ML040070236
| ML040070236 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 11/26/2003 |
| From: | Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| EPIP 1.1, Rev 44, EPIP 1.3, Rev 32, EPIP 2.1, Rev 28 | |
| Download: ML040070236 (101) | |
Text
POINT BEACH NUCLEAR PLANT EPIP INDEX EMERGENCY PLAN IMPLEMENTING PROCEDURES Revision 101 November 26, 2003 INDEX K... PROCEDURE REVISION EFFECTIVE PERIODIC NUMBER PROCEDtJRE TITLE NUMBER DATE REVIEW DATE I EPIP 1.1 Course of Actions ............................ 44 C 11/26/03 02/11/03 EPIP 1.2 Emergency Classification ............................ 39 R 04/04/03 12/27/02 EPIP 1.3 Dose Assessment and Protective Action Recommendations ............................ 32 R 11/26/03 05/09/03 EPIP 1.4 Credible High or Low Security Threat ......................... 2 C 0 1/10/03 01/10/03 EPIP 2.1 Notifications - ERO, State & Counties, and NRC ..... 28 R 11/26/03 05/09/03 EPIP 4.1 Technical Support Center (TSC) Activation and Evacuation ................................... 34 R 01/03/03 01/03/03 EPIP 4.2 Operations Support Center (OSC) Activation and Evacuation ................................... 16 R 01/03/03 01/03/03 EPIP 4.3 Emergency Operations Facility (EOF) Activation and Evacuation ................................... 30 R 08/29/03 01/03/03 EPIP 4.7 Offsite Radiation Protection Facility (OSRPF)
Activation and Evacuation .................................... 4 R 01/03/03 01/03/03 EPIP 5.1 Personnel Emergency Dose Authorization ................ 14 R 02/06/02 05/09/03 EPIP 5.2 Radioiodine Blocking and Thyroid Dose Accounting ................................... 13 R 03/20/01 01/03/03 EPIP 6.1 Assembly and Accountability, Release and Evacuation of Personnel........................................24 R 01/03/03 01/03/03 EPIP 7.3.1 Offsite Radiation Sampling and Survey ..................... 23 R 01/10/03 01/10/03 EPIP 7.3.2 Post-Accident Isokinetic Stack Sampling System ....... 7 R 07/12/02 05/09/03 EPIP 7.3.7 Estimating Radioiodine Air Concentrations ................ 5 R 07/12/02 05/09/03 EPIP 8.4.1 Post-Accident Sampling and Analysis of Potentially High Activity Reactor Coolant ............. 16 C 10/25/02 05/09/03 EPIP 8.4.2 Post-Accident Sampling of Containment Atmosphere ................................... 11 C 09/13/02 05/09/03 EPIP 8.4.3 Emergency Containment Sump "A" Sampling ............ 7 R 07/12/02 05/09/03 EPIP 10.1 Emergency Reentry ................................... 22 R 07/12/02 05/09/03 EPIP 10.2 Core Damage Estimation ................................... 20 R 02/03/03 05/09/03 EPIP 10.3 Post-Accident Containment Hydrogen Reduction ....... 6 C 03/26/03 03/26/03 C = Continuous Use (T - Temporary Change) R = Reference Use Page 1 of 2 I = Information Use
POINT BEACH NUCLEAR PLANT EPIP INDEX EMERGENCY PLAN IMPLEMENTING PROCEDURES Revision 101 November 26, 2003 INDEX PROCEDURE REVISION EFFECTIVE PERIODIC NUMBER PROCEDURE TITLE NUMBER DATE REVIEW DATE EPIP 11.2 Medical Emergency ................. 17 R 09/20/02 05/09/03 EPIP 12.1 Emergency Event De-Escalation, Termination, or Recovery Operations .................. 9 R 12/27/02 12/27/02 EPIP 12.2 Recovery Implementation ................. 15 R 01/10/03 05/09/03 C = Continuous Use (T - Temporary Change) R = Reference Use Page 2 of 2 I = Information Use
EPIP 2.1 NOTIFICATIONS - ERO, STATE AND COUNTIES, AND NRC DOCUMENT TYPE: Tcchnical CLASSIFICATION: NNSR REVISION: 28 EFFECTIVE DATE: November 26, 2003 REVIEWER: Plant Operation's Review Committee APPROVAL AUTHORITY: Department Manager PROCEDURE OWNER (title): Group Head OWNER GROUP: Emergency Preparedness
POINT BEACH NUCLEAR PLANT EPIP 2.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 NOTIFICATIONS - ERO, STATE AND COUNTIES, November 26, 2003 AND NRC TABLE OF CONTENTS SECTION TITLE PAGE 1.0 PURPOSE .......................................... 3 2.0 PREREQUISITES .......................................... 3 3.0 PRECAUTIONS AND LIMITATIONS .......................................... 4 4.0 INITIAL CONDITIONS .......................................... 4 5.0 PROCEDURE ......................................... 4 5.1 Notification of Emergency Response Organization (ERO) .......................................... 4 5.2 Notifications to State and Counties ......................................... 12 5.3 Notification to KNPP Control Room ......................................... 14 5.4 Notifications to the NRC ......................................... 15 5.5 Status Updates to State and Counties ......................................... 16 5.6 Status Updates to the NRC ......................................... 18
6.0 REFERENCES
......................................... 19 7.0 BASES ......................................... 19 ATTACHMENT A ERO NOTIFICATION SYSTEM SCENARIO SELECTION MATRIX ............. ............................ 20 ATTACHMENT B NUCLEAR ACCIDENT REPORTING SYSTEM FORM (NARS) .21 ATTACHMENT C PLANT STATUS UPDATE .23 ATTACHMENT D RADIOLOGICAL STATUS UPDATE .24 ATTACHMENT E STATUS REPORT ON PLANT SYSTEMS AND CONTROLS FOR AFFECTED UNIT .27 Page 2 of 28 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 2.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 NOTIFICATIONS - ERO, STATE AND COUNTIES, November 26, 2003 AND NRC 1.0 PURPOSE This procedure is to provide guidance for making initial and subsequent notifications of a classified emergency to members of the Point Beach Nuclear Plant Emergency Response Organization (ERO), State of Wisconsin, Manitowoc County, Kewaunee County, KNPP and the Nuclear Regulatory Commission.
2.0 PREREOUISITES 2.1 Responsibilities 2.1.1 Shift Manager (SM) has the ultimate responsibility to complete notifications per this procedure until a formal turnover to the Emergency Director has been conducted.
2.1.2 IF available to assist with this procedure, THEN the SM may assign these tasks to:
- Security Shift Commander (SSC)
- Operating Supervisor(s) (OS)
- Shift Technical Advisor (STA) 2.1.3 State and County Communicator shall assume notifications to the State and Counties upon activation of the Emergency Operations Facility (EOF).
2.1.4 ENS Communicator shall assume notifications to the NRC upon activation of the Technical Support Center (TSC).
2.2 Equipment 2.2.1 Notification of the Emergency Response Organization
- Point Beach Automated Notification System (primary means)
- Alpha-numeric paging accessed via telephone (backup means)
- Alpha-numeric paging system accessed via TSO (backup means)
- Manual Call Tree (backup means) 2.2.2 Notification of the State and County Emergency Managements
- Two-Digit Dial Select Telephone
- Commercial Telephones (PBX, GTE, Microwave) 2.2.3 Notification of the NRC
- Federal Telecommunications System (S) Emergency Notification System (ENS)
- Commercial Telephones (PBX, GTE, Microwave)
Page 3 of 28 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 2.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 NOTIFICATIONS - ERO, STATE AND COUNTIES, November 26, 2003 AND NRC 3.0 PRECAUTIONS AND LIMITATIONS 3.1 Completion of this procedure shall not prevent the operators from bringing the plant to a safe condition to protect the health and safety of the general public.
3.2 The State of Wisconsin Emergency Management, Manitowoc County Emergency Management, and Kewaunee County Emergency Government shall be notified within 15-minutes of event classification.
3.3 The NRC shall be notified immediately following the state and county notifications, not to exceed one hour from declaration of a classified emergency.
3.4 TSO knovledge is required for IBM mainframe access to the paging system.
3.5 Only approved personnel may activate the Point Beach Automated Notification System.
4.0 INITIAL CONDITIONS 4.1 An emergency has been declared or terminated.
4.2 A change from one emergency classification to another has occurred.
4.3 Further degradation of the level of safety of the plant, major changes in equipment or reactor status, or other major changes NOT involving a change in emergency classification have occurred.
5.0 PROCEDURE NOTE: The notifications of the Emergency Response Organization, State and Counties, KNPP, and Nuclear Regulatory Commission should be completed simultaneously if possible.
5.1 Notification of Emergency Response Organization (ERO)
WARNING The ERO activation can be delayed if a security threat is in progress that would jeopardize the ERO safety.
NOTE: IF ERO was already activated by an Alert or Site Emergency Classification, DO NOT repeat this section.
5.1.1 PBNP Automated Notification System (primary means)
Page 4 of 28 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 2.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 NOTIFICATIONS - ERO, STATE AND COUNTIES, November 26, 2003 AND NRC NOTE 1: Listen carefully because the system will give you other options.
To expedite the notification process, the following steps have been written to only list the specific voice prompt you need, at which time you can immediately respond without listening to the remaining prompt.
NOTE 2: If at any point you want to exit the system and start over, you should keep slowly pressing the "#" key until the system says "goodbye" and restart the entire process.
- a. Determine the information desired to be sent to the Emergency Response Organization using Attachment A. Record the information at the bottom of Attachment A.
- b. From any on-site telephone, dial ext. to access the PBNP Automated Notification System.
- c. When prompted "Please enter your scenario activation password," enter "1 " using the keypad on the telephone.
- d. When prompted "To start a scenario enter the scenario ID...," enter the 3-digit scenario number from Attachment A and press "#."
- e. Press " to start the scenario.
- f. When prompted, "The scenario is building," press "#", listen to "good-bye" and hang up.
- g. IF the ERO pager(s) in the Control Room do not activate and display the message within 3-4 minutes, THEN go to Step 5.1.2 to send the page.
- h. Periodic fax printouts will automatically be sent to the Control Room, Technical Support Center, and Emergency Operations Facility, and JPIC listing the represented people that are responding, their ERO position, and their estimated time of arrival.
Page 5 of 28 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 2.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 NOTIFICATIONS - ERO, STATE AND COUNTIES, November 26, 2003 AND NRC
- i. If the pager activation was successful, skip Steps 5.1.2 through 5.1.4 and return this procedure section and completed Attachment A to Emergency Preparedness or include in the TSC Manager turnover package.
Performed By:
Performer (Print and Sign) Date I Time 5.1.2 Alpha-Numeric Paging Accessed Via Telephone (backup means, not required if Step 5.1.1 was successful).
NOTE 1: Enter pager number to do a PBNP All-Call page of the ERO.
NOTE 2: Enter the 4 digit pager number to page a specific individual.
(Ref. Emergency Telephone Directory)
NOTE 3: You must enter the asterisks and two digit code to have the message sent to the pagers (i.e.," " would display "PBNP IJE, Please Stand by" or " ' ould display "Call Immediately
- a. Determine the pager message required:
- Use the following preprogrammed codes to provide event declarations.
= PB UE, Please Stand by
= PB ALERT. Report to ERF at once.
= PB SE. Report to ERF at once.
= PB GE. Report to ERF at once.
= EOF/JPIC Report to Green Bay (High or Low Credible Security Threat)
Page 6 of 28 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 2.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 NOTIFICATIONS - ERO, STATE AND COUNTIES, November 26, 2003 AND NRC
- Use the following preprogrammed codes to provide other information, with a call back number, if appropriate:
- b. Access the paging system by dialing ext.
if dialing on outside line), or
- c. Listen to the prerecorded message and an audible tone. Enter the four-digit pager number of the person or group you want to page as determined in the above notes.
- d. Listen to the next prerecorded message that asks you to enter your callback number. Enter the "**" code determined in Step 5.1.2.a and a phone number the person should call (only if appropriate).
- e. Listen for an audible tone again. The recording should then state that your message has been dispatched via the Wisconsin Electric paging system.
Your page has now been completed.
- f. IF the ERO pager(s) in the Control Room do not activate and display the message within 3-4 minutes, THEN go to Step 5.1.3 to send the page.
- g. If the pager activation was successful, skip Steps 5.1.3 and 5.1.4 and return this procedure section to Emergency Preparedness or include in the TSC Manager turnover package.
Performed By:
Performer (Print and Sign) Date / Time Page 7 of 28 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 2.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 NOTIFICATIONS - ERO, STATE AND COUNTIES, November 26, 2003 AND NRC 5.1.3 Alpha-Numeric Paging Accessed Via LAN Computer (backup means not required if Step 5.1.1 or 5.1.2 was successful).
NOTE: Do not use symbols in the pager message script.
- a. LAN IBM Mainframe (TSO)
- ~IF you do not have TSO access for the IBM Mainframe System, THEN go to Step 5.1.3.b.
- Access the mainframe MULTSESS menu from a computer.
- After selecting the TSO application and receiving the READY text, type in "PAGE" and the enter key.
- A paging screen will appear asking you for an alpha-numeric message and the pager number you want to reach. Type the message per the event classification and any activation needs of the Emergency Response Facilities.
- Tab to the pager number blank and enter to do a PBNP All-Call page of the ERO.
- Press ENTER to have your message sent.
- After a slight delay, a message comes up showing that your message was sent and who was paged.
- This completes the page. You can continue with another page or press PF3 as needed to return to the READY prompt. Type CESF and the enter key to log off TSO at this point.
IF the ERO pager(s) in the Control Room do not activate and display the message within 3-4 minutes, THEN go to Step 5.1.3.b to send the page.
- If the pager activation was successful, skip Step 5.1.4 and return this procedure section to Emergency Preparedness or include in the TSC Manager turnover package.
Performed By:
Performer (Print and Sign) Date / Time Page 8 of 28 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 2.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 NOTIFICATIONS - ERO, STATE AND COUNTIES, November 26, 2003 AND NRC
- b. Windows Corporate Paging System
- Access the paging system screen by selecting "Start-Applications--Corporate Paging System" on a LAN computer.
- Enter" 'in the pager number box to do a PBNP All-Call of the ERO.
- Type the message per the event classification and any activation needs of the Emergency Response Facilities in the message box.
- Ensure the box for "Message as Specified Above" is checked.
- Select the "Send Pager" icon to send your pager message.
- A message of "Sending Page" and "Ready for Next Page" is displayed in the lower left comer upon completion.
. Select "Exit" to leave the Corporate Paging System.
- IF the ERO pager(s) in the Control Room do not activate and display the message within 3-4 minutes, THEN go to Step 5.1.4 to activate the ERO by a manual call tree.
- If the pager activation was successful, skip Step 5.1.4 and return this procedure section to Emergency Preparedness or include in the TSC Manager turnover package.
Performed By:
Performer (Print and Sign) Date Time Page 9 of 28 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 2.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 NOTIFICATIONS - ERO, STATE AND COUNTIES, November 26, 2003 AND NRC 5.1.4 Manual Call Tree (reference Emergency Telephone Directory) (backup means, not required if Step 5.1.1 or 5.1.2, or Step 5.1.3 was successful).
NOTE 1: Use this process if all automated methods of notifying the ERO fail.
NOTE 2: IF unable to contact any of the following personnel, THEN assign that section to onsite individual.
- a. Contact two people from the Emergency Preparedness staff, an onshift STA, OS, or Security, and the On-Call Management for each discipline as indicated below, instructing them to:
Notify qualified ERO personnel for each position listed (ref ETD 01), determine FFD, fill the "" minimum positions first, and staff each position to the (#) level indicated.
(a) FFD #1 - "Are you able to respond?"
(b) FD #2 - If yes, "Have you consumed alcohol in the last five hours?"
(c) FED #3 - If no, instruct person to report immediately to emergency response facility and fill the position of
- Contact you with periodic status updates.
- Report to their emergency response facility upon completion of the notifications.
(a) EP Staff #1 (Name)
(1) *TSC Manager (1)
(2) ERF Communicator-CR (1)
(3) *ERF Communicator-TSC (1)
- (4) *Engineering Coordinator (I)
(5) *Operations Coordinator (1)
(6) *OSC Coordinator (1)
(7) *ENS Communicator (1)
(8) *Rad/Chem Coordinator (1)
(9) Security Coordinator (1)
(10) Plant Status Monitor-TSC (1)
(11) Administrative Support Leader-TSC (1)
(12) Rad/Chem Monitor (1)
(13) Reactor/Core Physics Engineer (1)
(14) PRA Engineer (1)
(15) Mechanical Systems Engineer (1)
(16) Electrical/I&C Engineer (1)
Page 10 of 28 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 2.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 NOTIFICATIONS - ERO, STATE AND COUNTIES, November 26, 2003 AND NRC (b) EP Staff #2 (Name)
(1) *Emergency Director (1)
(2) *EOF Manager (1)
(3) *ERF Communicator-EOF (1)
(4) *Dose/PAR Coordinator (1)
(5) *State/Counties Communicator (1)
(6) *Resource Coordinator (1)
(7) Plant Status Monitor-EOF (1)
(8) Dose/PAR Monitor (1)
(9) HPN/SRC Communicator (1)
(10) State Liaison (1)
(11) Offsite Assembly Area Coordinator (1)
(12) Administrative Support Leader-EOF (1)
(13) Kewaunee County Liaison (1)
(14) Manitowoc County Liaison (1)
(15) JPIC Manager (c) Onshift STA, OS, or Security (Name)
(1) *SM (Reentry Team Coordinator) from "off" crews (1)
(2) *Operating Supervisor (Operations Leader) from "off" crews (2)
(3) CO Reentry from "off" crews (4)
(4) AO Reentry from "off" crews (4)
(d) Radiation Protection (Name)
(1) *Offsite Radiation Protection Coordinator (1)
(2) *Radiation Protection Leader (1)
(3) *Field Team Leader (1)
(4) *Offsite RP Reentry (2)
(5) Onsite RP Reentry (4)
(6) Offsite RP Reentry (4)
(e) Maintenance Supervisor (Name)
(1) *Mechanical Leader (1)
(2) *Electrical Leader (1)
(3) Mechanical Reentry (4)
(4) Electrical Reentry (4)
(f) I&C Supervisor (Name)
(1) *I&C Leader (1)
(2) I&C Reentry (4)
Page I11 of 28 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 2.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 NOTIFICATIONS - ERO, STATE AND COUNTIES, November 26, 2003 AND NRC (g) Chemistry Supervisor (Name)
(1) *Chemistry Leader (1)
(2) Chemistry Reentry (4)
- b. Return this procedure section to Emergency Preparedness or include in the TSC Manager turnover package.
Performed By:
Performer (Print and Sign) Date Time 5.2 Notifications to State and Counties NOTE 1: The notification of state and county emergency government agencies shall be notified within 15 minutes of event classification, event termination, or change in protective action recommendations.
NOTE 2: The State Radiological Coordinator may place a separate call to obtain additional information for purposes of determining State and County Emergency Operation Center(s) activations.
NOTE 3: Priority levels are assigned to Two-Digit Dial-Select communications as follows:
1 Siren Activation 2 Event Notification/PAR Upgrade 3 Status Update 14 I General Information I.
5.2.1 The Emergency Director shall complete or delegate the completion of Attachment B,Nuclear Accident Reporting Form.
5.2.2 The Emergency Director shall approve the contents of Attachment B, Nuclear Accident Reporting System Form (NARS), prior to the release of the information.
5.2.3 Provide this procedure section and the completed form to the person designated to make the communications, conducting a verbal review of the information as required.
Page 12 of 28 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 2.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 NOTIFICATIONS - ERO, STATE AND COUNTIES, November 26, 2003 AND NRC NOTE: IF the Two-Digit Dial-Select is out-of-service, THEN use commercial telephones (ref. Emergency Telephone Directory) to make the notification.
5.2.4 Record a callback number for the facility you are calling from on Attachment B, Nuclear Accident Reporting System Form (NARS).
5.2.5 Using the Two-Digit Dial-Select telephone:
- Pick up the handset and ask if the line is clear. (Similar to Gai-tronics)
- IF the line is busy, THEN inform them of your Priority 2 notification.
- They will clear the line, unless a Priority 1 discussion is in progress.
- When the line is clear, continue with the notification.
NOTE 1: IF unable to contact a specific agency after Five (5) rings, THEN press the # key to stop the ringing and continue with the notification to the agencies online. Then use commercial telephone to contact those agencies which were not reached.
NOTE 2: Two locations will ring for the State: WVEM in Madison and State Patrol (off-hours). Press the # key to stop the ringing if one location does not answer.
5.2.6 Dial to contact the following agencies simultaneously:
- Manitowoc County Sheriff Dispatcher
- Kewaunee County Sheriff Dispatcher
- State of Wisconsin Emergency Management (WEM) 5.2.7 Record the time and the name of the person who answers FOR EACH AGENCY on Attachment B, Nuclear Accident'Reporting System Form (NARS), you are transmitting.
5.2.8 Request each agency to remain on the line while you communicate the event information.
5.2.9 Request each agency to remain on the line while you ask one agency (preferably the State) to repeat the information as a confirmation of accuracy.
5.2.10 Request each agency to transmit the event information to appropriate personnel within their agency, instructing those individuals to place a return call to you to verify the notification.
Page 13 of 28 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 2.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 NOTIFICATIONS - ERO, STATE AND COUNTIES, November 26, 2003 AND NRC 5.2.11 IF commercial telephone lines must be used to complete the notifications, THEN call each of the following agencies as appropriate, repeating Steps 5.2.7 through Step 5.2.10. (ref Emergency Telephone Directory).
- Manitowoc County Sheriff Dispatcher
- Kewaunee County Sheriff Dispatcher
- State of Wisconsin Emergency Management (WEM)
NOTE: IF unable to remain at the callback number, THEN ensure an alternate person has assumed your responsibilities at that location.
5.2.12 Fax Attachment B, Nuclear Accident Reporting System Form (NARS), to the following agencies using the pre-programmed keys or referencing the Emergency Telephone Directory.
- State of Wisconsin Emergency Management (WEM)
- Manitowoc County Emergency Management
- Kewaunee County Emergency Government
- Emergency Response Facilities (If Activating) 5.2.13 Remain at the callback number until the callback verifications have been received from the three agencies, recording the time and name of each caller on Attachment B, Nuclear Accident Reporting System Form (NARS).
5.2.14 Return Attachment B, Nuclear Accident Repbrting System Form (NARS), to the Emergency Director.
5.3 Notification to KNPP Control Room 5.3.1 Obtain an approved copy of Attachment B, Nuclear Accident Reporting System Form (NARS).
5.3.2 Contact the Kewaunee Nuclear Power Plant Control Room at ext. and relay the event information on Attachment B, Nuclear Accident Reporting Form.
Contact Name: Time:
Classification Transmitted:
Page 14 of 28 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 2.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 NOTIFICATIONS - ERO, STATE AND COUNTIES, November 26, 2003 AND NRC 5.3.3 Return this procedure section and all attachments used to the Emergency Director.
Performed By:
Performer (Print and Sign) Date / Time 5.4 Notifications to the NRC NOTE: The notification to the NRC shall be completed immediately following the notifications to the state and counties and not exceeding 60-minutes from event classification, event termination, or change in protective action recommendations.
5.4.1 Emergency Director shall provide this procedure and the completed Attachment B, Nuclear Accident Reporting System Form (NARS), (or a copy), from Step 5.2.1 to the person designated to make the notification. A verbal review of the information will be conducted, if necessary.
NOTE 1: If the FTS-ENS phone is out-of-service, use commercial telephones (ref. Emergency Telephone Directory) to make the notification.
NOTE 2: The NRC may request a continuous open line of communication be maintained without regard to event classification. This request shall be honored if at all possible.
5.4.2 Fax the Attachment B Nuclear Accident Reporting System Form (NARS) to the NRC using the pre-programmed fax key or referencing the Emergency Telephone Directory.
5.4.3 Contact the NRC Operations Center via the FTS-ENS phone by dialing the number exactly as listed on the phone. If number is busy, try the next number listed (ref. Emergency Telephone Directory).
5.4.4 Record the time and name of the NRC Duty Officer on Attachment B, Nuclear Accident Reporting System Form (NARS), you are transmitting.
5.4.5 Communicate the event information clearly and concisely.
5.4.6 Make an entry into the appropriate NRC log.
- Control Room NOMS Narrative Log
- Technical Support Center ENS Log Book Page 15 of 28 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 2.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 NOTIFICATIONS - ERO, STATE AND COUNTIES, November 26, 2003 AND NRC 5.4.7 IF not previously notified, THEN contact the NRC resident inspector.
Contact Name: Time:
Classification Transmitted:
5.4.8 Return or fax Attachment B, Nuclear Accident Reporting System Form (NARS), to the Emergency Director.
5.5 Status Updates to State and Counties NOTE 1: Status updates should be made to State and County Emergency agencies approximately hourly, upon a major change in plant/radiological status, or at their request.
NOTE 2: Use status boards Attachment C, Plant Status Update, Attachment D, Radiological Status Update, and/or Attachment E, Status Reports on Plant Systems and Control for Affected Unit as a verbal guideline for communicating status updates.
NOTE 3: IF unable to contact a specific agency, THEN continue with the notification to other agencies, attempt to contact those agencies which have not been contacted.
NOTE 4: IF the Two-Digit Dial-Select is out-of-service, THEN use commercial telephones (preferably via conference call referring to the Emergency Telephone Directory) to make the status update.
5.5.1 Using the Two-Digit Dial-Select telephone:
. Pick up the handset and ask if the line is clear. (Similar to Gai-tronics)
- IF the line is busy, THEN inform them of your Priority 3 notification.
They will clear the line, unless a Priority 1 or 2 discussion is in progress.
- When the line is clear, continue with the notification.
Page 16 of 28 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 2.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 NOTIFICATIONS - ERO, STATE AND COUNTIES, November 26, 2003 AND NRC NOTE: IF unable to contact a specific agency after five (5) rings, THEN press the # key to stop the ringing. Contact those agencies by commercial telephone after completing the status update.
5.5.2 Dial " , , and 'consecutively to contact the following agencies simultaneously:
- 53 - Manitowoc County EOC
- 43 - Kewaunee County EOC
- 83 - State of Wisconsin Emergency Management (WEM) EOC 5.5.3 Request each agency remain on the line while you:
- Ask the Emergency Director of each facility (first contact only) if they want subsequent EPIP 2.1, Attachment B (NARS), notifications made directly to the EOCs. At Step 5.2.6 replace with the appropriate two-digit dial-select numbers.
- Communicate the status update event information and answer questions.
5.5.4 IF commercial telephone lines must be used to complete the notifications, THEN call the following agencies (ref. Emergency Telephone Directory):
- Manitowoc County EOC
- Kewaunee County EOC
- State of Wisconsin Emergency Management (WEM) EOC 5.5.5 IF a request has been made by the State or County for a written update THEN complete the appropriate section(s) of Attachment C, D, or E, obtain the Emergency Director approval, and fax using the pre-programmed fax keys or referencing the Emergency Telephone Directory.
- State of Wisconsin Emergency Managernient (WEM)
- Manitowoc County Emergency Management
- Kewaunee County Emergency Government
- Emergency Response Facilities (If Activating) 5.5.6 Repeat Steps 5.5.1 through 5.5.5 each time a status update is required.
5.5.7 IF a written update of Attachment C, D, or E was faxed to the State or County, THEN return the appropriate completed attachment(s) to the Emergency Director.
Page 17 of 28 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 2.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 NOTIFICATIONS - ERO, STATE AND COUNTIES, November 26, 2003 AND NRC 5.6 Status Updates to the NRC NOTE 1: The NRC should receive status updates approximately hourly, upon a major change in plant/radiological status, or at their request.
NOTE 2: IF the FTS-ENS phone is out-of-service, THEN use commercial telephones (ref. Emergency Telephone Directory) to make the notification.
NOTE 3: The NRC may request that a continuous open line of communication be maintained without regard to event classification.
5.6.1 Contact the NRC Operations Center via the FTS-ENS phone by dialing the number exactly as listed on the NRC phone. If number is busy, try the next number listed (ref. Emergency Telephone Directory).
5.6.2 Fax written status updates received from the EOF to the NRC, THEN send confirmatory fax to the Emergency Director.
5.6.3 Request TSC Manager approval to fax other information requested from the NRC.
NOTE: The NRC may request additional material including but is not limited to, procedure changes, completed procedures, PPCS printouts, equipment status information, non-emergency 50.72 notifications, logs regarding LCO entries/exits, safety evaluations, etc.
- a. Any material faxed to the NRC must include the Communicators Name, Date and Time.
- b. . Fax the information subsequently to the Emergency Director.
Page 18 of 28 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 2.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 NOTIFICATIONS - ERO, STATE AND COUNTIES, November 26, 2003 AND NRC
6.0 REFERENCES
6.1 WE to NRC letter May 19, 1983, Staffing Levels for Emergency Situations, Point Beach Nuclear Plant 6.2 NRC letter to WE, December 20, 1985, Inspection Report Nos. 50-266/83-01 and 50-301/83-01 6.3 Emergency Plan, EP 5.0, Organizational Control of Emergencies 7.0 BASES B-1 10 CFR 50.47(b), Emergency Plans B-2 10 CFR 50.72, Immediate Notification Requirements for Operating Nuclear Power Reactors B-3 NUREG-1022, Event Reporting Guidelines, 10 CFR 50.72 and 50.73, Rev 1, January 1998 Page 19 of 28 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 2.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 NOTIFICATIONS - ERO, STATE AND COUNTIES, November 26, 2003 AND NRC ATTACHMENT A ERO NOTIFICATION SYSTEM SCENARIO SELECTION MATRIX Scenario Emergency Class Number lon Unusual Event.
_(_ _Alert 3( Site Emergency
>General v________ Emergency Disregard previous page.
Disregard previous page. Standby for corrected information. Do not call.
High or Low Credible Security Threat Determine the 3-digit scenario number by choosing the appropriate classification and approach message from the matrix above. Record here Page 20 of 28 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 2.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 NOTIFICATIONS - ERO, STATE AND COUNTIES, November 26, 2003 AND NRC ATTACHMENT B NUCLEAR ACCIDENT REPORTING SYSTEM FORM (NARS)
TI'ME ANSWERED State Warning Center I or 11_ _ (Time) Kewaunee Co. __________ (Time) Manitowoc Co. (Time)
'This is the Point Beach Nuclear Site calling from the (circle one) CR/TSC/EOFIAEOF. An incident has occurred at our facility. Please record the following information on your Nuclear Accident Reporting System form." (Read belovs Box I through Box 12)
- 1. Reason For Call: [lnitial Report EEmergency Classification Change OPAR Change
- 2. STATUS 3. STATION/AFFECTED UNIT U[A] Actual Event U[T] Point Beach LUnit I Unit 2 E]Both (Check unit)
OE[B] Drill
- 4. ONSITE CLASSIFICATION 5.TINIsE & DATE OF CLASSIFICATION I PAR CHANGE / TERMINATION
[][A] Unusual Event EJ[B] Alert O[Al Classification Time Date EAL #
EIEC] Site Area Emergency fl[D] General Emergency . [ P C. ._.....;
[][E Recovery [][B] Par Change Time Date Q[FJ Termninated ]O[C] RecoveryTlermination Time Date _-
- 6. RELEASE STATUS 7. TYPE OF RELEASE O[Al Unusual Event or Alert: O[A] NOT APPLICABLE O[AI] NONE O [A2] OCCURRING EI[A3] TERMINATED O[B] AIRBORNE C [B] Site Area Emergency or General Emergency: C I OBI] POTENTIAL f[B21 OCCURRING O[B33 TERMINATED[C] LIQUID
- 8. WIND DIRECTION 9. WIND SPEED & STABILITY CLASS FROM DEGREES MILES/HR.:
DOWNWINDSECTORS:A B C D E F G H J K L A N P Q R STABILITYCLASS: A B C D E F G (Circle affected sectors.) (Circle applicablestability class)
- 10. PROTECTIVE ACTION RECOMMENDATIONS O[A] NONE E[C] OTHER_
O[B] EVACUATE ALL SECTORS OUT TO MILES EVACUATE DOWNWIND SECTORS OUT TO __MILES It. ADDITIONAL INFORMATION ( EAL Description)
ED: APPROVAL SIGNATURE _DATE/TINIE APPROVED I
- 12. EMERGENCY COMMUNICATOR /
(Print/sign)l
- 1. "State Warning Center, please read back this message to verify accuracy." Pause to allow message o be read back)
- 2. "lave all agencies received this message?" ( Waitfor reply)
- 3. 'Relay this information to Emergency Management immediately. Irate the appropriate personnel verify this message by placing a return phone call. The return phone number is __
State and County Callback Verification Time Name Contact Telephone Number State of Wis. (Duty Officer)
Manitowoc Cty. (Emcrg. Mgr. Director)
Kewaunee Cty. (Emerg. Mgr. Director)
NRC NOTIFICATION - Callback Verification Not Required Duty Officer Name Time Continuous phone link requested: _ No Yes NRC message transmitted by __ from the Point Beach Nuclear Site (Name) (CRITSC)
Page 21 of 28 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 2.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 NOTIFICATIONS - ERO, STATE AND COUNTIES, November 26, 2003 AND NRC )
ATTACHMENT B NUCLEAR ACCIDENT REPORTING SYSTEM FORM (NARS)
Box #1 Reason For Call: Check appropriate.
Box #2 Check "Actual Event" only if the event is real.
Box #3 Check affected unit(s). TABLE I Box #4 Classification being declared. IF this is a PAR Change notification, THEN AFFECTE WIND DIRECTION D check the current classification. (FROM) DO1%'N1N D
SECTORS Box #5 Check the applicable events(s) and fill in the time and date. >351-9 (>351-369) HJK If a classification, fill in EAL# not required or a PAR upgrade or
>9 13 (>369-373) HJKL recovery/termination.
Box #6 Indicate whether a radioactive release is occurring. The definition of >13 -32 (>373-392) JKL radioactive release is the release of radioactive material to the environment >32-36 (>392-396) JKLM attributable to the emergency event. At a minimum, a potential radioactive
>36-54 (>396414) KLM release always exists at a SE and General Emergency because of the definition of SE and General Emergency. >54 -58 (414418) KLMN
>58 -77 (>418437) LMN Box #7 Indicate whether there is an airborne or liquid radioactive release in progress. >77-81 (>437-441) LMNP IF there is no release in progress, THEN Check Not Applicable. >81-99 (>441-459) MNP
>99 -103 (>459-463) MNPQ Box #8 Use the "Rad/Met Status Board" screen on PPCS (U-I 2226, U-2 2726). >103 -122 (463-482) NPQ Backups: *Tower 1 45 M, 15 Min Avg (U-I 2223, U-2 2723) >122-126 (>482-486) NPQR
- Tower 2 10 M, 15 Min Avg (U-I 2223, U-2 2723) >126-144 (>486-504) PQR
- YR-5832, "Met/Forebay Lvl Recorder" (integrate trend) >144 - 148 (>504-508) PQRA
- 1. Fill the blank indicating the "From" wind direction.
>148 - 167 (>508-527) QRA
- 2. Circle the appropriate downwind affected sectors using guidance of Table
>167-171 (>527-531) QRAB Box #9 Use the "Rad/Met Status Board" Stability Wind Direction Temperature Lapse >171-189 (>531-549) RAB screen on PPCS (U-l 2226, Class Fluctuation Rate U-2 2726). (ae. degrees)' (AT/AH. F/35 m) >189- 193 RABC Backup: YR-5832, "MetfForebay A c. 2 22.50 ATIAH 5 -1.2 >193 - 212 ABC Lvl Recorder" 22.5 >ar 2 17.5° -1.2 < ATIAH (integrate AT trend) B 2 >212-216 ABCD
- 1. Fill the blank indicating the C 17.5°> ae 12.50 -1.1 < T/AH >216-234 BCD wind speed. D 12.5 > 7a5 o09< _e zT/AH S
- 2. Circle the appropriate stability D_12_5_ __ co___7_50 _ 0_9_< ______ >234 - 238 BCDE class. E 7.50> re a 3.80 -0.3 < AT/tM *0.9 >238 - 257 CDE F 3
.8>oe?2 .l0 0.9<ATIAH*2.5 >257- 261 CDEF G 2.1 > e 2.5 < AT/Aft >261-279 DEF Box #10 Indicate protective action recommendations. >279 - 283 DEFG
- 2. IF this a PAR change, THEN include any previously chosen affected sectors to indicate all >283 - 302 EFG affected sectors. >302-306 EFGH Box I. IF classifying an event, THEN at a minimum describe the EAL being >306-324 FGH implemented. >324 - 328 FGHJ
>328 - 347 GHJ applicable information related to the PAR.
>347-351 GHJK Page 22 of 28 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 2.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 NOTIFICATIONS - ERO, STATE AND COUNTIES, November 26, 2003 AND NRC ATTACHMENT C PLANT STATUS UPDATE Check One: Actual Drill Exercise NOTE: Cross-out section(s) not being communicated.
- 1. Point Beach Nuclear Plant
- 2. Date/Time:
- 3. Description of Event:
- 4. Emergency Action Level(s):
5 Major Equipment Affected: (LIST)
- a. b.
C. = d.
e.
- 6. Reactor Status: (Check one) 7. Radiological boundaries Lost(L) or Challenged (C):
(Indicate all that apply)
- a. Critical a. Fuel Cladding
- b. Shutdown b. Reactor Coolant System
- c. Containment
- 8. Plant Personnel Status (Enter # or N/A for each type incident):
- a. #_ _ Deaths b. # Overexposure to Personnel
.c. #_ _ Injured Personnel Treated On-Site d. # Injured Personnel Treated Off-Site'
- e. #__ _ Contaminated Personnel On-Site f. # Contaminated Personnel Off-Site
- g. Other (explain):
- 9. Areas Affected by A Radiological Release
- a. Plume Path (Downwind Sectors): _ _ :_ _: .:_ Distance (mi)
- b. Deposition (Describe Location):
- 10. News Statement from the JPIC or Established Media Center
- a. The Next News Statement is Scheduled for: Date: Time:
- 11. State or Local Assistance Requested by the Plant Eme~roenev
-4 : . .':
flirector An~nrnval:
Date-/ Time / --------- -------
Manitowoc Co. Kewaunee Co. Wisconsin WEM NRC (Time) (Time) (Time) (Time)
Communicated By:
Page 23 of 28 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 2.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 NOTIFICATIONS - ERO, STATE AND COUNTIES, November 26, 2003 AND NRC ATTACHMENT D RADIOLOGICAL STATUS UPDATE Page 1 of 3 Check One: 0 Actual Drill Exercise NOTE 1: { denotes PPCS screen or point identification for obtaining data.
NOTE 2: Cross-out section(s) not being communicated.
- 1. Point Beach Nuclear Plant
- 2. Date/Time: /
- 3. Plant Status:
- a. General: Improving _____ Stable Degrading
- b. Electrical Power: Satisfactory ____ Problems If problems, describe:
- 4. Offsite Radiological Conditions:
- a. Release Prognosis:
No Release is expected Release is expected at the start time listed in 4b.
Release is in progress
- b. Event Times (Complete all applicable times):
Reactor Trip Start of release to containment Start of release to environment
- Release Stop
- *(Actual / Estimated / Default) Line out inappropriate word(s)
- c. Type of Release:
Liquid Controlled Monitored Airborne Uncontrolled Unmonitored Release Path:
- d. Plume Path (Downwind Sectors): : : : Distance _ (mi)
- e. Downwind Doses at the Plume Centerline:
Based on: Projections _ Field Measurement I Mi (SBCC) rem TEDE _ rem CDE Thyroid 2 Mi. rem TEDE ___ rem CDE Thyroid 5 Mi. rem TEDE ___ rem CDE Thyroid 10 Mi. rem TEDE ___ rem CDE Thyroid Page 24 of 28 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 2.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 NOTIFICATIONS - ERO, STATE AND COUNTIES, November 26, 2003 AND NRC ATTACHMENT D RADIOLOGICAL STATUS UPDATE Page 2 of 3
- f. Surface Deposition: Based on: Projection ______ Field Measurement dpm/100 cm - Ci/m 2 Location:
dpm/IOO cm - Ci/m2 Location:
dpm/100 cm - Ci/m2 Location:
(Line out inappropriate unit)
- g. Recommended protective actions were made at (Time: _ _ ) on the Wisconsin Nuclear Accident Reporting System form.
- 5. Meteorological Conditions: Releases/Met Summary)
- a. Wind Speed: MT1WSLO) _ _ MPH
- b. Wind Direction: {MTIWDLO) Degrees
- c. Stability Class (METSTAB)(circle one): A B C D E F G
- d. Mixing Layer Height: _ _ Ft.
- e. Precipitation {MT2PREC) (check one):
Light Rain _ _ Moderate Rain Heavy Rain _ None Light Snow _ Moderate Snow Heavy Snow
- 6. Reactor Status: _____ At Power (_ _ Megawatts Thermal) (RTO}
{Core) Tripped (Power Level at trip Megawatts Thermal) {RXTRIPJ
_____ Hot Shutdown (Current RCS Temperature deg. F.) I COLD)
Cold Shutdown (RCS is less than 200'F.)
- 7. Core Status: _____ No Damage Expected Core Damage sequence in progress (Est. Time: )
Gap Release (Est. Time: )
______ In-Vessel Severe Core Damage (Est. Time: )
_____ Vessel Melt Through (Est. Time: D Core Exit Increasing - Stable ^ ~Decreasing Temperature: {TCAVG)
{SAS Trend-Core Cooling)
- 8. Containment Status:
- a. Containment Spray F-962 & F-963): b. Containment Leak Rate
____ON None OFF Calculated ( cc/sec) CONTLR)
Design Rate (0.1% per day)
____ 100% per Day 100% per Hour
- c. Pressure SYSA140) d. Temperature SSA139)
(SAS Trends-Cont PPR) {SAS Trends-Cont HIT)
Increasing Increasing
______ Stable Stable Decreasing Decreasing Page 25 of 28 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 2.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 NOTIFICATIONS - ERO, STATE AND COUNTIES, November 26, 2003 AND NRC .
ATTACHMENT D RADIOLOGICAL STATUS UPDATE Page 3 of 3
- 9. Steam Generator Status:
- a. Leak Rate (Check One): b. Reactor Coolant Concentrations:
None - N/A (No Leak)
Full Pressure (# of tubes ) Normal Low Pressure (# of charging pumps ) 100x normal non-nobles
-___Calculated LR215} Calculated Concentration (Gallons per minute ____) (Attached Analysis)
- c. Partitioning: {Steam Generator} d. Release Path N/A (No leak) None Leak is above steam generator water Safety Valve (or PORV) level (default) Air Ejector Leak is below steam generator water level
- 10. Containment Bypass Status:
- a. Containment Bypass Leak Rate b. Release Path:
None None Calculated ( _ cc/sec) Filtered 0.1 % per Day Unfiltered 100% per Day 100% per Hour
- 11. Gross Release Rate Data:
- a. _ _ Not Applicable (No Leak) b. .. Not Available
- c. Total - Ci/sec Kr, Xe _ S lodines ___ Cs So Te,Sb _ %
Ba, Sr % Ru, Mo__% La, Y Ce, Np %
- 12. Specific Isotopic Release Data (Ci/sec):
- a. __ Not Applicable (No leak) b. Not available
- c. H-3 Sr-91 _ Te-131. - Xe-133 Mn-54 Y-91 Te-132 Xe-135 Co-58. Mo-99 I-131 Xe-138 Kr-85 Te-99m I-132 Cs-134 Kr-85m Ru-103 I-133 Cs-136 Kr-87 Ru-106 I-134 Cs-137 Kr-88 Sb-127 1-135 Ba-140 Sr-89 Sb-129_ _ Xe-131m,. La-140 Sr-90 Te-129m Xe-133 Ce-144 Emergency Director Approval: Date / Time /
Manitowoc Co. Kewaunee Co. Wisconsin NNEM NRC (Time) (Time) (Time) (Time)
Communicated By:
Page 26 of 28 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 2.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 NOTIFICATIONS - ERO, STATE AND COUNTIES, November 26, 2003 AND NRC ATTACHMENT E STATUS REPORT ON PLANT SYSTEMS AND CONTROLS FOR AFFECTED UNIT Page 1 of 2 Check One: 0 Actual 0 Drill 0 Exercise NOTE 1: } denotes PPCS screen or point identification for obtaining data.
NOTE 2: Cross-out section(s) not being communicated.
- 1. Basic Accident Information (Unit )
- a. Status Report Date/Time: l ; Report # -
(Date) (Time-24 Hours)
- b. Emergency Classification:
- c. (If applicable) Time of Reactor Shutdown: hrs.
- d. (If applicable) Time of Radiological Release to Containment: _______ hrs.
- e. (If applicable) Time of Radiological Release from Plant: hrs.
- 2. Status of Reactivity Control Subcritical Yes__ No__
- 3. Status of Core Cooling {Core)
- a. HighestTh F {TCH1ID)ColdestTc OF
- b. Incore Thermocouples: {TCAVG) Average Temperature -OF
- c. Pressurizer Heaters Available Yes . . No
- d. Subcooling Margin: {SYSA138) OF
- 4. . Status of Reactor Coolant System Integrity Core}
- a. Pressurizer or Reactor System Pressure PZRPRESS I psig
- b. Pressurizer Level PZRLVL)
- c. Primary System Relief Valves Closed PCV-435A&B} Yes__ No
- d. Letdown Flow {F-134) gpm
- e. Charging Pump Flow F-I 281 gpm
- 5. Status of Secondary Systems {Secondary)
- a. Steam Generator PressureSGAPRESS)"A" psig SGBPRESS} "B" _ psig
- b. Steam Generator Level SGAWRLVL) "A" % (SGBWRLVrL) "B"_ __ %
- c. Feedwater Flow, Auxiliary {F-4036) "A" gpm (F-4037) "B"_ _ gpm Main F-466) "A" _ _ _bmlh F-476) "B" _ _ klbm/h
- 6. Containment Containment)
- a. Pressure P-968) WR psig (P-945) NR psig
- b. Containment Spray Flow F-962 & F-963 1 gpm
- c. NaOH Addition Yes . . No Time Level {L-93 1)
- d. Containment Recirculation Coolers Running (Circle) WIAI-WIWI) 12 3 4
- f. H2 Concentration IHA964} %
- g. Containment Isolation Valves (Note any not closed)
Page 27 of 28 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 2.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 NOTIFICATIONS - ERO, STATE AND COUNTIES, November 26, 2003 AND NRC .
ATTACHMIENT E STATUS REPORT ON PLANT SYSTEMS AND CONTROLS FOR AFFECTED UNIT Page 2 of 2
- 7. Safeguards Systems Core
- a. Safety Injection Train A Train B High Head {F-924) gpm F-925) gpm Low Head {F-626_ _ gpm {F-928}_ gpm
- b. Accumulators Level Pressure psig psig Isolation Valve Open Yes/No Yes/No
- c. Refueling Water Storage Tank Level % Core) L-972)
- d. Component Cooling Water Temperature {T-6161inlet OF {T-4 21 )outlet ___F Flow {F-619) gpm
- e. Service Water No. of pumps running Temp(T-3510)
- 8. State of Meteorology {Releases/Met Summary) Primary Tower Inland Tower 10M 45M 0
- a. Wind Direction (avg.)
0
{MTIWLDO} {MTIWDHI)
{MT#WD)
- b. Wind Speed mph mph (MTIWSLO) {MTIVSHI ) I MT3WS)
C. {MT1DSD) 0 (MT3NVDSD) I
- d. AT/AH {MTIDT) OF
- e. Atmospheric Stability Class {METSTAB )
- f. Lake Breeze Conditions Exisit? (circle) {METLBREZJYes I No
- 9. Status of Power Supplies
- a. Offsite Power Unit 1 Y/N Unit 2 YIN Gas Turbine Y/N
- b. Diesel Running G01 YIN G02 Y/N G03 Y/N G04 Y/N Diesel Loaded G01 Y/N G02 Y/N G03 Y/N G04 Y/N
- 10. Other Equipment Remarks:
Emergency Director Approval: Date I Time I Manitowoc Co. Kewaunee Co. Wisconsin WEM NRC (Time) (Time) (Time) (Time)
Communicated By:
Page 28 of 28 REFERENCE USE
EPIP 1.3 DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATIONS DOCUMENT TYPE: Technical CLASSIFICATION: Safety Related REVISION: 32 EFFECTIVE DATE: November 26, 2003 REVIEWER: Plant Operation's Review Committee APPROVAL AUTHORITY: Department Manager PROCEDURE OWNER (title): Group Owner OWNER GROUP: Emergency Preparedness Verified Current Copy:
Signature Date Time List pages used for Partial Performance Controlling Work Document Numbers
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS TABLE OF CONTENTS Page 1 of 2 SECTION TITLE PAGE 1.0 PURPOSE .......................................... 4 2.0 PREREQUISITES..........................................................................................................4 3.0 PRECAUTIONS AND LIMITATIONS .......................................... 5 4.0 INITIAL CONDITIONS .......................................... 5 5.0 PROCEDURE................................................................................................................6 5.1 Protective Action Recommendations (PARs) .......................................... 6 5.2 Wisconsin Electric Dose Assessment Program (WEDAP) .......................................... 7 5.3 Radiation Monitoring System-System Server (RMS-SS) ......................................... 12 5.4 Offsite Field Measurements ................... 19 5.5 Manual Calculations ................... 20
6.0 REFERENCES
................... 51 7.0 BASES .................. 51 TABLES TABLE 1 RELEASE MONITORS ALARMING .......................................................... 13 TABLE 2 RELEASE RATE CALCULATIONS .......................................................... 15 TABLE 3 RELEASE RATE CONVERSION FACTORS - SURVEY METER METHOD ........ 23 TABLE 4 CLASSIFICATION OF ATMOSPHERIC STABILITY BY SIGMA THETA AND AT/AH ................ ....................................... 29 TABLE 5 BACKUP DETERMINATION OF ATMOSPHERIC STABILITY CLASS .............. 30 TABLE 6 TABLE OF CENTERLINE Xu/Q VALUES VERSUS DISTANCE FROM THE SITE ................................ 31 TABLE 7 SOURCE TERM ACTIVITY FRACTIONS ............................... 43 Page 2 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS TABLE OF CONTENTS Page 2 of 2 SECTION TITLE PAGE ATTACHMENTS ATTACHMENT A AFFECTED SECTORS BASED ON WIND DIRECTION .......................... 52 ATTACHMENT B GENERAL EMERGENCY OFFSITE PROTECTIVE ACTIONS ............... 53 ATTACHMENT C REINSTALLATION OF WEDAP SOFTWARE .......................................... 54 WORKSHEETS WORKSHEET I RELEASE RATE CALCULATIONS ................................. ............... 24 WORKSHEET 2 X/Q DETERMINATION ............................................... 28 WORKSHEET 3 ESTIMATED WHOLE BODY DOSE ............................................... 33 WORKSHEET 4 ESTIMATED THYROID DOSE ................................................ 35 WORKSHEET 5 ESTIMATED GROUND DEPOSITION....................................................... 38 WORKSHEET 6 ESTIMATED POPULATION DOSE ............................................... 40 Page 3 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS 1.0 PURPOSE This procedure provides several methods to project offsite dose due to a release of radioactive material. These projections will be used to provide Protective Action Recommendations (PARs) to the State and Counties.
2.0 PREREOUISITES 2.1 Responsibilities 2.1.1 The Shift Manager (SM) is responsible for the radiological dose assessment and protective action recommendations using WEDAP, prior to TSC/EOF activation and formal transfer of responsibilities to the Emergency Director.
If available, the SM may assign this task to the Operating Supervisor(s) (from unaffected unit) or the Shift Technical Advisor (STA). RMS-SS is used in the absence of WEDAP and Field Monitoring Team data is used in the absence of RMS-SS.
2.1.2 The Emergency Director may delegate the performance of radiological release evaluation portion of this procedure to the Dose/PAR Coordinator. The Dose/PAR Coordinator will advise the Emergency Director of the need to escalate the emergency classification or change protective action recommendations based upon radiological conditions.
2.1.3 The Dose/PAR Coordinator is responsible for the continuing dose assessment and Protective Action Recommendations to the Emergency Director using WEDAP, Field Monitoring Team data, RMS-SS, and/or manual calculations.
2.1.4 IF the Dose/PAR Coordinator is unable to perform radiological release evaluations, THEN the Rad/Chem Coordinator in the TSC will assume this responsibility.
2.2 Equipment 2.2.1 Wisconsin Electric Dose Assessment Program (WEDAP) 2.2.2 Radiation Monitoring System-System Server (RMS-SS) 2.2.3 Plant Process Computer System (PPCS)
Page 4 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS 3.0 PRECAUTIONS AND LIMITATIONS 3.1 Complete this procedure regardless of changing plant conditions.
3.2 PARs are made to the Sate and Counties by the Shift Manager or the Emergency Director, depending on the status of emergency facility activation. The Dose/PAR Coordinator (or the Rad Chem Coordinator if the EOF is not activated), performs dose projections and monitors offsite radiological conditions, develops the associated PAR and provides the PAR and basis to the Emergency Director.
3.3 PARs are developed from current rather than forecasted weather conditions. PARs are revised due to actual weather condition changes (e.g. wind shift occurs or atmospheric stability class changes) only when a revised dose projection or offsite radiological condition results in a change in PAR.
3.4 Use a realistic estimate of release duration in these calculations whenever possible.
IF the duration of the radiological release can NOT be determined from the current plant conditions, THEN, assume a duration of four hours.
3.5 IF the meteorological data can NOT be obtained from the PPCS or the control room instruments, THEN obtain the data from any of the following sources: (Reference ETD 02. Offsite Agency Call ust):
3.5.1 National Weather Service in Green Bay 3.5.2 Kewaunee Nuclear Power Plant 3.5.3 Two Rivers Coast Guard Station 4.0 INITIAL CONDITIONS 4.1 EPIP 1.1, Course of Actions, in progress.
4.2 RMS or plant conditions suggest that a release is in progress or anticipated.
Page 5 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS 5.0 PROCEDURE 5.1 Protective Action Recommendations (PARs)
NOTE 1: PARs are made to the State and Counties by the Shift Manager or the Emergency Director, depending on the status of emergency facility activation. The Dose/PAR Coordinator (or the Rad Chem Coordinator if the EOF is not activated), performs dose projections and monitors offsite radiological conditions, develops the associated PAR and provides the PAR and basis to the Emergency Director.
NOTE 2: PARs are developed from current rather than forecasted weather conditions. PARs are revised due to actual weather condition changes (e.g. wind shift occurs or atmospheric stability class changes) only when a revised dose projection or offsite radiological condition results in a change in PAR.
NOTE 3: In some cases (e.g., short-duration puff release, inclement weather),
sheltering may be an appropriate recommendation. This should be discussed with the state and/or counties, if appropriate.
5.1.1 IF the event is a General Emergency AND ALL the following criteria are met, THEN implement expanded PARS of evacuation for 0-5 miles all sectors and 5-10 miles downwind sectors. [EOF] (RerStep16.5)
- a. Substantial core damage in progress or projected (>20%) (> 30,000 R/hr in containment high radiation monitors)
- b. Large fission product in inventory in containment (more than GAP)
(LOSS criteria for RCS barrier in EPIP 1.2, Attachment C, exceeded)
- c. Imminent projected containment failure or release underway (LOSS criteria for containment barrier in EPIP 1.2, Attachment C, exceeded) 5.1.2 IF a General Emergency is declared AND there is indication of a lake breeze or low wind speed (<3mph),
THEN the PAR for the condition is evacuation 0-5 miles (all sectors).
5.1.3 IF a General Emergency is declared AND the conditions stated in step 5.1.1 and 5.1.2 DO NOT exist, THEN the default PAR is evacuation 0-2 miles (all sectors) and 2-5 miles (3 or 4 downwind sectors centered on the average wind direction).
Page 6of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS NOTE: Emergency Classifications and PARs shall be made to the State and Counties within 15 minutes of the emergency classification being declared or identification of a change in the required PAR.
5.1.4 PARs shall be documented on EPIP Form 2.1 and sent to the State and Counties.
5.1.5 There are no PARs required for Site Emergency, Alert, or Unusual Event emergency classifications.
5.1.6 IF a release is occurring or is imminent, THEN radiological release evaluation and dose projection shall be completed using steps 5.2-5.5 as applicable to determine or revise the emergency classification and/or PAR.
- a. WEDAP (section 5.2)
- b. RMS-SS (section 5.3)
- c. Offsite Field Measurements (section 5.4)
- d. Manual Calculations (section 5.5)
NOTE: Review section 3.0 prior to revising the PAR.
5.2 Wisconsin Electric Dose Assessment Program (WEDAP)
NOTE: The "Source Term" and "Release Path" categories will have drop-down menus to determine the severity of the event and should be opened to select the appropriate category for the event. When opened, each drop-down menu has been organized to list the options from the least severe to the most severe.
NOTE: IF WEDAP is NOT available in the Control Room, THEN go to Step 5.2 for assessment by using RMS-SS, R, F WEDAP is NOT available in the EOF (TSC if backup),
THEN go to Attachment C, "Reinstallation of WEDAP Software".
5.2.1 Power up the designated personal computer (PC) using the master power switch to "boot up" into Windows NT, selecting "stand-alone" if presented with a selection of configurations during bootup.
Page 7 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS 5.2.2 Log on to the PC using the PC number (label affixed to PC) as both the identification number and password, entering it in lower case.
5.2.3 Launch WEDAP by selecting "Business Applications - WEDAP" or the "WEDAP icon".
5.2.4 Select "Start" when prompted at WEDAP introduction screen.
5.2.5 Enter a "Title" for this dose assessment case to provide retrievability if the case is saved.
5.2.6 Click on "Data" on the toolbar and select the option "Case Basis".
5.2.7 Click on the appropriate "Accident Type" for the event.
5.2.8 Update all the data fields in the "Source Term" section.
5.2.9 Update all the data fields in the "Release Path" section.
5.2.10 Click "OK" to return to the summary page.
5.2.11 Verify details in the "Accident Data" section are based upon the data selected in Steps 5.2.5 - 5.2.9, returning to "Data" and "Case Basis" to make corrections if necessary.
5.2.12 Update "Reactor Shutdown Time" data field with the correct data if applicable.
5.2.13 Update "Release Start" by entering the time the release to environment began.
5.2.14 Update "Release End" by entering the correct data for an estimated time the release to environment will terminate.
IF release duration is unknown, THEN use four hours as a default value.
5.2.15 Update the "Meteorological Data" section categories by clicking on each data field and selecting the correct data:
- a. Met Date
- b. Stability Class (automatically updates "Building Wake" check box)
- c. Sigma Theta (Only key-in value from PPCS if stability class unavailable and >3 mph wind speeds)
Page 8 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS
- d. Lapse Rate (Only key-in value from PPCS if stability class is unavailable and <3 mph wind speeds)
- e. Precipitation
- f. Lake Breeze
- g. Wind Speed
- h. Wind Direction 5.2.16 Verify the data on the WEDAP main screen and make corrections if appropriate.
5.2.17 Click on the "Calculate" icon to perform the final dose assessment calculations, which automatically updates the dose assessment data fields.
5.2.18 Review the dose assessment result tabs (a single click for simple data OR double-click for expanded data).
- a. Dose
- b. Dose Rate
- c. Event Class
- a. IF in the Control Room AND the result of this assessment is an escalation of classification and/or PARs, THEN go to EPIP 1.1, Step 5.6, OR exit this procedure if NOT an escalation.
- b. IF in the EOF (TSC if backup) AND the result of this assessment is an escalation of classification and/or PARs, THEN immediately inform the Emergency Director and assist with EPIP 2.1 for initiating notifications, OR proceed to the next step for a continuous dose assessment if NOT an escalation:
Page 9 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS NOTE: The "View" icon on the toolbar is to access additional tables and maps available for reference use.
NOTE: To save the data from a series of case assessments, click on "File," "Save Scenario File," and then reclick on "File" and "Restart WEDAP" to start a new scenario with new cases.
5.2.20 Click on the "Print Case" icon to create a hard copy of the current case.
IF the printer connection is not established, THEN go to EPIP 1.3, Attachment C, Step 2.0.
5.2.21 Click on the "Add Case" or "Insert Case" icon as appropriate to run the next dose assessment.
- a. Determine if this case is to be based upon a cumulative dose and change the field as appropriate.
- b. Repeat Steps 5.2.5 - 5.2.19
- c. IF time permits to run a more detailed dose assessment case, THEN implement the following steps:
- Click on "Data," select the option "Equipment Status," enter the Unit affected, and update all the data fields in the "Equipment Status" section.
- Click on "Data," select the option "Measured Data," and select one of the following options for entering values from actual data sources:
(a) "RMS Data - Manual Input" and update the field with the RMS monitors and readings in high alarm status.
(b) "Offsite Measurements - Isotopic Data" and update the fields with the correct data, including selecting the nuclides involved.
(c) "Offsite Measurements - Survey Reading" and update the fields with the correct data.
(d) "Isotopic Release Rate" and select the nuclides involved, updating with the correct data.
Page 10 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS NOTE: Cases can be generated on actual event data or "what-if" scenarios.
- d. IF the case was built on a "what-if" scenario, THEN repeat Step 5.2.17, Step 5.2.18, and Step 5.2.20, THEN click on the "Delete Case" icon, AND repeat Step 5.2.21.
- e. IF the case was built on the actual events in progress, THEN repeat Steps 5.2.17 - 5.2.19 Performed By:
Performer (Print and Sign) Date / Time Page II of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS 5.3 Radiation Monitoring System-System Server (RMS-SS) 5.3.1 IF WEDAP AND RMS-SS are unavailable, THEN declare an ALERT to activate the Emergency Response Facilities (ERFs) so dose assessment can be performed using field data, AND go to EPIP 1.1, Step 5.5, AND Step 5.3 of this procedure, performing both simultaneously.
5.3.2 Verify RMS-SS is available:
- a. The letters "M" (master) and "S" (slave) are intermittently displayed in the upper right hand corner of the SS monitor. The time is also correct and moving forward. This indicates BOTH SSs are operating.
- b. An "X" appears in the upper right hand corner of the SS monitor and the time is correct and moving forward. This indicates that a single SS is operating.
5.3.3 Estimate Release Rate Using Data From RMS-SS NOTE: Using the "ESC" key returns the SS to the main menu screen
- a. Obtain a list of monitors in high alarm by performing the following:
- From the Main Menu Screen (MMS), highlight (using arrow keys)
"Display Status", press "Enter"
- Highlight "Status", press "Enter"
- Highlight item "20" (high alarm), press "enter" and all channels in high alarm will be listed
- b. Call up data (microcuriesfcc) on the RMS-SS for each monitor in high alarm by performing the following and log on Table 1:
- From the MMS, highlight "Data", press "Enter".
- Highlight "Ten Minute History" (or other interval as needed), press "Enter".
- Enter the DAM or SPING address (DAM1 to DAMS, SPING21 to SPING24), press "Enter".
Page 12 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS
- Enter channel number' , press "Enter".
- Press "Enter" to toggle between available screens
- c. Data may be printed by highlighting "Print" on the relevant screen and pressing "Enter".
TABLE 1 RELEASE MONITORS ALARMING READING DAM CHANNEL RMS # MONITOR MONITO)R READING (RCi/cc) 1RE-212 U1 Cont. Purge 2RE-212 U2 Cont. Purge lRE-231 SG 1A 2RE-231 SG2A I RE-232 SG 1B RE-221 Drum Area Vent RE-226 Comb A. E. High Range Steam Line RE-224 Gas Stripper Building 2RE-232 SG2B RE-225 Comb A. E. Low Range RE-214 Aux Building Vent IRE-305 Low Range Gas, UI Purge 1RE-307 Medium Range Gas, Ul Purge 1RE-309 High Range Gas, Ul Purge 2RE-305 Low Range Gas, U2 Purge 2RE-307 Medium Range Gas, U2 Purge 2RE-309 High Range Gas, U2 Purge RE-315 Low Range Gas, Aux Bldg Vent RE-317 Medium Range Gas, Aux Bldg Vent RE-319 High Range Gas, Aux Bldg Vent RE-325 Low Range Gas, Drumming Area Vent RE-327 Medium Range Gas, Drumming Area Vent Page 13 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS 5.3.4 IF the release path monitor(s) is/(are) failed high and the associated SPING(s) is/(are) out of service, THEN declare an ALERT to activate the Emergency Response Facilities (ERFs) so dose assessment can be performed using field data and/or WEDAP, AND go to EPIP 1.1, Step 5.5, to end, AND Step 5.3 of this procedure, performing both simultaneously.
5.3.5 Record the highest in-range (NOT failed) alarming RMS channel readings (Ci/cc) for each release path on Table 2 and calculate the release rate.
Page 4 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS TABLE 2 RELEASE RATE CALCULATIONS NOTE: Conversion factors assume nominal flow rates.
READING CONVERSION RELEASE RATE RMS # LOCATION (JiCi/cc) (cc-Ci/sec-jiCI) (Ci/sec)
RE-214 Auxiliary Building Vent x 33 =
RE-315 RE-317 RE-319 V x RE-221 Drummin Area Vent x 20 RE-327 IRE-212 Ul Containment Purge IRE-305 (O or 1 fan) x 6 =
IRE-307 IRE-309 + (2 fans) x 12 =
2RE-212 U2 Containment Purge 2RE-305 (O or 1 fans) x 6 =
2RE-307 2RE-309 * (2 fans) x 12 =
RE-224 Gas Stripper Bldg x 6 =
RE-225 Combined Air Ejectors x 0.012 =
RE-226 4 RE-231 A Steam Line Header RE-232 B Steam Line Header Atmospheric x 1.5 =
1 Safety x 4.0' 2 Safeties x 8.0 =
3 Safeties x 12.0 =
4 Safeties x 16.0 =
Release Rate Total (Ci/sec) =
Page 5 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS NOTE: IF desired PPCS points have poor or bad quality, THEN obtain aO and lapse rate readings from the Control Room indications, AND THEN reference Table 4 to determine stability class.
5.3.6 Calculate the Dispersion Factor (X/Q) at the Site.
- a. Obtain the wind speed and stability class from the PPCS "Release/MET Summary" screen. Record wind speed in Step 5.3.6.c equation.
- b. Select the appropriate Xu/Q factor value from the table below based upon the stability class. Record the X/Q factor value in Step 5.3.6.c equation.
Stability Class XuIQ A 9.92E-07 B 1.1 8E-05 C 4.28E-05 D 1.34E-04 E 2.55E-04 F 5.38E-04 G 1.04E-03
- c. Calculate the dispersion factor:
XuIQ(mph/m 3 /s) X/Q(slm 3 )
(step b above) wind speed (mph) 5.3.7 Determine the Estimated Duration (ERD) of release. Use four hours as a default if the ERD is unknown.
5.3.8 Estimate the Projected Whole Body Dose (TEDE) at the Site Boundary.
3280 x x x ~ =Rem Ci - hr (Table 2 Total) (Step 5.3.6.c) (ERD) [PROJ. W. B. DOSE (TEDE)]
5.3.9 Calculate Projected Thyroid Dose (CDE) at the Site Boundary.
Page 16 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS NOTE: Choose LOCA accident type unknown PROJECTED CONVERSION PROJECTED WHOLE BODY FACTOR THYROID DOSE ACCIDENT DOSE (TEDE) (Rem) (CDE)
TYPE (From Step 5.3.8) (Rem)
LOCA x 15 =
Gap Activity x3 =
Fuel Handling x20 =
SG Tube Rupture x 12 - =
5.3.10 IF the event meets the following criteria for a GENERAL EMERGENCY, THEN go to Step 5.3.14 and determine PARS.
5.3.11 IF the event meets the following criteria for a SITE EMERGENCY, THEN go to Step 5.3.15.
5.3.12 IF the event meets the following criteria for an ALERT, THEN go to Step 5.3.15.
One of more effluent radiation alarming monitor readings is >10 times high alarm setpoint for >15 minutes [Radiation Monitoring System Alarm Setpoint
& Response Book (RMSASRB)].
5.3.13 IF the event meets the following criteria for an UNUSUAL EVENT, THEN go to Step 5.3.15.
One or more effluent radiation alarming monitor readings is >high alarm setpoint for >60 minutes [(Radiation Monitoring System Alarm Setpoint &
Response Book (RMSASRB)].
Page 17 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS 5.3.14 Determine Protective Action Recommendations NOTE: Lake breeze conditions exist if the difference between actual wind direction values for inland an near shore meteorological towers is greater than 900.
- a. To determine protective action recommendations compare values from Step 5.3.9 and the values in the "Integrated Projected Dose" column below.
NOTE: In some cases (e.g., short-duration puff release, inclement weather) sheltering may be an appropriate recommendation.
This should be discussed with the state and/or counties, if appropriate.
INTEGRATED PROTECTIVE PROJECTED DOSE ACTION MILES SECTORS
>1 rem TEDE Evacuate 0-2 miles All (3600)
OR Evacuate 2-5 miles Downwind Sectors
>5rem CDE__ _ _ _ _ _ _ _ _
<3 mph Wind Speed OR Lake Breeze Evacuate 0-5 Miles All (3600)
AND
- b. Select downwind sectors using Attachment A.
5.3.15 Compare the results against the current classification and PARS.
IF the results of this assessment is an escalation of classification and/or PARS, THEN go to EPIP 1.1, Step 5.5, OR exit this procedure if NOT an escalation.
Performed By:
Performer (Print and Sign) Date / Time Page 18 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS 5.4 Offsite Field Measurements 5.4.1 Check if Plume Impacts Terrestrial Areas
- a. Wind Direction > 3050 OR
- b. Wind Direction <2100 5.4.2 Use Field Monitoring Team(s) to measure gamma dose rate at 1-mile from the site and log.
Maximum measured gamma dose rate: R/hr 5.4.3 IF measurement from Step 5.4.2 is Ž1 R/hr, THEN event is a GENERAL EMERGENCY.
NOTE: In some cases (e.g., short-duration puff release, inclement weather),
sheltering may be an appropriate recommendation. This should be discussed with the state and/or counties, if appropriate.
5.4.4 IF a General Emergency, THEN determine minimum Protective Action Recommendations, AND o to Step 5.4.6.
- a. Evacuation of 0-2 miles for all sectors, and 2-5 miles in the downwind sectors.
- b. Evacuation of all sectors (3600) to 5 miles, IF wind speed less than three (3) mph or lake breeze conditions exist.
5.4.5 IF measurements from Step 5.4.2 is 20.1 R/hr, THEN event is a SITE EMERGENCY, AND go to Step 5.4.6.
Page 9 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS 5.4.6 Compare the results of your assessment against the current classification and PARS.
IF the results of this assessment is an escalation of classification and/or PARS, THEN go to EPIP 1.1, Step 5.5, OR exit this procedure if NOT an escalation.
Performed By:
Performer (Print and Sign) Date / Time 5.5 Manual Calculations 5.5.1 Manual Calculation of Release Rates (Source Terms)
- a. Airborne effluents may be discharged from PBNP through the following vent stacks and their associated monitors:
- Auxiliary building vent (ABVNT)
RE-214, RE-315, RE-317, and RE-319
- Drumming area vent (DAVNT)
RE-221, RE-325, and RE-327
- Unit 1 containment purge vent (Cont. 1)
IRE-212, IRE-305, IRE-307, and IRE-309
- Gas stripper building vent (GSBVNT)
RE-224 NOTE: This CAE pathway vents to the Auxiliary Building Vent Stack.
- Combined air ejector decay duct (CAE) 1(2)RE-215, RE-225, RE-226 Page 20of 6 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS
- Main steam safety valves and atmospheric dump valves 1(2)RE-23 1 "A" Steam Generator 1(2)RE-232 "B" Steam Generator
- b. The release rates may be estimated using any of the following monitoring systems:
- Radiation monitoring system (which is designed to monitor-low and high level releases)
NOTE: The contact reading method is used when the other monitoring systems are inoperable.
- Contact readings using a hand-held survey meter. It is assumed that the direct contact readings are determined using an RO-2A, Teletector, or equivalent survey meter.
NOTE: The actual number of main steam safety valves and atmospheric dump valves open should be obtained from the Shift Manager to estimate the release rate.
- c. Record above normal monitor reading(s) in the "Reading" column in Section A of Worksheet 1. Enter a comment for any monitor reading that is off-scale or inoperable.
- d. Multiply the reading by the conversion factor and entering the result in the "Release Rate" column on Section A of Worksheet 1.
- e. IF monitor readings are available for all release paths, THEN go to Step 5.5. j.
NOTE: The direct contact survey is accomplished under the direction of the Rad/Chem Coordinator. It must be approved by the TSC Manager and the Shift Manager.
- f. Do NOT perform direct contact readings using a hand-held survey meter until the following actions have been done:
- Evaluate the radiological conditions prior to entering the Auxiliary Building or the Containment Building facade.
- Choose the proper survey meter and the most direct and desirable route to the stack, pipe, or vent.
Page 21 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS
- g. Perform direct contact readings using a hand-held survey meter when RMS readings are NOT available. Enter direct contact readings in the "Meter Reading" column of Section B of Worksheet 1.
To take the survey of the main steam safety valves and the atmospheric dump valves place the meter probe in contact with the centerline of the main steam header, three feet from the main steam line.
- Shield the survey probe with a minimum of 1/4 inch of lead on the main steam line/containment building side of the probe.
- Obtain the probe shield from the Radiation Protection supply locker in the Operations Support Center (OSC).
- h. For each direct contact reading in any area, enter the conversion factor from Table 3 in the "Conversion Factor" column on Worksheet 1.
Conversion factors are accident type dependent.
- i. Multiply the direct contact reading by the conversion factor to calculate the release rate. Enter the release rate in the "Release Rate" column of Section B of Worksheet 1.
- j. IF actual flow rates vary significantly from the assumed flow rates listed on Worksheet 1, THEN adjust the flow rates using Section C of Worksheet 1.
- k. Enter all calculated release rates in the appropriate spaces in Section D of Worksheet 1. Total all release rates to calculate the gross release rate.
- l. Sign and date Worksheet 1 and fax upon completion to the Dose/PAR Coordinator.
Page 22 of 56 REFERENCE USE
- POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATIONS November 26, 2003 TABLE 3 RELEASE RATE CONVERSION FACTORS - SURVEY METER METHOD Units of expression are Ci-h/s-rem.
ACCIDENT TYPE Gap Accident04 ) Steam Generator Tube Rupture")
Vent Pathway LOCA"' 0-12 hou rs > 12hours FHA(') No condenser Condenser Aux. Building 9.40 12.6 79.0 373 Drumming Area 6.00 8.00 41.1 104 Cont. Purge 2.60 3.50 20.0 74.0 Gas Stripper 2.48 3.31 20.0 83.0 Air Ejector 1.40 1.40E+04 Steam Line Atmospheric 164 Safety, 1 410 Steam Driven AFWP 0.235 Note: (1) The accident type acronyms are: LOCA - Loss of Coolant Accident and FlHA - Fuel Handling Accident (2) No condenser means that the vent pathway is NOT through the condenser. Condenser means the vent pathway is through the condenser.
(3) The release rate conversion factors were calculated using the following flow rates:
Vent Pathway Flow Rate (ft 3/min)
Auxiliary Building 70000 Drumming Area 43100 Containment Purge 12500 Gas Stripper 13000 Air Ejector 25 Atmospheric Vent 3200 Safety, 1 8000 Steam Driven AFWP 4.2 (4) The time intervals referred to in the Gap Accident are for the time periods 0 to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and greater than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor shutdown Page 23 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS WORKSHEET 1 RELEASE RATE CALCULATIONS Page 1 of 3 A. OPERATIONAL LOW-RANGE RELEASE MONITOR READOUTS (Assumed flow rates are in parentheses)
Conversion Reading Factor Release Rate Monitor (RCi/cc) (cc-Ci/s-RCi) (Cils)
Auxiliary Building Vent (70,000 cfm) 33 (RE-214, RE-315, RE-317, or RE-319)
Drumming Area Vent (43,100 cfm) 20 (RE-221, RE-325, or RE-327)
Unit 1 Containment Purge (RE-212, RE-305, RE-307, or RE-309)
(0 or 1 fan - 12,500 cfm) 6 (2 fans - 25,000 cfm) 12 Unit 2 Containment Purge (RE-212, RE-305, RE-307, or RE-309)
(0 or 1 fan - 12,500 cfm) 6 (2 fans - 25,000 cfm) 12 Gas Stripper Building Vent (13,000 cfm) (RE-224) 6 Combined Air Ejector (25 cfm) 0.01 (RE-215, RE-225, and RE-226)
Steam Driven Aux FW Pump [1(2)P-29] (4.2 cfm ea)
(RE-219, RE-231, RE-232, or measured conc.)
1 pump 0.002 2 pumps 0.004 Steam Line Vent (RE-231 and RE-232)
Atmospheric (3200 cfm) 1.5 1 Safety (8000 cfm) 4 2 Safeties (16000 cfm) 8 3 Safeties (24000 cfm) 12 4 Safeties (32000 cfm) 16 Page 24 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS WORKSHEET 1 RELEASE RATE CALCULATIONS Page 2 of 3 B. PLANT EFFLUENT VENT STACK CONTACT READINGS (Assumed flow rates are in parentheses)
Accident type: LOCA Gap Activity Fuel Handling S/G Tube Rupture Other Conversion Factor Meter Reading (Ci-hls-rem) Release Rate Monitor (R/hr) (Table 3) (Ci/s)
Auxiliary Building Vent (70,000 cfm)
Drumming Area Vent (43,100 cfm)
Unit 1 Containment Purge (0 or 1 fan - 12,500 cfm)
(2 fans - 25,000 cfm)
Unit 2 Containment Purge (0 or I fan - 12,500 cfm)
(2 fans - 25,000 cfm)
Gas Stripper Building Vent (13,000 cfm)
Combined Air Ejector (25 cfm)
Steam Driven AFWP Steam Line Vent Atmospheric (3200 cfm) 1 Safety (8000 cfm) 2 Safeties (16000 cfm) 3 Safeties (24000 cfm) 4 Safeties (32000 cfm)
Page 25 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS WORKSHEET I RELEASE RATE CALCULATIONS Page 3 of 3 C. ACTUAL VERSUS CONVERSION CURVE FLOW RATE RATIO Actual Flow Rate, cfm x Release Rate = Corrected Release Rate Assumed Flow Rate, cfm
( cfm) Ci Ci x - =
( cfm) s s D. ESTIMATE OF GROSS RELEASE RATE NOTE: The combined air ejector decay duct exhausts through the auxiliary building vent. Should a release occur through the combined air ejector duct, do NOT include its monitor reading in the gross release rate calculations because it will be reflected in the auxiliary building vent monitor reading.
Release Rate Vent (curies/s)
- 1. Auxiliary Building
- 2. Drumming Area
- 3. Gas Stri per Building
- 4. Combined Air Ejector Duct
- 5. Main Steam Line Vent
- 6. Unit I Containment Purge
- 7. Unit 2 Containment Purge
- 8. Steam Driven AFW Pump
- 9. Total Completed By: Date/Time l Route to Dose/PAR Coordinator upon completion.
Page 26 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS a
5.5.2 Determination of X/Q, Atmospheric Dispersion Factor (Worksheet 2)
- a. Obtain the following information from the indicated source and enter this in the appropriate space on Worksheet 2.
Data Source Wind speed (mph, 15-minute PPCS or average) Control Room Instrumentation
- . Wind direction (degrees, PPCS or.
15-minute average) Control Room Instrumentation
- Wind direction fluctuation PPCS or (cao, degrees) Control Room Instrumentation
- Temperature lapse rate PPCS or (AT/AH, 0F/35 m) Control Room Instrumentation
- Time of reactor shutdown Operations Coordinator
- Time of RCS breach Operations Coordinator
- Time of release from the plant Operations Coordinator NOTE: Realistic estimates of the duration of the release should be made whenever possible, with input from the Reactor/Core Physics Engineer. If the duration of the release is unknown, assume four hours.
- Estimated or actual duration Operations Coordinator or of the release (hours) projected estimate
- Gross release rate Worksheet I (curies/second)
Page 27 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS WORKSHEET 2 X/Q DETERMINATION Complete this form every two hours during a release or whenever changing radiological or meteorological conditions.
- 1. Wind speed, 15 minute average, mph
- 2. Wind direction, 15 minute average, degrees
- 3. Wind direction fluctuation, 0, degrees
- 4. Temperature lapse rate, AT/XH, F/35 m
- 5. Time of reactor shutdown
- 6. Time of RCS breach
- 7. Time of release from plant NOTE: Realistic estimates should be used whenever possible. If the duration release is unknown, assume four hours.
- 8. Estimated or actual duration of release, hours
- 9. Gross release rate, curies per second
- 10. Pasquill category
- 11. Centerline Xu/Q from Table 6:
Site Boundary Two Miles Five Miles Ten Miles Other x sec sec- mi xu 1 1 hr
-()-h2.24r( n x-( x (-)
Q m hr-m Q m wind speed mi
- 12. Centerline X/Q:
Site Boundary Two Miles Five Miles Ten Miles Other Completed By: Date/Time /
Route to Dose/PAR Coordinator upon completion.
Page 28 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS NOTE: Do NOT use so to determine the stability class when the wind speed is less than three miles per hour.
- b. Determine the stability class (Pasquill category) using the co or AT/AH chart recorder values in the Control Room and Table 4. Enter the stability class on Worksheet 2.
TABLE 4 CLASSIFICATION OF ATMOSPHERIC STABILITY BY SIGMA THETA AND AT/AH NOTE: When wind speed is less than three miles per hour, do NOT use 0 to determine the stability class.
Wind Direction Temperature Lapse Fluctuation Rate Stability Classification Pasquill Class (co, degrees) (AT/AH, 0 F/35 m)
Extremely unstable A c0o 22.5° AT/AH < -1.2 Moderately unstable B 22.5° > co 17.5° -1.2 < AT/AH * -1.1 Slightly unstable C 17.50> c00 12.50 -1.1 < AT/AH * -0.9 Neutral D 12.50 > 0so 7.50 -0.9 < AT/AH < -0.3 Slightly stable E 7.50 > co 3.80 -0.3 <AT/AH 0.9 Moderately stable F 3.80 > yo 2.10 0.9 < AT/AH
- 2.5 Extremely stable G 2.10 > 0 2.5 < AT/AH Determined for a 15-minute to one-hour period for horizontal diffusion.
Page 29 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS
- c. IF necessary to determine the backup stability class determination, THEN visually check the cloud cover and the incoming solar radiation.
Using this visual information and Table 5, enter the stability class on Worksheet 2.
TABLE 5 BACKUP DETERMINATION OF ATMOSPHERIC STABILITY CLASS Surface Wind Speed (U mph @ 50 meter DAY NIGHT height) Incoming Solar Radiation Thinly Overcast Strong Moderate Slight > 1/2 low < /2cloud U<4 A A-B B F G 4<U<7 A-B B C E F 7<U< 11 B B-C C D E 11 <U< 13 C C-D D D D 13*1 % low and < V2 cloud" refers to the percentage of cloud or sky overcast.
NOTE: To determine if there is lake effect wind, compare the wind direction at the inland tower to the wind direction at the main or backup tower. If the wind direction at the main or backup tower is easterly and the wind direction at the inland tower is westerly, the wind at the plant may be a lake effect breeze. If a lake breeze is suspected, the field monitoring teams must be advised to pay close attention to the wind direction.
- d. Enter the Xu/Q values for the site boundary, two miles, five miles, and ten miles from the site on Worksheet 2. The Xu/Q values can be taken from Table 6.
Page 30 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROC JRES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATIONS November 26, 2003 TABLE 6 TABLE OF CENTERLINE Xu/Q VALUES VERSUS DISTANCE FROM THE SITE (Units are m 2)
NOTE: To calculate the atmospheric dispersion factor, the centerline Xu/Q value is divided by the wind speed (in meters per second).
Distance From the Site (miles)
Stability Class Site Boundary 2 3 4 5 6 7 8 9 10 A 4.43E-07 5.53E-08 3.93E-08 3.07E-08 2.54E-08 2.17E-08 1.90E-08 1.69E-08 1.53E-08 1.40E-08 B 4.99E-06 7.83E-07 1.92E-07 6.93E-08 3.2 1E-08 2.76E-08 2.42E-08 2.17E-08 1.96E-08 1.80E-08 C 1.911E-05 5.8 1E-06 2.94E-06 1.77E-06 1.21E-06 8.82E-07 6.90E-07 5.66E-07 4.72E-07 3.95E-07 D 5.9913-05 2.14E-05 1.17E-05 7.61E-06 5.48E-06 4.22E-06 3.39E-06 2.80E-06 2.37E-06 2.05E-06 E 1.14E-04 4.32E-05 2.47E-05 1.67E-05 1.24E-05 9.64E-06 7.79E-06 6.54E-06 5.70E-06 5.06E-06 F 2.40E-04 9.86E-05 5.9 1E-05 4.12E-05 3.12E-05 2.49E-05 2.08E-05 1.78E-05 1.55E-05 1.37E-05 G 4.65E-04 2.21E-04 1.36E-04 9.56E-05 7.30E-05 5.89E-05 4.94E-05 4.24E-05 3.72E-05 3.3 lE-05 Lake Breeze 4.5413-05 2.35E-05 1.31E-05 1.02E-05 8.37E-06 7.07E-06 6.33E-06 5.74E-06 5.1 lE-06 4.75E-06 Page 31 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS
- e. IF a possible location other than the standard specified location is wanted, THEN enter the Xu/Q value for that distance from Table 6 on Worksheet 2.
Example:
The Xu/Q value for Class C stability @ 5 miles is 1.21E-06 n 2 . Calculate the X/Q values by dividing the XuIQ value by the wind speed (in meters per second). This can be represented by the equation:
X sec) =2.24 (sec- mile Zu/Q (rn 2 )
Q mn hr- n Wind Speed (miles/hr)
Enter the X/Q values on Worksheet 2.
- f. Sign and date Worksheet 2 and fax upon completion to the Dose/PAR Coordinator.
5.5.3 Whole Body Estimate (Worksheet 3)
- a. Enter the accident type on Worksheet 3. If the accident type is unknown, assume the accident type is a LOCA.
- b. Enter the gross release rate from Worksheet 2, Item 9, on Worksheet 3.
NOTE: The activity fractions are dependent on the accident type, the time from shutdown, whether containment spray was used, and, for steam generator tube rupture accidents, whether the release was through the condenser. Select only those activity fractions that are bolded.
- c. Enter the activity fractions on Worksheet 3 for the selected accident type.
Activity fractions are listed in Table 7.
- d. Enter the X/Q value for the desired distance from Worksheet 2, Item 12, on Worksheet 3.
Page 32 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS WORKSHEET 3 ESTIMATED WHOLE BODY DOSE Complete this form every two hours during a release or whenever changing radiological or meteorological conditions.
Accident type: LOCA Gap Activity Fuel Handling SG Tube Rupture Other Calculate the projected whole body dose using the equation: SECTOR DISTANCE miles Dosei = Q x F x-x DCFi x ERD Q TIME where: Dosei is the whole body dose due to radionuclide i, rem; Q is the gross release rate, curies/s.
F' is the activity fraction for radionuclide i, dimensionless. Activity fractions for radionuclides released in the LOCA, Gap Activity, Fuel Handling, and Steam Generator Tube Rupture accident types are listed in Table 7. The activity fractions for those radionuclides that contribute more than 90 percent of the total dose are printed in bold type. Those radionuclides that are NOT printed in bold type need NOT be included in the dose calculations.
XIQ is the atmospheric dispersion factor, s/M3 ;
DCF is the whole body dose conversion factor for the radionuclide i, rem-m3 /Ci-hr; ERD is the estimated duration of the release, hours. (If unknown, assume 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.)
Nuclide Q Fi X/Q DCF, ERD Dose, 1-131 5.3E+04 1-132 4.9E+04 1-133 1.5E+04 I-134 3.1E+04 1-135 8.IE+03 Kr-85 1.3E+00 Kr-85m 9.3E+01 Kr-87 5. 1E+02 Kr-88 1.3E+03 Rb-88 5.2E+02 Cs-138 1.6E+03 Xe-131r 4.9E+00 Xe-133 2.0E+01 Xe-133m 1.7E+01 Xe-135 1.4E+02 Xe-135m 2.5E+02 Xe-138 7.2E+02 Total Dose NOTE: Dose at other distances can be calculated by ratioing the X/Q values and multiplying by the dose calculated above.
Completed By: Date/Time_ A Route to Dose/PAR Coordinator upon completion.
Page 33 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS
- e. Enter the estimated release duration (ERD), in hours, from Worksheet 2, Item 8, on Worksheet 3.
- f. Calculate the projected whole body (WB) dose on Worksheet 3 using the equation:
Dosei. whoLboy = QxF x x DCR x ERD Q
where:
Dosei, whole bdy = whole body dose, rem; F, - activity fraction for radionuclide i, dimensionless. Activity fractions for radionuclides released in the LOCA, Gap Activity, Fuel Handling, and Steam Generator Tube Rupture accident types for various time periods post accident are listed in Table 7. The activity fractions for those radionuclides that contribute more than 90 percent of the total dose are bolded. Those radionuclides that are NOT bolded need NOT be included in the dose calculations.
Q = gross release rate, curies per second; X/Q = atmospheric dispersion factor, seconds perm; DCF1 = whole body dose conversion factor for nuclide i, rem-m 3 /Ci-hr; ERD estimated duration of the release, hours.
- g. Sum the calculated doses and enter it on Worksheet 3.
- h. Sign and date Worksheet 3 and fax to the Dose/PAR Coordinator.
5.5.4 Thyroid Dose Estimate (Worksheet 4)
NOTE: If the type of accident is unknown, then assume the accident type is a LOCA.
- a. Enter the accident type on Worksheet 4.
Page 34 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS WORKSHEET 4 ESTIMATED THYROID DOSE Complete this form every two hours during a release or whenever changing radiological or meteorological conditions.
Accident type: LOCA Gap Activity Fuel Handling SG Tube Rupture Other Calculate the projected whole body dose using the equation: SECTOR DISTANCE miles Dose =Q x Fi x X xDCFi x ERD Q TIME -
where: Dose, is the thyroid dose due to radionuclide i, rem; Q is the gross release rate, curies/s.
F, is the activity fraction for radionuclide i, dimensionless. Activity fractions for radionuclides released in the LOCA, Gap Activity, Fuel Handling, and Steam Generator Tube Rupture accident types are listed in Table 7. The activity fractions for those radionuclides that contribute more than 90 percent of the total dose are underlined. Those radionuclides that are NOT underlined need NOT be included in the dose calculations.
X/Q is the atmospheric dispersion factor, s/in3 ;
DCF is the whole body dose conversion factor for the radionuclide i, rem-m 3 /Ci-hr; ERD is the estimated duration of the release, hours. (If unknown, assume 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.)
Nuclide Q F, X/Q DCF, ERD Dose, 1-131 _______
_.3E 1___+06 1-132 7.7E+03 I-133 2.2E+05 I-134 1.3E+03 1-135 3.8E+04 Total Dose NOTE: Dose at other distances can be calculated by ratioing the X/Q values and multiplying by the dose calculated above.
Completed By: Date/Time l Route to Dose/PAR Coordinator upon completion.
Page 35 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS
- b. Enter the gross release rate from Worksheet 2, Item 9, on Worksheet 4.
NOTE: The activity fractions are dependent on the accident type, the time from shutdown, whether containment spray was used, and, for steam generator tube rupture accidents, whether the release was through the condenser. Select only those activity fractions that are underlined.
- c. Enter the activity fractions on Worksheet 4 for the selected accident type.
Activity fractions are listed in Table 7.
- d. Enter the X/Q value for the desired distance from Worksheet 2, Item 12, on Worksheet 4.
- e. Enter the estimated duration of the release (ERD), in hours, from Worksheet 2, Item 8, on Worksheet 4.
- f. Calculate the projected thyroid dose on Worksheet 4 using the equation:
Dosei.thyroid Q x Fi x Xx DCFi x ERD Q
where:
Dosei. thyroid = thyroid dose, rem; Q = release rate for nuclide i, curies per second; F1 activity fraction for radionuclide i, dimensionless. Activity fractions for radionuclides released in the LOCA, Gap Activity, Fuel Handling, and Steam Generator Tube Rupture accident types for various time periods post accident are listed in Table 7. The activity fractions for those radionuclides that contribute more than 90 percent of the total dose are underlined. Those radionuclides that are NOT underlined need NOT be included in the dose calculations.
X/Q = atmospheric dispersion factor, seconds per m; DCF 1 = thyroid dose conversion factor for nuclide i, rem-m 3 /Ci-hr; ERD - estimated duration of the release, hours.
Page 3of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS
- g. Sum the calculated doses and enter it on Worksheet 4.
- h. Sign and date Worksheet 4 and fax to Dose/PAR Coordinator.
5.5.5 Radionuclide Ground Deposition Estimation (Worksheet 5)
NOTE: If the type of accident is unknown, then assume the accident type is a LOCA.
- a. Enter the accident type on Worksheet 5.
- b. Enter the gross release rate from Worksheet 2, Item 9, on Worksheet 5.
NOTE: The activity fractions are dependent on the accident type, the time from shutdown, whether containment spray was used, and, for steam generator tube rupture accidents, whether the release was through the condenser. Select only those activity fractions that are bolded.
- c. Enter the activity fractions on Worksheet 5 for the selected accident type.
Activity fractions are listed in Table 7.
- d. Enter the X/Q value from Worksheet 2, Item 12, for the desired distance on Worksheet 5.
- e. Enter the estimated release duration (ERD), in hours, from Worksheet 2, Item 8, on Worksheet 5.
Page 37 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS WORKSHEET 5 ESTIMATED GROUND DEPOSITION Complete this form every six hours during a release or whenever changing radiological or meteorological conditions.
Accident type: LOCA Gap Activity Fuel Handling SG Tube Rupture Other Calculate the projected ground deposition using the equation: SECTOR DISTANCE miles Dep, = Q x F, x x Vel x ERD x 3600 Q TIME where: Dep. is the deposition of radionuclide i, curies/m 2 ;
Q is the gross release rate, curies/s.
F, is the activity fraction for radionuclide i, dimensionless. Activity fractions for radionuclides released in the LOCA, Gap Activity, Fuel Handling, and Steam Generator Tube Rupture accident types are listed in Table 7.
XIQ is the atmospheric dispersion factor, s/m 3; Veli is the deposition velocity for radionuclide i, m/s; ERD is the estimated duration of the release, hours. (If unknown, assume 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.)
3600 is the factor to convert hours to seconds.
Nuclide Q F, X/Q Vell ERD Dep _
I-131 0.01 1-132 0.01 I-133 0.01 I-134 0.01 1-135 0.01 Rb-88 0.001 Cs-138 0.001 Total Dose NOTE: Deposition at other distances can be calculated by ratioing the X/Q values and multiplying by the deposition calculated above.
Completed By: Date/Time l Route to Dose/PAR Coordinator upon completion.
Page 38 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS
- f. Calculate the ground deposition values using the equation:
Dep, = Q x E x X Veli x ERD x 3600 Q
where:
Dep, = deposition of radionuclide i, curies per meter';
Q = gross release rate, curies per second; F1 - activity fraction for radionuclide i, dimensionless. Activity fractions for radionuclides released in the LOCA, Gap Activity, Fuel Handling, and Steam Generator Tube Rupture accident types for various time periods post accident are listed in Table 7.
X/Q = atmospheric dispersion factor, seconds per m; Vell = deposition velocity of radionuclide i, 0.01 n/s for radioiodines and 0.001 m/s for all other radionuclides; ERD = estimated duration of the release, hours; 3600 = factor to convert hours to seconds.
- g. Sum the calculated depositions and enter it on Worksheet 5.
- h. Sign and date Worksheet 5 and fax to the Dose/PAR Coordinator.
5.5.6 Population Exposure (Worksheet 6)
- a. Calculate the projected population dose by using Worksheet 6.
- b. Enter the centerline whole body dose from Worksheet 3, on Worksheet 6.
- c. Enter the population figures. Use the population numbers for the sector and distance categories used in the dose calculations.
Page 39of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS WORKSHEET 6 ESTIMATED POPULATION DOSE Complete this form using the calculation from Worksheet 3.
Complete this form every six hours during a release or whenever changing radiological or meteorological conditions.
Calculated Population Dose Population dose (in person-rem) = Dose (in rem) X Population Distance Dose Population Dose Sector (miles) Population (rem) (person-rem) 2 5
10 Total Dose Population Figures (By Sector and Distance)
- Distance Sector 0 to 2 miles 2 to 5 miles 5 to 10 miles A 0 20 231 H 33 45 0 i 19 231 6036 K 22 131 4866 L 15 606 879 M 32 980 632 N 39 403 695 P 29 345 450 Q 41 286 416 R 22 87 435 NOTE: All other sectors have zero population.
Completed By: Date/Time l-Route to Dose/PAR Coordinator upon completion.
Page 40 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS
- d. Sum the population doses calculated for each radius to calculate the total population dose.
- e. Sign and date Worksheet 6 and fax to the Dose/PAR Coordinator.
5.5.7 Determine Protective Action Recommendations NOTE: Lake breeze conditions exist if the difference between actual wind direction values for inland and near shore meteorological towers is greater than 900.
- a. To determine protective action recommendations, evaluate the calculation results with the values in the "Integrated Projected Dose" column below.
NOTE: In some cases (e.g., short-duration puff release, inclement weather), sheltering may be an appropriate recommendation.
This should be discussed with the state and/or counties, if appropriate.
INTEGRATED PROTECTIVE MILES SECTORS PROJECTED DOSE ACTION
<5 rem CDE at I mile Required N/AN/A
>1 rem TEDE at I mile Evacuate 0-2 Miles All (3600)
>5 rem CDE at 1 mile Evacuate 2-5 Miles Downwind Sectors
<3 mph Wind Speed OR Lake Breeze Evacuate 0-5 Miles All (3600)
AND
>1 rem TEDE at 5 miles Evacuate 0-5 Miles All (3600 OR
>5 rem CDE at 5 miles Evacuate 5-10 Miles Downwind Sectors
<3 mph Wind Speed OR Lake Breeze Evacuate 0-10 Miles All (3600)
AND
- b. Select downwind sectors using Attachment A.
Page 41 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS 5.5.8 IF a General Emergency, THEN evaluate Attachment B for the potential need to issue expanded PARs.
5.5.9 Compare the results against the current classification and PARS.
IF the results of this assessment is an escalation of classification and/or PARS, THEN immediately inform the Emergency Director and assist with EPIP 2.1 for initiating notifications.
Performed By:
Performer (Print and Sign) Date / Time Page 42 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCL JRES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATIONS November 26, 2003 TABLE 7 LOCA SOURCE TERM ACTIVITY FRACTIONS - CONTAINMENT SPRAY NOT USED Page I of 8 Time 1-131 1-132 1-133 1-134 1-135 Kr-85 Kr-85m Kr-87 Kr-88 Rb-88 Cs-138 0.0 2.46F.02 3.52E-02 5.51E-02 6.42E-02 5.1013-02 0.001 0.043 0.083 0.117 0.000 0.000 0.5 2.75E-02 3.40E-02 6.07E.02 4.821-02 SA3E-02 0.001 0.044 0.071 0.116 0.084 0.057 1.0 3.08E-02 3.25E.02 6.70E.02 3.61 E-02 5.791302 0.001 0.046 0.061 0.115 0.113 0.053 1.5 3.40E-02 3.09E-02 7.27E.02 2.6913-02 6.0813-02 0.001 0.047 0.051 0.112 0.120 0.037 2.0 3.69E.n2 2.88E.02 7.80E.02 1.9613-02 6.27E-02 0.001 0.047 0.042 0.108 0.119 0.024 2.5 3.96F.02 2.6613-02 8.24F .02 1.41 E-02 6.3913-02 0.001 0.047 0.035 0.103 0.114 0.014 3.0 4.20E-02 2.4213-02 8.58.02 1.0 IE-02 6A3E-02 0.001 0.046 0.028 0.097 0.108 0.008 4.0 4.6313.02 1.9713-02 9.19E.02 4.9913-03 6.4213-02 0.001 0.043 0.018 0.083 0.093 0.003 5.0 5.00E-02 1.571E-02 9.64E.02 2.4413-03 6.27E.02 0.002 0.040 0.011 0.070 0.079 0.001 6.0 5.33E-02 1.2413-02 9.97E.02 1.1713-03 6.07E-02 0.002 0.037 0.007 0.059 0.066 0.000 7.0 5.6213-02 9.6513-03 1.0213.01 5.5813-04 5.7913-02 0.002 0.033 0.004 0.049 0.054 0.000 8.0 5.90E.02 7.4713-03 1.03E.01 2.6413-04 5A9E-02 0.002 0.030 0.003 0.040 0.045 0.000 9.0 6.13E.02 5.73E-03 1.05E.01 1.2413-04 5.16E02 0.002 0.027 0.002 0.033 0.036 0.000 10.0 6.i35.-02 4.3913-03 1.05F3.01 5.8013-05 4.8413-02 0.002 0.024 0.001 0.026 0.030 0000 12.0 6.74E-02 2.5413-03 1.04E-01 1.2513-05 4.2013-02 0.002 0.018 0.000 0.017 0.019 0.000 18.0 7.60E.02 4.64E.04 9.811E.02 1.1913-07 2.5913-02 0.003 0.008 0.000 0.004 0.005 0.000 24.0 8.19E3.02 8.111E-05 8.82F.02 1.0813-09 1.5313-02 0.003 0.004 0.000 0.001 0.001 0000 30.0 8.651.02 1.391-05 7.76E.02 0.000 8.8813-03 0.003 0.001 0.000 0.000 0.000 0.000 36.0 9.02E-02 2.3613-06 6.73E.02 0.000 5.0813-03 0.003 0.001 0.000 0.000 0.000 0.000 42.0 9-34E-02 3.9613-07 5.811E-02 0.000 2.88E-03 0.003 0.000 0.000 0.000 0.000 0.000 48.0 9.60E.02 6.6013-08 4.9713-02 0.000 1.621E-03 0.004 0.000 0.000 0.000 0.000 0.000 72.0 1.04E-01 0.000 2.5813-02 0.000 1.5913-04 0.004 0.000 0.000 0.000 0.000 0.000 96.0 1.10E-1 0.000 1.31 E-02 0.000 1.5 1E-05 0.005 0.000 0.000 0.000 0.000 0.000 120.0 1.15E-01 0.000 6.58E-03 0.000 1.4313-06 0.005 0.000 0.000 0.000 0.000 0.000 144.0 1.20E-01 0.000 3.30E-03 0.000 1.35E-07 0.006 0.000 0.000 no 0.000 0.000 168.0 1.25E-01 0.000 1.6513-03 0.000 1.2713-08 0.007 0.000 0.000 0.000 0.000 0.000 336.0 1.63E-01 0.000 1.2813-05 0.000 0.000 0.017 0.000 0.000 0.000 0.000 0.000 504.0 2.06E.01 0.000 9.4913-08 0.000 0.000 0.039 0.000 0.000 0.000 0.000 0.000 672.0 2.49E.01 0.000 0.000 0.000 0.000 0.086 0.000 0.000 0.000 0.000 0.000 720.0 2.60E.01 0.000 0.000 0.000 0.000 0.106 0.000 0.000 0.000 0.000 0.000 Notes: 1. The activity fractions that are NOT highlighted contribute less than ten percent of the whole body dose.
- 2. The activity fractions that are NOT underlined contribute less than ten percent of the thyroid dose.
- 3. Radionuclides that do NOT appear in the table contribute less than ten percent of the whole body and thyroid dose totals.
Page 43 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROC. JRES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATIONS November26, 2003 TABLE7 LOCA SOURCE TERM ACTIVITY FRACTIONS - CONTAINMENT SPRAY USED Page 2 of 8 1-133 Kr-87 Kr-88 - Xe-133 Xe-135 Xe-135m Xe-138 Rb-88 Cs 138
'ime 1.131 7.161-06 1.08E01 1.52E.01 2.85E-01 6.08E-02 7.73E-02 2.52E-01 0.00 0.00 0.0 3.19E-06 7.82E-06 9.17E02 .50E-01 3.17E-01 6.92E-02 3.86E-02 8.57E-02 1.09E-01 734E-02 0.5 3.5E-06 6.84E-02 1.0 3 97E 06 8.64E-06 7.84E-02 1.48E-01 3.552-0 1 7.802-02 2.8 1E-02 2.93E-02 1A6E-01 4.39E-06 9.38E-06 6.60E-02 1A5E-O1 3.92E-01 8.64E-02 2.59E-02 9.90E-03 1.55E-01 4.83E-02 1.5 4.77E-06 1.01 E-05 5.47E-02 1.40E01 4.262-01 9.36E-02 2.57E-02 3.301:-03 1.54E-01 3.04E.02 2.0 5.12E-06 1.072-05 4A8E-02 133E.01 4.57E-01 1.OOE-01 2.59E-02 1.082-03 I .47E-01 1.80E-02 2.5 5.43E-06 I.IIE.05 3.62E-02 1.25E.01 4.85E-01 1.06E-01 2.602-02 3.5 1E-04 1.39E-01 1.032-02 3.0 5.99E-06 1.19E-05 2.32E-02 1.07E.01 5.34E01 1.15E-01 2.602-02 3.61 E-05 1.20E-01 3.24E-03 4.0 6.47E-06 1.25E-05 1.46E-02 9.08E.02 5.77E-01 1.22E-01 2.54E-02 3.65E-06 1.02F-01 9.70E04 5.0 6.0 6.89E-06 1.29E-05 9.04E-03 7.63E-02 6.14E-01 1.27E-01 2.45E-02 3.632-07 8.52E-02 2.872-04 7.26E-06 1.32E-05 5.54E-03 6.26E-02 6.47E-01 1.30E-01 233E-02 0.00 7.03E-02 8.39E-05 7.0 7.61E-06 1.342-05 3.37E-03 5.15E-02 6.77E-01 1.32E.01 2.21E-02 0.00 5.76E.02 2.41E-05 8.0 6.93E-06 9.0 7.90E-06 1.35-05 2.03E-03 4.19E-02 7.02E-01 1.33E.01 2.08E-02 0.00 4.69E-02 10.0 8.162-06 1.34E-05 1.222-03 3.39E.02 7.25E-01 133E.01 1.94E.02 0.00 3.79E-02 1.98E-06 8.60E-06 1.33E-05 4.36E-04 2.19E-02 7.63E01 1.30E-01 1.67E-02 0.00 2.46E-02 1.59E-07 12.0 9.50E-06 1.23E-05 1.862-05 5.61E-03 8.37E-01 1.09E01 1.011E-02 0.00 6.27E-03 0.00 18.0 24.0 1.01 E-05 1.08E-05 7.60E-07 1.37E-03 8.81E-01 8.41E-02 5.88E-03 0.00 1.53E-03 0.00 1.05E-05 9.38E 06 3.05E-08 3.3 1E-04 9.10E-01 6.22E-02 3.352-03 0.00 3.702-04 000 30.0 1.08E-05 8.04E-06 0.00 7.89E-05 9.30E-01 4.45E-02 1.90E03 0.00 8.8 1E-05 0.00 36.0 42.0 I . O05 6.87E-06 0.00 1.872-05 9.45E-01 3.14E-02 1.06E-03 0.00 2.1 OE-05 0.00 48.0 1.132-05 5.83E-06 0.00 4.41E-06 9.56E-01 2.17E-02 5.94E-04 0.00 4.932-06 0.00 72.0 1 20E-05 2.96E-06 00 1.342-06 9.75E01 4.53E-03 5.70E-05 0.00 0.00 0.00 96.0 1.25E-05 1.492-06 0.00 0.00 9.80E-01 8.84E-04 5.38C-06 0.00 0.00 0.00 1.31 E-05 7.492-07 0.00 0.00 9.82E-01 1.67E-04 5.08E-07 0.00 0.00 0.00 120.0 144.0 I.37E t)5 3.77E-07 0.00 0.00 9.83E01 3.14E-05 0.00 0.00 0.00 0.00 168.0 1.43E-05 0.00 0.00 0.00 9.83E.01 5.84E-06 0.00 0.00 0.00 0.00 336.0 1.95E-05 0.00 0.00 0.00 9.75E-01 0.00 0.00 0.00 0.00 0.00 504.0 2.592-05 0.00 0.00 0.00 9.46E-01 0.00 0.00 0.00 0.00 0.00 672.0 3.32E-05 0.00 0.00 0.00 8.78E-01 0.00 0.00 0.00 0.00 0.00 720.0 3.51 E-05 0.00 0.00 0.00 8.48E-01 0.00 0.00 0.00 0.00 0.00 Notes: 1. The activity fractions that are NOT highlighted contribute less than ten percent of the whole body dose.
- 2. The activity fractions that are NOT underlined contribute less than ten percent of the thyroid dose.
- 3. Radionuclides that do NOT appear in the table contribute less than ten percent of the whole body and thyroid dose totals.
Page 44 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROC. JRES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATIONS November 26, 2003 TABLE 7 GAP ACTIVITY RELEASE SOURCE TERM ACTIVITY FRACTIONS - CONTAINMENT SPRAY NOT USED Page 3 of 8
'rime 1.131 1.11 1 5 KrRi5m Kr-87 Kr-88 Xe-133 Xe-135 Xe-138 Rb-88 Cs- 138 0.0 634E-04 1.42E-03 1.31 E-03 0.055 0.108 0.151 0.284 0.060 0.250 0.000 0.000 0.5 7.1XE-04 I.58E-03 1.41E-03 0.057 0.093 0.151 0.322 0.067 0.086 0.110 0.074 1.0 8.11E-04 1.76E-03 1.51 E-03 0.060 0.080 0.151 0.361 0.074 0.030 0.148 0.069 1.5 9.0 1E-04 1.92E03 1.60E-03 0.062 0.068 0.149 0.402 0.080 0.010 0.159 0.049 2.0 9.82E-04 2.07E-03 1.66E03 0.062 0.056 0.144 0.439 0.084 3.38E-03 0.158 0.031 2.5 1.06E03 2.20E-03 1.71E-03 0.062 0.046 0.137 0.471 0.088 1.12E-03 0.153 0.019 3.0 1.13E-03 2.31E-03 1.73E-03 0.062 0.038 0.129 0.502 0.090 3.63E-04 0.144 0.011 4.0 1.25E.03 2.48E-03 1.73E.03 0.058 0.024 0.112 0.558 0.093 3.75E-05 0.125 0.003 5.0 136E-03 2.62E-03 1.70E-03 0.055 0.015 0.096 0.605 0.094 3.82E-06 0.107 0.001 6.0 1.46E-03 2.73E-03 1.66E.03 0.050 0.010 0.081 0.646 0.094 3.84E-07 0.090 0.000 7.0 I .55E-03 2.79E-03 1.58E-03 0.045 0.006 0.067 0.685 0.093 0.000 0.075 0.000 8.0 163E.03 2.85E-03 1.50E-03 0.041 0.004 0.055 0.717 0.091 0.000 0.062 0.000 9.0 1.69E.03 2.87E.03 1.41 E-03 0.037 0.002 0.045 0.747 0.088 0.000 0.050 0.000 10.0 1.75-03 2.89E-03 1.33E-03 0.033 0.001 0.036 0.772 0.085 0.000 0.041 0.000 12.0 1.85E03 2.87E-03 1.15E-03 0.025 0.000 0.024 0.813 0.078 0.000 0.026 0.000 18.0 2.05E-03 2.65E.03 6.96E-04 0.011 0.000 0.006 0.885 0.056 0.000 0.007 0.000 24.0 2.15E-03 2.31E.03 3.99E-04 0.005 0.000 0.001 0.919 0.038 0.000 0.002 0.000 30.0 2.21 E-03 1.97E-03 2.26E-04 0.002 0.000 0.000 0.937 0.026 0.000 0.000 0.000 36.0 2.26E-03 1.69E203 1.27E-04 0.001 0.000 0.000 0.948 0.017 0.000 0.000 0.000 42.0 230E-03 1.42E-03 7.06E-05 0.000 0.000 0.000 0.955 0.011 0.000 0.000 0.000 48.0 2-33E-03 1.21E-03 3.94E-05 0.000 0.000 0.000 0.959 7.47E-03 0.000 0.000 0.000 72.0 2.46E-03 6.09E-04 3.75E-06 0.000 0.000 0.000 0.967 1.40E-03 0.000 0.000 0.000 96.0 2.56E-03 3.07E-04 3.53E-07 0.000 0.000 0.000 0.968 2.592-04 0.000 0.000 0.000 120.0 2.68E.03 1.54E-04 3.34E-08 0.000 0.000 0.000 0.968 4.81 3-05 0.000 0.000 0.000 144.0 2.80E-03 7.72E-05 3.14E-09 0000 0.000 0.000 0.967 8.85E-06 0.000 0.000 0.000 168.0 2.93E-03 3.86E-05 0.000 0.000 0.000 0.000 0.965 1.63E-06 0.000 0.000 0.000 336.0 3.89E-03 3.03E-07 0.000 0.000 0.000 0.000 0.933 1.162- 11 0.000 0.000 0.000 504.0 4.91E-03 2.262-09 0.000 0.000 0.000 0.000 0.854 0.000 0.000 0.000 0.000 672.0 5.57E-03 0.000 0.000 0.000 0.000 0.000 0.704 0.000 0.000 0.000 0.000 720.0 5.62E-03 0.000 0.000 0.000 0.000 0.000 0.649 0.000 0.000 0.000 0.000 Notes: 1. The activity fractions that are NOT highlighted contribute less than ten percent of the whole body dose.
- 2. The activity fractions that are NOT underlined contribute less than ten percent of the thyroid dose.
- 3. Radionuclides that do NOT appear in the table contribute less than ten percent of the whole body and thyroid dose totals.
Pagc 45 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROC. JRES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATIONS November 26, 2003 TABLE 7 GAP ACTIVITY RELEASE SOURCE TERM ACTIVITY FRACTIONS - CONTAINMENT SPRAY USED Page 4 of 8 Time 1-131 1.133 Kr-87 Kr-88 Xe-133 Xe.135 Xe.138 Rb-8R CS-uS8 0.0 6.38E-08 1.43E-07 1.08E-01 1.52E-01 2.86E-01 6.06E-02 251E01 0.00 0.00 0.5 7.22-08 1.59E-07 9.31E-02 1.52E-01 3.24E-01 6.7813-02 8.67E.02 1.10-01 7.45E-02 1.0 8.15E-08 1.77E-07 8.03E-02 1.52E.01 3.63E-01 7.46E-02 3.OOE-02 1A9E-01 6.98E-02 1.5 9.06E-08 1.94E-07 6.81E-02 1.50E.01 4.04E-01 8.01E-02 1.02E-02 1.60E.01 4.95E-02 2.0 9.87E-08 2.08E-07 S.65E-02 1.44E-01 4.42E-04 8.45E-02 3.40E-03 1.59E-01 3.13E-02 2.5 1.072-07 2.22E-07 4.66E 02 1.38E-01 4.74E-01 8.81E-02 1.122-03 1.54E-01 1.87E 02 3.0 I .131-07 2.32E-07 3.78E02 1.30E-01 5.05E-01 9.04E-02 3.65E-04 .45E-01 1.08E-02 4.0 1.26E-07 2.49E-07 2.44E02 1.13E-01 5.61E-01 936E-02 3.78E-05 1.26E-01 3.38E-03 5.0 1.37E-07 2.63E-07 1.55E-02 9.64E-02 6.08E-01 9.48E-02 3.84E-06 I.OXE-01 1.03E-03 6.0 1.47E-07 2.75E-07 9.642-03 8.13E-02 6.50E-01 9.46E-02 0.00 9.06E-02 3.05E-04 7.0 1.56E-07 2.81E-07 5.922-03 6.70E-02 6.89E-01 9.35E02 0.00 7.50E-02 8.92E-05 8.0 1.64E-07 2.871-07 3.62E-03 554E.02 7.21FOl 9.16E-02 0.00 6.19E.02 2.59E-05 9.0 1.70E-07 2.89E-07 2.192-03 4.50E-02 7.51E-01 8.87E 02 0.00 5.04E-02 7.45E-06 10.0 1.76E-07 2.91 E-07 1.32E-03 3.66E-02 7.76E-01 8.54E 02 0.00 4.10E-02 2.12E-06
!2.0 1.86E-07 2.89E-07 4.71 E-04 2.37E-02 8.18E-01 7.81E-02 0.00 2.66F,02 0.00 18.0 2.06E-07 2.66E-07 2.022-05 6.07E03 8.90E01 5.65E-02 0.00 6.79E.03 0.00 24.0 2.16E-07 2.32E-07 0.00 IA7E-03 . 9.24E-01 3.85E-02 0.00 1.642-03 0.00 30.0 2.22E-07 1.98E-07 0.00 3.50E-04 9.42E-01 2.58E-02 0.00 3.92E-04 0.00 36.0 2.27e-07 1.69E-07 0.00 8.29E-05 9.52E-01 1.71E-02 0.00 9.26E-05 0.00 42.0 2.3 1E-07 1.43E-07 0.00 1.95E-05 9.59E-01 1.14E-02 0.00 2.18E-05 0.00 48.0 234E-07 1.21E-07 0.00 4.58E-06 9.63E-01 7.50E-03 0.00 5.13E-06 0.00 72.0 2.46E-07 6.1 IE-08 0.00 0.00 9.70E-01 1.402-03 0.00 0.00 0.00 96.0 2.57E-07 3.08E-08 0.00 0.00 9.71E-01 2.60E-04 0.00 0.00 0.00 120.0 2.69E-07 1.54E-08 0.00 0.00 9.71E01 4.82E-05 0.00 0.00 0.00 144.0 2.81E-07 0.00 0.00 0.00 9.70E-01 8.88E-06 0.00 0.00 0.00 168.0 2.94E-07 0.00 0.00 0.00 9.68E-01 1.642-06 0.00 0.00 0.00 336.0 3.90E-07 0.00 0.00 0.00 9.37E-01 0.00 0.00 0.00 0.00 504.0 4.93E-07 0.00 0.00 0.00 8-58E-01 0.00 0.00 0.00 0.00 672.0 5.60E-07 0.00 0.00 0.00 7.08E-01 0.00 0.00 0.00 0.00 720.0 5.65 E-07 0.00 0.00 0.00 652E-01 0.00 0.00 0.00 0.00 Notes: I1. The activity fractions that are NO highlighted contribute less than ten percent of the whole body dose.
- 2. The activity fractions that are NOT underlined contribute less than ten percent of the thyroid dose.
- 3. Radionuclides that do NOT appear in the table contribute less than ten percent of the whole body and thyroid dose totals.
Page 46 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROC. JRES SAFETY RELATED Rcvision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATIONS November 26, 2003 TABLE 7 FUEL HANDLING ACCIDENT SOURCE TERM ACTIVITY FRACTIONS - CONTAINMENT SPRAY NOT USED Page 5 of 8 Time 1-131 1-132 1-133 1-134 1-135 Kr-85 Kr-85m Kr-87 Xe- 33 Rb-88 Cs-138 0.0 2.17E 03 0.000 2.59E-04 0.000 3.03E-07 0.014 0.000 0.000 0.963 0.000 0.000 0.5 2.17E03 0.000 2.55E-04 0000 2.88E-07 0.014 0.000 0.000 0.964 0.000 0.000 1.0 2.17E-03 0.000 2.52E-04 0.000 2.75E-07 0.014 0.000 0.000 0.964 0.000 0.000 1.5 2.17F:-03 0.000 2.48E-04 0.000 2.62E-07 0.014 0.000 0.000 0.964 0.000 0.000 2.0 2.18-03 0.000 2.45E-04 0.000 2.50E-07 0.014 0.000 0.000 0.964 0.000 0.000 2.5 2.18E203 0.000 2.41E-04 0.000 2.37E-07 0.014 0.000 0.000 0.964 0.000 0.000 3.0 2.18F-03 0.000 2.38E-04 0.000 2.25E-07 0.015 0.000 0.000 0.964 0.000 0.000 4.0 2.18E-03 0.000 2.30E-04 0.000 2.05E-07 0.015 0.000 0000 0.964 0.000 0.000 5.0 2.19E-03 0.000 2.24E-04 0.000 1.86E-07 0.015 0.000 0.000 0.964 0.000 0.000 6.0 2.19E-03 0.000 2.18E-04 0.000 1.69E-07 0.015 0.000 0.000 0.964 0.000 0.000 7.0 2.21E-03 0.000 2.12E-04 0.000 1.52E-07 0.015 0.000 0.000 0.964 0.000 0.000 8.0 2.21 E.03 0.000 2.05E-04 0.000 1.38E-07 0.015 0.000 0.000 0.965 0.000 0.000 9.0 2.20E-03 0.000 2.00E-04 0.000 1.25E-07 0.015 0.000 0.000 0.965 0.000 0.000 10.0 2.22F-03 0.000 1.95E-04 0.000 1.13E2-07 0.015 0.000 0.000 0.965 0.000 0.000 12.0 2.22F-03 0.000 1.83E-04 0.000 9.33E-08 0.015 0.000 0.000 0.965 0.000 0.000 18.0 2.25E.03 0.000 1.55E-04 0.000 5.18E-08 0.016 0.000 0.000 0.966 0.000 0.000 24.0 2.27E03 0.000 1.30E-04 0000 2.87E-08 0.016 0.000 0.000 0.966 0.000 0.000 30.0 231-F03 0.000 1.I OE-04 0.000 1.60E-08 0.017 0.000 0.000 0.966 0.000 0.000 36.0 2-32E-03 0.000 9.24E-05 0.000 8.83E-09 0.017 0.000 0.000 0.966 0.000 0.000 42.0 2.35E.03 0.000 7.77E-05 0.000 4.89E-09 0.018 0.000 0.000 0.966 0.000 0.000 48.0 237E 03 0.000 6.53E-05 0.000 2.71E-09 0.019 0.000 0.000 0.966 0.000 0.000 72.0 2.48E-03 0.000 3.28E-05 0.000 0.000 0.021 0.000 0.000 0.965 0.000 0.000 96.0 2.59E.03 0.000 1.64E-05 0.000 0.000 0.024 0.000 0.000 0.963 0.000 0.000 120.0 2.71E-03 0.000 8.24E-06 0.000 0000 0.027 0.000 0.000 0.961 0.000 0.000 144.0 2.82E-03 0.000 4.13E-06 0.000 0.000 0.031 0.000 0.000 0.958 0.000 0.000 168.0 2.94E-03 0.000 2.07E-06 0.000 0.000 0.035 0.000 0.000 0.955 0.000 0 000 336.0 3.84E-03 0.000 1.59E-08 0.000 0.000 0.084 0.000 0.000 0.907 0.000 0.000 504.0 4.66E-03 0.000 0.000 0.000 0.000 0.187 0.000 0.000 0.802 0.000 0.000 672.0 5.00E-03 0.000 0.000 0.000 0.000 0.364 0.000 0.000 0.623 0.000 0.000 720.0 4.92E-03 0.000 0.000 0.000 0.000 0.427 0.000 0000 0.560 0.000 0.000 Notes: 1. The activity fractions that are NOT highlighted contribute less than ten percent of the whole body dose.
- 2. The activity fractions that are NOT underlined contribute less than ten percent of the thyroid dose.
- 3. Radionuclides that do NOT appear in the table contribute less than ten percent of the whole body and thyroid dose totals.
Page 47 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROC. JRES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATIONS November 26, 2003 TABLE 7 FUEL HANDLING ACCIDENT SOURCE TERM ACTIVITY FRACTIONS - CONTAINMENT SPRAY USED Page 6of8 rime 1-131 Xe-133 0.0 2.171-07 9.66E-01 0.5 2.18E-07 9.66E-01 1.0 2.17E-07 9.66E-01 1.5 2.18E-07 9.66E-01 2.0 2.19E-07 9.66E-01 2.5 2.18E-07 9.66E-01 3.0 2.19E-07 9.66E-01 4.0 2.20E-07 9.67E.01 5.0 2.20E-07 9.67E-01 6.0 2.20E-07 9.67E-01 7.0 2.21E-07 9.67E-01 8.0 2.21E-07 9.67E-01 9.0 2.21E-07 9.67E-01 10.0 2.222-07 9.67E-01 12.0 2.22E-07 9.67E-01 18.0 2.26E-07 9.68E-01 24.0 2.282-07 9.68E-01 30.0 2.31 E-07 9.68E01 36.0 2.33E-07 9.68E-01 42.0 2.362-07 9.68E-01 48.0 2.371-07 9.68E.01 72.0 2.492-07 9.68E-01 96.0 2.592-07 9.66E-01 120.0 2.71E-07 9.64E-01 144.0 2.83E-07 9.61E01 168.0 2.94E-07 9.58E-01 336.0 3.85E-0 9.10E-01 504.0 4.68E-07 8.06E-01 672.0 5.02E-07 6.26E 01 720.0 4.94E-07 5.63E-01 Notes: 1. The activity fractions that are NOT highlighted contribute less than ten percent of the whole body dose.
- 2. The activity fractions that are NOr underlined contribute less than ten percent of the thyroid dose.
- 3. Radionuclides that do NOT appear in the table contribute less than ten percent of the whole body and thyroid dose totals.
Page 48 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROC, JRES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATIONS November 26, 2003 TABLE 7 STEAM GENERATOR TUBE RUPTURE SOURCE TERM - - RELEASE MODE - THROUGH THE CONDENSER - ACTIVITY FRACTIONS Page 7 of 8 1-135 Kr-85 Kr-85m Kr-88 Xe-133 Xe-135 Xe-138 Rb-88 Cs-138 rime 1-131 1-133 3.05E-08 3.16E-08 0.933 0.030 0.008 0.011 4.03E2-03 0.013 0.000 0.000 0.0 3.92E-08 0.5 3.93E-08 3.00-08 3.02E-08 0.937 0.028 0.007 0.011 3.90E-03 0.004 4.90E-03 3A3E-03 1.0 3.94E-08 2.98E-08 2.88E-08 0.943 0.026 0.006 0.011 3.77E-03 1.242-03 5.89E-03 2.87E-03 1.5 3.95E-08 2.94E-08 2.75E-08 0.947 0.024 0.005 0.011 3.65E-03 3.78E-04 5.71E-03 1.84E-03 2.0 3.96E-08 2.90E-08 2.61E-08 0.952 0.023 0.005 0.011 3.53E-03 1.16E-04 5.22E-03 1.06E-03 2.5 3.98E-08 2.86E-08 2.502-08 0.955 0.021 0.004 0.011 3.41 E-03 3.55E-05 4.67E-03 5.92E-04 3.0 3.97E-08 2.81 E-08 2.37E-08 0.955 0.019 0.004 0.011 3.28E-03 1.082-05 4.14E.03 3.20E-04 4.0 3.99E-08 2.74E-08 2.15E-08 0.963 0.017 0.003 0.011 3.082-03 1.022-06 3.27E.03 9.062-OS 5.0 3.99E-08 2.66E-08 1.952-08 0.967 0.014 0.002 *0.011 2.86E-03 9.51 E-08 2.56E-03 2.54E-05 6.0 3.98E-08 2.58E-08 1.76-08 0.970 0.012 0.002 0.011 2.662-03 8.892-09 2.01E-03 7.022-06 7.0 3.9913-08 2.501-08 1.59E-08 0.973 0.011 0.001 0.011 2.47E-03 0.00 157E-03 1.94E-06 8.0 3.98E-08 2.42E-08 1.44E-08 0.976 0.009 0.001 0.011 230E-03 0.00 1.23E-03 0.00 9.0 3.9713-08 2.35E-08 1.30E-08 0.978 0.008 0.001 0.010 2.14E-03 0.00 9.61E.04 0.00 10.0 2.27-08 1.18E-08 0.979 0.007 0.001 0.010 1.98E-03 0.00 7.53E.04 0.00 12.0 2.132-08 9.57E-09 0.982 0.005 0.00 0.010 1.71E-03 0.00 4.60E-04 0.00 3.91-08 18.0 1.74E-08 5.17E-09 0.987 0.002 0.00 0.010 1.09E-03 0.00 1.04E-04 0.00 3.89IE-08 1.422-08 2.782-09 0.989 0.001 0.00 9.80E-03 6.92E-04 0.00 2.382-05 0.00 24.0 3.831E-08 0.00 0.00 9.4RE-03 4.39E-04 0.00 5.38E-06 0.00 30.0 1.162-08 1.49E-09 0.990 36.0 3.65E-08 9.48E-09 8.01-E 10 0.990 0.00 0.00 9.24E-03 2.79E-04 0.00 1.222-06 O.0 42.0 3.5812-08 7.72E-09 4.302- 10 0.991 0.00 0.00 8.91E-03 1.77E-04 0.00 0.00 0.00 48.0 3.51 E-08 6.29E-09 0.00 0.991 0.00 0.00 8.66E-03 1.122-04 0.00 0.00 0.00 72.0 3.22E2-08 2.78E-09 0.00 0.992 0.00 0.00 7.57E-03 1.83E-05 0.00 0.00 0.00 96.0 2.951-08 1.23E-09 0.00 0.993 0.00 000 6.642-03 2.962-06 0.00 0.00 0.00 120.0 2.7 1E-08 5.402-10 0.00 0.994 0.00 0.00 5.83E-03 0.00 0.00 0.00 0.00 144.0 2.49E-08 2.382. 10 0.00 0.995 0.00 0.00 5.1 1E-03 0.00 0.00 0.00 0.00 168.0 2.28E-08 I.051-10 0.00 0.996 0.00 0.00 4.482-03 0.00 0.00 0.00 0.00 336.0 1.262-08 3.402-13 0.00 0.998 0.00 0.00 1.79E-03 0.00 0.00 0.00 0.00 504.0 6.87E-09 0.00 0.00 0.999 0.00 0.00 7.09E-04 0.00 0.00 0.0 0.00 672.0 3.802-09 0.00 0.00 1.000 0.00 0.00 2.84E-04 0.00 0.00 0.00 0.00 720.0 3.192-09 0.00 0.00 1.000 0.00 0.00 2.18E-04 0.00 0.00 0.00 0.00 Notes: I. The activity fractions that are NOT highlighted contribute less than ten percent of the whole body dose.
- 2. The activity fractions that are NOT underlined contribute less than ten percent of the thyroid dose.
- 3. Radionuclides that do NOT appear in the table contribute less than ten percent of the whole body and thyroid dose totals.
Page 49 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROC. JRES SAFETY RELATED Rcvision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATIONS November 26, 2003 TABLE 7 STEAM GENERATOR TUBE RUPTURE SOURCE TERM - - RELEASE MODE - NOT THROUGH THE CONDENSER - ACTIVITY FRACTIONS Page 8 of 8 Time 1.11 1-133 1.135 Kr 85 Kr-85m Kr-R8 Xc-133 Xe-135 Xe-138 Rb-88 Cs-138 0.0 3.92E-04 3.05E-04 3.16E-04 0.933 0.030 0.008 0.011 4.03E-03 0.013 0.00 0.00 0.5 3.93E-04 3.00-04 3.01E-04 0.937 0.028 0.007 0.011 3.90E-03 0.004 4.89E-03 3.43E-03 1.0 3.94E-04 2.98E-04 2.87E-04 0.943 0.026 0.006 0.011 3.77E-03 1.24E-03 5.89E.03 2.86E-03 1.5 3.95E-04 2.94E-04 2.74E-04 0.947 0.024 0.005 0.011 3.65E-03 3.78E-04 5.70E203 1.84E-03 2.0 3.96E-04 2.90E-04 2.61E.04 0.952 0.023 0.005 0.011 3.53E-03 1.16-04 5.22E-03 1.06E-03 2.5 3.98F,04 2.86F-04 2A9E-04 0.955 0.021 0.004 0.011 3.412-03 3.55E-05 4.67E-03 5.91E-04 3.0 3.97E-04 2.81E-04 2.37E-04 0.955 0.019 0.004 0.011 3.28E-03 1.08E-05 4.14F-03 3.19E-03 4.0 3.99E-04 2.74E-04 2.15E-04 0.963 0.017 0.003 0.011 3.08E-03 1.02E-06 3.27E-03 9.05E-05 5.0 3.99E-04 2.66E-04 1.95E-04 0.967 0.014 0.002 0.011 2.86E-03 9.512-08 256E-03 2.53E-05 6.0 3.98E-04 2.58-04 1.76F-04 0.970 0.012 0.002 0.011 2.66E-03 8.892-09 2.00E-03 7.01E-06 7.0 3.99E.04 2.50F-04 1.59E-04 0.973 0.011 0.001 0.011 2.47E-03 0.00 1.57E-03 1.94E-06 8.0 3.98E.04 2A2E-04 1.44E-04 0.976 0.009 0.001 0.011 2.30E-03 0.00 1.232-03 0.00 9.0 3.97E-04 2.35E-04 1.30E-04 0.978 0.008 0.001 0.010 2.14E-03 0.00 9.60E-04 0.00 10.0 3.96E.04 2.27E.04 1.18E-04 0.979 0.007 0.001 0.010 1.98E-03 0.00 7.52E-04 0.00 12.0 3.95E-04 2.13E-04 9.57E-05 0.982 0.005 0.00 0.010 1.71E-03 0.00 4.592-04 0.00 18.0 3.89E.04 1.74E-04 5.16E-05 0.987 0.002 000 0.010 1.09E-03 0.00 1.04E-04 0.00 24.0 3.81E-04 1A2E-04 2.77E-05 0.989 0.001 0.00 9.80E-03 6.922-04 0.00 2.37E-05 0.00 30.0 3.73E-04 1.16E-04 1.49E-05 0.990 0.00 0.00 9.48E-03 4.39E-04 0.00 5.38E-06 0.00 36.0 3.65E-04 9.48E-05 8.00E-06 0.990 0.00 0.00 9.24E-03 2.79E-04 0.00 1.22E-06 0.00 42.0 3.58E-04 7.72E-05 4.29E-06 0.991 0.00 0.00 8.91 E-03 1.77E-04 0.00 0.00 0.00 48.0 3.51E-04 6.29E-05 2.31E-06 0.991 0.00 0.00 8.66E-03 1I.12-04 0.00 0.00 0.00 72.0 3.22E.04 2.78E-05 0.00 0.992 0.00 0.00 7.57E-03 1.83E-05 0.00 0.00 0.00 96.0 2.95E-04 1.232-05 0.00 0.993 0.00 0.00 6.64E-03 2.96E-06 0.00 0.00 0.00 120.0 2.71 E-04 5.40E-06 0.00 0.994 0.00 0.00 5.83E-03 0.00 0.00 0.00 0.00 144.0 2.49E.04 2.38E-06 0.00 0.995 0.00 0.00 5.1 E-03 0.00 0.00 0.00 0.00 168.0 2.28E-04 1.05E-06 0.00 0.996 0.00 0.00 4.48E-03 0.00 0.00 0.00 0.00 336.0 126E-04 3.40E-09 0.00 0.998 0.00 0.00 1.79E-03 0.00 0.00 O.W 0.00 504.0 6.87E-05 0.00 0.00 0.999 0.00 0.00 7.09E-04 0.00 0.00 0.00 0.00 672.0 3.80E-05 0.00 0.00 1.000 0.00 0.00 2.84E-04 0.00 0.00 0.00 0.00 720.0 3.19E.05 0.00 0.00 1.000 0.00 0.00 2.18E-04 0.00 0.00 0.00 0.00 Notes: 1. The activity fractions that are IOT highlighted contribute less than ten percent of the whole body dose.
- 2. The activity fractions that are NOT underlined contribute less than ten percent of the thyroid dose.
- 3. Radionuclides that do NOT appear in the table contribute less than ten percent of the whole body and thyroid dose totals.
Page 50 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS
6.0 REFERENCES
6.1 EDS Report to Wisconsin Electric Power Company concerning NUREG-0578, March 7, 1980.
6.2 EPIP 1.1, Course of Actions 6.3 EPIP 2.1, Notifications - ERO, State & Counties, and NRC 6.4 ETD 02, Offsite Agency Call List.
6.5 NUREG/BR-0150, Volume 1, Revision 4, RTM-96, Response Technical Manual, Figures A-5 and A-6, March 1996.
6.6 Radiation Monitoring System Alarm Setpoint & Response Book 6.7 Radiological Engineer to Plant Manager/EP Coordinator memo dated June 13, 1988.
6.8 Reactor Engineer to Plant Manager memo dated April 6, 1984.
6.9 TID 14844, Calculation of Distance Factors for Power and Test Reactor Sites, March 23, 1962.
6.10 U. S. NRC Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1, October 1977.
6.11 U. S. NRC Regulatory Guide 1.4, Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss-of Coolant Accident for Pressurized Water Reactors, Revision 2, June 1976.
7.0 BASES B-1 NUREG-0654, Revision 1, Supp. 3, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants, July, 1996.
B-2 Point Beach Nuclear Plant, Emergency Plan, Appendix J, Evacuation Time Estimates for the Area Surrounding the Point Beach Nuclear Plant.
B-3 IE Information Notice No. 83-28, Criteria for Protective Action Recommendations for General Emergencies.
B-4 EPA 400-R-92-001, Manual of Protective Action Guidelines for Nuclear Incidents, May, 1992.
Page 51 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS ATTACHMENT A AFFECTED SECTORS BASED ON WIND DIRECTION NOTE: If wind speed is less than three (3) mph or lake breeze conditions exist, then recommend protective actions for all sectors (360°) 0-5 miles. Lake breeze conditions exist if the difference between actual wind direction values for inland and near shore meteorological towers is greater than 900.
Wind Direction* (Degrees From) Affected Downwind Sectors
>351 - 9 (>351 - 369**) H,J,K
>9 - 13 (>369 - 373**) H, J K, L
>13 - 32 (>373 - 396**) J,K, L
>32 - 36 (>392 - 396**) J,K,L,M
>36 - 54 (>396 - 414**) K,L,M
>54 - 58 (>414 - 418**) K,L,M,N
>58 - 77 (>418 - 437**) L,M,N
>77 - 81 (>437 - 441**) L,M,N,P
>81 - 99 (>441 - 459**) M,N,P
>99 - 103 (>459 - 463**) M, N,P,Q
>103 - 122 (>463 - 482**) N,P,Q
>122 - 126 (>482 - 486**) N, P,Q,R
>126 - 144 (>486 - 504**) P,Q,R
>144 - 148 (>504 - 508**) P,Q,R,A
>148 - 167 (>508 - 527**) Q, R,A
>167 - 171 (>527 - 531**) Q,R,A,B
>171 - 189 (>531 - 549**) R, A, B
>189- 193 R, A, B,C
>193 - 212 A, B,C
>212 - 216 A,B,C,D
>216 - 234 B,C,D
>234 - 238 B,C,D,E
>238 - 257 C, D, E
>257 - 261 C,D,E,F
>261 - 279 D,E,F
>279 - 283 D, E, F,G
>283 - 302 E,F,G
>302 - 306 E,F,G,H
>306 - 324 F,G,H
>324 - 328 F,G,H,J
>328 - 347 G,H,J
>347 - 351 G,H,J,K
- As read on PPCS or Control Room instruments.
- > 360 as read on chart recorder.
Page 52 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS ATTACHMENT B GENERAL EMERGENCY OFFSITE PROTECTIVE ACTIONS GENERAL EMERGENCY Declared Recommend Evacuation of 2-mile Radius and 5 miles Downwind. (1) (5)
< / Substantial Core Damage in Progress or Projected? (Actual/Potential for>
No 20% Fuel Damage)
(I) Situations requiring urgent action Yes by otisite officials (based on control i_
room indicators, no dose projections required). Initial Recom Fission Product is appro (2) >30,000 R/lr in containment high inventory in Containment? No - Evacuate radiation monitors. (More than Gap) Radius ani Downwinc (3) L.QSS-criteria for RCS barrier in EPIP 1.2. Attachment C. exceeded.
(4) LQ.SSj criteria for containment Yes barrier In EPIP 1.2. Attachment C, exceeded.
(5) In some cases (e.g.. short-duration Immnen puff release. inclement weather). Projected Containment Failure or No sheltering may be an appropriate Release Underway?
recommendation. This should be discussed with the state andlor counties it appropriate.
Page 53 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS ATTACHMENT C REINSTALLATION OF WEDAP SOFTWARE 1.0 NOTEBOOK PERSONAL COMPUTER (PC) ACCESS The Wisconsin Electric Dose Assessment Program (WEDAP) is a resident of the hard drive of the Level A notebook personal computers (PC) in the Control Room and EOF (TSC as a backup) dose assessment areas. The directory location is "J:\Apps\NP\WEDAP".
1.1 IF the WEDAP directory and files are NOT found on the hard drive of the notebook PC in the EOF (TSC),
THEN the notebook PC must be recloned and WEDAP reinstalled using the CD-Roms located in the EOF (TSC) inventory cabinet.
1.1.1 Recloning the notebook PC
- a. Insert the cloning "Install" CD-Rom.
- b. Reboot the notebook PC.
- c. Wait for the prompt, following any instruction prompts given.
1.1.2 Installing WEDAP from the cloning CD.
- a. Insert the "WEDAP" application CD-Rom.
- b. Select the "Start Bar - Enterprise Applications - Application Install - Install/Update Application" (top choice).
- c. Click on "Install" to run the auto-install.
1.2 Return to EPIP 1.3, Step 5.2.1 OR IF WEDAP is still unavailable, THEN perform manual calculations per EPIP 1.3, Step 5.4.
2.0 PRINTING DATA TO LOCAL PRINTER IN THE EOF (TSC) 2.1 Ensure the laserjet printer in the EOF (TSC) is connected to the notebook PC via the printer cable and the printer is in the "ON" position.
2.2 From WEDAP, select "File - Print" OR the "Printer Icon" to print a case.
Page 54 of 56 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS ATTACHMENT C REINSTALLATION OF WEDAP SOFTWARE 2.3 Return to EPIP 1.3, Step 5.2.20 IF able to print.
2.4 IF still unable to print, THEN reset the printer connection.
2.4.1 Select "Start - Settings - Printers - HP LaserJet 4000" and verify the printer properties have LPT1 selected for the port connection.
2.4.2 From WEDAP, select "File - Print" OR the "Printer Icon" to print a case.
2.4.3 Return to EPIP 1.3, Step 5.2.20 IF able to print.
2.5 IF still unable to print, THEN reinstall the printer drivers.
2.5.1 Obtain the cloning "Install" CD-Rom from the EOF (TSC) inventory cabinet and place in the notebook PC while still logged on.
2.5.2 Select Start - Settings - Printers 2.5.3 Execute "Add Local Printer" 2.5.4 Select "My Computer" and "Next" arrow 2.5.5 Select "LPT1" local port and "Next" arrow 2.5.6 At "Add Print Wizard" select "Have Disk...."
2.5.7 At "Install From Disk" select "Browse..."
2.5.8 When message of "A:\ Isn't Accessible" select "Cancel" 2.5.9 At "Local File Window" Select "My Computer" 2.5.10 Select "D"\Pmtdrvs\1386\HP4000-1\PC16\Oemnt4O.inf OR other appropriate printer.
2.5.11 Select "OK" at "Install from Disk" 2.5.12 Select "HP LaserJet 4000 Series PCL 6" OR other appropriate printer and "Next" arrow.
2.5.13 Name the printer HPLJ4000 OR other appropriate name and "Next" arrow Page 55of 6 REFERENCE USE
POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 32 DOSE ASSESSMENT AND PROTECTIVE ACTION November 26, 2003 RECOMMENDATIONS ATTACHMENT C REINSTALLATION OF WEDAP SOFTWARE 2.5.14 Select "Not Shared" and "Next" arrow 2.5.15 Select "Yes" to print a test page and "Finish" when completed 2.5.16 Select the newly installed printer as the "Default" 2.5.17 IF printer prints test page, THEN retry printing per Attachment C, Step 2.2 2.5.18 IF printer still does not print, THEN initiate a call for computer support.
2.6 Return to EPIP 1.3, Step 5.2.20.
Page 56 of 56 REFERENCE USE
EPIP 1.1 COURSE OF ACTIONS DOCUMENT TYPE:. Technical CLASSIFICATION: NNSR REVISION: 44 EFFECTIVE DATE: November 26, 2003 REVIEWER: Plant Operation's Review Committee APPROVAL AUTHORITY: Department Manager PROCEDURE OWNER (title): Group Head OWNER GROUP: Emergency Preparedness Verified Current Copy:
Signature Date Time List pages used for Partial Performance Controlling Work Document Numbers
POINT BEACH NUCLEAR PLANT EPIP 1.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 44 COURSE OF ACTIONS November 26, 2003 TABLE OF CONTENTS SECTION TITLE PAGE 1.0 PURPOSE .3 2.0 PREREQUISITES .3 3.0 PRECAUTIONS AND LIMITATIONS .3 4.0 INITIAL CONDITIONS .3 5.0 PROCEDURE .4
6.0 REFERENCES
.9 7.0 BASES .9 ATTACHMENT A ANNOUNCEMENT OF CLASSIFIED EVENT AND PROTECTIVE ACTION ........................... 10 ATTACHMENT B NOTIFICATION OF PERSONNEL OUTSIDE THE PROTECTED AREA ... 12 ATTACHMENT C ACTIVATION OF EMERGENCY RESPONSE DATA SYSTEM (ERDS) ........................... 15 Pace 2 of 15 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT EPIP 1.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 44 COURSE OF ACTIONS November 26, 2003 1.0 PURPOSE This procedure provides instructions for Control Room personnel responding to an off-normal event at the Point Beach Nuclear Plant (PBNP).
2.0 PREREQUISITES 2.1 Responsibilities 2.1.1 The Shift Manager (SM) is responsible for this procedure.
2.1.2 The SM is responsible for taking immediate actions to mitigate the.
consequences of the emergency.
2.1.3 The SM is responsible for implementing Emergency Plan Implementing Procedures (EPIPs) as referenced by this procedure until formally relieved by key personnel in emergency response facilities.
2.1.4 The SM may delegate assignments to qualified personnel as necessary.
2.2 Equipment None 3.0 PRECAUTIONS AND LIMITATIONS None 4.0 INITIAL CONDITIONS An off-normal occurrence with the potential for an emergency classification exists (or has existed) at PBNP.
Page 3 of 15 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT EPIP 1.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 44 COURSE OF ACTIONS November 26, 2003 Initials Time 5.0 PROCEDURE Date/Time entered Reason entered NOTE 1: Steps may be completed out of sequence, as appropriate.
NOTE 2: Steps that do not apply, may be marked "not applicable."
NOTE 3: Steps already formally turned over to Emergency Response Facilities (per Step 5.17) may be marked "not applicable."
NOTE 4: Control Room is responsible for all steps prior to transfer of responsibility. Text in [ ]'s denotes the Emergency Response Facility responsible for implementation of that step AFTER the formal transfer of responsibilities from the Control Room.
NOTE 5: Classifications are to be made consistent with in 15 minutes once plant parameters reach an Emergency Action Level (EAL) indication in the Control Room. (Ref NEI 99.02) 5.1 IF a credible HIGH or LOW security threat, THEN go to EPIP 1.4. N/A if attack in progress
[CR primary, EOF support]
5.2 Direct the Security Shift Commander to report to the Control Room. [CR]
5.3 Go to EPIP 1.2 (Step 5.1), Emergency Classifications, to determine if an emergency classification is required. EOF primary, TSC/CR support]_
WARNING If event is security related, then discuss the consequences of conducting an assembly and accountability with Security prior to implementation.
5.4 Complete Attachment A, Announcement of Classified Event and Protective Actions, and make the plant Gai-Tronics announcement. [CR]
Page 4 of 15 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT EPIP 1.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 44 COURSE OF ACTIONS November 26, 2003 Initials Time 5.5 IF normal working hours, THEN implement EPIP 1.1, Attachment B, to notify personnel outside the protected area of the event, ELSE implement EPIP 1.1, Attachment B, after notifications in Step 5.6 to notify personnel outside the protected area. [TSC]
NOTE 1: In some cases (e.g., short-duration puff release, inclement weather), sheltering may be an appropriate recommendation. This should be discussed with the state and/or counties, if appropriate.
NOTE 2: IF the event is classified as a GENERAL EMERGENCY, THEN minimum protective action recommendations are required.
- Evacuate 0-2 miles, all sectors
- Evacuate 2-5 miles, 3 or 4 downwind sectors NOTE 3: IF wind speed is less than three (3) mph or lake breeze conditions exist, THEN recommend protective actions for all sectors (3600) 0-5 miles. Lake breeze conditions exist if the difference between actual wind direction values for inland and near shore meteorological towers is greater than 900.
5.6 Go to EPIP 2.1, "Notifications - ERO, State & Counties, and NRC."
LiOF]
NOTE: Assign personnel to make each notification.
5.6.1 Emergency Response'Organization (pager activation)
Use EPIP 2.1, Section 5.1. [CR]
5.6.2 State & Counties (initiate within 15 minutes of declaration)
Use EPIP 2.1, Section 5.2 and EPIP 2.1 Attachment B, Nuclear Accident Reporting System Form. [EOF] (NARS) 5.6.3 KNPP Control Room.
Use EPIP 2.1, Section 5.3. [EOF]
5.6.4 Nuclear Regulatory Commission (NRC)
(immediately after State & County notifications, NOT to exceed 60 minutes from declaration).
Use EPIP 2.1, Section 5.4. [TSC]
Page 5 of 15 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT EPIP 1.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 44 COURSE OF ACTIONS November 26, 2003 Initials Time 5.7 IF emergency involves plant conditions which suggest a radioactive release is in progress or anticipated, THEN go to EPIP 1.3 (Step 5.1), Dose Assessment and Protective Action Recommendations. [EOF_
5.8 IF a backshift or weekend, THEN contact the onshift Radiation Protection Technologist and Radiochemical Technician to report to the Control Room for further instructions in support of the event. [CR]
NOTE: SM. to ensure the teams are aware of plant and Radiological Conditions.
5.9 Dispatch and track teams until this responsibility is assumed by the OSC. [OSCI 5.10 IF the event is an Unusual Event and additional staff is desired, THEN call in personnel using the Emergency Response Organization (ERO) Call List, ETD 01. [CR]
5.11 Implement the remaining sections per EPIP 6. 1, Assembly and Accountability, Release and Evacuation of Personnel, for the following:
5.11.1 Accountability (ref EPIP 6. 1, Step 5.2.2). [TSC]
5.11.2 Release of personnel (no radiological impediments) (ref EPIP 6.1, Step 5.3). [TSC 5.11.3 Evacuation of site to offsite assembly areas (includes radiological monitoring prior to leaving the plant site) (ref EPIP 6.1, Step 5.4). [TSC]
5.12 IF Alert or higher, THEN:
5.12.1 Activate Emergency Response Data System (ERDS) per EPIP 1.1, Attachment C, Activation of Emergency Response Data System (ERDS) (Within 60 minutes of declaration). [CR]
5.12.2 Issue high range dosimetry to Control Room personnel. [CR]
5.12.3 Ensure backshift RPTs and Chem Techs have high range dosimetry. CR]
Page 6 of 15 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT EPIP 1.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 44 COURSE OF ACTIONS November 26, 2003 Initials Time 5.13 IF the event is a General Emergency AND ALL the following criteria are met, THEN implement expanded PARS of evacuation for 0-5 miles all sectors and 5-10 miles downwind sectors. [EOF] (Re6.15) 5.13.1 Substantial core damage in progress or projected (>20%)
(> 30,000 R/hr in containment high radiation monitors) 5.13.2 Large fission product inventory in containment (more than GAP) (LOSS criteria for RCS barrier in EPIP 1.2, Attachment C, exceeded) 5.13.3 Imminent projected containment failure or release underway (LOSS criteria for containment barrier in EPIP 1.2, Attachment C, exceeded) 5.14 IF event involves a liquid release to the lake, THEN notify local water utilities per Offsite Agency Call List, ETD 02. [EOF]
5.15 IF TSC and/or EOF are NOT activated, THEN ensure periodic status updates are provided to the State, Counties, and NRC per EPIP 2.1. (Hourly) [CR]
5.16 IF activating the Emergency Response Facilities, THEN provide a turnover briefing to TSC Manager upon arrival in the Control Room. [CR]
5.16.1 Plant status 5.16.2 Notifications status and current EPIP 2.1, Attachment B form (NARS).
5.16.3 Status of Personnel on Protected Worker Log 5.16.4 Assembly and accountability status 5.17 Conduct a formal turnover of responsibilities to Emergency Response Facilitieg'as they are activated. [CR]
5.17.1 Technical Support Center (TSC)
- a. Plant assessment on classification recommendations per EPIP 1.2
- b. Onsite protective actions Page 7 of 15 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT EPIP 1I.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 44 COURSE OF ACTIONS November 26, 2003 Initials Time
- c. Onsite radiological assessment
- d. NRC Notifications per EPIP 2.1
- e. Assembly and Accountability, Release and Evacuation of Personnel per EPIP 6.1 5.17.2 Operations Support Center (OSC)
Add Statement Assume all reentry dispatch and tracking for:
Area of Responsibility
- a. Emergency reentry team.
- b. Search and Rescue team.
- c. Fire fighting team.
- d. Medical emergencies (EPIP 11.2)
- e. Non-PBNP or Contractor team, NMC Fleet personnel or Contractor team (outside protected area).
5.17.3 Emergency Operations Facility (EOF)
- a. Classification of emergencies per EPIP 1.2
- b. Offsite protective action recommendations per EPIP 1.3
- c. State and County notifications per EPIP 2.1
- d. Overall management of ERO activities
- e. Request for Federal Assistance, if needed
- h. Review and approval of news releases.
5.18 Initiate an action request associated with the event and insert a copy in the Operations Notebook (reference 6.14) and exit this procedure, returning it to Emergency Preparedness. [CRI Page 8 of 15 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT POINT BEACH NUCLEAR PLANT EPIP 1.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 44 COURSE OF ACTIONS November 26, 2003
6.0 REFERENCES
6.1 EPIP 1.2, Emergency Classifications 6.2 EPIP 1.3, Dose Assessment and Protective Action Recommendations 6.3 EPIP 1.4, Credible High or Low Security Threat 6.4 EPIP 2.1, Notifications - ERO, State & Counties, and NRC 6.5 EPIP 4.1, Attachment E, Activation of Emergency Response Data System (ERDS) 6.6 EPIP 5.1, Personnel Emergency Dose Authorization 6.7 EPIP 5.2, Radioiodine Blocking and Thyroid Dose Accounting 6.8 EPIP 6.1, Assembly and Accountability, Release and Evacuation of Personnel 6.9 EPIP 10.1, Emergency Reentry 6.10 EPIP 11.2, Medical Emergency 6.11 ETD 01, Point Beach Emergency Response Organization (ERO) Call List 6.12 ETD 02, Offsite Agency Call List 6.13 NEI 99-02, Regulatory Assessment Performance Indicator Guideline 6.14 IR 94-013, NPNPD-94-014, Response to Notice of Violation, October 5, 1994 6.15 NUREG-0150, Volume 1, Revision 4, RTM-96, Response Technical Manual, Figures A-5 and A-6, March 1996 7.0 BASES B-1 10 CFR 50.47(b), Emergency Plans B-2 10 CFR 50.47, Appendix E.IV, Content of Emergency Plans B-3 NUREG-0654, Criteria for Preparation and Evaluation of Radiological Response Plans and Preparedness in Support of Nuclear Power Plants, Revision 1, November 1980 Page 9 of 15 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT EPIP 1.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 44 COURSE OF ACTIONS November 26, 2003 ATTACHMENT A ANNOUNCEMENT OF CLASSIFIED EVENT AND PROTECTIVE ACTION Page I of 2 NOTE: Ensure each section that should be included in the announcement has a check in that check box. The individual making the announcement should read each of those sections when making the actual announcement.
1.0 CLASSIFICATION 1.1 Check the appropriate event classification level box.
1.2 Log the EAL chart classification number and condition of the event.
1.3 Emergency Response Facilities must be activated at an Alert or higher classification.
NOTE: Select Step 2.0, Step 3.0, or Step 4.0 based on the event in progress and the appropriate personnel protective actions required.
2.0 LIMITED PLANT EVACUATION 2.1 Log the areas where a limited plant evacuation is required.
2.2 Check the appropriate location box(s) where the evacuated personnel should report. Use "other" if a different assembly area is needed due to the unavailability of the ones listed.
NOTE: An evacuation of non-essential personnel to offsite assembly areas (Step 4.0) shall be conducted in lieu of Step 3.0 under emergency conditions that may endanger human life and health (i.e., fire, flooding, toxic gases, etc.) and the SM or TSC Manager has determined that non-essential personnel shall be evacuated to offsite assembly areas.
3.0 FULL-SITE ASSEMBLY AND ACCOUNTABILITY (Required at Site Emergency, Optional Earlier - Ref EPIP 6.1, Step 4.2) 3.1 Check "Your Assigned Assembly Area" if all locations are available.
3.2 Check the appropriate location box(s) where the personnel should assemble if any normal assembly areas are unavailable. Use "other" if a different assembly area is needed due to the unavailability of the ones listed.
4.0 OFFSITE ASSEMBLY AND ACCOUNTABILITY (In lieu of Step 3.0 - Ref EPIP 6.1, Step 4.3)
Check the appropriate offsite location box where personnel should assemble.
5.0 GATEHOUSE Check the appropriate gatehouse that personnel should exit through.
6.0 AVOID AREAS Log the hazardous area(s) that should be avoided by personnel assembling.
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POINT BEACH NUCLEAR PLANT EPIP 1.1 EMERGENCY PLAN MPLEMENTING PROCEDURES NNSR Revision 44 COURSE OF ACTIONS November 26, 2003 ATTACHMENT A ANNOUNCEMENT OF CLASSIFIED EVENT AND PROTECTIVE ACTION Page 2 of 2 SOUND THE FISHERMAN'S ALARM.
SOUND THE EVACUATION ALARM.
MAKE THE FOLLOWING ANNOUNCEMENT.
"ATTENTION ALL PERSONNEL. ATTENTION ALL PERSONNEL.
1.0 0 THERE ARE CONDITIONS AT THE PLANT THAT WARRANT A (AN) o UNUSUAL EVENT o ALERT O SITE EMERGENCY o GENERAL EMERGENCY o TERMINATION OF CLASSIFIED EVENT THESE CONDITIONS ARE (EAL chart classificationlcondition):
1 ALL ERO PERSONNEL REPORT TO YOUR ASSIGNED EMERGENCY RESPONSE FACILITY.
(required at an ALERT or Higher, Optional Earlier) 0 TESE CONDITIONS ALSO WARRANT A:
2.0 0 LIMITED PLANT EVACUATION OF THE FOLLOW'ING AREAS:
ALL REMAINING PERSONNEL IN THESE AREA(S) REPORT TO THE:
o (In RCA) RP STATION O (Outside RCA) NORTH SERVICE BUILDING CAFETERIA o (Other)
AND AWAIT FURTHER INSTRUCTIONS."
3.0 0 FULL SITE ASSEMBLY AND ACCOUNTABILITY (Required at SITE EMERGENCY, Optional Earlier):
ALL REMAINING PERSONNEL REPORT TO:
o YOUR ASSIGNED ASSEMBLY AREA o NORTH SERVICE BUILDING CAFETERIA o ADMIN BUILDING EL 26' OFFICE AREA o ENGINEERING BUILDING CAFETERIA o TRAINING BUILDING NORTH FOYER O WAREHOUSE #4 o (OTHER)_
4.0 0 OFFSITE ASSEMBLY AND ACCOUNTABILITY (In lieu of Step 3.0):
ALL REMAINING PERSONNEL REPORT TO:
o TWO CREEKS TOWN HALL o TWO RIVERS NATIONAL GUARD ARMORY 5.0 0 EXIT THROUGH o THE SOUTII GATEHOUSE o TIlE NORTH VEHICLE GATE (Only if the South Gatehouse Unavailable) 6.0 0 (IF filled in, THEN announce:) AVOID THE FOLLOWING AREA(S):
REPEAT ALARMS AND ANNOUNCEMENT Return the completed form to Emergency Preparedness or TSC Manager.
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POINT BEACH NUCLEAR PLANT EPIP 1.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 44 COURSE OF ACTIONS November 26, 2003 ATTACHMENT B NOTIFICATION OF PERSONNEL OUTSIDE THE PROTECTED AREA Page 1 of 3 1.0 PBNP AUTOMATED NOTIFICATION SYSTEM NOTE 1: Listen carefully because the system will give you other options. To expedite the notification process, the following steps have been written to only list the specific voice prompt you need, at which time you can immediately respond without listening to the remaining prompt.
NOTE 2: If at any point you want to exit the system and start over, you should keep slowly pressing the "#" key until the system says "goodbye" and restart the entire process.
1.1 PBNP Automated Notification System is unavailable, THEN go to Step 2.0 of this attachment.
1.2 From any on-site telephone, dial ext. to access the PBNP Automated Notification System.
1.3 When prompted "Please enter your scenario activation password," enter "
using the keypad on the telephone.
1.4 When prompted "To start a scenario enter the scenario ID....," enter" 1.5 Press' "to sclcct recording a ncw message. Other voice prompts will be given but you do not have to listen to the options.
1.6 . When prompted "After the tone, speak the new message....," read Attachment A, Announcement of Classified Event, and Protective Actions, and press "#." (Your message will automatically play back).
1.7 Press ". "to start the scenario. Other voice prompts will be given if you want to replay your message or rerecord it.
1.8 When prompted, "The scenario is building," press "#", listen to "good-bye" and hang up.
1.9 IF normal working hours and Step 1.0 was successful, THEN return to procedure Step 5.6.
1.10 IF outside normal working hours and Step 1.0 was successful, THEN return to procedure Step 5.7.
1.11 IE Step 1.0 was NOT successful, THEN go to next Step 2.0 of this attachment.
Completed By Date/Time Page 12 of 15 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT EPIP 1.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 44 COURSE OF ACTIONS November 26, 2003 ATACHM[ENIT B NOTIFICATION OF PERSONNEL OUTSIDE THE PROTECTED AREA Page 2 of 3 2.0 PBX Broadcast System 2.1 Notification of Personnel Outside Protected Area on South Side of Plant From a touch-tone phone, dial 2.1.1 to access voice system 2.1.2 when prompted for mailbox 2.1.3 _ when prompted for password 2.1.4 to compose message 2.1.5 and when prompted 2.1.6 when prompted 2.1.7 Read Attachment A, Announcement of Classified Event and Protective Actions, and press # when done recording.
2.1.8 ' lo send message 2.1.9 to exit PBX Broadcast System.
2.2 Notification of Personnel Outside Protected Area on North Side of Plant From a touch-tone phone, dial 2.2.1 access voice system 2.2.2 when prompted for mailbox 2.2.3 when prompted for passwornd 2.2.4 to compose message 2.2.5 when prompted 2.2.6 when prompted Page 13 of 15 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT EPIP 1.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 44 COURSE OF ACTIONS November 26, 2003 ATTACHMENT B NOTIFICATION OF PERSONNEL OUTSIDE THE PROTECTED AREA Page 3 of 3 2.2.7 Read Attachment A, Announcement of Classified Event and Protective Actions, and press # when done recording.
2.2.8 to send message 2.2.9 to exit PBX Broadcast System.
2.3 IF normal working hours, THEN return to procedure Step 5.6 2.4 IF outside normal working hours, THEN return to procedure Step 5.7.
Completed By Date/Time Return the completed form to Emergency Preparedness or TSC Manager Page 14 of 15 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT EPIP 1.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 44 COURSE OF ACTIONS November 26, 2003 ATTACHMENT C ACTIVATION OF EMERGENCY RESPONSE DATA SYSTEM (ERDS)
NOTE 1: ERDS shall be activated within one hour of declaration of an Alert or higher emergency.
NOTE 2: ERDS must be activated and deactivated from the Control Room due to being a controlled environment and the TSC PPCS configuration.
NOTE 3: ERDS can be activated from terminals PPCS or Only one Unit can transmit data at a time through a connection. If one Unit is 'connected' through' then the other Unit to be 'connected' must be activated through . When both Units are inadvertently activated through a single line then only one unit displays
'connected'. The other unit displays 'on line' with an 'error' message. The NRC receives alarms indicating validity of the data being transmitted should be checked. Both Units can transmit simultaneously by activating one Unit on each connection. The status displayed would be 'connected' in this case.
1.0 TO INITIATE THE ERDS 1.1 From Control Room drop PPCS or click on the MENU icon.
1.2 Click on Operator Station Programs.
1.3 Click on ERDS for the appropriate Unit.
1.4 Click on the Startup button.
NOTE: When ERDS is activated due to an Emergency the NRC must provide verbal concurrence before ERDS can be deactivated from PBNP.
2.0 TO DEACTIVATE THE ERDS 2.1 From Control Room drop PPCS click on the MENU icon.
2.2 Click on Operator Station Programs.
2.3 Click on ERDS for the appropriate Unit.
2.4 Click on the Shutdown button.
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