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Latest revision as of 06:29, 15 March 2020
| ML20027C814 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 09/10/1982 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20027C808 | List: |
| References | |
| PROC-820910-01, NUDOCS 8210270261 | |
| Download: ML20027C814 (244) | |
Text
{{#Wiki_filter:- . ~ - . - . . . . - ~ ... - - f } September 10, 1982 h _ Y > ~~
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/
G POINT BEACH NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES The following new and revised procedures are attached and should be inserted into your manual. Please destroy all revisions removed from your manual.
- 1. EPIP 1.1, " Initial Classification," Revision 3, dated 09-10-82.
- 2. EPIP 1.3, " Estimation of Source Term," Revision 3, dated 09-10-82.
- 3. EPIP 1.4, " Radiological Dose Evaluation," Revision 6, dated 09-10-82.
- 4. EPIP 1.5, " Protective Action Evaluation," Revision 4, dated 09-10-82.
- 5. EPIP 1.7, " Evaluation of Core Damaga," Revision 1, dated 09-10-82.
- 6. EPIP 1.8, " Emergency Off-Site Dose Estinations," Revision 2, dated 09-10-82.
- 7. EPIP 2.1, " Unusual Event - Immediate Actions," Revision 1, dated 09-10-82.
- 8. EPIP 2.3, " Unusual Event - Off-Site Agency Notification," Pevision 2, dated 09-10-82.
- 9. EPIP 3.1, " Alert - Immediate Actions," Revision 2, dated 09-10-82.
- 10. EPIP 3. 3, " Alert - Off-Site Agency Notification ," Revision 1, dated 09-10-82.
- 11. EPIP 4.1, " Site Emergency - Immediate Actions," Revision 2, dated 09-10-82.
- 12. EPIP 4. 3, " Site Emergency - Off-Site Agency Notification," Revision 1, dated 09-10-82.
- 13. EPIP 5.1, " General Emergency - Immediate Actions," Revision 2, dated 09-10-82.
- 14. EPIP 5. 3, " General Emergency - Off-Site Agency Notification,"
Revision 1, dated 09-10-82.
- 15. EPIP 6.5, " Technical Support Center & operations Support Center Activation," Revision 0, dated 09-10-82.
- 16. EPIP 7. 3.2, " Post-Accident Sampling & Analysis of Potentially High Level Reactor Coolant," Revision 4, dated 09-10-82.
q-emR 8210270261 821008 PDR ADOCK 05000266 PDR p
I Wisconsin Electnc m coune. 231 W. MICHIGAN, P.O. BOX 2046, MILWAUKEE, WI 53201 September 10, 1982 - - Mr. H. R. Denton, Director Office of Nuclear Reactor Regulation U. S. NUCLEAR REGULATORY COMMISSION Washington, D. C. 20555 Attention: Mr. R. A. '* lark, Chief Operating Reactor, Branch 3 Gentlemen: DOCKET NOS. 50-266 AND 50-301 EMERGENCY PLAN IMPLEMENTING PROCEDURES - POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 Enclosed are ten copies of the following revisions to the Point Beach Nuclear Plant Emergency Plan Implementing Procedures: PROCEDURES
- 1. EPIP 1.1, " Initial Classification", Revision 3, dated 09-10-82.
- 2. EPIP 1.3, " Estimation of Source Term", Revision 3, dated 09-10-82.
- 3. EPIP 1.4, " Radiological Dose Evaluation", Revision 6, dated 09-10-82.
- 4. EPIP 1.5, " Protective Action Evaluation", Revision 4, dated 09-10-82.
- 5. EPIP 1.7, " Evaluation of Core Damage", Revision 1, dated 09-10-82.
- 6. EPIP 1.8, " Emergency Off-Site Dose Estimations",
Revision 2, dated 09-10-82.
- 7. EPIP 2.1, " Unusual Event - Immediate Actions", Revision ~ 1, dated 09-10-82.
Mr. H. R. Denton September 10, 1982
- 8. EPIP 2.3, " Unusual Event - Off-Site Agency Notification",
Revision 2, dated 09-10-82. , ,
- 9. EPIP 3.1, " Alert - Immediate Actions", Revision 2, dated 09-10-82.
- 10. EPIP 3.3, " Alert - Off-Site Agency Notification",
Revision 1, dated 09-10-82.
- 11. EPIP 4.1, " Site Emergency - Immediate Actions",
Revision 2, dated 09-10-82.
; 12. EPIP 4.3, " Site Emergency - Off-Site Agency Notification", ; Revision 1, dated 09-10-82.
- 13. EPIP 5.1, " General Emergency - Immediate Actions",
Revision 2, dated 09-10-82. EPIP 5.3, " General Emergency - Off-Site Agency Notification ', i 14. Revision 1, dated 09-10-82. ,
- 15. EPIP 6.5, " Technical Support Center & Operations Support Center Activation", Revision 0, dated 09-10-82.
]
- 16. EPIP 7.3.2, " Post-Accident Sampling & Analysis of Potentially High Level Reactor Coolant", Revision 4, dated 09-10-82.
- 17. EPIP 7.3.3, " Post-Accident Sampling of Containment Atmosphere", Revision 4, dated 09-10-82.
- 18. EPIP 7.4.1, " Routine Check, Maintenance, Calibration &
Inventory Schedule for Health Physics Emergency Plan Equipment", Revision 6, dated 09-10-82. . 19. EPIP 7.4.2, " Emergency Plan Equipment Routine Check, j Maintenance & Calibration Instructions", Revision 4, dated 09-10-82. i
'20. EPIP 11'.1, "On-Site First Aid Assistance", Revision 3, dated 09-10-82.
~
- 21. EPIP 11.3, " Hospital Assistance", Revision 2, d'ated i 09-10-82.
- 22. EPIP 13.1, " Crisis Ccmmunications", Revision 2, dated 09-10-82.
, 23. EPIP 15.4, " Emergency Preparedness Reviewl', Rev$sion 0, dated 09-10-82.
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Mr. H. R. Denton September 10, 1982 FORMS , ,
- 1. EPIP-04 (09-82), " Status Report on Plant Systems &
Controls for Affected Unit", (attach to EPIP 1.2).
. 2. EPIP-07 (09-82), "For X/Q Determination", (attach to EPIP 1.4).
- 3. EPIP-08 (09-82) , " Estimated Whole Body & Thyroid Projected Doses", (attach to EPIP 1.4).
- 4. EPIP-09 (09-82), " Estimated Whole Body Dose Calcu-lation Worksheet for Specific Noble Gas Releases",
(attach to EPIP 1.4).
- 5. EPIP-10 (09-82), " Estimated Ground Deposition Calcu- <
lation Worksheet for Particulate Radionuclide Releases", (attach to EPIP 1.4).
- 6. EPIP-10a (0 9-8 2) , " Estimated Population Dose",
(attach to EPIP 1.8).
- 7. EPIP-ll (09-82), " Summary of Radiological Dose Evalu-ation Calculations", (attach to EPIP 1.4) .
- 8. EPIP-12 (09-82), " Initial Incident Report Form",
(attach to EPIP's 2.3, 3.3, 4.3, 5.3).
- 9. EPIP-13 (09-82), " Status Update Form", (attach to EPIP's 2.3, 3.3, 4.3, 5.3).
- 10. EPIP-22 (09-82), " Plant & Company Emergency Call List", (place after the Call List tab) .
- 11. EPIP-23 (0 9-8 2) , "Off-Site Agency Emergency Call List", (place after the Call List tab) .
,12. EPIP-24a (0 9-8 2 ) , " Site Boundary Control Center Emergency Plan Inventory Checklist", (attach to EPIP 7.4.1). ,
- 13. EPIP-24b (09-82), "TSC, ESC, South Gate & OSC Emergency Plan Inventory Checklist", (attach to EPIP 7.4.1).
- 14. EPIP-24f (09-82), " Emergency Plan First Aid Kit Inventory Checklist", (attach to EPIP 7. 4.1) .
- 15. EPIP-24g (0 9-8 2) , " Emergency Plan Burn Kit InvNntory",
(attach to EPIP 7.4.1).
Mr. H. R. Denton September 10, 1982
- 16. EPIP-24h (09-82) , " Emergency Plan First Aid Room Inventory", (attach to EPIP 7.4.1) . , ,
- 17. EPIP-24i (09-82) , " Emergency Plan Stretcher Inventory",
(attach to EPIP 7.4.1) .
- 18. EPIP-24j (09-82), " Emergency Trauma Kit Inventory",
(attach to EPIP 7.4.1) . ,
- 19. EPIP-25c (09-82), " Quarterly Emergency Plan Checklist",
(attach to EPIP 7.4.2).
- 20. EPIP-25d (09-82), " Semiannual & Annual Emergency Plan Checklist", (attach to 7.4.2) .
- 21. EPIP-33 (09-82), " Estimation of Core Damage", (' attach to EPIP 1.7).
- 22. EPIP-34 (09-82) , '" Calculation of Xe-133 Equivalent Release Rates", (attach to EPIP 1.8).
- 23. EPIP-35 (09-82), " Dose Calculations", (attach to EPIP 1.8).
- 24. EPIP-37 (09-82), " Medical Assistance Call List", (attach to EPIP 11.1) .
MISCELLANEOUS
- 1. " Table of Contents" dated 09-10-82.
- 2. " Table of EPIP Forms" dated 09-10-82.
These revisions consist of page changes which should be filed in your copies of the Emergency Plan Implementing Procedures in accordance with the attached instructions. Please return the receipt form for these ten copies to: - Wisconsin Electric Power Company Point Beach Nuclear Plant 6610 Nuclear Road Two Rivers, Wisconsin 54241 Very truly yours, 0 ' (fil/ a Assistant Vice Pre ident C. W. Fay Enclosures Copies to NRC Resident Inspecter (1) ' Incident Response Center, Region III (3)
') ') .
September 10, 1982
. /Mufb - Naohu%x v JoGdb/
d POINT BEACH NUCLEAR PLANT . . EMERGENCY PLAN IMPLEMENTING PROCEDURES The following new and revised procedures are attached and should be inserted into your manual. Please destroy all revisions removed from your manual.
- 1. EPIP 1.1, " Initial Classification," Revision 3, dated 09-10-82.
- 2. EPIP 1.3, " Estimation of Source Term," Revision 3, dated 09-10-82.
- 3. EPIP 1.4, " Radiological Dose Evaluation," Revision 6, dated 09-10-82.
- 4. EPIP 1.5, " Protective Action Evaluation," Revision 4, dated 09-10-82.
- 5. EPIP 1.7, " Evaluation of Core Damage," Revision 1, dated 09-10-82. ,
- 6. EPIP 1.8, " Emergency Off-Site Dose Estimations," Revision 2, dated 09-10-82.
- 7. EPIP 2.1, " Unusual Event - Immediate Actions," Revision 1, dated 09-10-82.
- 8. EPIP 2.3, " Unusual Event - Off-Site Agency Notification," Revision 2, dated 09-10-82.
- 9. EPIP 3.1, " Alert - Immediate Actions," Revision 2, dated'09-10-82.
- 10. EPIP 3. 3, " Alert - Of f-Site Agency Notification," Revision 1, dated 09-10-82.
- 11. EPIP 4.1, " Site Emergency - Immediate Actions," Revision 2, dated 09-10-82.
- 12. EPIP 4.3, " Site Emergency - Off-Site Agency Notification," Revision 1, dated 09-10-82.
- 13. EPIP 5.1, " General Emergency - Immediate' Actions ," Revision 2, dated 09-10-82. .
- 14. EPIP 5.3, " General Emergency - Off-Site Agency Notification,"
Revision 1, dated 09-10-82.
- 15. EPIP 6.5, " Technical Support Center & Operations Support Center Activation," Revision 0, dated 09-10-82.
- 16. EPIP 7.3.2, " Post-Accident Sampling & Analysis of Potentially High Level Reactor Coolant," Revision 4, dated 09-10-82.
1 9 Emergency Plan Implementing Procedures - 2 17. EPIP '. 3.3, " Post-Accident Sampling of Containment Atmosphere ," Rev A a. a 4, dated 09-10-82. - . 18. EPIP 7.4.1, " Routine Check, Maintenance , Calibration & Inventory 6, Schedule for Health Physics Emergency Plan Equipment," Revision dated 09-10-82. 19 EPIP 7.4.2, " Emergency Plan Equipment Routine Check, Maintenance
& Calibration Instructions," Revision 4, dated 09-10-82.
20. EPIP 11.1, "On-Site First Aid Assistance," Revision 3, dated 09-10-82. 21. EPIP 11.3, " Hospital Assistance," Revision 2, dated 09-10-82.
- 2 22.
EPIP 13.1, " Crisis Communications," Revision 2, dated 09-10-8 . 23. EPIP 15.4, "Dmergency Preparedness Review." Revision 0, dated 09-10-82. - The following new and revised forms are attached for insertion Please attach the form to the indicated procedure into your manual. and destroy all revisions removed from your manual. EPIP-04 (09-82) ,
" Status Report on Plant Systems & Controls for 1.
Affected Unit," (attach to EPIP 1.2).
- 2. EPIP-07 (09-82) , "For X/Q Determination," (attach to EPIP 1.4) .
" Estimated Whole Body & Thyroid Projected Doses,"
- 3. EPIP-08 (09-82) ,
(attach to EPIP 1.4) . EPIP-09 (09-82) , "Esticated Whole Body Dose Calculation Worksheet for Specific Noble Gas Releases," (attach to EPIP 1.4). 4.
" Estimated Ground Deposition Calculation Worksheet
- 5. EPIP-10 (09-82) ,
for Particulate Radionuclide Releases," (attach to EPIP 1.4) . (09-82)., " Estimated Population Dose ," (attach to EPIP 1.8).
- 6. EPIP-10a
- 7. EPIP-ll (09-82 ) , " Summary of Radiological Dose Evaluation Calcula-tions," (attach to EPIP 1.4). .
(attach to
- 8. EPIP-12 (09-82) , " Initial Incident Report Form,"
EPIP's 2. 3, 3. 3, 4. 3 and 5. 3) . 9. EPIP-13 (09-82) , " Status Update Form," (attach to EPIP's 2. 3, 3.3,
- 4. 3 and 5. 3) . '
'[
(place
- 10. EPIP-22 (09-82 )', " Plant & Company Emergency Call List,"
after the call list tab). .
Emirgsney Plan Implementing Procedures - 3 ,
- 11. EPIP-i3 (09-82) , "Offsite igency Emergency Call List," (place after the call list tab).
- 12. EPIP-24a (09-82) , " Site Boundary Control Center Emergency Plan Inventory Checklist," (attach to EPIP 7.4.1) .
- 13. EPIP-24b (09-82) , "TSC, ESC, South Gate & OSC Emergency Plan Inventory Checklist," (attach to EPIP 7.4.1) .
- 14. EPIP-24f (09-82) , " Emergency Plan First Aid Kit Inventory Checklist,"
(attach to EPIP 7.4.1) .
- 15. EPIP-24g (09-82) , " Emergency Plan Burn Kit Inventory," (attach to EPIP 7.4.1).
- 16. EPIP-24h (09-82) , " Emergency Plan First Aid Room Inventory," (attach to EPIP 7.4.1).
- 17. EPIP-241 (09-82) , " Emergency Plan Stretcher Inventory," (attach
~
to EPIP 7.4.1).
- 18. EPIP-24j (09-82) , " Emergency Trauma Kit Inventory," (attach to EPIP 7.4.1).
- 19. EPIP,25c (09-82) , " Quarterly Emergency Plan Checklist," (attach to EPIP 7.4.2).
- 20. EPIP-25d (09-82) , " Semi-Annual & Annual Emergency Plan Checklist,"
(attach to EPIP 7.4.2) .
- 21. EPIP-33 (09-82) , " Estimation of Core Damage," (attach to EPIP 1.7) .
- 22. EPIP-34 (09-82) , " Calculation of Xe-133 Equivalent Release Rates,"
(attach to EPIP 1.8).
- 23. EPIP-35 (09-82) , " Dose Calculations," (attach to EPIP 1.8) .
- 24. EPIP-37 (09-82) , " Medical Assistance Call List," (attach to EPIP 11.1). ,
EPIP-14 and EPIP-15 have been deleted. Please destroy copies removed from EPIP 4.3 and EPIP 5.3. " Also attached is a revised listing of the Table of Contents to be inserted into your manual. Please destroy the old revision. Also attached is a revised Table of EPIP Forms. Please insert this table into your manual. Please destroy the old revision. Please fill out the attached receipt form and return it to Ms. F. A. Zeman at the Point Beach fluclear Plant. d'~ J. E. Yaorr _i
, Septtmbar 10, 1982 0
POINT BEACH NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES , 09-10-82 o ! I hereby acknowledge receipt of EPIP 1.1, EPIP 1.3, EPIP 1.4, EPIP 1.5, EPIP 1.7, EPIP 1.8, EPIP 2.1, EPIP 2.3, EPIP 3.1, EPIP,3.3, EPIP 4.1, EPIP 4.3, EPIP 5.1, EPIP 5.3, EPIP 6.5, EPIP 7.3.2, EPIP 7.3.3, EPIP 7.4.1, EPIP 7.4.2, EPIP 11.1, EPIP 11.3, EPIP 13.1 and EPIP 15.4 and have inserted them into my manual. , Date 4 1
- l
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09-10-82
-A k
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) TABLE OF CONTENTS Revision Date 1.0 CLASSIFICATION & ASSESSMENT 1.1 Initial Classification . . . . . . . . . . . 3 09-10-82 1.2 Plant Status . .. . . . . . . . . . . . . . 0 03-31-81 1.3 Estimation of Source Term . . . . . . . . . . 3 09-10-82 1.4 Radiological Dose Evaluation . . . . . . . . 6 09-10-82 1.5 Protective Action Evaluation . . . . . . . . 4 09-10-82 1.6 Radioiodine Blocking & Thyroid Exposure Accounting . . . . . . . . . . . . . . . . 1 02-26-82 1.7 Evaluation of Core Damage . . . . . . . . . . 1 09-10-82
, 1.8 Emergency Off-Site Dose Estimations . . . . . 2 09-10-82 2.0 UNUSUAL EVENT IMPLEMENTING PROCEDURES I 2.1 Unusual Event - Immediate Actions . . . . . . 1 09-10-82 > 2.2 Unusual Event - Plant and Company Personnel Notification . . . . . . . . . . . . . . . 1 07-01-81 2.3 Unusual Event - Off-Site Agency Notification 2 09-10-82 3.0 ALERT IMPLEMENTING PROCEDURES 3.1 Alert - Immediate Actions . . . . . . . . . . 2 09-10-82 3.2 Alert - Plant & Company Personnel Nccification . . . . . . . . . . . . . . . 1 07-01-81 3.3 Alert - Off-Site Agency Notification . . . . 1 09-10-82 4.0 SITE EMERGENCY - IMPLEMENTING PROCEDURES 4.1 Site Emergency - Immediate Actions . . . . . 2 09-10-82 4.2 Site Emergency - Plant & Company Personnel i Notification . . . . . . . . . . . . . . 1 07-01-C1 4.3 Site Emergency - Off-Site Agency Notification 1 09-10-82 l 5.0 GENERAL EMERGENCY - IMPLEMENTING PROCEDURES i 5.1 General Emergency - Immediate Actions . . . . 2 09-10-82 5.2 General Emergency - Plant & Company Personnel Notification . . . . . . . . . . 1 07-01-81 5.3 General Emergency - Off-Site Agency Notification . . . . . . . . . . . . . . . 1 09-10-82 ) i
- 6.0 EVACUATION 6.1 Limited Plant Evacuation . . . . . . . . . 1 04-30-82 6.2 Plant Evacuation . . . . . . . . . . . . . . 1 02-26-82 O( ,,/ 6.3 Exclusion Area Evacuation .. . . . . . . . . 0 03-31-81 6.4 Energy Information Center Evacuation . . . . 0 03-31-81 09-10-82
! 6.5 TSC & OSC Activation . . . . . . . . . . . 0 4
- - - . ~ _ , . . , - - - . ~ - - . . ~ - - - - . - - - . _ , . , - - - , - - - _ - , - . . - - - - - . - - - - - - - - - - - - . --
Page 2 Revision Date (\, h
/ < - 7.0 CHEMISTRY & HEALTH PHYSICS RESPONSE & PREPAREDNESS 7.1 Internal Chem & HP Group Personnel Notificatio../
Initial Response 7.1.1 Chem & HP Group Personnel Notification
& Initial Response when Chem & HP Personnel are On-Site . . . . . . . 2 04-30-82
, 7.1.2 Chem & HP Group Personnel Notification
& Initial Response when Chem & HP Personnel are Off-Site . . . . . . . 1 03-17-82 7.1.3 HP Protective Actions by Operations Personnel Prior to Arrival of Chem
& HP Group Personnel . . . . . . . . 1 05-15-81 i 1
7.2 Health Physics Facility Activation 7.2.1 Activation of HP Facilities at Site Boundary Control Center . . . . . 2 03-17-82 7.2.2 Activation of HP Facilities at . Operations Support Center . . . . 1 03-17-82 4 7.2.3 DELETED ~ 7.2.4 Health Physics Communications . . . 1 03-17-82 4
) 7.2.5 Control & Use of vehicles . . . . . 1 03-17-82 7.3 Radiological Surveys 7.3.1 Airborne Sampling & Direct Dose Rate Survey Guidelines . . . . . . 3 03-17-82 7.3.2 Post-Accident Sampling & Analysis of Potentially High Level Reactor Coolant . . . . . . . . . . . . . 4 09-10-82 7.3.3 Post-Accident Sampling of Contain-ment Atmosphere . . . . . . . . 4 09-10-82 7.3.4 Movement of Required Chemistry Equip-
, ment & Material to the Technical Support Center Counting Room & Mini-Laboratory . . . . . . . . . 0 12-30-81 7.4 Emergency Equipment 7.4.1 Routine Check, Maintenance, Cali-bration & Inventory Schedule for Health Physics Emergency Plan Equipment . . . . . . . . . . . . 6 09-10-82 7.4.2 Emergency Plan Equipment Routine Check, Maintenance & Calibration Instructions . . . . . . . . . . 4 09-10-82 7.4.3 Use of Baird Model 530 Single Channel Iodine Spectrometer to i Os Determine Airborne Iodine Activities . . . . . . . . . . . . 1 05-15-81
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Page 3 4 f) x/m Revision Date 7.4.3.1 Use of Canberra Model 3100 Series 30 Multichannel Analyzer to Determine Airborne Iodine Activities . . . . 0 02-26-82
, 7.4.4 AMS-2 Air Particulate, Iodine &
1 Noble Gas Sampler / Detector . .. . 0 03-31-81 8.1 Personnel Assembly & Accountability . . . . 2 04-30-82 9.1 Security . . . . . . . . . . . . . . . .. . 0 03-31-81 10.0 Firefighting . . . . . . . . . . . . . . . . 0 03-31-81 11.0 FIRST AID & MEDICAL CARE 11.1 On-Site First Aid Assistance . . . . . . . 3 09-10-82 11.2 Injured Person's Immediate Care . . . . . . 1 05-15-81 11.3 Hospital Assistance . . .. . . . . . . . . . 2 09-10-82 11.4 Personnel Decontamination . . . . . . . . . . 0 01-29-82 12.0 REENTRY & RECOVERY PLANNING 12.1 Reentry Procedures for Emergency Operations 1 03-17-82 12.2 Personnel Exposure & Search & Rescue Teams . . . . . . . . . . . . . . . . . . . 2 04-30-82 12.3 Recovery Planning . . . . . . . . . . . . . 0 03-31-81 12.4 Personnel Monitoring Exposure Guidelines . . 0 01-29-82 13.0 PRESS 13.1 Crisis Communications . . . . . . . . . . . . 2 09-10-82 14.0 COMMUNICATIONS 14.1 Testing of Communications Equipment . . . . . 0 03-31-81 i 15.0 TRAINING, DRILLS & EXERCISES 15.1 Employee Training . . . . . . . . . . . . . . 1 09-04-81 15.2 Off-Site Personnel Training . . . . . . . . . 0 03-31-81 15.3 Drills & Exercises . . . . . . . . . . . . 2 04-30-82
- 15.4 Emergency Preparedness Review . . . . . . . . 0 09-10-82
! 16.0 WISCONSIN ELECTRIC GENERAL OFFICE PROCEDURES 16.1 Nuclear Engineering Section_ Notification & Response . . . . . . . . . . . . . . . . . 3 09-04-81 7 i I
n n
.- 09-10-82
.] TABLE OF EPIP FORMS U
EPIP EPIP Form Title Procedure 01 Emergency Plan Airborne Radiation Survey Record Site Boundary Control Center (03-81) 7.3.1 02 Emergency Plan Survey Record Site Boundary Control Center (09-81) 7.3.1 03 Dose Factor Calculations for Specific Noble Gas Analysis Results (03-81) 7.3.1 04 Status Report on Plant Systems & Controls for Affected Unit (09-82) 1.2 05 Worksheet for Status Report on Radiation Monitoring System for Unit (03-81) 1.2 06 Worksheet for Status Report on Radiation Monitoring System for Plant (03-81) 1.2 07 For X/Q Determination (09-82) 1.4 08 Estimated Whole Body & Thyroid Projected Doses (09-82) 1.4 09 Estimated Whole Body Dose Calculation Worksheet for Specific Noble Gas Releases (09-82) 1.4 10 Estimated Ground Deposition Calculation Worksheet for Particulate Radionuclide Releases (09-82) 1.4 10a Estimated Population Dose (09-82) 1.8 11 Summary of Radiological Dose Evaluation Calculations (09-82) 1.4 (AV) 12 Incident Report Form (09-82) 2.3, 3.3, 4.3, 5.3 13 Status Update Form (09-82) 2.3, 3.3 4.3, 5.3 14 Unused 15 Unused 16 Event Data Checklist (03-81) 5.3 17 Accounting Short Form (04-82) 8.1 18 Assembly Area Roster (03-81) 8.1 19 Drill / Exercise Scenario (03-81) 15.3
- 20 Drill / Observation Sheet (03-81) 15.3 Drill / Exercise Evaluation Report (03-81) 21 15.3 22 Plant & Company Emergency Call List (09-82) Call List Ta5 23 offsite Agency Emergency Call List (09-82) Call List Tab 24a Site Boundary Control Center Emergency Plan Inventory Checklist (09-82) 7.4.1 l 24b TSC, ESC, South Gate & OSC Emergency Plan Inventory
! Checklist (09-82) 7.4.1 24c Emergency Plan Health Physics Supplies at Two Rivers Community Hospital Inventory checklist (09-81) 7.4.1 control Room Emergency Plan Equipment Inventory Checklist 24d (06-82)
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7.4.1 l 24e Emergency Vehicle Inventory Checklist (04-82) 7.4.1 24f Emergency Plan First Aid Kit Inventory Checklist (09-82) 7.4.1
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Page 2 EPIP EPIP h Forms Title Procedure Emergency Plan Burn Kit Inventory (09-82)
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24g 7.4.1 24h Emergency Flan First Aid Poom Inventory,(09-82) 7.4.1 24i Emergency Plan Stretcher Inventory (09-82) 7.4.1 24j Emergency ."-auma Kit Inventory Checklist (09-82) 7.4.1 25a Emergency Venicle Checklist (06-82) 7.4.2 25b Monthly Health Physics Instrument & Air Sampler
- Functional Test Checklist (06-82) 7.4.2 25c Quarterly Emergency Plan Checklist (09-82) 7.4.2 25d Semi-Annual & Annual Emergency Plan Checklist (09-82) 7.4.2 26 Quarterly Communications Test (03-81) 14.1 27 Monthly Communications Test (03-81; 14.1 28 Emergency Plan Instrument Calibration Schedule (06-82) 7.4.2 29 Emergency Plan Counting Equipment & Frisker Calibration Schedule (06-82) 7.4.2 30 Reactor Coolant Post-Accident Sampling Analysis Report (09-81) 7.3.2 31 Containment Atmosphere Post-Accident Sampling Analysis Report (12-81) 7.3.3 32 Search & Rescue and Emergency Operations Checklist (04-82) 12.2 33 Estimation of Core Damage (09-82) 1.7 34 Calculation of Xe-133 Equivalent Release Rates (09-82) 1.8 35 Dose Calculations (09-82) 1.8 j 36 Unused f}
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37 Medical Assistance Call List (09-82) 11.1
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EPIP 1.1 MINOR
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Revision 3 09-10-82 INITIAL CLASSIFICATION 1.0 GENERAL The purpose of this procedure is to provide a means of classifying an event or condition at the Point Beach Nuclear Plant into one of four emergency classifications as described in the Point Beach Nuclear Plant Emergency Plan. Each emergency classification requires emercency organization noti-fications, mobilizations, and actions to be performed in order to appropriately react to the situation and provide for the health and safety of plant and public personnel. They are listed in order of increasing severity. 1.1 Unusual Event An unusual plant condition which either has occurred or might occur. This condition could possibly lead to a degradation in overall safety. This condition does not represent a significant radioactivity release, ( involves no offsite_ response, and may require no augmentation of I ; plant personnel. In spite of the above, prompt notification of the
\' counties and state is required. .
1.2 Alert Plant conditions in which events are in progress or have occurred which involve an actual or potential degradation of plant safety. Radiation releases are not likely to cause an offsite hazard. Prompt offsite notification is necessary and the plant organization may have to be augmented. 1.3 Site Emergency Plant conditions in which events are in progress or have occurred which involve actual or probable major failures of plant functions. Potential radioactive releases may have an impact on offsite people. Prompt notification of offsite agencies is required. The plant organization must be augnented and the technical support center, onsite operations support center, and emergency support center will be operational. An evacuation may be necessary. 1.4 General Emergency Plant conditions in which events are in progress or have occurred which involve actual or imminent substantial core degradation and a (( ,, potential for loss of containment integrity. releases may have an impact on offsite people. Potential radioactive Prompt notification
EPIP 1.1 Page 2 m \ of offsite agencies is required. The plant organization must be augmented and the technical support center, onsite operations support center, and emergency support center will be operational. An evacu-ation may be necessary. The emergency news center will be opened. The Shift Supervisor has the responsibility and authority to take immediate action to mitigate the consequences of the emergency. He will consult with the Duty & Call Superintendent and assign the appropriate emergency classi-fication and initiate the necessary Emergency Plan implementing procedures.
2.0 REFERENCES
2.1 Nuclear Regulatory Commission NUREG-0654, Revision 1, published November, 1980. 2.2 Point Beach Nuclear Plant Emergency Plan Sections 4.1 and 5.1. 3.0 PRECAUTIONS AND LIMITATIONS 3.1 All actions and notifications should be appropriately logged.
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3.2 Emergency Plan implementing procedures are not to be used to respond to security threats. One hour notification of the NRC is required
/'"Ng (V 3.3 using the red phone for security threats.
Certain events require notification to the NRC within one hour. These items are included on Table 1-1. Those items which are noted as "NRC Only" means that there is no classification for the events and no notification other than the NRC is required. These notifications are not considered as starting the Emergency Plan. 3.4 The " Indications Used" in Table 1-1 are those which one may expect if that level of emergency occurs very quickly. For more slowly developing situations, other indications may be judged appropriate. For example, a primary system leak rate of 40 gpm is an Unusual Event. Subsequently, charging may be lost and, in addition, the leak may worsen. One may not see charging flow 50 gpm greater than letdown flow when in fact an Alert should be declared. 3.5 For classification purposes where radiological dose is the primary parameter leading to a classification, use EPIP 1.8, " Emergency Off-Site Dose Estimation" for determination of dose. 4.0 INITIAL CONDITIONS None. NOTE: APPENDIX 1 0F NUREG-0654 (PAGE 1-3) CONTAINS THIS SENTENCE: "THE TIME IS HEASURED FROM THE TIME AT WHICH OPERATORS RECOGNIZE (EMPHASIS O ADDED) THAT EVENTS HAVE OCCURRED WHICH MAKE DECLARATION OF THE EMER-GENCY CLASS APPROPRIATE.
EPIP 1.1 Page 3 n v 5.0 PROCEDURE 5.1 Call the Duty & Call Superintendent for consultation to establish the initial classification. If he is unavailable, the Shift Supervisor is responsible for classification. 5.2 Select affected categories related to plant events or conditions at this time. Check (./) all applicable categories. Refer to Page , Category in Table 1-1
- 1. Safety System Functions 1
- 2. Abnormal Primary Leak Rate 1
- 3. Abnormal Coolant Temperature /
Pressure 2 < 4. Abnormal Primary / Secondary Leak 2
- 5. Core Fuel Damage 3
- 6. Secondary Coolant Anomaly 4
- 7. Abnormal Effluent 5
- 8. Major Electrical Failures 5
- 9. Control Room Evacuaticn 6
- 10. Fire 6
- 11. Plant Shutdown Function 7
- 12. Abnormal Radiation Levels at Site Boundary 8
- 13. Fuel Handling Accident 8
- 14. Serious or Fatal Injury 9
- 15. Security Threat ,
9
- 16. Hazards to Plant Operations 9
- 17. Natural Events 10
- 18. Reactivity Transient 10 a'
EPIP 1.1 Page 4 V Refer to Page Category in Table 1-1
- 19. Load Transient 11
- 20. Other 11 5.3 Beginning at the indicated page in Table 1-1 (attached), review initiating conditions for all categories checked above.
5.4 Record most severe emergency classification at this time. 5.5 Record date/ time of initial classification (subsequent columns for reclassification at a later date and time are provided if reclassifi-cation is required). Initial SWasequent Subsequent Date/ Time Date/ Time Date/ Time NOTE: IF THE SHIFT SUPERVISOR CANNOT COMMUNICATE WITH A DUTY &
'O CALL SUPERINTENDENT, THE SHIFT SUPERVISOR MUST NOTIFY THE STATE AND TWO COUNTIES WITHIN 15 MINUTES OF THE DECLARATION OF ANY CLASS OF EMERGENCY.
5.6 If events or conditions are classified as an Unusual Event, perform EPIP 2.1, " Unusual Event - Immediate Actions." ! 5.7 If events or conditions are classified as an Alert, perform EPIP 3.1,
" Alert - Immediate Actions."
5.8 If events or conditions are classified as a Site Emergency, perform EPIP 4.1, " Site Emergency - Immediate Actions." 5.9 If events or conditions are classified as a General Emergency, perform EPIP 5.1, " General Emergency - Immediate Actions." NOTE:
"One hour" refers to the requirement to notify NRC within one hotar (10 CFR 50.72).
"One hour - Open line" refers to the requirement to notify NRC within one 3
hour and maintain an open line for continuous communication (10 CFR 50.72). O .
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Note - Duty 6 Call Superintenient , ..-
'- .*3 S - Duty Shift Supervisor .pdsfg33 FSAk - Final Safety Analysis Report MASP - Modified Amended PENP Security Plan EMERGENCY CLASSIFICATION Emergency category initiating condation Indication used Classification
- 1. Safety System Functions Unplanned initiation of emergency cose cooling A y of the tollowing first-out reactor trip Unusual Event with injection to the psimary system panel annunciation with indicator confir- 1-Hour (7) mation noted:
- 1. " Containment press ht",
lPI-945, PI-947, PI-949 (2/3 >5 psig)l
- 2. " Steam line loop A lo-lo press"
[PI-468, PI-469, PI-482 (2/3 <530 psig))
- 3. " Steam line loop B 10-10 press" lPI-478, PI-479, PI-483 (2/3 <530 psig)l
- 4. " Pressurizer lo press SI" lPI-429, PI-430, PI-431 (2/3 <!735 psig)l
- 5. Wide range pressure <l500 psig -
Loss of containment integrity requiring When shutdown commences as determined by DSS Unusual Event shutdown by Technical Specifications and DCS 1-Hour (5) Loss of engineered safety feature requiring When shutdown commences as determined by DSS Unusual Event shutdown by Technical Specifications and DCS 1-Hour (5) Loss of fire protection system function When shutdown commences as determined by DSS Unusual Event requiring shutdown by Technical Specifi- and DCS l-Hour (5) I cations (i.e., both fire pumps inoperable) and no backup fire suppression system L
- 2. Abnormal Primar y Exceeding Technical Specification primary system When shutdown commences as determined by DSS Unusual Event teak Rate leak rate (10 gpm) and DCS 1-Hour (5)
_ . _ . _ _ . . . _ . _ _ . _ _ . . _ . . . _ ._ _ _ _ . _ _ _ . _ . . - . ._ _ ._ .-m_.___ _. _ _ _ _ _ . . _ _ _ . . . _ . _ . . ._ . . _ . . . _ . . _ . _ . Cs f Table 1
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l Pay 2
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} Emergency j Category Initiating condition Indication used Classification l' Leak rate >50 (gm A] of the follow 1 reg: Alert i 1. " Volume control tant level hi-lo" lLI-141 and/or LI-ll2 (6%l 1 l 2. Decreasing pressurizer level 1 (LI-426, L1-427, LI-428l 1 1 r 3. " Charging pump speed hi" I j 4. Charging line flow (FI-128) >50 w e more than letdown flow (F1-134) l Leak rate in excess of availebte pump Q of the following: Site Emergency capacity including charging, high head SI ! and low head 51 1. " Volume control tank level hi-lo [LI-141 and/or LI-Il2 <8%]
- 2. No pressurizer level indicated
[LI-426, LI-427, LI-428]
- 3. All available pumps running as indicated by
, the red light at the switch
, 4. Increasing core exit T/C temp as indicated by P-250 and confirmed on local readout. 1 j 3. Abnormal coolant Unexpected decrease in subcooling margin Both of the following: Unusual Event l Temperature / Pressure ' 1 1. alarm on P-250, if operable f 2. Confirmation by manual calculation i Pressure >2735 psag Pressure >2735 psig on PH-420 and NRC only 4 " Code, safety s,i P0HV not closed l-hour open line (2) DNBR <!.30 i i
- 4. Abnormal Primary / Exceeding Technical hpecification primary-secondary When shutdown commences as determined by DSS Unusual Event Secondary Leak leak rate and DCS 1-Hour (5)
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- Emergency categoy Initiatisig cos.dation Indication used Classification Gross failure of I SG tube (>400 gpsis) Jn loss of All of the f ollowing first-out reactor panel Alert offsite power (FSAR 14.2.4) annunciation with confirmation indications f 1. " Pressurizer to Press SI,"
(PI-429, PI-430, PI-431 (2/3 (1735 psig))
- 2. a. " Steam generator A level hi" lLI-461, LI-462, LI-463 (2/3 >70%)] ol
- b. " Steam generator B level hi" lLI-471 LI-472. L1-473 (2/3 >70%))
l 3. a. "4.16 kv bus undervoltage" j & 0 volts on A03 & A04 voltmeters.
- b. XO4 to A03 ammeter on CO2 (0 amps) j c. KO4 to A04 ammeter on CO2 (0 amps)
- 4. S1 flow 2400 gpm indicated by FI-924 &
FI-925 and pump discharge pressure , corresponding to flow. Rapid f ailure of >10 SG tubes (4000 < pas with A 1 of the following first-out reactor panel Site Emergency or without offsite AC annunciation with confirming indication:
- 1. " Pressurizer lo press SI" j [PI-429, PI-430, PI-431 (2/3 <!735 psig)l
- 2. a. " Steam generator A level hi"
[LI-461, LI-462, L1-463 (2/3 >70%)) i or , i
- b. " Steam generator B level hi"
[LI-471, L1-472. LI-473 (2/3 >70%)]
- 3. Si flow >4,000 gpm indicated by F1-626, F1-928, F1-924 & FI-925
- 5. Core Iuel Damage Gross fuel damage in core indicated Both of the following: Unusual Event
- 1. Letdown line radiation monitor (R9)
(sample line R109) 100 m alarm setpoint.
< 2. Sustained offscale & chemical analysis shows fission product concentration increase by i 100X.
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% ,. (~- / , Tabla is~ j
- y,q, 4 Emergency Category Initiatang condition Indication used Classification Massive f uel damage 300 pct /cc iodane-equivalent as determined by Alert by chemical analysis
- 1. Massive loss of fuel clad integrity Initiating conditaons Nos. 1, 2, 4 & 5 Genet'al Emergeracy
- 2. With simultaneous loss of primary system integr ity exist and No 3 is possible: 1-Hour open line (3)
- 3. With potential loss of containment integrity
- 1. 300 pel/cc iodine-equivalent determined by chemical analysis
- 2. Primary system leak >1000 gpa indicated by SI flow >1000 gpm (FI-924 & F1-925) and ptump
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discharge pressure corresponding to flow
- 3. Minimum contairemerit pressure suppression egaipment is not available (any of the following):
- a. No fan cooler operating and <2 spray pumps.
- b. No spray pump operating and <4 fan coolers
- c. <2 fan coolers running with ! spray pump
- 4. " Containment press hi" lPI-945 PI-947. PI-949 (2/3 >5 psig)]
- 5. " Cot.tainment spray" with 2/3 + 2/3 >25 psig lPI-945, PI-947, PI-949]
[PI-946, PI-948, PI-950)
- 6. Secondary Coolant Reduction in feedwater enthalpy incident 1. a i Decreasing feedwater temp indicated by Unusual Event Anomaly (FSAR 14.1.7) 70-418A & 70-438A on P-250 and
- b. confirmed by local temperature indicator ora outlet of No. 5 feedwater heater.
- 2. Unexpected increasing power on encore nuclear
- instrumentation Steam line break witta primary to secondary leak All of the following finst-out reactor trip Alert rate in excess of 10 gpm (FSAR 14.2.5) panel annunciation with confirmation
- 1-Hour open line (3)
- 1. Either:
- a. " Steam line loop A Lo-Lo press"
[PI-468, PI-469, PI-482 (2/3 <530 psig)] or
- b. " Steam line loop B Lo-Lo press" lPI-478, PI-479, PI-483 (2/3 <530 psig))
y (' ) i
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Page- 5 J . !' Emergency Category Initiatin<j Condition Indication Used Classification
- 2. Confirmed primary-to-secondary leak rate of at least 10 g[e.
- 3. Either:
- a. " Steam line loop A 1 sol channel alert" lF1-464. F1-465 (1/2 >3.9x10s Ib/hr))
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- b. " Steam line loop B isol channel alert" lF1-474 FI-475 (1/2 >3.9x10 8 lb/hr)l Secondary Coolant Transient initiated by loss of feedwater, followed Q of the following: General Emergency :
Anomaly by loss of auxiliary feedwater for >l hour 1-Hour open line (3) (FSAR 14.1.11) 3. Decreasing SG levels -
"A" SG lL1-4bt, LI-462. L1-463]
"B" SG [L1-471, LI-472, LI-473]
- 2. No auxiliary feedwater flow -
lF1-4002, F1-4007 FI-4014] lFI-4036, F1-4037]
- 7. Abnormal Effluent Radiological effluent Technical Specification limits Airborne effluents only Unusual Event exceeded but <10 tiraes the limit (FSAR 14.2.3) 1-Hour (8)
Radiological effluent Technical Specification limits Liquid ef fluents only Unusual Event exceeded (FSAR 14.2.2) 1-Hour (8) kadiological effluents >10 times Technical Airborne effluents only Alert Specification instantaneous limits. (An instan- 1-Hour _(8) taneous rate which, if continued for >2 hours, would result in a dose of about 1 mR at the site boundary under average meteorological conditions.)
- 8. Major Electrical sustained loss of of fsite power >l5 minutes Ay of the following: Unusual Event Failures (FSAR 14.1.2)
- 1. "4.16 kv bus undervoltage"
& O volts on A03 & A04 voltmeters.
2, XO4 to A03 ammeter on CO2 (0 amps).
- 3. XO4 to A04 ammeter on C02 (0 amps)
-_ .__ . - _ _ _ _ _ _ _ . - . . . - . _ - . _ . _ _ - - . .- - - . . - - _ - , = . . - - . , - - O T Table Page 6 %
- Emergency Category Instiating Condittora Indication Used Classifscation Sustained loss at onsite AC power capability Both of the following; Unusual Event
(>l5 minutes) 1-Hour (5) 1, "4. It, kv bus unde volt age" & O volts on AuS and A06 voltmeters
- 2. " Emergency Diesel Starting System Disabled" for both Diesels Loss of all vital onsite DC power <l5 minutes Both of the following: Site Emergency
- 1. "Asuaanciator power f ailure" on 001, CO2, 003, and C04
- 2. <100 volts on the voltmeters for all batteries Loss of offsite power and loss of all onsite AC M of the following: Site Emergency power for >15 minutes
- 1. "4.16 kv bus undervoltage" 0 volts on A03,104, A05, A06 & *Emerg Diesel starting system disabled" for both Diesels
- 2. XO4 to A03 ammeter on 002 (0 amps)
- 3. XO4 to A04 ammeter on 002 (0 amps)
Loss of of fsite and all onsite AC power with loss of Q of the following: General Emergency all auxiliary feedwater for 22 hours
- 1. Unit aua W meter XO2 on CO2 (0 m )
, ,2. Station aux W meter XO4 on CO2 (0 m )
- 3. XO4 to A03 ammeter on CO2 (0 amps)
- 4. XO4 to A04 ammeter on CO2 (0 amps)
- 6. XO2 to AO! ammeter on CO2 (0 amps)
- 7. a. No auxiliary feedwater flow lF1-4036, F1-4037]
- b. Decreasang SG level -
"A* SG (LI-461, LI-462, LI-463l "B" SG lLI-471, LI-472 LI-473l
- 9. Control koom Evacuation kvacuation of control soom >15 minutes & As seysired by DSS Site Emergency no control at remote shutdowne station 1-Hour open line (3)
- 10. Eire Fire in vital area os on the controlled side of plant As repu ted by Fire Brigade Chief Unusual Event lastang >10 minutes after initial use of fire extinguishing equipment.
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Table
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~; Eme r gency Category Initiating Condition Indacation used Classification Fare affecting 1 train of safety systems. As reported by Fire Brigade Chief Alert Fire af fectang 2 trairas of safety systems As repor ted by Fire Brigade Chief Site Emergency
- 11. Plant Shutdown Function Nonf unctiossal isidicatioras or alasms in the control both of the following: Unusual Event room on primary system pas ameters requiring plant 1-Hour (5)
- 1. "Asunuaciator power f ailure" on C04.
- 2. Failed indication as determined by DSS.
Turbine mechanical f ailure with cnnsequences 1. Annunciator " Turbine supervisory." Unusual Event
- 2. Indication on TH-6019 of bearing vibration
>7' ails.
- 3. Bearing vibration alarm on back of CO3.
- 4. Visual confirmation of turbine housing penetration by a blade or disc.
Significant loss of effluent monitoring capability & !. less of LW16 (RE223) during a release Unusual Event meteorological instruments which impairs ability to or perform emergency assessment. Loss of effluent 2. Loss of R18 (RE218) during a' release monitoring may/may not require plant shutdown. or
- 3. a. Loss of wind speed indication or wind direction indication and
- b. Loss ot H14 (RE214) and RMS II Channel 1 (HE315, kE317. RE319) or
- c. loss of HIS (RE215) and CR9 and RMS II Channel 5 (RE225, RE226) or
- d. loss of R21 (HE221) and RMS II Channel 2 (HE325. HE327)
, or
- e. Lors of GWil2 (RE224) and RMS II Channel 6 Failure of reactor protection system to All of the followinga Alert complete a trip which brings reactor subcritical 1-Hour open line (3)
- 1. Unplanned first out annunciator on C04 with confirmation from associated indicator
- 2. Intermediate range detector output not decaying
- 3. >l RCC RPI indicates fully withdrawn
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h (% - TablekA k % Page 6 -~
- Esergency Categoy Initaattnq Condition Indication used Classification All alarms (asununciatos s) lost $15 minutes while unit 1. " Annunciator power failure" on Col, CO2 & Alert is not in cold shutdown 1(2)CO3, 1(2)C04 Loss of functions needed tot cold shutdown for >4 Ay of the tollowing: Alert hours while at cold shutdown
- 1. Loss of service water Unit 1 = bouth & west header Unit 2 = north & west header
- 2. Loss of both trains of kHR
- 3. Loss of component cooling
- 12. Abnormal Radiation a. Effluent monitors detect levels cors'esponding to Ai borne effluents only Site Emergency Levels at Site any of the following:
(1) >50 mR/hr for \ hour (2) >250 mR/nr for % hour for the thyroid (3) >500 mR/hr whole body for 2 minutes (4) >2500 mk/h to the thyroid for 2 minutes at the site boundary for advesse meteorology
- b. Any of the above doses measured in the environs As seported to DSS by HP Supervisor
- c. Any of the dose rates projected, based on plant parameters
- a. Effluent monitors detect levels corresponding to Airborne effluents only General Emergency either TI) 1 R/hr whole body (2) 5 R/hr thyroid at the site t#oundary under actual meteorological conditions
- b. Either of the above doses measured in environs As reported to DSS by itP Supervisor
- c. Either of above dose rates projected based on other plant parameters -
- 13. Fuel llandling Accident Major damage to irradiated fuel in containment Both of the following: Alert
- 1. As seported to DSS by Core Loading Supvr.
- 2. Alata on Victorcen on manipulator & alarm on R211 t
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, d M, . Emergency Categosy Initiating Condition Indication Used Classification Fuel damage accident with selease of radioactivity Both of the following: Alert l to aiutiliary building (FSAR 44.2.1)
- 1. As reported to DSS by Supvr in charge of fuel handling 6. drunning area vent (R221)
- 2. Alarm on Victorcen on spent fuel pit bridge.
- 14. Serious or Fatal Injury transportation of seriously ot- fatally injured keported as judged by DSS Unusual Event iridividual f rom site to hospital (expect hospitalization for at least j (Reference EPIP 11.1) 48 hours) i
, 15. Security Threat Security threat or attempted sabotage Per HASP Per MASP & Appendices or 1-Hour Red Phone Only Ongoing security corpromise (Open Line) (4)
- 16. Hazards to Plant Unusual aircraft activity over facility Visual observation of Operations Supervisor g unusual Event Operation security force Near or onsite explosion or flammable or toxic gas As reported to DSS by plant personnel making Unusual Event release visual observation Missile isapacts from any source on facility Visual observation by Operations Supervisor Alert Missile impact causing damage to two trains of safety systems Visual observation by Operations Supervisor Site Emergency Aircraf t crash in protected area (within the fence) Visual observation by Operations Supervisor Alert Known explosion damage to facility affecting plant Visual observation by Operations Supervisor Alert operation. Toxic or flannable gases in facility envirorment excluding normal process gases Toxic or flammable gases entering into vital areas Visual observation by Operations Supervisor Site Emergency (control room, auxiliary building, etc.) excluding normal process gases i
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~ J p,ge n w e Emergency ygy C Initiating Conditson Indication used Classification
- 17. Natural Events Any carthquake Activation of 12 accelerographs and verified by actual physical giound shakin:q or by con-
! tactir.g Dr. David Willas, University of Wisconsin, Milwaukee Seismic Center at 1-414/963-4602. Unusual Event Any tornado visable from sate Verification by Operations Supervisor Unusual Event Low Lake Michigasa water leviel With sao (W pumps running, water level is 3.9' Unusual Event below O' on surge chamber level & confirmed by
- measusing forebay level at 10.9' below pumphouse floor (7' level)
Earthquake greater than operatisig basis earthquake Easthquake with attendant structural damage of Alert
; contaisement or spent fuel pit Any tornado striking the facility Visual observation by Operations Supervisor Alert Seiche near design level >6" of water in turbine hall Alert
.; Winds in excess of desigri levels Wind speed indicated as >100 mph Alert l Wind with damage Structural damage to containment Site Emergency Failure of protection for vital equipment at low M of the following: Site Emergency levels (i.e., caused by seiche > design levels)
- 1. >3' water in both EDG rooms.
- 2. >2' water ini vital switchgear room.
- 3. >2' water in auxiliary feed pump room.
- 18. Heactivity Transient Usacontrolled rod withdiawal (FSAk 14.1.1 & 14.1.2) Unusual Event CVCS Halfunction (FSAR 14.1.5) Unusual Event Accidental Craticality NRC Only (3)
a O O . TableIkN
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i i Emergency Category Initiating Condition Indicatioet Used Classification i 19. Load Transient Loss of Electrical Load (FSAR 14.1.10) Unusual Event
- 20. Other Condation that was s ants State end/or local of ficial DCS & DSS concurrence Unusual Event
- awareness Condition that warrants establishanent of technical DCS & DSS concussence Alert i support center & emergency support center i
Condition that war rants us e of anonitoring teams DCS & DSS concurrence Alert i Personnel contamination Health Physicist & DCS concurrence NRC-only 1-hour (10) Any unplarased reactor trip DCS & DSS concurrence NRC-only i 1-Hour (7) l Strike by employees or guard force DCS & DSS concurrence NRC-only 1-Hour (12) Loss of red phone (ENS) DCS & DSS concurrence NRC-only 1-Hour (13) i Personnel or procedural error DCS & DSS concurrer.ce NRC-only 1-Hour (6) i 10 CPR 20.403 DCS & DSS concurrence. NRC-only
, 1-Hour (11) i
)
? EPIP 1.3 MINOR Revision 3 09-10-82
[w)'i l ESTIMATION OF SOURCE TERM 1.0 GENERAL The purpose of this procedure is to estimate the source term (stack release rate in Ci/second) using the low range operational stack monitors, the Eberline RMS II Radiation Monitoring Systems or direct contact radiation measurements on the plant effluent vents. The plant effluent vent stacks are: 1.1 Auxiliary Building Vent (ABVNT) 4 1.2 Drumming Area Vent (DAVNT) 1.3 Gas Stripper Building Vent (GSBVNT) 1.4 Combined Air Ejector Decay Duct (CAE) 1.5 Main Steam Safety Valves and Atmospheric Dump Valves 2.0 REFERENCE f 2.1 EDS Report to Wisconsin Electric Power Company concerning NUREG-0578, March 7, 1980. 3.0 PRECAUTIONS i 3.1 If fuel damage or loss of reactor coolant system integrity has occurred, some or all of the following would be present: 3.1.1 The letdown radiation monitor (R9) may be unusually high or offscale. 3.1.2 The containment radiation monitors (R11 and R12) may be unusually high or offscale. ! 3.1.3 The containment area monitors (R2 and R7) may be unusually high or offscale. 3.1.4 The charging pump area monitor (R4) may be unusually high or offscale. s A l
e EPIP 1.3 Pagn 2 (s) _ 3.2 Health Physics procedures and requirements must be followed when applicable (i.e., entering a high radiation area). 3.3 Evaluation of the radiation monitoring system readouts and radio-logical hazards must be completed prior to any attempt to enter the auxiliary building or facade to take a contact reading on any stack. i 3.4 If this procedure is being used for determination of emergency classi-fication, use EPIP 1.8 " Emergency Off-Site Dose Estimations" for determination of projec'.ed dose off-site. EPIP 1.8 is a shorter, however more conservative procedure for determination of projected dose. 4.0 INITIAL CONDITIONS 4.1 Applicable portions of EPIP 1.2,'" Plant Status", is completed. 5.0 PROCEDURE FOR Xe-133 EOUIVALENT RELEASE RATE ESTIMATE - WORKSHEET NO. 1 5.1 Chemistry / Health Physics Supervisor or Designated Alternate 5.1.1 Obtain EPIP-05 and EPIP-06 of EPIP 1.2, " Plant Status," for the radiation monitoring systems. NOTE: IF EPIP-05 AND EPIP-06 IN EPIP 1.2, " PLANT ('"' STATUS," ARE NOT COMPLETED, OBTAIN THE METER READINGS FOR EACH PLANT EFFLUENT VENT STACK FROM THE REMOTE CONTROL ROOM READOUT AND RECORD THIS ON WORKSHEET NO. 1 AND THEN PROCEED WITH STEP 5.1.3. I l NOTE: PLANT EFFLUENT VENT STACK MONITOR READINGS ARE
' l ALSO AVAILABLE FROM THE TECHNICAL SUPPORT CENTER j DATA LOGGER. SEE ATTACHMENTS 1.3-14, 15, 16 & 17.
5.1.2 Enter the meter readings and flow rates in the appropriate columns on Worksheet No. 1 for the indicated vents. If the readings are offscale, not monitored, or the monitors are inoperable, enter the appropriate word "offscale," "not monitored," or " inoperable" in the meter reading column for the vent affected. 5.1.3 Designate individuals in accordance with ALARA concepts to obtain meter readings of the vents whose Eberline RMS II data is not available and the main steam header by per-forming Section 5.2 of this procedure if required. NOTE: IF STEP 5.1.3 NEEDS TO BE COMPLETED BECAUSE EBERLINE RMS II DATA IS NOT AVAILABLE, OR IF A STEAM GENERATOR TUBE RUPTURE IS BELIEVED TO HAVE OCCURRED WHICH PRODUCES THE POTENTIAL FOR RELEASES, OR RELEASES ARE
\ IN PROGRESS FROM THE MAIN STEAM HEADER OR THE ATMOSPHERIC STEAM DUMP, THEN PERFORM SECTION 5.3 0F THIS PROCEDURE AFTER APPROPRIATE MEASUREMENTS HAVE BEEN TAKEN IN SECTION 5.2.
i EPIP 1.3 Page 3 y ) 5.1.4 Perform Section 5.3 of this procedure to determine the gross Xe-133 equivalent release rate estimate. 5.2 Direct Stack Survey Team Designees NOTE: THE FOLLOWING SECTION WILL NOT BE INITIATED UNTIL THE EVALUATION DISCUSSED IN PRECAUTION 3.3 HAS BEEN COMPLETED AND THE SITE MANAGER (DUTY & CALL SUPERINTENDENT), THE DUTY & CALL HEALTH PHYSICS SUPERVISOR, AND THE DUTY SHIFT SUPERVISOR HAVE APPROVED INITIATION. THIS SECTION WILL BE ACCOMPLISHED UNDER THE DIRECTION OF HEALTH PHYSICS SUPERVISION. 5.2.1 Determine the most direct and desirable route to the plant effluent stack to be monitored. 5.2.2 Determine the Health Physics requirements to be met for the passage to the vent areas. 5.2.3 Determine the appropriate survey instrument to be used for the plant effluent vent to be monitored. 5.2.4 Proceed by the route determined in Step 5.2.1 to the stack f'~ and record the survey instrument reading in contact with the stack in the columns provided on Worksheet No. 1, Part C, s Plant Effluent Vent Stack Contact Readings. NOTE: IN THE CASE OF THE MAIN STEAM SAFETY VALVES AND ATMOSPHERIC STEAM DUMP VALVES, THE READING WILL BE TAKEN IN CONTACT WITH THE CENTERLINE OF THE MAIN STEAM HEADER, THREE FEET FROM THE MAIN STEAM LINE. SHIELD THE PROBE (WITH A MINIMUM OF .25 INCHES OF LEAD) ON THE SIDES FACING THE MAIN STEAM LINE AND THE CONTAINMENT. 5.3 Chemistry / Health Physics Supervisor or Designated Alternate 5.3.1 Choose the appropriate vent stack readouts in Part A, B, or C of Worksheet No. I to convert readings to a Xe-133 equiva-lent release rate. That is if the low range monitors go offscale, use the high range monitors. Conversely, if the normal monitors are onscale, use the normal monitors, or if both normal and high range monitors are offscale or inoper-able, use the vent stack contact readings. i 5.3.2 Use the appropriate attached conversion curves for each of the plant effluent vent to convert the chosen vent stack readout, (cpm or R/ hour) and flow rate, from Step 5.3.1 to an Xe-133 equivalent release rate in Curies /second and record the value on Worksheet No. 1, Part D, Estimate of Gross Xe-133 Equivalent Release Rate. Enter the appropriate
EPIP 1.3 Paga 4 () word "offscale," "not monitored," or " inoperable" for the cases where the plant effluent vent was not monitored, offscale, or inoperable. NOTE: THE FOLLOWING QUALIFYING NOTES HUST BE RECOGNIZED.
- 1. If the actual flow rate is different than the conversion curves flow rate, a ratio of:
Actual Flow Rate Conversion Curve Flow Rate should be applied to determine the release rate. l (Ratio) X Conversion Curve = Adjusted Xe-133 5 Release Rate
= Equiv. Release Rate
- 2. If the main steam header vent release rate needs to be determined, the following steps must be applied.
- a. Obtain from the Shift Supervisor an estimated f flow rate through the main steam header in lbm/ hour of s, team being dumped to the environ-ment and the specific volume (v) of the steam.
(O At 1000 psia, specific volume is 0.446 ft.3/lbm. At 500 psia, spe'cific volume is 0.928'ft.3/lbm. cc lbm/hrxvfbyx7.86 g ,
- b. Convert contact reading obtained at the main steam header to pCi/cc using the appropriate attached conversion curve (Attachment 1.3-13) for the main steam header.
l pCi/cc
- c. Multiply flow rate obtained in Step (a) by the concentration obtained in Step (b) to obtain the release rate (Xe-133 equivalent) from the main steam header.
Flow Rate Concentration , Main Steam Header I (cc/sec.) X (pCi/cc) Release Rate I 5.3.2 Sum the values (1) through (7) on Worksheet No. 1, Part D, to determine the gross Xe-133 equivalent release rate. i r t f~
EPIP 1.3 Page 5 t NOTE: IF GRAB SAMPLE RESULTS ARE AVAILABLE, THE RESULT OF SUCH SAMPLES SHOULD BE MORE ACCURATE THAN GROSS ) MONITOR READINGS AND HENCE SHOULD BE USED IN LIEU OF THE RELEASE RATES CALCULATED ABOVE OR IN ADDITION TO THE ABOVE IF THE RELEASE IS FROM AN UNMONITORED RELEASE PATH. t 5.3.3 Report the calculated gross Xe-133 equivalent release rate to the Shift Supervisor and the Technical Support Manager. 4 i .! I I i i 4
--.,.-v ,. , -,-, , , , , , - , - , - , - . , . . , . . - - , , . , , , , - - - - . ,-,,_ ,,,, , _ _,- - ,, ,- - - - - ,~--- - - , , - - - - - - - - - _ _ _
-n
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( WORKSHEET NO. 1 %) Xe-133 EQUIVALENT RELEASE RATE A. LOW RANGE OPERATIONAL VENT STACK READOUTS Meter Reading Flow Rate Conversion Curve Vent (cpm) (cfm) Attachment No. Auxiliary Building R14 61400 1.3-1 Drumming Area R21 43100 1.3-2 Gas Stripper Building GW-112 13000 1.3-3 Combined Air Ejector Decay CR-9 25 1.3-4 B. EBERLINE RMS - II VENT STACK READOUTS NOTE: THESE READINGS ARE ALSO AVAILABLE ON THE TECHNICAL SUPPORT CENTER DATA LOGGER. ATTACHMENTS 1.3-14, 15, 16 & 17.
.; N l } Meter Reading Flow Rate Conversion Curve \~s/ Vent (R/ hour) (cfm) Attachment No.
Auxiliary Building Ch. #1 61400 1.3-5 Drumming Area Ch. #2 43100 1.3-6 Gas Stripper Building Ch. #6 13000 1.3-7 Combined Air Ejector Decay Ch. #5 25 1.3-8 C. PLANT EFFLUENT VENT STACK CONTACT READINGS Meter Reading Flow Rate Conversion Curve Vent (mr/hr or R/hr) (cfm) Attachment No. Auxiliary Building 61400 1.3-9 Drumming Area 43100 1.3-10 Gas Stripper Building 13000 1.3-11 Combined Air Ejector Decay 25 1.3-12 (~'N Main Steam Header (See Se E) 1.3-13
i i 's D. ACTUAL VERSUS CONVERSION CURVE FLOW RATE RATIO n e sion Curve Value = Adjusted Releast Rate ur e F o R e
=
( ) X l
- E. STEAM HEADER CONTACT READING CALCULATION
- 1. lbm/hr X specific volume ft3 /lbm X 7.86 cc hr/ft3 sec NOTE: At 1000 psia specific volume r .446 ft 33/lbm At 500 psia specific volume = .928 ft /lbm lbm/hr X fta /lbm X 7.86 cc hr/ft3 see i
cc/sec l 2. Contact reading conversion from Attachment 1.3-13: i pCi/cc 4 3 R/hr = 4
- 3. Steam header release rate:
- l' ~
Flow rate cc/sec X Concentration pCi/cc = Release Rate cc/sec X ,Ci/cc p = pCi/sec (1) (2) F. ESTIMATE OF GROSS Xe-133 EQUIVALENT RELEASE RATE l l I Xe-133 Equivalent Release Rate Vent (Curies /Sec.) l 1. Auxiliary Building
- 2. Drumming Area
- 3. Gas Stripper Building l 4. Combined Air Ejector Decay Duct
- 5. Main Steam Header l
' 6. Sum (Gross Xe-133 I Equiv. Release Rate) OR
- 7. Grab Sample Results = Ci/sec.
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EPIP 1.4 MINOR Revision 6 j 09-10-82 (a RADIOLOGICAL DOSE EVALUATION 1.0 GENERAL The purpose of this procedure is to provide a method to quickly estimate (1) X/Q using meteorological overlays, (2) thyroid and whole body dose using X/Q and (3) ground deposition using an approximation of D/Q.
2.0 REFERENCES
2.1 U. S. MRC Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1," October 1977. 2.2 U. S. EPA, " Manual of Protective Action Guides and Protective Actions for Nuclear Incidents," EPA-520/1-75-001, September 1975. See Appendix D " Technical Bases for Methods that Estimate the Projected Thyroid Dose and Projected Whole Body Gamma Dose from Exposure to kj , Airborne Radioiodines and Radioactive Noble Gases." v 2.3 U. S. NRC Regulatory Guide 1.4, " Assumptions used for Evaluating the Potential Radiological Consequences of a Loss-of Coolant Accident for Pressurized Water Reactors," Revision 2, June 1976. 2.4 TID 14844, " Calculation of Distance Factors for Power and Test Reactor Sites," March 23, 1962. 3.0 PRECAUTIONS & LIMITATIONS I 3.1 For classification purposes where radiological dose is the primary parameter leading to a classification, use EPIP 1.8, " Emergency Off-Site Dose Estimation" for determination of dose. 3.2 Ensure that all PBNP maps to be used by this procedure and their corresponding meteorological overlays are based on the same scale. 3.3 This procedure will be accomplished in the technical support center by a person designated by the Shift Supervisor or the Technical Support Manager. It will usually be done in conjunction with the Chemistry / Health Physics Supervisor when available. 3.4 This procedure will also be accomplished in the ESC by a person designated by the RadCon/ Waste Manager. [ v
A' EPIP 1.4 Page 2 (""N 3.4 Wind speed and wind direction must be average values obtained from the analog recorders in the control room. NOTE: DO NOT USE INSTANTANEOUS VALUES. 3.5 If the radiological release duration is unknown, assume a duration of 8 hours. 3.6 If the meteorological parameters cannot be obtained from the control a room, obtain the data from the following priority backup list. J 3.6.1 Kewaunee Nuclear Power Plant. 3.6.2 National Weather Service in Green Bay. Ask for Two Rivers Coast Guard information, if available. 4.0 INITIAL CONDITIONS 4.1 A release of airborne radioactivity has occurred or a release is anticipated. 4.2 An emergency or potential emergency condition is anticipated to have
- ~.g offsite dose consequences. \s / - 5.0 PROCEDURE / CHEMISTRY & HEALTH PHYSICS SUPERVISOR OR DESIGNEE 5.1 Determination of X/Q, Atmospheric Dispersion Factor 5.1.1 Obtain the following information from the indicated source and enter this data in the appropriate space on form EPIP-07 (attached).
Source Data EPIP-04 (a) wind speed in-mph EPIP-04 (b) wind direction EPIP-04 (c) time of reactor shutdown ' EPIP-04 (d) time of release to containment EPIP-04 (e) time of release from the plant i Health Physics or Operating (f) duration or estimated dura-logs or projected estimate tion of the release in-hours EPIP 1.3 results (see note) (g) gross Xe-133 equivalent release rate in Ci/sec EPIP-04 (h) Stability class in o0 degrees NOTE: IF RELEASE DURATION IS UNKNOWN, ASSUllE 8 HOURS. G 5.1.2 Determine stability class by use of the 00 chart recorder in the control room and Attachment 1.4-1. Enter the stability class (h) on form EPIP-07.
P-S EPIP 1.4 Page 3 G' 5.1.3 Backup stability class determination. Visually check cloud cover and incoming solar radiation. With this information, use Attachment 1.4-3 to ascertain the appropriate stability class. Enter the stability class (h), on form EPIP-07. NOTE: IF INCOMING SOLAR RADIATION IS STRONG AND WINDS ARE FROM THE EAST OR SOUTHEAST, IT IS A POSSIBILITY THE WIND IS PRODUCED BY A LAKE EFFECT. CALL THE GREEN BAY NATIONAL WEATHER SERVICE FOR AID IN THIS DETER-MINATION. IF A LAKE BREEZE IS SUSPECTED, OFFSITE SURVEY TEAMS MUST BE REMINDED TO PAY CLOSE ATTENTION TO WIND DIRECTION. 5.1.4 Place the overlay corresponding to the stability class on the map. Using the plant location as a pivot point, align the centerline of the overlay to the downwind direction from the plant. NOTE: THE " TICK" MARKS ON THE CENTERLINE OF THE OVERLAYS ARE ONE MILE APART. 5.1.5 Determine the distance (i) to the dose projection location ( , if different from the standard centerline distances listed
) on form EPIP-07. Note the location description, sector, ard
.N' distance on fonn EPIP-07.
Enter the Xu/Q value (j) for the distances of site boundary, two miles, five miles, and ten miles on EPIP-07. The Xu/Q , values (j) can be cbtained from the overlay in the table in the lower righthand corner of the overlay. If a possible location other than the standard specified location is on a line, enter the Xu/Q (j) value for that line from the overlay on form EPIP-07. If the location is not on a line, move to the next inner-most line (toward the centerline) and enter the Xu/Q (j) value for that line on form EPIP-07. Example: Class "C" Xu/Q for 5 miles equals 1.21 x 10 ~6 m 2 i 5.1.5 Calculate the X/Q value from the Xu/Q value by using the equation: l X sec. = 2.24(sec./m) X WindXu/Q (m 2) Speed (mi/hr.) Q m" (hrs./mi) l Enter the X/Q values on form EPIP-07.
} 5.2 Whole Body Dose Estimate
%) 53TE: IF THE NOBLE GAS SOURCE TER11 IS DETERMINED BY GRAB SAMPLE RESULTS WHICH GIVES AN INVENTORY OF SPECIFIC NUCLIDES, THEN A CONSERVATIVE WHOLE BODY DOSE ESTIMATE CAN BE MADE BY COMPLETING FORM EPIP-09.
l -. . - - .. , -. , . . - . - _ . .
I t l a! j EPIP 1.4 3 Page 4 l l l _- / 5.2.1 Enter the gross Xe-133 equivalent release rate (g) on form EPIP-08 from form EPIP-07. l 5.2.2 Enter the estimated release duration, ERD, in hours (f) on I form EPIP-08 from form EPIP-07. 5.2.3 Calculate the projected whole body dose on form EPIP-08 by using the equation: l (k) (g) 3 3 l D(Rem) = X/Q (sec/m ) x Q (Ci/se'c) x Kr (Rem m /Ci - Hrs) , I I x ERD (Hrs) i where: D = whole body dose (Rem) l X/Q = atmospheric dispersion coefficient j determined in Step 5.1.5 (sec/m 3) (k) i 5 Q = release rate (Ci/sec) (g) ~ fg rem m 3
/ Kr = Dose Factor ( Ci hrs ) Attachment 1.4-2 i ERD = Estimated Release Duration (Hours) (f) 5.3 Thyroid Dose Estimate i
5.3.1 Calculate the projected thryoid dose by using the whole body dose calculated in Section 5.2 of this procedure. 5.3.2 Record the projected whole body dose on form EPIP-08 in Section 2. 5.3.3 Choose the appropriate figure based upon the type of accident which has occurred.
- a. Loss of Coolant Accident (LOCA) - Figure 1.4-1.
- b. Gap Activity Accident -
Figure 1.4-4.
- c. Fuel Handling Accident - Figure 1.4-4.
- d. Steam Generator Tube Rupture - Figure 1.4-5. NOTE: IF THE TYPE OF ACCIDENT IS UNKNOWN, USE THE LOCA
. FIGURES.
f 5.3.4 Obtain the ratio factor that relates the whole body dose to a thyroid dose from the figure chosen with the corresponding appropriate time after the accident and record on form i EPIP-08, Section 2.
l 5 EPIP 1.4 l Page 5 l n v 5.3.5 Calculate the projected thyroid dose my multiplying the whole body dose by the ratio factor obtained in Step 5.3.4 on form EPIP-08, Section 2. 5.4 Radionuclide Ground Deposition Estimation NOTE: FORM EPIP-10 CAN BE COMPLETED ONLY IF IODINE GRAB SAMPLE RESULTS OR PARTICULATE RELEASE RATES ARE AVAILABLE. IF FORM EPIP-10 CANNOT BE COMPLETED, PROCEED WITH STEP 5.4.5 0F THIS SECTION. 5.4.1 Enter the Xe-133 equivalent release rate or the specific particulate release rate on form EPIP-10 from grab sample results or from environmental monitoring results. 5.4.2 Enter the estimated duration of release (f) from form EPIP-07 on form EPIP- 10. 5.4.3 Enter the value of X/Q (k) on form EPIP-10 as determined in Step 5.1.5. 5.4.4 Complete Section 2 of form EPIP-10 to calculate the* ground deposition using the equation: Dep (pCi/m2 ) = F x .05 (m/sec) x 3600 (sec/hr) x 10 6 (pCi/Ci) x X/Q (sec/m 3) x Q (Ci/sec) x ERD (hrs) , 8 (k) (g) (f) Dep = F x 1.8 x 10 x X/Q x Q n EIP l Dep = ground deposition (pCi/m3 ) X/Q = atmospheric dispersion factor from Step 5.1.5 (sec/m3 ) (k) Q = radionuclide release rate (Ci/sec) (g) ERD = estimated release duration (hrs) (f) F = fraction of isotope subject to deposition (unitless) 3600 = conversion (sec/hr) 106 = conversion (pCi/Ci) 0.05 = assumed deposition velocity (m/sec) 5.4.5 Complete form EPIP-11 from available data and calculations y just performed. 5.4.6 Enter the date and time of these calculations and sign form EPIP-11.
4-i L 4 j' EPIP 1.4 j Page 6 i f 5.4.7 Forward completed attachments to the Technical Support l Manager for review. The Technical Support Manager will j relay results to the Site Manager. l i
- 5.5 Population Exposure t
- 5.5.1 Calculate projected population exposure by using form-
- EPIP-10a.
t ! 5.5.2 Enter from EPIP-08 whole body dose from center line on ! form EPIP-10a. I ! 5.5.3 Enter population figures from Figure 1.4-6. Use population number corresponding to the quadrant and distance categories for dose. 5.5.4 Total population dose from'each radius to find total ! population dose. l \ i \i 1 ( i l l ( l l l l i l l l
_- ~ _ - _ .-. . . ~ - _ . - _ - - - . - - - . - - . . - . . _ . . - . . . _ - . . - _ . - - . - - _ i 4 . 1 i .! 6 i l lh l ATTACHMENT 1.4-1 , i l l CLASSIFICATION OF ATMOSPHERIC STABILITY BY SIGMA THETA i t r Stability Pasquill a0 Classification Categories (degrees) , j .r i Extremely unstable A 00 2 22.5 I . ! Moderately unstable B 22.5 > 00 2 17.5 l Slightly unstable C 17.5 > 00 2 12.5 i l Neutral D 12.5 > 00 2 7.5 , Slightly stable E 7.5 > 00 2 3.8 [ I Moderately stable .F 3.8 > 00 2 2.1 Extremely stable G 2.1 > 00 ! i
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<4 A A-B B 4-7 A-B B C E F 7-11 B B-C C D E 11-13 C C-D D D D
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(V radiation and should be considered along with solar altitude when determining Incoming radiation that would be strong with clear skies can solar radiaticn. be expected to reduce to moderate with broken (5/8 to 7/8 cloud cover) middle clouds and to slight with' broken low clouds. Night refers to the period from one hour before sunset to one hour after sunrise. i l i l
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ao I EPIP 1.5 MINOR Revision 4
,-ss 09-10-82
(\, J PROTECTIVE ACTION EVALUATION 1.0 PURPOSE The purpose of this procedure is to provide a basic guide to determine protective action recommendations to be given to the public authorities and to provide a method to transmit these recommendations and other essential data for assessment to the appropriate public authorities.
2.0 REFERENCES
2.1 NUREG-0654, Revision 1, " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants," November, 1980. 2.2 NUREG-0654, Appendix 1, " Emergency Action Level Guidelines for Nuclear Power Plants." f 3.0 PRECAUTIONS AND LIMITATIONS (O)
\
3.1 Ask for the name and title of the person or agency being contected prior to transmitting any information. 3.2 If unable to contact an individual or agency, continue with the transmissions to the other individuals or agencies and then attemot to contact the persons or agencies who have not been cor.tacted. 3.3 All actions and recommendations should be appropriately logged. l 3.4 If the radiological release duration is unknown, assume a duraticn of 8 hours for use during an evaluation of the need for a protective action recommendation. l 3.5 When protective action recommendations are made, consider the recom-mendation over a 90 sector centered on the average wind direction and a full 360 area near (2 miles) the plant. 4.0 INITIAL CONDITIONS 4.1 Applicable portions of EPIP 1.2, " Plant Status," completed. 4.2 EPIP 1.3, " Estimation of Source Term," completed. l l 4.3 EPIP 1.4, " Radiological Dose Evaluation," completed. (h 4.4 Site Emergency or General Emergency has been declared. U i ( I
- .. . - - =. .- .- . . -_ . _ - . _--
e* [. / EPIP 1.5
) Page 2 l ! \ 5.0 PROCEDURE 5.1 _ Technical Support Manager 5.1.1 Obtain the completed attachments of EPIP 1.4, " Radiological Dose Evaluation," from the person completing them.
l' 5.1.2 Review the results of the dose projection calculations and deposition calculations for all affected areas. 5.1.3 Review Attachments 1.5-1 and 1.5-2. 5.1.4 Based on actual plant conditions, expected plant conditions in the future, weather conditions, local protection avail-able to the public, evacuation times and any other constraints, ! determine the most appropriate Protective Actions to reduce j l exposure to the public and relay the information to the emergency support center. 5.2 Emergency Support Manager NOTE: THE FOLLOWING STEPS MUST BE DONE BY THE EMERGENCY SUPPORT 11ANAGER OR HIS DESIGNATED ALTERNATE. UNTIL HE ARRIVES IN f (/' l THE EMERGENCY SUPPORT CENTER, THE SITE MANAGER IS ACTING AS EMERGENCY SUPPORT MANAGER. i ! l 5.2.1 Review the recommendation of the Technical Suppcrt Manager and/or Rad / Con Waste Manager, i t 5.2.2 Complete Section 2 (status update form) of the incident } report form contained in the offsite agency notification 1 i procedures. I 5.2.3 Contact the NRC and the persons and agencies notified on i NAWAS of the emergency and provide the information contained I in the status update form to them. ! l i I l 5.2.4 For a General Emergency, form EPIP-16 in EPIP 5.3, " General [ Emergency - Offsite Agency Notification," shall be used as [ the basis for followup messages to offsite technical per- , sonnel such as NSSS vendor and corporate engineering staff. f I l l 4
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9-EPIP 1.7 MINOR Revision 1 g 09-10-82
-- J EVALUATION OF CORE DAMAGE 1.0 PURPOSE The purpose of this procedure is to estimate core damage using a mathema-tical model based on an actual primary coolant sample activity, estimated volume introduced into the primary system through safety injection and a correction factor based on the time since reactor shutdown. This evaluation should be performed by the Core Physics Coordinator or a Duty Technical Advisors and routed to the Technical Support Manager and Site Manager.
2.0 REFERENCE Calculations performed by the Nuclear Engineering Section of Wisconsin Electric Power Company documented in a report to G. A. Reed dated I October 5, 1981 "C & HP Items Related to NUREG-0737." 3.0 PRECAUTIONS 3.1 If fuel damage or loss of reactor coolant system integrity has occurred, I- some or all of the following would be present:
\
3.1.1 The letdown radiation monitor (R9) may be unusually high or offscale. 3.1.2 The containment radiation monitors (R11 & R12) may be unusually high or offscale. 3.1.3 The containment area monitors (R2 & R7) may be unusually high or offscale. ! 3.2 Health Physics procedures and requirements must be followed when applicable (e.g., when entering a high radiation area). [ 3.3 Evaluation of the radiation monitoring system readouts and radiological I hazards must be completed prior to any attempt to enter the auxiliary l building to take a primary sample. I 4.0 INITIAL CONDITIONS 4.1 Applicable portions of EPIP 1.2, " Plant Status," are completed. l l i
. . - .- -~. , , , . . - - - . _ _ . . _ . , - - . . -.#- . . - - - , . . . - .-.-.--o.- -- .
I .. EPIP 1.7 Page 2 g 4.2 A reactor coolant sample has been taken and a contact reading of the sample bomb has been taken or a final total sample activity has been completed by implementing EPIP 7.3.2 " Post-Accident Sampling & Analysis of Potentially High Level Reactor Coolant." 4.3 A contact reading of the sample bomb in R/hr was taken and listed on form EPIP-30 or an actual sample activity has been received from lab analysis. 5.0 PRIMARY COOLANT SAMPLE ACTIVITY ESTIMATE PROCEDURE 5.1 Note the time of the sample contact reading taken in Section 4.3 on form EPIP-33. 5.2 Determine the amount of time since reactor shutdown to sample contact reading using the equation: Reactor Shutdown Time - Contact Reading Time = Time Since Shutdown 5.3 Convert the R/hr reading obtained using the teletector to Ci/ml using Attachment 1.7-1. 5.4 Enter the conversion factor from Section 5.3 on form EPIP-33. f, 5.5 Determ _ne the estimated Sample Activity using the equation: Estimated Sample Activity (Ci/ml) = Sample Bomb Contact Reading * (R/hr) x Conversion Factor Ci/ml l R/hr I !
- Contact reading is on shielded sample bomb which incorporates j 3 inches of external solid lead shielding.
5.6 Enter the estimated Sample Activity on form EPIP-33. 6.0 EXA!!PLE Coolant Sample Activity Estimate (Shielded Bomb) Teletector reading = 2.75 R/hr Reading time = 1700 Reactor Shutdown Time = 0900 Time since shutdown: 1700 hours - 0900 hours = 8 hours Ci ml = 1.63 x 10' 2.75 R/hr x 5.93 x 10- j Ci/ml
. . e-...r _.. . . - . , . . _ , , , . -
f -. e. EPIP 1.7 Page 3 7.0 CORE DAMAGE ESTIMATE PROCEDURE 7.1 Calculate-the estimated percentage of core damage using the following formula and table of correction factors. Interpolate correction fac-tors for times between those listed. Use best estimate for safety injection volume. 7.1.1 Estimated Sample Activity (ESA) Ci/ml 7.1.2 Estimated Safety Injection Volume (ESIV) gallons Available safety injection dilution sources are: Accumulators: 2 at 1,000 gallons each Refueling water storage tank: 275,000 gallons Boric acid storage tank: 1 of 3 at 5,000 gallons each Spray additive tank: 2,574 gallons 7.1.3 Correction Factor for Time Since Shutdovn [CF(t)]- hours 7.1.4 Enter the values from Sections 7.1.1, 7.1.2, and 7.1.3 on f-form EPIP-33. Calculate the percent core damage using the
\/N s ,) following forraula and Attachment 1.7-2 and enter the result -
l on form EPIP-33. Percent Core Damage (%) =
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. CF(t) 7.1.5 Route form EPIP-33 to the Site Manager and Technical Support Manager. 8.0 EXA!!PLE Percentage Core Damage Estimate Estimated Sample Activity = 1.63 x 10-1 Ci/ml Time since shutdown = 8 hours l Estimated safety injection volume = 2,000 gallons Percentage core damage (%) = 1.63 x 10_ 1 Ci/ml x (32,500 + 2,000) 547 Percentage core damage (%) = 9%
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( s EPIP 1.8 r' MINOR Revision 2 09-10-82 w/ EMERGENCY OFF-SITE DOSE ESTIIIATIONS 1.0 GENERAL The purpose of this procedure is to provide a method for the expeditious classification of an accident or event based on estimated off-site doses. The procedure provides a methodology to quickly estimate (1) stack release rates (source terms) and (2) off-site whole body and thyroid doses.
2.0 REFERENCES
2.1 U. S. MRC Regulatory Guide 1.109,. Calculation of Annual Dose to I!an from Routine Releases of Reactor Effluents for the Purpose of Evalu-ating Compliance with 10 CFR 50 Appendix I, Revision 1, October, 1977 2.2 U. S. EPA " Manual of Protective Action Guides and Protective Actions for Nuclear Incidents," EPA-520/1-75-001, September 1975, Appendix D 2.3 TID 14844 " Calculation of Distance Factors for Power and Test Reactor Sites," March 23, 1982 g
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2.4 EDS Report to Wisconsin Electric Power Company concerning NUREG-0578,
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i March 7, 1980. 2.5 Point Beach Nuclear Plant, Final Safety Analysis Report (FSAR) 3.0 PRECAUTIONS & LIMITATIONS 3.1 This procedure is intended for use in the control room by a person l designated by the Shift Superviser such as the Duty Technical Advisor. 3.2 This procedure is to be used only for immediate initial dose pro-jections. The initial dose projections are to be refined using EPIP 1.3 and 1.4 once more data becomes available, i.e., meteoro-logical data, air samples, and off-site survey dose measurements. 3.3 It is recognized that the RadCon/ Waste !!anager, in conjunction with the Chemistry & Health Physics Supervisor, is ultimately responsible for off-site dose assessments. However, the initial projections will normally be done by the Shift Supervisor or designee for purposes of classifying the event. x
I . EPIP 1.8
# Page 2 4.0 INITIAL CONDITIONS
,e-x i (x' ) 4.1 An emergency or potential condition which is anticipated to have l cff-site dose consequences.
4.2 A release of airborne radioactivity has occurred, or a release is anticipated, requiring a conservative estimate of the off-site dose consequences. 5.0 PROCEDURE 5.1 Calculation of Xe-133 Eauivalent Release Rates (Source Terms) 5.1.1 Airborne effluents may be discharged from PBNP through the following vent stacks:
- a. Auxiliary building vent (AEVUT)
- b. Drumming area vent (DAVNT)
- c. Unit 1 containment purge vent (Cont. 1)
- d. Unit 2 containment purge vent (Cont. 2)
( e. Gas stripper building vent (GSBVNT) ('~') f. Combined air ejector decay duct (CAE)
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- g. Main steam safety valves and atmospheric dump valves 5.1.2 The source terms (vent release rate in Ci/second) may be estimated by using any of the following monitoring systems.
- a. Low range operational stack monitors (designed to monitor low-level releases).
- b. Eberline RMS II radiation monitoring system (designed to monitor high-level releases).
- c. Contact readings using a hand-held survey meter (to be used when other monitor systems are non-operable).
5.1.3 The decision as to which monitoring system is to be used to estimate the source terms is dependent on the level of release and the operability of the monitor. 5.1.4 Meter readings are to be entered in the appropriate column on EPIP-34. If meter readings are "off-scale" or " inoperable," enter the appropriate comment in the meter reading column on EPIP-34. A source term estimate must be made for each vent which is exhibiting readings above normal operating readings.
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# Page 3 5.1.5 Direct contact readings using a hand-held survey meter are
,_ required under the following conditions:
{ \ ( ,/ _ a. Meter readings from the low range monitoring system or the RMS II system are not available.
- b. A steam generator tube rupture has occurred necessi-tating a hand-held meter reading at the main steam header.
5.1.6 Direct contact readings using a hand-held survey meter are not to be initiated until the follcwing conditions are accomplished:
- a. An evaluation of the radiological hazards must be com-pleted prior to any attempt to enter the auxiliary building or facade to take survey readings on any stack or vent.
- b. Before the surveys are done, the proper ~ survey meter and the most direct and desirable route to the stack to be monitored must be chosen.
- c. The surveys will be accomplished under the direction of the Health Physics Supervisor. The surveys must be approved by the Site Manager, Duty & Call Health Physics g'~x\ Supervisor, and the Duty Shift Supervisor.
\
5.1.7 For surveying the main steam safety valves and atmospheric dump valves, the reading will be taken in contact with the centerline of the main steam header, three feet from the main steam line. The survey probe is to be shielded with a minimum of 0.25 inches of lead on the side of the probe facing the main steam line and the containment. 5.1.8 The following data should be obtained from the Shift Super- ' visor in order to estimate release rates from the main I steam header:
- a. Estimated flow rate of steam through the main steam header in lbs/hr.
- b. Specific volume of the steam in ft 3/lb. At 1000 psia, specific volume of 0.446 ft 3 /lb. At 500 psia, specific !
volume is 0.928 ft 3/lb. Enter this data on the appropriate column in Section 3.0 of EPIP-34. 5.1.9 Sum the values on EPIP-34, Section 4.0, to determine the gross Xe-133 equivalent release rate. (m, s_
,> EPIP 1.8 Page 4 5.2 Whole Body Dose Projections
( ) 5.2.1 Off-site whole body dose rates may be calculated at the site boundary using the following equation: D(REM) = X/Q x Q x Kr HR Where: D = whole body dose rate (Rem /hr) X/Q = atmospheric dispersion coefficient (sec/m 3) Q = gross Xe-133 equivalent release rate (Ci/sec.) Kr = Dose Factor (rem-m3) Ci-hrs Projected off-site dose rates may be calculated by entering the total Xe-133 equivalent release rate calculated on l EPIP-34 in the appropriate column on EPIP-35 and multiplying the variables in the equations. 5.2.3 Enter the estimated release duration in the appropriate g column on EPIP-35. (A dose per hour is calculated by ( entering an exposure period of one (1) hour.) [) NOTE: THE X/Q VALUES LISTED ON EPIP-35 ARE ESTIMATED
'x _ , f BASED ON CALCULATED ACCIDENT !!ETER0 LOGY FOR 0-2 HRS.
AS GIVEN IN THE FSAR. IF REAL TI!!E !!ETEOROLOGICAL DATA IS AVAILABLE, X/Q VALUES CAN BE CALCULATED l AS OUTLINED Ill EPIP 1.4 SECTION 5.1. REFINE!!ENT OF THE PROJECTED OFF-SITE DOSES IIAY BE ACCCl!PLISHED BY SUBSTITUTING THE REAL TI!!E X/Q CALCULATED VALUE FOR THE ESTIllATED X/Q ON EPIP-35. 5.3 Thyroid Dose Projection 5.3.1 Calculate the projected thyroid dose at the site boundary on Section 2.0 of EPIP-35 by using the following equation: Thyroid Dose = Whole Body Dose x Conversion Factor 5.3.2 The conversion factor is dependent on the type of accident which has occurred. Conversion factors are tabulated for the following accidents:
- a. Loss of coolant accident (LOCA)
- b. Gap activity accident
- c. Fuel handling accident t'%
! ) d. Steam generator tube rupture \_-
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,r EPIP 1.8
' Page 5 5.3.3 Choose the appropriate type accident and calculate the
,s thyroid dose in Section 2.0 of EPIP-35 by multiplying the
( ) whole body dose calculated in Sectin 1.0 by the conversion x s' factor NOTE: IF THE TYPE OF ACCIDENT IS NOT KNOWN, USE THE LOSS OF COOLANT CONVERSION FACTOR. 5.4 Classification of the Event Based on Estimated Off-Site Doses 5.4.1 The event is to be classified as a Site Emergency if the projected off-site doses meet any of the following criteria:
- a. Effluent monitors detect levels corresponding to any of the following doses at or beyond the site boundary:
(1) >50 mR/hr whole body for b hour (2) >250 mR/hr for \ hour for the thyroid (3) >500 mR/hr whole body for 2 minutes (4) >2500 mR/hr to the thyroid for 2 minutes
/
( b. Any of the above dose rates are projected, based on plant parameters.
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I '~' / 5.4.2 The event is to be classified as a General Emergency if the projected off-site doses meet any of the following criteria:
- a. Effluent monitors detect levels corresponding to any of the following doses at or beyond the site boundary:
(1) 21 R/hr whole body (2) ?5 R/hr thyroid
- b. Either of above dose rates are projected based on plant parameters.
5.5 Protective Action Recommendation 5.5.1 Due to the conservative nature of the calculations in this procedure, use EPIP 1.4 to calculate dose projections for protective action recommendations unless it is apparent there is no time to use EPIP 1.4. 5.5.2 Enter dose rates and release c.uration estimate on EPIP-35. If duration of release is unknown, use a release duration of 8 hours.
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i S EPIP 1.8 I' Page 6 5.5.3 Recommend one of the following offsite protective actions s based on results of EPIP-35 calculations.
\' Whole Body Dose ,
- a. <1 R - No planned protective actions.
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- b. I to <5 R - Seek shelter as a minimum. Consider evacu- l ation.
- c. >5 R - Conduct evacuation in area affected and public l' within 2 miles of the plant.
Thyroid Dose
- a. <5 R - No planned protective actions.
- b. 5 to <25 R - Seek shelter as a minimum. Consider evacu-ation.
- c. >25 R - Conduct evacuation in area affected and public within 2 miles of the plant. j A
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. ;9
>+ -EPIP 2.1 MINOR Revision 1 09-10-82
) ,
UNUSUAL EVENT - IMMEDIATE ACTIONS 1.0 PURPOSE The purpose- of this procedure is to provide a series of immediate actions and clear direction to adequately respond to events or conditions classi-fied in accordance with EPIP 1.1, " Initial Classification," as an Unusual Event. An Unusual Event can lead to a degradation in overall safety. The situ-ation may be one in which time is available to take precautionary and constructive steps to prevent a more serious event or to mitigate any consequences that may occur. No significant release of radioactive material is expected and, therefore, offsite radiological response is not
~
expected to be necessary. No formal activation of the various centers, such as the technical support center, is anticipated, although the room may be used for communications, debriefing, and meetings. ( The Unusual Event status will be maintained until escalation in emergency L s classification is declared or a closecut of the event is made by informing offsite authorities, and by the completion of an incident report form as
> 1 contained in EPIP 2.3, " Unusual Event - OffsiteLAgency Notification."
V
2.0 REFERENCES
2.1 NUREG-0654, Revision 1, November, 1980. 3.0 PRECAUTIONS AND LIMITATIONS 3.1 All actions and notifications should be appropriately logged. 4.0 INITIAL CONDITIONS , 4.1 EPIP 1.1, " Initial Classification," completed. 5.0 PROCEDURE 5.1 Shift Supervisor / Designee 5.1.1 If the emergency affects any manned area of the plant other than the control room, announce the nature and location of the emergency using the Gai-tronics system. Make the announce-ment at least twice. Evacuate affected areas if necessary to protect personnel by implementation of EPIP 6.1, " Limited Plant Evacuation."
\
r r iPIP 2.1 Page 2 ( ') 5.1.2 Implement plant operating procedures as required to place
\
x/ the affected unit / units in a safe condition as the emergency warrants. 5.1.3 Designate an individual, such as the Duty rechnical Advisor or Duty & Call Superintendent, to perform Section 5.1 of EPIP 2.3, " Unusual Event - Offsite Agency Notification." 5.1.4 Implement EPIP 11.0, "First Aid and Medical Care," as necessary. 5.1.5 Implement EPIP 7.0, "CHP Radiological Response and Prepared-ness," as necessary. 5.1.6 Implement EPIP 10.1, "Firefighting," as necessary. 5.1.7 Implement EPIP 8.1, " Personnel Assembly and Accountability," as necessary. 5.1.8 Implement EPIP 12.2, " Personnel Exposure and Search and Rescue Team," as necessary. 5.1.9 Determine the need for additional personnel. Implement ( s EPIP 2.2, " Unusual Event - Plant and Company Personnel Notification," as required. { }
\~ / 5.1.10 Reevaluate emergency as conditions change by repeating Steps 5.1 through 5.5 of EPIP 1.1, " Initial Classification,"
and escalate to a more severe class if necessary by repeating Steps 5.7 through 5.9 of EPIP 1.1, " Initial Classification." 5.2 Operating Supervisor 5.2.1 Report to the control room. 5.2.2 If the Shift Supervisor is incapacitated, assume the responsi-bility and authority of the Shift Supervisor (until properly relieved by a qualified individual and coordinate the plant response as outlined in Section 5.5 of this procedure). 5.3 Duty Technical Advisor 5.3.1 Report to the control room and assume an appropriate advisory role. i! 5.3.2 Assist the Shift Supervisor as assigned in communications with the technical support center. O v
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l
/
( 5.4 Security Lieutenant U 5.4.1 Implement EPIP 9.1, " Security," as necessary. 5.4.2 Report to control room to obtain completed incident report form. 5.4.3 Implement Section 5.2 of EPIP 2.3, " Unusual Event - Offsite Agency Notification" as directed. 5.5 Duty & Call Superintendent 5.5.1 Report to the control room or the technical support center as required depending upon the availability of other senior management personnel. 5.5.2 Assume role of Plant Operations Manager as necessary. 5.5.3 Review the plant condition and the Emergency Classification status. Review and perform as necessary EPIP 1.2, " Plant Status," EPIP 1.8, " Emergency Offsite Dose Estimation," and EPIP 1.5, " Protective Action Evaluation." 5.5.4 Reclassify emergency as necessary and complete Section 1 of form EPIP-12, " Incident Report Form" attached to EPIP 2.3, [eml " Unusual Event - Offsite Agency Notification." V 5.5.5 Escalate to a more severe classification if necessary by implementation of EPIP 3.1, " Alert - Immediate Actions," EPIP 4.1, " Site Emergency - Immediate Actions," or EPIP 5.1,
" General Emergency - Immediate Actions."
5.5.6 Provide recommendations of any required protective actions for the public to State and local authorities. 5.5.7 Terminate the unusual event classification if plant condi-tions warrant that action by completing Section 1 of form EPIP-12, " Incident Report Form," attached to EPIP 2.3,
" Unusual Event - Offsite Agency Notification."
5.5.8 Contact by telephone the persons and agencies notified of the emergency and provide the information contained in the notification message of Section 1. 5.5.9 Assure completion of EPIP 2.3, " Unusual Event-Offsite Agency Notification." 5.6 Plant Supervisory Personnel 5.6.1 Report to assigned location and wait for further instruc-tions. l
l 1 l l , EPIP 2.1 j Page 4 l 5.7 Deactivation ! 5.7.1 If conditions no longer warrant the Unusual Event classifi- j j cation, provide a verbal summary of events to personnel l l notified in accordance with EPIP 2.2, " Unusual Event - Plant ! and Company Personnel Notification," and 2.3, " Unusual l Event - Offsite Agency tiotification." ! l 5.7.2 Notify plant personnel of the Unusual Event closecut as ] . required. I i 5.7.3 Complete the incident report form contained in EPIP 2.3, ! " Unusual Event - Offsite Agency Notification." i l - I 'l i , I ! i I {' l t e I l l l t [ l i l 1 l
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J EPIP 2.3 MINOR Revision 2 09-10-82 7-i 1 C UNUSUAL EVENT - 0FFSITE AGENCY NOTIFICATION 1.0 GENERAL The purpose of this procedure is to establish the initial offsite agency notification actions in response to plant conditions classified as an Unusual Event in accordance with EPIP 1.1, " Initial Classification." Necessary phone numbers are included in form EPIP-23, "Offsite Agency Emergency Call List."
2.0 REFERENCES
Mone 3.0 PRECAUTIONS AND LIMITATIONS 3.1 Obtain the name and title of the person being contacted prior to transmitting any information. 3.2 If unable to contact an individual or agency, continue with the notification of the other individuals or agencies and then attempt to (}
\.s,/
contact the persons or agencies who have not been notified. 3.3 All actions and notifications should be appropriately logged on form EPIP-12 (attached), " Unusual Event Incident Report Forn," Sections 1, 2 and 3 and/or on EPIP-23, "offsite Agency Emergency Call List." 4.0 INITIAL CONDITIONS 4.1 Unusual Event emergency conditions exist. 4.2 This procedure should be initiated as soon as possible after the initial classification and must be initiated within one hour of the initial classification. 5.0 PROCEDURE 5.1 Designee 5.1.1 Complete Section 1 of the incident report form (form EPIP-12, attached) using the information given by the Shift Supervisor. Examples of emergency response include: shut the unit dcwn, call in additional firefighters or secure doors against high winds. O
> a V
p' EPIP 2.3 Page 2
, 5.2 Security Lieutenant or Desianee l :
4 /
\~/ 5.2.1 Notify the Manitowoc County Dispatcher by telephone (tele-phone number listed on form EPIP-23, "Offsite Agency Emergency Call List"). Read Section 1 of the incident report form and ensure that the information is fully under-stood.
5.2.2 Notify Kewaunee County Dispatcher by telephone (telephone number listed on form EPIP-23, "Offsite Agency Emergency Call List"). Read Section 1 of the Incident Report Form and ensure that the information is fully understood. 5.2.3 Notify the State of Wisconsin Division of Emergency Govern-ment by telephone (telephone number listed on form EPIP-23, "Offsite Agency Energency Call List"). Read Section 1 of the Incident Report Form and ensure that the infcrmation is fully understood. 5.2.4 Pick up the NRC Operations Center, Bethesda, dedicated line. 5.2.5 When a response is heard, read Section 1 of the incident report form. [
\
j_s 5.2.6 If no response is received, contact the NRC Operations by (
; telephone (telephone number listed on form EPIP-23, "Offsite
(,_/ Agency Emergency Call List") and repeat Step 5.1.3. 5.2.7 Have the Shift Supervisor make an appropriate entry into the NRC Operations Center, Sethesda, phone log. 5.2.8 Attempt to contact the NRC resident inspector (telephone number listed on form EPIP-23, "Offsite Agency Emergency Call List"). This courtesy notificatica is to inform him of the unusual event. n
.v
1 EPIP 3.1 Mill 0R Revision 2 es 09-10-82
)
N/ ALERT - I!! MEDIATE ACTIONS 1.0 PURPOSE The purpose of this procedure is to provide a series of immediate actions and clear direction to adequately respond to events or conditions classi-fied as an Alert in accordance with EPIP 1.1, " Initial Classification." In this plant condition, the potential exists for limited releases of radioactivity in excess of Technical Specification limits. However, it is unlikely that an offsite hazard will be created. Limited plant evacuation of certain plant areas may become necessary. Prompt notification and followup information is to be given to Federal. State and local authorities although it is anticipated that no response by them is required. The technical support center may be activated as a center for communications, debriefing and meetings. Since a plant evacuation is not required, the only other center that might be activated would be the emergency support f center. k['~N g The Alert status will be maintained until an escalation to a Site or General (s_,/ Emergency occurs or a deescalation or closecut is made by informing offsite authorities, and by the completion of an Incident Report Form as contained in EPIP 3.3, " Alert - Offsite Agency !!otification." 2.0 REFERE!!CES 2.1 NUREG-0654, Revision 1, November, 1980. 3.0 PRECAUTIO!!S AND LIIIITATICflS 3.1 All actions and notifications should be appropriately logged. 3.2 Communication should be concise and accurate. 4.0 INITIAL CONDITIO!!S 4.1 EPIP 1.1, " Initial Classification," completed. 5.0 PROCEDURE 5.1 Shift Supervisor / Designee 5.1.1 Evacuate affected areas if necessary to protect personnel by implementation of EPIP 6.1, " Limited Plant Evacuation." v
f EPIP 3.1 Page 2
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(' ' 'l 5.1.2 Implement plant operating procedures to place the affected unit / units in a safe condition. 5.1.3 Perform Section 5.1 of EPIP 3.2, " Alert - Plant and Company Personnel Notification." 5.1.4 Designate an individual, such as the Duty Technical Advisor or Duty & Call Superintendent to perform Section 5.1, of EPIP 3.3, " Alert - Offsite Agency Notification." 5.1.5 Announce the nature and location of the emergency using the Gaitronics system. Make the announcemect twice. 5.1.6 Implement EPIP 11.0, "First Aid and Medical Care," as necessary. 5.1.7 Implement EPIP 10.1, "Firef ghting," as necessary. 5.1.8 Perform actions of the Plant Operations Manager (FOM) and the Technical Support Manager until properly relieved. 5.1.9 Notify the Energy Information Center (Ext. 246) and ask them
, to implement EPIP 6.4, " Energy Information Center Evacuation."
t,m 5.2 Operating Supervisor (\s) 5.2.1 Report to the control room. 5.2.2 If the Shift Supervisor is incapacitated, assume the respon-sibility and authority of the shift Supervisor (until relieved by a qualified individual) and coordinate the plant response as outlined in Section 5.1. 5.3 Duty Technical Advisor 5.3.1 Report to the control room to provide advice to the Technical Support Manager and Shift Supervisor. 5.3.2 Establish a communication link using the dedicated line with the technical support center as soon as practicable. 5.4 Security Lieutenant 5.4.1 Implement EPIP 9.1, " Security," as necessary. 5.4.2 Report to the control room to obtain a completed incident report form. 5.4.3 Implement Section 5.2 of EPIP 3.3. " Alert - Offsite Agency
-~ Notification" as directed.
._)
f 4 EPIP 3.1 Page 3 7 (J) 5.5 Duty & Call Superintendent 5.5.1 Report to the control room or the technical support center as required depending upon the availability of other senicr management personnel. If other senior management are unavailable, report to the technical support center. 5.5.2 Perform a detailed evaluation of the plant condition using EPIP 1.1, " Initial Classification," EPIP 1.2, " Plant Status," EPIP 1.8, " Emergency Offsite Dose Estimation," and EPIP 1.5,
" Protective Action Evaluation."
5.5.3 Assume role of Plant Operations Manager as necessary. 5.5.4 Assure completion of EPIP 3.3, " Alert - Offsite Agency Notification" 5.5.5 Reclassify emergency as necessary. Coordinate this duty with PCM when he becomes available. 5.6 Plant Operations Manager (POM) (Superintendent - Operations) g 5.6.1 Report to the technical support center. s s/ \ 5.6.2 Escalate to a more severe classification if necessary by (s_,/ implementation of EPIP 4.1, " Site Emergency - Immediate Actions," or EPIP 5.1, " General Emergency - Immediate Actions." Complete Section 1 of form EPIP-12, " Alert Incident Report Form." 5.6.3 Provide recommendations of any required protective actions for the public to State and local authorities if the Emer-gency Support Manager is unavailable. 5.6.4 Deescalate to a less severe classification if conditions no longer warrant the Alert classification and complete Section 1 of form EPIP-12, " Incident Report Form," attached to EPIP l 3.3, " Alert - Offsite Agency Notification." 5.6.5 Notify personnel notified in EPIP 3.2, " Alert - Plant and Company Personnel Notification." 5.6.6 Contact the persons and agencies notified in EPIP 3.3,
" Alert - Offsite Agency Notification," and provide the information contained in deescalation notification message using Section 1 of EPIP-12 attached to EPIP 3.3, " Alert -
Offsite Agency Notification." 5.6.7 Coordinate all control rocm, technical support center, and f3 security procedures. ,
\
EPIP 3.1 Page 4 (' ' ' ' / 5.6.8 Coordinate EPIP 6.1," Limited Plant Evacuation," if inple-mented. 5.6.9 Coordinate EPIP 8.1, " Personnel Assembly and Accountability," if implemented. 5.7 Site Manager (Hanager, Point Beach Nuclear Plant) 5.7.1 Report to the technical support center and assume overall responsibility for the emergency response and recovery operations. i 5.7.2 When the emergency support center is to be activated, report to the emergency support center and act as the Emergency Support !!anager until relieved. 5.8 Technical Suppcrt Manager (Superintendent - Technical Services) 5.8.1 Report to the technical support center. 5.8.2 Establish a communication link using the dedicated line with tF: control room as soon as practicable.
/
(-s 5.8.3 Determine the need for additional personnel. Implement g ) EPIP 3.2, " Alert-Plant and Company Personnel Notification," Ns/ as required. 5.9 Chemistry /HP Supervisor (Superintendent - Chemistry & Health Physics) 5.9.1 Report to the technical support center. 5.9.2 Implement EPIP 7.0, "CHP Radiological Response and Prepared-ness," as necessary. 5.9.3 Have Chemistry & Health Physics personnel report to their work station and establish a ccmmunication link to the technical support center. 5.10 Maintenance Supervisor (Superintendent - !!aintenance & Construction) ( l
- 5.10.1 Report to the technical support center.
5.10.2 Implement EPIP 12.2, " Personnel E.sposure and Search and Rescue Team," as necessary. 5.10.3 Have maintenance personnel report to an appropriate location for assignment. I s
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i l
- EPIP 3.1 I
1 Page 5 i 5.11 Desicnated Plant Supervisory Personnel (See Figure 5-4 of the Emergency Plan as to who is to report to the ; technical support center. This includes the off duty Technical i Advisors, Training Supervisor, I & C Supervisor, and Health Physics I
; Director if not assigned to the site boundary control center.)
5.11.1 Report to the technical support center. i i I ( l l i i r i e l l l
i s
!% e f EPIP 3.3 III!JOR Revision 1 09-10-82
(- kL-) ALERT - 0FFSITE AGENCY NOTIFICATION 1.0 PURPOSE The purpose of this procedure is to establish the initial offsite agency notification responsibilities in response to plant conditions classified as an Alert in accordance with EPIP 1.1, " Initial Classification." Necessary phone numbers are included in form EPIP-23, "Offsite Agency Emergency Call List."
2.0 REFERENCES
None i 3.0 PRECAUTI0flS AND LIMITATIONS 3.1 Obtain the name and title of the person being contacted prior to transmitting any information.
,- 3.2 If unable to contact an individual or agency, continue with the
(/ j notification of the other individuals or agencies and then attempt to I \,s' contact the persons or agencies who have not been notified. 3.3 All actions and notifications should be appropriately logged in form EPIP-23, "Offsite Agency Emergency Call List," or form EPIP-13 (attached), Sections 1, 2, and 3. i 4.0 INITIAL CONDITIONS 4.1 Alert emergency conditions exist. 4.2 This procedure should be initiated as soon as possible after the initial classification and must be initiated within one hour of the initial classification. 5.0 PROCEDURE 5.1 Desionee 5.1.1 Complete Section 1 of the incident report form (form EPIP-12, I I attached) using the information given by the Shift Supervisor. Examples of emergency response include: shut the unit down. call in additional firefighters, and secure the decrs against high wind.
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- - - . . , , - - - ---- - - , - .-.-,..n-.----
. .A EPIP 3.3 Page 2 (x_/ ) 5.2 Security Lieutenant or Designee ;
5.2.1 Pick up the NAWAS handset and make the following trans-mission: THIS IS POINT BEACH CALLING WARNING CENTER 2, !!ANITOWOC COUNTY, AND KEWAUNEE COUNTY. THIS IS POINT BEACH CALLING WARNING CENTER 2, MANITOWOC COUNTY AND KEWAUNEE COUNTY. NOTE: THE THREE CENTERS SHOULD RESPOND. NOTE ANY CENTERS NOT RESPONDING AND PROCEED WITH THE PROCEDURE. 5.2.2 Transmit Section 1 of the incident report form over the NAWAS system. Ensure that the three centers fully under-stand the transmission. 5.2.3 Contact by telephone, the centers (noted in Step 5.1.2 of this procedure) which were unable to be contacted over the , NAWAS system (phone numbers listed on EPIP-23, "offsite ( ,__ Agency Emergency Call List"). I i
\ ,,/ 5.2.4 Read Section 1 of the incident report form. Ensure that the information given is fully understcod.
5.2.5 Pick up the NRC Operations Center, Bethesda, dedicated line. When a response is heard, read Section 1 of the incident report form. 5.2.6 If no response is heard, contact the NRC Operations by telephone (telephone number listed on form EPIP-23, "Offsite Agency Emergency call List") and repeat the appli-cable portion of Step 5.1.2. 5.2.7 Have the Shift Supervisor make an appropriate entry into the NRC Operations Center, Bethesda, phone log. 5.2.8 Attempt to contact the NRC Resident Inspector (telephone number listed on EPIP-23, "Offsite Agency Emergency Call List"). Inform him of the Alert emergency condition. 5.2.9 Notify Kewaunee Nuclear Power Plant (telephone number listed on EPIP-23 "Offsite Agency Emergency Call List"). Inform them of the alert emergency condition.
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EPIP 4.1
!!INOR Revision 2 ,s 09-10-82 1 \
SITE E!!ERGEllCY - III!!EDIATE ACTICIIS 1.0 GEllERAL The purpose of this procedure is to provide a series of immediate actions and clear direction to adequately respond to events or conditions classi-fied as a Site Emergency in accordance with EPIP 1.1, " Initial Classification." Under the Site Emergency classification, there is a potential for offsite releases which could have an impact on the public to the extent that pro-tective actions would be required. Therefore, if not already accomplished, the plant will activate the technical support center, the onsite operations support center, the emergency support center, the site boundary control center, and possibly the emergency news center. Either limited plant or plant evacuation may become necessary. The initiation of a Site Emergency requires prompt notification to State and local authorities so that they may alert key personnel. [y r~'N The Site Emergency status will be maintained until an escalation to a ( ! General Emergency occurs, deescalation to a less severe emergency classifi-
cation occurs or a closecut it made by informing offsite authorities, and by the completion of an incident report form as contained in EPIP 4.3,
" Site Emergency - Offsite Agency Notification."
2.0 REFERENCES
None 3.0 PRECAUTIONS AND LI!!ITATIONS 3.1 All actions and notifications should be appropriately logged. 3.2 All communication should be concise and accurate. 4.0 INITIAL CONDITIO!!S 4.1 Site Emergency has been declared. T v
. ._-- - - - - . - - - - - - - - - . - - . - - - - . _ _ . ....- _ - - . - . . - _ _ - =_-
a i t l EPIP 4.1 ! j Page 2 4
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\v}
1 5.0 PROCEDURE i
! 5.1 shift Supervisor / Designee ,
t 5.1.1 Announce the nature and location of the emergency using the Gai-tronics system. !!ake the anncuncement at least twice. - l The announcement should be repeated periodically. Evacuate ! affected areas if necessary to protect personnel by implemen- l a tation of EPIP 6.1, " Limited Plant Evacuation " . ) 5.1.2 Implement plant operating procedures to place the affected > l unit / units in a safe condition. 5.1.3 Designate an individual, such as the Duty Technical Advisor i or Duty & Call Superintendent to perform Section 5.1 of I EPIP 4.3, " Site Emergency - Offsite Acency Motification." li I i 5.1.4 Implement EPIP 11.0, "First Aid and t!edical Care," as necessary. I 5.1.5 Implement EPIP 10.1, "Firefighting," as necessary. i i i f ~~s 5.1.6 Perform actions of the Plant Operations Manager until 4 I, ) properly relieved. 5.1.7 Notify the Energy Information Center (Ext. 246) and have them implement EPIP 6.4, " Energy Information Center Evacu-ation." 5.2 Operating Supervisor 5.2.1 Report to the control room. 5.2.2 If the Shift Supervisor is incapacitated, assume the respon-sibility and authority of the Shift Supervisor (until prcperly relieved by a qualified individual) and coordinate the plant response as outlined in Section 5.1 of this procedure. 5.3 Duty Technical Advisor , 5.3.1 Report to the control room to provide advice to the Technical . Support !!anager and the Shif t Supervisor. j 5.3.2 Establish a communication link using the dedicated line with the technical support center as soon as practicable. 5.4 Security Lieutenant
/' N s 5.4.1 Implement EPIP 9.1, " Security," as necessary.
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EPIP 4.1 Page 3
,n l i L.) 5.4.2 Report to the control room to obtain a completed incident report form.
5.4.3 Implement Section 5.2 of EPIP 3.3, " Alert - Offsite Agency , Notification." 5.5 Duty & Call Superintendent 5.5.1 Report to the control room or the technical support center. 5.5.2 Perform a detailed evaluation of the plant condition using EPIP 1.1, " Initial Classification," EPIP 1.2, " Plant Status," EPIP 1.8, " Emergency Offsite Dose Estimation," EPIP, 1.5
" Protective Action Evaluation," and other available informa-tion.
5.5.3 Assume role of Plant Operations Manager as necessaty. 5.5.4 Reclassify emergency as necessary. 5.5.5 Notify personnel notified in EPIP 4.2, " Site Emergency - Plant and Company Personnel Notification" of reclassifi-f,s cation. (( \
"'s // 5.5.6 Contact the persons and agencies notified in EPIP 4.3, " Site Emergency - Offsite Agency Notification," and provide the information contained in a reclassification notification f' message using Section 1 of form EPIP-12 attached to EPIP 4.3,
" Site Emergency - Offsite Agency Notification."
5.6 Plant Operations Manager (Superintendent - Operations) 5.6.1 Report to the technical support center. 5.6.2 Escalate to a General Emergency if necessary by implemen-tation of EPIP 5.1, " General Emergency - Immediate Actions." Complete Section 1 of form EPIP-12, " Incident Report Form." l 5.6.3 If the Emergency Support Manager is unavailable, provide recommendations of protective actions for the public to State and local authorities. 5.6.4 Deescalate to a less severe classification if conditions no longer warrant the Site Emergency classification and complete Section 1 of form EPIP-12, " Incident Report Form," attached to EPIP 4.3, " Site Emergency - Offsite Agency Notification." 5.6.5 Coordinate EPIP 6.0, " Evacuation," if implemented. (m' 5.6.6 Coordinate EPIF 8.1, "Fersonnel Assembly and Accountability," if implemented. 5.6.7 Coordinate control room, technical support center, onsite operations support center and security procedures.
EPIP 4.1 Page 4
5.7 Site flanager (!!anager - Point Beach Nuclear Plant) 5.7.1 Report to the technical support center and assume overall responsibility for the emergency response and recovery operations.
5.7.2 When the emergency support center is to be activated, report to the emergency support center and act as the Emergency support Manager until relieved. 5.8 Technical support !!anager (Superintendent - Technical Services) 5.8.1 Report to the technical support center. 5.8.2 Establish communication links using the dedicated lines with the control room, the emergency support center and the onsite operations support center as soon as practicable. 5.8.3 Assure completion of EPIP 4.3, " Site Emergency - Offsite Agency Notification." 5.9 Chemistry /HP Supervisor (Superintendent - Chemistry & Health Physics) f 5.9.1 Report to the technical support center. (f'~'/}
\.,
5.9.2 Implement EPIP 7.0, "CHP Radiological Response and Pre-paredness," as necessary. 5.9.3 Have Chemistry & Health Physics personnel report to the onsite operations support center and establish a ccmmuni-cation link to the technical support center. 5.10 !!aintenance Supervisor (Superintendent - !!aintenance & Construction) 5.10.1 Report to the technical support center. 5.10.2 Implement EPIP 12.2, " Personnel Exposure and Search and Rescue Team," as necessary. 5.10.3 Have !!aintenance personnel report to an appropriate location for assignment. 5.11 Emergency Support !!anager (Director, Nuclear Power Department) 5.11.1 Report to the emergency support center. 5.11.2 Act as liaison between plant personnel and offsite author-s ities. r i
\d
e EPIP 4.1 Page 5 (N)
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5.12 Designated Plant Supervisory Personnel (See Figure 5-5 of the Emergency Plan as to who is to report to the technical support center. This includes off-duty Technical Advisors, I & C Supervisor, Core Physics Coordinator, Training Supervisor, and the Maintenance Supervisor) . 5.12.1 Report to the technical support center. 5.12.2 If there is a plant evacuation, have personnel report to the onsite operations support center. 5.12.3 If the Site Emergency occurs outside of normal working hours, have personnel report te the onsite operations support center by way of the site boundary control center. 5.12.4 If the Site Emergency occurs during normal working hours and there is not a plant evacuation, have personnel report to an appropriate location. 5.13 HP Director (Health Physicist) f7 -- 5.13.1 Report to the site boundary control center.
\_- 5.13.2 Form an offsite survey team consisting of qualified Chemistry & Health Physics personnel at the site boundary control center.
5.13.3 Establish a communication link to the emergency support center using the dedicated telephone line as soon as prac-ticable. 5.14 Designated Company Personnel (See Figure 5-5 of the Emergency Plan as to who is to report to the emergency support center. This includes the Rad / Waste Manager, radiation survey communicator, and offsite agency communicator. 5.14.1 Report to the emergency support center 5.15 Emergency News Center Director 5.15.1 Report to the emergency news center if it is established. Otherwise report to the emergency support center. 5.15.2 Coordinate and provide periodic press updates. 5.15.3 If required, prepare and coordinate the operation of the
N Emergency News Center in accordance with EPIP 14.0, " Crisis s
v) Communications."
4 i e b ? * } EPIP 4.1 1 Page 6 [ i ; 5.16 System Analysis and Procedural Support Coordinator ] (Superintendent, Reactor Engineering, Nuclear Engineering Section) l Report to the technical support center.
- I I
5.17 Designated Company Personnel ! 'l I i l (See Figure 5-5 of the Emergency Plan as to who is to report to the ! corporate headquarters. This includes the Administrative & Logistics l l !!anager, Design, Construction & Planning !!anager, Radwaste Technical l Support Coordinator, and the Licensing Support Coordinator.) 5.17.1 Report to the corporate headquarters. j l . I f 1 l 5 lCill> , l t l l I t I i n h 9 . s
~
- I EPIP 4.3
!!Ill0R Revision 1 09-10-32 SITE E!!ERGEllCY - 0FFSITE AGE!!CY !!OTIFICATIO!! ,
1.0 PURFOSE The purpose of this procedure is to establish the initial offsite agency notification responsibilities for response to plant conditions classified as a Site Emergency in accordance with EPIP 1.1, " Initial Classification."
!Iecessary telephone numbers are included in form EPIP-23, "Offsite Agency Emergency Call List."
2.0 REFERE! ICES tione 3.0 PRECAUTIO!!S AllD LI!!ITATICflS 3.1 Obtain the name and title of the person being contacted prior to transraitting any information. )
/
, 3.2 If unable to contact an individual or agency, continue with the notification of the other individuals or agencies and then attempt to ,
contact the persons or agencies who have not been notified. ' 3.3 All actions and notifications should be apprcpriately logged in form EPIP-23, "Offsite Emergency Call List," and form EPIP-14 (attached), Sections 1, 2, and 3. 4.0 IllITIAL C0!!DITI0tl5 4.1 Site Emergency conditions exist. 4.2 This procedure must be initiated within 15 minutes of the initial classificatien as a Site Emergency. 5.0 PROCECURE 3.1 Designee A 5.1.1 Complete Section 1 of the incident report form (form EPIP-12, j, attached) using the information supplied by the Shift Super-visor. E. samples of emergency response include unit shutdown and limited plant evacuation. I l
EPIP 4.3 Page 2 s 5.2 Security Lieutenant or Designee j
\' / 5.2.1 Pick up the IIAWAS handset and make the following transmission:
THIS IS POINT BEACH CALLIllG WARflING CEllTER 2, STATE PATROL IN FO!!D DU LAC, !!ANITOWOC COU!ITY, AND KEWAUNEE COUNTY. THIS IS POItiT BEACH CALLIllG WARNING CE!!TER 2, STATE PATROL IN FO!!D DU LAC, MANITOWOC COUNTY, AllD KEWAUNEE COUNTY. NOTE: THE FOUR CENTERS SHOULD RESPOND. NOTE A!!Y CEllTERS IIOT RESPONDING AND PROCEED WITH THE PROCEDURE. fl0TE: Ill THE EVENT OF AN EXERCISE OR DRILL, THE ABOVE
!!ESSAGE !!UST BEGIN AND END WITH THE PHRASE "THIS IS A DRILL, REPEAT, THIS IS A DRILL."
5.2.2 Transmit Section 1 of the incident report form over the NAWAS system. Ensure that the four centers fully understand the transmission. ( 5.2.3 Contact by telephone, the centers (noted in Step 5.1.4 of this procedure) which are unable to be contracted over the
- NAWAS system (telephone numbers listed on form EPIP-23,
)
s ,,/ "Offsite Agency Emergency Call List"). 5.2.4 Read Section 1 of the incident report form. Ensure that the information given is fully understood. 5.2.5 Pick up the NRC Operations Center, Bethesda, dedicated line. When a response is heard, read Section 1 of the incident report form. 5.2.6 If no response is heard, contact the NRC Operaticns by telephone (telephone number listed on form EPIP-23, "Offsite Agency Emergency Call List") and repeat the applicaole portion of Step 5.1.2. 5.2.7 Have the Shift Supervisor make an appropriate entry into the NRC Operations Center, Bethesda, phone log. 5.2.8 Attempt to notify the NRC Resident Inspector (telephone number listed on form EPIP-23, "Offsite Agency Emergency Call List"). Inform him of the Site Emergency 5.3 Designee B 5.3.1 Complete Section 1 of the incident report fora (form EPIP-12) using the information supplied by the Shift Supervisor. [ 'N Examples of emergency response include unit shutdown and
\s_fI limited plant evacuation.
l l I
i EPIP 4.3 ! Page 3 ,
?
J i d 5.3.2 Determine with the Site !!anager or designated representative ; which of the additional agencies listed on form EPIP-23, !
"Offsite Agency Emergency Call List," should be notified at !
l this time. i I Contact, by telephone the agencies identified above and read
- 5.3.3
- Section 1 of the incident report form. l I
i ! 5.3.4 Ensure that the information given is fully understood. j i j l , l h i e 1 t l ! f I I i i r ! ! I } l l ) ! I' ! j . , x ! i i i I l I l ; l I r, j i I i l ! I i O i d 4 t
,,,,wm,_-am, m _mm. r--a,_w m p,r ym m w-
A EPIP 5.1
!!I?!OR Revision 2
--x 09-10-82
's GEllERAL E!!ERGE!!CY - I!UIEDIATE ACTIO!!S 1.0 PURPOSE The purpose of this procedure is to provide a series of immediate actions and clear direction to adequately respond to events or conditions classi-fied as a General Emergency in accordance with EPIP 1.1, " Initial Classification."
Under this classification, there is a greater potential for offsite releases which could have an impact en the public to the extent that protective actions would be required. Therefore, if not already accomp_ished, the plant will activate the technical support center, the onsite operations support center, the emergency support center, the site boundary control center, and the emergency news center. Either plant or limited plant evacuations may become necessary. The initiation of a General Emergency requires prompt notification to State j and local authorities so that they may activate their emergency control (/,_ centers and dispatch key personnel.
'~
The General Emergency status will be maintained until a deescalation to a less severe emergency classification occurs or a closecut is made by in-forming offsite authorities, and by the completion of an incident report form as contained in EPIP 5.3, " General Emergency - Offsite Agency llotifi-cation." 2.0 REFEREllCES 2.1 !!UREG-06 54, Revision 1, ?!ovember , 1980. 3.0 PRECAUTIotlS Af!D LIl!ITATIO!!S 3.1 All actions and notifications should be apprcpriately logged. 3.2 All communications shculd be concise and accurate. 4.0 I!!ITI AL CO!!DITIOfl5 4.1 EPIP 1.1, " Initial Classification," ccmpleted. 1
,~ \_/
4 A EPIP 5.1 Page 2 5.0 PROCEDURE 5.1 shift Supervisor / Designee 5.1.1 Announce the nature and location of the emergency using the Gai-tronics system. Make the announcement at least twice. The announcement should be repeated periodically. Sound the evacuation alarm if a plant evacuation is warranted. Evacuate affected areas if necessary by implementation of EPIP 6.0,
" Evacuation."
5.1.2 Implement plant operating procedures as required to place the affected unit / units into a safe condition. 5.1.3 Designate an individual, such as the Duty Technical Advisor or Duty & Call Superintendent, to perform Section 5.1 of EPIP 5.3, " General Emergency - Offsite Agency Notification" 5.1.4 Implement EPIP 11.0, "First Aid and Medical Care," as necessary. 5.1.5 Implement EPIP 10.1, "Firefighting," as necessary. 5.1.6 Perform actions of the Plant Operations Manager, until
/ 3 properly relieved.
a 5.1.7 Notify the energy information center and have them implement EPIP 6.4, " Energy Information Center Evacuation." 5.2 Operating Supervisor 5.2.1 Report to the contrcl room. 5.2.2 If the Shift Supervisor is incapacitated, assume the respon-sibility and authority of the Shift Supervisor (until properly relieved by a qualified individual) and coordinate the plant response as outlined in Section 5.1. 5.3 Duty Technical Advisor 1 5.5.1 Report to the control room to provide advice to the Technical Support Manager and the Shift Supervisor. 5.3.2 Establish a communication link using the dedicated line with i the technical support center as soon as practicable. l l 5.4 Security Lieutenant 5.4.1 Implement EPIP 9.1, " Security," as necessary. (.g ) 5.4.2 Report to the centrol room to obtain a completed incident d report form. 1 5.4.3 Implement Section 5.2 of EPIP 3.3, " Alert - Offsite Agency Notification." I
a A EPIP 5.1 Page 3 x/s 5.5 Duty & Call Superintendent 5.5.1 Report to the control room or the technical support center. 5.5.2 Assume role of Plant Operations IIanager (PO!!) as necessary. 5.5.3 Perform a detailed evaluation of the plant condition using EPIP 1.1, " Initial Classification," EPIP 1.2, " Plant Status," EPIP 1.8, " Emergency Offsite Dose Estimation," EPIP 1.5,
" Protective Action Evaluation," and other available informa-tion.
5.5.4 Reclassify emergency as necessary. Coordinate this duty with the POM when he becomes available. 5.5.5 Notify personnel listed in EPIP 5.2, " General Emergency - Plant and Company Personnel Notification" of reclassification. 5.5.6 Contact the persons and agencies listed in EPIP 5.3, " General Emergency - Offsite Agency Notification," and provide the information contained in a reclassification notification message using Section 1 of form EPIP-12 attached to EPIP
. 5.3, " General Emergency - Offsite Agency Notification."
([ t 5.6 Plant Operations Manager (Superintendent - Operations) y ,
)
5.6.1 Report to the technical support center. 5.6.2 Coordinate EPIP 6.0, " Evacuation," if implemented. 5.6.3 Coordinate EPIP 8.1, " Personnel Assembly and Accountability," if implemented. 5.6.4 Deescalate to a less severe clacs if conditicns no longer warrant the General Emergency classification and complete Section 1 of form EPIP-12, " Incident Report Form" attached to EPIP 5.3, " General Emergency - Offsite Agency Motification." l 5.6.5 Coordinate control room, technical support center, onsite operations support center and security procedures. 5.7 Site !!anager (IIanager - Point Beach Nuclear Plant) 5.7.1 Report to the technical support center and assume overall responsibility for the emergency response and recover; operations. 5.7.2 When the emergency support center is to be activated, report __ to the emergency support center and act as the Emergency support flanager until relieved. (
r A EPIP 5.1 Page 4 s- 5.8 Technical Support Itanager (Superintendent - Technical Services) 5.8.1 Report to the technical support center. 5.8.2 Establish communication links using the dedicated lines with the control room, the emergency support center, and the onsite operations support center as soon as possib3e. 5.8.3 Assure completion of EPIP 5.3, " General Emergency - Offsite Agency Notification." 5.8.4 If the acting Emergency Support Ilanager, provida recommenda-tions of protective actions for the public to State and local authorities per EPIP 1.5. " Protective Action Guides." 5.9 Chemistry /HP Supervisor (Superintendent - Chemistry & Health Physics) 5.9.1 Report to the technical support center. 5.9.2 Implement EPIP 7.0, "CHP Radiological Response and Pre-paredness," as necessary. f . 5.9.3 Have Chemistry & Health Physics personnel report to the
', onsite operations support center and establish a communi-((,7 ) cation link to the technical support center using the dedicated line.
5.10 !!aintenance Supervisor (Superintendent - ?!aintenance & Construction) 5.10.1 Report to the technical support center. 5.10.2 Implement EPIP 12.2, " Personnel Exposure and Search and Rescue Team," as necessary. 5.10.3 Have maintenance personnel report to an appropriate location for assignment. 5.11 Emergency Support !!anager (Director, Muclear Power Departmentl l 5.11.1 Report to the emergency support center. 5.11.2 Act as liaison between plant and offsite authorities. 5.11.3 Provide reccmmendations of protective actions for the public l to State and local authorities per EPIP 1.5, " Protective Action Guides." 5.12 Designated Flant Supervisory Personnel I i ( ,) (See Figure 5-6 of the Emergency Plan as to who is to report to the technical support center. This includes the !!aintenance Supervisor , the off-duty Technical Advisors, the I & C Supervisor, the Core Physics Coordinator, the Training Supervisor and the Shift Support Coordinator.)
J' EPIP 5.1 Page 5 i ( 5.12.1 Report to the technical support center. 5.12.2 If the General Emergency occurs outside of regular working hours, have personnel report to the site boundary control center on their way to the operations support center. 5.12.3 If the General Emergency occurs during regular working hours and there is a plant evacuation, have personnel report to the operations support center. 5.12.4 If the General Emergency occurs during regular working hours and there is not a plant evacuation, have personnel report l to an appropriate location. 5.13 HP Director (Health Physicist) 5.13.1 Report to the site boundary control center. 5.13.2 Form an offsite survey team consisting of qualified Chemistry & Health Physics personnel at the site boundary control center.
, 5.13.3 Establish a communication link to the emergency support
('[~^ ; center using the dedicated telephone line as soon as
,' possible.
5.14 Designated Company Personnel (See Figure 5-6 of the Emergency Plan as to who is.to repott to the emergency support center This includes the Rad / Waste !!anager, the radiation survey communicator, and the offsite agency communicator.) I 5.14.1 Report tc the emergency support center. 5.15 Emergency flews Center Director 5.15.1 Report to the emergency news center and assume responsi-bility for release of information about the emergency 5.15.2 Assure prcper communications exist between the Emergency news center and the emergency support center. 5.15.3 Prepare and coordinate the cperation of the emergency news center in accordance with EPIP 14.0, " Crisis Communications." 5.16 System Analysis and Procedural Support Coordinator (Superintendent, Reactor Engineering, !!uclear Engineering Section)
,- Report to the technical support center.
i s.- i.17 Designated Company Personnel (See Figure 5-6 of the Emergency Plan as to who is to report to the c.orporate headquarters. This includes the Design, Construction &
e J EPIP 5.1 l Page 6 ! l 1 Planning !!anager, the Radwaste Technical support Coordinator, the Licensing Suppert Coordinator, the Administrative & Logistics llanager, the Utility Engineering Director, the Architect Engineer Director, the Director of NSS Supply, and the Director of Quality Control.) l 5.17.1 Report to the corporate headquarters. I 1 l l r i
. . - . - . . . ~ - - - . . . . - - . - . - .
- - - . - . - - - . . - - .. _~ -- -
I 1 j EPIP 5.3
!!Ill0R Revision 1 09-10-82 i GE!!ERAL E!!ERGEtICY - 0FFSITE AGEllCY !!OTIFICATIO!!
i f 1.0 PURPOSE Tha purpose of this procedure is to establish the initial effsite agency notification responsibilities for response to plant conditions classified { l as a General Emergency in accordance with EPIP 1.1, " Initial Classification." ! tiecessary phone numbers are included in form EPIP-23, "offsite Agency l Emergency Call List." j ! 2.0 REFERE! ICES I
! i fione t I
3.0 PRECAUTIOflS AflD LIl!ITATIoriS ! i 3.1 Obtain the name and title of the person being contacted prior to (
- transmitting any information. [
t . I / , 3.2 If unable to contact an individual or agency, continue with the ; I notification of the other individuals or agencies and then attempt to : ( contact the persons or agencies who have not been notified. , t 3.3 All actions and notifications should be appropriately logged in form ! EPIP-23, "Offsite Agency Emergency Call List." ar.d form EPIP-1: (attached), Sections 1, 2, and 3. [ I 4.0 ItIITIAL C0f1DITIOf!S : l 4.1 General Emergency conditions exist. l 4.2 This procedure must be initiated within 15 minutes of the initial l classification as a General Emergency. 3.0 PROCEDURE j 5.1 Desionee A 5.1.1 Complete Section 1 of the incident report form (form EPIP-12, l attached) using the information supplied by the Shift Super- i visor. ' e t _ _, , w. _wn--,.--+
EPIP 5.3 Page 2
- 9 5.2 Shift Lieutenant or Designee 5.2.1 Pick up the NAWAS handset and make the following trans-mission
THIS IS POINT SEACH CALLING WARNIIIG CE!!TER 2, STATE PATROL IN FO!!D DU LAC, !!ANITOWOC COUNT'l AND KEWAUNEE COUNTY. THIS IS POINT BEACH CALLING WARNI!IG CENTER 2, STATE PATROL IN FOND DU LAC, IIANITOWOC COUNTY AND KEWAUMEE COUNTY. NOTE: THE FOUR CEllTERS SHOULD RESPO!ID. NOTE AN'l CENTERS NOT RESPONDIllG AND PROCEED WITH THE PROCEDURE. l t NOTE: IN THE EVENT OF AN EX"RCISE OR DRILL, THE AE0VE I !!ESSAGE !!UST BEGI!! AND END WITH THE PHRASE "THIS IS A DRILL, REPEAT, THIS IS A DRILL." 5.2.2 Transmit Section 1 of the incident report form over the NAWAS system. Ensure that the four centers fully understood
, the transmission.
5.2.3 Contact by telephone, the centers (noted in Step 5.1.4 of this procedure) which were unable to be contacted over the flAWAS system (phone numbers listed in form EPIP-23, "Offsite Agency Emergency Call List"). 5.2.4 Read Section 1 of the incident report form. Ensure that the information given is fully understood. l 5.2.5 Pick up the NRC Operations Center, Bethesda, dedicated line. When a response is heard, read Secticn I of the incident report form. i 5.2.6 If no response is heard, contact the NRC Operations Center, l Bethesda, by telephone (telephone number listed on form I EPIP-23, "Offsite Agency Emergenc'; Call List") and repeat I the applicable portion of Step 5.1.6. j 5.2.' Have the Shift Supervisor make an apprcpriate entry into the NRC Operations Center, Sethesda, phone log. 5.2.3 Attempt to notify the tiRC Resident Inspector (phcne number i listed in form EPIP-23, "Offsite Agency Emergency Call l List"). Inform him of the General Emercenc'. l 5.2.10 Motify the Kewaunee ?luclear Pcwer Plant. I 5.3 Designee B l 5.3.1 Complete Section 1 of the incident report form (form EPIP-12)
- using the information supplied by the Shift Supervisor ,
l l l
\
EPIP 5.3 , Page 3 ! 5.3.2 Determine with the site !!anager or designated representative which of the additional agencies listed en form EPIP-22, "offsite Agency Emergency Call List," should be notified at this time. l 5.3.3 Contact by telephone, the agencies identified above and read section 1 of the incident report form. 5.3.4 Ensure that the information given is fully understeed. 5.3.5 Complete form EPIP-16 (attached). 5.3.6 Form EPIP-16 will be used as a basis for follow-up messages to offsite technical personnel such as NSSS vendors and corporate engineering staff. i i
/
E O
a
- tPIP o.a IIINOR
, Revision 0 09-10-82 TECHNICAL SUPPORT CENTER & OPERATIONS SUPPORT CENTER ACTIVATION 1.0 PURPOSE 1.1 To provide instructions for the activation of the technical support center after the declaration of an alert, site emergency or general emergency.
1.2 To outline the technical support center ventilation system operation
- in the event of high airborne activity 1.3 Operation of the technical support center emergency pouer suppl'2 is also a part of this precedure.
2.0 ACTIVATION OF TECHNICAL SUPPORT CENTER 2.1 Set up 10 tables as shown on Attachment 6.5-1. They may be obtained from the rooms in the adjacent operations support center and health physics areas of the technical support center. ( 2.2 Install phones from the technical support center storage cabinets in the appropriate areas as shown on At'.achment 6.5-1. 2.3 Confirm that all phones operate by noting if dial tone is present when the receiver is lifted. Confirn that the numbers listed en the face of the phone matches the number on the wall jacks. 2.4 Distribute paper and pencils to each table. 2.5 Distribute a copy of the EPIP's to the table in frcnt of the black-board and the table near the dose plotting map (see Attachment 6.5-1). 2.6 Obtain a copy of each of the following manuals frca the front office area and bring them to the technical support center. They ma', be obtained frcm the office of the !!anager, General Superintendent, or the training offices. 2.6.1 Operating procedures. 2.6.2 Emergency operating procedures. 2.7 Shift the ventilation system from the normal to the emergency opera-ting made by implementing Section 4.0 2.6 Date and time the current charts en the safety parameter chart re-corders in the technical suppcrt center.
- EPIP 6.5 Page 2 3.0 DATA LCGGER OPERATICM 3.1 Push the start button on the data logger. Enter the correct date and time on the printout from the data logger. The designations for each of the 37 channels are contained in Attachment 6.5-2.
3.2 The conversion of incore thermocouple MV to degrees Fahrenheit with the reference junction at 160 is acccmplished by use of the incore thermocouple table (see Attachment 6.5-3). 3.3 The conversion of radiological monitoring point volts to mR/hr or R/hr is accomplished by use of the conversion tables (see Attachments 6.5-4, 6.5-5 and 6.5-6). 4.0 EMER3EMCY VENTILATICM SYSTEM 4.1 The technical support center heating and ventilating system has a normal and emergency operating mode. Under normal cperation the air intake is from the outside air vent on the east wall of the technical l support center building. The intake air under normal operation is essentially unfiltered. In the emergency mode, there are two optional air ints.ke locations.
, one is adjacent to the normal intake on the east wall of the techni-cal support center building and the other is on the north wall of the Unit 2 turbine halll.
4.2 To shift the heating, ventilating anc air conditioning system frcm the normal to emergency mode: i 4.2.1 Turn the autoicff/ occupied switch on Panel H-1 to the occu-l pied position. See Attachment 6.5-7 for location of Panel , M-1. i 4.2.2 Turn the normal / emergency control switch on Panel M-1 to the emergency position. 4.2.3 Select the north or south (east) emergency in ake depending on meteorological conditions. Select the upvind intake duct. 5.0 IECHMICAL SUFFGh! CENTER AUS:ILIARY AIR CCMEITIOMING 5.1 Turn en compressor CH2 cn the west wall of El. 12.5' of the technical support center building (see Attachment 6.5-7). l 5.2 Turn en air handling unit AHU2 cn the technical support center building I rccm north wall (see Attachment 6.5-1). i
- - - _ . , - _ , ,-- , - - . , - - , . - ,- - ~ -
EPIP 6.5
. Page 3 6.0 E!!ERGEMC7 POWER 6.1 The power source for the technical support center in 1801 450 V. See Attachment 6.5-8 for the main disconnect location.
6.2 The emerger.cy power source is not operational at this time. i l l l i ( ( i l i l \
j ATTACHME:.T 6.5-1
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[\ 3 14 mV Active 29) RTD ) 15 mV Active 36) Junction 3cx "3" ) 16 *F Active Uni: 1 Reference RID Junc :cn Scx "A" i 17 F Active Unit 1 Reference RTD Junction Sex "3"
; 18 *F Active Unit 2 Reference RTD Junction. 5cx "A" i 19 *F Active Unit 2 Reference RTD Junction Ecx "3" i 20 ;pm Active Unit 1 Auxiliary Feed Flow "A" SG
- 21 gpm Active Unit i Auxiliary Feed Flow "3" SG 22 gpm Active Unit 1 SI Flow Train "A" 23 gpm Active Unit 1 SI Flow Train "B" 24 ft Unit 1 Containment Sump Level 25 ---
Unit 1 Containment Hic.h F.anc,e RMS 26 V Active Unit 1 Containment Purge Stack RMS-II Ch 43 27 gpm Unit 2 Auxiliary Feed Flcw "A" SG 23 gpm Unit 2 Auxiliary Feed Ficw "3" SG 29 gpm Active Unit 2 SI Flow Train "A"
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31 ft Unit 2 Centainment St=c Level . 32 --- Uni 2 Containment High Range RMS ( 33 V Active Unit 2 Containment Purge Stack RMS-II Ch e4 l 34 V Active Drumming Area 7ent Stack RMS-II ch e2
- 35 V Active Combined Area 7en
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ATTACHMENT 6.5-4 I O DRUMMING AREA VENT STACK R*4S-II CH #2 AND l + COMBINED AIR EJECTOR DISCHARGE RMS-II CH #5 I VOLTAGE TO R/HR CONVERSION TABLE l RANGE 1 to 10' R/HR I l i l Volts Units R/hr I i 0. .001 ! 0.1 .001.35 l r i O.2 .001.847 l O.3 .002.511 I l' 0.4 .003.414 l 0.5 .004.641 1 0.6 .006.309 ( 0.7 .008.576 ! I \ 0.8 .011.659 0.9 .015.848 .
- 1. .021.544 1.1 .029.286 l.2 .039.810 1.3 .054.116 i 1.4 .073.564 j 1.5 .100 !
1.6 .135.935 l.7 .184.794 1.8 .251.18S 1.9 .341.454
- 2. .464.158 ,
2.1 .630.957 2.2 .857.695 2.3 1.165.914 2.4 1.584.893 ; 2.5 2.154.434 2.6 2.928.644 2.7 3.981.071 a 2.9 5.411.695 l 2.9 7.356.422
- 3.
- 10.000 9
_. __,-c...
-v,- - r-
~
i ATTACHMENT 6. 5-5 i 1
. i i i l
@ l UNIT 1 RMS-II CH u3 & UNIT 2 RMS-II CH d4
; CCNTAINMENT PURGE STACKS .
I t VOLTAGE TO R/HR CONVERSION TABLES RANGE 10 ' TO 10' R/HR 1 i Volts Units - R/HR I l j 0. 0.1 '
- 0.1 .135 l 0.2 .184 1
0.3 .251 t 0.4 .341 ) 0.5 .464 ! 0.6 .630 j 0.7 .857 I i 0.8 1.165 I i 0.9 1.584
- 1. 2.154 j l.1 2.928 i 1.2 3.931 !
1.3 5.411 l 1.4 7.356 , 1.5 10. ! l.6 13.593 l 1.7 18.478 l 25.118 1.8 l.9 34.145
- 2. 4G.415 l 2.1 63.095 .
2.2 85.769 , 2.3 116.591 2.4 158.489 2.5 215.443 2.6 292.864 2.7 398.107 2.8 541.169 2.9 735.642
- 3. 1000.
h l t
- - - - _ . - . _. .._w,-,--. _ _ _ . . . -,,,
._m_.
* . ATTACHMENT 6 .5-6
. AUXILIARY BUILDING VENT STACK RMS-II CH #1 &
i GAS STRIPPER BUILDING VENT STACK RMS-II CH *2 VOLTAGE TO R/HR CONVERSION TABLE RANGE 10-' TO 10" R/HR Volts Units - R/HR
- 0. 0.01 0.1 .013 l 0.2 .018 l i 0.3 .025 l O.4 .034 l O.5 .046 l j 0.6 .063 l
! 0.7 .085 I 0.8 .116 O.9 .158
- 1. .215 !
j 1.1 .292 4 1.2 .398 ! 1.3 .541 ( l.4 .735 ; 1.5 1. I i 1.6 1.35 l 1.7 1.847 1.8 2.511 1.9 3.414 2, 4.641 2.1 6.309 2.2 8.576 2.3 11.659 2.4 15.848 2.5 21.544 - l 2.6 29.286 , i 2.7 39.S10 t 2.8 54.116 [ 2.9 73.564 I
- 3. 100.
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- EFIP '.3.2 MINOR Pevision 4 09-10-S2 POST- ACCIDEIIT SAI!?LI!!G AI:D A?!AL' ISIS OF POTE?iTIALLY HIGH LEVEL REACIOR COOLA?lT 1.0 I?;TRODUCTIO?I 1.1 This prccedure outlines the steps necessary to collect, handle and analyze a high level reactor coclant sample which could result frcm gross fuel failure.
, 1.2 Eauicment List l Set un the following in the primar-. sample heca p icr te cellecting your sample:
1.2.1 The equipment detailed in Figures 2A and 2E. nth the e.xcepticn of the sample becs. - 1.2.2 Two magnetic stirrers and two 50 ml poly beakers and a 50 i ml beaker. I 1.2.3 A pH/mv meter, pH probe and chloride / reference elec-trodes. I j 1.2.4 A piston burette. ( 1.2.5 A lead brick wall of sufficient size to stcre residue frcm analysis. > 1.2.6 Chemical transfer pump. 1.2.7 Remote handling tools located in the c a b :.ne t celc th - hood. 1.2.8 Prepare a 1.0 liter side,rn flask with a ccrrectc; sized solid s tcppe r and rt6ce r septum ccer tr.e sider. 1.2.9 Gas siringe The follo'.:ing equipment is also necessar; for this pr:c s re and need to be made ready 1.2.10 The gas partitlene: for H._ analysis.
- EPIP 7.3.2 i Page 2 l . 1
- 1 1.2.11 The spec,ial cart used for transport of the sample bort.
i 2 Tools for ccnnecting and disconnecting sample bceb; j '. 2.12 i.e., 11/16" open end wrench or equivalent. 1.2.13 Remote valve turning tool. This tool as well as those mentioned in Step 1.2.12 are necessary for sampling and should be taken along and placed on the sample bomb transport cart. t
- The following reagents are also necessary and need to be prepared.
I l 1.2.14 0.111flaOH for boron. Obtain a supply from normal boren l analysis. 1.2.15 2.0i! HNO: for chloride analfsis. 3 l 1.2.16 IIanitol for boron analysis. 1.3 Preliminar'. Stecs Initials ( 1.3.1 Standardize the pH meter. 1.3.2 Organize as much of the equipment as possible behind lead brick walls in an arrangement that allows for unobstructed view of all operations with the aid of the convex mirror. (See Figure 2.) 1.3.3 Put new rubbet septum on gas bomb. 1.3.4 Conditicn and check out chloride / reference electrodes. 1.3.3 Check cut and prime the pisten burette aith fresh 0.1?! I!aCH solution. 1.3.6 Check out the cperaticn and calibration of the chemical transfer pump by pu.'cping chlorlde free delenized Jater thrcugh the pump. 2.0 PRELIMI:iARY E'!ALUAIIO'i I l !iOIE THIS EVALU.iTIU:I SHALL EE CCMPLETED FRIOR IO AliY ATIE!!PI IO EliTEE c, .c., c.,-...,
. ..IL U 7. m..~_ 2. .c . .1. r i.n r~ a . IU v: n.u n nr.ec, a n t . u. l :
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2 h.-t a. li ..s. ,.,.- 1. c,. n,. .i. cu 5 A!!?LE U?IDER EI!ERGE: ICY COI;DITIC!IS . l
- - -._-. _ . - . . . - = - - - - . - - . .--.- - -._. .-
l l l * ! l
' EPIP 7.3.2 !
Fage 3 J , j 2.1 Possible Indication of Fuel Damage Initials i Some or all of the following would be- present if fuel { damage had occurred: I 2 2.1.1 The letdown radiation monitor (R9) would be unusually high or offscale. 2 l ! 2.1.2 The containment radiation monitors (R11 and R12) l would be unusually high or offscale. i \ 2.1.3 The containment area mcnitors (R2 and R7) would l l be reading unusually high or offscale. : (
- 2.1.4 The auxiliary building stack monitor (R14) uculd
^
I ! show a significant increase due to auxiliary l buildina. airborne activit from the letdcwn and charging pump areas. , ! 2.1.5 Evaluation of Sample Room Conditiens 1 ! a. The sample rocm area monitor (R6) and l ! charging pump area monitor (R4) would give - an indication of conditions in the auxiliary l i building and sample room. l l
- b. After evaluation of the radiation monitoring i
system readouts, Health Physics will determine . j what airborne and radiation surveys would be l l appropriate before auxiliarv. buildina. entrv.. l I !
- c. Verife the reculrements tor aux;.liary buildinc sample room entry, i.e., (1) RWP requirements, ,
(2) clothing requirements, (3) respiratory i requirements, and (4) dosinetry requirements including extremity dose monitoring requirements, ! and (5) health physics coverage requirements ; including timekeeping. 3.0 REACICR CCOLAIII SA:!PLI!!G PROCEDURE
!!OTE : THIS PROCEDURE SHALL !!OT EE I!iITIATED L"i!IL THE EVALUATICM5 DIS- !
CUSSED III SECTIO!! 2.0 HAVE BEE!! CCI!?LETED A::D REVIEWED ET DUTT s ( CALL SUPERI!!TE!!DE!II (CCORDI?!ATOR), DUTT HEALTH PHTSICS ! SUPERVISIC?i AIID THE DUTT SHIFT SUPERVISCF Arid THEIE APPR07AL l HAS EEE!I GRA JIED . l 3.1 Collecting a Pressurized Sample (Refer to Figure 1) Initials [ r
- IJOTE
- THE FOLLCNI?;G STEPS WILL EE ACCCI!?LISHED !EER THE DIRECTICTI 0F HEALTH FHTSICS SUFCr775I M A'iD 2iLi !
l 1 I G .a.c y r e v%p..c ' E
. .. . T .". .W. .cmAr m. .". ' ^^
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l
. EPIP 7.3.2 f Page 4 l 9 3.1.1 The following steps (a through f) must be accomplished before opening the incontainment sample isolation valve 955 (Step 3.1.2) and the ;
hot leg sample isolation valve 966C (Step 3.1.3). I t
- a. Verify that the demineralized water header pressure is appros:imately 100 to 120 psi. ,
NOTE: THIS STEP !!AY BE DELETED IF REACTOR , t
!1AKEUP WATER IS USED FOR THE FLUSH. i
- b. Proceed to the sample rocm and install the shielded sample bomb on the outside wall of ;
the sample room using the fittings provided. I i CAUTION: BEFORE RE!!O'/ING THE Si AGE LOCT CAPS i TO INSTALL THE E0?!E. OPE:I 7ALVES 939, 940 AND 921 TO RELIEVE 5YSTE;! PRESSURE. CLOSE VALVES 939, 940 AND 941. PLACE A WASTE EUCEET , DIRECTLY UNDER THE B0!!B . USE A PAFER TOWEL SHIELD A'ID RUBEER GLOVES WHEN REMOVING CAPS. After installing the bomb verify that the diminecalized water line is connected from - valve 945 to the demineralized water manifold. Open demineralized H2 O valves 945, 947, and 948 and check for lef:s en the bomb fittings. Shut valves 945, 947, and 948.
- c. Enter the sample rocm and close the fellowing valves on the sample panel.
- 1. 961C - Normal hot leg semple ccmb inlet ,
- 2. 964C - normal hot leg sample bomb cutlet. l l
- 3. 965C - ncrmal hot lea saTole brnass. l l
- 4. 968 - nornal hot leg return calce. .
4 I
- 5. 971 - normal hot leg sink sample valve.
l d. Open the following calves en t a sample cr+nel. 1 I i
- 1. 969A - sample systen purg to e clu.r e '
, control tank j
i i 1 i i
~~c -vr , aw , _ _ _ _ _ _ . , . , - -__
i I t . EPIP 7.3.2 Page 5 f I 9 2. 956C - normal hot leg sample supply valve. j 3. 990 - residual heat removal sample
- supply valve.
l l e. Open valve 938 (high level hot leg sample valve) located on the wall behind the sample panel,
- f. Leave the sample room and open the following valves on the sample room wall.
- 1. 939 - sample bomb inlet. (Wide Open)
-l
- 2. 940 - sample bcmb bypass. (Wide Open) l s
l 3. 941 - sample bomb outlet. (Wide Open) j l l HOTE: FOR DRILLS AND PRACIICE OPEN VALVE 941 ONLY ONE-QUARTER TURN f
- TO ELIMINATE N-16 GAMMAS. -
I h l 3.1.2 Open the incontainment hot leg sample isolation l l valve (valve 955) and the residual heat removal i sample isolation valve (valve 959) by means of l the switches located outside the No. 1 pipeway l for Unit 1 or No. 4 pipeway for Unit 2. l If the valve No. 955 will not open because of containment isolation, perform the follcwing ; steps (1 through 3). 1
- 1. Request that the Control Room reset the con-tainment isolation signal.
I
- 2. Turn the local control switch positions for j valves 551, 933, and 955 to the "clcse" ;
positloa ;
- 3. Turn the local control switch for valve j 955 to the "open" position. l I
NOTE: SECTION 3.1.2 HUST BE ACC0!!PLISHED BEFOR: ; SAFETY INJECTION RECIRCULATION HAS EEGUU. 3.1.3 Leave the area and request control room supervision to open the hot leg sample . isolation valve (966C). I I i till l1 i
-. ...---_---.i
l EPIP 7.3.2 ! Page 6 ( 3.1.4 Verify sanple f1cw by radiation level. l f I 3.1.5 After a recirc time of 30 minutes, return to the ! sample station and using the remote valve j ] j operating tool, fully open valves 9B and 9A and l BA and 8B. l i ; j a. Slowly and completel close valve 940. i l
- b. Leave the primary auxiliary building. l l
l NOTE: THE VALVE OPERATING TOOL SHOULD BE USED } I TO OPERATE ALL VALVES EXCEPT 945, 946, ; 947 AND 948 (FLUSH VALVES). i i After 15 additienal minutes, return to collect I 3.1.6 the sample. Close valves 9B and 9A and ther. ' valves SE and 8A using the remote valve ;
- operating tool. Make note of the sample l
! collection time. l i NOTE: DO NOT DISCONNECT THE SAMPLE BOMS UUTIL i SAMPLE FLOW IS SECURED AND THE DI FLUSH , i IS COMPLETE AS EVIDENCED BY REDUCTION IN n RADIATION LEVELS. I t
- 3.1.7 Request control room supervision to '
! immediately close the hot leg sample ' isolation valve 966C. ! NOTE: IT IS VERY IHFORTANT THAT THE HOT LEG SAMPLE ISOLATION VALVE 966C IS CLOSED l PRIOR TO STARTING THE DI FLUSH. WAIT FOR CONFIRMATION FROM THE COUTROL ROOM. ,
?
4.0 SAMFLE LINE FLUSHING i 4.1 Leave valve 939 open. and fully open valves 940 and 941 Open valves 945 and 946. Allow the lines to flush for at [ least 15 minutes. Do net remain in the area of the ! sample station during this flush , 4.2 After accut 15 ninutes return and measure radiation levels. If a chemistry & Health Physics Superviscr determines that the levels are satisfactory, close whitev valve 946 and using the remote valve tocl. cicse valve 919. Ihen open f valve 947 and valve 945 and allow about a 15-minute DI ! flush. L I {
- EPIP 7.3.2 Page 7 i l l
1 4.3 After abcut 15 minutes, close valves 940 and 941 with the I remote valve tool and then close valves 945, 947, and 948. Disconnect valve 945 from the demineralized water manifold and cap both ends. Disconnect the sample bomb frca the l I1 fittings using a paper towel to prevent spraying. Remove [ j the shielded sample bomb from its supp' ort. Remove excess ; j liquid from the top and bottom bomb fittings with a j syringe and dispose behind lead shielding. Replace the j Swagelok caps on the wall fittings and on the bomb. ( ! Transport the bomb, remote valve tool and wrenches to l l the chemistrv lab on a cart. I NOTE: AFTER DRILLS AND PRACTICE RUNS, RETURN ALL { { EQUIPMENT AND VALVE LINEUPS TO MORIIAL AS , FOLLOWS: } CLOSE VALVES: { 1. 966C - Centainment hot leg sample isolaticn f' i valve 1 961C - Normal hot leg sample bomb inlet
^
- 2. l
- 3. 964C - Normal hot leg sample bomb outlet ,
- 4. 965C - Normal hot leg sample bypass i
)
l 5. 971 - Normal hot leg sink sample valve { l ;
- 6. 938 - High level hot leg sample valve l l
- 7. 939 - High level sample bcmb inlet j i
- 8. 940 - High level sample bomb bypass i i
- 9. 941 - High level sample bcmb outlet P
- 10. 945, 946, 947, 945 - Demineralized water l flush valves i a
MOTE: DISCOMMECT VALVE 945 FROM THE DEMIMERALIZED l WATER lIANIFOLD. ADVISE COMTROL TO REDUCE DEMIMERALIZED WATER HEADER PRESSURE IC j MORMAL. , OPEH VALVES:
- 1. 956C - Normal hot leg sample supply valve e
O .
1 i i i I EPIP 7.3.2 i 1 l Page 8 i 4 F l i
- 2. 968 - Normal hot leg return valve f
j 3. 969A - Sample system purge to volume centrol ; tank i f 5.0 SEPARATION OF THE PRESSURIZED SAMPLE AND ANALYSIS OF THE GASECUS L AND LIOUID CO!IPONENT (Refer to Figures 2A and 2B)
- 5.1 Collecting the Gasecus Sample Frcm the Pressurized Sample .
j 5.1.1 Place the shielded sample bomb in the sample j holder in the primary sample heed. f
- 3.1.2 Connect the sample bomb to the shielded gas collection bcmb by means of the fittings !
! provided. Place lead bricks in the : l area of this ccnnection for shielding. i ; ! 5.1.3 Ccnnect the valve manifold to the oocesite end of ! , the sample bomb and verif'y that valve 11 en the 3 i manifold is open. ' l l 5.1.4 Make sure that the vacuum line is attached to {
- the gas collection bomb at the valve 1 location. !
l Open valves 1 and 2. Secure valve 3. Evacuate
~
t the gas bomb and ccnnecting lines. With vacuum I still on, secure valve 1. Secure vacuum. 5.1.5 Before proceeding, make sure no inleakage has i occurred into the gas bomb by cbserving the ! vacuum gauge reading. Using the remote valve j tool, fully open valves 9A and 98. Cpen valve l 8A one-quarter turn. Crack cpen valve SB and ,t control degassing by throttling valve 83. ; Allow the syste.? to degas fcr 5 minutes. l Check that valves 9A and 9E, SA and SE are , f fully open. Close valve 2. I i NOTE: OBSERVE THE VACUUM GAUGE. IT SHOULD RISE VERY SLOWLY. IF THE RISE IS TOO RAPID, CLOSE VALVE SE SLIGHTLY. RISE SHOULD EE l 5" HG/MIM. 5.2 Analysis of Gaseous Sample I t 5.2.1 Hydrogen ! i E Use a syringe to draw a 1 cc sample. Use the injection port en the gas partitioner fcr this analysis. till i r
~ . _-
I l J EPIP 7.3.2
- Page 9. -;
I t l 5.2.2 Radioactive IIcble Oas s Use a syringe to draw a 1/2 cc sample and inject i this into the flask prepared in Section 1.2.3.* l Allow 30 minutes for thermal mixing. Draw a L 1/2 cc sample of this dilution and proceed as ; ! normal. l l
- Additional dilution should be performed if f i the contact reading is >l ar/ hour. l 1
i { MOTE: SEE SECTIONS 7.0 AND S.0. , I 5.3 Collecting the Liouid Sample From the Pressurized Sample l 5.3.1 Add one drcp of 2 !! nitric acid (per 10 ml of i sample) to the chloride beaker for pH . j adjustment. I UOTE: IT IS EXTREI!ELY IIIPORTANT TO VERIFT THAT VAL 7E 2 HAS BEEH CLOSED BEFORE PROCEEDI?iG. ) 5.3.2 Open valve 3 slowly. Allow the liquid sample , to drain into the 50 ml beaker. Direct a slow : e stream of air through the vent line on valve 3 if necessary to recover the total liquid sample. l I 5.3.3 Close valves SA and EB, 9A and 9B, and valve 3. i k 5.4 Analysis of Licuid Samples f 5.4.1 Boron /pH Analysis
- a. Transfer a 5 ml sample using the chemical ;
transfer pump into a 50 ml poly beaker l containinc a stir bar. ~ i UOTE: OBSERVE THE TRAMSFER PUUP OPERATICM. h* HEIL SAMPLE BEGIN5 TO ENTER THE ! BEARER, THE TRANSFER RATE IS 0.5
!!L/SECCND OR 10 SEC = 5 I!L. I
- b. After transfer is complete, record the pH. ,
i
- c. Plug in the magnetic stirrer add mannitol, and proceed Nith the bcron analysis.
HOTE: IF THE PRI!!ARY SYSTEl! HAS EEE!! EORATED, i 5 11L OR I:0RE OF TITRANT !!A'l SE MEEDEC TO REACH AN ENDFOIIII. illl> . t i
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NOTE: AFTER DRILLS AND PRACTICE RUNS, THE t l BORON TITRATOR HUST BE FLUSHED.WITH I I DE10NIZED WATER AND FUT IN DRY LAY- ! UP. ALL ELECTRODES SHOULD EE PLACED ! IN LAYUP SO THEY ARE CONDITIONED FOR ! IMMEDIATE USE. h t 5.4.2 Chloride Analysis i i Transfer the remainder of the sample to the ; I second poly beaker containing the chloride f l electrode. Start the stirring action and record E l the potential. Use the calibration-curve'for j the ch]oride electrode to determine chloride l concentration. . i -! l i NOTE: CHLORIDE SAMPLE MUST EE pH ADJUSTED. l SEE STEP 5.3.1. i ( NOTE: HIGH LEVELS OF RADICACTIVE IODINE IN THE j i COOLANT WILL INTERFERE WITH THE CHLORIDE ; ANALYSIS. REFER TO THE ATTACHED IODINE / l CHLORIDE CORRECTION CURVE (ATTACHMENT l
. 7.3.2-1) TO MAKE THE PROPER ADJUSTHENT l t
TO THE CHLORIDE ELECTRODE ANALYSIS. i i 5.4.3 Iodine Analysis and Gamma Scan l l I l Using the specially prepared 2 cc syringe, with- l l draw 0.3 cc of the sample frem the poly beaker ! l used for the chloride analysis and inject thi-l sample into a 1000 ml poly bottle containing ! l demineralized water. Make additional dilutions i i in the same manner.* Count as normal. ! l
- Additional cilution should be performed until l the contact reading is <1 mr/hcur. ;
MOTE: SEE SECTIONS 7.0 AND 8.0. ! l : l 5.S Reporting of Results , l h Complete and forward Reactor Coolant Post-Accident Sampling Analysis t Report (EPIP-30). , i . 1
-6.0 SAMPLE RESIDU: i r
i 4 Place all sample residue in the specially prepared lead pig for t l disposal. ) l l lllI
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EPIP 7.3.2 ; Page 11 i t 7.0 SA!!PLES TAKE!i TO KEWAU?!EE I!UCLEAR PLANT FOR COU!! TING
Reference:
Post-accident counting agree: rent with Wisconsin Public Service, " Kewaunee Nuclear Plant. l l Kewaunee Nuclear Plant does not utilize the 5 cc glass vial and I cc test l tube geometries. Therefore, " normal" samples will have to be diluted and l placed in one liter poly bottles if they are sent to the Kevaunee Nuclear Plant for analysis. 8.0 LABELI!!G OF SAMPLES Label all chloride, noble gas, iodine and gamma scan samples with all I pertinent information such as: sample number, name of sample, date and l time of sa.mpling, sa:r.ple volume and dilution (s ) . l l l l l l i i I I l l l 1 I i i 1 1 ) 1 s
. [
I 1 , ! i I. , ATTACHMENT 7.3.2-1 l CORRECTION FOR REACTOR COOLANT IODINE , j INTERFERENCE WITH CHLORIDE ELECTRODE RESPCNSE I
1.0 INTRODUCTION
Chloride as determined by the chloride specific icn electrode is subject l to interference caused by the presence of high levels of other halogens, specifically iodine. The following procedure outlines the method used to estimate the correction for this interference. 2.0 PROCEDURE i l 2.1 Neasure the chloride concentration using the chloride specific
- ion electrode.
I i i l 2.2 Ferform the iodine analyses as outlined in Section 5.4.3 of this l l procedure. i l 2.3 Convert the iodine concentration to ppa using the folicwing conversion i factors. Isotope pCi/cc + ppm Conversion Factor , i ! I-130 ~5 1 ! I-131 2.54 X 3.85 X 10 10 4 i I-132 4.71 X 10.6 . I-133 4.23 X 10 o 6 i 1 I-134 1.78 X 10 - > j I-135 1.38 X 10
- I
- 2.4 Sun the concentration, in ppm, of each icdine isotcpe and use the attached curve to determine the estimated chloride concentraticn i correction factor.
?
l 3.0 EXAMPLE i ! l l Reacter coolant Analysis ! Estimated f Isotope Concentraticn (uCi/cc) Conversion Factor Concentration :;;mi I-131 2.56 X 100 pCi/cc :: 3.85 X 10 4 . 9.66 X 10.1 , I I-133 1.45 X 102 pCi/cc X 4.23 F 10 o ~ 6.13 X 10
- l I-135 5.65 X 103 pCi/cc "
1 . 3 5 :: 10 " 7.80 . 10 ~2 l TOTAL 1.07 ppm 1 , ChloriJe concentration trcm correcticn curve ippm) = 0.42 ppm f i i Subtract this /alue frem the chloride ccncentration determined 'c; the ; ! chloride electrode. l till , l I
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!!INOR Revision 4 C9-10 c2 O
POST-ACCIDEMT SA!!PLIliG OF CONTAIUMEMT A!MOSPHERE l I 1.0 INTRODUCTICtl This procedure outlines the steps necessary to collect, handle and analyze ; a potentially high radioactive containment atmosphere sample resulting l from gross fuel failure and loss of reactor coolant system integrity to ! determine hydrogen and radioactive gas concentrations. . l I i 2.0 PRELIMI!!ARY EVALUATIOM l i r llOTE : THE FOLLOWIIIG EVALUATIO!! SHALL BE CCMPLETED PRIOR TO ANT ATTEMPT l TO ENTER THE FACADE OR R11/R12 CUBICLE TO PERFORM A VALVE LINEUP l l OR COLLECT A COMTAINME!IT ATIIOSPHERE SAMPLE. i 2.1 Indications of Possible Fuel Damage ) i l Some or all of the following would be present if fuel damage or : loss of reactor coolant system integrity had occurred: l The letdown radiation mcnitor (R9) would be unusually G 2.1.1 I high or ofiscale. [ l 2.1.2 The containment radiation monitors (R11 and R12) would be t unusually high or offscale. j 2.1.3 The containment area monitors (R2 and R7) would be unusually I high or offscale. l P 2.1.4 The automatic acticns of EOP- A have caused containment i isolation. 2.2 Evaluation of Radiolcq.ical Hazards in Access Areas Required for Sampling Initials 2.2.1 After evaluation of the radiation monitoring I systen readouts, *cerify with Health Physics ' l that the appropriate airborne and radiaticn ( surveys have been made befoce entering the j facade. ; f I i i t i I ~ till l 1 f L F
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I A EPIF 7.3.3 Page 2 2.2.2 'le r : f; the req'nrements for facade and Ell!-1? cubicle entr;
- a. Radiation
- cork permit requirements
- b. Clothing requirements
- c. kespiratori requireren's
- d. Dosimetry requirements including e::tremity dose mcnitoring
- e. Health physics cc'Jerage require.ments including timekeeping
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..r. -3 SHALL APPRO'/E THE I!!PLE'!ENTATION OF THIS FRCCEDUKE . THE FOLLOWING STEFS WILL BE ACCO!!PLISHED UNDER THE DIRECTICH OF HEALTH PHYSICS SUPERVISICM.
3.1 Val *ze Lineurs 3.1.1 The conta urent atmosphere s nple 'ill be collected using the R11'E12 snel c.c s ccter . . 3.1.2 Entr*. to the facade shall be frcm the patc.ble water roca (Unit ]l cr the non-r,uclear rocm (Unit 2). r- * '-
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0, 4 EPIP 7.3.3 Page 3 I
- b. Verify that the continucus vent valve 32005 and 3200U is closed.
- c. Close valve 3200K.
3.1.5 Hook the 100' service air hose to the Chicago fitting on the elevator side of the Rll/R12 cubicle established for sampling line purging. Verify that valve 3200Y is closed. NOTE: THE 100' HOSE IS STOREL INSIDE THE
- UNIT 1 Rll/R12 CUBICLE ALONG WITH IHE PRESSURE REGULATOR.
3.1.6 Return to the room mentioned in Step 3.1.2 f with the air hose and pressure regulato. . i 3.1.7 Hook up the service air hose to an available outlet in the turbine hall using the pressure i regulator designed for this precedure. Use suitable pins to lock the Chicago fitting in place. f 3.1.8 Verify with the control roca that the Rll/R12 j monitor is lined up to monitor and discharge (G to containment atmosphere. l i 3.1.9 Request control room supervisicn to open the l suction and discharge (A0V's) isolation valves l and start the pump. ; i i l 3.1.10 Verify sample flow by increased radiation levels. j f i i 3.1.11 Allow five minutes for sample recircing. Request j ! control rcom supervision to step the pump and j l close all suction and discharge (A07) isolation , l valves. I 3.2 Sample Cellecticn j 3.2.1 Enter the facade and proceed to the samcle point. Take along two 2 cc gac syringes in a hellowed-out lead brick. i ! CAUTICN: CCNTAINME?!T FRESSURE COULD THEORETI- I CALLY BE AS HIGH AS 60 FSIG. HOLD l THE SYRI? IGE FLU? GER SECURELY. ALSC, i LOCK THE GAS SYRIMGES BEFORE NITH-l DRAWING FROM THE SAliPLING SEPTUII, i USING THE EUILT-IU LCCKIIiG CEVICE ' CN IHE SYRI??GE. 2 . l s 8 i
c EFIP 7.3.3 l Page 4 l lt I h 3.2.2 Remove the set screw and take one 1/2 cc and one 1 cc gas sample. Place the syringes in j the lead brick. ; 1 i 3.2.3 Replace the set screw and cpen valve 32007. [ l 3.2.4 Leave the facade and return to the room ( mentioned in Section 3.1.2. 3.3 Sample Line Purging , t I 3.3.1 Open service air valve and adjust the pressure ; to a setting of 10 psig greater than measured i containment pressure. i 3.3.2 Request control rcom supervisior. to open the l pump discharge isolation valve (3200A). ! 3.3.3 Request control room supervision to start the I 3 R11/R12 pump. 1 l L 3.3.4 Verify purge effectiveness by measuring the ! l reduction in radiation levels after approximately l 15 minutes of purging. , ___ l 3.3.5 Request control rocm supervision to close the pump discharge isolation valve, secure the pump. - and cpen the pump suction isolation valves. ; f 3.3.6 Continue the purge for 10 more minutes. } 3.3.7 Request control roem supervision tc.close all l pump discharge and suction isolation valves and secure the pump. l 3.3.5 Secure the service air valve. NOTE: AFTER ORILLS AND PRACTICE RCIS , RETURN l ALL EQUIPMENT AND VAL 7E LINEUPS TO AS FCUND COUDIIICN. l 4.0 CCNIAINME![T AIMOSPHERE ANALYSIS I 4.1 Vols-e Adjustments . 4.1.1 Eefore proceeding with the hydrogen, radioactive nobel gas l and radioactive iodine ar.alyses . the sample centents of Lcth ' syringes must be brcught to atnespheric pressure. Use the l shielded sacrificial glass bcsb for this purpose. j l till ! l i ( ! i
. EPIP 7.3.3 Page 5 4.1.2 Insert the syringe through the rubber septum of the glass bcmb. Unlock the syringe locking device and let the
, syringe and bomb equilibrate for approximately 30 seconds. l Relock the syringe and withdraw from the septum. Store the j syringe in the lead brick.
- 1
- 4.1.3 Repeat Step 4.1.2 for the other syringe. 1 i, I i 4.2 Hydrocen !
1 Assuming normal equipment setup and preparations are complete, use the sample injection port on the gas partitioner, inject a 1 cc gas sample and croceed , using normal hydrogen analysis procedures. , I 4.3 Radioactive Mcble Gases and Iodines 4.3.1 Couple the silver zeolite column and the evacuated glass bomb as shown in Figure 2. i i I 4.3.2 Inject the 1/2 cc containment atmosphere sample into the ' column through the septum. Remove the syringe and store in the lead brick. i Using a second syringe tip (without the plunger) puncture G 4.3.3 ; the column septum and fully insert the syringe tip. j 4.3.4 Crack open the upper glass bomb valve between the bomb and the column. Allow air to slowly bleed through the column to : the bomb. Flow can be verified by cbserving the gentle i reflux of the siver zeolite surface. When ficw has ceased, momentarily open the upper valve wide open and then close ! completelv. I 4.3.5 Remove the column frem the bcmb and store the bcmb behind shielding in the hcod. I Icdines : t 4.3.6 Remove the septum frcm the column and pce: the silver zeolite ! into a counti:.g test tube and cao. l 4.3.7 If the silver zeolite / iodine sample is less than ene mR/hr i contact, ccunt the sample directly on the MCA using the ; test tube gecmetry and a multiplying factor of two. i 4.3.6 If the icdine activity is too high to count directl; , determir.e the radiation level in mR/hr at ene fcot. Alsc, determine the percent isotopic composition using the I:CA and attenu- l atinc the sample if necessarv~
~
O i. l I
l l i j , EPIP 7.3.3 i Page 6 i u h Determine the total iodine activity using the following i equation: l j
=
R/hr @ l' I i C(Ci) 6E T i 1 l . The following table can be used as an aid in determining the l " Total Average Energy /y" (E ) for the above equation. T (1) (2) (1) x (2) Average y % Composition Ueighted y Isotcpe Energy (Fraction) Energy i 131 I 0.380 13 I ,2 , 0.731 I,"7 0.530 I'"? 0.857 13a I 1.233 Total Energy /y (ET) Each individual iodine isotcpic concentration (pCi/cc) is calculated as follows: pCi/cc I(1) = C(Ci) x 2 x 10+6 x (Fractional % Compositien) 9 . i Iloble Gases f 4.3.9 Withdraw a 1/2 cc gas sample frem the glass homo in Step 4.3.5. If the contact reading on the syringe is less then one mR/hr, inject the sample into a 5 cc vial and count as normal. If the contact reading is greater than one mR/hr, further dilutiens are necessary. Dilution precedure- Inject the 1/2 cc sa.mple intc a one liter poly bottle and alle, to equilibriate. Withdraw 1/2 cc frcm the poly bottle. If the contact reacing is less then ene mR/hr, in]ect into a 5 cc vial and count as normal. If the contact reading is greater than ene mR/hr, dilute further l , I:0TE: FOR EACH DILUTIC.'I, USE A NEW STRIIISE CR :!AEE CERTAI:-I IHE OLD S7RIIiGE IS COIIPLETELY FURGED. LAELE IICELE GAS I SAI!PLES AMD IODINE SAI!PLES WITH ALL PERTIMEIII INFOR-IIATION SUCH AS: SAIIPLE IIUMSER, IIAI!E CF SAMPLE , DATE AND TII:E OF SAMPLE , SA'IPLE '70LUI!E AI;C DILUTICli(S ) . 5.0 CALCULATICIIS j
!.I Fressure and Teccerature Correction Ask control recm supervisicn for the temperature snd pressure in 9 containment (psig and F). Cetermine atmospheric pressure (cm Hg) an"
- . _ . . - _ _ _ _ _ _ _ _ _ . _ _ _ __ . _ _. _ _ _ _____._. _ _ _ .____ ~ _
+
. EPIP 7.3.3 t
Pace 7 8 Y d I j temperature ( F) from the barometer in the laboretor; Cc:wert this to j psia. Apply the following correction factor to all results: 1 Initials 6 i i Concentration (pCi/cc) ..a (P + 14.7) T + 459 i P T i j lab lab + 459 i i
. P (mm Hg) '
I P .
= 14.7 psi x lab (psla) 760 rrJn Hg l I i 52 Complete and forward Containment Atmospheric Post-Accident Sampling !
j Analysis Report (EPIP-31). , ( i l e : f t i. l
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EPIP 7.4.1 l MINOR
; Revision 6 09-10-82 O ROUTINE CHECK, MAINTENANCE, CALIBRATION & INVENTORY SCHEDULE FOR HEALTH PHYSICS EMERGENCY PLAN EQUIPMENT i
i 1.0 PURPOSE The purpose of this procedure is to establish the routine checks, mainte- . nance, calibration and inventory schedules for health physics related material and equipment applicable to the Emergency Plan. i 2.0 EMERGENCY PLAN EQUIPMENT STORAGE LOCATIONS 2.1 Emergency Plan equipment is normally maintained in a state of opera-tional readiness at the following locations. 2.1.1 Health physics station i 2.1.2 Technical support center (TSC) 2.1.3 Emergency support center (ESC)
, 2.1.4 Operations support center (OSC) 2.1.5 Site boundary control center (SBCC) l 2.1.6 Control room 2.1.7 Two Rivers Community Hospital (NFAR and triage area) 2.1.8 Point Beach Nuclear Plant first aid room (see EPIP 11.0) i 2.1.9 South gatehouse.
t 2.1.10 Other items of Emergency Plan equipment such as first aid j kits, burn kits, trauma kits, stretchers, and the emergency l vehicle.are maintained at specified locations throughout the plant. 3.0 ROUTINE CHECK, MAINTENANCE AND CALIBRATION SCHEDULES i i Routine checks, maintenance and calibration of Emergency Plan equipment , will be consistent with the scheuule outlined in Attachment "A" and the ! instructions contained in EPIP 7.4.2, " Emergency Plan Equipment Routine Check, Maintenance & Calibration Instructions."
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A% EPIP 7.4.1 Page 2 4.0 INVENTORY SCHEDULE 4.1 Inventory of health physics related Emergency Plan equipment will be consistent with the schedules provided in Attachment "A". 4.2 Inventory of Emergency Plan equipment will be accomplished utilizing _ the inventory checklists listed below and attached to this procedure. Missing or deficient items noted by the inventory will be promptly
- replaced by personnel assigned to accomplish the inventory. The results of all inventories will be reviewed by the Health Physics Supervisor who will ensure that all discrepancies are corrected. The completed inventory forms will then be forwarded to the Superin-tendent - Technical Services and the Health Physicist.
4.2.1 Inventory Checklists
- a. Site boundary control center (form EPIP-24a)*
. b. 'OSC, ESC, and South Gatehouse (form EPIP-24b)*
- c. Two Rivers Community Hospital (form EPIP-24c)*
i
- d. Control room (form EPIP-24d)*
- e. Emergency vehicle (form EPIP-24e)
- f. First aid kits (form EPIP-24f)
- g. Burn kits (form EPIP-24g)
- h. PBNP first aid room (form EPIP-24h)*
- i. Stretchers (form EPIP-24i)
- j. Trauma kits (form EPIP-24j) i l
*The form needs to be filled out with an item by item count on an annual basis. Quarterly checks can be accomplished I
by verification of administrative controls such as seals.
! J$ 1 a a fs ATTACHMENT "A" EMERGENCY PLAN EQUIPMENT ROUTINE CHECK, MAINTENANCE, CALIBRATION AND INVENTORY SCHEDULE
?? ?
> 2? O $ -
I; 5e t .L 8 Cross o e a e Reference E $ 5 8 $
- 1. Emergency Vehicle
- a. Radio operational test '
X
- b. Vehicle visual inspection and engine start X ,
- c. Emergency equipment inventory X 1 2 1 d. Vehicle test drive X X i
- 1. November through March r' 2. April through October k s 2. First Aid Kits, Burn Kits, Trauma
( Kits and Stretchers 3
- a. Inventory X
- 3. January, April, July,
, September
- 3. Vamp Portable Area Monitors
- a. Functional check X
- b. Calibration X i
- 4. Emergency Center Air Samplers (115 V AC)
- a. Functional test X i b. Preventive maintenance i (where applicable) X
- c. Flow rate calibration X
- 5. SBCC Air Sampler (Battery 12 V DC)
- a. Functional test X
- b. Flow rate calibration X l s
h
#4
>, 5 x t k 2 3 h %
Cross s y g 7 $ , Reference j j o, 8 j
- 6. AC Generator (Gasoline Powered)
- a. Functional test X
- b. Spare gasoline changed X
- c. Maintenance X
- 7. Batteries - Replacement
- a. Traffic warning lights X
- b. Survey / counting instruments X
- c. Flashlights X
- d. Portable radios (KRQ 717) x
- e. Dosimeter chargers x 4
g 4. Alkaline type batteries to be used where possible and to be replaced yearly. Standard carbon cells, if used, to be load tested for 5 minutes , quarterly and replaced yearly
, or as load test dictates.
- 8. Potable Water (Stored) i l a. Water changed X
- 9. Counting Instruments
- a. Functional test x
- b. Calibration x
- c. Counting efficiency determination x
- 10. Frisker Type Instruments
- a. Functional test X
- b. Calibration x
- c. Efficiency determination X
- 11. Portable Survey Instruments I i
j a. Functional test X
\ b. Calibration x
O h (G 3 8
> ?? o k M
% 5 t 4 a 6 C No. Item $ $ $
Reference 3 E cx 0 k
- 12. Pocket Dosimeters and TLD's
- a. Dosimeter drift / response check X
- b. TLD's changed X
- 13. Respirators
- a. Inspection X
- 14. MSC SCBA Units
- a. Inspection X f5N b. Functional test X
- 15. Bio-Paks (Oxygen Rebreathers)
( )
- a. Inspection X
- b. Functional test X .
- c. Periodic maintenance X
- 16. Inventory of Emergency Plan 3
Equipment - Complete X
- 5. This inventory includes all equipment listed for each center on forms EPIP-24a, b, c, d and h.
i
- 17. Portable Radio (KRO 717)
Functional Check X
- 18. Traffic Warning Light Functional Check X
- 19. Technical Support Center A!!S-2/R!l-14 Air Monitoring System
- a. Calibration X
- 20. Silver Zeolite ( AgZi !!oisture Q('~'s Indicator Check X
y. EPIP 7.4.2 MINOR Revision 4 09-10-82 EMERGENCY PLAN EQUIPMENT ROUTINE CHECK, MAINTENANCE AND CALIBRATION INSTRUCTIONS 1.0 PURPOSE The purpose of this procedure is to provide instructional guidelines for the performance of routine checks, maintenance, calibration and inventory of health physics related Emergency Plan equipment. 2.0 PRECAUTIONS 2.1 Personnel handling radioactive sources or other radioactive material will use remote handling equipment, shielding as appropriate and common sense to prevent unnecessary personal exposure. 2.2 A calibrated survey meter will be used when working with sources of radioactive material. 2.3 Appropriate personnel monitoring devices (TLD, high and low range dosimeters) will be worn. 2.4 General safety preca,utions will be adhered to at all times. 3.0 GENERAL INSTRUCTIONS 3.1 Shortages of material or equipment found during inventory will be noted on the appropriate inventory form. Restocking of all missing items will be accomplished expeditiously as possible and noted on the inventory record. 3.2 Items of equipment requiring repair or calibration by other than Health Physics requires the initiation of a maintenance request. The words " Emergency Plan Equipment" will be written in bold letters in i the " Defect / Request" block of the maintenance request form. l 3.3 Equipment removed from an Emergency Plan location for other than l short periods (one day) for calibration or routine maintenance will be replaced with a similar item from the health physics station unless otherwise directed by the Health Physics Supervisor. 4.0 PORTABLE SURVEY INSTRUMENTS AND AREA MONITORS (VAMP) 4.1 Portable survey instruments and area monitors normally assigned for Emergency Plan use (forms EPIP-24a-h) are scheduled for routine
/N calibration consistent with HP 13.2, " Portable Survey Instruments and
( ) Calibration Procedures," and form EPIP-28, " Emergency Plan Instrument Calibration Schedule." l l
EPIP 7.4.2 Page 2 hv 4.2 Functional checking and testing of portable survey instruments and vamp area monitors will consist of response testing each instrument with a radioactive source placed in a known and consistent geometry. Results are recorded on form EPIP-25b. 4.3 Functional check and Test 4.3.1 Eberline PIC-6A, Rad Owl Two, Radector III, Mini-Rad, HPI-1010 and VAMP Area Monitors These instruments do not have an installed check source. A small Cs-137 check source, serial number CS-11, will be utilized for response testing of these instruments. 5.0 FRISKER-TYPE SURVEY INSTRUMENTS 5.1 Frisker-type survey instruments normally assigned for Emergency Plan usage (form EPIP-24a-h) are scheduled for routine calibration and efficiency determinations consistent with HP 13.3, " Personal Friskers and Portal Monitor Description and Calibration," and form EPIP-29,
" Emergency Plan Counting Equipment and Frisker Calibration Schedule."
5.2 Functional checking and testing of frisker-type instruments will I consist of exposing the instrument to a known source in a consistent geometry. Results are recorded on form EPIP-29. 5.3 Functional Check and Test 5.3.1 Install fresh batteries and verify that the battery check position operates where applicable. 5.3.2 Thyac III, Model 490 Retract the beta shield and expose the GM tube detector. Place the detector opening directly over the uranium beta source that is attached to the instrument case. Record the results. 5.3.2 GSM-5 Attach a HP-210 detector to the GSM-5 and place the detector on the SH-4 holder for reproducible geometry. Use the Sr-90 check source, serial number S-23, for the response check. Record the results. 5.3.3 RM-3C Attach an HP-210 detector to the RM-3C and place the detector fe $g on the SH-4 holder for reproducible geometry. Use the Sr-90 g check source, serial number S-23, for the response check. Record the results.
r EPIP 7.4.2 Page 3 ( ~h 6.0 COUNTING INSTRUMENTS 6.1 Counting equipment normally assigned for Emergency Plan use (form EPIP-24a-h) are scheduled for routine calibration and efficiency determinations on form EPIP-29, " Emergency Plan Counting Equipment and Frisker Calibration Schedule," and will be completed consistent with HP 13.5, " Counting Equipment Efficiency Determinations." 6.2 Functional checking and testing of counting equipment will consist of response testing each instrument with a known radioactive source in a consistent geometry. Results are recorded on form EPIP-29. 6.3 Functional Check and Test 6.3.1 Nuclear Chicago Counter Scaler Attach an HP-210 detector to the instrument and place the detector on the SH-4 holder for reproducible geometry. Use the Sr-90 check source, serial number S-23, for the response check. Record the results. 7.0 AIR SAMPLERS f\ }
,/
7.1 Air samplers normally assigned for Emergency Plan usage (form Nos. EPIP-24a-h) will be maintained and flow calibrated using the procedures in HP 13.6, " Maintenance and Calibration of RAP-1 and RAS-1 Air Samplers," and HP 13.10, " Maintenance and Calibration of High Volume Air Samplers." Record results on applicable forms listed in the above procedures. 7.2 Functional checking and testing of the various types of air samplers is described below. Record results on form EPIP-25b. 7.3 Functional Check and Test 7.3.1 115 V AC Power Air Samplers Install filters and operate air samplers for five minutes. 7.3.2 Battery (12 V DC) Powered Air Samplers
- a. Check electrical leads for damage. The battery clips should not be bent and should engage the battery termi-nals firmly.
- b. Install air filters and connect the electrical leads to l
a vehicle battery and operate the vehicle engine at a fast idle rate. [\ c. Operate the air sampler for approximately two minutes. , 's_- Any overheating of the sampler is an indication of a problem.
EPIP 7.4.2 Page 4 O i 8.0 DOSIMETRY DEVICES 8.1 Dosin.eters normally assigned for Emergency Plan use will be drif t and response checked consistent with HP 10.1.3, " Dosimeter Calibration / Response and Drift Check Procedure." Note the required entry on form EPIP-25d. 9.0 RESPIRATORY EQUIPMENT Respiratory protection equipment assigned for Emergency Plan use will be inspected, tested and maintained consistent with HP 12.1, " Respiratory Protection." Note required entry on form EPIP-25c, and d. 10.0 FIRST AID KITS, BURN KITS, AND STRETCHERS 10.1 First aid and burn kits found with the lead seal intact do not have to be physically inventoried. Kits found with the lead seal broken will be inventoried and the missing items replaced. Note required entries on EPIP-24f, "First Aid Kit Inventory Checklist," form EPIP-24g, " Emergency Burn Kit Inventory," and EPIP 24-i, " Stretchers." 11.0 EMERGENCY VEHICLE (A i Visual inspection of the emergency vehicle will be accomplished per form EPIP-25a, " Emergency Vehicle Checklist". The test run, when required, should follow the route from the plant to Highway 42 via Nuclear Road, then right to Tapawingo Road and return to the plant. The radio operational check between the vehicle and the control room will be made from Highway 42. 12.0 SILVER ZEOLITE FILTE'R MOISTURE CHECK Visual inspection of the moisture indicating devices should be performed annually. Check each filter's indicator. If it is blue, the filter has no moisture in it. If it is pink, moisture is present and the filter should have the excess moisture driven off. (Reference file HP 9.6, RadeCo Company letter to R. S. Bredvad from Frar.cis S. Smith, dated 5-29-81, for procedure.) 13.0 GASOLINE POWERED AC GENERATOR 13.1 Functional Test 13.1.1 Check oil level at full mark. 13.1.2 Ensure all loads are disconnected from the alternator and install grounding stake. 13.1.3 Add a small amount of gasoline to the fuel tank. () 13.1.4 Open the fuel valve.
a r EPIP 7.4.2 Page 5 G 13.1.5 Make sure the stop switch is away from the spark plug. 13.1.6 Choke the engine. 13.1.7 Start, by pulling the starter cord. 13.1.8 Run for at least 30 minutes, place a small load on the unit during the test (high volume or low volume air sampler). 13.1.9 Remove the load from the unit and shut the fuel valve. Allow the unit to stop on loss of fuel. 13.2 Maintenance Annual maintenance to be done according to Maintenance callup pro-cedure by Maintenance group. 14.0 CARBON CELL POWERED EQUIPMENT 14.1 Traffic warning lights equipped with carbon cell batteries are to be load tested and documented on EPIP-25c in the following manner:
-, 14.1.1 Ensure correct battery installation.
14.1.2 Turn on light and allow to operate for 5 minutes. 14.1.3 If the light appears to be bright and not diminishing in intensity after the 5-minute test, battery is suitable for continued use. 14.1.4 If the light fades or goes dead after 5 minutes, replace the battery in storage with a new one. 14.1.5 Carbon cells are to be replaced once per year. I i i O
. , - - . - , . - - - +w- - ----
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gi* EPIP 11.1 MINOR Revision 3 09-10-82 ON-SITE FIRST AID ASSISTANCE
1.0 INTRODUCTION
AND PURPOSE 1.1 General Industrial Safety and First Aid Practices General industrial safety and first aid practices adopted for use in conventional plants are in effect at Point Beach Nuclear Plant. Since personal injuries or emergencies may or may not involve radio-activity, the possibility of radioactive contamination of an injured person is addressed throughout this procedure. 1.2 First Aid The Point Beach organization includes persons experienced in first-aid procedures who will be called in the event of injury. The plant is provided with an emergency shower for use with a severely contami-nated but less severely injured person, and a complete first aid room equipped with facilities and medical instruments suitable for physical hyx) examinatio's. On-site first aid facilities are further described in Section 4.0 of this procedure. 1.3 Hospital Assistance l EPIP 11.3, " Hospital Assistance," outlines specific procedures to be ! used in the event of serious personal injury or illness at Point Beach Nuclear Plant. Since the possibility exists that treatment and transportation of a patient may be complicated by radioactive con- 4 tamination, a fully equipped controlled access treatment room (the nuclear first aid room) has been provided at Two Rivers Community Hospital, Two Rivers, Wisconsin. A list of radiation and contami-nation control materials in the treatment room is given in EPIP 11.3. 1.4 Emergency Vehicle An emergency vehicle is available at all times and contains emergency first aid and oxygen breathing equipment (described in Section 4.0). This vehicle is normally parked in the extension building garage. In addition, arrangements have been made for backup assistance by the s City of Two Rivers Fire Department emergency vehicle in case of multiple need. This backup ambulance planning is described in EPIP 11.3. l lO
1 6 EPIP 11.1 Page 2 a 1.5 Plant Personnel Responsibility It is the responsibility of involved plant pe'rsonnel to beco'me familiar with this procedure and specifically with instructions with regard to their individual actions required. , 1.6 Telephone Contacts Telephone contacts required by this procedure can be found in Attachment 11.1-1. I
2.0 REFERENCES
2.1 PBNP 8.8, " Injuries, Accident Reporting, and Industrial Safety." 2.2 SSO 1, " Procedures for Using Accident Report Forms Related to l Accidents at Point Beach Nuclear Plant." 2.3 HP 10.2, "Use of Personnel Monitoring Devices During an Emergency." l 2.4 EPIP 12.2, " Search and Rescue." l j J'~%g 2.5 EPIP 11.2, " Injured Person's Immediate Care." 2.6 EPIP 11.3, " Hospital Assistance." l i 3.0 DEFINITIONS ( The following definitions are used, in addition to Section 2 of the l Emergency Plan, to define terms used in this procedure. 3.1 First Aid Representative An individual certified by the American Red Cross (or an equivalent program) to administer first aid to the injured. t l 3.2 Personal Injury An injury which requires either first aid or professional medical attention and may involve lost time. 3.3 Disabling Injury l An injury which requires professional medical attention and involves lost time, but would not be a life threatening injury. 3.4 Serious Injury l t An injury which requires professional medical attention and could ( ( result in a fatality or permanent disability. i i
-, . _ . _ , _ . _ - - __-,..?
3 EPIP 11.1 Page 3 U 3.5 Personal Injury Report, Forms 1032 & 1033 The Wisconsin Electric injury report used to report personal injuries. 3.6 Disabling Injury Report Same as personal injury report. 3.7 Motor Vehicle Accident Report, Form No. 1020 l l The Wisconsin Electric report used to report every accident involving l Company-owned vehicles or a privately owned car used on company I business. 3.8 Attending Physician's Report i The Wisconsin Electric report which is required when a doctor provides care to a Company employee for a work-related injury. i 3.9 First Aid j 's Immediate and temporary care given the victim of an accident or j serious illness until the services of a physician can be obtained. I i 4.0 ON-SITE FIRST AID ASSISTANCE 1 l 4.1 General , on-site medical preparedness programs are the responsibility of the l Point Beach Nuclear Plant Industrial Safety Coordinator. First aid training programs are carried out in accordance with company Medical Department and Company Safety Department requirements and applicable regulatory requirements. 4.2 First Aid Room Location and Equipment The Point Beach first aid room is located in the extension building i on the second level. It is equipped as follows: basic furniture l (desk, chairs, table, cabinets); sink; examination table; examination j cabinet; examination equipment; scale; first aid supplies including assorted bandages and gauze dressings, tape, splints, bandage j scissors, splinter forceps, portable burn kit, and portable first aid l kit. 4.2.1 Responsibility l The Company Medical Director is responsible for determining the equipment for the first aid room. The Point Beach s, Industrial Safety Coordinator is responsible for maintaining the supply inventory.
e e v EPIP 11.1 Page 4 (o 4.3 Emergency Vehicle Description A Company-owned vehicle is provided and will be used to transport i seriously injured personnel. The vehicle is equipped as follows: i stretcher, blanket and pillow; first aid kit; burn kit; oxygen ) breathing unit. ! l 4.3.1 Responsibility Specifying emergency vehicle equipment is the responsibility of the Company Medical Director. Maintenance of equipment and supplies is the responsibility of the Point Beach Indus-trial Safety Coordinator. 4.4 other On-Site First Aid Provisions l Most first aid supplies are located on the uncontaminated or " clean" side of the plant. If, for emergency reasons, it is necessary to transfer first aid supplies to the controlled area, the unused supplies will be retained in the Health Physics Station for ultimate disposal or release to the " clean" side. Supplies are available at the following locations: 4.4.1 Gatehouse
- a. First aid kit i
4.4.2 Turbine Building
- a. One stretcher, first aid kit, and burn kit; located south of the control room.
- b. One stretcher, first aid kit, and burn kit; located in the Unit 1 truck access at the 8' level.
- c. First aid kit located in the control room.
- d. Burn kit located in the control room.
- e. Trauma kit located in the control room.
4.4.3 Switchyard
- a. First aid kit
- b. Burn kit 4.4.4 Unit 1 and Unit 2 Facades
- a. Stretcher, first aid kit, and burn kit; located on 66' and 26' levels outsida each containment's personnel hatch.
1 i EPIP 11.1 Page 5
)
4.4.5 Site Boundary Control Center
- a. First aid kit I
- b. Burn kit 4.4.6 Checkpoint Charlie (entrance to controlled area)
- a. First aid kit
- b. Burn kit
- c. Scoop stretcher
- d. Oxygen breathing unit
- e. Trauma kit 4.4.7 Technical Support Center
- a. First aid kit
- b. Burn kit
- c. Trauma kit
- d. Stretcher 4.5 General Administrative Responsibilities in Case of Injury (see EPIP 11.2 for procedures) 4.5.1 Employee Responsibilities I
- a. Personal Injury and/or Disabling Injury ,
i
- 1. Report injury to supervisor and first aid repre-sentative.
- 2. Ensure that the attending physician receives a
" Physician's Release for Return to Work" to complete.
If unable to do so due to extent of injuries, this form will be transmitted by a person on behalf of the injured employee. A supply of these forms is available in the emergency vehicle.
- b. Vehicle Accident
- 1. Report all vehicle accidents promptly to supervisor and control room.
e EPIP 11.1 Page 6 Us 4.5.2 Employee's Supervisor's Responsibilities
- a. Personal Injury and/or Disabling Injury (1) Ensure that first aid coverage is provided by a qualified First Aid Representative when needed. A list of qualified First Aid Representatives is available in the control room, first aid station, technical support center and Checkpoint " Charlie."
(2) Prepare the " Employee Personal Injury Accident Report." (3) Indicate safety rule violation, if any, on the employee " Personal Injury Accident Report." (4) Investigate and make preliminary recommendations on the employee " Personal Injury Accident Report" for corrective measures which could prevent recurrence of the accident. (5) Submit a copy of prepared " Personal Injury Accident j'~') Reports" to the appropriate group head, within eight working hours. 4 j (6) Ensure that the " Attending Physician's Report" is completed and returned to the Industrial Safety Coordinator whenever a doctor is consulted regarding a work-related injury. , (7) A serious injury or fatality is an " unusual event" and must be reported to the NRC within one hour (EPIP 1.1). A fatality must also be reported to the Point Beach Industrial Safety Coordinator. If the i serious injury or fatality is the result of a boiler l or pressure vessel failure (refer to PBNP 3.23.2), the State of Wisconsin Department of Industry, Labor and Human Relations must also be notified within 24 hours (see Attachment 11.1-1 for telephone number). (8) In the absence of the Group Head, report the personal injury accident or the vehicle accident to the Accident Investigation Committee or the acting Committee Chairman.
- b. Vehicle Accident (1) Prepare the " Motor Vehicle Accident Report."
(2) Indicate appropriate comments and recommendations on the " Motor Vehicle Accident Report." (3) Submit a copy of the " Motor Vehicle Accident Report" to the appropriate group head, within eight working hours. L
_. - - _= ~ - e f EPIP 11.1 Page 7 s ("'
\
4.5.3 Injured Employee's Group Head's Responsibilities
- a. Receive and review all personal injury and vehicle accident reports and promptly forward them to the Industrial Safety coordinator.
' b. Report vehicle accidents that are major or serious in nature or result in lost time personal injury to the Accident Investigation Committee Chairman. l c. Report personal injuries that result in lost time or i death and near miss experiences which could have re-sulted in serious injury to the Accident Investigation l Committee Chairman or the acting Committee Chairman. l d. Report all lost time (disabling) injuries to the Accident l Prevention Department, Milwaukee Public Service Building (see Attachment 11.1-1). This will require reporting of the initial day lost and the day the employee returned to work.
- e. Request medical followup, if needed, from the Company
% Medical Director (see Attachment 11.1-1).
U -
- f. Establish sufficient liaison with the injured to main-j tain an up-to-date knowledge of his medical status.
- g. Determine any special needs of the injured man's family
- and advise the Manager - Point Beach Nuclear Plant.
t l i l
e , c
- V 4 EPIP 11.3 MINOR Revision 2
/ 09-10-82 HOSPITAL ASSISTANCE
1.0 INTRODUCTION
As outlined in EPIP 11.1, this procedure specifies plans to be used in the event of serious personal injury or illness at Point Beach. Since the possibility exists that treatment of an injured person may be complicated by radioactive contamination, a fully equipped, isolated, and controlled access treatment room, the Nuclear First Aid Room or NFAR, has been pro-vided at Two Rivers Community Hospital in Two Rivers, Wisconsin. This room is equipped with filtered ventilation, sink, decontamination supplies, protective clothing, signs, radiation monitoring equipment, and other necessary equipment. The Health Physicist and the Company Medical Director are responsible for the training and retraining of hospital and plant personnel involved in offsite medical plans. 2.0 PROCEDURE FOR HANDLING SERIOUSLY INJURED PERSONS f 2.1 General Description (Detailed instructions and responsibilities in
) subsequent subsections)
(V. 2.1.1 Injury or Sickness Resulting in Loss of Consciousness or Mobility in the Clean Area Control room personnel and the Shift Supervisor will be notified of the apparent nature and extent of the injury and location of the injured person. If an injury occurs in a
" clean area"; i. e., an area free of contamination, first aid should be administered by trained plant personnel and the injured person should be transported for medical treat-ment as necessary.
2.1.2 Injury or Sickness Resulting in Loss of Consciousness or Mobility in the_ Controlled Area Although r r /try in a contaminated area is not likely to involv- m tes adioactive contamination, special procedures are ra e tv . Enr handling an injured and potentially contav.aatte girson. The Shift Supervisor is to direct first eid measures and have the injured person moved to the health physics station where, if call out time allows, health physics professionals will take charge. The R. ) l
4 EPIP 11.3 Page 2 73 circumstances of the injury and the condition of the injured influence action with respect to decontamination of the injured, removal of protective clothing, and transport to the hospital. In any case where a victim sustains serious injury, medical aid takes precedence over decontamination procedures. 2.1.3 Subsequent Action NOTE: IF THE TSC IS ACTIVATED, THE MAINTENANC2 SUPERVISOR SHOULD ASSUME THE DUTY SHIFT SUPERVISOR RESPONSI-BILITIES FROM BELOW.
- a. The Duty Shift Supervisor is to assign an individual to drive the emergency vehicle to transfer the injured person to the hospital. He will inform the driver as to which entrance to use. If the victim is contaminated, the west entrance at tne NFAR will be used. Otherwise the regular emergency entrance will be used. An employee trained in first aid should accompany the injured person in the emergency vehicle.
O t b. The health physics professionals are to be notified and
~J proceed to the Two Rivers Community Hospital to assist in decontamination procedures as required. They should arrive before the victim, if possible, to facilitate organization of the NFAR.
NOTE: IF THERE IS MORE THAN ONE SERIOUS INJURY COMPLICATED BY CCNTAMINATION, THE FIRST VICTIM TO ARRIVE AT THE HOSPITAL SHOULD BE DIRECTED TO THE NFAR. SUBSEQUENT VICTIMS SHOULD BE DELIVERED TO THE NORMAL EMERGENCY ROOM ENTRANCE.
- c. The Shift Supervisor is to notify the Two Rivers l Community Hospital (see Attachment 11.1-1 to EPIP 11.1) of the nature of the emergency, if contaminated or l clean, and expected time of arrival at the hospital.
- d. The Shift Supervisor will notify the Site Manager of the injury.
- e. The Site Manager or his designated alternate should notify the injured person's family.
- f. PBNP 8.8, " Injuries, Accident Reporting & Industrial Safety" should be used for documentation and followup of the injury.
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W EPIP 11.3 Page 3 O
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2.1.4 Responsibility of Hospital Personnel Upon being notified that a seriously inj}}