ML20054E823
| ML20054E823 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 05/28/1982 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20054E819 | List: |
| References | |
| PROC-820528-01, NUDOCS 8206140291 | |
| Download: ML20054E823 (35) | |
Text
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05-28-82
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. TABLE OF CONTEN"3 Revision Date 1.0 CLASSIFICATION & ASSESSMENT
.1.1 Initial Classification 2
04-30-82 1.2 Plant Status 0
03-31-81 1.3 Estimation of Source Term...
1 04-30-82 1.4 Radiological Dose Evaluation 5
05-28-82 1.5 Protective Action Evaluation 3
04-30-82 1.6 Radiciodine Blocking & Thyroid Exposure Accounting 1
02-26-82 1.7 Evaluation of Core Damage.
0 04-30-82 1.8 Emergency Off-Site Dose Estimations 1
05-28-82 2.0 UNUSUAL EVENT 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 3.0 ALERT IMPLEMENTING PROCEDURES 3.1 Alert - Immediate Actions..
0 03-31-81 3.2 Alert - Plant & Company Personnel l
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 & Company Personnel Notification 1
07-01<01 4.3 Site Emergency - Off-Site Agency Notification 0
03-31-81 5.0 GENERAL EMERGENCY - IMPLEMENTING PROCEDURES 5.1 General Emergency - Immediate Actions.
0 03-31-81 5.2 General Emergency - Plant & 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 1
04-30-82 6.2 Plant Evacuation 1
02-26-82 6.3 Exclusion Area Evacuation..........
0 03-31-81 6.4 Energy Information Center Evacuation
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0 03-31-81 8206140291 820608 PDR ADOCK 05000266 F
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Page 3 i
Revision Date 7.4.3.1 Use of Canberra Model 3100 Series 30
!!aitichannel Analyzer to Determine Airborne Iodine Activities 0
02-26-82
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7.4.4 AMS-2 Air Particulate, Iodine &
Noble Gas Sampler / Detector....
0 03-31-81 8.1 Personnel Assembly & Accountability.
2 04-30-82 9.1 Security 0
03-31-81 10.0 Firefighting 0
03-31-81 11.0 FIRST AID & MEDICAL CARE 11.1 On-Site First Aid Assistance 2
02-26-82 11.2 Injured Person's Immediate Care.
1 05-15-81 11.3 M9 spital Assistance.
1 04-30-82 11.4 Personnel Decontamination..........
0 01-29-82 12.0 REENTRY & RECOVERY PLANNING 12.1 Reentry Procedures for Emergency Operations 1
03-17-82
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12.2 Personnel Exposure & Search & Rescue Teams.
2 04-30-82 12.3 Recovery Planning..............
0 03-31-81 12.4 Personnel Monitoring Exposure Guidelines 0
01-29-82 13.0 PRESS 13.1 Crisis Communications....
1 09-04-81 14.0 COMIUNICATIONS
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14.1 Testing of Communications Equipment.
0 03-31-81 15.0 TRAINING. DRILLS & EXERCISES 15.1 Employee Training 1
09-04-81 15.2 Off-Site Personnel Training.
0 03-31-81 15.3 Drills & Exercises 2
04-30-82 16.0 WISCONSIN ELECTRIC GENERAL OFFICE PROCEDURES 16.1 Nuclear Engineering Section Notification &
Response
3 09-04-81
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05-28-82 r%
i 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 & 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 Monitor;.ng System for Plant (03-81) 1.2 07 For X/Q Determination (09-81) 1.4 08 Estimated Whole Body & 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 Particulate Radionuclide Releases (09-81) 1.4 10a Estimated Population Dose (05-82) 1.8 11 Summary of Radiological Dose Evaluation Calculations (09-81) 1.4 12 "nusual 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 Accounting Snort Form (04-82) 8.1 18 Assembly Area Roster (03-81) 8.1 19 Drill / Exercise Scenario (03-81) 15.3 20 Drill / Observation Sheet (03-81) 15.3 21 Drill / Exercise Evaluation Report (03-81) 15.3 22 Plant & Company Emergency Call List (02-82)
Call List Tab 23 Offsite Agency Emergency Call List (05-82)
Call List Tab 24a Site Boundary Control Center Emergency Plan Inventory Checklist (04-82) 7.4.1 24b TSC, ESC, South Gate & OSC Emergency Plan Inventory Checklist (04-82) 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 (04-82) 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) 7.4.1
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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 & Air Sampler Functional Test Checklist (04-82) 7.4.2 25c Quarterly Emergency Plan Checklist (04-82) 7.4.2 25d Semi-Annual & Annual Emergency Plan Checklist (04-82) 7.4.2 26 Quarterly Communications Test (03-81) 14.1 27 Monthly Communications Test (03-81) 14.1 28 Emergency Plan Instrument Calibration Schedule (05-81) 7.4.2 29 Emergency Plan Counting Equipment & 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 Search & Rescue and Emergency Operations Checklist (04-82) 12.2 33 Estimation of Core Damage (04-82) 1.7 34 Calculation of Xe-133 Equivalent Release Rates (05-82) 1.8 35 Dose Calculations (05-82) 1.8
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r EPIP 1.4 HINOR Revision 5 05-28-82 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. NRC Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Iart 50, Appendix I, Revision 1,"
October 1977.
2.2 U. S. EPA, " Manual of Protective Action Guides and Protective Actions for Nuclear Incidents," EPA-520/1-75-001, September 1975.
See Appendix D " Technical Bases for Methods that Estimate the Projected
[
Thyroid Dose and Projected Whole Body Gamma Dose from Exposure to Airborne Radioicdines and Radioactive Noble Gases."
2.3 U. S. NRC Regulatory Guide 1.4, " Assumptions used for Evaluating the Potential Radiological Consequences of a Loss-of Coolant Accident for Pressurized Water Reactors," Revision 2, June 1976.
2.4 TID 14844, " Calculation of Distance Factors for Power and Test Reactor Sites," March 23, 1962.
3.0 PRECAUTIONS & LIMITATIONS 3.1 Ensure that all PBNF maps to be used by this procedure and their corresponding meteorological overlays are based on the same scale.
3.2 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.
3.3 This procedure will also be accomplished in the ESC by a person designated by the RadCon/ Waste Manager.
3.4 Wind speed and wind direction must be average values obtained from the analog recorders in the control room.
NOTE:
DO NOT USE INSTANTANEOUS VALUES.
a 5
- EPIP 1.4 Page 2
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3.5 If the radiological release duration is unknown, assume a duration.
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.
316.1 Kewaunee Nuclear Power Plant; 3.6.2 National Weather Service in Green Bay. Ask for Two Rivers Coast Guard information, if available.
4.0 INITIAL CONDITIONS
't 4.1 A release of airborne radioactivity has occurred or a release is anticipated.
4.2 An emergency or potential emergency condition is anticipated to have offsite dose consequences.
5.0 PROCEDURE 5.1 Determination of X/Q, Atmospheric Dispersion Factor
~~
5.1.1 Obtain the following information from the indicated source and enter this data in the appropriate space on form EPIP-07 (attached).
Source Data EPIP-04 (a) wind speed in-mph-EPIP-04 (b) wind direction EPIP-04 (c) time of reactor shutdown EPIP-04 (d) time of release to containment EPIP-04 (e) time of release from the plant Health Physics or Operating (f) duration or expected duration logs or projected estimate of the release in-hours (see EPIP 1.3 results note)
(g) gross Xe-133 equivalent release rate in Ci/sec NOTE:
IF RELEASE DURATION IS UNKNOWN, ASSUME 8 HOURS.
5.1.2 Determine stability class by use of the os chart recorder in the control room and Attachment 1.4-1.
Enter the stability class (h) on form EPIP-07.
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.
a u.
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EPIP 1.4 Page 3 NOTE:
IF INCOMING SOLAR RADIATION IS STRONG AND WINDS ARE FROM THE EAST OR SOUTHEAST, IT IS A POSSIBILITY THE WIND IS PRODUCED BY A LAKE EFFECT. CALL THE GREEN BAY NATIONAL WEATHER SERVICE FOR AID IN THIS DETER-MINATION.
IF A LAKE BREEZE IS SUSPECTED, OFFSITE SURVEY TEAMS MUST BE REMINDED TO PAY CLOSE ATTENTION.
TO WIND DIRECTION.
5.1.4 Place the overlay corresponding to the stability class on the map. Using the plant location as a pivot point, align the centerline of the overlay to the downwind direction from the plant.
NOTE: THE " TICK" MARKS ON THE CENTERLINE OF THE OVERLAYS ARE ONE MILE APART.
5.1.5 Determine the distance (i) to the dose projection location if different from the standard centerline distances listed on form EPIP-07. Note the location description, sector, and distance on form EPIP-07.
Enter the Xu/Q value (j) for the distances of site boundary, C.
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 form EPIP-07.
If the location is not on a line, move to the next inner-most line (toward the centerline) and enter the Xu/Q (j) value for that line on form EPIP-07.
Example:
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Class "C" Xu/Q for 5 miles equals 1.21 x 10 m
5.1.5 Calculate the X/Q value from the Xu/Q value by using the equation:
i
= 2.24(sec./m) X
"/Q ("
)
X sec.
Q m"
(hrs./mi)
Wind Speed (mi/hr.)
l Enter the X/Q values on form EPIP-07.
i 5.2 Whole Body Dose Estimate NOTE:
IF THE NOBLE GAS SOURCE TERM IS DETERMINED BY GRAB SAMPLE RESULTS WHICH GIVES AN INVENTORY OF SPECIFIC NUCLIDES, THEN A CONSERVATIVE WHOLE BODY DOSE ESTIMATE CAN BE HADE BY COMPLETING FORM EPIP-09.
5.2.1 Enter the gross Xe-133 equivalent release rate (g) on form EPIP-08 from form EPIP-07.
i 4
f EPIP 1.4 Page 4 5.2.2 Enter the expected inhalation period, EIP, 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 EID (Hrs) where:
D = whole body dose (Rem)
X/Q = atmospheric dispersion coefficient 3
determined in Step 5.1.5 (sec/m ) (k)
Q = release rate (Ci/sec) (g) 3 Kr=DoseFactor(['ihs) Attachment 1.4-2 EIP = Expected Inhalation (Exposure) Period (Hours) (f) 5.3 Thyroid Dose Estimate 5.3.1 Calculate the projected thryoid dose by using the whole body dose calculated in Section 5.2 of this procedure.
5.3.2 Record the projected whole body dose on form EPIP-08 in Section 2.
5.3.3 Choose the appropriate figure based upon the type of accident which has occurred.
a.
Loss of Coolant Accident (LOCA) - Figure 1.4-1.
b.
Gap Activity Accident - Figure 1.4-4.
c.
Fuel Handling Accident - Figure 1.4-4.
d.
Steam Generator Tube Rupture - Figure 1.4-5.
NOTE:
IF THE TYPE OF ACCIDENT IS UNICICWN, USE THE LOCA FIGURES.
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.
- - _ _ = _ _ - = -
-=w EPIP 1.4 Page 5 5.3.5 Calculate the projected thyroid dose my multiplying the whole body dose by the ratio factor obtained in Step 5.3.4 on form EPIP-08, Section 2.
5.4 Radionuclide Ground Deposition Estimation NOTE:
FORM EPIP-10 CAN BE COMPLETED ONLY IF IODINE GRAB SAMPLE RESULTS OR PARTICULATE RELEASE RATES ARE AVAILABLE.
IF FORM EPIP-10 CANNOT BE COMPLETED, PROCEED WITH STEP 5.4.5 0F THIS SECTION.
5.4.1 Enter the Xe-133 equivalent release rate or the specific particulate release rate on form EPIP-10 from grab sample results or from environmental monitoring results.
5.4.2 Enter the duration of release expected inhalation period (f) from form EPIP-07 on form EPIP-10.
5.4.5 Enter the value of X/Q (k) on form EPIP-10 as determined in Step 5.1.5.
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5.4.4 Complete Section 2 of form EPIP-10 to calculate the ground deposition using the equation:
2 Dep (pCi/m ) = F x.05 (m/sec) x 3600 (sec/hr) x 108 3
(pci/Ci) x X/Q (sec/m )
x Q (Ci/sec) x EIP (hrs)
(k)
(g)
(f) 8 Dep = F x 1.8 x 10 x X/Q x Q
x EIP 3
Dep = ground deposition (pCi/m )
X/Q = atmospheric dispersion factor from 3
Step 5.1.5 (sec/m ) (k)
Q = radionuclide release rate (Ci/sec) (g)
EIP = estimated release duration (hrs) (f)
F = fraction of isotope subject to deposition (unitiess) 3600 = conversion (sec/hr) 108 = conversion (pCi/Ci) 0.05 = assumed deposition velocity (m/sec) 5.4.5 Complete form EPIP-11 from available data and calculations just performed.
3 EPIP 1.4 Page 6
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5.4.6 Enter the date and time of these calculations and sign form EPIP-11*.
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 Calcu.1. ate 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 Figure 1.4-6.
Use population number corresponding to the quadrant and distance categories for dose.
5.5.4 Total population dose from each radius to find total population dose.
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-l ATTACHMENT 1.4-1 CLASSIFICATION OF ATMOSPHERIC STABILITY BY SIGMA THETA i
Stability Pasquill 00 Classification Categories (degrees)
Extremely unstable A
00 2 22.5 Moderately unstable, B
22.5 > 00 2 17.5 i
Slightly unstable C
17.5 > 00 2 12.5 I
I Neutral D
12.5 > os 2 7.5 f
I Slightly stable E
7.5 > 00 2 3.8 l
I Moderately stable F
3.8 > 09 2 2.1 i
7.
Extremely stable G
2.1 > 00 k
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ATTACHMENT 1.4-2 WHOLE BODY DOSE RATE CONVERSI0'N FACTORS m.
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._m EPIP 1.4 Page 8 I, m ATTACHMENT 1.4-3 BACKUP DETERMINATION OF ATMOSPHER.'C 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
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A-B B
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C E
F 7-11 B
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The neutral class D, should be assumed for overcast conditions during day or night.
" Strong" incoming solai adiation corresponds to a solar altitude greater than
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radiation and should be considered along with solar altitude when determining solar radiatica.
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.
ATTACHMCIT 1.4-6 EMERGCICY PLANNING ZONE POPULATION DATA l' 10-m i tes
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s EPIP 1.8 m
MINOR Revision 1 i
05-28-82 EMERGENCY OFF-SITE DOSE ESTIMATIONS 1.0 GENERAL The purpose of this procedure is to permit the expeditious classification of an accident or event based on estimated off-site doses. The procedure provides a methodology to quickly estimate (1) stack release rates (source terms) and (2) off-site whole body and thyroid doses.
2.0 REFERENCES
2.1 U. S. 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 2.3 TID 14844 " Calculation of Distance Factors for Power and Test Reactor
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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 Facility Description & Safety Analysis Report (FFDSAR) 3.0 PRECAUTIONS & LIMITATIONS 3.1 This procedure is primarily intended for use in the control room by a person designated by the Shift Supervisor such as the Duty Technical Advisor.
3.2 This procedure is to be used only for Unmediate initial dose pro-jections. The initial dose projections are to be refined using EPIP 1.3 and 1.4 once more data becomes available, i.e., meteoro-logical data, air samples, and off-site survey dose measurements.
3.3 It is recognized that the RadCon/ Waste Manager, in conjunction with the Chemistry & Health Physics Supervisor, is ultimately responsible for off-site dose assessments. However, the initial projections will
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normally be done by the Shift Supervisor or assigned designee for purposes of classifying the event or accident because of augmentation time.
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EPIP 1.8 N
Page 2 4.0 INITIAL CONDITIONS 4.1 An emergency or potential condition 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) 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.
a.
Low range operational stack monitors (designed to monitor low-level releases).
b.
Eberline RMS II radiation monitoring system (designed to mcnitor high-level releases).
c.
Contact readings using a hand-held survey meter (to be used when other monitor systems are non-operable).
5.1.3 The decision as to which moni.
.ng system is to be used to estimate the source terms is supendent on the level of release and the operability of the monitor.
5.1.4 Meter readings are to be entered in the appropriate column on EPIP-34.
If meter readings are "off-scale" or " inoperable,"
enter the appropriate comment in the meter reading column on EPIP-34.
A source term estimate must be made for each vent which is exhibiting readings above normal operating readings.
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5.1.5 Direct contact readings using a hand-held survey meter are required under the following conditions:
l a.
Meter readings from the low range monitoring system or the RMS II system are not available.
b.
A steam generator tube rupture has occurred necessi-tating a hand-held meter reading at the main steam header.
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5.1.6 Direct contact readings using a hand-held curvey meter are not to ce initiated until the following conditions are i
accomplished:
a.
An evaluation of the radiolcgical hazards must be ccm-pleted prior to any attempt to enter the auxiliary building or facade to take survey readings on any stack or vent.
b.
Before the surveys are done, the proper survey meter and j
the most direct and desirable route to the stack to be monitored must be chosen.
i 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 Supervisor.
5.1.7 For surveying the main steam safety valves and atmospheric dump valves, the reading will be taken in contact with the centerline of the main steam header, three feet from the main steam line. The survey probe is to be shielded with a minimum of 0.25 inches of lead on the side of the probe facing the main steam line and the containment.
5.1.8 The following data must be obtained from the Shift Supervisor in order to estimate release rates from the main steam header:
a.
Estimated flow rate of steam through the main steam header in lbs/hr.
3 b.
Specific volume of the steam in ft /lb. At 1000 psia, 3
specific volume of 0.486 ft /lb. At 500 psia, specific 3
volume is 0.928 ft /lb.
Enter this data on the appropriate column in Section 3.0 of EPIP-34.
5.1.9 Sum the values on EPIP-34, Section 4.0, to determine the gross Xe-133 equivalent release rate.
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EPIP 1.8 m
Page 4 5.2 Whole Body Dose
- Projections 5.2.1 off-site whole body doses may be calculated at the site boundary using the following equation:
D(REM) = X/Q x Q x Kr HR Where:
D = whole body dose rate (Rem /hr) 3 X/Q = atmospheric dispersion coefficient (sec/m )
Q = gross Xe-133 equivalent release rate (Ci/sec.)
3
- Kr = Dose Factor (rem-m )
Ci-hrs Projected off-site doses may be calculated by entering the total Xe-133 equivalent release rate calculated on EPIP-34 in the appropriate column on EPIP-35 and multiplying the variables in the equations.
7.
5.2.3 Enter
.e expected exposure period in the appropriate columr on EPIP-35.
(A dose per hour is calculated by
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enter;ng an exposure period of one (1) hour.)
NOTE:
THE X/Q VALUEJ LISTED ON EPIP-35 ARE ESTIMATED BASED ON CALCULATED ACCIDENT METER 0 LOGY FOR 0-2 HRS.
AS GIVEN IN THE FFDSAR.
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 Pr)jection 5.3.1 Calculate the projected thyroid dose at the site boundary on Section 2.0 of EPIP-35 by using the following equation:
Thyroid Dose = Whole Body Dose x Conversion Factor 5.3.2 The conversion factor is dependent on the type of accident which has occurred.
Conversion factors are tabulated for the following accidents:
a.
Loss of coolant accident (LOCA) b.
Gap activity accident Fuel handling accident c.
d.
Steam generator tube rupture
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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 Sectin 1.0 by the conversion factor.
NOTE:
IF THE TYPE OF ACCIDENT IS NOT KNOWN, USE THE LOSS OF COOLANT CONVERSION FACTOR.
5.4 Classification of the Event Based on Estimated Off-Site Doses 5.4.1 The event is to be classified as a Site Emergency if the project.ed off-site doses meet any of the following criteria:
a.
Effluent monitors detect levels corresponding to any of the following doses at or beyond the site boundary:
(1)
>50 mR/hr whole body for hour (2)
>250 mR/hr for hour for the thyroid (3)
>500 mR/hr whole body for 2 minutes (4)
>2500 mR/hr to the thyroid for 2 minutes b.
Any of the above dose rates are projected, based on plant parameters.
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) 1 R/hr whole body (2) 5 R/hr thyroid b.
Either of above dose rates are projected based on plant parameters.
5.5 Protective Action Recommendation i
5.5.1 Due to the conservative nature of the calculations in this f
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.
l 5.5.2 Enter dose rates and release duration estimate on EPIP-35.
l' If duration of release is unknown, use a release duration of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
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EPIP 1.8
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Page 6 5.5.3 Recomme'nd one of the following offsite protective actions based on results of EPIP-35 calculations.
Whole Body Dose a.
>0.1 R - Advise State to have population to seek shelter.
b.
>l R - Tell State to consider evacuation of women and children.
c.
>3 R - Advise State to evacuate public in affected area and all people within 2 miles of the plant.
Thyroid Dose a.
>5 R - Advise State to have public seek shelter and consider evacuation of women and children.
b.
>25 R - Advise State to evacuate public in affected area and all people within 2 miles of the plant.
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ESTIMATED POPULATION DOSE i
.i complete using calculations from EPIP-08 gnd population figures from corresponding sectors and distances'from Attachment 1.4-6.
O e
I Calculated Population Dose N
Population Dose (man Rem) = Dose (Rem) X Population Two mile radius X
=
Five mile X
=
I Ten mile X
=
h Total Dose c
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COMPLETED BY TIME /DATE i
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EPIP-10a (05-82)
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0FFSITE ACENCY EMERGENCY CALL LIST L
l FEDERAL AGENCIES:
i 1.
United States Nuclear Regulatory Commission Telephone Person Time l
Name Frequency Number Notified Notified Initials l
NRC Operations All hours Red Phone Center or 1-202/951-0550 NRC Office of All hours F312/932-2500 Inspection and (Ask for Enforcement, Duty Officer)
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Region III
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,,7 NRC Resident Inspectors:
Plant Ext.
Home s
a.
W. G. Guldemond s
's 1,
b.
R. L. Hague s
g 2.
United States Department of Energy
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Telephone Person Time
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E Frequency Number Notified N6tified Initials Chicago Operations Weekdays 1-312/972-4800 Center, Region V (8AM-SPM) s (Radiological V
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Assistance Team)
All other 1-312/972-5731
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hours 4
-s 3.
United States Coast Guard Telephone Person
-Time 5
Name Frequency Number Notified Notified,
Initials,y USCG, Sturgeon All hours 1-743-3366 Bay USCG, Two All hours 793-1304 7
Rivers y
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EPIP-23 Page 1 of 4 (05-82)
I L,
' ATE AGENCIES:
I-1.
State of Wisconsin Telephone Person Time Name Frequency Number Notified Notified Initials l
Wisconsin Dept. of Weekdays 1-608/266-7464 i
Health and Social (9AM-SPM)
Services, Section j
of Radiation Pro-l tection 1.
I Lawrence J. McDonnell, Home phone y
Chief Section of Radiation Protection Wisconsin Division All hours 1-608/266-3232 of Emergency or NAWAS Government Wisconsin State All hours 1-921-0448 Patrol 1-921-0442 or NAWAS
'UNTY AGENCIES:
1.
Manitowoc County Telephone Person Time Name Frequency Number Notified Notified Initials Manitowoc County All hours 683-4200 Sheriff, County or NAWAS Traffic 2.
Kewaunee County Telephone Person Time Name Frequency Number Notified Notified Initials Kewaunee County All Hours 1-388-3100 Dispatcher or NAWAS PRIVATE AGENCIES:
Telephone Person Time Name Frequency Number Notified Notified Initials Kewaunee Nuclear All hours 793-2229 Power Plant EPIP-23 Page 2 of 4 (05-82)
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'IVATE AGENCIES: (Cont'd) l Telephone Person Time Name Frequency Number Notified Notified Initials L
Institute of All hours 1-404/953-0904 Nuclear Power Operations American Nuclear Insurers All hours 1-203/677-7305 Westinghouse Electric Corp.
j Field Serv. Hgr.
Office 1-412/256-3820 (R. Grimm)
Home Hot Line Stone & Webster All hours 1-617/973-0008 Engineering Corp.
8echtel Power All hours 1-415/768-3840 Corporation FIRE AND MEDICAL AGENCIES Fire Emergency Telephone Person Time Name Frequency Number Notified Notified Initials Two Creeks Fire All hours 684-0133 Department (Emergency line) 2.
Medical Assistance Telephone Person Time Name Frequency Number Notified Notified Initials Doctors Clinic, Ltd.
793-2281 S. Lawrence Kaner, M.D.
Stephen L. Weld, M.D.
University Hos-pital, Madison Emergency Room All hours 1-608/262-2398 Frank C. Larson, M.D.
1-608/262-2718 Robert F. Schilling, M.D.
1-608/262-3188 Robert R. Radtke, Ph.D.
1-600/162-8769 (Health Physicist)
EPIP-23 Page 3 of 4 (05-82)
e' RE AND MEDICAL AGENCIES: (Cont'd)
Telephone.
Person Time Name Frequency Number Notified Notified Initials Two Rivers All hours 793-1151 Emergency or 1152 Vehicle Community Hos-All hours 793-1178 pital, Two Rivers I
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EPIP-23 Page 4 of 4 (05-82)
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POINT BEACll NUCLEAR PLANT CALCULATION OF Xe-133 EQUIVALENT RELEASE RATES 1.0 LOW RANGE OPERATIONAL VENT STACK READINGS Flow Rate Meter Reading Conversion Factor Release Rate (CFM)
(CPH)
Curies (Curies /s-c) sec-cpm Auxiliary Building 61400 X
5.8 X 10'8
=
Drumming Area 43100 X
1.2 X 10 a
=
Unit 1 Containment Purge 12500 X
2.1 X 10~8
=
25000 X
4.2 x 10 s
=
Unit 2 Containment Purge 12500 X
2.1 x 10~8
=
25000 X
4.2 x 108
=
Gas Stripper Building 13000 X
=
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Combined Air Ejector 25 X
7.8 X 10_8
=
2.0 EBERLINE RMS-11 VENT STACK READOUTS Flow Rate Meter Reading Conversion Factor Relelse Rate (CFH)
(R/hr)
Curies (Curies /sec) sec-R/hr Auxiliary Building 61400 X
3.0 X 103
=
Drumming Area 43100 X
2.2 X 103
=
Unit 1 Containment Purge 12500 X
1.6 X 104
=
25000 X
3.2 X 104
=
Unit 2 Containment Purge 12500 X
1.6 X 104
=
25000 X
3.2 X 104
=
Gas Stripper Building 13000 X
6.2 X 102
=
Combined Air Ejector 25 X
3.6
=
EPIP-34 Page 1 of 3 (05-82)
3.0 PLANT EFFLUENT VENT STACK CONTACT READINGS Flow Rate Meter Reading Conversion Factor Ralease Rate (CFM)
(R/hr)
Curies-hr (Curies /sec) sec-R i
Auxiliary Building 61400 X
3.0 X 102
=
Drumming Area 43100 X
2.3 X 102
=
1 Unit 1 Containment 12500 X
8.0 X 10
=
25000 X
1.6 X 102
=
Unit 2 Containment 12500 X
8.0 X 101
=
25000 X
1.6 X'102
=
Gas Stripper Building 13000 X
8.0 X 104
=
Combined Air Ejector 25 X
1.6 X 102
=
t Estimated Steam X Specific X Conversion X Meter X Conversion Release Rate Release Voltune Factor Reading Factor Ci/sec
=
(1b/hr)
(ft /lbm) hr-cm3 3
(R/hr)
Curies-hr 3
3 sec-ft cm -R Main Steam Header X
X
?.86 X
X 8.0 x 10~1
=
Assume 1000 psia steam which will give a conservative specific volume. At 3
1000 psia specific volume =.446 ft /lbm.
Steam generator safety valve rating is 5
8.33 x 10 lb/hr. Atmospheric relief 4
valve capacity is 3.3 X 10 lb/hr with both valves open.
EPIP-34 Page 2 of 3
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4.0. ESTIMATE OF GROSS Xe-133 EQUIVALENT RELEASE RATES Xe-133 Vent Equivalent Release Rate (Curies /sec)
Auxiliary Building Drtmuning Area Unit 1 Containment Purge Unit 2 Containment Purge Gas Stripper Building Combined Air Ejector Decay Duct Main Steam Header TOTAL Completed By Date Time n
I d
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EPIP-34 Page 3 of 3 3
(05-82)
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I POINT BEACH NUCLEAR PLANT DOSE CALCULATIONS
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l.0 ESTIMATION OF SITE BOUNDARY WilOLE BODY DOSES RATES X/Q X
Release X
Dose Conversion Whole Body
=
3 (sec/m )
Rate Factor Dose Rate 3
(Ci/sec)
(REMS-m )
(REMS /hr)
Ci-hr 2.6 X 104 X
X 26.9
=
2.0 ESTIMATION OF SITE BOUNDARY TilYROID DOSES RATES Type of Accident Conversion Whole Body Dose Thyroid Dose Rate Factor Rate (R/hr)
(Rem /hr) 1.
Loss of Coolant (LOCA) 5.02 X 102 X
=
2.
Gap Activity Accident 4.84 X
=
3.
Fuel llandling Accident 4.84 X
=
4.
Steam Generator Accident 6.25 X
=
3.0 PROTECTIVE ACTION DOSE DETERMINATION NOTE:
USE ONLY IF TIME IS LIMITED.
l Whole Body Dose Rate Release Duration Estimate Whole Body Dose X
=
Thyroid Dose Thyroid Dose Rate X
Release Duration
=
l X
=
l Completed By Date Time EPIP-35 (05-82)
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