ML20080M340
| ML20080M340 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 09/09/1983 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20080M321 | List: |
| References | |
| PROC-830909-01, NUDOCS 8310030624 | |
| Download: ML20080M340 (241) | |
Text
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September 9, 1983 b ~~
U/N f POINT EACH NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES
, The following revised procedures are attached and should be inserted into your manual. Please destroy all revisions removed from your manual.
- 1. EPIP 1.3, "Estimatiloa of Source Term," Revision 7, dated 08/26/83.
- 2. EPIP 1.4, " Radiological Dose Evaluation," Revision 8, dated 08/26/83.
- 3. EPIP 1.6, "Radiciodine Blocking & Thyroid Exposure," Revision 2, dated I; 09/09/83.
- 4. EPIP 1.8, " Emergency Off-Site Dose Estimations," Revision 4,' dated 08/26/83.
- 5. EPIP 2.1, " Unusual Event - Innediate Actions," Revision 2, dated 09/09/83.
- 6. EPIP 2.2, " Unusual Event - Plant & Company Personnel Notification, Revision 2, dated 09/09/83.
- 7. EPIP 2.3, " Unusual Event - Offsite Agency Notification," Revision 4, dated 09/09/83..
8.. EPIP 3.1, " Alert - Immediate Actions," Eevision 3, dated 09/09/83.
- 9. EPIP 3.2, " Alert - Plant & Company Personnel Notification," Revision 2, dated 09/09/83.
- 10. EPIP 3.3, " Alert .Offsite Agency Notification," Revision 3, dated 09/09/83.
I 11. EPIP 4.1, " Site Emergency - Immediate Actions," Revision 3, dated 09/09/83.
EPIP 4.2, " Site Emergency ~ Plant & Company Personnel Notification,"
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. 12.
! Revision 2, dated 09/09/83.
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- 13. EPIP 5.1, " General Emergency - Innediate Actions, Revision 3, dated 09/09/83.
- 14. EPIP 5.2, " General Emergency - Plant & Company Personnel Notification,"
Revision 2, dated 09/09/83.
- 15. EPIP 6.1, " Limited Plant Evacuation, Revision 3, dated'.09/09/83. -
8310030624 830928 PDR ADOCK 05000266 F PDR
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.EPIP's September 9,1983
- 16. EPIP 6.2, " Plant Evacuation," Revis' ion 3, dated 09/09/83.
- 17. EPIP 6.3, " Exclusion Area Evacuation," Revision 2, dated 09/09/83.
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,18.- EPIP 6.5, " Technical Support Center & Operations Support Center Activation,"
Revision 3, dated 09/09/83.
L 19. EPIP 6.6, " Plant Evacuation for Personnel Using North Gate," Revision 0, dated 08/26/83.
- 20. 'EPIP 7.1.1, " Chemistry & Health Physics Group Personnel Notification &
Initial Response When Chemistry & Health Physics Personnel Are On Site,"
Revision 3, dated 09/09/83. _
- 21. EPIP 7.2.1, " Activation of Health Physics Facilities at Site Boundary Control Center," Revision 3, dated 09/09/83.
- 22. EPIP 7.2.2, " Activation' of Chemistry & Health Physics At Technical Support Center / Operations Support Center," Revision 3, dated 08/26/83. -
- 23. EPIP 7.2.4, " Health Physics Communications," Revision 3, dated 09/09/83.
- 24. EPIP 7.3.2, " Post-Accident Sampling & Analysis of Potentially High Level Reactor Coolant," Revision 8, dated 08/26/83.
- 25. EPIP 7.3.3, " Pest-Accident Sampling of Containment Atmosphere," Revision 7, dated 08/26/83.
- 26. EPIP 7.3.5, " Post-Accident Sampling of the Auxiliary Building & Druming Area vent Stacks Using the Isokinetic Stack Sampling System, Revision 0, dated 09/09/83.
- 27. EPIP 8.1, " Personnel Assembly & Accountability," Revision 4, dated 09/09/83.
- 28. EPIP 11.1, "On-Site First Aid Assistance," Revision 4, dated 09/09/83.
- 29. . EPIP 11.2, " Injured Person's Inunediate Care," Revision 2, dated 09/09/83..
- 30. EPIP 11.3, " Hospital Assistance," Revision 4, dated 09/09/83.
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- 31. EPIP 12.1, " Reentry Procedures for Emergency Operations," Revision 2, dated 08/26/83.
- 32. EPIP 12.2, " Personnel Exposure & Search & Rescue Teams," Revision 3, dated 08/26/83.
- 33. EPIP 14.2, " Paging System Operation," Revision 0, dated .09/09/83. ..
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EPIP's
- September 9, 1983 The following procedure has been canceled. Please remove your copy from your manual and destroy.
EPIP 7.2.5, " Control s Use of vehicles," Revision 1, dated 03/17/82.
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The following revised forms are attached for insertion into your manual.
..Please attach the form to the indicated procedure and destroy all revisions removed from your manual.
- 1. EPIP-07 (09-83), "For X/Q Determination," (attach to EPIP 1.4).
- 2. . EPIP-08 (0943), " Estimated Whole Body & Thyroid Projected Doses " ,
(attach to EPIP 1.4) .
- 3. EPIP-09 (09-83), " Estimated Whole Body Dose Calculation Worksheet for Specific Noble Gas Releases," (attach to EPIP 1.4).
- 4. EPIP-10 (09-83) , " Estimated Ground Deposition Calculation Worksheet for Particulate Radionuclide Releases," (attach to EPIP 1.4). .
- 5. EPIP-11 (09-83), "Sununary of Radiological Dose Evaluation Calculations,"
(attach to EPIP 1.4).
- 6. EPIP-22 (09-83) , " Plant & Company Emergency Call List," (place after the call list tab).
- 7. EPIP-23 (OS83), "Offsite Agency Emergency Call List," .(place after the call list tab).
- 8. EPIP-24a (08-83), " Site Bcundary Control Center Emergency Plan Inventory Checklist," (attach to EPIP 7.4.1).
- 9. EPIP-24b (08-83) , "TSC (OSC), ESC & South Gate Emergency Plan Inventory Checklist," (attach tci EPIP 7.4.1) .
- 10. EPIP-24c (08-83) , " Emergency Plan Health Physics Supplies at Two Rivers Conununity Hospital Inventory Checklist," (attach to EPIP 7.4.1) .
- 11. EPIP-24d (08-83) , " Control Room Emergency Plan Equipment Inventory Checklist,"
(attach to EPIP 7.4.1) .
- 12. EPIP-24e (08-83) , " Emergency vehicle Inventory Checklist," (attach to EPIP 7.4.1) . .
- 13. EPIP-25a (08-83) , " Emergency VehicJe checklist," (attach to EPIP 7.4.2) .
- 14. EPIP-2Sb (08-83), " Monthly Health Physics Instrument & Air Sampler Functional .,
Test Checklist," (attach to EPIP 7.4.2) .
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EPIP's: September 9, 1983
'15. EPIP-25c (08-83), " Quarterly Emergency Plan Checklist," (attach to EPIP 7.4.2) .
- 16. EPIP-25d (08-83), " Semi-Annual & Annual Emergency Plan Checklist,"
(attach to EPIP 7.4.2) . .
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- 17. EPIP-28 (08-83)', " Emergency Plan Instrument Calibration Schedule,"
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(attach to EPIP 7.4.2) . ,
- 18. . EPIP-29. (08-83), " Emergency Plan Counting Equipment & Frisker Calibration Schedule," - (attach to EPIP 7.4.2) .
4 19. EPIP-30 (08-83), " Reactor Coolant Post-Accident Sampling Analysis Report," +
I (attach to EPIP 7.3.2) .
- 20. EPIP-34 (09-83) , " Calculation of Xe-133 Equivalent Release Rates,"
(attach to EPIP 1.8)..
- 21. EPIP-35 (09-83), " Dose Calculations," (attach to EPIP 1.8) . ,
- 22. EPIP-37 ' (09-82)', "Med! cal Assistance Call List," (attach to EPIP 11.1, EPIP 11.2 and EPIP 11.3). .
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. Flentje at the Point Beach Nuclear Plant. ,
i J. E. Knorr ( h a
cmz Ai.tachments
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EMERGENCY PLAN IMPLEMENTING PROCEDURES d SEPTEMBER 9, 1983 4
I hereby acknowledge receipt of EPIP 1.3, EPIP 1.4, EPIP 1.6, EPIP 1.8, EPIP 2.1, EPIP 2.2, EPIP 2.3, EPIP 3.1, EPIP 3.2, EPIP 3.3, EPIP 4.1, PiIP 4.2,' - ' - ~'
EPIP 5.1, EPIP 5.2, EPIP 6.1, EPIP 6.2, EPIP 6.3, EPIP 6.5, EPIP 6.6, EPIP 7.1.1, EPIP 7.2.1, EPIP 7.2.2, EPIP 7.2.4, EPIP 7.3.2, EPIP 7.3.3, EPIP 7.3.5, EPIP 8.1, EPIP, 11.1, EPIP 11.2, EPIP 11.3,- EPIP 12.1, EPIP 12.2 and EPIP 14.2 and have insertad them into my manual.
i Date
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TABLE OF CONTENTS l
I Revision Date 1.0 CLASSIFICATION & ASSESSMENT L .1.1 Initial Classification ........... 5 07-01-83
! 1.2 Plant Status . . . . .. ..... ..... 1 07-01-83 1.3 Estimation of Source Term . . . . . . . ... 7' 08-26-83 e 1.4 Radiological Dose Evaluation ... . .. .. 8 08-26-83 1.5 Protective Action Evaluation ... ..... 4 09-10-82 1.6 Radioiodine Blocking & Thyroid Exposure:
Accounting . . . . ....... ..... 2 09-09-83 1.7 Evaluation of Core Damage . . . . . . . . . . 2 07-01-83 1.8 Emergency Off-Site Dose Estimations . . . . . 4 08-26-83 l
2.0 UNUSUAL EVENT IMPLEMENTING PROCEDURES 2.1 Unusual Event - Immediate Actions . . . ... 2 09-09-83
- 2.2 Unusual Event - Plant and Company Personnel .
Notification . . . ... . . . . . . . ... 2 09-09-83 2.3 Unusual Event - Off-Site Agency Notification 4 09-09-83 I
( 3.0 ALERT IMPLEMENTING PROCEDURES 3.1 Alert - Immediate Actio'ns . . . . . . . . . . 3 09-09-83 3.2 Alert - Plant & Company Personnel Notification . . . . . .... . .. . .. 2 09-09-83 3.3 Alert - Off-Site. Agency Notification .. .. 3 09-09-83 4.0 SITE EMERGENCY - IMPLEMENTING PROCEDURES i.
4.1 Site Emergenc.y - Immediate Actions . . ... 3 09-09-83 4.2 Site Emergency - Plant & Company Personnel Notification . . . . . .. .. . . . . .. 2 09-09-83 4.3 Site Emergency - Off-Site Agency Notification 1 09-10-82 5.0 GENERAL EMERGENCY - IMPLEMENTING PROCEDURES 5.1 General Emergency - Immediate Actions . . .. 3 09-09-83 5.2 General Emergency - Plant & Company Personnel Notification . ..'. . . . . .. 2 09-09-83 5.3 General Emergency - Off-Site Agency Notification . . . . . . ... . .. ... 1 09-10-82 6.0 EVACUATION 6.1 Limited Plant Evacuation ... . . .. . . . 3 09-09-83 6.2 Plant Evacuation . . . .. ... ... . .. 3 09-09-83 a
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't $2 Revision Date 6'. 3 Exclusion Area Evacuation . . . . . . . . . . 2 09-09-83 6.4 Energy Information Center Evacuation .... 0 03-31-81 6.5 TSC & OSC Activation ........<.... 3 09-09-83 6.6 Plant Evacuation for Personnel Using North Gate . ................... 0 08-26-83 7.0 CHEMISTRY & HEALTH PHYSICS RESPONSE & PREPAREDNESS 7.1 Internal Chen & HP Group Personnel Notification /
Initial Response 7.1.1 Chem & HP Group Personnel Notification
& Initial Response when Chem & HP Personnel are On-Site ....... 3 09-09-83 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 Opera *_icns Personnel Prior to Arrival of Chem .
& HP Group Personnel . . . . . . . . 1 05-15-81 -
p 7.2 Health Physics Facility Activation Es
- . _j' 7.2.1 Activation of HP Facilities at Site Boundary Control Center ..... 3 09-09-83 7.2.2 Activation of HP Facilities at ,
Operations Support Center .... 3 08-26-83 7.2.3 DELETED 7.2.4 Health Physics Communications ... 3 09-09-83 7.2.5 DELETED 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 ............. 8 08-26-83 7.3.3 Post-Accident Sampling of Contain-ment Atmosphere ......... 7 08-20-63 7.3.4 Movement of Required Chemistry Equip-ment & Material to the Technical Support Center Counting Room.&
Mini-Laboratory ......... 0 12-30-81 7.3.5 Post-Accident Sampling of the Auxiliary Building & Drumming Are Vent Stacks ..
Using the Isokinetic Stack Sampling ..
System . . . . . . . . . . . . . . 0 09-09-83 9
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\. , Revision Date 7.4 Emergency Equipment 7.4.1 Routine Check, Maintenance, Cali-bration & Inventory Schedule for Health Physics Emergency Plan
, Equipment .... . . . . . . . . 7 05-27-83
- 7. 4.2 Emergency Plan Equipment Routine Check, Maintenance & Calibration Instructions . . . . . . . . . . . 5 05-27-83 7.4.3 Use of Baird Model 530 Single channel Iodine Spectrometer to Determine Airborne Iodine Activities . . .....e . . . . 1 05-15-81 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 &
Noble Gas Sampler / Detector . . . . 0 03-31-81 8.1 Personnel Assembly & Accountability . . . . 4 09-09-83 .
,-s 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 . . . . . . . . 4 09-09-83 11.2 Injured Person's Inmediate Care . . . . . . . 2 09-09-83 11.3 Hospital Assistance . . .. . . . . . . . . . 4 09-09-83 11.4 Personnel Decontamination . . . . . . . . . . 0 01-29-82 12.0 REENTRY & RECOVERY PLANNING 12.1 Reentry Procedures for Emergency Operations 2 08-26-83 12.2 Personnel Exposure & Search & Rescue ,
Teams . . .. . ... . . . . . . . . . . . 3 08-26-83 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. ,
09-09-83 14.2 Paging System Operation . . . . . . . . . . . 0
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, 15.0 TRAINING, DRILLS & EXERCISES Revision Date 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
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16.1 Nuclear Engineering Section Notification &
Response . . . . . . . . . . . . . . . . . . 4 07-01-83 f
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09-09-83 57h1 .
q ,/ TABLE OF EPIP FORMS EPIP EPIP Form Title Procedure '
g 01 Emergency Plan Airborne Radiation Survey Record Site Boundary Control Center (01-83) .
7.3.1 4- 02 - Emergency Plan Survey Record Site Boundary Control Center (01-83) 7.3.1 03 Dose Factor Calculations for Specific Noble Gas Analysis Results (03-81) 7.3.1 Status Report on Plant Systems & Controls for Affected 04 d Unit (01-83) .
1.2
. 05 Worksheet for Status Report on Radiation Monitoring System for Unit (07-83) 1.2 06 -Worksheet for Status Report on Radiation Monitoring System for Plant (07-83) 1.2
, 47 For X/Q Determination (09-83) 1.4 08 Estimated Whole Body & Thyroid Projected Doses (09-83) 1.4 "
09 Estimated Whole Body Dose Calculation Worksheet for . ,
Specific Noble Gas Releases (09-83) 1.4 10 Estimated Ground Deposition calculation Worksheet for
/'7'; Particulate Radionuclide Releases (09-83) 1.4 10a Estimated Population Dose.(09-82) 1.8
'J/ 11. Summary of Radiological Dose Evaluation Calculations (09-83) 1.4
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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 (C ,-82) 8.1 18- Assembly Area Roster (03-81) '
8.1 19 Drill / Exercise Scenario (03-81) 15.3 l 20 Drill / Observation Sheet (03-81) 15.3
! 21 Drill / Exercise Evaluation Report (03-81) 15.3 22 Plant & Company Emergency Call List (09-83) Call List Tab 23 Offsite Agency Emergency Call List (09-83) Call List Tab 24a Site Boundary Control Center Emergency Plan Inventory Checklist (08-83) 7.4.1 24b TSC, ESC, South Gate & OSC Emergency Plan Inventory Checklist (08-83) 7.4.1 24c Emergency Plan Health Physics Supplies at Two Rivers l
Community Hospital Inventory Checklist (08-83) 7.4.1 24d Control Room Emergency Plan Equipment Inventory Checklist - ' ~ ~
(08-83) 7.4.1 -
24e Emergency Vehicle Inventory Checklist (08-83) 7.4.1 24f Emergency Plan First Aid Kit Inventory Checklist (09-82) 7.4.1 i- <
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'J' Title-24g Emergency Plan Burn Kit' Inventory (09-82) 7.4.1 24h Emergency Plan First Aid Room Inventory (09-82) 7.4.1 241 Emergency Plan Stretcher Inventory (09-82). 7.4.1 24j Emergency Trauma Kit Inventory Checklist (09-82) 7.4.1 25a Emergency Vehicle Checklist (08-83) .
7.4.2 a, 25b . Monthly Health Physics Instrument & Air Sampler
- Functional Test Checklist (08-83) 7.4.2 25c' Quarterly Emergency Plan Checklist (08-83) . 7.4.2 25d Semi-Annual & Annual Emergency Plan Checklist (08-83) 7.4.2 26 Quarterly Communications Test (03-81) 14.1 27 Monthly Communications Test (01-83) . 14.1 28 Emergency Plan Instrument Calibration Schedule (08-83) 7.4.2 j 29 - Emergency Plan Counting Equipment & Frisker Calibration Schedule (08-83) 7.4.2 30 Reactor Coolant Post-Accident Sampling Analysis Report (08-83) .
7.3.2 31 Containment Atmosphere Po3t-Accident Sampling Analysis Report (07-83) 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 (09-83) 1.8 m 35 Dose Calculations (09-83) - 1.8
/ ' *. 36 Unused 7
,;. 37 Medical Assistance Call List (09-82) 11.1, 11.2 11.3 i'
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EPIP 1.3 MINOR Revision 7 08-26-83
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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 Buil' ding Vent, R14 (ABVNT) 1.2 Drumming Area Vent, R21 (DAVNT) 1.3 Gas Stripper Building Vent, RE-224 (GSBVNT) .
1.4 Unit.1 Containment Purge, IRE-305 9 1.5 Unit 2 Containment Purge, 2RE-305 1.6 Combined Air Ejector Decay Duct, RE-225 (CAE) ,
1.7 ' Main Steam Safety Valves and Atmospheric Dump Valves, 1(2)RE-231 and 1(2)RE-232 r
2.0 REFERENCE 2.1 EDS Report to Wisconsin Electric Power Company concerning NUREG-0578, -
March 7, 1980.
3.0. PRECAUTIONS 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 (1R9) or the failed fuel radiation monitor (2RE-109) may be unusually high or offscale.
3.1.2 The containment radiation monitors (IR11 and 1R12 or 2RE-211 and 2RE-212) may be unusually high or offscale.
i 3.1.3 The containment area monitors (1R2 and 1R7 or 2RE-102 and ' - -~
2RE-107) may be unusually high or offscale. ~~
, 3.1.4 The charging pump area monitor (IR4 or 2RE-104) may be unusually high or offscale.
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3.2 - 1: ?.1th 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 auxi.liary building or facade to take a contact reading on any stack.
- 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 projected 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.
6 5.0' PROCEDURE FOR Xe-133 EQUIVALENT 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
<C's 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 l ON WORKSHEET NO. 1 AND THEN PROCEED WITH STEP 5.1.3.
NOTE: PLANT EFFLUENT VENT STACK MONITOR READINGS ARE ALSO AVAILABLE FROM THE TECHNICAL SUPPORT CENTER DATA LOGGER. SEE ATTACHMENTS 1.3-1, 2 & 3.
5.1.2 Enter the meter readings in the appropriate column on Work-sheet No. 1 for the indicated vents. If the readings are f- 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 l- obtain meter readings of the vents whose Eberline RMS monitor l readings are unavailable by performing Section 5.2 of this procedure, if required. _
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NOTE: IF STEP 5.1.3 NEEDS TO BE COMPLETED BECAUSE EBERLINE l' i RMS MONITOR READINGS ARE UNAVAILABLE, THEN PERFORM
- l. _ . . SECTION 5.3 0F THIS PROCEDURE AFTER APPROPRIATE
. MEASUREMENTS HAVE BEEN TAKEN IN SECTION 5.2.
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5.1.4 Perform Section 5.3 of this procedure to determine the estimated Xe-133 equivalent release rate.
5.2 Direct Stack Survey Team Designees 5 NOTE: THE FOLLOWING SECTION WILL NOT BE INITIATED UNTIL TIIE EVALUATION DISCUSSED IN PRECAUTION 3.3 HAS BEEN COMPLETED AND
'.' THE SITE MANAGER (DUTT & 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.
a 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
,C and record the survey instrument reading in contact with the stack in the columns provided on Worksheet No. 1, Part C, G 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 CONTAINEENT.
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 ho.1 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.
5.3.2 Use the appropriate conversion factors for each of the plant effluent vent to convert the chosen vent etack readout, (cpm, pCi/cc or R/ hour) from Step 5.3.1 go an Xe-133 equivalent--
release rate in curies /second and record the value on Worksheet No.1, Part F, Estimate of Gross Xe-133 Equivalent Release Rate. Enter the appropriate 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 MUST BE RECOGNIZED.
, _ - - - . _ _ - . . _ , ~ . . _ _ - . - - _ . . . _ _ __ _ _ . _ _ _ _ _ __ ~ _ _ _ _ . . _ _
a_ ;.;e _m=usw :t = ~. n-;awmmu :www.g.xuww_
EPIP 1.3 t M, Page 4 p.,c-7 WEY f~~ 1. If the actual flow rate is different than 'the assumed conversion factor flow rate, a ratio of:
Actual Flow Rate Assmed Flow Rate
~
should be applied to determine the release rate.
(Ratio) x Release Rate Value = Adjusted Xe-133 Release Rate
- 2. Determine the steam line atmospheric vent, or the
- main steam header vent release rate in accordance.
f with the following:
- a. Obtain from the Shift Supervisor an estimated flow rate through the main steam header in Iba/ hour of steam being dumped to the environ-
, ment and the specific volume (v) of the steam. ,
NOTE: AT 1000 P3IA, SPECIFIC VOLUME IS
,-3 0.446 FT 3/LBM.- AT 500 PSIA, SPECIFIC
,fj ,
VOLUME IS 0.928 FT8 /LBM.
J C lbm/hr x v x 7.86 ft
- l:
t
- b. Convert contact reading, if required, the main steam header to pCi/cc using the appropriate conversion factor (Worksheet No. 1 Sect. C).
i pCi/cc NOTE: ACTUAL pCI/CC READINGS ARE AVAILABLE FROM STEAM LINE MONITORS 1RE-231, 1RE-232, 2RE-231 AND 2RE-232.
l
- 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.
Main Steam Header Flow Rate
- Concentration (pCi/cc)
~
Release Rate (cc/sec.)
5.3.2 Sum the values (1) through (5).on Worksheet No. 1, Part F, ' ' '
or use grab sample results #7 on Worksheet~No. 1, Part F, ~
to determine the gross Xe-133 equivalent release rate.
l.
y,s . , .-
,- ;;.g_. . y .. ,,
.q ; .
. _ ,. 3 ga w_/m.
k EPIP 1.3
- Page 5
>'D
.,,0 c.-
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.
5.3.3 Report the calculated gross Xe-133 equivalent release rate to the Shift Supervisor and the Technical Support Manager.
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. a ,.c WORKSHEET NO. 1 Xe-133 EQUIVALENT RELEASE RATE A. OPERATIONAL LOW-RANGE RELEASE MONITORS READ 0UTS t$ Xe-133 Equiv.
Flow Rate Conversion Release Rate Meter Reading (cfm) Factor Ci/sec
. 9 i Auxiliary Building Vent 5.8 x 10 cpm 61400
. s Drumuming Area Vent cpm 43100 . 1.3 x 10 U1 Containment Purge, 1 fan cpm 12500 2.1 x 10 s i fans cpm 25000 4.2 x 10s
~
U2 Containment Purge, 1 fan ~ eps 12500 2.~1 x 10 6 -
I H 2-fans eps 25000 4.2 x 1(fs q
. Gas Stripper Building Vent pCi/cc 13000 6.2
_ 2 Combined Air Ejector pCi/cc 25 1.6 x 10 Steam Line Atmospheric vent pCi/cc Refer to Seetion "E" B. EBERLINE RMS - II !ENT STACK READOUTS NOTE: THESE READINGS ARE ALSO AVAILABLE ON THE TECHNICAL SUPPORT CENTER DATA LOGGER. ATTACHMENTS 1.3-1, 2, 3.
l
!~
Xe-133 Equiv.
Meter Reading Flow Rate Conversion Release Rate
! (R/ hour) (cfm) Factor Ci/sec 3
Aux. Building Vent, Ch. #1 61400 3.0 x 10 Drununing Area Vent, Ch. #2 43100 2.1 x 103 U2 Containment Purge 12500- 1.6 x 104 25000 3.2 x 10 4 U1 Containment Purge 12500 1.6 x 10 4
~
25000 3.2 x 104 l 2 GS Bldg. Vent, Ch. #6 13000 6.2 x 10 Combined Air Ejector
- Decay, Ch. #5 25 3.4
,r - , , , , .*,r+.,- .y., ,,d
_~- -
__ w. a. -
_;. . -- e . , a ~ :~-:. ~cnaugt
';*l : j C. PLANT EFFLUENT VENT STACK CONTACT READINGS Xe-133 Equiv.
Meter Reading Flow Rate Conversion Release Rate Vent (R/hr) (cfa) Factor Ci/sec Auxiliary Building 61400 300
- l. 2-
! Drunuming Area 43100 2.3 x 10 -
1 U1 Containment Purge 12500 8.0 x 101 25000 1.6 x 102 I
- U2 Containment Purge 12'500 8.0 x 101 25000 1.6 x 102 4
Gas Stripper Building 13000 8 x 10
~
2 '
Combined Air Ejector Decay 25 1.6 x 10
/%- Main Steam Header Refer to Section "E"~
,? .;
'D; D. ' ACTUAL VERSUS CONVERSION CURVE FLOW RATE RATIO Actual Flow Rate x Release Rate Value = Adjusted Releast Rate Assumed Flow Rate
( )x =
E. STEAM HEADER XE-133' EQUIVALENT RELEASE RATE CALCULATION
- 1. lbm/hr x specific volume, ft3 /lbm x 7.86 cc-hr/ft 3-sec NOTE: At 1000 psia specific volume = .446 ft 33/lbm At 500 psia specific volume = .928 ft /lbm 3
lbm/hr x it 3/lbm x 7.86 cc-hr/ft -sec
= cc/sec
- 2. Contact reading from Section C (if contact reading used):
R/h'r x 8.0 x 102 pCi/ hrs = Ci/cc
~ ' "
NOTE: IF 1RE-231, 1RE-232, 2RE-231 OR 2RE-232-(STEAM LINE MONITORS) ARE AVAILABLE,_.THE CONCENTRATIONS CAN BE USED DIRECTLY IN E.3.
_[ A _ _--
w.1_"- aes .: -: _ ma '2hcd5 C'-
, "N c,;:1
- 3. Steam header release rate:
Flow rate cc/sec x Concentration pCi/cc = Release Rate
_6
, cc/sec x x 10 Ci/cc = Ci/sec Step E.1 Step A.7 or E.2 F. ESTIMATE OF GROSS Xe-133 EQUIVALENT RELEASF RATE Xe-133 Equivalent Release Rate Vent (Curies /Sec.)
.l.-Auxiliary Building
- 2. Drumming Area
, 3. Gas Stripper Building
- 4. Combined Air Ejector Decay Duct
~5. Main Steam Header
- 6. Unit 1 Containment Purge
- 7. Unit 2 Containment Purge ;
..= 8. Sun (Gross Xe-133 le Equiv. Release Rate) 0_R
- 9. Grab Sample Results = Ci/sec.
Completed By Time Date
- 6 e , - - - - - - , - ~ , , , - , - - , - - - - -
.---w -e,,- ,,,, ,e--, -,_n.,- , - - - - - - , - ,e- - - , - , - , ,,-,w,.-e vy,-g- --n-w., ,,,w- --
- aw _ w :.n c w ,-w , c. , ,_ ~ v. , . c uwp 7 -
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ATTACHMENT 1.3-1 6-t
't h_D
(,9j DRCCCNG AREA VENT S ' TACK EMS-II CH #2 &
"~~'
COMBIND AIR EJECTOR DISCHARGE DIS-II CH a5 VOI.TAGE TO R/HR CONVERSION TABLE E - RANGE 1 to 10" R/HR
- lolts Units R/hr ,
0 0.001' O.1 0.00135 O.2'- 0.001847-
' O.3 0.002511 0.4 -0.003414
'O.5 , 0.004641 0.6 0.006309 O '. 7 0.008576
~
0.8 0.011659- .
0.9 0.015848
.1.0 0.021544
,/ Eh 1.1' O.029286 *
-.( ' - ;)
2 1.2- ,
0.039810
- 1.3 .0.054116 1.4- 0.073564
-1.5 0.100 1.6 0.135935 1.7 0.184784 1.8 0.~251188 ,, . ,
1.9 0.341454 - .
2.0 0.464158
> 2.1 0.630957 -
2 .'2 0.857695 2.3 1.165914 2.4 1.584893 :
2.5 2.154434 .
2.6~ 2.92S644 ' ,
2.7 3.981071 ,
2.8 5.411695 ' t 2.9 7.356422 '
3.0 10.0 .
5
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'e i , 'e ATTACHMENT , 1.2-2' '
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' CONTAINMENT P*TRGE STACTS
/ ,
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VOLTAGE TO R/HR CONVERSION TABLES ii ,
ROIGE 10" TO 10* R/HR \ 'l
\ , ,~ < - ; t
) .i .; ,
i
- I Volts-Unite - R/HR c 3
+
.A r
- 3
. - I. .&,
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5 40.1, ,
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. 135.
+
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- 0.3 4.I51 ,
i 0.4 *
-. 341 ' . .J .
0.5 .454 - .
0.6 ;630 .
' .s '4 0.7 .857 '
. s .o 1.165
...s ' O.8 '\q ,;
/ 7,7l 0.9 x 1.594 ?; s ' l, V; .
,1. - , r.154 4 l.1 ',
'2.928 '
s 1.2 .\
3iSS1 ' -
1.3 5.411
- 1. 4 -: 7.356 ,
- 10. N 1.5 l.6 13.593 .
l.7 18'478 l g' l.8 25;118 '
l.9 342f45
- 2. _46.415 , 1 2.1 4
. . 6 3.0 95 --
2.2 G5.769 2.3 116.591 ~
2.4 158.483 .
215.443.
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2.6 292.964 2.7 ,398.107 2.8 541.169 2.9 . 735.642
- 3. ,
1000. ,
4 T
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p.- --p.Wr-- 4 y.-T F t h & F -t@ 5O -
T T-""T %
.. . . . + y a n.p.. ,.s..., . _ ,,
_g.,
,. ATfACHMENT 1.3-3 i
,% AUXILIARY BUILDING VENT STACK RMS-I* CH #1 &
GAS STRIPPER BUILDING VENT STACK RMS-II CH #2 g ,
s VOLTAGE TO R/HR CONVERSION TABLE RANGE 10~' TO 10' R/HR
' f.
Volta Units - R/HR
- d. 0.01 0.1 .013
'O.2 .018 0.3- .025 '
. 0.4
.034
.046 O.5
.063
~
0.6 0.7 .085 0.8 :.116 0.9 .158
- 1. .215 -
1.1 .292
. 1.2 .398
[Gh, 1.3 .541 c, -a 1.4 .735
' c9 1.5 1.
1.6 1.35 1.7 1.847
( 1.8 2.511
!- 1.9 3.414
- 2. 4.641 2.1 6.309 g 2.2 8.576 2.3
^
11.659 2.4 15.848 2.5 21.544 2.6 29.286 2.7 39.810 2.8 . 54.116 2.9 73.564
- 3. 100.
4 sg a
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- .. - =i. .
o- ey , = . e_
g46,g O . (e, ,,Q. __
p . .
EPIP 1.4 MINOR
. j. g Revision 8 08-26-83 0.-;
c.'29)
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 RC Regulatory Guide 1.109, Calculation of Annual Doses to Man t 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 Projectad Thyroid Dose and Projected Whole Body Gamma Dose from Exposure to Airborne Radioiodines and Radioactive Noble Gases."
- 2.3 U. S.~ NRC Regulatory Guide 1.4, " Assumptions used for Evilluating the Potential Radiological Consequences of a Loss-of Coolant Accident for Pressurized Water Reactors," Revision 2,' June 1976.
2.4 - TID 14344, " Calculation of Distance Factors for Power and Test Reactor Sites," March 23, 1962.
3.0 PRECAUTIONS & LIMITATIONS 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 The responsibility for implementation of this procedure will be , .
assumed by ESC personnel after activation of the ESC. .
e- --- ,.,,.ww
---==~y- m,.,,,,,,4g-no--,a .,,,m ---p-,v.nn.,e --,.,e--.. --,e-.- -r,-w.-- .e--~ ~ , , - - .w,-p - - m . m w ww,,-- . ,,e e -----w. e.< .. ,,e w -
b.x. a . .: .
a B.i ~ .as x.c::r e >
a' - % &Jn_ .-
EPIP 1.4
. Page 2 ,
- Q)
,a:
3.4 Wind speed and wind directia, nust be average values obtained from the analog recorders in the control room.
NOTE: DO NOT USE INSTANTANEOUS VALUES.
9 3.5 If the radiological release duration is unknown, assume a duration 1 -
of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
~
3.6 If the meteorological parameters cannot be obtained from the control room,' obtain the data from the following priority backup list.
3.6.1 Kewaunee Nuclear Power Plant. See EPIP-23, "Offsite
, Agency. Call List."
-t ,
.l.
g 3.6.2 National Weather Service in Green Bay. Ask for Two Rivers
" Coast Guard information, if available. See EPIP-23, "offsite Agency Call List."
4.0 INITIAL CONDITIONS 4.1 A release of airborne radioactivity has occurred or a release is
- anticipated, ne
,1 y; .6 4.2 An emergency or potential emergency condition is anticipated to have offsite dose consequences.
.\
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 f
EPIP-04 (a) wind speed in-mph EPIP-04 (b) wind direction EPIP-04 (c) time of reactor thutdown EPIP.-04 (d) time of release to containment EPIP-04 (e) time of release from the plant 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 a0 degrees-NOTE: IF RELEASE DURATION IS UNKNOWN, ASSUME 8 HOURS.
e
- P t w' t -
e-- t* v--*'-v----- e---*--*e"-r--'t--w----s- -e-v--+=--ut=-- e8*i* -
--+-- -----=-w v --se -* --ee- *w-- W - - - - *ei- --- v*c:8==p-eww-** w'rev-r--- - -" - * ' - ' -
^
. : 2 . - ~ ,. ,_- .- . : ,7.g .g _; ; a_ _ , sijgy . ~mc_.w3 y m . ;
EPIP 1.4 Page 3
. ,t 5.1.2 Determine -t?bility class by use of the c0 or AT chart recorder values in the control room and Attachment 1.4-1.
Enter the stability class (h) on form EPIP-07.
NOTE: DO NOT USE 06 FOR WIND SPEEDS <3 MPH.
i 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.
L 5.1.4 Place the overlay corresponding to the stability class on -
the map. _ Using the plant location as a pivot point, align l- s
! the centerline of the overlay to the downwind direction from C the plant.
NOTE: THE " TICK" MARKS ON THE CENTERLINE OF THE OVERLAYS i: ARE ONE MILE APART.
t 5.1.5 Determine the distance (i) to the dose projection location if different from the standard centerline distances listed on fo.m EPIP-07. Note the location description, sector, and distance on form 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 obtained 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 fona 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.
l-
! Example:
8 m 2 Class "C" Xu/Q for 5 miles equals 1.21 x 10 5.1.5 Calculate the X/Q value from the Xu/Q va.lue by using the equation:
( _
X sec. = 2.24(sec./m) X WindK"/Q (* )
Speed (mi/hr.)
Q. m 3 (hrs./mi) j Enter the X/Q values on form EPIP-07.
. . _ _ . - -_ _ , . - . _ _ _ _ . - _ . _ . . _ - _ _ . - . _ . - . - . . _ _ _ - _ . __ - . . . _ _ _ . . _ . _ . _ . . ~ . _
. . ,u. , , . ' .
. : :[ _x
_w EPIP 1.4 Page 4 Q.3,1
[ i, .
y 5.2- Whole Body P.m Estimate NOTE: IF THE NOBLE GAS SOURCE TERM IS DETERMINED BY GRAB SAMPLE
< RESULTS WHICH GIVZS AN INVENTORY OF SPECIFIC NUCLIDES, THEN A CONSERVATIVE WHOLE BODY DOSE ESTIMATE CAN BE MADE BY L COMPLETING FORM EPIP-09.
5.2.1 Enter the ' gross Xe-133 equivalent release rate (g) on form EPIP-08 from form EPIP-07.
5.2.2 Enter the estimated release duration, ERD, in hours (f) on form EPIP-08 from form EPIP-07.
, 5.2.3 - Calculate the projected whole-body ' dose on form EPIP-08 by
.using the equation:
(k)- (g) 3 3 D(Rem) = X/Q (sec/m ) x Q (Ci/sec) x Kr (Rem m /Ci - Hrs) x ERD (Hrs) .
where: -
f . . n, D = whole body dose (Rem) r 1 NC# X/Q = atmospheric dispersion coefficient determined in Step 5.1.5 (sec/m3 ) (k)
Q = release-rate (Ci/sec) (g) 3 Kr=DoseFactor([*"h g ) Attachment 1.4-2 ERD = Estimated Release Duration (Hours) (f) 5.3 Thyroid Dose Estimate l
l 5.3.1 Calculate the projected thryoid dose by using the whole body j
dose calculated in Section 5.2 of c.his procedure.
5.3.2 Record the projected whole body dose on form EPIP-08 in l
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.'4-2.' -
- c. Fuel Handling Accident - Figure 1.4-3.
d ' Steam Generator Tube Rupture - Figure 1.4-4. .
- l NOTE: IF THE TYPE OF ACCIDENT IS UNKNOWN, USE THE LOCA FIGURES.
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EPIP 1.4 Page 5 n,..
- y. .]
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 EPIP-08, Section 2.
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 I' FORM EPIP-10 CANNOT'BE COMPLETED, PROCEED WITH STEP 5.4.5
'8 0F THIS SECTION.
5 . 4 . 'A 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 estimat.d duration of release (f) from form
- ,.... . EPIP-07 on form EPIP-l').
3
(. _./ 5.4.3 Enter the value of X/Q (k) ou 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/m 2 ) = F x .05 (m/sec) x 3600 (sec/hr) x 10 8 (pci/Ci) x X/Q (sec/m3) x Q (Ci/sec) x ERD (hrs) 8 (k) (g) (f)
Dep = F x 1.8 x 10 x X/Q x Q x EIP
. 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 t
(unitiess) -
3600 = conversion (sec/hr)
?
10s = conversion (pCi/Ci) 0.05 = assumed deposition velocity (m/sec)
- - - - - , . - . -. - . - . . - _ - . . . . - - . . - . - . - . - -~ - , -
- ~
- _ :=_ - e =: -u _-- w-~. . ,_
EPIP 1.4 Page 6
.)
5.4.5 Complete form EPIP-ll from available data and calculations just performed.
5.4.6 Enter the date and time of these calculations and sign form
-EPIP-ll.
5.4.7 Forward completed attachments to the Technical Support Manager for. review. The Technical Support Manager will relay results to the Site Manager.
5.5 Population Exposure 5.5.1 Calculate projected population exposure by using form
-EPIP-10a.
5.5.2 Enter from EPIP-08 whole body dose from center line on form EPIP-10a.
5.5.3 Enter population figures from Attachment 1.4-4. Use population number corresponding to the quadrant and distance categories .
for dose. -
l'
'f s .5.5.4 Total population dose from each radius to find total population dose. .
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's ATTACHMENT 1.4-1 CLASSIFICATION OF ATMOSPHERIC STABILITY BY SIGMA THETA Stability- Pasquill as AT/6H C_lassification Categories (decrees) . (*F)
Extremely unstable A 00 2 22.5 <-1.2 Moderately unstable B 22.5 > 00 2 17.5 -1.2 to -1.1
, Slightly unstable C 17.5 > 00 2 12.5 -1.1 to -0.9 Neutral D 12.5 > 00 2 7.5 -0.9 to -0.3 Slightly stable E 7.5 > 00 2 3.8 -0.3 to 0.9 . Moderately stable F 3.8 > 00 2 2.1 0.9 to 2.5 ,
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ATTACHMENT.1.4-2 WHOLE BODY DOSE RATE CONVERSION FACTORS
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_ a + ~a._-- :: a a :x a na.-... -. L. e N]~ .y ATTACHMENT 1.4-3
, BACKUP DETERMINATION OF ATMOSPHERIC STABILITY CLASS
( Surface Wind Speed, Day Night (at 50 meters) Incoming Solar Radiation . Thinly Overcast mph Strong Moderate Slight > 1/2 low cloud < 1/2 cloud
<4 A A-B B F G l 4-7 A-B B . C E F 7-11 B B-C C' D E 11-13 C C-D D D D
>13 C D D D D The neutral class D, should be assumed for overcast conditions during day or night.
" Strong" incoming solar radiation corresponds to a solar altitude greater than -
60* with clear skies; " slight" incoming solar radiation corresponds to a solar. (yr ,q altitude from 15'-35' with clear skies. Cloudiness will decrease incoming solar
~
- f. . radiation and should be considered along with solar altitude when determining
'- # solar radiation. Incoming radiation that would be strong with clear skies can 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.
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EPIP 1.6 MINOR O Revision 2
!;{}. 09-09-83 RADI0 IODINE BLOCKING AND THYROID EXPOSURE ACCOUNTING
, 1.0 GENERAL Potassium i~odide, a stable iodine, may be used in the event of a plant
- emergency as a blocking agent to prevent the uptake of radioactive iodine l by the thyroid gland. The thyroid gland, which is located at the base of the neck, depends upon iodine for the synthesis of the thyroid hormones and is normally supplied through one's diet. The thyroid is capable of absorbing and storing only a limited amount of iodine et any one time and excess amounts ingested are eliminated in the urine. Therefore, the use of stable iodine will prevent unnecessary thyroid exposure.
2.0 REFERENCE 2.1 . Letter Erwin S. Huston, M.D. , dated November 6,1980, and attachment :
" Protection Against Radioactive Iodines."
/N 3.0 PRECAUTIONS 3.1 Potassium iodide will only be ackninistered to personnel as approved by the Company Medical Director consistent with this procedure.
3.2 The use of potassium iodide will be authorized by the Health Physics Director or the senior Health Physics Supervisor on site. 3.3 After an initial dose (one tablet) of potassium iodide has been ackninistered, its continued use on a daily basis will be determined by the Company Medical Director or other designated physician. 3.4 A roster of plant personnel authorized to use potassium iodide as a blocking agent will be maintained at the operations support center, and the control room. 3.5 A copy of the pharmaceutical company instructions for the use of potassium iodide tablets is. reproduced on Attachment "A" to this procedure. This is furnished for information only. 4.0 STORAGE LOCATION Single dose 130 mg tablets of potassium iodide will be stored in the emer-gency lockers located at the operations support center and the control room. The shelf life of potassium iodide tablets are as indicated on the _ pharmaceutical container. p
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l EPIP 1.6 l
.y Page 2
/' 3 .
v 5.0~ n IE ADMINISTRATION
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In the event of an emergency, potassium ' iodide will be administered to plant personnel if it is expected that the projected dose to the thyroid of l the particular individuals who may be exposed during any working period j
.might exceed 0.9 Rem total dose commitment (equivalent to one maximum i permissible body burden from I-131) due to radioiodine concentrations in I breathing air.
1
-Individuals will not be routinely exposed to greater than 40 MPC-hour equivalent dose'in any seven consecutive days whenever practicable..This guideline will be exceeded only during unusual emergency conditions where quick. response is essential or protective response is impossible based on the current circumstances.
- 6.0 THYROID EXPOSURE CALCULATIONS 6.1- The dose to the thyroid from airborne concentrations of radioiodine may be calculated as follows. .
6.1.1 Total Dose Commitment, RADS /pci, Inhaled Conversion Factors b I-131 1.480 RADS /pCi
-k. / I-132 I-133 0.054 R&DS/pci 0.400 R&DS/pCi I-134 0.025 RADS /pCi I-135 0.124 RADS /pCi 6.1.2 The total amount of radioiodine inhaled in pCi is calculated by multiplying the average airborne concentratien in pCi/cc by the breathing rate in cc/ hour by the total time of exposure in hours. The thyroid exposure in RADS is then calculated by inultiplying the total amount in pCi by RADS /pCi in the above table.
6.1.3 Breathing Ratrs
- a. Assume 1.25E06 cc/ hour (= 3.47E-043m /sec.) for short exposure times or exposures while working.
- b. Assume 8.35E05 cc/ hour (= 2.32E-043m /sec.) for long exposure times (in excess of a single day).
6.1.4 If the concentration of each iodine isotope is not known, conservatively apply the dose factor for I-131 as given above towards the total gross iodine. activity determinated. . se
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EPIP 1.6
- p. Page 3
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6.1.5 Example Gross Iodine = 5.4E-07 pCi/cc in air Breathing Rate = 1.25E06 cc/heur Expected Exposure Time = 1 hour I-131 RADS /pCi = 1.48 Calculation: 5.4E-07 pCi/cc X 1.25E06 cc/ hour X 1.48 R&DS/pci X 1 hour
= 0.999 RADS Exposure to the Thyroid 6.2 ' Other Data Associated with Radioactive Iodine Exposures si See Attachment 1.6-1. ,
7.0 DOSE ACCOUNTABILITY FOR EXPOSURES TO AIRBORNE RADIOIODINE' It is imperative that accurate exposure times and radiciodine [V , 7.1 concentrations encountered be maintained for each individual's-exposure to an airborne radioiodine environment for dose calculation purposes. 7.2 The following minimum information should be documented for each exposure. 7.2.1 Date and time. 7.2.2 Names of individuals involved. 7.2.3 Duration of exposure. 7.2.4 Concentrations of airborne radioiodine. 7.2.5 Reference to specific analysis by sample number or manner in which concentration of airborne radioiodine was derived. 1 aews
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i [ f-ATTACHMENT 1.6-1 r-OTHER DATA ASSOCIATED WITH RADIOACTIVE IODINE EXPOSURES P-r I is. Soluable Iodines 131 132 133 134 135 h L MPC Air Occupational 9 x 10-8 pCi/cc 2 x 10-7 pCi/cc 3 x 10-s pci/cc 5 x 10-7 pCi/cc 1 x 10-7 pCi/cc , MPC Air Gen. Public 1 x 10-10 pCi/cc 3 x 10-8 pCi/cc 4 x 10-10 pCi/cc 6 x 10-8 pCi/cc 1 x 10-9 pCi/cc Maximum Permissible l' Body Burden 0.7 pCi 0.3 pCi 0.3 pCi 0.2 pCi 0.3 pci . 1.2 Mev t( Average Energy 0.23 Mev 0.65 Mev 0.54 Mev --- f-V 40 HPC-hr. Equiv. 0.324 pCi W.B. 7.200 pCi W.B. 1.080 pCi W.B. --- --- 520 MPC-hr. Equiv. 4.212 pCi W.B. 93.600 pCi W.B. 14.040 pCi W.B. . --- --- 5,
% to Organ of Interest --- --- --- ---
Inhalation 23% 23% 23% 23% 23% [' Ingestion 30% 30% 30% 30% 30% p.
- i. .
Quality Factor (Thyroid) 0.20 --- --- --- --- RADS /pci Inhaled 1.48 RADS 0.054 RADS 0.40 RADS 0.025 RADS 0.124 RADS Half-Life, T'-s 8.0 days 2.3 hours 20.8 hours 52.6 min. 6.6 hours j [' c
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- Attachment 1.6-1, continued ...
Useful Equations: hoseRate-R= m i R = Dose rate to organ of interest, Rem / day 1. I q = Body burden, pCi 4 m = Mass of the organ of reference, gm E = Effective energy per disintegration, Mev/ dis f = Fraction of the radioactivity in body whict.' is in organ of reference Q.F. = Quality factori Rem / day Dose Commitment - DC (Acute Uptake) DC = 74 E q, T/m ! Units as described above. T = Effective half life in days i . f 4 l l e
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. EPIP 1.6 ATTACHMENT "A"
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O' This attachment is furnished for information only. The administration of potassium will be as stated in procedure EPIP 1.6. Posent Poetimes insert For HOW POTASSIUM IODIDE VIORKS Certain forms of ladia= help your thyroid gland work right. Moet people get the iodine they need from foods, like iodized salt or ash. The thymid can store" or hoid only a catain amount of THYRO BLOCK" ladim In a radiation essergency, radioactive iodine may be released in (POTAselues socical the air. This material may be breathed or swaHowed. It may (pronounced pos Tass +um EYE.oneyed) enter the thyroid gland and damage it. The damage would pro-(atiewonesed:K4 - bably not show itself for years. Chddren are most likely to have TAeLETS and SOLUTION U.S P. thyroid damage. l If yon take potassina iodide, it will fill up your thyroid gland. t- 'linie reduces the chance that harmful radioactive iodine will
"*" O' 07 " - TAKE POTASSIUM IODIDE ONLY WHEN PUBLIC HEALTH OFFICIALS TELL YOU. IN A RADIATION WHO SHOULD NOT TAKE POTASSIUM IODIDE EMERGENCY, RADIOACTIVE 10 DINE COULD BE ,Ik only papis wb abouM nu tah pa* ===n===== lodMe me pople RELEASED INTO THE AIR. P(yrASSIUM IODIDE (A wk know thy me hgic 2 m You may tah psamium FORM OF IODINE) CAN HELP PROTECT YOU. iodide even if you are taking a== die === for a thyroid problem (for
- ====pla a thyroid hormone or antithyroid drugt. Pregnant and IF YOU ARE TOLD TO TAKE THIS MEDICINE, TAKE IT namns women and kbiu and chddren may aim uh eis drug.
ONE TIME EVERY 24 HOURS. DO NCT TAKE IT MORE . OFTEN. MORE WILL N(Fr HELP YOU AND MAY IN- HOW AND WHEN'TO TAKE POTASSIUM IODIDE ~ CREASE THE RISK OF SIDE EFFECTS. DO NOT TAKE Poteesium Iodide should be taken as soon as posenble atter ~ THIS DRUG IF YOU KNOW YOU ARE ALLERGIC TO y ,gga g ,gs g g ,g,g, u g y ,yaa ,g a g g ,y a ,,ga ,, ,,,y g 4 IODIDE. (SEE SIDE EFFECTS BELOW.) bon More wGl not hip you beaum th eyroM can bM*' on-m ly limited amounts of iodine. Larger doses willincrease the risk
- ^ of side eNects. You will probably be told not to take the drug for more than 10 days.
INDICATIONS SIDE EFFECTS THYROID BLOCKINO IN A RADIATION EMERGENCY Usually, side effects of potassium lodide happen when people ONLY. take higher doses for a long time. You should be careful not to take more than the racammanded dose or take it for longer than DIRECTIONS FOR USE you are told. Side effects are unlikely because of the low dose and i Use only as directed by State or local public health authorities in the short time you will be taking the drug. the went M a radiation omwsoney' Pcseible side effects include skin rashes, sweihng of the salivary l- DOSE glands, and "lodism"(metallic taste, burmng mouth and throat, Tablete: ADULTS AND CHILDREN 1 YEAR OF sore teeth and gums, symptoms of a head cold, and sometimes AGE OR OLDER: One (1) tablet once a se-meh upset and diarrheal. day. Crush for smallchGdra A few people have an allergic reaction with more sonous symp-BABIES UNDER 1 YEAR OF AGE: tems. These could be feyw and joint pains, or sweihng of parts of One half (1/2) tablet once a day. Crush the face and body and at times severe shortness of breath requir-( first. ing immediate medie=1 attention. I Solution: ADULTS AND CHILDREN 1 YEAR OF .g. g ,,7 ,,,, ,,,,ggyigy g gg gy,g o d day. gland, undanctivity M de thN gland, w &gunent M de mymid sland(sh ! BABIES UNDER 1 YEAR OF AGE:
- i Add 3 drope to a small amount of liquad WHAT TO DO IF SIDE EFFECTS OCCUR If me sMe diects am mven w if you han an aHwsic maction, For off dosage forms:T for 1 days unless directed otherwise stop taking potassium iodide. Den, d poes&le, can a doctw or by State or local public health authorities. public health authority for instructions.
Store at controlled room temperature between 15' and 30*C (59' to 86'F). Keep container tightly closed and protect from light. HOW SUPPLIED Do not use the solution if it appears brownish in the nossie of the THYRO BLOCKM TABLETS (Potassium lodide. U.S.P.) bot-bottle. ties of 14 tablets (NDC 003? 0472 20J Each white, round, scored tablet containe 130 mg potassium fadida IAA" THYRO BLOCKW SOLUTION (Potassium Iodide Solution / ' Potassium iodide should not be used 6y people allergic to iodide U.S.P.) 30 ml(1 ft os.) light resistant, measured-drop dispensing - - Keep out of the reach of chddren. In case of overdose or muergic units (NDC 0037 4287 25). Each drop contains 21 mg potassium reaction, contact a physician or the public health authority. y;a, wA m as
' Each THYRO. BLOCK TAB ET contains 130 mg of ACg ja potassium iodade. CARTER WALT. ACE. INC. ,
Each drop of THYRO. BLOCK" SOLUTION contains 21 mg of Cranoury, New Jersey 08512 t potassium iodide. CW-107915-10f79 Iseue 1009 I m-__ - - - , . _ , _ _ _ _ _ _ _ . _ . _ _ . - _ . _ . _ . . _ _ _ _ _ _ _ . . _ _ . - . _ . _ . - _ _ --
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g u .. . , a EPIP 1.8 MINOR
,w % Revision 4 1
08-26-83
-EMERGENCY OFF-SITE DOSE ESTIMATIONS 1.0 Munn The purpose of this procedure is to provide a method for the expeditious .
classification of an accidant 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. NRC Regulatory Guide 1.109, Calculation of Annual Dose to Man 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 -
..s 2.3 TID 14844 " Calculation of Distance Factors for. Power and Test Reactor 4 Sites," March 23, 1982 .
.. )
. 2.4 - EDS Report to Wisconsin Electric Power Company concerning NUREG-0578, 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 j- designated by the Shift Superintendent such as the Duty Technical j Advisor for the purpose of emergency classification.
3.2 This procedure should be used for emergency classification determi-nation where adverse meteorological condition assumptions are ! involved. This procedure can be used by TSC or ESC personnel for
- . that purpose.
3.3 This procedure is to be used only for immediate initial dose pro-l 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 and when time allows. 3.4 It is recognized that the RadCon/ Waste Manager, 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 Superintendent or designee for purposes of classifying the event.
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i_m : _ ~ n. EPIP 1.8 Page 2 e,.m 4.0- INITIAL CONDITIONS 4.1 An emergency or potential condition which is anticipated to have off-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 Equivalent Release Rates (Source Terms) 5.1.1 Airborne effluents may be discharged from PBNP through the
'following vent stacks:
- a. Auxiliary building vent (ABVNT)
- b. Drumming area vent (DAVNT)
- c. Unit 1 containment purge vent (Cont. 1)
- d. Unit 2 containment purge vent (Cont. 2) f e .. Gas stripper building vent (GSBVNT)
- f. Combined air ejector decay duct (CAE)
- 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.
4
. 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. Eberline computerized radiation monitoring system (designed to monitor low and high level releases).
- d. 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 l estimate the source terms is dependent on the level of t release and ute operability of the monitor. .. i 5.1.4 Meter readings are to be entered in the appropriate column ^l 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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'*9' 5.1.5 Direct contact readings using a hand-held survey meter are required when meter readings from the low range monitoring system or the RMS II system are not available.
~
5.1.6 Direct contact readings using a hand-held survey meter are not to be initiated until the following conditions are accomplished:
- a. An evaluation of the radiological hazards must be com-plated 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 ,
Supervisor, and the Duty Shift Superintendent. . t
._ 5.1.7 For surveying the main steam safety valves and atmospheric 1 dump valves, the reading will be taken in contact with the Q' -
centerline of the main ste.am 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-l visor in order to estimate release rates from the main steam safety valves and atmospheric dump valves:
- a. Estimated flew rate of steam through the main steam l header in lbs/hr.
- b. Specific volume of the steam in ft3 /lb. At 1000 psia, specific volume of 0.446 ft3 /lb. At 500 psia, specific volume is 0.928 ft3 /lb.
Enter this data on the appropriate column in Section 3.0 of EPIP-34. 5.1.9 Sun the values on EPIP-34, Section 4.0, to determine the gross Xe-133 equivalent release rate.
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't 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:
l D = whole body. dose rate (Rem /hr) X/Q = atmospheric dispersion coefficient (sec/m3) Q = gross Xe-133 equivalent release rate 'Ci/sec.) l Kr = Dose Factor (ree-m3 ) Ci-hrs. Projected off-site dose rates may be calculated by entering L the total Xe-133 equivalent release rate calculated on j.' 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~ coltaan 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 BASED ON CALCULATED ACCIDENT METER 0 LOGY FOR 0-2 HRS. AS GIVEN IN THE FSAR. IF REAL TIME METEOROLOGICAL DATA IS AVAILABLE, X/Q VALUES CAN BE CALCULATED AS OUTLINED IN EPIP 1.4 SECTION 5.1. REFINEMENT OF THE PROJECTED OFF-SITE DOSES MAY BE ACCOMPLISHED BY SUBSTITUTING THE REAL TIME X/Q CALCULATED
- VALUE FOR THE ESTIMATED 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 Facter
- l. 5.3.2 The conversion factor is. dependent on the type of accident
! which has occurred. Conversion factors are tabulated for the following accidents:
- j. a. Loss of coolant accident (LOCA) l .
i b. Gap activity accident l
., c. Fuel handling accident
- d. Stead generator tube rupture -
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~g 5.3.3 . Choose the appropriate type accident and calculate the thyroid dose in Section 2.0 of EPIP-35 by multiplying the whole body dose calculated in Section 1.0 by.the conversion factor.
NOTE: IF THE TYPE OF ACCIDENT IS NOT KNOWN, USE THE LOSS OF COOLANT CONVERSION FACTOR. 1 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: af - Effluent monitors detect levels corresponding to any of
~
the following doses at or beyond the site boundary: (1) >50 mR/hr whole body for \ hour L (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 i; . .q
-' i
- b. Any of the above-dose rates are projected, based on plant parameters and adverse meteorological conditions as assumed in this procedure.
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) 25 R/hr thyroid
- b. Either of above dose rates are projected based on plant
- parameters and actual meteorological conditions.
5.5 Protective Action Recommendatien i. l 5.3.1 Due to the conservative nature of the calculations in this l 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. , Enter dose rates and release duration estimate on EPIP-35. 5.5.2 If duration of release is unknown, use a release duration of 8 hours.
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5.5.3 Recommend one of the following offsite prote.:tive actions based on results of EPIP-35 calculations. L. '
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Whole Body Dose - 2
- a. <1 R - No planned protective actions.
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- b. I to <5 R - Seek shelter as a minimum. . Consider evacu-
ation.. .
- c. >5 R - Conduct evacuation in area affected and public ,
within 2 miles of the plant. ', l .Y Thyroid Dose ;( 'd;
- a. <5 R - No planned protective actions. ,, , ,
- b. 5 to <25 R - Seek shelter as a minimum. Considerevacu[' ,
ation. o ,
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- c. >25 R - Conduct evacuation in area affected and public - - -
within 2 miles of the plant. .
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M30P.
.63 -
Revision 2: V > 09-09-83' , UNUSUAL EVENT - IME DIATE ACTIONS i j . 1.0 PURPOSE - , j , 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,'8 as an Unusual Event. An Unusual Event can lead to a degradation in overallf 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 radicactive material is expected and, therefore, offsite radiological response is not expected to be necessary. No formal activation of the various centers, . l; 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 classification is declared or a closecut'of the-event is made by informing
. D' -
'offsite authorities, and by the completion of an incident report form as j.. contained in EPIP 2.3, " Unusual Event - Offsite Agency Notification."
2.0 REFERENCES
2.1 NUREG-0654,-Revision 1, November, 1980. l 3.0 PRECAUTIONS AND LIMITATIONS 3.1 All actions and notifications should be appropriately logged. l 3.2 When the TSC is manned, classification becomes the responsibility of I the TSC -(Plant Operations Manager) unless otherwise directed by the Site Manager. [ 4.0 INITIAL CONDITIONS 4.1 EPIP 1.1, " Initial Classification," completed. 5.0 PROCEDURE-5.1 . Shift Superintendent or Plant Operations Manager /Desiquee 5.1.1 If the emergency affects any manned area of the plant other than the control room, announce the nature and >1ocation of
' - ' the emergency using the Gai-tronics system. Make.the announce-ment at least twice.
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o EPIP 2.1 Page 2 gp;s. The following example is a guideline for classification announcements:
" ATTENTION ALL PERSONNEL, ATTENTION ALL PERSONNEL. THERE ARE CONDITIONS AT THE PLANT THAT WARRANT AN UNUSUAL EVENT CLASSIFICATION. THESE CONDITIONS ARE . +
5.1.2 Evacuate- affected areas if necessary to protect personnel by implementation of EPIP 6.1, " Limited Plant Evacuation." 5.1.3 Implement plant operating procedures as required to place the affected unit / units in a safe condition as the emergency warrants. 5.1.4 Designate an individual, such as a backup Duty Technical Advisor to establish and maintain commiunications with the TSC. 5.1.5 Implement EPIP 11.0, "First Aid and Medical' Care," as necessary. . 5.1.6 Implement EPIP 7.0, "CHP Radiological Response and Prepared - 5.1.7 . t , "Firefighting," as necessary. 5.1.8 Implement EPIP 8.1, " Personnel Assembly and Accountability," as necessary. 1 i 5.1.9 Implement EPIP 12.2, " Personnel Exposure and Search and Rescue Team," as necessary. 5.1.10 Determine the need for additional personnel. Implement EPIP 2.2, " Unusual Event - Plant and Company Personnt.1 l Notification," as required. 5.1.11 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 l- 5.2.1 Report to the control room. 5.2.2 If the Shift Superintendent is incapacitated, assume the responsibility and. authority of the Shift Superintendent -
. (until properly relieved by a qualified individual and --
coordinate the plant response as outlined in Section 5.5 of this procedure). 5.3 Duty Technidal Advisor , 5.3.1 Report to the control room and assume an appropriate advisory role.
~ ~ ~
_ _ -__,_.L . _ _ A EPIP 2.1 Page 3 3 ( ; '.} 5.3.2 Assist.the Shift Superintendent as assigned in communications with the technical support center. ( 5.4 Security Lieutenant 5.4.1 .Implenient 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 s-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
.4 status. Review and perform as necessary EPIP 1.2, " Plant ij . Status," EPIP 1.8, " Emergency Offsite Dose Estimation," and EPIP 1.5, " Protective Action Evaluation."
5.5.4 Reclassify emergency as necessary and complete form EPIP-12,
" Initial Incident Report Form" attached to EPIP 2.3, " Unusual l Event - Offsite Agency Notification."
l 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 - Inunediate Actions," or EPIP 5.1,
" General Emergency - Inunediate Actions."
l 5.5.6 Provide recommendations of any required protective actions l 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 1-EPIP-12, " Incident Report Form," attached.to EPIP 2.3,
" Unusual Event - Offsite Agency No'ification."
1 5.5.8 Contact by telephone the persons and agencies notified of the emergency and provide the information contained in the notification message. - 5.5.9 Assure completion of EPIP 2.3, " Unusual Event-Offsite Agency Notification." 5.6 Plant Supervisory. Personnel , 5.6.1 keporttoassignedlocationandwaitforfurtherinstruc-tions.
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5.7 Deactivation - 5.7.1 If condicions no longer warrant the Unusual Event classifi-cation, provide a verbal summary of events to personnel' notified in accordance with EPIP 2.2., " Unusual Event - Plant and Cogany Personnel Notification," and 2.3, " Unusual Event - Offsite Agency Notification." 5.7.2 Notify plant personnel of the Unusual Event closeout as r required.- 5.7.3 Coglate the incident report form contained in EPIP 2.3, "Ubusual Event - Offsite Agency Notification." J e 9
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e-EPIP 2.2 MINOR l Q,, Revision 2
- i 09-09-83 UNUSUAL EVENT - PLANT AND COMPANY PERSONNEL NOTIFICATION a
1.0 GENERAL The purpose of this procedure is to 1) establish the notification responsi-bilities and sequence to be performed by designated plant personnel;
- 2) provide notification to personnel from the plant and corporate offices; and 3) augment plant personnel resources as necessary during plant conditions classified as an Unusual Event in accordance with the Emergency Plan Implementing Procedures. Necessary phone numbers are included in form EPIP-22, " Plant and Company Emergency Call List."
2.0 REFERENCES
None . 3.0 PRECAUTIONS AND LINITATIONS 3.1 If unable to contact an individual, continue with the notification of the other individuals.and then attempt to contact the persons who (("7) .y have not been notified. 3.2 All actions and notifications should be appropriately logged. 4.0 INITIAL CONDITIONS Unusual Event emergency conditions exist. 5.0 PROCTOURE Key Company personnel may be notif4ed via the pager system by referring to EPIP 14.2, " Paging System Operation." 5.1 shift Superintendent 5.1.1 Contact a Duty & Call Superintendent and discuss plant conditions with him. 5.1.2 Notify the Duty. Technical Advisor and discuss plant condition's with him. 5.2 Duty & Call Superintendent .. 5.2.1 If required, contact the Duty & Call Chemistry & Health Physics Supervisor and discuss CHP manpower needs. Ensure that all information and needs are understood.
i EPIP 2.2 Page 2
]: i S.2.2 If required, contact other Duty & Call Superintendents and needed plant and company personnel (phone numbers listed in form EPIP-22, " Plant and Company Emergency Call List").
5.2.3 contact the Emergency Support Manager and provide information
> concerning plant status as necessary (phone numbers listed in form EPIP-22, " Plant and Company Emergency Call List").
5.3 Duty & Call Chemistry & Health Physics Supervisor 5.3.1 If required, contact and notify Chemistry & Health Physics personnel concerning plant status and required actions. S e 9 I f" s ' \ j . 1 O I i 1 l t
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ww- - - - = --- - z - i EPIP 2.2 MINOR Revision 2
'/
09-09-83 UNUSUAL EVENT - PLANT AND COMPANY PERSONNEL NOTIFICATION
.i .
1.0 GENERAL . The purpose of this procedure is to 1) establish the notification responsi-bilities and sequence to be performed by designated plant personnel;
- 2) provide notification to personnel from the plant and corporate offices; and 3) augment plant personnel resources as necessary during plant conditions classified as an Unusual Event in accordance with the Emergency Plan Implementing Procedures. Necessary phone numbers are included in form EPIP-22, " Plant and Company Emergency Call List."
2.0 REFERENCES
None , 3.0 PRECAUTIONS AND LIMITATIONS O~. 7 3.1 If unable to contact an individual, continue with the notification of
/ the other individuals and then attempt to contact the peYsons who have not been notified.
3.2 All actions and notific ations should be appropriately logged. 4.0 INITIAL CONDITIONS Unusual Event emergency conditions exist. 5.0 PROCEDURE Key Company personnel may be notified via the pager system by referring to EPIP 14.2, " Paging System Operation."' . 5.1 Shift Superintendent 5.1.1 Contact a Duty & Call Superintendent and discuss plant conditions with him. l 5.1.2 Notify the Duty Technical Advisor and discuss plant conditions with him. 5.2 Duty & Call Superintendent .
~
5.2.1 If required, contact the Duty & Call Chemistry & Health Physics Supervisor and discuss CHP manpower needs. Ensure
" that all information and needs are understood.
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EPIP 2.2 I Page 2 5.2.2 If required, contact other Duty & Call Superintendents and needed plant and company personnel (phone numbers listed in ,, form EPIP-22, " Plant and Company Emergency Call-List"). 5.2.3 Contact the Emergency Support Manager and provide information concerning plant status as necessary (phone numbers listed in form EPIP-22, " Plant and Company Emergency Call List"). 5.3 Duty & Call Chemistry & Health Physics Supervisor i If required, contact and notify Chemistry & Health Physics 5.3.1 personnel concerning plant status and required actions. O "D cy e 1 4 9
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EPIP 2.3 MINOR O Revision 4 t, ) 09-09-83 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
None 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 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), " Initial Incident Report Form," 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. 5.0 PROCEDURE 5.1 Designee 5.1.1 Complete the initial incident report form (form EPIP-12, attached) using the information given by the Shift Superin-tendent. Examples of emergency response include: shut the
- unit down, call in additional firefighters or secure doors .
against high winds.
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5.2 Security Lieutenant or Designee 5.2.1 Notify the Nanitovoc County Dispatcher by telephone (tele-phone number listed on form EPIP-23, "Offsite Agency Emergency Call Lista). Read the initial incident report form and ensure that.the information is fully understood. 5.2.2 ' Notify Kewaunee County Dispatcher by telephone (telephone number listed on form EPIP-23, "Offsite Agency Emergency Call List"). Read the initial 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 Emergency Call List"). Read the initial incident report form and ensure that the information is fully understood. 5.2.4 Pick up the NRC Operations Center, Bethesda, dedicated line. . 5.2.5 When a response is heard, read the initial incident report
..s form.
- (, 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").
5.2.7 Have the Shift Superintendent make an appropriate entry into the NRC Operations Center, Bethesda, phone log. 5.2.8 Attempt to contact the NRC resident inspector (telephone 4 number listed on form EPIP-23, "Offsite Agency Emergency call List").. This courtesy notification is to inform him of the unusual event. e 1
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' ,O MINCR Revision 3 U #7 09-09-83 ALERT - IMMEDIATE ACTIONS 1.0 PURPOSE The purpose of this procedure is to provide a series of ismediate actions and. clear. direction to adequately respond to events or conditions classi-fled 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 infomation 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 evacuatica is not required, the only other center that might be activated would be the emergency support center.
'~
The Alert status will be maintained until an escalation to a Site or General Emergency occurs or a deescalation or closeout is made by informing offsite authorities, and by the completion of an Incident Report Form as contained in EPIP 3.3, " Alert - Offsite Agency Notification."
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. l 3.2 Communication sh'ould be concise and accurate. ( I 3.3 When the TSC is manned, classification becomes the responsibility of the TSC (Plant Operations Manager) unless otherwise directed by the Site Manager. 4.0 INITIAL CONDITIONS 4.1 EPIP 1.1, " Initial Classification," completed. -- w
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5.0 PROCEDURE 5.1 Shift Superintendent or Plant Operations Manager / Designee 5.1.1 Evacuate affected areas if necessary to protect personnel by
; implemer.tation _of EPIP 6.1, " Limited Plant Evacuation." l 4
5.1.2 Announce the nature and location of the emergency using the Gai-tronics system. Make the announcement twice. : The following is a guideline for classification announcements: 3 " ATTENTION ALL PERSONNEL, ATTENTION ALL PERSONNEL. THERE
- I ARE CONDITIONS AT THE PLANT THAT WARRANT AN ALERT CLASSIFI-CATION. THESE CONDITIONS ARE .
5.1.3 Implement plant operating procedures to place the affected unit / units in a safe condition. P 5.1.4 Perform Section 5.1 of EPIP 3.2, " Alert - Plant and Company - Personnel Notification." w 5.1.5 Designate an individual, such as a backup Duty Technical i -) Advisor to establish and maintain communications with the
'9 TSC.
5.1.6 Implement EPIP 11.0, "First Aid and Medical Care," as necessary. 5.1.7 Implement EPIP 10.1, "Firefighting," as necessary. 5.1.8 ' Perform actions of the Plant Operations Manager (POM) 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." 5.2 Operating Supervisor 5.2.1 Report to the control room. 5.2.2 If the Shift Superintendent is incapacitated, assume the responsibility and' authority of the Shift Superintendent (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 Superintendent. 5.3.2 - Estiablish a communication link using the dedicated line with the technical support center as soon as practicable.
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t EPIP 3.1 Page 3 O y. 5.4 security Lieutenant 5.4.1 Implement EPIP 9.1, "Se :urity," as necessary. i' ? 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. 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. If other senior management are unavail-q able, report to the technical support center. II 5.5.2 ' Perform a detailed evaluation of the plant condition using < EPIP '. 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 Opcations Manager .as necessary.
3 Assure completion of EPIP 3.3, " Alert - Offsite Agency 5.5.4 Notification". 5.5.5 Reclassify emergency as necessary. Coordinate this duty with PON when he becomes available. 5.6 Plant Operations Manager (POM) (Superintendent - Operations) 5.6.1 Report to the technical support center. 5.6.2 Escalate to a more severe classification if necessary by
. implementation of EPIP 4.1, " Site Emergency - Immediate Actions," or EPIP 5.1, " General Emergency - Immediate Actions."
Complete form EPIP-12, " Initial 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 l longer warrant the Alert classification and complete form EPIP-12, " Initial Incident Report Form,". attached to EPIP-3.3, " Alert - Offsite Agency Notification." - 5.6.5 Notify personnel notified in EPIP 3.2, " Alert - Plant and Company Personnel Notification."
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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, EPIP-12, attached to EPIP 3.3, " Alert - Offsite Agency ?- Notification."
5.6.7 . Coordinate all control room, technical support center, and security procedures. 5.6.8 Coordinate EPIP 6.1," Limited Plant Evacurtion," if imple-mented.
- k. 5.6.9 Coordinate EPIP 8.1, " Personnel Assembly and Accountability,"
if implemented. y.' 5.7 Site Manaaer (Manager, 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.
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5.8 Technical Support 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 the. control room as soon as practicable. 5.8.3 Determine the need for additional personnel. Implement EPIP 3.2, " Alert-Plant and Company Personnel Notification," as required. 5.9 Chemistry /HP Supervisor (Superintendent - Chemistry & Health Physics) 5.9.1 Report to the technical support center. l 5.9.2 Implement EPIP 7.0, "CHP Radiological Response and Prepared-ness," as necessary. I 5.9.3 Have Chemistry & Health Physics personnel report to their work station and establish a communication link to the technical support center. . . l 5.10 Maintenance Supervisor (Superintendent - Maintenance & Construction) 5.10.1 ' Report to the technical support center.
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'L t 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 assip ment.
5.11 Designated 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 Advisors, Training Supervisor, I & C Supervisor, and Health Physics Director if not assigned to the site boundary control center.) j 5.11.1 Report to the technical support center. 9 g'
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* [ Revision 2
~N 09-09-83 I ALERT - PLANT AND COMPANY PERSONNEL NOTIFICATION
. 1.0 PURPOSE -
The purpose of this procedure is to 1) establish.the notification responsi-bilities and sequence for designated, plant personnel; 2) provide notification to personnel from the plant and corporate offices; and 3) augment plant human resources as necessary during plant conditions classified as an Alert ii in accordance with the Emergency Plan implementing procedures. Necessary
- I phone numbers are included in form EPIP-22, " Plant and Company Emergency Call List."
2.0 REFERENCES
2.1' NUREG-0654, Revision 1, November,1980. - 3.0 PRECAUTIONS AND LINITATIONS
~
3.1 If unable to contact an individual continue with the notification of the other individuals and then attempt to contact the persons who j s have not'been notified. 3.2 All actions and notifications should be appropriately logged on EPIP-22, Plant and Company Emergency Call List." 4.0 INITIAL CONDITIONS Alert emergency conditons exist. 5.0 PROCEDURE l Key Company personnel may be notified via the pager ::ystem by referring to EPIP 14.2, " Paging System Operation." 5.1 Shift Superintendent 5.1.1 Contact a Duty & Call Superintendent (phone numbers listed on the Plant and Company Emergency Call List) and discuss plant conditions with him. 5.1.2 Notify the Duty Technical Advisor and discuss plant condi- , tions with him. - L P
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- EPIP 3.2 Page 2
( . 5.2 Duty & Call Superintendent 5.2.1 Contact a Secondary Duty & Call Superintendent (phone numbers listed en the " Plant and Company Emergency Call List"). Inform the secondary Duty & Call Superintendent that an Alert has been declared and discuss manpower needs with him. - 5.2.2 Contact the Duty & Call Chemistry & Health Physics Supervisor (phone numbers listed on the " Plant and Cos;,any Emergency ' Call List"). Inform the Duty & Call Chemistry & Health Physics Supervisor that an Alert has been declared and discuss manpower needs with him. 5.3 Secondary Duty & Call Superintendent 5.3.1 Contact other Duty & Call Superintendents and needed plant personnel listed on the Plant and Company Emergency Call List and inform them an Alert has been declared. Discuss r.anpower needs with the appropriate supervisors. , 5.3.2 Contact the Emergency Support Hanager and provide information concerning plant status as necessary (phone numbers listed on EPIP-22, " Plant and Company Emergency Call List"). 1
'im/ 5.4 hotified Supervisory Personnel including the Duty & Call Chemistry
& Health Physics Supervisor 5.4.1 The nocified supervisors will contact and notify their personnel concerning plant status and actions expected of them.
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y.. EPIP 3.3 MINOR Revision 3 g4.. ;/ 09-09-83 l ALERT - 0FFSITE AGINCY NOTIFICATION 'l , i 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 3.0 PREC&UTIONS AND LIMITATIONS , 3.1 Obtain the name and title of the person being contacted prior to transmitting any information. O (_;/ 3.2 If unable to contact an individual or agency, continue with the notification of the other individuals or agencies and then attempt tc contact the persons or agencies who have not been notified.
- 3.3 All actions and notifications should be appropriately logged on form EPIP-23, "Offsite Agency Emergency Call List," or form EPIP-12 (attached), " Initial Incident Report Form."
t 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. The goal is to couplete this notification within 15 minutes of the initial classification.
5.0 PROCEDURE l i l 5.1 Desianee 5.1.1 Complete the initial incident report form (form EPIP-12, attached) using the information given by the Shift Superin-tendent. Examples of emergency response include: shut the .. E unit down, call in additional firefighters, and secure the , doors against high wind. w.
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- , I t 5.2 Security Lieutenant or Designee [
5.2.1 Pick up the NAWAS hgndset and make the following trans-mission:
-THIS IS POINT BEACH CALLING WARNING CENTER 2, MANITOWOC COUNTY, AND EEWAUNEE COUNTT. THIS IS POINT BEACH CALLING WARNING CENTER 2, MhMITOWOC COUN T AND EEWAUNEE COUN T.
NOTE: THE THREE CENTERS SHOULD RESPOND. MOTE ANY CENTERS NOT RESPONDING AND PROCEED WITH THE PROCEDURE. t r 5.2.2 Transmit.the initial incident report form over the NAWAS lt -system. Ensure that the three centers fully understand the
- transmission.
5.2.3 contact by telephone, the centers (noted in Step 5.2.1 of
- this procedure) which were unable to be contacted over the
-)- NANAS system (phone numbers listed on EPIP-23, "Offsite g ..
Agency Emergency Call-List").. 5.2.4 Read the initial 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 the' initial 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 5.2.1. ! 5.2.7 Have the Shift Superintendent make an appropriate entry into i the NRC Operations Center, Bethesda, phone log. I L 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. l 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. , l
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o j . i EPIP 4.1 m MINOR ([ ', Revision 3 , 09-09-83
~
SITE EMERGENCY - IMMEDIATE ACTIONS
- l. 1.0 GENERAL The purpose of this procedure is to provide a series of isusediate actions and clear direction to adequately respond to events or conditions classi-fled as a Site Bnergency 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-tactive 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. . l The initiation of a Site Emergency requires prompt notification to State and local authorities so that they may alert key personnel.
..' The Site Emergency status will be maintained until an escalation to a General Emergency occurs, doescalation to a less severe emergency classifi-I cation occurs or a closecut is 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 LIMITATIONS 3.1 All actions and notifications should be appropriately logged. 3.2 All communication should be concise and accurate. L 3.3 When the TSC is manned, classification becomes the responsibility of the TSC (Plant Operations Manager) unless otherwise directed by the Site Manager. 4.0 INITIAL CONDITIONS 4.1 Site Emergency has been declared. - ? . i e l
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5.0 PROCEDJRE .
< 5.1 shift Superintendent or Plant Operations Manager / 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. The following example is a guideline for classification announcements:
" ATTENTION ALL PERSONNIL, ATTINTION ALL PERSONNEL. THERE '
ARE CONDITIONS AT THE PLANT THAT WARRANT A SITE EMERGENCY CLASSIFICATION. THESE CONDITIONS ARE . 5.1.2 Evacuate affected areas if necessary to protect personnel by implementation of EPIP 6.1, " Limited Plant Evacuation." 5.1.3 Implement plant operating procedures to place the affected . unit / units in a safe condition. . 4 5.1.4 Designate an individual, such as.a backup Duty Technical Advisor to establish and maintain communications with the j y .; . TSC. 5.1.5 Implement EPIP 11.0, " Firs't Aid and Medical Care," as necessary. 5.1.6 Implement EPIP 10.1, "Firefighting," as necessary. l 5.1.7 Perform actions of the Plant Operations Manager until properly relieved. 5.1.8 Notify the Energy Information Center (Ext. 246) and have them implement EPIP 6.4, " Energy Information Center Evacu-ation." 5.2 operatina Supervisor
- 5.2.1 Report to the control room.
5.2.2 If the Shift Superintendent is incapacitated, assume the responsibility and authority of the Shift Superintendent (until properly relieved by a qualified individual) and coordinate the plant response as outlined in Section 5.1 of this procedure. 5.3 Duty Technical Advisor .. t 5.3.1 Report to the control room to provide advice-to the Technical l Support Manager and the Shift Superintendent. 5.3.2 Establish a communication link using the dedicated line with
- the technical support center as soon as practicable.
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IPIP 4.1 p, Page 3 4 5.4 - Security Iieutenant 5.4.1 Implement EPIP 9.1, " Security," as necessary,
- 5.4.2 Report to the control room to obt'ain a completed incident report form. *
.5.4.3 haplement Section 5.2 of EPIP 4.3, " Site Emergency - 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 IPIP 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 necessary.
) 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-cation.
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 8 message using 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 - Inunediate Actions." Complete form EPIP-12, " Initial Incident Report Form." 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 classificatio'n if conditions no - longer warrant the Site Emergency classification and complete form EPIP-12, " Initial Incident Report Form," attached to N EPIP 4.3, " Site Emergency - Offsite Agency Notification." 5.6.5 Coordinate EPIP 6.0, " Evacuation," if implemented. 5.6.6 Coordinate EPIP 8.1, " Personnel Assembly and Accountability," if implemented.
. . _ _- . - ~ . . _ _ __ _ _ - - _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ . - _ _ _ . - _ __ ___
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5.6.7 Coordinate control room, technical support center, onsite operations support center and security procedures. 5.7 Site Manager (Manager - Point Beach Nuclear Plant) b 5.7.1 _ Report to the technical support center and assume overt.ll J responsibility for the emergency response and recovery op rations. . 1 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 '5.8 Technical Support Manager (Superintendent - Technical Services)
- ~
5.8.1 Report to the technical support center. l; 5.8.2 Establish communication links using the dedicated lines with the control room, the emergency support center and the , j ' onsite operations support center as soon as practicable. . l l- 5.8.3 Assure completion of EPIP 4.3, " Site Emergency - Offsite l Agency Notification." t 5.9 Chemistry /HP Supervisor (Superintendent - Chemistry & Health Physics) l 5.9.1 Report to the technical support center. 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 communi-cation link to the technical support center. l r 1 l 5.10 Maintenance Supervisor (Superintendent - Maintenance & 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 petsonnel report to an appropriate location for assignment. 5.11 Emergency Support Manager (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- - ities. l l-
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1 l ., i 5.12 _D_esignated Plant Supervisory Personnel . ! (See Figure 5-5 of the Emergency Plan as to who ia 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 Energency occurs outside of nomal working ~~~ hours, have personnel report to the onsite operations suppcrt 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 (Heal *.h 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 si,te boundary control center.
5.13.3 Establish a communication link to the emerg'ency 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 ethe operation of the Emergency News Center in accordance with EPIP 14.0, " Crisis Communications." B n - - , , , , , , _ _ , . , . , , _ _ , , 7._,., ._,,_, e a, a , - . + . . . - - ,.--.-..w.- - - - , . ,-a-, +,, . -,,, , - . ,,. , ,,,__,, ,,w, ,__ . ,, , . , , . , ,,
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, 5.16 Sgten Analysis and Procedural Support Coordinator
.(Superintendent, Reactor Engineering, Nuclear Engineering Section)
Report to the technical support center. .
$ 5.17 ' Designated Company Personn d -
f (See Figure 5-5 of the Emerger.cy Plan as to who is to report to the = corporate headquarters. This includes the Admir.istrative & Logistics Manager, Design, Construction & Planning Manager, Radwaste Technical Sqmrt Coordinator, and the Licensing Support- Crord.inator.) i 5.17.2 Report to the corporate liendquarters. e (/ %. l-I I 4 l
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EPIP 4.2 [o ' MINOR Revision 2 09-09-83 SITE EMERGENCY - PLANT AND COMPANY PERSONNEL HOTIFICATION 1.0 GENERAL The purpose of this procedure is 1) establish the notification responsi-bilities and sequence for designated plant supervisory personnel, 2) provide notifjcation to plant personnel abd corporate offices and 3) augment plant huma.t resources as necessary during plant conditions classified as a Site Emergency in accordance with the Emergency Plan implementing procedures. ', 14ecessary phone numbers are included in form EPIP-22, " Plant and Company Emergency Call List."
2.0 REFERENCES
None. . 3.0 PRECAUTIONS AND LIMITATIONS
.) 3.1 If unable to contact an individual continue with the notification of
_./ the other individuals and then attempt to contact the persons who have not been notified. 3.2 All actions and notifications should be appropriately logged on form EPIP-22, " Plant and Company Emergency Call List." 4.0 INITIAL CONDITIONS Site Emergency conditions exist. 5.0 PROCEDURE Key Company personnel may be notified via the pager system by referring to EPIP 14.2, " Paging System Operation." 5.1 Shift Superintendent 5.1.1 Contact a Duty & Call Superintendent (phone numbers listed in form EPIP-22, " Plant and Company Emergency call List") and discuss plant conditions with him. 5.1.2 Assure that the Duty Technical Advisor is aware of the Site Emergency. - k
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.v 5.2 Duty & Call superintendent 5.2.1 Contact a secondary Duty & Call Superinteqdent (phone ntunbers listed in form EPIP-22, " Plant and Company Emergancy call List") and inform him of the Site Emergency. Discuss manpower needs with the secondary Duty & Call Superintendect.
5.2.2 . Contact the Duty & Call Chemistry & Health Physics Supervisor l . (phone numbers listed in form EPIP-22, # Plant and Company Emergency Call List") and infom hha that a Site E.nergency
- has been declared. Discuss manpower needs with the Duty & ,
call Chemistry & Health Physics Supervisor. l 5.3 SecondaryDuty&CallSuperintiendent' g 5.3.1 Contact other Duty & Call Superintendents and needed personnel
- ' . listed in form EPIP-22, " Plant and Company Emergency Call List," and inform them of the Site Emergency. Discuss manpower needs with the appropriate supervisors. ~ ,
5.3.1 . Contact the Emergency Support Manager and provide information r - concerning plant status as necessary (phone numbers listed
.(. , in form EPIP-22, " Plant and Company Emergency Call List").
~~
5.4 Notified Supervisory Personnel Including the Duty & Call Chemistry
& Health Physics Supervsior .
5.4.1 The notified supervisors will contact and notify their personnel concerning plant status and actions expected of them. l e Mme# v-> q -.,y73w--y 7-%77 gp-y g i. --- -. c. _p , , , ,_g ,.w.-.y ,, ,-._,.,7 - ,--,-., , . -,,-.pm-y p n9gywg. . ,e,a y w,ye-,.__y9eera
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.9 4.,j EPIP 5.1 MINOR Revision 3
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09-09 GENERAL EMERGENCY - IMMEDIATE ACTIONS 4 l.0 PURPOSE - The purpose of this procedure is.to provide a series of immediate actions and clear'directi:n to adequately respond to events or conditions classi-
- fled as a General Emergency in accordance with EPIP 1.1, " Initial Classififation."
Under this classification,.there is a greater potential for offsite releases ,
; which could have an impact on the public to the extent that protective 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 the emergency news center. Either plant or limited plant evacuations may become necessary. . The initiation of a General Emergency requires prompt notification to State and local authorities so that they may activate their emergency control s centers and dispatch key personnel. 1
# The.Gener'al 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 Notifi-cation."
2.0 REFERENCES
2.1 NUREG-0654, Revision 1, November, 1980. 3 10 PRECAUTIONS AND LIMITATIONS 3.1 All actions and notifications should be appropriately legged. , 3.2 All communications should be concise and accurate. 3.3 When the TSC is manned, classification becomes the responsibility of the TSC (Plant Operations Manager) unless otherwise directed by the Site Manager. 4.0 INITIAL CONDITIONS 4.1 EPIP 1.1, " Initial Classification," completed.
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EPIP 5.1 ~
., Page 2
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d J 5.0 PROCEDURE , 5.1 Shift Superintendent or Plant Operatices Manager / Designee 5.1.1 Announce the nature and locatica of the unergency using the .* Gai-tronics system. Make thejannouncement at least twice. i The announcement should be1 repeated periodically. , E The following example is a guideline for classification < announcements; , 7 l' '
"ATTEKIION ALL PERSONNEL,' LTTENTION ALL PERSONNEL. THERE / '
ARE CONDITIONS AT THE PLWT THAT WARRANT A GENERAL EMRGENCY
^
CLASSIFICATION. THESE' CONDITIONS ARE . 63 5.1.2 Sound the evacuation '51 arm if a plant evacuation is.f varranted. Evacuate affected areas if necessary by implementation of EPIP 6.0, " Evacuation." ; e' 4 5.1.3. Implement plant operating procedures as required. to place . the affected unit / units' into a safe conditiop. ( g
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-,h 5.1.4 Designate aa individual; such as a backup Duty Technical, f Advisor to establish 2and maintain communications with the '
TSC. V j 5.1.5 Implement EPIP 11.0, "First Aid and Medical Care',8'.'as necessary. 5.1.6 Implement EPIP 10.1, "Firefighting," as necessary. ! 5.1.7 Perform actions of the Plant Operations Managers until ' properly relieved. , i 5.1.8 Notify the energy information center and have tires implement EPIP ,6.4, " Energy Information Center Evacuation.?
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j ' i 5.2 Operating Supervisor i 5.2.1 Report to the control room.
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5.2.2 If the Shift Superintendent is incapacitated, assumer the responsibility and authority of the Shift Superintendent l (until properly relieved by a qualp,fied individual) and f coordinate the plant response'as o'utlined'in Section 5.1. 5.3 Duty Technical Advisor j, Report to the control room to provide advice to'the' Technical '
; 5.3.1 Support Manager and the Shift Superintendent. '
5.3.2 Establish a communication link using the dedicated line with the technical support center as soon as practicable. '
- ~ . - - _ - m ._. m _ - ~ _ s EPIP 5.1 Page 3 S .]
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.
c 5.4.3 Implement Section 5.2 of IPIP 5.3, " General Emergency - Offsite-Agency Notification." 5.5 Luty & Call Superintendent 5.5.1 Report to-the control room or the technical support center. 4 5.5.2 Assume role of Plant operations Manager (POM) as necessary. t 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 Evaluatioit," and other available informa- ,
tion. 5.5.4 Reclassify emergency as necessary. Coordinate this duty (~ , /
'with the PON 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 t Emergency - Offsite Agency Notification," and provide the l information contained in a reclassification notification
- message using form EPIP-12 attached to EPIP 5.3, " General Emergency - Offsite Agency Notification."
5.6 Plant Operations Mana'ger (Superintendent - Operations) 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 class if conditions no longer warrant the General Emergency classification and complete of form EPIP-12, " Initial Incident Report Form" attached to EPIP 5.3, " General Emergency - Offsite Agency Notification."'
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5.6.5 Coordinate control room, technical support center, onsite N
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, , _a __ _ ,,. ~ _ . -- .. -. EPIP 5.1 Page 4 p,, 5.7 ' Site Manager (Manager - 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 Manager (Superintendent Technical Services) 5.8.1- Report to the technical support center. s 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 possible.. 5.8.3 Assure completion of EPIP 5.3, " General Emergency - Offsite Agency Notification." 5.8.4 If the acting Emergency Support Manager, provide recommenda-tions of protective actions for the public to State and ['] i local authorities per EPIP.1.5, " Protective Action Guides." 5.9 Chemistry /HP Supervisor (Superintendent - Chemistry & Health Physics) 5.9.1 lieport to the technical support center.
^
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 communi-cation link to the technical support center using the dedicated line. 5.10 Maintenance Supervisor (Superintendent - Maintenance & 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 Manager (Director, Nuclear Power Department)
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5.11.1 Report tp the emergency support center.
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EPIP 5.1 Page 5
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5.11.2 Act as liaison between plant and offsite authorities. 5.11.3 Provide recommendations of protective actions for the public to State and local authorities per EPIP 1.5, " Protective Action Guides." 5.12 Desiaated Plant Supervisory Personnel (See Figur*e 5-6 of the Emergency Plan as to who is to report to the technical support center. This includes the Maintenance Supervisor, the off-duty Technical Advisors, the I & C Supervisor, the Core Pt ics Coordinator, the Training Supervisor and the Shift Support Coordinator.) 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 cont: ol 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. b 5.12.4 If the General Emergency occurs during regular working hours and there is not a plant evacuation, have personnel report 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 i
& 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. l 5.14 Designated Company Personnel (See Figure 5-6 of the Emergency Plan as to who is to report to the emergency support center. This includes the Rad / Waste Manager, the
- 1. radiation survey communicator, and the offsite agency communicator.
- l. -
5.14.1 Report to the emergency support center. 5.15 Emergency News Center Director
. 5.15.1 Report to the emergency news center and assume responsi- .
bility f,or release of information about the emergency. I I l
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0 EPIP 5.1 Page 5
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5.15.2 Assure proper comununications exist between the Emergency news center and the emergency support center. 5.15.3 Prepare and cc, ordinate the operation of the emergency news center in accordance with EPIP 14.0, " Crisis Comununications." 5.16 System Analysis and Procedural Support Coordinator (Superintendent, Reactor Engineering, Nuclear Engineering Section) Report to the technical support center. 5.17 Designated Company Personnel i- (See Figure 5-6 of the Emergency Plan as to who is to report to the-corporate headquarters. This includes the Design, Construction & Planning Manager, the Radwaste Technical Support Coordinator, the Licensing Support. Coordinator, the Adutinistrative & Logistics Manager, the Utility Engineering Director, the Architect Engineer Director, the Director of NSS Supply, and the Director of Quality Control.) , 5.17.1 Report to the corporate headquarters. w I l i W l
_. =.~.a.~ u .au. . JU . EPIP 5.2 MINOR O. Revision 2 09-09-83
.M GENERAL ENERGENCY - PLANT AND COMPANY PERSONNEL NOTIFICATION li 1.0 GENERAL i.
l- The purpose of this procedure is 1) establish the notification responsi-l: bilities and sequence for designated plant personnel; 2) provide notification to plant personnel and corporate offices; and 3) augment plant human resources as necessary during plant conditions classified as a General Emergency in accordance with the Emergency Plan implementing procedures. Necessary phone numbers are included in EPIP-22, " Plant and Company Emergency Call List."
2.0 REFERENCES
None . 3.0 PRECAUTIONS AND LINITATIONS 3.1 If unable to contact an individual continue with the notification of x". e the other individuals and then attempt to contact the persons who have not been notified. 3.2 All actions and notifications must be appropriately logged on form EPIP-22, " Plant and Company Emergency Call' List." 4.0 INITIAL CONDITIONS General Emergency conditions exist. 5.0 PROCEDURE Key Company personnel may be notified via the pager system by referring to EPIP 14.2, " Paging System Operation." S.1 Shift Superintendent 5.1.1 Contact a Duty & Call Superintendant (phone numbers listed in EPIP-22, " Plant and Con.pany Emergency Call List") and discussplantconditionswit{.him. 5.1.2 Assure that the Duty Technical Advisor is aware of the General Emergency. w ~.n ,-r a ,,m-- , -- - - - , , - , ve a, e.wa. ,- ,,-e,n- .- . , ~ ~en - e- -, e- - ~ --,- w , . -.e - . ,e
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e En . . EPIP 5.2 Page 2 r 5.2 Duty & Call Superintendent 5.2.1 Contact a secondary Duty & Call Superintendent (phone numbers listed in EPIP-22, " Plant and Company Emergency Call List") and inform him that a General Emergency has been declarti. Discuss manpower needs with the secondary Duty & Call Super-intendent and assure that he performs section 5.3 of this procedure. , f 5.2.2 Contact the Duty & Call Chemistry & Health Physics Supervisor (phone numbers listed in form EPIP-22, " Plant and Company Emergency Call List") and inform him that a General Emergency has been declared. ~ Discuss manpower needs with the Duty &
. Call Chemistry & Health Physics' Supervisor.
5.3 Secondary Duty & Call Superintendent 1 5.3.1 Contact other Duty & Call Superintendents and needed plant personnel listed on the " Plant and Company Emergency Call . List" and inform them that a General Emergency has been , declared. Discuss manpower needs with the appropriate supervisors. 5.3.2' Contact the Em'e rgency Support Manager and provide information
~
concerning plant status as necessary (phone numbers listed in form EPIP-22, " Plant and Company Emergency Call List"). I 5.4 Notified Supervisory Personnel Including the Duty & Call Chemistry
& Health Physics Supervisor 5.4.1 The notified supervisors will contact and notify their personnel concerning plant status and actions expected of them.
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EPIP 6.1 MINOR y Revision 3
- / 09-09-83 LIMITED PLANT EVACUATION o .
1.0 GENERAL This procedure describes the steps to be taken in the event of a limited plant evacuati.on. This procedure will be used when conditions warrant r small areas inside the protected area to be evacuated. Assembly areas are defined on a-case-by-case basis.
2.0 REFERENCES
None 3.0 PRECAUTIONS AND LIMITATIONS
. 3.1 All actions and notifications should be appropriately logged. .
l
, -- 3.2 Health Physics personnel may require evacuation of rooms, areas, or the affected portions thereof to prevent the unnecessary spread of p
l h contamination. l 3.3 When the TSC is manned, the responsibility for evacuation and evacuation i announcements is transferred to the TSC (Plant Operations Manager) unless otherwise directed by the Site Manager. 4.0 INITIAL CONDITIONS A limited plant evacuation will be considered when any of the following conditions exist. s 4.1 Unanticipated radiation level increase at any area radiation monitor in excess of 100 mr/hr. 4.2 A non-scheduled containment evacuation alar 1n. 4.3 Unanticipated airborne activity at any area gas or particulate monitor which indicates activity in excess of the maximum pcr=issible concen-trations specified in Appendix B Table I to 10 CFR Part 20. 4.4 Excessive radioactive surface contamination levels due to a major spill of radioactive materials. 4.5 other emergency conditions, such as fire, that may endanger human ., life or health as deemed necessary by the Duty Shift Superintendent or Health Physics Supervisor. Y a---4,-.,*e.,..- , , .w. -
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5.0 : PROCEDURE 5.1 Shift Superintendent or Plant Operations Manager / Designee . 5.1.1 Identify the areas that have to be evacuated. 5.1.2 Choose the assembly area where personnel will be relocated.
-If possible use the following areas:
- a. Health physics station, if evacuation is from areas within the controlled area or o-o b. Plant cafeteria, if evacuation is from areas outside the j controlled area.
5.1.3 Fill in the underlined announcement blanks in Step 5.1.4 with the appropriate information determined in Steps 5.1.1 and 5.1.2. :
- 5.1.4 Sound the plant evacuation alarm (and fire alarm if appro-
, priate) and announce over the PA system: (NOTE: AN Q1 ANNOUNCEMENT CANNOT BE MADE WHILE THE ALARM IS SOUNDING.)
! " ATTENTION, ALL PERSONNEL: THERE ARE CONDITIONS AT THE PLANT (- THAT WARRANT.A LIMITED PLANT EVACUATION IN THE
- l AREA (S). ALL PERSONNEL IN THE AREA (S)
(Specify Area) EVACUATE IMMEDIATELY AND REPORT TO THE AND AWAIT FURTHER INSTRUCTIONS." l (Specify Area) , 5.1.5 Repeat the alarm sounding and announcement two more times. Repeat the alarm and announcement again after an interval of L two to five minutes. 5.1.6 Notify the Duty & Call Superintendent and Health Physicist l of the limited plant evacuation. 5.1.7 Initiate EPIP 8.1, " Personnel Assembly and Accountability," if not already done. 5.1.8 Initiate EPIP 7.0, "CHP Radiological Response and Prepared-ness," as required. 5.1.9 Reevaluate the ability to re-enter evacuated area (s) and ~ attempt to isolate affected area (s) as required.
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a =._ _.n _2 == xxx: ;; - ~ 4 EPIP 6.1-(O). 5.1.10 Consider the initiation of EPIP 6.2, " Plant Evacuation," if the hazard continues to increase in severity. 5.1.11 Work may resume in evacuated area (s) when it has been deter- . mined by the Shift Superintendent and a chemistry & Health Physics Supervisor that no significant radiation hazard or other hazard to personnel remain. 5.2 Health Physicist / Health Physics Supervisor 5.2.1 Determine the scope of the radiation and contamination problem by implementing radiation surveys of affected area (s). 5.2.2 Specifying appropriate protective devices, commence a decon-
.tamination operation and set up appropriate health physics postings of the affected area (s), if required.
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.h EPIP 6.2 MINOR L .l- ,y Revision 3 j 09-09-83 PLANT EVACUATION 1.0 m ur m .
This procedure describes the steps and instructions to be taken in the. event of a plant evacuation. This procedure will be used when conditions are such that the plant, including the protected area, must be evacuated. Assembly areas are defined in particular locations and are constant for all
. plant evacuations.
2.0 REFERENCES
None-3.0 PRECAUTIONS AND LIMITATIONS 3.1 All actions and notifications should be appropriately logged. ,- 3 3.2 A plant evacuation will probably not be necessary for an Unusual
- )/ Event or Alert classification.
3.3 Unless otherwise directed by supervision, personnel should exit the controlled area as they usually would after discarding protective , clothing and frisking themselves at " Checkpoint Charlie." 3.4 Unless otherwise directed by the guard at the gatehouse, personnel leaving the protected area should punch out at the gatehouse, leave their ID badges at SAS and exit through the south door, bypassing all other monitoring devices. .. 3.5 When the TSC'is manned, the responsibility for evacuations and evacuation announcements is transferred to the TSC (Plant Operations Manager) unless otherwise directed by the Site Manager. 4.0 INITIAL CONDITIONS A plant evacuation will be considered when any of the following conditions exist. l 4.1 Radiation levels in general areas of the protected area are in excess
-of 100 ar/hr.
4.2 Airborne activity in general areas of the protected area are in '
- excess of maximum permissible concentration and exposures are ex- ~
pected to exceed 40 MPC hours.
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EPIP 6.2 Page 2 a.-.. 4.3 Other emergency conditions where it is deemed necessary to evacuate nonessential personnel.from the plant.
, 5.0 PROCEDURE i- 5.1 Shift Superintendent or Plant Operations Manager /Designes-t 5.1.1. Notify security personnel that a plant evacuation is imminent and instruct them to implement procedure PBSP 1.9, " Emergency Evacuation Procedure.."
5.1.2 Notify'the Duty & Call Superintendent, Duty Technical Ad-visor, and the Superintendent - Chemistry & Health Physics l or Health Physicist of the impending plant evacuation. 5.1.3 Alert the Energy Information Center of the impending plant evacuation, by calling Ext. 246. Request that visitors be evacuated from the center using EPIP 6.4, " Energy Infor-nation Center Evacuation." . I 5.1.4 Sound the plant evacuation alarm and fishermen's pier evacu-
.ation alarm and announce over the P.A. System:
,}.
j " ATTENTION ALL PERSONNEL, ATT1DiTION ALL PERSONNEL, THERE ARE CONDITIONS AT THE PLANT THAT WARRANT A PLANT EVACUATION. ALL PERSONNEL SHALL IMMEDIATELY ASSEMBLE IN THE FOLLOWING AREAS: PLANT PERSONNEL REPORT TO WITH ASSIGNED EMERGENCY EMERGENCY DUTIES LOCATIONS PLANT PERSONNEL REPORT TO i 'NOT ASSIGNED EL. 18.5' 0F ! EMERGENCY DUTIES THE TECHNICAL j SUPPORT CENTER BUILDING VISITORS AND REPORT TO CONTRACTORS SITE BOUNDARY CONTROL CENTER , AND AWAIT FURTHER INSTRUCTIONS." 5.1.5 Repeat the alarm' sounding and announcement two more times. !' 5.1.6 Initiate EPIP 8.1, " Personnel Assembly &; Accountability," if .. not already done. l. 5.1.7 Initiate EPIP 7.0, "CHP Radiological Response and Prepared-ness," if not already done.
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5.1.8 . Consider. the initiation of EPIP 6.3, " Exclusion Area Evacu-ation," if the hazard continues to increase in severity or spreads to-areas outside the protected area or it is deemed necessary to evacuate personnel from established assembly
.. areas at the plant.
5.1.9 Contact the Township of Two Creeks and request them to make 2 the Two Creeks Town Hall available for an assembly area for plant personnel by calling 755-2049 or 755-4196. NOTE: '(Telephone numbers are applicable 24 hours per day.) 5.2 Visitors and contractors These persons should keep their dosimeters and TLD's, exit at.the gatehouse, and report to the site boundary control center. When exiting the gatehouse, the portal monitors should be bypassed and the south door should be used. At the site boundary control center, people should remain in their cars except the supervisors doing accountability checks. After accountability is done, the Health . Physics Director will determine what personnel monitoring will be f.-
- required.. After the Health Physics Director is satisfied with con-t_ tamination levels, the dosimeters and TLD's will be collected prior to release.
5.3 Personnel Not Assigned Emergency Duties These persons should keep their dosimeters and TLD's and report to the assembly area on the 18.5' level of the technical support center building. O 4 e
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V EPIP 6.3 MINOR'
/ Revision 2
' j[g 00-09-83 EXCLUSION AREA EVACUATION
'I 1.0 GENERAL q This procedure describe the steps and instructions to be taken if an exclusion area. evacuation is anticipated. This procedure will be used when conditions are such that the plant and the area around it, i.e., energy information center, nature trail, switchyard, fishing pier and roadways to the exclusion gates, must be. evacuated.
2.0 REFERENCES
; None 3.0 ' PRECAUTIONS AND LIMITATIONS 3.1- All actions and notifications should be appropriately documented.
,7 3.2 The security checkpoint, assembly area, personnel monitoring and
~ O# "i decontamination station can be established at either the site boundary control center or the Two Creeks Town Hall. This will depend upon the magnitude of the release and meteorological conditions. The
, Health Physics Director will recomunend to the Site Manager which facility is preferred.
3.3 When the TSC is manned, the responsibility for evacuations and evacuation announcements is transferred to the TSC (Plant Operations Manager) unless otherwise directed by the Site Manager. l 4.0 PREREQUISITE CONDITIONS . 4.1 EPIP 6.2, " Plant Evacuation," completed. 4.2 Exclusion area evacuation will be considered when any of the following conditions exist. 4.2.1 Radiation levels in general areas of the exclusion area are in excess of 10 mr/hr whole body dose rate. (See Section 1.0) 4.2.2 Airborne concentrations of radioiodine are greater than 5.3 x 107 pCi/cc averaged over any two hour period in general areas of the exclusion area. (This would result in a two~ hour dose to the thyroid of 2 Rem assuming that. the predomi- - nate isotope is I-131.) l . l L
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w. O P EPIP 6.3 Page,2 yl 4.2.3 When emergency or support personnel radiation doses in assembly areas and/or emergency response facilities are approaching or exceeding the following radiation dose limits:
- a. Whole body gamma: 1.5 Res
).
- b. Thyroid: 5 Rea
- c. Beta skin dose: 3 Rem 1,
4.2.4 As other emergency conditions may dictate.
~~
5.0 PROCEDURE I' 5.1 Designee 5.1.1
, If not already done, contact the Township of Two Creeks and l: request them to make the Two Creeks Town Hall available for l; - .an assembly area for plant personnel by calling 755-2049 or ;
755-4196.
*I. NOTZ: (Telephone numbers are applicable 24 hours per day.)
l
' >} 5.1.2 Ensure that EPIP 6.2, " Plant Evacuation," is completed.
L 5.1.3 Instruct the chemistry / Health Physics Supervisor and the Health Physics Director to identify assembly areas or support centers that must be evacuated in accordance with the exposure criteria listed in Section 4.2 above. 5.1.4 Instruct the Health Physics Director to establish a personnel monitoring and decontamination station at the Two Creeks Town Hall or the site boundary control center. 5.1.5 Instruct the Shift Security Lieutenant to establish a check point and assembly area at the Two Creeks Town Hall or site boundary control center. 5.1.6 For each assembly area or support center identified for need of evacuation in Step 5.1.3, designate the alternate location to be used. If possible, use the alternate areas listed in the following table. i Support Center or Assembly Alternate Location Area to be Evacuated to be Used . . .
~
Technical Support Center Control Room Security Building Site Boundary Control Center (Extension B llding) or Two Creeks Town Hall Onsite Operations Support Center Site Boundary Control Center
-(Staging Area). or Two Creeks Town Hall
~~
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o 9 EPIP 6.3 Page 3 i ;
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Emergency Support Center ' Two Creeks Town Hall Site Boundary Control Center' Two Creeks Town Hall i 5.1.7 ' Inform gach assembly area and support center identified in Step 5.1.3 that personnel must be evacuated and communicate to them the following information. ,
- a. The alternate location to which personnel should report (Refer to step 5.1.6 of this procedure).
- b. Preferred route to follow to the alternate assembly area.
- c. Protective measures to be taken by personnel before they j, evacuate the area.
l U d. After arriving at new assembly area, initiate personnel
' accountability procedures in accordance with EPIP 8.1,
" Personnel Assembly and Accountability," and report- -
results to the technical support center or control room. b > l '. 5.1.8 Continue to update all assembly areas'and support centers V . with respect _to where personnel should report and insure that personngl are made awar.e of- possible radiation hazards in areas requiring access and re-entry. 5.1.9 Re-evaluate. the ability to re-enter plant assembly areas or support centers and attempt to isolate affected areas as l required. l l I .
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p EPIP 6.5 MINOR d Revision 3
,J
../ 09-09-83 TECHNICAL SUPPORT CENTER & OPERATIONS SUPPORT CENTER ACTIVATION 1.0 PURPOSE ,
4: 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 power supply is also a part of this procedure. 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
.s physics areas of the technical support center.
5 t
.[7 2.2 Install phones from the technical support center storage cabinets in
.the appropriate areas as shown on Attachment 6.5-1.
2.3 Confirm that all phones operate by noting if dial tone is present when the receiver is lifted. Confirm that the numbers listed on the face of t'.. 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 front of the black-board and the table near the dose plotting map (see Attachment 6.5-1). l 2.6 Obtain a copy of each of the following manuals from the front office area and bring them to the technical support center. They may be obtained from the office of the Manager, General Superintendent, or the training offices. 2.6.1 Operating procedures. 2.6.2 Emergency operating procedures. l 2.7 Shift the ventilation system from the normal to the emergency opera-ting mode by implementing Section 4.0. . Date and time the current charts on the safety parameter chart re-2.8
' corders in the technical support center.
O
. - _ . _ _ _ - , _ - _ _ ~ _ . . . . _ . _ _ . _ . _ . _ . _ _ _ - . _ _ . . . _ . _ . ~ . _ . _ . _ - _ _ . _ . _ . _ .
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a< _ , l EPIP 6.5 p., "9" (, / , 2.9 Dispatch a person with systems training (Duty Technical Advisor) to control room to aid in communications between the TSC and control room. 3.0' DATA LOGGER OPERATION 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 accomplished 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). 1 . 4.0 EMERGENCY VENTILATION SYSTEM 4.1 The technical support center heating and ventilating system has a :
normal and emergency operating mode. Under normal operation the air intake as from the outside air vent on the east wall of the technical
] support center building. The intake air under normal operation is
/ essentially unfiltered.
In the emergency mode, there are two optional air intake 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 hall 1. 4.2 To' shift the heating, ventilating and air conditioning system from the normal to emergency mode: - 4.2.1 Turn the auto /off/ occupied switch on Panel M-1 to the occu-pied position. See Attachment 6.5-7 for location of Panel M-1. 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 intake depending on meteorological conditions. Select the upwind intake duct. 5.0 TECHNICAL SUPPORT CENTER AUXILIARY AIR CONDITIONING
~
5.1 Turn on compressor CH2 on the west wall of El. 18'.5' of the technical' ~ support center building (see Attachment 6.5-7).
*~
' 5.2 Turn on air handling unit ANU2 on the technical support center building room north. wall (see Attachment 6.5-1).
^
. _ _ a,. -
EPIP 6.5
'- ~- Page 3 6.0 EMERGENCY POWER 6.1 The power source for the technical support center in 1B01480 V. See Attachment 6.5-8 for the inain disconnect location.
6.2 The emergency power source is not operational at ,this time. P a f i e e s" %* x
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. Personnel Status RMS TABLE TABLE , __ _ _ , j 398 Core Coord. ,
755-4631 395 i DESK Data Proc. Coord. 755-4680 'SBCC Ringdown I j Environmental Dose Plot Status Map T
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Data Loccer Point Designations l Channel Unit Status Parameter 0 mV Active 3) ) 1 av Active 12) Unit 1 Reference ) 2 mV Active 13) RTD ) Unit 1 Inco n 3 mV Active ~18) Junction Box "A" ) amoc uples o 4 av Active 22) ) 5 av Active 26) Unit 1 Reference ) 6 av Active 29) RTD ) 7- av Active 36) Junction Box "B" ) 8 mV Active 3) ) 9 av Active 12) Unit 2 Reference ) , 10 mV Active 13) RTD ) Unit 2 Incore 11 mV Active ~ 18) Junction Box "A" ) Thermocouples 12 mv Active 22), ) 13 mV Active 26) Unit 2 Reference ) V 14 mV Active 29) ATD ) 15 av Active _36) Junction Box "B" ) 16- *F- Active Unit 1 Reference RTD Junction Box "A" 17 *
.F Active Unit 1 Reference RTD Junction Box "B" 18 *F Active- Unit 2 Reference RTD Junction Box "A" 19 *F Active Unit 2 Reference RTD Junction Box "B" 20 gpm Active Unit 1 Auxiliary Feed Flow "A" SG 21 gpm . Active Unit 1 Auxiliary Feed Flow "B" SG 22 gpm Active Unit 1 SI Flow Train "A" 23 gym Active Unit 1 SI Flow Train "B" 24 ft Unit 1 Containment Sump Level 26 V Active Unit 1 Containment Purge Stack RMS-II Ch #3 27 gpm Unit 2 Auxiliary Feed Flow "A" SG 28 gpm Unit 2 Auxiliary Feed Flow "B" SG 29 gpm Active -Unit 2 SI Flow Train "A" 30 gpm Active Unit 2 SI Flow Train "B" 31 ft Unit 2 containment Sump Level L 33 V Active Unit 2 Containment Purge Stack RMS-II Ch #4 34 V Active Drumming Area Vent Stack RMS-II Ch #2 35 V Active combined Area vent Stack. RMS-II Ch #5 '
- 36. V Active Gas Stripper Building Vent Stack RMS-II Ch #6 37 V Active Auxiliary Building Vent Stack RMS-II Ch #1 e
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- POINT DEAL.. NilCLEAR PLANT - INCORE T/C TABLE - REFE.. NCE JUNCTION AT 160. DEG F DEO F MV DEG F MV DEG F MV DE8 F MV DEG F MV DEG F 1 MV 0.00' 152. 7.60 497. 15.20 824. 22.00 1146. 30.40 1472. 30.00 1811.
0.20 .161. .7.80 505. 15.40 833. 23.00 1155. 30.60 1481. 38.20 1821. , 0.40 170. 8.00 514. 15.60 841. 23.20 1163. 30.80 1490. 38.40 1829. 0.60 100. 8.20 523. 15.00 850. 2?-40 1171. 31.00 1498. 38.60 1839. 1 0.00 189. 8.40 532. 16.00 858. 23.60 1180. 31.20 1507. 38.80 1848.
, 1.00 198. 8.60 540. 16.20 867. 23.80 1188. 31.40 1516. 39.00 1857.
1.20 200. 8.80 549. 16.40 875. 24.00 1197. 31.60 1524. 39.20 1867. ; l 1.40 217. 9.00 558. 16.60 883. 24.20 1205. 31.80 1533.- 39.40 1876. . 227. 9.20 567. 16.80 892. 24.40 1214'. 32.00 1542, 39.60 1885. i 1.60 - j 1.00 236. 9.40 576. 17.00 901. 24.60 1223. 32.20 1551. 39.80 1894. 2 00 245. 9.60 584.- -17.20 909. 24.80 1231. 32.40 1540. 40.00 1904. 2.20 254. 9.80 593. 17.40 918. 25 00 1240. 32.60' 1568. 40.20 1913. 1577. ! 2.40 263. 10.00 602.. 17.60 926. 25.20 1248. 32.80 40.40 1922. l 2.60 272. 10.20 610. 17.80 935. 25.40 1256. 33.00 1586. 40.60 1932. 1 2.00 282. 10.40 618. 18.00 943. 25.60 1265. 33.20 1595. 40.80 1941. I 3.00 290. 10.60 627. 18.20- 951. 25 80 1274. 33.40 1604. 41.00 1950, 3.20 300. 10.80 636. 18.40 960. 26.00 1282. 33.60 1613. 41.20 1960. ! 3.40 309. 11.00 645. 18.60 968. 26.20 1291. 33.80 1621. 41.40 1969. 3.60 318. 11.20 653. 18.80 977. 26.40 1299. 34.00 1631. 41.60 1979. 3.80 327. 11.40 662. 19.00 985. 26.60 1300, 34.20 1639. 41.80 1988. g 4.00 336. 11.60 671. 19.20 ~ 993. 26.80 1316. 34.40 1649. 42.00 ~1 998. - 4.20 345. 11.80 679, 19.40 1002. 27.00 1325. 34.60 1657. 42.20 2008. 4.40 354. 12.00 688. 19.60 1010. 27.20 1334. 34.80 1666. 42.40 2017. 4.60 363. 12.20 696. 19.80 1019. 27 40 1342. 35.00 1675. 42.60 2026. ; 4.00 372. 12.40 705. . 20.00 1028. 27.60 1351. 35.20 1684. 42.80 2036. i 5.00 381. 12.60 714. 20.20 1036. 20.40 1045. 27.80 28.00 1359, 35.40 35.60 1693. 1702. 43.00 43.20 2045. 2055. p [ j 5.20 390. 12.00 722. 1368. y> l
- 5.40 399. 13.00 730. 20.60 1053. '28.20 1377. 35.80 1711. 43.40 2065. l.
1 5.60 5.80 400. 417. 13.20 13.40 739. 747. 20.80 21.00 1061. 1070. 28.40 28.60 1385. 1394. 36.00 36.20 1720. 1729. 43.60 43.80 2074. 2084. [ 6.00 426. 13.60 756. 21.20 1078. 28.00 1403. 36.40 1738. 44.00 2094. I 6.20 434. 13.80 765. 21.40 1087. 29.00 1411. 36.60 1748. 44.20 2103. I ! 4.40 444. 14.00 773. 21.60 1095. 29.20 1420. 36.80 1756. 44.40 2113. Y l 6.60 452. 14.20 782. 21.80 1103. 29.40' 1429. 37.00 1746. 44.60 2123. l 6.00 462. 14.40 790. 22.00 1112. 29.60 1437. 37.20 1775.
- 44 00 2133.
] 7.00 470. 14.60 799. 22.20 1120. 29.80 1446. 37.40 1784. 45.00 2142. ? 7.20 479. ' 14.80 807. 22.40 1129. 30.00 1455. 37.60 1793. 45.20 2152. l 7.40 488. 15.00 816. 22.60 1138. 30.20 1463. 37.80 1802. 45.40 2162. i A AO Hil Tttrste i r- en His p r e g o c air p ' issn r y y n n A y gso ngn g
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ATTACIDENT 6.5-4
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DRUMMING AREA VENT STACK RMS-II CH #2 &- COMBINED AIR EJECTOR DISCHARGE RMS-II CH #5 VOLTAGE TO R/HR CONVERSION TABLE RANGE 1 to 10" R/HR Volts Units R/hr 0 0.001 0.1 0.00135
- -0.2 0.001847
^4 0.3 0.002511 O.4 0.003414 0.5 0.004641 0.6 0.006309
- 0.7 0.008576 '
0.8 0.011659 . O.9 0.015848
,,, 1.0 0.021544
. 1.1 0.029286 QV. 1.2 0.039810 1.3 0.054116 1.4 0.073564 1.5 0.100 1.6 0.135935 1.7 0.184784 1.8 0.251188 1.9 0.341454 2.0 0.464158 l 2,1 0.630957 2.2 0.857695 2.3 1.165914 l 2.4 1.584893 2.5 2.154434 2.6 2.928644 2.7 3.981071 2.8 5.411695 2.9 7.356422 3.0 10.0
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ATTACHMENT 6.5-5 m UNIT 1 RMS-II CH #3 & UNIT 2 RMS-II CH #4 ( CONTAINMENT PURGM STACKS VOLTAGE '1O R/HR CONVERSION TABLES _ RANGE 10 ' TO 10' R/HR Volts Units - R/HR O. 0.1 0.1 .135 0.2 .184 0.3 .251 0.4 .341 0.5 .464 . 0.6 .630' - 0.7 .857
/~ % 0.8 1.165 0.9 1.584 y-
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- 2. 46.415 l
2.1 63.095 l 2.2 85.769 l 2.3 116.591 I 2.4 158.489 l 2.5 215.443 2.6 292.864 2.7 398.107 2.8 541.169 2.9 735.642 l 3. 1000. l- .. g , - . = y -.--m - pyr <a..m= m y 3 >-. pw -p y- - ,w w --y w y w-r-v wy- g - ---
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ATTACHMENT G.5-6 AUXILIARY BUILDING VENT STACK RMS-II CH #1 & GAS STRIPPER BUILDING VENT STACK RMS-II CH #2 VOLTAGE TO R/HR CONVERSION TABLE RANGE 10-' TO 10' R/HR s i volts Units - R/HR
- 0. 0.01-0.1 .013 0.2 .018 0.3 .025 0.4 .034 0.5 .046
, 0.6 .063 0.7 .085 0.8 .116 0.9 .158 .
- 1. .215 -
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- 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 2.6 29.286 .
2.7 39.810 2.8 54.116 2.9 73.564
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EPIP 6.6 O ,- MINOR Revision 0
-' 08-26-83 PLANT EVACUATION FOR PERSONNEL USING NORTH GATE
- j. 1.0 PURPOSE To provide for evacuation, assembly and ac~ countability for personnel that use the north gate as an entrance to the Point Beach Nuclear Plant. This procedure will provide for safe and efficient evacuation of personnel using the north gate.
2.0- DISCUSSION 2.1 Personnel who have key cards which only allow exit from the Point Beach Nuclear Plant site by the north gate must have an evacuation, assembly and acccuntability procedure separate from that of the personnel which use the south gate. , North gate key cards will not allow exit through the south gate.-
- 2. 2.
^
2.3 South gate key cards will not allow exit through the north gate. O 3.0 PROCEDURE' 3.1 Upon hearing the evacuation alarm (a repetitive quickly rising tone) listen for a short period to instructions following the alarm. 3.2 If the evacuation is a limited plant evacuation,- follow the instructions given.
. 3.3 For a' plant evacuation, leave your work area using your key card at all security access points.
NOTE: YOU WILL NOT BE ABLE TO OPEN THE NORTH GATE DOOR UNLESS YOU PUNCH OUT AT EACH SECURITY ACCESS POIliT. FRISK OUT OF CONTROLLED SIDE WORK AREAS UNIISS DIRECTED OTHERWISE. r ( 3.4 Leave your key card with guards at the north gate. 3.5 Take dosimetry, i.e. self-reading dosimeter and TLD, to the assembly point at the Two Creeks Town Hall on the northwest corner of Tapawingo Road and State Highway 42. m
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,o .
Page 2 4
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3.6 The supervisors for each work group should account for all the personnel under his supervision on that day. Report any missing personnel to the Security representative at'the Two Creeks Town HalA. 3.7 . Personnel will be checked by health physics personnel fas appropriate. . f .
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o . e:' J EPIP 7.1.1 A MINOR I Revision 3
-' 09-09-83 CHEMISTRY & HEALTH PHYSICS GROUP PERSONNEL NOTIFICATION AND INITIAL RESPONSE WHEN CHEMISTRY & HEALTH PHYSICS PERSONNEL ARE ON SITE 1.0 ' PURPOSE The purpose of this procedure is to establish guidelines for the initial response of the chemistry & Health Physics group iri cupport of an Alert, .
.S'ite or General Emergency which.may require Chemistry _& Health Physics response during normal duty hours while chemistry & Health Physics per-sonnel are on site. A rapid and organized response by the Chemistry & ,
Health Physica Group is necessary to facilitate early assessment of site radiological conditions. The three major areas of concern are as follows:
, a. The area within the protected area including the plant buildings.
- b. The area outside of the protected area but within the exclusion area -
-(site boundary perimeter lines).
p,
- c. Those areas off-site (beyond the exclusion area).
i 2.0 PRECAUTIONS & LIMITATIONS !' 2.1 Assigned personnel .will wear the prescribed protective clothing, dosimetry devices, and other prescribed protective equipment when on their job assignments.
. 2.2 Whenever possible,-standard health physics procedures are to be L followed. ~
2.3 It is to be understood that these are implementation guidelines and that the existing plant and radiological conditions may necessitate changes to these guidelines and/or the. sequence in which they are implemented. Appendix "A" should be used to verify completion of procedural steps. 3.0 CHEMISTRY & HEALTH PHYSICS GROUP INITIAL RESPONSE l 3.1 Upon notification that an Alert, Site, or General Emergency is in. ~ effect, all Chemistry & Health Physics group personnel on site not already assigned an emergency function will report to the health physics station. e
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) l 3.2 Upon arrival at the health physics station, the Health Physics Director and Radiochemist will take a roll call of Health Physics and Chemistry personnel, respectively. Personnel not accounted for will be paged.
If an evacuation has been ordered, the Shift Lieutenant will be notified of missing personnel.
- A 3.3 The Health Physics Director and Radiochemist will appoint a Senior Health Physics Supervisor and Senior Chemistry supervisor, respec-tively, to assist the chemistry / Health Physics Supervisor direct group operation in event of an escalation to a site Emergency.
3.4 The Health Physics Director will establish a communications link with
, the TSC.
3.5 The Health Physics Director will assign one Health Physics Supervisor
, and two Radiation Control Operators to the OSC/TSC to implement EPIP 7.2.2. The Radiochemist will assign one Chemistry Supervisor and two Radiochemical Technicians to the OSC/TSC to help implement EPIP 7.2.2. They should obtain the following equipment .
Dosimeters (0-500 mR) As available cm Dosimeters (0-5000 mR) 25 ea.
. Dosimeter Chargers 2 ea.
( N As available - Teletector PIC 6A As available other Instruments and Equipment As available , 3.6 Under direction of the Senior Health Physics Supervisor, Health Physics personnel will collect and make ready the following equipment or their equivalents. This is for SBCC. Rad.0wl One 1 ea. Hini-Scaler battery pack 1 ea. HPI-1010 1 ea. Bio-Paks 5 ea. Spare oxygen cylinders (charged) 12 ea. l Sodasorb replacement bags 12 ea.
~
The remaining Chemistry & Health Physics supervision and personnel will remain alert for further instructions from the Chemistry / Health Physics Supervisor in the TSC. . 3.8 In .the event of a limited plant evacuation (EPIP 6.1), the Health . Physics Director will direct health physics response from the health .
. physics station. The Radiochemist will direct chemistry response
- from the health physics station. The Chemistry / Health Physics Super-visor in the TSC will be kept informed of these actions.
3.9 In the event of the need for protected area /off-site surveys, the Health Physics Director will make' assignments as necessary and inform the Chemistry / Health Physics Supervisor in the TSC.
_ ._ ~. -. -_ .__- _--~-
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EPIP 7.1.1 O .; Page 3
.;/ i 4.0 CHEMISTRY & HEALTH PHYSICS GROUP RESPONSE FOR A SITE OR GENERAL EMERGENCY 4.1' The Health Physics Director will report t's the site boundary control center utilizing the site emergency vehicle. The balance of Chemistry
& Health Physics personnel will report to the health physics station.
4.2 The Senior Health Physics Supervisor will assign two (2) Nuclear Plant Specialists - Health Physics and two (2) Radiation Control ' operators to report, using personal vehicles, to the site boundary control center to assist the Health Physics Director.
. 4.3 In the event of a plant evacuation, the Senior Health Physics Super-visor and Radiochemist will:
y 4.3.1 Assign personnel as follows: OSC/TSC SBCC Health Physics Supervisor (all) Rad control Operators (2) Nuclear Piant Specialist - Nuclear Plant Specialist - Chemistry (all) Health Physics (all) Radiochemist (1) ACT's assigned to HP (all)
' ]- - Rad Control Operators (2)
Rad / Chem Technician (all)
'4.3.2 Assign one site boundary control center individual to obtain a carryall vehicle (other than the assigned site emergency vehicle), and wait with the vehicle at the west entrance l
door near Ready Stores. This vehicle will be used to trans-port equipment to the site boundary control center. 4.3.3 Assign one site boundary control center individual to.acti- ' vate Chemistry & Health Physics facilities at the emergency support center and then report to the site boundary control center. l l
- 4.3.4 Upon completion of the above procedure guidelines, the Senior Health Physics Supervisor will direct the Health Physics personnel assigned to the site boundary control l
center to report utilizing private vehicles and/or health ! physics assigned Company vehicles: Two company vehicles in addition to the carryall assigned in Step 4.3.2 should be taken to the SBCC for use by the mobile survey teams and the ' Kewaunee/ environmental shuttle team. e l '
. . _ . . _ _ ~ _ . . . . . _ _ _ . _ . . , . _ . _ _ , . . . , _ . . . - _ . . _ _ , , , . _ , . _ _ . . . . . , - . . . . _ _ . . - . . . _ . , _ . _ . , . . . _ _ _ _ . . , , _ _ . . _ , . . . _ ,
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APPENDIX "A"
.,,g EPIP 7.1.1 CHECKLIST s .: <
CHEMISTRY & HEALTH PHYSICS GROUP PERSONNEL NOTIFICATION AND INITIAL RESPONSE WHEN CHEHISTRY & HEALTH PHYSICS PERSONNEL ARE ON SITE i Date 3 INITIALS TIME
'1.0 ALERT STATUS 1.1 Chemistry & Health Physics group personnel report to the health physics station.
1.2 All Chemistry & Health Physics group personnel (en duty present and/or accounted
,j for.
1.3 shift Security Lieutenant notified of . missing personnel. - r*, 1.4 Communications link with TSC established. i a
- 1.5 Personnel assigned.to OSC/TSC as per Sections 3.5 and 3.6.
! 2.0 SITE OR GENERAL EMERGENCY STATUS l l 2.1 Alert status procedural steps complete. 2.2 Personnel assigned to the SBCC as per Section 3.4. 2.3 Equipment listed in Sections 3.5 & 3.6
- assembled.
2.4- For a plant evacuation,-acting Health Physics Supervisor will: (Section 4.3) l l 2.4.1 ' Assign personnel to the TSC/OSC and SBCC (Section 4.3.1). 2.4.2 Assign one CBCC individual to cet a carryall vehicle and wait at the west entrance door by Ready Stores i (Section 4.3.2). , l - 2.4.3 Assign one SBCC individual to activate the ESC (Section 4.3.3). l l l I . , _ _ _ - . , - . _ - . - , - - . , _ _ _ . . - . - . . - . _ . ~ . , _ . _ _ . _ , . . _ . _ . . _ . . _ _ . . - . _ . . _ _ . . _ . . . _ _ _ _ _
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- e. .t, INITIALS TIME 2.4.4 Monitor loading of equipment (Sec-tion 4.3) into carryall and direct driver to proceed to the SBCC.
2.4.5 Direct Chemistry & Health Physics
. personnel to proceed to the SBCC or TSC/OSC as assigned (Section 4.3).
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,D Revision 3
.' 09-09-83
( ACTIVATION OF HEALTH PHYSICS FACILITIES AT
' SITE BOUNDARY CONTROL CENTER - 1.0 PURPOSE The primary purpose of this procedure is to provide guidelines for acti-vating the site boundary control center during a Site or General Emergency requiring plant evacuation or in the event that surveys outside the pro ~
tected area are required. Hodifications to these guidelines may be
; - implemented by the Health Physics Director (Health Physicist) to meet the existing plant and site radiological conditions so as to ensure the con- ,
tinued safety of plant personnel and the general public. 2.0 ACTIVATION OF HEALTH PHYSICS FACILITIES AT SITE BOUNDARY ColfrROL CENTER 2.1 Health Physics Director ; The Health Physics Director or his designated alternate is respon-
>% sible for directing health physics activities at the site boundary
('j/' ~ control center and for providing radiation protection assistance as reque,sted by the chemistry / Health Physics Supervisor. .When the Radcon/ Waste Hanager is available, the Health Physics Director should report to him. Appendix "A", Health Physics Director Duties, provides the specific guidelines for accomplishment of these duties. l l 2.2 Assistant to the Health Physics Director When manpower allows, the Health Physics Director will assign a chemistry & Health Physics Supervisor to perform the duties of Assis-tant to the Health Physics Director. The Assist.nt Health Physics. Director is responsible-for directing Chemistry & Health Physics personnel frem the site boundary control center and for the coordi-nation of all health physics related activities with the Health Physics Director. Appendix "B" provides the guidelines for accom-l plishment of these duties. 2.3 The following teams will be manned by personnel as assigned by the Health Physics Director or the Assistant to the Health Physics Director. Team duties are outlined in the respective appendix.
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Team Appendix 4 Site Boundary Control Center / Radiation Control Team B Counting Team C I I Survey Teams C Kewaunee/ Environmental Shuttle Team C
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- 1. Obtain environmental data (wind speed, direction and stability class) from the Chemistry / Health Physics Supervisor in the technical support center.
- 2. Use results from EPIP 1.4, " Radiological Dose Evaluation," and EPIP 1.5,
~~~~^
" Protective Action Evaluation," procedures and determine the extent
; and location for the initial and followup environmental surveys as
, required.
- 3. When manpower allows, designate a chemistry & Health Physics. Super-visor to perform the duties of Assistant to the Health Physics Di rector at the site boundary control center (EPIP 7.2.1, Appendix "B").
If manpower is not sufficient, perform the duties listed in Appendix -
"B".
C 4. Coordinate with the RadCon/ Waste Manager, when available, control and exposure doctmentation within the exclusion area and off-site.
- 5. Coordinate with the RadCon/ Waste Manager when available on the evalu-l ation' of environmental radiological survey results, project dose consegaences, and make recommendations consistent with the Emergency Plan with respect to the general population (EPIP 1.4 and EPIP 1.5).
- 6. Coordinate off-site surveys with Radiation Control / Waste Manager when available.
l 7. Assist in evaluating medical emergencies and coordinate use of the i site emergency vehicle with the Chemistry / Health Physics Supervisor. ! 8. Establish access controls to coordinate access to the operations ! support center and the protected area. Ensure that all personnel entering or exiting the site are properly accounted for and are equipped with the necessary dose evaluation devices.
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a EPIP 7.2.1 Page 4 APPENDIX "B"
$ITE BOUNDARY CONTROL CENTER HEALTH PHYSICS RESPONSIBILITIES ASSISTANT TO THE HEALTH PHYSICS DIRECTOR
- 1. Direct the available Chemistry & Health Physics Group personnel in setting up and making available for use all site boundary control center health physics equipment. Verify the availability and opera-tional status of equipment after it is checked out.
- 2. Designate Chemistry & Health Physics personnel to man the following radiation control teams as personnel become available for duty.
- a. Counting team (one Nuclear Plant Specialist-HP, one Radiation Control Operator).
- b. Survey teams; two, two-man teams. One survey team should be -
~
given primary responsibility for plume and whole body ganuna measurements at locations to be specified. .
- c. Site boundary control center / radiation support team (remaining Radiation Control Operators and Auxiliary Operator Trainees).
- d. Kewaunee/ environmental shuttle team (if required).
- 3. Initiate health physics radio communications radio check (Channel 3 of FH radios). Ask control room personnel to ask Appleton to minimize radio traffic.
- 4. . Receive environmental radiological survey instructions from the Health Physics Director and direct survey team leader to conduct the surveys.
- 5. Coordinate all environmental radiological surveys. Ensure that all surveys are properly logged and identified.
- 6. Coordinate counting of air samples and smear surveys with the counting team leader. Receive and review the completed sample results from the
. sample team leader.
- 7. Report all environmental radiological surveys in their complets:d form to the Health Physics Director for evaluation.
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- 8. Coordinate with the Health Physics Director on samples requiring multi-channel analyzer counting. Direct the site boundary control center / radiation support team leader to trarsport samples to the operations support center or as otherwise directed for MCA counting.
Receive and repprt the completed analysis to the Health' Physics Director. SITE BOUNDARY CONTROL CENTER HEALTH PHYSICS RESPONSIBILITIES SITE BOUNDARY CONTROL CENTER / RADIATION CONTROL TEAM
- 1. Set up and verify operational status of personnel friskers.
- 2. Monitor personnel and equipment for contamination and perform decon-tamination as necessary.
- 3. Implement control and documentation of personnel entering or exiting the exclusion area. .
~
- 4. Implement controls for dosimetry issue, use, and documentation of personnel exposure and control of exposure data.
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! . 5. Coordinate all health physics activites with the Assistant to the Health Physics Direqtor.
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APPENDIX C SITE BOUNDARY CONTROL CENTER HEALTH PHYSICS RESPONSIBILITIES COUNTING TEAM l'. Set up and verify the operational status of all site boundary control center counting equipment. - 2.. Perform other duties as directed.
. SITE BOUNDARY CONTROL CENTER HEALTH PHYSICS RESPONSIBILITIES SURVEY TEAM
- 1. Set up and verify the operational status of the site boundary control center air sampling and radiological survey equipment. .
- 2. Conduct all radiological surveys and air sampling. Record all air sample data and radiological survey results.
- 3. Ensure that all air samples and radiological surveys are properly logged and identified prior to turn in to the Assistant to the Health Physics Director.
I 4. Perform other duties as directed. I- SITE BOUNDARY CONTROL CENTER i HEALTH PHYSICS RESPONSIBILITIES KEWAUNEE/ ENVIRONMENTAL SHUTTLE TEAM
- 1. Transport samples to Kewaunee Nuclear Plant for analysis as directed by the Assistant to the Health Phys,ics Director.
l 2. . Retrieve samples from mobile survey teams and transport to TSC for analysis. I
- 3. Document results of analysis and report results to the Health Physics Director by radio or telephone.
- 4. Perform other duties as directed.
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EPIP 7.2.2 HINOR 1 Revision 3
. 08-26-83 ACTIVATION OF CHEMISTRY & HEALTH PHYSICS AT TECHNICAL SUPPORT CENTER /0PERATIONS SUPPORT CENTER 1.0 ~ PURPOSE 1.1 The purpose of this procedure is to establish guidelines for acti-vating the Chemistry & Health Physics facilities at the technical support center / operations support center (TSC/OSC) in support of an emergency situation which may require evacuation-of the main plant buildings.
1.2 The Chemistry / Health Physics Supervisor and certain designated mem-bers of the Chemistry & Health Physics Group are responsible for , activating the health physics equipment at the TSC/OSC The extent i and sequence of implearntation of these guidelines will be outlined , in EPIP 7.1.1. .
. _. 2.0 ACTIVATION OF HEALTH PHYSICS' FACILITIES AT TSC/OSC -
) ,
2.1 For emergency conditions during which a plant evacuation is not required, the Chemistry / Health Physics Supervisor and Health Physics Director will determine to what extent, if any, health physics cover-age will be provided at the TSC/OSC. 2.2 For emergency conditions which require plant evacuation, Appendix "A" guidelines of EPIP 7.1.1 should be followed. The sequence for imple-mentation of Appendix "A" guidelines depends upon whether Chemistry & Health Physics Group personnel are on or off-site when notification is received (EPIP 7.1.1 and EPIP 7.1.2). l 3.0 HEALTH PHYSICS RESPONSIBILITIES FOR TSC/OSC/ RAD SUPPORT TEAM 3.1 When Chemistry & Health Physics Personnel are On-Site (EPIP 7.1.1) 3.1.1 Obtain five (5) PIC-6A survey instruments. 3.1.2 Proceed to the TSC/OSC and: l.
- a. Move the AHS-2 continuous air sampler (cart-mounted) into the TSC/OSC hallway and set up for operation.
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- b. Place the Vamp area monitor at the south gate in oper-ation.
- c. Set up and place into operation the south gate low volume air sampler. .
- d. Proceed to the TSC/OSC and begin preparation.to provide health physics support as described under OSC/HP equip-ment activation, Section 3.3 of this procedure.
3.1.3 There are two Nuclear Chicago counter-scalers available for
- use. One is normally kept at SBCC. The other Nuclear Chicago counter-scaler may be used by health physics in day-to-day activities. This unit is to be taken to OSC for use.
3.2 Notification When Chemistry & Health Physics Personnel are Off-Site (EPIP 7.1.2_)_ 3.2.1 Upon receipt of instruction to activate the TSC/OSC, one . member of the OSC/ rad support _ team will proceed to the ESC located in the basement of the Energy Information Center
/. ' ,
and:
\~/ a. Set up and place into operation the low volume air sampler and Vamp area monitor.
- b. Perform a communications check of the portable radio (red) located in the Duty Technical Advisor's sleeping
- quarters.
- c. Proceed to the TSC/OSC.
3.2.2 The remainder of the OSC/ rad support team will set up and
- i. place into operation the Vamp area monitor and the low volume air sampler at the south gate.
3.2.3 Proceed to the TSC/OSC and move the AMS-2 continuous air sampler (cart-mounted) into the TSC/OSC hallway; set up and place the AMS-2 into operation. 3.2.4 Begin preparation to provide health physics coverage as duscribed under OSC/HP equipment activation, Section 3.3 of this procedure. l
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3.3 OSC/HP Equipment Activation 3.3.1 Prepare the health physics equipment from the emergency locker for use. 3.3.2 Prepare red radio for communications check.
.3.3.3 Prepare the Nuclear Chicago counter-scaler for use.
3.3.4 Provide health physics support as required at the TSC/OSC and in-plant support as requested by the Chemistry / Health Physics Supervisor. 3.3.5 Assist in' response to medical emergencies within the pro-tected area (EPIP 11.0). 3.3.6- Coordinate with the Chemistry / Health Physics Supervisor at' the TSC/OSC on in-plant personnel exposure and documenta-tion. , verify that all personnel who are departing from the OSC are
~
3.3.7 certain as to details of their approved assignments and are complying with all health physics requirements. Whenever h practicable, entries into high radiation or airborne areas will be made under the radiation work permit system. 3.3.8 Determine contaminated area access point and set up SOP and
. control point at TSC/OSC entrance to Unit I turbine hall.
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- EPIP 7.2.4
- MINOR Revision 3
,? 09-09-83 IMALTHPfSICSCOMMUNICATIONS 1.0 PURPOSI D
The purpose of.this procedure is to provide communcations guidelines for the Chemistry & Health Physics group to assist in the perforinance of their duties during an Emergency Plan situation requiring plant evacuation and/or in the event that surveys outside of the protected area are required. l 2.0 COMMUNICATIONS, GENERAL J 2.1 Radiological response comununications between health physics response teams (EPIP 7.2.1) will normally be accomplished utilizing Channel 3 of the FM (red) radio network. Telephone coussunications should be held to a minimum. 2.2 The following radio locations are maintained at all times: ; Location Type (s) 2.2.1 Control room Base station 12 portables 2.2.2 Technical support center Base station 4 portables 4 1 2.2.3 Site boundary control center Portable base 3 portables 2.2.4 Emergency support center 1 portable (DTA's) F 2.2.5 Medical' vehicle 1 portable 2.2.6 HP storage room (TSC) 1 portable t
- 2.3 LRadio Communications Network Functional Check 2.3.1 Upon arrival at their assigned locations, health physics
,- personnel shall place radios in an operating mode and stand by for a radio check. The' site boundary control center is
-responsible for initiating the radio check. The results of a the comununications check should be recorded in the site boundary control center logbook. -
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2.3.2 Mobile or portable radio units should also be given a func-tional check prior to departing from the site boundary control center for the performance of assigned duties. 2.3.3 Radio antennas must not be in contact with metal structures . when being used to transmit. , 3.0 RADIO PROTOCOL 3.1 To eliminate confusing radio transmissions and to expedite communi-cations, . the foloving should be adhered to: 3.1.1 Identify the radio call-sign and your unit or location at I the start of each transmission. EXAMPLE: SITE BOUNDARY CONTROL CENTER, SURVEY TEAM NO. 1 3.1.2 Use of radios are for business purposes only. 3.1.3 Limit the time of all transmissions. .
. ..; 3.1.4 FCC regulations prohibit the use of vulgar or profane language. . 3.1.5 Upon completion of the conversation, sign off as follows:
EXAMPLE: SURVEY TEAM NO. 1, CLEAR & STANDING BY. 4.0 USE OF TELEPHONES 4.1 The use of the telephone communications network by health physics personnel during an Eniergency Plan situation will be limited to the following: 4.1.1 NRC Health Physics Dedicated Line These lines are located in the Ch'mistry e & Health Physics group office and at the site boundary control center. They provide a means .of direct communD:ations with the NRC health physics offices during an emergency. .The use of these lines will be only as directed by the Chemistry / Health Physics Supervisor, the Health Physics Director or other ranking plant supervisors. 4.1.2 Plant PBX Telephone System This system provides direct dialing between plant locations , within- the on-site and protected areas. The use of these lines is to be limited to business-related calls.
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4.1.3 Off-Site Telephone Lines These lines provide for direct dialing to off-site locations. The use of these lines is to be limited to business-related calls. Use should be minimized to the extent practicable. t 0 6 e G e . 6
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1.0 INTRODUCTION
1.1 This procedure outlines the steps necessary to collect, handle and analyse a high level reactor coolant sample which could result from gross fuel failure.
'1.2 Equipment Lis3 set up the following in the primary sample hood prior to collecting I
. your sample:
1.2.1 The equipment detailed in Figures 2A and 2B, with the exception
,of the sample bomb. ,
1.2.2 One magnetic stirrer and one 50 al poly beaker and a 50 ml beaker. _h. y O' l.2.3 A pH/av meter and pH probe. - 1.2.4 A piston burette.
- 1.2.5 A lead brick wall of sufficient size to store residue from analysis.
1.2.6 Automatic pipets, continuously adjustable through 5 m1, or equivalent. Remote handling tools located in the cabinet below the i 1.2.7 hood. 1.2.8 Prepare a 1.0 litet sidearm flask with a correctly sized solid stopper and rubber septum over the sidearm. 1.2.9 Gas syringe The following equipment is also necessary for this procedure and need to be made ready. 1.2.10 The gas partitioner for H2 analysis. 4 e
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1.2.11 The special cart used for transport of the sample bomb. 1.2.12 Tools for connecting and disconnecting sample bomb; i.e.,
. 11/16" open end wrench or equivalent.
l'.2.13 Remote valve turning tool. This tool as_well as those i mentioned in Step 1.2.12 are necessary for sampling 3 . and should be taken along and placed on the sample bomb transport cart. 1.3 Reagents The follwing reagents are also necessary and need to be prepared. 1.3.1 0.lN NaOH for boron. Obtain a supply from normal boron analysis.. 1.3.2 Manitol for boron analysis. 1.4 Preliminary Steps Initials 1.4.1 Standardize the pH meter. 3 1.4.2 Organize as much of the equipment as possible behind lead brick walls in an arrangement (~=2) ' that allows for unobstructed view of all , operations with the aid of the convex mirror. (See Figure 2.) 1.4.3 Put new rubber septum on gas' bomb. 1.4.4 Check out and prime the piston burette with fresh 0.1N NaOH solution. 1.4.5 Make'sure that the vacuum line is attached to the gas collection bomb at the valve 1 location. Open valves 1 and 2. Secure valve 3. . 2.0 PRELIMINARY EVALUATION NOTE: THIS EVALUATION SHALL BE COMPLETED PRIOR TO ANY ATTEMPT TO ENTER THE AUXILIARY BUILDING OR SAMP!E ROOM TO OBTAIN A REACTOR COOLANT SAMPLE UNDER EMERGENCY CONDITIONS. l 2.1 - Possible Indication of Fuel Damage i Some or all of the following would be present if fuel damage had occurred: - 2.1.1 The letdown radiation monitor (R9) would be unusually high or offscale. l ..
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>: :.J Initials 2.1.2 The Unit 2 failed fuel monitor (2RE-109) will be unusually high or offscale.
2.1.3 The Unit 1 containment radiation monitors (R11 and R12) or the Unit 2 containment radiation monitors (RE-211 and RE-212) would be unusually
- - high or offscale.
i 2.1.4 The Unit I containment area monitors (R2 and R7) or the Unit 2 containment area monitors
. (RE-102 and RE-107) would be reading unusually
' high or offscale.
2.1.5 The auxiliary building stack monitor (R14) would show a significant increase due to auxiliary building airborne activity from the letdown and charging pump areas. 2.1.6 Evaluation of Sample Room Conditions .
... a. The sample room area monitor (R6 or RI-106) and charoing pump area monitor (R4 or RI-104) would give a Icdication of conditions in the auxiliary building and sample room.
- b. After evaluation of the radiation monitoring system readouts, Health Physics will determine what airborne and radiation surveys would be appropriate before auxiliary building entry.
- c. Verify the requirements for auxiliary building
. sample room entry, i.e., (1) RWP requirements, (2) clothing requirements, (3) respiratory requirements, and (4) dosimetry requirements including extremity dose monitoring requirements, and (5) health physics coverage requirements including timekeeping.
2.2 Possible Loss of Component Cooling t 2.2.1 Verify that component cooling is still in service to the affected unit. Sample cannot be obtained without-component cooling to sample room heat exchangers.
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3.0 RIACTOR COOLAnff SAMPLING PROCEDURE NOTE: THIS PROCEDURE SHALL NOT BE INITIATED UNTIL THE EVALUATIONS DIS-CUSSED IN SECTION 2.0 HAVE BEEN COMPLETED AND REVIEWED BY DUTY & CALL SUPERINTENDENT (COORDINATOR), DUTY HEALTH PHYSICS , SUPERVISION AND THE DUTY SHIFT SUPERINTENDENT, AND THEIR APPROVAL ! HAS BEIN GRANTED. 3.1 Collectina a Pressurized Sample (Refer to Fig'are 1) Initials , NOTE: THE FOLLOWING STEPS WILL BE ACCOMPLISHED UNDER THE DIRECTION OF HEALTH PHYSICS SUPERVISION AND ONLY AFTER COMPLETING SECTION 1.0 0F THIS PROCEDURE. 3.1.1 The following steps (a through f) must be s accoglishSd bef' ore opening the incontainment sample isolation valve 955 (Step 3.1.2) and the hot leg sample isolation valve'966C (Step 3.1.3).
. a. Verify that the domineralized water header pressure is approximately 100 to 120 psi. ,
l_ NOTE: THIS STEP NAY BE DELETED IF REACTOR _- ' fN MAEEUP WATER IS USED FOR THE FLUSH.
- b. Proceed to the sample room install the shielded sample benb on the outside wall of the sample room using the fittings provided.
If the bomb is already installed, verify that the fittings are tight. CAUTION: BEFORE REMOVING THE SWAGE LOCK CAPS TO INSTALL THE BOMB, OPEN VALVES 939, 940 AND 941 TO RELIEVE SYSTEM
- PRESSURE. CLOSE VALVES 939, 940 AND 941. PLACE A WASTE BUCKET DIRECTLY UNDER THE B0HB. USE A PAPER TOWEL SHIELD AND RUBBER GLOVES WHEN REMOVING CAPS.
- c. Verify that the ' dimineralized water line is connected from valve 945 to the de-mineralized water manifold. Open demineralized H 2 O valves 945, 947, and 948 and check for leaks on the bomb fittings.
Shut valves 945, 947, and 948.
- d. Enter the sample room and close the following valves on the sample panel. -
- 1. 961C -_ Normal hot leg sample bomb inlet.
- 2. 964C - normal hot leg sample bomb outlet.
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- 3. 965C - normal hot leg sample bypass.
- 4. 968 - normal hot leg return valve.
f 5. 971 - normal hot leg sink sample valve.
- e. Notify the control room that the failed
' fuel monitor (RE-109) will be taken out-of-service for sampling; then close:
9388 - detect'or RE-109 inlet valve < 938A - detector RI-109 outlet valve
- f. Further verify that there is component cooling
, flow to the sample room heat exchangers by viewing the local flow indicator (FI-603) on tne sample panel.
- g. Open the following valves on the sample panel. -
- 1. %9A - sample system purge to volume
> .,N control tank.
- 2. 956C - normal hot leg sample supply valve. .
, 3. 990 - residual heat removal sample i supply valve. , l h. For Unit 2 verify that the DI water valve j (2-991) located on the east wall of the sample room is open.
- 1. Leave the sample room and position the following valves wide open. These valves are located on the sample room wall.
- 1. 939 - sample bomb inlet.
- 2. 940 - sample bomb bypass.
- 3. 941 - sample bomb outlet.
l~ NOTE: FOR DRILLS AND TRAINING EXERCISES OPEN VALVE 941 ONLY ONE-QUARTER TURN TO ELIMINATE N-16 GAMMAS. . I
~' .
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_ . -. _. . _ _ . . _- _ . . . . __ -_ ~....__-. . _ . ~ _:. - _ . - .. _ - .- .- . EPIP 7.3.2
%,. Page 6 Open the incontainment hot leg sample isolation 3.1.2 valve (valve 955) and the residual heat removal i sample isolation valve (valve 959) by means.of the switches located outside the No. 1 pipeway for Unit 1 or No. 4 pipeway for Unit 2.
CAITfION: IF THE AFFECTED UNIT IS ALRIADY ON RHR, LEAVE THE AREA IMNEDIATELY AFTER OPINING VALVE 959 AS BACK-GROUND RADIATION LEVELS WILL RISE SHARPLY. If the valve No. 955 will not open because of _ containment isolation, perform the following
. steps (1 through 3).
- 1. Request that the Control Room reset the con-tainment isolation signal.
- 2. Turn the local control switch positions for valves 951, 953, and 955 to the "close" .
position.
, 3. Turn the local control switch for valve q ,,! 955 to the "open" position.
! NOTE: SECTION 3.1.2 MUST BE ACCOMPLISHED BEFORE SAFETY INJECTION RECIRCULATION'HAS BEGUN. 3.1.3 Leave the area and request control room to open the hot leg sample isolation valve (966C). . 3.1.4 Verify sample flow by an indrease in the radiation level. 3.1.5 After a minimum recirc time of 15 minutes, return to the sample station and using tite remote valve operating tool, fully open valves 9B and 9A and 8A and 8B. 4
- a. Slowly and completely close valve 940.
- b. Leave the primary auxiliary building.
NOTE: THE VALVE OPERATING TOOL SHOULD BE USED TO OPERATE ALL VALVES EXCEPT 945, 946, 947 AND 948 (FLUSH VALVES). , d
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- l .
3.1.6 After 5 additional minutes, return to collect the sample. Close valves 9B and 9A and then
- valves 8B and 8A using the remote valve operating tool. Make note of the sample' .
dollection time.
~ '
NOTE: DO NOT DISCOBBIECT THE SAMPLE BOMB UNTIL c . SAMPLE FLOW IS SECURED AND THE DI FLUSH
- IS COMPLETE AS EVIDENCED BY REDUCTION IN RADIATION LEVELS.. ;
3.1.7 Request control room to immediately close the hot leg sample isolation valve 966C. NOTE: - IT IS VERY IMPORTANT THAT THE HOT LEG SAMPLE ISOLATION VALVE 966C IS CLOSED PRIOR To STARTING THE DI FLUSH. WAIT FOR CONFIRMATION FROM THE CONTROL ROOM. > 4.0 SAMPLE LINE FLUSHING 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 i least 15 minutes.
~)
NOTE: DO NOT REMAIN IN THE AREA 0F THE SAMPLE STATION DURING THIS FLUSH. After about 15 minutes return and measure radiation levels. 4.2 If a Chemistry & Health Physics Supervisor determines that the levels are satisfactory, close whitey valve 946 and , using the remote valve tool, close valve 939. Then open valve 947 and valve 948 and allow about a 15-minute DI-flush. 4.3 After about 15 minut'es, close valves 940 and 941 with the 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 from the fittings using a paper towel to prevent spraying. Remove the shielded sample bomb from its support. Remove excess liquid from the top and bottom bomb fittings with a syringe and dispose behind lead shielding. Replace the Swagelok caps on the wall fittings and on the bomb. Transport the bomb, remote valve tool and wrenches to the chemistry lab on a cart. NOTE: AFTER DRILLS AND TRAINING EXERCISES, RETURN ALL EQUIPMENT AND VALVE LINEUPS TO NORMAL..(SEE SECTION 4.4). O mw -- , ~, ,_..me,.-, - - - - - - , y 4, , , , - ,__,,-.,,,-.,,.m. ,-wyy-,,,,, , , , ,.,,,,---,,-._,,,m,-,-4..__.-,,,-,-,,q,,,,,,,-g...,__,, ,,.. , , ,, , , , , -.,_,
-~.
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EPIP 7.3.2 Page 8 4.4 Enter the sample room and notify control room that the failed fuel monitor (RE-109) is-to be returned to service and that the sample room valving is to be returned to normal. 4.4.1 Close Valves:
- 1. 961C - Normal hot leg sample bomb inlet
- 2. 964C - Normal hot leg sample bypass
- 3. 965C - Normal hot leg sample bypass
. 4. 971 - Normal hot leg sink sample valve
- 5. 939 - High level sample bomb inlet
- 6. 940 - High level sample bomb bypass
- 7. 941 - High level sample bomb outlet
- 8. 945, 946, 947, 948 - Domineralized water l .
flush valves i f., ,\ ('#/ NOTE: DISCONNECT VALVE 945 FROM THE DEMINERALIZED WATER MANIFOLD. ADVISE CONTROL TO REDUCE DENINERALIZED WATER HEADER PRESSURE TO NORMAL. 4.4.2 Open Valves:
- 1. 9388 - Failed fuel monitor RE-109 inlet
- 2. 938A - Failed fuel monitor RE-109 outlet
- 3. 956C - Normal hot leg sample supply valve
- 4. 968 - Normal hot leg return valve
- 5. 969A - Sample system purge to volume control tank l.
- 6. 966C - Hot leg sample isolation valve.
5.0 SEPARATION OF THE PRESSURIZED SAMPLE AND ANALYSIS OF THE GASEOUS
- AND LIQUID COMPONENT (Refer to Figures 2A and 2B) i 5.1 Collectino the Gaseous Sample From the Pressurized Sample l
Place the shielded sample bomb in the sample 5.1.1 holder in the primary sample hood.
-g-, -c- g .ay-, y ,e-+a- --.,--y .n -.. - ,% , i.----re, ~,,,--e, ~ . , -,--e, , ..w---c.,r.g -,-,-r w----s--t+- y-,--r---- -vw -,- -
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a _ ._ ~.w wi ..w .--- :=.---. - - - a- - EPIP 7.3.2 Page 9 5.1.2 Connect the sample bomb to the shielded gas collection bomb by means of the fittings provided. Place lead bricks in the area of this connection for shielding. 5.1.3 connect the valve manifold to the opposite end of
- the sample bomb and verify that valve 11 on the manifold is open.
5.1.4 Make sure that the vacuum line is attached to the gas collection bomb at the valve 1 location. Open valves 1 and 2. Secure valve 3. Evacuate the gas bomb and connecting lines. With vacuum still on, secu_re valve 1. Secure vacuum. 5.1.5 Before proceeding, make sure no inleakage has occurred into the gas bomb by observing the vacuum gauge reading. Using the remote valve
, tool, fully open valves 91 and 98. Open valve 81 one-quarter turn. Crack open valve 88 and control degassing by throttling valve 88. -
~
Allow the system to degas for 5 minutes. Check that valves 9A and 9B, 81 and 88 are
/,N fully open. Close valve 2. \ !
fl0TE: OBSERVE THE VACUUM GAUGE. THE VACUUM SHOULD DROP VERY SLOWLY. IF THE DROP-
. IS TOO RAPID, CLOSE VALVE 8B SLIGHTLY.
DROP SHOULD BE 5-10" HG/ MIN. 5.2 Analysis of Gaseous Sample 5.2.1 Hydrogen l Use a syringe to draw a 1 cc sample. Use the injection port on the gas partitioner for' this analysis. 5.2.2 Radioactive Noble Gas-Use a syringe to draw a 1/2 cc sample and inject thiIs into the flask prepared in Section 1.2.8.* l Allow 30 minutes for thermal mixing. Draw a l 1 cc sample of this dilution and proceed as j normal. i 1
- Additional dilution should be performed if the contact reading is >l ar/ hour. -
NOTE: SEE SECTIONS 7.0 AND 8.0.
-. 'L . . ._a. :.;;
EPIP 7.3.2 _, Page 10 i 1 Collecting the Liquid Sample From the Pressurized Sample-5.3 NOTE: IT IS EXTREMELY IMPORTANT TO VERIFY THAT VALVE 2 HAS BEEN CLOSED BEFORE PROCEEDING. i 5.3.1 Open valve 3 slowly. Allow the liquid sample
. to drain into the 50 ml beaker. Direct a slow stream of air through the vent line on valve 3 if necessary tt; recover the total liquid sample.
5.3.2 Close valves 8A and 8B, 9A and 9B, and valve.3. 5.4 Analysis of Liquid Samples 5.4.1' Boron /pH Analysis
- a. Transfer a 5 ml sample using an automatic pipetter into a 50 ml poly beaker containing ~
a stir bar.
- b. After transfer is complete, record the pH. i c..Pluginthem$gneticstirrer,addmannitol, 4 s and proceed with the boron analysis.
l -
- ,e
~ '
NOTE: IF THE PRIMARY SYSTEM HAS BEEN BORATED, 5 ML OR.MORE OF TITRANT MAY BE NEEDED TO REACH AN ENDPOINT. NOTE: AFTER DRILLS AND PRACTICE RUNS, THE BORON TITRATOR MUST BE FLUSHED WITH-DEIONIZED WATER iT) PUT IN DRY LAY-UP. ALL. ELECTRODES SHOULD BE PLACED IN LAYUP SO THEY ARE CONDITIONED FOR . IMMEDIATE USE. ALSO PURGE ANY WATER THAT MAY BE HELD UP IN THE 280 ML GAS EXPANSION BOMB. 5.4.2 . Chlcride Analysis i l NOTE: THE CHLORIDE ANALYSIS WILL BE PERFORMED BY WE LAB SERVICES USING THEIR ION CHROMATOGRAPHY ANALYZER. e 4 Im - + -.-s--.- ~ , p-e ., 4--n----en,--,, ,,n - --n ,--,-.,,-m. ,--.-e- =-.a,e- ,-w,-e, w w -w-- e e,w -www-a,w,--.m e , --we ,- 6+
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EPIP 7.3.2 Page 11
,q Initials.
5.4.3 Iodine Analysis and Gaansa Scan Using the specially prepared 2 cc syringe or adjustable automatic pipet, withdraw 0.3 cc (or less) of the sample from the poly beaker and inject this sample into a 1000 ml poly bottle containing hineralized water. Make additional-dilutiohs in the same manner.* Count as normal. D
- Additional dilution should be performed until ,
the contact reading is <1 mr/ hour. NOTE: SEE SECTIONS 7.0 AND 8.0.
~
5.5 Reporting of Results
~
Complete and forward Reactor Coolant Post-Accident Sampling Analysis Report (EPIP-30). . 6.0 SAMPLE RESIDUE , Place all sample residue in the specially prepared lead pig for
. k' T.I disposal.
'7.0 SAMPLES TAKEN TO KEWAUNEE NUCLEAR PLANT FOR COUNTING'
Reference:
Post-accident counting agreement with Wisconsin Public Service, Kewaunee Nuclear Plant. Kewaunee Nuclear Plant does not utilize the 5 cc glass vial and 1 cc. test tube geometries. Therefore, " normal" samples will have to be diluted and , placed in one' liter poly bottles if they are sent to the Kewaunee Nuclear
' Plant for analysis.'
8.0. LABELING OF SAMPLES . Label all chloride, noble gas, 4~ue nd gamma scan samples with all l~ pertinent information such as. c. W number, name of sample, date and time of sampling, sample volov. ad ,. ution(s) . , l w e 4
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EPIP 7.3.3 MINOR 1.Q Revision 7
': 'f' r
08-26-83 POST-ACCIDENT SAMPLING OF CONTAINMENT ATMOSPHERE 1.0 ' INTRODUCTION This procedure outlines the steps necessary to collect, handle and analyze a potentially high radioactive. containment atmosphere sample resulting from gross fuel failure and loss of reactor coolant system integrity to
-determine hydrogen and radioactive gas concentrations.
.e 2.0 " PRELIMINARY EVALUATION 1 { NOTE: THE FOLLOWING EVALUATION SHAT 1 BE COMPLETED PRIOR TO ANY ATTEMPT
- TO ENTER THE FACADE OR R11/R12 CUBICLE TO PERFORM A VALVE LINEUP OR COLLECT A CONTAINMENT ATMOSPHERE SAMPLE.
n 2.1 L - Indications of Possible Fuel Damage - Some or all of the following would be present if fuel damage or
,f loss of reactor coolant system integrity had occurred:
o (-: .
=% 2.1.1 The letdown radittion monitor (R9) and failed fuel monitor (RE-109) would be unusually high or offscale.
- 2.1.2 The containment radiation monitors 1R11 and 1R12, or 2RE-211 and 2RE-212 would be unusually high or offscale.
2.1.3 The containment area monitors 1R2 and 1R7 or 2RE-102 and 2RE-107 would be unusually high or offscale. 2.1.4 The automatic actions of E0P-1A have caused containment isolation. 2.2 Evaluation of Radiological Hazards in Access Areas
- Required for Sampling Initials 2.2.1 After evaluation of the radiation monitoring system readouts, verify with Health Physics that the appropriate airborne and radiation surveys have been made before entering the facade.
9 t-s ---- r -eymw,e,e,as-,- ,-em--.,,,-,-- e- .,a-- - , .., p,- , - .n.w---wwa-w--, + , ., m-,, m.--e--wa-g -,n.,, --,,e.m---4 ---wv-e- - ,g,,,sm-e--mr e,- en+
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w ;_. w u -_~ ~ -- - - < - - = - EPIP 7.3.3 Q Page 2
+g a .'
Initials 2.2.2 Verify the requirements for facade and IR11/1R12 or 2RE-211/2RE-212 cubicle entry.
- a. Radiation work permit requirements
- b. Clothing requirements
- c. Respiratory requirements
- d. Dosimetry requirements including extremity dose monitoring '
- e. Health physics coverage requirements including timekeeping.
3.0 CONTAINMENT ATMOSPHERE SAMPLING PROCEDURE NOTE: TE FOLLOWING PROCEDURE SHALL NOT BE INITIATED UNTIL TE EVALUATION DISCUSSED IN SECTION 2.0 HAS BEEN COMPLETED.
,N TE DUTY & CALL SUPERINTENDENT (COORDINATOR), TE DUTY &
CALL HEALTH PHYSICS SUPERVISOR AND TE DUTY SHIFT SUPER-(d-) INTENDENT SHALL APPROVE TE IMPLEENTATION OF THIS PROCEDURE. TE FOLLOWING STEPS WILL BE ACCOMPLISED UNDER TE DIRECTION OF EALTH PHYSICS SUPERVISION. 3.1 Unit 1 Containment Atmosphere Sampling Using the IR11/1R12 Sampling System 3.1.1 Valve Lineup
- a. Entry into the facade sha_11 be from the potable water room.
- b. Verify with the control room that the IR11/1R12 sampling system is lined up in accordance with the following:
(1) The containment isolation valves 3200C and 3200G are closed. (2) The 3200A&B A0V's in the R11/R12 cubicle are closed. (3) The IP707 forced purge pump is - secured. - G
EPIP 7.3.3
- o. Page 3
)
. , . .,y Initials
- c. Proceed to the R11/R12 cubicle, and place (
the IR11/1R12 sampling system in the following linenp: r-(1) Open valves 1-3200J and 1-3200L. (2) Close valve 1-3200M. (3). Verify that the continuous vent valves 1-3200S and 1-3200W are closed. (4) Close valve 1-3200K.
- d. Connect the 100' service air hose to the Chicago fitting located on the elevator side of the cubicle established for sample -
line. purging.
- NOTE: TE AIR HOSE AND PRESSURE' REGULATOR
- r. 1 ARE STORED INSIDE THE POTABLE WATER
( ,/ ROOM. - e., Verify that valve 1-3200Y is closed.
- f. Proceed to the potable water room with the air hose and pressure regulator.
NOTE: FOR RCT TRAINING EXERCISES, DO NOT , USE THE POTABLE WATER ROOM SERVICE AIR H00KUPS, SINCE THEIR USE UNNECESSARILY BURDENS SECURITY. THE SERVICE AIR H00KUPS LOCATED ON THE EL. 66' CONTROLLED SIDE FACADE WALL ARE TO BE USED. (1) Attach the service air hose to an tvailable turbine hall service air outlet using the pressure regulator designated for this procedure. (2)- Lock the Chicago fitting in place using the appropriate pins.
- g. Verify with the control room that the -
1R11/1R12 monitor is lined up to monitor,
- and discharge to, containment atmosphere.
4
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- _: m = --__2- - -
EPIP 7.3.3 m -> Page 4
/
Initials
- h. Request the control room to open the 1-3200A&B A0V sample system valves and
- the containment isolation valves 1-3200C&G. f
- i. Verify sample flow by an increase in
-radiation levels in the cubicle, and return to the potable water room.
J. Allow 15 minutes for sample recircing. . Request control room to stop the pump
. and close 1-3200A, 3, C & G A0V isolation valves.
3.1.2 Sample Collection
- a. Enter _the facade and proceed to the sample point. Take along two 2 cc gas syringes in -
a hollowed-out lead brick. One syringe ' should have 1 cc of AgZ inside the syringe
-f;. barrel.
CAUTION: CONTAINMENT PRESSURE COULD THE0RETI-
, CALLY BE AS HIGH AS 60 PSIG. HOLD THE SYRINGE PLUNGER SECURELY. ALSO,
. LOCK THE GAS SYRINGES BEFORE WITH-DRAWING FROM THE SAMPLING SEPTUM, USING THE BUILT-IN LOCKING DEVICE ON THE SYRINGE.
- b. Remove the set screw and take two 1 cc gas samples. Place the syringes in the lead brick.
- c. Replace the set screw and ope'n valve 3200Y.
- d. Leave the facade and return to the potable water room.
3.1.3 Sample Line Purging
. a. Open service air valve and adjust the pressure t.o a setting of 10 psig greater than measured containment pressure,
- b. Request control room to open the pump -
discharge isolation valve 1-3200A.
- - - - . - - - - - , , -,,-c.. ,n-.---,, e . - - - , - -, - - --
. . . ~ w_. -. - 5A ----
N .. EPIP 7.3.3 q Page 5 e Initials
- c. Request. control room to start the IR11/1R12 Pump.
- d. Verify' purge effectiveness by measuring the reduction in radiation levels after
. approximately 15 minutes of purging.
- e. Request control room to close the 1-3200A pump discharge isolation valve, secure the
. pump, and open the 1-3200B&C pump _ suction
- s. isolation valves.
- f. Continue the purge for 10 more r.inutes.
- g. Request control room to close all pump discharge and suction isolation valves and secure tbe pump. ,-
, h. Secure the service air valve.
1 s
-) NOTE: AFTER DRILLS AND PRACTICE RUNS, RETURN ALL EQUIP!fENT AND VALVE LINEUPS TO THE AS-FOUND CONDITION.
3.2 Unit 2 Containment Atmosphere Sampling Using the RE-211/ RE-212 Sampling System, After Containment Isolation 3.2.1 Valve Line-Up
- a. Verify with the control room that the following containment isolation conditions exist:
(1) Valves 3200A, B & C have closed. I i (2) Pumps P707A&B have been secured. (3) Valve 3200G is lined up to return flow to the containment (Position 1). (4) Valves 3200D, E, F & H are closed.
- b. Obtain the designated 100' service air line and pressure regulator from the potable water room. -
I - l '. l
, . , . .--...n- . , . , ---,- . . . , . , . , , . . - , , - - . , . , , - , . - - - . , - - . - - . . . . ,
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EPIP 7.3.3
;- Page 6 Initials
- c. Proceed to the nonnuclear room with the air hose.and pressure regulator.
~
NOTE: FOR RCT TRAINING EXERCISES, DO NOT USE THE NONNUCLEAR ROOM SERVICE AIR H00KUPS, SINCE THEIR USE UNNECESSARILY BURDENS SECURITY. THE SERVICE AIR '
, H00KUPS LOCATED ON EL. 66' CONTROLLED SIDE FACADE WALL ARE TO BE USED.
(1) Attach the service air hose to an available turbine hall service air outlet using the pressure regulator designated for-this procedure.
, (2) Lock the Chicago fitting in place, using the appropriate pins. -
- d. Proceed to the RE-211/RE-212 cubicle and perform the following:
,,/ (1) Connect the service air hose to the Chicago fitting attached to valve 3200Y, and verify that the valve is closed.
NOTE: THE VALVE IS LOCATED ON THE ELEVATOR SIDE OF THE R211/R212 [ CUBICLE. l (2) Lock the Chicago fitting in place, l-l using the appropriate pins. (3) Enter the cubicle and perform the following: (a) Verify A0V-3200A&B are closed by visual observation. , (b) Manually close valves 3200K, l N, P, Q, W, EE & FF. t (c) Manually open valve 3200J & L. G
E
^
EPIP 7.3.3 l
~N, Page 7
, ' -)
Initials
- e. Request the control. room perform the following:
NOTE: TE SAMPLE PUMP P707A SEALS ARE RATED FOR 5 PSI. TO PREVENT AN INADVERTENT AIRBORNELRELEASE, THE CONTAINMENT PRESSURE MUST
-BE LESS THAN 5 PSI BEFORE PRO-CEEDING.
1 (1) _ Verify containment pressure is less
, ~ than-5 psi.
(2). Place the sample mode switch located in the cable spreading room in the SEPTUM position. (3) Open A0V's 3200A&B and the containment - isolation valve 3200C. (4) Start sample pump P707A. ,
- f. Verify sample flow by observing a flow increase on FIT-3288 and return to the nonnuclear room.
- g. Allow 15 minutes for sample recirculation and return to the cubicle with two (2) 2 ce gas-tight syringes in a hollowed-out lead brick. One syringe should have 1 cc
- l. of AgZ inside the syringe barrel.
I 3.2.2 Sample Collection l l a. Obtain two 1 ce gas samples from the sample septum by means of the gas-tight syringes. Withdraw the syringe plunger only. once. Do not purge the syringe as-the AgZ will retain the iodine from each withdrawal. NOTE: LOCK THE SYRINGE PLUNGERS PRIOR TO WITHDRAWING FROM THE SEPTUM.
- b. Plac~e the .;yringes 'in the lead bricks for l transport.
l
~
l
. .. ___-_..-,.-_.._.c.__ _ . . . _ _ _ _ _ . . _ _ _ . _ _ . . _ _ . . _ . . -
n.c_. ~ = .- 02 a ~. 1- - - - - - EPIP 7.3.3 Q Page 8 Initials
- c. Establish a service air pressure of 5 psi on the regulator and open valve-3200Y.
3.2.3 Sample Line Purge
- a. Return to the nonnuclear room and request the control room ~close valves 3200B&c.
- b. Allow the system to purge forward'for 25 minutes, then request the contro.
room perform the following:
. (1) Secure the sample pump P707A.
(2) Close A0V-3200A'and place valve 3200M in its normal position (Position 1). - (3) -Open A0V-3200B&c. 3 .. c. Allow the system to purge backwards'25
/ minutes and request the control room close valves 3200B&C.
- d. Return to the cubicle and perform the following:
(1) Verify the effectivenss of.the purge by measuring the reduction of the radiation levels. (2) Close the service air hose regulator, close valve-3200Y and remove the service air hose. (3) Enter the cubicle and open valves 3200K, N, P & Q. (4) Close valves 3200J & L. I 1 ~ I l k
- =.;..--
~ . - _ . - -
EPIP 7.3.3 Page 9
]
.. /
Initials
- e. Notify the control room that sampling has been completed, and that valves 3200W, EE & FF are closed.
NOTE: AFTER ALL DRILLS AND PRACTICE EXERCISES, ALL EQUIPMENT AND VALVE LINEUPS ARE TO BE RETURNED TO THE AS-FOUND CONDITION. 4.0 CONTAINMENT ATMOSPHERE ANALYSIS 4.1 Volume Adjustments 4.1.1 Before proceeding with the hydrogen, radioactive noble gas and radioactive iodine analyses, the sample contents of both syringes must be brought to atmospheric pressure. Use the shielded sacri- . ficial glass bomb for this purpose. - 4.1.2 ~ Insert the syringe through the rubber septum of the class bomb. Unlock the syringe locking device and let the syringe and bomb equilibrate for approximately 30 seconds. Relock the syringe and withdraw from the septum. Store the syringe in the lead brick. 4.1.3 Repeat Step 4.1.2 for the other syringe. 4.2 Hydrogen Assuming normal equipment setup and preparations are l complete, use the sample injection port on the gas l partitioner, inject a 1 cc gas sample and proceed using l normal hydrogen analysis procedures. i 4.3 Radioactive Noble Gases & Iodines l Noble Gases I 4.3.1 Use the 2 cc syringe with the 1 cc of AgZ for the noble gas and iodine separation / analysis. l 4.3.2 Inject the 1 cc containment atmosphere sample into a one liter poly bottle. Purge the syringe cace or twice while in the poly bottle in order - to recover all of the noble gases. Remove the I l
~
~
. - _ _ _ _ _ _ _ - _ 21
. g b syringe and store in the lead brick. Tape over the syringe hole in the poly bottle. Let the gas come to equilibrium for a minimum of.15 minutes while proceeding with the iodine analysis section.
4.3.3 Withdraw a 1 cc gas sample from the poly bottle in Step 4.3.2. If the contact reading on the syringe is less than 1 mR/hr, inject the sample into a 5 cc vial and count as normal. If the contact reading is greater than 1 mR/hr, further dilutions are necessary. Dilution procedure: Inject the 1 ce sample into a one liter poly bottle and allow to equilibrate. Withdraw 1 cc from the poly bottle. If the contact reading is less than one mR/hr, inject into a 5 cc vial and count as normal. If the contact reading is greater than 1 mR/hr, dilute further. ; NOTE: FOR EACH DILUTION, USE A NEW SYRINGE OR MAKE CERTAIN THE OLD SYRINGE IS COMPLETELY PURGED.
, LABEL NOBLE GAS SAMPLES AND IODINE SAMPLES
~
WITH ALL PERTINENT INFORMATION SUCH AS: SAMPLE NUMBER, NAME OF SAMPLE, DATE AND TIME OF SAMPLE, SAMPLE VOLUME AND DILUTION (S). Iodines 4.3.4 Unscrew the syringe top and remove the internal plunger. Pour the silver zeolite into a counting test tube and cap. 4.3.5 If the silver zeolite / iodine sample is less than one mR/hr contact, count the sample directly on the MCA using the test tube geometry. 4.3.6 If the iodine activity is too high to count directly, determine the radiation level in mR/hr at one foot. Also, determine the percent isotopic composition using the MCA and attenuating the sample if necessary. Determine the total iodine activity using.the following equation; R/hr @ l' C(CI) - 6E T - o
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EPIP 7.3.3
. m. Page 11 The following table can be used as an aid in determining the " Total Average Energy /y" (E T
) f r the above equation.
(1) (2) (1) x (2) Average y % Composition Weighted y Isotope Energy (Fraction) Energy I-131 0.380 I-132 0.731 I-133 0.530 I-134 0.857 I-135 1.238 Total Weighted y Energy: (ET ) Each individual iodine isotopic concentrtion (pCi/cc) is calculated as follows: pCi/cc I(g) = C(Ci) x 2 x 10+6 x (Fractional % Composition) . 5.0 CALCULATIONS Pressure & Temperature Correction (a; 5.1, ,
, Ask control room supervision for the temperature and pressure in containment (psig and *F). Determine atmospheric pressure (mm Hg) and temperature (*F) from the barometer in the laboratory. Convert this to psia. Apply the following correction factor to all results:
Initials Concentration (pCi/cc) x (P
. + 14.7) T + 459 P
lab Tlab + 459 P (mm Hg)' P lab (psia) = 14.7 psi x 760 mm Hg 5.2 Complete and forward Containment Atmospheric Post-Accident Sampling Analysis Report (EPIP-31). e
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X. ' EPIP 7.3.5
-i MINOR
. Revision 0 '
09-09-83' POST-ACCIDENT SAMPLING OF THE AUXILIARY BUILDING & DRUMMING AREA VENT STACKS-USING THE IS0 KINETIC STACK SAMPLING SYSTEM 1.0 PURPOSE 1.~ 1 The isokinetic stack' sampling' system is used to o'tain b an accurate sample of the auxiliary building and drumming area exhaust stacks during an accident condition. This procedure provides instructicnal
-guidelines and precautions for the use of the system.
1.2 In the event of a plant emergency requiring initiation of the Point Beach Nuclear Plant Emergency Plan, air sampling is necessary to determine the extent of plant. damage and airborne contamination. In
. addition,;these samples allow the Health Physicist to determine.the .
risks involved from the standpoint of health and safety. This - procedure does not cover the mechanics of analysis, but is specifically directed towards obtaining these samples. This procedure recognizes that masking of radioiodine peaks may occur (:- -m.- during multichannel analysis if the radioiodine charcoal filter is contaminated by radioactive air particulates, external contamination and/or radioactive noble gases.
~
2.0 PRECAUTIONS 2.1' Do'not let the-isokinetic sampling system run longer than one-half hour during -any major nuclear accident. The lead shielding requirements were based on the worst case nuclear accident and the accumulation of particulate and noble gases inside the pig for greater than one-half hour could possibly raise radiation levels above those allowed by 10 CFR 20 for the time required to remove the j sampling filters to the laboratory for analysis. i ! 2.2 Personnel assigned to survey teams shall wear the prescribed , l protective clothing, dosimetry devices, and other protective equipment required when conducting surveys. 2.3 Survey teams shall be aware of the exposure authorized for the specific job assignment and shall not exceed the maximum authorized exposure. l 2.4 - Survey teams shall carry survey instruments and. continuously monitor the areas they.are entering. - l 2.5 ' Standard health-physics procedures are to be followed when-radioactive contaminated material is being handled. t _- I
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. _ , EPIP 7.3.5 1 Page 2 3.0 PROCEDURE
.3.1 ' This procedure is written to minimize the radiation received while retrieving the sampling units.
. NOTE: EACH SAMPLE UNIT CONTAINS APPROXIMATELY 230 POUNDS OF LEAD.
TWO OR MORE PEOPLE WILL BE REQUIRED TO LIFT EACH UNIT. l'; There are two sampling stations-for the isokinetic stack sampling system. One monitors the auxiliary building vent stack and the other . monitors the drumming area vent stack. Each sampler and control unit are convenientiv located on El.-26'. This~ facilitates-the use of a cart for transporting the sample pig to the chemistry lab. The auxiliary building vent stack sampler is located in the stairwell adjacent to the Unit 1 elevator. The sampler for the drumming area vent stack is located inside the double doors to the drum preparation room. 3.2 With pump running, close the isolation valve. 3.3 Disconnect the inlet.to the filter. Let pump run one minute to purge noble gases. i.
'3.4 Then pump off and disconnect filter discharge. Place the filter shield assembly on the cart.
3.5- Seal the inlet and outlet tubes with tape or other appropriate means. 3.6 Directions 3.6.1 From the auxiliary building vent stack sampler, go through the door in the stairwell and right past the elevator. Go through the security doors and into the lab. 3.6.2 From the drumming area vent sampler, go out through the l double security door to the outside walkway and proceed l south then east around the facade. As you approach the i service building, enter the (bor to the left. As you approach the area of the Unit 1 elevator, proceed as in Step 3.o.l.
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'I Page 3 3.~ 7 Due to the high rad levels associated with the filters in the pig, do not remove them from the shield or vent them as required for other samples. .If necessary, remove the screw as shown in the attached drawing, n and aim this toward the MCA. Use shielding as necessasy to lower the count rate to an acceptable level.- Do not discard these filters by normal methods. Special handling will be required due to the high radiation levels.
NOTE: DO NOT OPEN THE FILW R SHIELD WITHOUT SPECIAL PRECAUTIONS AS DETERMINED BY HEALTH PHYSICS. ONLY THE SAMPLING SCREW MAY BE REMOVED FOR ANALYSIS. 3.8 Notify health physics personnel immediately with the percent isotopic analysis and determine whether the sampler should be set up for another sample. 3.9 Determine contact radiation levels for determination of total activity-in the filters. Activity determination will be done by the '
, QAD program on TSO. Combining the total activity with percent .
3 isotopic analysis from. chemistry and stack flow rates will give
.-- isotopic release-rates.
(,- 3.10 If another sample is required, install another pig with piping and filters installed in the sample line and turn the pump back.on. Note the time. t e
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- s.
MINOR
\ Revision 4
# 09-09-83 i ' PERSONNEL ASSEMBLY AND ACCOUNTABILITY i
- 1.0 GENERAL
-The purpose of this' procedure is to detail a method for.(1) the assembly of' personnel on the plant site in the event of an emergency situation and (2) the subsequent accounting of personnel. The goal of this procedure is to account for all personnel within 30 minutes of the evacuation alarm.
2.0 PRECAUTIONS & LIMITATIONS , 2.1 Fersonnel accountability roster sheets (forms EPIP-17-and EPIP-18, attached) must be completed quickly and accurately and forwarded to ' the appropriate supervisor as soon as possible. 3.0 INITIAL CONDITIONS : 3.1 - An emergency has been declared as a result of plant conditions.
. , 3.2 A limited plant, plant, or an exclusion area evacuation has been ordered requiring the accountability of all personnel in the area evacuated.
3.3 The Shift Superintendent has determined that personnel assembly and
-accountability.is necessary.
4.0~ PROCEDURE 4.1 Shift Superintendent 4.1.1 Determine and communicate as required any special instruc-tions necessary for safe evacuation of personnel in the plant (for example, verbally communicate the assembly areas, designate any assembly area not to be used, designate certain areas of the plant to be avoided, etc. ) . Assembly Areas For Evacuation: Control Room * , Technical Support Center * , 4
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a EPIP 8.1~ Page 2 g Site Boundary Control Center
- Emergency Support Center *
( security Building (Extension Building)* and Gatehouse
. For Limited Plant Evacuation:
Health Physics Station Cafeteria
+ For Plant Evacuation:
- ,- Operations Support Center *, El.' 8', TSC Building Evacuation Assembly Area El. 18.5', TSC Building For Exclusion Area Evacuation:
Two Creeks Town Hall-
- Center for emergency operation.
4.2 Security Shift Commander 4.2.1 Designate an' individual to perform Section 4.4 of this ,. . procedure for security posts. 4.2.2 Obtain a list of all personnel currently on the plant site from the appropriate security systems (badge checks, computer printouts, etc.) 4.2.3 As attendance is collected from the assembly areas (see Section 4.1.1), indicate ou the list obtained in Step 4.2.2 l l that.the individual has been accounted for. I 4.2.4 After the assembly areas and security personnel have sub- ! mitted their rosters, compile a list of missing personnel using form EPIP-17. 4.2.5 Attempt to contact missing personnel using the Gai-tronics system. 4.2.6 If unable to contact the missing personnel, obtain from the missing person's supervisor the last known or probable ' location and/or job assignment. Enter this data on form EPIP-17. 4.2.7 Transmit copies of form EPIP-17 to the Maintenance Super- - visor. 4.2.8 Update form EPIP-17 as changes to rosters arrive and as missing personnel are located. c - . . - . - .,.. , c . -y,.~.,-. .%-, ,m,,- -..,-. . ..--..--.,,.....---,++--...-.,-r%.*- --_--- -- . __ .__. _ _ - - _ _ _
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-.,. Page 3 4.2.9 Transmit any changes in form EPIP-17 to the Maintenance Supervisor immediately.
4.3 -Designated Supervisor at the Assembly Area (Including
-Centers for Emergency Operations) 4.3.1 Upon arrival at the assembly area, one supervisor should
- g compile a roster of all personnel in his group who are p present and accounted for using form EPIP-18 (attached) or i
an area roster. At each in-plant center, there should be 'a !~ roster of persons who are to report to that center. Each person present should be checked off. I 4.3.2' When it is felt that'the roster is completed as well as-posrible, give the Security Shift Commander at TSC El. 18.5" or at the site boundary control center of all personnel present and accounted for by name. 4.3.3 Update the respective group roster as personnel arrive at or depart from the assembly area. ;
~
4.3.4 Report changes of the roster to the Security Shift commander
. periodically or as determined necessary by the Security
! Shift C - nder. (v! 4.4 Security Officer / Designee 4.4.1 Compile a roster of all security personnel using form EPIP-18. 4.4.2 Upon completion of the roster, notify the Security Shift Commander. Alert him to any missing personnel. I 4.4.3 Maintain the roster current as personnel arrive at or depart from the security building or security posts. l 3 e
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EPIP 11.1 MINOR ['). , Revision 4 il 09-09-83 I ON-SITE FIRST AID ASSISTANCE
1.0 INTRODUCTION
AND PURPOSE [ 1.1 General Industrial Safety and First Aid Practices i I 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. i 1.2 First Aid i The Point Beach organization includes persons experienced in first aid procedures who will be called in the event of. injury. The plant , l- is provided with an emergency shower for use with a severely contami-L _. nated but less severely injured person, and a complete first aid roon l.T equipped with facilities and medical instruments suitable for physical j examinations. On-site first aid facilities are further described in Section 4.0.of this procedure. I 1.3 Hospital Assistance 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 possibilit exists that treatment and transportation of a patient may be complicated by radioactive con-tamination,' a fully equipped controlled access treatment room (the nuclear first aid room) has been provided at Two Rivers Conununity Hospital, Two Rivers, Wisconsin. A list of radiation and contami-l nation control materials in the treatment room is given in EPIP 11.3. l !~ 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. A portable FM (red) radio-is stored by the garage door for use in the medical vehicle. Arrangements have been made for backup assistance by the City of Two Rivers Fire Department emergency vehicle in case of multiple need. This backup. ambulance planning is described in EPIP 11.3. . _m
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EPIP 11.1
.,..- Page 2
? h 1.5 Plant Personnel Responsibility It is the responsibility of involved plant personnel to become familiar with this procedure and specifically with instructions with re, gard to their. individual actions required.
1.6 Telephone Contacts Telephone contacts required by this procedure can be found in EPIP-37 (: (attached). ,-
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 Accidents at Point Beach Nuclear. Plant." 2.3 HP 10.2, "Use of Personnel Monitoring Devices During an Emergency." . 2'. 4 EPIP 12.2, " Search and Rescue." - 2.5- EPIP 11.2, " Injured Person's Immediate Care."
~
'l X 2.6 EPIP.11.3, " Hospital Assistance."
3.0 ' DEFINITIONS The following definitions are used, in addition to Section 2 of the 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. 3.2 Personal Injury l l- An injury which requires either first aid or professional medical i attention and may involve lost time. i. 3.3 Disabling Injury An injury which requires professional medical attention and involves lost time, but would not be a life threatening injury.
~ '
3.4 Serious Injury
- An injury which requires professional medical attention and could result in a fatality or pennanent disability. -, y..Nm a w. g -~--+y, - +- ., e-A.-y--e ,r~-swngy--c-,y--p e w y+u------w=.-m4- 4 y w. -,-w4-w^e--- g-e y 9gi-gra-ew--w*y-=c g 4rr --- +--+e -9wt+>-r-
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EPIP 11.1 Page 3 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-The Wisconsin Electric report used to report every accident involving company-owned vehicles or a privately owned car used on company business. 3.8 Attending Physician's Report The Wisconsin Electric report which is required when a doctor provides care to a Company employee for a work-related injury. 3.9 First Aid _; Immediate and temporary care given the victim of an accident or
; serious illness until the services of a physician can be obtained.
4.0 ON-SITE FIRST AID ASSISTANCE 4.1 General On-site medical preparedness programs are the responsibility of the 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 I.ocation and Equipment' The Point. Beach.first aid room is located in the extension building on the second level. It is equipped as follows: basic furniture (desk, chairs, table, cabinets); sink; examination table; examination cabinet; examination equipment; scale; first aid supplies including assorted bandages and gauze dressings, tape, splints, bandage scissors, splinter forceps, portable burn kit, and portable first aid kit. 4.2.1 Responsibility
- The Company Medical Director is responsible for determining the equipment for the first aid room. The Point Beach -
Industrial Safety coordinator is responsible for maintaining the supply inventory.
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-; j 4.3 Emergency Vehicle Description A company-owned vehicle is provided and will be used to transport seriously injured personnel. The vehicle is equipped as follows:
stretcher, blanket and pillow; first-aid kit; burn kit; oxygen breathing unit; portable FM (red) radio located by the garage door. 4.3.1 Responsibility q . 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 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:
'v l 4.4.1 Gatehouse
- a. First aid kit 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 I
~
4.4.4 Unit 1 and Unit 2 Facades l t
- a. Stretcher, first aid kit, and burn kit; located on 66'
' and 26' levels outside each containment's personnel ' _ hatch.
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EPIP 11.1 Page 5 c. x ; h 4.4.5 Site Boundary control center
- a. First aid kit
- b. Burn kit 4.4.6 Checkpoint Charlie (entrance to controlled area)
- a. First aid kit I
- b. Burn kit
- c. Scoop stretcher
- d. Oxygen breathing unit J
- e. Trauma kit 4.4.7 Technical Support center
- a. First aid kit $
I
- b. Burn kit
.)
- c. Trauma kit
- d. Stretcher <
4.5 General Ackninistrative Responsibilities in Case of Injury - * (see EPIP 11.2 for procedures) 4.5.1 Employee Responsibilities
. f l
- a. ' Personal Injury and/or Disabling Injury
- 1. Report injury to supervisor and first' aid repre-sentative. ,
' I,,
- 2. Ensure that the attending physic'ian 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 Report all vehicle accidents promptly to supervisor 1.
and control room. 4 O f
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4.5.2 Employee's Supervisor's Responsibilities
- a. Personal Injury and/or Disabling Injury f
(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 n. Report." L (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
"'N Reports" to the appropriate group head, within eight working hours.
. .( )
(6) Ensure that the " Attending Physician's Report" is . completed and returned to the Industrial Safety coordinator whenever a doctor is consulted regardung a work-related injury. , (7) A serious injury or fatality is an " unusual event" and must be reported to the NRC within 15 minutes (EPIP 1.1). A fatality must also be reported to the
~
Point Beach Industrial Safety Coordinator. If the serious injury or fatality is the result of a boiler ' 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 attached form EPIP-37 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 consents and recommendations on i the " Motor Vehicle Accident Report."
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+. Page 7 i
t1 , (3) Submit a copy of the " Motor vehicle Accident Report" to the appropriate group head, within eight working hours. 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.
- c. . Report personal injuries that result in lost time'or death and near miss experieness which could have re-sulted in serious injury to the Accident Investigation committee chairman or the acting committee chairman.
- d. Report all lost time (disabling) injuries to the Accident :
Prevention Department, Milwaukee Public Service Building (see RPIP-37, attached). 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 EPIP-37, attached).
- f. Establish sufficient liaison with the injured to main-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. 1 l i e t
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.g l EPIP 11.2 MINOR S Revision 2 j 09-09-83 INJURED PERSON'S IMMEDIATE CARE 1.0 PURPOSE The purpose of this procedure is to provide Point Beach Nuclear Plant personnel guidance in the issnediate care of an injured person.
2.0 IMMEDIATE CARE - 2.1 Minor Personal Injury Minor injuries will be treated at the plant first aid station by a first aid representative. 2.2 Personal Injury (Not serious but' requiring professional medical attention). - After appropriate first aid the injured will be transported, normally
.O by a supervisor from the injured person's group, in a Company vehicle I other than the emergency vehicle to the Doctor's Clinic (if no contasi-nation is involved) and if it is between the hours of 0800 to 1700, Monday through Friday. At times other than this or when contamination is involved, the injured person will be transported to the Two Rivers Community Hospital (see EPIP-37, attached, for telephone numbers).
2.3 Disabling Injury (Serious illness or injury) The procedure for the care of seriously ill or injured persons will be in accordance with Section 2.4, " Resuscitation," and EPIP 11.3,
" Hospital Assistance."
2.4 Resuscitation If a person is found and appears to be unconscious, you must first establish unresponsiveness before attempting resuscitation. 2.4.1 Establish Unresponsiveness
- a. Establish unresponsiveness by gently tapping or shaking the patient and calling the patient's name.
- b. If unresponsiveness is established, call for help by calling the control room on the Gai-tronics.
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2.4.2 - Positienino Patient and Opening Airway a.. Place patient flat on back on a hard surface.
- b. Open airway by lifting up the neck and pushing the forehead down.
c.. Check for breathing by listening and viewing for chest movement (approximately five seconds). 2.4.3 Patient Not Breathinq
;, a. With head positioned for open airway, pinch nostrils
", shut with thumb and finger.
- b. Place mouth over patient and give four quick breaths. If quick breaths are not successful, reopen airway and reattempt four quick breaths. If still unsuccessful, perform procedure for obstructed airway (see Section 2.6).
. c. Stop and check for breathing and heartbeat. Heartbeat
/D is checked by placing two fingers over the carotidartery
' (j ' (carotidartery runs up the neck on either side of the
" Adams Apple") (approximately five seconds).
- d. If patient is not breathing, and has no heartbeat, perform CPR.
- e. If patient is not breathing, but has a heartbeat, continue resuscitation by giving one breath every five seconds; i.e., 1 one thousand, 2 one thousand, 3 one thousand, 4 one thousand, breath.
- f. Continue as long as possible, but always look for indi-cations that the patient is breathing on his/her own.
If this is true, discontinue resuscitation. 2.5 CPR (Cardiopulmonary Resuscitation) 2.5.1 CPR should only be performed by person's certified in the
- CPR pro
- :edure.
2.5.2 If you are not certifi.d in CPR, you should attempt to get help as soon as possible. , 2.5.3 For personnel who are certified in CPR, correct riiythe values are listed below as a reminder. i
- a. Inflate lungs once after every five chest compressions
_ (two rescuers).
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i EPIP 11.2 Page 3
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- b. Inflate lungs twice after every 15 chest compressions (one rescuer).
- c. Remember to find the correct hand-on-chest position before giving chest compressions.
2.6 obstructed Airway (Unconscious Patient) 2.6.1 Ensure two attempts have been made to get air' into the lungs. 2.6.2 Roll patient towards you (front) and give four back blows to the upper back with the heel of the hand. 2.6.3 Position patient onto his/her back and give four abdomical thrusts. This is done by strattling pstient's legs and.with the heel of the hand push forward on the lower abdomen. 2.6.4 Gently probe mouth. , 2.6.5 Reopen airVay and attempt to breath intd lungs.
, 2.6.6 Continue as long as possible or until airway is cleared.
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2.7 If Patient is Breathing But in Need of Oxygen 2.7.1 Open cylinder or resuscitation unit with handwheel. 2.7.2 Set flow to six liters / minute. 2.7.3 Place mask on face. l l [ l l i f .. l 1
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a, l a EPIP 11.3 MINOR [\ Revision 4 09-09-83 l HOSPITS*. ASSISTANCE [ 1.0l IN11tODUCTION i 19 outlined in EPIP 11.1, this procedure specifies plans to be used in the evant 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 treatatut room, the Nuclear First Aid Room (NFAR), has been provided at Two Rivers Community Hospital in Two Rivers, Wisconsin. This roce is equipped with filtered ventilation, sink, decontamination supplies, protective '
. clothing, signs, 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 i 2.1 General Description (Detailed instructions and responsibilities in A, subsequent subsections) (.*f 2.1.1 Injury or Sickness Resulting in Loss of Consciousness or Mobility in the Clean Area control room personnel and the Shift Superintendent 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 l
aid should be administered by trained plant personnel and the injured person should be transported for medical treat-menti as necessary. 2.1.2 Injury or Sickness Resulting in Loss of Consciousness or Mobility in the Controlled Area , Although an injury in a contaminated area is not likely to involve gross radioactive contamination, special procedures are to be used for handling an injured and potentially contaminated person. The Shift Superintendent is to direct first aid 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 e6 (
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EPIP 11.3 Page 2 t 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. g- 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 MAINTENANCE SUPERVISOR SHOULD ASSUME THE DUTY SHIFT SUPERINTENDENT RESPONSI- ~ BILITIES FROM BELOW. f a. The Duty Shift Superintendent is tc assign an individual 1 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 es,ergency entrance will be used. An employee trained in first aid should accompany the injured person in the emergency vehicle.
- b. The health physics professionals are to be notified and
- (# proceed to the Two Rivers Community Hospital to assist in decontactination 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 f COMPLICATED BY CONTAMINATION, 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 Superintendent is to notify the Two Rivers l Community Hospital (see attached form EPIP-37) of the l nature of the emergency, if contaminated or clean, and expected time of arrival at the hospital.
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- d. The Shift Superintendent will notify the Site Manager of i the injury.
- e. The Site Manager or his designated alternate should notify the injured person's family.
- f. PBNP 3.5.2, " Injuries, Accident Reporting & Industrial
- Safety" should be used for documentation and followup of the injury.
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'2.1.4 Responsibility of Hospital Personnel
_Upon being notified that a seriously injured, contaminated 8 person is being transferred, hospital personnel in charge of emnergencies will assure that a physician and sufficient personnel are available, evacuata the NFAR of all persons 4
, and materials not deemed necessary and assist in moving the injured person upon arrival. Any person or. item leaving the treatment room after-the arrival of the contaminated victim will be monitored for radioactive contamination. All items leaving the treatment room will be contained in sealed plastic bags if found to be contaminated.
; 2.1.5 .Following Emergency Treatment After emergency treatment is completed, the patient will be decontaminated with the assistance of Point Beach Health Physics personnel. The NFAR and all supplies and equipment involved will be thoroughly decontaminated by Point Beach
-personnel. In addition, surveys will be made in areas nearby '
to ensure that radioactive contamination has not occurred.
- These areas should include the emergency vehicle, the hallway O and the hospital entrance. All, liquid and solid wastes s-accumulated as a result of treatment and decontamination -
'" ~
will be transferred to the Point Beach Nuclear Plant for disposal in the plant waste disposal facilities. 2.2 Person Discovering the Injured Person 2.2.1 Inmiediately notify the Duty Shift Superintendent of the injury and the location of the patient. l~ 2.2.2 If the patient is in a radiation field greater than 25 Rem / hour, or if serious airborne contamination is present, move the patient to an area with lower radiation dose rates, if possible. NOTE 1: IN ALL CASES ANY ACTIONS TAKEN SHOULD MINIMIZE THE POSSIBILITY OF FURTHER INJURY TO THE , PATIENT. IF MOVING THE, PATIENT WILL CAUSE EVEN MORE SERIOUS INJURY TO THE PATIENT, THE RADIATION EXPOSURE IS OF SECONDARY IMPORTANCE. GET ADDITIONAL HELP BEFORE MOVING THE PATIENT. NOTE 2: IP IHE PATIENT IS IN AN EXTREMELY HIGH RADIATION FIELD (500 REM / HOUR OR GREATER) MOVE THE PATIENT IMMEDIATELY, REGARDLESS OF HIS INJURIES. 2.2.3 Remain with the patient. If first aid qualified, perform emergency first aid and assist in transferring him to the emergency vehicle as directed by the Duty Shift Superintendent. g w= =-g-*-w------* w +w-9-,em.=--ue--.9-emgg-M---+<-m-% win-,--yyqe,-gg e 9- mm-*erw---uwW-yr --
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' EPIP 11.3 Page 4 2.3 Duty Shift Superintendent 2.3.1 - If the injury occurs on day shift, notify the Point Beach Industrial Safety Coordinator or a Chemiutry & Health Physics supervisor of the injury and the patient's location. i l 2.3.2 -Assign an emergency vehicle driver from available Operations personnel or from the chemistry & Health Ihysics Group and - dispatch the driver and vehicle to a suitable exit. NOTE: IF.THE PLANT ENERGENCY VEHICLE IS NOI AVAILABLE, CONTACT THE TWO RIVERS FIRE DEPARTMEhT FOR ASSISTANCE. NOTIFT THE PLANT GUARD AND DIRECT ii 'THE TWO RIVERS VEHICLE TO THE APPROPRIATE BUILDING l EXIT UPON ITS ARRIVAL. SEE ATTACHMENT 11.1-1 FOR
, TELEPHONE NUMBER. VERIFT APPROPRIATE USE OF PERSONNEL MONITORING DEVICES AS SET FORTH IN SECTION 4.2.
2.3.3 Assure that first aid coverage is provided and instruct.the . person administering first aid to accompany the patient to the hospital.
- f. 2.3.4 Notify the Two Rivers Community Hospital and inform them of:
- a. Nature of the injury or illness, if known.
- b. Condition of the patient.
- c. Whether or not patient is radioactively contaminated.
- d. Means of transportation and expected time of arrival.
REFER TO ATTACHED FORH EPIP-37 FOR TELEPN NE NUMBER. 2.3.5 If patient is radioactively contaminated, notify Health 4 Physics personnel. 2.3.6 Assure that radiation monitoring instruments are placed in the emergency vehicle if the patient is radioactively contami- . nated. NOTE: FIRST CHOICE INSTRUMENTS ARE THE EBERLINE PIC-6A AND THE EBERLINE RM-14 WITH HP210 PANCAKE PROBE. 2.3.7. Notify the Duty & Call Superintendent. 4- . e t
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EPIP 11.3 g Page 5 L .', 2.4 Emergency Vehicle Driver 2.4.1 Upon being assigned, obtain the necessary radiation moni-toring instruments from the Health Physics Station, if required. 2.4.2 Ensure that the FM (red) radio is put in the vehicle. 2.4.3 Stand by with the vehicle at the designated building exit and assist persons in handling the patient. 2.4.4 After receiving the patient, proceed directly to the Two _ Rivers Community Hospital.
- a. Noncontaminated patients will be taken to the emergency ambulance entrance.
- b. Contaminated patients will normally be taken to the entrance on the west end of the hospital.
2.4.5 Enroute to the hospital, call the control room via the FM (red) radio to establish contact for relaying information on changes in the patient's condition or other pertinent infor-nation. 2.4.6 Upon arrival, assist in transferring the injured person to l- the treatment room and if the patient is radioactively contaminated, maintain radiation control and monitoring L until relieved by Health Physics personnel. [ 2.5 Health Physics Personnel l l 2.5.1 Upon notification, proceed to the Two Rivers Community l Hospital to assist in patient decontamination procedures. Arrive in advance of the emergency vehicle carrying the victim, if possible. l l 2.5.2 Upon arrival, identify yourselves to hospital personnel and provide assistance as requested.
- 2.5.3 Insure that radioactive contamination is not being spread into hallways of the hospital or outside the entrance door.
Maintain restricted. areas and post as necessary. L 2.5.4 Monitor hospital personnel (refer to Section 4.3) and equipment entering and leaving the restricted area. NOTE: POINT BEACH NUCLEAR PLANT PERSONNEL SHOULD REMEMBER THAT THE ATTENDING PHYSICIAN'S ORDERS MUST BE OBEYED AND.ONLY THE PHYSICIAN IS IN _. DIRECT CHARGE OF THE SITUATION. 2.5.5 Following the emergency treatment, monitor the patient prior to transferring to another area.
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2.5.C Monitor equipment and personnel and decontaminate as required. 2.5.7 Bag all disposable or radioactively contaminated items and place bags in the plant es?.rgency vehicle. Note items of hospital-owned equipment which may require replacement. 2.5.8 Decontaminate the~ treatment room and adjoining areas as necessary. 2.6 Health Physicist As soon as possible following the emergency, the Health Physicist
-will.have the treatment room surveyed and insure that decontamination of any hospital facilities used is complete.
'2.7 Duty & Call Superintendent 2.7.1 Notify the Manager - Point Beach Nuclear Plant of the emergency.
2.7.2 If the Two Rivers Fire Department emergency vehicle was used - to transport a radioactively contaminated patient, notify the Fire Department and request that the vehicle remain at , O the hospital until plant personnel check for radioactive contamination of the vehicle and/or its equipment.
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3.0 PROCEDUkE FOR HOSPITAL PERSONNEL The information obtained from the Point Beach Nuclear Plant Duty Shift Superintendent will determine the actions of hospital personnel. 3.1 Patient Not Contaminated by Radioactive Material These patients will be handled by standard Two= Rivers Consnunity - Hospital emergency procedures. ( ) 3.2 Patient Contaminated by Radioactive Material 3.2.1 The hospital will assure that a qualified physician and - sufficient qualified personnel are available to administer treatment to the injured person. 3.2.2 The NFAR will be evacuated of all personnel not involved in the treatment of the incoming patient. 3.2.3 Those hospital personnel needed for treatment or handling of the injured will don protective clothing. 3.2.4 After the victim is in the NFAR, all persons exiting, and - items being removed from, the NFAR will be monitored for
- contamination.
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- 3. 2.5 ' All contaminated items will be sealed in plastic bags and deposited in the NFAR for further disposition.
3.2.6 After treatment has been completed, the patient will be transferred to another location. Point Beach Health Physics personnel will then decontaminate the NFAR and transfer all contaminated mat.erial' to Point Beach Nuclear Plant for ultimate disposal. NOTE: ALL ITEMS SUCH AS PROTECTIVE CLOTHING, ABSORBENT PAPER, ETC., NECESSARY FOR USE BY HOSPITAL PERSONNEL IN TREATMENT OF CONTAMINATED PATIENTS WILL BE SUPPLIED BY WISCONSIN ELECTRIC POWER COMPANY AND WILL BE KEPT IN THE NFAR. 4.0 MONITORING OF MEDICAL PERSONNEL
- i Assisting personnel will be provided with monitoring devices whenever contamination is involved or whenever such personnel are required on site or within any evacuated area. ;
4.1 Plant Emergency Vehicle s Use of plant emergency vehicle with plant personnel in attendance requires no additional personnel monitoring devices during the transient from the plant to the hospital. 4.2 Two Rivers Fire Department Emergency Vehicle Use of the Two Rivers Fire Department emergency vehicle with Fire Department. personnel in attendance requires personnel monitoring devices for all non-plant personnel. A self-reading pocket dosimeter and a TLD badge will be issued from the unused TLD supply stored at !. the south gatehouse. A Visitor TLD Badge Issue Report will be completed as soon as practicable. Upon releasing these perso'rinel, their pocket dosimeters will be read and recorded on the visitor TLD Badge Issue Report. The TLD badges will be retrieved and processed as soon as possible. 4.3 Hospital Personnel Self-reading pocket dosimetry devices and TLD badges will be issued I to all hospital personnel assisting in the treatment of an injury which has been further complicated with significant radioactive contamination that could pose as a source of exposure to those per-l sonnel. These devices are maintained in the Emergency vehicle and i taken directly to the NFAR at the Two Rivers Community Hospital by-the Health Physics personnel dispatched to the hospital. A Visitor's
~
TLD Badge Issue Report will be completed as soon as practicable. As soon as hospital personnel have completed their treatment of the injured person, the pocket dosimeter will be read and recorded on the Visitor TLD Badge' Issue Report and the TLD will be retrieved and , l processed as soon as possible. l t - - - - -
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4 EPIP 11.3
, Page 8 J
4.4 Additional Facilities If there are requirements to transport an injured employee with significant radioactive contamination to additional hospital facili-ties or to another hospital, all personnel in the proximity of the injured person will be issued self-reading pocket dosimetry dev' es and TLD badges. These devices will be retrieved and processed e.4 soon as practicable. 4.5 High Whole Body Exposure Incidents For those incidents where personnel may be transferred to the hospital due to a high whole body exposure (greater than 25 R), personnel monitoring for non-plant personnel is not necessary unless the high whole body exposure is complicated by radioactive contamination. In this case, personnel monitoring devices would be issued as outlined in preceding sections. 5.0 ARRANGEMENTS FOR OFFSITE MEDICAL ASSISTANCE FOR SERIOUS INJURIES OR ' CONTAMINATED INJURIES . 5.1 Two Rivers Coastunity Hospital Arrangements have been made with the hospital for treatment of Point Beach Nuclear Plant patients. Hospital personnel have been instructed and trained with regard to potentially radioactive patients and contamination. Hospital personnel are periodically retrained by plant personnel and Company medical representatives. Refer to attached form EPIP-37 for. telephone numbers. The following health physics supplies are available in the nuclear first aid room at the Two Rivers Community Hospital. e
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4 EPIP 11.3 Page 9 l NFAR_ Triage Item Quantity Area Absorbent paper ' 50 feet -- Bags, plastic, assorted sizes (need garbage can size) 50 50 Bucket, plastic , 1 1 Decontamination supplies: Cotton applicators, pkg. I 1 Decon soap, 1 qt. bottle 1 1 Hand brush 2 2 Potassium permanganate, 7 cap. pkg. I 1 Sodium bisulfite, 7 cap. pkg. 1 1
. Filter paper for smear surveys, pkg. and envelopes 2 2 Gloves:
Cotton pall bearers, pair 8 8 Rubber, pair . 8 8 Half-face respirators with particulate filters 4 4 Marking pens, pkg. 1 1 Mops, sponge, with spare sponge 2 2 Protective clothing: Lab coats 6 6 Surgeon's cap 6 6 N Plastic shoe covers 25 25 Medical Assistance Plan 1 1 Emergency Call List . . 1 1 Radiation warning signs and tags, assorted 10 10 Radiation warning tape, roll 1 1 Tape, masking: 1" roll 2 2 2" roll 2 2 Victoreen Thyac survey meter with end window, GM probe 1 1 D-cell batteries, box 1 1 Masslinn mop 1 1 Barrier tape 1 1 D'simeters: o 0-500 mrem 10 -- 0-2 Rem . 5 -- Mini-rad survey instrument 1 1 , Scissors 1 1 Tuck tape, rolls - 2 2 i Miscellaneous forms CHP-21, Survey Form (Blank) 1 pad -- CHP-34, Dosimetry Rezero Sheet 5 5 CHP-39, Personnel' Contamination Report 5 5 CHP-82, Quarterly Inventory Hospital 5 5 CHP-83, High-Range Dosimeter Issue Sheet 5 5
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l EPIP 11.3 Page 10 5.2 Area Physicians At least two area physicians have taken radiological health instruc-tion courses under full or partial spcasorship of the company and are on the Two Rivers Community Hospital staff. 5.3 Two Rivers Fire Department Emergency Vehicle Arrangements have been made for the City of Two Rivers emergency vehicle to respond in the event of injury to persons at the Energy Information Center or in the event the plant emergency vehicle is already in use. Refer to attached form EPIP-37 for telephone numbers. 5.4 Backup Hospital - University of Wisconsin Hospital, Madison Arrangements have been made with the University of Wisconsin Hospital in Madison,. Wisconsin, to provide backup services in the event that the services of Two Rivers Community Hospital become temporarily unavailable or that additional services are required. The University - Hospital provides its own training and equipment; Point Beach Nuclear Plant has no maintenance obligations in these areas.
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Revision 2 08-26-83 g REENTRY PROCEDURES FOR EMERGENCY OPERATIONS
- 1.0 GENERAL
- The purpose of this procedure is to detail the method foi monitoring per-sonnel during emergency repair / operation or search and rescue operations and provide instructions for reentering areas that have become radioactively
, contaminated and/or have high or uncertain radiation levels. Monitoring of !
personnel for purposes other than the reentry for emergency repair / operation p or search and-rescue operations will be in accordance with the normal health physics procedures or as delineated in the Point Beach Nuclear Plant Emergency Plan. 2.0 PRECAUTIONS AND LIMITATIO'NS 2.1 Personnel engaged in either emergency repair / operation or search and .' rescue operations should keep in mind the concept of time-distance-shielding to minimize radiation exposure as much as possible.
~) 2.2 The " buddy system" is lin effect and an individual will not be allowed-to trave *1 through potentially high radiation areas alone unless he is within sight of a buddy.
2.3 For purposes of. emergency repair / operation, personnel will not receive , a dose exceeding 25 Rem to the whole body. ' For purposes of search and rescue operations, personnel should not 2.4 receive a dose exceeding 100 Rem to the whole body. 2.5 All personnel who may receive radiation doses greater than 25 Rem will participate on a voluntary basis only.
.2.6 Any exposure to radiation in excess of 10 CFR 20 limits should be l
authorized by the Health Physicist or Superintendent - Chemistry &- ! Health Physics and have the concurrence of a Duty & Call Superin-L tendent or Site Manager. In an emergency, the Shift Superintendent i should try to notify these persons for extended exposure authori-zation in excess of 10 CFR 20 limits, but has the authority to take immediate actions as remiired. 3.0~ INITIAL CONDITIONS 3.1 As a result of previous training all participating personnel will be , aware of the possible hazards associated with radiation doses greater than 25 Rem to the whole body. l l
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* ..t 3.2 Any completed radiation surveys of areas to be entered by emergency repair / operations or search and rescue personnel will be made available to the teams.
4.0 PROCEDURE 4.1 Team Leader' - n-4.1.1 Determine with the Shift Superintendent and Chemistry /HP Supervisor which route'to take to the location of interest.
- l. Review any surveys of areas to be travelled or occupied by the team.
4.1.2 With.the Chemistry /HP Supervisor, determine each team member's allowable dose and calculate the stay time for each member. 4.1.3 Arrange, in advance,'for any anticipated necessary reliefs g for the team members. NOTE: . STEPS 4.1.4 THROUC4 4.1.6 ARE DEPENDENT UPON THE RADIOLOGICAL . . CONDITIONS BOTH EXISTING AND POTENTIAL. .IF,.FOR EXANPLE,
- THE EMERGENCY IS CONFINED TO THE AUXILIARY BUILDING, THE O TEAM M&Y REQUIRE MINIM &L DOSIMETRY TO SEARCH THE TURBINE HALL.
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4.1.4 Determine with the Chemistry /HP Supervisor the protectiv.e' clothing and respiratory equipment necessary. 4.1.5 Equip team members with.the following personnel dosimetry:
- a. Low range self-reading dosimeter (0-200 mR).
- b. Hedium range self-reading dosimeter (0-5R) l i
- c. High range self reading dosimeter (0-200R)
- d. Personnel TLD capable of recording doses in excess of 100 Rem.
- e. Extremity monitoring dosimeter (s) as prescribed by the Chemistry / Health Physics Supervisor.
. 4.1.6 Equip at least one team member with a high range beta-gamma survey instrument, such as Teletector.
4.1.7 Each team will have a portable radio for communications capability with the control room and Health Physics super-vision. 4.1.8 Ensure the team has proper keys. Determine exit point and proper disposal of contaminated
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4.1.9 clothing before returning. __ . _ _ _ _ _ . _ . _ _ . . . _ _ . _ _ . _ . _ _ . _ , _ _ . _ .-_---__ _ ._.-~. _ . _
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4.2 Repair / Operation Team 4.2.1 Determine with the Shift Superintendent exactly what work is . to be performed, how many people will be required, and what tools'and spare parts are needed. 4.2.2 Iquip each team member with protective clothing, respiratory
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protection equipment and personnel monitoring devices. All clothing openings are to be taped.
- 4.3 Chemistry /HP Supervisor or Designee 4.3.1 Determine if potassium iodide a hinistration is necessary c.
and administer it to the search and rescue, repair / operation '
- team members if needed. See EPIP 1.6, "Radioiodine Blocking and Thyroid Exposure Accounting," for guidance.
4.3.2 Brief all repair / operation'and search and rescue members of , the hazards of radiation doses in excess of 25 Rem to the whole body. - 4.3.3 Ensore that the teams have met all the necessary require-
- ments prior to entering a contaminated or radiation area.
A' ' ) 4.3.4 During the team effort monitor the radio and log radiation L levels as reported by the team and compare the readings to those expected.- Keep track of the team's time and estimate the dose they are receiving as appropriate. Note also Bio-Pak depletion time. *
' 4.3.5 10 CFR 20 limits exposure to the whole body, extremities, i skin, and internals. The exposure records of any team -
member who exceeds 10CFR 20 limits should be forwarded to the' Company Medical Director. 4.3.6 If the whole body do'se of a team member exceeds 25 rem or his dose is uncertain or suspected of exceeding 25 rem or his internal dose is estimated to be greater than or equal to 10,000 MPC hours, he should be referred to a physician i for appropriate medical care. 4.4 Maintenance Supervisor i 4.4.1 The Maintenance Supervisor is responsible for accountability and search and rescue. He will work with the Chemistry / Health Physics Supervisor in the selection of the team. 4.'4.2 As soon as. one team is sent out, a second team should be set
- up and dressed.
4.4.3 The Maintenance Supervisor should work with the Plant Oper-1 ations Manager and Chemistry / Health Physics Supervisor. 1 1
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,1 EPIP 12.2 MINOR
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08-26-83 PERSONNEL EXPOSURE & SEARCH AND' RESCUE TEAMS 1.0 GENERAL The purpose of this procedure is to provide the guidance and requirements necessary to conduct efficient search and rescue operations.
.2 . 0 PRECAtrfIONS AND LIMITATIONS 2.1 Proper radiological controls are to be maintained during search and rescue operations. Proper health physics practices must be adhered to in accordance with EPIP 12.1, " Reentry Procedures for Emergency i Operations."
3.0 INITIAL CONDITIONS 3.1 EPIP 8.1, " Personnel Assembly and Accountability," is completed or persons are known to be missing or in need of help. - tu 3.2 Review EPIP 12.1, " Reentry Procedures for Emergency Operations." 4.0 PROCEDURE 4.1 Maintenance Supervisor 4.1.1 Assemble a search and rescue team or teama, each team con' sisting of at least two persons. Of the two personnel, at least one will be trained in first aid. At least one will
- be qualified in health physics and both will be familiar with the plant.
NOTE: FOR THE PURPOSES OF THIS PROCEDURE, THE HEALTH PHYSICS QUALIFIED PERSON WILL BE CALLED THE HEALTH PHYSICS REPRESENTATIVE. 4.1.2 Appoint the most qualified team member as the search and rescue team leader. The search and rescue team leader will be in charge of the team while conducting search and rescue operations. 4.1.3 Coordinate all search and rescue teams so that duplication of effort and unnecessary radiation exposure does not occur. 1 4.1.4 Work with the Plant Operations Manager an'd Chemistry / Health - Physics Supervisor.
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_ _ ._ _ _ _ _ ^ M : _ . _. . .m . .
+
EPIP 12.2 Page 2
'9 .
L/ 4.1.5 Use a map of the plant to mark off areas which have been searched. 4.1.6 Recall the search'and rescue team (s) when search and rescue operations are no longer necessary or when all missing persons are accounted for. , 4.2 Health Physics Representative 4.2.1 Ensure that all team members meet the personnel dosimetry, protective clothing and respiratory requirements of EPIP 12.1,
" Reentry Procedures for Emergency Operations."
4.2.2 Insure that no team member receives a whole body dose greater than 100 Ren while conducting search and rescue operations. 4.2.3 The Health Physics representative will have the authority to secure search and rescue operations of the team and to order
-the team out of contaminated or radiation areas.
4.3 Search and Rescue Team Leader - n 4.3.1 Obtain the following information prior to performing search
- and rescue operations: .
- a. Identification of each missing individual.
- b. Last known location of each individual.
- c. The job each individual was working on.
- d. Any significant plant status known that may affect the search. .
- e. Allowable radiation exposure limits for each team member.
4.3.2 Ensure that the team is equipped with a first aid kit and knows the locations of stretche'rs. 4.3.3 Proceed to the last known location of the missing individual and if necessary expand the search to adjacent areas. 4.3.4 Maintain close communications with the Maintenance Supervisor on all team actions including notification when any personnel are located. NOTE: TEAM MEMBERS SHOULD NOT SEPARATE WITHOUT THE DIRECT - PERMISSION OF THE , MAINTENANCE SUPERVISOR AND TEAM LEADER.
. i
o 9 EPIP 12.2 Page 3
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4.3.5 Provide first aid and medical care as necessary and transport or escN t the located individual (s) to a safe location as soon as possible. 4.3.6 Determine exit point for contassination control purposes. 9 6 1 L 6 e _ . . , , _ ,,_r ,-- - __ ,_ ,, ,. ,..m.,, , ..-. ..m, , ..,,_ , -- --,..
a EPIP 14.2 f - MINOR Revision 0 09-09-83 PAGING SYSTEM OPERATION ( 1.0 GENERAL The purpose of this procedure is to list the steps necessary for proper communication over the paging system. 2.0 PRECAUTIONS & LIMITATIONS . 2.1 This procedure applies to pushbutton telephones only. If you have a rotary dial telephone, have the control room make the page. 2.2 Maxiaum message length is 30 seconds when using the telephone. 3.0 PROCEDURE 3.1 Pagina From the Site (
~
3.1.1 Dial on a PBX telephone. 3.1.2 Listen for a relatively loud beep. - 3.1.3 Dial the desired group or individual number (see Attachment 14.2-1). 3.1.4 Listen for the beeping tone. 3.1.5 Wait approximately 3 seconds after the tone then state your ' message and hang up. 3.1.6 Personnel directed to come to the site should be told to
- place their paging unit in the monitor (thunderbolt) position.
NOTE: THIS WILL ALLOW LONG MESSAGES TO BE TRANSMITTED BY USING CHANNEL 3 ON THE RED FM RADIOS WHICH THE PAGING UNIT SHOULD RECEIVE. 3.2 Paging from Offsite 3.2.1 Call the plant. 3.2.2 Ask for Ext. 3.2.3 Repeat Steps 3.1.2 through 3.1.6.
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w..
ATTACHMENT 14.2-1 PAGER NUMBERS Group No. Duty & Call Superintendents Duty Technical Advisors IGC Maintenance Chemistry & Health Physics Duty & Call Superintendents Name Number .
. J. C. Reisenbuechler
-( ,
G. J. Maxfield R. E. Link J. J. Zach T. J. Koehler Duty Technical Advisors , Name Number T. L. Fredrichs W. B..Froom T. R. Branas J. G. Schweitzer P. N. Kurtz M. J.. Logan T. G. Staskal i G. R. Sherwood N. L. Hoefert G. L. Rau E. H. Wellenstein S. M. Barkhahn R. R. Winget , J. E. Knorr W. A. Hennig - O_ .
Attachment 14.2-2 (Cont'd.) Administration Name Number F. A. Flentje I&C Name Number A. J. Pohl ,
- Duty Maintenance Name Number '
(
~
N. W. J. Herrman Duty Chemistry & Health Physics ' Name Number P. J. Skramstad R. S. Bredvad ' L. D. Epstein ' E. J. Manos M. L. Braun D. P. LeQuia I E. J. Lange R. A. Neustadter T. L. Slack K. R. Rathgaber C. L. Nash i H. J. Gleason i P. J. Matson J. V. Moniot M. D. Moseman O
- 1__. , . . $._ . _. .. . [ _ _ - _2_ _ ._ ~ .h i 2 a-POINT BEACH NUCLEAR PLANT
/
FOR X/Q DETERMINATION n To be filled out by Chemistry & Health Physics Supervisor or RadCon/ Waste
-ci Manager or designate. During a release, complete every 2 hours or as required
./ by changing radiological or meteorological conditions.
(a) Wind speed sph l (b) Wind direction 4 (c) Time of reactor shutdown ,, (d) Time of release to containment (e) Time of release from the plant
'(f) Estimated release duration hours * .
.(g) Xe-133 equivalent source term Ci/sec (h) Stability class l
~
' Distance to dose projection location if different from standard preset (i) I centerline locations below miles Location Description & Sector -
(j) (X p)/Q from overlay: N., Centerline (Isodose Line) Site Boundary Two Mile Five Mile
- Ten Mile other (k) X/Q Site Boundary Two Mile Five Mile Ten Mile --
Other i 2.24 (
*) Xu/Q (m-a)
X/Q =- wind Speed (mph)
= 2.24 = 2.24 ( )
*If unknown, assume 8 hours in order to obtain an initial dose estimate. ..
TIME /DATE COMPLETED' COMPLETED BY Route to RadCon/ Waste-Manager upon completion. EPIP-07 (09-83)
- - - - . . . .. .. - . 1 2 . . - . . - - . . - . - ~. - ~.=.. . --
POINT BEACH NUCLEAR PLANT
. 1 ESTIMATED WHOLE BODY & THYROID PROJECTED DOSES *
'f; To be completed by Chemistry & Health Physics Supervisor, RadCon/ Waste Manager
, or designate. During a release, complete every 2 hours as required by changing radiological or meteorological conditions. l 1
- 1. Calculate the projected whole body dose due to noble gases (using values from EPIP-07).
3 Dose (Rem) = X/Q(Sec./m ) X Q(Ci/Sec.) x Kr C - s x ERD (hrs) Dose (Rem) = (k) (g) Kr from (f) attach. 1.4-2 Dose (Rem)*: Isopleth Centerline (Isodose) Line Site Boundary (a) Two Mile Five Mile Ten Mile Other ,
. *Dooes at various distances can be obtained by X/Q ratios and dose calcu- ._ . lation from (a) above.
J
- 2. Calculate the projected thyroid dose.
Dose (Rem) = Whole Body Dose (Rem) X Ratio Factor (From No. I above) ' (Figures 1.4-1, 4 & 5) Dose (Rem): Isopleth Centerline (Isodose) Line Site Boundary Two Mile Five Mile Ten Mile Other l
- 3. Sector (s) Effected NOTE: CONSIDER SECTORS OVER A 90' ANGLE CENTERED ON THE AVERAGE WIND DIRECTION AND A FULL 360' AREA WITHIN 2 MILES OF THE PLANT.
TIME /DATE COMPLETED COMPLETED BY
~
Route to Radcon/ Waste Manager when completed. EPIP 08 (09-83)
r k ~
/.
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) *' POINT BEACH NUCLEAR PLANT ESTIMATED WHOLE BODY DOSE CALCULATION WORKSHEET FOR SPECIFIC NOBLE GAS RELEASES To be completed by Chemistry & Health Physics Supervisor or RadCon/ Waste Manager or designate. During a ! release, complete every 2 hours or as required by changing radiological or meteorological conditions. ! i
- 1. Enter data as required below
- a. Specific Noble Gas release rates (Ci/sec) (record in column 1 of section II below)
- b. X/Q as determined in step 5.1.5 (sec/m3 ) = (k) from EPIP-07* .
<. .c . Estimated Release Duration (hrs) = (f) from EPIP-07* {,
- 2. Calculate dose for each nuclide and' sum all doses to get total dose using the formula l'
- i-3
- Isotope Release Rate (Ci/sec) x X/Q (sec/m ) x Release Duration hrs) x Dose Rate Conversion = Dose (Rem) i (k) (f) fRem m3 1
, #hCihrs
'.j Kr-85 x x x L84 =
,'i Kr-85m x x x 1.34 x 102 =
Kr-87 x_ x x 6.77 x 19 2 = Kr-88 x x x 1.68 x 108 = 1 Xe-133 x x x 3.36 x 101 = ' Xe-133m x x x . 2.87 x 103 = Xe-135 y x x 2.06 x 102 = , Xe-135m x x x 3.56 x 108 = !. j Xe-138 x x x 1.01 x 103 = i
- Ar-41 x x x 1.01 x 108 - !
Total Whole Body Dose = Rem i E f
- s !
I [ i' l TIME /DATE COMPLETED COMPLETED BY i
' i Route to RadCon/ Waste Manager when completed. t t_
I l EPIP il (09-83) I t } f - - - - - - - - _ _ - _ _ - _ _ _ _ _ _ _ _ _ . - _ _ _
p POINT BEACHI EAR PLANT ! V u. ESTIMATED GROUND DEPOSITION CALCULATION WORKSHEET FOR PARTICULATE RADIONUCLIDE RELEASES
^
To be completed by Chemistry & Health Physics Supervisor or RadCon/ Waste Manager or designate. 'During a release, complete every 6 hours or as required by changing radiological or meteorological. conditions. ,
'I
- 1. Enter data as required below j
- a. ' Specific Particulate Release rates or Xe-133 equivalent. release-rate (Ci/sec) record in column 2 of section II below). !~
a- . I 3
- b. X/Q (sec/m ) = (k) from EPIP-07*
- c. Duration of release ERD (hrs.) = (f) from EPIP-07* ['
p i 2. Calculate deposition for each nuclide and sua all depositions to get total deposition using the l . formula: p l Dep (pCi/m2 ) = **g (myC )x (sec/m ) x Q (Ci/sec) x ERD (hrs) ff l m p Ci X f-Isotope x sec/mD x Q M /sec) x M Ws) E WsMe W/N f' (k) (g) (f)s ~ I I-131 er equiv* 9 x 10 8 x .x x - = ~l' Cs-137 1.8 x lo s x x x =
~
1.8 x 10s x x
, Sr-89 x -
=. s -
Sr-90 1.8 x lo s x x x I,, 4
=x',' -
i Total Deposition = pCi/m 2 {, s i; f .
- If only total Iodine is available, use of this value will. result in an overly conservative estimate ~ }.
i of Deposition of I-131. i I
** The product- of F, 0.05, 3600 and 108is evaluated and set equal to A. .y
. TIME /DATE COMPLETED COMPLETED BY _' \w , Route to RadCon/ Waste Manager when completed. ._ t EPIP-10 ' (09-83) i
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.-- ~. . .
- - .. =. . n - .- A-POINT BEACH NUCLEAR PLANT
SUMMARY
OF RADIOLOGICAL DOSE EVALUATION CALCULATIONS m,
- To be completed by the Chemistry & Health Physics Supervisor, RadCon/ Waste Manager
, '. or designate. .During a release,-complete as often as new information is available from EPIP-08 through EPIP-10.
' Complete using calculations from EPIP-08 through EFIP-10:
Dose estimation location (if differont from below): <
- Estimated Thyroid Dose (Specific Nuclide Determination, Yes , No )
Isopleth Centerline (Isodose Line) Site Boundary
. Two Mile
-Five Mile Ten Mile Other
- Estimated Whole Body Dose Due to Noble Gases (Specific Nuclide Determination, Yes , No ) ,
Isopleth
- renterline (Isodose Line) j Site Bounda'ry Two Mile Five Mile Ten Mile ,
Other
- Estimated Deposition Isopleth Centerline (Isodose Line)
Site Boundary Two Mile Five Mile . Ten Mile Other
- Source Terms based on: .
RMS Sample analysis results Calculations performed by: Signature Date Time Reviewed by- Date Route to'Radcon/ Waste Manager when completed. RadCon/ Waste Manager will review
~
and forward information to the Site Manager and/or Emergency Support Manager. j EPIP-11 (09-83)
j' ^
- PLANT & COMPANY EMERGENCY CALL LIST
-t
.PBNP PLANT PERSONNEL
-1. Duty & Call-Superintendents (Group No. S501)
-Name ' f Pager No.
~
Plant' Ext. Home Phone Time Notified
~ ~ ~ .. a _ _ . _ _ ._ _
T.~J. Koehler. R. E. Link '
- J. C. Reisenbuechler' /
G. J. Maxfield I l . i 2.. Shift Superintendents
-Nrme
\
L. J. Kamyszek i Plant Ext. Home Phone Time Notified
-i I ,
x,_ R. D. Mitchell . I l
'I.
L.!Bleeker 1 { C.-M. Gray E. Ziller R.'J. Mulheron ~ c T. W. Carot K. J. Draska a ,
-3.
Chemistry (Group Nos. S540 & S530)
.Nrme Pager No.
Plant Ext Home Phone Time Notified
.P. J. Skramstad f T. L.' Slack'
'R.A. Neustadter T.~L. Fredrichs 1' . . -
i s :i EPIP-22 (09-83)- i
; 8' i'
l' m
,' ~ 4. LHealth Physics (Group Nos. S540 & S530)
[
'Name Pager No. Plant Ext. Home enone. Time Notified
.P. J. Skramstad R..S. Bredvad L. D. Epstein- 3 i
- M. D. Moseman -!
E. J. Manos- * ( D. P. LeQuia l E. J. Lange j.
- 5. -Instrumentation & Control (Group No. S520)
Name Pager No. Plant Ext. Home Phone Time Notified . A. J. Pohl ,/ I G. L. Rau f. E. A. LeClair Duty'& Call _ _ . _ . -
'6. . Maintenance (Group No. S530) ,
I Name' Pager No. . Plant Ext. Home Phone fTimeNotified W. J. Herrman I i IM. E. Crouch R.~0. Gerroll j l
-J. O. Schoenberger T..R. Branam E. H. Wellenstein i
~
R. D.~Niemisto ~ i D. E. Duenkel .
-Duty & Call .
i
.EPIP-22 Page 2 of 5
-(09-83) 1
1
* - Reactor Engineering
- 7. -
Name P_lant Ext.- Home_ Phone' Time Notified R. L. Harris N.-L. Pitterle '
~
'8. Plant Administration & Security 1Name Pager No. ' Plant Ext. Home Phone i Time Notified
'J. J. Zach- .
T. J. Koehler-- - R. Krukowski- [ ~ J. D. Mielke -
~
- -~ -
. F. ~A. Flentje g l .
i
'J.:E. Knorr j "()
- 9. Fire Brigade-Menbers NOTE: REFER TO PBNP FIRE PROTECTION MANUAL CALL LIST, SECTION FEP 2.0
- 10. Duty Technical Advisors (Group - Nos'.
i Name Pager No. Plant Ext. Home Phonei Time Notified
, E. H. We'1enstein W. B. Fromm W.-A.'Hennig f J. E. Knorr J. - G. - Schweitzer j P. N. Kurtz. ,.
N. L. Hoefert i I R. R. Winget. t G. R. Sherwood
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EPIP Page 3 of 5
-(09-83)
- : .. .. / .-. . i Duty Technical Advisors (Cont'd)- Name- Pager No. _ -Plant Tvt: Home Phone _ Time Notified
-T. R. Branas f .
-S. M. Barkhahn ,
G. L. Rau M.-J. Logan
.T. G. Staskal !
T. L.~ Fredrichs . WEPC0 PERSONNEL'
- 1. Company Administration & Departments Name Company Ext. Home Phone Time Notified -
C. W.-Fay,
'( ~, Duty Emergency Support Manager Beeper No .
L' e _ ands -
' Wisconsin Electric Power Company Medical Department
' Nuclear Engineering Section Communications Department _
)
(24-hour media line) Answer Service WE Accident Prevention ,
- 2. Nuclear Engineering Section Personnel Name- Company Ext. Home Phone Time Notified D. K. Porter, Duty Emergency Support Manager
-R. A.' Newton, Duty Emergency Support Manager G. D. Frieling, Duty Emergency Support Manager - -.
EPIP Page 4 of 5 f(09-83) C
m-_ , , . . _ _ _ . , _ ..- _ _ _ _ _ _ - , _ _
- -. . .e -
V 4-j' -Nuclear Engineering Section Personnel (Cont'd) E. J. Lipke, Duty Emergency Support Manager-
;C.1W.'Krause, Duty Emergency Support. Manager S..A. Schellin.
J. E. Knorr . - .
- 3. Insurance Personnel' l Name Company Ext. Home Phone ,
Time Notified W. J. Dundas, - Supt. Insurance & Claims f 7
-Division j W. E. Staum, Alternate f l
i
'"" J..G.'Remmel i
b .. s
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EPIP-22 Page 5 of 5 (09-83)- c
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4 A i e- [, OFFSITE AGENCY EMERGENCY CALL LIST FEDERAL AGENCIES:
- 1. United States Nuclear Regulatory' Commission Telephone Person Time
' Frequency . Number Notified Notified Initials Name NRC Operations All hours );
Center- or
~~
NRC Office of All hours \ In<pection and- (Ask for Enforcement, Duty Officer) .
~~~
Region III , NRC Resident Inspectors: Plant Ext. ,__ Home
',/ '
- a. . R. L. Hague
- b. B. E. Fitzpatrick .
2.' - United States Department of Energy 4 Telephone Person- Time
..,'Name Frequency Number Notified Notified Initials Chicago Operations Weekdays -
Center, Region V. (8AM-5PM) (Radiological
- Assistance Team) All other hours
- 3. United States Coast Guard Telephone Person Time Name Frequency Number INotified Notified Initials
.MSO, Milwaukee USCG, Sturgeon All hours Bay USCG, Two All hours Rivers '
9 Page 1 EPIP-23 ..g 4 (09-83) <
, , . - ~
- 1. ' United States' National' Weather Service Telephone . Person .
Time
' Frequency Number Notified -Notified Initials Name.
EAll hours
.NWS, Green Bay NAWA5 STATE AGENCIES:
-1. State of Wisconsin Telephone- Person' Time Name Frequency Number- Notified Notified. Initials Wisconsin' Dept. of Weekdays
. Health and Social -(9AM-5PM)
. Services, Section cf Radiation Pro-tection.
Lawrence J. McDonnell,- Home phone . Chief Section of Radiation
. , Protection
\;,*/ Wisconsin Division All hours /'
cf Emergency- - or NAWAS' Government
- Wisconsin State All hours __
Patrol or NARAS 1
.- COUNTY AGENCIES: .
- 1. Manitowoc County Telephone Person Time Name Frequency Number . Notified Notified Initials Manitowoc County All hours Sheriff, County or NAWAS Traffic _ or radio
- 2. Kewaunee County Telephone Person Time Frequency Number Notified Notified Initials Name
.Kewaunee County All~ Hours , ,___._" .
Dispatcher or NAWAS
'EPIP-23 Page 2 of 4 (09-83) <
PRIVATE AGENCIES: Telephone Person Time' Name Frequency Number Notified Notified Initials Kewaunee Nuclear All hours Power Plant Institute of All hours-Nuclear Power operations . I American Nuclear Insurers All hours Westinghouse Electric Corp. Operating Plant Regional Mgr. Office (B. Johnson) Home l lst Alternate Home }
.(C. Spurmont)
,0ffice
-} -
2nd Alternate Home ! (C. Rowland) Office ;
, Stone & Webster All hours
{
' Engineering Corp.
Bechtel Power All hours I Corporation
-University of Office-Wisconsin - or
)
Milwaukee Seismic Center _ _ , _ _ . l (D. Willis) l FIRE AND MEDICAL AGENCIES
- 1. Fire Emergency-Telephone Person Time
.Name Frequency Number Notified Notified Initials Two Creeks Fire All hours Department
! k
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- EPIP-23 Page 3 of 4 (09-83) e m
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_ , ; : :, ..: -.-.; .. u - ~ . - - . e
. "As
'2 . ' Medical Assistance Telephone ' Person Time Frequency' Number Notified Notified Initials Name-Doctors Clinic, Ltd.
( S. Lawrence Kaner, M.D. Stephen L. Weld, M.D. University Hos- / pital, Madison / I Em'ergency Room All hours I-Frank C. Larson, M.D. . Robert F. Schilling, M.D. . Robert.R. Radtke, Ph.D. __ (Health Physicist) Two Rivers All hours
. Emergency i Vehicle !
i -
. Community Hos- All hours ~\
pital, "Two Rivers
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-t EPIP-23 Page 4 of 4 (09-83) C
2- .
. . = -.. . . . . -x --
POINT BEACH NUCLEAR PLANT SITE BOUNDARY CONTROL CENTER
) EMERGENCY PLAN INVENTORY CHECKLIST Item No. Item Required on Hand Sampling Equipment and Supplies ,
- 1. AC generator (5,000 watt)' 1
- 3. Electric high volume air sampler 1
- 4. Poly gas sample bottles 12
- 5. Charcoal cartridges for air sampler, high volume 48 __
- 6. Charcoal cartridges for air sampler, low volume 50
- 7. Silver zeolite cartridges for air sampler, low volume 5
- 8. Filters for air samplers (pkg. of 100) 2
- 9. Gasoline for AC generator (gallons) 2
- 10. Sample tags 50
. 11. Plastic bags 50
- 12. 100' extension cord 2
- 13. Planchets 20 13a. _High volume air sample filter 1 .
.13b. 1 qt. oil 1 -
13c. 1 pt. OB oil 1 13d. Flask 1 m.
')/
. 13e. Dyz-lene ,
1 Respiratory Protection Equipment .
- 14. Full-face respirators 4
- 16. Full-face filter cartridge 12 Fire Protection Equipment
- 18. Fire *vtinguisher, dry chemical 1 Radiation Survey and Monitoring Instrument
- 19. HPI-1010 1
- 20. Radector III (.1 mR/hr - 1,000 R/hr) 1
- 21. Victoreen Model 490 Thyac III 1
- 22. PIC-6A survey instrument (1 mR/hr - 1,000 R/hr) 2
- 23. RM3C personnel survey frisker 1
- 24. Johnson Associates, GSM-5, 0-50k cpm, 0-200 mR/hr 1
- 25. MSC-1 sampler holder for GSM-5 1
- 26. Check sources; 2 - Cs-137 and 1 - Sr-90 3
- 27. Filters for smears (pkg. of 100) 2
- 28. Nuclear Chicago counter scaler 1
- 29. Coin envelopes (box) 1/2
- 30. HP-210 probe 2
- 31. SH4 probe holder 1 -
- 32. Earphones for Thyac III survey instrument 3
- 33. Side window probe 2 EPIP-24a (08-83)
_ . . . - .- . - . w:ar_ :-.. . . . - n-
.....--...ua.-. -. -., w . x.u .
. Page 2 of 6 Required On Hand
- 34. Cord, BNC-BNC connector 2
- 35. Cord, amphenol - BNC connector 2 Personnel Monitoring Equipment
- 36. Personnel Thermoluminescent Dosimeters (TLD) 100
- 37. Self-reading dosimeters, 0-5 R 12
- 38. Self-reading dosimeter charger
- 2 38a. "AA" batteries, boxes 3 First Aid and Decontamination Supplies
- 39. First aid kit 1
~
- 40. Burn kit 1
- 41. Emergency drinking water tablets (bottles; -
50 tables per bottle) 5
- 42. Water (gallons) 20
- 43. Decon soap, powder (5 lb.) 1
- 44. Decon soap, liquid (qt.) 1
- 45. Hand brush 4 .
- 46. Cotton applicators (box) 1 -
- 47. Potassium permanganate (4 oz.) 1
- 48. Sodium bisulfate (1 lb.) i f)
- 49. Kim towels (box) 1
- d 50. Massilinn (pkg.) 1 "409" cleaner (btl.)
- 51. 2
- 52. " Spic'n Span" (box) 2
- 53. Massilinn mop 1
- 54. Regular sponge map 2
- 55. Rag mop 1
- 56. Wringer 1
- 57. Large mop bucket 1
- 58. Kimwipes (box) 1
[
- 59. Bucket, plastic. 2
! 60. Cotton swabs (packets) 5
- 61. Gauze sponges, 2" x 2" (100 per pkg.) 1
- 62. Nail brushes 4 I 62a. Potassium Iodide tablets, bottles 4 Radiation Hazard Signs and Supplies
- 63. Radiation warning tape (roll) 1
- 64. Radiation placards 10
- 65. Radioactive material and radiation hazard tags 10
- 66. Radiation contamination hazard tags 10
- 67. Contamination, high radiation, radioactive l' material, and radiation area inserts (ea.) 10 l 68. Yellow / magenta ribbon (rolls) 8
- 69. Yellow / magenta rope (roll) 1 .
l l l EPIP-24a (08-83)
_ .-.4 s - a ~. w .m: +..a w ~ .w;
~
GA -n. e a Page 3 of 6 j Required On Hand ( Communication Equipment and Supplies
~
- 70. . Portable 2-way radio KRQ-717 1
- 71. Telephone, plan FBK-extension with outside line capability 1
- 72. .WE telephone book _
1
- 73. Two Rivers /Manitovoc telephone book 1 Traffic Signs and Equipment
- 74. Traffic cones for barricades 20
- 75. Traffic lights for barricades e
- 76. - Chains and padlocks for barricades 4
- 77. Traffic flashlight 4 -~
- 78. " Closed Area" placards 6
- 79. Traffic warning light batteries (spare) clothing and Toiletry Supplies 79a. Cloth hoods 25 '
- 80. Coveralls 25 .
.81. Rainwear 6
- 82. Rubber boots 10
[1 83. Shoe covers, plastic 25 [/ y; 84. 85. Overshoes, winter Gloves, rubber disp ~o sable 6 6-
- 86. Gloves, cotton disposable 6
- 87. Mittens, winter 6
- 88. Towels 12
- 89. Washcloths 12 89a. Lineman's gloves 6 89b. Rubber gloves, boxes 1 l
l Stationery and Miscellaneous Supplies
- 90. Desk table and chair 1
- 91. Writing paper (pad) 1
- 92. Pens and pencils Assortment
- 93. Tape, masking (rolls) 2
- 94. Tuck tape (rolls) 10
- 95. Logbook 1
- 96. Absorbent paper (roll) 1 i 97. Paper cups (box) 1 l 98. -Plastic bags 50
! 99. Scissors 1 100. Pocketknife 1 101. Screwdrivers (set) 1 102. ' Plastic funnel 4 103. Flashlight- 1 , 104. Batteries (for flashlight and survey instruments) 50 105. Flashlight ~ bulbs 6 EPIP-24a (08-83) l-
- u. ~=-.~z. u ~ .- - w ... - -., - . - .. - . ..~ - ~r.-,. . , - - - .
.~. _ - - . .
Page 4 of 6
. m. >)
Required On Hand Stationery and Miscellaneous Supplies, continued ... 106. Bulbs, incandescent 8 107. Electric clock 1
- 108.. Electric heater 'S 109. Wet / dry vacuum cleaner '.
1 110. .Netal drum (55-gallon) 1 111. Dal-lene (quart), gasonline stWbilizer. 1 112. Lead bricks 12 113. Safety solvent (low) 1 114. Metal funnels 2 115. Pencil sharpener 1
; 116. Chalk .
1 117. Bulletin Board 1 118. Chalkboard 1 119. Table (reg.) 1 120. Picnic tables 2 i 121.- Calculator 1
. Emergency Plan Documents ,
122. PBNP Emergency Plan 1 122a. Emergency Plan Implementing Procedures 2 g% 123. Health Physics Manual' 1 , {( .' / 123a. Health Physics Calibration Manual . 1 123b. Radioactive Materials Handling Manual 1. . s124. Dose Isopleth/ Map Package 1 125. Personnel Roster- 10 126. Potassium Iodide Approval, Use List 1 127. DOE, Region V, Radiological Assistance Handbook 1 128. State'of Wis. Peacetime Radiological Response Plan 1 EPIP Forms 129. EPIP-01, Emergency Plan Airborne. Radiation Survey 5 130. EPIP-02, Emergency Plan Survey Record 5 131. EPIP-03, Dose Factor Calculation Sheet 5 132. EPIP-04, Status Report on Plant Systems and Controls 5 133. EPIP-05, Worksheet for Status Report on RMS for Unit 5 l 134. EPIP-06, Worksheet for Status Report on RMS for Plant 5 135. EPIP-07, X/Q Determination 5 ! 136. .EPIP-08, Estimated Whole Body and Thyroid Projected 5 137. EPIP-09, Estimated Whole Body Calculation Worksheet 5 138. EPIP-10, Estimated Ground Deposition Calculation 5 139. EPIP-17, Accounting Short Form, 5
- , 140. EPIP-18, Assembly Area Roster 5 r 141. Xe-133 Equivalent Release Rate, Worksheet No.1 5 141a. EPIP-36, Master. Dose Logsheet 5
- EPIP-24a l .(08-83) l
_ _ . . . _ _ _ _ . _ - _ - _ _ . . - . . _ . . _ _ . _ . . , _ . . _ . ~ . . . _ . _ . _ . . _ . . _ .
^ .g_ _,.J _ - QJ_1C_Z _m _a -- - - . - - - _ - s .- -
A Page 5 of 6
~fD Required on Hand EPIP Procedures ,
142. EPIP 1.4, Radiological Dose Evaluation 5 143. EPIP 1.5, Protective Action Evaluation 5 144. .EPIP 7.1.1, Chemistry & Health Physics Personnel 3 Notification and Initial Response when Chemistry & Health Physics Personnel are On-Site 5 . 145. EPIP 7.'2.1, Activation of Health Physics- Facilities at Site Boundary control Center 5 - 146. EPIP 7.2.2, Activation of Health Physics Facilities at Operations Support Center 5 CHP Forms 148. CHP-02, Iodine Airborne Survey (pad of 50) 1 149. CHP-21, Hiscellaneous Survey (pad of 50) 1 150. CHP-31, Radiation Work Permit (pad of' 50) 1 151. CHP-34, Dosimeter Rezero (pad of 50) 1 152. CHP-37, Irregular or Offscale Dosimeter Report (pad of 50) . . 1 , j- 153. CHP-22,~ Air Particulate Sample (pad of 50) 1 - , l 154. CHP-25, Counting Log Sheet (pad of 50) 1 l 155. CHP-33b, Visitors Honitored per 10 CFR 20 i (pad of 50) 1 J /" 156. CHP-33c, Visitor Personnel Honitoring Record (pad of 50) 1 157. CHP-35, Dosimeter Summary Sheet (pad of 50) 1 158. CHP-38, Lost or Damaged TLD Report (pad of 50) 1 159. CHP-39, Personnel Contamination Report (pad of 50) 1 160. CHP-40, Individual Radiation Exposure Report (pad of 50) 1 160a. CHP-41, Personnel Occupational Radiation Exposure Summary 1 160b. CHP-41a, Radiation Workers Checklist 1 161. CHP-44,' Timekeeping Log - High Radiation Work
- Location (pad of 50) 1 162. CHP-56, Personal Bioassay Evaluation (pad of 50) 1 163. CHP-106, Occupational External Radiation Exposure History (pad of 50) 1 Emergency Plan Sampling Kits #1 #2 164. Emergency Plan Sampling Kits - Each kit contains the following
- 2 /
- 1. Battery powered air sampler 1 /
- 2. Scott cartridge holder 1 /
l' 3. Silver Zeolite cartridge hold-- 1 / l 4. Stop watch with batteries 1 /
- 5. Air Particulate filters (env.) 1 /
- 6. Silver Zeolite cartridge 5 / .
- 7. Scott charcoal cartridge 5 /
- 8. PIC-6A survey meter 1 /
- 9. Water filled gas sample bottle (1 liter) 2 /
f EPIP-24a (08-83)
.,- _ - _ =- "_:.-.- a ... -,--.: ' . -.- - : L .- Ji_
Page 6 of 6 Required On Hand
#1 #2 .
- 10. Liquid sample cubitainers (1 liter) 2 /
- 11. Scissors ( 1 pair /
- 12. Plastic suit. 2 sets- /
- 13. Gloves (surgeons) .
6 pair /-
- 14. Self-reading dosimeters (0 - 5,000 mR) 2 /
- 15. Self-reading dosimeter charger 1 /
- 16. Plastic Bags 12 x 18 inch size 6 /
5x8 inch size 6 /
- i. . 3x5 inch size 12 /
- 17. . Flashlight with spare bulb and batteries 1 /
- 18. Smears-(100 each/ box) 2 /
- 19. Tuck Tape (roll) 1 /
20 .' Sharpie,-Flair pen, grease pencil and pencil 4 /
- 21. Sample ID tags (pad) 1 /
- 22. Sampling Procedures EPIP 7.3.1 Airborne Sampling and Direct Dose Rate 5 ea /
Survey Guidelines , EPIP 7.3.1 Atmospheric Radioactive Iodine Sample 5 ea / . Attachment Collection and Counting
- 23. Sampling Forms
./
EPIP-01 Airborne Radiation Survey Record-
- 5 ea /
EPIP-02 Emergency Plan Survey Record 5 ea / Sample Identification Survey Map 5 ea / 2 and 5 Mile Sample Identification Survey Map 5 ea / l 24. CHP-34 Rezero Sheet 5 ea / [. 25. 9 V batteries 2 ea / ! 26. Cs-137 source 1 ea /
- 27. Clipbnard 1 ea /
- 28. Fuses 5 ea ~
/
- 29. Coin envelopes . 1 pkg /
1 Completed By Date l Reviewed By ' Date (Health Physics Supervisor) EPIP-24a-(08-83) i
. . ~ _ . _ . . . . . . . . _ . _ , . . . , _ . , . _ . . _ _ _ . _ . . , _ _ . . - _ . . _ . . _ . . . . . . . . ,_ _,. ... _ _,.._...__. . ...,,, . . _ _ _ . _ _
~
~..a-.~...a-~:~~...- - - - ~ - - - ~ - - ~ "
POINT BEACH NUCLEAR PLANT
- c. TSC (OSC), ESC & SOUTH GATE
- EMERGENCY PLAN INVENTORY CHECKLIST TECHNICAL SUPPORT CENTER & OPERATIONS SUPPORT CENTER Item Suggested Inv.
No. Item Inventory Check i Air Sampling Equipment
- 1. Low volume air sampler 1
- 2. High volume air sampler 2
- 3. AMS-2 cart mounted air sampler 1
- 4. Particulate filters, low volume, box 1
- 5. Charcoal filters, low volume, box 1
- 6. Particulate filters, high volume,-box 1
- 7. Charcoal filters, high volume, box 1
- 8. Silver zeolite filters 15
- 9. Plastic bottles,1 liter 12
- 10. 50'. extension cord 2 Dosimetry Equipment .
- 11. Self-reading dosimeters (0-5,000 mR) 40
- 12. Self-reading dosimeters (0-200 R) 6
- 13. Self-reading dosimeter charger 2
.( , s
.)
- 14. Bat.teries, Size AA, pkg. 1 Survey & Monitoring Equipment .-
- 15. Victoreen vamp 1
- 16. Rad Owl II 1
- 17. Thyac III - side window probe 1
- 18. Batteries, Size D 24
- 19. Batteries, Size 9 volt 6
- 20. Smear filters, box 20
- 21. Smear envelopes, box 2 21a. \" lead detector shield (teletector) 1 Signs
- 22. Three-pocket placards 24
- 23. " Radiation Area" inserts 24
- 24. "High Radiation Area" inserts 24
- 25. "RWP Required" inserts 24
- 26. " Airborne Area" inserts 24
- 27. " Contaminated Area" inserts 24
- 28. " Radioactive Materials" inserts 24 EPIP-24b -
(08-83)
..c, _
Ti Ll :, - - .- -
.. - - . . . . . ~ _ . ~ . .
< Page 2 of 4 S ' Item ' Suggested Inv.
(. .c ) No. Item -Inventory Check Respiratory Protection Equipment
- 29. Clear-Vue respirator 6'
.30. Ultra-Vue respirator 6
- 31. Filter cartridges, box 1
- 32. Smoke test kit 1
- 33. Bio-Pak 60 7 CHP Forms
- 34. CHP-02, Icdine Airborne Survey, pad 1
- 35. CHP-21, Miscellaneous Surveys, pad 1
- 36. CHP-31, Radiation Work Permit, pad 1
- 37. CHP-34, Dosimeter Resero Sheet by Work Activity, pad 1
- 38. CHP-37, Irregular or offscale Dosimeter Report, pad 1
- 39. CHP-22, Air Particulate Sample,. pad 1 EPIP Forms ,
- 40. EPIP-01, Emergency Plan Airborne Radiation
,, survey 10
[T 41. EPIP-02, Emergency Plan Survey Record 10 (#'7 42. EPIP-03, Dose Factor Calculation Sheet 10
- 43. EPIP-04, Status Report on Plant Systems &
Controls 5
- 44. EPIP-05, Work Sheet for Status Report on RHS for Unit 5
- 45. EPIP-06, Work Sheet for Status Report on RHS for Plant 5
- 46. EPIP-07, X/Q Determination 5
- 47. EPIP-08, Estimated Whole Body & Thyroid Projected ,
5
- 48. EPIP-09, Estimated Whole Body Calculation Work Sheet 5
- 49. EPIP-10, Estimated Ground Deposition Calculation 5
- 50. EPIP-17, List of Hissing Personnel. 5
- 51. EPIP-18, Assembly Area Roster 5
.52. Xe-133 Equivalent Release Rate, Worksheet No.1 5 EPIP Procedures
- 53. EPIP 1.4, Radiological Dose Evaluation 5
- 54. EPIP 1.5, Protective Action Evaluation 5
- 55. EPIP 7.1.1, Chemistry & Health Physics Personnel Notification & Initial Response ~
When Chemistry & Health Physics Personnel are On-Site 5 EPIP-24b (08-83) -
~
L_ - ~T~~
~ . _. l . .a :- J ' - - -- - ---
Page 3 of 4
, ' Item Suggested Inv.
.y No. Item Inventory Check EPIP Procedures, continued ...
- 56. :EPIP 7.2.1, Activation of Health Physics (
Facilities at Site Boundary Control
. center 5 4 57. EPIP 7.2.2, Activation of Health Physics Facilities at Technical Support Center /
Operations Support Center 5 Miscellaneous
- 59. Barricade tape, yellow / magenta, rolls 5
- 60. -Tuck tape, rolls 2
- 61. Not spot tags 50
- 62. Radiation material hazard tags 50
- 63. Radioactive material contamination tags 50
- 64. Yellow / magenta tape, rolls 6
- 65. Yellow / black warning tape, roll 5
- 66. Plastic bags, 3 x 5 50 '
- 67. Plastic bags, 5 x 7 50 .
- 68. Potassium iodine use-(personnel list) 1 Protective Clothing
~
.\
~'
, 74. Coveralls 20 pr
- 75. Cotton gloves 20 pr
- 76. Rubber gloves 20 pr
- 77. Pallbearer gloves .:20 pr
.78. Cloth hoods 20
- 79. _ Canvas booties 20 pr
- 80. Plastic suits 20 sets
- 81. Shoecovers, white plastic 1 cs Miscellaneous ,
- 82. PBNP F.mergency Plan 1
- 83. Emergency Plan Implementing Procedures 1
- 84. HP Manual 1
- 85. Air sample number assignment list 1
- 86. Bio-Pak 60 manual 1
- 87. Log book 1
- 58. Cs-137 Check Source 1
- 89. Small foot-size bags 2 rolls
- 90. Large Stanley; utility knife 4
, 91. 55-gallon drum with lid and 1 roll of blotting paper 1
- 92. 55-gallon drum with lid and box of medium ,
plastic bags and roll of large plastic bags 1: _
- 93. . Scissors 2 pr.
EPIP-24b ~.
-(08-83)
+, , , , . ,e, , , , . , , - - . - , , , , . ~ - ~ - . ,,-.n.. , , . - - , . - , , . .- , - - ~ - - , -n ,n,. ~ . , . ,,- ...,,,...-.-w. .--,,,,n. . . .
._~2_.. -.:-__.,.-~..m_-..-~~.____a_:__.____.,. ~
Page 4 of 4 m. 4.
^
. Item Suggested Inv.
4
;; .j No. Item' Inventory Check EMERGENCY SUPPORT CENTER
- 1. Coveralls, cotton 12 pr
- 2. Gloves, cotton 12 pr
, 3. Hoods,-cloth 12
- 4. Low. volume air sampler 1
- 5. Filters, charcoal . 6
- 6. Filters, air particulate 1 box
- 7. Rad Owl II survey instrument 1
- 8. Cs-137 check source 1 Self-reading dosimeters, high range (0-5,000 mR)
~
- 9. 12
- 10. Self-reading dosimeter rezero unit 1.
s 11. Shoecovers, white plastic 50 pr
- 47 12. Victoreen Vamp 1
- 13. Respirators, clear-vue 6
- 14. Respirators, ultra-vue 6
- 15. Filters, respirator particulate 1 box
- 16. PBNP Emergency Plan .
1
-17. Emergency Plan Implementing Procedures 1 ,
SOUTH GATE-
.m.,
Air Sampling r7
~=M
- 69. Low volume air sampler 1
'70. Particulate filters, box 1
- 71. Charcoal filters, box 1
- Radiation Survey & Monitoring Instruments
- 72. Vamp area monitor 1
- 73. Extension cord, 50' 1 l
l Completed By Date Reviewed By Date (Health Physics Supervisor) d EPIP-24b' ..
~
(08-83) L
~~
_ . . . -._.m__.1.____.._ i_.. _ _ _ _ ~ _ . _ . . _ r POINT BEACH NUCLEAR PLANT { EMERGENCY PLAN HEALTH PHYSICS SUPPLIES AT t. TWO RIVERS COMMUNITY HOSPITAL INVENTORY CHECKLIST Item NFAR Triage Area . No. Item Req'd. Available Req'd. Available
; Decontamination Supplies
- 1. Cotton applicators (pkg.) 1 1
- 2. Decon powder 1 1
- 3. Decon soap (1 qt. bottle) 1 1
- 4. Hand brush 2 2
- 5. Potassium permanganate (7 cap. pkg.) 1 1
- 6. Sodium bisulfate (7 cap. pkg.) 1 1 Radiation Survey Equipment and Supplies
- 7. Self-reading dosimeter.(0-500 mrem) 5 5
- 8. Self-reading dosimeter (0-2 Rem) 3 2 8a. ~Self-reading dosimeter charger 1 1 .
- 9. Radiation warning signs and tags (assorted) 10 10 -
- 10. Radiation warning tape (roll) 1 1
,- . 11. Radiation barrier ribbon (roll) 1 1 i
- 12. Filter paper for' smear surveys (box of 100 ea.) 2 2
- 13. Envelopes (box) 1/2 1/2 Protective Clothing l 15. Lab coats 6 6
- 16. Surgeon's caps 6 6 17 . - Canvas or nylon shoe covers 10 N/A
- 18. Gloves, rubber disposable 8 8 l 19. Gloves, cotton disposable 8 8 l 20. Plastic shoe covers 25 25 l Miscellaneous
- 21. Marking pens (pkg.) 1 1
'22.
Absorbent paper (50 ft. roll) 1 N/A
- 23. Bags, plastic (assorted sizes) 50 50
- 24. Bucket, plastic 1 1
- 25. Hop,' sponge, with spare sponge 2 2
- 26. Masslinn mop 1 1
- 27. Masslinn, bag 1 N/A
- 28. Scissors 1 1
- 29. Tuck tape (roll) 2 2
- 30. Masking tape 1" (roll) 2 2 .
1
- 31. Masking tape 2" (roll) 2 2 e
EPIP-24c (08-83)
L. .L
~
+a. . - - . ..._ =- = .. a: : . - = . - - - .
.s .
Page 2 NFAR Triage Area 7 Req'd. Reg'd. Available Available Respiratory Protection Equipment
- 32. Full-face respirators with particulate filters 4 4
- 33. Smoke, tubes /squeese bulb i N/A-Documents and Procedures
- 34. Hedical Assistance, Plan- 1 1
-35. Esergency call list ~l 1 Forms
- 36. CHP-21, Survey Form, pad 1 -N/A
- 37. CHP-34, Dosimetry Rezero Sheet 5 5
- 38. CHP-39, Personnel Contamination Report 5 5
- 39. CHP-83, High-Range Dosimeter Issue Sheet 5 5
-s Medical Assistance Plan Revision Date-
) Call List Revision Date Completed By Date Reviewed By Date Health Physics Supervisor I-l' i
I l t EPIP-24c (08-83)
_ . . ., _ _ _ - _m- - _ ._- -.u 2_.-- . _ . _ - . . . - .
?' .
, fC'; - POINT BEACH NUCLEAR PLANT
., ~ : .
~
CONTROL ROOM EMERGENCY PLAN EQUIPMENT INVENTORY CHECKLIST Required On Hand 1.- Self-reading dosimeters (0-5000 mR) 15 j Self-reading dosimeters (0-200'R) 4
- 2. Self-reading dosimeter charger 1
- 3. ' Landsverk self-reading dosimeter set
- a. Self-reading dosimeters (0-5000 mR) 3 1
- b. Self-reading dosimeters-(0-20000 mR) 9
, c. Self-reading dosimeter charger 1
- 4. Burn kit 1
- 5. First aid kit
- 2
- 6. Flashlight 1 .
. 7. Radector III 1
- 8. Bio-Paks 6
- 9. MSA - SCBA . 2
- 10. Respirators and air lines 6 4
. 11. ' Cloth coveralls 6
- 12. Canvas booties 6 pr.
- 13. Canvas head covers 6
- 14. Eye goggles 6
- 15. Potassium iodide tablets 50 bottles
- 16. Potassiu.a iodide tablets use list - 1
- 17. Respirators with cartridge 4
- 18. Smears (box) with envelopes 1
%W EPIP-24d (08-83) 4, 4-.m , - - . . . .s_.. . ,, . . , , . . , - , . , , . - , , - . . . . - . , . , , * - .
. . , , , , - . _ . . . - . . ~ . . . - - . . . - , . . - . - . , _ . , _ . . . - _ . - - , . . - . . . - _
__ . _ . . _ _ _ _ -- u.. w: - ~ - - _ _ e F' Page 2 O Required On-Hand
- 19. Batteries (Size AA) 2.
- 20. Batteries (Size D) 8
-21. Tuck tape 1 roll
- 22. Pallbearer's gloves ,
24 pr.
- 23. Surgeon's gloves 12 pr.
*If the l'ead seal is broken, the contents of the first aid kit must be inventoried.
Inventory By Date Reviewed By Date
- Health Physics Supervisor
\ ,I e
i-
.e 4 EPIP-24d (08-83)
_ _ . . . _. s_ m. -_._w._.____.. _ . __ _-- >_
/
/
Pr.
,' POINT BEACH NUCLEAR PLANT EHERGENCY VEHICLE INVENTORY CHECKLIST DATE Item Required On Hand
- 1. First aid kit
- 1
- 2. Burn kit 1
- 3. . Oxygen resuscitator 1
- 4. Stretcher. 1
, 5. Pillow 1
- 6. Scott foam ambulance blanket 2 1 pkg. 5
- 7. Miscellaneous medical forms
,-m 8. TLD's and TLD issue forms (CHP-41A) 10 ea. ,
- 9. Mini-rad survey instruments 2
- 10. Thyac III with end window probe 2
- 11. HP-210 probe 1
*If the lead seal is broken, the contents of the first. aid kit must be inventoried.
Inventory By Date Reviewed By Date Health Physics Supervisor EPIP-24e (08-83)
. . _ . _ . . . _ _ . --_ _a n _ . : . _ . ,__ u . . .- .
i .
< m. -
.'; POINT BEACH NUCLEAR PLANT EMERGENCY VEHICLE CHECKLIST DATE
. Unsatisfactory Satisfactory 1.0 WEEKLY INSPECTION 1.1 Tire pressure-( 32-35 psi) and tread condition 1.2 Radiator water level 1.3 Engine oil level 1.4 Lights and turn signals 1.5 Fuel tank level (>3/4 full) ,
1.6- Battery charger connected
- (November through March)
. _ ;' 1.7 0xygen bottle pressure (21650 psi).
1.8 Vehicle starts easily 1.9 Radio operational check Explain all unsatisfactory items: 2.0 TEST DRIVE (Weekly November through March; Monthly April through October) Note any operational problems: NOTE: VEHICLE SHOULD BE RUN 10-15 MINUTES PRIOR TO CHECK. ,
.EPIP-25a Page 1 of 2 (08-83)
_ ._ .. -- . _-- ... w -- - ~
^ - - - = - - - - - - - - " = - ' " - " " " - -
e p- s
.[' 3.0 Maintenance request No. subenitted for correction of observed problems / defects.
I~ Checked By .., Reviewed By Date . Health Physics Supervisor 9
,Q,
,.s t
s s N 4 1
-' t ' s EPIP-25a Page 2 of 2~
(08-83) ' s t
0 .
.9 .
POINT BEACH NUCLEAR PLANT
-m ,
1 MONTHLY HEALTH PHYSICS INSTRUMENT AND
. AIR SAMPLER FUNCTIONAL TEST CHECKLIST Month, Year References EPIP 7.4.1 - Routine Check, Maintenance, Calibration and Inventory ll; Schedule of Health Physics Emergency Plan Equipment EPIP 7.4.2 - Emergency Plan Equipment Routine checks, Maintenance
- l. and Calibration Instructions SITE BOUNDARY CONTROL CENTER II.3TRUMENTATION .
Check Source Item Type of Seriale ' Source Check No. Equipment Number I 1Used Criteria Results
- 1. Thyac III Installed cpm _
cpm
- 2. GSM-5 S-23 eps y 3 cpm
, 3. RM-3C S-23 cpm - cpm 7
- 4. PIC-6A Cs-11 mR/hr mR/hr J
- 5. P1C-6A Cs-11 mR/hr mR/hr i
- 6. >h Cs-11 mR/hr mR/hr l PIC-6A ' .
\
- 7. PIC-6A Cs-11 mR/hr mR/hr,
- 8. Radector III Cs-11 mR/hr mR/hr I l ' l mR/hr
- 9. HPI-1010 7
. g, .
Cs-11 mR/hr l S-23 cpm cpm
- 10. Nuclear Chicago J
/ ;
AIR SAMPLERS, i '
\
Item Satisfactory No. m T Functional Test / , NOTE: SOURCE CHECK CRITERIA High Volume - TO BE ENTERED FROM CURRENT 1. CALIBRATION STICKER ON EACH
- 2. Battery (12 V DC) UNIT. RESULTS MUST BE WITHIN 120% OF THIS VALUE'. _
Page 1 of 4 EPIP-25b P (08-83) ; i
...,-=-....--~-----.-:------------~---- '
o OPERATIONS SUPPORT CENTER
. .m INSTRUMENTATION Source Item Type of Serial Check check No. Equipment Number Source Criteria Results
- 1. Rad Owl II Cs-6 mR/hr mR/hr
- 2. Thyac III Int. cpm cpm
- 3. Thyac III Int. cpm cpm
- 4. Vamp Area Monitor Cs-6 mR/hr mR/hr AIR SAMPLERS Item Satisfactory No. Description Functional Test
- 1. Low volume (115 V AC)
- 2. High Volume (115 V AC)
- 3. High Volume (115 V AC)
- 4. AMS-2 (cart-mounted)
Check Source check Source Criteria Criteria
- a. AMS-2 cpm cpm
- b. RM-14 cpm cpm Use check source CS-6.
EPIP-25b Page 2 of 4 (08-83)
--.. - . . ... - -.. - - . . , . . - . - . - - - . - . . ~ . - - - - - . . - . - - .
EMERGENCY SUPPORT CENTER INSTRUMENTATION Check Check Item Type of Serial Check Source Source No. Equibnent Number Source . Criteria Results
- 1. Rad Owl II Cs-5 mR/hr mR/hr
- 2. Vamp Area Monitor Cs-5 mR/hr mR/hr AIR SAMPLERS Item Satisfactory No. Description Functional Test
- 1. Low Volume (115 V AC)
SOUTM GATE INSTRUMENTATION Check Sous ce Item Type of Seriti Source Chech No. Equipment Number Used Criteria Results i
- 1. VAMP Monitor Cs-6 mR/hr mR/hr i AIR SAMPLERS Item Type of Satisfactory l No. Equipment ' Functional Test
- 1. Low Volume CONTROL ROOM INSTRUMENTATION l
Check Source ! Item Type of Serial Source Check No. Equipment Number Used Criteria Results
- 1. Radector III Cs-3 mR/hr mR/hr EPIP-25b Page 3 of 4 (08-83)
M
+
FIRST AID ROOM INSTRUMENTATION . Check Source Item Type of Serial Source Check No. Equipment Number Used Criteria Results
- 1. Thyac III Internal epa cpm EMERGENCY VEHICLE INSTRUMENTATION Ites No. Equipment Number" Used. Criteria Results
- 1. Thyac III Internal cpm cpm
- 2. Thysc III Internal cpm cpm ,
- 3. Mini-Rad Cs-3 mR/hr mR/hr
- 4. Mini-Rad Ca-3 mR/hr mR/hr Checked By Date Reviewed By Date Health Physics Supervisor EPIP-25b Page 4 of 4 (08-83)
- - ~ . . _. _. _ _
.. - _ _ - ,. n 6
./
Of POINT BEACH NUCLEAR PLANT l 1 QUARTERLY EMERGINCY PLAN CHICKLIST 4 Quarter 1 2 3 4 (circle one) Year
Reference:
EPIP 7.4.1 - Routine Check, Maintenance, Calibration and Inventory of Schedule of Health Physics Emergency Plan Equipment EPIP 7.4.2 - Snergency Plan Equipment Routine Checks, Maintenance
~
and Calibration Instructions SITE BOUNDARY CONTROL CENTER RESPIRATORY EQUIPMENT
~
Item No. Tyge, Serial No. Inspection ,
- 1. Full-face
- 2. Full-face
- 3. Full-face __ __
', 4. Full-face
, :)
COMMUNICATIONS
. Portable FM Radio Functienal check with control room WARNING LIGHTS, TRAFFIC r
Traffic Warning Lights All traffic warning lights functioning AC GENERATOR (Gasoline Powered) Functional Test
~.
Page 1 of 4 EPIP-25c (08-83)
- - - - - - -+ . , , . - , . , n ,-# e., - -.-s,.w-_...m._,.7w.m._,.,..q,_,,,.,7__,,,,,y , _ . - . , . , , ,--...,,,,.,g ..,,,y.,...y ., _, , , ,__,
0
') DRY CELL BATTE* AEPLACEMElff (For SBCC, Control Room, TSC, 03C, ESC and Two 3 Rivers Hospital)
NOTF.: If alkaline batteries are used, battery changeout is required annually rather than quarterly. If carbon or mercury batteries are used, a quarterly 5-minutetestshallbecompletedtoverifyoperability. Item Battery Changed / No. , Type of Equipment M Quantity Tested Date Due
- 1. Traffic Warning Light
- 2. Survey /Frisker Instruments
- 3. Flashlights
- 4. Portable Radio
- 5. Stop Watch
- 6. Self-Reading Dosimeter Cha.rger ;
CONTROL ROOM (,' RESPIRATORY EQUIPMENT
~
Item Type of Serial Functional No. Equipment Number Inspection Test
- 1. Bio-Pak
- 2. Bio-Pak
- 3. MSA-SCBA
- 4. MSA-SCBA
- 5. Supplied Air Mask
- 6. Supplied Air Mask 7.' Supplied Air Mask
.8. Supplied Air Mask
- 9. Supplied Air Mask *
- 10. Supplied Air Mask
- 11. Supplied Air Mask Hose
- 12. Supplied Air Mask Hose
- 13. Supplied Air Mask Hose
- 14. Supplied Air Mask Hose
- 15. Supplied Air Mask Hose
- 16. Supplied Air Mask Hose
- 17. Supplied Air Valve
- 18. Supplied Air Valve
- 19. Supplied Air Valve -
i 20. Supplied Air valve
- 21. Supplied Air Valve
- 22. Supplied Air Valve Page 2 of 4 EPIP-25c (08-83) .
_ . - - _ ._-.._.---...-----.~.--::w ' Control Room Respiratory Equipment, continued.... O i Item Type of Serial
;/ No. Equipment Number Inspection ,
23.' Supplied Air Hose.
- 24. Supplied Air Hose
- 25. Supplied Air Hose
- 26. Supplied Air Hose
- 27. Supplied Air Hose
- 28. Supplied Air Hose i
- 29. Spare Mask
- 30. Spare Mask *'
31.. Spare Mask
- 32. Spare Mask
- 33. Bio-Pak
- 34. Bio-Pak
- 35. Bio-Pak
- 36. Bio-Pak TECHNICAL SUPPORT CENTER /0PERATIONS SUPPORT CENTER' RESPIRATORY EQUIPMENT
- Item Type of Serial Serial
- ,
l No. Eguipment Number Inspection Number Inspection l I * -1. Clear-Vue 1. 4. ,, y~j 2. 3. 5. 6.
- 2. Ultra-Vue 1. 4.
2._ 5.
- 3. 6.
- 3. Bio-Pak 1. 7.
- 2. 8.
- 3. 9.
- 4. 10. ,
- 5. 11. ;
- 6. 12.
- 4. MSC-SCBA 1.
QMMUNICATIONS Pottable Radio KRQ-717 Functional Test with * (2 units) Control Room Page 3 of 4 EPIP-25c
-(08-83)
-,, ,. , ,, , . , . . ,__._,.._.,____.m.-.... . . . . . . . . . _ . _ . _ _ . , _ _ .. _ ., _ ..-..-, - _,._.-_ __ _ ~_... __._ . _.__ - ,_
z_ . -~a - - .- .. ..-:-. ~ - - - - - - a
~/
4 EMERGENCY SUPPORT CENTER
-I RESPIRATORY EQUIPMENT Item Type of Serial Serial No. Equipment Numb ~er Inspection Number Inspection
- i. Clear-Vue 1. 4.
- 2. 5.
- 3. 6.
- 2. Ultra-Vue 1. 4,
- 2. 5.
- 3. 6.
TWO RIVERS COMMUNITY HOSPITAL RESPIRATORY EQUIPMENT Item Type of Serial No. Equipment Number Inspection , 1. Clear-Vue 1.
- 2.
, 3.
'(,/
?
4*
- 2. Ultra-Vue 1.
2. 3. 4. REMARKS: ( NOTE: Include maintenance request numbers for all items requiring repairs. Inventory By Date t l Reviewed By Date l Page 4 of 4 . l EPIP-25c ( (08-83)
- 2.
- ._ _ _ ._ a _ _ __.2 . _ _ _ _ . . _ _ . _ _ _ . ..__-.____ _.
9
/ POINT BEACH NUCLEAR PLANT SEMI-ANNUAL & ANNUAL EMERGENCY PLAN CHECKLIST 1st Half 2nd Half Year (check one)
Reference:
_ EPIP 7.4.1 - Routine check, Maintenance, Calibration and Inventory of Schedule of Health Physics Emergency Plan Equipment EPIP 7.4.2 - Emergency Plan Equipment Routine Checks, Maintenance and Calibration Instructions SITE BOUNDARY CONTROL CENTER ' AIR SAMPLERS Item Preventive Flow Rate No. g Maintenance Calibration
- 1. High Volume (115 V AC) ;
- 2. DC Battery Powered
)
(1 SELF-READING DOSIMETERS , Self-Reading Dosimeters
- Drift / Response Checked Date Last Completed Date Due I- TLD's TLD's Changed
- Date Changed Date Due
- Includes SRD's and TLD's from emergency vehicle.
l l i l - \ - EPIP-25d Page 1 of.5 (08-83)
... . n. - - - . . - _a. . - - . - :=.-- .--u:.--, .w -- . .
f] 4 MISCELLANEOUS Item No. .
- 1. Potable Water (20 gal.) a. Date Changed
- b. Date Due
- 2. Gasoline a. Date Changed f
- b. Date Due
- 3. Fire Extinguisher Serial Number -
Date Last Inspected
- 4. AgZ Filters Moisture Indicator Checked
- 5. AC Generator Periodic Maintenance TECHNICAL SUPPORT CENTER / OPERATIONS SUPPORT CENTER AIR SAMPLERS Item Preventive Flow Rate -
N_o Maintenance Calibration
- 1. High Volume (115 V AC)
- 2. Low volume (115 V AC)
. 3. AMS-2 Cart Mounted SELF-READING DOSIMETERS Self-Raading Dosimeters Drift / Response Checked Date Last Completed Date Due k
- EPIP-25d Page 2 of 5 (08-83)
--+ em- e w-. --mee--e e er*-- g % w-ee-me.+e --t* --ma wg ,,w m.,-g ywy-,,.9e,.-3,,wm99 .- 9,m9= y, vi y.g y, y%qwg _g w g yg 9 -, -,w. wr, -g, , , _ , ,9 , y,,
. . . . . . _ _ . . . - . . - - .. - - . . . - . . - .- - .... . . ...~ ~ ---- - --- - - 'N RESPIRATORY EQUIPMENT Item S_erial Periodic No. Number Functional Test Maintenance
- 1. Bio-Pak
( l EMERGENCY SUPPORT CENTER AIR SAMPLERS Item Preventive Flow Rate . No., M Maintenance Calibration -
- 1. Low Volume (115 V AC)
)
s SELF-READING DOSIMETERS . Self-Reading Dosimeters Drift / Response Checked Date Last Completed Date Due SOUTH GATE AIR SAMPLERS Item Preventive Flow Rate No. Equipment Maintenance Calibration
- 1. Low Volume CONTROL ROOM SELF-READING DOSIMETERS Self-Reading Dosimeters Drift / Response Checked Date Last Completed -
Date Due EPIP-25d Page 3 of 5 (08-83)
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'% ~
RESPIRATORY EQUIPMENT e Item Type of Serial Periodic j No. Equipment Number Inspection Functional Test Maintenance
- 1. Bio-Pak
- 2. Bio-Pak'
- 3. Bio-Pak
'4. Bio-Pak
, 5. Bio-Pak
- 6. Bic-Pak
- 7. MSA SCBA N/A
- 8. MSA SCBA N/A
- 9. Supplied Air / N/A -
- (Comp. Unit) / N/A i
- 10. Supplied Air
~
/ N/A (Comp. Unit) / N/A-
- 11. SupplieElAir / N/A (Comp. Unit) / . N/A
- 12. Supplied Air /- N/A
. (Comp. Unit) / N/A
- 13. Supplied Air / N/A (comp. Unit) / N/A
- 14. Supplied Air / N/A
- l (Comp. Unit) / N/A TWO RIVERS COMMUNITY HOSPITAL
! SELF-READING DOSIMETERS Self-Reading Dosimeters Drift / Response Checked Date Last Completed Date Due EPIP-25d Page 4 of 5 (08-83)
. z . . __ -
. . _ - - . . --.:-.-.--.-~~-----
,m
'.' ', REMARKS:
Checked By Date Reviewed By Date Health Physics Supervisor l l l i l i i f I 1- . EPIP-25d Page 5 of 5 (08-83)
' ^ '
.n- - : -- _.
~ -'
POINT BEACH NU('LRAR PLAlfr EMERGENCY PLAN INSTRUMENT CALIBRATION SCHEDULE n 1 PORTABLE SURVEY INSTRUMENTS The following listed instrtments are scheduled for calibration during the month indicated in accordance with Health Physics Procedure HP 13.2. MoltrH: April / October (Emergency Plan In '.ruments) YEAR: Equipment Type Inventory Number Date Completed Initials Location
- PIC-6A 5066 PIC-6A 6035 PIC-6A 6593 PIC-6A 6594 Radector III 5457 Radector III 5458
' ~ t Rad Owl II 5217 1 i
\' Rad Owl II 5263 .
f l VAMP 6579 VAMP 6580 VAMP 6581 Mini-Rad 79511 Mini-Rad 79533 l h.p.i. Model 1010 6314
- Location Key L
- 1. Site Boundary Control Center 5. Guard. House
- 2. Operations Support Center 6. First Aid Room
- 3. ' Technical Support Center 7. Control Room
- 4. NFAR/ Triage 8. Emergency Plan Vehicle l
t REVIEWED BY Health Physics Supevisor - DATE EPIP-28 (08-83)
, c* .
POINT BEACH NUCLEAR PLANT EMERGENCY PLAN COUNTING EQUIPMENT AND FRISKER CALIBRATION SCHEDULE FRISKER CALIBRATION AND EFFICIENCY DETERMINATION The following frisking instruments are scheduled for electronic calibration and efficiency determination during the indicated month in accordance with health physics procedure HP 13.3 and HP'13.4.1. MONTH: APRIL /0CTOBER Equipment Type Inventory Number Date Completed Initials Location
- Thyac III 1664 Thyac III 2350
~
Thyac III 2351 Thyac III 235::
\ '
Thyac III , 2353 Thyac III 2354 GSM-5 3221 RM-3C 3376 [
- Location Key
- 1. Site Boundary Control Center 5. Emergency Vehicle '
- 2. Operations Support Center 6. First Aid Room
- 3. Technical Support Center 7. Control Room
- 4. NFAR NOTE: THE TWO THYAC'S FROM THE EMERGENCY VEHICLE ARE TO BE CHECKED WITH AN END WINDOW PROBE (NORMALLY ATTACHED TO THYAC) AND THE HP-210 i PROBE, ALSO KEPT IN THE EMERGENCY VEHICLE.
~
EPIP-29 Page 1 of 2 (08-83)
' ~ ^ ^~
~
f.
. 4 COUNTING EQUIPMENT The following counting instruments'are scheduled for efficiency determination during the indicated month in accordance with health physics procedures HP 13.4.1, EPIP 7.5.3 and EPIP 7.5.4. ,' MONTH: APRIL / OCTOBER , .s ,
Equipment Type Inventory Number._ Date Completed Initials Location
- Canberra Model 30 MCA 6696 _ l Nuclear Chicago 3482 Nuclear Chicago 5094 TECHNICAL SUPPORT CENTER AIR MONITORING EQ'JIPMENT .'
. The following equipment is scheduled for electronic calibration, gaseous
, i calibration, and efficiency determination during the indicated month in
(,, ' accordance with EPIP 7.4.4 and HP 13.4.1. MONTH: JANUARY Equipment Type Inventory Number Date Completed _ Initials Location
- AMS-2 5525
~
RM-14 6693 REVIEWED BY (Health Physics Supervisor) DATE , l
- Location Key
. 1. Site Boundary Control Center
, 2. Operations Support Center __ l 3. Technical Support Center l EPIP-29 Page 2 of 2 (08-83)
. .. L .-J
- - . . . - -. : .76- .
l{ - - e' g POINT BEACH NUCLEAR PLANT REACTOR COOLANT POST-ACCIDENT SAMPLING ANALYSIS REPORT 1.0 ANALYSIS OF G&SIOUS SAMPLE 1.1 Hydrogen Analysis i i 1.1.1 Scale used on gas partitioner 1.1.2 Millivolt reading on chart recorder 1.1.3 % hydrogen from calibration curve 1.1.4 Voltane of sample bomb in al , 1.1.5 Atmospheric pressure (nun /Hg) 1.1.6 cc/Kg hydrogen in coolant * (STP) ," 0
*cc/Kg H2 (STP) = ( x 5) x 1000 f
),
y"':
= 3.68 (1 1 3) * (1 1 5)
(1.1.4) 1.2 Radioactive Noble Gases 1.2.1 Decay time in minutes 1.2.2 Sample count time in seconds 1.2.3 Dete'ctor 1.2.4 Geometry 1.2.5 Common multiplier *
- 1.2.6 Volume of sidearm flask 280 (1.2.6)
,g , (1.1.4) 0.5
= 5.6 x 102
~
(1) See Section 5.2.2 of EPIP 7.3.2. EPIP-20 (08-83)
_ _ _. ._--:.~.-. .,-_._-.._
--.__.a. _
.[
Page 2
^ .
1.2.7 MCA Results f Isotope Concentration (UCi/cc) Xe-133 Kr-85m Kr-88 Xe-133m Xe-135
-Xe-138 Kr-87
. Xe-135m Ar-41 Kr-85
-Xe-131m 2.0 ANALYSIS OF LIQUID SAMPLE 2.1 Boron and pH 2.1.1 Volume of sample al .'
2.1.2 pH of sample (,) 2.1.3 Normality of NaOH ,
- 2.1.4 Volume of NaOH used al l
2.1.5 Concentration of boron
- ppe l
- ppm Boron x (2.1.4) x 10810 2.2 Chloride 2.2.1 Chloride concentration ppm 2.3 Iodine Analysis 2.3.1 Decay time min 2.3.2 Sample count time sec 2.3.3 Detector 2.3.4 Geometry EPIP-30 (08-83)
- . . _ - - - , . , . . - - - , - . -- - - . , - . , , , . .,,.n.. , . ,_____.,s,,-.-,,.,,, ., .,..,,.wn., ,---,.,,.-,,2. - - , - , - - - - ,
_ . . - _ _ . _ - ~ ~ _ . -- ----.-=-.~.x<-w~. 1
. .s ;
Page 3
.O.*,
t' 2.3.5 Common multiplier *
*ag = 1075 xF S
- V, = volume of sample (first dilution)
F = Any additional dilution factors (2 or more dilutions) (1) See Section 5.4.3 of EPIP 7.3.2. 2.3.6 NCA Resu'lts t
, Isotope Concentratt.a suti/cc)
I-130 I-131 , I-132 f' "'N I.133
\ j '. .
./
I-134 I-135 Total 3.0 ROUTING AND APPROVAL Date Initials l 3.1 Calculations completed by 3.2 Analysis completed by l l 3.3 Chemistry & Health Physics Supervisor 3.4 Chemistry / Health Physics Supervisor (TSC) 3.5 Director (TSC) l EPIP-30 (08-83)
A N w t
\J)
. )
J r
-t
. POINT BEACH NUN.ran PLANT CALCULATION OF Xe-133 EQUIVALENT RELEASE RATES i
i Responsibility - Shift Supervisor or designee. Frequency.- During classification only. i 1.0 LOW RANGE OPERATIONAL VENT STACK READINGS . Meter Reading Conversion Factor Release Rate
~
Flow Rate , (pci/cc or cpm) (cfa) (Curies /sec) Auxiliary Building 61400 _ x 5.8 x 10",8 = l
- Drumming Area 43100 x 1.3 x 10 s- ,
Gas Stripper Building 13000 x 6.2 = Combined Air Ejector 25 x 1.6 x 10,2 = , i l 4 I., 2.0 EBERLINE RMS-II VENT STACK READOUTS i 4 Flow Hate Meter Reading Conversion Factor Release Rate (CFM) (R/hr) . Curies - Hrs (Curies /sec) } sec-R Auxiliary Building 61400 x 3.0 x 108 = Drumming Area 43100 x 2.1 x 108 = 6.2 x 102 } Gas Stripper Building 13000 x . l l Combined Air Ejector 25 x 3.4 = , I I f i ; i i , i i i i EPIP-34 -
- (09-83) {
i
,O '\' I N. . ' .-
l 9 3.0 PLANT EFFLUENT VENT STACK CONTACT READINGS i Flow Rate Meter Reading Conversion Factor Release Rate . (CFM) (R/hr) Curies-hr (Curies /sec) sec-R Auxiliary Building 61400 x 3.0 x 102 . Drumming Area 43100 x 2.3 x 102 . Das Stripper Bui2 ding 13000 x 8.0 x 10 4 = Combined Air Ejector 25 x 1.6 x 102 = c Estimated Steam x Specific x Conversion x Neter X Conversion Release Rate ' Release Volume Factor Reading Factor = Ci/sec (lb/hr) (ft /lba) 8 hr-cm3 (R/hr) Curies-br sec-ft3 cm3 -R t i Hain Steam Header x x 7.86 x x 8.0 x 10~4 = l Assume 1000 psia steam which will give i a conservative specific volume. At i 1000 psia specific volume = .446 ft 3/lba. l Steam generator safety valve rating is 8.33 x 103 lb/hr per valve. Atmospheric l' relief valve capacity is 3.3 X 104 lb/hr with both valves open. i, i, 1 ( f r i EPIP-34 F (09-83) i
l,
. _p,
.]
. -i
. .g" /
i l 4.0 ESTIMATE OF GROSS Xe-133 EQUIVALENT RELEASE RATES ) Xe-133 Vent Equivalent Release Rate + (Curies /sec) ; Auxiliary Building , Drumming Area , Gas Stripper Building Combined Air Ejector Decay Duct i Main Steau Header - ',
. TOTAL l
I 2 Completed By Date Time ; i i I l l 4 i i i t a . 4 I i I I i. t
! EPIP-34 (09-83) ,
y , . -x - ( , POINT BEAC q ;l. EAR PLANT k j/ t' DOSE CALCULATIONS Responsibility - Shift Supervisor or designee. . Frequency - During classification only. .f,
?
1 1.0 ESTIMATION OF SITE BOUNDARY WHOLE BODY DOSES RATES X/Q X Release X Dose conversion = Whole Body I 3 ' (sec/m ) Rate Factor Dose Rate (Ci/sec) (REMS-m8 ) (RENS/hr) Ci-hr 2.6 X 104 X X 26.9 = 2.0 ESTIMATION OF SITE BOUNDARY' THYROID DOSES RATES Type of Accident Conversion - Whole Body Dose Thyroid Dose Rate Factor , Rate (R/hr) (Rem /hr)
- 1. Loss of Coolant (LOCA) 360 X =
- 2. Gap Activity Accident . 2.0 X =
- 3. Fuel Handling Accident 77.1 X =
- 4. Steam Generator Accident 6.25 to 62.5 X _,
=
3.0 PROTECTIVE ACTION DOSE DETERMINATION NOTE: USE ONLY IF TIME IS LIMITED. i i Whole Body Dose Rate Release Duration Estimate
- Whole Body Dose f
X = Thyroid Dose Rate X Release Duration Estimate * = Thyroid Dose ,
= i X
- If release duration is unknown, use 8 hours. -
I Completed By Date Time EPIP-35 (09-83)
-..__-o<___-__-___ ~
. ..__- . . _ . ' . ..._._.n-ncu---------.-------...-_-._._.=
) .- - ,- MEDICAL ASSISTANCE CALL LIST Plant Ext. Home PBNP Personnel
- J. J. Zach, Manager - Point Beach Nuclear- Plant .
P. J. Skramstad, Superintendent - Chemistry & Health Physics R. S. Bredvad, Health Physicist M. L. Braun, Industrial Safety Coordinator Health Physics Duty & Call " Beeper" dhemistryDuty& Call" Beeper" 4 Hospital Assistance Emergency vehicle, Two Rivers Fire Department
- Community Hospital, Two Rivers Doctors' Clinic, Ltd., Two Rivers
/^'s
( ) University Hospital, Madison; Emergency Room F. C. Larson, M.D. R. F. Schilling, M.D. R. R. Radtke, Ph. D. (Health Physicist) WEPCO Medical Department Dr. E. Huston, Medical Director Accident Prevention Department State of Wisconsin Department of Industry, Labor and Human Relations, Safety and Buildings Division, Boiler Section EPIP-37 (09-82)
I - . . . _ _ . _ . . , _ _ _ . _ _ . . _ . _ . U MEDICALESSIS5ENCECALLLIST Plant Ext. Home
, PBNP Personnel J. J. Zach, Nanager - Point Beach Nuclear Plant ,
P. J. Skramstad, Superintendent - Chemistry &- Health Physics R. S..Bredvad, Health Physicist
- N. L. Braun, Industrial Safety' Coordinator Health Physics Duty & Call " Beeper" Chemistry Duty & Call " Beeper" Hospital Assistance Emergency Vehicle, Two Rivers Fire Department Community Hospital, Two Rivers Doctors' Clinic, Ltd., Two Rivers
.(..'\ ~, f~
University Hospital, Madison; Emergency Room F. C. Larson, M.D. R. F. Schilling, M.D. R. R. Radtke, Ph. D. (Health Physicist)
~
WEPCO
\ -
Medical Department
~
Dr. E. Huston, Medical Director f Accident Prevention Department State of Wisconsin Department of Industry, Labor and Human Relations, Safety and Buildings Division, Boiler Section - i e e 1 EPIP-37~ (09-82)
~ % . _ _,\
MEDICAL ASSISTANCE CALL LIST Plant Ext. Home k PBNP Personnel
- s. .
J. J.. Zach, Nanager - Point Beach Nuclear Plant P. J. Skramstad, Superintendent - Chemistry & Health Physics R. 5. Bredvad,-Health Physicist M. L. Braun, Industrial Safety Coordinator Health Physics Duty & Call " Beeper" Chemistry Duty & Call " Beeper" Hospital Assistar.ce L Emergency Vehicle, Two Rivers Fire Department I Community Hospital, Two Rivers , Doctors' Clinic, Ltd., Two Rivers - f\
\, ,. University Hospital, Madison; Emergency Room
' F. C..Larson, M.D.
~
R. F. Schilling, M.D. R. R. Radtke, Ph. D. (Health Physicist) l l WEPCO Medical Department
~
Dr. E. Huston, Hedical Director Accident Prevention Department State of Wisconsin Department of Industry, Labor and Human Relations,
; Safety and Buildings Division, Boiler Section 1 1
e 1 l
~'
EPIP-37 (09-82) l i:}}