Area and maintained above Monitors the Technical
- R-5 Fuel Storage Building Area Specification Monitor minimum water level
- R-25/26 Vapor Containment High Radiation Area Monitors 2.3.3 {All)
Report of visual observation of (Unit 2 or Unit 3) irradiated fuel uncovered
( C. (
EMERGENCY PLAN NON-QUALTY RELATED PROCEDURE IP-EP-120 Revision 0 IMPLEMENTING R
"'Entergy PROCEDURES REFERENCE USE Page 11 of 29 Attachment 1 - Emergency Action Levels CATEGORY 3.0 REACTOR COOLANT SYSTEM Category General Site Area Alert Unusual Event 3.1 3.1.3 {>200'F, 5 200F } 3.1.2 {>2001F} 3.1.1 {>200 0F}
RCS Leakage RVLIS cannot be maintained [Unit 2] Primary system leakage exceeding Unidentified or pressure
> 41% [Unit 3] > 33% with no RCPs capacity (> 75 gpm) of single boundary leakage running charging pump > 10 gpm OR OR With the reactor vessel head removed, Identified leakage it is reported that water level in the > 25 gpm Reactor Vessel is dropping in an uncontrolled manner and core uncovery is likely 3.2 3.2.2 {>2001F} 3.2.1 {>2001F}
Primary to Unisolable release of secondary side to Unisolable release of Leconae atmosphere from the affected steam secondary side to atmosphere Leakage generator(s) with primary to secondary from the affected steam leakage exceeding capacity (> 75 generator(s) with primary to gpm) of a single charging pump secondary leakage >
Technical Specifications limit 3.2.3 {>2000 F} in any steam generator Unisolable release of secondary side to atmosphere from the affected steam generator(s) with primary to secondary leakage > Technical Specification limit in any steam generator AND Coolant activity > 300 ptCi/cc of 1-131 equivalent 3.3 3.3.1 >2000 F}
RCS Subcooling RCS subcooling < S initiation setpoint due to RCS leakage
( ( .7 EMERGENCY PLAN NON-QUALITY RELATED PROCEDURE IP-EP-120 Revision 0 IMPLEMENTING
'Entergy PROCEDURES REFERENCE USE Page 12 of 29 Attachment 1 - Emergency Action Levels CATEGORY 4.0 CONTAINMENT Category General Site Area Alert Unusual Event 4.1 4.1.4 {>200'F} 4.1.2 {>2000 F} 4.1.1 >200 0 F}
Containment Confirmed Phase "B" isolation signal following confirmed Rapid uncontrolled decrease in Both doors open on a Integrity Status LOCA with less than minimum containment cooling containment pressure following VC airlock for > 4 hrs.
safeguards equipment operating, Table 4.3 initial increase due to RCS failure OR AND OR Inability to close Any indicators of fuel clad loss, Table 4.1 Loss of primary coolant inside containment pressure containment with containment relief or purge valves pressure or sump level response which results in a 4.1.5 {>2001F} not consistent with LOCA radiological release EITHER: conditions pathway to the environment for > 4 hrs.
Rapid uncontrolled decrease in containment pressure following initial increase due to RCS failure OR OR Any Phase "A" or Loss of primary coolant inside containment with Phase "B" or containment pressure or sump level response not ionain veno consistent with LOCA conditions solaon valve(s) not
. ~~~~~~~~~~~~~~~~~~~~~~~~c when required AND which results in a Any indications of fuel clad damage, Table 4.2 radiological release pathway to the environment
( ( (
MGENNNIPEC P NON-QUALITY RELATED PROCEDURE IP-EP-120 Revision 0 IMPLEMENTING l Enfergy PROCEDURESl REFERENCE USE Page 13 of 29 Attachment 1 - Emergency Action Levels CATEGORY 4.0 CONTAINMENT Category General Site Area Alert Unusual Event 4.1 4.1.6 {>2000 F} 4.1.3 {>200F}
Containment EITHER: EITHER:
Integrity Status Any Phase "A" or Phase "B" or Containment Any Phase "A" or Phase "B" (cont.) Ventilation Isolation valve(s) not closed when required or Containment Ventilation following confirmed LOCA Isolation valve(s) not closed OR when required following confirmed LOCA Inability to isolate any primary system discharging OR outside containment AND Inability to isolate any primary system discharging outside Radiological release to the environment exists as a result containment AND AND Any indicators of fuel clad damage, Table 4.2 Radiological release to the environment exists as a result 4.2 4.2.2 {>2001F} 4.2.1 {>2000 F)
SG Tube Rupture Unisolable faulted (outside VC) ruptured steam generator Unisolable faulted (outside VC) w/Secondary AND ruptured steam generator Release Any indicators of fuel clad damage, Table 4.2 4.3 4.3.1 {>200'F}
Combustible Gas >4% Hydrogen concentration in containment Concentrations
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EMERGENCY PLAN NON-QUALITY RELATED PROCEDURE IP-EP-120 Revision 0 nt
-c=E:: OEIMPLEMENTING ner~g.POEUE REFERENCE USE Page 14 of 29 Attachment 1 - Emergency Action Levels CATEGORY 4.0 CONTAINMENT Table 4.1 Fuel Clad Loss Indicators
- Coolant activity> 300 g+/-Ci/cc of -131 equivalent
- Containment radiation monitor R-25/R-26 reading > 17 R/hr
- RED path in F-0.2, CORE COOLING Table 4.2 Fuel Clad Damage Indicators
- ORANGE or RED path in F-0.2, CORE COOLING
- RED path in F-0.3, HEAT SINK AND Heat sink is required
- Coolant activity> 300 gClicc of 1-131 equivalent
- Containment radiation monitor R-25/R-26 reading > 17 R/hr Table 4.3 Minimum Containment Cooling Safeguards Equipment Fan Cooler Units Operating Spray Pumps Required
<3 2 3 1 5 0
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ENN IPEC NON-QUALrryRELATEDPROCEDURE IP-EP-120 Revision 0 EMERGENCY PLANNO-U LT REA DP OCD E IMPLEMENTING Lntergy. PROCEDURES REFERENCE USE Page 15 of 29 Attachment 1 - Emergency Action Levels CATEGORY 5.0 RADIOACTIVITY RELEASE Category General Site Area Alert Unusual Event 5.1 5.1.4 {All} 5.1.3 {All} 5.1.2 {All} 5.1.1 {All}
Effluent Monitors A valid reading on any A valid reading on any A valid reading on any monitors Table A valid reading on any monitors monitors Table 5.1 column monitors Table 5.1 column 5.1 column "Alert for > 15 min. unless Table 5.1 column "NUE' for> 60
'GE" for > 15 min. unless "SAE" for> 15 min. unless dose assessment can confirm mi. unless sample analysis can dose assessment can dose assessment can confirm releases are below Table 5.2 column confirm release rates confirm releases are below releases are below Table 5.2 "Alert" within this time period. < Table 5.1 column 'NUE" within Table 5.2 column "GE" column SAE" within this time this time period.
within this time period. period.
5.2 5.2.5 {AII} 5.2.4 {All} 5.2.2[All} 5.2.1 {All)
Dose Projections/ Dose projections or field Dose projections or field Confirmed sample analysis for Confirmed sample analysis for Environmental surveys resulting from an surveys resulting from an gaseous or liquid release rates gaseous or liquid release rates Measurements/ actual imminent release actual imminent release which >Table 5.1 column "Alert' limits for > > Table 5.1 column "NUE" limits Release Rates which indicate doses/dose indicate doses/dose rates > 15 min. for > 60 min.
rates > Table 5.2 column Table 5.2 column "SAE' at the 5.2.3 {All}
"GE" at the site boundary or site boundary or beyond.
beyond. Dose projections or field surveys resulting from an actual imminent which indicate doses/dose rates >
Table 5.2 column "Alert" at the site boundary or beyond.
________ ___ I __ ________ ______ . _______ ________ ___ i.I
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EMERGENCY PLAN NoN-QuALITY RELATED PROCEDURE IP-EP-120 Revision 0 Ak E~~MPEGENCYINGA
- ntergy PROCEDURES REFERENCE USE Page 16 of 29 Attachment 1 - Emergency Action Levels CATEGORY 5.0 RADIOACTIVITY RELEASE Category General Site Area I Alert I Unusual Event 5.3 5.3.2 {All) 5.3.1 All)
Area Radiation Sustained area radiation levels Any sustained direct ARM Levels > 15 mRem/hr in EITHER: readings > 100 x alarm or Control Room offscale high resulting from an uncontrolled process OR Central Alarm Station and Secondary Alarm Station 5.3.3 {All)
Sustained abnormal area radiation levels > 8 R/hr within any areas, Table 5.3 AND Access is required for safe operation or shutdown
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EMERGENCY PLAN NON-QUALITY RELATED PROCEDURE IP-EP-120 Revision 0
-- IMPLEMENTING
' lntergy. PROCEDURES REFERENCE USE Page 17 of 29 Attachment 1 - Emergency Action Levels CATEGORY 5.0 RADIOACTIVITY RELEASE Table 5.1 Effluent Monitor Classification Thresholds Monitor GE SAE Alert UE R-27 44 pCi/cc 4.4 pCi/cc 4.4E-1 Ci/cc 4.4E-3 uCi/cc (1200 Ci/sec) (120 CVsec) (12 Ci/sec) (1.2E-1 CVsec)
R-44 44 pCi/cc 4.4 pCi/cc 4.4E-1 ,Ci/cc 4.4E-3 pCi/cc R-54 N/A N/A 2.5E-1 pCi/cc 2.5E-3 pCi/cc R-49 N/A N/A 2.7E-2 pCi/cc 2.7E-4 pCi/cc R-27 44 pC/cc 4.4 pCi/cc 4.4E-1 pCi/cc 4.4E-3 pCi/cc (1200 Ci/sec) (120 CVsec) (12 Ci/sec) (1.2E-1 CVsec)
R-1 4 N/A N/A N/A 4.4E-3 gCVcc R-1 9 N/A N/A 475 gCVcc 9.50 gCi/cc Table 5.2 Dose Projection/Env. Measurement Classification Thresholds GE SAE Alert TEDE 1000 mRem 100 mRem 10 mRem CDE Thyroid 5000 mRem 500 mRem N/A External Exposure Rate 1000 mRem/hr 100 mRem/hr 10 mRem/hr Thyroid exposure rate (for 5000 mRem/hr 500 mRem/hr N/A 1 hr. of inhalation)
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ENN IPEC NONQUALiTyRELATEDPROCEDURE IP-EP-120 Revision 0 EMERGENCY PLAN ZEntergy PROCEDURES REFERENCE USE Page 18 of 29 Attachment 1 - Emergency Action Levels CATEGORY 5.0 RADIOACTIVITY RELEASE Table 5.3 Plant Areas UNIT 2 UNIT 3
- Condensate Storage Tank
- Auxiliary Feedpump Building
- P.A.B.
- Service Water Intake Structure
- Fuel Storage Building
- Service Water Valve Pit East
- Control Building
- Fuel Storage Building
- Service Water Pumps
- Primary Auxiliary Building/Fan House
- Refueling Water Tank
- 480 Volt Switchgear Room (Control . Diesel Fuel Tank Building)
- Vital Area Access to Containment
- Cable Spreading Room/Electrical Tunnel . Appendix R Diesel Generator
- Diesel Generator Building/Fuel Tank Area . Backup Service Water
- Auxiliary Feedwater Pump Building
- Battery Room (Control Building 33 0" ele.)
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ENN PECNON-QUALITY RELATED PROCEDURE IP-EP-120 Revision 0
- ~IMPLEMENTING EfEntergy PROCEDURES REFERENCE USE Page 19 of 29 Attachment 1 - Emergency Action Levels CATEGORY 6.0 ELECTRICAL FAILURES Category General Site Area Alert Unusual Event 6.1 6.1.5 {>2001F} 6.1.4 {>200 0F} 6.1.2 {<20 0 0F, Defuel} 6.1.1 {All}
Loss of AC Power Loss of all 480 volt Loss of AC power to all 480 Loss of AC power to all 480 volt busses Unplanned loss of offsite power Sources safeguards bus (5A, volt safeguard busses (5A, (5A, 2A3A, 6A) for > 15 min. capability to all 480V safeguard 2A/3A, 6A) AC power 2A/3A, 6A) for > 15 min. 6.1.3 {Hot} busses (5A, 2A/3A, 6A) for> 15 AND EITHER: AND AC power capability to 480 volt Power restoration to Inability to power required safeguard busses (5A, 2A/3A, 6A) required core cooling core cooling systems with reduced to only one Table 6.1 source for systems is not likely in alternate power sources for > 15 min.
4 hrs. > 15 min.
OR Actual or imminent entry into ORANGE or RED path on F-0.2, "CORE COOLING" 6.2 6.2.2 {> 2001F} 6.2.1 {2000 F)
Loss of DC Power Loss of bus voltage (< 105 [Unit 2] Unplanned loss of bus Sources vdc) for > 15 min. on all of voltage (< 105 vdc) for > 15 the DC Busses. min. on any DC Bus resulting in the loss of decay heat removal capability
[Unit 3] Unplanned loss of bus voltage (< 105 vdc) for > 15 min. on all of the DC Busses
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EMERGENCY PLAN NON-QUALITY RELATED PROCEDURE IP-EP-120 Revision 0
.- IMPLEMENTING
'tntergy r
PROCEDURES REFERENCE USE Page 20 of 29 Attachment 1 - Emergency Action Levels CATEGORY 6.0 ELECTRICAL FAILURES Table 6.1 Safeguard Bus AC Power Sources UNIT 2 UNIT 3
. 480 V EDG 21
- 480V EDG 31
- 480V EDG 22
- 480VEDG 32
- 480 V EDG 23
- 480V EDG 33
. Unit Auxiliary transfomer*
- Unit Auxiliary transformer
- Station Auxiliary transformer*
- Station Auxiliary transformer
- 13.8 KV gas turbine auto transformer*
- 13W92 feeder
- With 86P or 868U tripped, all offsite power
- 13W93 feeder supplies must be considered as one power
- Appendix R Diesel supply.
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-Entergy PROCEDURES REFERENCE USE Page 21 of 29 Attachment 1 - Emergency Action Levels CATEGORY 7.0 EQUIPMENT FAILURES Category General Site Area Alert Unusual Event 7.1 7.1.1 {>2000°F)
Technical Plant is not brought to required Specifications/ operating mode within Technical Requirements Specifications LCO Action Statement Time.
7.2 7.2.5 {All} 7.2.2 {>2000 F} 7.2.1 {>200'F}
System Failures Control Room evacuation Turbine failure generated missiles which Report of main turbine failure requiring or Control Room AND causes or potentially causes any required turbine trip resulting in:
Evacuation Plant control cannot be safety related system or structure to become Damage to turbine generator seals established per [Unit 2] AOl nprbe causing a release of lubricating oil 27.1.9 [Unit 3] ONOP-FP- 7.2.3 {All) or hydrogen 1A in [Unit 2] 5 15 min. Entry into [Unit 2] AOl 27.1.9 [Unit 3] ONOP- OR
[Unit 3]
- 30 min. FP-1A Turbine casing penetration 7.2.4 {200-F)
Reactor coolant temperature cannot be maintained
- 2000°F
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ENN IPEC NON-QUALITY RELATED PROCEDURE IP-EP-120 Revision 0
_===r~nt IMPLEMENTING
-iiEntergy PROCEDURES REFERENCE USE Page 22 of 29 Attachment 1 - Emergency Action Levels CATEGORY 7.0 EQUIPMENT FAILURES Category General Site Area Alert Unusual Event 7.3 7.3.4 {>2001F} 7.3.3 {>20017F 7.3.1 {>200 0F}
Loss of Loss of most (approx. 75%) Unplanned loss of most (approx. 75%) safety Unplanned loss of most (approx. 75%)
Indications/ safety system annunciators system annunciators or indications on Control safety system annunciators or Alarms/ or indications on Control Room Panels for > 15 min. indications on Control Room Panels for Communication Room Panels AND > 15 min.
Capability AND Increased surveillance is required for safe AND Loss of ability to monitor plant operation Increased surveillance is required for critical safety function status AND EITHER: safe plant operation AND A significant plant transient in progress A significant plant transient OR 7.3.2 {All}
in progress [Unit 2] PICS [Unit 3] CFMS and QSPDS Loss of all communications capability are unavailable affecting the ability to EITHER:
Perform routine operations OR Notify offsite agencies or personnel
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EMERGENCY PLAN NON-QUALITY RELATED PROCEDURE IP-EP-120 Revision E=Z=V IMPLEMENTING
-v-ntergy PROCEDURES REFERENCE USE Page 23 of 29 Attachment 1 - Emergency Action Levels CATEGORY 8.0 HAZARDS Category General Site Area Alert Unusual Event 8.1 8.1.4 {All} 8.1.3 {All) 8.1.2 {All) 8.1.1 {All}
Security Threats Security Event Intrusion into a Intrusion into plant Protected Area by an Bomb device or other indication of which results in: plant security vital adversary attempted sabotage discovered within Loss of plant area by an OR plant Protected Area contol romthe adversary OR Control Romthe Any security event which represents an actual Notification of any credible site specific Control Room OR substantial degradation of the level of safety of security threat by the Security Shift AND Any security the plant. Supervisor or outside agency (NRC, Loss of remote event which military or law enforcement) shutdown represents actual capability or likely failures of plant systems needed to protect the public.
8.2 8.2.3 {All) 8.2.1 {All)
Fire or Explosion Fire or explosion in any plant area, Table 8.1, Confirmed fire in or contiguous to any which causes or potentially causes any plant area, Table 8.1 not extinguished in required safety related system or structure to < 15 min. of Control Room notification.
become inoperable 8.2.2 {All}
Report by plant personnel of an explosion within Protected Area boundary resulting in visible damage to non-vital permanent structures or equipment.
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EMERGENCY PLAN NON-QUALITY RELATED PROCEDURE IP-EP-120 Revision 0 Aft rIMPLEMENTING Lntergy PROCEDURES REFERENCE USE Page 24 of 29 Attachment 1 - Emergency Action Levels CATEGORY 8.0 HAZARDS Category General Site Area Alert Unusual Event 8.3 8.3.3 (All) 8.3.1 {AII}
Man-Made Events Vehicle crash or projectile impact which causes Vehicle crash into or projectile which or potentially causes any required safety impacts plant safety related structures or related system or structure to become systems within Protected Area boundary inoperable, Table 8.1 8.3.2 (All) 8.3.4 {All) Report or detection of toxic or flammable Report or detection of toxic or flammable gases gases that could enter or have entered within a plant area, Table 8.1, in concentrations within the Protected Area boundary in that will be life threatening to plant personnel or amounts that could affect the health of preclude access to equipment (even when plant personnel or safe plant operation using personal protective equipment) needed OR for safe plant operation Report by local, county or state officials, for potential evacuation of site personnel based on offsite event
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ENN IPEC EMERGENCY PLAN NON-QUALITY RELATED PROCEDURE IP-EP-120 Revision 0 IMPLEMENTING i ntergy. PROCEDURES REFERENCE USE Page 25 of 29 Attachment 1 - Emergency Action Levels CATEGORY 8.0 HAZARDS Category General Site Area Alert Unusual Event 8.4 8.4.4 (All) 8.4.1 {All)
Natural Events Earthquake felt inplant based upon a Earthquake felt in plant based upon a consensus of Control Room Operators on duty consensus of Control Room Operators on AND duty Kinemetrics Strong Motion Accelographs in the AND EITHER Unit 3 VC produce an alarm in the Control Kinemetrics Strong Motion Room Accelographs in the Unit 3 VC AND produce an alarm in the Control Room Amber and red Peak Shock Annunciators OR indicate seismic activity At least one amber Peak Shock Annunciator is lit 8.4.5 {All)
Sustained winds > 90 mph onsite 8.4.2 (All)
Tornadostrikes a plant vital area, Table 8.1 Tornado by plant Reportplant personnel of tornado within Protected Area boundary 8.4.6 (All)
Assessment by the Control Room personnel 8.4.3 (All) that a natural event has occurred which causes River level 2 14.5' (0 MSL) or potentially causes any required safety OR system or structure to become inoperable, Service water bay (intake structure) level Table 8.1 <-4.5' (0 MSL) 8.4.7 {All)
River level > 15' (0 MSL)
OR Low service water bay (intake structure) level resulting in a loss of service water flow
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ENN IPEC NON-QUALiTY RELATED PROCEDURE IP-EP-120 Revision 0 A& ~~EMERGENCY PLANNo-ULYREADPOCUE
-- IMPLEMENTING
'ntergy PROCEDURES REFERENCE USE Page 26 of 29 Attachment 1 - Emergency Action Levels CATEGORY 8.0 HAZARDS Table 8.1 Plant Areas Unit 2 Unit 3
- Condensate Storage Tank
- Auxiliary Feedpump Building
- P.A.B.
- Service Water Pump Structure . CAS/SAS
- Service Water Valve Pit East . Fuel Storage Building
- Fuel Storage Building a Control Building
- Primary Auxiliary Building/Fan House
- Control Room a Vapor Containment Building
- Service Water Pumps
- 480 Volt Switchgear Room (Control
- Refueling Water Tank Bldg.)
- EDG Rooms
- Cable Spreading Room/Electrical Tunnel . Diesel Fuel Tanks
- Central Control Room . Vital Area Access to Containment
- Diesel Generator Building/Fuel Tank a Appendix R Diesel Generator Area
- Backup Service Water
- Auxiliary Feedwater Pump Building
- Battery Room (Control Bldg. 33'0" ele.)
- Central Alarm Station
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ENN IPEC I-P10 Rvso EMERGENCY PLAN NON-QUALITY RELATED PROCEDURE IP-EP-120 Revision IMPLEMENTING
--- Entergy. PROCEDURES REFERENCE USE Page 27 of 29 Attachment 2 - Emergency Action Levels CATEGORY 9.0 Category General Site Area Alert Unusual Event 9.1 9.1.7 (All) 9.1.5 (All) 9.1.3 (All) 9.1.1 {All}
Other As determined by the Shift As determined by the Shift Manager or Any event, as Any event, as Manager or Emergency Director, Emergency Director, events are in determined by the Shift determined by the Shift events are in progress which progress which indicate actual or likely Manager or Emergency Manager or Emergency indicate actual, or imminent core failures of plant systems needed to Director, that could Director, that could lead damage and the potential for a protect the public. Any releases are not cause or has caused to or has led to a large release of radioactive expected to result in exposures which actual substantial potential degradation of material in excess of EPA PAGs exceed EPA PAGs. degradation of the level the level of safety of the outside the site boundary. of safety of the plant. plant.
9.1.6 {>200 0F) 9.1.8 {>200 0 F) 9.1.4 f>200 0 F) 9.1.2 f>2000 FJ Any event, as determined by the Shift Any event, as determined by the Manager or Emergency Director, that could Any event, as Any event, as Shift Manager or Emergency lead or has led to EITHER: determined by the Shift determined by the Shift Director, that could lead or has led Manager or Emergency Manager or Emergency to a loss of any two fission product Loss or potential loss of both fuel clad Director, that could lead Director, that could lead barriers and loss or potential loss and RCS barrier, Attachment A. or has led to a loss or to or has led to a loss or of the third, Attachment 2. OR potential loss of either potential loss of Loss or potential loss of either fuel clad fuel clad or RCS barrier, containment, or RCS barrier in conjunction with a loss Attachment 2. Attachment 2.
of containment, Attachment 2.
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ENN IPEC EMERGENCY PLAN fI NON-QUALITY RELATED PROCEDURE i-P10 IP-EP-120 Rvso Revision 0 L=Entergy. PROCEDURES REFERENCE USE Page 28 of 29 Attachment 2 - Fission Product Barrier Thresholds FUEL CLADDING BARRIER Potential Loss Loss
- ORANGE path in F-0.2, CORE COOLING
- RED path in F-0.2, CORE COOLING
- RED path in F-0.3, HEAT SINK AND Heat sink is required
- Coolant activity> 300 pCilcc 1-131 equivalent
- Core Exit Thermocouple Readings [Unit 2] > 7000 F
- Core Exit Thermocouple Readings > 1200 OF
[Unit 3] > 715 F
- RVLIS [Unit 2]
- 41% [Unit 3]
- 33% w/ no RCPs running
- Containment radiation monitor R-25 or R-26 > 17 R/hr
- Emergency Director Judgment
- Emergency Director Judgment RCS BARRIER Potential Loss Loss
- RED path on F-0.4, INTEGRITY
- RED path on F-0.3, HEAT SINK AND Feed & Bleed is required
- Unisolable faulted (outside VC) ruptured steam generator
- Primary system leakage exceeding capacity (> 75 gpm) of a * [Unit 2] R-41 or R-42 offscale due to RCS leakage single charging pump [Unit 3] R-1 1 or R-12 > 0.06 pCi/cc due to RCS leakage
- Emergency Director Judgment
- Emergency Director Judgment
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EMERGENCY PLAN NON-QUALITY RELATED PROCEDURE IP-EP-120 Revision 0 M E ePR D ERF C g9fIMPLEMENTING
==Entergy POEUE REFERENCE USE Page 29 of 29 Attachment 2 - Fission Product Barrier Thresholds CONTAINMENT BARRIER Potential Loss Loss
- RED path F-0.5, CONTAINMENT II. Rapid uncontrolled decrease in containment pressure following initial increase due to RCS failure
- EITHER:
Core exit thermocouples >12000 F
- EITHER:
Any Phase A" or Phase "B" or containment ventilation Isolation valve(s)
OR not closed when required following confirmed LOCA Core exit thermocouples [Unit 2] >700 F [Unit 3] > 715 F OR with RVLIS [Unit 2] <41% [Unit 3] <33% w/ no RCPs Inability to isolate any primary system discharging outside containment AND AND Restoration procedures not effective within 15 min. Radiological release to the environment exists as a result
- Confirmed phase 'B" isolation signal following confirmed LOCA
- Both doors open on a VC airlock for > 4 hrs.
with less than minimum containment cooling safeguards OR equipment operating Fan Cooler Units Oper. Spray Pumps Req'd Inability to close containment pressure relief or purge valves which results in a radiological release pathway to the environment for > 4 hrs.
<3 2 3 1 OR 5 0 Any Phase "A" or Phase B" or containment ventilation isolation valve(s) not
- Containment pressure 47 psig and increasing closed when required which results in a radiological release pathway to the environment
- 24 % hydrogen concentration in containment * - Unisolable release of secondary side to atmosphere from the affected steam
- Containment radiation monitor R-25 or R-26 reading generator(s) with primary to secondary leakage > Technical Specifications
>68 R/hr limit in any steam generator
- Emergency Director Judgment
- Loss of primary coolant inside containment with containment pressure or sump level response not consistent with LOCA conditions
- Emergency Director Judgment .