NRC 2003-0081, Revised Emergency Plan Implementing Procedures

Revised Emergency Plan Implementing Procedures

ML032671256
Person / Time
Site:	Point Beach
Issue date:	09/10/2003
From:	Cayia A Nuclear Management Co
To:	Document Control Desk, Office of Nuclear Security and Incident Response
References
NRC 2003-0081
Download: ML032671256 (91)

Text

Nie Committed to Nuclear Exceln Point Beach Nuclear Plant Operated by Nuclear Management Company, LLC NRC 2003-0081 September 10, 2003 Document Control Desk U.S. Nuclear Regulatory Commission Washington DC 20555 DOCKETS 50-266 AND 50-301 EMERGENCY PLAN IMPLEMENTING PROCEDURE REVISIONS POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 Enclosed are copies of revised procedures to the Point Beach Nuclear Plant Emergency Plan Implementing Procedure Revisions. The revised procedures dated August 29, 2003 should be filed in your copy of the manual.

Sincerely, 4'

FAF/kmd Enclosures cc: NRC Resident Inspector (wiole)

Incident Response Center, Region IlIl 6590 Nuclear Road

• Two Rivers, Wisconsin 54241 AU+

Telephone: 920.755.2321

POINT BEACH NUCLEAR PLANT EPIP INDEX EMERGENCY PLAN IMPLEMENTING PROCEDURES Revision 99 August 29, 2003 INDEX PROCEDURE REVISION EFFECTIVE PERIODIC NUMBER PROCEDURE TITLE NUMBER DATE REVIEW DATE EPIP 1. Course of Actions ................................... 43 C 02/11/03 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 ................................... 31 R 08/29/03 05/09/03 EPIP 1.4 Credible High or Low Security Threat ......................... 2 C 01/10/03 01/10/03 EPIP 2.1 Notifications - ERO, State & Counties, and NRC ..... 26 R 01/20/03 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 i 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 99 August 29, 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

NUCLEAR POWER BUSINESS UNIT EPIP FORM EMERGENCY PLAN IMPLEMENTING PROCEDURES CANCELED INDEX Revision 2 CANCELED INDEX November 30, 1999 PROCEDURE REVISION EFFECTIVE CANCELED NUMBER FORM TITLE NUMBER DATE DATE EPIP-1.3a Emergency Event - Immediate Actions - Duty Shift Superintendent (Insert behind EPIP 1.3)

(Incorporated into EPIP 1.1) ................................. 5 CANCELED 11/30/99 EPIP- 1.3b Emergency Event - Immediate Actions - Shift Technical Advisor (Insert behind EPIP 1.3)

(Incorporated into EPIP 1.1) .................... 4 CANCELED 11/30/99 EPIP-1.3c Emergency Event - Immediate Actions - Plant Operations Manager (Incorporated into EPIP-1.3a, PIM EOF 4.1, PIM EOF 4.5 and PIM TSC 2.7) .................................... 5 CANCELED 10/28/98 EPIP-1.3d Emergency Event - Immediate Actions - Site Manager (Incorporated into PIM TSC 2.1 and PIM EOF 4.1) ................................... 4 CANCELED 10/28/98 EPIP-1.3e Emergency Event - Immediate Actions Emergency Support Manager (Incorporated into PIM EOF 4.1) ......... 4 CANCELED 10/28/98 EPIP-04 PBNP Status Report on Plant Systems and Controls for Affected Unit (Insert behind EPIP 4.1)

(Incorporated into EPIP 2.1) .................... 1 CANCELED 11/30/99 EPIP-4.la Technical Support Center Activation Checklist (Incorporated into PIM TSC 2.1, PIM TSC 2.7, and PIM TSC 2.5) ............ 3 CANCELED 10/28/98 EPIP-4.2a Operations Support Center Activation Checklist (Incorporated into PIM OSC 3.1) ....................... 3 CANCELED 10/28/98 EPIP-4.2b Operations Support Center Team Status. CANCELED 05/03/96 EPIP-4.2c Communicator - OSC - Activation and Responsibilities (Incorporated into PIM OSC 3.7) .............. 3 CANCELED 10/28/98 EPIP4.2d Technical Person - OSC - Activation and Responsibilities (Incorporated into PIM OSC 3.7) ........... 2 CANCELED 10/28/98 EPIP4.2e Information Management Support - OSC - Activation and Responsibilities ............. 1 CANCELED 10/28/98 EPIP4.2f Health Physics Support - OSC - Activation and Responsibilities (Incorporated into PIM OSC 3.2) ................................. 2 CANCELED 10/28/98 EPIP-4.2g Reentry Team Qualification Listing (Insert behind EPIP 4.2) (Incorporated into PIM OSC 3.2, 3.3, 3.4, 3.5, 3.6 and 3.7) .................. 2 CANCELED 11/30/99 EPIP-4.3a Emergency Operations Facility Activation Checklist (Incorporated into PIM EOF 4.2, PIM EOF 4.5 and EPIP 4.3) .................... 6 CANCELED 10/28/98 Page 1 of 5

NUCLEAR POWER BUSINESS UNIT EPIP FORM EMERGENCY PLAN IMPLEMENTING PROCEDURES CANCELED INDEX Revision 2 CANCELED INDEX November 30, 1999 PROCEDURE REVISION EFFECTIVE CANCELED NUMBER FORM TITLE NUMBER DATE DATE EPIP-4.4a Alternate Emergency Operations Facility Activation Checklist (Incorporated into PIM EOF 4.2) .............. 4 CANCELED 10128/98 EPIP-4.5a Alternate Offsite Health Physics Facility (AOSHPF) Activation Checklist (Incorporated into PIM OSRPF 5.1) .3 CANCELED 10/28/98 EPIP4.6a Corporate Emergency Center Activation Checklist .2 CANCELED 10/28/98 EPIP-05 PBNP RMS Status Release Point Monitors (Insert behind EPIP 4.1) (Incorporated into PIM TSC 2.8 and PIM EOF 4.6) ....................... 1 CANCELED 11/30/99 EPIP-5. I a Emergency Plan Dose Authorization (Insert behind EPIP 5.1) (Incorporated into EPIP 5.1) ...... 3 CANCELED 11/30/99 EPIP-5.2a Dose Accountability for Exposures to Airborne Radioiodine (Insert behind EPIP 5.2)

(Incorporated into EPIP 5.2) .................... 1 CANCELED 11/30/99 EPIP-06 PBNP RMS Status - Area Type Monitors (Insert behind EPIP 4.1) (Incorporated into PIM TSC 2.8 and PIM EOF 4.6) .............................. 3 CANCELED 11/30/99 EPIP-6.4.5a Alternate Offsite Health Physics Facility Activation ... 0 CANCELED 01/22/92 EPIP-6.6a Accountability Short Form. CANCELED 02/88 EPIP-6.6b Assembly Area Roster . CANCELED 02/88 EPIP-6.6c Assembly Area Designation - Accountability List (Incorporated into EPIP 6.6 Attachment 1).............. 7 CANCELED 03/31/99 EPIP-6.6d Accountability Summary - Front Office ...................... 2 CANCELED 12/29/97 EPIP-6.6e Accountability Summary - TSC ................................. 2 CANCELED 12/29/97 EPIP-6.6f Accountability Summary - NSB Cafeteria ................... 2 CANCELED 12/29/97 EPIP-6.6g Accountability Summary - Control Room ................... I CANCELED 12/29/97 EPIP-6.6h Accountability Summary - HP Station ......................... I CANCELED 12/29/97 EPIP-6.6i Accountability Summary - OSC ................................. 0 CANCELED 12/29/97 EPIP-6.6j Accountability Summary - CAS ................................. 0 CANCELED 12/29/97 EPIP-6.7a Event Involvement Summary (Insert behind EPIP 6.7) (Incorporated into EPIP 6.1) .I CANCELED 11/30/99 EPIP-6.7b Emergency Event Information Sheet (Insert behind EPIP 6.7) (Incorporated into EPIP 6.1) .2 CANCELED 11/30/99 EPIP-6.7c Personnel "Disnissal-From-Site" Briefing Checklist (Insert behind EPIP 6.7) (Incorporated into EPIP 6.1) .2 CANCELED 11/30/99 Page 2 of 5

NUCLEAR POWER BUSINESS UNIT EPIP FORM EMERGENCY PLAN IMPLEMENTING PROCEDURES CANCELED INDEX Revision 2 CANCELED INDEX November 30, 1999 PROCEDURE REVISION EFFECTIVE CANCELED NUMBER FORM TITLE NUMBER DATE DATE EPIP-07 For X/Q Determination.................................................. CANCELED 03/85 EPIP-07 RMS Status (Process Monitors)

(Insert behind EPIP 4.1) (Incorporated into PIM TSC 2.8 and PIM EOF 4.6) .............................. 2 CANCELED 11/30/99 EPIP-7.1 a Health Physics Personnel Assignments (Incorporated into EPIP 7.1) .................................... 3 CANCELED 10/28/98 EPIP-7. lb Emergency Plan Equipment Requiring Transport from the Health Physics Station (Incorporated into PIM OSC 3.2) .................................... 1 CANCELED 10/28/98 EPIP-7.2.1a SBCC Radiation Control Team Equipment Inventory and Functional Test Checklist (Incorporated into PIM OSRPF 5.3) .......................... 4 CANCELED 10/28798 EPIP-7.2. lb Offsite Mobile Survey Team Equipment Inventory and Functional Test Checklist (Incorporated into PIM OSRPF 5.2) .......................... 3 CANCELED 10/28/98 EPIP-7.2. Ic Sample Shuttle Vehicle Equipment Inventory and Functional Test Checklist (Incorporated into PIM OSRPF 5.2) .......................... 2 CANCELED 10/28/98 EPIP-7.2. ld Offsite Health Physics Facility Offsite Health Physics Director Checklist (Incorporated into PIMOSRPF5.1) .......................... 3 CANCELED 10/28/98 EPIP-7.2.I e Dosimetry Device Issue Record and Exposure Log (Insert behind EPIP 7.2.1) (Incorporated into PIM OSC 3.2 and PIM OSRPF 5.3) ......................... 0 CANCELED 11/30/99 EPIP-7.2. If Meteorological Data (Pad Format, copy of form should be in your manual) (Incorporated into PIM TSC 2.8 and PIM EOF 4.6) ......................... I1 CANCELED 11/30/99 EPIP-7.3. la Offsite Airborne Radiation Survey Sample Analysis (Insert behind EPIP 7.3.1) (Incorporated into EPIP 7.3.l) ........................... CANCELED 11/30/99 EPIP-7.3. lb Ground Deposition (Insert behind EPIP 7.3.1)

(Incorporated into EPIP 7.3.1) .......................... 1 CANCELED 11/30/99 EPIP-7.3. Ic Dose Factor Calculations For Specific Noble Gas Analysis Results (Insert behind EPIP 7.3. 1)

(Incorporated into EPIP 7.3.1) .......................... 0 CANCELED 11/30/99 EPIP-7.3. Id Offsite Airborne Radiation Survey Sample Data (Insert behind EPIP 7.3.1) (Pad Format, copy of form should be in your manual) (Incorporated into EPIP 7.3.1) .......................... 1 CANCELED 11/30/99 rI Page 3 of 5

NUCLEAR POWER BUSINESS UNIT EPIP FORM EMERGENCY PLAN IMPLEMENTING PROCEDURES CANCELED INDEX Revision 2 CANCELED INDEX November 30, 1999 PROCEDURE REVISION EFFECTIVE CANCELED NUMBER FORM TITLE NUMBER DATE DATE EPIP-08 Estimated Whole Body and Thyroid Projected Doses ......................................................................... CANCELED 03/85 EPIP-8.4.1a Reactor Coolant Post Accident Sampling Analysis Report ...................................... 3 CANCELED 06/30/98 EPIP-8.4.2a Containment Atmosphere Post-Accident Sampling Analysis Report ...................................... 0 CANCELED 12/29/97 EPIP-09 Estimated Whole Body Dose Calculation Worksheet for Specific Noble Gas Releases................................. CANCELED 03/85 EPIP-9.2a Estimated Population Dose ........................................... CANCELED 12/30/93 EPIP-9.2b Summary of Radiological Dose Evaluation Calculations (Insert behind EPIR 9.2.)........................ CANCELED 12/30/93 EPIP-10 Estimated Ground Deposition Calculation Worksheet for Particulate Radionuclide Releases ........................ CANCELED 03/85 EPIP-I0. I a Reentry Team Preparation and Deployment (Insert behind EPIP 10.1) (Incorporated into EPIP 10.1) ............................. 5 CANCELED 11/30/99 EPIP- 10. lb Reentry Team Debrief (Insert behind EPIP 10.1)

(Incorporated into EPIP 10.1) .............................. 3 CANCELED 11/30/99 EPIP- 10. lc Operation Support Center Team Status (Insert behind EPIP 10.1) (Incorporated into EPIP 10.1) .............................. 2 CANCELED 11/30/99 EPIP-I l.la Search and Rescue/Emergency Reentry Checklist ........ CANCELED 03/90 EPIP-1 1.lb Search and Rescue/Emergency Reentry Team Dispatch Checklist ..................................................... CANCELED 03/90 EP1P-1 1.3a Offsite Medical Assistance Checklist (Insert behind EPIP 11.3) (Incorporated into EPIP 11.2) ............................. 7 CANCELED -11/30/99 EPIP-1 1.3b Health Physics Response Checklist Ambulance Assistance ............................ 1 CANCELED 01/24/97 EPIP-I 1.3c Radiation Protection Response Checklist Emergency Room (ER) (Insert behind EPIP 11.3)

(Incorporated into EPIP 11.2) ............................. 6 CANCELED 11/30/99 EPIP-12 PBNP Incident Report Form (Insert behind EPIP 2.1) (Incorporated into EPIP 2.1) ............................. 10 CANCELED 11/30/99 EPIP- I 2.2a Recovery Plan Action Items (Insert behind EPIP 12.2) (Incorporated into EPIP 12.2) ................ 1 CANCELED 11/30/99 Page 4 of 5

NUCLEAR POWER BUSINESS UNIT EPIP FORM EMERGENCY PLAN IMPLEMENTING PROCEDURES CANCELED INDEX Revision 2 CANCELED INDEX November 30, 1999 PROCEDURE REVISION EFFECTIVE CANCELED NUMBER FORM TITLE NUMBER DATE DATE EPIP-13 PBNP Status Update - Plant (Insert behind EPIP 2.1) (Incorporated into EPIP 2.1) .................... 4 CANCELED 11/30/99 EPIP- I3a PBNP Status Update - Radiological (Insert behind EPIP-13, behind EPIP 2.1)

(Incorporated into EPIP 2.1) ........ ........... 2 CANCELED 11/30/99 EPIP-14 Event Notification Worksheet (Insert behind EPIP 2.2) (Incorporated into EPIP 2.1) ..... 1l CANCELED 11/30/99 EPIP-22 Emergency Response Organization (ERO) Call List (Insert behind Call List Tab) (Incorporated into ETD 01) .... 36 CANCELED 11/30/99 EPIP-23 Offsite Agency Call List (Insert behind Call List Tab) (Incorporated into ETD 02) .... 33 CANCELED 11/30/99 EPIP-24 Emergency Response Facilities Telephone List (Insert behind Call List Tab) (Incorporated into ETD 03) .... 21 CANCELED 11/30/99 EPIP-25 W.E. Corporate Personnel Call List (Insert behind Call List Tab)

(Incorporated into ETD 04) ....... ........... 32 CANCELED 11/30/99 EPIP-26 Oil and Hazardous Material Spill Call List (Insert behind Call List Tab) (Incorporated into ETD 06) .... 29 CANCELED 11/30/99 EPIP-27 Notification/Augmentation Guideline (Incorporated into EPIP-3.2 and EPIP-22) ................... 1 CANCELED 10/28/98 EPIP-30 Reactor Coolant Post Accident Sampling Analysis Report . CANCELED 02/89 EPIP-3 1 Containment Atmosphere Post-Accident Sampling Analysis Report. CANCELED 02/89 EPIP-33 Estimate of Core Damage Worksheet. CANCELED 08/87 EPIP-34 Calculation of XE-133 Equivalent Release Rates . CANCELED 08/87 EPIP-35 Dose Calculations. CANCELED 09/85 Page 5 of 5

EPIP 1.3 DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATIONS DOCUMENT TYPE: Technical CLASSIFICATION: Safety Related REVISION: 31 EFFECTIVE DATE: August 29, 2003 REVIEWER: Managers Supervisory Staff 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 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 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 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 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 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 OFFS1TE PROTECTIVE ACTIONS ............... 53 ATTACHMENT C REINSTALLATION OF WEDAP SOFTWARE .......................................... 54 WORKSHEETS WORKSHEET 1 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 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 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 PREREQUISITES 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)

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POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 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 If the current wind direction is on or within 2 degrees of a sector line, then the two affected sectors are designated as the downwind sector. Downwind sector selection for the PAR shall include the adjacent sectors to the downwind sector(s). This will always result in either a 3 or 4 sector keyhole.

3.5 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.

3.6 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):

3.6.1 National Weather Service in Green Bay 3.6.2 Kewaunee Nuclear Power Plant 3.6.3 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.

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POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 2003 RECOMMENDATIONS 5.0 PROCEDURE 5.1 Protective Action Recommendations (PARs)

NOTE: 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.

NOTE: 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: If the current wind direction is on or within 2 degrees of a sector line, then the two affected sectors are designated as the downwind sector.

Downwind sector selection for the PAR shall include the adjacent sectors to the downwind sector(s). This will always result in either a 3 or 4 sector keyhole.

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] (RefStep6.15)

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 required PAR is evacuation 0-2 miles (all sectors) and 2-5 miles (3 or 4 downwind sectors centered on the average wind direction).

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POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 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, OR, IF 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.

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POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 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 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 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

d. PAR's 5.2.19 Compare the results of 5.2.18 against the current classification and PARs.

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 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 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 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 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 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 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 "" (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.

OR

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 (microcuries/cc) 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 (DAM I to DAM8, 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 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 2003 RECOMMENDATIONS

• Enter channel number (1 to 9), 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 I RELEASE MONITORS ALARMING DAM CHANNEL RMS # MONITOR READING.

(Rci/cc) 1 3 lRE-212 Ul Cont. Purge 2 3 2RE-212 U2 Cont. Purge 3 9 lRE-231 SG 1A 4 9 2RE-231 SG2A 5 2 1RE-232 SG 1B 5 7 RE-221 Drum Area Vent 5 8 RE-226 Comb A. E. High Range Steam Line 6 6 RE-224 Gas Stripper Building 6 2 2RE-232 SG2B 7 1 RE-225 Comb A. E. Low Range 7 4 RE-214 Aux Building Vent 21 5 IRE-305 Low Range Gas, U1 Purge 21 7 1RE-307 Medium Range Gas, Ul Purge 21 9 IRE-309 High Range Gas, U1 Purge 22 5 2RE-305 Low Range Gas, U2 Purge 22 7 2RE-307 Medium Range Gas, U2 Purge 22 9 2RE-309 High Range Gas, U2 Purge 23 5 RE-315 Low Range Gas, Aux Bldg Vent 23 7 RE-317 Medium Range Gas, Aux Bldg Vent 23 9 RE-319 High Range Gas, Aux Bldg Vent 24 5 RE-325 Low Range Gas, Drumming Area Vent 24 7 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 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 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 14 of 56 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 2003 RECOMMENDATIONS TABLE 2 RELEASE RATE CALCULATIONS NOTE: Conversion factors assume nominal flow rates.

READING CONVERSION RELEASE RATE RMS # LOCATION (RCi/cc) (cc-Ci/sec-RiCI) (Ci/sec)

RE-214 Auxiliary Building Vent x 33 =

RE-315 RE-317 RE-319 RE-221 Drummin, Area Vent x 20 =

RE-325 RE-327 IRE-212 UI Containment Purge 1RE-305 (0 or fan) x 6 =

1RE-307 1RE-309 Ir (2 fans) x 12 =

2RE-212 U2 Containment Purge 2RE-305 (0 or 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 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 -

r Release Rate Total (Ci/sec)

Page 15 of 56 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 2003 RECOMMENDATIONS NOTE: IF desired PPCS points have poor or bad quality, THEN obtain aG 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 XuIQ 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 Xu/Q A 9.92E-07 B 1.18E-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:

(sp )XuIQ(mph/3 Is) - w X/Q(s/M 3 )

(step b above) XQmp/ 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.

re m - mr n _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

3280 - 3_

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 16of 56 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 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 __ x 20 =

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.

a. Projected Whole Body Dose (TEDE) at Site Boundary is Ž1 Rem.

OR

b. Projected Thyroid Dose (CDE) at Site Boundary is 25 Rem.

5.3.11 IF the event meets the following criteria for a SITE EMERGENCY, THEN go to Step 5.3.15.

a. Projected Whole Body Dose (TEDE) at Site is Ž0.1 Rem.

OR

b. Projected Thyroid Dose (CDE) at Site Boundary is Ž0.5 Rem.

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 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 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.

INTEGRATED PROTECTIVE PROJECTED DOSE ACTION MILES SECTORS

<1 rem TEDE None eDE Required N/A N/A

>1 rem TEDE Evacuate 0-2 miles All (3600)

OR Evacuate 2-5 miles Downwind Sectors

Ž!5 rem CDE__ _ _ _ _ _ _ _ _

<3 mph Wind Speed OR Lake Breeze Evacuate 0-5 Miles All (3600)

AND

>1 rem TEDE OR 25 rem CDE

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 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 2003 RECOMMENDATIONS 5.4 Offsite Field Measurements 5.4.1 Check if Plume Impacts Terrestrial Areas

a. Wind Direction > 305° 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.

5.4.4 IF a General Emergency, THEN determine minimum Protective Action Recommendations, AND go to Step 5.4.6.

a. Evacuation of 0-2 miles for all sectors, and 2-5 miles in the downwind sectors.

OR

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.

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 Page 19 of 56 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 2003 RECOMMENDATIONS 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, RE-305, 1RE-307, and RE-309

• Unit 2 containment purge vent (Cont. 2) 2RE-212, 2RE-305, 2RE-307, and 2RE-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

• Main steam safety valves and atmospheric dump valves 1(2)RE-231 "A" Steam Generator 1(2)RE-232 "B" Steam Generator

b. The release rates may be estimated using any of the following monitoring systems:

• PPCS

• Radiation monitoring system (which is designed to monitor low and high level releases)

Page 20of 56 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 2003 RECOMMENDATIONS 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 5.5.1 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.

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/ inch of lead on the main steam line/containment building side of the probe.

Page 21 of 56 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 2003 RECOMMENDATIONS

• 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.

1. Sign and date Worksheet 1 and fax upon completion to the Dose/PAR Coordinator.

Page 22 of 56 REFERENCE USE

( POINT BEACH NUCLEAR PLANT C EPIP 1.3 SAFETY RELATED

(

EMERGENCY PLAN IMPLEMENTING PROCEDURES Revision 31 DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATIONS August 29, 2003 TABLE 3 RELEASE RATE CONVERSION FACTORS - SURVEY METER METHOD Units of expression are Ci-h/s-rem.

ACCIDENT TYPE Gap Accident('4 Steam Generator Tube Rupture 2 '

Vent Pathway LOCA("' 0-12 hours > 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> FHA"'l 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 FHA - 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 (ft3 /min)

Auxiliary Building 70000 Drumming Area 43100 Containment Purge 12500 Gas Stripper 13000 Air Ejector 25 Atmospheric Vent 3200 Safety, I 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 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 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 (Kci/cc) (cc-Ci/s-Lci) LCi/s)

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)

(Oor 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 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 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) RRelease Rate Monitor (R/hr) (Table 3) (Ci/s)

Auxiliary Building Vent (70,000 cfm)

Drumming Area Vent (43,100 cfm)

Unit 1 Containment Purge (Oor I 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)

I 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 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 2003 RECOMMENDATIONS WORKSHEET 1 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 C cfm) x

_ Ci Ci 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 (curiesls)

1. Auxiliary Building

2. Drumming Area

3. Gas Stripper Building

4. Combined Air Ejector Duct

5. Main Steam Line Vent

6. Unit 1 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 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 2003 RECOMMENDATIONS 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 (Gq, degrees) Control Room Instrumentation

• Temperature lapse rate PPCS or (AT/AH, 0 F/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 1 (curies/second)

Page 27 of 56 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 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, (T, degrees

4. Temperature lapse rate, AT/AH, 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 XuIQ from Table 6:

Site Boundary Two Miles Five Miles Ten Miles Other x sec sec - mi xu I 1 hr

-()= 2.24 (~ )x- (-)x(-

Q m hr - m Q m wind speed

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 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 2003 RECOMMENDATIONS NOTE: Do NOT use ae 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 a 6 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 a0 to determine the stability class.

Wind Direction Temperature Lapse Fluctuation Rate Stability Classification Pasquill Class (a(, degrees)* (AT/AH, F/35 m)

Extremely unstable A <X9 2 22.50 AT/AH < -1.2 Moderately unstable B 22.50 > (ye 17.50 -1.2 < AT/AH -1.1 Slightly unstable C 17.50> (ye Ž 12.50 -1.1 < AT/AH < -0.9 Neutral D 12.50 > ae > 7.5 -0.9 < AT/AH < -0.3 Slightly stable E 7.50> a 3.80 -0.3 < AT/AH < 0.9 Moderately stable F 3.80 > e 2.10 0.9 < AT/AH < 2.5 Extremely stable G 2.10 > a6g 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 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 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 > low < M cloud U<4 A A-B B F G 4<U<7 A-B B C E F 7<U<ll B B-C C D E 11*U<13 C C-D D D D 13 % low and < % 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 30of 6 REFERENCE USE

( (

( POINT BEACH NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCLJRES EPIP 1.3 SAFETY RELATED' Revision 31 DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATIONS August 29, 2003 TABLE 6 TABLE OF CENTERLINE Xu/Q VALUES VERSUS DISTANCE FROM THE SITE (Units are m72)

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 3.21E-08 2.76E-08 2.42E-08 2.17E-08 1.96E-08 1.80E-08 C 1.9lE-05 5.8 IE-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 5.99E-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 IE-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 3.31 E-05 Lake Breeze 4.54E-05 2.35E-05 1.3 1E-05 1.02E-05 8.37E-06 7.07E-06 6.33E-06 5.74E-06 5.1 IE-06 4.75E-06 Page 31 of 56 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 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 1.2 1E-06 mi2 . Calculate the X/Q values by dividing the Xu/Q value by the wind speed (in meters per second). This can be represented by the equation:

_ 224(sec mile XU/Q (m-2 )

Q m3 - hr- n Wind Speed (mileslhr)

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 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 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 Fi X X DCFj x ERD Q TIME where: Dosei is the whole body dose due to radionuclide i, rem; Q is the gross release rate, curies/s.

F1 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.

X/Q 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 F. X/Q DCF, ERD Dose I-131 5.3E+04 1-132 4.9E+04 1-133 1.5E+04 I-134 3. lE+04 I-135 8.lE+03 Kr-85 1.3E+00 Kr-85m 9.3E+01 Kr-87 5. lE+02 Kr-88 1.3E+03 Rb-88 5.2E+02 Cs-138 1.6E+03 Xe-131m 4.9E+00 Xe-133 2.OE+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 XIQ values and multiplying by the dose calculated above.

Completed By: Date/Time I Route to Dose/PAR Coordinator upon completion.

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POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 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:

Doseiwhole body = Qx x x DCF x ERD Q

where:

Dosei, whole body = 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 per m DCF1 = whole body dose conversion factor for nuclide i, rem-m3 /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 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 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 Dosei = Q X Fi X X DCFi 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/M3 ;

DCF1 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 Fj X/Q DCFi ERD Dose, 1-131 1.3E+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 /

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 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 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 QxFix xDCFixERD Q

where:

Dosei, thyroid = thyroid dose, rem; Q = release rate for nuclide i, curies per second; 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 underlined. Those radionuclides that are NOT underlined need NOT be included in the dose calculations.

X/Q = atmospheric dispersion factor, seconds per m DCF1 = thyroid dose conversion factor for nuclide i, rem-m 3 /Ci-hr; ERD = estimated duration of the release, hours.

Page 36 of 56 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 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 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 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 Depi = Q x Fi X x Veli x ERD x 3600 Q TIME where: Depi is the deposition of radionuclide i, curies/m 2 ;

Q is the gross release rate, curies/s.

Fi 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/M3 ;

Veli is the deposition velocity for radionuclide i, mis; 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 _

1-131 0.01 1-132 0.01 1-133 0.01 1-134 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 XQ values and multiplying by the deposition calculated above.

Completed By: DateMme 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 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 2003 RECOMMENDATIONS

f. Calculate the ground deposition values using the equation:

Dep, = Q x Fi x x Veli x ERD x 3600 Q

where:

Depi = deposition of radionuclide i, curies per meter';

Q = gross release rate, curies per second; 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.

X/Q = atmospheric dispersion factor, seconds per m; Vel - deposition velocity of radionuclide i, 0.01 m/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 39 of 56 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 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 1

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 J 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 /

Route to Dose/PAR Coordinator upon completion.

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POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 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.

INTEGRATED PROTECTIVE MILES SECTORS PROJECTED DOSE ACTION

<1 rem TEDE None AND Rqie / /

<5 rem CDE at 1 mile

>1 rem TEDE at 1 mile Evacuate 0-2 Miles All (3600)

OR

>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 1 mile OR

>5 rem CDE at mile

>1 rem TEDE at 5 miles Evacuate 0-5 Miles All (360°)

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)

>I rem TEDE at 5 miles OR

>5 rem _CDE at_5_miles __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

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 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 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

C POINT BEACH NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROC(L JRES EPIP 1.3(

SAFETY RELATED(~

Revision 31 DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATIONS August 29, 2003 TABLE 7 LOCA SOURCE TERM ACTIVITY FRACTIONS - CONTAINMENT SPRAY NOT USED Page of 8 Time 1-131 1-132 1-133 1-114 1-135 IKr.R5 Kr-Rim Kr-R7 Kr-RR Rh-R ('c.ml 0.0 2.46E-02 3.52E-02 5.51E.02 6.42E-02 5.IOE-02 0.001 0.043 0.083 0.117 0.000 0.000 0.5 2.75E-02 3.40E-02 6.07E-02 4.82E-02 5.43E-02 0.001 0.044 0.071I 0.116 0.084 0.057 1.0 3.08E.02 3.25E-02 6.70E-02 3.6I1E-02 5.79E.02 0.001 0.046 0.061 0.115 0.113 0.053 1.5 3.40E-02 3.09E-02 7.27E-02 2.69E-02 6.08E-02 0.001 0.047 0.051 0.112 0.120 0.037 2.0 3.69E.02 2.88E-02 7.80E-02 I1.9613-02 6.27E-02 0.001 0.047 0.042 0.108 0.119 0.024 2.5 3.96E-02 2.66E-02 8.24E.02 1.41E-02 6.39E-02 0.001 0.047 0.035 0.103 0.114 0.014 3,0 4.20E-02 2.4212-02 T.5E.02 I .OIIE-02 6.43E-02 0.001 0.046 0.028 0.097 0.108 0.008 4.0 4.63E-02 1.97E-02 9.19E-01 4.99E-03 6.42E-02 0.001 0.043 0.0 18 0.083 0.093 0.003 5.0 5.OOE-02 I1.57E-02 9.64E-02 2.44E-03 6.27E-02 0.002 0,040 0.011 0.070 0.079 0.001 6.0 5.33E-02 I1.24E-02 9.97E-02 .17E-03 6.07E-02 0.002 0.037 0.007 0,059 0.066 0.000 7.0 5.62E-02 9.65E-03 1.02E-01 5.5 81-04 5.79E-02 0.002 0.033 0.004 0.049 0.054 0.000 8.0 5.90E-02 7.47E-03 1.03E-01 2.64E-04 5.49E-02 0.002 0.030 0.003 0.040 0.045 0.000 9.0 6.13E.02 5.73E-03 1.05E-01 1.24E-04 5.16E.02 0.002 0.027 0.002 0.033 0.036 0.000 10.0 6.35E-02 4.39E-03 1.05E-01 5.80E-05 4.84E-02 0.002 0.024 0.001 0.026 0.030 0.000 12.0 6.74E-02 2.54E-03 1.04E-01 I1.25E-05 4.20E-02 0.002 0.0 18 0.000 0.017 0,019 0.000 18.0 7.60E-02 4.64E-04 9.81E.02 1I1-07 2.59E-02 0.003 0.008 0.000 0.004 0.005 0.000 24.0 8.19E-02 8.1 1E-05 8.82E-02 I1.08E-09 I1.53E-02 0.003 0.004 0.000 0.001 0.001 0.000 30.0 8.65E-02 1.39E-05 7.76E.02 0.000 8.88E-03 0.003 0.001 0.000 0.000 0.000 0.000 36.0 9.02E-02 2.36E-06 6.73E-02 0.000 5.08E-03 0.003 0.001 0.000 0.000 0.000 0.000 42.0 9.34E-02 3.96E-07 5.81E-02 0.000 2.88E-03 0.003 0.000 0.000 0.000 0.000 0.000 48.0 9.60E-02 6.60E-08 4.97E.02 0.000 I1.62E-03 0.004 0.000 0.000 0.000 0.000 0.000 72.0 1.04E-01 0.000 2.58E-02 0.000 I1.59E-04 0.004 0.000 0.000 0.000 0.000 0.000 96.0 1.10E-01 0.000 1.3 1E-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 1.43E-06 0.005 0.000 0.000 0.000 0.000 0.000 144.0 1.20E-01 0.000 3.302-03 0.000 I1.35E-07 0.006 0.000 0.000 0.000 0.000 0.000 168.0 1.25E-01 0.000 1.65E-03 0.000 I1.27E-08 0.007 0.000 0.000 0.000 0.000 0.000 336.0 1.63E-01 0.000 I1.28E-05 0.000 0.000 0.017 0.000 0.000 0.000 0.000 0.000 504.0 2.06E-01 0.000 9.49E-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 NOT3 appear in the table contribute less than ten percent of the whole body and thyroid dose totals.

Page 43 of 56 Page

~REFERENCE 43of56 USE

( POINT BEACH NUCLEAR PLANT ( EPIP 1.3 (

EMERGENCY PLAN IMPLEMENTING PROC.4JRES SAFETY RELATED Revision 31 DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATIONS August 29, 2003 TABLE 7 LOCA SOURCE TERM ACTIVITY FRACTIONS - CONTAINMENT SPRAY USED Page 2 of 8 Time 1-131 1-133 Kr-87 Kr-88 Xe-133 Xe-135 Xe-135m Xe-138 Rb-88 Cs- 138 0.0 3.19E-06 7.16E-06 1.08E-01 1.52E.01 2.851E-01 6.08E-02 7.73E-02 2.52E-O1 0.00 0.00 0.5 3.55E-06 7.82E3-06 9.17E-02 1.SOE-01 3. 171-01 6.92E-02 3.861E-02 8.57E-02 1.09E-01 7.34E-02 1.0 3.97E-06 8.64E-06 7.84E-02 1.48E-01 3.55E-01 7.80E2-02 2.8 IE-02 2.93E-02 1.46E-01 6.84E-02 1.5 4.39E-06 9.381E-06 6.60E-02 IA45E-01 3.921E-01 8.64E3-02 2.59E-02 9.90E-03 1.55E-01 4.83E-02 2.0 4.77E-06 I .0 E-OS 5.47E-02' 1.40E.01 4.2613-01 9.361E-02 2.57E-02 3.30E-03 1.54E-01 3.04E-02 2.5 5.12E-06 1.07E-05 4.48E.02 1.33E-01 4.57E-01 1.OOE-01 2.59E-02 1.08E-03 1.47E-01 1.80E-02 3.0 5.43E-06 l.I E-05 3.62E.02 1.25E-01 4.851E-0 I 1.06E-01 2.60E3-02 3.5 IE-04 1,39E-01 1.03E-02 4.0 5.99E-06 1I9E-05 2.32E-02 1.07E-01 5.34E-01 1.15E-01 2.601E-02 3.61E-05 1.20E-01 3.24E-03 5.0 6.47E-06 I1.25E3-05 1.46E-02 9.08E-02 5.77E-01 1.22E.O1 2.541E-02 3.65E-06 1.02E-01 9.701E-04 6.0 6.89E-06 I1.291E-05 9.04E.,03 7.63E-02 6.14E-01 1.27E-01 2.45E-02 3.63E-07 8.52E-02 2.87E-04 7.0 7.26E-06 1.32E-05 5.54E-03 6.26E-02 6.47E-01 1.30E-0J1 2.33E.02 0.00 7.03E-02 8.39E-05 8.0 7.61RE-06 1.34E3-05 3.37E-03 5.15E-02 6.77E-01 1.32E-01 2.21E-02 0.00 5.76E-02 2.4 RE-0S 9.0 7,90E-06 1.35E-05 2.03E-03 4.19E-02 7.02E-01 1.33E-01 2.08E-02 0.00 4.69E-02 6.93E-06 10.0 8. i6E-06 I1.34E3-05 1.22E-03 3.39E-02 7.25E-01 1.33E-01 1.94E.02 0.00 3.79E-02 1.98E-06 12.0 8.60E-06 I1.33E-05 4.36E3-04 2.19E-02 7.63E-01 1.30E-01 1.67E-02 0.00 2.46E-02 1.59E-07 18.0 9.50E-06 1.23E-05 1.86E-05 5.61E-03 8.37E-01 1.09E.O1 1.0 IE-02 0.00 6.27E-03 0.00 24.0 1.0IE-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 30.0 I.OSE-OS 9.38E-06 3.05E-08 3.3 IE-04 9.10E-O1 6.22E-02 3.35E-03 0.00 3.70E-04 0.00 36.0 1.08E-05 8,04E-06 0.00 7.89E-05 9.30E-01 4.45E-02 1.90E-03 0.00 8.8 1E-05 0.00 42.0 1.I OE-0S 6.87E-06 0.00 1.87E-05 9.45E-01 3.14E-02 1.06E-03 0.00 2. 1OE-05 0.00 48.0 1.1 3E-05 5.83E-06 0.00 4.41E-06 9.56E-01 2.17E-02 5.94E-04 0.00 4.93E-06 0.00 72.0 1.20E-0S 2.96E-06 0.00 1.34E-06 9.75E-01 4.53E-03 5.70E-05 0.00 0.00 0.00 96.0 1.25E-05 1.49E-06 0.00 0.00 9.80E-01 8.84E-04 5.38E-06 0.00 0.00 0.00 120.0 1.3 1E-OS 7.49E-07 0.00 0.00 9.82E-01 1.67E-04 5.08E-07 0.00 0.00 0.00 144.0 1.37E-05 3.77E-07 0.00 0.00 9.83E-01 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 2.59E-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-OS 0.00 0.00 0.00 8.48E-01 0.00 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 44 of 56 REFERENCE USE

( POINT BEACH NUCLEAR PLANT f EPIP 1.3 (

EMERGENCY PLAN IMPLEMENTING PROCL JRES SAFETY RELATED(

Revision 31 DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATIONS August 29, 2003 TABLE 7 GAP ACTIVITY RELEASE SOURCE TERM ACTIVITY FRACTIONS - CONTAINMENT SPRAY NOT USED Page 3 of 8 Time 1-431 1-133 1-135 Kr.R5m Kr-R7 Kr-RR Xe-133 Xe- 135 Xe-138 Rb-88 Cs-138 0.0 6.34E-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 7.18E-04 1.58E-03 1.41 E-03 0.057 0.093 0.151 0.322 0.067 0.086 0.110 0.074 I.0 8.11E-04 1.76E-03 1.5 1E-03 0.060 0.080 0.151 0.361 0.074 0.030 0.148 0.069 I.5 9.01E.04 1.92E-03 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 1.66E-03 0.062 0.056 0.144 0.439 0.084 3.38E-03 0.158 0.031 2.5 1.06E-03 2.20E-03 1.7 1E-03 0.062 0.046 0.137 0.471 0.088 1I.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 .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 1.36E-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 lA6E-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 1.55E-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 1.63E-03 2.85E-03 I .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 1.41E-03 0.037 0.002 0.045 0.747 0.088 0.000 0.050 0.000 10.0 175E-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 I.85E-03 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 2.21E-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 1.69E-03 1.27E-04 0.001 0.000 0.000 0.948 0.017 0.000 0.000 0.000 42.0 2.30E-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-0S 0.000 0.000 0.000 0.959 7.47E-03 0.000 0.000 0000 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 2.59E-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 4.8 IE-05 0.000 0.000 0.000 144.0 2.80E-03 7.72E-05 3.14E-09 0.000 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 1.316E-I I 0.000 0.000 0.000 504.0 4.91E-03 2.26E-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: 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 45 of 56 REFERENCE USE

POINT BEACH NUCLEAR PLANT (

( EMERGENCY PLAN IMPLEMENTING PROCL JRES f EPIP 1.3 SAFETY RELATED(

Revision 31 DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATIONS August 29, 2003 TABLE 7 GAP ACTIVITY RELEASE SOURCE TERM ACTIVITY FRACTIONS - CONTAINMENT SPRAY USED Page 4 of 8 Time I-I31 1.133 Kr-R7 Kr-RR Xe-133 Xc-135 Xe-138 Rb-88 Cs- 138 0.0 6.38E-08 I1.43E-07 1.08E.01 1.52E-01 2.86E-0OI 6.06E3-02 2.51E01 0.00 0.00 0.5 7.22E3-08 1.59E-07 9.31E-02 1.52E-01 3.24E-01 6.78E5-02 8.67E-02 1.10E-01 7.45E02 1.0 8.15SE-OS 1.77E-07 8.03E-02 1.52E-01 3.63E-01 7.46E3-02 3.00E-02 1.49E-01 6.98E-02 1.5 9.06E-08 I1.94E-07 6.81E-02 1.50E-O1 4.0413-01 8.0 1E-02 1.02E-02 1.60E-01 4.95E-02 2.0 9.87E-08 2.08E3-07 5.65E-02 1.44E-01 4.42E-04 8.45E-02 3.40E-03 1.59E-01 3.13E-02 2.5 I.071E-07 2.2213-07 4.66E-02 1.38E-01 4.74E-0I 8.81IE-02 I 12E-03 1.54E-01 1.87E-02 3.0 1I3E-07 2.32E3-07 3.78E.02 1.30E-01 5,05E-01 9.04E-02 3.65E-04 1.45E-01 1.08E.02 4.0 2.49E3-07 2.44E-02 1.13E-01 5.6 1E-0OI 9.36E-02 3.78E-05 1.26E-01 3.38E-03 5.0 1.37E-07 2.631E-07 1.55E-02 9.64E-02 6.08E-01 9.48E-02 3.84E-06 1.08E-01 1.03E-03 6.0 1.47E-07 2.75E-07 9.64E-03 8.13E.02 6.50EO1 9.46E.02 0.00 9.06E-02 3.05E-04 7.0 1.56E-07 2.8S13-07 5.92E-03 6.70E-02 6.89E-01 9.351E-02 0.00 7.50E-02 8.92E-05 8.0 1.64E-07 2.87E-07 3.62E-03 5.54E.02 7.21E-01 9.16E.02 0.00 6.19E-02 2.59E-05 9.0 1.701320 2.89E-07 2.19E-03 4.50E.02 7-51E-01 8.87E-02 0.00 5.04E-02 7.45E-06 10.0 1.761E-07 2.9 E-07 1.32E-03 3.66E-02 7,76E01 8.54E-02 0.00 4.10E-02 2.12E-06 12.0 I.86E-07 2.89E-07 4.7 1E-04 2.37E.02 8.18E-01 7.81E-02 0.00 2.66E-02 0.00 18.0 2.0611-07 2.02E-05 6.07E-03 8.90E-01 5.65E-02 0.00 6.79E-03 0.00 24.0 2. 161-07 2.32E-07 0.00 1I47E.03 9.24E-01 3.85E-02 0.00 1.64E-03 0.00 30.0 2.22E-07 1.98E-07 0.00 3.501E-04 9.42E-01 2.58E-02 0.00 3.921E-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 IE-07 I.43E3-07 0.00 I.9513-05 9.59E-01 1.14E-02 0.00 2.18E-05 0.00 48.0 2.34E-07 1.21 E-07 0.00 4.58E-06 9.63E-01 7.50E-03 0.00 5.13E-06 0.00 72.0 6.1 IE-08 0.00 0.00 9.70E-01 1.40E-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 9.71E.01 4.82E-05 0.00 0.00 0.00 144.0 2.81IE-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 1.64E-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 5.65E-07 0.00 0.00 0.00 6.52E.01 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 46 of 56 REFERENCE USE

( POINT BEACH NUCLEAR PLANT ( EPIP 1.3 (

EMERGENCY PLAN IMPLEMENTING PROCi'tJRES SAFETY RELATED(

Revision 31 DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATIONS August 29, 2003 TABLE 7 FUEL HANDLING ACCIDENT SOURCE TERM ACTIVITY FRACTIONS - CONTAINMENT SPRAY NOT USED Page 5 of 8 Time 3lI 41 1-I32 -I 3 I-13A 1-1 35 Kr-Ri Kr-Rim KriR7 Xe-133 Rh-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 2.17E-03 0.000 2.55E-04 0.000 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 2.17E-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 2.18E-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 2.18E-03 0.000 2.4 1E-04 0.000 2.37E-07 0.014 0.000 0.000 0.964 0.000 0.000 3.0 2.18E-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 0.000 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 2.21E-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 2.22E-03 0.000 1.95E-04 0.000 1.13E-07 0.015 0.000 0.000 0.965 0.000 0.000 12.0 2.22E-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 2.27E-03 0.000 1.30E-04 0.000 2.87E-08 0.016 0.000 0.000 0.966 0.000 0.000 30.0 2.31E-03 0.000 I. IOE-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 2.37E-03 0,000 6.53E-05 0.000 2.7 1E-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 2.71 E-03 0.000 8.24E-06 0.000 0.000 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 5.009-03 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 0.000 0.560 0.000 0.000 Notes: I1. 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 tahle 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 PROCL.- JRES SAFETY RELATED(

Revision 31 DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATIONS August 29, 2003 TABLE 7 FUEL HANDLING ACCIDENT SOURCE TERM ACTIVITY FRACTIONS - CONTAINMENT SPRAY USED Page 6 of 8 Time 1-131 Xe-133 0.0 2.17E-07 9.66E-01 0.5 2.18E-07 9.66E-01 I.0 2.17E-07 9.66E-01 1.5 2.I8E-07 9.66E-01 2.0 2.19E-07 9.66E-01 2.5 2.18E-07 9.66E-O1 3.0 2.19E-07 9.66E-01 4.0 2.20E-07 9.67E01 5.0 2.20E-07 9.67E-01 6.0 2.20E-07 9.67E-01 7.0 2.2.E-07 9.67E-01 8.0 2.21E-07 9.67E-01 9.0 2.21E-07 9.67E-01 10.0 2.22E-07 9.67E-01 12.0 2.22E-07 9.67E-01 18.0 2.26E-07 9.68E-01 24.0 2.28E-07 9.68E-01 30.0 2.31 E-07 9.68E-01 36.0 2.33E-07 9.68E-01 42.0 2.36E-07 9.68E-01 48.0 2.37E-07 9.68E-01 72.0 2.49E-07 9.68E-01 96.0 2.59E-07 9.66E-01 120.0 2.7 1E-07 9.64E-01 144.0 2.83E-07 9.61E-01 168.0 2.94E-07 9.58E-01 336.0 3.85E-07 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: 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.

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( POINT BEACH NUCLEAR PLANT ( EPIP 1.3 (

EMERGENCY PLAN IMPLEMENTING PROCjiJRES SAFETY RELATED(

Revision 31 DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATIONS August 29, 2003 TABLE 7 STEAM GENERATOR TUBE RUPTURE SOURCE TERM - - RELEASE MODE - THROUGH THE CONDENSER - ACTIVITY FRACTIONS Page 7 of 8 Time 1-131 1-133 1-135 Kr-85 Kr-85m Kr-88 Xe- 133 Xe- 135 Xe-138 Rb-88 Cs-138 0.0 3.92E-08 3.05E-08 3.16E-08 0.933 0.030 0.008 0.011 4.03E-03 0.013 0.000 0.000 0.5 3.93E-08 3.OOE-08 3.02E-08 0.937 0.028 0.007 0.011 3.90E-03 0.004 4.90E-03 3.43E-03 1.0 3.94E-08 2.98E-08 2.88E-08 0.943 0.026 0.006 0.011 3.77E-03 1.24E-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 2.61 E-08 0.952 0.023 0.005 0.011 3.53E-03 1.1 6E-04 5.22E.03 1.06E-03 2.5 3.98E-08 2.86E-08 2.50E-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 2.8 1E-08 2.37E-08 0.955 0.019 0.004 0.011 3.28E-03 1.08E-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 3.08E-03 1.02E-06 3.27E-03 9.06E-05 5.0 3.99E-08 2.66E-08 1.95E-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 1.76E-08 0.970 0.012 0.002 0.011 2.66E-03 8.89E-09 2.01E-03 7.02E-06 7.0 3.99E-08 2.50E-08 1.59E-08 0.973 0.011 0.001 0.011 2.47E-03 0.00 1.57E-03 1.94E-06 8.0 3.98E-08 2.42E-08 1.44E-08 0.976 0.009 0.001 0.011 2.30E-03 0.00 1.23E-03 0.00 9.0 3,97E-08 2.35E-08 I.30E-08 0.978 0.008 0.001 0.010 2.14E-03 0.00 9.61E-04 0.00 10.0 3.96E-08 2.27E-08 1I.18E-08 0.979 0.007 0.001 0.010 1.98E-03 0.00 7.53E-04 0.00 12.0 3.95E-08 2.13E-08 9.57E-09 0.982 0.005 0.00 0.010 1.71E-03 0.00 4.60E-04 0.00 18.0 3.89E-08 1.74E-08 5.17E-09 0.987 0.002 0.00 0.010 1.09E-03 0.00 1.04E-04 0.00 24.0 3.8 1E-08 1.42E-08 2.78E-09 0.989 0.001 0.00 9.80E-03 6.92E-04 0.00 2.38E-05 0.00 30.0 3.73E-08 1.16E-08 1.49E-09 0.990 0.00 0.00 9.48E-03 4.39E-04 0.00 5.38E-06 0.00 36.0 3.65E-08 9.48E-09 8.01E-10 0.990 0.00 0.00 9.24E.03 2.79E-04 0.00 1.22E-06 0.00 42.0 3.58E-08 7.72E-09 4.30E-I0 0.991 0.00 0.00 8.91E-03 1.77E-04 0.00 0.00 0.00 48.0 3.5 1E-08 6.29E-09 0.00 0.991 0.00 0.00 8.66E-03 1.12E-04 0.00 0.00 0.00 72.0 3.22E-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 2.95E-08 1.23E-09 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-08 5.40E- I0 0.00 0.994 0.00 0.00 5.83E-03 0.00 0.00 0.00 0.00 144.0 2.49E-08 2.38E-10 0.00 0.995 0.00 0.00 5.1 IE-03 0.00 0.00 0.00 0.00 168.0 2.28E5-08 1.05E-I 0 0.00 0.996 0.00 0.00 4.48E-03 0.00 0.00 0.00 0.00 336.0 I .26E-08 3.40E- 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 0.00 0.00 672.0 3.80E-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. 19E-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 C EPIP 1.3 (

( EMERGENCY PLAN IMPLEMENTING PROCE JRES SAFETY RELATED(

Revision 31 DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATIONS August 29, 2003 TABLE7 STEAM GENERATOR TUBE RUPTURE SOURCE TERM - - RELEASE MODE - NOT THROUGH THE CONDENSER - ACTIVITY FRACTIONS Page 8 of 8 Time 1-131 1-133 1-135 Kr-85 Kr-85m Kr-88 Xe-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.OOE-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 I.5 3.95E-04 2.94E-04 2.74E-04 0.947 0.024 0.005 0.011 3.65E-03 3.78E-04 5.70E-03 1.84E-03 2.0 3.96E-04 2.90E-04 2.61E-04 0.952 0.023 0.005 0.011 3.532-03 1.16E-04 5.22E-03 1.06E-03 2.5 3.98E-04 2.86E-04 2.49E-04 0.955 0.021 0.004 0.011 3.41 E-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 4.14E-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 9.51 E-08 2.56E-03 2.532-05 6.0 3.98E-04 2.58E-04 1.76E-04 0.970 0.012 0.002 0.011 2.66E-03 8.89E-09 2.00E-03 7.01 E-06 7.0 3.99E.04 2.50E-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 2.42E-04 1.44E-04 0.976 0.009 0.001 0.011 2.30E-03 0.00 1.23E-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.I8E-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 1.71 E-03 0.00 4.59E-04 0.00 18.0 3.89E-04 1.74E-04 5.16E-05 0.987 0.002 0.00 0.010 1.09E-03 0.00 1.04E-04 0.00 24.0 3.81E-04 1.42E-04 2.77E-05 0.989 0.001 0.00 9.80E-03 6.92E-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 2.31 E-06 0.991 0.00 0.00 8.66E-03 1.12E-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 1.23E-05 0.00 0.993 0.00 0.00 6.64E-03 2.96E-06 0.00 0.00 0.00 120.0 2.71E-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 IE-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 1.26E-04 3.40E-09 0.00 0.998 0.00 0.00 1.79E-03 0.00 0.00 0.00 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: 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 50 of 56 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 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 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 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 (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 90°.

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 52of 56 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 2003 RECOMMENDATIONS ATTACHMENT B GENERAL EMERGENCY OFFSITE PROTECTIVE ACTIONS EMERGENCY Declared Recommend Evacuation of 2-mile Radius and 5 miles Downwind. (1)

K i/ ~Substantial\

Core Damage in Progress or Projected? (Actual/Potential for No

> 20% Fuel Damage)

\(2)

Yes, (1) Situations requiring urgent action Initial Recomrr by offsite officials (based on control Fission Product is approp room indicators, no dose Inventory in Containment? No- P Evacuate projections required). (More than Gap) Radius and Downwin(

(2) >30,000 R/hr in containment high radiation monitors.

Yes (3) LOSS criteria for RCS barrier in EPIP 1.2, Attachment C, exceeded.

(4) LOSS criteria for containment Imminent barrier in EPIP 1.2, Attachment C. Projected Containment Failure or No exceeded. Inr-v? Relea...

Page 53 of 56 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES SAFETY RELATED Revision 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 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 31 DOSE ASSESSMENT AND PROTECTIVE ACTION August 29, 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 LPT 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 13, 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 "LPT 1" 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"\Prntdrvs\1386\HP4000- 1\PC 16\Oemnt40.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 55 of 56 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 1.3 EMERGENCY PLAN IMPLEMENTING PROCEE )URES SAFETY RELATED Revision 31 DOSE ASSESSMENT AND PROTECTIVE ACTI1 O)N August 29, 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 4.3 EMERGENCY OPERATIONS FACILITY (EOF) ACTIVATION AND EVACUATION DOCUMENT TYPE: Technical CLASSIFICATION: NNSR REVISION: 30 EFFECTIVE DATE: August 29, 2003 REVIEWER: N/A 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 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 30 EMERGENCY OPERATIONS FACILITY (EOF) August 29, 2003 ACTIVATION AND EVACUATION TABLE OF CONTENTS SECTION TITLE PAGE 1.0 PURPOSE .3 2.0 PREREQUISITES .3 3.0 PRECAUTIONS AND LIMITATIONS .5 4.0 INITIAL CONDITIONS .5 5.0 PROCEDURE ............ 6 5.1 Activation ......... 6 5.2 Evacuation ......... 7

6.0 REFERENCES

........... 7 7.0 BASES .......... 8 ATTACHMENT A EMERGENCY OPERATIONS FACILITY LAYOUT ...................................... 9 ATTACHMENT B OPERATION OF THE EOF EMERGENCY VENTILATION SYSTEM &

ANNUNCIATOR PANEL ........................................................................ 10 ATTACHMENT C DELETED - MOVED TO EPIP 1.3 ................................................................... 12 ATTACHMENT D ACTIVATION OF THE IODINE AND NOBLE GAS (ING)

RADIATION MONITORS ........................................................................ 13 ATTACHMENT E PLANT PROCESS COMPUTER SYSTEM (PPCS) .............. .......................... 15 ATTACHMENT F WPS - KNPP SITE BOUNDARY FACILITY .................... .............................. 23 ATTACHMENT G ALTERNATE EMERGENCY OPERATIONS FACILITY (AEOF) 700 NORTH ADAMS STREET, GREEN BAY ................................................ 24 ATTACHMENT H ACTIVATION OF THE REMOTE PPCS WAVE APPLICATION ................. 26 Page 2 of 27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 30 EMERGENCY OPERATIONS FACILITY (EOF) August 29, 2003 ACTIVATION AND EVACUATION 1.0 PURPOSE This procedure provides instructions for the activation of the Emergency Operations Facility (EOF). The EOF is activated upon declaration of an ALERT, or higher classification, or at any other time deemed necessary by the Shift Manager (SM). Activation of the EOF does not require the declaration of an emergency. Attachment A, Emergency Operations Facility Layout, describes the facility layout.

This procedure also describes the method by which the EOF and Offsite Radiation Protection Facility (OSRPF) is evacuated and responsibilities transferred.

2.0 PREREQUISITES 2.1 Responsibilities 2.1.1 Emergency Director:

a. Directs the overall management of the emergency response and recovery operations, including requests for federal assistance.

b. Upon activation of the EOF, assumes a formal turnover from the SM for non-delegable responsibilities, including-

• Classification/Re-classification of emergencies

• Protective Action Recommendations

• Notification of Federal, State, and County authorities

• Authorizing the use of potassium iodide

• Authorizing emergency radiation dose extensions

c. Decision to evacuate the EOF and OSRPF and relocate to alternate areas.

2.1.2 EOF Manager:

a. EOF activation prior to the arrival of the Emergency Director.

b. Commands and controls the EOF emergency response activities.

Page 3 of 27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 30 EMERGENCY OPERATIONS FACILITY (EOF) August 29, 2003 ACTIVATION AND EVACUATION 2.1.3 Dose/PAR Coordinator:

a. Directs the Offsite Radiation Protection Facility Coordinator to activate the EOF emergency ventilation system per Attachment B, Operation of the EOF Emergency Ventilation System & Annunciator Panel.

b. Activates the Wisconsin Electric Dose Assessment Program - WEDAP per EPIP 1.3, Dose Assessment and Protective Action Recommendations.

c. Initiates the activation of the Iodine and Noble Gas (ING) Monitors per Attachment D, Activation of the Iodine and Noble Gas (ING) Radiation Monitors.

d. Directs offsite dose assessment. Develops Protective Action Recommendations (PARs) based on dose for the Emergency Director's approval.

2.1.4 Plant Status Monitor:

a. Activates Plant Process Computer System (PPCS) workstation per Attachment E, Plant Process Computer System (PPCS).

b. Supports event monitoring by serving as the resource for plant and environmental data. Maintains plant status boards.

2.1.5 ERF Communicator - Maintains continuous communications between the CR, TSC, EOF and JPIC. Assists with event classification.

2.1.6 Dose/PAR Monitor - Supports radiological response by serving as resource for offsite assessment of radiological conditions and assists with development of Protective Action Recommendations (PARs) based on dose. Maintains rad/met status boards.

2.1.7 HPN/SRC Communicator - Communicates information to NRC and State of Wisconsin Department of Health and Family Services - State Radiological Coordinator.

2.1.8 State/County Communicator - Communicates information to State and County agencies.

2.1.9 State Liaison - Ensures that the State of Wisconsin has adequate information to implement offsite emergency plans. Reports to the State Emergency Operations Center.

Page 4 of 27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 30 EMERGENCY OPERATIONS FACILITY (EOF) August 29, 2003 ACTIVATION AND EVACUATION 2.1.10 County Liaison - Ensures that Kewaunee County and Manitowoc County has adequate information to implement offsite emergency plans. Reports to the County Emergency Operation Centers.

2.1.11 Resource Coordinator - Obtains resources needed for emergency response, including communications with supporting agencies.

2.1.12 Offsite Assembly Area Coordinator - Assists the Security Coordinator in.

controlling site ingress/egress, including release and/or evacuation of personnel to offsite assembly areas.

2.1.13 Administrative Support Leader - Provides clerical and administrative support to emergency organization.

2.2 Equipment 2.2.1 EOF inventory per EPMP 1.3, Routine Inventory of TSC, EOF, AEOF, JPIC and OSC Emergency Preparedness Supplies.

2.2.2 PPCS Workstations 2.2.3 WEDAP Workstation 2.2.4 Communications equipment per EPMP 2. 1, Testing of Communications Equipment.

3.0 PRECAUTIONS AND LIMITATIONS Evacuation of the EOF shall include the coordination of the evacuation for the OSRPF.

4.0 INITIAL CONDITIONS 4.1 This procedure shall be implemented upon declaration of an ALERT or higher classification or at the discretion of the Shift Manager to provide the Control Room support with offsite interfaces.

4.2 Evacuation of the EOF and OSRPF shall be completed when any of the following conditions exist.

4.2.1 Emergency response personnel radiation doses in the EOF/OSRPF are exceeding or are projected to exceed the following for the duration of the event:

a. Whole body (TEDE) 4 rem (calculated)

b. Thyroid (CDE) 25 rem (calculated)

Page 5 of 27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 30 EMERGENCY OPERATIONS FACILITY (EOF) August 29, 2003 ACTIVATION AND EVACUATION 4.2.2 Other emergency conditions exist (i.e., fire, toxic or flammable gases, or loss of power).

5.0 PROCEDURE 5.1 Activation 5.1.1 The EOF Manager shall ensure the completion of the EOF Position Instruction Manual 4.2, EOF Manager.

NOTE: The facility may be activated earlier based upon the EOF Manager's discretion if determined there is an understanding of the events in progress and adequate staffing resources in -place to respond to the emergency.

5.1.2 Minimum staff positions are:

a. Emergency Director

b. EOF Manager

c. Dose/PAR Coordinator

d. State/Counties Communicator

e. ERF Communicator

f. OSRPF Coordinator

g. Resource Coordinator 5.1.3 The EOF emergency ventilation system, iodine and noble gas (ING) radiation monitors, and PPCS equipment shall be activated per the attachments to this procedure.

5.1.4 Each ERO position shall activate and assume their area of responsibility and function within the EOF using their Position Instruction Manual.

Page 6of 27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 30 EMERGENCY OPERATIONS FACILITY (EOF) August 29, 2003 ACTIVATION AND EVACUATION 5.2 Evacuation 5.2.1 The EOF and OSRPF will be evacuated under the direction of the EOF Manager.

5.2.2 The key to an orderly evacuation is good communications, formal turnover with personnel assuming EOF and OSRPF responsibilities, and documentation of actions and notifications.

5.2.3 Minimize the number of vehicles used to transport people and equipment to other facilities.

a. The Alternate Offsite Radiation Protection Facility is the KNPP Site Boundary Facility (SBF) located about one mile west of KNPP on Kewaunee County Nuclear Road per Attachment F, WPS - KNPP Site Boundary Facility.

b. The Alternate EOF (AEOF) is located in the Wisconsin Public Service corporate office at 700 North Adams Street, Green Bay, WI in Room D2-3 (per Attachment G, AEOF - Green Bay). Data from the PPCS is obtained per Attachment H, Activation Of The Remote PPCS WAVE Application.

5.2.4 Transfer responsibility for all communications to the TSC until the AEOF is activated. Some communicators may temporarily relocate to that facility prior to activation of the AEOF.

5.2.5 Transfer responsibility for the OSRPF oversight and offsite dose assessments for protective action recommendations to the TSC.

5.2.6 Ensure all personnel are accounted for after reaching the relocation area(s).

5.2.7 Activate the AEOF by each ERO position reassuming their area of responsibility and function using their Position Instruction Manual.

5.2.8 Develop an immediate plan for reentry of the EOF/OSRPF area, if possible.

6.0 REFERENCES

6.1 Point Beach Nuclear Plant Emergency Plan 6.2 EPIP 1.3, Dose Assessment and Protective Action Recommendations 6.3 EPIP 4.7, Offsite Radiation Protection Facility (OSRPF) Activation and Evacuation Page 7 of 27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 30 EMERGENCY OPERATIONS FACILITY (EOF) August 29, 2003 ACTIVATION AND EVACUATION 6.4 EPMP 1.3, Routine Inventory of TSC, EOF, AEOF, JPIC and OSC Emergency Preparedness Supplies 6.5 EPMP 2.1, Testing of Communications Equipment 6.6 PIM EOF 4.1, Emergency Director 6.7 PIM EOF 4.2, EOF Manager 6.8 PIM EOF 4.3, Administrative Support Leader 6.9 PIM EOF 4.4, Resource Coordinator 6.10 PIM EOF 4.5, Dose/PAR Coordinator 6.11 PIM EOF 4.6, Dose/PAR Monitor 6.12 PIM EOF 4.7, HPN/SRC Communicator 6.13 PIM EOF 4.10, State/County Communicator 6.14 PIM EOF 4.11, State Liaison 6.15 PIM EOF 4.12, County Liaison 6.16 PIM EOF 4.13, Offsite Assembly Area Coordinator 6.17 PIM EOF 4.14, ERF Communicator 6.18 PIM EOF 4.15, Plant Status Monitor 7.0 BASE!

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 B4 NUREG-0737, Clarification of TMI Action Plan Requirements B-5 Calculation 2002-0017, RE-242 High Alarm Setpoint Analysis, 8/19/02 B-6 CA025588, SBCC RMS Alarms Page 8 of 27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 30 EMERGENCY OPERATIONS FACILITY (EOF) August 29, 2003 ACTIVATION AND EVACUATION ATTACHMENT A EMERGENCY OPERATIONS FACILITY LAYOUT OSRPF 0

-0

-v m

Page 9of 27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 30 EMERGENCY OPERATIONS FACILITY (EOF) August 29, 2003 ACTIVATION AND EVACUATION ATTACHMENT B OPERATION OF THE EOF EMERGENCY VENTILATION SYSTEM & ANNUNCIATOR PANEL Page 1 of 2 NOTE: Contact the Control Room prior to implementing this procedure to advise them of the RMS alarm they will be receiving.

1.0 DESCRIPTION

- EMERGENCY VENTILATION SYSTEM The EOF's emergency ventilation system has a normal and emergency operation mode. Under all modes of operation, fresh air is taken in from the vent on the south end of the west side of the building. Under normal conditions the air is filtered by roughing and electrostatic filters. In the emergency mode, a minimum amount of outside air is taken into the building and incoming air is routed through an additional high efficiency particulate filter.

2.0 EMERGENCY OPERATION OF THE EMERGENCY VENTILATION SYSTEM 2.1 The control panel for the SBCC ventilation system (MI) is located in the mechanical equipment room. Access to the mechanical equipment room is through the men's restroom and locker area.

2.2 To shift from the normal to the emergency mode, manually place the switch S3 on panel Ml to the "Emergency" position.

3.0 EMERGENCY OPERATIONS POWER SUPPLY Electrical power to the Site Boundary Control Center, and therefore the EOF, is provided by Wisconsin Public Service Corporation (WPSC) via a distribution feeder. In case of loss of electrical power, call WPSC. The telephone number for WPSC can be found in the Emergency Telephone Directory.

4.0 DESCRIPTION

- EOF ANNUNCIATOR PANEL 4.1 The EOFs annunciator panel monitors eight parameters in the Site Boundary Control Center building. The control room may receive a common alarm upon annunciation of some of the eight alarms.

4.1.1 Holding tank high level - alarms on high level, holding tank must be pumped by a contractor.

4.1.2 Dosing tank high level - alarms on high level.

4.1.3 Fire detector - annunciates upon detection of a fire.

4.1.4 Emergency mode - annunciates when building HVAC system is switched to the emergency mode.

Page 10 of 27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 30 EMERGENCY OPERATIONS FACILITY (EOF) August 29, 2003 ACTIVATION AND EVACUATION ATTACHMENT B OPERATION OF THE EOF EMERGENCY VENTILATION SYSTEM & ANNUNCIATOR PANEL Page 2 of 2 4.1.5 Building temperature low - annunciates upon exceeding the setpoint for the building temperature. This usually indicates a heating system failure.

4.1.6 Pump failure - annunciates whenever a pump associated with control panel MI, does not start on demand, after a 30-second time delay.

4.1.7 Air filter plugged - annunciates when the electrostatic air filter is plugged and the differential pressure across the filter exceeds the setpoint.

4.1.8 Compressed air low pressure - annunciates when the air pressure in the supply header to the Johnson Controls control system falls below the setpoint.

4.2 Response to annunciator panel alarms.

4.2.1 Be prepared to respond to the Control Room questions regarding the cause of the alarm.

4.2.2 Take actions and/or call for the assistance as required.

Page I11 of 27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 30 EMERGENCY OPERATIONS FACILITY EOF) August 29, 2003 ACTIVATION AND EVACUATION ATTACHMENT C DELETED - MOVED TO EPIP 1.3 Page 12 of 27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 30 EMERGENCY OPERATIONS FACILITY (EOF) August 29, 2003 ACTIVATION AND EVACUATION ATTACHMENT D ACTIVATION'OF THE IODINE AND NOBLE GAS (ING) RADIATION MONITORS Page 1 of 2 Coordinate with the Offsite Radiation Protection Coordinator:

1.0 ACTIVATION 1.1 Install a new charcoal filter in the Iodine and Noble Gas Monitor.

1.2 Start the iodine and noble gas sample pump in the heating and ventilation room adjacent to the men's lavatory.

1.3 Record the initial sample flow rate and start time.

Flow Rate Start Time 2.0 INTERPRETATION OF RMS READOUTS 2.1 The concentration of noble gas is determined by multiplying the observed count rate on the readout labeled "RE-242" by the calibration constant posted adjacent to the meter.

The resulting units are gCi/cc Xe-133 dose equivalents.

2.2 The iodine activity on the charcoal cartridge is obtained by multiplying the observed count rate on the readout labeled "RE-241" by the calibration constant posted adjacent to the meter. The resulting units are gCi - I-131 dose equivalents.

2.3 Calculation 2002-0017 determined for RE-242 under LOCA accident conditions that each interval of 5000 cpm on the meter readout corresponds to a submersion dose rate of 100 mrem/hour in the environs outside the SBCC. (B-5) (B-6)

Page 13 of 27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 30 EMERGENCY OPERATIONS FACILITY (EOF) August 29, 2003 ACTIVATION AND EVACUATION ATTACHMENT D ACTIVATION OF THE IODINE AND NOBLE GAS (ING) RADIATION MONITORS Page 2 of 2 2.4 To convert the iodine activity into a concentration, calculate the volume of air that passed through the filter. The concentration of iodine is approximately the activity on the filter (Ci) divided by the total volume (cm3 ) for sampling periods less than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, this assumes no short-lived isotopes are present.

NOTE: For longer sampling periods and when short-lived iodine isotopes are expected to be present, the following formula may be used to calculate the iodine concentration:

C= (XAeXt)tS F p(l-eLts)

Where: Units C = concentration in air gCi/cc F = sample volume cc A = decay constant, 0.693T'/ 2 mind A = total activity on filter gCi t = elapsed time from sample stop to count start min ts = total sample time min p = filter collection efficiency Any changes to the alarm setpoints shall be made in accordance with the Radiation Monitoring System Alarm Setpoint & Response Book (RMSASRB) kept in the Control Room.

Page 14 of 27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 30 EMERGENCY OPERATIONS FACILITY (EOF) August 29, 2003 ACTIVATION AND EVACUATION ATTACHMENT E PLANT PROCESS COMPUTER SYSTEM (PPCS)

Page of 8 NOTE 1: Use PPCS terminal drops 121 (TSC) and 125 (EOF) to display the plant status board.

NOTE 2: Use PPCS terminal drops 122 (TSC) and 126 (EOF) to display the rad/met status board.

NOTE 3: If the PPCS workstation is inoperable, you can access PPCS data on a LAN computer per EPIP 4.3, Attachment H, Activation of the Remote PPCS Wave Application.

1.0 PPCS START UP (applies-to all PPCS monitor drops) 1.1 Turn on the monitors, if not already on.

1.2 Check if the affected unit is selected. PB 1@PPCS or PB2 @PPCS displayed in the lower right hand corner of screen.

1.3 IF the affected unit is selected, THEN go to Step 1.13 NOTE: The computer reboots when changing between units.

1.4 IF the affected unit is not selected on the PPCS screen, THEN obtain the PPCS user name and password from the envelope in the sealed facility storage cabinet.

1.5 Select the arrow above the menu icon and left click to bring up the WDPF Main Menu.

1.6 Click on the user/login menu:

NOTE 1: The user name and password are case sensitive (i.e. make sure Cap Locks is off).

NOTE 2: If multiple attempts to enter the user/login password fail, the system will lock out the drop for approximately 15 minutes before allowing a login to occur.

1.7 Enter the user name and password.

1.8 Left click on login.

1.9 Click on PB1 @PPCS or PB2@PPCS in the lower right corner to bring up the "Change Unit" window.

Page 15 of 27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 30 EMERGENCY OPERATIONS FACILITY (EOF) August 29, 2003 ACTIVATION AND EVACUATION ATTACHMENT E PLANT PROCESS COMPUTER SYSTEM (PPCS)

Page 2 of 8 1.10 Click on the desired unit, PB1 @PPCS or PB2@PPCS, in the "Change Unit" window pull down menu.

1.11 Click on "OK".

1.12 Click on "OK" in response to the "Change Unit Warning".

NOTE: You do not need to select "acknowledge" for the shutdown and reboot to occur.

1.13 Turn on the overhead projector by depressing the power (/I) switch at the front of the unit.

2.0 DISPLAY OF PPCS DATA 2.1 To display the Plant Status Board (PSB), go to Step 2.1. 1, OR to display the Rad/Met Status Board proceed to step 2.2.

2.1.1 Select window number (WI) from the menu bar.

NOTE: The DIRECTORY screen provides a display of all the screens available to the PPCS user.

2.1.2 Click the DIRECTORY icon at the bottom of the screen to bring up the DIRECTORY window.

2.1.3 Click on the Plant Status Board button under Miscellaneous (2225 for Unit 1 or 2725 for Unit 2) in the DIRECTORY window.

NOTE: If unable to view the menu bar, move the cursor to the very bottom of the screen and click, downsize the displayed window, or move the displayed window to the back of the desktop.

2.1.4 Select window number (W5) from the menu bar. This selects the window for the projected image.

2.1.5 To display the Plant Status Board screen with the projector:

a. Click the DIRECTORY icon at the bottom of the screen to bring up the DIRECTORY window.

Page 16 of 27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 30 EMERGENCY OPERATIONS FACILITY (EOF) August 29, 2003 ACTIVATION AND EVACUATION ATTACHMENT E PLANT PROCESS COMPUTER SYSTEM (PPCS)

Page 3 of 8

b. Move the mouse to the far right (off the monitor screen and onto the projected screen) and click on the Plant Status Board button under Miscellaneous (2225 for Unit 1 or 2725 for Unit 2) from the DIRECTORY window.

2.1.6 Go to Step 2.3 to manually enter data onto the projected screen and to Step 2.4 to trend plant data.

2.2 Displaying the Rad/Met Status Board 2.2.1 Select window number (Wl) from the menu bar.

NOTE: The DIRECTORY screen provides a display of all the screens available to the PPCS user.

2.2.2 Click the DIRECTORY icon at the bottom of the screen to bring up the DIRECTORY window.

2.2.3 Click on the Rad/Met button under Miscellaneous (2226 for Unit 1 or 2726 for Unit 2) from the DIRECTORY window.

NOTE: If unable to view the menu bar, move the cursor to the very bottom of the screen and click, downsize the displayed window, or move the displayed window to the back of the desktop.

2.2.4 Select window number (W5) from the menu bar. This selects the window for the projected image.

2.2.5 To display the Rad/Met Status Board screen with the projector:

a. Click the DIRECTORY icon at the bottom of the screen to bring up the DIRECTORY window.

b. Move the mouse to the far right (off the monitor screen and onto the projected screen) and Click on the Rad/Met Status Board button under Miscellaneous (2226 for Unit 1 or 2726 for Unit 2) from the DIRECTORY window.

2.2.6 Go to Step 2.3 to manually enter data onto the projected screen and to Step 2.5 to trend Radiation Monitoring System (RMS) data.

Page 17 of 27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 30 EMERGENCY OPERATIONS FACILITY (EOF) August 29, 2003 ACTIVATION AND EVACUATION ATTACHMENT E PLANT PROCESS COMPUTER SYSTEM (PPCS)

Page 4 of 8 2.3 Manual Entry of Data Fields 2.3.1 Move the mouse to the far right (off the monitor screen and onto the projected screen).

2.3.2 Click on the desired blue outlined block(s) to select the area for data or information entry.

NOTE: Use capital letters to increase the readability of the projected image.

2.3.3 Type the data or information to be displayed.

2.3.4 After updating the status board, print the applicable PPCS window in accordance with Step 3.0.

NOTE: All trends are viewed on the drop's monitor, not the projected image.

2.4 View and Trend Plant Status Data 2.4.1 Ensure a different window number W-2, W-3, or W-4 is selected.

- 2.4.2 Click on the plant system to be viewed or trended from the DIRECTORY screen.

2.4.3 Move the cursor to the desired data point (e.g. temperature, pressure).

2.4.4 Right click to bring up the menu window.

2.4.5 Left click on the menu option desired (Information or Mini-Trend). The information or trend will be displayed on the monitor screen.

2.4.6 If desired, groups or selected data points may be displayed by using the Trend Group Attribute Window by performing the following:

a. Left click on the Graphics icon on the lower tool bar to bring up the "Trend Display" window.

Page 18 of 27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 30 EMERGENCY OPERATIONS FACILITY (EOF) August 29, 2003 ACTIVATION AND EVACUATION ATTACHMENT E PLANT PROCESS COMPUTER SYSTEM (PPCS)

Page 5 of 8

b. Click on "Create".

c. Click on "Live Trend".

d. Click on "Modify Properties" to bring up the "Group Attributes Window".

e. To display a group, click on "Copy from Group" and perform Steps 2.4.6.f-g. If an individual data point is desired to be trended go directly to Step 2.4.6 h.

f. Click on the group you wish to trend from the Group listing in the "Select a Group" window.

g. Click "Apply", which closes the Select a Group window and then go to Step 2.4.61.

h. To display an individual point, click on "Add Point" on the Group Attribute Window.

NOTE 1: Up to eight (8) data points may be trended in each Trend Display Window.

NOTE 2: The point names may be found on the group listing as described in Step 2A.6 f above. A list of Point Names is also available on an operator aid at the Plant Status Board work areas.

i. Enter the point name (e.g. LT972 or RE21 1).

j. Click on "OK".

k. Continue to add points by repeating Steps 2.4.6 h. - j.

1. Select and change the live time interval, if desired.

m. Change the graph scales, if desired, by performing the following:

• Click on the point you which to change the scale.

• Click on modify.

Page 19 of 27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 30 EMERGENCY OPERATIONS FACILITY (EOF) August 29, 2003 ACTIVATION AND EVACUATION ATTACHMENT E PLANT PROCESS COMPUTER SYSTEM (PPCS)

Page 6 of 8

• Click on "Default" in Scale Limits

• Select "User Entered" from menu

• Select linear or logarithmic scale

• Enter the High scale value in the High block

• Enter the Low scale value in the Low block

• Click on "OK".

n. Click on "Apply." The graph will appear and display the information.

2.5 View and Trend Radiation Monitoring System (RMS) Data.

2.5.1 Ensure a different window number W-2,W-3, or W-4 is selected and then click on the RMS grid icon (2260 for Unit 1 and 2760 for Unit 2) from the DIRECTORY. The RMS Grid should be displayed.

2.5.2 Move the cursor to the desired RMS monitor number to be viewed or trended on the RMS Grid.

2.5.3 Right click to bring up the menu window.

2.5.4 Left click on the menu option desired (Information or Mini-Trend). The information or trend will be displayed on the monitor screen.

2.5.5 If desired, selected RMS points may be displayed by using the Trend Group Attribute window by performing Step 2.4.6.

2.5.6 To view the RMS history bar graph trends (last 24-1 minute periods, 24-10 minute periods, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or 24 days) click on the box in front of the desired RMS monitor.

Page 20 of 27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 30 EMERGENCY OPERATIONS FACILITY (EOF) August 29, 2003 ACTIVATION AND EVACUATION ATTACHMENT E PLANT PROCESS COMPUTER SYSTEM (PPCS)

Page 7 of 8 3.0 PRINTING PPCS SCREENS 3.1 If the background area behind the windows is not exposed, reduce the window size slightly.

NOTE: A screen printout may be obtained by following Step 3.2. Select "PrintScreen" instead of "Snapshot." No further actions are needed and the printout is routed automatically to the color printer.

3.2 With the cursor over the background area, hold down the right mouse button and scroll down until "Snapshot" is highlighted, then release the right button.

3.3 In the SNAPSHOT window, select HIDE WINDOW DURING CAPTURE and then click on the SNAP button. "Select Window" will appear on the bottom of the window.

NOTE: It takes approximately 5-8 seconds for the snapshot to be recorded. If you do not left click on the window desired within approximately 8 seconds after "Select window" is displayed, the snap process will stop.

3.4 Within 5 seconds of clicking on the SNAP button, left click on the window you desire to print. "Snap Succeeded" will appear on the bottom of the snapshot window after 5-8 seconds.

3.5 Click on "View" in the SNAPSHOT window. The Image Tool (V3.6FCS) window will appear and display the captured window.

3.6 Click on File>Print Preview on the Image Tool (V3.6FCS) window to preview the image to be printed. Do not confuse this with the Image Tool: Palette, which is not used and may be closed, if desired.

3.7 Click on File>Print on the Image Tool (V3.6FCS) window to display the tools used to modify the size and orientation of the print image.

3.8 Make adjustments to the orientation and size of the printed image:

3.8.1 Select the orientation (landscape or portrait).

3.8.2 Scale the size of the image using the slider or AV buttons, while viewing the image on the Image Tool Print Preview window.

Page 21 of 27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 30 EMERGENCY OPERATIONS FACILITY (EOF) August 29, 2003 ACTIVATION AND EVACUATION _

ATTACHMENT E PLANT PROCESS COMPUTER SYSTEM (PPCS)

Page 8 of 8 3.9 When in the TSC, select:

3.9.1 TSCLJ to print black and white.

3.9.2 TSCSC to print color.

3.10 When in the EOF, select:

3.10.1 SBCLJ to print black and white.

3.10.2 SBCSC to print color.

3.11 Click on "Print" in the Print or Print Preview window to print the selected screen.

3.12 IF the printer fails to print in the TSC, THEN check the ethernet switches on TSC-T on the rack in the Southwest corner wall rack are plugged in.

3.13 IF the printer fails to print in the EOF, THEN contact security to open the door to the Switch Room in the SBCC and check the ethernet switches on SBC-T are plugged in.

Page 22 of 27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 30 EMERGENCY OPERATIONS FACILITY (EOF) August 29, 2003 ACTIVATION AND EVACUATION ATTACHMENT F WPS - KNPP SITE BOUNDARY FACILITY WPS - KNPP SITE BOUNDARY FACILITY KEWAUNEE NUCLEAR PLANT POINT BEACH NUCLEAR PLANT MISHICOT Page 23 of 27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 30 EMERGENCY OPERATIONS FACILITY (EOF) August 29, 2003 ACTIVATION AND EVACUATION ATTACHMENT G ALTERNATE EMERGENCY OPERATIONS FACILITY (AEOF) 700 NORTH ADAMS STREET, GREEN BAY Page 1 of 2

i EAST RIVER ;:r )! N RE'S

~~~~~~~~~~~ 143 Hw 54, Hwy57

,Media Moitoring .

(A2) ., ir ~'B"Parking ot ~

(WPS' Public ER R G Parking  :-J

~~~~~~~~~~~~~~~~I- i AX DERivision

- ~~~~~~~~~:. MADISJ~iST.§$.

700N.Adams St: (Dl)~~~~~~~~~~~~~~~~~~~~~~~~~l K-EOF

&PB-AEOF~~~~~~~~~~~~~~~~~~

EMASYz FOX RIVER Entr'a Main . Respos C r Cr

' ~~ ~ ~ ~ j i:  : "'z:n KI. I-Take 1-43 north to Green Bay - Exit 187 Webster Avenue. Go south to University Avenue. Take University Avenue west across the East River to the next intersection, Elm Street. Take Elm Street west to N. Adams Street Page 24 of 27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 30 EMERGENCY OPERATIONS FACILITY (EOF) August 29, 2003 ACTIVATION AND EVACUATION ATTACHMENT G ALTERNATE EMERGENCY OPERATIONS FACILiTY (AEOF) 700 NORTH ADAMS STREET, GREEN BAY Page 2 of 2

• Pi 'ones kept in storage closet & must be setup HPN/SRC I

Communicator

• 920/433-7616

• 700/380-1002 *920/431-6407 (STA5) *700/380-1013 (STA18)

Offsite Assemt )ly HPN/PMCL

• 920/433-7628 Area Coordinat tor I *920/388-0103 -

I

• 920/431-6403 Rsuc (STA16)

• 920/433-7617 Resource Dose/PAR (STA6) Coordinator Monitor Dose/PAR Coordinator 70080-1011 1 700/380-1013 920/431-6402 (STA1) 920/431-6404 (STA4A)

MCL./RSCL l Two-Digit Dial-Selectl 920/388-0101 920-433-7621 Plant Status File EOF Managf er 920/388-0102 920/431-6451 Monitor CD (D-(STA2B) (STA14) 920/433-7613 920/433-7607 go 9)

Emergency 920/431-6401 920/431-6482 ERF Director (STA2) (STA2A) Communicator W 0 E M

KNPP Damme co 0E)

Two-Digit Dial-Select (STA1 0) 0 0)

State/Count,y ~201431-6405 Communicat or 920/433-7618 700/380-1015 N

(STA8) ENS CD c- x CO <

920/433-1131 0

cu CY)

(STA1 5A)

Admin Support Leader N+<

Page 25 of 27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 30 EMERGENCY OPERATIONS FACILITY (EOF) August 29, 2003 ACTIVATION AND EVACUATION ATTACHMENT H ACTIVATION OF THE REMOTE PPCS WAVE APPLICATION Page 1 of 2 CAUTION Periodically verify PPCS WAVE data is identical to PPCS data displayed at another emergency response facility.

1.0 For using the PBNP AEOF WAVE/WEDAP Notebook PC, complete the following steps OR go to Step 2.0 if using a Point Beach LAN computer in the TSC or EOF.

1.1 Connect PC to analog telephone line and power up PC.

1.2 Perform steps to logon by following the "Windows 2000 Project LAPTOP Dial-Up Instructions". (Located with Laptop Computer) 2.0 Log in to the computer dialog box using your assigned day-to-day ID and password.

3.0 Open Internet Explorer.

NOTE: It will take a few minutes for the Java applet software to load.

4.0 Enter ppcsprdOln to navigate to the PPCS web server. (Java applet will load and initialize).

5.0 When the initial unit selection screen appears, select Unit I or Unit 2.

Page 26 of 27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 30 EMERGENCY OPERATIONS FACILITY (EOF) August 29, 2003 ACTIVATION AND EVACUATION ATTACHMENT H ACTIVATION OF THE REMOTE PPCS WAVE APPLICATION Page 2 of 2 6.0 To display PPCS Directory, select "Display Process Diagram".

6.1 Select and click on the PPCS screen to be displayed.

6.2 Select Diagram Main Menu from the tool bar to return to the PPCS Directory or to display other PPCS screens.

7.0 To display information from a PPCS point, select Display Point Information.

8.0 To create a trend graph, perform the following:

8.1 Press the Groups button, THEN set the Plot Properties.

8.2 Select the desired points to trend.

8.3 IF required, select and change the Time Intervals.

8.4 After the graph is created, press the Tabular Trend button to view the data values.

9.0 To generate a data point review, select Display Point Review from PPCS HSR.

Page 27 of 27 REFERENCE USE