ML022410302

Radiological Emergency Response Plan Implementing Procedures

ML022410302
Person / Time
Site:	Kewaunee
Issue date:	08/21/2002
From:	Webb T Nuclear Management Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NRC-02-079
Download: ML022410302 (111)

Text

Kewaunee Nuclear Power Plant Point Beach Nuclear Plant N490 Highway 42 6610 Nuclear Road Kewaunee, WI 54216-9511 Two Rivers, Wl 54241 920.388 2560 920 755 2321 Nac Committed to Nuclea~rExcellen ,e Kewaunee / Point Beach Nuclear 5

Operated by Nuclear Management Company, LLC NRC-02-079 August 21, 2002 10 CFR 50, App. E U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Ladies/Gentlemen:

Docket 50-305 Operating License DPR-43 Kewaunee Nuclear Power Plant Radiological Emergency Response Plan Implementing Procedures Pursuant to 10 CFR 50 Appendix E, attached is the latest revisions to the Kewaunee Nuclear Power Plant Radiological Emergency Response Plan Implementing Procedures (EPIPs). These revised procedures supersede the previously submitted procedures.

Pursuant to 10 CFR 50.4, two additional copies of this letter and attachment are hereby submitted to the Regional Administrator, U. S. Nuclear Regulatory Commission, Region III, Lisle, Illinois. As required, one copy of this letter and attachment is also submitted to the Kewaunee Nuclear Power Plant NRC Senior Resident Inspector.

Sincerely, Thomas J. Webb Regulatory Affairs Manager SLC Attachment cc - US NRC Senior Resident Inspector, w/attach.

US NRC, Region III (2 copies), w/attach.

Electric Division, PSCW, w/o attach.

QA Vault, wo/attach. 1&0ý-45

DOCUMENT TRANSMITTAL KEWAUNEE NUCLEAR POWER PLANT FROM: - DIANE FENCL - KNPP TRANSMITTAL DATE 08-20-2002 EMERGENCY PLAN IMPLEMENTING PROCEDURES TRANSMITTAL FORM OUTSIDE AGENCY COPIES (1-20)

JT. Webb - NRC Document Control Desk (1)V Krista Kappelman - PBNP - EP (10)*

T. Webb - NRC Region I1 (2,3)* Craig Weiss - Alliant Energy (11)*

T. Webb - NRC Resident Inspector (4) (receives Appx. A phone numbers)*

T. Webb - State of Wisconsin (5)* Jill Stern - Nuclear Management Company (12)*

T. Webb - KNPP QA Vault (NRC Letter & Memo Only) (15)*

PERSONAL COPIES (21-40) These copies are for the personal use of the listed individuals for reference or emergency response.

J. Bennett (33) D. Seebart (24) J. Ferris (13) T. Coutu (28)

REFERENCE COPIES - CUSTODIAN (41-100) These copies are for general reference by anyone. They are distributed throughout the plant and corporate offices. The named individual is the responsible custodian for the procedures and shall insure they are properly maintained.

NO Library - KNPP (59) Resource Center - Training (82)

C. Sternitzky - ATF-2 (44) D. Krall - CR/SS Office (51, 56)

M. Daron - Security Building (46) M. Lambert - TSC (50)

M. Lambert - EOF (81) W. Galarneau - RAF (53)

M. Lambert - OSF (52) W. Galarneau - SBF/EMT (54)

LOREB - STF (62, 66, 67,68, 70,72, 73,74) W. Galarneau - RPO (55)

STF Library (43) STF (86, 87, 88)

WORKING COPIES (101-199) These copies of procedures are kept in the areas designated for use in response to an emergency.

W. Galarneau - RAF/RPO (106, 107) D. Krall - CR/Communicator (l1 6 )(Pardal Distribution)

W. Galarneau - SBF/ENV (108, 109) .. Simulator/Communicator (117)

W. Galarneau - SBF/EM Team (110, 111, llA) M. Fencl - Security (121)

W. Flint - Cold Chem/HR Sample Room (113) M. Kuether - Security Building (120)

M. Kuether - SBF/SEC (114) Ops Admin. (126)

Originals to KNPP QA Vault Please follow the directions when updating your EPIP Manual. WATCH FOR DELETIONS!!! These are controlled procedures and random checks may be made to ensure the manuals are kept up-to-date.

• THIS IS NOT A CONTROLLED COPY. ITISA COPYFOR INFORMATION ONLY.

I

KEWAUNEE NUCLEAR POWER PLANT REVISION OF EMERGENCY PLAN IMPLEMENTING PROCEDURES August 20, 2002 Please follow the directions listed below. If you have any questions regarding changes made to the EPIPs, please contact Dave Seebart at ext. 8719.

EPIP Index, dated 08-20-2002.

". REMOVE -INSERT "PROCEDURE . -REV. PROCEDURE REV.

EPIP-AD-04 AJ EPIP-AD-04 AK EPIP-ENV-01 V EPIP-ENV-01 W EPIP-ENV-03C V EPIP-ENV-03C W EPIP-ENV-04A S EPIP-ENV-04A T EPIP-ENV-04B W EPIP-ENV-04B X EPIP-ENV-04C W EPIP-ENV-04C X EPIP-ENV-04D N EPIP-ENV-04D 0 Form EPIPF-ENV-02-01 M Form EPIPF-ENV-02-01 N K)

I CERTIFY Copy No. (WPSC No.) of the Kewaunee Nuclear Power Plant's EPIPs has been updated.

SIGNATURE DATE Please return this sheet to DIANE FENCL.

Diane Fencl Enclosure 2

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 08-20-2002 PROC. NO. TITLE REV. DATE EP-AD EPIP-AD-01 Personnel Response to the Plant Emergency J 01-08-2002 Siren EPIP-AD-02 Emergency Class Determination AD 07-19-2002 EPIP-AD-03 KNPP Response to an Unusual Event AF 06-20-2002 EPIP-AD-04 KNPP Response to Alert or Higher AK 08-20-2002 EP-AD-5 Site Emergency Deleted 04-27-87 EPIP-AD-05 Emergency Response Organization Shift Relief D 05-09-2002 Guideline EP-AD-6 General Emergency Deleted 04-24-87 EPIP-AD-07 Initial Emergency Notifications AR 06-20-2002 EP-AD-8 Notification of Alert or Higher Deleted 02-26-96 EP-AD-9 Notification of Site Emergency Deleted 04-27-87 EP-AD-10 Notification of General Emergency Deleted 04-27-87 EPIP-AD- 11 Emergency Radiation Controls R 04-11-2002 EP-AD-12 Personnel Assembly and Accountability Deleted 03-26-94 EP-AD-13 Personnel Evacuation Deleted 04-25-94 EP-AD-13A Limited Area Evacuation Deleted 03-01-83 EP-AD-13B Emergency Assembly/Evacuation Deleted 03-01-83 EP-AD-13C Site Evacuation Deleted 03-01-83 EP-AD-14 Search and Rescue Deleted 05-25-94 EPIP-AD-15 Recovery Planning and Termination 0 10-30-2001 EP-AD-16 Occupational Injuries or Vehicle Accidents Deleted 03-14-97 During Emergencies EP-AD-17 Communications Deleted 03-05-84 EPIP-AD-18 Potassium Iodide Distribution P 02-27-2002 EPIP-AD-19 Protective Action Guidelines Q 11-27-2001 PAGE I OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 08-20-2002 TITLE REV. DATE KNPP Response to a Security Threat C 05-23-2002 EP-ENV EPIP-ENV-01 Environmental Monitoring Group Organization W 08-20-2002 and Responsibilities EPIP-ENV-02 Environmental Monitoring Team Activation X 10-02-2001 EP-ENV-3A Environmental Protection Director Actions and Deleted 09-26-84 Directives EP-ENV-3B EM Team Actions Deleted 09-26-84 EPIP-ENV-03C Dose Projection Using RASCAL Version 2.2 W 08-20-2002 Software EP-ENV-3D Revision and Control of ISODOSE II Deleted 02-14-95 EP-ENV-3E Manual Determination of X/Q Deleted 04-24-87 EP-ENV-3F Manual Determination of X/Q (Green Bay Deleted 05-30-86 Meteorological Data)

EP-ENV-3G Manual Dose Projection Calculation Deleted 06-02-89 EP-ENV-3H Protective Action Recommendations Deleted 04-13-90 EPIP-ENV-04A Portable Survey Instrument Use T 08-20-2002 EPIP-ENV-04B Air Sampling and Analysis X 08-20-2002 EP-ENV-4C Environmental Monitoring Teams Deleted 04-13-90 EPIP-ENV-04C Ground Deposition Sampling and Analysis X 08-20-2002 EPIP-ENV-04D Plume Tracking for Environmental Monitoring 0 08-20-2002 Teams EP-ENV-5A LCS-1 Operation Deleted 04-14-86 EP-ENV-5B MS-3 Operation Deleted 04-14-86 EP-ENV-5C SAM II Operation Deleted 04-14-86 EP-ENV-5D PAC-4G (Alpha Counter) Operation Deleted 04-14-86 EP-ENV-5E Reuter-Stokes Operation Deleted 08-27-85 PAGE 2 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 08-20-2002 PROC. NO. TITLE REV. DATE EP-ENV-6 Data Analysis, Dose Projections and Protective Deleted 12-21-81 Action Recommendations EP-ENV-6 Alternate Sample Analysis and Relocation of Deleted 04-14-86 EM Team EP-ENV-6A Relocation of Site Access Facility (Habitability) Deleted 03-23-84 EP-ENV-6B SAF Environmental Sample Analysis Relocation Deleted 03-23-84 EP-ENV-7 Site Access Facility Communications Deleted 09-26-84 EP-ENV-8 Total Population Dose Estimate Calculations Deleted 04-14-86 EP-EOF EP-EOF-1 Corporate Emergency Response Organization Deleted 03-11-94 EPIP-EOF-02 Emergency Operations Facility (EOF) Activation AA 08-06-2002 EPIP-EOF-03 EOF Staff Action for Unusual Event AC 02-06-2002 EPIP-EOF-04 EOF Staff Action for Alert or Higher AJ 08-06-2002 EP-EOF-5 Corporate Staff Action for Site Emergency Deleted 04-24-87 EP-EOF-6 Corporate Staff Action for General Emergency Deleted 04-24-87 EP-EOF-7 Notification of Unusual Event Deleted 04-06-94 EP-EOF-8 Relocation of EOF Deleted 03-01-83 EPIP-EOF-08 Continuing Emergency Notifications X 06-20-2002 EP-EOF-9 Interface with Support Organizations Deleted 03-05-84 EP-EOF-9 Notification of Site Emergency Deleted 04-24-87 EP-EOF- 10 Notification of General Emergency Deleted 04-24-87 EPIP-EOF-11 Internal Communication and Documentation U 11-15-2001 Flow EPIP-EOF-12 Media Center/Emergency Operation Q 06-20-2002 Facility/Joint Public Information Center Security PAGE 3 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 08-20-2002 PROC. NO. TITLE REV. DATE EP-OP EP-OP-1 Control Room Emergency Organization Deleted 04-24-87 EP-OP-2 Emergency Control Room Activation for Deleted 04-24-87 Emergency Response EP-OP-3 Control Room Communications Deleted 04-24-87 EP-OSF EP-OSF-1 Operation Support Facility Emergency Deleted 04-24-87 Organization EPIP-OSF-02 Operational Support Facility Operations U 02-06-2002 EPIP-OSF-03 Work Orders During an Emergency P 05-09-2002 EP-OSF-4 Operational Support Facility Communications Deleted 04-24-87 EPIP-OSF-04 Search and Rescue E 05-23-2002 EP-RET EP-RET-1 Radiation Emergency Team Organization Deleted 04-16-96 EPIP-RET-02 In-Plant Radiation Emergency Team V 05-23-2002 EPIP-RET-02A Radiation Protection Office/Radiological T 11-29-2001 Analysis Facility (RPO/RAF) Activation EPIP-RET-02B Gaseous Effluent Release Path, Radioactivity, S 08-06-2002 and Release Rate Determination EP-RET-2C Containment Air Sampling and Analysis Deleted 03-01-83 EPIP-RET-02D Emergency Radiation Entry Controls and M 06-12-2001 Implementation EP-RET-2E Handling of Injured Personnel Deleted 04-16-96 EP-RET-2F Personnel Decontamination Deleted 04-13-90 EPIP-RET-03 Chemistry Emergency Team 0 02-01-2000 EPIP-RET-03A Liquid Effluent Release Paths L 11-29-2001 EP-RET-3B Post-Accident Reactor Coolant Alternate Deleted 01-25-88 Sampling Procedure PAGE 4 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 08-20-2002 PROC. NO. TITLE REV. DATE EPIP-RET-03C Post Accident Operation of the High Radiation P 01-15-2002 Sample Room EPIP-RET-03D Containment Air Sampling Analysis Using N 01-15-2002 CASP EP-RET-3E Post Accident Operation of High Rad Sample Deleted 08-27-85 Room Inline Multiported Count Cave EPIP-RET-04 SBF Activation S 06-20-2002 EP-RET-4A EOF Radiological Monitoring Deleted 03-10-83 EPIP-RET-04A SBF Operation/Relocation Deleted 10-02-2001 EP-RET-4B Radiological Controls at Site Access Facility Deleted 07-12-94 EP-RET-4C Site Radiological Monitoring Deleted 07-12-94 EP-RET-4D SAM-11 Operation Deleted 07-12-94 EP-RET-5 Plume Projection Deleted 09-26-84 EPIP-RET-05 Site Boundary Dose Rates During Controlled H 10-09-2001 Plant Cooldown EP-RET-5A Plume Projection Deleted 04-27-87 EP-RET-6 Dose Projection Deleted 04-24-87 EP-RET-7 Radiological Analysis Facility/Radiation Deleted 04-24-87 Protection Office Communications EPIP-RET-08 Contamination Control of the Aurora Medical Deleted 05-23-2002 Center EPIP-RET-09 Post-Accident Population Dose L 04-16-2002 EP-SEC EP-SEC-1 Security Organization Deleted 04-24-87 EPIP-SEC-02 Security Force Response to Emergencies X 02-06-2002 EP-SEC-2A Manual Activation of Emergency Sirens Deleted 04-16-82 EPIP-SEC-03 Personnel Assembly and Accountability AE 07-19-2002 EPIP-SEC-04 Security Force Actions for Dosimetry Issue P 10-02-2001 PAGE 5 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 08-20-2002 PROC. NO. TITLE REV. DATE EP-SEC-5 Security Force Response to the EOF Deleted 07-28-88 EPIP-SEC-05 Personnel Evacuation G 06-20-2002 EP-TSC EPIP-TSC-01 Technical Support Center Organization and R 08-06-2002 Responsibilities EPIP-TSC-02 Technical Support Center Activation T 02-06-2002 EPIP-TSC-03 Plant Status Procedure V 10-09-2001 EPIP-TSC-04 Emergency Physical Changes, Major Equipment N 05-09-2002 Repair EP-TSC-5 Technical Support Center Communications Deleted 04-24-87 Equipment EP-TSC-6 Assessment of Reactor Core Damage Deleted 09-30-86 EPIP-TSC-07 RV Head Venting Time Calculation J 06-20-2002 EPIP-TSC-08A Calculations for Steam Release from Steam N 12-14-2001 Generators EPIP-TSC-08B* STM1RLS Computer Program G 06-20-2002 EP-TSC-8C* See EP-TSC-8B Deleted 04-16-92

• EP-TSC-8B was totally deleted; therefore, EP-TSC-8C was changed to EP-TSC-8B EP-TSC-9 Core Damage Assessment Using Released Deleted 09-30-86 Radionuclides EPIP-TSC-09A* Core Damage Assessment J 05-16-2002 EPIP-TSC-09B* CORE Computer Program Deleted 05-16-2002 EP-TSC-9C* See EP-TSC-9B Deleted 04-16-92

• EP-TSC-9A, Rev. D was totally deleted; therefore, EP-TSC-9B became EP-TSC-9A. EP-TSC-9B was previously EP-TSC-9C.

EPIP-TSC-10 Technical Support for IPEOPs K 05-09-2002 PAGE 6 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 08-20-2002 FIGTTRES EPIP FIG# Figure EPIPFG DESCRIPTION REV. DATE EP-SEC-5 Technical Support EPIP-APPX-A-06 EP-FIG-003 APPX-A-06-03 Center - KNP Floor Plan B 06-12-2001 Site Boundary Facility EPIP-APPX-A-06 EP-IG-oo5 APPX-A-06-02 KNP Floor Plan A 10-31-2000 Radiological Analysis Facility - KNP Floor EPIP-APPX-A-06 EP-FIG-0os APPX-A-06-01 Plan A 10-31-2000 EPIP-EOF-12 Division Office Building Form EPIPF-EOF-02-01 EP-nr1-009 EOF-12-01 (2nd Floor) Floor Plan B 10-24-2000 State/County Work Area - WPSC D2-1 EPIP-APPX-A-06 EP-FIG-012 APPX-A-06-08 Floor Plan C 10-31-2000 NRC Work Area EPIP-APPX-A-06 EP-FIG-013 APPX-A-06-09 WPSC D2-4 Floor Plan A 10-31-2000 Population Distribution by Geographical Sub EPIP-AD-19 EP-RG-014 AD-19-01 Areas (with sectors) A 10-31-2000 EOF - WPSC D2-3 EPIP-APPX-A-06 EP-FIG-022 APPX-A-06-04 Floor Plan C 10-30-2001 Location of JPIC and Media Briefing Center EPIP-EOF-12 EP-FIG-024 EOF-12-02 Map C 06-20-2002 KNP Site Map &

EP-SEC-5 EP-FIG-026 SEC-05-01 Evacuation Routes C 06-20-2002 Floor Plan - Media APPX-A-6 EP-FIG-034 --- Briefing Center Deleted 08-04-98 General Office EPIP-EOF-12 Building - WPSC (1st EPIP-APPX-A-06 EP-FIG-035 APPX-A-06-06 Floor) Floor Plan C 10-24-2000 Floor Plan - Corporate EP-FIG-037 --- Response Center Deleted 08-04-98 APPX-A-6 EP-FIG-038 --- Floor Plan - JPIC Deleted 08-04-98 APPX-A-6 EPIP-OSF-02 EP-FIG-039 OSF-02-01 High Priority Work A 10-02-2001 EPIP-OSF-02 EP-FiG-039A OSF-02-02 Lower Priority Work A 10-02-2001 JPIC - Federal Work EPIP-APPX-A-06 EP-FIG-043 APPX-A-06-10 Area - WPSC D2-9 B 12-21-2001 JPIC - State and County Work Area EPIP-APPX-A-06 EP-n-o0 APPX-A-06-07 WPSC D2-8 C 12-21-2001 JPIC - Utility Work EPIP-APPX-A-06 EP-FIG-045 APPX-A-06-05 Area - WPSC D2-7 C 12-21-2001 Aurora Medical Center RET-08 EP-FIG-046 RET-08-01 Location Deleted 05-23-2002 EPIP-APPX-A-02 --- APPX-A-02-01 ERO Call Tree Deleted 12-04-2001 PAGE 7 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 08-20-2002

"*-/; .... . ..... EvISION NUMBER TITLE REVISION DATE APPENDIX A APPX-A-1 Communication System Description AF 08-04-98 EPIP-APPX-A-02 Response Personnel Call List Deleted 02-06-2002 EPIP-APPX-A-03 Off-Site Telephone Numbers Deleted 02-06-2002 EPIP-APPX-A-06 KNPP Emergency Response Facility Telephone AA 12-21-2001 Numbers PAGE 8 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 08-20-2002 FORM EPIPF TITLE REV. DATE APPENDIX B EP-AD AD-07-01 Event Notice (Wisconsin Nuclear Accident Reporting Form) S 05-23-2002 AD-07-02 State Call-Back - Question Guideline C 11-15-2001 AD-I 1-01 Emergency Radiation Work Permit G 04-11-2002 AD-18-01 Airborne Radioiodine Dose Accountability and Potassium B 08-06-2002 Iodide Distribution AD-18-02 Record of Known Allergy To or Voluntary Refusal to A 02-27-2002 Take Potassium Iodide EP-ENV ENV-01-01 Environmental Dispatch Area Activation Checklist D 10-31-2000 ENV-01-02 EMT Status B 10-31-2000 ENV-01-03 Meteorological and Plant Status Data C 12-14-2001 ENV-01-04 EMT Orders/Field Data B 10-31-2000 ENV-02-01 EMT Activation Checklist N 08-20-2002 EP-EOF EOF-02-01 EOF Activation Checklist T 08-06-2002 EOF-02-02 EOF Deactivation Checklist M 08-06-2002 EOF-04-01 SRCL Initial Action Checklist C 12-14-2001 EOF-04-02 Telephone Communications Log Sheet A 12-14-2001 EOF-08-03 Fax for Emergency Declaration or Status Updates G 11-27-2001 EOF-08-05 Plant Emergency Status Report A 11-27-2001 EOF-08-06 Radiological Status Report D 11-27-2001 EOF- 11-02 Operating Status F 11-15-2001 EOF-11-03 Environmental Status Board F 11-15-2001 EOF-12-01 I.D. Badge Registration Form G 10-24-2000 PAGE 9 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 08-20-2002 FORM EPIPF TITEV.

EP-OSF OSF 2.2 Maintenance Work in Progress Deleted 07-08-98 OSF-03-01 Operational Support Facility Team Briefing C 12-04-2001 EP-RET RET-02A-02 Emergency Sample Worksheet E 06-05-2001 RET-02B-01 Containment Stack Release (Grab Sample) D 08-06-2002 RET-02B-02 Auxiliary Building Stack (Grab Sample) D 08-06-2002 RET-02B-03 Auxiliary Building Stack (Sping Reading) D 08-06-2002 RET-02B-04 Containment Stack (Sping Reading) C 08-06-2002 RET-02B-05 Steam Release D 08-06-2002 RET-02B-06 Field Reading (Grab Sample) B 08-06-2002 RET-04-01 SAM-2 Counting Equipment Worksheet E 06-12-2001 RET 8.3 Hospital Survey 1 Deleted 06-05-2001 RET 8.4 Hospital Survey 2 Deleted 07-25-97 RET 8.5 Hospital Survey 3 Deleted 07-25-97 RET-08-06 Hospital Survey 4 Deleted 05-23-2002 RET-09-01 Post-Accident TLD Record Sheet D 04-16-2002 EP-SEC SEC-03.01 Emergency Accountability Log A 03-28-2000 SEC-04-01 Emergency Dosimeter Log G 06-20-2002 EP-TSC TSC-01.01 Plant Status Summary for SAM Implementation B 02-06-2002 TSC-01.02 Severe Accident Management Summary and Strategy B 02-06-2002 Recommendation TSC-01.03 Severe Accident Management - Status B 02-06-2002 TSC-02-01 TSC and OSF Activation Checklist 0 09-27-2001 PAGE 10 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 08-20-2002 FORM EPIPF TITLE REV. DATE TSC 2.2 TSC Ventilation Checklist H 04-01-99 TSC-02-03 Emergency Response Data System (ERDS) Link Initiation G 05-04-2001 Checklist TSC-02-04 TSC Chart Recorder Operation Checklist D 01-30-2001 TSC-02-05 TSC and OSF De-activation Checklist A 10-09-2001 TSC-03-01 Plant System Status L 06-12-2001 TSC-03-02 Plant Equipment Status L 06-12-2001 TSC-03-03 Environmental Status Board J 06-12-2001 TSC-03-04 Radiation Monitors I 01-08-2002 TSC-04-01 Emergency Physical Change Request G 05-09-2002 TSC-04-02 Emergency Physical Change Safety Review Deleted 05-09-2002 TSC-04-03 Emergency Physical Change Index F 08-29-2000 TSC-07-01 Head Venting Calculation G 06-20-2002 TSC-08A-01 Steam Release Data Sheet (Energy Balance) H 12-14-2001 TSC-08A-02 Steam Release Calculation Sheet (Energy Balance) G 12-14-2001 TSC-08A-03 Steam Release Data/Calculation Sheet (Open Valve) E 12-14-2001 TSC-08A-04 Steam Release Data/Calculation Sheet (STMRLS D 12-14-2001 Program)

TSC-09A-01 Core Exit Thermocouple Data D 05-16-2002 TSC-09A-02 Fuel Rod Clad Damage Estimate D 05-16-2002 TSC-09A-03 Fuel Rod Overtemperature Damage Estimate E 05-16-2002 TSC 9A.4 Core Damage Based on Activity Ratios Deleted 05-16-2002 TSC-09A-05 Core Damage Assessment (Monitoring Data) E 05-16-2002 TSC 9A.6 Core Damage Summary Deleted 05-16-2002 PAGE 11 OF 11

-iq*WISCONSIN PUBLIC SERVICE CORP."I - No* EPIP-AD-04 Rev. AK

... . Title KNPP Response to Alert or Higher Keaunee eT'4 N"Cli Powr, Plant

.niergencyPlan ImplementingProcedure . Date AUG 202002 Page 1 of 32 Reviewed By Bill Bartelme3YsPR Approved By 13 Dave Seebart Nula e SRO Approval Of E3 Yes Safety ReviewTepry Related 0 No Required [No Changes Required 0 No 1.0 Purpose 1.1 This procedure provides instruction for the Shift Manager/Emergency Director and other initial response personnel for an appropriate response to an Alert, Site Emergency, or General Emergency.

2.0 General Notes 2.1 The Shift Manager (SM) is the initial Emergency Director (ED) in all situations. Any transfer of this responsibility shall be documented in the Shift Manager's log and communicated to all on-site directors.

2.2 As more information becomes available, initial protective action recommendations should be adjusted in accordance with plant conditions, dose projections, time available to evacuate, estimated evacuation times, and meteorological conditions (EPIP-AD-19, "Protective Action Guidelines").

2.3 IF notified by radio-pager and the message is not understood, THEN emergency response personnel should confirm contact by telephoning Meridian Mail at 1-800-236-1588. A Meridian Mail voice message will indicate that the radio-pager activation was for an actual declared emergency and NOT a drill or exercise.

2.4 IF approached by the media during a declared emergency, THEN refer them to the Telephone Response Center at (920) 433-1400 or 1-800-838-6192 and tell them that this is their most accurate source for information.

3.0 Precautions and Limitations 3.1 The classification of an event should be performed within 15 minutes of recognizing that conditions exist requiring that classification and the subsequent declaration on "Event Notice," Form EPIPF-AD-07-01. "Event Notice," Form EPIPF-AD-07-01, should be initiated and in progress to state and local emergency governments within 15 minutes of the emergency level being declared, or as soon as possible without further compromise to plant or public safety.

3.2 The SM should remain in the Control Room during a declared emergency.

n:\nucdoc\procedures\draft\epip\eadO4.doc-Chtrisne Simmons!Christine Simmons-Jeanne Ferris REFERENCE USE

3.3 The following responsibilities of the ED shall NOT be delegated:

3.3.1 Determination of emergency classification (EPIP-AD-02, "Emergency Class Determination").

3.3.2 Authorization of emergency exposures in excess of 10CFR Part 20 limits (EPIP-AD- 11, "Emergency Radiation Controls").

3.3.3 UNTIL the Emergency Response Manager assumes the responsibility following EOF activation, recommendations of protective actions to off-site authorities (EPIP-AD-19).

3.4 The ED should carefully consider the status of activities (especially those identified in Step 3.3 above) before relocating to the TSC. Relocation to the TSC prior to TSC activation is not recommended.

3.5 An emergency classification should be made within 15 minutes of recognizing that conditions exist requiring classification in accordance with the EALs. This 15 minute goal is in addition to the 15 minute notification requirement once an emergency declaration has been made on "Event Notice," Form EPIPF-AD-07-01. There are times when it maybe appropriate to delay classification while significant changes in plant parameters are evaluated for their impact on classification. Examples of such events are an unanticipated:

"* Plant Trip

"* SI Initiation

"* Entry into an orange or red path

"* Loss of a safety system If such an event should occur during classification, it may be appropriate to exceed the 15 minute goal to ensure an accurate classification.

4.0 Initial Conditions 4.1 This procedure shall be implemented upon declaration of an Alert, Site Emergency, General Emergency, or when directed by the Shift Manager or Emergency Director.

5.0 Procedure 5.1 SMIED shall take the following Initial Actions:

5.1.1 IF a security threat exists, THEN go to EPIP-AD-20, "KNPP Response to a Security Threat" (Reference Operations Procedure E-0-08).

5.1.2 Contact the Shift Technical Advisor (STA) and direct them to report to the Control Room.

REFERENCE USE

I 5.1.3 IF the event can be declared and terminated within one notification, THEN the SM/ED has the option to require assembly based on the nature of the event and their judgement of threat to plant staff safety. In case assembly is not warranted, go to Step 5.1.6.c.

5.1.4 IF assembly could present an unacceptable risk to plant employees as a result of a security event, THEN do NOT initiate assembly. Go to Step 5.1.6 (Reference Operations Procedure E-0-08).

5.1.5 Initiate personnel assembly.

a. Prepare your Gai-tronics message by making the choices identified in the box below in Step 5.1.5.c.

b. Sound the plant siren.

c. Read aloud two times on the Gai-tronics the message below.

"Attention all personnel. We are experiencing an (Choose One)

(Alert/SiteEmergency/GeneralEmergency). Emergency response organization personnel should report to their duty locations. All other personnel should report to the nearest assembly area."

Choose (1) or (2)

(1) No additional personnel protective actions are required at this time.

(2) Personnel should avoid the following plant areas because of (type hazard):

(plant area)

(plant area)

(plant area) 5.1.6 Contact the Security Shift Captain/Site Protection Director.

a. Verify "Security Force Response to Emergencies," EPIP-SEC-02, actions are being implemented for an Alert or Higher.

"* Verify on-site members of the general public are directed to leave the site in accordance with EPIP-SEC-02.

"* Verify control measures for site access/egress are established in accordance with EPIP-SEC-02.

b. IF personnel assembly has been initiated, THEN verify that 'Tersonnel Assembly and Accountability," EPIP-SEC-03, is initiated.

c. Describe briefly the emergency event.

REFERENCE USE

54-l 'SERVK "I EC RP NoRev. AK tMlSCONSlN PUBLICE CORP. No. EPIP-AD-04 V2, ... ., .Title KNPP Response to Alert or Higher Nuclear Power P~ant A, Emergency.Plan Ilen i Date AUG 20 2002 Page 4 of 32 Note Protective actionsfor thepublic are requiredfora GeneralEmergency only.

5.1.7 Complete the "Event Notice," Form EPIPF-AD-07-01.

Note Adverse meteorology exists if.

1. The 10 AND 60 meter wind speed is less than 5 mph, AND

2. Delta Tis greaterthan +2.4FOR Sigma Theta is less than 3.01 degrees.

(Refer to GraphicDisplay #52from the PPCSterminal).

a. IF adverse meteorology does NOT exist, THEN complete Box 7 by getting the downwind sector(s) from the guide on the back of Form EPIPF-AD-07-01.

b. IF adverse meteorology does exist, THEN enter N/A in Box 7 and explain in Box 10.

c. IF the event is a General Emergency and adverse meteorology does NOT exist, WHEN completing Part #9, THEN check the following items:

e (B) 0 to 2 mile radius, AND Note The three sectors in (D), include the downwind sectorfrom Part#7 and one sector either side.

• (D) 2 to 5 miles in sectors ,

d. IF the event is a General Emergency and adverse meteorology exists, WHEN completing Part #9, THEN check the following item:

• (C) 0 to 5 mile radius.

e. IF the event is an Alert or Site Emergency, WHEN completing Part #9, THEN check the following item:

• (A) None Note IF there is more than one Notifier and Emergency Response Facility (ERF)

Communicator-ControlRoom (CR), TEN Steps 5.1.8 and 5.1.10 should be done in parallel.

5.1.8 Direct the Notifier or ERF Communicator-CR to initiate notifications per EPIP-AD-07, "Initial Emergency Notifications," using the "Event Notice," Form EPIPF-AD-07-01, completed in Step 5.1.7.

REFERENCE USE

iWiSCONSIN PUBLICSERVICE CORP. No. EPIP-AD-04 Rev. AK

. *--.J" Title KNPP Response to Alert or Higher 4 Kewaunee.

(?* Nuclear;Power= [ant

" .. ef PlanImipldentingProcd Date AUG 20 2002 Page 5 of 32 5.1.9 IF the event notification is a combination declaration and termination (quick in and out event), THEN determine the need to activate ERO radio pagers.

5.1.10 If appropriate, direct the Notifier or ERF Communicator-CR to activate pagers for all emergency response personnel (group code 9233) in accordance with EPIP-AD-07 Step 5.4. (See KPB Emergency Telephone Directory for individual pager codes.)

5.1.11 Direct the STA to notify the NRC in accordance with Step 5.6.3 of this procedure.

5.1.12 Review "State Call-Back - Question Guideline," Form EPIPF-AD-07-02, to prepare for questions which are most likely to be asked by State Duty Officer or State Radiological Coordinator.

5.1.13 Log all significant events and actions.

5.1.14 Verify Control Room Ventilation System operation.

5.1.15 Report any increase in Control Room radiation to the Radiological Protection Director (RPD) for habitability assessment.

5.1.16 Request support from Technical Support Center (TSC) or OSF staff as needed.

5.1.17 Update facility directors as needed including such information as:

0 Current Emergency Classification

• Conclusions that led to the current classification 0 Conditions that may be improving or declining

• Potential changes in status and possible classification changes 5.1.18 Until relieved by a designated ED, continue to make assessments of plant conditions and perform the required actions of the ED (Section 5.2 of this procedure) go to Step 5.2.6.

REFERENCE USE

,.m-',WSCONSINPUBLIC SERVICE CORP. No. EPIP-AD-04 Rev. AK STt KNPP Response to Alert or Higher Plant. S Date AUp22wP o MWPR ifkrc r Date AUG 20 2002 'Pe6of3 5.2 Emergency Director (Designated) shall:

5.2.1 WHEN notified that an Emergency has been declared:

a. Report to the Control Room.

b. IF an Emergency Director has been designated, THEN until released,

"* If appropriate, plan a shift relief per EPIP-AD-05.

"* Assist the designated Emergency Director.

c. IF an Emergency Director has NOT been designated, THEN notify the Shift Manager of your intent to assume the responsibilities of the Emergency Director and continue implementation of this procedure.

5.2.2 When appropriate, accept a briefing from the Shift Manager and STA. Key points listed below:

a. Classification chart used to determine emergency level.

b. Protective Action Recommendation in effect.

C. Status of off-site and KNPP notifications.

d. Status of plant accountability.

e. Status of plant operation.

f. Control Room support priorities.

Note Verbally inform the Shift Managerthatyou have accepted the ED responsibilities.

5.2.3 Accept formal turnover of responsibilities (for ED) from SM to include:

"* Direction and supervision of emergency response operations

"* Approval of changes in emergency classifications

"* Review and approval of all exposures in excess of 10 CFR Part 20 limits

"* PARs (unless transferred to the ERM)

"* Protective actions for plant personnel

"* Continuous accident assessment 5.2.4 Notify other directors and Control Room staff of the transfer of the ED responsibility to you and your location.

REFERENCE USE

• r,WISCONSIN PUBLIC SERVICE CORP. ,2-. No. EPIP-AD-04 Rev. AK

' '. . ,Title KNPP Response to Alert or Higher

• -Kewaunfee Nu clearPower Plant

  A.',;2r, re a le r d Date AUG 20 2002 Page 7 of 32 5.2.5 Ensure date and time is entered in the Control Room log for turnover of responsibilities for ED from SM.

5.2.6 When appropriate:

a. Relocate to the Technical Support Center (TSC)

b. Direct TSC Support Personnel to enter date and time of arrival in TSC chronological log.

5.2.7 If appropriate, direct the Offsite Communicator in the TSC to take responsibility for off-site notifications from the Control Room.

5.2.8 Brief the TSC staff on the plant conditions.

5.2.9 Ensure the overall emergency level is continually reviewed.

a. Event Classification (EPIP-AD-02)

b. PAR (EPIP-AD-19)

C. Emergency Radiological Exposures (EPIP-AD-1 1)

It is not requiredto de-escalatefrom an Emergency Action Level, termination or direct entry into recovery is preferable.However, there may be occasions when it is more appropriateto de-escalate.

EPIP-AD-02and other EPIPs are not written tofacilitatede-escalation.

Therefore, any decision to de-escalateinstead of enteringrecovery must be based on a thorough review of EPIP-AD-02 and careful use of appropriate procedures.

5.2.10 IF plant conditions have met the conditions for escalating or de-escalating the emergency classification (EPIP-AD-02), set the time and emergency level being declared, THEN:

a. IF assembly could present an unacceptable risk to plant employees as a result of a Security Event, THEN do NOT initiate assembly.

Go to Step 5.2.10(d).

REFERENCE USE

b. IF accountability has NOT already been completed, THEN:

1. Direct a Control Room staff member to sound the plant siren.

2. WHEN the plant siren has been sounded, read aloud two times on the Gai-tronics the message below:

"Attention all personnel. We have (Choose One) escalated/de-escalated from (Choose One) (UnusualEvent/Alert/Site Emergency/General Emergency) to (Choose One) ((UnusualEvent/Alert/Site Emergency/General Emergency). Designated emergency response directors should take appropriate action.

Emergency Personnel shall report to their emergency duty station. All other personnel should report to the nearest assembly area."

Choose (1) or (2)

(1) No additional personnel protective actions are required at this time.

(2) Personnel should avoid the following plant areas because of (type hazard):

__(plant area)

(plant area)

(plant area)

REFERENCE USE

4 V "RVCENo. EPIP-AD-04 Rev. AK S ~ Title KN-PP Response to Alert or Higher LEmergency Pa mlmnin redre* Date AUG 20 2002 Pa e 9 of 32

c. IF personnel assembly has been completed, THEN:

1. Direct a Control Room staff member to sound the plant siren.

2. When the plant siren has been sounded, read aloud two (2) times on the Gai-tronics the message below:

"Attention all personnel. We have (Choose One) escalated/de-escalated from (Choose One) (UnusualEvent/Alert/Site Emergency/General Emergency) to (Choose One) (UnusualEvent/Alert/Site Emergency/General Emergency). Designated emergency response directors should take appropriate action."

Choose (1) or (2)

(1) No additional personnel protective actions are required at this time.

(2) Personnel should avoid the following plant areas because of________________(type hazard).

_______________________(plant area)

______________________(plant area)

______________________(plant area)

d. IF the EOF has NOT__ accepted responsibility for off-site notifications and PARs, THEN:

Note Protective actionsfor the public are requiredfor a GeneralEmergency only.

1. Review current and potential protective action recommendations (EPIP-AD-l 9).

2. IF time permits, THE._NN contact off-site authorities via the Dial-Select to discuss pending changes in classification and/or appropriate PAR.

3. Initiate revised event classifications and/or PAR on "Event Notice,"

Form EPJPF-AD-07-01.

4. Review and sign all "Event Notice," Form EPIPF-AD-07-01, that are generated from the CRITSC.

5. Forward approved "Event Notice," Form EPIPF-AD-07-01, to the EOF Communicator for transmission to off-site agencies.

6. Verify that required notifications are made (EPIP-AD-07 or EPIiP-EOF-08, "Continuing Emergency Notifications").

REFERENCE USE

WISCONSIN pUBLIOSERVICE CORP.' . No. EPIP-AD-04 Rev. AK

Title K NPP Response to Alert or Higher S

..-

Date S AUG 20 2002 Page 10 of 32

e. IF the EOF has taken responsibility for off-site notifications and PARs, THEN ensure the ERM is notified of the emergency level escalation and the time it was declared.

f. Direct the Shift Technical Advisor to notify the NRC in accordance with Step 5.6.3 of this procedure.

5.2.11 Determine the response status with an information collection brief. Include the following emergency response organization Directors:

a. Event Operations Director (EOD):

"* Off-site Notifications (EPIP-AD-07)

"* Plant Operations Status

"* Control Room support priorities

b. Radiological Protection Director (RPD):

"* Status of Radiological Effluent Releases (potential off-site dose consequences)

"* Off-site Dose Assessment Evaluation

"* Emergency Radiation Controls (EPIP-AD-1 1) (actions taken in response to this procedure)

"* Status of Personal Injuries or Vehicle Accidents

"* Availability of Potassium Iodide (EPIP-AD-18, "Potassium Iodide Distribution")

"* Status of plant conditions that could warrant evacuation of non-essential plant personnel

c. Technical Support Center Director (TSCD):

"* TSC Activation and Operational Status (EPIP-TSC-02, Technical Support Center Activation")

"* Significant Plant Trends

"* "Core Damage Assessment" (EPIP-TSC-09A, "Core Damage Assessment")

d. Support Activities Director (SAD):

• OSF Activation and operational status 0 OSF Facility Operations (EPIP-OSF-02, "Operational Support Facility Operations")

e Maintenance Activities

• "Search and Rescue" (EPIP-OSF-04, "Search and Rescue")

REFERENCE USE

1 WISCONSIN PUBLIC SERVICE CORP.`- No. EPIP-AD-04 lRev. AK Title

~ KNPP Response to Alert or Higher fee

~Kewu PwerPlant ,2 K4mv

____Date AUG 20 2002 -Page 1- of 32

e. Site Protection Director (SPD):

"* Removal of Visitors from site (i.e., fishermen) (EPIP-SEC-02)

"* Personnel Accountability (EPIP-SEC-03)

"* Access Control

"* Significant Security Activities

f. Severe Accident Management Team Leader (SAMTL):

"* SAM Team Status

"* Severe Challenge Status

"* Strategies Implemented

"* Strategies being Evaluated

"* New Strategy Recommendations 5.2.12 Determine priorities of major tasks required to minimize the impact on the public and mitigate the incident. Weigh activities in the following areas:

"* Operations

"* Radiological

"* Technical Support

"* Maintenance

"* Security 5.2.13 Inform Emergency Response Manager (ERM) of:

"* Status of the plant.

"* On-site or off-site radiological releases or potential releases.

"* Priorities of tasks to minimize the impact to the public.

"* Incidents of public interest (i.e., fires, spills, personnel contaminations, and personnel injuries).

REFERENCE USE

SERVICE N. EPIP-AD-04 Rev. AK "Title KNPP Response to Alert or Higher

_ ,XewauneeGW62 Power Plantf3 Pr Date AUG 20 2002Pae1of3 5.2.14 When appropriate, brief the Plant Emergency Response Organization on plant conditions and priorities. Give specific guidance and assignments considering the following:

a. If required, direct evacuation of non-essential personnel from the plant.

"* Direct the SPD to initiate a plant evacuation.

"* Direct the RPD to assist the SPD in the plant evacuation.

"* Contact the Manitowoc and Kewaunee County Emergency Directors and the ERM to coordinate the evacuation (may use Dial Select).

"* The SPD implements and coordinates instructions.

"* Update the Manitowoc and Kewaunee County Emergency Directors and the ERM on the status of the evacuation (may use Dial Select).

b. If appropriate, instruct the data coordinator to initiate plant parameter trends on the following:

"* Safety Assessment System

"* Digital Display (#3)

"* PPCS Trend Recorders 5.2.15 IF the ERM has NOT assumed the responsibility, THEN provide Plant Emergency status updates to off-site authorities.

a. IF off-site EOCs are activated, THEN use the Dial Select to contact off-site organizations.

b. IF off-site organization EOCs are NOT activated, WHEN those organizations initiate a request, THEN provide status updates.

c. Use the "State Call-Back - Question Guideline," Form EPIPF-AD-07-02, or "Plant Emergency Status Report," Form EPIPF-EOF-08-05, and/or "Radiological Status Report," Form EPIPF-EOF-08-06, as information guides.

5.2.16 Review the plant Emergency Response Staffing requirements and need for any Emergency Director Assistants.

5.2.17 If appropriate, plan for a shift relief per EPIP-AD-05.

5.2.18 Review the requirements of Section 5.1 of EPIP-AD-15, "Recovery Planning and Termination," and determine if recovery or termination activities can be implemented.

5.2.19 IF Final Conditions (Section 6.0) have NOT been met, THEN go to Step 5.2.7.

REFERENCE USE

XT5WISCONSIN PUBLIC SERVICE CORP. . No. EPIP-AD-04 Rev. AK

-,o.. .. Title KNPP Response to Alert or Higher une NuclearP ant se&ec,.. t Plahi Imp-lementing Prociidure. r Date AUG 20 2002 Page 13 of 32 5.2.20 WHEN Final Conditions (Section 6.0) are met:

a. Notify the Emergency Response Manager of the event termination or entry into recovery and the suspension of the use of the use of EPIPs.

b. IF the event is an ENTRY INTO RECOVERY, THEN read aloud two times on the Gai-tronics the message below:

"Attention all personnel. We have entered plant recovery operations.

Review final conditions of all procedures and restore all emergency response materials and equipment to their proper location.

Appropriate inventories should be performed and supplies replenished as appropriate. Use of EPIPs is suspended when all final actions have been completed to the satisfaction of the facility Director. The Recovery Manager is and the Environmental Liaison is ___

c. IF the event is an emergency class TERMINATION, THEN read aloud two times on the Gai-tronics the message below:

"Attention all personnel. We have terminated the Emergency response.

Review final conditions of all procedures and restore all emergency response materials and equipment to their proper location. Appropriate inventories should be performed and supplies replenished as appropriate."

d. Ensure that termination or recovery notifications have been initiated by the NRC communicator.

e. Verify that "Event Notice," Form EPIPF-AD-07-01, is being transmitted accordance with EPIP-AD-07 or EPIP-EOF-08.

f. Verify all work areas are returned to normal status and emergency procedures, forms, etc. are returned to there proper place.

g. Collect all completed records, logs, forms, notes, and other documentation and give them to the TSCD.

h. Implement EPMP-02.01, "Declared Emergency Evaluation and Documentation."

5.3 The Notifier shall:

5.3.1 WHEN notified or upon hearing the Event announcement (except when a Security Event is in progress), report immediately to the SM in the Control Room.

REFERENCE USE

5.3.2 WHEN directed by the Emergency Director/Shift Manager, perform event notifications, go to EPIP-AD-07.

5.3.3 IF an Emergency Response Facility (ERF) Communicator-Control Room (CR) is NOT available, THEN assume the role of the Control Room Communicator and go to Step 5.4.4.

5.3.4 Until released, remain in the Control Room and help the designated Control Room Communicator.

5.3.5 WHEN released, report back to the Shift Captain.

5.4 Emergency Response Facility (ERF) Communicator shall:

5.4.1 WHEN directly notified, paged by radio-pager, or hearing the event announcement:

a. Report to the Control Room immediately.

b. IF the ERF Communicator-CR has been designated, THEN until released, assist the designated ERF Communicator-CR.

c. IF an ERF Communicator-CR has NOT been designated, THEN assume the responsibilities of the ERF Communicator-CR and continue to implement this procedure.

5.4.2 Notify the SM/ED of your arrival and assumption of the ERF Communicator-CR duties.

5.4.3 If applicable, obtain the status of notifications and verification call backs from the Notifier.

5.4.4 IF there is an event: DECLARATION, ESCALATION, DE-ESCALATION, CHANGE IN PAR, TERMINATION, OR ENTRY INTO RECOVERY, AND directed by the SM/ED, go to EPIP-AD-07 OR EPIP-EOF-08 AND make the appropriate event notifications.

5.4.5 Review the need for the Notifier or additional communicator support.

5.4.6 IF additional Communicator support is needed, THEN contact the Technical Support Center Director 5.4.7 IF off-site notifications are complete or if a Notifier is implementing them, THEN enter the 4-Way Communications Link. The "dial in number" and "access number" are listed in the KPB Emergency Telephone Directory, ETD 03, "Emergency Response Facilities Telephone List."

5.4.8 Notify the EOD of any significant events.

REFERENCE USE

rWISCONSINPUBLIC SERVICE CORP . No. EPIP-AD-04 Rev. AK

• j."aT itle KNPP Response to Alert or Higher

~~~Kewaun -NuclearPower& at '

SPro ur -*K Date AUG 20 2002 Pa e 15 of 32 5.4.9 If appropriate, plan for a shift relief per EPIP-AD-05.

5.4.10 IF Final Conditions (Section 6.0) have NOT been met, THEN go to Step 5.4.4.

5.4.11 WHEN Final Conditions (Section 6.0) are met:

a. Verify that the bell switch on the emergency government verification line is in the ON position.

b. Verify all work areas are returned to normal status and emergency procedures, forms, etc. are returned to their proper place.

c. Collect all completed records, logs, forms, notes, and other documentation and give them to the EOD.

5.5 The Control Room Support Person (SP-C) shall:

5.5.1 WHEN directly notified, paged by radio-pager, or hearing the event announcement:

a. Report to the Control Room immediately.

b. IF a Control Room Support Person has been designated, THEN until released, assist the Control Room Support Person, as instructed.

c. IF a Control Room Support Person has NOT been designated, THEN assume the responsibilities of the Control Room Support Person and continue to implement this procedure.

5.5.2 Initiate or maintain accountability in the Control Room (EPIP-SEC-03).

5.5.3 Support the Control Room staff with:

a. Chronological log of events

b. Copying

c. Answering telephones 5.5.4 Review the need for additional Control Room Support Personnel.

5.5.5 IF additional Support Personnel are needed, THEN notify the EOD.

5.5.6 If appropriate, plan for a shift relief per EPIP-AD-05, "Emergency Response Organization Shift Relief Guideline."

5.5.7 Notify the EOD of any significant issues.

5.5.8 IF Final Conditions (Section 6.0) have NOT been met, THEN go to Step 5.5.2.

REFERENCE USE

5.5.9 WHEN Final Conditions (Section 6.0) are met:

a. Verify all work areas are returned to normal status and emergency procedures, forms, etc. are returned to their proper place.

b. Collect all completed records, logs, forms, notes, and other documentation and give them to the EOD.

5.6 Shift Technical Advisor shall:

Note The Shift Technical Advisor shall be capable of responding to the Control Room within 10 minutes.

5.6.1 Report to the Control Room to be briefed on plant conditions.

5.6.2 Assist the Shift Manager in assessing plant conditions and determining emergency classification as defined in EPIP-AD-02, "Emergency Class Determination."

Note The respondingNRC Communicatormay be asked to assist in NRC notification.Off-site and other needed ERO or ERF communicationsshall be completed before the ERF Communicator-CR can provide this support, unless there is more than one ERF Communicator-CRavailable.

5.6.3 Perform NRC Notification:

a. Gather information needed to prepare the NRC "Event Notification Worksheet," Form GNP- 11.04.04-1.

Note If needed, the commercial telephone number is (301) 951-0550.

b. Notify the NRC (Headquarters, Bethesda) as soon as possible, but not more than one hour after declaration of the Event, using the Emergency Notification System (ENS) phone with the red sticker.

Note The NRC may request continuous communicationsper I OCFR50.72(c)(3).

The STA must coordinatethis activity with accident assessment until arrival of an NRC Communicator OR activation of the TSC allows them to assume this activity.

c. Provide the NRC with the necessary information from a completed Event Notification Worksheet.

REFERENCE USE

VWiSCONSlN pUBLIC'SERVICE CRP -No. EPIP-AD-04 Rev. AK Plat - Title KNPP Response to Alert or Higher

"*,*.'*Ke aunee Nu'cle-a'r P.'o~w ~er Plant : *,,

• raemeentmyP h:. Procedure Date AUG 20 2002 Page 17 of 32 5.6.4 WHEN the NRC Communicator arrives OR the TSC accepts responsibility for NRC communications and plant status and other activities are at a point that it is appropriate, turn NRC communications over by taking the following actions:

a. Brief on plant conditions, the status of NRC notification and updates.

b. Inform them that you are turning over responsibility for NRC communications to them.

5.6.5 Support the Control Room staff with technical and analytical assistance in diagnosing abnormal events and to ensure adequate core cooling.

5.6.6 Monitor plant conditions and provide assistance as needed to the Shift Manager.

5.6.7 IF Final Conditions (Section 6.0) have NOT been met, THEN go to Step 5.6.5.

5.6.8 WHEN Final Conditions (Section 6.0) are met:

a. Verify all work areas are returned to normal status and emergency procedures, forms, etc. are returned to their proper place.

b. Collect all completed records, logs, forms, notes, and other documentation and give them to the EOD.

5.7 Event Operations Director (EOD) shall:

5.7.1 WHEN notified that an Emergency has been declared:

a. Report to the Control Room.

b. IF an Event Operations Director has been designated, THEN until released, e If appropriate, plan a shift relief per EPIP-AD-05, AND e Assist the designated Event Operations Director.

c. IF an Event Operations Director has NOT been designated, THEN assume the responsibilities of the Event Operations Director and continue implementation of this procedure.

REFERENCE USE

Note Verbally inform the Shift Managerthatyou have accepted the EOD responsibilities.

5.7.2 Accept formal turnover of responsibilities (for EOD) from SM to include:

"* TSC and EOF communications

"* Maintaining verification of accountability

"* Staffing of Control Room

"* Processing work requests

"* Monitoring fire fighting operations and maintaining accountability of fire team

• Obtaining additional assistance from Emergency Response Organization

• Monitoring and support of plant operations 5.7.3 Notify the SM/ED of your arrival and assumption of Event Operations Director responsibilities.

5.7.4 Ensure date and time is entered in the Control Room log for turnover of responsibilities for EOD from SM.

5.7.5 WHEN they are activating, verify DAROME communication links with TSC and EOF.

5.7.6 When appropriate, accept a briefing from the Shift Manager and STA.

5.7.7 Verify Control Room personnel accountability is being maintained.

5.7.8 Review Control Room staffing requirements, AND

a. Direct the Notifier/Communicator to contact additional operations personnel as needed and request that they report to the site (See KPB Emergency Telephone Directory for names and numbers).

b. Release any personnel NOT required.

5.7.9 Assess overall plant status.

• Verify equipment status and instrument indications.

• Verify Radiation monitors for abnormal indications.

• Review corrective actions that have been taken.

5.7.10 As necessary, make any recommendations to the Shift Manager.

REFERENCE USE

rewauneeupUelr -UWUi r-i,.

ny Plan Implemnenting Procedure <,4 Date 6iEme AUG 20 2002 Page 5.7.11 Brief the Emergency Director of any changes on:

• Off-site Notifications (EPJP-AD-07 or EPIP-EOF-08) e Plant Operations Status

• Control Room support priorities 5.7.12 Inform the RPD of any changes in radiological indications.

5.7.13 If required, request technical or maintenance support from the ED.

5.7.14 Prepare all work requests (WR) for approval.

a. Review WR and designate retest requirements.

b. If required to do the job, determine and initiate system lineups and tagouts.

5.7.15 Brief the Control Room staff periodically on:

e Emergency response status e Priorities

• Specific guidance and assignments 5.7.16 If appropriate, plan for shift relief per EPIP-AD-05.

5.7.17 IF Final Conditions (Section 6.0) have NOT been met, THEN go to Step 5.7.5.

5.7.18 WHEN Final Conditions (Section 6.0) are met:

a. Verify all work areas are returned to normal status and emergency procedures, forms, etc. are returned to their proper place.

b. Collect all completed records and logs, as described in procedure "Declared Emergency Evaluation and Documentation," EPMP-02.01.

c. Schedule a self critique with all event participants in the CR (all shifts) as soon as practical. The procedure "Drill and Exercise Critiques,"

EPMP-02.04, should be used as a guide.

REFERENCE USE

PULCSERVICE CORP.

-4WISo.NSi No. EPIP-AD-04 Rev. AK Z - Title KNPP Response to Alert or Higher Kewaune Nuclear Power Plant Date AUG 20 2002 Page 20 of 32 5.8 Radiological Protection Director (RPD) shall:

5.8.1 WHEN notified that an Emergency has been declared:

a. Report to the Technical Support Center (TSC).

b. IF a Radiation Protection Director has been designated, THEN until released,

"* If appropriate, plan a shift relief per EPIP-AD-05.

"* Assist the designated RPD.

c. IF a Radiation Protection Director has NOT been designated, THEN assume the responsibilities of the RPD and continue implementing this procedure.

5.8.2 Notify the ED/TSCD of your arrival in the TSC and assumption of RPD responsibilities.

5.8.3 Direct the staff to activate the RPO/RAF (EPIP-RET-02A, "RPO - RAF Activation").

5.8.4 When conditions warrant, the RPD shall relocate the RPO to the RAF.

5.8.5 Direct staff to establish Radiation Emergency Team organization (EPIP-RET-02, "In-Plant Radiation Emergency Team").

5.8.6 If required, verify personnel accountability in RPO is being maintained.

5.8.7 If required, assist the SAD in search and rescue operations (EPIP-OSF-04).

5.8.8 Check radiological and meteorological information available in the TSC.

5.8.9 If needed, contact the Data Coordinator or Operations Communicator for additional Area and Process radiation monitor information.

5.8.10 Verify that emergency radiation controls are being implemented (EPIP-AD- 11).

5.8.11 Verify controlled area access is being maintained (EPIP-RET-02D, "Emergency Radiation Entry Controls and Implementation").

REFERENCE USE

.... .  :ý11- IRev. A K SCONSIN PUBLIC SERVICE CORP. ' No. EPIP-AD-04

-- "-i Title KNPP Response to Alert or Higher

• '*;eKewaune Nuclear Power Plant DeG 20a 1 mergn c*PlanImplemewnting "ProceduMre";;7 Date AUG 20 2002 Parle 21 of 32 5.8.12 As dictated by the emergency event, direct the staff to implement additional In-Plant Radiation Emergency Team (IRET) and Chemistry Emergency Team (CET) procedures.

"* "Gaseous Effluent Release Path, Radioactivity, and Release Rate Determination," EPIP-RET-02B

"* "Liquid Effluent Release Paths," EPIP-RET-03A

"* "Post Accident Operation of the High Radiation Sample Room,"

EPIP-RET-03C

"* "Containment Air Sampling Analysis Using CASP," EPIP-RET-03D

"* "SBF Operation/Relocation," EPIP-RET-04A

"* "Site Boundary Dose Rates During Controlled Plant Cooldown,"

EPIP-RET-05

"* "Contamination Control of the Aurora Medical Center," HP-01.020

"* "Post Accident Population Dose," EPIP-RET-09 5.8.13 IF dose calculation capability is NOT available in the EOF AND a radioactive release has occurred or there is the potential for a release, THEN:

a. Direct the staff to perform dose projections (EPIP-ENV-03C, "Dose Projection Using RASCAL Version 2.2 Software").

b. Maintain an overall awareness of environmental conditions and the contributing factors for development of protective action recommendations in accordance with procedure EPIP-AD-19.

5.8.14 Monitor plant conditions for indications of radioactive iodine and with concurrence of the ED make KI available, if appropriate (EPIP-AD-l 8).

5.8.15 If required, assist the SPD with Personnel Evacuation (EPIP-SEC-05).

Note Transportationof a contaminatedinjuredperson shall be to the Aurora Medical Center and an IRET should be dispatchedto the hospital.

Note IF there is a question as to the extent of injuries, THEN it should be treatedas a critical injury.

REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No EPIP-AD-04 Rev. AK t '*,'- . *-.-A-Title KNPP Response to Alert Higher or e eNuClear Power Plant, rnrec* ** hld*i*Procedur ~YDate AUG 20 2002 Parle "22of32 Note Off-Site Support Agencies and theirphone numbers are listed in the KPB Emergency Telephone Directory.

5.8.16 IF there are injuries or vehicle accidents associated with plant personnel or contractors, THEN contact the appropriate support agencies.

a. IF the injury is a "Medical Attention (Critical) Injury" or a vehicle accident with injuries (see NAD-02.09 for definition of critical injuries), THEN:

1. Contact the County Sheriffs office with jurisdiction at the location of the injury(s). (Kewaunee County has jurisdiction on the KNPP site.)

0 Kewaunee County Dispatch - 911

• Manitowoc County Dispatch - (920) 683-4200

2. Notify the dispatcher of the accident and/or injury and request a rescue squad (all critically injured personnel shall be transported by rescue squad).

3. Provide the dispatcher with the following information:

• Your name, position, and return telephone number.

" The location of the accident and when it occurred.

• How many and how the injury(s) occurred.

• Nature and extent of injuries and condition of the patient(s).

• If any, extent of radioactive contamination and instructions that transportation of a potentially contaminated injured person shall be to the Aurora Medical Center.

• Plant name, location.

• If required, plant access instructions.

4. IF the injury is on-site, THEN:

• Inform the SPD of your request for a rescue squad and its estimated time of arrival.

• Direct the SPD to have the vehicle driven to the proper plant entrance.

REFERENCE USE

5. IF the accident potentially involves radioactive contamination, THEN:

• Dispatch an IRET member or to the accident site for contamination control.

o Dispatch an IRET member to the Aurora Medical Center to assist the hospital staff.

6. Insure that the requirements for "Occupational Injuries or Vehicle Accidents During Operations," NAD-02.09, are implemented.

7. Inform the Emergency Director, Emergency Response Manager, and the Spokesperson of the accident and details of the injuries.

b. IF the Injury is a "Medical Attention (Non-critical) Injury," THEN:

Note Any KNPP or contractorvehicle may be usedfor transportof (non critical)injuredpersonneL

1. Arrange for transportation of the injured person.

2. Direct the SPD to have the vehicle driven to the proper plant entrance.

"3. Contact the hospital or clinic and provide the following information:

• Your name, position, and return telephone number.

• When, how many, and how the injury(s) occurred.

• Nature of injuries and condition of the patient.

• If any, extent of radioactive contamination.

• Plant name, location, and access instructions.

• Estimated time of arrival for the patient(s) at the hospital or clinic.

4. IF there are contaminated injuries, THEN send an IRET member to the Aurora Medical Center to assist the hospital staff.

5. Insure that the requirements "Occupational Injuries or Vehicle Accidents During Operations," NAD-02.09, are implemented.

6. Inform the Emergency Director, Emergency Response Manager, and the Spokesperson of the accident and details of the injuries.

REFERENCE USE

SCONSIN PUBLIC SERVICE CORP. No. EPIP-AD-04,Rev Z- Title, KNPP Response to Alert or Hiý 11W~- PowerPlaTitle

-;a 0 !n

' Date AUG 20 2002 Page 5.8.17 Brief the Emergency Director of plant radiological conditions:

0 Status of Radiological Effluent Releases (potential off-site dose consequences).

• Emergency Radiation Controls (EPIP-AD- 11) (actions taken in response to this procedure).

• Status of Personal Injuries or Vehicle Accidents.

9 Availability of Potassium Iodide (EPIP-AD-18).

5.8.18 Review the personnel requirements in the RPO/RAF and:

a. As needed, direct the staff to contact additional Radiation Emergency Team (RET) members.

b. Release any RPO/RAF staff not required.

5.8.19 If appropriate for long term accident support, then coordinate with the ALD to establish contract support.

5.8.20 If appropriate, plan for a shift relief per EPIP-AD-05.

5.8.21 IF Final Conditions (Section 6.0) have NO.T been met, THEN go to Step 5.8.5.

5.8.22 WHEN Final Conditions (Section 6.0) are met:

a. Verify all work areas are returned to normal status and emergency procedures, forms, etc. are returned to their proper place.

b. Collect all completed records, logs, forms, notes, and other documentation and give them to the TSCD.

c. Verify all samples collected have been cataloged and appropriately stored.

d. Schedule a self critique with all event participants in the RPO/RAF (all shifts) as soon as practical. The procedure "Drill and Exercise Critiques,"

EPMP-02.04, should be used as a guide.

REFERENCE USE

WWSCONSIN PUBLIC SERVICE CRP. No. EPIP-AD-04 Rev. AK Title KNPP Response to Alert or Higher ewaKne'Nu c lear Power PlantA'-kýK "Planerdenc 15 Date AUG 202002 Page 25 of 32 5.9 Technical Support Center Director (TSCD) shall:

5.9.1 WHEN notified that an Emergency has been declared:

a. Report to the Technical Support Center (TSC).

b. If a Technical Support Center Director has been designated, UNTIL released:

"* Assist in the activation of the TSC per EPIP-TSC-02.

"* If appropriate, plan a shift relief per EPIP-AD-05.

"* Assist the designated TSCD.

c. IF a Technical Support Center Director has NOT been designated, THEN assume the responsibilities of the TSCD and continue implementing this procedure.

5.9.2 Notify the Emergency Director of your assumption of TSCD responsibilities.

5.9.3 Notify TSC staff of your assumption of TSCD responsibilities.

5.9.4 Verify that the TSC is being activated (EPIP-TSC-02).

5.9.5 Verify accountability is being maintained in the TSC (EPIP-SEC-03).

5.9.6 Determine the TSC activity status by obtaining the following information from TSC staff.

a. Operations Coordinator:

• TSC support of control room activities

• Technical support of IPEOPs (EPIP-TSC-10, "Technical Support for IPEOPs")

b. Engineering Coordinator:

"* Design change activities (EPIP-TSC-04, "Emergency Physical Changes, Major Equipment Repair")

"* Work requests (EPIP-OSF-03, "Work Requests During an Emergency")

"* Support Activities REFERENCE USE

4

-fdýWISCONSIN .PUBLIC SERVICE CORP.` No. EPIP-AD-04 Rev. AK t2% Titl K PRepns o lr or Higher KeanPNuclearPower Plant

,enProcedue Date AUG 20 2002 Page 26 of 32

e. Core Hydraulics Coordinator:

0 Core Damage Assessment (EPIP-TSC-09A)

• If appropriate, Steam Release Calculations (EPIP-TSC-08A, "Calculations for Steam Release from Steam Generators")

e If appropriate, Head Venting Calculations (EPIP-TSC-07, "RV Head Venting Time Calculation")

d. Quality Control Coordinator:

0 QC concerns

• Warehouse activities

e. Data Coordinator:

• Status of data collection and posting (EPIP-TSC-03)

• Significant changes in plant parameters

f. Communicators e EOF, CR, JPIC Communication (3-Way Conference)

• NRC communications

• Emergency Response Data System 5.9.7 Contact the Emergency Director (ED) and obtain information on plant status.

5.9.8 Brief the Emergency Director on TSC activities.

• TSC Activation and Operational Status (EPIP-TSC-02) 0 Significant Plant Trends

• Core Damage Assessment (EPIP-TSC-09A) 5.9.9 Ensure the TSC staff is informed of plant status and ED priorities.

5.9.10 Review TSC staffing requirements.

5.9.11 If appropriate, plan for a shift relief per EPIP-AD-05.

5.9.12 IF Final Conditions (Section 6.0) have NOT been met, THEN go to Step 5.9.5.

REFERENCE USE

5.9.13 WHEN Final Conditions (Section 6.0) are met:

a. Ensure the TSC and OSF are de-activated per "Technical Support Center Activation," EPIP-TSC-02.

b. Collect all records and logs as described in procedure "Declared Emergency Evaluation and Documentation," EPMP-02.01.

c. Schedule a self critique with all event participants in the TSC (all shifts) as soon as practical. The procedure "Drill and Exercise Critiques,"

EPMP-02.04, should be used as a guide.

5.10 Support Activities Director (SAD) shall:

5.10.1 WHEN notified that an Emergency has been declared:

a. Report to the Technical Support Center (TSC).

b. IF a Support Activities Director has been designated, THEN until released,

"* If appropriate, plan a shift relief per EPIP-AD-05.

"* Assist the designated SAD.

c. IF a Support Activities Director has NOT been designated, THEN assume the responsibilities of the SAD and continue implementing this procedure.

5.10.2 Notify the Emergency Director of your assumption of SAD responsibilities.

5.10.3 Notify the OSF staff that you have assumed the responsibilities of Support Activities Director.

5.10.4 Direct the OSF coordinator to implement EPIP-OSF-02.

5.10.5 Designate an OSF assembly area giving consideration to manpower pool size and environmental conditions.

5.10.6 If needed, direct the OSF coordinator to initiate search and rescue operations (EPIP-OSF-04).

5.10.7 Contact the Emergency Director for information on plant status and immediate actions.

5.10.8 Direct emergency maintenance activities in accordance with the priorities established by the Emergency Director.

5.10.9 If required, request engineering support from the Engineering Coordinator.

5.10.10 Review the maintenance staffing requirements to mitigate the incident.

REFERENCE USE

flW ISONSINWPUBLIC SERVICE CORP.--, No. EPIP-AD-04 Rev. AK

~2Title KNPP Response to Alert or Higher 4 .r*Kwaunee uclear Power Plant 7 e'm Date AUG 20 2002 Pale 28 of 32 5.10.11 Brief the Emergency Director on OSF activities.

"* OSF Activation and operational status

"* OSF Facility Operations (EPIP-OSF-02)

"* Maintenance Activities

" Search and Rescue (EPIP-OSF-04) 5.10.12 Ensure the OSF staff is informed of plant status and ED priorities.

5.10.13 If appropriate, plan for a shift relief per EPIP-AD-05.

5.10.14 IF Final Conditions (Section 6.0) have NOT been met, THEN go to Step 5.10.6.

5.10.15 WHEN Final Conditions (Section 6.0) are met:

a. Verify all work areas are returned to normal status and emergency procedures, forms, etc. are returned to their proper place.

b. Collect all completed records, logs, forms, notes, and other documentation and give them to the TSCD.

c. Schedule a self critique with all event participants in the OSF (all shifts) as soon as practical. The procedure "Drill and Exercise Critiques,"

EPMP-02.04, should be used as a guide.

5.11 Site Protection Director (SPD) shall:

5.11.1 WHEN notified that an Emergency has been declared:

a. Report to the Security Building.

b. If a Site Protection Director has been designated, UNTIL released:

e If appropriate, plan a shift relief per EPIP-AD-05.

• Assist the designated SPD.

c. IF a Site Protection Director has NOT been designated, THEN assume the responsibilities of the SPD and continue implementing this procedure.

5.11.2 Notify the ED/TSCD of your arrival in the Security Building and assumption of the SPD responsibility.

5.11.3 Direct the implementation of "Security Force Response to Emergencies,"

EPIP-SEC-02.

5.11.4 Establish "Personnel Assembly and Accountability," EPIP-SEC-03.

REFERENCE USE

I 5.11.5 IF Search and Rescue is required due to accountability results, THEN notify the Support Activities Director.

5.11.6 Direct the security staff to issue dosimetry to personnel responding from off-site (EPIP-SEC-04).

5.11.7 When appropriate, relocate to the TSC.

5.11.8 Obtain information from the RPD or the Control Room concerning fire, chemical, or radiological hazards present within the protected area.

5.11.9 IF hazards identified by the RPD or the Control Room warrant it, THEN restrict ERO personnel movement.

5.11.10 IF directed by the ED, THEN initiate a plant evacuation (EPIP-SEC-05).

5.11.11 Brief the Emergency Director on security activities:

• Removal of Visitors from site (i.e., fishermen) (EPIP-SEC-02) 9 Personnel Accountability (EPIP-SEC-03)

• Plant Evacuations (EPIP-SEC-05) 0 Access Control

• Dosimetry Issue (EPIP-SEC-04)

• Significant Security Activities 5.11.12 Ensure that the Security Force and staff are informed of any significant issues relative to their activities.

5.11.13 Ensure accountability is maintained (EPIP-SEC-03).

5.11.14 Review security staffing requirements and make appropriate adjustments.

5.11.15 If appropriate, plan for a shift relief per EPIP-AD-05.

5.11.16 IF Final Conditions (Section 6.0) have NOT been met, THEN go to Step 5.10.8.

REFERENCE USE

I 7;YWISCONSIN PUBLICSERVICECORP. a No. EPIP-AD-04 Rev. AK P...W Title KNPP Response to Alert or Higher K uclear Power "anee t"1

'd Date AUG 20 2002 Page 30 of 32 5.11.17 WHEN Final Conditions (Section 6.0) are met:

a. Verify all work areas are returned to normal status and emergency procedures, forms, etc. are returned to their proper place.

b. Collect all completed records, logs, forms, notes, and other documentation and give them to the TSCD.

c. Schedule a self critique with all event participants in Security (all shifts) as soon as practical. The procedure "Drill and Exercise Critiques,"

EPMP-02.04, should be used as a guide.

6.0 Final Conditions 6.1 Plant Emergency has been Terminated or Recovery actions have begun and the responsible Director has suspended the use of EPIPs.

7.0 References 7.1 Kewaunee Nuclear Power Plant Emergency Plan 7.2 COMTRAK 87-152, Downgrading of EALs 7.3 COMTRAK 88-068, Calling in additional communicators as required 7.4 NRC Inspection Report K-87-195, same as Reference 7.2 7.5 10CFR50.72(c)(3), Maintaining open communications with the NRC 7.6 NAD-02.09, Occupational Injuries or Vehicle Accidents During Operations 7.7 EPIP-AD-02, Emergency Class Determination 7.8 EPIP-AD-05, Emergency Response Organization Shift Relief Guideline 7.9 EPIP-AD-07, Initial Emergency Notifications 7.10 EPIP-AD-1 1, Emergency Radiation Controls 7.11 EPIP-AD-15, Recovery Planning and Termination 7.12 EPIP-AD-18, Potassium Iodide Distribution 7.13 EPIP-AD-19, Protective Action Guidelines 7.14 EPIP-AD-20, KNPP Response to a Security Threat REFERENCE USE

,WISCONSIN PUBLIC SERVICIE CORP No. EPIP-AD-04 Rev. AK Title KNPP Response to Alert or Higher

~ iKewaunee Nuclear:Power Plant i [ ......g ncPlaiilmplemehg Oear _enDate AUG 20 2002 Page 31 of 32 7.15 EPIP-ENV-03C, Dose Projection Using RASCAL Version 2.2 Software 7.16 EPIP-EOF-08, Continuing Emergency Notifications 7.17 EPIP-OSF-02, Operational Support Facility Operations 7.18 EPIP-OSF-03, Work Requests During an Emergency 7.19 EPIP-OSF-04, Search and Rescue 7.20 EPIP-RET-02, In-Plant Radiation Emergency Team 7.21 EPIP-RET-02A, RPO - RAF Activation 7.22 EPIP-RET-02B, Gaseous Effluent Release Path, Radioactivity, and Release Rate Determination 7.23 EPIP-RET-02D, Emergency Radiation Entry Controls and Implementation 7.24 EPIP-RET-03A, Liquid Effluent Release Paths 7.25 EPIP-RET-03C, Post Accident Operation of the High Radiation Sample Room 7.26 EPIP-RET-03D, Containment Air Sampling Analysis Using CASP 7.27 EPIP-RET-04A, SBF Operation/Relocation 7.28 EPIP-RET-05, Site Boundary Dose Rates During Controlled Plant Cooldown 7.29 HP-01.020, Contamination Control of the Aurora Medical Center 7.30 EPIP-RET-09, Post-Accident Population Dose 7.31 EPIP-SEC-02, Security Force Response to Emergencies 7.32 EPIP-SEC-03, Personnel Assembly and Accountability 7.33 EPIP-SEC-05, Personnel Evacuation 7.34 EPIP-TSC-02, Technical Support Center Activation 7.35 EPIP-TSC-04, Emergency Physical Changes, Major Equipment Repair 7.36 EPIP-TSC-07, RV Head Venting Time Calculation 7.37 EPIP-TSC-10, Technical Support for IPEOPs REFERENCE USE

7.38 EPIP-TSC-09A, Core Damage Assessment 7.39 KPB Emergency Telephone Directory 7.40 EPMP-02.01, Declared Emergency Evaluation and Documentation 7.41 EPMP-02.04, Drill/Exercise Critique and Assessment 8.0 Records 8.1 The following QA records and non-QA records are identified in this directive/procedure and are listed on the KNPP Records Retention Schedule. These records shall be maintained according to the KNPP Records Management Program.

8.1.1 QA Records

"* Event Notice, Form EPIPF-AD-07-01

"* Event Notification Worksheet, Form GNP-1 1.04.04-1 8.1.2 Non-QA Records None REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-ENV-O1 Rev. W Title Environmental Monitoring Group Kewaunee Nuclear Power Plant Organization and Responsibilities Emergency Plan Implementing Procedure Date AUG 20 2002 Page 1 of 7 Reviewed By Dave Seebart Approved By W. L. Yarosz NulaI1 e PORC 11 Yes SRO Approval Of 11 Yes NSfeartyYe Review Temporary Related El No Required 2 No Changes Required El No 1.0 Purpose 1.1 This procedure provides instruction for the Environmental Monitoring Group for formulating and recommending timely Protective Action Recommendations (PARs) to the Emergency Response Manager.

2.0 General Notes 2.1 PARs are developed using plant data, field data and off-site dose projections.

2.2 Collect data using the following techniques in the order presented.

2.2.1 Project the Total Effective Dose Equivalent (TEDE) based on information provided by available plant sources including meteorological and radiological release data.

"2.2.2 Determine the boundaries of a radioactive spill or plume, and the total area affected.

2.2.3 Collect samples to determine the isotopic makeup of the plume or spill.

2.2.4 Sampling area for the Environmental Monitoring Teams (EMTs) normally extends from the protected area fence to a 10 mile radius of the plant. However, if dose projections or field readings indicate doses > 1 rem TEDE or > 5 rem thyroid to any population outside the 10 mile radius of the plant then sampling should continue beyond the 10 mile radius. Areas monitored and sampled by the EMTs may include areas such as the access road, parking lot(s), training facilities or other locations on-site but outside the protected area fence as needed.

3.0 Precautions and Limitations 3.1 EMTs should NOT enter areas where projected or measured external radiation dose rates exceed 1 R/hr without specific direction from the Environmental Protection Director (EPD) or Radiological Protection Director (RPD).

4.0 Initial Conditions 4.1 This procedure may be implemented at the declaration of an Unusual Event.

4.2 Activate the EMTs when an Alert, Site Emergency, General Emergency is declared.

n.\nucdoc\procedures\draft\epip\eenvOl.doc-Chdstine Simmons/Chrstine Simmons-Dan Bouche REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-ENV-O1 Rev. W Title Environmental Monitoring Group Kewaunee Nuclear Power Plant Organization and Responsibilities Emergency PlanImplementing Procedure Date AUG 20 2002 Page 2 of 7 5.0 Procedure 5.1 Environmental Protection Director (EPD) responsibilities:

5.1.1 IF an Unusual Event has been declared, THEN implement EPIP-EOF-03, "Corporate Action for Unusual Event."

5.1.2 IF an Alert, Site Area, or General Emergency has been declared, THEN implement EPIP-EOF-04, "Corporate Action for Alert or Higher."

5.2 The Dose Projection Calculator (DPC) shall:

5.2.1 Report to the EPD upon arrival at the Emergency Operations Facility (EOF).

5.2.2 Assist the EPD in the activation of the Environmental Dispatch Area using Form EPIPF-ENV-01-01, "Environmental Dispatch Area Activation Checklist."

5.2.3 During the initial facility activation, complete Form EPIPF-EOF-08-06, "Radiological Status Report," using the following resources:

5.2.3.1 Information posted on the status boards 5.2.3.2 Meteorological data from the following sources:

a. PPCS/SPDS Computer

b. Green Bay National Weather Service

c. Point Beach Nuclear Plant 5.2.3.3 Obtain current plant status and off-site radiological release information from the following:

a. Engineering/Licensing Coordinator

b. EOF status boards

c. Radiological Analysis Facility (RAF)

d. PPCS/SPDS Computer 5.2.4 Provide the information recorded on Form EPIPF-EOF-08-06 to the following personnel:

a. Environmental Protection Director (EPD)

b. State Radiological Coordinator Liaison (SRCL)

c. Environmental Monitoring Team Coordinator (EMTCD)

REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-ENV-01 Rev. W Title Environmental Monitoring Group Kewaunee Nuclear Power Plant Organization and Responsibilities "Emergency PlanImplementing Procedure Date AUG 20 2002 Page 3 of 7 5.2.5 After the initial form is complete, update the form at least every hour (more frequently if conditions are changing) during the first 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of a declared emergency.

5.2.6 After the initial 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, update the form as conditions change.

5.2.7 As directed by the EPD, perform off-site radiological dose projections in accordance with EPIP-ENV-03C, "Dose Projection Using RASCAL Version 2.2 Software."

5.2.8 Compare the off-site radiological dose projection results with the following:

a. Off-site radiological dose projection results obtained by the RAF

b. EMT field data 5.2.9 Report the dose projection results and the comparison to the EPD and SRCL.

5.2.10 Assist the EPD and EMTCD as necessary.

5.2.11 Continue dose assessment activities as directed by the EPD.

5.3 The Environmental Monitoring Team Coordinator (EMTCD) shall:

5.3.1 Upon arrival at the Emergency Operations Facility (EOF), report to the EPD.

5.3.2 Assist EPD in the activation of the Environmental Dispatch area using Form EPIPF-ENV-01-01, "Environmental Dispatch Area Activation Checklist."

5.3.3 Obtain meteorological and plant status information from the Dose Projection Calculator (DPC) and complete Form EPIPF-ENV-01-03, "Meteorological and Plant Status Data."

5.3.3.1 IF all of the following meteorological conditions exist, THEN the potential for a lake breeze effect exists.

a. KNPP or Point Beach Nuclear Plant (PBNP) wind direction is between 020 and 170 degrees, AND

b. Green Bay National Weather Service or PBNP Inland Tower wind direction is between 210 and 330 degrees, AND

c. The time is between 0700 and 2000.

5.3.3.2 IF a potential for a lake breeze effect exists, THEN direct EMTs to verify the plume has NOT traveled in a northern or southern direction along the lakeshore.

REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-ENV-O1 Rev. W Title Environmental Monitoring Group Kewaunee Nuclear Power Plant Organization and Responsibilities Emergency Plan Implementing Procedure Date AUG 20 2002 Page 4 of 7 5.3.4 Draw the projected plume on the Emergency Planning Zone (EPZ) grid map located in the Environmental Dispatch Area using the following:

5.3.4.1 Wind direction as the projected plume centerline 5.3.4.2 The projected plume boundaries (based on the stability class) as the lateral edges 5.3.5 Direct the Environmental Monitoring Team Communicator (EMTCM) to establish and maintain communications with the EMTs.

5.3.6 With EPD concurrence, develop a strategy and EMT orders for the following:

a. Plume tracking

b. Sample collection

c. Sample analysis 5.3.6.1 Relay the strategy to the EMTs through the EMTCM.

5.3.7 Obtain a copy of Form EPIPF-ENV-01-02, "EMT Status," from the EMTCM.

"" Team Designation and team members' names

"* Standing Order implemented by each team

"* Current Annual Dose (TEDE)

"* Date and Time Activated

"* Team Status (EMT activities in progress including order being implemented by each team, team location, etc.)

5.3.8 Direct the EMTCM to provide the EMTs with initial and updated meteorological and plant status information using EPIPF-ENV-01-03, "Meteorological and Plant Status Data."

REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-ENV-01 Rev. W Title Environmental Monitoring Group Kewaunee Nuclear Power Plant Organization and Responsibilities Emergency Plan Implementing Procedure Date AUG 20 2002 Page 5 of 7 EnvironmentalMonitoringTeams (EMTs) should NOT enter areaswhere projected or measuredexternal radiationdose rates exceed 1 R/hr without specific directionfrom the EPD or RPD.

Note EMT members are instructedto report exposure every hour or when 100 mrem has been received.

5.3.9 Track the cumulative radiation exposure for each EMT member as follows:

5.3.9.1 Obtain deep dose equivalent (DDE) from EMTs every hour.

5.3.9.2 Add the DDE to the current annual TEDE.

5.3.9.3 Direct the EMTCM to periodically report the sum of the current annual TEDE and cumulative DDE to the EMT members.

5.3.10 IF the sum of the current annual TEDE and cumulative DDE approaches administrative limits, THEN consider authorization for increased radiation exposure in accordance with NAD-01. 11, "Dosimetry and Personnel Monitoring."

5.3.11 IF radiological conditions are such that EMTs could exceed 10CFR20 limits THEN consider emergency exposure in accordance with EPIP-AD-1 1, "Emergency Radiation Controls."

5.3.12 Ensure that all data received from the EMTs is provided to the EPD and DPC in a timely manner.

5.3.13 Plot EMT field data on the EPZ grid map in the Environmental Dispatch Area.

5.3.14 Continue monitoring team activities as directed by the EPD.

5.4 Environmental Monitoring Team Communicator (EMTCM) duties:

5.4.1 Upon arrival at the EOF, report to the EMTCD.

5.4.2 Assist in the activation of the Environmental Dispatch Area using Form EPIPF-ENV-01-01, "Environmental Dispatch Area Activation Checklist."

5.4.3 Establish communications with each activated EMT.

REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-ENV-01 Rev. W Title Environmental Monitoring Group Kewaunee Nuclear Power Plant Organization and Responsibilities Emergency Plan Implementing Procedure Date AUG 20 2002 1 Page 6 of 7 5.4.4 Obtain the information required on EPIP-ENV-01-02, "EMT Status," from the EMTs and forward the form to the EMTCD.

5.4.5 Transmit orders and other information from the EMTCD to the EMTs using the following:

a. Fax

b. Cellular phone

c. Radio 5.4.6 Record information from the EMTs on form EPIPF-ENV-01-04, "EMT Orders/Field Data," and forward the form to the EMTCD.

5.4.7 Perform the responsibilities of the EMTCM as long as the EMTs are activated.

5.5 The Environmental Monitoring Team (EMT) members shall:

5.5.1 Activate EMTs in accordance with "Environmental Monitoring Team Activation,"

EPIP-ENV-02.

5.5.2 Implement EPIP-ENV-04D, "Plume Tracking for Environmental Monitoring Teams."

6.0 Final Conditions 6.1 Plant Emergency has been Terminated or Recovery actions have begun and the Emergency Response Manager has suspended the use of EPIPs.

7.0 References 7.1 KNPP Emergency Plan (Appendix D: Letters of Agreement) 7.2 EPIP-AD-1 1, Emergency Radiation Controls 7.3 EPIP-ENV-02, Environmental Monitoring Team Activation 7.4 EPIP-ENV-03C, Dose Projection Using RASCAL Version 2.2 Software 7.5 EPIP-ENV-04D, Plume Tracking for Environmental Monitoring Teams 7.6 EPIP-EOF-03, Corporate Action for Unusual Event 7.7 EPIP-EOF-04, Corporate Action for Alert or Higher 7.8 NAD-01. 11, Dosimetry and Personnel Monitoring REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-ENV-O1 Rev. W Title Environmental Monitoring Group Kewaunee Nuclear Power Plant Organization and Responsibilities "EmergencyPlanImplementing Procedure Date AUG 20 2002 Page 7 of 7 8.0 Records 8.1 The following QA records and non-QA records are identified in this directive/procedure and are listed on the KNPP Records Retention Schedule. These records shall be maintained according to the KNPP Records Management Program.

8.1.1 QA Records

"* Environmental Dispatch Area Activation Checklist, Form EPIPF-ENV-01-01

"* EMT Status, Form EPIPF-ENV-01-02

"* Meteorological and Plant Status Data, Form EPIPF-ENV-01-03

"* EMT Orders/Field Data, Form EPIPF-ENV-01-04

"* Radiological Status Report, Form EPIPF-EOF-08-06 8.1.2 Non-QA Records None REFERENCE USE

,WISCONSIN PUBLIC SERVICE No EPP-ENV-03C Rev. W

. .. .. Title Dose Projection Using RASCAL

,A&,Kewaunee Nuclear Power Version 2.2 Software 1n.eeIethenm-1Proeitre7,,. Date AUG 20 2002 Pa e1of20 Reviewed By Dave Seebart Approved By Dave Seebart Nuclear PORC SRO Approval Of 3 Yes 03Yes Review 3 Yes Tempora l Safety 0 No Related 0 No Required 0 No Changes Required 1.0 Purpose 1.1 This procedure provides instruction for assessing radiological dose due to radiological emergencies using Radiological Assessment System for Consequence Analysis (RASCAL)

Version 2.2 Software.

1.2 RASCAL is a set of computer based tools to estimate the following: source term, atmospheric transport, dose from a radiological accident, dose from field measurements of radiological concentrations, and compute decay of radionuclides.

2.0 General Notes 2.1 For releases of radionuclides too small to be adequately evaluated using RASCAL, refer to SP-32B-268, "Site Boundary Doses from Gaseous Effluents."

2.2 After activation of the EOF and the RAF, each dose projection printout should be reviewed and approved by both the Radiation Protection Director (RPD) and the Environmental Protection Director (EPD) prior to distribution to the Emergency Director (ED) or Emergency Response Manager (ERM).

2.3 Kewaunee Nuclear Power Plant (KNPP) Meteorological Data is available from the Plant Process Computer - Group Output Block #9, Graphics Display #54 or #111, Point Summary

1. M@@@@@, or the Technical Support Center.

2.4 Point Beach Meteorological Data is available through the Point Beach Nuclear Power Plant Control Room (See KPB Emergency Telephone Directory for the telephone number).

2.5 RASCAL may be run from any computer connected to the primary network server used at KNPP.

2.6 Two computers, connected to reliable power sources and provided with hard disk drives and necessary software, are provided as stand alone dose calculating stations to be used to run RASCAL Version 2.2. They are in:

"* EOF Dispatch Area (GB D2-6)

"* RAF Calibration Room n:nucdoc'procedures~draft~epip~eenvO3c.doc-Chnst~ne Simmons/Christine Simmons-Jeanne Ferris REFERENCE USE

3.0 Precautions and Limitations 3.1 Lake Breeze is NOT calculated by RASCAL.

3.1.1 To determine if Lake Breeze is present, see Table 1.

3.1.2 IF Lake Breeze is present, THEN RASCAL projections may NOT be correct.

3.2 Due to the uncertainties of initial conditions and the unfolding accident sequence, RASCAL should be used to bound the possible range of dose projections. Set up several sets of inputs to cover the possible range of plant conditions (source terms), event data, and meteorological conditions.

3.3 Dose projections produced by RASCAL are rough estimates and should serve only as a guide during a declared emergency. Protective Action Recommendations should be based as a minimum on the level of declared emergency as stated in EPIP-AD-19, "Protective Action Guidelines," and when available actual conditions as measured in the field.

3.4 Ensure the requirements of NAD-05.23, "Computer Software Management Program," are met for the RASCAL Computer Program.

4.0 Initial Conditions 4.1 This procedure is to be used in conjunction with RASCAL software whenever conditions at the Kewaunee Nuclear Power Plant involve a release, or potential release of radioactive materials to the atmosphere.

5.0 Procedure 5.1 Starting RASCAL without Network Support.

Note The computer in the EOFdispatch area is "Stand Alone" and does NOT have a network connection. It is equippedwith a harddrive which is setup to boot and run RASCAL automatically.IF RASCAL doesn 't start, THEN perform Step 5.1.1 using a designatedback-up Lap Top computer.

5.1.1 In the EOF Dispatch Area, perform the following steps:

5.1.1.1 Ensure a laser printer is connected to the computer 5.1.1.2 Restart (reboot) the computer REFERENCE USE

"{ WiSCONSIN PUBLIC SERVICE'CORP.tS No. EPIP-ENV-03C Rev. W

~k~4ewaneeTitle Dose Projection Using-RASCAL

. Kewaunee.Nucle-a-'r-we~rPlant. Version 2.2 Software

"-pldAnJTMlemeDtihk Pro' Date AUG 20 2002 - Page 3 of 20 Note In the RAF, RASCAL may be runfrom the network using Step 5.2. When it is run stand alone, using Step 5.1.2, it is NOT set upfor printing.

5.1.2 In the RAF or RAF Calibration Room, perform the following steps:

5.1.2.1 Remove the network cable from the wall 5.1.2.2 Restart (reboot) the computer 5.1.2.3 Select Start, then Run 5.1.2.4 Type C:\RASCAL22\RASCAL22.BAT 5.1.2.5 Enter Note Contact the Help Desk at extension 8100 ifproblems are encountered.

5.2 Starting RASCAL from a Network computer.

5.2.1 Log onto the network using your normal Login ID.

5.2.2 Select the desired printer.

5.2.2.1 Click on the START button 5.2.2.2 Click on the SETTINGS icon 5.2.2.3 Click on the PRINTERS icon 5.2.2.4 Select the desired printer and right click on the icon 5.2.2.5 Left click on the SET AS DEFAULT 5.2.2.6 Close printers folder 5.2.3 Run the RASCAL Program 5.2.3.1 Select Start, then Run 5.2.3.2 Type N:\APPS\RASCAL22\RASCAL22.BAT REFERENCE USE

5.3 WHEN the RASCAL Version 2.2 Program starts and displays text showing the version, THEN press any key or any mouse button to continue.

5.3.1 Select one of the following menu choices:

" Source Term to Dose (ST-DOSE) should be used to asses the consequences of potential or ongoing releases. ST-DOSE estimates the integrated doses and consequences resulting from the accidental release of radionuclides to the atmosphere.

"* Close-In Source Term to Dose is designed for a materials accident. In a materials accident the effects are usually close to the source. A "close-in" straight-line Gaussian plume model estimates doses within 25 to 800 meters from the accident site.

"* Field Measurement to Dose (FM-DOSE) computes doses from measured environmental radionuclides in the air or on the ground.

"* Decay Calculator computes the activities of radionuclides present after decay and ingrowth for a period specified by the user.

"* Exit/Return to System.

5.4 IF ST-DOSE or Close-In source is chosen, THEN select "Create New Case."

Note The case name will appearas a title on theprintouts and,therefore, should be both descriptiveand unique. For example: Tube rupture- InitialRun, No fuel damage.

5.4.1 Enter a CASE TITLE on the main data entry form in the first field (i.e., Kewaunee Plant Emergency Drill).

5.4.1.1 Pressing F6 will clear the field and allow quick entry.

5.4.1.2 Add your initials to the title to help identification of your printout.

5.4.2 Site Name, enter "K" for Kewaunee.

5.4.3 Effective Release Height, enter OM.

5.4.4 Default Units: Select (Ci) 5.4.5 Data Source: IF the data entered are not measured data, THEN select projected. IF the data entered are real data for an actual incident, THEN select actual.

REFERENCE USE

-WlSCONSlN PUBLIC SERVICECORP . No. EPIP-ENV-03C Rev. W

. .Z,-"Title Dose Projection Using RASCAL waunee Version 2.2 Software e~FgePI~anImplementingProcedure Date AUG 20 2002 Page 5 of 20 5.4 .6 Select one of the following source term calculation methods:

"* Isotopic Release Rate

"* Isotopic Concentrations

"* Mix specified by Analyst

"* Plant Conditions

"* Containment Monitor Reading

"* Spent Fuel/Spent Fuel Pool Note Contact the RPDfor isotopic release rate information (Form EPIPF-RET-02B-01 or Form EPIPF-RET-02B-02).

5.4.6.1 IF the source term release rates for each radionuclide has been estimated independently, THEN select isotopic release rate.

5.4.6.1.1 Release Units: Select units of the release, first select metric prefix, then select sec., min., or hr.

5.4 6.1.2 Release Rates: Enter release rate for each radionuclide to a maximum of three significant figures.

5.4.6.1.3 Zero - resets all release rates to zero.

5.4.6.1.4 Select MAIN MENU or press F10 Key to exit form.

5.4.6.2 IF the source term release concentration for each radionuclide has been estimated independently, THEN select isotopic concentrations.

5.4.6.2.1 Release Rate: Enter release rate for the accident then select cc, ft3, liter, or g., then select sec., min., or hr.

5.4.6.2.2 Concentration Units: Select the units of concentration, first select metric prefix, then select cc, ft3, liter, or g.

5.4.6.2.2 Concentration: Enter concentration of each radionuclide to a maximum of three significant figures.

5.4.6.2.3 Zero - resets all concentrations to zero.

REFERENCE USE

%WISCNSIN PUBLICSERVICE CORPV-4 No. EPIP-ENV-03C Rev. W Title Dose Projection Using RASCAL Version 2.2 Software an Smergency, Date AUG 20 2002 Page 6 of 20 Note This pushbutton imports datafrom the decay calculator.The data imported is added to the concentrationsalreadypresent on the form.

5.4.6.2.4 Import: (Option) Allows the decay of several isotopic concentrations over different time periods and then adding them together.

5.4.6.2.5 Select MAIN MENU. Press F10 key to exit form.

Note Contactthe RPDfor SPING data or steam release information (FormsEPIPF-RET-02B-03,EPIPF-RET-02B-04,or EPIPF-RET-02B-05).

5.4.6.3 IF gross release rate information is available on Form EPIPF-RET-02B-03 (Auxiliary Building Stack Release), Form EPIPF-RET-02B-04 (Containment Stack Release), or Form EPIPF-RET-02B-05 (Steam Release), THEN select Mix Specified by Analyst.

5.4.6.3.1 Enter the gross release rate in Ci/sec.

Note Sum ofpercentage of release may not be greaterthan 100%.

Note Default valuesfor percentageof release are 98% noble gases, 2%

iodines.

5.4.6.3.2 Percentage of Release: Enter the estimated percentages of the release that is in each of the listed categories.

5.4.6.3.3 Select MAIN MENU or press F10 Key to exit form.

5.4.6.4 IF the release pathway is known, THEN select Plant Conditions.

5.4.6.4.1 Select one of the following release pathways:

"* Large dry or sub atmospheric containment (leakage/failure)

"* Steam generator tube rupture

"* Bypass of containment REFERENCE USE

No. EPIP-ENV-03C Rev. W 1Ri Title Dose Projection Using RASCAL uceaPwe PlaVersion 2.2 Software

- ziLentin,, rnn~I PDate AUG 20 2002 Page 7 of 20 5.4.6.4.2 IF the release pathway is large dry or subatmospheric containment leakage/failure, THEN select:

Note Core Conditionscan be obtainedfrom the ControlRoom or the TSC if it is activated.

a. Core conditions:

"* Gap release (15-30 min)

" In-vessel severe core damage (>30 min.)

"* Vessel melt through

b. Enter reactor power for the last few months or a default of 1,650 Mw(T)

c. Select sprays (ON or OFF)

d. Select release path (Filtered or Unfiltered)

e. Select leak Rate (percent per hr)

f. Select MAIN MENU or press F10 Key to exit form 5.4.6.4.3 IF release pathway is Steam Generator Tube Rupture, THEN:

Note Core Conditions can be obtainedfrom the ControlRoom or the TSC if it is activated.

a. Select the coolant concentrations using the description that is closest to probable core condition:

"* Gap release (uncovered 15-30 min.)

" In-vessel severe core damage (>30 min.)

"* Typical coolant

"* Coolant with 100x normal non-nobles

b. Select Steam Generator Conditions (Partitioned or Not Partitioned)

REFERENCE USE

Note Default is one tube.

c. Select Release Rate using one of five leak rate categories, based on number of tubes or pumps active.

d. Select release is from (steam jet air ejector or safety valves).

e. Select MAIN MENU or press F10 Key to exit form.

5.4.6.4.4 IF the release pathway is Bypass of containment, THEN:

Note Core conditionscan be obtainedform the ControlRoom or TSC if it is activated.

a. Select one of the following core conditions:

"* Gap release (15-30 min.)

"* In-vessel severe core damage (>30 miin.)

" In-vessel melt through

b. Enter Reactor Power level last few months or a default of 1,650 Mw(T)

c. Select release path (filtered or unfiltered)

d. Select leak rate (percentage per hour)

e. Select MAIN MENU or press F10 Key to exit form.

5.4.6.5 IF the containment area radiation levels are known, THEN select Containment Monitor Reading.

5.4.6.5.1 Select Location of Monitor (PWR) 5.4.6.5.2 Enter Reactor Power for the last few months or allow default of 1,650 Mw(t) 5.4.6.5.3 Enter Monitor Reading in R/hr 5.4.6.5.4 Select containment sprays (ON or OFF) 5.4.6.5.5 Select Release Path (filtered or unfiltered) 5.4.6.5.6 Select Leak Rate from one of the eight leak rate categories in percent per hour 5.4.6.5.7 Select MAIN MENU or press F10 Key to exit form REFERENCE USE

.zWISCONSIN PUBLIC SERVICE CORP. No EPIP-ENV-03C Rev. W ZF .Title Dose Projection Using RASCAL

• i*:*ewaunee 'Nuclear P*ower=lant  ;-Version 2.2 Software

- e P Ik'an lmlemhenýn

,merge roe Date AUG 20 2002 Page 9 of 20 5.4.6.6 IF the accident is based on the spent fuel, THEN select Spent Fuel/Spent Fuel Pool 5.4.6.6.1 Select Fuel Condition (Zircalloy Fire-New Batch Only or Fuel Cladding Failure-Gap Release) 5.4.6.6.2 Enter Reactor Power for the last few months or allow default of 1,650 Mw(t) 5.4.6.6.3 Enter Last Batch put in Pool (date and time) 5.4.6.6.4 Enter number of batches 5.4.6.6.5 Select sprays (ON or OFF) 5.4.6.6.6 Select Release Path (filter or unfiltered) 5.4.6.6.7 Select Leak Rate (one of the seven leak rates in percent per hour) 5.4.6.6.8 Select MAIN MENU or press F10 Key to exit form 5.4.7 Select EVENTS from the main menu.

Note Radionuclides are decayedfrom shutdown time except when the isotopic releaserates containment monitor or spentfiel option are used.

5.4.7.1 If required, enter the day and time the Reactor Shutdown, or IF the analysis does not model a reactor trip, THEN enter the time the release started in the SHUTDOWN field.

Note The releasestartto containment time may be the same as shutdown or up to one year later.It may not be before shutdown.

5.4.7.2 If required, enter date and time for Release to Containment or Other Structure when the release from the Reactor Coolant System occurred.

Note The releasestart to environment shall not be before the releaseto containment but may be up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after it.

5.4.7.3 If required, enter the day and time for Release to Environment (Start of Exposure) when the release to the atmosphere occurred.

REFERENCE USE

• -WISCONSlN PUBLIC SERVICE CORP.; %; No. EPIP-ENV-03C Rev. W

., Title Dose Projection Using RASCAL Kewaunee W-a',-n- 1cear Power Plant, Version 2.2 Software

"'-v *itire Plan lii lemeting Procidure xII,"

Date AUG 202002 Page 10 of 20 Note The release end time can be from I minute to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the start of the release.

Note IF a leak rate of 100% per hour is to be selected in the source-term section, THEN the release end time cannot be more than I hour later than the release starttime.

5.4.7.4 If required, enter the End of Release to Environment day and time.

Note Exposure end time shall be the same as or later than the releaseto environment end. However, it cannot be more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after the release to environment end.

5.4.7.5 If required, enter the End of Exposure day and time, time when dose calculations will end.

5.4.7.6 WHEN all the Event Times are entered correctly, THEN select MAIN MENU or "pressF10.

5.4.8 Select METEOROLOGICAL DATA from the Main Menu.

Note The time enteredfor thefirst set of met data should correspondto the start of release.

5.4.8.1 Enter date and time meteorological data was obtained.

5.4.8.2 Enter the 10 meter wind speed.

5.4.8.3 Enter the 10 meter wind direction.

Note RASCAL does NOT calculate the meteorologicalstability classification.

Table 3 can be used to determinePasquillcategories.

5.4.8.4 Select the stability class of the mixing layer. A choice list of stability classes is displayed when the stability field is highlighted.

REFERENCE USE

5.4.8.5 Enter Mixing Layer Height (Default 500m)

Note Precipitationaffects the wet deposition rate. The precipitationtype and intensity can be found in National WeatherService hourly weather reports. Table 2 provides the conversion of weather reportprecipitation symbols to the appropriateprecipitationclass and intensity.

Note IF a weather reportshows more than one precipitationtype, THEN choose the type giving the most intense model precipitation Note IF rain and snow precipitationare reportedwith equal intensity, THEN enter the correspondingrain intensity.

5.4.8.6 Select Precipitation Type

"* None

"* Light Rain

"* Moderate Rain

"* Heavy Rain

"* Light Snow

"* Moderate Snow

"* Heavy Snow 5.4.8.7 WHEN all of the data is entered correctly, THEN select MAIN MENU or press F10 key to exit this form.

5.4.9 IF additional meteorological data for other times is to be entered, THEN repeat Step 5.4.8.

Note There are two dispersion models: Plume or Puff. Useplume when projecting dose based on a single met data set. Use puff when projecting dose based on several different met data sets,for extremely low wind speed conditions,or when more datapoints on the plots are desired.

Select the PLUME option to calculate doses using a straight-line Gaussian plume model.

REFERENCE USE

Note All of the meteorology data that have been entered and that are effective during the intervalfrom release to the environment through the end of exposure are used in calculatingdoses with a Puffmodel.

Select the PUFF model to calculates doses for 0-2 miles using straight-line Gaussian plume model and for greater distances using a Lagrangian puff model.

5.4.10 Select CALCULATION OPTIONS from the Main Data Entry Form (Plume or Puff).

Note This option is NOT includedfor CLOSE-IN STDOSE calculations(0-2 MI).

5.4.11 Select BUILDING WAKE (ON or OFF)

Select on to include building wake into calculation.

Note The release will be assumed to be at ground level if the wind speed is I mph or more and the rate of diffusion will be increased to accountfor the effects of the buildingwake. If wind speed is less than I mph, the release will be assumed to be at the specific releaseheight and the diffusion rate will not be adjusted.

Select OFF to exclude building wake effects.

Note RASCAL defaults to a 10 mile radiusfrom the plant with a spatialresolution of 0.67 mile.

5.4.12 Select CALCULATION RADIUS (10 miles (16KM) or 25 miles (40 KM)).

Note The calculatepushbutton is not available ifyou have not defined a title and a source term or ifyou have selected a new plant site andpreviouslyselected source term option is invalidfor the new plantsite.

The form that appears summarizes the input and reports calculation progress.

REFERENCE USE

• 'WISCONSIN PUBLIC SERVICE CORP. No. EPIP-ENV-03C Rev

, *'"," ;*;.*Title

• • -*., Dose Projection Using RJASCA]

PlantVersion

=ower Plantuclear;wer 2.2 Software e "y amr ncy* ementin Procedure Date AUG 202002 Pae 5.4.13 Select CALCULATE to begin calculations.

Note Three summary reports and ten graphicreportsare generated.Only significant results are displayed. Values <10-3 rem are converted to zeros.

5.4.13.1 Select the desired report for the list below:

MAXIMUM VALUES to display a table of the Maximum Doses at selected distances from the release point.

• COMPUTED SOURCE TERM REPORT for a summary of the radionuclides making up the release will be displayed and radionuclide and the fraction of the core inventory released.

Note Not availablefor CLOSE-IN ST DOSE calculations(0-2 MI).

The remaining options are:

• TOTAL ACUTE BONE DOSE to plot the Total Acute Bone Dose on the map and give insight into early health effects for reactor accidents.

9 ACUTE LUNG DOSE to plot the Acute Lung Dose on the map and provide insight into early health effects for accidents where lung dose dominates such as Pu releases.

e TEDE to plot the Total Effective Dose Equivalent on the map for comparison with EPA guidance.

• THYROID DOSE to plot the Thyroid Dose on the map for comparison with EPA thyroid PAGs.

• CLOUD SHINE DOSE to plot the Cloud Shine Dose on the map for calculating the DDE from the plume.

REFERENCE USE

Note The total Deep Dose Equivalent (DDE)equals cloud shine + initial groundshine.

"* INITIAL GROUND SHINE DOSE to plot Ground Shine Dose on the map for calculating DDE from deposition.

"* 4-DAY GROUND SHINE DOSE to plot the deposition component of the Total Effective Dose Equivalent on the map (not normally viewed).

"* ACUTE BONE INHALATION DOSE to plot the Inhalation Component of the Total Acute Bone Dose on the map (not normally viewed).

2

"* DEPOSITION to plot the Ground Deposition levels in JtCi/cm and on the map (not normally viewed).

5.4.13.2 Select (VIEW/PRINT) to see projected data. If a printout is required, select (Print (ALT-P) or Enter (ALT-P))

5.4.13.3 Select (Save File) to save your calculations for later review.

5.4.13.4 Select MAIN FORM or press (Fl 0) to exit this form.

5.4.14 Select (Mainform (F-10)) or the F-10 key to return to the main menu.

5.5 Comparison of RASCAL Dose Projection Results with Environmental Monitoring Team (EMT) Survey Results.

5.5.1 IF available, THEN obtain plume centerline field radiation survey results (mR/hr) at 0.5, 1.0, 2.0, 5.0, and/or 10 miles from the plant.

5.5.2 Using the maximum values results (screen and printout) for the completed dose projection, add the doses (rem) from the Cloud Shine line and the Initial Ground Shine line together (for the appropriate distance from the plant).

5.5.3 Convert the sum of Cloud Shine and Ground Shine Dose from rem to mrem (multiply by 1,000).

5.5.4 Convert the sum of Cloud Shine and Initial Ground Shine Dose to a dose rate (mrem/hr) by dividing the sum by the total exposure time (hours) entered in the event times menu.

5.5.5 Compare the dose rate (mrem/hr) from the dose projection determined in Step 5.5.4 to the dose rate (mrem/hr) measured by the field team at the corresponding centerline distance from the plant.

REFERENCE USE

I*S PUBLIC 'SE*VI'SERVICE CORP.;`

IN No. EPIP-ENV-03C Rev.

IR W CORPB

.itle Dose Projection UsingRASCAL wa e NPlant ,Version leaPower 2.2 Software 7N a hIMmier Ced ntingProced, Date AUG 20 2002 Page 15 of 20 5.6 IF Field Measurements to Dose (FM-Dose) is chosen, .THENselect CREATE NEW CASE.

Note A title shall be entered to calculate results.

5.6.1 Enter a title.

Note Informationfor this task can be found on Form EPIPF-RET-02B-06, "Field Reading (Grab Sample). "

5.6.2 If known, enter the date and time the sample was collected.

5.6.3 Ground Concentration Units: Select units, first select metric unit and (Ci or Ba). Then select 02, CM2 or ft2).

5.6.4 Air Concentration Units: Select units, first select metric units and (Ci or Ba) then select (M3, CM 3, or ft3).

5.6.5 Enter ground concentrations.

Note Surface CorrectionFactor,Resuspension Factor,andReentry Delay are set at default values and should only be changed ifspecific instructionsto do so are given.

5.6.5.1 Enter exposure time.

5.6.5.2 Enter concentration for each nuclide deposited.

5.6.5.3 Use "scroll up" or "scroll down" for additional nuclides.

5.6.5.4 Select MAIN MENU or press F10 to exit form.

5.6.6 Enter air concentration.

5.6.6.1 Enter exposure time.

5.6.6.2 Enter concentration for each nuclide.

5.6.6.3 Use "scroll up" or "scroll down" for additional nuclides.

5.6.6.4 Select MAIN MENU or press F10 to exit form.

\,5.6.7 Select the concentrations to be used in the calculations (air, ground, or both).

REFERENCE USE

iSONSIN PUBLIC 'SERVICE CORP. No. EPIP-ENV-03C Rev. W v *1 Title Dose Projection Using RASCAL hn <Version 2.2 Software

• -.E-idr ~ Date AUG 20 2002 Page 16 of 2(

5.6.8 Select the dose units, metric unit and (REM or Su).

5.6.9 Select calculate.

5.6.10 Select the view desired.

6.0 Final Conditions 6.1 Plant Emergency has been Terminated or Recovery actions have begun and the Emergency Response Manager has suspended the use of EPIPs.

7.0 References 7.1 NAD-05.23, Computer Software Management Program 7.2 EPIP-AD-19, Protective Action Guidelines 7.3 SP-32B-268, Site Boundary Doses from Gaseous Effluents 7.4 NUREG/CR-5247/PNL-8454, Vol. 1, Rev. 1, RASCAL Version 2.2 User's Guide 7.5 Workbook of Atmospheric Dispersion Estimates, D. Bruce Turner, 1970 7.6 NUREG/BR0150, Vol. 1, Rev. 2, RTM-92 Response Technical Manual 7.7 EPA-400-R-92-001, Manual of Protective Action Guides and Protective Actions For Nuclear Incidents 7.8 NUREG/CR-5247, Vol. 2, Rev. 2, RASCAL Version 2.2 Workbook 7.9 EPIP Forms 7.9.1 Form EPIPF-RET-02B-01, Containment Stack Release (Grab Sample) 7.9.2 Form EPIPF-RET-02B-02, Auxiliary Building Stack (Grab Sample) 7.9.3 Form EPIPF-RET-02B-03, Auxiliary Building Stack (Sping Reading) 7.9.4 Form EPIPF-RET-02B-04, Containment Stack (Sping Reading) 7.9.5 Form EPIPF-RET-02B-05, Steam Release 7.9.6 Form EPIPF-RET-02B-06, Field Reading (Grab Sample)

REFERENCE USE

8.0 Records 8.1 The following QA records and non-QA records are identified in this directive/procedure and are listed on the KNPP Records Retention Schedule. These records shall be maintained according to the KNPP Records Management Program.

8.1.1 QA Records

• RASCAL Projection Printouts 8.1.2 Non-QA Records None REFERENCE USE

LAKE BREEZE Determine Lake Breeze Effect The following conditions must be met for a possible Lake Breeze Effect:

KNPP or PBNP wind direction is between 200 and 170%,

AND PBNP Inland Tower or Green Bay NWS wind direction is between 2100 and 3300, AND Meteorological Data Record time is between 0700 and 2,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, AND Meteorological Data Record date and date of Lake Breeze onset time are the same.

Table 1 EPIP-ENV-03C Rev. W Date: AUG 20 2002 Page 18 of 20 REFERENCE USE

WEATHER REPORT SYMBOL, MODEL CLASS, AND INTENSITY

- .7.° WEATHER REPORT SYMBOL MODEL CLASS INTENSITY None NONE --

A SNOW Moderate IC-, IP- SNOW Light IC, IP SNOW Moderate IC+, IP+ SNOW Heavy L-, L, L+ RAIN Light R-, RW- RAIN Light R, RW RAIN Moderate R+, RW+ RAIN Heavy S-, SG-, SP-, SW- SNOW Light S, SG, SP, SW SNOW Moderate S+, SG+, SP+, SW+ SNOW Heavy ZL-, ZL, ZL+, ZR- RAIN Light ZR RAIN Moderate ZR+ RAIN Heavy rage i OT U Table 2 EPIP-ENV-03C Rev. W Date: AUG 20 2002 Page '19 OT ZU REFERENCE USE

STABILITY CLASSIFICATION To specify a stability classification without using RASCAL, first obtafin Delta T or Sigma Theta from the Meteorological data. Values of Delta T or Sigma Theta will correspond to the various stability

<.-; classifications as shown below STABILITY PASQUILL SIGMA THETA (ao) 60M - 10M CLASSIFICATION CATEGORIES (DEGREES) DELTA T (OF/50M)

Extremely Unstable A a0 Ž_22.5 DELTA T _ -1.71 Moderately Unstable B 22.5 > aO _>17.5 -1.71 <DELTA T:5 -1.53 Slightly Unstable C 17.5 > ar0'e 12.5 -1.53 < DELTA T*5 -1.35 Neutral D 12.5 > a0 _7.5 -1.35 < DELTA T 5 -0.45 Slightly Stable E 7.5 > a0 _3.8 -0.45 < DELTA T _ 1.35 Moderately Stable F 3.8 > a0 Ž_2.1 1.35 < DELTA T _3.60 Extremely Stable G 2.1 > aD 3.60 < DELTA T

Reference:

ANSIIANS-2.5-1984 LU UI LU Table 3 EPIP-ENV-03C Rev. W Date: AUG 20 2002 raeu* 01 XU L

REFERENCE USE

"WISCONSIN PUBLIC SERVICE CORP. No. EPIP-ENV-04A Rev. T Title Portable Survey Instrument Use Kewaunee Nuclear Power Plant "EmergencyPlanImplementing Procedure Date AUG 20 2002 Page 1 of 6 Reviewed By Brad Gauger Approved By W. L. Yarosz Nuclear 13 PORC 13 SRO Approval Of Ye Safety '] Yes Review 0 Yes Temporary 0 Yes Related 0 No Required l No Changes Required 0 No 1.0 Purpose 1.1 This procedure provides instruction for using portable survey instruments used by the Environmental Monitoring Teams (EMTs).

2.0 General Notes 2.1 Environmental Monitoring Teams are responsible for following this procedure when using portable survey instruments.

3.0 Precautions and Limitations 3.1 Do not wrap, in plastic, the detector of any instrument that can be used to measure Beta radiation. Wrapping the detector in plastic during operation may shield Beta radiation.

Instruments and their detectors may be placed in a plastic bag to prevent contamination while "beingtransported.

3.2 Each instrument and its attached detector have been calibrated as a set. DO NOT interchange instruments and detectors unless authorized by the Radiation Protection Group.

Interchanging instruments and detectors invalidates the instrument/detector calibration.

3.3 EMTs should verify an adequate supply available and wear protective clothing when exiting the vehicle.

4.0 Initial Conditions 4.1 This procedure is used during a declared plant emergency by the EMTs when operating portable survey instruments.

n:\nucdoc\procedures\draft\epip\eenv04a.doc-Christine SimmonslChristine Simmons-Rick Adams REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-ENV-04A Rev. T Title Portable Survey Instrument Use Kewaunee Nuclear Power Plant Emergency Plan Implementing Procedure Date AUG 20 2002 Page 2 of 6 5.0 Procedure Note Preoperationalinstrument checks are documented on Form EPIPF-ENV-02-O1, "EMTActivation Checklist."

Note IF any instrumentfails a preoperationalcheck, THEN obtain a spare instrument OR contact the RPO/RAFfor assistance.

5.1 Prior to using any portable survey instruments, perform a preoperational instrument check which consists of:

• Inspecting the instrument for deterioration or defect (frayed electrical connections, broken meter face, etc.).

a Verifying the instrument has been calibrated within the due date listed on the instrument calibration sticker.

• Verifying the batteries are satisfactory.

0 Verifying the instrument response to a check source is satisfactory.

5.2 Ion Chamber Use 5.2.1 Turn the function switch to check the battery(s).

5.2.1.1 IF the battery(s) levels indicates satisfactory, THEN use the instrument.

Otherwise replace the battery(s) and recheck them.

5.2.2 Turn the function switch to the ZERO position. Check that the meter reads zero. If not, set it to zero with the ZERO knob. For ALARA, this should be done in a low bkg. area.

5.2.2.1 The zero setting may be checked in any radiation field.

5.2.3 Perform a source check of the instrument and ensure the meter reads within +/-20% of the check source value as specified on the calibration sticker.

5.2.4 Set the function switch to the desired range of operation. The switch position selected is usually the full scale reading of that range.

5.2.4.1 The effective center of the ion chamber is usually marked by dimples at the front and sides of the instrument case. Otherwise the center can be found by looking at it with the window open.

5.2.4.2 Do not expose the instrument to fields of radiation significantly above full scale for the range selected or damage may result.

REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-ENV-04A Rev. T Title Portable Survey Instrument Use Kewaunee Nuclear Power Plant Emergency Plan Implementing Procedure Date AUG 20 2002 Page 3 of 6 5.2.5 When measuring Beta, open the sliding Beta shield on the bottom of the case and face the bottom of the instrument toward the radiation source. Multiply the Beta Correction Factor value listed on the calibration sticker by the difference of window open minus window closed readings to determine the Beta dose rate in mRADihr.

5.2.5.1 To open or close the shield, depress the friction release button and manually move the slide, or let it fall due to gravity. When the shield is open, protect the thin mylar face against puncture damage.

5.2.6 Perform a radiation survey.

Note Survey readingsare normally taken with the Beta window closed (Gamma only).

Note A high Beta/Gamma ratio at I meter indicatesthe presence of the plume at ground level (an airsample may be warranted).

Note A high Beta/Gamma ratio at 3 inches indicatesground deposition (environmentalsampling may be warranted).

Note No largeBeta/Gamma ratio indicates the plume may be overhead, weak, or you are not in the plume.

a. Determine the Gamma radiation level.

1. Hold the detector, with the Beta window closed, approximately 1 meter above the ground.

b. Determine the corrected Beta radiation level.

1. With the Beta window open, hold the survey meter approximately 1 meter above ground to determine the Beta/Gamma reading.

2. Subtract the reading taken in Step 5.2.6.a.1 from the reading taken in Step 5.2.6.b. I to obtain the uncorrected Beta reading.

(Uncorrected Beta reading = Beta/Gamma reading - Gamma reading)

3. Multiply the uncorrected Beta reading obtained in Step 5.2.6.b.2 by the Beta Correction Factor (BCF) listed on the instrument calibration sticker to obtain the corrected Beta radiation level.

(Corrected Beta radiation level = uncorrected Beta reading x BCF)

REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-ENV-04A Rev. T Title Portable Survey Instrument Use Kewaunee Nuclear Power Plant Emergency Plan Implementing Procedure Date AUG 20 2002 Page 4 of 6 Note HighercorrectedBeta radiationlevels at 3 "as compared to 1 meter indicate the presence of ground deposition.

5.2.7 Determine the presence of ground deposition.

a. Perform Steps 5.2.6.a and 5.2.6.b holding the detector at 1 meter AND approximately 3" above the ground.

b. Compare the corrected Beta reading taken at 3" to the reading taken at 1 meter.

5.3 Operate the ASP-1 with the HP-260 Detector 5.3.1 Perform a battery check.

a. Place the selector switch to the BATTERY CHECK position.

b. Confirm the meter indicates within the "BATT OK" area.

1. IF NOT OK, THEN the batteries need to be replaced.

5.3.2 Perform an instrument response to a check source.

Note Readings are sensitive to the check source/sampleposition on the detector. The instrument response to a check source readingshould be within _+20% of the required check source readingwritten on the calibrationsticker.

a. Place the HP-260 detector directly on contact with the check source.

b. Place the SELECTOR switch to a setting that gives an upscale reading, approximately 50% of full scale.

c. Compare the check source reading with the required check source reading on the instrument calibration sticker.

REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-ENV-04A Rev. T Title Portable Survey Instrument Use Kewaunee Nuclear Power Plant Emergency Plan Implementing Procedure Date AUG 20 2002 Page 5 of 6 5.3.3 Perform a contamination survey.

a. Place the FAST/SLOW instrument response switch to the FAST position.

b. Hold the detector within Y2" from the surface (ground, equipment, personnel, etc.) to be surveyed.

c. Move the detector over the surface to be surveyed at a rate of approximately 2" per second.

d. Continuously monitor the meter reading and adjust the SELECTOR switch multiplication factor so that the meter reads approximately 50% of full scale.

e. Multiply the meter reading by the selected multiplication factor to determine the contamination level in counts per minute (CPM).

5.3.4 Perform analysis of air sample media.

a. Place the FAST/SLOW instrument response switch to the FAST position.

b. Place the HP-260 detector directly on contact with either the filter paper or the iodine sampling canister to be monitored.

"c. Place the selector switch to the lowest range that does not produce an off-scale reading.

d. Obtain the stabilized reading and multiply it by the selected multiplication factor to determine the gross Counts Per Minute (CPM) for the sample.

e. Subtract the background CPM from the value obtained in Step d above to determine the net CPM.

6.0 Final Conditions 6.1 Plant Emergency has been terminated or Recovery actions have begun and the Emergency Response Manager has suspended the use of EPIPs.

7.0 References 7.1 HP-06.xxx, Instrument Operating Procedure Series Procedures 7.2 INPO 91-014, Rev. 01, Guidelines for Radiological Protection at Nuclear Power Stations, October 1995 REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-ENV-04A Rev. T Title Portable Survey Instrument Use Kewaunee Nuclear Power Plant "EmergencyPlan Implementing Procedure Date AUG 20 2002 Page 6 of 6 8.0 Records 8.1 The following QA records and non-QA records are identified in this directive/procedure and are listed on the KNPP Records Retention Schedule. These records shall be maintained according to the KNPP Records Management Program.

8.1.1 QA Records None 8.1.2 Non-QA Records None REFERENCE USE

No EPI-ENV-04B Rev. X

'Y iS"CONSIN PUBLIC SERVICE CORP. ,

. , -* .*W Title Air Sampling and Analysis

. Kewaunee u 0wer Plant' merYencyPlan Imvlemenftin cedure-, Date AUG 20 2002 Page 1 of 15 Reviewed By Brad Gauger Approved By W. L. Yarosz Nuclear 0Yes ie [ReYes SRO Approval Of DYes Safety 21 Nos ReviewPORCoSTemporary Of Related I No Required []No Changes Required 0No 1.0 Purpose 1.1 This procedure provides instruction for the Environmental Monitoring Teams (EMTs) for collecting and analyzing air samples during a declared plant emergency.

2.0 General Notes 2.1 The EMTs shall collect and analyze air samples in accordance with this procedure when directed.

3.0 Precautions and Limitations 3.1 Care shall be taken during sample acquisition to prevent sample cross contamination.

3.2 To keep personnel exposure ALARA, the air sampler may be left at the sample location to collect the air sample while the EMT waits in a low-dose area.

3.3 EMTs should not enter areas where projected or measured external radiation dose rates exceed 1 R/hr without specific direction from the Environmental Protection Director (EPD) or Radiological Protection Director (RPD).

3.4 EMT's should always verify adequate supply of and wear protective clothing when exiting the vehicle.

4.0 Initial Conditions 4.1 This procedure is used during a declared plant emergency by the EMTs when the teams are directed to collect and/or analyze environmental air samples.

n:\nucdoc\procedures\draft\epip\eenvO4b.doc-ChrisUtne SimmonslChrlstine Sifmons-Rick Adams REFERENCE USE

5.0 Procedure 5.1 Prepare for Air Sample Collection Note Wheneverpractical,perform Steps 5.1.1 and 5.1.2 prior to going to the sample location.

5.1.1 Obtain a 2-inch (Gelman) filter paper for particulates, a silver zeolite cartridge for iodine, and a Marinelli beaker for noble gas samples.

5.1.2 Prepare the air sampler for sample collection.

Note The air samplers are stored in a "ready configuration," meaning Steps "a" through "e" are complete. Begin with Step 'f. " Steps "a " through "Y"are included in case complete disassembly and re-assembly are necessary.

a. Attach the blue cartridge housing (large diameter threaded end) to the air sampler inlet.

b. Attach one of the gold filter housings to the blue cartridge housing.

c. Attach the gold coupler to the gold filter housing.

d. Attach one end of a tygon tube to the gold coupler and the other end to the outlet port of the Marinelli beaker.

e. Attach one end of a second tygon tube to the inlet port of the Marinelli beaker and the other end to the blue cartridge housing (small gold diameter threaded end).

f. Verify that the inlet and outlet stop-cocks on the Marinelli beaker are fully open (parallel to flow).

g. Insert a silver zeolite cartridge into the blue cartridge housing with the arrow on the cartridge pointing in the direction of air flow.

1. IF an air gap exists between the silver zeolite cartridge and the blue cartridge housing, THEN place a cartridge seal ring around the silver zeolite cartridge.

h. Attach the second gold filter housing to the blue cartridge housing.

i. With a pen, gently mark an "X" on one side of a particulate filter.

j. Insert the particulate filter into the second gold filter housing over the vents with the marked "X" side facing out, ensuring that the filter is placed into the filter housing side recessed to accept it.

REFERENCE USE

3LIC SERVICE CORP. N No. EPIP-ENV-04B Rev. X I**o * *N 2 Title Air Sampling and Analysis 1K~aii nee Nucle-rPwi ln

~Ž~ii ~~iz mpeheting"Procedure . Date AUG 20 2002 Pa e 3 of 15

k. Attach the gold filter retaining ring to the gold filter housing.

1. Verify that the cartridge and filter housings are sealed tightly so that no air will bypass it during sampling.

5.2 Collect an Air Sample Note Air samples are normally collected at locations on the plume centerline.Plume centerline is locatedat the point where the highest Gamma radiationlevels are observed while traversingthe plume.

5.2.1 Drive to the air sample location.

5.2.2 Measure the Gamma radiation levels (dose rates) using the ion chamber with the window closed, while en route to the sample location.

Note Do not collect an airsample at a location where submersion in the plume is not verified unless specifically instructedto take such action by the Environmental Monitoring Team Coordinator(EMTCd).

5.2.3 Verify submersion in the plume by determining the corrected Beta radiation level at the sample location.

a. Determine the Gamma level.

1. Hold the detector, with the Beta window closed, approximately 1 meter above the ground.

b. Determine the corrected Beta radiation level.

1. With the Beta window open, hold the survey detector approximately 1 meter above ground to determine the Beta/Gamma reading.

2. Subtract the reading taken in Step 5.2.3.a from the reading taken in Step 5.2.3.b.1 to obtain the uncorrected Beta reading.

(Uncorrected Beta reading = Beta/Gamma reading - Gamma reading)

3. Multiply the uncorrected Beta reading obtained in Step 5.2.3.b.2 by the Beta Correction Factor (BCF) listed on the instrument calibration sticker to obtain the correct Beta radiation level.

(Corrected Beta radiation level = uncorrected Beta reading x BCF)

c. IF Step 5.2.3.b.3 above results in a positive (greater than zero) corrected Beta radiation level, THEN submersion in the plume is verified.

REFERENCE USE

WISCONSIN PUBLIC SERVICE No. EPIP-ENV-04B Rev. X Title Air Sampling and Analysis eWadn~e~Niiclir Power Plant

, EPlan Date AUG 20 2002 Page 4 of 15 5.2.4 Record date and time, sample location (grid coordinates), sample type and Gamma radiation level (dose rate) on Form EPIPF-ENV-01-04, EMT Orders/Field Data or on Attachment A of EPIP-ENV-04D, EMT Standing Order SO-1.

5.2.5 Operate the air sampler to collect an air sample.

a. Verify the number listed on the instrument calibration sticker for particulate, iodine, and noble gas samples is dialed in on the air sampler thumbwheel switches.

b. Place the ON/OFF power switch in the ON position (toggle switch).

c. Start the air sampler by pressing the START button (black).

d. Record the sample collection start time on a radioactive sample tag.

Note The airsampler will automaticallyshut off when 300 liters of airsample is collected.

e. WHEN the air sampler shuts off, then fully close both the inlet and outlet stop-cocks to the Marinelli beaker (perpendicular to flow).

f. Record the sample collection end time on the radioactive sample tag.

g. Record the number from the air sampler LED readout on the radioactive sample tag.

h. Place the air sampling equipment in a poly bag and place in the EMT vehicle.

5.2.6 Go to a location with background Gamma radiation levels (outside the plume) prior to performing sample analysis or labeling and bagging samples (Steps 5.3 and 5.4).

5.2.7' IF directed by the EMTCd, THEN collect an alternate gross-air grab sample.

a. Don a clean pair of rubber gloves.

b. Obtain a water-filled, one liter bottle from the EMT kit.

c. Remove the cap and invert the bottle.

Note Maintain the bottle inverted until the cap is replaced.

d. Allow the water to empty onto the ground.

e. Recap the bottle tightly.

f. Place the bottle in clean poly bag.

g. Proceed to a location with background Gamma radiation levels.

REFERENCE USE

SCONSIN PUBLIC SERVICE CORP> J No. EPIP-ENV-04B Rev. X

_V Title Air Sampling and Analysis cv.Plan ImolemeitinfPFocedure Date AUG 20 2002 Page 5 of 15

h. Complete the radioactive sample tag with the following information:

"* Sample location (to the nearest one-half of a grid coordinate)

"* General area dose rate (mR/hr) at sample location

"* Type of sample (noble gas)

"* Date of sample

"* Time of sample

"* Initials of individual completing the sample tag

i. Place the radioactive sample tag into the poly bag with the one liter bottle.

j. Seal the bag.

k. Using the ion chamber with the window closed, perform an on-contact Gamma radiation dose rate survey of the bag.

1. Label the bag with the on-contact Gamma radiation dose rate.

5.3 Analyze an Air Sample Note Analyze the sample only when locatedin an areawith background Gamma radiationlevels (outside the plume). Don a clean pairof rubbergloves priorto handlingsamples.

5.3.1 Count a silver zeolite cartridge (1-131 sample).

a. Using EPIP-ENV-04A, prepare the ASP-i, with HP-260 probe, or equivalent, for a silver zeolite cartridge sample.

b. Determine the background CPM for the area where you are doing the analysis.

c. Place the HP-260 probe directly on the upstream side of the silver zeolite cartridge.

d. Determine the CPM reading for the sample.

e. Subtract the background reading from the sample reading to determine the net CPM for the sample. Record this value as the net CPM for the sample.

f. Using the graphs in Attachment A, determine the 1-131 concentration (jtCi/cc) for the sample. Record this value on Form EPIP-ENV-01-04, "EMT Orders/Field Data."

g. Label and bag the silver zeolite cartridge sample according to Step 5.4 of this procedure.

REFERENCE USE

SCONSINTitle NoSERVICE N. Air Sampling and Analysis Rev.

EPIP-ENV-04B X Kewaunee e Nuclear Power Pa mergency PlanImplekienting Prokeddr-e Date AUG 20 2002 Page 6 of 15 5.3.2 Count a particulate filter (particulate sample).

a. Using EPIP-ENV-04A, prepare the ASP-1 with HP-260 probe, or equivalent, for a particulate filter sample.

b. Determine the background CPM for the area where you are doing the analysis.

c. Place the HP-260 probe directly on the upstream side of the particulate filter.

d. Determine the CPM reading for the sample.

e. Subtract the background reading from the sample reading to determine the net CPM for the sample. Record this value as the net CPM for the sample.

f. Using the graphs in Attachment B, determine the particulate concentration (jiCi/cc) for the sample. Record this value on Form EPIP-ENV-01-04, "EMT Orders/Field Data."

g. Label and bag the particulate filter sample according to Step 5.4 of this procedure.

5.3.3 Analyze a Marinelli beaker noble gas sample.

a. Label and bag the Marinelli beaker gas sample according to Step 5.4 of this procedure.

5.4 Label and Bae Air Samples Note Label and bag the airsamples when at a location with backgroundGamma radiationlevels (outside the plume) and use a cleanpair ofgloves.

5.4.1 Place the particulate filter sample in a small poly bag.

5.4.2 Place the silver zeolite cartridge sample in the same poly bag with the particular filter.

REFERENCE USE

~~~SO~NPULIC SERVICE CORP.,,,ý.. No EPIP-ENV-04B Rev. X

. Title Air Sampling and Analysis

• Kzre Nuclear Poive Plan...~

Emr~erihcPlaii lehg cr AUG 20 2002 Page 7 of 15 5.4.3 Complete a radioactive sample tag with the following information:

"* Sample location (to the nearest one-half of a grid coordinate)

"* General area dose rate (mR/hr) at sample location

"* Type of sample(s) (iodine, particulate, and noble gas)

"* Date

"* Time sample started

"* Time sample ended

"* Flow rate of air sampler (from air sampler calibration sticker)

"* Initials of individual completing the sample tag 5.4.4 Place the radioactive sample tag in the poly bag with the particulate filter sample and silver zeolite cartridge sample.

5.4.5 Seal the poly bag.

.. 5.4.6 Place the bag in the deep well of the Marinelli beaker noble gas sample.

5.4.7 Place the bagged particulate filter sample, silver zeolite cartridge sample, and the Marinelli beaker noble gas sample into a larger clean poly bag.

5.4.8 Seal the outermost poly bag.

5.4.9 Using the ion chamber with the window closed, perform an on-contact Gamma radiation dose rate survey of the outermost bag.

5.4.10 Label the outermost bag with the on-contact Gamma radiation dose rate.

5.5 Verify that the following information is recorded for all air sample analysis results on Form EPIPF-ENV-01-04, "EMT Orders/Field Data:"

"* Sample date and time

"* Sample location (to the nearest one-half of a grid coordinate)

"* Sample type (iodine, particulate, noble gas, or dose rate)

"* Readings (general area dose rate in mR/hr or net sample analysis results in jpCi/cc) 5.6 Report all air-sample analysis results to the EMTCd via fax, telephone, or radio using Foim EPIPF-ENV-01-04, "EMT Orders/Field Data."

REFERENCE USE

-2WISCONSIN PUBLIC SERVICE CORP. No. EPIP-ENV-04B Rev. X Title Air Sampling and Analysis

-in Kew~uni6 Nici o rP t iEm"iure W Date AUG 20 2002 Page 8 of 15 5.7 Deliver air sample to KNPP Security Building or alternate location, if directed.

5.8 While you are en route, notify the RPO/RAF via radio or cellular telephone that air samples will be delivered and estimated time of air sample delivery.

6.0 Final Conditions 6.1 This procedure is complete when all orders (EMT Standing Order SO-i, Attachment A of EPIP-ENV-04D, or "EMT Orders/Field Data," Form EPIPF-ENV-01-04) requiring air sampling have been completed, suspended, or terminated, the results have been reported to the EMTCd, and all air samples have been delivered.

7.0 References 7.1 EPIP-ENV-04A, Portable Survey Instrument Use 7.2 EPIP-ENV-04D, Plume Tracking for Environmental Monitoring Teams 7.3 HP-06.043, Battery Powered Air Sampler, Model H-810-B2 8.0 Records 8.1 The following QA records and non-QA records are identified in this directive/procedure and are listed on the KNPP Records Retention Schedule. These records shall be maintained according to the KNPP Records Management Program.

8.1.1 QA Records

• EMT Orders/Field Data, Form EPIPF-ENV-01-04 a EMT Standing Order SO-1, Attachment A of EPIP-ENV-04D 8.1.2 Non-QA Records

• Radioactive Sample Tags REFERENCE USE

( ( C Attachment A EPIP-ENV-04B Rev. X Date: AUG 20 2002 Page 9 of 15 REFERENCE USE

Net CPM Vs 1-131 Concentration 8OO - .. / I O.OOOE-i0-O ____

Net CPM Attachment A EPIP-ENV-04B Rev. X Date: AUG 20 2002 Page 10 of 15 REFERENCE USE

( C Net CPM vs. 1-131 Concentrations 1.OOOE-04 0 6 O. .. 0 5 ...."-

0 U E-05 ________ 4~

2.OOOE 05 - " ° . .........

0.,OOOE+O0 - ________ "_______..*__,

Net CPM Attachment A EPIP-ENV-04B Rev. X Date: AUG 20 2002 Page 11 of 15 REFERENCE USE

(

mRlhr vs. 1-131 Concentrations 8.OOOE-05 0 6.OOOE-05 0

U 4.OOOE-05 2.O00E+O0-u5 O.'OO4 *f 1 cjý ss) rl, 0 e

mRlhr Attachment A EPIP-ENV-04B Rev. X Date: AUG 20 2002 Page 12 of 15 REFERENCE USE

( ( I Particulate uCi/cc 1.OOOE-07 8.OOOE-08 U

U 6.OOOE-08 0

4.OOOE-08 2.OOOE-08 O.O00E+00 0z 00 00 61 60 9Z, tS3 Net CPM Attachment B EPIP-ENV-04B Rev. X Date: AUG 20 2002 Page 13 of 15 REFERENCE USE

C Particulate uCi/cc 1.OOOE-06 8.000E-07 0

0 6.000E-07 0

4.000E-07 2.000E-07 O.O00E+00

@0 Net CPM Attachment B EPIP-ENV-04B Rev. X Date: AUG 20 2002 Page 14 of 15 REFERENCE USE

Particulate uCilcc 9 .000E -06 8.000 E-06 't'>';- - - - -

6..OOOE-06 _____

2.OOOE-06 ~__ _____~ ~ .~4q 0.000 E+00 NetCP Attchen BEPI-EN046e.X Dt:AG 020 ae1 f1 REFERECE US

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-ENV-04C Rev. X Title Ground Deposition Sampling and Analysis Kewaunee Nuclear Power Plant Emergency PlanImplementing Procedure Date AUG 20 2002 Page 1 of 5 Reviewed By Brad Gauger Approved By W. L. Yarosz Nuclear l Yes PORC e SRO Approval Of 0 Yes Safety Review Yes Temporary Related El No Required EI No IChanges Required Ef No 1.0 Purpose 1.1 This procedure provides instruction for performing ground deposition sampling and analysis during a declared plant emergency.

2.0 General Notes 2.1 The Environmental Monitoring Teams (EMTs) shall collect and analyze ground deposition samples in accordance with this procedure when directed.

2.2 Environmental Inc. (Midwest Lab.) (Previously Teledyne) (847-564-0700) shall be contacted for more detailed soil/vegetation/water/snow samples.

3.0 Precautions and Limitations S 3.1 Wear rubber gloves while collecting all samples listed below and change gloves frequently to prevent sample cross contamination. EMTs should verify adequate supply available and wear protective clothing when exiting the vehicle.

3.2 Do NOT use plastic to wrap the detector of any instrument used to measure Beta radiation.

Wrapping the detector in plastic during operation may shield Beta radiation. Instruments and their detectors may be placed in a plastic bag to prevent contamination while being transported.

3.3 EMTs shall not enter areas where projected or measured external radiation dose rates exceed 1 R/hr without specific direction from the Environmental Protection Director (EPD) or Radiological Protection Director (RPD).

3.4 Each instrument and its attached probe have been calibrated as a set. Do NOT interchange instruments and probes unless authorized by the Radiation Protection Group. Interchanging instruments and probes invalidates the instrument/probe calibration.

4.0 Initial Conditions 4.1 This procedure is to be used during a declared plant emergency by the EMTs when the teams are directed to collect and/or analyze ground deposition samples.

n:\nucdoc\procedures\draft\epip\eenv04c doc-Chnstine Simmons/Chnstine Simmons-Rick Adams REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-ENV-04C Rev. X Title Ground Deposition Sampling and Analysis Kewaunee Nuclear Power Plant Emergency Plan Implementing Procedure Date AUG 20 2002 Page 2 of 5 5.0 Procedure 5.1 Ground Deposition Screening Techniques Note Background readingson roads and most fields will rangefrom 10 to 150 CPM.

Therefore, 300 CPMwas selected as a reasonableaction level.

5.1.1 IF directed to a specific sample location, THEN travel to that sample location.

5.1.2 IF directed to determine the presence of ground deposition, THEN reference EPIP-ENV-04A, Step 5.2.7.

5.1.3 Measure the Gamma radiation level (dose rate) using the ion chamber closed window (probe extended outside of vehicle) while en route to the sample location.

5.1.4 Record the dose rate, time, and sample location on Form EPIPF-ENV-01-04, "EMT Orders/Field Data."

5.1.5 Select a representative surface from which a smear sample could be obtained (i.e., road pavement or other horizontal surface).

5.1.6 Perform a survey of the surface using an ASP-1 with the IHP-260 probe.

a. Place the FAST/SLOW instrument response switch to the FAST position.

b. Hold the detector within 1/2/2-inch from the surface to be surveyed.

c. Move the detector over the surface to be surveyed at a rate of approximately 2 inches per second.

d. Continuously monitor the meter reading and adjust the selector switch multiplication factor to the lowest range that does not produce an off-scale reading.

e. Multiply the meter reading by the selected multiplication factor to determine the contamination level in counts per minute (CPM).

f. IF the reading obtained in Step 5.1.6.e above is 300 CPM or greater, THEN perform Step 5.2 of this procedure.

g. IF the meter reading obtained in above Step 5.1.6.e is less than 300 CPM, THEN go to next sample location (if any) and repeat Step 5.1 above.

REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-ENV-04C Rev. X Title Ground Deposition Sampling and Analysis Kewaunee Nuclear Power Plant Emergency PlanImplementing Procedure Date AUG 20 2002 7 Page 3 of 5 5.2 Collect Ground Deposition Samples 5.2.1 Collect a smear sample from the same surface measured in Step 5.1.6.1, Ground Deposition Screening.

Note Put on a clean pairof rubbergloves prior to handlingsamples.

a. Obtain cloth smear disc (NU-CON).

b. Record the following information on the NU-CON cloth smear.

1. Date of sample

2. Time of sample

3. Location of sample

4. Technician (name of individual taking sample)

c. Wipe a 4-inch square or 18-inch "S"shaped area with the cloth smear disc.

d. Fold the smear holding paper in half so that the cloth smear disc is folded onto itself.

e. IF directed, THEN analyze smear per Step 5.3 below.

f, Label and bag smear per Step 5.4 below.

5.3 Analyze Ground Deposition Samples 5.3.1 IF directed, THEN determine the activity (in disintegrations per minute (DPM)) of the ground deposition cloth smear disc sample using an ASP-1 with the IHP-260 probe.

Note Count the sample only when located in an area with backgroundGamma radiationlevels (outside the plume). Don a cleanpairof rubbergloves prior to handlingsamples.

a. Determine the background CPM.

1. Hold the HP-260 probe in the air.

2. Record the results of Step 5.3.1.a.1 above as background (BKGD) CPM.

b. Determine the gross sample CPM.

1. Place the HP-260 probe directly on contact with the cloth smear disc sample (small raised bumps on the detector will prevent contamination of the detector).

2. Record the results of Step 5.3.1.b.1 above as gross sample CPM.

REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-ENV-04C Rev. X Title Ground Deposition Sampling and Analysis Kewaunee Nuclear Power Plant Emergency Plan Implementing Procedure Date AUG 20 2002 Page 4 of 5

c. Determine the net sample CPM.

1. Subtract the background CPM from Step 5.3.1.a.2 above from the cloth smear disc gross sample CPM from Step 5.3.1.b.2.

(Net sample CPM = smear sample CPM - background CPM)

d. Determine the net sample DPM.

1. Multiply the net CPM obtained in Step 5.3.1.c.1 above by the efficiency factor (EF) listed on the ASP-I instrument calibration sticker.

(Net sample DPM = net sample CPM x EF)

e. Record results from Step 5.3.1.d above, as DPM/100 cm 2 or DPM/smear if

< 100 cm 2 area was surveyed on Form EPIPF-ENV-01-04, "EMT Orders/Field Data."

5.3.2 Verify that the following information is recorded for all ground deposition samples on Form EPIPF-ENV-01-04, "EMT Orders/Field Data:"

• Sample date and time a Sample location (to the nearest one-half of a grid coordinate)

• Sample type (ground deposition or dose rate)

• Readings (sample results in DPM/100 cm 2 , DPM/smear, or mR/hr) 5.3.3 Report all ground deposition sample analysis results to the Environmental Monitoring Team Coordinator (EMTCd) via fax, telephone, or radio using Form EPIPF-ENV-01-04, "EMT Orders/Field Data."

5.4 Label and Bag Ground Deposition Samples 5.4.1 Place each smear sample in a clean poly bag.

5.4.2 Complete the radioactive sample tag.

Note All labels or tags shall contain thefollowing information:

"* Sample location (to the nearest one-half of a grid coordinate)

"* General area dose rate (mR/hr) at the sample location

"* Type of sample (ground deposition)

"* Date

"* Time sample taken

"* Initials of individual completing the sample tag REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-ENV-04C Rev. X

!Title Ground Deposition Sampling and Analysis Kewaunee Nuclear Power Plant Emergency Plan Implementing Procedure Date AUG 20 2002 Page 5 of 5 5.4.3 Place the radioactive sample tag in the bag along with the smear disc.

5.4.4 Seal the bag.

5.4.5 Using the ion chamber with window closed, perform an on-contact Gamma radiation dose rate survey of the bag.

5.4.6 Label the bag with the on-contact Gamma radiation dose rate.

5.4.7 Unless otherwise directed, deliver the ground deposition samples to the KNPP Security Building. Notify the RPO/RAF of the estimate delivery time.

5.4.8 While en route, notify the RPO/RAF via radio or cellular telephone that ground deposition samples will be delivered and estimated time of sample delivery.

5.5 IF final conditions as stated in Step 6.1 have not been met, THEN return to Step 5.1 of this procedure.

6.0 Final Conditions 6.1 This procedure is complete when all orders ("EMT Orders/Field Data," Form EPIPF-ENV-01-04) requiring ground deposition sampling have been completed, suspended, or terminated, the results have been reported to the EMTCd, and all samples have been delivered.

7.0 References 7.1 EPIP-ENV-04A, Portable Survey Instrument Use 7.2 EPIP-ENV-04D, Plume Tracking for Environmental Monitoring Teams 7.3 Teledyne Isotopes Letter of Agreement 8.0 Records 8.1 The following QA records and non-QA records are identified in this directive/procedure and are listed on the KNPP Records Retention Schedule. These records shall be maintained according to the KNPP Records Management Program.

8.1.1 QA Records 0 EMT Orders/Field Data, Form EPIPF-ENV-01-04 8.1.2 Non-OA Records

"-Radioactive Sample Tags REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-ENV-04D Rev. 0 Title Plume Tracking for Environmental Kewaunee Nuclear Power Plant Monitoring Teams Emergency PlanImplementing Procedure Date AUG 20 2002 Page I of 10 Reviewed By Rick Adams Approved By W. L. Yarosz Nuclear [] Yes PORC 1: Yes SRO Approval Of 11 Yes Safety Review Tem po rary Related 0 No Required 0 No Changes Required 2 No 1.0 Purpose 1.1 This procedure provides instruction for locating and tracking an airborne radiological release.

2.0 General Notes 2.1 None 3.0 Precautions and Limitations 3.1 Perform all actions for tracking an airborne radiological release (plume) while keeping personnel exposures As Low As Reasonably Achievable (ALARA).

3.2 Environmental Monitoring Teams (EMTs) shall NOT enter areas where projected or measured external radiation dose rates exceed 1 R/hr without specific direction from the Environmental Protection Director (EPD) or Radiological Protection Director (RPD).

3.3 IF the presence of radioactive iodine in the plume is suspected or detected, THEN refer to EPIP-AD-18, "Potassium Iodide Distribution," for guidance.

3.4 Each instrument and its attached probe have been calibrated as a set. Do NOT interchange instruments and probes unless authorized by the Radiation Group. Interchanging instruments and probes invalidates the instrument/probe calibration.

3.5 EMTs should verify adequate supply available and wear protective clothing when exiting the vehicle.

4.0 Initial Conditions 4.1 An emergency has been declared and a radiological release (plume) has occurred, is imminent, or in progress.

4.2 Off-site monitoring may be implemented to confirm that a radiological release (above normal limits) is not occurring.

4.3 EMT activation per EPIP-ENV-02, "Environmental Monitoring Team Activation," is complete.

n:Vnucdoc\procedures\draft\epip\eenvO4d.doc-Chrstine Simmons/Christine Simmons-Brad Gauger REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-ENV-04D IRev. 0 Title Plume Tracking for Environmental Kewaunee Nuclear Power Plant Monitoring Teams "EmergencyPlan Implementing Procedure Date AUG 20 2002 Page 2 of 10 5.0 Procedure 5.1 Actions for the EMTs 5.1.1 Obtain current annual dose (TEDE) from the Radiological Analysis Facility (RAF) or Emergency Operations Facility (EOF).

5.1.2 Contact the EMTCd, AND 5.1.2.1 Relay the annual dose information for each team member.

5.1.2.2 Obtain meteorological and plant conditions.

5.1.3 Complete Form EPIPF-ENV-01-03, "Meteorological and Plant Status Data."

5.1.4 IF changes or discrepancies in meteorological or plant conditions are observed, THEN report them to the EMTCd.

rojected or measured external radiationdose rates exceed I R/hr without specific direction Environmental from the EPD Monitoring Teamsor(EMTs)

RPD. shall NOT enter areas where Note The first team activatedshouldperform EMT Standing Order SO-i, the second team activatedshould perform EMT Standing OrderSO-2, and the third team activatedshouldperform EMT Standing OrderSO-3.

5.1.5 Implement EMT Standing Orders (SO) based on the team designation as follows:

5.1.5.1 Team A, implement SO-1 5.1.5.2 Team B, implement SO-2 5.1.5.3 Team C, implement SO-3 5.1.6 IF any conflicts occur with the performance of orders assigned, THEN immediately contact the EMTCd for resolution.

REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-ENV-04D Rev. 0 Title Plume Tracking for Environmental Kewaunee Nuclear Power Plant Monitoring Teams Emergency PlanImplementing Procedure Date AUG 20 2002 Page 3 of 10 5.1.7 Report field data results promptly to the EMTCd or the RPO/RAF.

a. Use the "EMT Field Data" section of Standing Orders to record Gamma and Beta radiation dose rates.

b. Use Form EPIPF-ENV-01-04, "EMT Orders/Field Data," for air sample and ground deposition sample analysis results.

5.1.8 WHEN an order is completed, suspended, or terminated, THEN request additional instructions from EMTCd or RPO/RAF.

5.1.9 Continue field monitoring activities as directed by the EMTCd until relieved or activities are terminated.

6.0 Final Conditions 6.1 This procedure is complete when all EMT orders (Form EPIPF-ENV-01-04, "EMT Orders/Field Data") have been completed or terminated.

7.0 References 7.1 EPIP-AD-18, Potassium Iodide Distribution 7.2 EPIP-ENV-04A, Portable Survey Instrument Use 7.3 EPIP-ENV-04B, Air Sampling and Analysis 7.4 EPIP-ENV-04C, Ground Deposition Sampling and Analysis 7.5 EPIP-ENV-02, Environmental Monitoring Team Activation REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-ENV-04D IRev. 0 Title Plume Tracking for Environmental Kewaunee Nuclear Power Plant Monitoring Teams Emergency Plan Implementing Procedure Date AUG 20 2002 Page 4 of 10 8.0 Records 8.1 The following QA records and non-QA records are identified in this directive/procedure and are listed on the KNPP Records Retention Schedule. These records shall be maintained according to the KNPP Records Management Program.

8.1.1 QA Records

"* Meteorological and Plant Status Data, Form EPIPF-ENV-01-03

"* EMT Orders/Field Data, Form EPIPF-ENV-01-04

"* EMT Standing Order SO-1, Attachment A

"* EMT Standing Order SO-2, Attachment B

"* EMT Standing Order SO-3, Attachment C

"* Emergency Planning Zone (EPZ) Grid Map

"* Form HPF-1 14, Map J-1, Physical Layout of Kewaunee Nuclear Power Plant 8.1.2 Non-QA Records None REFERENCE USE

EMT STANDING ORDER SO-1 Page 1 of 2 DATE/TIME:

TEAM (Circle One): A B C ORDER ID: EMT STANDING ORDER SO-1 INSTRUCTIONS: (1) Locate the plume centerline in the vicinity of the site boundary by performing Gamma radiation dose rate surveys according to EPIP-ENV-04A, "Portable Survey Instrument Use."

(2) During a radioactive release, read dosimeters every 15 minutes.

Report dosimeter readings every hour or every 100 mrem (whichever comes first) to the EMTCd.

(2) Collect an air sample on plume centerline according to EPIP-ENV-04B, "Air Sampling and Analysis."

(3) Deliver air sample to KNPP Security Building or alternate location, if directed. Notify RPO/RAF of estimated delivery time.

(4) When directed, determine the extent of ground deposition using EPIP-Env-04C, "Ground Deposition Sampling and Analysis."

DIRECTIONS FOR REPORTING FIELD DATA:

1. SAMPLE DATE/TIME - Enter date/time dose rate reading was taken, date/time air sample collection was completed, or date/time deposition sample was collected.

2. GRID COORDINATES - Specify sample location to the nearest one-half of a grid coordinate.

3. SAMPLE TYPE - Enter appropriate description.

Iodine (I)

Particulate (P)

Noble Gas (NG)

Dose Rate (DR)

Deposition (DP)

4. READING - Enter reading using correct units.

Dose Rate - mrem/hour Air Sample (Iodine, Particulate, or Noble Gas) - gCi/cc Deposition - dpm/100 cm 2 or dpm/smear if< 100 cm 2 is surveyed Attachment A EPIP-ENV-04D Rev. 0 Date: AUG 20 2002 Page 5 of 10 REFERENCE USE

EMT STANDING ORDER SO-1 Page 2 of 2 EMT FIELD DATA SAMPLE DATE/TIME GRID SAMPLE TYPE READING COORDINATES (mremlhr)

DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mremihr DR mremihr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/lhr DR mrem/hr DR mrem/hr Attachment A EPIP-ENV-04D Rev. 0 Date: AUG 20 2002 Page 6 of 10 REFERENCE USE

EMT STANDING ORDER SO-2 Page 1 of 2 DATE/TIME:

TEAM (Circle One): A B C ORDER ID: EMT STANDING ORDER SO-2 INSTRUCTIONS: (1) Locate and track the leading boundary (edge) of the plume by performing Gamma radiation dose rate surveys according to EPIP-ENV-04A, "Portable Survey Instrument Use."

(2) During a radioactive release, read dosimeters every 15 minutes.

(3) Report dosimeter readings every hour or every 100 mrem (whichever comes first) to the EMTCd.

(4) When directed, determine the extent of ground deposition using EPIP-ENV-04C, "Ground Deposition Sampling and Analysis."

DIRECTIONS FOR REPORTING FIELD DATA:

1. SAMPLE DATE/TIME - Enter date/time dose rate reading was taken, date/time air sample collection was completed, or date/time deposition sample was collected.

2. GRID COORDINATES - Specify sample location to the nearest one-half of a grid coordinate.

3. SAMPLE TYPE - Enter appropriate description.

Iodine (I)

Particulate (P)

Noble Gas (NG)

Dose Rate (DR)

Deposition (DP)

4. READING - Enter reading using correct units.

Dose Rate - mrem/hour Air Sample (Iodine, Particulate, or Noble Gas) - pLCi/cc Deposition - dpm/100 cm 2 or dpm/smear if< 100 cm 2 is surveyed Attachment B EPIP-ENV-04D Rev. 0 Date: AUG :20 2002 Page 7 of 10 REFERENCE USE

EMT STANDING ORDER SO-2 Page 2 of 2 EMT FIELD DATA SAMPLE DATE/TIME GRID SAMPLE TYPE READING COORDINATES (mrem/hr)

DR mrem/hr DR mrem/hr DR mren/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mrern/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mreni/hr DR mremlhr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr Attachment B EPIP-ENV-04D Rev. 0 Date: AUG 20 2002 Page 8 of 10 REFERENCE USE

EMT STANDING ORDER SO-3 Page 1 of 2 DATE/TIME:

TEAM (Circle One): A B C ORDER ID: EMT STANDING ORDER SO-3 INSTRUCTIONS: (1) Locate and track the lateral boundaries (edges) of the plume within 5 miles of KNPP by performing Gamma radiation dose rate surveys according to EPIP-ENV-04A, "Portable Survey Instrument Use."

(2) During a radioactive release, read dosimeters every 15 minutes.

Report dosimeter readings every hour or every 100 mrem (whichever comes first) to the EMTCd.

(3) WHEN the release is terminated, THEN locate and track the trailing edge of the plume.

(4) Report Gamma radiation dose rate readings to EMTCd or RPO/RAF every 15 minutes or more frequently, if directed.

(5) When directed, determine the extent of ground deposition using EPIP-Env-04C, "Ground Deposition Sampling and Analysis."

DIRECTIONS FOR REPORTING FIELD DATA:

1. SAMPLE DATE/TIME - Enter date/time dose rate reading was taken, date/time air sample collection was completed, or date/time deposition sample was collected.

2. GRID COORDINATES - Specify sample location to the nearest one-half of a grid coordinate.

3. SAMPLE TYPE - Enter appropriate description.

Iodine (I)

Particulate (P)

Noble Gas (NG)

Dose Rate (DR)

Deposition (DP)

4. READING - Enter reading using correct units.

Dose Rate - mrem/hour Air Sample (Iodine, Particulate, or Noble Gas) - pCi/cc Deposition - dpm/100 cm 2 or dpm/smear if< 100 cm 2 is surveyed Attachment C EPIP-ENV-04D Rev. 0 Date: AUG 20 2002 Page 9 of 10 REFERENCE USE

EMT STANDING ORDER SO-3 Page 2 of 2 EMT FIELD DATA SAMPLE DATE/TIME GRID SAMPLE TYPE READING COORDINATES (mrem/hr)

DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mren/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr DR mrem/hr Attachment C EPIP-ENV-04D Rev. 0 Date: AUG 20 2002 Page 10 of 10 REFERENCE USE

EMT ACTIVATION CHECKLIST DATE/TIME STARTED: I TEAM: A B C (Circle One)

ITEM ACTION INITIALS

1. Perform portable survey instrument preoperational checks using EPIP-ENV-04A.

a. Ion Chamber (Serial # ____

1) Physical Condition SAT / UNSAT (Circle One)

2) Calibration SAT / UNSAT

3) Battery SAT/UNSAT

4) Source Response: SAT / UNSAT

b. ASP-1 with HP-260 probe (Serial #

1) Physical Condition SAT / UNSAT (Circle One)

2) Calibration SAT / UNSAT

3) Battery SAT/UNSAT

4) Source Response SAT / UNSAT

2. Obtain battery powered air sampler (Model H-810-B2).

a. Air sampler serial number:

b. Verify air sampler accessories are all available:

- Tygon tubing

- Gold filter retaining ring

- Gold filter housing (2)

- Blue cartridge housings (2)

- Plastic cartridge seal rings (2)

3. Obtain Environmental Monitoring Team Kit.

NOTE: IF seal is not broken, THEN do not inventory kit. IF seal is broken, THEN inventory kit using most recent revision of Form HPF-115,Emergency Equipment Monthly Inventory.

4. Obtain cellular phone and FAX kit.

5. Obtain portable high-band radio and whip antenna.

6. Obtain personnel dosimetry for each team member:

a. High range SRPD (zeroed)

b. Low range SRPD (zeroed)

c. TLD

7. Don a reflective vest (each team member).

8. Establish communications with the Environmental Monitoring Team Coordinator (EMTCd) or the RPO/RAF.

"---"Form EPIPF-ENV-02-01 Rev. N Date: AUG 20 2002 Page 1 of 2

EMT ACTIVATION CHECKLIST ITEM ACTION INITIALS

9. Verify all required equipment is loaded into vehicle to be used by the EMT.

10. Activate the vehicle's amber light.

11. Obtain current annual TEDE for each team member from the RPO/RAF and record on Form EPIPF-ENV-01-02, EMT Status.

NOTE: When steps I through 11 above are completed, EMT activation is complete.

12. Report the following information to the EMTCd Using Form EPIPF-ENV-01-02, EMT Status:

a. Team designator (A, B, or C)

b. Team membership (names)

c. Current annual TEDE (mRem)

d. Date/time activated

13. Obtain meteorlogical and plant status from the EMTCd or the RPO/RAF using Form EPIPF-ENV-01-03, Meteorological and Plant Status Data.

14. Synchronize the EMT timepiece(s) with the time from the Honeywell computer. To obtain honeywell computer time, contact the EMTCd or Radiological Protection Director (RPD).

15. Initiate Standing Order SO-i, SO-2, or SO-3 according to EPIP-ENV-04D, Plume Tracking for Environmental Monitoring Teams, or other orders as directed.

DATE/TIME COMPLETED:

Maintain completed checklist in EMT Log.

"I--*--Form EPIPF-ENV-02-01 Rev. N Date: AUG 20 2002 Page 2 of 2