ML022680294
| ML022680294 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom, Limerick  |
| Issue date: | 09/19/2002 |
| From: | Gallagher M Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML022680294 (129) | |
Text
/ '-o.1dur s Limerick Generating Station, Units I & 2 Peach Bottom Atomic Power Station, Units 2 & 3 ExeIInm Nuclear I
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Standard Emergency PrOCedreSNlar t Nuclear
EP-AA-1 10 Exekn~ ,xm Revision 3 Page 1 of 2 Nucear Level 2 - Reference Use ASSESSMENT OF EMERGENCIES
- 1. PURPOSE Provide guidance on the tools and processes used to gather and evaluate data and information to effectively assess accident conditions.
- 2. TERMS AND DEFINITIONS None
- 3. RESPONSIBILITIES None
- 4. MAIN BODY 4.1 REFER TO the following supporting procedures, as applicable:
rLi~merick / Peach Bottom 4.1.1 EP-MA-110-100, "Emergency Response Organization (ERO) Computer Applications," provides guidance on the activation and/or operation of the following applications:
"* U.S. NRC Emergency Response Data System (ERDS)
"* Emergency Preparedness Data System (EPDS)
"* Plant Monitoring System (PMS)
"* Projection Screens
"* Electronic Status Boards
"* News Writer / Chronological Events Description Log
"* Potassium Iodide (KI) Spreadsheet
"* Offsite Siren Activation
EP-AA-1 10 Revision 3 Page 2 of 2 EIid-WestROG 4.1.2 EP-MW-110-100, "ERO Computer Applications," provides guidance on the activation and/or operation of the following applications:
- Accessing ERO applications from a network computer.
- Plant Parameter Display System (PPDS)
- Significant Events Log (SEL)
- Station Priorities Log (SPL)
- KI Spreadsheet
- News Writer 4.1.3 EP-MA-1 10-200, "Dose Assessment," provides guidance on the activation and/or operation of the following applications:
- Dose Assessment and Protective Action Recommendation (DAPAR) 4.1.4 EP-MW-1 10-200, "Dose Assessment," provides guidance on the activation and/or operation of the following applications:
- DAPAR
- MESOREM
- C-Model 4.1.5 EP-AA-110-301, "Core Damage Assessment (BWR)"
4.1.6 EP-AA-110-302, "Core Damage Assessment (PWR)"
- 5. DOCUMENTATION None
- 6. REFERENCES None
- 7. ATTACHMENTS None
f, EP-MA-1 10-100 Ex,,l Revision 0 Page 1 of 33 NucleaT Level 2 - Reference Use ERO COMPUTER APPLICATIONS
- 1. PURPOSE 1.1 This procedure provides the guidance for gathering information and the operation of equipment associated with various data acquisition and display methods.
- 2. TERMS AND DEFINITIONS 2.1 The Chronological Events Log, is an option under the News Writer Program that allows for the electronic documentation of significant event activities for dissemination to the news media.
2.2 The Emergency Response Data System (ERDS), is a direct near real-time electronic data link between the onsite computer system and the NRC Headquarters Operations Center that provides for the automated transmission of a limited data set of selected parameters.
2.3 The Emergency Preparedness Data System (EPDS), is an emergency facility data system used to aid in assessing plant response and status during emergencies. EPDS is a computer based real-time data acquisition and display system, which acquires, stores and re-packages data from the Plant Monitoring System (PMS) and Radiological Monitoring System (RMS) for display in the Technical Support Center (TSC) at Limerick and Peach Bottom Stations and the common Emergency Operations Facility (EOF) at the Coatesville, Pennsylvania. Service Center.
2.4 KI (Potassium Iodide) Spreadsheet, is an EXCEL spreadsheet used to calculate 1-131 concentration and thyroid dose based on an air sample analysis. It also provides a recommendation on KI issuance to Exelon emergency workers.
2.5 News Writer is an electronic program used by the Emergency Public Information Organization for the generation and review of press releases for distribution to the news media. News Writer is also used to store standard biographies for Exelon Spokespersons.
2.6 The Plant Monitoring System (PMS), refers to the station process computer application at Limerick and Peach Bottom Generating Stations. The data feed for EPDS and ERDS data links is feed from the PMS.
2.7 The Priority Status Board, is an electronic means of automatically displaying entries made on the TSC board in the Operations Support Center (OSC) and EOF for Limerick and Peach Bottom Stations.
EP-MA-1 10-100 Revision 0 Page 2 of 33
- 3. RESPONSIBILITIES None
- 4. MAIN BODY 4.1 Limerick Generating Station (LGS) Instructions:
"* Emergency Preparedness Data System (EPDS) Operation - REFER to Attachment 1
"* EPDS Data Reboot Process - REFER to Attachment 2
"* Potassium Iodide (KI) Spreadsheet Users Guide - REFER to Attachment 3
"* U.S. NRC ERDS Activation - REFER to Attachment 4
"* Instructions for Establishing Priority Status (OSC Team) Board - REFER to Attachment 5
"* Obtaining Radiological Data from RM-1 1 - REFER to Attachment 6
"* Obtaining MET Data from PMS - REFER to Attachment 7
"* Offsite Siren Activation - REFER to Attachment 16
"* TSC Overhead Projector Display Instructions - REFER to Attachment 17 4.2 Peach Bottom Atomic Power Station (PBAPS):
"* Emergency Preparedness Data System (EPDS) Operation - REFER to Attachment 1
"* EPDS Data Reboot Process - REFER to Attachment 2
"* Potassium Iodide (KI) Spreadsheet Users Guide - REFER to Attachment 3
"* Plant Monitoring System (PMS) Log-In Instructions - REFER to Attachment 8
"* U.S. NRC ERDS Activation - REFER to Attachment 9
"* Basic Instructions for Establishing Priority Status (OSC Team) Board - REFER to Attachment 10
"* TSC Electronic Display Board Instructions - REFER to Attachment 11
"* TSC Overhead Projector Display Instructions - REFER to Attachment 12
"* Offsite Siren Activation - REFER to Attachment 16 4.3 Coatesville Facility:
"* Operation of EOF Projection Controller- REFER to Attachment 13
"* JPIC Outlook Access - REFER to Attachment 14
"* News Writer / Chronological Events Description Log User Guide - REFER to Attachment 15
EP-MA-110-100 Revision 0 Page 3 of 33
- 5. ATTACHMENTS 5.1 Attachment 1, Emergency Preparedness Data System (EPDS) Operation 5.2 Attachment 2, EPDS Data Receiver Reboot Process 5.3 Attachment 3, Potassium Iodide (KI) Spreadsheet Users Guide 5.4 Attachment 4, Emergency Response Data System (ERDS) Activation [Limerick]
5.5 Attachment 5, Basic Instructions for Establishing Priority Status (OSC Team) Board
[Limerick]
5.6 Attachment 6, Obtaining Radiological Data from RM-1 1 [Limerick]
5.7 Attachment 7, Obtaining Meteorological Data from PMS [Limerick]
5.8 Attachment 8, Plant Monitoring System (PMS) Log-In Instructions [Peach Bottom]
5.9 Attachment 9, Emergency Response Data System (ERDS) Activation [Peach Bottom]
5.10 Attachmentl0, Basic Instructions for Establishing Priority Status (OSC Team) Board
[Peach Bottom]
5.11 Attachment 11, TSC Electronic Display Board Instructions [Peach Bottom]
5.12 Attachment 12, TSC Overhead Projector Display Instructions [Peach Bottom]
5.13 Attachment 13, Operation of the EOF Projection Controller [Coatesville EOF]
5.14 Attachment 14, JPIC Outlook Access [Coatesville JPIC]
5.15 Attachment 15, News Writer/ Chronological Events Description Log Users Guide
[Coatesville JPIC]
5.16 Attachment 16, Offsite Siren Activation [Limerick I Peach Bottom]
5.17 Attachment 17, TSC Overhead Projector Display Instructions [Limerick]
EP-MA-110-100 Revision 0 Page 4 of 33 ATTACHMENT I Emergency Preparedness Data System (EPDS) Activation Page 1 of 3 A. TO OPEN ONE OR SEVERAL DISPLAYS NOTE: Always use left mouse button STEP I TURN ON power to the computer and printer STEP 2 If "Group Main" is NOT open then:
", DOUBLE CLICK on "Desktop Manager" icon
"* DOUBLE CLICK on "Main" and follow open steps (4.3)
STEP 3 If "Group Main" IS open then:
- Using the mouse, MOVE arrow to top bar (center) of "Group Main" STEP 4 HOLD the mouse button down and MOVE display to the bottom right hand corner of the screen
- DOUBLE CLICK on "EPDS" in "Group Main" STEP 5 Using the mouse, MOVE the arrow to the menu bar
"* CLICK on station of interest
"* CLICK on unit of interest STEP 6 Using the mouse, MOVE the arrow to the "down" scroll bar arrow
"* CLICK the mouse and LOCATE the parameter of interest
"* DOUBLE CLICK on the parameter of interest
EP-MA-110-100 Revision 0 Page 5 of 33 ATTACHMENT I Emergency Preparedness Data System (EPDS) Activation Page 2 of 3 B. TO OPEN MORE DISPLAYS STEP 1 CLICK on "Utilities" STEP 2 CLICK on 1/4 up left STEP 3 LOCATE "Group Main" STEP 4 DOUBLE CLICK on "EPDS" STEP 5 SELECT affected Station/Unit STEP 6 SELECT Parameter STEP 7 CLICK on "Utilities" STEP 8 CLICK on 1/4 up right STEP 9 Repeat previous steps for more displays (1/4 down left, then 1/4 down right)
C. TO SET UP AUTO AUTOMATIC PRINTING STEP I CLICK on "Utilities" STEP 2 CLICK on "Periodic Report STEP 3 CLICK on Station/Unit of interest box STEP 4 CLICK on frequency of interest STEP 5 CLICK on parameters of interest STEP 6 CLICK on "OK" ("ACTIVE" is displayed)
STEP 7 CLICK on the "down" arrow in the upper right corner of the display NOTE: "Restore" can be used to view active selections "Quit" terminates automatic printing
EP-MA-110-100 Revision 0 Page 6 of 33 ATTACHMENT I Emergency Preparedness Data System (EPDS) Activation Page 3 of 3 D. TO TREND A PARAMETER Note: Trending will tie up terminal until trend is complete STEP 1 In display of interest, DOUBLE CLICK on value to be trended.
STEP 2 If necessary to adjust the trend ranges, then:
"* CLICK on scale
"* Using the mouse, POSITION the cursor to the right of the value to be changed
"* Click on the mouse button STEP 3 STRIKE "Back Space" key to delete numbers to be changed STEP 4 TYPE in the new value and CLICK on "OK" STEP 5 To cancel trend display, CLICK on "Exit" E. TO PLAYBACK A PARTICULAR DISPLAY OR TREND VALUE NOTE: The system will play back condensed 30 second snapshots every few seconds over the time period selected.
STEP I CLICK on "Playback" in the display of interest STEP 2 CLICK on "On" STEP 3 SET value for the amount of time to be played back STEP 4 CLICK on "OK" STEP 5 To turn off playback:
"* CLICK on "Playback"
"* CLICK on "Off' F. TO PRINT AN INDIVIDUAL REPORT STEP 1 CLICK on "Utilities" in the display of interest STEP 2 CLICK on "Print Screen"
EP-MA-1 10-100 Revision 0 Page 7 of 33 ATTACHMENT 2 EPDS Data Reboot Process Page 1 of I PREREQUISITE:
A. EPDS appears unresponsive with an apparently operable sending modem and/or B. Notification from NISD has been received that the EOF LAN was "down" but has been restored to normal functionality.
PROCESS:
Reboot the EOF EPDS data receiver using either of the following methods:
- 1. If at the EOF, then PERFORM the following:
1.1 ENTER the Telecommunications Room and LOCATE the EPDS Data Receiver PC.
NOTE: Several PCs are in the room. The Data Receiver is one of several along the north wall of the room (left wall as you enter the room.) The PC farthest from the door is the EOF LAN server. The Data Receiver is immediately to the left of the server (the side closer to the door.)
1.2 PERFORM either:
1.2.1 PRESS the reboot button; or 1.2.2 TURN OFF the power switch and WAIT about 15 seconds, then TURN ON the power switch 1.3 TEST EPDS functionality.
1.3.1 If EPDS functionality is normal, then PROCEED with intended activities.
1.3.2 If EPDS is NOT normally functional, then CONTACT the NISD EP representative or CALL the Exelon Help Desk at 803:4357.
1.3.3 NOTIFY appropriate concerned parties such as emergency response leadership, lead drill controller, or site EP Coordinators of EPDS status.
- 2. If NOT at the EOF, then PERFORM a remote reboot as follows:
2.1 Using a standard touchtone telephone, DIAL (610) 380-3906.
2.2 Wait a few seconds, then ENTER the security code by "1248" on the telephone keypad.
You should hear a tone.
NOTE: The EPDS Data Receiver should reboot in about 20 seconds and will be available normally in a few minutes.
2.3 TEST EPDS functionality per Step 1.3.
EP-MA-1 10-100 Revision 0 Page 8 of 33 ATTACHMENT 3 KI Spreadsheet Users Guide Page I of 3 KI Spreadsheet Program can be accessed via either:
"* Icon on designated DAPAR lap-top computers, or
"* Common drive paths:
Limerick Generating Station (LGS): \\PECO\.PBS2_DATAI.PBS_SRVS.PBS.PECO\EPDAPAR Peach Bottom Atomic Power Station (PBAPS): \\PECO\.PBS2_DATAI.PBSSRVS.PBS.PECO\EPDAPAR NOTE: An EXCEL spreadsheet (Table 3-1) has been provided to calculate 1-131 concentration and thyroid dose, as wellas generate a recommendation on KI issuance to Exelon emergency workers. The spreadsheet is launched by clicking on the icon labeled "KI Assessment". This opens a shared, locked Microsoft Excel spreadsheet that will perform the assessment per input data that provided.
NOTE: The spreadsheet is protected to prevent accidental changes being made to the calculations.
The only cells that can be changed are those fields colored purple on the spreadsheet display screen. Cell E4 contains the current date/time for recordkeeping purposes and should not be altered by the user.
- 1. ENTER the following information in text fields for event documentation (none of these cells are required to perform the calculation):
- The station name for which the calculation is being done (cell E5);
- The sample collection point or descriptor (cell E9);
- The sample cartridge type used (zeolite or charcoal) (cell E10);
- The sampler start time, if known (cell El 1);
0 The sampler ending time, if known (cell E12);
- The sample analysis point or descriptor (cell E16);
- The sample analysis time (cell E17).
- 2. The following values are required to be entered in order to do the calculation:
- The air sampler running time in minutes (cell E13) ; this value is not calculated automatically from the entered running times; 0 The air sampler flow rate over the running time, in cubic feet per minute (cell E14);
- The background count rate, in cpm, on instrument at the location at which the sample was counted (cell E18);
- The pre-filter count rate, in cpm; a gross (background included) measurement is expected (cell E19);
0 The sampler cartridge count rate, in cpm; a gross (background included) measurement is expected (cell E20);
0 The number of hours remaining in which the persons for whom the calculation is being made may be exposed to iodine (cell 06);
EP-MA-110-100 Revision 0 Page 9 of 33 ATTACHMENT 3 KI Spreadsheet Users Guide Page 2 of 3 The percent of possible exposure time that the persons for whom the calculation is being made are expected to actually be exposed (cell 07); use the default value of 50% unless a better estimate can be made.
- 3. The following intermediate information is calculated by the spreadsheet, and values displayed for the user:
- The total sample count rate, in cpm (cell E23);
- The total sample volume, in cubic centimeters (cell E24);
- The total sample concentration, in giCi/cm3 (cell E26).
- 4. The estimated thyroid dose value can be read from cell 018 (displayed in green lettering). The percent of the dose as fraction of the 50 rem PAG can be read from cell 019. Ifthe value of P18 does exceed the PAG value, a recommendation to issue KI appears a box immediately below the dose estimate (range M21 to R22). Ifthe value of 018 does not exceed the PAG, the word "NOT" appears in cell 021, changing the recommendation to not issuing KI. The number of hours that emergency workers may be exposed to a plume at the current dose level without exceeding the PAG is given in cell P25.
- 5. A summary report is printed containing all input data and calculated information when the "print" icon is clicked, located on the Excel button bar.
- 6. The report contains zones to record the following:
A) Information relating to contacting the Exelon Occupational Health Services Department (OHSD):
"* The time the call was made;
"* Whether contact was successfully made;
"* The name of the person contacted;
"* Whether concurrence for KI was obtained from OHSD;
"* Ifconcurrence is not obtained from OHSD, the reason given.
B) The recommendation of the Radiation Protection Manager whether to issue KI. A recommendation must be circled, then signed and dated.
C) The approval or denial of KI by the Station Emergency Director.
NOTE: Whether KI issuance is approved or denied must be circled, then signed and dated.
- 7. Copies of the completed KI report should be made and distributed. The original should be controlled for incident documentation.
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EP-MA-1 10-100 Revision 0 Page 11 of 33 ATTACHMENT 4 U.S. NRC Emergency Response Data System (ERDS) Activation For Limerick Generating Station (LGS)
Page 1 of 2 STEP 1 TURN ON Emergency Preparedness Data System (EPDS) monitor a EOF "A" primary / EOF "B" backup STEP 2 DOUBLE CLICK on "NRC1 .... COM8" icon.
STEP 3 DOUBLE CLICK on the letter "M"(in "Manual Session").
NOTE: Session state should say "IN SESSION" when successful connection is established.
STEP 4 DOUBLE CLICK on "NRC2 .... COM9" icon.
STEP 5 DOUBLE CLICK on the letter "M"(in "Manual Session").
NOTE: Session state should say "IN SESSION" when successful connection is established.
COMPUTER POINT ENGINEERING UNITS DESCRIPTION B000/B1000 % Power APRM 1 SIM Thermal Power B001/3B001 % Power APRM 2 SIM Thermal Power B002IB002 % Power APRM 3 SIM Thermal Power B1003B003 % Power APRM 4 SIM Thermal Power El109/E2109 CPS A SRM Count Rate El133/E2133 CPS B SRM Count Rate E111O/E2110 CPS C SRM Count Rate El 134/E2134 CPS D SRM Count Rate E1114/E2114 IN/NOT IN A SRM Position El 1381E2138 IN/NOT IN B SRM Position E1115/E2115 IN/NOT IN C SRM Position El 139/E2139 IN/NOT IN D SRM Position E1240/E2240 Inches Water Level Shutdown Range Reactor Level E1239/E2239 Inches Water Level Upset Range Reactor Level E1419/E2419 Inches Water Level Fuel Zone Range Reactor Level B E1339/E2339 Inches Water Level Fuel Zone Range Reactor Level A E1418IE2418 Inches Water Level Wide Range Reactor Level B E1338/E2338 Inches Water Level Wide Range Reactor Level A E1238/E2238 Inches Water Level Narrow Range Reactor Level C E1237/E2237 Inches Water Level Narrow Range Reactor Level B E1236/E2236 Inches Water Level Narrow Range Reactor Level A E1241/E2241 MLB/HR Total Feedwater Flow El 340/E2340 GPM RCIC System Flow
EP-MA-110-100 Revision 0 Page 12 of 33 ATTACHMENT 4 U.S. NRC Emergency Response Data System (ERDS) Activation For Limerick Generating Station (LGS)
Page 2 of 2 COMPUTER POINT ENGINEERING UNITS DESCRIPTION E12341E2234 PSIG Narrow Range Reactor Pressure E1430/E2430 PSIG Upset Range Reactor Pressure B El 353/E2353 PSIG Upset Range Reactor Pressure A E14201E2420 KGPM HPCI System Flow E1341/E2341 KGPM A RHR System Flow E1421/E2421 KGPM B RHR System Flow E1466/E2466 KGPM C RHR System Flow El 506/E2506 KGPM D RHR System Flow El 342/E2342 KGPM A Core Spray Flow E1422/E2422 KGPM B Core Spray Flow E1192/E2192 GAL Drywell Floor Drain Sump Level 4TE076 pCi/Sec North Stack Total Effluent E1088/E2088 mR/Hr Steam Jet Air Ejector Rad Mon 1RA191/1RA291 R/Hr Drywell Area Post LOCA Rad 2RA1 91/2RA291 RPHr Drywell Area Post LOCA Rad 3RA1 91/3RA291 R/Hr Drywell Area Post LOCA Rad 4RA191/4RA291 R/Hr Drywell Area Post LOCA Rad E1082JE2082 mPIHr Main Steam Rad Monitor E1425/E2425 PSIG Narrow Range Drywell Pressure E14231E2423 PSIG Wide Range Drywell Press B PSIG Wide Range Drywell Press A E13431E2343 E1515/E2525 Deg. F Drywell Atmosphere Temp E1658/FE2658 Deg. F Drywell Atmosphere Temp El 424/E2424 Deg. F Suppression Pool Airspace Temp B El 344/E2344 Deg. F Suppression Pool Airspace Temp A El 680/E2680 FT Suppression Pool Water Level El 602/E2602 FT Suppression Pool Water Level El 186/E2186 FT Suppression Pool Level B E1210/E2210 FT Suppression Pool Level A B21V0065/B21V0065 Drywell H2 Concentration B21V0064/B21V0064 Drywell 02 Concentration E1083/E2083 FT Condensate Storage Tank Level TS.SP.I MPH Tower I Wind Speed T2.SP.U MPH Tower 2 Wind Speed T1.DR.I Degrees Tower I Direction T2.DR.U Degrees Tower 2 Direction T1 .DT.UL Deg. F Tower I Delta-Temp T2.DT.UL Deg. F. Tower 2 Delta-Temp T1.ST.I Degrees Tower I Sigma Theta T2.STI Degrees Tower 2 Sigma Theta
EP-MA-110-100 Revision 0 Page 13 of 33 ATTACHMENT 5 Instructions for Establishing Priority Status (OSC Team) Board [LIMERICK]
Page 1 of 2 NOTE: Upon completion of the following steps, the priority status board terminals at the EOF and OSC will display the same information as the TSC terminal.
Any priorities entered prior to the EOF / OSC connections will not be transmitted to their PC.
STEP I TURN ON computer.
STEP 2 SELECT "CANCEL" at Password and Printer Hardware Windows. (The NetMeeting Program should start-up.)
STEP 3 SELECT "CALL" on menu.
STEP 4 SELECT "Host Meeting", and then SELECT "OK" STEP 5 On "NetMeeting" Window, SELECT TOOLS, and then SELECT SHARING STEP 6 On "Sharing" Window, SELECT "PRIORITY.WBD - IBID", and then SELECT "SHARE" STEP 7 On "NetMeeting" Window, SELECT "CALL", and then SELECT "NEW CALL" STEP 8 On "Place a call" Window, HIGHLIGHT "10.250.254.61" for the EOF, and then SELECT "CALL".
NOTE: If connection cannot be made, then CALL the EOF and ASK someone to reboot priority status board computer. VERIFY automatically accept calls feature is "checked on" Call Menu, then RETRY previous step.
STEP 9 On "NetMeeting" Window, SELECT "CALL", and then SELECT "New Call" STEP 10 On "Place a call" Window, SELECT "10.254.243.194", and then SELECT "CALL" NOTE: If connection cannot be made, then CALL the OSC and ASK someone to reboot priority status board computer. VERIFY automatically accept calls feature is "checked on" Call Menu, then RETRY previous step.
CAUTION Failure to perform STEP 11 will render that section of the screen unusable by the EOF and OSC STEP 11 MINIMIZE "NetMeeting" Window.
EP-MA-110-100 Revision 0 Page 14 of 33 ATTACHMENT 5 Instructions for Establishing Priority Status (OSC Team) Board [LIMERICK]
Page 2 of 2 STEP 12 MAXIMIZE "Priority.wbd - ibid" Window.
STEP 13 VERIFY operation of the Priority Status Board by contacting the OSC & EOF after recording initial message At the completion of drill/emergency, PERFORM the following:
STEP I On "NetMeeting" Window, SELECT "CALL", and then SELECT "HANG UP" STEP 2 From the START Menu, SELECT "SHUT DOWN"
EP-MA-1 10-100 Revision 0 Page 15 of 33 ATTACHMENT 6 Obtaining Radiological Data from RM-11 For Limerick Generating Station (LGS)
Page 1 of 2 STEP 1 SELECT Grid 1.
STEP 2 SELECT the release point of interest. (Example: North Stack Channel RE26076-4.)
NOTE: Pressing the "Esc" button on the keyboard will return the user to the Main Menu from any other screen.
STEP 3 SELECT the "MONITOR DETAIL" button STEP 4 RECORD the current Process Flow value for the selected release point STEP 5 SELECT the "PREV" button STEP 6 SELECT either the "15 MIN AVG" value or the "60 MIN AVG" value.
STEP 7 VERIFY the selected value is surrounded by a box.
STEP 8 RECORD which "AVG" value was chosen in the table on ERP-300, Appendix 6 page 3 for the selected release point.
STEP 9 PRESS the "right" mouse button.
STEP 10 SELECT "Time Trend" from the pull down menu.
NOTE: There are two values in the bottom right hand corner of the Channel Detail Screen. For Step 10, the value furthest right is the value where the cursor is placed. The value adjacent is the most recent 15-minute or 60 minute average.
STEP 11 PLACE the cursor near the line that has the highest value.
Description RM-11 Channel Mesorem Jr. Channel North Stack Total Effluent RE26076-4 4TE076 Unit I South Stack "A" Noble Gas RE26185A-3 3GE185 Unit I South Stack "B Noble Gas RE26185B-3 6GE185 Unit 2 South Stack "A" Noble Gas RE26285A-3 3GE285 Unit 2 South Stack "A" Noble Gas RE26285B-3 6GE285 STEP 12 RECORD the selected value for the release point in the appropriate table below:
EP-MA-1 10-100 Revision 0 Page 16 of 33 ATTACHMENT 6 Obtaining Radiological Data from RM-11 For Limerick Generating Station (LGS)
Page 2 of 2 STEP 13 SELECT the "GRID 1" button in the top right hand corner to return to the Grid 1 Display.
NOTE: N/A should be entered in the tables below for release points that were not selected.
EP-MA-1 10-100 Revision 0 Page 17 of 33 ATTACHMENT 7 Obtaining MET Data From Plant Monitoring System (PMS)
For Limerick Generating Station (LGS)
Page 1 of 1 A. IF IN THE CONTROL ROOM -- PERFORM the following at a unit 1 Plant Monitoring System (PMS) workstation:
STEP I SELECT menu at bottom of CRT screen to bring up the Limerick Unit 1 main menu STEP 2 SELECT monitor box on left hand side of the screen to bring up monitor display menu STEP 3 SELECT either 15 minute Average or hourly Average meteorological data.
STEP 4 PRESS F20 to print.
B. IF IN THE TSC -- PERFORM the following at the VT terminal:
STEP I TURN ON the VT terminal.
STEP 2 At the "Local" prompt, TYPE "C(space) LG1 pa" or LGI pb.
STEP 3 ENTER Username "HPI" STEP 4 ENTER Password "TSC" STEP 5 SELECT either:
- 15 minute Average Met Data or,
- Hourly Average Met data.
C. LOGOFF STEP I PRESS F2 to print.
EP-MA-1 10-100 Revision 0 Page 18 of 33 ATTACHMENT 8 Plant Monitoring System (PMS) Log-In Instructions For Peach Bottom Atomic Power Station (PBAPS)
Page 1 of 1 STEP I With the "Microsoft Windows NT Workstation" screen displayed, PRESS (Cntrl+AIt+Del) simulataneously to access the login screen display.
STEP 2 At the "Login Info" screen, ENTER the following:
"* TSC or OSC workstations Username: pms Password: pbpms
" SMB (Reactor Engqineeringq Computer Room) workstations Username: rxeng Password: pbpms
"* Control Room - Unit 2 workstations Username: u2pms Password: leave blank (no password)
" Control Room - Unit 3 workstations Username: u3pms Password: leave blank (no password)
PRESS Enter key or SELECT OK CAUTION This is a Human Performance Error Likely Situation. In the following action, you must choose the correct Unit # to recive the data for that unit.
STEP 3 From the Windows NT Desktop, SELECT START menu.
STEP 4 SELECT the appropriate unit data to be transmitted:
"* PB2 for Unit #2 data, or
"* PB3 for Unit #3 data The PMS screen will now be activated.
STEP 5 VERIFY that the correct Unit is displayed on the PMS screen.
EP-MA-110-100 Revision 0 Page 19 of 33 ATTACHMENT 9 U.S. NRC Emergency Response Data System (ERDS) Activation For Peach Bottom Atomic Power Station (PBAPS)
Page 1 of 2 INITIATE ERDS link to the NRC via a Plant Monitoring System (PMS) Terminal located in either the Control Room or Technical Support Center (TSC).
With the PMS computer program activated (per Attachment 9), PERFORM the following steps to establish ERDS link to the NRC:
STEP I SELECT the EPDS menu or TYPE EPD.
STEP 2 SELECT the NRC Link Activation or TYPE the letters NRC.
STEP 3 SELECT "Fl" to activate.
STEP 4 SELECT either:
"* "F1"to activate Unit 2 link, or
"* "F3" to activate Unit 3 link.
STEP 5 ENTER the password "USNRC" and PRESS Return key.
COMPUTER POINT ENGINEERING UNITS DESCRIPTION C229 / C529 1E-9 to 100 % power Average Wide Range Neutrom Monitor D524 / D824 Reset / Trip Al Channel Main Steam Line High Radiation D525 I D825 Reset I Trip B1 Channel Main Steam Line High Radiation D526 I D826 Reset I Trip A2 Channel Main Steam Line High Radiation D527 I D827 Reset I Trip B2 Channel Main Steam Line High Radiation H004 H304 0 to 1500 psig A Channel Reactor Pressure H005 H305 0 to 1500 psig B Channel Reactor Pressure H037 / H337 norm / HiHi Drywell Floor Drain Sump Level H050 / H350 0 to 42 feet Condensate Storage Tank Level H053 / H353 0 to 6000 gpm HPSI Flow H054 / H354 0 to 700 gpm RCIC Flow H055 / H355 0 to 8000 gpm A Loop Core Spray Flow H056 / H356 0 to 8000 gpm B Loop Core Spray Flow J154 I J654 1E-7 to 0.1 uCifcc Low Range Main Stack Radiation J155 / J655 1 E-4 to 1E2 uCi/cc Mid Range Main Stack Radiation J156 I J656 0.1 to IE5 uCilcc High Range Main Stack Radiation J158 / J658 1E-7 to 0.1 uCilcc Low Range Main Stack Radiation J159 / J659 1E-4 to 1E2 uCi/cc Mid Range Main Stack Radiation J160/J660 0.1 to 1E5 uCi/cc High Range Main Stack Radiation M002 / M302 1 to 1E6 mR/hr Off-Gas Radiation (SJAE Discharge)
M004 / M304 0.1 to 1E6 cps Radwaste Liquid Effluent Radiation
EP-MA-1 10-100 Revision 0 Page 20 of 33 ATTACHMENT 9 U.S. NRC Emergency Response Data System (ERDS) Activation For Peach Bottom Atomic Power Station (PBAPS)
Page 2 of 2 COMPUTER POINT ENGINEERING UNITS DESCRIPTION R006 0 to 359 degrees 320' Tower 2 Wind Direction R007 0 to 100 mph 320' Tower 2 Wind Speed R008 0 to 99 degrees 320' Tower 2 Sigma Theta SPDS 0030 / 0330 30 to 230 degrees F Average Torus Temperature SPDS 0200 I 0500 0 to 125% power Average Non-Bypassed APRM Power SPDS 0201 I 0501 -325 to 371 inches Average Compensated Reactor Level SPDS 0202 10502 -2 to 225 psig Average Selected Drywell Pressure SPDS 0222 0.1 to 1E6 cps Average Inserted SRM Count Rate SPDS 0223 / 0523 1 to 21 feet Average Torus Level SPDS 1274 /1574 0 to 25,000 gpm A Loop LPCI Flow SPDS 1275 1575 0 to 25,000 gpm B Loop LPCI Flow SPDS 1276 /1576 0 to 30% H2 Torus Hydrogen SPDS 1277 /1577 0 to 30% 02 Torus Oxygen SPDS 1278 / 1578 0 to 30% H2 Drywell Hydrogen SPDS 1279 / 1579 0 to 30% 02 Drywell Oxygen SPDS 1287 / 1587 1E-7 to 1 E5 uCi/cc Average Main Stack Radiation SPDS 1288 / 1588 1E-7 to I E5 uCifcc Average Vent Stack Radiation SPDS 1289 / 1589 75 to 55 degrees F Bulk Average Drywell Temperature SPDS 1293 / 1593 0 to 21 M#/hr Total Feedwater Flow T061 /T361 1 to 1E8 Rem/hr Channel 2 Drywell High Radiation T062 / T362 1 to 1E8 Rem/hr Channel 3 Drywell High Radiation T063 / T363 I to 1E8 Rem/hr Channel 4 Drywell High Radiation T081 /T381 I to 1E8 Rem/hr Channel 1 Drywell High Radiation
EP-MA-110-100 Revision 0 Page 21 of 33 ATTACHMENT 10 Instructions for Establishing Priority Status (OSC Team) Board [PEACH BOTTOM]
Page 1 of 2 NOTE: Upon completion of the following steps, the priority status board terminals at the EOF and OSC will display the same information as the TSC terminal.
Any priorities entered prior to the EOF / OSC connections will not be transmitted to their PC.
STEP 1 TURN ON computer.
STEP 2 SELECT "CANCEL" at Password and Printer Hardware Windows. (The NetMeeting Program should start-up.)
STEP 3 SELECT "CALL" on menu.
STEP 4 SELECT "Host Meeting", and then SELECT "OK" STEP 5 On "NetMeeting" Window, SELECT TOOLS, and then SELECT SHARING STEP 6 On "Sharing" Window, SELECT "PRIORITY.WBD - IBID", and then SELECT "SHARE" STEP 7 On "NeiMeeting" Window, SELECT "CALL", and then SELECT "NEW CALL" STEP 8 On "Place a call" Window, SELECT "10.250.254.61" for the EOF, and then SELECT "CALL".
NOTE: If connection cannot be made, then CALL the EOF and ASK someone to reboot priority status board computer. VERIFY automatically accept calls feature is "checked on" Call Menu, then RETRY previous step.
STEP 9 On "NetMeeting" Window, SELECT "CALL", and then SELECT "New Call" STEP 10 On "Place a call" Window, SELECT "per29281", and then SELECT "CALL" NOTE: If connection cannot be made, then CALL the OSC and ASK someone to reboot priority status board computer. VERIFY automatically accept calls feature is "checked on" Call Menu, then RETRY previous step.
CAUTION Failure to perform STEP 11 will render that section of the screen unusable by the EOF and OSC STEP 11 MINIMIZE "NetMeeting" Window.
STEP 12 MAXIMIZE "Priority.wbd - ibid" Window.
EP-MA-1 10-100 Revision 0 Page 22 of 33 ATTACHMENT 10 Instructions for Establishing Priority Status (OSC Team) Board [PEACH BOTTOM]
Page 2 of 2 STEP 13 VERIFY operation of the Priority Status Board by contacting the OSC & EOF after recording initial message At the completion of drill/emergency, PERFORM the following:
STEP I On "NetMeeting" Window, SELECT "CALL", and then SELECT "HANG UP" STEP 2 From the START Menu, SELECT "SHUT DOWN
EP-MA-1 10-100 Revision 0 Page 23 of 33 ATTACHMENT 11 TSC Electronic Display Board Instructions [PEACH BOTTOM]
Page 1 of 2 A. TO CREATE A NEW MESSAGE (Not on file):
STEP I SELECT: GEN FILE STEP 2 TYPE file name for file (must be 8 or less characters)
STEP 3 PRESS: <ENTER>
STEP 4 EDIT beginning at the character before the message STEP 5 PRESS: "FUNC", then PRESS "TRAVEL SPEED", and SELECT: 1 STEP 6 PLACE desired features before each "MESSAGE/WORDS" by pressing "FUNC" followed by the desired feature STEP 7 TYPE: MESSAGE (see attached "MESSAGE FILES")
STEP 8 PRESS: <ENTER>
B. TO TRANSMIT MESSAGES (in file):
STEP I SELECT: SEL FILE STEP 2 TYPE desired file name (i.e., WELCOME, DRILLALE, DRILLSIT, etc.)
STEP 3 PRESS: <ENTER>
STEP 4 PRESS: TRANSMIT STEP 5 Port? SELECT: 1 STEP 6 PRESS: <ENTER>
C. IN THE EVENT OF A POWER OUTAGE (No message on screen):
STEP I SELECT: ERASE FILE STEP 2 TYPE: ALL STEP 3 PRESS: <ENTER>
EP-MA-1 10-100 Revision 0 Page 24 of 33 ATTACHMENT 11 TSC Electronic Display Board Instructions [PEACH BOTTOM]
Page 2 of 2 MESSAGE FILES File Name File WELCOME DRILLALE Roll center, spell, flash, "Welcome", split screen, burst "Technical Support", split screen, roll center, "Center" DRILLSIT Roll up, "This is a Drill", split screen, ripple, "Site Area Emergency",
split screen, roll down, "This is a Drill", burst, "Site Area Emergency" DRILLGEN Roll up, "This is a Drill", split screen, ripple, "General Emergency",
split screen, roll down, "This is a Drill", burst, "General Emergency" ALERT Spell, "Alert", Roll down, "Alert", split screen, "Emergency Classification is", split screen, burst, flash, "Alert", flash SITE AREA Roll center, "Site Area Emergency", scroll center, "Site Area Emergency", split screen, "Emergency Classificationis", split screen, zip, flash, "Site Area Emergency" GENERAL Roll center, "General Emergency", scroll center, "General Emergency", split screen, "Emergency Classificationis", split screen, zip, flash, "General Emergency"
EP-MA-110-100 Revision 0 Page 25 of 33 ATTACHMENT 12 TSC Overhead Projector Remote Control Instructions {PEACH BOTTOM]
Page 1 of I B
TO TO FROM L PROJ: Press to control the left projector CTR PROJ: Press to control the center projector L PROJ I R PROJ: Press to control the right projector CTR PROJ R PROJ l 3 P MNS Im PMS 4 FROM PMS 1: Displays PMS 1 on the selected projector PS PI 5 PMS 2: Displays PMS 2 on the selected projector PMS 3: Displays PMS 3 on the selected projector TERM I PMS 4: Displays PMS 4 on the selected projector PMS 5: Displays PMS 5 on the selected projector TERM 2 TERM 1: Displays Terminal 1 on the selected projector STERMI 3 TERM 2: Displays Terminal 2 of the selected projector TERM 3: Displays Terminal 3 on the selected projector
\1 J USER'S REMOTE r STANDBY: Toggles the selected projector into or out of the standby mode. Holding this key down for more than 2 seconds will toggle all the projectors. It is recommended to place the projectors in standby mode rather than turning them off, unless the projectors will not be used for more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
OFF: Turns the selected projectors off. If this key is held down for more than 2 seconds, all of the projectors are turned off.
1%,
EP-MA-110-100 Revision 0 Page 26 of 33 ATTACHMENT 13 Operation of the EOF Projector Controller Page 1 of I LERG
-rIVIIEPDS 1 2 0
3
. E 0-EPDS 1 2 3 0 E 4 '5 6 E WE Projector Selection and Powerup Selection a computer display on one of the following To Darken a Screen without Deenergizing the PCs: EPDS1, EPDS2, EPDS3, EPDS4, EPDS5, Projector(s)
TMI1, TMI2, DOSE1, or DOSE2. To darken on display, press the projector button for On the Projection Controller, press the projector the projector you wish to darken and then under the button (LEFT, CTR, RIGHT, ENC1, or ENC2) for the STANDBY group on the Projector Controller, press projector on which you wish to project a PC display. SINGLE.
DO NOT SELECT PROJECTOR ENCl or ENC2 To darken all projectors, press ALL under the WITHOUT CONCURRENCE FROM FACILITY STANDBY group on the Projector Controller To MANAGEMENT. deenergize a display and raise the screen, press the Then press the source PC button projector button for the projector you wish to The screen will come down and the projector will deenergize and then under the OFF group on the warmup and countdown to "0"at which time the Projector Controller, press SINGLE.
image seen on the PC will appear on the projector To deenergize all projectors and raise all screens, screen. press ALL under the OFF group on the Projector Repeat for up to two other PCs as desired. Controller At any time a PC display can be projected on one or more screens simply by pressing the projector To Deenergize a Projector(s) button and then the source PC. Note: Deenergizing a projector should not be done if the projector will be needed shortly (use STANDBY instead ) The unit will go through a timed cycle of several minutes before reenergizing if an attempt is made to turn it on immediately after turning it off.
EP-MA-110-100 Revision 0 Page 27 of 33 ATTACHMENT 14 JPIC OUTLOOK Access Page 1 of 1 The JPIC PCs, Writer 1 and writer 2, are equipped for use of Microsoft Outlook e-mail in both send and receive modes.
A. Instructions for logging on to Outlook are as follows:
STEP I LOG ON either Writer I PC or Writer 2 PC in the normal manner.
STEP 2 DOUBLE CLICK on the Outlook icon on the desktop. The Choose Profile window will appear.
STEP 3 CLICK the arrow at the right side of the Profile Name box.
STEP 4 SELECT your name from the list by clicking on it, and then CLICK on OK.
The Enter Password Window will appear.
NOTE: If your name is not on this list, you do not have Outlook send/receive access from this location. You should arrange for a person whose name is on this list to log on.
STEP 1 TYPE your normal LAN user ID in the password space. Example:
UOOOABC.
STEP 2 ASSURE that the entry in the Domain Name box is pecouser, and then CLICK on OK.
STEP 3 DELETE any other entry and type in pecouser as necessary.
You are now logged onto Microsoft Outlook.
You CAN:
"* Send company e-mail
"* Receive company e-mail
"* Send internet e-mail
"* Receive e-mail You CANNOT:
"* Save e-mails to the personal folders on your office PC if those folders are located on the hard drive of your office PC.
"* Access e-mails in the personal folders on your office PC if those folders are located on your office PC hard drive.
STEP 1 CLICK on the "Start" button on the task bar.
EP-MA-110-100 Revision 0 Page 28 of 33 ATTACHMENT 15 News Writer / Chronological Events Description Log Users Guide Page 1 of 2 STEP 2 CHOOSE the "Newswriter" icon.
STEP 3 After "Newswriter" loads:
- a. Print out Biographies. After the JPIC has been staffed, biographies for the Spokespersons present need to be obtained.
"* Click on "Biography" under the box for "Requested Document".
"* Select the appropriate file under the section marked "Biographies" by either double clicking on the file name or single click on the file and then click on "View".
"* Select "File" from the Toolbar at the top of the page, the select Print from the pulldown menu.
"* Repeat this process to obtain Biographies for all Spokespersons present.
- b. Print out approved Press Releases. The News Writer prepares the Press Release by revising Boilerplate files in the program.
- 1. In the Newswriter program, Click on "Press Release" under the "Requested Document" box.
- 2. Select the appropriate station by Clicking on the station under the "Station Name" box. Both the Boilerplate files and any unique Press Release files should nbw be listed under the "Press Release" box.
NOTE: If the file you want is not listed, you may need to refresh the Newswriter files by clicking on either Biographies or Chronological Events Description Log and then click back onto Press Release.
The saved file should now appear.
- 3. Double Click on the file name for the Press Release that you want. The word processor should access the file.
- 4. Select "File" from the Toolbar at the top of the page, then select Print.
- 5. Exit the word processor to return to the Newswriter program.
EP-MA-110-100 Revision 0 Page 29 of 33 ATTACHMENT 15 News Writer / Chronological Events Description Log Users Guide Page 2 of 2 C. Print out approved Chronoloqical Events Description Loqs.
- 1. In the "Newswriter program, Click on "Chronological Events Description Log" under the "Requested Document" box.
NOTE: Ifthe file you want is not listed, you may need to refresh the Newswriter files by clicking on either Biographies or Press Releases and then click back onto Chronological Events Description Log. The saved file should now appear.
- 2. Double click on the file name for the Chronological Events Description Log file that you want. The word processor should access the file.
- 3. Select "File" from the Toolbar at the top of the page, then select Print.
- 4. Exit the word processor to return to the Newswriter program.
EP-MA-1 10-100 Revision 0 Page 30 of 33 ATTACHMENT 16 Offsite Siren Activation Page 1 of 2 II i Limerick / Peach Bottom I TIME: / DATE: INITIALS
- 1. INITIAL SIREN ACTIVATION INFORMATION:
- a. Requesting Official: (Name) (Phone)
- c. Date / Time authorization given: / / at
- d. Date / Time to activate: I / at
- e. Siren Mode (Alert or Attack):
- 2. COMPUTER ACTIVATION (If required, otherwise N/A.)
- a. If computer is locked up orunresponsive, then REBOOT computer by either:
"* Simultaneously DEPRESS "CRTL", "ALT" and "DELETE" keys; or
"* CYCLE power switch (ON/OFF) 3a. ACTIVATION OF ALL SIRENS: (On REAC-3000 front panel)
(1) Using "CURSOR" Up/Down Arrow buttons, SELECT appropriate siren mode (Alert or Attack)
(2) DEPRESS "ENTER" button twice 3b ACTIVATION OF SIRENS FOR A SINGLE COUNTY: (REAC-300 panel)
(1) Using "CURSOR" Up/Down Arrow buttons, SELECT appropriate siren mode (Alert or Attack)
(2) DEPRESS "ENTER" button once (3) DEPRESS "CURSOR" Down arrow buttom once (4) DEPRESS "ENTER" button once (5) Using "CURSOR" Up/Down Arrow buttons, SELECT appropriate County and LIST below.
(6) DEPRESS "ENTER" button once (7) DEPRESS red "ACTIVATION" button 3c. ACTIVATION OF SIRENS FOR A MUNICIPALITY: (REAC-300 panel)
(1) Using "CURSOR" Up/Down Arrow buttons, SELECT appropriate siren mode (Alert or Attack)
(2) DEPRESS "ENTER" button once (3) DEPRESS "CURSOR" Down arrow buttom twice (4) DEPRESS "ENTER" button once (5) Using "CURSOR" Up/Down Arrow buttons, SELECT appropriate Municipality and LIST below:
(6) DEPRESS "ENTER" button once (7) DEPRESS red "ACTIVATION" button
EP-MA-110-100 Revision 0 Page 31 of 33 ATTACHMENT 16 Offsite Siren Activation Page 2 of 2 M imrick /Peach Bottom 3d. ACTIVATION OF A SINGLE SIREN: (REAC-300 panel)
(1) Using "CURSOR" Up/Down Arrow buttons, SELECT appropriate siren mode (Alert or Attack)
(2) DEPRESS -ENTER" button once (3) DEPRESS "CURSOR" Down arrow buttom three times (4) DEPRESS "ENTER" button once (5) Using "CURSOR" Up/Down Arrow buttons, SELECT the desired siren(s) and LIST below:
(6) DEPRESS "ENTER" button once (7) DEPRESS red "ACTIVATION" button
- 4. REPORT results of siren activation(s) to requesting authority.
EP-MA-1 10-100 Revision 0 Page 32 of 33 ATTACHMENT 17 TSC Overhead Projector Display Instructions [LIMERICK]
Page 1 of2 LGS STATUS BOARDIDATA SYSTEM OPERATION Goal:
- 1. Provide good information flow.
- 2. Get data systems up and running.
Terminals: (Start-up as appropriate)
- 1. PMS - 2(two) terminals next to drafting table.
- 2. Simulated PMS - behind security table. - used in drills if simulator is playing.
- 3. EPDS - 3(three) terminals in cubicles. Subset of PMS has RAD & MET data also.
Transmits data to NRC.
Ligihts:
- 1. Dim lighting so that screens are easier to read.
- 2. Main switches are by the entrance and the door to the engineering room.
Hand Held Control Box:
- 1. Activates one-gun and pull down screens.
- 2. Located near the EP Director on desk.
- 3. To activate hit any one of the purple buttons to get box to light up in order to see the Touch Menu.
- 4. Select the "Emergency Management" button on the touch menu.
- 5. First, select a screen ( left, center, right ) and then second, select computer terminal data (PMS1, PMS2, SimPMS, EPDSI, EPDS2, EPDS3) you want displayed on that screen.
- 6. Typical setup is to use EPDSl (right screen), EPDS2(center screen), & EPDS3(left screen).
- 7. To turn off select the "Exit" button and then the "All Off" button.
EP-MA-110-100 Revision 0 Page 33 of 33 ATTACHMENT 17 TSC Overhead Projector Display Instructions [LIMERICK]
Page 2 of 2 EPDS Terminals:
- 1. When you turn them on they will automatically come on with EPDS running.
- 2. Numbers on the terminal correspond to with the Hand Held Control Box touch pad menu.
- 3. Maximize screen.
- 4. Select Plant Unit / Simulator(drill only) from the pull down menu at the top.
- 5. Technical support group lead will provide info on what unit/data to display in a real emergency.
- 6. Typical Setup:
EPDS1 - Accident Unit - 12 DAS Display (right screen)
EPDS2 - Accident Unit - 0 Plant Overview (center screen)
EPDS3 - Accident Unit - 1 Summary Display (left screen)
- 7. Be familiar with the screens and what data is available on each.
- 8. The Plant Overview screen has a trending option. Double-click on any parameter and it will give you a 30 min. trend of that parameter. The "Scale" option from the pull down menu allows you to change the scale setup.
- 9. The "Playback" option from the pull down menu gives a Trend Playback.
Priority Status Board:
- 1. Information written on board displays at the EOF and OSC, the computer terminal next to the board displays what they see.
- 2. Board is pressure sensitive.
- 3. Follow the instructions on the card. The card has two sides - one with detailed instructions and one with simplified instructions.
- 4. To write on board select a pen - (as a rule use black) and write with the black marker.
- 5. To erase select Erase (broad or narrow) then erase. '
Helpful Hint When the director changes priorities press the erase button and quickly mark the new priorities in small numbers next to the old priorities. (Since the erase button was pressed the small new priority numbers will not show at the other sites.) Then press erase and erase the old priority numbers, press the black pen and write the new priorities in large numbers. This saves time and allows you concentrate on what the director is communicating.
- 6. The "Snapshot" button allows you to take a snapshot of the board to be stored in the computer.
EP-MA-1 10-200 Exekrn,. Revision 0 Page 1 of 34 Nuclear Level 2 - Reference Use DOSE ASSESSMENT PURPOSE 1.1. This procedure provides guidance for performing offsite radiological dose assessments during an emergency using Dose Assessment and Protective Action Recommendation (DAPAR) Program for Limerick Generating Station (LGS) and Peach Bottom Atomic Power Station (PBAPS).
1.1.1. As a Windows-based application designed in Microsoft ACCESS, DAPAR uses many standard user interfaces. Instructions are not provided in basic computer operations in the Windows environment. The user must be familiar with these to efficiently operate the program. It is also assumed user is familiar with health physics fundamentals. Emergency Response Organization (ERO) training will provide an overview of dose assessment methodologies.
- 2. TERMS AND DEFINITIONS 2.1. Centerline (plume): An imaginary line drawn in the middle of the plume along its downwind travel direction. The plume concentrations and deposition are assumed to be the highest along the centerline.
2.2. Cloud Shine: Gamma radiation from radioactive materials in the air (plume).
2.3. Committed Dose Equivalent (CDE): Committed dose equivalent means the dose equivalent to organs or tissues of reference (T) that will be received from an intake of radioactive material by an individual during the 50-year period following the intake.
2.4. 2.4 Committed Effective Dose Equivalent (CEDE): Committed effective dose equivalent is the sum of the products of the weighting factors applicable to each of the body organs or tissues that are irradiated and the committed dose equivalent (CDE) to these organs or tissues. Thyroid values are taken from EPA-400, Table 5-4 to be consistent with the NRC RASCAL dose assessment program used by the Pennsylvania Emergency Management Agency (PEMA) / Bureau of Radiation Protection (BRP). Actual meteorology is used, since it gives the most accurate dose projection.
2.5. Core Damage: Damage to the components that comprise the reactor core.
Core damage typically refers to the failure of fuel cladding and/or fuel melting as a result of overheating.
EP-MA-1 10-200 Revision 0 Page 2 of 34 2.6. Curie (Ci): A unit of radioactivity equal to 3.7E+1 0 disintegrations per second.
2.7. DAPAR
Dose Assessment and Protective Action Recommendation (DAPAR) software provides two major functions (Quick Assessment and Full Assessment) in order to perform dose assessment. (Refer to Attachment 1 for a Basis System Flow Diagram.)
A. Quick Assessment is used by the Shift Dose Assessor to arrive at offsite dose projections and PARs, or to verify classifications in as prompt a time as possible during fast breaking events without taking too much time away from their event mitigating actions. A monitored release is the only method used in the quick assessment. Some assumptions and standard numbers are used to limit the amount of data Control Room personnel must enter prior to calculating a PAR.
B. Full Assessment is used by the called-in ERO Staff in the TSC/EOF and allows for more detailed assessment of a release. The following methods may be used to project offsite doses:
"* MonitoredRelease: Offsite radiological assessment related to a monitored value taken at one of several release locations (Plant Vent Stack, Waste Processing Vent Stacks and Turbine Building Vent Stack) within the plant.
"* ContainmentLeakage/ Failure:Offsite radiological assessment related to a default, known, or predicted level of containment leakage or failure.
"* Field Team Survey and Sample Analysis: Offsite radiological assessment related to comparisons of field team radiological survey and isotopic sample concentrations with predicted plume dispersion.
"* Release Point Sample Analysis: Offsite radiological assessment related to a measured isotopic concentration taken at the point of release to the environment.
2.8. Delta T: The difference in temperature from the lower temperature sensor and the upper temperature sensor on the Exelon meteorological tower. Delta T is used to calculate stability class.
2.9. Deposition
The contamination found on the surface of the ground.
2.10. Dose Commitment: The dose that will be accumulated by a specific organ over a specified period following uptake.
2.11. Dose Conversion Factor (DCF): The dose equivalent per unit intake of a radionuclide (mrem/uCi) or the effects of exposure to a given concentration of an isotope in a plume. R/hr per uCi/cc.
EP-MA-1 10-200 Revision 0 Page 3 of 34 2.12. Dose Proiection: The calculation of individual radiation exposure at a given location at some time in the future. Dose projections are performed in response to an actual or anticipated release of radioactive material to the environment.
2.13. Emergency Planning Zone (EPZ): An area around a nuclear power plant in which plans are in place for an emergency at the plant. Plans are in place to take immediate protective actions for individuals located within 10 miles of the Nuclear Plants. This area is called the Plume Exposure Emergency Planning Zone. In addition, longer-term plans are in place for the Ingestion Pathway Emergency Planning Zone which is within 50 miles of the plant.
2.14. Evacuation Exposure Period: The period during which those being evacuated are exposed to the radioactive plume.
2.15. Millirem (mR): One one-thousandth of a Rem. The Rem is a unit of measure that defines the extent of biological injury that results to the body when it is exposed to radiation.
2.16. Emergency Preparedness Data System (EPDS): Electronic graphical display of plant, meteorological and radiological data needed for accident and dose assessment.
2.17. Protective Action Guidelines (PAGs): Radiation exposure guidelines established by the Environmental Protection Agency which are used to determine the appropriate protective actions to be taken on the part of emergency workers and the general public. These actions include sheltering and evacuation.
2.18. Protective Action Recommendations (PARs): A recommendation made by Exelon personnel to the offsite authorities on the appropriate protective actions to be taken on the part of the general public. The PARs are based on plant conditions or dose projections using the PAGs for guidance.
2.19. Release in Progress: Defined as ANY radioactive release that is a result of, or associated with, the emergency event.
The definition requires the assessment of both plant conditions and effluent monitors to fully evaluate the situation.
"* If effluent monitors show an obvious increase, there is a release.
"* If effluent monitors show a minor increase, a pathway from RCS to Containment to Environment must be evaluated.
"* If effluent monitors are by-passed, a pathway from RCS to Containment to Environment must be evaluated.
EP-MA-1 10-200 Revision 0 Page 4 of 34 An illustration is as follows (Note that these MUST be associated with the particular event):
Have ANY of the following occurred?
"*ANY increase in effluent radiation monitors
"*ANY positive pressure in containment with RCS leakage
"*ANY radioactivity (other than naturally occurring) detected by air sampling in site ventilation, buildings, areas or offsite areas NO
"*ANY reactor trip or rapid shutdown. with ANY pnmary-to secondary leakage or CVCS leakage, venting or draining NO release is occurnng outside of containment
"*ANY secondary system steam release with primary to secondary leakage
"*ANY other event related indication of gas or liquid release from YES A release is in progress 2.20. Safety Relief Valve: A valve that serves to reduce excessive pressure in the Reactor Coolant System (RCS) to protect them from being damaged by excessive pressure.
2.21. Site Boundary: For classification and dose projection purposes, the Site Boundary is the Exclusion Area Boundary, a 2500-foot (LGS) / 2700-foot (PBAPS) radius around the plant. The actual boundary is specified in the ODCM.
2.22. Station Vent: That part of the plant's ventilation system through which the containment building and auxiliary building air may be processed to the outside atmosphere. The discharge of the station vent is continuously monitored for abnormal amounts of radiation and would be isolated long before radiation levels approach federal limits.
2.23. Sectors: Pre-designated areas offsite in which Protective Actions such as evacuation will be recommended.
2.24. Total Effective Dose Equivalent (TEDE): Total Effective Dose Equivalent (TEDE) means the sum of the deep-dose equivalent (for external exposures) and the committed effective dose equivalent (for internal exposures). For the purpose of this procedure TEDE also includes 4 days of deposition exposure.
EP-MA-110-200 Revision 0 Page 5 of 34
- 3. RESPONSIBILITIES 3.1. An on-shift Radiation Protection Technician (RPT) at the unaffected station shall serve as the Shift Dose Assessor and perform required dose assessments prior to responsibility being transferred to either the Technical Support Center (TSC) or Emergency Operations Facility (EOF).
3.2. The TSC Radiological Controls Coordinator shall relieve the Shift Dose Assessor and perform required assessments if the transfer of PAR / dose assessment responsibilities to the EOF is delayed.
3.3. The EOF Dose Assessor shall relieve the TSC Radiological Controls Coordinator when directed by the EOF Dose Assessment Coordinator, and perform required dose assessments. Responsibility for dose assessments can be assumed directly from the Shift Dose Assessor.
- 4. MAIN BODY 4.1. Initiating Conditions:
4.1.1. An emergency has been declared; AND 4.1.2. Events require the calculation of radiological effects due to an actual or potential release of radioactive materials near or beyond the site boundary.
CAUTION Use of the program to project doses based on normal plant readings would indicate offsite doses many magnitudes higher than actual offsite doses. The program should not be used to calculate the actual dose received by populations. As part of the post accident investigations, a more in depth analysis is needed to actually assign doses receives to members of the public.
EP-MA-110-200 Revision 0 Page 6 of 34 4.2. Start Up 4.2.1. If the main computer screen has DAPAR icons, then USE left mouse click on the icon to start the program.
NOTE: Backups to the hard drive DAPAR software are a common network drive on the LAN and CD-ROM disk with each dose assessment computer.
The common drive paths are:
"* Limerick Generatinq Station (LGS):
\\PECO\.PBS2_DATA1.PBSSRVS.PBS.PECO\EPDAPAR
" Peach Bottom Atomic Power Station (PBAPS):
\\PECO\.PBS2_DATA. .PBS_SRVS.PBS.PECO\EPDAPAR
- 1. If the assigned Dose Assessment Computer cannot access the program over the Exelon LAN or the DAPAR program will not run, then INSTALL the program on any computer from backup CDs or Disks located in the OSC, TSC or the EOF.
4.2.2. VERIFY that the correct station version of the DAPAR program is being used.
NOTE: There is a different version of DAPAR for each Station. Refer to Figures 1-1 & 1-2. Each version takes into account different release points and gaseous effluent radiation monitor conversion factors.
Figure 1-2
EP-MA-1 10-200 Revision 0 Page 7 of 34 CAUTION Once the User selects "Quick Assessment" or "Full Assessment," returning to the title screen will reset all program values.
4.2.3. From the Title Screen, SELECT either "Full Assessment" or "Quick Assessment" and then GO TO either:
- 1. QUICK ASSESSMENT - Section 4.3
- 2. FULL ASSESSMENT - Section 4.4 4.2.4. PROVIDE the DAPAR Input Sheet (Attachment 7) to the following individual, based on facility, for system / event status information:
"* Control Room 4- STA/Independent Assessor (or Shift Manager)
"* TSC -4 Operations Communicator (or Operations Manager)
"* EOF -4 Operations Advisor (or Technical Support Manager)
EP-MA-1 10-200 Revision 0 Page 8 of 34 4.3. Quick Assessment: (Figures 2-1 & 2-2)
NOTE: The Quick Assessment operations and calculations are identical to the Full Assessment method for a monitored release, but uses a default release path and core damage assumptions for the determination of offsite doses.
This allows for a rapid assessment from the Main Control Room.
!!qpotor Infor. w i-.Oqq,ta Q Meloorelopical
ý -9 Figure 2-1: LIMERICK Figure 2-2: PEACH BOTTOM 4.3.1. Monitor Information- User chooses the appropriate monitor from the listed effluent monitors.
- 1. SELECT the applicable release point:
STATION MONITOR READOUT Limerick North Stack pCi/sec South Stack pCi/cc Main Stack pCi/sec Peach Bottom Vent (Rx Bldg) Stack pCi/sec Torus Vent cpm
- REFER to Attachment 5 to obtain data from Emergency Preparedness Data System (EPDS) to input into DAPAR.
EP-MA-110-200 Revision 0 Page 9 of 34 4.3.2. ENTER Reading Information - Enter the appropriate monitor reading.
4.3.3. ENTER Time After Shutdown Information - Enter the time since the reactor was shutdown in hours and minutes (hh:mm).
4.3.4. ENTER MeteorologicalData - Enter the appropriate data from plant instruments as follows:
- 1. If meteorological data (wind speed / direction and stability class) are NOT available via EPDS or locally in Control Room, then GO TO Attachment 2.
NOTE: The conditions Good or Adverse in the following step are in relation to the weather. Adverse is heavy rain or any other condition that would hinder the flow of traffic.
4.3.5. CLICK ON the Conditions button to open the Weather Conditions Window (Figure 3).
ICorsditionz Timr of Tiume OWeeIL Figqure 3
- 1. SELECT the appropriate conditions for the program to calculate the Maximum Evacuation Time Estimate (ETE).
NOTE: Once the user sets the evacuation conditions, the program will place the Max ETE value in the Release Duration and Max ETE text boxes.
4.3.6. Under Release Duration, CHANGE the displayed time to the known release duration.
- 1. If a good estimate of the release duration cannot be determined, then USE the default ETE value entered by the program.
4.3.7. SELECT the PARs button - The program will calculate the downwind doses based on user inputs and display Protective Action Recommendation Window. GO TO Section 4.9.
EP-MA-110-200 Revision 0 Page 10 of 34 4.4. Full Assessment The Full Assessment operations and calculations are identical to the Quick Assessment method for a monitored release, but it allows the user to make more choices in performing dose projection calculations.
Choosing the Full Assessment option directs the program to a baseline data entry window (Figure 4). The window is divided into four input areas.
I Ful Asessm nt Figure 4 4.4.1. Source Term - This allows user to choose the appropriate source term depending on plant conditions and the type of accident that has occurred:
- 1. SELECT Reactor Core Accident if the source of the release is from the reactor core.
A. Under "Type of Damage", SELECT Gap or Melt.
B. ENTER the % Damage based on core damage estimates or known conditions in the plant.
C
EP-MA-1 10-200 Revision 0 Page 11 of 34
- 2. SELECT Spent Fuel Accident if the release is caused by damage to the spent fuel.
A. Under "Fuel Type", CHOOSE between New Fuel or Old Fuel.
B. Under "Fuel Status", CHOOSE between Under Water or Dry.
NOTE: The program uses a gap release scenario and defaults to a reactor Time After Shutdown based on this choice.
Limerick only
- 3. SELECT Backwash Demin Spectrum if the release results from a backwash operation.
EP-MA-1 10-200 Revision 0 Page 12 of 34 4.4.2. Dominant Release Path - This allows user to choose the most appropriate release path: (Figures 5-1 & 5-2)
Figure 5-1: LIMERICK Figure 5-2: PEACH BOTTOM Figure 5-1: LIMERICK (Cont'd) Figure 5-2: PEACH BOTTOM (Cont'd)
- 1. If a release through containment or drywell is Icontainment Reductiorm chosen, then DETERMINE if containment sprays are 'ON' or 'OFF'. (Figure 6)
EP-MA-110-200 Revision 0 Page 13 of 34
- 2. DETERMINE Containment I Drywell I Containment Reductions holdup time, and SELECT the appropriate condition. (Figure 7)
Figure 7
- 3. If a release through the Aux Bldg or Rx Bldg., then DETERMINE the building holdup time. (Figure 8) ý5,HofdtP'The <2 Hour t 7~ 2 -24 Hoxrs
>24 HoursT N1OTE.
Selection o0< 2hours- GCUIculteý
ýhe hhetdose, > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> the Figure 8
l .e~el R I I -
Figure 9b
EP-MA-1 10-200 Revision 0 Page 14 of 34
- 5. If a release through a filtered Vent or SBGT, then CHOOSE if the filters are working or not. (LGS: Figure 10a & b / LGS: Figure 1Oc)
NOTE: If the release has been ongoing for a long time or contains a large amount of liquids filters may not be working.
I RESFler H 3 I SBGT Filter Reductions I Figure 10a (LGS) Figure 10b (LGS) d cios.- II I Fite R
Figure 10c (PBAPS) 4.4.3. ENTER Meteorological Data- Enter the appropriate data from plant instruments.
4.4.4. Assessment Methods - CHOOSE the appropriate assessment method based on available inputs. Assessment methods:
- 1. Monitored Release - SELECT this method for a release through a monitored release point such as the main stack or Rx Bid vent stacks or through the Main Steam Relief Valves. GO TO Section 4.5.
- 2. Containment Leakage - SELECT this method for containment failure scenarios.
GO TO Section 4.6.
- 3. Field Team Data - SELECT this method if field team survey or sample data is available. GO TO Section 4.7.
- 4. Release Path - SELECT this method if a sample of a release has been obtained and a release flow rate can be estimated. GO TO Section 4.8.
EP-MA-1 10-200 Revision 0 Page 15 of 34 4.5. Monitored Release (Figure 11) rRgluI 1 4.5.1. SELECT the applicable release point:
STATION MONITOR READOUT Limerick North Stack pCi/sec South Stack pCi/cc Main Stack pCi/sec Peach Bottom Vent (Rx Bldg) Stack pCi/sec Torus Vent cpm 4.5.2. ENTER Reading Information - Enter the appropriate monitor reading.
4.5.3. SELECT the Print button to print a report of offsite dose projections based on the monitored release.
- REFER to Attachment 3, Dose Assessment Report (Printout).
- REFER to Attachment 6 to save report(s) as ADOBE Acrobat file.
- 1. SELECT a different monitor and/or change readings to recalculate doses.
- 2. SELECT the Back button to change input data on Full Assessment Form.
4.5.4. SELECT the PAR button to view PAR form - GO TO section 4.9.
EP-MA-110-200 Revision 0 Page 16 of 34 4.6. Containment Leakaqe/Failure (Figure 12)
Fiqure 12 4.6.1. SELECT the appropriate containment release mode:
- 1. Leakage - Program defaults to the Design Leakage rate per the station UFSAR. If a different percentage of leak rate has been calculated by TSC engineers enter that value in the % per day text box.
- 2. Failureto Isolate - Assumes 100% of the isotopes available for release are released in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> time period.
- 3. CatastrophicFailure-- Assumes 100% of the isotopes available for release are released in a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> time period.
4.6.2. [After User enters data the program calculates offsite doses] PERFORM one of the following:
- 1. SELECT the Print button to print offsite dose projections based on containment failure.
- REFER to Attachment 3, Dose Assessment Report (Printout).
- REFER to Attachment 6 to save report(s) as an ADOBE Acrobat file.
- 2. SELECT the Back button to change input data on Full Assessment Form.
EP-MA-1 10-200 Revision 0 Page 17 of 34 4.7. Field Team Analysis (Figure 13)
The program calculates the plume Travel Time and Release Time to allow Dose Assessment personnel to compare previous dose assessment reports with data measured in the field.
4.7.1. Dose Rate Survey- SELECT this method if Field Team Survey Data is available.
4.7.2. Air Sample Results - SELECT this method if Field Team Air Sample Data is available.
Figure 13
EP-MA-110-200 Revision 0 Page 18 of 34 4.7.3. ENTER the Field Team information as follows:
NOTE: The program will not allow "mr/hr" readings for sample data or isotopic results for survey data.
- 1. ENTER Downwind (miles) - straight-line distance from release point to sample location.
- 2. ENTER Crosswind (miles) - the distance the team was away from the centerline when the sample was taken. The program will warn user if reported sample location is wider than expected plume width
- 3. IF the analysis basis is Dose Rate Survey- ENTER the Field Team Survey reading in "mR/hr" into the box labeled Level.
- 4. IF Analysis basis is Air Sample Results - ENTER the uCi/cc values for each known isotope in the table at the upper right section of the form.
NOTE: Prior to obtaining analysis results from field air sample, the 1-131 concentration, in uCi/cm 3 , calculated using the KI Spreadsheet Program per EP-MW(MA)-110-100 shall be used.
- 5. ENTER Survey Time - Enter the time the survey or sample was taken.
4.7.4. [After User enters data the program calculates offsite doses] PERFORM one of the following:
- 1. SELECT the Print button to print offsite dose projection reports based on Field Team Analysis.
- REFER to Attachment 3, Dose Assessment Report (Printout).
A. REFER to Attachment 6 to save report(s) as an ADOBE Acrobat file.
- 2. SELECT the Back button to change input data on Full Assessment Form.
- 3. IF Field Team samples were the selected basis, SELECT the PAR button to view PAR form - GO TO section 4.9.
EP-MA-110-200 Revision 0 Page 19 of 34 4.8. Release Point Analysis (Figure 14)
Fiqgure 14 4.8.1. ENTER the known Isotopic Concentrationfor each isotope (if unknown leave blank).
4.8.2. ENTER Vent Flow Rate (or estimate flow rate for other releases) in SCFM.
4.8.3. [After User enters data the program calculates offsite doses] PERFORM one of the following:
- 1. SELECT the Print button to print offsite dose projections based on Release Point Analysis.
- REFER to Attachment 3, Dose Assessment Report (Printout).
- REFER to Attachment 6 to save report(s) as an ADOBE Acrobat file.
- 2. SELECT the Back button to change input data on Full Assessment Form.
EP-MA-1 10-200 Revision 0 Page 20 of 34 4.9. Protective Action Recommendations (Figure 15)
The Protective Action Recommendation (PAR) form displays a summary of the downwind dose projections with a map showing which Sectors (colored areas) where Protective Actions Recommendations should be made.
Figqure 15
EP-MA-1 10-200 Revision 0 Page 21 of 34 4.9.1. The RR button will display the total release - ,------ ,--
rates for isotopic groups in Ci/sec. a Rates !
(Figure 16) Nioble Gasis:j FEiO2 SHalogens:~>> :r0D1YE+00 FPartculates: toOE+OO Fb Figure 16 4.9.2. SELECT the Go Back button and modify inputs. This will return user to either Quick Assessment Form or one of the Assessment Method forms available in the Full Assessment mode.
4.9.3. SELECT Printto print the PAR report.
"* REFER to Attachment 4, PAR Report (Printout).
"* REFER to Attachment 6 to save report(s) as an ADOBE Acrobat file.
4.9.4. SELECT the STATE REPORT button to display DAPAR BRP PARAMETER REPORT and PRINT copy of form.
4.9.5. After each dose calculation is performed, FAX STATE REPORT and copies of associated Dose Assessment and PAR Reports to the Pennsylvania Emergency Operations Center (EOC) - Attention "BRP".
- 5. DOCUMENTATION:
None
- 6. REFERENCES 6.1. Exelon DAPAR Program Software Requirements Specification 6.2. Commitments - None
EP-MA-1 10-200 Revision 0 Page 22 of 34
- 7. ATTACHMENTS 7.1. Attachment 1, Basic Program Flow Diagram 7.2. Attachment 2, Determination of Stability Class 7.3. Attachment 3, Sample Dose Assessment Report 7.4. Attachment 4, Sample Protective Action Recommendation (PAR) Report 7.5. Attachment 5, EPDS Radiological and Meteorological data 7.6. Attachment 6, ADOBE Acobat File Saving 7.7. Attachment 7, DAPAR Input Sheet 7.8. Attachment 8, DAPAR BRP Report - Full Assessment (EXAMPLE)
\'. _
EP-MA-1 10-200 Revision 0 Page 23 of 34 ATTACHMENT I BASIS PROGRAM FLOW DIAGRAM I I I Field Team Release Point Analysis Analysis I I The above diagram shows basic tasks that can be performed by the DAPAR program and how a user would navigate between them.
There are two methods available to perform calculations:
- 1. Quick Assessment - Normally used by the Control Room and TSC Dose Assessors to quickly determine the appropriate Protective Action Recommendation for a gaseous effluent monitored release point. Program automatically picks conservative choices, limiting the number of user inputs needed to get results.
- 2. Full Assessment - Normally used by EOF Dose Assessor, and TSC Dose Assessor if EOF activation is'delayed. Program allows for more choices and user inputs to provide analysis of different releases and/or field monitoring data.
EP-MA-1 10-200 Revision 0 Page 24 of 34 ATTACHMENT 2 DETERMINATION OF STABILITY CLASS Page 1 of 2
- 1. If Met Tower data is unavailable from ERO Applications' programs or via local indications in the Control Room, another source of meteorological data may be used such as the Meteorological Vendor, National Weather Service or a local TV or Radio broadcast stations.
- a. Wind Speed (MPH) - Obtain and enter wind speed in Miles per Hour (MPH)
- b. Wind Direction (From) - Obtain and enter the direction the wind is coming FROM in degrees. (0-3600)
- c. Stability Class (A-G) - Obtain and enter the stability class.
Stability Class Categories A Extremely unstable conditions B Moderately unstable conditions C Slightly unstable conditions D Neutral conditions E Slightly stable conditions F Moderately stable conditions G Extremely stable conditions
- 2. If the stability class is not available or provided, use the following tables to choose appropriated value:
NOTE: Meteorological Vendor normally provides AT/Az or C7.
- a. If Surface Wind Speed (in mph) is available, then USE Table 1-1.
- b. If delta temperature (AT) or sigma theta ((ye), then USE station-specific table (if provided).
NOTE: The conditions Good or Adverse in the following step are in relation to the weather. Adverse is any weather condition, which would hinder the flow of traffic.
EP-MA-1 10-200 Revision 0 Page 25 of 34 ATTACHMENT 2 DETERMINATION OF STABILITY CLASS Page 2 of 2 Table 1-1 Table 1-2 Limerick (Tower 1) _
CIass AT (3 (deg A <-2.5 25 B -2.5 to -2.3 20 C -2.2 to -2.0 15 D -1.9 to -0.7 10 E -0.6 to +1.9 5 F +2.0 to +5.2 2.5 G > +5.2 1.7 Table 1-3 Peach Bottom (Tower 2)
A < -2.9 25 B -2.9 to -2.7 20 C -2.6 to -2.4 15 D -2.3 to -0.8 10 E -0.7 to +2.3 5 F +2.4 to +6.2 2.5 G > +6.2 1.7
EP-MA-1 10-200 Revision 0 Page 26 of 34 ATTACHMENT 3 SAMPLE DOSE ASSESSMENT REPORT Page 1 of 2 Peach Bottom Dose Assessment Method: Monitored Release Time: 18:50 Date: CBfl9tQM02 Relase Path: <RCS>-<DryWell>- <Torus>-<RBCont>- PRF: 0.16
<SBGT>-<MnStack>- <ENV>
Core Damage :10% Gap Time After SID (hours): 0320 Wind Direction (from) : 10 Release Duration (hours): 4.00 Monitor: Main Stack WROM Release Height: Elevated Reading (uCVseo) :1.00E+05 Monitor Reading for GE : 3.32E+05 Distance External External Inhalation 4 Day 4 Day Thyroid (miles) DDE DDE CEDE Deposition TEDE Dose CDE (mRAhr) (mRem) (mRem) DDE (mRem) (mRem)
(mRem)
S.B. <.1 <.1 2.55E-01 1.82E-01 4 75E-01 1.16E401 1.0 1.18E+01 2.58E+01 1.72E+02 1.23E+02 3.21E402 7.82E+03 1.5 2.22E-01 4.84E+01 3.23E+02 2.31E+02 6.02E+02 1.47E+04 2.0 2.28E+01 4.97E+01 3.32E+02 2.36E+02 6.18E+02 1.50E+04 2.5 1.84E+01 4.01E+01 2.68E+02 1.91E+02 4.98E+02 1.21E+04 3.0 1.58E+01 3A.E+01 2.31E+02 1.64E+02 4.30E+02 1.05E+04 3.5 1.31E+01 2.85E+01 1.91E+02 1.368E02 3.55E-02 8.65E+03 4.0 1.10E+01 2.40E+01 1.612E+02 1.14E+02 2.99E+02 7.28E+03 45 9.24E+00 2.02E+01 1.35E+02 9.60E+01 2.51E-202 6.11E+03 6.0 6.86E+00 1.50E+01 9.99E+01 7.12E+01 1.88E+02 4.53E+03 5.5 7.33E+00 1.60E+01 1.07E+02 7.61E+01 1.99E402 4.84E+03 6.0 6.47E+00 1.41E+01 9.42E2+01 6.72E+01 1.76E402 4.27E+03 6.5 5.72E+00 1.25E201 8.34E+01 5.94E+01 1.55E+02 3.78E+03 7.0 418E200 9.12E+00 6.090E+01 434E201 1.13E202 2.76E+03 IPAG ExceededAt (Miles) TEDE: None CDE(thyroid) :45 miles Page 1 of 2 Peach Bottom DAPAR vI.0
EP-MA-1 10-200 Revision 0 Page 27 of 34 ATTACHMENT 3 SAMPLE DOSE ASSESSMENT REPORT Page 2 of 2 Peach Bottom Dose Assessment IMthod: tVbnitored Release Time: 18"52 Date: C8.Ar2)Q2 Relase Path: <RCS>-<DryWeIl>-<Torus>-<RBContr>- PRF: 0.16
<SB GT>-<MnStack>- <ENV>
Core Damage : 10% Gap Time After SD (hours):O030 Wind Direction (from) : 10 Release Duration (hours): 4:00 Monitor : Main Stack WROM Release Height : Elevated Reading (uC Vs ec) :1.00 E+05 Monitor Reading for GE : 3.32E+05 Distane Extemal External Inhalation 4 Day 4 Day Thyroid (miles) DDE DDE CEDE Deposition TEDE Dose CDE (mRihr) (mRem) (mtRem) DDE (mRem) (mRem)
(mRemr) 7.5 3.6440O0 7.95E+00 5.31E+01 3.78E+01 9.8E-t01 2.41E+03 8.0 3.47E+00 7.56E+00 5.05E+01 3.60E+01 9.OE+01 2.29E203 85 2.93E200 6.39E+00 4.27E,01 3.04E+01 7.95E+01 1.04E+03 0.0 2.55E+00 5.55E+00 3.71E+01 2.64E-01 6.01E-431 1.68E+03 0.5 2.40E+00 5.24E+00 3.50E+01 2.50E+01 6.52E+01 1.59E+03 10.0 2.52E+00 5.61E+00 3.68E+01 2.62E+01 6.85E+01 1.67E+03 IPAG Exeiedd At (Miles): TED E: None C DE (thyroid) : 4.5 miles Page 2 of 2 Peach Bottom DAPAR vl.0
EP-MA-110-200 Revision 0 Page 28 of 34 ATTACHMENT 4 SAMPLE PROTECTIVE ACTION RECOMMENDATION (PAR) REPORT Page 1 of I Peach Bottom Dose Based Protective Action Recommendations Time: 12.41 Date: 0711tie202 Sectors to be Evacuated Assessment Method:
Monitored Release Evacuation Conddicrs:
Adverse Stability Class:
Wind Direcdon (from) m Wind Speed (mph):
Release Durablon (hrs):
Generalized Guidance Evacuate when dose is:
- 1) >= 1000 mRemTEDE
- 2) >= 5030 mRem Thyroid Shelter when evacuation is not possible.
Euacuate: All sectors betwveen0to 5 rilesand sct ors WSW, W, WNWbetvwen 5to 10 miles Affected Area Dose Tables Emergency Le',el GENERAL EMERGENCY r E > CDE Thy >
Ring I 1.15E+05 3.54E+05 Affected Sectors (D-2 mnk Y_
W Ring 2 8 97E+04 2.77E+05 Adjaoert Sectors Ring 3 2 50E+04 7.722E04 WSW,WNW Group Release Rates (uCifsec)
Noble Gases HaloQerns Particulates True (NRC): 5.oo00oI F1102E+07 3.83E I5 Peach Bottom DAPAR vi .0 Page '1 of 1I 1 of P each B ottom DAPAR v1.0
EP-MA-1 10-200 Revision 0 Page 29 of 34 ATTACHMENT 5 EPDS RADIOLOGICAL AND METEOROLOGICAL DATA Page I of 1 DAPAR input data is obtained through EPDS. Instructions for use of the EPDS system use procedure EP-MA-1 10-100, "ERO Computer Applications".
The EPDS menu contains a DAPAR screen selection:
STEP 1: Using the mouse, MOVE the arrow to the menu bar STEP 2: CLICK on station of interest STEP 3: CLICK on unit of interest STEP 4: SCROLL down to "DAPAR".
STEP 5: CLICK on "DAPAR"
EP-MA-1 10-200 Revision 0 Page 30 of 34 ATTACHMENT 6 ADOBE ACROBAT FILE SAVING Page 1 of 2 STEP 1: From the DAPAR PAR report tool bar left mouse click on "File", scroll down left mouse click on print. The following text box appears:
KStoPBtestl pdf testl.pdt Hie nane, IKStoPBtst Of ~ Sae'
~Save a,- ypeý IPFýFfde(-DFJ -a STEP 2: SAVE report in appropriate file:
" If this is a drill, then SAVE the dose projection in the "Drills and Exercises" folder in the site common drive.
" If this is a real event, then SAVE the dose projection in the "Real Event" folder in the site common drive.
The common drive paths are:
Limerick Generatinq Station (LGS):
\\PECO\.PBS2_DATAI .PBSSRVS.PBS.PECO\EPDAPAR Peach Bottom Atomic Power Station (PBAPS):
\\PECO\.PBS2_DATAI .PBSSRVS.PBS.PECO\EPDAPAR STEP 3: If the assigned Dose Assessment Computer cannot access the program, then PERFORM the following:
- 1. TYPE in a file name
- 2. SAVE file type as PDF
- 3. Left mouse CLICK on the "Save" command button NOTE: The dose projection should appear as an Adobe PDF file.
EP-MA-110-200 Revision 0 Page 31 of 34 ATTACHMENT 6 ADOBE ACROBAT FILE SAVING Page 2 of 2 STEP 4: If the Adobe PDF does not appear, then left mouse CLICK on the Adobe icon on the bottom of the screen.
- 1. Left mouse CLICK on the Abobe print button from the tool bar f7JZ.ýý FM--
- 2. When the adobe 'Print" box appears, left mouse CLICK on the printer "Name" drop down menu arrow.
St. DW-*
- 3. Scroll down and HIGHLIGHT the desired printer
- 4. When the desired printer appears in the "Name" field, left mouse CLICK "OK" command button to print.
STEP 5: Left mouse CLICK the X in the upper right hand corner to return to the DAPAR PAR report.
EP-MA-1 10-200 Revision 0 Page 32 of 34 ATTACHMENT 7 DAPAR INPUT SHEET Page 1 of I Date: / / Time: Station / Unit:
OBTAIN FROM: CR (STA/IA) / TSC (Ops. Communicator)IEOF (OperationsAdvisor)
IMONITOR INFORMATION RELEASE POINT #1: LIMERICK: PEACH BOTTOM:
[]North Stack ] Main Stack South Stack ]Vent Stack
[]UNMONITORED Torus Hard Pipe Vent
[ UNMONITORED DESCRIBE FROM RPV TO RELEASE POINT:
RELEASE DURATION: []No Release In Progress START TIME: I STOP TIME: Total Duration: hrs
,REUEF INPUTS (PWR ONLY) ., SIG PRESSURE:_ pslg I NO. SRVs OPEN: I PORV OPEN: IYES I (I NO TIME AFTER RX SHUTDOWN > RX POWER: % I RX TRIP at: hrs. I ATWAS: I ]YES I []NO
_CNTMT VENTING EXPECTED [] NO I []YES - REASON:
'CONTAINMENT REDUCTIONS SPRAYS: ON I OFF HOLD UP TIME: <1 HR 1 112-24 HRS I []> 24 HRS
.TORUS/WETWELtREDUCTIONS: []BYPASSED I (]SATURATED I (]SUBCOOLED SBGT FILTERREDUCTIONS . ; [IFILTERS WORKING I [I FILTERS NOT WORKING
$1G REDUCTIONS (PWRONLY) (I SECONDARY BOILING I [(SECONDARY SOLID I [ISECONDARY DRY OBTAIN FROM: CR (STA/IA) / TSC (Core/HydraulicEngr.) / EOF (Techncial Advisor)
I REACTOR CORE ACCIDENT I SPENT FUEL ACCIDENT TYPE OF DAMAGE: I GAP I I MELT FUELTYPE: I NEW I I OLD AMOUNT OF DAMAGE: % FUEL STATUS: I UNDER WATER I I DRY OTHER:
EP-MA-1 10-200 Revision 0 Page 33 of 34 ATTACHMENT 8 DAPAR BRP PARAMETER REPORT - FULL ASSESSMENT (EXAMPLE)
Page 1 of 2 NOTE: "QUICK ASSESSMENT" Report also provided.
BAPAR BRP PARAIMETER REPORT-FULL ASSESSMENT SITE LIMERICK STATION D=se Au9g09.2002 Tirm 0S.19A1I PM Rcklne Pinthy ýcRCS2-c Df- .ctd b-CR BCTrV:-cSDGTD-cNaruSzct-c ENV-PIuUM2N463K :37.flm ct m Tjme Afgr SID0l O~hour-SOURCETERM MET DATA.
93 RccLiorCorcAccidcnt Wihd:*Sped 1 mikttijr TypeofrDmnWrP 0 tp 0 Mek Wihd Directbn 1 deegrg; Ana urld Damable 10% Deda T 1
- m. e D ur -bq Re kl E0 ) b u,'l oS pacnt Fucl A c aidcnt r dalTyp D NeON 0 Old RcI~as~ FbvR*.e 1h9E4Olcn'Tl'sec-1 mw&aulam 0 UdgIdrW;gKr 0 Div W .thariCandki-.Adr*erse o3 B=kw,,h Dcnin Spacrum RELEASE CONCENTRATIONS (uCi/oco) RELEASE%
Nobla 141 Hal0scn5 Par3inuIaM*-. NobLk £i- 3alo10cn!
S.83 E-03 1.19 E-0s 2.93 E-O'7 99.7922% 0.202 %
Reduction Factors Drywell Cc-tainmert VetWell Retcotionfs bca cjg G Canw rahm rtSpw2y'Orr 6 BV~-e 0 Holdkup Time c2 Jou r 0 CanwthmerK SpraC'ON' 0 Stumud 0 2 -2,L Hcau G9 Haldizp Trne: ,c 2 Hoa-r 0 Suboaakld 0 b-.2d Woum 0 2-22 Huars o !,2& Hours SBGT Filter Reduatilns RERS Filter RedLticns 0 FiLets fat Wartking 0 F'iLer Nat Warking 0 ritel$Wartring 0 Fileso Wa*.i TOTAL PRF .01 Page 1 of 2 UIMIERICKDAPAR vl.O
EP-MA-1 10-200 Revision 0 Page 34 of 34 ATTACHMENT 8 DAPAR BRP PARAMETER REPORT - FULL ASSESSMENT (EXAMPLE)
Page 2 of 2 DAPAR BRP PARAMErTER REPORT - FULL ASSESSMENT ASSESSMENT METHOD 23 Monitorod RcmIm ManuLar Naorth L:ck RE Reading 1111111 ,,Chr~ec 11 Conlainin nt Lcaokgc'Failu a o Lent~gQ e a 0 tah r'ildrw Wobte (100% perdaJy o Catlra pt t railurc (100% in 1 hfa rl o3 Field Team Aanasis Bamis 0 Surtcf DOonwhd Leel(mRnhi C rcmwinid Su rte Time 0 &rmplk Dcrnwhd Sa,,ejTime C rasnwand o3 Rclkcas Point$Sawnmpl rkw Rat P age 2 of 2 U ME R ICK DAPAR vl.0 Page 2 of 2 UMERICKDAPAR vl.O
EP-AA-110-301 o Revision 0 Page 1 of 25 Nuclear Level 2 - Reference Use CORE DAMAGE ASSESSMENT (BWR)
- 1. PURPOSE 1.1. The purpose of this attachment is to provide emergency response personnel with the methodology to estimate the degree of possible core damage at Exelon Nuclear's Boiling Water Reactor (BWR) stations. REFER to EP-AA 110-302 for methodology to estimate potential core damage for a Pressurized Water Reactor (PWR).
1.2. Core damage may be assessed by:
"* Evaluating the drywell radiation levels (and confirmed by evaluating the extent of time the core was uncovered),
"* Concentration of certain isotopes in a reactor coolant analysis, or
"* Concentration of hydrogen in the primary containment.
This procedure is intended to provide an acceptable alternative to existing station core damage assessment models and methods utilized by Reactor Engineering.
- 2. TERMS AND DEFINITIONS 2.1. BWR - Boiling Water Reactor 2.2. Cladding - The outer coating (usually zirconium alloy, aluminum or stainless steel), which covers the nuclear fuel elements to prevent corrosion of the fuel and the release of fission products into the coolant.
2.3. Containment Type
- Clinton (Mark Ill)
- Dresden (Mark I)
- LaSalle (Mark II)
- Limerick (Mark II): 764 assemblies 3 Containment Volume (384,570 ft 3) = Suppression Pool (149,380 ft ) + Drywell (235, 190 ft')
- Peach Bottom (Mark I): 764 assemblies 3 3 3
Containment Volume (303,600 ft ) = Suppression Pool (127,800 ft ) + Drywell (175, 800 ft )
- Quad Cities (Mark I)
EP-AA-1 10-301 Revision 0 Page 2 of 25 2.4. Core Release Fraction - The fraction of each isotope in the core inventory that is assumed to be released from the core under given core conditions.
2.5. Fission Products - The nuclei (fission fragments) formed by the fission of heavy elements or by subsequent radioactive decay of the fission fragments.
2.6. Gap - The space inside a reactor fuel rod that exists between the fuel pellet and the fuel rod cladding.
2.7. Gap Release - The release into containment of fission products in the fuel pin gap.
2.8. In-Vessel Core Melt - A condition during a reactor accident in which some of the cladding or reactor fuel melts as a result of overheating the fuel and remains inside the reactor vessel.
2.9. In-Vessel Core Melt Release - A release into containment from the reactor vessel, which assumes the entire core has melted, releasing a representative mixture of radioisotopes.
2.10. Shutdown -- As defined by station emergency operating procedures, normally assumed to be less than 4% for a BWR.
2.11. Slump - Relocation of molten reactor core during an accident.
2.12. Source Term - The amount and isotopic composition of material released or the release rate, used in modeling releases of material to the environment.
2.13. Spiked Coolant - Reactor coolant containing increased concentrations of non-noble isotopes, sometimes seen with rapid shutdown or depressurization of primary system.
2.14. Spiked Coolant Release -The release into containment of 100 times the non noble gas fission products found in the coolant.
2.15. Subcritical - The reactor condition when the number of neutrons released by the fission is not sufficient to achieve a self-sustaining nuclear chain reaction.
Defined under station emergency operating procedures.
2.16. TID - Total Isotopic Distribution
EP-AA-110-301 Revision 0 Page 3 of 25
- 3. RESPONSIBILITIES 3.1. The TSC Core/ThermalHydraulic Engineershall serve as the Core Damage Assessment Methodology (CDAM) Evaluator.
3.2. The TSC Radiation Controls Engineershall coordinate radiological and chemistry information with the Core/Thermal Hydraulic Engineer in support of core damage assessment.
3.3. The TSC Managershall coordinate core damage assessment activities.
- 4. MAIN BODY 4.1. ASSESS the status of critical BWR safety functions and MONITOR for indications that the core may already be uncovered or may soon become uncovered.
- 1. PROJECT core damage if uncovered using the following methods, as applicable:
- Attachment 3, "Core Uncovery Time Method"
- Attachment 4, "Containment Hydrogen Concentration Method" 4.2. MONITOR radiation levels in containment to confirm and assess core damage.
- 1. PROJECT core damage using Containment Radiation Level Method (Attachment 1).
4.3. CONTINUE to assess core damage a reactor coolant sample to confirm extent of core damage using the Attachment 2 (Reactor Coolant Sampling Method).
4.4. CONTINUE to assess core damage and INFORM those assessing consequences, classification and protective actions.
- 5. DOCUMENTATION 5.1. Reactor core damage assessment methods derived from U.S. NRC RTM-96, Chapter A (Reactor Core Damage Assessment). Figures included in RTM 96, Chapter A were generated using CONDOS II (NUREG/CR-2068).
EP-AA-1 10-301 Revision 0 Page 4 of 25
- 6. REFERENCES 6.1. U.S. Nuclear Regulatory Commission (NRC) Response Technical Manual (RTM) 96, March 1996 6.2. Exelon Nuclear Radiological Emergency Plan Annex for Clinton Generating Station 6.3. Exelon Nuclear Radiological Emergency Plan Annex for Dresden Generating Station 6.4. Exelon Nuclear Radiological Emergency Plan Annex for LaSalle County Generating Station 6.5. Exelon Nuclear Radiological Emergency Plan Annex for Limerick Generating Station 6.6. Exelon Nuclear Radiological Emergency Plan Annex for Peach Bottom Atomic Power Station 6.7. Exelon Nuclear Radiological Emergency Plan Annex for Quad Cities Generating Station
- 7. ATTACHMENTS 7.1. Attachment 1, Containment Radiation Level Method 7.2. Attachment 2, Reactor Coolant Sampling Method 7.3. Attachment 3, Core Uncovery Time Method 7.4. Attachment 4, Containment Hydrogen Concentration Method
EP-AA-1 10-301 Revision 0 Page 5 of 25 ATTACHMENT 1 CONTAINMENT RADIATION LEVEL METHOD Page 1 of 18 Per RTM-96, Chapter A (Method A.4), these calculations should provide the maximum reading expected under the conditions stated. The calculations assume: (1) a prompt release to containment of all fission products in the coolant, spike, gap or from in-vessel core melt; (2) uniform mixing in the containment; and (3) an unshielded monitor that can see most of the containment volume (minus torus / suppression pool volume). Because the mix is most likely different from that assumed in the calibration of the monitor, the actual reading at the upper end of the scale could differ by a factor of 10-100 if a shielded detector is used for higher radiation measurements.
The levels of damage indicated should be considered minimum levels unless there are inconsistent monitor readings. Inconsistent readings may be caused by the uneven mixing in containment (e.g., steam rising to top of dome, not enough time for uniform mixing to occur).
Figures have been prepared for each station, which represent plots of percent core damage versus containment radiation readings and percent clad damage versus containment radiation readings. Uncorrected containment radiation readings shall be used to provide a preliminary estimate of percent core and clad damage during the first ten (10) hours following a reactor shutdown.
CAUTION Containment radiation levels cannot be used to assess core damage in all cases. The release may bypass the containment, be retained in the coolant, be released over a long period of time, or not be uniformly mixed. Therefore, a low containment radiation level reading does not guarantee a lack of core damage.
This method should not be used if containment radiation monitors do not "see" more than 50% of Drywell volume.
- 1. MONITOR containment radiation levels to assess the degree of clad and/or core damage.
NOTE: The readings taken following a Loss of Coolant Accident (LOCA) into the primary containment will be most accurate using the containment radiation monitors.
MidWest ROG REE o PM-1 10-1001 for a listing of appropriate plant parameter IIpoints to be used following a LOCA.I
EP-AA-1 10-301 Revision 0 Page 6of25 ATTACHMENT I CONTAINMENT RADIATION LEVEL METHOD Page 2 of 18
- 2. DETERMINE the time following the event and the uncorrected containment radiation reading and compare to the following figures for assessing the degree of core or clad damage.
Dresden I SREFER to Figure 1-1 for PERCENT CORE DAMAGE VERSUS CONTAINMENT and Figure 1-2 for CLAD DAMAGE ASSESSMENT F LaSalle I
RiEFER to Figure 1-3 for PERCENT CORE DAMAGE VERSUS CONTAINMENT and Figure 1-4 for CLAD DAMAGE ASSESSMENT FRFRt iue15fr PERCENT CORE DAMAGE VERSUS I CNANETadFiure 1-6 for CLAD DAMAGE ASSESSMENT Clinton PREFER toFiIgureand 1-8 fo PERCENTCORE DAMAG VERSUS CONT d ig re -9an 1-0 orCLAD DAMAGE ASSESSMENT AIa ME REFER to Figure 1-11 for PERCENT OF FUEL INVENTORY AIRBORNE IN THE CONTAINMENT VERSUS APPROXIMATE SOURCE AND DAMAGE ESTIMATE REFER to Figure 1-12 for PERCENT OF FUEL INVENTORY AIRBORNE IN THE CONTAINMENT VERSUS APPROXIMATE SOURCE AND DAMAGE ESTIMATE
EP-AA-1 10-301 Revision 0 Page 7 of 25 ATTACHMENT I CONTAINMENT RADIATION LEVEL METHOD Page 3 of 18 FIGURE 1-1 Dresden Station: Core Melt Assessment Percent Damage Versus Containmentradiation Readings (Uncorrected)
Page 1 of I Time After Accident
-I-@10hrs .-- 6 hrs --- 4hrs --- 2 hrs x--1 hr -- ,r--30 min --m--6 min 100 Z/v- v1K
- I/ I/ A 1 ii II z
10 / I y -i 0 a)
IV 11/ 1: CO E O 0 A /1 I L)
C,,
w 11 1 1 I I I 13 1 E+03 1 E+04 1 E+05 I E+06 Containment Monitor Rad/hr.
EP-AA-1 10-301 Revision 0 Page 8 of 25 ATTACHMENT 1 CONTAINMENT RADIATION LEVEL METHOD Page 4 of 18 FIGURE 1-2 Dresden Station: Clad Damage Assessment LOCA with Noble Gas Release Only Page 1 of I Time After Accident hrs --
1-0-l 6 hrs -.-- 4hrs -x-2 hrs --x 1 hr -- A--30min --- 6min 100 ,
UII 10 z
0 0m
/ xi 0.1" V LUJ o Ol 00.1 0001 1 A I PEFlf 1 E+01 1 P-02 1 E+03 1.E+04 I.Ei-05 Containment Monitor Rad/hr.
EP-AA-110-301 Revision 0 I Page 9of25 ATTACHMENT 1 CONTAINMENT RADIATION LEVEL METHOD Page 5 of 18 FIGURE 1-3 LaSalle Station: Core Melt Assessment Percent Damage Versus Containmentradiation Readings (Uncorrected)
Page 1 of I Time After Accident
-I-s10 hrs ---- 6 hrs -- 4 hrs --- 2 hrs -x-1 hr --t30min --- 6 min 100 p , I I I I I
/ A /
/ /1/ /I 1 A I/ I I/
z
/ / 0 CID E I-0 w Cl)
I-0 "o A -J!
/l' 1
01 1.E+O3 1 E+04 1.E+05 1E+06 Containment Monitor Rad/hr.
EP-AA-1 10-301 Revision 0 Page 10 of 25 ATTACHMENT I CONTAINMENT RADIATION LEVEL METHOD Page 6 of 18 FIGURE 1-4 LaSalle Station: Clad Damage Assessment LOCA with Noble Gas Release Only Page 1 of I Time After Accident
--- 10hrs .-- 6 hrs -- 4 hrs -- 2 hrs I hr --- 30mmin -- 6min 100 10 Yz IIII
/ II C,,
a)
E 0.1. .
A / ;
0 r //
00 I ,
. f il I l 0,/01
- 0 1E I-05 1
E+03 1.E 1
E-+01 1.E+02 1 POO0 Containment Monitor Rad/hr.
EP-AA-110-301 Revision 0 Page 11 of 25I ATTACHMENT 1 CONTAINMENT RADIATION LEVEL METHOD Page 7 of 18 FIGURE 1-5 Quad Cities Station: Core Melt Assessment Percent Damage Versus Containmentradiation Readings (Uncorrected)
Page 1 of 1 Time After Accident
-.- l0hrs ---- 6hrs -.- 4hrs --- 2 hrs -x-1 hr -.-- 30min -w-6 mirn 100 1 11 V I
z 0
I/I A F-10 A XJ X 0) 0 /" L)
E, E ý1///X I
/i C.)
A/
H Cy I r IZA 17, 01 01 1E+04 1E*05 1E+06 1E+03 Containment Monitor Rad/hr.
EP-AA-1 10-301 Revision 0 Page 12 of 25 ATTACHMENT I CONTAINMENT RADIATION LEVEL METHOD Page 8 of 18 FIGURE 1-6 Quad Cities Station: Clad Damage Assessment LOCA with Noble Gas Release Only Page 1 of 1 Time After Accident s lOhrs 6--6hrs -- 4 hrs -w-2hrs ---- 1 hr ---- 30 nin -i--6 mini 100 IIII.. . A AI Y I [A Ii ll "?
10 l / Iii0 U 01 Y' 11 11I 0001IF 1.E+00 EfOl 1IB02 1E#03 IE+04 IE0 Containment Monitor Radlhr.
EP-AA-1 10-301 Revision 0 Page 13 of 25 ATTACHMENT 1 CONTAINMENT RADIATION LEVEL METHOD Page 9 of 18 FIGURE 1-7 Clinton Station Core Damage Assessment LOCA with Noble Gas Release Only In Containment Page I of I Time After Accident
-- 10 hrs -e--6 hrs e--4 hrs -K-2 hrs --- 1 hr -*---30 min -- 6 min 100 I 17 7 / 1/ 1i1 1i
-1/I I I /I I x zi zI "IY Z- I z 10 0 l
C,)
E I Z / 0 0
C.) 1
.0 z C-)
n'1I 1 I I E+03 1.E+04 1.E+05 1 E+06 Containment Monitor Rad/hr.
EP-AA-1 10-301 Revision 0j Page 14 of 25I ATTACHMENT 1 CONTAINMENT RADIATION LEVEL METHOD Page 10 of 18 FIGURE 1-8 Clinton Station Core Damage Assessment LOCA with Noble Gas Release Only In Drywell Page 1 of 1 Time After Accident
-I--10 hrs ---- 6 hrs -- 4 hrs --- 2 hrs -- 1 hr
- 30 min -- 6 min 100 I 4- -4 III/4
/I-~,- / .*---
. .I . . .. ..-
z I I/ / I/ I/
i /* /i z
- ~ I ~ / 0 10 I! x F 7y z 0
E I-ca Z 0 C.-
.)
////1 z , !,
I 01 1E 03 1 E+04 1 E-05 1 E+06 Drywell Monitor Radlhr.
EP-AA-1 10-301 Revision 0 Page 15 of 25 ATTACHMENT 1 CONTAINMENT RADIATION LEVEL METHOD Page 11 of 18 FIGURE 1-9 Clinton Station Clad Damage Assessment LOCA with Noble Gas Release Only In Containment Page 1 of 1 Time After Accident
.10 hrs -.-- 6 hrs -e--4 hrs -w-2 hrs -- *-1 hr ---- 30 mm -m-6 mIn 100
/V
/z 101 0
S0 E I-001 0001 1 E+00 1 E+01 1 E+02 1 E+03 I E+04 1 E+05 Containment Monitor Rad/hr.
EP-AA-1 10-301 Revision 0 Page 16 of 25 ATTACHMENT I CONTAINMENT RADIATION LEVEL METHOD Page 12 of 18 FIGURE 1-10 Clinton Station Clad Damage Assessment CLINTON STATION LOCA with Noble Gas Release Only In Drywell Page I of 1 Time After Accident 1.-
0-lOhrs .- -6 hrs - 4hrs
-- - -2 hrs --- 1 hr - -i-30min - .---6min 100 100 z
z ký I' S~0
/
1Z 01 /
I-V Y 1 ZI 11 Y/
001 0011 0.001 1 E+00 1.E+01 I E+02 1.E+03 ,
1.E+04 1 E+05 Drywell Monitor Rad/hr.
EP-AA-1 10-301 Revision 0 Page 17 of 25 ATTACHMENT I CONTAINMENT RADIATION LEVEL METHOD Page 13 of 18 FIGURE 1-11 LIMERICK GENERATING STATION Percent of Fuel Inventory Airborne in the Containment vs. Approximate Source and Damage Estimate Page 1 of 3
% Fuel*
Curve Inventory No. Released Approximate Source and Damage Estimate 1 100. 100% TID-14844, 100% fuel damage, potential core melt.
2 10. 10% TID, 100% NRC gap activity, total clad failure, partial core uncovered.
- 3. 3% TID, 100% WASH-1400 gap activity, major clad failure. Z 0
3 1. 1% TID, 10% NRC gap, Max. 10% clad failure.
I-4 .1 .1%TID, 10% NRC gap, 1% clad failure, local heating of CI 5-10 fuel assemblies.
5 .01 .01% TID, .1% NRC gap, clad failure of 3/4 of a fuel I assembly (36 rods). W 6 10-3 .01% NRC gap, clad failure of a few rods 10-4 100% coolant release with spiking.
7 5X10-6 100% coolant inventory release.
10-6 Upper range of normal airborne noble gas activity in containment.
100% Fuel Inventory = 100% Noble Gases +25% Iodine + 1% particulates.
NOTES (1)These curves account for the finite containment volume and shield wall seen by the detector but do not account for any monitor physical or shielding characteristics or calibration uncertainties.
(2)The curves assume that both airborne noble gases and iodines are significant. Sprays (ifused) would make the iodine and particulate contribution (presently about 50%) insignificant. However, particulate plateout on the monitor casing and direct shine doses from components may make the readings unreliable.
(3)Curve uncertainties are on the order of a factor of 5 to 10.
EP-AA-1 10-301 Revision 0 Page 18 of 25 ATTACHMENT 1 CONTAINMENT RADIATION LEVEL METHOD Page 14 of 18 FIGURE 1-11 LIMERICK GENERATING STATION Percent of Fuel Inventory Airborne in the Containment vs. Approximate Source and Damage Estimate Page 2 of 3 LGS CONTAINMENT RADIATION MONITOR CURVES to 0- 10 o0ot O 0p
-I z 4/ I W 1 -
zO 10T 100 TIME AFTER SHUTDOWN (HRS) 1-100% TID 2-10% TID 3-1% TID 4-0.1% TID 5 -0.01% TID 6-0.001% TID
EP-AA-110-301 Revision 0 Page 19 of 25I ATTACHMENT 1 CONTAINMENT RADIATION LEVEL METHOD Page 15 of 18 FIGURE 1-11 LIMERICK GENERATING STATION Percent of Fuel Inventory Airborne in the Containment vs. Approximate Source and Damage Estimate Page 3 of 3 LGS CONTAINMENT RADIATION MONITOR CURVES 0 z 0
0 I
I" 0
C0) 0
.I) z z w z
0 U
103 10-1 100 ito 102 TIME AFTER SHUTDOWN (HRS) 4 - 0.1% TID 5 - 0.01% TID 6 -0.001% TID 7 - 100% REACTOR COOLANT I
EP-AA-1 10-301 Revision 0 Page 20 of 25 ATTACHMENT I CONTAINMENT RADIATION LEVEL METHOD Page 16 of 18 FIGURE 1-12 PEACH BOTTOM ATOMIC POWER STATION Percent of Fuel Inventory Airborne in the Containment vs. Approximate Source and Damage Estimate Page 1 of 3
% Fuel*
Curve Inventory No. Released Approximate Source and Damage Estimate 1 100. 100% TID-14844, 100% fuel damage, potential core melt.
2 10. 10% TID, 100% NRC gap activity, total clad failure, partial core uncovered.
- 3. 3% TID, 100% WASH-1400 gap activity, major clad I z failure. 0 I
3 1. 1% TID, 10% NRC gap, Max. 10% clad failure. Cn 0
4 .1 .1% TID, 10% NRC gap, 1% clad failure, local heating of _
5-10 fuel assemblies. 0 5 .01 .01% TID, .1% NRC gap, clad failure of 3/4 of a fuel assembly (36 rods). uJ 6 10-3 .01% NRC gap, clad failure of a few rods 104 100% coolant release with spiking.
7 5X10-6 100% coolant inventory release.
10-6 Upper range of normal airborne noble gas activity in containment.
- 100% Fuel Inventory = 100% Noble Gases +25% Iodine + 1% particulates.
NOTES (1)These curves account for the finite containment volume and shield wall seen by the detector but do not account for any monitor physical or shielding characteristics or calibration uncertainties.
(2) The curves assume that both airborne noble gases and iodines are significant. Sprays (ifused) would make the iodine and particulate contribution (presently about 50%) insignificant However, particulate plateout on the monitor casing and direct shine doses from components may make the readings unreliable.
(3)Curve uncertainties are on the order of a factor of 5 to 10.
EP-AA-110-301 Revision 0 Page 21 of25 ATTACHMENT 1 CONTAINMENT RADIATION LEVEL METHOD Page 17 of 18 FIGURE 1-12 PEACH BOTTOM ATOMIC POWER STATION Percent of Fuel Inventory Airborne in the Containment vs. Approximate Source and Damage Estimate Page 2 of 3 PEACH BOTTOM CONTAINMENT RADIATION MONITOR CURVES 107 106 I cis0 0
A M 0 0 103 E-4 102 z0 0 X
00 TIME AFTER SHUTDOWN (HRS)
PEACH BOTTOM MONITOR RESPONSE CURVES FOR PRIMARY CONTAINMENT LOW RANGE MONITORS CURVE INDEX
- 1. 100% FUEL INVENTORY (100% TID-14844)
- 2. 10% FUEL INVENTORY (100% GAP ACTIVITY/R.G. 1.25)
- 3. 1% FUEL INVENTORY (10% NRC GAP-CLAD FAILURE)
- 4. 0.1% FUEL INVENTORY
- 5. 0.01% FUEL INVENTORY
- 6. 0.001% FUEL INVENTORY
EP-AA-110-301 Revision 0 Page 22 of 25 ATTACHMENT I CONTAINMENT RADIATION LEVEL METHOD Page 18 of 18 FIGURE 1-12 PEACH BOTTOM ATOMIC POWER STATION Percent of Fuel Inventory Airborne in the Containment vs. Approximate Source and Damage Estimate Page 3 of 3 PEACH BOTTOM CONTAINMENT RADIATION MONITOR CURVES 107 *
- 101 \
z 0
0 r~o (j 1003 E-4 H
0 z 0 H ~I-10I:1I 0
z 3
00 S 10-31 it)-' 100 10, 107 10, TIME AFTER SHUTDOWN (HRS)
PEACH BOTTOM MONITOR RESPONSE CURVES FOR PRIMARY CONTAINMENT LOW RANGE MONITORS CURVE INDEX 4 0.1% FUEL INVENTORY 5 -. 01% FUEL INVENTORY 6 -. 001% FUEL INVENTORY 7 100% COOLANT ACTIVITY
EP-AA-1 10-301 Revision 0 Page 23 of 25 ATTACHMENT 2 REACTOR COOLANT SAMPLING METHOD Page 1 of 1 Per RTM-96, Chapter A (Method A.5), for BWR this method of confirming core damage assumes that releases from the core are uniformly mixed in the coolant and torus /
suppression pool with there is no dilution from injection. If most of the core release is confined to the reactor coolant system, the concentrations in the coolant could be up to 10 times higher. The baseline coolant concentrations are for 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> after shutdown of a core that has been through at least one refueling cycle. The half-life of the fission products should be considered in analyzing samples. The plant-specific coolant system volume does not have a major influence on coolant concentrations (< 20%).
CAUTION Since samples may require hours to collect and analyze, and may not be representative of primary system concentrations (e.g., no flow through sample line), coolant concentrations should NOT be required to confirm core damage.
I. COMPARE coolant isotopic concentrations with the concentrations listed in Table 2-1 to estimate core damage for gap releases or in-vessel melting.
Table 2-1 BASELINE BWR COOLANT CONCENTRATION1 NC - Not Calculated 1 Table 2-1 is consistent with Table A-4 (BWR Baseline Coolant Concentration) from U.S. NRC Response Technical Manual (RTM) 96, March 1996 2 Source for "normal coolant" is ANSI/ANS 18.1, 1984 (confirmed by NUREG/CR-4245, Table 3.2) 3 Concentration in the reactor coolant system and torus / suppression pool
EP-AA-1 10-301 Revision 0 Page 24 of 25 ATTACHMENT 3 CORE UNCOVERY TIME METHOD Page 1 of I Per RTM-96, Chapter A (Method A.3), it can be assumed that the fuel in the core will heat up at 1-20 F per second within 5-10 minutes after the top of an active core isuncovered. These heatup estimates are reasonable within a factor of two if the core is uncovered within a few hours of shutdown (including failure to scram) for a boil-down case (without injection). If there is injection, core heatup may be stopped or slowed because of steam cooling. However, steam cooling may not prevent core damage under accident conditions.
- 1. DETERMINE the time that the core was or is projected to be uncovered.
- 2. ESTIMATE the possible core damage by comparing the time of core uncovery to the values in Table 3-1.
Table 3-1 4 CORE DAMAGE VS. TIME THAT REACTOR CORE IS UNCOVERED`
Time 20% of the Core Core core is uncovered Temperature Temperature Possible Core Damage (minutes) (OF) (°C) 0 >600 >315 None 30-45 1800-2400 980-1300 GAP Release
- Local fuel melting
- Burning of cladding with steam production (exothermic Zr-H20 reaction with rapid H2 generation)
- Rapid fuel cladding failure (gap release core) 30-90 2400-4200 1300-2300 In-Vessel Melt
- Rapid release of volatile fission products (in vessel severe damage release from the core)
- Possible relocation (slump) of molten core
- Possible uncoolable core 120-180+ >4200 >2300 Vessel Melt-Through Melt-through of vessel with possible containment failure and release of additional less-volatile fission products 4 Table 3-1 is consistent with Table A-2 (Core Damage vs. Time That Reactor Core Is Covered) from U.S. NRC Response Technical Manual (RTM) 96, March 1996
EP-AA-110-301 Revision 0 Page 25 of 25 ATTACHMENT 4 CONTAINMENT HYDROGEN CONCENTRATION METHOD Page 1 of I This method may be used to assess the core damage based on the hydrogen concentration in samples of the containment atmosphere.
Per RTM-96, Chapter A (Method A.6), the hydrogen concentrations using this method are for wet samples; however, most hydrogen samples are dry (steam removed). If a dry sample concentration is used, one may overestimate considerably the level of core damage. This method assumes that all hydrogen is released to the containment and is completely mixed in the containment atmosphere.
CAUTION Since containment samples may require hours to collect and analyze, and may not be representative of actual concentrations, hydrogen should NOT be relied upon to confirm core damage in all cases.
- 1. COMPARE the hydrogen percentage obtained to the graph in Figure 3 to estimate percentage of metal-water reaction and possible levels of core damage. Figure 4-1s I
% MetalWater Reaction & Core Damage State 50 40 30 SPossible Melt Through 20 4( Possible Uncoolable core 10 S*Start Fuel Melt Clad Failure 0
0.1 1 10 100 H2 % In Containment
-B-BWR Mk III -X-BWR Mk I & 11 Figure 4-1 is consistent with Figure A-13 (Percentage of Hydrogen in Containment Relative to Core Damage) from U.S. NRC Response Technical Manual (RTM) 96, March 1996
EP-AA-i111 Exek ,n Revision 4 Page 1 of 18 Nuclear Level 2 - Reference Use EMERGENCY CLASSIFICATION AND PROTECTIVE ACTION RECOMMENDATIONS
- 1. PURPOSE 1.1 This procedure provides guidance for the classification of an emergency condition.
1.2 This procedure provides guidelines for determining Protective Action Recommendations (PARs) to be made to offsite authorities during a General Emergency.
1.3 This procedure provides guidance for event termination and entry into Recovery.
Emergency Classification .................................................... REFER to Section 4.1 Downgrading an Emergency Classification ......................... REFER to Section 4.2 Transition to Recovery/Termination ..................................... REFER to Section 4.3 Plant Based PARs ............................................................... REFER to Section 4.4 Dose Based PARs ............................................................... REFER to Section 4.5 Overall PAR Determination ................................................. REFER to Section 4.6
- 2. TERMS AND DEFINITIONS 2.1 Classification - Emergency classifications are divided into FIVE (5) categories or conditions, covering the postulated spectrum of emergency situations. The first four (4) emergency classifications are characterized by Emergency Action Levels (EALs) associated with Initiating Conditions and address emergencies of increasing severity. The fifth, the Recovery classification, is unique in that it may be viewed as a phase of the emergency, requiring specific criteria to be met and/or considered prior to its declaration. The classifications are as follows:
2.1.1 Unusual Event - Events are in progress or have occurred which indicate a potential degradation of the level of safety of the plant. No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety occurs.
2.1.2 Alert - events are in progress or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant. Any releases are expected to be limited to small fractions of the Environmental Protection Agency (EPA) Protective Action Guideline exposure levels.
I EP-AA-1 11 Revision 4 Page 2 of 18 2.1.3 Site Area Emergency - Events are in progress or have occurred that involve actual or likely major failures of plant functions needed for protection of the public. Any releases are not expected to exceed EPA Protective Action Guideline exposure levels except near the site boundary.
2.1.4 General Emergency - Events are in progress or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity. Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area.
2.1.5 Recovery - That period when the emergency phase is over and activities are being taken to return the situation to a normal state (acceptable condition). The plant is under control and no potential for further degradation to the plant or the environment is believed to exist.
2.2 Emergency Action Levels (EALs) - a Pre-determined, Site-specific, observable threshold for a plant Initiating Condition that places the plant in a given emergency class. An EAL can be: an instrument reading; an equipment status indicator; a measurable parameter; a discrete, observable event; or another phenomenon which, if it occurs, indicates entry into a particular emergency class.
2.3 Emergqency Director (ED) - the Director of the facility in Command and Control.
One of the following: the Shift Emergency Director (CR), Station Emergency Director (TSC) or the Corporate Emergency Director (EOF).
2.4 EPA Protective Action Guideline - exposure levels determined by the Environmental Protection Agency for the evacuation of the offsite public following a release of radioactive materials. These levels have been established at one (1)
Rem TEDE or five (5) Rem CDE Thyroid.
2.5 Imminent - mitigation actions have been ineffective and trended information indicates that the event or condition will occur within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
2.6 Initiating Condition (IC)- one of a predetermined subset of nuclear power plant conditions where either the potential exists for a radiological emergency, or such an emergency has occurred.
2.7 Potential - mitigation actions are not effective and trended information indicates that the parameters are outside desirable bands and not stable or improving.
2.8 Protective Action Recommendations (PARs) - PARs are made by Exelon personnel whenever a General Emergency is declared. Additionally, if in the opinion of the Emergency Director, conditions warrant the issuance of PARs, a General Emergency will be declared (Exelon will not issue PARs for any accident classified below a General Emergency).
EP-AA-1 11 Revision 4 Page 3 of 18 2.8.1 Offsite protective actions provided in response to a radioactive release include evacuation and taking shelter.
- 1. Evacuation is the preferred action unless external conditions impose a greater risk from the evacuation than from the dose received.
- 2. Exelon personnel do not have the necessary information to determine whether offsite conditions would require sheltering instead of an evacuation.
Therefore, an effort to base PARs on external factors (such as road conditions, traffic/traffic control, weather or offsite emergency worker response) should not be attempted.
2.8.2 At a minimum, a plant-based PAR to evacuate a 2 mile radius and 5 miles downwind, is issued at the declaration of a General Emergency based on NUREG-0654, Rev.1 Supplement 3. Depending on plant conditions (e.g., a LOSS of all three fission product barriers per the EALs), a PAR to evacuate a 5 mile radius and 10 miles downwind may be issued instead of the minimum PAR.
- 1. The PAR must be provided to the State, and designated local agencies as applicable, within 15 minutes of (1) the classification of the General Emergency or (2) any change in recommended actions.
- 2. The PAR must be provided to the NRC as soon as possible and within 60 minutes of (1) the classification of the General Emergency or (2) any change in recommended actions.
2.8.3 The Emergency Director may elect to specify PARs for any combinations of
[MWROG] Subareas / [MAROG] Sectors or the entire EPZ (or beyond) regardless of plant and dose based guidance.
2.8.4 PARs should not be extended based on the results of dose projections unless the postulated release is likely to occur within a short period of time. Plant based PARs are inherently conservative such that expanding the evacuation zone as an added precaution would result in a greater risk from the evacuation than from the radiological consequences of a release. It also would dilute the effectiveness of the offsite resources used to accommodate the evacuation.
2.8.5 Protective actions taken in areas affected by plume deposition following the release are determined and controlled by offsite governmental agencies.
- 1. Exelon is not expected to develop offsite recommendations involving ingestion or relocation issues following plume passage.
- 2. Exelon may be requested to provide resources to support the determination of post plume protective actions.
EP-AA-111 Revision 4 Page 4 of 18
- 3. RESPONSIBILITIES 3.1 The Shift Emergency Director(Shift Manager), when in Command and Control (C&C), has the non-delegable responsibility for classification of emergencies and final determination of PARs.
3.2 The Station Emergency Director,when in Command and Control, has the non delegable responsibility for classification of emergencies and final determination of PARs.
3.3 The CorporateEmergency Director,when in Command and Control, has the non-delegable responsibility for final determination of PARs. Classification remains with the Station Emergency Director.
3.4 The TSC groups (e.g., Technical Support, Operations, Facility Support, RP/Chemistry) are responsible for monitoring and assessing conditions within their areas in support of classification.
3.5 The Shift Emergency Director(CR) / Technical Manager(TSC) or Technical Support Manager(EOF), in the facility with the Emergency Director having Command and Control, is responsible for evaluating the plant-based PARs from the PAR flowcharts.
3.6 The designatedShift Dose Assessor (CR) / RadiationProtectionManager (TSC) / Radiation ProtectionManager(EOF), in the facility with the Emergency Director having Command and Control, is responsible for evaluating the dose based PARs from the results of the dose assessment analyses and field team surveys/samples.
- 4. MAIN BODY 4.1 Emergency Classification NOTE: Once indication of an abnormal condition is available, classification declaration must be made within 15 minutes. This time is available to ensure that the classification and subsequent actions associated with the classification, if warranted, are appropriate. It does not allow a delay of 15 minutes if the classification is recognized to be necessary. It is meant to provide sufficient time to accurately assess the emergency conditions and then evaluate the need for an emergency classification based on the assessment performed.
The decision to downgrade or terminate the event and enter Recovery is NOT time dependent.
NOTE: If the event escalates to a higher classification before the notification can be made for an initial (or previous) declaration, the time requirements in the previous note restart and notification for the first classification is not made.
EP-AA-111 Revision 4 Page 5 of 18 4.1.1 When an abnormal condition is being evaluated, REFER to the appropriate Station EAL Matrix and PERFORM the following:
- 1. IDENTIFY the Unit Mode for the state of the plant prior to the abnormal condition.
Plant Modes BWRs PWRs 1 Power Operations 1 Power Operations 2 Startup 2 Startup 3 Hot Shutdown 3 Hot Standby 4 Cold Shutdown 4 Hot Shutdown 5 Refueling 5 Cold Shutdown D Defueled 6 Refueling
- 2. REVIEW the Initiating Conditions (ICs) applicable to the operating mode as follows.
A. Starting with the highest (General Emergency) classification level on the left side of the matrix and continue to the lowest (Unusual Event) classification level on the right side of the matrix.
B. IF more than one IC applies to the event, SELECT the highest IC that may be applicable (from all of the ICs that were determined to have been met).
NOTE: Classification is made on a Unit basis. For events affecting both Units, the highest classification on either Unit is used for notification.
A. IF the EAL Threshold Values have been met or exceeded, THEN:
- NOTE the EAL number associated with the IC.
- DECLARE the event.
- RETURN to the appropriate EP-AA-1 12 ERO position checklist. And immediately begin notifications.
B. IF the EAL Threshold Values have not been met or exceeded, THEN return to the appropriate EP-AA-1 12 ERO position checklist.
EP-AA-111 Revision 4 Page 6 of 18 4.2 Downgrading an Emerqency Classification 4.2.1 An Alert Classification may be downgraded to an Unusual Event if conditions warrant.
4.2.2 A Site Area Emergency or General Emergency shall not be downgraded to a lower classification.
- 1. A Site Area Emergency Classification, once declared, shall remain in effect until a General Emergency Classification is warranted or until such time as conditions warrant exiting to Recovery.
- 2. A General Emergency Classification, once declared, shall remain in effect until such time as conditions warrant exiting to Recovery.
4.3 Transition to Recovery/Termination 4.3.1 Complete the Termination/Recovery Checklist (Attachment 1).
- 1. If conditions will allow for the termination of the emergency and entry into Recovery, exit this procedure and enter EP-AA-1 15, Recovery.
- 2. If conditions do not support termination of the emergency and entry into Recovery, continue following the guidance provided in Section 4.1.2.
4.4 Plant Based Protective Action Recommendations (PARs) 4.4.1 Upon declaration of a General Emergency, EVALUATE the results of the plant based PARs using the following attachments:
- Attachment 2, Braidwood Plant Based PAR Flowchart
- Attachment 3, Byron Station Plant Based PAR Flowchart
- Attachment 4, Dresden Station Plant Based PAR Flowchart
- Attachment 5, LaSalle Station Plant Based PAR Flowchart
- Attachment 6, Quad Cities Station Plant Based PAR Flowchart
- Attachment 7, Clinton Station Plant Based PAR Flowchart
- Attachment 8, Limerick/Peach Bottom Plant Based PAR Flowchart 4.4.2 Continue to EVALUATE plant based PARs as Fission Product Barrier status or wind direction changes.
EP-AA-111 Revision 4 Page 7 of 18 4.5 Dose Assessment Based Protective Action Recommendations (PARs)
NOTE: If radiation monitor readings provide sufficient data for assessment, it is NOT apropriate to wait for field monitoring data to become available to confirm or expand a PAR within the 10-mile EPZ.
NOTE: Many assumptions exist in dose assessment calculations, involving both source term and meteorological factors, which make computer predictions over long distances highly questionable.
4.5.1 Dose projections are NOT required to support the decision process in the plant based PAR Flowcharts. However, it is expected that a dose projections be performed as soon as possible by the facility in Command and Control at a General Emergency with a release in progress per EP-MW(MA)-1 10-200.
4.5.2 From the Control Room:
- 1. If a release is in progress at a General Emergency classification, and time permits, then PERFORM an offsite dose assessment using the "Quick Assessment" dose model option.
4.5.3 From the TSC or EOF:
- 1. PERFORM dose projections, using the Full Assessment" dose model option, to determine whether the plant-based protective actions are adequate using the following methods as applicable:
- 2. Monitored Release:
NOTE: If dose assessment results indicate the need to recommend actions beyond 10 miles, then DISPATCH Field Monitoring Teams to downwind areas to verify the calculated exposure rates prior to issuing PARs outside the 10 mile EPZ.
A. If a release is in progress, then ASSESS the calculated impact to determine whether the plant based PARs are adequate.
B. If a release is not in progress, then USE current meteorological and core damage data to project effluent monitor threshold values that would require 2, 5, and 10 mile evacuations.
- RE-ESTABLISH threshold values whenever meteorological conditions or core damage assessment values change.
EP-AA-111 Revision 4 Page 8 of 18
- 3. Containment Leakage/Failure:
A. If a release is in progress, THEN assess the calculated impact to determine whether the plant based PARs are adequate.
B. If a release is not in progress, then USE current meteorological and core damage data on various scenarios (design leakage, failure to isolate, catastrophic failure) to project the dose consequences and determine whether the plant based PARs are adequate.
- 4. Field Survey Analysis: Actual field readings from Field Teams should be compared to dose assessment results and used as a dose projection method to validate calculated PARs and to determine whether the plant or release based protective actions are adequate.
- 5. Release Point Analysis: Actual sample data from monitored or unmonitored release points should be utilized in conjunction with other dose assessment and projection methods to validate calculated PARs and to determine whether the plant based protective actions are adequate.
4.6 Overall Protective Action Recommendations (PARs) 4.6.1 EVALUATE the results of the plant based PARs and determine which Subareas/Sectors are to be evacuated.
4.6.2 IF a release is in progress, THEN:
- 1. EVALUATE the results of the dose based PARs and determine if EPA Protective Action Guides (EPA PAGs) of I Rem TEDE or 5 Rem CDE Thyroid are exceeded and if additional Subareas/Sectors require evacuation.
- 2. ADD any Subarea/Sector requiring evacuation as determined by dose assessment to the plant based PARs.
4.6.3 IF no release is in progress, THEN:
- 1. PERFORM dose projections on possible conditions as time permits to determine if PAGs could be exceeded.
- 2. CONSIDER adding any Subareas/Sectors requiring evacuation as determined by dose projection to the plant based PARs.
4.6.4 COMBINE the results of the plant based and appropriate dose based PARs onto the State/Local notification form.
4.6.5 RETAIN any copies of plant and/or dose based PAR reports (Attachments 1-8 or dose code printouts).
EP-AA-1 11 Revision 4 Page 9 of 18
- 5. DOCUMENTATION - NONE.
- 6. REFERENCES - NONE
- 7. ATTACHMENTS Attachment 1, Termination/Recovery Checklist Attachment 2, Braidwood Plant-Based PAR Flowchart Attachment 3, Byron Plant-Based PAR Flowchart Attachment 4, Dresden Plant-Based PAR Flowchart Attachment 5, LaSalle Plant-Based PAR Flowchart Attachment 6, Quad Cities Plant-Based PAR Flowchart Attachment 7, Clinton Plant-Based PAR Flowchart Attachment 8, Limerick/Peach Bottom Plant-Based PAR Flowchart
EP-AA-111 Revision 4 Page 10 of 18 ATTACHMENT I TERMINATIONIRECOVERY CHECKLIST Page 1 of 2 True False
- 1. Conditions no longer meet an Emergency Action Level and it LJ 0i appears unlikely that conditions will deteriorate.
List any EAL(s) which is/are still exceeded and a justification as to why a state of emergency is no longer applicable:
- 2. All required notifications for entry into the Recovery Phase have Li [i been prepared.
STOP for Unusual Event.
CONTINUE for Alert, Site Area and General Emergency classifications
- 3. Plant releases of radioactive materials to the environment are L3 0i under control (within Tech Specs) or have ceased and the potential for a uncontrolled radioactive release is acceptably low.
- 4. The radioactive plume has dissipated and plume tracking is no 0i 0i longer required. The only environmental assessment activities in progress are those necessary to determine the extent of deposition resulting from passage of the plume.
- 5. In-plant radiation levels are stable or decreasing, and acceptable Di Di given the plant conditions.
- 6. The reactor is in a stable shutdown condition and long-term core Li Di cooling is available.
- 7. The integrity of the Reactor Containment Building is within Ll Li Technical Specification limits.
EP-AA-1 11 Revision 4 Page 11 of 18 ATTACHMENT 1 TERMINATIONIRECOVERY CHECKLIST Page 2 of 2 True False
- 8. The operability and integrity of radioactive waste systems, ri I decontamination facilities, power supplies, electrical equipment and plant instrumentation including radiation monitoring equipment is acceptable.
- 9. Any fire, flood, earthquake or similar emergency condition or threat L3 E3 to security no longer exists.
- 10. Any contaminated injured person has been treated and/or [i Ii transported to a medical care facility.
- 11. Offsite conditions do not unreasonably limit access of outside Li Li support to the station and qualified personnel and support services are available.
- 12. Discussions have been held with Federal, State and County [i Li agencies and agreement has been reached and coordination established to terminate the emergency.
It is not necessary that all responses listed above be 'TRUE'; however, all items must be considered prior to event termination or entry into Recovery. For example, it is possible that some conditions remain which exceed an Emergency Action Level following a severe accident but entry into Recovery is appropriate. Additionally, other significant items not included on this list may warrant consideration such as severe weather.
Comments:
Approved: Date/Time:
Emergency Director (in C&C of event classification)
EP-AA-111 Revision 4 Page 12 of 18 ATTACHMENT 2 BRAIDWOOD PLANT-BASED PAR FLOWCHART Page 1 of I NPRs.'
I iA General Emergency Declared?
No 7 Required~
Loss of 'FUEL' Fission Product Barrier SNo I Yes SLoss Product Barrier of 'RCS' Fission No Evacuate 2 Mile Radius '& 5K Mile's _Dow-nwind.
2 Mile Radius, 5 Miles Downwind SLoss of 'CONTAINMENT' Fission Product Barrier WD (from) Subareas 0240 to 0430 1, 10,14 I Yes 0440 to 0590 1, 10, 11, 14 0600 to 1120 1,10,11
'Evcute51Mile Radius'&'i1 0 1130 to 1360 1, 7, 10, 11 SMlilesflo3wr wiind. 1370 to 1530 1,7,10 1540 to 1790 1,2,7,10 5 Mile Radius, 10 Miles Downwind 1800 to 2040 1,2,10 WD (from) Subareas 2050 to 2360 1,2,3,10 0140 to 0270 1, 2, 3, 6, 7, 10, 11, 14, 15 2370 to 2890 1,3,10 0280 to 0560 1,2, 3, 6, 7, 10, 11, 14, 15, 16 2900 to 3290 1,3,6,10 3300 to 3540 1,6,10 0570 to 0730 1,2, 3, 6, 7, 10, 11, 12, 14, 15, 16 3550 to 0230 1,6,10, 14 0740 to 0830 1,2, 3, 6, 7, 10, 11, 12, 14, 16 0840 to 0930 1,2, 3, 6, 7, 10, 11, 12, 14 0940 to 1040 1, 2, 3, 6, 7, 8, 10, 11, 12, 14 1050 to 1210 1, 2, 3, 4, 6, 7, 8, 10, 11, 12, 14 1220 to 1490 1, 2, 3, 4, 6, 7, 8, 10, 11, 14 1500 to 1630 1,2, 3, 4, 6, 7, 10, 11, 14 1640 to 1810 1,2, 3, 4, 5, 6, 7, 10, 11, 14 1820to2100 1,2,3,5,6,7,10,11,14 2110 to 2420 1, 2, 3, 5, 6, 7, 10, 11, 13, 14 2430 to 2740 1, 2, 3, 6, 7,10,11, 13,14 2750 to 3070 1, 2, 3, 6, 7, 9,10,11,13,14 3080 to 0130 1,2, 3, 6, 7, 9, 10, 11, 14 NOTE: Ensure dose based PARs are evaluated when a release is in progress.
EP-AA-111 Revision 4 Page 13 of 18 ATTACHMENT 3 BYRON PLANT-BASED PAR FLOWCHART Page 1 of I No N o6P ARs ,
I W.
General Emergency Declared?
Yes ReIq u ired.
l I
Loss of 'FUEL' Fission Product Barrier Il Yes Loss of 'RCS' Fission Product Barrier Yes.
2 Mile Radius. 5 Miles Downwind I
I Loss of 'CONTAINMENT' Fission Product Barrier Yes WD (from) 0080 0690 to to 0680 1280 19,23 Subareas 19, 20, 23 129° to 2270 17,19,23 (Eivacuate'5MileRadius &i60! 2280 to 2880 19,23 Q :MilesD'ownwi~nd., 2891 to 3450 19, 23, 25 3460 to 0070 19, 20, 23, 25 5 Mile Radius, 10 Miles Downwind WD (from) Subareas 0220 to 0510 14, 17, 19,20,23, 25 0520 to 0820 12, 14, 17, 19,20, 23, 25 0830 to 1000 12, 17, 19, 20,23, 25 1010 to 1250 10, 12, 17, 19,20,23,25 1260 to 1390 10, 17, 19,20,23,25 1400 to 1710 10, 17, 19,20,23, 25,40 1720 to 2090 17, 19,20,23,25,40 2100 to 2200 17, 19,20,23,25, 39,40 2210 to 2520 17, 19,20,23,25, 27, 39 2530 to 2640 17, 19,20,23,25, 27 2650 to 2850 17, 19,20, 23, 25, 27, 28 2860 to 3260 17, 19,20,23,25,28 3270 to 0210 17, 19,20,23,25 NOTE: Ensure dose based PARs are evaluated when a release is in progress
EP-AA-111 Revision 4 Page 14 of 18 ATTACHMENT 4 DRESDEN PLANT-BASED PAR FLOWCHART Page 1 of I General Emergency No ~ NoPARs Declared?
,Yes I-1 I Required I Loss of 'FUEL' Fission Product Barrier Yes F oss of 'RCS' Fission .. Evacuate 2 Mile,, adius & 5 Product Barrier Miles JDownwiind.
I Yes 2 Mile Radius, 5 Miles Downwind Loss of 'CONTAINMENT' Fission Product Barrier WD (from) Subareas 0020 to 0460 1,3.4,7 0470 to 1820 1,3.4 Yes 1830 to 2920 1,3,4,12
'Evacuate,5 Mile Radius,&,10; 2930 to 2990 1,3,4
>M ile's -D o'rW i n d.2 f 3000 to 3380 1, 3, 4, 9 3390 to 0010 1, 3,4, 7, 9 5 Mile Radius, 10 Miles Downwind WD (from) Subareas 0020 to 0260 1, 3,4, 7, 9,10,11, 12 0270 to 0441 1, 3,4, 7, 8,9, 11, 12 0450 to 0680 1, 3,4, 7,8,9, 12 0690 to 0830 1,2, 3, 4, 5, 7, 8, 9, 12 0840 to 0920 1, 2, 3, 4, 5, 7, 9,12 0930 to 1120 1,2,3,4,7,9,12 1130 to 1430 1,2,3,4,6, 7,9,12 1440 to 1770 1, 3,4, 6, 7, 9,12 1780 to 1990 1, 3, 4, 6, 7, 9, 12, 13 2000 to 2250 1, 3, 4, 7, 9, 12, 13 2260 to 2490 1, 3, 4, 7, 9, 12, 13, 14 2500 to 2660 1, 3, 4, 7, 9, 12, 14 2670 to 2860 1, 3,4, 7, 9,12, 14, 15 2870 to 3210 1, 3,4, 7, 9, 12, 15 3220 to 3440 1, 3,4, 7, 9,12, 15, 16 3450 to 3530 1, 3, 4, 7, 9, 10, 12, 15, 16 3540 to 0010 1, 3, 4, 7, 9, 10, 12, 16 NOTE: Ensure dose based PARs are evaluated when a release is in progress.
EP-AA-1 11 Revision 4 Page 15 of 18 ATTACHMENT 5 LASALLE PLANT-BASED PAR FLOWCHART Page 1 of I General Emergency I NoJ ~ No PARs Declared? IT ; ~Req'uiredj Yes Loss of 'FUEL' Fission Product Barrier Yes Loss of 'RCS' Fission ICEvacuate2 Mile Radius & 5.11 Product Barrier Miles .Downwin6d.
I Yes 2 Mile Radius, 5 Miles Downwind Loss of 'CONTAINMENT' Fission Product Barrier WD (from) Subareas 0190 to 0350 1. 2.3 I Yes 0361 to 1680 1,3 1690 to 3010 1 Ihvacuate-5 Mile Radius & 10 3020 to 0180 1, 2 LE Miles Downwiind.
5 Mile Radius, 10 Miles Downwind WD (from) Subareas 0020 to 0260 1,2, 3,4,5 0270 to 0560 1,2,3,4 0570 to 0760 1,2,3,4,7 0770 to 0960 1,2,3,7 0970 to 1160 1,2, 3, 7,8 1170 to 1210 1,2,3,8 1220 to 1490 1,2,3,8,11 1500 to 1780 1, 2, 3, 10, 11 1790 to 1970 1,2,3, 10 1980 to 2180 1,2,3,6,10 2190 to 2330 1, 2, 3, 6, 9, 10 2340 to 2420 1,2, 3, 6, 9, 13 2430 to 2650 1,2,3,9,13 2660 to 2810 1,2,3,13 2820 to 3160 1,2, 3, 13, 17 3170 to 3420 1,2,3,5, 17 3430 to 00101,2, 3, 5 NOTE: Ensure dose based PARs are evaluated when a release is in progress.
EP-AA-111 Revision 4 Page 16 of 18 ATTACHMENT 6 QUAD CITIES PLANT-BASED PAR FLOWCHART Page 1 of I General Emergency No ~NPARs
'N Declared?
- L ~ I ;: -RequiredI Loss of 'FUEL' Fission Product Barrier 4 Yes Loss of 'RCS' Fission - Evacuate,2 MlleýRadus &.5' Product Barrier 0 2MilesD~owrw~ihd'.
Yes I
2 Mile Radius, 5 Miles Downwind I Loss of 'CONTAINMENT' Fission Product Barrier Yes SNo WD (from) 0090 to Illinois 0240 1,3 Iowa 1,2,6 0250 to 0290 1,3 1,2,4,6 vMele Radius & 10 0300 to 0810 1 1,2,4,6 0820 to 0900 1 1,2,3,4,6 L-Miles"Downwind.,i 0910 to 1160 1 1,2,3,4 1170 to 1650 1 1,2,3 5 Mile Radius, 10 Miles Downwind 1660 to 1860 1 1,2,3,5 WD (from) Illinois Iowa 1870 to 2150 1 1,2,5 0020 to 0250 1,2,3,6 1,2,3,4, 5, 6, 12 2160 to 2400 1,2 1,2,5 0260 to 0310 1,2,3 1,2,3,4, 5, 6,12 2410 to 2890 1,2 1,2 0320 to 0490 1,2,3 1,2,3,4, 5,6,10,12 2900 to 3180 1,2,3 1,2 0500 to 0580 1,2,3 1,2,3,4,5, 6,8,10,12 3190 to 0080 1,3 1,2 0590 to 0750 1,2,3 1,2,3,4,5, 6,8,10 0760 to 0870 1,2,3 1, 2, 3, 4, 5, 6,8 0880 to 1060 1,2,3 1,2,3,4,5,6,7,8 1070 to 1160 1,2,3 1,2,3,4,5,6,7 1170 to 1460 1,2,3 1,2,3,4,5,6,7,9 1470 to 1690 1,2,3 1,2,3,4,5,6,9 1700 to 1860 1,2,3 1,2, 3,4, 5, 6, 9,11 1870 to 2150 1,2,3 1,2, 3,4, 5,6,11 2160 to 2290 1,2,3,4 1,2,3,4,5,6,11 2300 to 2390 1,2,3,4 1,2,3,4,5,6 2400 to 2670 1,2,3,4,5 1,2,3,4,5,6 2680 to 2960 1,2,3,5 1,2,3, 4, 5,6 2970 to 318° 1,2,3,5,6 1,2,3,4,5,6 3190 to 0010 1,2,3,6 1,2,3,4,5,6 NOTE: Ensure dose based PARs are evaluated when a release is in progress.
EP-AA-1 11 Revision 4 Page 17 of 18 ATTACHMENT 7 CLINTON PLANT-BASED PAR FLOWCHART Page 1 of I General Emergency Declared?
Yes Loss of 'FUEL' Fission Product Barrier Yes Loss of 'RCS' Fission Product Barrier Yes 2 Mile Radius, 5 Miles Downwind Loss of 'CONTAINMENT' WD (from) Subareas Fission Product Barrier 0000 to 3600 1 Yes 5 Mile Radius, 10 Miles Downwind WD (from) Subareas 0210 to 0480 1, 5,6 0490 to 0660 1, 6 0670 to 0900 1,6,7 0910 to 0940 1,7 0950 to 1320 1,7,8 1330 to 1570 1,2,8 1580 to 1960 1,2 1970 to 2280 1,2,3 229° to 251' 1,3 2520 to 281' 1,3,4 2820 to 308' 1,4 3090 to 3380 1, 4,5 3390 to 0200 1, 5 NOTE: Ensure dose based PARs are evaluated when a release is in progress.
EP-AA-111 Revision 4 Page 18 of 18 ATTACHMENT 8 LIMERICK/PEACH BOTTOM PLANT-BASED PAR FLOWCHART Page 1 of I I General Emergency Declared?
of 'FUEL' Fission SLOSS
. *, Yes LOSS of 'RCS' Fission 'Mle-ow wid
- Evacuate 2'!Mill eýRadius
& 5*
I Product Barrier 1ý LOSS of 'CONTAINMENT' Fission Product Barrier I4I of&ALL 3 Barrleri NOTE: Ensure dose-based PARs are evaluated when a release is in e5 MieRadius & progress.
es Downwind-.-,-
WIND DIRECTION
'I DOWNWIND WIND DIRECTION DOWNWIND (FROM) SECTOR(S)* (FROM) SECTOR(S)*
355 to 005 SSE/S/SSW 175 to 185 NNW/N/NNE 006 to 017 SSE/SISSW/SW 186 to 197 NNW/NINNE/NE 018 to 027 S / SSW/SW 198 to 207 NINNE/NE 028 to 039 S / SSW ISW / WSW 208 to 219 N/NNEINE/ENE 040 to 050 SSW /SW / WSW 220 to 230 NNE / NE / ENE 051 to 062 SSW/SW I WSW / W 231 to 242 NNE/NEIENE/E 063 to 072 SW/WSW/W 243 to 252 NE/ENE/E 073 to 084 SW/WSWIWIWNW 253 to 264 NE/ENEIE/ESE 085 to 095 WSW/W/WNW 265 to 275 ENE/E/ESE 096 to 107 WSW/W/WNW/NW 276 to 287 ENE/EIESE/SE 108 to 117 WIWNW/NW 288 to 297 E/ESEISE 118 to 129 W/WNWINW/NNW 298 to 309 E/ESE/SE/SSE 130 to 140 WNW / NW / NNW 310 to 320 ESE/SEISSE 141 to 152 WNW/NWINNW.IN 321 to 332 ESE/SEISSE/S 153 to 162 NW/NNW/N 333 to 342 SE/SSE/S 163 to 174 NW/NNWIN/NNE 343 to 354 SE/SSEIS/SSW
- BOLD refers to affected Sector(s). These sectors are based on dose model stability class "D", and in some cases, an extra sector was included for conservatism.
EP-AA-1 12 Exek ,on. Revision 6 Pagel of 15 NucleaT Level 2 - Reference Use EMERGENCY RESPONSE ORGANIZATION (ERO) / EMERGENCY RESPONSE FACILITY (ERF) ACTIVATION AND OPERATION
- 1. PURPOSE 1.1 This procedure describes the activation and operation of the ERO and ERF and outlines their responsibilities.
- 2. TERMS AND DEFINITIONS 2.1 Command and Control: When in Command and Control, the designated Emergency Response Facility (ERF) has overall responsibility for Exelon Nuclear's emergency response efforts:
- Shift Emergency Director (Control Room),
- Station Emergency Director (TSC), or
- Corporate Emergency Director (EOF)
Transfer of Command and Control may occur prior to declaring facility activated, if in the Emergency Director's judgment, the following criteria are met:
- 1. Adequate staff levels are present in support of the non-delegable responsibilities being transferred;
- 2. The staff has been fully briefed as to the status of the event and currently proposed plan of action; and
- 3. A turnover between the Emergency Director relinquishing Command and Control and the Emergency Director assuming Command and Control has been completed. The Command and Control Turnover Briefing Form (Attachment 1) should be used to coordinate the transfer of non-delegable responsibilities between facility Emergency Director positions.
2.2 Emergency Personnel: Those organizational groups that perform a functional role during an emergency condition. Within Exelon Nuclear, emergency personnel include the Managers and Directors of the Emergency Response Organization, accident assessment personnel, radiological monitoring teams, fire brigades, first aid teams, and security personnel.
2.3 ERO Activation: The process used with the intention of fully staffing the facility to assume the positional responsibilities described in the Emergency Plan. ERO activation time is measured from the time when the event was classified until the responders have reported into the facility.
EP-AA-1 12 Revision 6 Page 2 of 15 2.4 Facility Activation: It is the goal of the organization to be capable of activating the applicable Emergency Response Facility within 15 minutes of achieving minimum staffing. The facility can be declared activated when the following conditions are met:
- 1. Minimum staffing has been achieved.
- 2. Personnel have been briefed on the situation.
- 3. The facility is functionally capable of performing the appropriate activity.
Although the response time will vary due to factors such as weather and traffic conditions, a goal of 60 minutes for minimum staffing, following the classification of an Alert or higher emergency classification, has been established for the ERO personnel responding to the station emergency facilities and the EOF.
While the minimum staffing criteria applies to the JPIC, the 60-minute response and 75-minute activation times are not applicable. Public Information personnel must first coordinate the decision to activate the JPIC with the appropriate offsite authorities.
- 3. RESPONSIBILITIES 3.1 Non-Delegable Responsibilities 3.1.1 The following responsibilities will be transferred from the Shift Emergency Director to the Station Emergency Director and ultimately the Corporate Emergency Director, but cannot be delegated to other ERO personnel by the Emergency Director in Command and Control:
- 1. Final decision to notify offsite authorities - Although the notification approval responsibility may not be delegated, actual notification communication may be delegated.
- 2. Final decision to recommend protective actions to offsite authorities Although the PAR determination responsibility may not be delegated, actual recommendation communications may be delegated.
3.1.2 The following responsibilities will be transferred from the Shift Emergency Director to the Station Emergency Director, but cannot be delegated to other ERO personnel.
- 1. Final decision to declare the emergency classification.
- 2. Final decision for issuance of thyroid blocking agents to Exelon Nuclear emergency workers andlor onsite personnel.
- 3. Authorization of personnel exposure per EPA-400 limits.
EP-AA-112 Revision 6 Page 3 of 15 3.1.3 The above non-delegable responsibilities will move with the transfer of Command and Control as indicated:
Control Room TSC EOF (Shift Emer-iency Director) (Station Emergiency Director) (Corporate Emer-gency Director)
Classification l Classification PARs 0 PARs lo PARs Notifications 1 Notifications 0 Notifications Emergency Exposure Emergency Exposure Controls - Controls
- 1. If the TSC is not functional and the EOF is adequately staffed and briefed, Command and Control of overall emergency response and the non-delegable responsibility for PAR determination and the notification of offsite authorities can be transferred directly from the Shift Emergency Director to the Corporate Emergency Director. The Control Room will retain responsibility for event classification and emergency exposure controls until the Station Emergency Director is ready to accept.
- 2. If the Emergency Director is incapacitated, then Command and Control can either be moved back through the Emergency Director chain or given to facility subordinates based on the following line of succession:
- Control Room (CR) - A licensed Senior Reactor Operator
- Technical Support Center (TSC) - Operations Manager
- Emergency Operations Facility (EOF) - EOF Director 3.1.4 Responsibility for performing offsite dose assessments and coordination of field monitoring teams may be transferred to the EOF, prior to the formal transfer of Command and Control for PAR decision-making. This transfer may be initiated once the EOF Protective Measures Group is adequately staff and concurrence is obtained from the TSC and EOF Radiation Protection Managers.
EP-AA-112 Revision 6 Page 4 of 15
- 4. MAIN BODY 4.1 Control Room 4.1.1 The Shift Manager in the Control Room has the responsibility to initially recognize that an event at the station has occurred, which requires classification and subsequent activation of the Emergency Plan.
4.1.2 The Shift Manager shall assume the responsibilities of the Shift Emergency Director following event classification and implement the emergency response activities identified in EP-AA-112-100, Attachment 1, Shift Emergency Director Checklist.
4.1.3 At the Alert or higher Classification, the Control Room shall ACTIVATE the Technical Support Center (TSC), Operational Support Center (OSC), Emergency Operations Facility (EOF), and Joint Public Information Center (JPIC).
Mobilization of ERO personnel is optional at the Unusual Event classification with the exception of an Unusual Event due to a credible security threat (HU1), which requires the staffing of emergency facilities.
4.2 Technical Support Center / Operational Support Center 4.2.1 The TSC and OSC shall achieve Minimum Staffing within 60 minutes of an Alert declaration, with facility activation occurring within 15 minutes of achieving minimum staffing.
4.2.2 Position specific responsibility checklists for the TSC and OSC are found in EP AA-1 12-200 and EP-AA-1 12-300 respectively.
4.2.3 The TSC supports the Control Room, performs non-delegable duties when in Command and Control, assesses plant status and potential off-site impact, and coordinates on-site emergency response efforts.
4.2.4 The OSC SHALL be activated whenever the TSC is activated, but may be subsequently de-activated if deemed unnecessary by the Station Emergency Director when at the classification of Alert or Unusual Event.
- 1. The purpose of the OSC is to provide a location where on-site operations support personnel will report during an emergency and from which they will be dispatched in support of emergency operations.
- 2. The OSC serves as a central location for coordination of team activities, a staffing pool for performance of in-plant activities, an assembly area for accountability of select station personnel and as a storage area for emergency supplies.
4.2.5 OSC Teams shall be requested by the TSC using the guidance found in EP-AA 112-200, Attachment 1, OSC Emergency Team Dispatch Guidance.
EP-AA-1 12 Revision 6 Page 5 of 15
- 1. TSC Managers/Coordinators shall complete EP-AA-1 12-200, Attachment 2, OSC Team Request Form and forward to the Maintenance Manager for transmittal to the OSC.
4.3 Emergqency Operations Facility (EOF) 4.3.1 The EOF shall achieve Minimum Staffing within 60 minutes of an Alert declaration, with facility activation occurring within 15 minutes of achieving minimum staffing.
4.3.2 If the EOF is activated at a classification level of Unusual Event, then the EOF may be subsequently de-activated if its continued operation is agreed to be unnecessary by the Station Emergency Director and the Corporate Emergency Director.
4.3.3 Position specific responsibility checklists for the EOF are found in EP-AA-1 12 400.
4.3.4 The EOF supports the TSC and provides long-term support to the affected station.
- 1. The EOF Organization is responsible for evaluating, coordinating and directing the overall company activities involved in the emergency response.
- 2. The EOF will assume Command and Control of overall emergency response efforts to allow the station to focus attention on station activities. The non delegable responsibilities for PAR decision-making and the notification of offsite authorities will also transfer to the EOF, but responsibility for event classification and emergency exposure controls will remain with the Station Emergency Director.
4.3.5 If the EOF is, or becomes uninhabitable, the Corporate Emergency Director will transfer responsibility for dose assessment and coordination of field survey teams back to the TSC. Available Exelon facilities or a TSC at an unaffected station should be considered as an alternate location.
EP-AA-112 Revision 6 Page 6 of 15 MidWestROG 4.3.6 The Emergency News Center (ENC) function is co-located in the Cantera EOF and serves to gather factual information concerning the emergency event, write press releases and event chronologies, and interface with Exelon Nuclear spokespersons at the JPIC that are participating in news conferences. The ENC shall be activated with the EOF.
4.4 Joint Public Information Center (JPIC) 4.4.1 The JPIC shall be activated with the EOF at the Alert declaration level. While minimum staffing positions have been identified, no formal response times associated with this facility have been established. Activation of the JPIC should occur as soon as possible following achieving minimum staffing, based on event conditions and media interest.
4.4.2 Position specific responsibility checklists for the Emergency Public Information Organization are found in EP-AA-1 12-600.
4.4.3 The JPIC is designed to bring Exelon Nuclear spokespersons together with Federal, State, and Local governmental agencies so the coordination and dissemination of information to the public can be carried out quickly and accurately via the media.
4.4.4 The Joint Public Information Centers (JPIC) are located in near-site facilities.
- 1. Mazon JPIC (IL) - Near-site to Dresden, Braidwood and LaSalle
- 2. Morrison JPIC (IL) - Near-site to Quad Cities and Byron
- 3. Bloomington JPIC (IL) - Near-site to Clinton Station
- 4. Coatesville EOF (PA) - Limerick and Peach Bottom 4.5 Field Monitorinq Teams 4.5.1 The position specific checklist for Field Monitoring Team personnel and guidelines for radiological plume monitoring and environmental sample collection, records and communications are located in EP-AA-112-500.
- 5. DOCUMENTATION None
- 6. REFERENCES None
EP-AA-1 12 Revision 6 Page 7 of 15
- 7. ATTACHMENTS 7.1 Attachment 1, Command and Control Turnover Briefing Form 7.2 Attachment 2, Shift Turnover 7.3 Attachment 3, FFD Call-Out Record 7.4 Attachment 4, FFD Verification Form 7.5 Attachment 5, Dose Assessment Turnover Form 7.6 Attachment 6, Pre-scripted PA System Announcements for Event Classification 7.7 Attachment 7, Information Request / Message Sheet
EP-AA-112 Revision 6 Page 8 of 15 ATTACHMENT 1 COMMAND & CONTROL TURNOVER BRIEFING FORM Page 1 of 2
- 1. Affected Station: Unit(s):
- 2. Classification Level: El Gen Emergency 0I Site Area Emergency El Alert [l UE EAL #: Classified at (Time):
- 3. Offsite Notification Status
- a. Latest State/Local: No: Time:
- a. Latest NRC: No: Time:
- 4. Pertinent Information / Status
- a. ERDS Activated? At: 0] YES El NO
- b. Accountability initiated? At: E] YES L3 NO
- c. Site Evacuation Initiated? At: [] YES El NO
- d. Release Occurring? Stack/Vent: 0_ YES El NO
- e. In-Plant / Site Radiological Concerns? L3 YES El NO
- f. Offsite Assistant Requested? 13 YES El NO
- g. Station Priorities Reviewed? Q_YES El NO
- 5. Upon the transfer of Command and Control, the followingq will be performed by:
- a. Event Classification ............................................................................ L3 CR El TSC
- b. PAR Decision-Making .......................................................... L CR LI TSC EL EOF
- c. State/Local Notifications ....................................................... L CR EL TSC E] EOF
- d. NRC Notifications ................................................................. 0 CR LI TSC 03 EOF
- e. Emergency Exposure Controls .......................................................... El CR El TSC
- 6. Command and Control
- a. Adequately staffed to support non-delegable duties? ............ . . . . . . . . . . L3 YES 0I NO
- b. Briefed on event status/currently proposed plan of action? ....... . . . . . . L3 YES LI NO
Station Emergency Director: Notify CR, TSC and OSC personnel of the transfer and responsibilities assumed. L3 YES El NO Corporate Emergency Director: Notify EOF, JPIC, State and NRC personnel of the transfer and responsibilities assumed. LI YES El NO Use of Page 2 of this form (Key System Status) is optional and intended to be used as a user aid for MAROG. Designated data displays (i.e., PPDS), if available, may serve this purpose.
EP-AA-1 12 Revision 6 Page 9 of 15 ATTACHMENT 1 COMMAND & CONTROL TURNOVER BRIEFING FORM Page 2 of 2 AFFECTED UNIT(S) ONLY: KEY SYSTEM STATUS I UNIT # at I UNIT # at I Pln Codtin Pln Condiions E3 On-Line 03 At Power:____ On-Line ElAt Power: %
0l Off-Line: 13 Cooling Down / 03 Cold Shutdown Time of Rx Shutdown:__
0 Stable 03 Unstable 0 Improving am/pm 0 Deteriorating I Time of Rx Shutdown:__
0I Stable am/pm 0 Improving 00ff-Line: 10 Cooling Down /I Cold Shutdown 1011R1-0 UntbeL etroaig Fiso Prdc Bare-ttsFsinPrdc are tt Fuel ROS Cntmt 0ue 0nm Intact: L3 0 0 03 13 03 07 0 13 0 Potential LOSS:
Potential LOSS: 03 I Intact:
I ^CLl i UIM IP1I- Ij IJIN*LIIP- MAIN TURBINE LI ON-LINE U TRIPPED.
ESW/SX D]YESOlNO ESW / SX 0 YES Q NO sw O3YES D NO. SW 13 YES 0_ NO CONDENSATE/FEED D YES 03 NO CONDENSATE/FEED 0-YES 03 NO RHR LOOP A [3 YES 13 NO. RHR LOOP A 13 YES D NO RHR LOOP B D YES L3 NO RHR LOOP B D YES DlNO RHR LOOP __ 0YES 0 NO RHR LOOP D YES 0 NO RHR LOOP 0 D_YES 0 NO RHRLOOP Q YES D NO C/SLOOPA 1D YESONO C/S LOOP A 0 YES 13 NO C/SLOOPB D YES 0 NO13 NA" C/S LOOP B D YES D NO L3 NA:
OFFSITE POWER L3 YES 03 NO OFFSITE POWER 13 YES 0LNO DIESEL 03 YES 0 NO. DIESEL __ 0 YES 0 NO DIESEL ___ OYES O NO DIESEL -- 0 YES 0 NO DIESEL D_YES 0 NO: DIESEL__ 0 YES 0 NO DIESEL 0 YES 0 NO: DIESEL 0]YES 0 NO HPCI/S 0 YES 0 NO HPCI/S 0 YES 0 NO.
RCIC DYES 0 NO RCIC 03 YES 0 NO:
ADS D YES Ol NO ADS D YES L3 NO:
CRDA OYES D NO CRDA D YES 13 NO:
CRD B D YES E- NO CRDB D YES 0 NO:
SBLC A 0 YES U NO.
SBLC A D YES 0 NO SBLCB DYES D NO SBLCB 13 YES D NO.
SBGTS A DYES [] NO SBGTSA DYES L3 NO SBGTS B 03 YES 0] NO SBGTS B 0 YES 03 NO RCP A 0 YES Q NO RCP A D]YES L3 NO RCP B 0 YES D NO: RCP B E] YES D NO RCP C 13 YES D NO RCP C D YES Q_NO RCP D O YES EDNO' RCP D [3 YES D NO CVA [ YES ONO CV A E3 YES Q NO CVA 0 YES D NO CV A D YES D NO SIA [] YES [] NO SIA D YES D NOo SIB D YES Q NO SIB L3 YES 0_ NO CCA YES D NO CCA D3YES El NO C 13 DYES O NO CC B O)YES E3 NO
EP-AA-1 12 Revision 6 Page 10 of 15 ATTACHMENT 2 SHIFT TURNOVER Page 1 of 1 This attachment describes the process and information exchange, which should occur during a shift turnover of personnel.
- 1. PROVIDE a briefing of events to your relief person including the following, as applicable:
"* Basis for the current emergency classification and applicable EALs.
"* Position log and other documents generated during the shift.
"* State/Local and NRC notification forms issued.
"* Activities scheduled to occur during the next shift.
"* Plant and radiological data that are significant and are relevant to activities and responsibilities of your EP position.
"* Contacts established within the Exelon Nuclear organization and with outside organizations. In particular, review contacts that need to be made on a periodic basis and the type of information that should be exchanged.
"* Significant events that could occur during the next shift that will impact activities and actions that are the responsibility of your position.
- 2. INFORM key personnel in your Emergency Response Facility and key contacts at other facilities of the shift change of the position and PROVIDE the name of your replacement.
- 3. REVIEW logs and other records to verify significant information has been recorded and is legible.
- 4. FILE copies of all documents generated with the Administrative/Logistics Coordinator. This should include logs, message forms, and checklists.
- 5. OBTAIN a copy of your shift schedule from the TSC Logistics Coordinator / EOF Administrative Coordinator.
- 6. VERIFY with the TSC Security Coordinator of the arrangements for access when returning on the next shift.
EP-AA-112 Revision 6 Page 11 of 15 ATTACHMENT 3 FFD CALL-OUT RECORD Page 1 of I CALLER NAME: DATE: _/ /
TIME NAME POSITION CONSUMED FIT for DUTY Facility ETA ALCOHOL? & Sent To AVAILABLE?
YES NO YES NO COMMENTS:
Page of
EP-AA-112 Revision 6 Page 12 of 15 ATTACHMENT 4 FFD VERIFICATION FORM Page I of I Arrival time: Name:
Emergency Response Position:
Questions for individual Called Out:
- 1. "Have you consumed alcohol within five hours prior to your Emergency Response Facility arrival time?" ........................................ El YES L3 NO
- 2. "Are you Fit for Duty?" . ........................................................................ E3 YES E3 NO If YES for Question 1, PROCEEDwith "Request for Behavioral Observation" below.
If NO for question 2, EXCLUDE the individual from participation.
REQUEST FOR BEHAVIORAL OBSERVATION
, will require behavioral observation prior to assuming emergency response duties.
INOTE: Personnel will have any required behavioral observation completed prior to assuming their duties.
RESULTS: (Choose one)
A. Behavioral observation has been conducted and determined that this individual is Fit For Duty.
B. Behavioral observation has been conducted and determined that this individual should not be assigned emergency response duties. The following actions are recommended:
/ i (Signed, Observer) (Title) (Time) (Date)
EP-AA-112 Revision 6 Page 13 of 15 ATTACHMENT 5 DOSE ASSESSMENT TURNOVER SHEET STATION: I UNIT:
4MONITOR INFORMATION.': K g j'" V '
RELEASE POINT #1: READING (RANGE): EXHAUST FLOW:
RELEASE POINT #2: READING (RANGE): EXHAUST FLOW:
RELEASE DURATION: STARTTIME: STOP TIME:
'RELIF_ INPUTS PWR ONLY) \ 1 SIG PRESSURE: _ psig I NO. SRVs OPEN: I PORV OPEN: L- YES 01E NO
'TIME AFTER RXSHIUTDOWN £1 RX POWER: % I RX TRIP at: hrs. I ATWAS: D3 YES IJ NO 0l REACTOR CORE ACCIDENT 0l SPENT FUEL ACCIDENT 0L WASTE GAS DECAY TANK FUEL TYPE: 03 NEW 10 OLD ACCIDENT (PWR ONLY)
TYPE OF DAMAGE: 0 GAP I 0 MELT AMOUNT OF DAMAGE: % FUEL STATUS: 03 UNDER WATER 0 BACKWASH DEMIN SCENARIO
[] DRY (LIMERICK ONLY)
ENTERED:
'DOMINANT RELEASE PATH
'WIND METEOROLOGICALDATA SPEED (MPH): WIND DIRECTION (FROM):
0
.. ' '- .. , IDELTA TEMP Ff: STABILITY CLASS (A-G):
.ASSESSMENT METHOD SELECTED:
...... REDUCTIONS
,-ENT* SPRAYS: 0- ON 10 OFF HOLD UP TIME: I < 1 HR I Q 2-24 HRS 10E > 24 HRS
- TORUSIWErWIELLREDUC"IONS 0] BYPASSED I 0 SATURATED I 0 SUBCOOLED
- SBGTFILTER-REDUCTIONS I' 3 FILTERS WORKING I 0l FILTERS NOT WORKING "SJG REDUCTIONS,(PVVRONLY)* 0 SECONDARY BOILING I 0] SECONDARY SOLID I 0] SECONDARY DRY RESULTS OF DOSE CALCULATIONS: (Attach copy of generated DAPAR reports, if applicable)
TEDE:SB mRemlhr 12 MILES mRem/hr 15 MILES __ mRemlhr 110 MILES __ mRem/hr CDETHYROID: SB _- mRemlhr 12 MILES __ mRem/hr 15 MILES __ mRemlhr/ 10 MILES __ mRemlhr FIELD SURVEY RESULTS OF DOSE CALCULATIONS: (Attach copy of generated DAPAR reports, if applicable)
TEDE: __ MILES - mRem/hrl __I MILES __ mRemlhrI ___ MILES __ mRem/hr CDETWHYMOI: - MILES __ mRem/hr /I__MILES mRem/hr / MILES mRemlhr RECOMMENDED PROTECTIVE ACTIONS OFFSITE:
OTHER INFORMATION:
COMPLETED BY: DATE I TIME: at hrs.
EP-AA-1 12 Revision 6 Page 14 of 15 ATTACHMENT 6 PRE-SCRIPTED PA SYSTEM ANNOUNCEMENTS FOR EVENT CLASSIFICATION Page 1 of 1 The following pre-scripted messages are for guidance only and should be modified based on the Shift Manager's judgment to account for event-specific contingencies.
- 1. Unusual Event Classification (Repeat twice)
"Attention Station personnel. An Unusual Event has been declared due to (brief descriptionof cause). ERO members should standby for further instructions."
OPTIONAL FACILITY STAFFING: "Attention Station personnel. An Unusual Event has been declared due to (briefdescription of cause). ERO members report to your respective emergency response facilities. Non-ERO personnel, contractors and visitors should standby for further instructions."
- 2. Alert Classification (Repeat twice)
"Attention Station personnel. An Alert has been declared due to (briefdescription of cause). ERO members report to your respective emergency response facilities. Non ERO personnel, contractors and visitors should standby for further instructions."
- 3. Site Area Emer-qency Classification (Repeat twice)
"Attention Station personnel. A Site Area Emergency has been declared due to (brief description of cause). ERO members report to your respective emergency response facihties. Non-ERO personnel, contractors and visitors should standby to implement personnel accountability actions."
- 4. General Emergency Classification (Repeat twice)
"Attention Station personnel. A General Emergency has been declared due to (brief description of cause)."
- If accountability has not yet been initiated, include the following:
"ERO members report to your respective emergency response facilities. Non-ERO personnel, contractors and visitors should standby to implement personnel accountability actions.
EP-AA-1 12 Revision 6 Page 15 of 15 ATTACHMENT 7 INFORMATION REQUEST I MESSAGE SHEET Page 1 of I
-U RECEIVED AT: Date / / Time _ am./p.m.. by FROM: /
(Name) (Position Title)
U) @ 0 Control Room 0 TSC 13 OSC E EOF O JPIC O NRC 0 STATE )
ILl TO: I (Name) (Position Title)
U, @ 0 Control Room 0 TSC 0 OSC 0 EOF o JPIC 0 NRC L3 STATE(
0 LI cn w REQUEST:
z 0
0 U
z COMMITMENT:
COPY AND POST COMMITMENTS
-I ANSWER:
w U) z 0
IL w TO:
- w. /
(Name) (Position Title)
@ 0 Control Room 0 TSC [] OSC Q3 EOF L3 JPIC O NRC El STATEE(
FROM: I (Name) (Position Title)
@ 0 Control Room 0l TSC 0] OSC 0 EOF 0 JPIC 03 NRC 03 STATE (
COMMUNICATED AT: Date / / Time _ a.m./p.m. by (Position Title)
-U