ML20049J624
| ML20049J624 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 02/26/1982 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20049J620 | List: |
| References | |
| PROC-820226-01, NUDOCS 8203180510 | |
| Download: ML20049J624 (52) | |
Text
D e e 02-26-82 O TABLE OF CONTENTS Revision Date 1.0 C_L_ASSIFICATION AND ASSESSMENT 1.1 Initial Classification . . . . . . . . . . . 0 03-31-81 1.2 . Plant Status- . . .. . . . . . . . . . . . . 0 03-31-81 1.3 Estimation of Source Term . . . . . . . . . . 0 03-31-81 1.4 Radiological Dose Evaluation . . . . . . . . 2 09-04-81 1.5 Protective Action Evaluation . . . . . . . . 2 02-26-82
.1. 6 Radiciodine Blocking and Thyroid Exposure Accounting . . . . . . . . . . . . . . . . 1 02-26-8 j 2.0 UNUSb?.L EVI:NT IMPLEMENTING PROCEDURES 2.1 Unusual Event - Immediate Actions . . . . . . 0 03-31-81 2.2 Unusual Event - Plant and Company Personnel Notification . . . . . . . . . . . . . . . 1 07-01-81 2.3 Unusual Event - Off-Site Agency Notification 1 02-26-81 j 3.0 ALERT IMPLEMENTING PROCEDURES 3.1 Alert - Immediate Actions . . . . . . . . . . 0 03-31-81 3.2 Alert - Plant and Company Personnel Notification . . . . . . . . . . . . . . . 1 07-01-81 3.3 Alert - Off-Site Agency Notification . . . . 0 03-31-81 4.0 SITE EMERGENCY - IMPLEMENTING PROCEDURES 4.1 Site Emergency - Immediate Actions . . . . . 0 03-31-81
. 4.2 Site Emergency - Plant and Company Personnel l
Notification . . . . . . . . . . . . . . . 1 '07-01-81 4.3 Site Emergency - Off-Site Agency Notification 0 03-31-81 l 5.0 GENERAL EMERGENCY - IMPLEMENTING PROCEDURES 5.1 General Emergency - Immediate Actions . . . . 0 03- 31-81 5.2 General Emergency - Plant and Company Personnel Notification . . . . . . . . . . 1 07-01-81 5.3 General Emergency - Off-Site Agency Notification . . . . . . . . . . . . . . . 0 03-31-81 6.0 EVACUATION 6.1 Limited Plant Evacuation . . . . . . . . . . 0 03-31-81 6.2 Plant Evacuation . . . . . . . . . . . . . . 1 02-26-82 6.3 Exclusion Area Evacuetion . . . . . . . . . . 0 03-31-81 6.4 Energy Information Center Evacuation . . . . 0 03-31-81 l 8203180510 820312 i PDR ADOCK 05000266 l F PDR
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(J Revision Date 7.0 CHEMISTRY & HEALTH PHYSICS RESPONSE AND PREPAREDNESS 7.1 Internal Chem & HP Group Personnel Notification /
Initial Response 7.1.1 Cnem & HP Group Personnel Notification and Initial Response when Chem & HP Personnel are On-Site . . . . . . 0 03-31-81 7.1.2 Chem & HP Group Personnel Notification and Initial Response when Chem & HP Personnel are Off-Site . . . . . . 0 03-31-81 7.1.3 HP Protective Actions by Operations Personnel Prior to Arrival of Chem
& HP Group Personnel . . . . . . . 1 05-15-81 7.2 Health Physics Facility Activation 7.2.1 Activation of HP Facilities at Site Boundary Control Center . . . . . 1 09-04-81 7.2.2 Activation of HP Facilities at Operations Support Center . . . . 0 03-31-81
/ 7.2.3 Activation of HP Facilities at
(' 7.2.4 Technical Support Center . . . . .
Health Physics Communications . . .
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09-04-81 03-31-81 7.2.5 Control and Use of Vehicles . . . . 0 03-31-81 7.3 Radiological Surveys 7.3.1 Airborne Sampling and Direct Dose Rate Survey Guidelines . . . . . . 2 09-04-81 7.3.2 Post-Accident Sampling and Analysis of_Potentially High Level Reactor Coolant . . . . . . . . . . . . . 3 12-30-81 7.3.3 Post-Accident Sampling of Contain-ment Atmosphere . . . . . . . . . 3 12-30-81 l
7.3.4 Movement of Required Chemistry Equip-i ment and Material to the Technical Support Center Counting Room and l Mini-Laboratory . . . . . . . . . 0 12-30-81 7.4 Emergency Equipment l
7.4.1 Routine Check, Maintenance, Cali-bration and Inventory Schedule for i Health Physics Emergency Plan Equipment . . . . . . . . . . . . 3 01-29-82 7.4.2 Emergency Plan Equipment Routine l (s Check, Maintenance and Calibration Instructions . . . . . . . . . . . 2 07-01-81 l 7.4.3 Use of Baird Model 530 Single Channel Iodine Spectrometer to Determine Airborne Iodine Activities . . . . . . . . . . . . 1 05-15-81
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q r Page 3 Revision Date 7.4.3.1 Use of Canberra Model 3100 Series 30 Multichannel Analyzer to Determine Airborne Iodine Activities . . . . 0- 02-26-82 7.4.4 AMS-2 Air Particulate, Iodine and Noble Gas Sampler / Detector . . . . 0 03-31-81 8.1 Personnel Assembly and Accountability . . . . 0 03-31-81 9.1 Security .................. s 0 03-31-81 10.0 Firefighting ... . ..... . . . . . . . 0 03-31-81 11.0 FIRST AID AND MEDICAL CARE 11.1 On-Site First Aid Assistance . . . . . . . . 2 02-26-82 11.2 Injured Person's Immediate Care . . . . . . . 1 05-15-81 11.3 Hospital Assistance . .. . . . . . . . . . . 0 03-31-81 11.4 Personnel Decontamination . . . . . . . . . . 0 01-29-82 12.0 REENTRY AND RECOVERY PLANNING j 12.1 Reentry Procedures for Emergency Operations 0 03-31-81
/ 12.2 Personnel Exposure and Search'and Rescue Teams . . ................. 0 03-31-81 12.3 Recovery Planning . ............ . 0 03-31-81 4
12.4 Personnel Monitoring Exposure Guidelines . . 0 01-29-82 13.0 PRESS 13.1 Crisis Communications . .... . . . . . . . 1 09-04-81 14.0 COMMUNICATIONS 14.1 Testing of Communications Equipment . . . . . 0 03-31-81 15.0 TRAINING, DRILLS AND EXERCISES 15.1 Employee Training . . . . . . . . . . . . . . 1 09-04-81 15.2 Off-Site Personnel Training . . . . . . . . . 0 03-31-81
, 15.3 Drills and Exercises ......... . . . 1 05-15-81 16.0 WISCONSIN ELECTRIC GENERAL OFFICE PROCEDURES 16.1 Nuclear Engineering Section Notification and Response .... . ............ 3 09-04-81 N
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. 02-26-82 O
l TABLE OF EPIP FORMS EPIP EPIP Form Title Procedure 01 Emergency Plan Airborne Radiation Survey Record Site Boundary Control Center (03-81) 7.3.1 02 Emergency Plan Survey Record Site Boundary Control Center (09-81) 7.3.1 03 Dose Factor Calculations for Specific Noble Gas Analysis Results (03-81) 7.3.1 04 Status Report on Plant Systems snd Controls for Affected Unit (03-81) 1.2 05 Worksheet for Status Report on Radiation Monitoring System for Unit (03-81) 1.2 06 Worksheet for Status Report on Radiation Monitoring System for Plant (03-81) 1.2 07 For X/Q Determination (09-81) 1.4 08 Estimated Whole Body and Thyroid Projected Doses (09-81) 1.4 09 Estimated Whole Body Dose Calculation worksheet for Specific Noble Gas Releases (09-81) <
1.4 10 Estimated Ground Deposition Calculation Worksheet for a
Particulate Radionuclide Releases (09-81) 1.4 V
11 Summary of Radiological Dose Evaluation Calculations (09-81) 1.4 12 Unusual Event Incident Report Form (03-81) 2.1
! 13 Alert Incident Report Form (03-81) 3.3 14 Site Emrgency Incident Report Form (03-81) 4.3 15 General Emergency Incident Report Form (03-81) 5.3 16 Event Data Checklist (03-81) 5.3 17 List of Missing Personnel (03-81) 8.1 18 Assembly Area Roster (03-81) 8.1 19 Drill / Exercise Scennrio (03-81) 15.3 20 Drill / Observation Sheet (03-81) 15.3 21 Drill / Exercise Evaluation Report (03-81) 15.3 22 Plant and Company Emergency Call List (02-82) Call List Tab 23 Offsite Agency Emergency Call List (02-82) Call List Tab 24a Site Boundary Control Center Emergency Plan Inventory Checklist (01-82) 7.'.1 24b TSC, South Gate and OSC Emergency Plan Inventory Checklist (01-82) 7.4.1 24c Emergency Plan Health Physics Supplies at Two Rivers Community Hospital Inventory Checklist (09-81) 7.4.1 24d Control Room Emergency Plan Equipment Inventory Checklist (09-81) 7.4.1 24e Emergency Vehicle Inventory checklist (05-81) 7.4.1 24f Emergency Plan First Aid Kit Inventory Checklist (02-82) 7.4.1
! 24g Emergency Plan Burn Kit Inventory (02-82) 7.4.1
} 24h Emergency Plan First Aid Room Inventory (05-81) 7.4.1 24i Emergency Plan Stretcher Inventory (09-81)
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Page 2 EPIP EPIP Forms Title Procedure 25a Emergency Vehicle checklist (10-81) 7.4.2 25b Monthly Health Physics Instrument and Air Sainpler Functional Test Checklist-(02-82) 7.4.2 25c Quarterly Emergency Plan Checklist (01-82) 7.4.2 25d Semi-Annual and Annual Emergency Plan Checklist (07-81) 7.4.2 26 Quarterly' Communications Test (03-81) 14.1 27 Monthly Communications Test (03-81) 14.1 28 Emergency Plan Instrument Calibration Schedule (05-81) 7.4.2 29 Emergency Plan Counting Equipment and Frisker Calibration Schedule (07-81) 7.4.2 30 Reactor Coolant Post-Accident Sampling Analysis Report (09-81) 7.3.2 31 Containment Atmosphere Post-Accident Sampling Analysis Report (12-81) 7.3.3 32 Accounting Short Form (02-82) 8.1 O
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EPIP 1.5 l HINOR Revision 2 CI 02-26-82 PROTECTIVE ACTION EVALUATION 1.0 PURPOSE The purpose of this procedure is to provide a basic guide to determine protective action recommendations to be given to the public authorities and to provide a method to transmit these recommendations and other essential data for assessment to the appropriate public authorities.
2.0 REFERENCES
2.1 NUREG-0654, Revision 1, " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants," November, 1980.
2.2 NUREG-0654, Appendix 1, " Emergency Action Level Guidelines for Nuclear Power Plants."
! 3.0 PRECAUTIONS AND LIMITATIONS 3.1 Ask for the name and title of the person or agency being contacted prior to transmitting any information.
3.2 If unable to contact an individual or agency, continue with the transmissions to the other individuals or agencies and then attempt to contact the persons or agencies who have not been contacted.
3.3 All actions and recommendations shoeld be appropriately logged.
! 4.0 INITIAL CONDITIONS 4.1 Applicable portions of EPIP 1.2, " Plant Status," completed.
4.2 EPIP 1.3, " Estimation of Source Term," completed.
l 4.3 EPIP 1.4, " Radiological Dose Evaluation," completed.
4.4 Site Emergency or General Emergency has been declared.
5.0 PROCEDURE 1
l 5.1 Technical Support Manager
-~s 5.1.1 Obtain the completed attachments of EPIP 1.4, " Radiological
' Dose Evaluation," from the person completing them.
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t 4 1 EPIP 1.5 Page 2 x
5.1.2 Review the results of the dose projection calculations and deposition calculations for all affected areas.
5.1.3 Review Attachments 1.5-1 and 1.5-2.
5.1.4 Based on actual plant conditions, expected plant conditions in the future, weather conditions, local protection avail-able to the public, evacuation times and eny other constraints, determine the most appropriate Protective ,
Actions to reduce exposure to the public and relay the in-formation to the emergency support center.
5.2 Emergency Support Manager NOTE: THE FOLLOWING STEPS MUST BE DONE BY THE EMERGENCY SUPPORT MANAGER OR HIS DESIGNATED ALTERNATE. UNTIL HE ARRIVES IN THE EMERGENCY SUPPORT CENTER, THE SITE MANAGER IS ACTIFG AS EMERGENCY SUPPORT MANAGER.
5.2.1 Review the recommendation of the Technical Support Manager and/or Rad / Con Waste Manager.
5.2.2 Complete Section 2 (follow-up message) of the incident D, '
report form contained in the appropriate offsite agency notification procedure, (for example, if the incident is classified as a Site Emergency, then Section 2 of the Inci-dent Report Form of EPIP 4.3, " Site Emergency - Offsite Agency Notification," would be completed).
5.2.3 contact the NRC and the persor.s and agencies notified on NAWAS of the emergency and provide the information contained l in Section 2 of the incident report form to them.
i 5.2.4 For a General Emergency, form EPIP-16 in EPIP 5.3, " General l
Emergency - Offsite Agency Notification," shall be used as j the basis for followup messages to offsite technical per-sonnel such as NSSS vendor and corporate engineering staff.
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EPIP 1.5 Page 3 ATTACHMENT 1.5-1 Recommended protective actions to reduce whale body and thyroid dose from exposure to a gaseous plume Proiected Dose (Rem) to Individual in General Public Recommended Action ("} Comments Whole body <1 No planned protective actions.(b) Previously recommended or State may issue an advisory to seek protective actions may Thyroid <5 shelter and await further instructions. be reconsidered or terminated.
Whole body 1 to <5 Ceek shelter as a minimum. If constraints exist, special or Consider evacuation. Evacuate unless consideration should be given Thyroid 5 to <25 constraints make it impractical. for evacuation of children -
Monitor environmental radiation levels, and pregnant women. ;
Whole body 5 and above conduct mandatory evacuation. Seeking shelter would be an or Monitor environmental radiation levels alternative if evacuation Thyroid 25 and above and adjust area for mandatory evacuation were not immediately possible.
based on these levels.
Control access.
(a)These actions are recommended for planning purposes. Protective action decisions at the time of the incident must take into consideration existing conditions and the dangers associated with certain protective actions.
(b)At the time of the incident, officials may implement low-impact protective actions in keeping with the principle of maintaining radiatian exposure as low as reasonable achievable.
Reference:
Abstracted from EPA 520/1-75-001, " Manual of Protective Actions Guides and Protective Actions for Nuclear Incidents," Table 5.1 (Revised 6/79)
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EPIP 1.6 MINOR
(]* Revision 1 02-26-82 RADI0 IODINE BLOCKING AND THYROID EXPOSURE ACCOUNTING 1.0 GENERAL Potassium iodide, a stable iodine, may be used in the event of a plant emergency as a blocking agent to prevent the uptake of radioactive iodine 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 at 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."
3.0 PRECAUTIONS 3.1 Potassium iodide will only be administered 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 administered, 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.
l 4.0 STORAGE LOCATION l
l Single dose 300 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.
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Page 2 5.0 DOSE ADMINISTRATION 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 the particular individuals who may be exposed during any working period might exceed 0.9 Rem total dose commitment (equivalent to one maximum permissible body burden from I-131) due to radiciodine concentrations in breathing air.
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 radiciodine may be calculated as follows.
6.1.1 Total Dose Commitment, RADS /pCi, Inhaled Conversion Factors I-131 1.480 RADS /pCi (w
I-132 0.054 RADS /pCi I-133 0.400 RADS /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 concentration in pCi/cc by the breathing rate in ec/ hour by the total time of exposure in hours. The thyroid exposure in RADS is then calculated by multiplying the total amount in pCi by RADS /pCi in the above. table.
6.1.3 Breathing Rates
- a. Assume 1.25E06 cc/ hour (= 3.47E-043m /sec.) for short l 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 j above towards the t(tal gross iodine activity determinated.
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EPIP 1.6 Page 3 6.1.5 Examole Gross Iodine = 5.4E-07 pCi/cc in air Breathing Rate = 1.25E06 cc/ hour Expected Exposure Time = 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> I-131 RADS /pCi = 1.48 Calculation:
5.4E-07 pCi/cc X 1.25E06 cc/ hour X 1.48 RADS /pCi X 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
= 0.999 RADS Exposure to the Thyroid 6.2 Other Data Associated with Radioactive Iodine Exposures See Attachment 1.6-1.
7.0 DOSE ACCOUNTABILITY FOR EXPOSURES TO AIRBORNE RADI0 IODINE
\,_, 7.1 It is imperative that accurate exposure times and radioiodine concentrations encountered be maintained for each individual's exposure to an airborne radioiodine environment for dose calculation purposes.
7.2 The following rainimum 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 es posure.
7.2.4 Concentratior; of air. borne radioiodine.
7.2.5 Reference to specific analysis by sample number or manner in
( which concentration of airborne radioiodine was derived.
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ATTACHMENT 1.6-1 OTHER DATA ASSOCIATED WITH RADIOACTIVE IODINE EXPOSURES Soluable Iodines 131 132 133 134 135 i
MPC Air Occupational 9 x 10-9 pCi/cc 2 x 10-7 pCi/cc 3 x 10-8 pCi/cc 5 x 10-7 pCi/cc 1 x 10-7 pCi/cc
- MPC Air Gen. Public 1 x 10-19 pCi/cc 3 x 10-9 pCi/cc 4 x 10-10 pCi/cc 6 x 10-9 pCi/cc 1 x 10-9 pCi/cc Maximum Permissible Body Burden 0.7 pCi 0.3 pCi 0.3 pCi 0.2 pCi 0.3 pCi .
Average Energy 0.23 Mev 0.65 Mev 0.54 Mev ---
1.2 Mev 40 MPC-hr. Equiv. 0.324 pCi W.B. 7.200 pCi W.B. 1.080 pCi W.B. --- ---
l 520 MPC-hr. Equiv. 4.212 pCi W.B. 93.600 pCi W.B. 14.040 pCi W.B. --- ---
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% to Organ of Interest --- --- --- --- ---
Inhalation 23% 23% 23% 23% 23%
Ingestion 30% 30% 30% 30% 30%
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 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> 20.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 52.6 min. 6.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
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- Attachment 1.6-1, continued ... .
i Useful Equations:
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' Dose Rate - R = SIE qf (Q.F.) <
R = Dose rate to organ of interest, Rem / day I
q = Body burden, pCi l
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! m = Mass of the organ of reference, gm -
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E = Effective energy per disintegration, Mev/ dis i
f = Fraction of the radioactivity in body which is in organ of reference Q.F. = Quality factor, Rem / day Dose Commitment - DC (Acute Uptake) i DC = 74 E q T/m Units as described above.
4 T = Effective half life in days j !
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EPIP 1.6
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ATTACHMENT "A" 1 1
l This attachment is furnished for information only. The administration of potassium will be as stated in procedure EPIP 1.6. j l
Pettent Package Insert For HOW POTASSIUM IODIDE WORKS Certain forms of iodine help your thyroid gland work right. Most people get the iodine they need from foods, like iodized salt or fish. The thyroid can " store" or hold only a certain amount of THYRO BLOCK" iodine-In a radiation emergency, radioactive iodine may be released in (POTASSlUM IODIOE) the air. This material may be breathed or swallowed. It may (pronounced poe TASS +um EYE oh-dyed) enter the thyroid gland and damage it. The damage would pro-(abbreviated: KI) bably not show itself for years. Children are most likely to hava TABLETS and SOLUTION U.S P. thyroid damage.
If you take potassium iodide, it will fill-up your thyroid gland.
This reduces the cl.ance that harmful radioactive iodine will enter the thyroid gland.
TAKE POTASSIUM IODIDE ONLY WHEN PUBLIC IIEALTli OFFICIALS TELL YOU. IN A RADIATION WHO SHOULD NOT TAKE POTASSIUM IODIDE EMERGENCY, RADIOACTIVE IODINE COULD BE The only people who should not take potassium iodide are people RELEASED INTO THE AIR. POTASSIUM IODIDE (A who know they are allergic to iodide. You may take potassium FORM OF IODINE) CAN HELP PROTECT YOU. iodide even if you are taking medicines for a thyroid problem (for
- 18mple, a thyroid hormone or antithyroid drug). Pregnant and IF YOU ARE TOLD TO TAKE THIS MEDICINE.TAKE IT nuning we and h aM eMdan may awe % dw ONE TIME EVERY 24 HOURS. DO NOT TAKE IT MORE OFTEN. MORE WILL NOT HELP YOU AND MAY IN- HOW AND WHEN'TO TAKE POTASSIUM IODIDE CREASE Tile RISK OF SIDE EFFECTS. DO NOT TAKE Potassium Iodide should be taken as soon as possible atter THIS DRUG IF YOU KNOW YOU ARE ALLERGIC TO public health officials tell you. You should take one does every 24 IODIDE. (SEE SIDE EFFECTS BELOW.1 hours. More will not help you because the thyroid can " hold" on-ly limited amounts of lodine. Larger doses will increase the risk of side effecta. You will probably be told not to take the drug for more than 10 days.
\ INDICATIONS SIDE EFFECTS THYROID BLOCKING IN A RADIATION EMERGENCY Usually, eide effects of potassium iodide happen when people ONLY. take higher doses for a long time. You should be careful not to take more than the recommended dose or take it for longer than DIRECTIONS FOR USE you are told. Side effects are unlikely because of the low dose and Use only as directed by State or local public health authorities in the short time you will be takmg the drug.
the event of a radiation emergency. Possible side effects include skin rashes, swelling of tha salivary DOSE glands, and " iodism"(metallic taste, burmng mouth r.nd throat.
Tablets: 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 stomach upset and diarrhea).
day. Crush for smallchildren. A few people have an allergic reaction with more serious symp-BABIES UNDER 1 YEAR OF AGE: toms. These could be fever and joint pains, or swelling of parts of One half (1/2) tablet once a day. Crush the face and body and at times severe shortness of breath requir-II"L- ing immediate medical attention.
O O DER, d drops oo Taking iodide may rarely cause overactivity of the thyroid half glass of liquid and drink each day.
gland, underactivity of the thyroid gland, or enlargement of the thyroid gland (goiter).
BABIES UNDER 1 YEAR OF AGE:
( Add 3 drops to a small amount of liquid WHAT TO DO IF SIDE EFFECTS OCCUR If the side effects are severe or if you have an allergic reaction, for all dosage forms: Take fo 10 days unlesa directed otherwise 8 top takmg potassium iodide. Then, if possible, call a doctor or i
by State or local public health authorities.
t public health authority for instructions.
l 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 nozzle of the THYRO BLOCKW TABLETS (Potassium Iodide. U.S.P.) bot-l ties of 14 tablets (NDC 0037-0472-20.1 Each white, round, scored bottle.
tablet contains 130 mg potassium iodide.
WARNING THYRO-BLOCKm SOLUTION (Potassium Iodide Solution, Potassium iodide should not be used by people allergic to .sdide. U.S.P.) 30 ml(1 fl. oz.) light-resistant, measured-drop dispensing Keep out of the reach of children. In case of overdose or allergic units (NDC 0037-4287-25). Each drop contains 21 mg potassium reaction, contact a physician or the public health authority. iodih DESCRIPTION * "I d Each THYRO-BLOCKW TABLET contains 130 mg of potassium iodide- CARTER-WALLACE, INC.
Each drop of THYRO BLOCK" SOLUTION contains 21 mg of Cranbury, New Jersey 08512 potassium iodide.
CW-107915-10/79 Issue 10/79
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EPIP 2.3 HINOR Revision 1 v/ 02-26-82 UNUSUAL EVENT - OFFSITE 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), " Unusual Event Incident Report Form," Sections 1, 2 and 3 and/or on EPIP-23, "Offsite Agency Emergency Call List."
4.0 INITIAL CONDITIONS 4.1 Unusual Event emergency conditions exist.
4.2 This procedure should be initiated as soon as possible after the initial classification and must be initiated within one hour of the initial classification.
5.0 PROCEDURE 5.1 Designee 5.1.1 Complete Section 1 of the incident report form (form EPIP-12, attached) using the information given by the Shift Supervisor. Examples of emergency response include: shut the unit down, call in additional firefighters or secure doors against high winds.
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EPIP 2.3 l Page 2 '
s 5.1.2 Pick up the NRC Operations Center, Bethesda, dedicated line.
5.1.3 When a response is heard, read Section 1 of the incident report form.
5.1.4 If no response is received, contact the NRC Operations by i
telephone (telephone number listed on form EPIP-23, "Offsite Agency Emergency Call List") and repeat Step 5.1.3.
5.1.5 Make an appropriate entry into the NRC Operations Center, Bethesda, phone log.
5.1.6 Notify the Manitowoc County Dispatcher by telephone (telephone number listed on form EPIP-23. "Offsite Agency Emergency Call List"). Read Secton 1 of the incident report form and ensure that the information is fully understood.
5.1.7 Notify Kewaunee County Dispatcher by telephone (telephone number listed on form EPIP-23, "Offsite Agency Emergency Call List"). Read Section 1 of the Incident Report Form and ensure that the information is fully understood.
[O' 5.1.8 Notify the state of Wisconsin Division of Emergency Govern-1 ment by telephone (telephone number liste.d on form EPIP-23, "Offsite Agency Emergency Call List"). Read Section 1 of the Incident Report Form and ensure that the information is fully understood.
5.1.9 Attempt to contact the NRC resident inspector (telephone number listed on form EPIP-23, "Offsite Agency Emergency call List"). This courtesy notification is to inform him of the Unusual Event.
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EPIP 6.2
] MINOR Revision 1 02-26-82 ,
l PLANT EVACUATION ,
1 1.0 GENERAL This procedure describes the steps and instructions to be taken in the event of a plant evacuation.
1
2.0 REFERENCES
None
, 3.0 PRECAUTIONS AND LIMITATIONS 7 i
! 3.1 All actions and notifications should be appropriately logged.
3.2 A plant evacuation will probably not be necessary for an Unusual Event or Alert classification.
,- 3.3 Unless otherwise directed by supervisior., personnel should exit the L 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 1
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.
4.0 INITIAL CONDITIONS i
A plant evacuation will be considered when any of the following conditions exist.
4.1 Radiation levels in general areas of the protected area are in excess of 100 mr/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.
4.3 Other emergency conditions where it is deemed necessary to evacuate nonessential personnel from the plant.
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EPIP 6.2 Page 2 i
5.0 PROCEDURE 5.1 Shift Supervisor / Designee 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 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-mation Center Evacuation."
5.1.4 Sound the plant evacuation alarm and fishermen's pier evacu-ation alarm and announce over the P.A. System:
" ATTENTION ALL PERSONNEL, ATTENTION ALL PERSONNEL, THERE ARE CONDITIONS AT THE PLANT THAT WARRANT A PLANT EVACUATION.
( ALL PERSONNEL SHALL IMMEDIATELY ASSEMBLE IN THE FOLLOWING
, \ AREAS:
i PLANT PERSONNEL REPORT TO WITH ASSIGNED EMERGENCY EMERGENCY DUTIES LOCATIONS PLANT PERSONNEL REPORT TO NOT ASSIGNED EL. 18.5' 0F EMERGENCY DUTIES THE TECHNICAL 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.
5.1.7 Initiate EPIP 7.0, "CHP Radiological Response and Prepared-a ness," if not already done.
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EPIP 6.2 i Page 3 i -
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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 ;
j areas at the plant.
i l 5.1.9 Contact the Township of Two Creeks and request them to make
] the Two Creeks Towr. Hall available for an assembly area for
- plant personnel by calling 755-2049 or 755-4196.
NOTE: (Telephone numbers are applicable 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day.) l l
5.2 Visitors and Contractors
- i j 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 i 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 i 4
Physics Director will determine what personnel monitoring will be required. After the Health Physics Director is satisfied with con-i ~ I, tamination levels, the dosimeters and TLD's will be collected prior to release.
5.3 Personnel Not Assigned Emergency Duties f i
- 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 i
building.
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. i EPIP 7.4.3.1 HINOR ,
s Revision 0 02-26-82 i
USE OF CANBERRA MODEL 3100 SERIES 30 MULTICHANNEL ANALYZER TO DETERMINE AIRBORNE IODINE ACTIVITIES 1
1 1.0 GENERAL The Series 30 MCA may be operated in several modes. This procedure ad-dresses the use of the Series 30 MCA with an NaI detector for the purpose of analyzing radioactive iodine in charcoal and silver zeolite filters when the plant is in a condition requiring use of the Emergency Plan.
2.0 REFERENCES
2.1 Canberra Series 30 MCA Operating Manual i
2.2 Canberra Model 3100-01 High Voltage Power Supply Operating Manual 3.0 SYSTEM COMPONENTS AND CONNECTIONS 3.1 Components r
3.1.1 Series 30 MCA 3.1.2 Nuclear 400 Pre-Amp 3.1.3 Packard NaI Detector l
3.1.4 Model 3100-01 High Voltage Power Supply Hodule .
3.2 System Assembly 3.2.1 Series 30 MCA and Model 3100-01 High Voltage Power Supply l
l a. Ensure power switch is in the off position and the high
! voltage power supply switch is in the off position.
l b. Connect the Series 30 MCA power cord to the 115 V AC 60 Hz electrical outlet.
3.2.2 Nuclear 400 Pre-Amp
- a. Connect the high voltage output from the Model 3100-01 high voltage power supply (SHV connector) to the high voltage connection on the Pre-amp using a cable with SHV and MHV connections.
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0 EPIP 7.4.3.1 Page 2 C\ b. Connect the output from the Pre-amp to the front of the Series 30 MCA at the SIGNAL connector. Use a cable with a BNC connector on each end.
3.2.3 Packard NaI Detector Connect the detector output to the input of the Nuclear 400 1 Pre-Amp.
I 4.0 MCA SERIES 30 SETUP FOR USE 4.1 Set the Model 3100-01 high voltage power supply at 1300 V DC. Turn on the high voltage power supply switch.
f 4.2 Position the Following Controls or Switches as Indicated 4.2.1 ADC GAIN to 512 4.2.2 ADC OFFSET to 0 4.2.3 LLD to 0.3 4.2.4 ULD to MAXIMUM 4.2.5 INPUT LEVEL to LOW 4.2.6 PRESET to TL, set for 10,000 second count time (1.4) 4.2.7 MEMORY to 1/2 4.2.8 ACQ to PHA, Add.
4.2.9 I/O to Out, Ext.
4.2.10 EXPAND to 0FF 4.2.11 ROI ENTER to 0FF j 4.3 Turn power switch on.
l l 4.4 Move CLEAR DATA, TIME switch to CLEAR DATA position.
4.5 Move ROI CLEAR switch to the CLEAR ALL position.
5.0 ENERGY CALIBRATION A Co-60 and Cs-137 rod source should be used to determine the relationship between channel number and photopeak energy. The maximum number of channels
. available is 512. Assuming a 0-2048 kev range, this becomes 4 kev per channel. A properly calibrated system would then store the upper Co-60
- (133? kev) photopeak in channel 332 (1332 kev /4 kev per channel = 333) and I
the Js-137 (662 kev) photopeak in channel 165 (662 kev /4 kev per channel =
l 165).
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M EPIP 7.4.3.1
/ Page 3 h
l 5.1 Place the cursor in channel 333 with the SCAN paddle. The cursor location will be displayed in the upper left corner of the CRT as CL 333.
5.2 Place the co-60 and Cs-137 rod sources in a clean plastic bag and insert them into the NaI detector well.
5.3 Set the VERTICAL switch to the 103 .
5.4 Depress the COLLECT pushbutton to start data acquisition (red light on).
5.5 Adjust the AMP GAIN control until the upper Co-60 photopeak centroid coincides with the cursor. Normal setting of the AMP GAIN is
. 9.0 - 9.5.
NOTE: REPEATED OPERATION OF THE CLEAR DATA WHILE MAKING ADJUST-MENTS WILL SIMPLIFY THE PROCESS. CLOCKWISE ROTATION OF THE AMP GAIN AND ADC ZERO CONTROLS MOVES THE PEAK CENTROID TO
! THE RIGHT; COUNTER-CLOCKWISE ROTATION HOVES IT TO THE LEFT.
5.6 When the upper peak is centered, place the cursor at channel 165.
I 5.7 Adjust the ADC ZERO control until the Cs-137 peak centroid coincides f ~'s
\v) with the cursor.
5.8 Recheck the upper co-60 peak centroid and readjust the AMP GAIN as
, necessary.
5.9 When all adjustments are correct, lock the AMP GAIN control.
5.10 Depress the COLLECT pushbutton to stop data acquisition (red light out). Return the Co-60 and Cs-137 rod sources to storage.
6.0 BACKGROUND
COLLECTION 6.1 3et the MEMORY to 2/2.
6.2 Set a count time of 1000 seconds (1,3) and place the PRESET to the TL position.
6.3 Place clear data toggla switch to CLEAR DATA position to clear the CRT.
6.4 Depress the COLLECT pushbutton.
6.5 At the end of the data collection, the background for the entire spectrum will be stored in the second half of the MEMORY (2/2) for l later use.
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EPIP 7.4.3.1 Page 4
. s 7.0 SAMPLE COUNTING AND DATA COLLECTION 7.1 Set the MEMORY to 1/2.
7.2 Set a cennt time of 1000 seconds and place the PRESET to the TL position.
i I
7.3 Place the sample to be counted in a plastic bag and place it on the detector in the proper geometry.
7.4 Clear data by depressing CLEAR DATA switch and ROI CLEAR ALL.
7.5 Depress the COLLECT pushbutton (red light on).
P 7.6 After the count has been completed (red light out), scan the display for peaks using the SCAN paddle to move the cursor. Iodine peaks may j be found at the following channel numbers (CL):
^
ISOTOPE CHANNEL NUMBER ENERGY kev i I-131 91 364.5 I-132 193 772.7 I-133 132 529.9
- I-134 212 847.04 I-135 315 1260.5 7.7 The beginning a!.d end of each Iodine photopeak must be identified and noted. Place the cursor at the desired peak and place the EXPAND toggle switch to ON. Use the cursor location (CL) and cursor channel (CC) information displayed on the CRT to assist in location of the i
beginning and end of each peak. The beginning of the photopeak is the channel where the counts begin to rise toward the peak.
EXAMPLE t
Channel No. 145 146 147 148 149 150 151 Counts 371 363 345 387 413 630 790 Start of the peak is channel No. 147.
i To find the end of the photopeak, move the cursor to the end of the
! peak while remaining in the EXPAND position. .The end of the photopeak is the channel where the counts stop decreasing and start to rise again.
EXAMPLE Channel No. 176 177 178 179 180 181 182 183 184 Counts 490 383 362 335 324 360 369 308 345
\
End of the peak is channel No. 180.
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i EPIP 7.4.3.1
, Page 5 7.8 Return to beginning of the peak and place the ROI toggle switch to i
the ON position.
7.9 With the SCAN paddle, move the cursor to the end of the peak. This action will " paint" the peak and integrate this area. The total number of counts in the integrated area is the number located at the top far right corner of the CRT. Turn the ROI to off before moving to the next peak. Use the ROI CLEAR ALL or ONE as necessary to clear errors, j NOTE: THE ROI " CLEAR ONE" WILL CLEAR EVERYTHING TO THE RIGHT OF j THE CURSOR, UP TO THE NEXT ROI DISPLAYED ON THE CRT. THE l
ROI " CLEAR ALL" WILL CLEAR EVERYTHING DISPLAYED ON THE CRT WHEN IN THE EXPAND "0N" MODE AND EVERYTHING ON THE ENTIRE SPECTRUM WITH THE EXPAND IN THE "0FF" POSITION.
7.10 Repeat as necessary to integrate each peak. Record the following information for each Iodine peak,
- a. Start Channel
- b. Stop channel
~
- c. Counts in Start Channel s_- d. Counts in Stop Channel
- e. Total Integrated Counts 7.11 Add the counts in the start and stop channels (7.10c and 7.10d) 7.12 Divide the total in 7.11 by 2 to obtain average Compton counts.
7.13 Multiply the total in 7.12 by the number of channels between the start and stop channels (7.10b - 7.10a + 1) to obtain total compton counts.
7.14 Subtract the number obtained in 7.13 from the total integrated counts (7.10e). This will subtract the Comptons counts and background counts from the total sample counts and give you total net sample counts.
NOTE: IF THERE ARE IODINE PEAKS IN THE BACKGROUND, COMPLETE SECTION 7.10 - 7.14 CALCULATIONS FOR THE SAME CHANNELS FOR THE BACKGROUND DATA GTORED IN MEMORY 2/2. SUBTRACT THESE NET BACKGROUND PEAK COUNTS FROM THE TOTAL NET SAMPLE COUNTS, IN STEP 7.14, TO GET THE CORRECTED TOTAL NET SAMPLE COUNTS.
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EPIP 7.4.3.1 Page 6 i
7.15 EXAMPLE Compton Subtraction Calculation
- a. Start Channel 149 l i
- b. Stop Channel 182
- c. Counts in Start Channel 822
- d. Counts in Stop Channel 621
- e. Total Integrated Counted 74,413 Add (c) and (d): 822 + 621 = 1,443 counts Divide (c) + (d) by 2: 1,443/2 = 722 counts Multiply 722 counts by the number of channels between 149 and 182 to obtain total Compton counts.
- (182 - 149 + 1) = 34 channels
- 722 x 34 = 24,548 counts Subtract total Compton counts from total sample integrated counts 74,413 - 24,548 = 49,865 sample peak counts.
Background Subtraction Calculation (to be used only if there is signi-ficant Iodine peaks in the background)
- a. Start Channel 149
- b. Stop Channel 182
- c. Counts in Start Channel 87
- d. Counts in Stop Channel 90
- e. Total Integrated Background Peak Counts 8,540 Add (c) and (d): 87 + 90 = 177 counts Divide (c) + (d) by 2: 177/2 = 88 counts (average background Compton)
Multiply 88 by the number of channels between 149 and 182 (182 - 149 + 1) = 34 channels: 88 x 34 = 2,992 counts (total bkg Compton)
Subract total background Compton counts from total integrated back-ground peak counts.
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EPIP 7.4.3.1 Page 7 i
, j 8,540 - 2,992 = 5,548 net background peak counts.
i Subtract net background peak counts from sample peak counts 49,865 counts - 5,548 counts = 44,317 corrected total net sample counts.
8.0 SAMPLE ACTIVITY CALCULATIONS 8.1 Use the following formula to calculate the activity for each peak (isotope). ,
4 Activity _
~
(Total Net Counts)(60 sec/ min)(Decay Factor) pCi (Count Time sec.)(Yield)(Eff.)(2.22 E 6 dpm/pC1)
Where: Decay. Factor = e (t)
Yield = Fraction of gamma rays per disintegration at i
primary peak energy.
1 Eff. = Efficiency at primary peak energy.
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EPIP 7.4.3.1
, Page 8 TABLE 1 EFFICIENCIES AND YIELDS FOR PACKARD NaI DETECTOR AND CANBERRA SERIES 30 MULTICHANNEL ANALYZER MSA CHARCOAL Isotope Energy (kev) % Efficiency Yield Half-Life (min)
I-131 365 8.8 .812 11,592 I-132 773 4.6 .762 138 I-133 530 6.45 .873 1,248 I-134 847 4.18 .954 52.6
- I-135 1,260 2.60 .286 396.6
! SCOTT CHARC0AL (In plant geometry)
Isotope Energy (kev) % Efficiency Yield Half-Life (min)
I-131 365 9.4 .812 11,592 I-132 773 4.85 .762 138 I-133 530 7.0 .873 1,248 p
f I-134 847- 4.35 .954 52.6 I-135 1,260 2.62 .286 396.6 SCOTT CHARCOAL (Environmental geomet.ry) and SILVER ZEOLITE Isotope Energy (kev) % Efficiency Yield Half-Life (min)
I-131 365 11.5 .012' 11,592 I-132 773 5.8 .752 138 I-133 530 8.6 .873 1,248 I-134 847 5.2 .954 52.6 I-135 1,260 3.1 .286 396.6 x
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.- - - - _ = . . -_ _ . _ - _ .. .. __ .-- . . --.
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EPIP 7.4.3.1 Page 9 8.2 Example
8.2.1 Given
, a. Total net counts in peak whose centroid is at channel i
133 (530 kev) is 15,000 counts.
- b. Coun" time was 1,000 seconds.
- c. Time since collection to count time was 20 minutes, j d. Sample was a MSA charcoal.
1
8.2.2 Solution
I
- a. Peak is identified as I-133 (530 kev primary peak)
- b. Half-life of I-133 is 1,248 minutes.
- c. Efficiency for MSA charcoal for I-133 is 6.5%.
- d. Yield is .873 for I-133.
- e. Completing the formula from Step 8.1:
i (15,000 cts)(60 sec/ min) [e .6 3 l = 7.22E-3 pCi Activity = 28m pCi (1000 sec)(.873)(.065)(2.22 E 6 dpm/pCi)
. 8.3 Determine the concentration in air (pci/cc) by dividing the activity (pci/ filter) by the volume of air that passed through the filter. E.g.,
l 7.22E-3 pCi/ filter with a volume of 2.85 E7 cc through the filter:
! = 2.53 E-10 pCi/cc I-133 in air.
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A EPIP 11.1 m MINOR
\ Revision 2 02-26-81 ON-SITE FIRST AID ASSISTANCE
1.0 INTRODUCTION
AND PURPOSE 1.1 General Industrial Safety and First' Aid Practices General industrial safety and first aid practices adopted for use in conventional plants are in effect at Point Beach Nuclear Plant.
Since personal injuries or emergencies may or may not involve radio-activity, the possibility of radioactive contamination of an injured person is addressed throughout this procedure.
1.2 First Aid The Point Beach organization includes persons experienced in first aid procedures who will be called in the event of injury. The plant is provided with an emergency shower for use with a severely contami-nated but less severely injured person, and a complete first aid room
[ s\ equipped with facilities and medical instruments suitable for physical examinations. On-site first aid facilities are further described in Section 4.0 of this procedure.
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 Flant. Since the possibility exists that treatment and transportation of a patient may be complicated by radioactive contami-nation, a fully equipped controlled access treatment room (the nuclear fAcst aid room) has been provided at Two Rivers Community Hospital, Two Rivers, Wisconsin. A list of radiation and contami-nation control materials in the treatment room is given in EPIP 11.3.
1.4 Emergency Vehicle An emergency vehicle is available at all times and contains emergency first aid and oxygen breathing equipment (described in Section 4.0).
This vehicle is normally parked in the extension building garage. In addition, arrangements have been made for backup assistance by the City of Two Rivers Fire Department emergency vehicle in case of multiple need. This backup ambulance planning is described in EPIP 11.3.
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EPIP 11.1 m Page 2
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l 1.5 Plant Personnel Responsibility It is the responsibility of involved plant personnel to become familiar with this procedure and specifically with instructions with regard to their individual actions required.
1.6 Telephone contacts Telephone contacts required by this procedure can be found in Attachment 11.1-1.
2.0 REFERENCES
2.1 PBNP 8.8, " Injuries, Accident Reporting, and Industrial Safety."
2.2 MeS 76-02, " 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."
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 i
l An injury which may or may not require professional medical attention and does not involve lost time.
3.3 Disabling Injury An injury which requires professional medical attention and involves l lost time, but would not be e life threatening injury.
3.4 Serious Injury An injury which requires professional medical attention and could j result in a fatality or permanent disability.
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EPIP 11.1 '
Page 3 3.5 Personal Injury Report, Form 1024 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 The Wisconsin Electric report used to report every accident involving Company-owned vehicles or a privately owned car used on company business.
I 3.8 Physician's Release to Return to Work, Form No. 2-65 The Wisconsin Electric report which must be filled out by the' doctor who treated the injured person.
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.
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, 4.b 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 Rcom Location 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.
i 4.2.1 Responsibility
[ T The Company Medical Director is responsible for determining
\s_,/ the equipment for the first aid room. The Point Beach Industrial Safety coordinator is responsible for maintaining the supply inventory.
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.
4.3.1 Responsibility Specifying emergency vehicle equipment is the responsibility of the Company Medical Director. Maintenance of equipment and supplies is the responsibility of the Point Beach Indus-l trial Safety Coordinator.
4.4 Other On-Site First Aid Provisions l
! Most first aid supplies are located on the uncontaminated or " clean"
! side of the plant. If, for emergency reasons, it is necessary to l 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
'N) the following locations:
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EPIP 11.1 Page 5 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.
1
- 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.
4.4.3 Switchyard
- a. First aid kit 4
- b. Burn kit
\
4.4.4 Unit I and Unit 2 Facades
- a. Stretcher, first aid kit, and burn kit; located on 66' level outside each containment's personnel hatch.
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
- b. Burn kit
- c. Scoop stretcher
- d. Oxygen breathing unit j 4.4.7 Technical Support Center
- a. First aid kit
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/ h b. Burn kit m -'ve-- m. m + y i.--- , .4 ,,.% - g.,., .-..- _. - .--,-w w. - -.- -s.. -
, e--
6 EPIP 11.1 Page 6 4.5 General Administrative Responsibilities in Case of Injury (see EPIP 11.2 for procedures) 4.5.1 Employee Responsibilities
- a. Personal Injury and/or Disabling Injury
- 1. Report injury to supervisor and first aid repre-sentative. <
- 2. Prepare " Personal Injury Report." If unable to prepare due to nature or extent of injuries, this report will be prepared by a person on behalf of the injured employee.
- 3. Insure that the attending physician receives a
" Physician's Release for Return to Work" to complete.
If unable to do so due to extent of injuries, this form will be transmitted by a person on behalf of the injured employee. A supply of these forms is available in the emergency vehicle.
' 'g b. , Vehicle Accident s- / 1. Report all vehicle accidents promptly to supervisor.
- 2. Prepare " Motor Vehicle Accident Report." If unable to prepare due to the extent of personal injury, this report will be prepared by a person on behalf of the injured employee.
4 4.5.2 Employee's Supervisor's Responsibilities
- a. Personal Injury and/or Disabling Injury
- 1. Receive, review for completeness, and sign the
" Personal Injury Report."
- 2. Indicate safety rule violation, if any, on the
" Personal Injury Report."
- 3. Investigate personal injuries that do not result in lost time and make preliminary recommendations on the " Personal Injury Report" for corrective measures which could prevent recurrence of the accident.
- 4. Submit the " Personal Injury Report" to the Point
~s Beach Industrial Safety Coordinator promptly, but not to exceed eight working hours after the accident has occurred.
EPIP 11.1
, Page 7
- 5. A serious injury or fatality is an " unusual event" and must be reported to the NRC within one hour (EPIP 1.1). A fatality must also be reported to the Point Beach Industrial Safety coordinator. If the 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 hsurs (see Attachment 11.1-1 for telephone number).
- 6. 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. Receive, review for completeness and sign the " Motor Vehicle Accident Report.d
- 2. Indicate appropriate comments and recommendations on the " Motor vehicle Accident Report."
' , , 3. Submit the " Motor Vehicle Accident Report" to the Point Beach Industrial Safety Coordinator promptly, but not to exceed eight working hours-after the accident has occurred.
4.5.3 Injured Employee's Group Head's Responsibilities
- a. Report vehicle accidents that are major or serious in nature or result in lost time personal injury to the Accident Investigation Committee Chairman,
- b. Report personal injuries that result in lost time or death and near miss experiences which could have re-sulted in serious injury to the Accident Investigation Committee Chairman or the acting Committee Chairman.
- c. Report all lost time (disabling) injuries to the Accident Prevention Department, Milwaukee Public Service Building (see Attachment 11.1-1). This will require reporting of the initial day lost and the day the employee returned to work.
- d. Request medical followup, if needed, from the Company Medical Director (see Attachment 11.1-1).
(' e. Establish sufficient liaison with the injured to maintain an up to-date knowledge of his medical status.
- f. Determine any special needs of the injured man's family and advise the Manager - Nuclear Operations.
1 EPIP 11.1 Page 8
)
ATTACHMENT 11.1-1 MEDICAL ASSISTANCE CALL LIST PBNP Personnel Plant Ext. Home G. A. Reed, Manager - Nuclear Operations P. J. Skramstad, Superintendent - Chemistry &
Health Physics R. 5. Bredvad, Health Physicist J. V. Moniot, Industrial Safety Coordinator Health Physics Duty & Call " Beeper" ---
Chemistry Duty & Call " Beeper" ---
Hospital Assistance I
Emergency Vehicle, Two Rivers Fire Department .
Community Hospital, Two Rivers Doctors' Clinic, Ltd., Two Rivers 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 j
)
Dr. E. Huston, Medical Director Accident Prevention Department {
State of Wisconsin
) Department of Industry, Labor and Human Relations, Safety and Buildings Division, Boiler Section
2 . .
) PLANT AND COMPANY EMERGENCY CALL LIST PBNP PLANT PERSONNEL:
- 1. Duty & Call Superintendents Name Plant Ext. Home Phone Time Notified G. A. Reed, Manager - Nuclear Operations J. J. Zach, General Superintendent R. E. Link, Supt. - Eng., Quality & Regulatory T. J. Koehler, Superintendent - Operations i Duty & Call Beeper No.
- 2. Shift Supervisors Name Plant Ext. Home Phone Time Notified L. J. Kamyszek .,
\
I R. D. Mitchell l 1
I. L. Bleeker l C. M. Gray l
E. Ziller j R. J. Mulheron
- 3. Chemistry Name Plant Ext. Home Phone Time Notified P. J. Skramstad, Superintendent - Chemistry j
& Health Physics T. L. Slack, Nuclear Plant Specialist -
Chemistry R. A. Neustadter, Nuclear Plant Specialist - ,
j Chemistry j T. L. Fredrichs, Nuclear Plant Engineer -
g Radwaste
) _ _ . __- . i EPIP-22 Page 1 of 4 (02-82)
e ,
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) 4. Health Physics Name Plant Ext. Home Phone Time Notified P. Skramstad, Superintendent - Chemistry &
Health Physics i R. S. Bredvad, Health Physicist L. E. Epstein, Health Physics Supervisor i f
C. D. Bolle, Health Physics Supervisor i
M. D. Moseman, Nuclear Plant Specialist -
Health Physics J. V. Moniot, Nuclear Plant Specialist -
Health Physics E. J. Manos, Nuclear Plant Specialist -
Health Physics
- 5. Instrument & Control
'~
Name Plant Ext. Home Phone Time Notified
~
~
J. C. Reisenbuechler, I & C Engineer A. J. Pohl, Nuclear Plant Engineer E. A. LeClair, I & C Supervisor
- 6. Maintenance -
Name Plant Ext. Home Phone Time Notified W. J. Herrman, Superintendent - Maint.
& Constr.
}
i D. A. Magyar, Maintenance Supervisor M. E. Crouch, Maintenance Supervisor R. O. Gerroll, Maintenance Supervisor J. O. Schoenberger, Maintenance Supervisor-t G. Bernhoft, Nuclear Plant Engineer T. R. Branam, Nuclear Plant Engineer EPIP-22 Page 2 of 4 (02-82)
n
~
)7. Reactor Engineering ~ ~ ~ ~ ~ '
R. L. Harris, Reactor Engineet ;
N. L. Pitterle, Nuclear Plant Fngineer
\
- 8. Plant Administration and Security \_
Name Plant Ext. Home Phone Time Notified i
G. A. Reed, Manager - Nuclear Operations l J. J. Zach, General Superintendent
, R. Krukowski, Security Supervisor J. D. Mielke, Supv. - Administrative Services ',
F. A. Zeman, Supervisor - Staff Services
- 9. Fire Brigade Members i Note: Refer to PBNP Fire Protection Manual Call List, Section FEP 2.0.
WEPCO COMPANY PERSONNEL: .
l
- 1. Company Administraton and Departments '
Name Company Ext. Home Phone Time Notified C. W. Fay, Assistant Vice President '
Duty Emergency Support Manager Wisconsin Electric Power Company /
Medical Department Nuclear Engineering Section Office Communications Department WE Accident Prevention 1
I EPIP-22 Page 3 of 4 (02-82) 1
N
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' 2. Nuclear Engineering Section Personnel Name Company Ext. Home Phone Time Notified D. K. Porter i
\
R. A. Newton i 2
l G. D. Frieling I E. J. Lipke S. A. Schellin C. W. Krause .
~~
- 3. Insurance Personnel --
~
Name Company Ext. Home Phone Time Notified W. J. Dundas, Supt, Insurance & >
Claims Div.
W. E. Staum, Alternate 1
l J. G. Remmel, Alternate .'
i
\
)
EPIP-22 Page 4 of 4 (02-82)
N OFFSITE AGENCY EMERGENCY CALL LIST FEDERAL AGENCIES:
- 1. United States Nuclear Regulatory Commission Telephone Person Time N"re Frequency Number Notified Notified Initials NRC Operations All hours Red Phone C nter or 1-301/492-8111 NRC Office of All hours 1!312/932-2500 ,
Inspection and (Ask for Enforcement, Duty Officer)
R2gion III NRC Resident Inspectors: Plant Ext. Home
- c. W. G. Guldemond 294 ,
- b. R. L. Hague 194
- 2. Uniteo States Department of Energy
) Telephone Person Time une Frequency Number Notified Notified Initials Chicago operations Weekdays Center, Region V (8AM-5PM)
(Rrdiological '
Assistance Team) All other i hours ..
- 3. United Stat.cs Coast Guard Telephone Person Time Nrme Frequency Number Notified Notified Initials USCG, Sturgeon- All hours Bay USCG, Two All hours Rivers
)
EPIP-23 Page 1 of 4 (02-82)
.' ATE AGENCIES:
- 1. State of Wisconsin Telephone Person Time Nrme Frequency Number Notified Notified Initials Wisconsin Dept. of Weekdays H2alth and Social (9AM-SPM)
Sarvices, Section of Radiation Pro-tection Liwrence J. McDonnell, Home.. phone _ _ _..
Chief Section of Radiation Protection Wisconsin Division All hours ~
of Emergency or NAWAS G:vernment Wisconsin State All hours Patrol or NA'WAS' IUNTY AGENCIES:
- 1. Manitowoc County Telephone Person Time Name Frequency Number Notified Notified Initials Minitowoc County All hours Shsriff, County or NAWAS Traffic
- 2. Kewaunee County Telephone Person Time Name Frequency Number Notified Notified Initials Ktwaunee County All Hours _ _ , _ , , , ,
Dispatcher or NAWAS PRIVATE AGENCIES:
Telephone Person Time Ntme Frequency Number Notified Notified Initials Kswaunee Nuclear All hours j
"ower Plant ._'
)
EPIP-23 Page 2 of 4 (02-82)
w
.IIVATE AGENCIES: (Cont'd)
Telephone Person Time Name Frequency Number Notified Notified Initials Institute of All hours Nuclear Power >
Operations f
American Nuclear i Insurers All hours Westinghouse Electric Corp. I Field Serv. Mgr. Office :
(R. Grimm) Home '
Hot Line
- Stone & Webster All hours !
Engineering Corp. l.
Bachtel Power All hours I Corporation '
IRE AND MEDICAL AGENCIES
- 1. Fire Emergency Telephone Person Time Name Frequency Number Notified Notified Initials Two Creeks Fire All hours Dzpartment (Emergency line)
- 2. Medical Assistance Telephone Person Time Name Frequency Number Notified Notified Initials Doctors Clinic, Ltd. \
S. Lawrence Kaner, M.D. \
Stephen L. Weld, M.D.
University Hos-pital, Madison Emergency Room All hours
, l Frank C. Larson, M.D. I Robert F. Schilling, M.D.
'cbert R. Radtke, Ph.D.
}HealthPhysicist)
EPIP-23 Page 3 of 4 (02-82)
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- N IRE AND MEDICAL AGENCIES: (Cont'd)
Telephone Person Time Nrme Frequency Number Notified' Notified Initials Two Rivers All hours
' i Emergency Vchicle l Community Hos- All hours pital, Two Rivers
~~
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. I EPIP-23 Page 4 of 4 (02-82)
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! MONTHLY HEALTH PHYSICS INSTRUMENT AND AIR SAMPLER FUNCTIONAL TEST CHECKLIST
Reference:
EPIP 7.5.1 - Routine check, Maintenance, Calibration and Inventory Schedule of Health Physics Emergency Plan Equipment EPIP 7.5.2 - Emergency Plan Equipment Routine Checks, Maintenance and Calibration Instructions SITE BOUNDARY CONTROL CENTER INSTRUMENTATION Checi; - Source Item Type of Serial Source Check No. Equipment Number Used Criteria Results
- 1. Thyac III Installed cpm cpm
- 2. GSM-5 S-23 cpm __ cpm
- 3. RM-3C S-23 cpm cpm I
- 4. PIC-6A Cs-ll mR/hr mR/hr
() 5. PIC-6A _
Cs-ll mR/hr mR/hr
- 6. PIC-6A Cs-ll mR/hr mR/hr
- 7. PIC-6A Cs-11 mR/hr mR/hr
- 8. Radector III Cs-11 mR/hr mR/hr
- 9. HPI-1010 Cs-11 mR/hr mR/hr
- 10. Nuclear Chicago S-23 cpm cpm AIR SAMPLERS Item Satisfactory No. g Functional Test NOTE: SOURCE CHECK CRITERIA
- 1. High Volume TO BE ENTERED FROM CURRENT CALIBRATION STICKER ON EACH
- 2. Gasoline Powered UNIT. RESULTS MUST BE WITHIN 120% OF THIS VALUE.
- 3. Battery (12 V DC)
O EPIP-25b Page 1 of 4 (02-82)
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9 OPERATIONS SUPPORT CENTER 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
- 4. AMS-2 (cart-mounted)
Check Source Check Source Criteria Criteria
- a. AMS-2 cpm cpm
- b. RM-14 cpm cpm l Use check source CS-6.
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i I EPIP-25b Page 2 of 4
! (02-82) 1 .n _ . - - . -. - . _ . . - -
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INSTRUMENTATION Check Check Item Type of Serial check Source Source No. Equipment 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
SOUTH GATE
[
INSTRUMENTATION Check Source Item Type of Serial Source Check No. Equipment Number Used Criteria Results
- 1. VAMP Monitor Cs-6 mR/hr mR/hr AIR SAMPLERS Item Type of Satisfactory No. Equipment Functional Test
- 1. Low Volume CONTROL ROOM INSTRUMENTATION Check Source Item Type of Serial Source Check No. Equipment Number Used Criteria Results
- 1. Radector III Cs-3 mR/hr mR/hr V
EPIP-25b Page 3 of 4 (02-82)
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FIRST AID ROOM
~
INSTRUMENTATION Check Source Item Type of Serial Source Check No. Equipment Number Used Criteria Results
- 1. Thyac III Internal cpm cpm EMERGENCY VEHICLE s.
INSTRUMENTATION Item No. Equipment Number Used Criteria Results
- 1. Thyac III Internal cpm cpm
- 2. Thyac III Internal cpm -cpm
- 3. Mini-Rad Cs-3 mR/hr mR/hr V
- 4. Mini-Rad Cs-3 mR/hr mR/hr checked By Date Reviewed By Date Health Physics Supervisor EPIP-25b Page 4 of 4 (02-82)
f X ACCO SHORT FORM (' ')
\
) !
/
- Accounted Name & Search & '.
For Badge of Last Rescue Found >
Group Yes No Missing Location Sent (Time)
Operations Duty Shift (including Duty ,
Technical Advisors)
Chemistry & Health Physics Operations Support Center (Mustering Area)
Maintenance & Construction S
~
Operations Relief Crew .
Administrative & Engineering -
Quality & Regulatory Services Technical Services (Reactor Engineering, I&C, Training)
Nuclear Regulatory Commission Technical Support Center EPIP-32 (02-82)