Text

Revision 5 to EP-PS-244, Dose Assessment Staffer.
	ML022470236
Person / Time
Site:	Susquehanna
Issue date:	08/23/2002
From:	; Susquehanna
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	EP-PS-244
	Download: ML022470236 (40)
	v • d • e

Aug. 23, 2002 Page 1 of 1 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2002-USER INFORMATION:

EMPL#:23244 CA#: 0363 Phone#: 254-3658 TRANSMITTAL INFORMATION:

TOl A A 08/23/2002 LOCATION: DOCUMENT CONTROL DESK FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)

THE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY

,OR ELECTRONIC MANUAL ASSIGNED TO YOU:

244 - 244 - DOSE ASSESSMENT STAFFER REMOVE MANUAL TABLE OF CONTENTS DATE: 08/08/2002 ADD MANUAL TABLE OF CONTENTS DATE: 08/22/2002 CATEGORY: PROCEDURES TYPE: EP ID: EP-PS-244 REPLACE: REV:5 REPLACE: REV:5 UPDATES FOR HARD COPY MANUALS WILL BE DISTRIBUTED WITHIN 5 DAYS IN ACCORDANCE WITH DEPARTMENT PROCEDURES. PLEASE MAKE ALL CHANGES AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX UPON RECEIPT OF HARD COPY. FOR ELECTRONIC MANUAL USERS, ELECTRONICALLY REVIEW THE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX.

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TAB 7 EP-PS-244-7 MIDAS OPERATING PROCEDURE TABLE OF CONTENTS A. INTRODUCTION/SYSTEM STARTUP 2

"* AIRBORNE DOSE ASSESSMENT FLOWCHART 4

"* EVALUATION OF UNMONITORED RELEASES FROM STATION BLOWOUT PANELS 5

"* SSES BLOWOUT PANEL LOCATIONS 6 B. MENU B: FORWARD CALCULATIONS 7 C. MENU C: EVENT TREE NUREG-1228 CALCULATIONS 12 D. MENU D: DEFAULT ACCIDENT CALCULATIONS 15 E. MENU E-W: BACK CALCULATIONS 18 F. DESCRIPTION OF INFORMATION PROVIDED ON THE MIDAS DOSE

SUMMARY

REPORT 23 G. INFORMATION FOR DISTANCES BETWEEN 10 AND 50 MILES 26 H. ACCIDENT DESCRIPTIONS 27 EP-AD-000-112, Revision 18, Page I of 33

TAB 7 EP-PS-244-7 A. INTRODUCTIONISYSTEM STARTUP K> 1. The following conventions are used in this procedure to describe computer operations:

a. Bold, upper case text (i.e., CURRENT DATE), denotes text which appears on the screen.

b. Underlined, uppercase text (i.e., LOGIN) denotes text to be typed.

c. Bracketed, upper case text (i.e., [ENTER]), denotes special keys which are to be pressed.

d. Most mouse selections can be made with a single click.

"* Single click RESET to cancel previous screen selections.

"* Double click RESET to back out of present menu.

"* Double click to EXIT menu.

2. The met and vent spreadsheet will appear with all of the meteorological and ventilation release rate parameters across the top of the page. The current time period is highlighted in the left-hand column. The first time interval is 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months before the current time and the last time interval is 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months after the current time.

3. All required meteorological and ventilation data for MIDAS can be obtained using the METNENT DATA ACQUISITION OPTIONS tab.

4. To start MIDAS:

a. Turn ON each component (monitor, computer, and printer) of the computer system on which MIDAS is loaded.

b. At the MIDAS logon screen, enter the password MIDAS and [ENTER].

c. At the MIDAS MAIN MENU screen, select A: MIDAS (Dose Calculator) and [ENTER].

d. The system will then display the CURRENT DATE. Ifthe date is correct, press [ENTER]. Ifthis date is incorrect, type the correct date using the format which is illustrated in the prompt and press [ENTER].

e. The system will then display the CURRENT TIME, which is stored in the computer system's clock (24-hour clock format). Ifthe time is correct, press [ENTER]. Ifthis time is incorrect, type the correct time using the format which is illustrated in the prompt and press [ENTER].

EP-AD-000-112, Revision 18, Page 2 of 33

TAB 7 EP-PS-244-7

f. The MIDAS logon screen will now appear for 20 seconds.

g. The ACCIDENT MENU SELECTION screen will appear. Use the AIRBORNE DOSE ASSESSMENT FLOWCHART to select the appropriate calculation option and CONFIRM your selection.

5. To exit MIDAS, double-click EXIT on each menu screen that appears. At the SECURITY MENU, press [F8] to log off.

EP-AD-000-112, Revision 18, Page 3 of 33

TAB7 TAB 7 EP-PS-244-7 AIRBORNE DOSE ASSESSMENT FLOW CHART I

MIDAS DOSE

SUMMARY

DETEFINE RELEASE RATES FROM THE BLOWOLUT PANEL TABLE. USE THEM FOR A REPORT MENU B CALCULA11ON EP-AD-000-112, Revision 18, Page 4 of 33

TAB 7 EP-PS-244-7 EVALUATION OF UNMONITORED RELEASES FROM STATION BLOWOUT PANELS DIRECTIONS

1. Select the appropriate station blowout panel location.

2. Select an appropriate accident source term mix.

3. Use the corresponding design base release rates for input into MENU B.

4. Enter the release rates for one (1) fifteen-minute time period.

NOTE: If Clad Failure or Fuel Melt mixes are selected, multiply the site total noble gas, 1-131, and particulate release rates by the appropriate fraction of clad failure or fuel melt prior to entering the values onto the vent spreadsheet (e.g., the multiplier for 50% FUEL MELT would be 0.5).

[1 ] BLOWOUT PANEL LOCATION [3 ] DESIGN BASIS (SITE TOTAL) RELEASE RATES NOBLE GAS 1-131 '. 2PARTICULATE RCIC PUMP ROOM (pCi/mm) (pCdmin) (pC/min)

[2 ] ACCIDENT SOURCE TERM Normal Reactor Coolant Activity 1.2E+02" 1.8E+02 1.1 E+03 (LOCA) Reactor Depressurization-No FD 2.6E+06 8.4E+04 2.2E+04 (LOCA) 100% Clad Failure 2.1E+09 2.4E+08 9.1E+07 (LOCA) 100% Fuel Melt 4.3E+10 1.3E+09 1.7E+09 HPCI PUMP ROOM (pCi/min) (pCi/min) (pCi/min)

Normal Reactor Coolant Activity. 2.1E+03* 3.2E+03 1.9E+04 (LOCA) Reactor Depressurization-No FD 4.6E+07 1.5E+06 3.8E+05 (LOCA) 100% Clad Failure 3.7E+10 4.3E+09 1.6E+09 (LOCA) 100% Fuel Melt 7.5E+11 2.3E+10 3.OE+10 HPCIIRCIC ROUTING AREA (pCi/min) (JCi/min) (pCi/min)

Normal Reactor Coolant Activity 3.2E+03* 4.9E+03 2.9E+04 (LOCA) Reactor Depressunzation-No FD 7.0E+07 2.2E+06 5.8E+05 (LOCA) 100% Clad Failure 5.7E+10 6.5E+09 2.4E+09 (LOCA) 100% Fuel Melt 1.1E+12 3.5E+10 4.6E+10 RWCU PENETRATION ROOM (pCi/min) (pCi/min) (pCdmin), -

Normal Reactor Coolant Activity 7.3E+03" 5.8E+03 6.6E+04 (LOCA) Reactor Depressunzation-No FD 1.6E+08 2.6E+06 1.3E+06 (LOCA) 100% Clad Failure 1.3E+11 7.6E+09 5.5E+09 (LOCA) 100% Fuel Melt 2.6E+12 4.1E+10 1.0E+11 RB/TB MAIN STEAM TUNNEL (pC/min) (pCu/min) (pCi/mm)

Normal Reactor Coolant Activity 2.6E+04* 3.9E+04 2.3E+05 (LOCA) Reactor Depressurization-No FD 5.6E+08 1.8E+07 4.7E+06 (LOCA) 100% Clad Failure 4.6E+11 5.2E+10 1.9E+10 (LOCA) 100% Fuel Melt 9.1E+12 2.8E+11 3.7E+11 FD = FUEL DAMAGE

Value less than that defining a release (See previous page).

REFERENCE:

EC-RADN-1018, Evaluation of Unmonitored Releases from Station Blowout Panels, Revision 2, File R2-1.

EP-AD-000-112, Revision 18, Page 5 of 33

TAB 7 EP-PS-244-7 SSES BLOWOLUT PANEL LOCATIONS N%

-MAIN STEAM-- -- MAIN STEAM.

-' :TUN7-EL-

.... N-: -: -:: --

TUNNEL: ' -

U2 TURBINE z- L U-: CONTROL " Ul TURBINE STRUCU---STU RE- L - :

BUILDING BUILDING MAIN-STEAM*TUNNEL:

REACTF3oR BUILDING.

AY- -TRUCK -: '. PIPE ROUTING.

":RI/R miA RHRRCICI u*PL/ J [a .R RHR *8: RCIC U AREA T-TUNNEL ACCESS NO HIGH ENERGY PIPING EP-AD-000-112, Revision 18, Page 6 of 33

TAB 7 EP-PS-244-7 B. MENU B: FORWARD CALCULATIONS REQUIRED INPUTS ENGINEERING OR OPERATIONS SUPPORT IS REQUESTED FOR THESE CALCULATIONS.

PLANT CONDITIONS

TIME OF REACTOR SHUTDOWN

RELEASE START TIME

DURATION OF RELEASE

PROJECTION TIME

ACCIDENT SOURCE TERM SELECTION MET DATA S10 MWIND SPEED

10 M WIND DIRECTION

STABILITY CLASS

PRECIPITATION RATE VENT DATA

SITE TOTAL NOBLE GAS RELEASE RATES

SITE TOTAL 1-131 RELEASE RATES

SITE TOTAL PARTICULATE RELEASE RATES

1. The METNENT DATA CONTROL TABLE screen will appear.

a. Select START NEW SCENARIO and then CONFIRM, OR

b. If you have already initiated calculations and wish to modify either the existing met spreadsheet file or vent spreadsheet, select CURRENT SCENARIO EDIT and CONFIRM.

c. Other options are available in the lower right hand section of the display if you wish to RESET or change your initial selection or EXIT the screen.

2. The METEOROLOGICAL DATA spreadsheet will appear with all of the required meteorological parameters across the top of the page. Place the cursor on the data period corresponding to the start of release. Input the following met data:

EP-AD-000-112, Revision 18, Page 7 of 33

TAB 7 EP-PS-244-7 NOTE 1: Ifthe met data remains the same for successive time periods, the operator need only enter the met data once. MIDAS will persist the data to future time periods automatically.

NOTE 2: Any time historical data is being used in MIDAS (i.e., met and vent data entered into the spreadsheets within the two-hour period up to and including the current time), all met and vent data must be manually entered over all affected time periods up to and including the current time.

If a value is to be repeated in a field it can still be manually copied down the spreadsheet using the .K (copy last) key while that value is highlighted.

a. In the column labeled 10M SPD, enter the wind speed from the 10 meter onsite (primary) meteorological tower in MILES PER HOUR (MPH).

NOTE 1: Ifthe primary meteorological tower data is not available, refer to the Met Vent Data Acquisition Options tab for other options.

b. In the column labeled 1OM WD, enter the wind direction from the 10-meter onsite (primary) meteorological tower in DEGREES FROM (DEG FM).

c. In the column labeled STAB CLS, enter the actual value for AT in DEGREES CENTIGRADE (preferred method) or the wind speed corrected stability class (Letter Code) if the primary tower data is not available.

MIDAS will convert the letter entry to a numerical value.

d. In the column labeled RAIN-LMH, enter the precipitation rate in INCHES PER 15 MINUTES (IN/15M). Divide the PICSY precipitation rate (inches/hr) by 4. If the precipitation rate is not available, estimation may be made by using the following table:

NO PRECIPITATION _(zero)

DRIZZLE or MIST LIGHT STEADY RAIN MEDIUM HEAVY DOWNPOUR HEAVY

e. Type X when all data has been entered to save the data and exit out of the meteorological spreadsheet.

3. A WEATHER SELECTION screen will appear if any of the meteorological data inputs are missing from the spreadsheet.

a. If this screen appears, select RESET until you have returned to the METNENT DATA CONTROL TABLE screen.

EP-AD-000-112, Revision 18, Page 8 of 33

TAB 7 EP-PS-244-7

b. Select CURRENT SCENARIO EDIT and enter any missing meteorological values on the spreadsheet.

c. Type X when all data has been entered to save the data and exit out of the meteorological spreadsheet.

4. The vent (GASEOUS VENT AND FLOW) spreadsheet will appear next.

Enter vent data from the START OF RELEASE. The data entry for each 15 minute period is as follows:

NOTE: Vent data may be entered in a regular numerical presentation (10000) or in scientific notation (1.OE+04).

a. In the column labeled TOT NG RELEASE, enter the site total noble gas release rate in p.Ci/min.

b. In the column labeled TOT 1-131 RELEASE, enter the site total 1-131 release rate in pCi/min.

c. In the column labeled TOT P RELEASE, enter the site total particulate release rate in pCilmin.

d. When the data entry is complete, press the X key to save the information and exit the spreadsheet.

5. From the ACCIDENT SOURCE TERM SELECTION screen, select an appropriate accident source term, then CONFIRM. Select RESET if you wish to change your previous selection.

If no specific information on the type of release is available from Engineering, use the following as a guide in the selection of an appropriate accident source term.

a. Obtain Reactor Power from Engineering, Operations or as follows:

1. From PICSY, select Unit #1 or Unit #2 formats to view affected unit

2. Type STA and press [ENTER]

3. "Reactor Power" is in the top left section

4. Click on MET VENT to return to the Met/Vent data display

b. If the reactor is operating at or greater than 10% power, select the ATWS source term.

c. If reactor power is at less than 10%, select the LOCA (Clad Failure) source term.

EP-AD-000-1 12, Revision 18, Page 9 of 33

TAB 7 EP-PS-244-7

d. If conditions indicate a fuel handling incident and a release from the refueling floor (Reactor Building floor 818'), select Fuel Handling Accident.

6. The RELEASE TIMING SELECTION screen will appear next. There are three lines to the screen.

a. On Line 1, select TRIP DATE (date and time of reactor trip). Using the calendar wheel, enter the appropriate date and time of reactor trip.

CONFIRM to close the calendar wheel.

1) The time of reactor trip must be equal to or earlier than the START OF RELEASE.

2) The time of reactor trip can be set up to roughly one year (8,190 hours0.0022 days 0.0528 hours 3.141534e-4 weeks 7.2295e-5 months ) prior to the START OF RELEASE.

NOTE 1: MIDAS assumes the reactor must be shutdown before a release can occur. The TRIP DATE triggers the start of decay for the accident mix.

NOTE 2: Even during an ATWS, where a release is in progress and the reactor has not shut down, a TRIP DATE must be entered to run MIDAS. It is recommended the same date and time for the START OF RELEASE be used for the TRIP DATE.

Entering a date and time for reactor trip has no impact on decay of the ATWS mix.

b. On Line 2, select START OF RELEASE DATE. Using the calendar wheel, enter the appropriate date and time of the start of release.

CONFIRM to close the calendar wheel.

NOTE: The START OF RELEASE is defined as the date and time of the first vent data entry. This time range includes the two-hour period prior to and including the current time.

c. On Line 3, select REMAINING DURATION of the release. Using the NUMPAD enter the duration of r6lease, in minutes, and select EN or press

[ENTER] to close the numpad. If the duration of release is not known, use the default of 360 minutes, except thai for blow-out panel calculations, the assumed release duration is 15 minutes.

NOTE: The REMAINING DURATION (DURATION OF RELEASE) can use forecasted or persisted data for up to 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months into the future.

EP-AD-000-112, Revision 18, Page 10 of 33

TAB 7 EP-PS-244-7

d. Select CONFIRM to continue with the calculation or RESET to change any of your previous choices.

7. The PPL

SUMMARY

DATA SELECTION screen allows the user to select different options for the MIDAS DOSE

SUMMARY

REPORT.

a. Select the projection time from the left-hand column if other than the default of six hours is needed.

b. Select the PEAK SECTOR dose rate option if other than the default CURRENT AFFECTED SECTOR is required; then CONFIRM. Ifyou wish to change any of your previous choices, select RESET.

NOTE: The PEAK SECTOR is used to determine the highest dose rate in all 16 sectors. The CURRENT AFFECTED SECTOR is used to estimate dose rates based on current wind speed and direction.

8. After the calculations have completed, the MIDAS DOSE

SUMMARY

REPORT will be displayed on the screen.

a. Ifyou want to select a different projection time or sector designation from the PPL

SUMMARY

DATA SELECTION screen, select RESTART REPORT.

b. Ifyou wish to view additional report options, select CONTINUE and, on the next page, MORE REPORTS.

c. Ifyou wish to continue with the next calculation, double click EXIT. This will return you to the ACCIDENT MENU SELECTION screen where the dose calculation process can be repeated using updated input values.

d. Ifa hard copy is desired of any printout or plot displayed on the screen, press [PRINT SCRN].

NOTE: If a hard-copy printout is made of the MIDAS DOSE

SUMMARY

REPORT, be sure to fill in the required information documenting the name of the dose calculator, reviewer, and date the calculation was performed.

EP-AD-000-112, Revision 18, Page 11 of 33

TAB 7 EP-PS-244-7 C. MENU C: EVENT TREE NUREG-1228 CALCULATIONS REQUIRED INPUTS ENGINEERING OR OPERATIONS SUPPORT IS REQUESTED FOR THESE CALCULATIONS.

PLANT CONDITIONS

RELEASE PATHWAY

CORE CONDITION

CONTAINMENT CONDITIONS

FILTRATION

PROJECTION TIME MET DATA

10 MWINDSPEED

10 M WIND DIRECTION

STABILITY CLASS

PRECIPITATION RATE

1. The EVENT TREE NUREG-1228 SELECTION screen will appear.

a. Using information provided by Engineering Support or Operations, select one cell in each row of the menu. When a cell in the current row is selected, the next row then appears.

b. [PRINT SCREEN] when final selections are made on the EVENT TREE NUREG-1228 SELECTION screen to document the calculation inputs.

c. CONFIRM entries to continue with the calculation or RESET if you wish to change any of your selections. You may also double-click EXIT to return to the ACCIDENT MENU SELECTION screen.

2. The METNENT DATA CONTROL TABLE screen will appear.

a. Select START NEW SCENARIO and then CONFIRM, OR

b. Ifyou have already initiated calculations and wish to modify the existing met spreadsheet file, select CURRENT SCENARIO EDIT and CONFIRM.

c. Other options are available in the lower right hand section of the display if you wish to RESET your initial entries or EXIT the screen.

EP-AD-000-112, Revision 18, Page 12 of 33

TAB 7 EP-PS-244-7

3. The METEOROLOGICAL DATA spreadsheet will appear with all of the required meteorological parameters across the top of the page.

NOTE: Ensure met data is entered for the current time. MIDAS will persist the data to future time periods automatically.

a. In the column labeled 10M SPD, enter the wind speed from the 10-meter onsite (primary) meteorological tower in MILES PER HOUR (MPH).

NOTE 1: If the primary meteorological tower data is not available, refer to the Met Vent Data Acquisition Options tab for other options.

b. In the column labeled 1DM WD, enter the wind direction from the 10-meter onsite (primary) meteorological tower in DEGREES FROM (DEG FM).

c. In the column labeled STAB CLS, enter the actual value for AT in DEGREES CENTIGRADE (preferred method) or the wind speed corrected stability class (Letter Code) if the primary tower data is not available.

MIDAS will convert the letter entry to a numerical value.

d. In the column labeled RAIN-LMH, enter the precipitation rate in INCHES PER 15 MINUTES (IN/15M). Divide the PICSY precipitation rate (inches/hr) by 4. If the precipitation rate is not available, estimation may be made by using the following table:

NO PRECIPITATION O(zero)

DRIZZLE or MIST LIGHT STEADY RAIN MEDIUM HEAVY DOWNPOUR HEAVY

e. Type X when all data has been entered to save the data and exit out of the meteorological spreadsheet.

4. A WEATHER SELECTION screen will appear if any of the meteorological data inputs are missing from the spreadsheet.

a. Ifthis screen appears, select RESET until you have returned to the METNENT DATA CONTROL TABLE screen.

b. Select CURRENT SCENARIO EDIT and enter any missing meteorological values on the spreadsheet.

c. Type X when all data has been entered to save the data and exit out of the meteorological spreadsheet.

EP-AD-000-112, Revision 18, Page 13 of 33

TAB 7 EP-PS-244-7

5. The PPL

SUMMARY

DATA SELECTION screen allows the user to select different options for the MIDAS DOSE

SUMMARY

REPORT.

a. Select the projection time from the left-hand column if other than the default of six hours is needed.

b. Select the PEAK SECTOR dose rate option if other than the default CURRENT AFFECTED SECTOR is required; then CONFIRM. If you wish to change any of your previous choices, select RESET.

NOTE: The PEAK SECTOR is used to determine the highest dose rate in all 16 sectors. The CURRENT AFFECTED SECTOR is used to estimate dose rates based on current wind speed and direction.

6. After the calculations have completed, the MIDAS DOSE

SUMMARY

REPORT will be displayed on the screen.

a. Ifyou want to select a different projection time or sector designation from the PPL

SUMMARY

DATA SELECTION screen, select RESTART PROGRAM.

b. Ifyou wish to view additional report options, select CONTINUE and, on the next page, MORE REPORTS.

c. Ifyou wish to continue with the next calculation, double click EXIT. This will return you to the ACCIDENT MENU SELECTION screen where the dose calculation process can be repeated using updated input values.

d. If a hard copy is desired of any printout or plot displayed on the screen, press [PRINT SCRN].

NOTE: If a hard-copy printout is made of the MIDAS DOSE

SUMMARY

REPORT, be sure to fill in the required information documenting the name of the dose calculator, reviewer, and date the calculation was performed.

EP-AD-000-112, Revision 18, Page 14 of 33

TAB 7 EP-PS-244-7 D. MENU D: DEFAULT ACCIDENT CALCULATIONS REQUIRED INPUTS ENGINEERING OR OPERATIONS SUPPORT IS REQUESTED FOR THESE CALCULATIONS.

MET DATA

10 MWINDSPEED

10 M WIND DIRECTION

STABILITY CLASS

PRECIPITATION RATE SOURCE TERM 0 ACCIDENT SOURCE TERM SELECTION

PERCENT OF CLAD FAILURE OR FUEL MELT

PROJECTION TIME

1. The METNENT DATA CONTROL TABLE screen will appear.

a. Select START NEW SCENARIO and then CONFIRM.

b. If you have already initiated calculations and wish to modify the existing met spreadsheet file, select CURRENT SCENARIO EDIT and CONFIRM.

c. Other options are available in the lower right hand section of the display if you wish to RESET your initial entries or EXIT the screen.

2. The METEOROLOGICAL DATA spreadsheet will appear with all of the required meteorological parameters across the top of the page.

NOTE: Ensure met data is entered for the current time. MIDAS will persist the data to future time periods automatically.

a. In the column labeled 10M SPD, enter the wind speed from the 10-meter onsite (primary) meteorological tower in MILES PER HOUR (MPH).

NOTE 1: Ifthe primary meteorological tower data is not available, refer to the Met Vent Data Acquisition Options tab for other options.

b. In the column labeled IOM WD, enter the wind direction from the 10-meter onsite (primary) meteorological tower in DEGREES FROM (DEG FM).

EP-AD-000-112, Revision 18, Page 15 of 33

TAB 7 EP-PS-244-7

c. In the column labeled STAB CLS, enter the actual value for AT in DEGREES CENTIGRADE (preferred method) or the wind speed corrected stability class (Letter Code) if the primary tower data is not available.

MIDAS will convert the letter entry to a numerical value.

d. In the column labeled RAIN-LMH, enter the precipitation rate in INCHES PER 15 MINUTES (IN/15M). Divide the PICSY precipitation rate (inches/hr) by 4. If the precipitation rate is not available, estimation may be made by using the following table:

NO PRECIPITATION O(zero)

DRIZZLE or MIST LIGHT STEADY RAIN MEDIUM HEAVY DOWNPOUR HEAVY

e. Type X when all data has been entered to save the data and exit out of the meteorological spreadsheet.

3. A WEATHER SELECTION screen will appear if any of the meteorological data inputs are missing from the spreadsheet.

a. Ifthis screen appears, select RESET until you have returned to the METNENT DATA CONTROL TABLE screen.

b. Select CURRENT SCENARIO EDIT and enter any missing meteorological values on the spreadsheet.

c. Type X when all data has been entered to save the data and exit out of the meteorological spreadsheet.

4. From the ACCIDENT SOURCE TERM SELECTION screen, select an appropriate accident source term, then CONFIRM.

5. A PERCENT FAILURE FOR LOCA screen will appear if the clad failure or fuel melt accident source term is selected. Input the percent of clad failure or fuel melt using the numpad and CONFIRM.

6. The PPL

SUMMARY

DATA SELECTION screen allows the user to select different options for the MIDAS DOSE

SUMMARY

REPORT.

a. Select the projection time from the left-hand column if other than the default of six hours is needed.

b. Select the PEAK SECTOR dose rate option if other than the default CURRENT AFFECTED SECTOR is required; then CONFIRM. If you wish to change any of your previous choices, select RESET.

EP-AD-000-112, Revision 18, Page 16 of 33

TAB 7 EP-PS-244-7 NOTE: The PEAK SECTOR is used to determine the highest dose rate in all 16 sectors. The CURRENT AFFECTED SECTOR is used to estimate dose rates based on current wind speed and direction.

7. After the calculations have completed, the MIDAS DOSE

SUMMARY

REPORT will be displayed on the screen.

a. If you want to select a different projection time or sector designation from the PPL

SUMMARY

DATA SELECTION screen, select RESTART PROGRAM.

b. If you wish to view additional report options, select CONTINUE and, on the next page, MORE REPORTS.

c. If you wish to continue with the next calculation, double click EXIT. This will return you to the ACCIDENT MENU SELECTION screen where the dose calculation process can be repeated using updated input values.

d. If a hard copy is desired of any printout or plot displayed on the screen, press [PRINT SCRN].

NOTE: Ifa hard-copy printout is made of the MIDAS DOSE

SUMMARY

REPORT, be sure to fill in the required information documenting the name of the dose calculator, reviewer, and date the calculation was performed.

EP-AD-000-112, Revision 18, Page 17 of 33

TAB 7 EP-PS-244-7 E. MENU E-W: BACK CALCULATIONS "REQUIRED INPUTS ENGINEERING OR OPERATIONS SUPPORT IS REQUESTED FOR THESE CALCULATIONS.

PLANT CONDITIONS

TIME OF REACTOR SHUTDOWN

RELEASE START TIME

DURATION OF RELEASE

ACCIDENT SOURCE TERM SELECTION

PROJECTION TIME MET DATA S10QMWINDSPEED 0 10 M WIND DIRECTION

STABILITY CLASS

& PRECIPITATION RATE FIELD DATA 0 3 FT (CW) SURVEY METER READING

DISTANCE FROM PLANT

IODINE CARTRIDGE NET CPM OR DEFAULT IODINE MIX

1. The METNENT DATA CONTROL TABLE screen will appear.

a. Select START NEW SCENARIO and then CONFIRM.

b. Ifyou have already initiated calculations and wish to modify the existing met spreadsheet file, select CURRENT SCENARIO EDIT and CONFIRM.

c. Other options are available in the lower right hand section of the display if you wish to RESET your initial entries or EXIT the screen.

2. The METEOROLOGICAL DATA spreadsheet will appear With all of the required meteorological parameters across the top of the page.

NOTE: Ensure met data is entered for the current time. MIDAS will persist the data to future time periods automatically.

a. In the column labeled 10M SPD, enter the wind speed from the 10-meter onsite (primary) meteorological tower in MILES PER HOUR (MPH).

EP-AD-000-112, Revision 18, Page 18 of 33

TAB 7 EP-PS-244-7 NOTE 1: If the primary meteorological tower data is not available, refer to the Met Vent Data Acquisition Options tab for other options.

b. In the column labeled 1DM WD, enter the wind direction from the 10-meter onsite (primary) meteorological tower in DEGREES FROM (DEG FM).

c. In the column labeled STAB CLS, enter the actual value for AT in DEGREES CENTIGRADE (preferred method) or the wind speed corrected stability class (Letter Code) if the primary tower data is not available.

MIDAS will convert the letter entry to a numerical value.

d. In the column labeled RAIN-LMH, enter the precipitation rate in INCHES PER 15 MINUTES (IN/15M). Divide the PICSY precipitation rate (inches/hr) by 4. Ifthe precipitation rate is not available, estimation may be made by using the following table:

NO PRECIPITATION O(zero)

DRIZZLE or MIST LIGHT STEADY RAIN MEDIUM HEAVY DOWNPOUR HEAVY

e. Type X when all data has been entered to save the data and exit out of the meteorological spreadsheet.

3. A WEATHER SELECTION screen will appear if any of the meteorological data inputs are missing from the spreadsheet.

a. If this screen appears, select RESET until you have returned to the METNENT DATA CONTROL TABLE screen.

b. Select CURRENT SCENARIO EDIT and enter any missing meteorological values on the spreadsheet.

c. Type X when all data has been entered to save the data and exit out of the meteorological spreadsheet.

4. From the ACCIDENT SOURCE TERM SELECTION screen, select an appropriate accident source term, then CONFIRM.

If no specific information on the type of release is available from Engineering, use the following as a guide in the selection of an appropriate accident source term:

a. Obtain Reactor Power from Engineering, Operations or as follows:

1. From PICSY, select Unit #1 or Unit #2 formats to view affected unit EP-AD-000-112, Revision 18, Page 19 of 33

TAB 7 EP-PS-244-7

2. Type STA and press [ENTER]

3. "Reactor Power" is in the top left section

4. Click on MET VENT to return to the Met/Vent data display

b. If the reactor is operating at or greater than 10% power, select the ATWS source term.

c. If reactor power is at less than 10%, select the LOCA (Clad Failure) source term.

d. If conditions indicate a fuel handling incident and a release from the refueling floor (Reactor Building floor 818'), select Fuel Handling Accident.

5. The next screen is the FIELD MONITOR PARAMETER SELECTION screen.

Select the appropriate cells and input the information requested using the numpad on the screen or enter the data using the computer keyboard. Once the data entry is complete, CONFIRM to continue with the calculation.

a. Ifair sample data is available, enter either the IODINE CARTRIDGE reading in net counts per minute or an IODINE CONCENTRATION value in pICi/cc. A zero (0) value may be entered for the net count per minute or the pCi/cc measurement, if indicated.

b. Select the DEFAULT MIX option if you wish to characterize the iodine source term when air sample data is not available.

6. On the RELEASE TIMING SELECTION screen, enter the estimated remaining duration for the release, then CONFIRM. If the duration of release is not known, use the default of 360 minutes.

7. The PPL

SUMMARY

DATA SELECTION screen allows the user to select different options for the MIDAS DOSE

SUMMARY

REPORT.

a. Select the projection time from the left-hand column if other than the default of six hours is needed.

b. Select the PEAK SECTOR dose rate option if other than the default CURRENT AFFECTED SECTOR is required; then CONFIRM. Ifyou wish to change any of your previous choices, select RESET.

NOTE: The PEAK SECTOR is used to determine the highest dose rate in all 16 sectors. The CURRENT AFFECTED SECTOR is used to estimate dose rates based on current wind speed and direction.

EP-AD-000-112, Revision 18, Page 20 of 33

TAB 7 EP-PS-244-7

8. After the calculations have completed, the MIDAS DOSE

SUMMARY

REPORT will be displayed on the screen.

a. If you want to select a different projection time or sector designation from the PPL

SUMMARY

DATA SELECTION screen, select RESTART PROGRAM.

b. Ifyou wish to view additional report options, select CONTINUE and, on the next page, MORE REPORTS.

c. Ifyou wish to continue with the next calculation, double click EXIT. This will return you to the ACCIDENT MENU SELECTION screen where the dose calculation process can be repeated using updated input values.

d. Ifa hard copy is desired of any printout or plot displayed on the screen, press [PRINT SCRN].

NOTE: Ifa hard-copy printout is made of the MIDAS DOSE

SUMMARY

REPORT, be sure to fill in the required information documenting the name of the dose calculator, reviewer, and date the calculation was performed.

e. Remote Monitoring System perimeter monitoring location dose rates can be displayed by MIDAS using the perimeter monitoring dose rate screen option.

NOTE: The displayed values are only numeric dose estimates based on MIDAS calculations. They are not "real-time" readings from the perimeter monitor system.

Directions for accessing the MIDAS perimeter monitor dose rate screen option are as follows:

1) At the MIDAS DOSE

SUMMARY

REPORT screen, select CONTINUE.

2) On the next screen select MORE REPORTS.

3) From the MORE REPORTS SELECTION screen, select FM GAMMA DOSE RATE PLOT and CONFIRM.

4) From the REPORT PARAMETER SELECTION screen, choose the appropriate projection time and CONFIRM.

EP-AD-000-112, Revision 18, Page 21 of 33

TAB 7 EP-PS-244-7

5) From the MAP SELECTION screen, select MAP SCALE and input 1.25 miles, then CONFIRM.

6) On the next screen, select MAP FEATURES.

7) On the next screen, select CALCULATED PERIMETER MON DOSE RATES and CONFIRM.

8) To exit, select CONTINUE, MORE REPORTS, and EXIT.

EP-AD-000-112, Revision 18, Page 22 of 33

TAB 7 EP-PS-244-7 F. DESCRIPTION OF INFORMATION PROVIDED ON THE MIDAS DOSE

SUMMARY

REPORT

1. PRINT DATE/TIME Date and time MIDAS DOSE

SUMMARY

REPORT was printed.

2. CURRENT TIME PERIOD Current meteorological time period used for dose projections provided on quarter hour increments to match met spreadsheet entries.

3. REACTOR SHUTDOWN Date and time of reactor shutdown.

4. START OF RELEASE This is the date and time of first dose calculation as indicated by the first positive vent release rate value entered on the vent data spreadsheet or if the vent spreadsheet is not used, the date and time of the met data used for the current projection period.

NOTE: For MENU C: NR-1228 CALCULATIONS, MENU D: DEFAULT CALCULATIONS, and MENU E-W: BACK CALCULATIONS, it is conservatively assumed that the date and time of reactor shutdown is concurrent with the start of release.

5. MENU SELECTION Identifies the dose calculation option used for the current dose projection summary report. Choice of four options:

"* MENU B: FORWARD CALCULATIONS

"* MENU C: NR-1228 CALCULATIONS

"* MENU D: DEFAULT CALCULATIONS

"* MENU E-W: BACK CALCULATIONS

6. SOURCE TERM Identifies the source term used for the current dose projection summary report calculations. Choice of six options:

", ATWS-Normal Reactor Coolant Activity (UNDECAYED),

"* Normal Reactor Coolant Activity (DECAYED)

EP-AD-000-112, Revision 18, Page 23 of 33

TAB 7 EP-PS-244-7

"* (LOCA) Coolant Activity Leak with Depressurization Spike-No Fuel Damage

"* (LOCA) Cladding Failure-Gap Release

"* (LOCA) Fuel Melt-Early In-Vessel Release

"* Fuel Handling Accident

7. MET DATA Meteorological data (wind speed, wind direction, stability class, and precipitation rate) used for the summary report dose projections.

8. CURRENT AFFECTED SECTOR OR PEAK SECTOR DOSE RATES This table provides the TEDE, EDE, and THYROID CDE dose rates calculated at the OSCAR and EPB distances. These rate calculations are based on a variable projection/integration period for the current affected sector or peak sector.

9. PROJECTED DOSES This table provides a TEDE and THYROID CDE dose projection calculated at the OSCAR, EPB, 2-mile, and 10-mile distances for varying projection times.

The projection time will appear in the header line e.g., 4 HOUR PROJECTED DOSES on the MIDAS DOSE

SUMMARY

REPORT. The sector designation for this dose projection is based on the maximum calculated dose determined from all sixteen sectors for the given projection time. Information for distances between 10 and 50 miles is available using the "More Reports" feature.

10. CALCULATEDIREVIEWED BY The sign-off for review of calculation results is done for documentation purposes. The intended review does not necessarily mean an independent verification of each input to the calculation but more an interactive discussion between the RPC/HP Level II Dose Calculator and/or DASU/DAST (or dose calculator) to ensure the calculated results are reasonable based on current plant and environmental information.

This review should occur before the calculated results are used for any emergency classification determinations or protective action recommendations.

11. COMMENTS Section added to provide space for additional statements of qualification or background information pertaining to the dose projections.

EP-AD-000-112, Revision 18, Page 24 of 33

TAB 7 EP-PS-244-7 MIDAS DOSE

SUMMARY

REPORT DATE/TIME: 8/19/97 11:25 CURRENT TIME PERIOD: 8/19/97 11:38

2) PRI NT MI DAS DOSE

SUMMARY

REPORT REACTOR sHUTDOWN: 8/19/97 18:53 MIND SPEED (MPH):. 5 START OF 3RELEASE: 8/19/97 MENU SELECTION: FORWARD CALCULATIONS SOURCE TERM: LOCA (CLAD FAILURE) 18:53 0 WIND FROM STABILITY CLASS:

(DEG):

PRECIPITATION: NO 129 D

CESE)

CURRENT (SITE TOTAL) RELEASE RATE (uCi/min)

NOBLE GAS 1-131 PARTICULATES 6.98E+29 9.96E+81' 9.96E+81 CURN AFECE SETO DOERAE

[ F

.t"l-flT ON - OSCAR 1i it* isL J I I

-- mA AFFECTED DOSE RATE dT -v l .

DOSE RATE AFFECTED (mrem/br) SECTOR (mr-em.Jhrz) SECTOR 883.42 .INW 775.90 IIN 883.42 775.90 9.22 1-.16 1 CALCULATED BY: DATE:

REUIEWED BY: DATE:

COMMENTS:

!R=STAnT REPORTI +4 I UE EP-AD-000-112, Revision 18, Page 25 of 33

TAB 7 EP-PS-244-7 G. INFORMATION FOR DISTANCES BETWEEN 10 AND 50 MILES

1. From the MIDAS DOSE

SUMMARY

REPORT screen, select CONTINUE and, on the next page, MORE REPORTS.

2. Select TEDE 4-DAY DOSE REPORT or THYROID CDE DOSE REPORT, depending on which PAR guide has been exceeded at the 10-mile distance.

3. On the REPORT PARAMETER SELECTION screen, select PROJECTION TIME until the appropriate PROJECTION TIME (0.25,4, 6, or 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months ) is displayed on the screen; then select CONFIRM.

4. The screen will now display projected doses at the EPB and at 2, 5, 10, 25, and 50 miles. To obtain finer increments of distance, select CONTINUE until the desired range of distances is displayed.

NOTE: An objective is to determine the approximate distance from the plant at which dose projections are less than 1 rem TEDE and 5 rem THYROID CDE. A PAR is then likely to be issued to the next furthest 5-mile distance increment from the plant.

Example: A PAR for distances to 30 miles may be selected if projected doses become less than the PAG values (1 rem TEDE, 5 rem THYROID CDE) between 25 and 30 miles from the plant.

EP-AD-000-112, Revision 18, Page 26 of 33

TAB 7 EP-PS-244-7 H. ACCIDENT DESCRIPTIONS A. DEFAULT ACCIDENT DESCRIPTIONS (MENU B AND MENU D)

1. NORMAL REACTOR COOLANT ACTIVITY This accident scenario is defined as the release of reactor coolant system liquid and steam activity from the primary coolant system with no damage to the fuel and no activity spiking. The source term for this accident is normal reactor coolant system liquid and steam activity.

2. LOCA (RX DP-NO FD)

This accident scenario is defined as the release of reactor coolant system liquid and steam activity from the primary coolant system. Depressurization of the primary coolant system is assumed, resulting in an activity spike in the reactor coolant. The source term for this accident is normal reactor coolant liquid and steam activity plus the depressurization activity spike. There is no fuel damage.

3. LOCA (CLAD FAILURE)

This accident scenario is defined as a Loss-of-Coolant Accident which results in damage to the reactor fuel cladding. The source term for this accident is nbrmal reactor coolant liquid and steam activity and a percentage of the activity in the fuel clad gap. For Menu D calculations, that percentage is entered as part of the calculation process. For Menu B calculations, the valid vent data entered define the severity of the event.

4. LOCA (FUEL MELT)

This accident scenario is defined as a Loss-of-Coolant Accident which results in damage to the reactor fuel. The source term for this accident is normal reactor coolant liquid and steam activity and a percentage of the activity in the reactor fuel. For Menu D calculations, that percentage is entered as part of the calculation process. For Menu B calculations, the valid vent data entered define the severity of the event.

5. FUEL HANDLING ACCIDENT This accident scenario is defined as a fuel handling accident which results in the release of spent fuel activity. The source term for this accident is spent fuel gap activity assuming a decay time after shutdown of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

EP-AD-000-112, Revision 18, Page 27 of 33

TAB 7 EP-PS-244-7

6. ATWS This accident scenario is used for releases from a reactor unit continuing to operate at or greater than 10% power. The source term for this accident is normal reactor coolant system liquid and steam activity. The source term is undecayed; that is, no reactor trip is assumed to have occurred.

NOTE: For Menu D calculations, design basis assumptions are utilized.

For example, design basis leakage rates are assumed and iodine filtration efficiency of 99% is assumed in those pathways for which filters are in place.

NOTE: The source term for Menu D accident types is fixed. Release rate is calculated by MIDAS by dividing the total activity released by a predetermined release duration (6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for all but fuel handling accidents, for which release duration is 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ).

B. NUREG 1228 ACCIDENT TYPES (MENU C)

1. LOCA - DRYWELL RELEASE This accident is a Loss-of-Coolant Accident with an activity release into the drywell which bypasses the suppression pool for which filtration of activity by the Standby Gas Treatment System takes place before release to the eifvironment.

2. LOCA - WETWELL RELEASE This accident is a Loss-of-Coolant Accident with an activity release through the suppression pool for which filtration of activity by the Standby Gas Treatment System takes place before release to the environment.

3. LOCA - CONTAINMENT BYPASS RELEASE This accident is a Loss-of-Coolant Accident with an activity release to the environment that bypasses the containment and the Standby Gas Treatment System.

4. ZIRCALLOY FIRE IN ONE THREE MONTH OLD BATCH This accident is a zircalloy fire in spent fuel that results in an activity release similar to a core melt. It assumes that the activity is filtered by the Standby Gas Treatment System prior to release.

EP-AD-000-112, Revision 18, Page 28 of 33

TAB 7 EP-PS-244-7

5. SPENT FUEL GAP RELEASE This accident is a release of fuel gap activity from the spent fuel pool with treatment by the Standby Gas Treatment System prior to release.

NOTE: Menu C (from NUREG-1228 Event Tree Analyses) is used to relatively quickly provide a bounding estimate of offsite dose, for situations where there are substantial uncertainties in prediction of source term and any resultant doses.

EP-AD-000-1 12, Revision 18, Page 29 of 33

TAB 7 EP-PS-244-7 NUREG 1228 MENU STRUCTURE FOR DRYWELL RELEASE DRYWELL "11ý,WETWELL ,;'sPOENTOFUELA,,"

RELEASE RELEASE "*BPASS" RELEASE~ 4'POOL' RELEASE' (100% Clad Failure) (100% Fuel Melt) (100% Fuel Melt) Core Condition GAP RELEASE IN-VESSEL VESSEL MELT UNCOVERED SEVERE THROUGH 15-30 MIN DAMAGE UNCOVERED

> 30 MIN SPRAY ON SP OFF Status of Drywell Containment Spray HOLDUP TIME HOLDUP TIME HOLDUP TIME Drywell Holdup Time:

<1 HOUR 2-12 HOURS 24 HOURS Time from Release into Containment to Start of Release into Environment LEAK RATE LEAK RATE LEAK RATE DESIGN DESIGN 100% HOUR 100% DAY 100% DAY LEAK RATE LEAK RATE UNFILTERED FILTERED UNFILTERED FILTERED Catastrophic Failure to Isolate Containment 1% Day Containment Failure EP-AD-000-112, Revision 18, Page 30 of 33

TAB 7 EP-PS-244-7 NUREG 1228 MENU STRUCTURE FOR WETWELL RELEASE REIS DRYELL~t WETWELL CONTAINMENT

-' ,.qTIFUE4ILJ RELEASE BYPASS, RELEASE POOL RELEASE,..ý (100% Clad Failure) (100% Fuel Melt) (100% Fuel Melt) Core Condition GAP RELEASE IN-VESSEL VESSEL MELT UNCOVERED SEVERE THROUGH 15-30 MIN DAMAGE UNCOVERED

> 30 MIN SATURATED LSUBOOLED Conditions in Suppression Pool HOLDUP TIME HOLDUP TIME Wetwell Holdup Time:

2-12 HOURS 24 HOURS Time from Release into Wetwell to Start of Release into Environment LEAK RATE LEAK RATE DESIGN DESIGN LEAK RATE 100% HOUR 100% DAY 100% DAY LEAK RATE LEAK RATE UNFILTERED FILTERED UNFILTERED FILTERED Catastrophic Failure to Isolate Containment 1% Day Containment Failure EP-AD-000-112, Revision 18, Page 31 of 33

TAB 7 EP-PS-244-7 NUREG 1228 MENU STRUCTURE FOR CONTAINMENT BYPASS RELEASE RELEAS

~DRYWOELLV:I CONTAINMENT JWETEL. *.S PENT FUEL POOL BYPASS

~RELEASE RELEASE (100% Clad Failure) (100% Fuel Melt) (100% Fuel Melt) Core Condition GAP RELEASE IN-VESSEL VESSEL MELT UNCOVERED SEVERE THROUGH 15-30 MIN DAMAGE UNCOVERED

> 30 MIN UNFILTERED FILTERED Is Release Filtered?

RELEASE RATE RELEASE RATE TYPICAL DESIGN Release Rate, in 100% HOUR 100% DAY RELEASE RATE Terms of Percent of Core Inventory Catastrophic Failure to Isolate Containment Failure " Containment 1% Day EP-AD-000-112, Revision 18, Page 32 of 33

TAB 7 EP-PS-244-7 NUREG 1228 MENU STRUCTURE FOR SPENT FUEL POOL RELEASE

~RELEASE~ ~BYPASS~.

!*:i*?RELEASE '*!*?,,

ZIRCALLOY FIRE IN GAP RELEASE GAP RELEASE Condition of Spent ONE 3 FROM ONE 3 FROM 15 Fuel MONTH OLD MONTH OLD BATCHES BATCH BATCH (TOTAL POOL)

SPRAY ON SPRAY OFF Status of Containment Spray (Default) into Pool HOLDUP TIME HOLDUP TIME Time from Release

<1 HOUR 2-12 HOURS from Fuel to Start of Release into Environment LEAK RATE LEAK RATE LEAK RATE 100% HOUR 100% DAY Release Rate, in 100% DAY UNFILTERED FILTERED Terms of Percent of Source Inventory Catastrophic Failure of Containment EP-AD-000-112, Revision 18, Page 33 of 33

TAB 11 EP-PS-244-11 PAR AIRBORNE RELEASES EP ENTERED MONITOR CONDITONS:

- PLANT STATUSIPROCEDURES

- ONSITE RAD CONDITIONS CONTINUE

- STATUS OF RELEASE AT ASSES PA-1

- DOSE PROJECTIONS SM PA-1 AS GENERI EMRGENCY BEEN* NO DELARED PA-i PA-3 NOES:

NO OR UNKNOWN ,

1.

THREA CAN BUSD IT EEO SECIN41O H RCDR O OEDTIE NOMTO NTEAO 2DOEPROJECTIONS IDOINOTINCG D DORARAYRCI ED OMEN TEDOSES DU>EM TO G DRON DEPOSITION.IO RECOMMEND 4.5CDEM CYOMMID CDOE EQIALT TO CMIDLHYRID 010 EVACUATINGo.

IE *fASSMNCNIU AND SHELTERING ASESE,1I 2-10 MILES PA-1 PA-4 NOTES:

1. PA-0 CAN BE USED TO REFER TO SECTION 4.1 OF THE PROCEDURE FOR MORE DETAILED INFORMATION ON THE ACTION TO BE TAKEN.

2. DOSE PROJECTIONS DO NOT INCLUDE DOSE ALREADY RECEIVED.

3. TEDE - WHOLE BODY 9050D) IS THE SUM OF EFFECTIVE DOSE EQUIVALENT RESULTING FROM EXPOSURE TO EXTERNAL SOURCES THE COMMITTED EFFECTIVE DOSE EQUIVALENT (CEDE) FROM ALL SIGNIFICANT INHAILATION PATHWAYS AND THE DOSE DUE TO GROUND DEPOSITION.

4. COE - COMMITTED DOSE EQUIVALENT TO THE CHILD THYROID.

EP-AD-000-126, Revision 9, Page 1 of 6

TAB 11 EP-PS-244-11 PAR LIQUID RELEASES ENTRY:

INDICATIONS OF A POTENTIAL LIQUID RELEASE

- UNISOLABLE RADWASTE TANK RELEASE

- LEAK TO COOLING TOWER BASIN

- LEAK TO SPRAY POND PL-1 Isotopic Limit ENSURE CHEM/ESD RADIONUCLIDE (uCi/mI) TAKES AND ANALYZES Aa-11 Om 1.1 E"6 SAMPLES As-76 7.2E-7 RO-2 Ba-140 1.1 E-6 Ce-1 41 3.6E 4s Co-58 1.1 E-4

> R=TC -o NO ACTION CONTINUE Co-60 1.2E"6 REQUIREMENTS (AT REQUIRED MONITORING Cr-51 7.2E-5 Cs-134 2.4E 4 Cs-137 2.4E6 Fe-55 2.4E 5 Yes Fe-59 2.4E 4 H-3 2.4E 4 RAD PERSONNEL 1-129 1.2E-8 NOTIFY DANVILLE AND 1-131 3.6E-8 BRP THAT A RELEASE HAS OCCURRED La-140 7.2E"7 6

Mn-54 Mo-99 3.6E7 7.2E-6 PL-4 I1 Na-22 4.8E*6 CHEM/FTD EVALUATES Nb-95 - 3.6E-6 RELEASE vs PAG 6

Ni-59 3.6E7 Ni-63 6.0E"7 7

P-32 3.6E-Ru-103 2.4E-6 *No NOTIFY DANVILLE Ru-106 3.6E-7 ES RELEASE EXCE RAD PERSONNEL Sb-124 7.2E-7 ANY OF THE TABLE LIMITSNOIYDVLL

OR DOESL-'50 > SUM1_0THAT THE EX OF No-TA-N*ARI NO PAR IS Sb-125 3.6E-6 FRACTnIONS EXCEED 1.0 AT

DANVILLE?J RGIE REQUIRED Sr-89 2.4E"7 PL-6 PL P L-8 Sr-90 9.6E-8 Tc-99m 1.1 E-5 Y-90 7.2E-7 Yes Zn-65 3.6E-6 Zr-95 2.4E6 RAD PERSONNEL NOTIFY DEP/BRP FOR DANVILLE TO DIVERT DRINKING WATER SUPPLY & ESTIMATED TIME OF ARRIVAL OF RELEASE AT DANVILLE PL-7 NOTES:

1. PL-# CAN BE USED TO REFER TO SECTION 4.2 OF THE PROCEDURE FOR MORE DETAILED INFORMATION ON THE ACTION TO BE TAKEN.

2. CALLS TO DANVILLE ARE COURTESY INFORMATION CALLS ONLY. PROTECTIVE ACTION RECOMMENDATION CALLS MUST BE MADE BY DEP/BRP.

EP-AD-000-126, Revision 9, Page 2 of 6

TAB 11 TAB 11 EP-PS-244-11 PUBLIC PROTECTIVE ACTION RECOMMENDATION GUIDE AIRBORNE RELEASES EI PA-1 MONITOR CONDITIONS FOR PAR APPLICATION The following conditions should be continuously evaluated to determine if a PAR should be implemented or changed:

"* Plant status and prognosis for changes in conditions

"* Onsite radiological conditions

" . Status of actual or potential radioactive releases

"* Offsite dose projections or actual offsite radiological conditions

"* Escalation in Emergency Classification (i.e., General)

(Go to PA-2)

PA-2 HAS A GENERAL EMERGENCY BEEN DECLARED?

o YES - Ifa GENERAL EMERGENCY has been declared, a PAR must be made within 15 minutes of the emergency declaration. The PAR requirement is found in NUREG-0654. (Go to PA-3)

EJ NO - If a GENERAL EMERGENCY has not been declared, continue to monitor plant status, parameter trends, and prognosis for termination or escalation of the event. (Go to PA-1)

PA-3 IS THERE A VALID DOSE PROJECTION INDICATING DOSES OF Ž_1 REM TEDE OR>

5 REM CDE CHILD THYROID AT A DISTANCE OF

> 2 MILES?

o YES - If the projected doses at 2 miles are > 1 REM TEDE or > 5 REM CDE child thyroid, then full evacuation (0-10 miles) is recommended.

(Go to PA-5) 0 NO/UNKNOWN - (Go to PA-4)

EP-AD-000-126, Revision 9, Page 3 of 6

TAB 11 EP-PS-244-11 E- PA-4 RECOMMEND EVACUATION 0-2 MILES; SHELTER 2-10 MILES Limited Evacuation (0-2 miles) and sheltering is appropriate for events that are significant enough to cause a General Emergency classification and dose projections are low, unknown, or below full evacuation guidelines.

O PA-5 EVACUATE 0-10 MILES Full evacuation of members of the general public is recommended at this point based on the emergency classification and dose projections.

EP-AD-000-1 26, Revision 9, Page 4 of 6

TAB 11 EP-PS-244-11 LIQUID EJ PL-1 ENTRY This section is entered when there are indications of a potential radioactive liquid release.

Indications of potential releases include:

"* an unisolable radwaste tank release.

"* leaks to cooling tower basin

"* leak to spray pond (Go to PL-2) o PL-2 CHEMISTRY/ENVIRONMENTAL SAMPLING DIRECTOR (ESD) TAKES AND ANALYZES SAMPLE (Go to PL-3)

PL-3 IS RELEASE > TECHNICAL REQUIREMENTS LIMITS (AT THE RELEASE POINT)?

0 YES - Releases are at or greater than Technical Requirements limits when Chemistry determines that the limits are exceeded based on methodologies described in the ODCM and applicable Chemistry procedures.

o NO - If the release is < Technical Requirements limits, then no notifications are required and monitoring should continue.

(Go to PL-4) o PL-4 RAD PERSONNEL NOTIFY DANVILLE AND BRP THAT A RELEASE HAS OCCURRED Depending on which facility is activated, the notification to Danville and BRP will be made by the RPC (TSC) or the Radiological Liaison (EOF).

DO NOT MAKE ANY PROTECTIVE ACTIONS RECOMMENDATIONS AT THIS TIME.

EP-AD-000-126, Revision 9, Page 5 of 6

TAB 11 EP-PS-244-11 0 PL-5 CHEM/FTD EVALUATES RELEASE VERSUS PAGs The results of the sample analysis are compared to the PAGs for radionuclides in drinking water. The analysis calculates the expected concentration at Danville, taking into account the.dilution afforded by the river.

PL-6 DOES RELEASE EXCEED PAGs (AT DANVILLE)?

O YES - Ifa single isotope exceeds the PAG or the sum of the fractions exceeds 1.0, then a protective action recommendation should be made for Danville to DIVERT its DRINKING WATER supply to a backup supply until the release has passed.

(Go to PL-7) 0 NO - If the PAGs are not exceeded, monitoring should continue and the State should be notified that no PAR for the liquid release is required. (Go to PL-8) o PL-7 RAD PERSONNEL NOTIFY DEP/BRP OF PAR Depending on which facility is activated, the PAR notification to DEP/BRP will be made by the RPC (TSC) or the Radiological Liaison (EOF). The PAR FORM shall be used to document the PAR.

DO NOT COMMUNICATE THE PROTECTIVE ACTION RECOMMENDATION TO DANVILLE. THE DEP/BRP IS RESPONSIBLE FOR THIS COMMUNICATION.

O PL-8 RAD PERSONNEL NOTIFY DEP/BRP No PAR is required. Depending on which facility is activated, the RPC (TSC) or the Radiological Liaison (EOF) shall notify DEP/BRP that no PAR is required.

EP-AD-000-126, Revision 9, Page 6 of 6

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