ML033500233

Radiological Emergency Response Plan Implementing Procedures

ML033500233
Person / Time
Site:	Kewaunee
Issue date:	12/08/2003
From:	Coutu T Nuclear Management Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NRC-03-115
Download: ML033500233 (35)

Text

Committed to Nuclear Excellence Kewaunee Nuclear Power Plant Operated by Nuclear Management Company, LLC NRC-03-115 10 CFR 50, App. E December 8, 2003 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 KEWAUNEE NUCLEAR POWER PLANT DOCKET 50-305 LICENSE No. DPR-43 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.

Thomas Coutu Site Vice President, Kewaunee Nuclear Power Plant Nuclear Management Company, LLC SLC Enclosure cc: Senior Resident Inspector, Kewaunee, w/enc.

Administrator Region III (2 copies), w/enc.

Public Service Commission of Wisconsin, w/o enc.

QA Vault, w/o enc.

N490 Highway 42

• Kewaunee, Wisconsin 54216-9510 Telephone: 920.388.2560

.- DOCUMENT TRANSMITTAL KEWAUNEE NUCLEAR POWER PLANT

. FROM: DIANE FENCL - KNPP TRANSMITFAL DATE 12-04-2003 EMERGENCY PLAN IMPLEMENTING PROCEDURES TRANSMITTAL FORM OUTSIDE AGENCY COPIES (1-20)

S.-Camion - NRC Document Control Desk (1)t - Krista Kappelman - PBNP - EP (10)*

S. Campion - NRC Region III (2, 3)* Kevin Joachim - Alliant Energy (11)*

S. Campion - NRC Resident Inspector (4) (receives Appx. A phone numbers)*

S. Campion - State of Wisconsin (5)* - Jill Stern - Nuclear Management Company (12)*

S. Campion - KNPP QA Vault (NRC Letter & Memo Only) (15)* Chuck Zoia - NRC Region III (13)*

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

J. Bennett (33) R. Johnson (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 - CRISS Office (51, 56)

M. Daron - Security Building (46) C. Grant - TSC (50, 95)

C. Grant - EOF (81) W. Galarneau - RAF (53)

C. Grant - OSF (52,96) IV. Galarneau - SBFIEMT (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 - RAFIRPO (106, 107)(Partial Distribution) C. Grant - TSC Response Blue Binder (Partial Distribution)

W. Galarneau - SBF/ENV (108, 109)(Partdal Distribution) C. Grant - TSC Response Red Binder (Partial Distribution)

W. Galarneau - SBF/EM Team (110, 111, 11A)(PartialDistribution) C rant -SC (;espon Bin r (atil Ditr W. Flint - Cold Chem/HR Sample Room (113) C. Grant - EOF Response Binder (Partial Distribution)

S. Zutz - SBFISEC (114) D. Krall - CR Response Binder artial Distribution)

E. Gilson - Security (121) K. Stangel - SCR Response Binder (Partial Distribuion)

S. Zutz - Security Building (120) D. Krall - CR Tag Desk (Partial Distribution)

Ops Admin. (126) K. Stangel - SCR Tag Desk (Partial Distribution)

C. Grant (Liaison Nlanuals)(EPIP.AD-02 and EOF-04 &APPX-A.06 Figures only)

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 COPY FOR INFORMATION ONLY.

I

KEWAUNEE NUCLEAR POWER PLANT REVISION OF EMERGENCY PLAN IMPLEMENTING PROCEDURES December 04, 2003 Please follow the directions listed below.

EPIP Index, dated 12-04-2003.

REMOVE INSERT PROCEDURE REV. PROCEDURE REV.

EPIP-AD-02 AH EPIP-AD-02 AI Return a signed and dated copy of tis s within 10 days of trasmittal date, to te-sender. If you have any questions or comments, please contact Jeie Morlino at 8719.

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.

'. , . a:,

2

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 12.04-2003 PROC. NO. TITLE REV. DATE EP-AD EPIP-AD-01 Personnel Response to the Plant Emergency Siren L 09-09-2003 EPIP-AD-02 Emergency Class Determination. . Al 12-04-2003 EPIP-AD-03 . KNPP Response to an Unusual Event AJ 09-09-2003 EPIP-AD-04 KNPP Response to Alert or Higher AO 09-09-2003 EP7-AD-5 Site Emergency Deleted 04-27-87 EPIP-AD-05 Emergency Response Organization Shift Relief E 02-18-2003 Guideline EP-AD-6 General Emergency .; Deleted 04-24-87 EPIP-AD-07 -Initial Emergency Notifidations AV 09-09-2003 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- I1 Emergency Radiation Controls 5 12-19-2002 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 P 09-12-2002 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 Determining Protective Action Recommendations T 09-19-2003 PAGE 1 OFli

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 12-04-2003 PROC. NO. TITLE REV. DATE EPIP-AD-20 KNPP Response to a Security Threat E 09-30-2003 EP-ENV EPIP-ENV-01 Environmental Monitoring Group Organization X 07-31-2003 and Responsibilities EPIP-ENV-02 Environmental Monitoring Team Activation Y 07-31-2003 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 Software X 09-19-2003 EP-ENV-3D Revision and Control of ISODOSE H 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 U 07-31-2003 EPIP-ENV-04B Air Sampling and Analysis Y 07-31-2003 EP-ENV-4C Environmental Monitoring Teams Deleted 04-13-90 EPIP-ENV-04C Ground Deposition Sampling and Analysis Y 07-31-2003 EPIP-ENV-04D Plume Tracking for Environmental Monitoring P 07-31-2003 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: 12-04-2003 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 EM Deleted 04-14-86 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 AB 07-31-2003 EPIP-EOF-03 EOF Staff Action for Unusual Event AE 07-31-2003 EPIP-EOF-04 EOF Staff Action for Alert or Higher AL 07-31-2003 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 AA 07-31-2003 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-1 1 Internal Communication and Documentation W 07-31-2003 Flow EPIP-EOF- 12 Media Center/Emergency Operation Facility/Joint R 06-19-2003 Public Information Center/Security

-PAGE 3 OF l

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 12-04-2003 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 W 11-04-2003 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-l Radiation Emergency Team Organization Deleted 04-16-96 EPIP-RET-02 In-Plant Radiation Emergency Team X 07-31-2003 EPIP-RET-02A Radiation Protection Office/Radiological Analysis V 11-04-2003 Facility (RPO/RAF) Activation EPIP-RET-02B Gaseous Effluent Release Path, Radioactivity, and T 09-19-2003 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 P 02-18-2003 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: 12-04-2003 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 CASP N 01-15-2002 EP-RET-3E Post Accident Operation of High Rad Sample Deleted 08-27-85 Room Inline Multiported Count Cave EPIP-RET-04 SBF Activation U 06-19-2003 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-II Operation Deleted 07-12-94 EP-RET-5 Plume Projection Deleted 09-26-84 EPIP-RET-05 Site Boundary Dose Rates During Controlled I 07-31-2003 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 Deleted 09-19-2003 EP-SEC EP-SEC-1 Security Organization Deleted 04-24-87 EPIP-SEC-02 Security Force Response to Emergencies Z 07-31-2003 EP-SEC-2A Manual Activation of Emergency Sirens Deleted 04-16-82 EPIP-SEC-03 Personnel Assembly and Accountability AG 05-20-2003 EPIP-SEC-04 Security Force Actions for Dosimetry Issue P 10-02-2001 PAGE 5 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 12-04-2003 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 S 01-28-2003 Responsibilities EPIP-TSC-02 Technical Support Center Activation U 01-20-2003 EPIP-TSC-03 Plant Status Procedure W 05-05-2003 EPIP-TSC-04 Emergency Modifications 0 04-29-2003 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 P 09-02-2003 Generators EPIP-TSC-08B* STMRLS Computer Program H 07-31-2003 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 K 05-05-2003 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 I Technical Support for IPEOPs L 07-31-2003 PAGE 6 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 12.04-2003 FTrI RE5S EPIP FIG I Figure EPIPFG DESCRIPTION REV. DATE EPIP-SEC-05 Technical Support EPIP-APPX-A-06 EP.r,-003 APPX-A-06-03 Center - KNP Floor Plan B 06-12-2001 Site Boundary Facility -

EPIP-APPX-A-06 EP.FIG0o5 APPX-A-06-02 KNP Floor Plan A 10-31-2000 Radiological Analysis EPIP-APPX-A-06 EP-F7G-00s APPX-A-06-01 Facility - KNP Floor Plan A 10-31-2000 EPIP-EOF-12 Division Office Building Form EPIPF-EOF-02-01 EP-FIG009 EOF-12-01 (2nd Floor) Floor Plan C 06-19-2003 State/County Work Area -

EPIP-APPX-A-06 E-MIG-012 APPX-A-06-08 WPSC D2-1 Floor Plan C 10-31-2000 NRC Work Area -

EPIP-APPX-A-06 EP-FI"G-13 APPX-A-06-09 WPSC D2-4 Floor Plan A 10-31-2000 Population Distribution by Geographical Sub-EPIP-AD-19 -IG014 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 D 04-29-2003 Location of JPIC and Media Briefing Center EPIP-EOF-12 EP-.rG-024 EOF-12-02 Map D 06-19-2003 KNP Site Map &

EPIP-SEC-05 EP.FG`-026 SEC-05-01 Evacuation Routes E 09-19-2003 Floor Plan - Media APPX-A-6 EP-FIG-034 Briefing Center Deleted 08-04-98 EPIP-EOF-12 EPIP-APPX-A-06 EP-rG-03s APPX-A-06-06 Media Briefing Center D 04-29-2003 Floor Plan - Corporate APPX-A-6 EP-FIG-037 - - - Response Center Deleted 08-04-98 APPX-A-6 EP-rG-038 - - - Floor Plan - JPIC Deleted 08-04-98 EPIP-OSF-02 EP-FIG039 OSF-02-01 High Priority Work B 07-31-2003 EPIP-OSF-02 EP-IG-039A OSF-02-02 Lower Priority Work B 07-31-2003 JPIC - Federal Work EPIP-APPX-A-06 EPIG043 APPX-A-06-10 Area - WPSC D2-9 C 04-29-2003 JPIC - State and County Work Area -

EPIP-APPX-A-06 EPFG.044 APPX-A-06-07 WPSC D2-8 D 04-29-2003 JPIC - Utility Work EPIP-APPX-A-06 EP.FIG045 APPX-A-06-05 Area - WPSC D2-7 D 04-29-2003 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: 12-04-2003 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 Figures AB 04-29-2003 PAGE 8 OF 11

• EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 12-04-2003 FORM EPIPF l TITLE REV. DATE APPENDIX B EP-AD AD-07-01 Event Notice - Nuclear Accident Reporting System Form V 05-05-2003 (NARS)

AD-07-02 State Call-Back - Question Guideline C 11-15-2001 AD-07-03 Fax Event Notice C 09-19-2003 AD-07-04 ERO Event Notification Deleted 07-31-2003 AD-i 1-01 Emergency Radiation Work Permit H 12-19-2002 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 Take A 02-27-2002 Potassium Iodide EP-ENV ENV-01-01 Environmental Dispatch Area Activation Checklist E 07-31-2003 ENV-01-02 EMT Status C 07-31-2003 ENV-01-03 Meteorological and Plant Status Data C 12-14-2001 ENV-01-04 EMT Orders/Field Data C 07-31-2003 ENV-02-01 EMT Activation Checklist 0 07-31-2003 EP-EOF EOF-02-01 EOF Activation Checklist V 09-19-2003 EOF-02-02 EOF Deactivation Checklist N 01-28-2003 EOF-04-01 SRCL Initial Action Checklist D 01-20-2003 EOF-04-02 Telephone Communications Log Sheet A 12-14-2001 EOF-08-03 Fax for Emergency Declaration or Status Updates H 01-20-2003 EOF-08-05 Plant Emergency Status Report A 11-27-2001 EOF-08-06 Radiological Status Report E 01-20-2003 EOF-1 1-02 Operating Status G 11-07-2002 PAGE 9 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 12-04-2003 FORM EPIPF TITLE REV. DATE EOF-I 1-03 Environmental Status Board G 11-07-2002 EOF-12-01 I.D. Badge Registration Form G 10-24-2000 EP-OSF OSF 2.2 Maintenance Work in Progress Deleted 07-08-98 OSF-03-01 Operational Support Facility Team Briefing l C 12-04-2001 EP-RET RET-02A-02 Emergency Sample Worksheet E 06-05-2001 RET-02B-01 Containment Stack Release (Grab Sample) E 09-19-2003 RET-02B-02 Auxiliary Building Stack Release (Grab Sample) E 09-19-2003 RET-02B-03 Auxiliary Building Stack Release (Sping Reading) E 09-19-2003 RET-02B-04 Containment Stack Release (Sping Reading) D 09-19-2003 RET-02B-05 Steam Release E 09-19-2003 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 I 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 H 11-04-2003 EP-TSC TSC-01.01 Plant Status Summary for SAM Implementation C 01-28-2003 TSC-01.02 Severe Accident Management Summary and Strategy B 02-06-2002 Recommendation _

PAGE 10 OF 11

. EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 12-04-2003 FORM EPIPF TITLE REV. DATE TSC-01-03 Severe Accident Management - Status C 07-31-2003 TSC-02-01 TSC and OSF Activation Checklist P 01-20-2003 TSC-02-02 TSC Ventilation Checklist J 09-19-2003 TSC-02-03 Emergency Response Data System (ERDS) Link Initiation H 01-20-2003 Checklist TSC-02-04 TSC Chart Recorder Operation Checklist E 01-20-2003 TSC-02-05 TSC and OSF De-Activation Checklist C 01-28-2003 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 Modification Request H 04-29-2003 TSC-04-02 Emergency Physical Change Safety Review Deleted 05-09-2002 TSC-04-03 Emergency Modification Index G 04-29-2003 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) H 09-02-2003 TSC-08A-03 Steam Release Data/Calculation Sheet (Open Valve) E 12-14-2001 TSC-08A-04 Steam Release Data/Calculation Sheet (STMRLS Program) D 12-14-2001 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 F 11-04-2003 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 TSC-09A-07 Core Damage Assessment Results A 05-05-2003 PAGE 11 OF 11

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-AD-02 Rev. AI

- . ~Title Emergency Class Determination Kewaunee Nuclear Power Plant Emergency Plan implementing Procedure Date DEC 42003 Page of 21 Reviewed By Rich Johnson Approved By Rich Johnson Nuclear PORC SRO Approval Of Safety E Yes Review 0 Yes Temporary El Yes Related 0 No Required 0 No Changes Required 0 No 1.0 Purpose 1.1 This procedure provides instruction for determining proper emergency classification listed in order to activate the appropriate level of response from the Kewaunee Nuclear Power Plant (KNPP) emergency response organization and off-site response organization.

2.0 General Notes 2.1 None 3.0 Precautions and Limitations 3.1 Plant monitors used to determine whether emergency classification levels are being exceeded should be checked for accuracy prior to declaring an emergency class (e.g., compare against redundant channels, determine if consistent with system status, or verification by sample analysis when required by Chart A(1).

3.2 This procedure is not written to facilitate de-escalation. Therefore, any decision to de-escalate must be based on a thorough review of procedures and plant conditions. If appropriate, it is preferable to terminate or enter recovery. However, there may be occasions where it is appropriate to de-escalate.

3.3 Once indication is available that an emergency action level has been met, classification must be made as soon as possible and must not exceed 15 minutes. A classification should not be made before an emergency action level has been met. Once a classification has been declared, notification must be initiated and in progress to the State and County agencies within 15 minutes of event classification using "Event Notice," Form EPIPF-AD-07-01.

During the initial 15-minute classification assessment, there may be rapidly changing conditions. Classification during this initial period should be based on currently available plant status.

4.0 Initial Conditions 4.1 This procedure applies during any plant evolution that may result in an emergency declaration.

J:\appdata\procpws\dratt\epip\eadO2.doc-Amy Kudick/Amy KudickJeanne Ferris REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-AD-02 I Rev. Al Title Emergency Class Determin ation Kewaunee Nuclear Power Plant Emergency Plan Implementing Procedure Date DEC 42003 Page 2 of 21 5.0 Procedure 5.1 Determine if a plant emergency exists during abnormal plant conditions by referring to Table 2-1, Emergency Action Level Charts.

5.2 IF a plant emergency exists, THEN perform the required actions of the appropriate emergency procedure listed below:

5.2.1 EPIP-AD-03, "KNPP Response to an Unusual Event" 5.2.2 EPIP-AD-04, "KNPP Response to Alert or Higher" 5.3 As plant conditions change, continue referring to the Emergency Action Level Charts.

5.4 Determine if the emergency should be reclassified.

5.5 IF the event is reclassified, THEN return to Step 5.2.

5.6 IF Final Conditions (Section 6.0) are not met, THEN return to Step 5.3.

i K-' 5.7 IF Final Conditions (Section 6.0) are met, THEN use of this procedure may be suspended.

6.0 Final Conditions 6.1 Plant Emergency has been Terninated 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 EPIP-AD-01, Personnel Response to the Plant Emergency Siren 7.3 EPIP-AD-03, KNPP Response to an Unusual Event 7.4 EPIP-AD-04, KNPP Response to Alert or Higher 7.5 COMTRAK 89-001, NRC Inspection Report 88-11, Improve Guidance for Fires Chart G 7.6 OEA 87-246, Report OE 2265, Improve Description of Unusual Aircraft Activity Chart P 7.7 NRC Letter 07-11-94, Branch Position on Acceptable Deviations to NUREG-0654 7.8 OEA 96-083, NRC IN 1997-045 Chart A(2)

REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-AD-02 I Rev. Al Title Emergency Class Determination Kewaunee Nuclear Power Plant Emergencv PlanImplementing Procedure IDate DEC 4 2003 I Page 3 of 21 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-OA Records None REFERENCE USE

EMERGENCY ACTION LEVEL CHARTS The following charts are separated into different abnormal operating conditions which may, depending upon K./ their severity, be classified as an Unusual Event, Alert, Site Emergency, or General Emergency.

l*4 it-2J--;.4. i,;'~.;.;- - ............... CHART PAGE normal Radiological Effluent A (1) 5 Gaseous Effluent Action Levels A (2) 6-8 Fuel Damage Indication B 9 Primary Leak to LOCA C 10 Primary to Secondary Leak D 11 Loss of Power E 12 Engineered Safety Feature Anomaly F 13 Loss of Indication G 14 DELETED H 14 Secondary Side Anomaly I 15 Miscellaneous Abnormal Plant Conditions 16 Fire and Fire Protection K 17 DELETED L 17 Earthquake M 18 High Winds or Tornado N 18 Flood, Low Water, or Seiche 0 19 External Events and Chemical Spills P 20 Security Contingency Q 21 Table 2-1 EPIP-AD-02 Rev. Al Date: DEC 4 2003 Page 4 of 21 REFERENCE USE

CHART A(1)

ABNORMAL RADIOLOGICAL EFFLUENT EMERGENCY KNPP INDICATION CLASSIFICATION CLASSIFICATION CRITERIA Effluent monitors detect levels corresponding to greater than I SEE CHART A(2) rem/hr whole body or 5 rem/hr GENERAL thyroid at the site boundary under EMERGENCY "actual meteorological" conditions.

Projected or measured dose rates to be provided by the Projected or measured in the environs Radiological Protection Director or Environmental dose rates greater than 1 rem/hr whole GENERAL Monitoring Teams. body or 5 rem/hr thyroid at the site EMERGENCY boundary.

Effluent monitors detect levels corresponding to greater than 50 SEE CHART A(2) mr/hr for 1/2 hour OR greater than 500 SITE EMERGENCY SEE CHART A(2) mr/hr for two minutes (or five times these levels to the thyroid) OR for "adverse meteorology."

At the site boundary, projected or measured dose rates greater than 50 Projected or measured dose rates to be provided by the mr/hr for 1/2 hours OR greater than Radiological Protection Director or Environmental 500 mr/hr for two minutes (or five SITE EMERGENCY Monitoring Teams. times these levels to the thyroid) or EPA Protective Action Guidelines are projected to be exceeded outside the site boundary.

SEE CHART A(2) Radiological effluents greater than 10 ALERT times ODCM instantaneous limits. __________

a. Containment R-2 OR R-7 2 1,000 times baseline established in the Control Room, OR

b. Charging Area R4 2 1,000 times baseline Radiation levels or airborne established in the Control Room, OR contamination which indicate a severe degradation in the control of

c. SFP Area R-5 1,000 times baseline established radioactive materials (e.g., radiation ALERT in the Control Room, OR levels suddenly increase by a factor of 1,000).

d. Plant area air sample indicates airborne contamination > 1,000 times the occupational DAC values.

(1) Gaseous Releases: See Chart A(2)

(2) Liquid Releases: Notification by the Offsite Dose Calculation Manual UNUSUAL EVENT Rad-Chem Group of violating ODCM 3.3.1 limits.

Table 2-1 EPIP-AD-02 Rev. Al Date: DEC 4 2003 Page 5 of 21 REFERENCE USE

CHART A(2)

GASEOUS EFFLUENT ACTION LEVELS

.1. AUX BUILDING VENT RELEASES - WITH .IrNIFWANT CORE nAMAGIE Instrument readings assuming a post accident gas release AND Containment High Range Radiation Monitors 42599 (R-40) and 42600 (R-4 1) reads 1000 R/hr for > 2 minutes within one-half hour of the accident.

NOTE: Use adverse meteorology conditions (ADV MET) only when, 10m and 60m wind speed < 5mph AND Delta-T > +2.4 degrees F or Sigma Theta is < 3.01 degrees. All other cases are average meteorology (AVG MET).

NOTE: R-13 and R-14 are expected to be off scale high during all events on this page.

ASV&SFP AUX BLDG SPING MONITORS AUX BLDG STACK MONITORS ECMLEASRS.

MID RANGE HIGH RANGE * -'

CPM (01-07) CPM (01-09) R-35 R-36 R/11R PPCS PT G9086G PPCS PT G9088G MR/IR TOTAL .

NUMBERAV NINGBE AVG MET ADV MET AVG MET ADV MET AVG AD ADV AVG MET ADV MET RUNNING ~~~~~MET MET I *. I.IE+4 6.5E+1 ** 7.9E+2 1.27E+2 7.9E-1 2 8.8E+5 5.5E+3 3.25E+l * ** 3.9E+2 6.35E+I 4.OE-1 GENERAL 3 5.9E+5 3.7E+3 2.16E+1 ** 2.6E+2 4.2E+I 2.6E-1 EMERG.

4 4.4E+5 2.7E+3 1.62E+1 2.OE+2 3.175E+I 2.OE-1 1 8.8E+4 5.5E+2 3.OE+0

• 6.3E+3 3.9E+1 6.3E+0

• 2 4.4E+4 2.7E+2 1.5E+0

• 3.1E+3 1.9E+1 3.1E+0

• SITE EMERG.

3 2.9E+4 1.8E+2 I.OE+0 2.1E+3 1.3E+1 2.1E+0 E 4 2.2E+4 1.3E+2 _ _ 1.5E+3 9.5E+0 1.5E+0 1 1.0E+3 6.2E+0 *

• 7.0E+1 * *

• 2 5.0E+2 3.IE+0 *

• 3.5E+I l ALERT 3 3.3E+2 2.OE+O *

• 2.3E+1 * *

• 4 2.5E+2 I.5E+0 *

• l.75E+1 * *

• I 1.0E+2 6.2E-1 *

• 7.0E+0 * *

• 2 5.0E+1 3.1E-1 *

• 3.5E+0 * *

• UNUSUAL 3 3.3E+1 2.OE-1 *

• 2.3E+0 * *

• EVENT 4 2.5E+1 1.5E-1 *

• 1.7E+0 * * *

• Offscale Low

• • Offscale High (Confirmation Only)

Table 2-1 EPIP-AD-02 Rev. Al Date: DEC 4 2003 Page 6 of 21 REFERENCE USE

CHART A(2)

GASEOUS EFFLUENT ACTION LEVELS continued

.2. AUX BUILDING VENT RELEASES WITHOUT CORE nA MA GE NOTE: Use adverse meteorology conditions (ADV MET) only when, 10m and 60m wind speed < 5mph AND Delta-T > +2.4 degrees F or Sigma Theta is 3.01 degrees. All other cases are average meteorology (AVG MET).

NOTE: R-13 and R-14 are expected to be off scale high during all events on this page.

SV & SFP AUX BLDG SPING MONITORS CLASS.

MID RANGE HIGH RANGE .. ,,

TOTAL CPM (01-07) CPM (01-09)

NUMBER PPCS PT G9086G PPCS PT G9088G t AVG MET ADV MET AVG MET ADV MET  ? in * :.

I ** 9.4E+4 1.6E+4 I.OE+2 2 ** 4.7E+4 8.OE+3 5.0E+I GENERAL 3 ** 3.IE+4 5.3E+3 3.3E+1 EMERG.

4 ** 2.3E+4 4.OE+3 2.5+1 I 7.5E+5 4.6E+3 8.OE+2 5.OE+O 2 3.7E+5 2.3E+3 4.OE+2 2.5E+0 SITE 3 2.5E+5 1.5+3 2.6E+2 1.6E+0 EMERG.

1.8E+5 I.1E+3 2.0E+2 1.2E+0 SV & SFP AUX BLDG SPING MONITORS FANS EMERG.

TOTAL LOW RANGE MID RANGE CLASS.

NUMBER Cilcc (01-05) CPM (01-07)

RUNNING PPCS PT G9084G PPCS PT 9086G 1I** 8.6E+3 2 ** 4.3E+3 ALERT 3 ** 2.8E+3 4 2.1E+3 I 6.3E-2 8.6E+2 2 3.1E-2 4.3E+2 UNUSUAL 3 2.1E-2 2.8E+2 EVENT 4 1.5E-2 2.IE+2

• • Offscale High (Confirmation Only)

Table 2-1 EPIP-AD-02 Rev. Al Date: DEC 4 2003 Page 7 of 21 REFERENCE USE

CHART A(2)

GASEOUS EFFLUENT ACTION LEVELS continued

3. STEAM LINE RELEASE UCA NT COREJDAMAGF Instrument readings assuming radioactive steam is releasing at a total of 1.4E+5 pounds per hour to the atmosphere AND Containment High Range Radiation Monitor 42599 (-40) or 42600 (R-41) reads 1000 R/hr for > 2 minutes within one-half hour of the accident.

.'gXt-t'"-

r,1_z.,¢!-,iSt i am Line Steam Line Monitors to Steam team Line ine 1onitors Mnitor Emergency Classification R-15 (cpm)

R-31 (mR/hr)

R-32 (R/hr)

R-33 (mRhr)

R-34 (R/hr) ":i-

-. e a

,",,,,,,t,,;.  ;)Vq,,,>,;;

• • 1.3E+3 1.3E+0 1.3E+03 1.3E+0 General Emergency

• • 6.0E+1 6.OE+1 _ Site Emergency

• • 1.5E-1 1.5E-1 - Alert 2.OE+05 Unusual Event

• • Offscale High (Confirmation Only)

SHIELD BUILDING STACK RELEASE Instrument readings assuming SBV System is operating in the recirculation mode.

Reactor Bldg. Discharge Vent SPING Emergency Classification PPCS PT G9077G PPCS PT G9079G (02-07) (02-09) ........... 4 M id Range (cpm) High Range (cpm) ' _________________________l_,_______________

1.3E+05 1.5E+2 General Emergency 6.7E+03 7.OE+O Site Emergency I.5E+1 Alert

.- - 0Unusual Event Table 2-1 EPIP-AD-02 Rev. Al Date: DEC 4 2003 Page 8 of 21 REFERENCE USE

i I CHART B FUEL DAMAGE INDICATION KNPP INDICATION EMERGENCY CASFCTO CLASSIFICATION CRITERIA CLASSIFICATION (1) CET > 1.200 Degrees for greater than 15 minutes, OR Plant conditions exist that make the (2) R40 or R41 > 1,000 R/hr, OR release of large amounts of GENERAL radioactivity in a short time period EMERGENCY (3) SACRG-1, Severe Accident Control Room Guideline possible.

Initial Response has been implemented.

(Major damage is more than one spent fuel element damaged.) Major damage to spent fuel in SITE containment or auxiliary building. EMERGENCY (1) Fuel Handling accident in Containment

a. AlarmonR-IlORR-12, AND

b. Dropped spent fuel assembly, OR

c. Report of a large object dropped in Rx core, OR (2) Fuel Handling Accident in Auxiliary Bldg.

a. Alarm on R-13 or R-14, AND

b. A large object dropped in spent fuel pool, OR

c. A dropped spent fuel assembly, OR

d. A loss of water level below spent fuel. l (1) R-9 indication is offscale high, AND Severe loss of fuel cladding ALERT (2) Laboratory analysis confirms RCS activity levels a. Very high coolant activity comparable to USAR Appendix D, Table D.4-1. sample

b. Failed fuel monitor indicates greater than 1% fuel failures within 30 minutes or 5% total fuel failures.

(1) Fuel Handling Accident in Containment Fuel damage accident with release ALERT

a. A confirming report, AND of radioactivity to containment or

b. Alarm on R- II R12, auxiliary building.

OR (2) Fuel Handling Accident in Auxiliary Bldg.

a. A confirming report, AND

b. Alarm on R-13 OR R-14. l (1I) With RCS Temperature > 5000 F,l (1)

Temerature With RCS > 500'FHigh reactor coolant activity UNUSUAL

a. > 1.0 plCilgram DOSE Equivalent I-131 for 48 sample. EVENT hours, OR

b. Exceeding 60 Ci/gram for Dose Equivalent 1-131, OR

c. > 91/E ACi/cc As determined by SP-37-065 (from T.S. 3.1.c)

(I) R-9 is greater than 5.0 R/hr, AND Failed fuel monitor indicates greater UNUSUAL than 0.1% equivalent fuel failures EVENT (2) Verified by 'CS chemistry sample anaysis. . within 30 minutes. EVENT Table 2-1 EPIP-AD-02 Rev. Al Date: DEC 4 2003 Page 9 of 21 REFERENCE USE

CHART C PRIMARY LEAK TO LOCA XJ yNOTE: This chart does not apply when leakage from the Reactor Coolant System is caused by a Steam Generator

.tube rupture.

KNPP INDICATION EMERGENCY CASFCTO CLASSIFICATION CRITERIA CLASSIFICATION (1) LOCA is verified per IPEOP E-1, "Loss of (1) Loss of coolant accident, GENERAL Reactor or Secondary Coolant," AND AND EMERGENCY (2) ECCS failure is indicated by: (2) Initial or subsequent failure of ECCS, AND

a. SI and RHR pumps not running, OR (3) Containment failure or

b. Verification of no flow to the reactor potential failure exists (loss vessel, OR of 2 of 3 fission product barriers with a potential loss

c. Core exit thermocouples indicate greater of 3rd barrier).

than 1,200'F, AND (3) Failure or potential failure of containment is indicated by:

a. Physical evidence of containment structure damage, OR

b. Containment Pressure is > 23 PSIG and loss of all containment fan coil units and both trains of ICS, OR

c. Containment hydrogen monitor indicates 2 10% hydrogen concentration, OR

d. Containment pressure exceeds 46 psig.

(1) SI System is activated and RCS leakage Reactor Coolant System leakage SIm exceeds charging system capacity as verified greater than make-up pump EMERGENCY by Control Room indications or IPEOPs. capacity.

(1) Charging flow verses letdown flow indicates Reactor Coolant System leak rate ERT an unisolable RCS leak > 50 gpm. greater than 50 GPM. AL (1) Initiation of reactor shutdown required by Exceeding Reactor Coolant Technical Specification, Section T.S. 3.1.d. System leak rate, Technical UNUSUAL Indicated leakage may be determined using Specifications, requiring reactor EVENT Reactor Coolant System mass balance shutdown.

calculations performed by SP-36-082.

Table 2-1 EPIP-AD-02 Rev. Al Date: DEC 4 2003 Page 10 of 21 REFERENCE USE

CHART D PRIMARY TO SECONDARY LEAK EMERGENCY KNPP INDICATION CLASSIFICATION CLASSIFICATION CRITERIA (1) Entry into IPEOP E-3, "Steam Generator Tube Rapid failure of steam generator SITE Rupture," is expected or has occurred, AND tubes with loss of off-site power. EMERGENCY (2) Primary-to-secondary flow > 800 GPM OR RCS pressure decreasing uncontrollably, AND (3) All three transformers Main Aux., Reserve Aux.,

and Tertiary Aux., are de-energized. I Rapid gross failure of one steam ALERT (1) Entry into IPEOP E-3, "Steam Generator Tube generator tube with loss of Rupture," is expected or has occurred, AND off-site power.

(2) Primary-to-secondary leak rate > 400 GPM, AND (3) All three transformers: Main Aux., Reserve Aux., and Tertiary Aux., are de-energized.

(1) Entry into IPEOP E-3, "Steam Generator Tube Rapid failure of multiple steam ALERT Rupture," is expected or has occurred, AND g (2) Primary-to-secondary leak rate greater than 800 GPM indicated by SI flow OR RWST level change. I UNUSUAL (1) Primary-to-secondary leakage > 150 gallons per Exceeding Primary-to-Secondary EVENT day for more than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (TS 3. .d.2). leak rate Technical Specification.

(Do not delay declaration if leakage suddenly increases above 150 gallons per day AND plant shutdown actions are initiated.)

Table 2-1 EPIP-AD-02 Rev. Al Date: DEC 4 2003 Page 11 of 21 REFERENCE USE

CHART E LOSS OF POWER EMERGENCY KNPP INDICATION CLASSIFICATION CLASSIFICATION CRITERIA (1) RCS is > 350'F, AND Failure of off-site and on-site GENERAL AC power, AND EMERGENCY (2) Buses 1 through 6 are de-energized including the Total loss of auxiliary D/G supplies to buses 5 and 6, AND feedwater makeup capability for greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. (Loss (3) Loss of the turbine driven AFW pump, AND of power plus loss of all AFW

- ~would lead to clad failure and (4) Conditions exist for greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. potential containment failure.)

(1) Buses through 6 are de-energized including the DIG supplies to buses 5 and 6 or longer than Loss of off-site power, ANEM SITE 15 minutes. (Does not apply when core is EMERGENCY unloaded or cavity is flooded with internals Loss of on-site AC power (for removed.) more than 15 minutes).

(1) Low voltage lockout OR de-energized condition on all safeguards DC distribution cabinets for Loss of all vital on-site DC SITE greater than 15 minutes. power (for more than 15 EMERGENCY

a. BRA 102 and BRB 102, OR -inutes).

b. BRA 104 and BRB 104, OR

c. BRA 102 and BRB 104, OR

d. BRB 102 and BRA 104 (Does not apply when core is unloaded or cavity is flooded with internals removed.)

(1) Low voltage lockout OR de-energized condition on all safeguards DCdisibution cabinets for Loss of all vital on-site DC ALERT less than 15 minutes. power (for less than 15

a. BRA 102 and BRB 102, ORminutes).

b. BRA 104 and BRB 104, OR

c. BRA 102 and BRB 104, OR

d. BRB 102 and BRA 104 (Does not aply when core is unloaded or cavity is flooded wit internals removed.)

(1) Buses 1 through 6 are de-energized, AND Loss of off-site power, AND ALERT (2) The D/G supplies to buses 5 and 6 do not respond as designed. AC power is restored to bus Loss of on-site AC power (for 5 or 6 within 1 minutes. (Does not apply when less than 15 minutes.)

core is unloaded or cavity is flooded with internals removed.) -

(1) With the Reactor Coolant System above cold shutdown condition: Loss of off-site power, OR UNUSUAL

a. All three transformers: Main Aux., Reserve Loss of on-site power Aux., and Tertiary are de-energized, OR capability.

b. Both D/Gs unavailable (unable to supply bus 5 or 6 by any means).

(1) Core is unloaded or reactor cavity is flooded with Loss of off-site power AND UNUSUAL internals removed, AND ffst owr N EVEo N TA (2) Buses I through 6 are de-energized including the Loss of on-site AC power (for D/G supplies to buses 5 and 6 or longer than more than 15 minutes).

15 minutes.

Table 2-1 EPIP-AD-02 Rev. Al Date: DEC 4 2003 Page 12 of 21 REFERENCE USE

CHART F ENGINEERED SAFETY FEATURE ANOMALY EMERGENCY KNPP INDICATION CLASSIFICATION CLASSIFICATION CRITERIA (1) RCS > 200'F with a loss of cooling capability Complete loss of any function SITE or inventory control: needed when RCS > 2000 F. EMERGENCY

a. Sustained loss of negative reactivity control, OR

b. Steam dump, S/G safeties, and power operating reliefs not operable (> 350'°F),

OR

c. Inability to feed S/Gs (No AFW or Main Feedwater/Condensate Flow), OR

d. Sustained loss of RCS inventory control, OR

e. Sustained loss of both trains of RHR, AND the inability to sustain either natural OR forced circulation with the steam generators (S 3500 F).

(A Site Emergency should be declared upon the initiation of bleed and feed per FR H.1, "Response to Loss of Secondary Heat Sink.") l (Apply this criteria when the RCS is < 200'F.) Complete loss of any function ALERT needed when RCS < 200'F.

(1) Loss of both trains of RHR (Does not apply when core is unloaded OR cavity is flooded with internals removed.)

(1) Failure of both Rx trip breakers to open upon Failure of the Reactor receipt of a valid signal. Applies even if Protection System to initiate IPEOP FR S. 1 is not entered. and complete a reactor trip ALERT which brings the reactor subcritical.

(1) Loss of ESF function, required support function Inability to reach required UNUSUAL or required Tech Spec instruments OR shutdown within Tech Spec EVENT Exceeding Tech Spec Safety Limits, limits AND (2) upon discovery, inability or failure to take required shutdown or mode change actions within the required time.

(Total loss of AFW system when required (FR-H. 1 implemented) should be declared a UE regardless of Tech Spec action compliance.) l Table 2-1 EPIP-AD-02 Rev. Al Date: DEC 4 2003 Page 13 of 21 REFERENCE USE

CHART G LOSS OF INDICATION EMERGENCY KNPP INDICATION CLASSIFICATION CLASSIFICATION CRITERIA (1) Total loss of Annunciator System computer Most or all alarms (annunciators) SITE alarms, and sequence of events recorder for lost and a plant transient initiated EMERGENCY greater than 1 minutes, AND or in progress.

(2) Uncontrolled plant transient in progress or initiated during the loss.

(1) Total loss of Annunciator System, computer Most or all alarms (annunciators) ALERT alarms, and sequence of events recorder. (Not lost.

applicable when plant is at or below cold shutdown.)

(I) Significant loss of ESF or Rx Protection Indications or alarms on process UNUSUAL instrumentation. An Unusual Event should or effluent parameters not EVENT NOT be declared for a non-emergency Tech functional in control room to an Spec backdown, when the affected parameter extent requiring plant shutdown remains monitorable. or other significant loss of assessment capability.

(Not applicable when plant is at or below cold shutdown.)

CHART H (DELETED)

Table 2-1 EPIP-AD-02 Rev. Al Date: DEC 4 2003 Page 14 of 21 REFERENCE USE

CHART I SECONDARY SIDE ANOMALY EMERGENCY KNPP INDICATION CLASSIFICATION CLASSIFICATION CRITERIA (1) Main steam line break that results in a SI Steam line break, AND SITE actuation, AND EMERGENCY Primary-to-secondary leak (2) a. R-15 or R-19 reads offscale high with > 50 GPM, AND confirmation by chemistry analysis, OR Indication of Fuel Damage.

b. Primary-to-secondary leakage > 50 gpm, AND (3) a. R-9 or CNTMT high range rad monitors (42599, 42600) indicate > 10 R/hr, OR

b. CNTMT hydrogen monitor indicates > 1%

hydrogen concentration.

(1) Main steam line break that results in a SI Steam line break with ALERT actuation, AND significant (greater than 10 GPM) primary-to-secondary

a. R-15 OR R-19 reads a factor of 1000 above leakage.

normal, OR (Applies even if events occur in

b. Primary-to-secondary leakage > 10 gpm. opposite steam generators.)

(1) Turbine trip and observation of penetration of Turbine rotating component UNUSUAL casing. failure causing rapid plant EVENT shutdown.

(1) The uncontrolled depressurization of the Rapid depressurization of the UNUSUAL secondary system that results in an SI actuation. secondary side. EVENT (Unusual Event should be declared even if transient was mitigated by closure of the Main Steam Isolation Valves.

Table 2-1 EPIP-AD-02 Rev. Al Date: DEC 4 2003 Page 15 of 21 REFERENCE USE

CHARTJ MISCELLANEOUS ABNORMAL PLANT CONDITIONS KNPP INDICATION EMERGENCY CLASSIFICATION CRITERIA CASFCTO CLASSIFICATION (1) Containment boundary failure or potential Other plant conditions that make a GENERAL failure: release of large amounts of EMERGENCY radioactivity in a short time period

a. Containment pressure > 46 psig, OR possible; e.g., any core melt situation.

b. Loss of all containment fan coil units and both trains of ICS, OR Examples:

- Failure of main FW and AFW

c. Containment hydrogen monitor systems for greater than 2 10% hydrogen concentration, 30 minutes without Safety Injection and Residual Heat AND Removal flow. Plus a containment failure is (2) Loss of core cooling capability: imnent.

a. Loss of SI and RHR flow, - Transient requiring the AND operation systems withof shutdown a failure of these (3) Failure of shutdown system when required shutdown systems. In Failure osytaddition, failure of SI and

a. Entry into IPEOP FR-S.1, "Response to RHR and containment failure Nuclear Power Generation/ATWS," OR is imminent.

b. Loss of AFW for greater than 30 minutes with loss of main FW and condensate.

(1) Evacuation of Control Room (E-0-06 event). Evacuation of control room and SITE control of shutdown systems EMERGENCY required from local stations.

(1) Conditions that warrant increased awareness on Other plant conditions that warrant UNUSUAL rt of the plant staff will be evaluated by the increased awareness on the part of EVENT Plant Manager or his designate. This is to plant staff or state and/or local determine if conditions are applicable for authorities.

activating the E.P.

Example: Loss of AFW system when required, validated upon implementation of FR H. 1 "Response to Loss of Secondary Heat Sink."

Table 2-1 EPIP-AD-02 Rev. Al Date: DEC 4 2003 Page 16 of 21 REFERENCE USE

CHART K FIRE AND FIRE PROTECTION KNPP INDICATION EMERGENCY CLASSIFICATION CRITERIA CASFCTO CLASSIFICATION (1) A fire within the Auxiliary Building, A fire compromising the functions SITE Technical Support Center, safeguards alley, of safety systems. EMERGENCY D/G rooms, Battery Rooms, or screenhouse that defeats redundant safety trains of ESF equipment causing the required ESF system to be inoperable.

(1) A fire within the Auxiliary Building, A fire potentially affecting safety ALERT Technical Support Center, safeguards alley, systems.

DIG rooms, Battery Rooms, or screenhouse that lasts more than 10 minutes OR causes a single train of required ESF equipment to be inoperable.

(1) Any fire within the protected area lasting A fire within the plant lasting UNUSUAL more than 10 minutes. more than 10 minutes. EVENT CHART L (DELETED)

Table 2-1 EPIP-AD-02 Rev. Al Date: DEC 4 2003 Page 17 of 21 REFERENCE USE

k.

CHART M EARTHQUAKE EMERGENCY KNPP INDICATION CLASSIFICATION CLASSIFICATION CRITERIA (1) Activation of seismic recorder with TRIGGER, An earthquake greater than SITE OBE, and DBE lights lit in relay room on Design Basis Earthquake (DBE). EMERGENCY RR 159, AND~

(2) Verification of a seismic event by physical experience or from U. of W. - Milwaukee Seismic Center.

(1) Activation of seismic recorder with TRIGGER, An earthquake greater than ALERT and OBE lights lit in relay room on RR159, Operational Basis Earthquake AND e aEE). a (2) Verification of a seismic event by physical experience or from U. of W. - Milwaukee Seismic Center.

(1) Activation of seismic recorder with TRIGGER An earthquake felt inplant or UNUSUAL light lit in relay room on RR159, OR detected on station seismic EVENT instrumentation.

(2) An earthquake felt in the Plant*.

(*Should be confirmed by evidence of physical damage or verification from University of Wisconsin Seismic Center.)

NOTE: 1.) Telephone numbers for U of W - Milwaukee Seismic Center are in the KPB Emergency Telephone Directory, ETD 02.

2.) The Point Beach Seismic Monitor may be used if the KNPP Monitor is out of service.

CHART N HIGH WINDS OR TORNADO EMERGENCY KNPP INDICATION CLASSIFICATION CLASSIFICATION CRITERIA (1) Winds in excess of 100 mph for greater than Sustained winds in excess of SITE 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, AND design levels with plant not in EMERGENCY cold-shutdown.

(2) Plant above cold shutdown condition. col___hutdown.

(1) A tornado which strikes the facility, AND Any tornado striking facility. ALERT (2) Causes damage to render a single train of requiredESFeguipment to be inoperable. _

(1) A tornado observed on-site causing significant Any tornado on-site. UNUSUAL damage to the facility. __EVENT Table 2-1 EPIP-AD-02 Rev. Al Date: DEC 4 2003 Page 18 of 21 REFERENCE USE

CHART 0 FLOOD, LOW WATER, OR SEICHE Y

EMERGENCY CLASSIFICATION KNPP INDICATION . CRITERIA CLASSIFICATION FOREBAY LEVEL Flood, low water, or Indicated for > 15 minutes seiche near design ALERT CORRESPOND levels.

0 PUMPS I PUMP 2 PUMPS TOLAE LEVEL NOTE 3 NOTE 94%* 2 588 ft.

< 50%

• NOTE 5 NOTE 5 < 568.5 ft.

OR Deep water Wave 2 22.5 ft.

FOREBAY LEVEL 50-year flood, low Indicated for > 15 minutes water level or seiche UNUSUAL CORRESPOND EVENT 0 PUMPS 1 PUMP 2 PUMPS TOLAE LEVEL NOTE 2 298%* 288%

• 2 586 ft.

<53.1%* <46.9%* NOTE 5 < 569.5 ft.

_______ N OTE 4 _ _ _ _ _ _ _ _

OR Deep water wave 18 ft. (as confirmed by the U.S. Coast Guard, Two Rivers)

NOTE 1: Above the bottom of bar No. I painted on the south wall of the forebay.

NOTE 2: Above the bottom of bar No. 2 painted on the south wall of the forebay.

NOTE 3: Above the bottom of bar No. 3 painted on the south wall of the forebay.

NOTE 4: Applies to an uncontrollable decrease (cannot be restored by operator action. If the water box inlet valves are throttled, use other means to determine lake level per E-CW-04, "Loss of Circulating Water.")

NOTE 5: The corresponding forebay level for the associated lake level is below the circulating water pump trip setpoint of 42%. Therefore, this criterion will not be reached.

• Computer point for forebay level is L09075A and should be used because of its greater accuracy.

Plant elevations and lake elevations are referenced to International Great Lakes Datum (IGLD), 1955 (IGLD 1955 = IGLD 1985 - 0.7 FEET)

Table 2-1 EPIP-AD-02 Rev. Al Date: DEC 4 2003 Page 19 of 21 REFERENCE USE

CHART P EXTERNAL EVENTS AND CHEMICAL SPILLS EMERGENCY KNPP INDICATION CLASSIFICATION CLASSIFICATION CRITERIA cassAircraft crash affectingvital SITE (1) An aircraft crash into plant buildings which cau structures by impact OR fire. EMERGENCY a complete loss of an SF function.

(1) A missile strikes plant buildings, OR Severe damage to safe EMERGENCY missiles or exp osion.

(2) An explosion occurs within a plant building, which causes a complete loss of an ESF function.

Uncontrolled release of toxic SITE (1) Release of flammable or toxic gas, which causes or flammable gas is confirmed EMERGENCY or is likely to cause evacuation of stations within vital area.

necessary to control shutdown systems, AND (2) Portable monitors indicate toxic or explosive concentrations of the gas at life threatening levels in those vital areas.

.~ ~ ~Arrf crs.nfciiy LR (I) An aircraft crashes into plant buildings AND Aircraft crash on facility. ALERT causes a single train of required ESF equipment to be inoperable.

. . .. . ~~~~~~~Missile impact from whatever ALERT (1) A missile strikes the facility AND causes a sinle source on facility.

train of required ESF equipment to be inoperabl e.

flammableofgasat (1) Release of toxic.1)or Release toxicor gas at lifeUncontrolled life or flamnmable release of toxic gas is confirmed ALERT threatening levels enters the protected area AND within the protected area.

impacts sale operation of the plant. withintheprotectedarea.

Known damage to explosionplant ALERT (1) Self-explanatory. facility affecting operation. l Aircraft crash on-site or UNUSUAL (1) An aircraft crash within the site boundary, OR unusual aircraft activity over EVENT facility.

(2) Unusual aircraft activity such as erratic flying, dropged unidentified object, or other hostile acts, which threaten the plant or plant personnel. (Any other persistent aircraft activity for which identification attempts through the FAA or other agencies have been unsuccessful.)

. Release or flammable release oftxicrflmmabegaoniteUncontrolled of toxic UNUSUAL EVENT (1) Release of toxic or flammable gas on site, ANŽ!D gas is confirmed on site.

(2) Portable monitors indicate toxic or explosive concentrations at life threatening levels of the gas near the spill area.

Table 2-1 EPIP-AD-02 Rev. Al Date: DEC 4 2003 Page 20 of 21 REFERENCE USE

i ; . 1 CHART 0 SECURITY CONTINGENCY EMERGENCY KNPP INDICATION CLASSIFICATION CLASSIFICATION CRITERIA (1) Physical attack on the plant that has resulted in Loss of physical control of the GENERAL unauthorized personnel occupying the control plant. EMERGENCY room or any other vital areas as described in the Security Plan.

(1) Physical attack on the plant involving Imminent loss of physical SITE imminent occupancy oT the control room, control of the plant. EMERGENCY auxiliary shutdown panels, or other vital areas as defined by the Security Plan.

(1) Security safeguards contingency event that Ongoing security compromise. ALERT results in a hostile force entering the protected area of the plant, but not gaining control over shutdown capability orof any vital areas as defined in the Security Plan, OR (2) Security safeguards contingency event that results in a site specific HIlevel CREDIBLE threat as defined in the Security Plan.

(1) Security safeguards contingency event that Security threat or attempted UNUSUAL results in a site specific LO level CREDIBLE entry or attempted sabotage. EVENT threat as defined in the Security Plan, OR (2) Security safeguards contingency event that results in a Bomb threat accompanied by interception of bomb materials, OR (3) Security safeguards contingency event that results in an attempted entry into the protected area of the plant by a hostile force, OR (4) Security safeguards contingency event that results in undetonated bomb found within the protected area.

NOTE: Security staff will NOT act as notifier during security events. Utilize Control Room staff for notifications.

Table 2-1 EPIP-AD-02 Rev. Al Date: DEC 4 2003 Page 21 of 21 REFERENCE USE