ML040420378
| ML040420378 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 02/02/2004 |
| From: | Timmerman P FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 0402-48039 RA-EP-02240, Rev 01 | |
| Download: ML040420378 (47) | |
Text
(.
Davis Besse Power Station Transmittal / Receipt Acknowledgement C
Control Copy Number: 1665 Transmittal Number:
0402-48039 Transmittal Date:
02-02-2004 To: DOC. CONTROL DESK Mail Stop / Address:
USNRC DIVISION OF EMERGENCY PREPARDNESS WASHINGTON, D.C. 20555 Document holders are responsible for control and maintenance of documents in accordance with the actions specified by this transmittal. Outdated material shall either be removed and destroyed or marked to reflect that it is superseded or voided and is no longer considered controlled.
Note: Destroy Safeguard information by shredding.
File documents in tab order as identified on the Table of Contents Contact Document Control with any questions at (419)-321-7483
(:.
Davis Besse Power Station Transmittal / Receipt Acknowledgement (I
Control Copy Number: 1665 Transmittal Number:
0402-48039 Transmittal Date:
02-02-2004 TOC I TOC 2 Type old EPIB PROC new EPIB PROC Number Sht/Sec Changes RA-EP-02240 RA-EP.02240 Rev Status 0000 APPROVED 0001 APPROVED
Page I of 45 Davis-Besse Nuclear Power Station EMERGENCY PLAN IMPLEMENTING PROCEDURE RA-EP-02240 Offsite Dose Assessment REVISION 01 Prepared by:
Paul F. Timmerman Procedure Owner:* Manager - Regulatory Affairs Effective Date:
FEB 0 2 2004 Procedure Classification:
X Safety Related Quality Related Non-Quality Related L
I I
I I
LEVEL OF USE:
IN-FIELD REFERENCE
2 RA-EP-02240 Revision 01 TABLE OF CONTENTS Page 1.0 PURPOSE.................................................................
3
2.0 REFERENCES
3 3.0 DEFINITIONS.................................................................
4 4.0 RESPONSIBILITIES.................................................................
4 5.0 INITIATING CONDITIONS..................................................................
4 6.0 PROCEDURE.................................................................
5 6.1 Projection of Offsite Dose Rates Using Plant Data..................................................... 5 6.2 Projection of Offsite Dose Rates Using Field Monitoring Data.................................. 5 6.3 Meteorological Data.................................................................
6 6.4 Total Population Dose................................................................ 6 7.0 FINAL CONDITIONS.................................................................
6 8.0 RECORDS..................................................................
7 ATTACHMENT I Dose Calculations Using SPDS................................................................
8 ATTACHMENT 2 Instructions for Offsite Dose Assessment Nomogram 10 ATTACHMENT 3 Station Vent Release Calculations.
12 ATTACHMENT 4 Secondary Side Release Calculations.
18 ATTACHMENT 5 Calculations for Containment Releases Using RE 4596A or RE 4596B..... 27 ATTACHMENT 6 Calculations for Releases From Containment Using RE 4597AB or RE 4597BB.................................................................
33 ATTACHMENT 7 Dose Projections Based on Field Monitoring Data...................................... 34 ATTACHMENT 8 Estimation of Total Population Dose............................................................ 38 ATTACHMENT 9 Meteorological Data.................................................................
42 COMMITMENTS................................................................
45
3 RA-EP-02240 Revision 01 1.0 PURPOSE
.1.1.
This procedure is intended to estimate offsite dose rates from noble gases and radioiodides during accidental, uncontrolled airborne releases.
2.0 REFERENCES
2.1.
Developmental 2.1.1 NRC Regulatory Guide 1.4, Assumptions Used for Evaluating the Potential Consequences of a Loss of Coolant Accident for Pressurized Water Reactors 2.1.2 NRC Regulatory Guide 1.109, Calculation of Annual Dose to Man From Routine Releases or Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR
- 50. Appendix I 2.1.3 NRC Regulatory Guide 1.145, Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants 2.1.4 EPA-400-R-92-001, May 1992, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents 2.1.5 Letter; Correction Factor for Noble Gas Measurements Assuming All Activity as Xe'33.
from Gregory Stoetzel, Battelle Pacific Northwest Laboratories, September 24, 1984 2.1.6 BT-10372, Letter from Bechtel to Toledo Edison concerning Quantification of Radiation Release from Main Steam Line, June 4, 1980 2.1.7 Davis-Besse Nuclear Power Station Emergency Plan 2.2 Implementing 2.2.1 RA-EP-02245, Protective Action Guidelines 2.2.2 Davis-Besse Nuclear Power Station Emergency Plan Telephone Directory
4 RA-EP-02240 Revision 01 3.0 DEFINITIONS 3.1 DADS - The Data Acquisition and Display System (DADS) provides plant parameters, meteorology data, and dose calculations. DADS updates MODCOMP data at 30-second intervals and Validyne data at I second intervals. The meteorological data is provided at 15 minute intervals, and is an average over that time period. DADS stores information from the last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.2 LAKE BREEZE - A meteorological condition that may occur on clear, sunny days. During a lake breeze, a radioactive release can travel inland, rise, reverse course in an overhead return flow, and then return to land in a convoluted path.
3.3 MODCOMP - The station computer which monitors plant instruments and systems.
3.4 SAFETY PARAMETER DISPLAY SYSTEM (SPDS) - The SPDS is a group of graphic displays developed to assist with monitoring plant operations.
3.5 SECTOR - One of the 16 areas bounded by radii 221/2 degrees apart into which the 10 mile EPZ is divided. Sectors are designated by the letters A through R, excluding I and 0. Sector A lies north of DBNPS, Sector E lies east, Sector J lies south, and Sector N lies west.
3.6 VALIDYNE - A high speed data acquisition system that monitors 100 critical plant parameters.
4.0 RESPONSIBILITIES 4.1 Emergency Director shall:
4.1.1 Direct calculation of the release and dose rates using available, qualified dose assessment personnel including Licensed Reactor Operators and Senior Reactor Operators.
4.2 Qualified Dose Assessment Personnel shall:
4.2.1 Perform dose calculations in accordance with Section 6.0 of this procedure.
4.2.2 Report the results of dose calculations to the Emergency Director or Dose Assessment Coordinator, as applicable.
5.0 INITIATING CONDITIONS This procedure shall be implemented at the request of the Emergency Director, or Dose Assessment Coordinator when an accidental airborne release of radioactivity is in progress or imminent.
5 RA-EP-02240 Revision 01 6.0 PROCEDURE 6.1.
Proiection of Offsite Dose Rates Using Plant Data 6.1.1 Determine the release pathway of the radioactive release.
- a.
JF the release is from more than one point [e.g., Steam Jet Air Ejector (SJAE) and Atmospheric Vent Valve (AVV)],
THEN sum the resulting dose rates for each point to obtain the total dose rate.
6.1.2 Dose Assessment Instructions using In-Plant Radiation Detector Data
- a.
The Safety Parameter Display System (SPDS) Process Book
- 1.
Select the Dose Calculation tab.
- 2.
Double click the "Dose Rate Calculation an PARs" display title.
- 3.
Refer To Attachment 1, Dose Calculations using SPDS.
- b.
The Offsite Dose Assessment Nomogram per Attachment 2, Instructions for Offsite Dose Assessment Nomogram.
- c.
The appropriate hand calculation below:
RELEASE INDICATIONS ATTACHMENT RE 4598 (Station Vent) 3 Secondary Side Releases 4
RE 4596 (Dome Monitors) 5 RE 4597 (Containment Atmosphere) 6 6.1.3 Refer To RA-EP-02245, Protective Action Guidelines, to determine protective action recommendations.
6.2 Projection of Offsite Dose Rates Using Field Monitoring Data 6.2.1 Refer To Attachment 7, Dose Projections Based on Field Monitoring Data, when usinglfield data.
6.2.2 Refer To RA-EP-02245, Protective Action Guidelines, to determine protective action recommendations.
C P.
6 RA-EP-02240 Revision 01 6.3 Meteorological Data 6.3.1 Obtain 15 minute average meteorological data from any of the following:
- Access the SPDS Process Book to access the meteorological data.
- Access the DADS nongraphic terminal to call up the meteorological data.
6.3.2 IF the systems in 6.3.1 cannot be accessed, THEN monitor meteorological data in accordance with Attachment 9. Meteorological Data.
6.3.3 IF a lake breeze is occurring while an airborne radioactive release is in progress or
- imminent, THEN the Dose Assessment Coordinator should:
- a.
Refer To Attachment 9, Meteorological Data, for lake breeze conditions.
- b.
Inform the Ohio EMA of the lake breeze and that the plume may not follow the course indicated by the meteorological tower wind direction.
- c.
Inform the Radiation Monitoring Teams (RMTs) that higher-than-projected dose rates may occur in the plume pathway.
6.4 Total Population Dose NOTE 6.4.1 The Radiation Protection Section will provide a more definitive estimate of the total population dose after more detailed population and radiological data have been obtained.
6.4.1 During Recovery from an emergency event, obtain an estimate of the total population dose using Attachment 8, Estimation of Total Population Dose.
7.0 FINAL CONDITIONS 7.1 Dose assessment personnel have been relieved of all emergency support duties.
7.2 All equipment and supplies have been returned to their normal storage locations.
7.3 Records have been collected and forwarded to the Emergency Preparedness Unit which will subsequently forward them to Nuclear Records Management.
I I
7 RA-EP-02240 Revision 01 8.0 RECORDS 8.1 The following quality assurance records are completed by this procedure and shall be listed on the Nuclear Records List, captured, and submitted to Nuclear Records Management in accordance with NG-NA-00106:
- '8.1.1 Printouts from the Dose Assessment computer program 8.1.2 Offsite Dose Nomograms
- 8.1.3 Data Sheet 1:
Total Effective Dose Equivalent (TEDE) Rate 8.1.4 Data Sheet 2:
Thyroid Dose Rates from Radioiodines 8.1.5 Data Sheet 3:
Release Rate from Main Steam Line Monitor Readings 8.1.6 Data Sheet 4:
Release Rates from Noble Gases and Radioiodines Using Primary Parameters 8.1.7 Data Sheet 5:
Release Rate from Unisolated Once Through Steam Generator (OTSG) Steam Sample 8.1.8 Data Sheet 6:
Release Rates from Steam Jet Air Ejector (SJAE) Releases 8.1.9 Data Sheet 7:
Estimated Release Rate with Solid OTSG 8.1.10 Attachment 5: Calculations for Containment Releases Using RE4596A or4596B 8.1.11 Attachment 6: Release Rate Calculations for Releases from Containment Using RE 4597 AB or RE 4597 BB 8.1.12 Attachment 7: Dose Projections Based on Field Monitoring Data 8.1.13 Attachment 8: Estimation of Total Population Dose 8.2 The following non-quality assurance records are completed by this procedure and may be captured and submitted to Nuclear Records Management, in accordance with NG-NA-00106:
8.2.1 None
8 RA-EP-02240 Revision 01 ATTACHMENT 1: DOSE CALCULATIONS USING SPDS Page 1 of 2 NOTE Ensure that the correct instrument is selected. The Drop Down boxes allow different instruments to be selected.
Instrument readings that are applicable to the selected release paths will appear.
Some instrument readings do not have a corresponding computer point. These inputs require manual entry per Section B, using Manual Inputs.
A.
USING COMPUTER INPUTS
- 1.
CLICK the Release Path(s) determined in Step 6.1.1
- 2.
VERIFY instrument readings for the Release Path(s) selected are correct.
- a.
IF instrument readings are not displayed or appear incorrect, (1)
VERIFY the computer selection box is checked for the instrument.
(2)
VERIFY the correct instrument(s) is selected.
(3)
IF the instrument reading is now correct, GO TO step A.3.
(4)
IF the instrument reading(s) requires manual input, GO TO step B.2.
- 3.
ENTER the hours since reactor trip (0-24) AND PRESS the Enter Key.
- 4.
ENTER the release start (HH:MM) AND PRESS the Enter Key.
- 5.
ENTER the projected release duration (in hours; default is 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) AND PRESS the Enter Key.
- 6.
IF a General Emergency has been declared, THEN click GENERAL EMERGENCY DECLARED
- 7.
REVIEW the Dose, Dose Rates and Protective Action.
- 8.
REFER TO RA-EP-02245, Protective Action Guidelines, to determine protective action recommendations.
- 9.
GO TO step A.3 to repeat dose assessment and protective action calculations, if required.
. 9 RA-EP-02240 Revision 01 ATTACHMENT 1: DOSE CALCULATIONS USING SPDS Page 2 of 2 NOTE...
e
- Ensure that the correct instrument is selected. The Drop Down boxes allow different instruments to be selected.
l
- Instrument readings that are applicable to the selected release paths will appear.
Some instrument readings do not have a corresponding computer point. These inputs require manual entry per Section B using
'Manual Inputs.
B.
USING MANUAL INPUT
- 1.
CLICK the Release Path(s).
- 2.
CLICK the computer selection box for the radiation instrument(s) AND VERIFY that the computer selection box is empty.
- a.
To calculate an' Iodine value when the Station Vent Radiation Monitors (RE4598 AB or RE4598 BB) are in the accident range, perform the following calculation:
Iodine = (NG) x (R)
Where: NG
=
RE4598 AB or RE 4598 BB Channel I or 2 Noble Gas value R
RE4598 I:NG ratio value
- 3.
CLICK the computer selection box for the met tower instruments AND VERIFY that the computer selection box is empty.
- 4.
ENTER the selected instrument reading(s) in the instrument box(s).
- 5.
ENTER the hours since reactor trip (0-24) AND PRESS the Enter Key.
ENTER the release start (HH:MM) AND PRESS the Enter Key.
- 7.
ENTER the projected release duration (in hrs.; default is 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) AND PRESS the Enter Key.
- 8.
IF a General Emergency has been declared, THEN click GENERAL EMERGENCY DECLARED.
- 9.
REVIEW the Dose, Dose Rates and Protective Actions
- 10.
REFER to RA-EP-02245, Protective Action Guidelines, to determine protective action recommendations.
II.
GO TO step B.3 to repeat dose assessment and protective action calculations, if required.
10 RA-EP-02240 Revision 01 ATTACHMENT 2: INSTRUCTIONS FOR OFFSITE DOSE ASSESSMENT NOMOGRAM Page 1 of 2
_____1.
Obtain a Nomogram (Figure 1).
- 2.
Record Name, Date, and Time on the Nomogram.
- 3.
Determine monitor reading:
3.1 IF the release is from the Station Vent, THEN plot the appropriate RE 4598 noble gas reading in pCi/cc on Scale B (AA1BA Channel I - Normal Range, AB/BB Channel I - Mid-Range, or AB/BB Channel 2 - High Range).
3.2 IF the release is from the Main Steam Safety Valve (MSSV), Atmospheric Vent Valve (AVV), or AUXLIARY FEEDWATER PUMP TURBINE (AFPT),
THEN plot the cpm reading of RE 600 or RE 609 in the Gross Mode on Scale B.
- 4.
Determine Total Effective Dose Equivalent (TEDE) rates.
NOTE4.1 Flowrate given on nomogram are conservative values for each release pathway.
4.1 Plot the flow rate on Scale (A).
4.2 Draw a line from the monitor reading on Scale (B) to the flow rate on Scale (A). This line intersects Scale (C) at the release rate.
4.3 Determine stability class, and windspeed.
Resources available for determining stability class and windspeed are:
SPDS Plant Process Computer RTVAX 4.4 Plot stability class on Scale (1).
4.5 Plot windspeed on Scale (2).
4.6 Draw a line from the stability class on Scale (1) to the wind speed on Scale (2). This line intersects Scale (3) at the x/Q value.
4.7 Draw a line from the release rate on Scale (C) to the y/Q value on Scale (3).
This line intersects Scale (4) at the TEDE rate for the Site Boundary (0.75 miles).
4.8 Determine TEDE rates at 2, 5, and 10 miles by dividing the Site Boundary TEDE rate by 5, 15, or 40.
4.9 IF the 0.75 mile dose for the release is 2 I rem TEDE, REFER TO RA-EP-02245, Protective Action Guidelines, to determine protective action recommendations.
1 1 RA-EP-02240 Revision 01
.ATTACHMENT 2: INSTRUCTIONS FOR OFFSITE DOSE ASSESSMENT NOMOGRAM Page 2 of 2 Figure 1. Offsite Dose Assessment Nomogram Offsite Dose Assessment Nomogram s~
F
-IJ'~~~~1s..
AlZ A
A X
.4.::.
S.--wue-IATSIM 0
471AT0
12 Ri Re ATTACHMENT 3: STATION VENT RELEASE CALCULATIONS Page 1 of 6 I
NOTE k-EP-02240
- vision 01 I
The following Total Effective Dose Equivalent (TEDE) calculation is based solely on Noble Gas. The contribution from radioiodides and particulates have been neglected to expedite calculations.
CAUTION Use DATA SHEET I and DATA SHEET 2 for dose calculation only if SPDS is not available.
DATA SHEET 1: TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE) RATE
- 1.
Record the date and time Date Time_
- 2.
Record the appropriate Noble Gas activity from RE 4598 in Step 4.
(AA/BA Channel I - Normal Range, AB/BB Channel I - Mid Range, or AB/BB Channel 2 - High Range).
- 3.
Record the Unit Vent flow rate from Computer Point F885 (or F883) in Step 4.
- a.
IF flow rate is NOT available, THEN use 146 KCFM AND contact the TSC to verify the flow rate.
- 4.
Calculate the estimated release rate for Noble Gas by multiplying the values below and entering in Column (E) of Table 2.
_ x KCFM x 0.472 c CCi Ci cc scc.KCFM-pCi ScC (From 2.)
(From 3.)
(Release Rate)
- 5.
Record the wind speed.
Convert the wind speed to m and enter in Column (C) of Table 2.
sec mph x 0.447 mr/sec =
m mph scc Wind)
{Wind)
(Speed)
Speedj
. 1
13 RA-EP-02240 Revision 01 ATTACHMENT 3: STATION VENT RELEASE CALCULATIONS Page 2 of 6 DATA SHEET I (Cont.)
Table 1. x.U (m2) for Stability Classes as a Function of Downwind Distances Q
STABILITY CLASS MILES A
B C
D E
F G
0.75 2.1E-6 1.4E-5 3.5E-5 9.9E-5 2.OE-4 4.5E-4 4 1.3E-3 2
L.IE-7 2.OE-6 5.8E-6
- 2.2E-5 4.6E-5 1.0E-4 2.8E-4 5
7.1 E-9 3.2E-7
.lIE-6 5.5E-6 1.3E-5 3.1E-5 8.2E-5 10 8.9E-10 8.OE-8 3.2E-7 2.OE-6 5.IE-6 I.3E-5 3.4E-5
- 6.
Record Stability Class. (circle one) A B C D E F G (From Attachment 9)
- 7.
Using Table I of this attachment, enter XU (m:) at distances of 0.75, 2, 5, and 10 miles Q
for the Stability Class circled above in Column (B) of Table 2.
- 8.
In Table 2, divide Column (B) by Column (C), and enter result in Column (D).
- 9.
In Table 2, multiply Column (D) by Column (E) and enter result in Column (F).
- 10.
Determine the appropriate Noble Gas Correction Factor from Table 3 and enter result in Column (G) of Table 2.
- 11.
Multiply Column (F) by Column (G) and enter in Column (H) of Table 2.
Table 2. Total Effective Dose Equivalent (TEDE) Rate Column (A)
Column (B)
Column (C)
Column (D)
Column (E)
Column (F)
Column (G)
Column (H)
Downwind Release Noble Gas Noble Gas TEDE Distance xV (m 2)
Windspeed Q
Rate conc.
Correction Rate (Miles)
Q (sec)
(sec (ac)
(P)
Factor (Rem)
From From From From N/A Table 1 Step 5 B/C=D Step 4 DxE=F Table 3 FxG=H 0.7 5 2.00 15.00
=
1 0.0 0
14 RA-EP-02240 Revision 01 ATTACHMENT 3: STATION VENT RELEASE CALCULATIONS Page 3 of 6 DATA SHEET I (Cont.)
Table 3. Noble Gas Correction Factor (NGCF)
(Round time to the nearest value)
- 1.
IF fuel damage or cladding failures have occurred, THEN use the following Table to obtain the Noble Gas Correction Factor (NGCF).
OTHERWISE, use 10.0 for the Noble Gas Correction Factor (NGCF).
Hours After NGCF Hours After NGCF Reactor With Fuel Reactor With Fuel Shutdown Damage Shutdown Damage 0
1540 31 22.8 0.5 892 32 22.6 673 33 22.4 1.5 565 34 22.2 2
491 35 22.0 2.5 432 36 21.9 3
381 37 21.8 3.5 338 38 21.6 4
301 39 21.5 4.5 268 40 21.4 5
240 41 21.4 6
193 42 21.3 7
158 43 21.2 8
130 44 21.1 9
108 45 21.1 10 90.6 46 21.0 11 77.0 47 21.0 12 66.3 48 20.9 13 57.8 49 20.9 14 51.0 50 20.8 15 45.5 51 20.8 16 41.2 52 20.8 17 37.7 53 20.7 18 34.8 54 20.7 19 32.5 55 20.7 20 30.7 56 - 60 20.6 21 29.1 61 - 65 20.5 22 27.9 66 - 75 20.4 23 26.9 76 - 96 20.3 24 26.0
>97 20.2 25 25.3 26 24.7 27 24.2 28 23.8 29 23.4 30 23.1
15 RA-EP-02240 Revision 01 ATTACHMENT 3: STATION VENT RELEASE CALCULATIONS Page 4 of 6
~~~~~NOTE The following Thyroid calculation is based on the inhalation pathway for radioiodides. The external dose from radioiodide is neglected to expedite calculations.
DATA SHEET 2:
THYROID DOSE RATES FROM RADIQIODIDES
- 1.
Record the date and time Date Time
- 2.
Record the value of 1-131 activity from Channel 3 of RE 4598 AA/BA in Step 4.
- a.
Noble gases can make the 1-131 reading falsely high. Request that Radiation Protection personnel verify the 1-131 reading.
- b.
IF the release continues, THEN insert a silver zeolite cartridges into RE 4598 AA or RE 4598 BA.
- c.
IF the RE 4598 AA/BA Iodine-131 reading exceeds 3.0E 2 pCi/cc, THEN request that RP personnel provide the 1-131 concentration.
- 3.
Record the Unit Vent flow rate from Computer Point F885 (or F883) in Step 4.
- a.
IF flow rate is NOT available, THEN use 146 KCFM AND contact the TSC to verify the flow rate.
- 4.
Calculate the estimated release rate of 1-131 by multiplying the values below and enter in Column (E) of Table 5.
ici x _KCFM x 0.472 ccCi
=
ec cc sec*KCFM-pCi sec (From 2.)
(From 3.)
(Release Rate)
- 5.
Record the wind speed.
Convert the wind speed to me and enter in Column (C) of Table 5.
sec
-mph x 0.447 rnsec mph sec (Wind)
{Wind) kSpecd)
SpZe)
16 RA-EP-02240 Revision 01 ATTACHMENT 3: STATION VENT RELEASE CALCULATIONS Page 5 of 6 DATA SHEET 2 (Cont.)
Table 4. x.! (m-2) for Stability Classes as a Function of Downwind Distances Q
STABILITY CLASS MILES A
B C
D E
F G
0.75 2.1 E-6 1.4E-5 3.5E-5 9.9E-5 2.OE-4 4.5E-4 1.3E-3 2
- 1. IE-7 2.OE-6 5.8E-6 2.2E-5 4.6E-5 3.01E4 2.8E-4 5
7.1 E-9 2.IE-6 1.1 E-6 1.2E-5 4.3E-5 3.1 E-5 8.2E-5 10 8.9E-10 8.OE-8 3.2E-7 2.OE-6
- 5. IE-6 1.3E-5 3.4E-5 6.
Record Stability Class (circle one) A B C D E F G (From Attachment 9).
- 7.
Using Table 4. of this attachment, enter x.' (m-2) for the Stability Class in step 6, at distances of 0.75, 2, 5, and 10 miles in Column (B) of Table 5.
- 8.
In Table 5, divide Column (B) by Column (C), and enter in Column (D).
- 9.
In Table 5, multiply Column (D) by Column (E) and enter in Column (F).
- 10.
Determine the appropriate Radioiodide Correction Factor from Table 6 and enter in Column (G) of Table 5. Multiply Column (F) by Column (G) and enter in Column (H) of Table 5.
Table 5. Thyroid Dose Rate Column (A)
Column (B)
Column (C)
Column (D)
Column (E)
Column (F)
Column (G)
Column (H)
X Release Radioiodide Thyroid Downwind Windspeed Q
Rate conc.
Radioiodide Dose Rate Distance X9 (ma2)
(C (C)
(.Ci' Correction Rem (Miles)
Q
\\sec) m sTc C cc )
Factor.hr)
From From From From N/A Table 4 Step 5 B/C=D Step 4 DxE=F Table 6 FxG=H 0.75
=
2.00 5.00 10.00
17 RA-EP-02240 Revision 01 ATTACHMENT 3: STATION VENT RELEASE CALCULATIONS Page 6 of 6 Table 6. Radioiodine Correction Factor (Round time to the nearest value)
Hours After Reactor Correction Shutdown Factor 0
2.88 E+06 0.5 2.86 E+06 1
2.83 E+06 1.5 2.81 E+06 2
2.79 E+06 2.5 2.77 E+06 Hours After Reactor Correction Shutdown Factor Hours After Reactor Shutdown Correction Factor 26 27 28 29 30 31 32 33 34 35 2.25 E+06 2.24 E+06 2.23 E+06 2.22 E+06 2.21 E+06 2.19 E+06
- 2.18 E+06 2.17 E+06 2.16 E+06
- 2.15 E+06 65 - 67 1.97 E+06 68 - 70 1.96 E+06 71 - 73 1.95 E+06 74 - 77 1.94 E+06 78 - 81 1.93 E+06 82 - 86 1.92 E+06 3
3.5 4
4.5 5
2.75 E+06 2.73 E+06 2.71 E+06 2.70 E+06 2.68 E+06 5.5 6
6.5 7
7.5 8
8.5 9
9.5 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 2.67 E+06 2.65 E+06 2.64 E+06 2.62 E+06 2.61 E+06 2.59 E+06 2.58 E+06 2.57 E+06 2.55 E+06 2.54 E+06 36 37 38 39 40 41 42 43 44 45 2.14 E+06 2.14 E+06 2.13 E+06 2.12 E+06 2.11 E+06 2.10 E+06 2.10 E+06 2.09 E+06 2.08 E+06 2.07 E+06 87 - 92 93 -98 1.91 E+06 1.90 E+06 99 - 107 1.89 E+06 108 - 118 1.88 E+06 119-135 1.87E+06 136 - 173 1.86 E+06 46 - 47 2.06 E+06 2174 1.85 E+06 2.52 E+06 2.49 E+06 2.47 E+06 2.45 E+06 2.43 E+06 2.41 E+06 2.39 E+06 2.37 E+06 2.36 E+06 2.34 E+06 2.32 E+06 2.31 E+06 2.29 E+06 2.28 E+06 2.27 E+06 48 - 49 2.05 E+06 50 - 51 2.04 E+06 52 - 53 2.03 E+06 54 - 55 2.02 E+06 56 - 57 2.01 E+06 58 - 59 2.00 E+06 60 - 61 1.99 E+06 62 - 64 1.98 E+06
18 RA-EP-02240 Revision 0 1 ATTACHMENT 4: SECONDARY SIDE RELEASE CALCULATIONS Page I of 9
- 1.
IF the release is from more than one point (for example: AFPT and SJAE),
THEN add the dose rates from each point to obtain the total dose rate.
- 2.
For Main Steam Safety Valve (MSSV), Atmospheric Vent Valve (AVV), and Auxiliary Feedwater Pump Turbine (AFPT) releases, determine which parameters are available as calculation inputs.
- a.
IF primary system parameters are available THEN REFER TO DATA SHEET 4.
- b.
IF main steam line monitors (RE 600/RE 609) are available, THEN REFER TO DATA SHEET 3.
- c.
IF the Once Through Steam Generator (OTSG) is solid, THEN REFER TO DATA SHEET 7.
- d.
IF an OTSG steam sample is available, THEN REFER TO DATA SHEET 5.
- 3.
IF a Steam Jet Air Ejector (SJAE) release occurs AND the Station Vent monitors are functioning, THEN perform Station Vent calculations using DATA SHEET I and DATA SHEET 2 of.
- 4.
IF a SJAE release occurs, AND the Station Vent monitors are NOT functioning, THEN REFER TO DATA SHEET 6.
19 RA-EP-02240 Revision 01 ATTACHMENT 4: SECONDARY SIDE RELEASE CALCULATIONS Page 2 of 9 DATA SHEET 3 Release Rate from Main Steam Line Monitor Readinps a-------------------------- ---
NOTE The release rates estimated using this method are gross approximations. More accurate release rates may be determined by using RCS activity and estimated primary to secondary leak rates.
~~~~NOTE RE 609 (Computer Point R787) is for OTSG No. 1, and RE 600 (Computer Point R788) is for OTSG No. 2 Recrd he at an tie Dte__________________Tie________________________l
- 1.
Record the date and time Date Time
- 2.
Record average steam flow rate in Ibm/hr.
- a.
Consult TSC Engineers.
- b.
IF a Main Steam Safety Valve (MSSV) or Atmospheric Vent Valve (AVV) release is occurring, THEN use Table 1. of this attachment.
- c.
IF an Auxiliary Feedwater Pump Turbine (AFPT) release is occurring, AND duration of release is less than one hour, THEN use 4.4 E4 Ibm/hr OTHERWISE Contact TSC Engineers for release rates from AFPT lasting longer than one hour.
- d.
Record in Step 6.
- 3.
Verify that the Analyze/Gross Mode Switch of RE 600 or RE 609 is in the GROSS MODE position.
- 4.
Calculate net reading of RE 600 or RE 609 (circle one)
- 300 cpm =
cpm RE 600 or RE 609 (circle one)
- 5.
Calculate radionuclide concentration in the steam by multiplying the net RE 600 or RE 609 reading by the value obtained from Figure I of this attachment.
--Cpm x________
______Pci cc (From 4.)
(Figure 1 value)
- 6.
Calculate Release Rate by multiplying the steam flow with the activity concentration then by the given correction factor.
Ibm pC' x 3.5 E-6 Ci (FromX
~
c S,
(ec (From 2.)
(From 5.)
(Release Rate)
20 RA-EP-02240 Revision 01 ATTACHMENT 4: SECONDARY SIDE RELEASE CALCULATIONS Page 3 of 9 DATA SHEET 3 (Cont.)
Release Rate From Main Stream Line Monitor Readings
- 7.
Perform one of the following:
- a.
Insert the Release Rate into Step 4 of DATA SHEET I of Attachment 3 and complete DATA SHEET 1.
- b.
Plot the noble gas release rate on scale (C) of the Offsite Dose Assessment Nomogram and complete Attachment 2, Instructions for Offsite Dose Assessment Nomogram.
Table 1. Average Main Steam Safety Valve (MSSV) Flow Rate vs. Time After Reactor Trip Minutes after Reactor Trip Average Steam Flow Rate
( Ihm 2
3 4
5 6
8 10 15 20 9.00 E5 7.00 E5 5.97 E5 5.37 E5 4.97 E5 4.70 E5 4.30 E5 4.00 E5 3.59 E5 3.34 E5 25 30 35 40 50 3.15 E5 3.00 E5 2.89 E5 2.78 E5 2.59 E5
>60 2.42 E5
21 RA-EP-02240 Revision 01 ATTACHMENT 4: SECONDARY SIDE RELEASE CALCULATIONS Page 4 of 9 DATA SHEET 4 Release Rates from Noble Gases and Radioiodides Using Primary Parameters NOTE I
I I 2 IIIIII II I
IIaI, 2I DATA SHEET 4 assumes all activity leaking from the Primary is released to atmosphere.
This assumption is accurate if steam is being released directly from the OTSG via an open Main Steam Safety Valve (MSSV), an open Atmospheric Vent Valve (AVV), an unisolable steam leak to the atmosphere, or if the affected Once Through Steam Generator:
(OTSG) is being used to supply Auxiliary Feed Pump Turbines. In other cases, the calculation is conservative.
Place emphasis on the latest leak rate as it will vary throughout the transient. The latest leak rate can be obtained by monitoring safety injection flow rate (i.e., HPI and Makeup).
7 ----------
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - -~~~~~~~~~~~~~~~~~~~~
- 1.
Record the date and time.
Date Time
- 2.
Obtain the primary to secondary leak rate in gpm from the TSC engineers or EOF Operations Advisor and record in Step 4.
- 3.
Obtain the latest Reactor Coolant I-13 land Xe-133 concentration ( ici) cc
- a.
IF fuel damage is NOT indicated, AND activity concentrations are NOT known, THEN obtain pre-trip values from the Emergency RP Manager, and multiply the 1-131 value by 10 (to account for Iodine spiking).
- b.
IF fuel damage is indicated, AND activity concentrations are'NOT known, THEN obtain estimates from TSC Operations Engineers.
- c.
Record in Step 4.
- 4.
Calculate the Release Rate.
Radioiodine: _
gpm x PCi x 6.3E-5= _Ci cc sec (From 2)
(1-131)
(Release Rate)
Noble Gas: _
gpm x __
x 6.3E-5 =
cc sec (From 2)
(Xe-133)
(Release Rate)
- 5.
Perform one of the following:
- a.
Insert the Noble Gas Release Rate into Step 4 of DATA SHEET I of and complete DATA SHEET 1.
- b.
Insert the 1-133 Release Rate into Step 4 of DATA SHEET 2 of Attachment 3 and complete DATA SHEET 2.
- c.
Plot the Noble Gas Release Rate on scale (C) of the Offsite Dose Assessment Nomogram and complete Attachment 2.
I
22 RA-EP-02240 Revision 01 ATTACHMENT 4: SECONDARY SIDE RELEASE CALCULATIONS Page 5 of 9 DATA SHEET 5 Release Rate from Unisolated OTSG Steam Sample
- 1.
Record the date and time Date Time
- 2.
Determine the total steam flow in Ibm/hr, from the following:
- a.
Consult TSC Engineers.
- b.
IF a MSSV or AVV release is occurring, THEN use Table 1. of this attachment.
- c.
IF an AFPT release is occurring, AND release duration is less than one hour, THEN use 4.4E4 Ibm/hr, OTHERWISE Contact TSC Engineers for release rates from AFPT lasting longer than one hour.
- d.
Record in Step 4.
- 3.
Obtain the Xe-133 or 1-131 concentration (ACi of the OTSG steam sample from the Emergency RP Manager. Record in Step 4. (Sample 110 may be converted directly to (pa provided the sample was analyzed at room temperature.)
- 4.
Calculate the Release Rate by multiplying the steam flow by the concentration then by the correction factor (based on water density).
_ bm x _
x 1.27E-7 =
Ci hr gm sec (From 2.)
(From 3.)
(Release Rate) 5.
Perform one of the following:
- a.
Insert the Noble Gas Release Rate into Step 4 of DATA SHEET I of and complete DATA SHEET 1.
- b.
Insert the 1-131 Release Rate into Step 4 of DATA SHEET 2 of Attachment 3 and complete DATA SHEET 2.
- c.
Plot The Noble Gas Release Rate on scale (C) of the Offsite Dose Assessment Nomogram and complete Attachment 2.
23 RA-EP-02240 Revision 01 ATTACHMENT 4: SECONDARY SIDE RELEASE CALCULATIONS Page 6 of 9 DATA SHEET 6 Release Rate from Steam Jet Air Ejector (SJAE) Releases NOTE SJAE Releases pass through the Station Vent, and will contribute to the Station Vent Monitor Readings.
I I
- 1.
Record the date and time Date
_Time
- 2.
Record the SJAE Noble Gas activity in cpm from RE 1003A or RE 1003B in Step 5.
- 3.
Record the SJAE flow rate in cfm from FI 1002 in Step 5.
- 4.
Choose the appropriate correction factor and record in Step 5.
For RE 1003A, use 1.3 E-1 1
- For RE 100313, use 1.5 E-11I
- 5.
Calculate the Release Rate of Noble gases by multiplying the values below:
- cpmx _
cfmx Ci sec (From 2.)
(From 3.)
(From 4.)
(Release Rate) 6.
Perform one of the following:
- a.
Insert the Release Rate into Step 4 of DATA SHEET I of Attachment 3 and complete DATA SHEET 1.
- b.
Plot The Noble Gas Release Rate on scale (C) of the Offsite Dose Assessment Nomogram and complete Attachment 2.
24 RA-EP-02240 Revision 01 ATTACHMENT 4: SECONDARY SIDE RELEASE CALCULATIONS Page 7 of 9 DATA SHEET 7 Estimated Release Rate with Solid Once Through Steam Generator (OTSG)
NOTE Complete this data sheet for every incident in which the relief valves open. The number of MSSVs open and length of time that they are open may only be obtainable by direct observation.
Record the date and time.
Date Time
- 2.
Calculate the net reading of RE 600 or RE 609 (circle one) cpm - 300 cpm =
cpm (Gross Reading)
(Background)
(Net Reading)
- 3.
Use time after reactor shutdown to determine the Reactor Coolant activity conversion factor from Figure 1.
Pc Record in Step 5 & 7.
ccc
- 4.
Determine flow rate for MSSVs. (Maximum flow rate of each MSSV is 1.46 E5 cc Sec Record in Step 5.
x 1.46E5 cc =
CC number of )
MSSVs open)
- 5.
Determine Release Rate of MSSVs and record in Step 8:
Pci Cc x c
x cpm x 1.0 E-6 Ci -
Ci sec cpm V0 ~t sec (From 4.)
(From 3.)
(From 2.)
(Release Rate)
- 6.
Determine flow rate for AVVs: (Check one), and record in Step 7.
E One AVV open 9.5 E4 cc El Two AVVs open 1.9 E5 cc sec sec
25 RA-EP-02240 Revision 01 ATTACHMENT 4: SECONDARY SIDE RELEASE CALCULATIONS Page 8 of 9 DATA SHEET 7
- 7.
Determine Release Rate for AVV and record in Step 8.
cc x CC x
cpmx 1.0E-6 Ci =
Ci sCc
.cpm ci sec (From 6.)
(From 3.)
(From 2.)
(Release Rate)
- 8.
Determine Total Release Rate.
Ci Ci Ci sec +
sec -
scc (From 5.)
(From 7.)
(Total Release Rate)
- 9.
Perform one of the following:
- a.
Insert the Release Rate into Step 4 of DATA SHEET 1, Attachment 3 and complete DATA SHEET 1.
- b.
Plot the release rate on Scale (C) of the Offsite Dose Assessment Nomogram and complete Attachment 2.
26 RA-EP-02240 Revision 01 ATTACHMENT 4: SECONDARY SIDE RELEASE CALCULATIONS Page 9 of 9 NORMAL REACTOR COOLANT ACTIVITY (0.1% FAILED FUEL) CONVERSION FACTOR vs. TIME AFTE R SHUTDOWN Hours after Shutdown
)ICiVCC cOM 0
9.00E-06 0.5 1.20E-05 1
1.42E-05 1.5 1.70E-05 2
1.95E 05 2.5 2.30E-05 3
2.75E-05 3.5 3.30E-05 4
3.95E-05 4.5 4.80E-05 5
5.70E-05 5.5 6.80E-05 6
8.20E-05 6.5 9.50E-05 7
1.10E-04 7.5 1.27E-04 8
1.50E-04 Hours after Shutdown 8.5 9
9.5 10 10.5 11 11.5 12 12.5 13 13.5 14 14.5 15 15.5 16 wICifcc cpm 1.75E-04 2.02E-04 2.40E-04 2.80E-04 3.40E-04 3.90E-04 4.60E-04 5.30E-04 6.20E-04 7.02E-04 8.14E-04 9.50E-04 1.10E-03 1.25E-03 1.40E-03 1.60E-03 Hours after Shutdown 16.5 17 17.5 18 18.5 19 19.5 20 20.5 21 21.5 22 22.5 23 23.5 24 ACi/cc cpm 1.75E-03 1.95E-03 2.15E-03 2.45E-03 2.70E-03 3.00E-03 3.45E-03 3.75E-03 4.20E-03 4.55E-03 5.10E-03 5.60E-03 6.10E-03 6.60E-03 7.20E-03 8.00E-03 FIGURE 1.
C,.
10-2 10-3 10-'
1:
1 20 2I.
1lout S
27 RA-EP-02240 Revision 01 ATTACHMENT 5: CALCULATIONS FOR CONTAINMENT RELEASES USING RE 4596A OR RE 4596B Page 1 of 6 NOTE Obtain containment radiation level from SPDS, Radiation Trends.
R Obtain containment pressure from SPDS, Containment Trends, or by accessing CRT DISPLAYS: points P314, P315, P316, and P317.
- CAUTION, Use this attachment for the following conditions only:
Station Vent Monitors are 'not available or s
It is known that the release is bypassing the Station Vent Monitors.
Record the date and time Date Time
- 2.
Determine the containment radiation level: RE 4596A or RE 4596B (Circle one) and record in Step 6.
Rem hr
- 3.
Determine the elapsed time since the reactor was tripped or a significant downpower maneuver occurred (i.e., greater than 30%).
hours
- 4.
IF containment spray is available, Check one THEN use Figure 1, of this attachment, Figure 1. 0l spray available OTHERWISE use Figure 2 of this attachment Figure 2. D no spray available
- 5.
Determine the radiation monitor multiplication factor from Figure I or Figure 2 and record in Step 6.
Xe-133 factor 1-131 factor
- 6.
Determine the uncorrected release rate.
Rem X Ci hr sec (From 2.)
Xe-133 Factor (Xe-133 Release Rate)
(From 5)
Re m X
= _Ci hr ScC (From 2.)
1-13IFactor (1-131 Release Rate)
(From 5)
28 RA-EP-02240 Revision 01 ATTACHMENT 5: CALCULATIONS FOR CONTAINMENT RELEASES USING RE 4596A OR RE 4596B Page 2 of 6 NOTE 7.
The prior calculation assumes the Technical Specification leak rate of 0.5% per' day at 38.0 PSIG. A leak area of 0.13 square inches should be used, unless it is known that additional leak paths from containment exist, and the leak area can be estimated. The calculation provided in Step 7 may be utilized to correct for any leak area or containment pressure.
7.
IF conditions warrant, THEN correct for containment pressure, and leak rate using the following equation:
a.
XE-133 Uncorrected CTMT XE-133 Release Rate Corrected (from 6)
X Leak Area X
Pressure
=
Release Rate
[
sci] X[
[813 in3 Xs ec]
b.
1-131 Uncorrected FCfMT 1-131 Release Rate Corrected (from 6)
X Leak Area X
Pressure
=
Release Rate CL [
[X A ig
[
sec]
~XL [
0.13 In2] ~
38 psig 1
=e
- 8.
Record the wind speed.
Convert the wind speed from mph to m/sec.
mphx 0.447 ml"' -
m mph sec (Wind Speed)
(Wind Speed)
- 9.
Record Stability Class (From Attachment 9)
A B
C D
E F
G (Circle one)
29 RA-EP-02240 Revision 01 ATTACHMENT 5: CALCULATIONS FOR CONTAINMENT RELEASES USING RE 4596A OR RE 45961 Page 3 of 6
- 10.
Using Table 1, enter the x"R (m2) at distances of 0.75, 2, 5, and 10 miles for the Q
Stability Class in step 9 in Column (B) of Tables 2 & 3.
- 11.
Tables 2 & 3, divide Column (B) by Column (C) and enter in Column (D).
- 12.
In Tables 2 & 3, multiply Column (D) by Column (E) and enter in Column (F).
- 13.
Determine the appropriate Noble Gas Correction Factor and enter in Column (G) of Table 2.
IF fuel damage or cladding failures have occurred, THEN, use Table 3 of Attachment 3 to obtain Noble Gas Correction Factor.
Otherwise, use 10.0 for Noble Gas Correction Factor.
Multiply Column (F) by Column (G) and enter in Column (H) of Table 2.
- 14.
Determine the appropriate 1-131 Correction Factor from Table 6 of Attachment 3 and enter in Column (G) of Table 3. Multiply Column (F) by Column (G) and enter in Column (H) of Table 3.
30 RA-EI'-02240 Revision 01 ATTACHMENT 5: CALCULATIONS FOR CONTAINMENT RELEASES USING RE 4596A OR RE 459613 Page 4 of 6 TABLE 1. 7JI (my2) for Stability Classes as a Function of Downwind Distances Q
STABILITY CLASS MILES A
B C
D E
F G
0.75 2.1 E-6 1.4E-5 3.5E-5 9.9E-5 2.0E-4j 4.5E-4 1.3E-3 2
- 1. IE-7 2.0E-6 5.8E-6 2.2E-5 4.6E-5 1.OE4 2.8E4 5
7.1E-9 3.2E-7 I.IE-6 5.5E-6 1.3E-5 3.1 E-5 8.2E-5 10 8.9E-10 8.OE-8 3.2E-7 J 2.OE-6 J 5.IE-61 1.3E-5 J 3.4E-5 T1ABlE 2. Total Effective Dose Equivalent (Tede) Rate Column (A)
Column (B)
Column (C)
Column (D)
Column (E)
Column (F)
Column (G)
Column (H)
Downwind x
Release Nobel Gas TEDE Distance Windspeed Q
Rate Conc.
Noble Gas Rate (Miles) xR (m)2)
( WC).
Correction (hrm)
(MM-0 -Cmi)
Lcc-)
Factor khr)
From From From From Att. 3 N/A Table I Step8 B/C=D Step7 DxE=F Table3 FxG=H 0.75 2.00 5.00 10.00 TABLE 3. Thyroid Dose Rate Column (A)
Column (B)
Column (C)
Column (D)
Column (E)
Column (F)
Column (G)
Column (H)
Downwind x
Release 1-131 Thyroid Distance Windspeed Q
Rate Conc.
1-131 Dose Rate (Miles)
/JL.2) c
(. c)
(sc)
(cc)
Correction (Rem)
(M' M (AM-0 (V~sec t~C)
Factor h
From From From From Att. 3 N/A Table I Step8 B/C=D Step7 DxE=F Table6 FxG=H 0.75 5.00 1 0.0 0
(.
(.
(.
CTMT Rad Monitor Multiplication Factor for Release Rate
-3 with C Spra Available 10 i i -i-i -4Li il 151 I
i I I I 11 I L I..
1... L.. r. I I
?..
= T+
Calculation
~ Xe-133 0-'4
.0 0
t:
Lo O'~
.a f,
0
-N--4a-
........... ---. I.....-.... -
- -
- I
.I 10.4 4 5 i i i MI i il i i i 1 1,111-11 1 1 I 1-1 1-1 1 1 Mr! 1 1 1 1-1 11 I 1 1-1 1 II 1 il I-131 91 0
0%
0%
0 0%
0 z
0 z
m z
-1 C,,
1 ii g
4_,,,
-I.
-1 1 1111-1
-6 1 i:I I
L -
I I
I I-I I
I I
I I
I I -I 10
=
m-_ z
.===
i 21: 1 1 1 1 1 f I I L.-le-I I I I I 17IM1kHI 1HIIIIHt I
I
.7 10 II I
0 2
4 6
81 l0 12 14 16 18 20 22 24 Time (Hours) 0 V
m zM C'>"z 4 1
C:: 0%
M~~
Ci2
- o m
F.0
(
'33 RA-EP-02240 Revision 01 ATTACHMENT 6: CALCULATIONS FOR CONTAINMENT RELEASES USING RE 4597 AB OR RE 4597 BB Page I of I
- 1.
Record the date and time.
Date Time r---------------------------N-
--T-- ----__---------------------
l
~~~~~NOTE 2 Obtain containment Noble Gas concentration from SPDS Radiation Trends.
a Obtain containment pressure from SPDS, Containment Trends; or by accessing CRT DISPLAYS: points P314, P315, P316 and P317.
- 2.
Determine the Containment Noble Gas concentration from RE 4597 AB (Ch. I or Ch. 2) OR RE 4597 BB (Ch. I or Ch.2)
(Circle instrument and channel used)
AND enter Containment Noble Gas concentration in Step 5.
Pci cc
- 3.
Determine the containment pressure in psia and convert to psig, if necessary.
psia - 14.7 =
psig
- 4.
Determine the Containment Leak Rate Fraction by multiplying the square root of containment pressure in PSIG times 8.3 E4 and enter in Step 5.
psig x 8.3 E-4 =
leak rate (From 3.)
(fraction per day)
IF Containment pressure cannot be obtained, THEN use 5.0 E-3 leak rate fraction per day and enter leak rate fraction in Step 5.
- 5.
Determine the Release Rate from containment.
0.928 cc Ci x
x ci Ci sec lICi cc sec (From 4)
(From 2)
(Release Rate)
- 6.
Perform one of the following:
- a.
Insert the Noble Gas Release Rate into Step 4 of DATA SHEET I of and complete DATA SHEET L
- b.
Plot the release rate on Scale (C) of the Offsite Dose Assessment Nomogram and complete Attachment 2.
34 RA-EP-02240 Revision 01 ATTACHMENT 7: DOSE PROJECTIONS 13ASED ON FIELD MONITORING DATA Page I of 4 NOTE This calculation does not include that contribution to TEDE from radioiodide internal exposure. The maximum amount of difference' associated with this assumption is 3% of the total.
TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE)
I.
Record date and time.
Date Time
- 2.
Record the distance downwind that the sampling location lies from the release point (to the nearest 1/2 mile) miles.
- 3.
Record Stability Class (From Attachment 9, Meteorological Data, Step 4)
(circle one)
A B
C D E F G
- 4.
Record survey meter reading (closed-window). (A) mREM fir Record 0.75 mile, 2 mile, 5 mile, 10 mile values in Column (A) of Table 1.
- 5.
Record 74 (meter 2) value at the sampling location (from Table 4. of this attachment).
Q (B)______
Record 0.75 mile, 2 mile, 5 mile, 10 mile values in Column (B) of Table 1.
- 6.
Record X' (m 2) values for 0.75, 2, 5, and 10 miles in column (C) (from Table 4. of this Q
attachment).
- 7.
Divide (A) by (B) and multiply by (C) then divide by 1000 to obtain the TEDE rate for each downwind distance below and record in Column (D).
I Table 1. TEDE Rate (A)
(B)
(C)
(D) mRE.M1 7'
(.n 2)
XZ (m2)
REM hr Q
~
m)h Downwind From Step 4 From Step 5 From Table 4 (A) x C + 1000 = REMT Distance B
fir 0.75 mile 2 mile 5 mile ok
_ X_____X__
10 mile
35 RA-EP-02240 Revision 01 ATTACHMENT 7: DOSE PROJECTIONS BASED ON FIELD MONITORING DATA Page 2 of 4 THYROID DOSE RATE (CDE)
I 3
4 Record date and time.
Date Time Record sample:
start time.
stop time.
Record net reading of air sampler cartridge net cpm.
Record air sampler flow rate CFM.
Record sample collection time ____-_____minutes.
Determine Sample volume CFM x minutes =
ft3 Flowrate Collection Time (Total Volume)
(From 4.)
(From 5.)
ACi 0
- 7.
Multiply the net cpm reading by 4.2 E-9 'c and divide by the sample volume.
CPM net cpm x 4.2 E-9 +
_ ft =
cc Net Reading Sample Volume (Iodine Air Conc.)
(From 3.)
(From 6.)
- 8.
Record the distance downwind that the sampling location lies from the release point (to the nearest 1/2 mile) _
miles.
- 9.
Record Stability Class (from Attachment 9, Meteorological Data, Step 4)
(circle one) A B
C D E F G
- 10.
Multiply Iodine Air Concentration by the appropriate correction factor from Table 6. of to obtain Thyroid Dose Rate at sampling location.
pci x (A)_
from Table 6.
(From 7) of Attachment 3.
Record above value (A) in Column A of Table 2.
I.
Record Xu` (ma2) value at the sampling location (from Table 4. of this attachment)
Q (B)
XI' (m)
Q Record above value (B) in Column B of Table 2.
I
36 RA-EP-02240 Revision 01 ATTACHMENT 7: DOSE PROJECTIONS BASED ON FIELD MONITORING DATA Page 3 of 4
- 12.
Record Ž- (m 2) values for 0.75, 2, 5, and 10 miles in Column (C) (from Table 4. of this Q
attachment).
- 13.
Divide (A) by (B), and multiply times (C) to obtain Thyroid Dose Rate (D)
[Committed Dose Equivalent (CDE)].
Table 2. ThyroidI Dose Rate (CDEtr)
A B
C D
Downwind REM X1(
-n2 XI (m 2)
REM Distance hr
"~-
0 Q
hr From Step 10 From Step 11 From Step 12 (A) XC= REM
~
~
~
~ ~
Bhr 0.75 mile 2 mile 5 m ile 10 m ile
- 14.
Total Organ Dose Equivalent (TODE) to the Thyroid is equal to:
TEDEr +
CDEtr
= TODEtr (REN1/hr)
(REM/hr)
(REM/hr)
TODEtr = Total Organ Dose Equivalent (TODE) to the Thyroid at distance r TEDEr = Total Effective Dose Equivalent (TEDE) at distance r CDEtr = Committed Dose Equivalent (CDE) to the Thyroid at distance r l
Table 3. TODE to the Thyroid Downwind TEDEr CDEtr TODEtr Distance (aREM )
( REM )
( REM )
____hr hr hr 0.75 mile 2 mile 5 mile (10 mile I
I
37 RA-EP-02240 Revision 01 ATTACHMENT 7: DOSE PROJECTIONS BASED ON FIELD MONITORING DATA Page 4 of 4 Table 4..X- (m2 ) for Various Stability Classes as a Function of Distance Stability Class MILES A
B C
D E
F G
0.75 2.IE-6 I.4E-5 3.5E-5 9.9E-5 2.OE4 4.5E-4 1.3E-3 I
9.OE-7 8.OE-6 2.1E-5 6.3E-5 1.3E-4 2.9E4 8.0E-4 1.5 2.6E-7 3.6E-6 9.88E-5 3.3E-5 7.OE-5 1.6E4 4.3E-4 2
L.IE-7 2.OE-6 5.8E-6 2.2E-5 4.6E-5 1.OE4 2.8E-4 2.5 5.7 E-8 1.3E-6 3.9E-6 1.5E-5 3.3E-5 7.7E-5 2.1E-4 3
3.3 E-8 8.9E-7 2.8E-6 1.2E-5 2.6E-5 6.OE-5 1.6E-4 3.5 2.IE-8 6.5E-7 2.1E-6 9.3E-6 2.IE-5 4.9E-5 1.3E4 4
1.4E-8 5.OE-7 1.7E-6 7.6E-6 1.7E-5 4.IE-5 I.1E-4 4.5 9.8E-9 4.OE-7 1.3E-6 6.4E-6 1.5E-5 3.5E-5 9.4E-5 5
7.1 E-9 3.2E-7
.1.1 E-6 5.5E-6 1.3E-5
- 3. 1 E-5 8.2E-5 5.5 5.4E-9 2.7E-7 9.3E-7 4.8E-6
- 1. lE-5 2.7E-5 7.3E-5 6 & 6.5 3.8E-9 2.1E-7 7.5E-7 4.0E-6 9.5E-6 2.3E-5 6.2E-5 7 & 7.5 2.4E-9 1.5E-7 5.6E-7 3.2E-6 7.8E-6 1.9E-5 5.1E-5 8 & 8.5 1.6E-9 1.2E-7 4.5E-7 2.6E-6 6.6E-6 1.7E-5 4.3E-5 9 & 9.5 I.IE-9 9.4E-8 3.7E-7 2.2E-6 5.6E-6 1.5E-5 3.8E-5 10 8.9E-10 8.OE-8 3.2E-7 2.OE-6 5.1 E-6 1.3E-5 3.4E-5
38 RA-EP-02240 Revision 01 A1TACHMENT 8: ESTIMATION OF TOTAL POPULATION DOSE Page 1 of 4 NOTE Use this attachment during Recovery, as a first estimate of Total Population dose from the release.
I.
IF the Safety Parameter Display System (SPDS) is available, GO TO Step 2, SPDS Calculation, OTHERWISE, GO TO Step 3, Manual Calculation
- 2.
SPDS Calculation
- a.
Click the DOSE CALCU tab on the SPDS Process Book
- b.
Double click on the POPULATION DOSE choice
- c.
Select the Total Dose tab and perform the following actions:
(1)
Select desired RE 4598 Channel (A or B)
(2)
Verify Date of Exposure (3)
Verify Time exposure began (HH:MM)
______ (4)
Verify Release duration
______ (5)
Verify Date of Reactor Trip (6)
Verify Time of Reactor Trip (HH:MM)
(7)
Click the CALCULATE DOSE button (8)
Select AUTOMATIC or MANUAL calculations (9)
Select ihe desired sector NOTE 2.c (10):
The number of persons per sector can be obtained from local officials or from the "Development of Evacuation Time Estimates fcr Davis-Besse Nuclear Power Station.
(10)
IF MANUAL was selected in step 2.c. (8)
THEN fill-in the Number of Persons for each Mile column on the TOTAL EFFECTIVE DOSE EQUILAVENT table OTIIERlWISE, N/A this step (I1)
Click the ADD TO CUMULATIVE WORKSHEET button (12)
Repeat steps (9) through (I1) for desired sector(s)
(13)
Select Cum Exposure tab to determine total cumulative dose for selected sector(s)
(14)
To clear Cumulative Exposure Worksheet:
(a)
Select Total Dose tab (b)
Click the CLEAR CUMULATIVE WORKSHEET button
39 RA-EP-02240 Revision 01 ATTACHMENT 8: ESTIMATION OF TOTAL POPULATION DOSE Page 2 of 4 NOTE Use this attachment during Recovery, as a first estimate of Total:
Population dose from the release
- 3.
Sector Worksheet Instructions
- a.
Record Total Effective Dose Equivalent (TEDE) or thyroid dose rate for a given release in REM/hr in Column (A).
(1)
Use the 0.75 mile TEDE and thyroid dose rates for the 0-2 mile population, the 2 mile TEDE and thyroid dose rates for the 2-5 mile population, and the 5 mile TEDE and thyroid dose rates for the 5-10 mile population for conservatism.
- b.
Multiply Column (A) times exposure duration and record in Column (B).
- c.
Record the number of persons in the affected sector for the given distance and time of exposure in Column (C).
(1)
IF an evacuation has occurred, THEN local officials may have the number of individuals remaining in the sector.
(2)
IF an evacuation has not occurred, OR local officials do not have the required information, THEN take the data from "Development of Evacuation Time Estimates for Davis-Besse Nuclear Power Station".
- d.
Multiply Column (B) times Column (C) and record in Column (D).
- e.
Total the Column (D) values.
- f.
Enter the Column (D) values on the appropriate Cumulative Exposure Worksheet, of this attachment.
T40 RA-EP-02240 Revision 01 ATTACHMENT 8: ESTIMATION OF TOTAL POPULATION DOSE Page 3 of 4 1.
2.
3.
Date of exposure:
Sector:
Time exposure began:
Exposure duration:
hours TOTAL EFFECTIVE DOSE EOUIVALENT (TEDE)
(A)
(B)
(C)
(D)
REM Number of Mile hr REM Persons PERSON-REM 2-5 15
-1 0 i
I__
I__
I__
Total Effective Dose Equivalent (TEDE) PERSON-REM_
THYROID (A)
(B)
(C)
(D)
REM Number of Mile hr REM Persons PERSON-REM 02--
2-5
-10
_t___
5-1 I_ __
Total Thyroid PERSON-REM_
41 RA-EP-02240 Revision 01 ATTACHMENT 8: ESTIMATION OF TOTAL POPULATION DOSE Page 4 of 4 Cumulative Exposure Worksheet
- 1.
Record the total PERSON-REM values from each Sector Worksheet. Sum the total PERSON-REM values to obtain the estimated Total Population Dose.
. TEDE Total Thyroid Date/Time/Sector PERSON-REM PERSON-REM
<~~~
_II Total Date Completed Name
42 RA-EP-02240 Revision 01 ATTACHMENT 9: METEOROLOGICAL DATA Page I of 3
- 1.
Obtain 15 minute average meteorological data from any of the following:
Access the SPDS Process Book to access the meteorological data.
Access the DADS nongraphic terminal to call up the meteorological data.
- 2.
IF the systems in Step I cannot be accessed, THEN obtain meteorological data from the following:
- a.
Access data from the Meteorological Tower using the points listed below:
Parameters MET Tower Points Wind Speed, 612' Elevation, in MPH M006 Wind Speed, 827' Elevation, in MPH M005 Wind Direction, 612' Elevation, in degrees M003 Wind Direction, 827' Elevation, in degrees M002 Ambient Temperature, 612' Elevation, in 'F M012 Temp. Differential, 827'-612', in 'F M01I Temp. Differential, 917'-612', in 'F MO 10
- b.
Contact the National Weather Service, or equivalent, using the Emergency Plan Telephone Directory.
- 3.
Use wind speed and wind direction from one of the following elevations of the Meteorology Tower, in order of preference.
- a.
10 meters (612 feet above sea level)
- b.
75 meters (827 feet above sea level)
- c.
100 meters (917 feet above sea level)
- d.
Use conservative wind speed of 2 mph (0.9 m/s).
- 4.
Obtain atmospheric Stability Class from one of the following indicators in order of preference:
- a.
Lower delta T (827'- 612') (see Table 1.)
- b.
Upper delta T (917' - 612') (see Table 2.)
- c.
Standard deviation of wind direction from 10 meter elevation (see Table 3.)
- d.
Use conservative Stability Class of F.
43 RA-EP-02240 Revision 01 ATTACHMENT 9: METEOROLOGICAL DATA Page 2 of 3
- 5.
For Periodic Updates, contact the National Weather Service (NWS), or equivalent, to investigate upcoming weather conditions.
- a.
The NWS telephone number is listed in the Emergency Plan Telephone Directory in the Other Resources Section.
- 6.
IF in the Emergency Operations Facility (EOF),
THEN determine if a lake breeze is occurring by looking for the following simultaneous conditions:
- a.
Calendar date between March 15 and September 15.
- b.
Time of day between sunrise and sunset.
- c.
Wind direction from between 00 to 90°.
- d.
Wind speed less than 12 mph.
- e.
Wind speed decreases with height on Meteorological Tower.
- f.
Stability Class A through D.
- 7.
IF a lake breeze is occurring while an airborne radioactive release is in progress or imminent, THEN the Dose Assessment Coordinator should:
- a.
Inform the Ohio EMA of the lake breeze and that the plume may not follow the course indicated by the Meteorological Tower wind direction.
- b.
Inform the Radiation Monitoring Teams (RMTs) that higher-than-projected dose rates may occur in the plume pathway.
44 RA-EP-02240 Revision 01 ATTACHMENT 9: METEOROLOC;ICAL DATA Page 3 of 3 Table 1. Stability Class from Lower Differential Temperature QtnhilitIl e T)
AT°OTZ/(7S-I V~IL I....I...-S~U
~I.f ~f A
B C
D E
F G
Extremely unstable Moderately unstable Slightly unstable Neutral Slightly stable Moderately stable Extremely stable AT < -2.2
-2.2 <AT < -2.0
-2.0 <AT < -1.7 1.7 <AT < -0.6
-0.6 <AT < 1.7 1.7<AT< 4.6 4.6 <AT Table 2. Stabilitv Class from Upper Differential Temperature Sqt~hilitv (-lacc flpcor~r~nion Pnnn. ATOPH(lM-In~m A
B C
D E
F G
Extremely unstable Moderately unstable Slightly unstable Neutral Slightly stable Moderately stable Extremely stable AT < -3.1
-3.1 <AT < -2.8
-2.8 <AT < -2.5
-2.5 <AT < -0.8
-0.8 <AT < 2.5 2.5 <AT < 6.6 6.6 <AT Table 3. Stabilitv Class from Standard Deviation of Wind Direction Slhii I-Cne R) --o V
. I ISAL" I I't DM[IIALIU.
A B
C D
E F
G Extremely unstable Moderately unstable Slightly unstable Neutral Slightly stable Moderately stable Extremely stable SD > 22.5 22.5 > SD > 17.5 17.5 > SD > 12.5 12.5 >SD> 7.5 7.5 >SD> 3.8 3.8>SD> 2.1 2.1 >SD
45 RA-EP-02240 Revision 01 COMMITMENTS Step Number Reference Comments,
TERMS 0 13593 TERMS 0 13594 TERMS 0 13539 Distance calculation methodology has been reexamined for compatibility with RA-EP-02245 Output data (dose rate) has been made consistent throughout this procedure Dose rates based on CTMT dome monitor and CTMT atmosphere sampling system Step 6.3.3 TERMS 0 14992 Addresses lake breeze TERMS 0 13506 Noble gas correction factor which changes with time after reactor shutdown