ML20050A723

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Public Version of Revision 3 to Emergency Plan Implementing Procedure EPIP 1.4, Radiological Dose Evaluation.
ML20050A723
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 03/08/1982
From:
WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20050A714 List:
References
EPIP-1.4-01, EPIP-1.4-1, NUDOCS 8204020149
Download: ML20050A723 (14)
v • d • e


Text

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a 03-08-82 TABLE OF CONTENTS Revision Date 1.0 CLASSIFICATION 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 . . . . . . . . 3 03-08-82 l 1.5 Protective Action Evaluation . . . . . . . . 2 02-26-82 1.6 Radiciodine Blocking and Thyroid Exposure Accounting ... ... . . . . . . . . . . 1 02-26-8 l

2.0 UNUSUAL EVENT IMPLEMENTING PROCEDURES 2.1 Unusual Event - Inunediate Actions . . . . . . 0 03-31-81 2.2 Unusual Event - Plant and Company Personnel llotification . . .. . . . . . . . . . . . 1 07-01-81 2.3 Unusual Event - Off-Site Agency Notification 1 02-26-81 3.0 ALERT IMPLEMENTING PROCEDURES 3.1 Alert - Inunediate 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 - Inunediate Actions . . . . . 0 03-31-81 4.2 Site Emergency - Plant and Company Personnel Notification .. .... . . . . . . . . . 1 07-01-81 4.3 Site Emergency - Off-Site Agency Notification 0 03-31-81 5.0 GENERAL EMERGENCY - IMPLEMENTING PROCEDURES 5.1 General Emergency - Inunediate 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 Evacuation . . . . . . . . . . C 03-31-81 6.4 Energy Information Center Evacuation . . . 0 03-31-81 8204020149 820317 PDR ADOCK 05000266 F PDR

Page 2 Revision date 7.0 CHEMISTRY & HEALTH PHYSICS RESPONSE AND PREPAREDNESS 7.1 Internal Chem & HP Group Personnel Notification /

Initial Response 7.1.1 Chem & 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 E 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 7.2.4 Activation of HP Facilities at Technical Support Center . . . . .

Health Physics Communications . . .

1 0

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- j ment Atmosphere . . . . . . . . . 3 12-30-81 '

7.3.4 Movement of Required Chemistry Equip-ment and Material to the Technical Support Center Counting Room and Mini-Laboratory . . . . . . . . . 0 12-30-81 7.4 Emergency Equipment 7.4.1 Routine Check, Maintenance, Cali-bration and Inventory Schedule for Health Physics Emergency Plan Equipment . . . . . . . . . . . . 3 01-29-82 7.4.2 Emergency Plan Equipment Routine Check, Maintenance and Calibration k Instructions . . . . . . . . . . . 2 07-01-81 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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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 Nc,ble Gas Sampler / Detector . . . . 0 03-31-81 8.1 Personnel Assembly and Accountability . . . . 0 03-31-81 9.1 Security . ................. 0 03-31-81 10.0 Firefighting ................ 0 03-31-81 , .

11.0 FIRST AID AND MEDICAL CAP.E 11.1 On-Site First Aid Assistance . . . . . . . . 2 02-26-82 11.2 Injured Person's Inmediate Care . . . . . . . 1 05-15-81 11.3 Hospital Assistance . . ........... 0 03-31-81 11.4 Personnel Decontamination . . . . . . . . . . 0 01-29-52 12.0 REENTRY AND RECOVERY PLANNING

(' 12.1 Reentry Procedures for Emergency Operations 0 03-31-81 1

12.2 Personnel Exposure and Search and Rescue

. Teams . . . . . . . ... . . . . . . . . . . 0' 03-31-81 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 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 1 1

16.1 Nuclear Engineering Section Notification and Response ................. 3 09-04-81

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EPIP 1.4

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i MINOR Revision 3 03/08/82 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 approxunation 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 Part 50, Appendix I, Revision 1,"

October 1977. .

2.2 U. S. EPA, " Manual of Protective Action Guides and Protective Actions for Nuclear Incidents," EPA-520/1-75-001, September 1975. See Appendix D " Technical Bases for Methods that Estimate the Projected Thyroid Dose and Projected Whole Body Gamma Dose from Exposure to Airborne Radioiodines and Radioactive Noble Gases."

2.3 U. S. NRC Regulatory Guide 1.4, " Assumptions used for Ev'aluating 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 AND LIMITATIONS 3.1 Ensure that all PBNP maps to be used by this procedure and their j 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 i Chemistry / Health Physics Supervisor when available.

4.0 INITIAL CONDITIONS 4.1 A release of airborne radioactivity has occurred or a release is anticipated.

4.2 An emergency or potential emergency condition is anticipated to have

( offsite dose consequences. I l

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EPIP 1.4 p Page 2 t

5.0 PROCEDURE j 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 EPIP 1.3 results (g) gross Xe-133 equivalent release rate in ci/sec 5.1.2 Visually check cloud cover and incoming solar radiation.

With this information, use Attachment 1.4-1 to ascertain the appropriate stability class. Enter the stability class (h),

on form EPIP-07.

5.1.3 Place the overlay corresponding to the stability class on the map. Using the plant as a pivotal 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.

5.1.4 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 Ku/Q value (j) for the distances of site boundary, two miles, five miles, and ten miles on EPIP-07. The Xu/Q values (j) can be obtained from the overlay in the table in the lower righthand corner of the overlay. If a possible location other than the standard specified location is on a line, enter the Xu/Q (j) value for that line from the overlay on form EPIP-07. If the location is not on a line, move to the next inner-most line (toward the centerline) and enter the Xu/Q (j) value for that line on form EPIP-07.

Example:

Class "C" Xu/Q for 5 miles equals 1.21 x 10 ~8 m'

EPIP 1.4 g Page 3 5.1.S Calculate the X/Q value from the Xu/Q value by using the equation.

X sec.

=~2.24(sec./m) X Xu/O (m 2)

Q m3 (hrs./mi) Wind Speed (mi/hr.)

Enter the X/Q values on form EPIP-07.

5.2 Whole Body Dose Estimate NOTE: IF TIE NOBLE GAS SOURCE TERM IS DETERMINED BY GRAE SAMPLE RESULTS WHICH GIVES AN INVENTORY OF SPECIFIC NUCLIDES, THEN A CONSERVATIVE WHOLE BODY DOSE ESTIMATE CAN BE MADE BY COMPL3 TING FORN EPIP-09.

5.2.1 Enter the gross Xe-133 equivalent release rate (g) on form EPIP-08 from foria EPIP-07.

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 (Rea m /Ci - Hrs) x EIP (Hrs) where:

D = whole body dose (Rem)

X/Q = atmospheric dispersion coefficient.

determined in Step 5.1.5 (sec/m 3) (k)

Q = release rate (C1/sec) (g)

Kr = Dose Factor ( ) 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.

1 5.3.2 Record the projected whole body dose on form EPIP-08 in Section 2.

EPIP 1.4 Page 4 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.

NO'IE : IF THE TYPE OF ACCIDENT IS UNKNOWN, 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.

5.3.5 Calculate the projected thyroid dose my multiplying the whole body dose by the ratio factor obtained in Step 5.3.4 h on forla EPIP-08, Section 2.

5.4 Radionuclide Ground Deposition Estimation

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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 i

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.

5.4.3 Enter the value of X/Q (k) on form EPIP-10 as determined in Step 5.1.5.

5.4.4 Complete Section 2 of form EPIP-10 to calculate the ground l

deposition using the equation: j Dep (pci/m2 ) = F x .05 (m/sec) x 3600 (sec/hr) x 10 8 (pci/Ci) x X/Q (sec/m 3) x Q (Ci/sec) x EIP (hrs) .,  ;

t (k) (g) (f)

I Dep = F x 1.8 x lo s x X/Q x Q x EIP D I

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EPIP 1.4

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Dep = ground deposition (pC1/m 3) -

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X/Q = atmospheric dispersion factor from

Step 5.1.5 (sec/m 3).(k) j Q = radionuclide release rate-(Ci/iec) (g) .

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EIP = estimated release duration;(hrs) (f) ~'j

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F = fraction of isotope subject to deposition (unitless) 3600 = conversion (sec/hr) .- ,

108 = conversion (pCi/Ci)  ;- ,, 1 0.05 = assumed deposition velocity (m/sec) 5.4.5 Complete form EPIP-11 from available data and calculations ,

just performed. -

5.4.6 Enter the date and time of these calculations and sigri form

[ EPIP-ll.

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5.4.7 Forward completed attachments to the Technical Support -

Manager for review. The-Technical Support Manager vill '

relay results to the Site Manager.

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, ATTACHMENT 1.4-1 DETERMINATION OF A7.OSPHERIC STABILITY CLASS

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- Surface Wind Speed; ~~ Day Night

- (at 50 meters)

  • Incoming Solar Radiation Thinly Overcast
p. ' raph Strong Moderate Slight > 1/2 low cloud < 1/2 cloud

, <4 A A-B B

, 4-7 A-B B C E F

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7-11 B B-C C D E 11-13 , C C-D D D D

>13 'C' D D D D

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^rbe neutral class D, should be asstuned for overcast conditions during day or night. -

-"s'c'ronga , incoming solar fadiation corresponds to a solar altitude greater than 1 . 60* with clear _ skies; " slight" incoming solar radiation corresponds to a solar altitude from 15'-35' with clear skies. Cloudiness will decrease incoming solar radiation und should'be considered along with solar altitude when detenmining solar radiation. -Incoming radiation that would be strong with clear skies can

,- be egected to reduce to moderate with' broken (5/8 to 7/8 cloud cover) middle clou.is an'd to slight with broken low clouds. Night refers to the period from' one, hour,befiire sunset to one hour after sunrise.

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