ML031350621

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Radiological Emergency Response Plan Implementing Procedures
ML031350621
Person / Time
Site: Kewaunee Dominion icon.png
Issue date: 05/09/2003
From: Coutu T
Nuclear Management Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NRC-03-051
Download: ML031350621 (54)
v • d • e


Text

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NMC Committed to Nuclear Excellen Kewaunee Nuclear Power Plant Operated by Nuclear Management Company, LLC NRC-03-051 10 CFR 50, App. E May 9, 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 attachrent are hereby submitted to the Regional Administrator, U. S. Nuclear Regulatory Commission, Region ll, Lisle, Illinois. As required, one copy of this letter and attachment is also submitted to the Kewaunee Nuclear Power Plant NRC Senior Resident Inspector.

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Thomas Coutu Site Vice-President, Kewaunee Plant 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, w/o attach.

N490 Highway 42

  • Kewaunee, Wisconsin 54216-9510 Telephone: 920.388.2560

DOCUMENT TRANSMITTAL KEWAUNEE NUCLEAR POWER PLANT FROM: DIANE FENCL - KNPP TRANSMITTAL DATE 05-05-2003

.- \

EMERGENCY PLAN IMPLEMENTING PROCEDURES TRANSMITTAL FORAI OUTSIDE AGENCY COPIES (1-20) tSK-Cion - RCDocument Control j Krista Kappelman - PBNP - EP (10)*

S. Campion - NRC Region III (2,3)* Craig Weiss - 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 'ault (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) W. Bartelme (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)

I. Daron - Security Building (46) C. Grant - TSC (50)

C. Grant - EOF (81) NV. Galarneau - RAF (53) 2 C. Grant - OSF (52) - U. 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)

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

WV. Galarneau - RAFIRPO (106, 1 07 )(Partial Distribution) Ops Admin. (126)

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

WV. Galarneau - SBF/EM Team (110,111, 111A)(Partia Distribution) C. Grant - EOF Response Binder (Partial Distribution)

W. Flint - Cold Chem/HR Sample Room (113) D. Krall - CR Response Binder (Partial Distribution)

S. Zutz - SBF/SEC (114) K. Stangel - SCR Response Binder (Partial Distribution)

M. Fencl - Security (121) D. Krall - CR Tag Desk (Partial Distribution)

S. Zutz - Security Building (120) K. Stangel - SCR Tag Desk (Partial Distribution)

Originals to KNPP QA Vault Please follow the directions when updating your EPIP Manual. WVATCH 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. IT IS A COPY FOR INFORMATION ONLY.

I

KEWAUNEE NUCLEAR POWER PLANT REVISION OF EMERGENCY PLAN IMPLEMENTING PROCEDURES May 05, 2003 Please follow the directions listed below.

EPIP Index, dated 05-05-2003.

REMOVE INSERT PROCEDURE REV. PROCEDURE REV.

EPIP-AD-02 AF EPIP-AD-02 AG EPIP-TSC-03 V EPIP-TSC-03 W EPIP-TSC-09A J EPIP-TSC-09A K Form EPIPF-AD-07-01 U Form EPIPF-AD-07-01 V Form EPIPF-TSC-09A-07 A Return a signed and dated copy of this transnittal letter, within 10 days of transmittal date, to the sender. -If you have any questions orcornments,please contact Jerie Morlino at 755-6557.

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: 05-05-2003 PROC. NO. TITLE REV. DATE EP-AD EPIP-AD-01 Personnel Response to the Plant Emergency Siren K 11-26-2002 EPIP-AD-02 Emergency Class Determination AG 05-05-2003 EPIP-AD-03 KNPP Response to an Unusual Event AH 03-18-2003 EPIP-AD-04 KNPP Response to Alert or Higher AM 03-18-2003 EP-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 N6tifications AT 03-18-2003 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-1 1 Emergency Radiation Controls S 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 Comnunications Deleted 03-05-84 EPIP-AD-1 8 Potassium Iodide Distribution P 02-27-2002 EPIP-AD-19 Protective Action Guidelines 5 01-20-2003 PAGE 1 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 05-05-2003 PROC. NO. TITLE REV. DATE EPIP-AD-20 KNPP Response to a Security Threat D 01-20-2003 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-EN V-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: 05-05-2003 PROC. NO. TITLE REVr. 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 AA 08-06-2002 EPIP-EOF-03 EOF Staff Action for Unusual Event AD 01-20-2003 EPIP-EOF-04 EOF Staff Action for Alert or Higher AK 01-20-2003 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 Z 01-28-2003 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-11 Internal Communication and Documentation V 11-07-2002 Flow EPIP-EOF-12 Media Center/Emergency Operation Facility/Joint Q 06-20-2002 Public Information Center Security PAGE 3 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 05-05-2003 PROC.3!10. TITLE 1 REV. J_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 V 11-26-2002 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 04-29-2003 EPIP-RET-02A Radiation Protection Office/Radiological Analysis U 11-07-2002 Facility (RPO/RAF) Activation EPIP-RET-02B Gaseous Effluent Release Path, Radioactivity, and S 08-06-2002 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: 05-05-2003 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 T 10-17-2002 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-RET4C 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 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 Conmunications EPIP-RET-08 Contamination Control of the Aurora Medical Deleted 05-23-2002 Center EPIP-RET-09 Post-Accident Population Dose M 04-29-2003 EP-SEC EP-SEC-1 Security Organization Deleted 04-24-87 EPIP-SEC-02 Security Force Response to Emergencies Y 11-14-2002 EP-SEC-2A Manual Activation of Emergency Sirens Deleted 04-16-82 EPIP-SEC-03 Personnel Assembly and Accountability AF 11-26-2002 EPIP-SEC-04 Security Force Actions for Dosimetry Issue P 10-02-2001 PAGE 5 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 05-05-2003 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 0 11-26-2002 Generators EPIP-TSC-08B* STMRLS Computer Program G 06-20-2002 EP-TSC-8C* See EP-TSC-813 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

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

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 05-05-2003 FICUTREq 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-FIG-005 APPX-A-06-02 KNP Floor Plan A 10-31-2000 Radiological Analysis EPIP-APPX-A-06 EP-FIG-008 APPX-A-06-01 Facility - KNP Floor Plan A 10-31-2000 EPIP-EOF-12 Division Office Building Form EPIPF-EOF-02-01 EP-FIG-009 EOF-12-01 (2nd Floor) Floor Plan B 10-24-2000 State/County Work Area -

EPIP-APPX-A-06 EP-FIG-012 APPX-A-06-08 WPSC D2-1 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-FIG-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 D 04-29-2003 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-FIG034 - -- Briefing Center Deleted 08-04-98 EPIP-EOF-12 EPIP-APPX-A-06 EP-FIG-035 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-FIG-038 --- Floor Plan - JPIC Deleted 08-04-98 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 C 04-29-2003 JPIC - State and County Work Area -

EPIP-APPX-A-06 U-FIG-04 APPX-A-06-07 WPSC D2-8 D 04-29-2003 JPIC - Utility Work EPIP-APPX-A-06 EP-HG-045 APPX-A-06-05 Area - WPSC D2-7 D 04-29-2003 Aurora Medical Center RET-08 EP-F]G-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: 05-05-2003 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: 05-05-2003 FORI EPIPF 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 B 03-06-2003 AD-07-04 ERO Event Notification B 03-06-2003 AD-11-01 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 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 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: 05-05-2003 FORI EPIPF TITLE REV. DATE EOF-1 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 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 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: 05-05-2003 FORM EPIPF TITLE REV. DATE TSC-01.03 Severe Accident Management - Status B 02-06-2002 TSC-02-01 TSC and OSF Activation Checklist P 01-20-2003 TSC-02-02 TSC Ventilation Checklist I 01-20-2003 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 OSFDe-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) 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 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 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 TSC-09A-07 Core Damage Assessment Results A 05-05-2003 PAGE 11 OF 11

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-AD-02 Rev. AG Title Emergency Class Determination Kewaunee Nuclear Power Plant Eimergency Pla Iplementing Procedure Date MAY 5 2003 Page 1 of 21 Reviewed By Dave Mielke Approved By Jerrie Morlino Nuclear Yes lP C El Yes SRO Approval Of El Yes Safety OY Review 0 Yes Temporary 0 Ye Related 0 No Required 0 No Changes Required l3 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 exceeded, classification must be made as soon as possible and must not exceed 15 minutes. 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," Forn 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\draft\epip\eadO2.doc-Amy KudicktAmy Kudick-jeanne Ferris REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-AD-02 Rev. AG Title Emergency Class Determination Kewaunee Nuclear Power Plant

[ Emergency Plan Implementing Procedure Date MAY 5 2003 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.

<- 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 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 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 Rev. AG Title Emergency Class Determination Kewaunee Nuclear Power Plant Emergency Plan Implementing Procedure Date MAY 5 2003 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 OA Records None 8.1.2 Non-QA Records None REFERENCE USE

EMERGENCY ACTION LEVEL CHARTS The following charts are separated into different abnormal operating conditions which may, depending upon

'- their severity, be classified as an Unusual Event, Alert, Site Emergency, or General Emergency.

CHART PAGE Abnormal Radiological Effluent A () 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 J 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. AG Date: MAY 5 2003 Page 4 of 21 REFERENCE USE

CHART A(1)

ABNORMAL RADIOLOGICAL EFFLUENT KNPP INDICATION EMERGENCY CLASSIFICATION CLASSIFICATION CRITERIA Effluent monitors detect levels corresponding to greater than 1 rem/hr GENERAL SEE CHART A(2) whole body or 5 rem/hr thyroid at the EMERGENCY site boundary under "actual meteorological" conditions.

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

Effluent monitors detect levels corresponding to greater than 50 mr/hr SEE CHART A(2) for 1/2 hour OR greater than 500 mr/hr SITE EMERGENCY 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 mr/hr for 1/2 hours OR greater than 500 by the Radiological Protection Director or mr/hr for two minutes (or five times SITE EMERGENCY Environmental Monitoring Teams. these levels to the thyroid) or EPA PAGs 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 > 1.OE+4 mr/hr, OR
b. Charging Area R-4 > .OE+4 mr/hr OR Radiation levels or airborne contamination which indicate a severe degradation in the control of
c. SFP Area R-5 2 1.OE+4 mr/hr, OR radioactive materials (e.g., radiation ALERT levels suddenly increase by a factor of
d. Plant area air sample indicates airborne 1,000).

contamination > 1,000 times the occupational DAC values.

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

Offsite Dose Calculation Manual limits UNUSUAL EVENT (2) Liquid Releases: Notification by the exceeded.

Rad-Chem Group of violating ODCM 3.3.1 limits.

Table 2-1 EPIP-AD-02 Rev. AG Date: MAY 5 2003 Page 5 of 21 REFERENCE USE

CHART A(2)

GASEOUS EFFLUENT ACTION LEVELS

1. AUX BUILDING VENT RELEASES - WITH SJ!;NIFICANT CORE DAMlAE Instrument readings assuning a post accident gas release AND Containment High Range Radiation Monitors 42599 (R-40) and 42600 (R41) 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.

FANS l AUX BLDG SPING MONITORS AUX BLDG STACK MONITORS CLASS.

MID RANGE IIIGII RANGE R-*6 CPM (01-07) CPM (01.09) R-35 R PPCS PT G9086G PPCS PT G9088G MRIIR RR TOTAL -- 1: .1-,^

NUNIBER AVG MET ADV MET AVG MET ADV MET AVG ADV AVG MET ADV MET RUNNING MET MET -

I ** I.1E+4 6.5E+1 ** 7.9E+2 1.27E+2 7.9E-I 2 8.8E+5 5.5E+3 3.25E+1 ** 3.9E+2 6.35E+1 4.OE-1 GENERAL 3 5.9E+5 3.7E+3 2.16E+I ** 2.6E+2 4.2E+1 2.6E-1 EMERG.

4 4.4E+5 2.7E+3 1.62E+1 - 2.0E+2 3.175E+1 2.OE-1 I 8.8E+4 5.5E+2 3.0E+0

  • 6.3E+3 3.9E+1 6.3E+0
  • 2 4.4E+4 2.7E+2 I.SE+0
  • 3. I E+3 I.9E+I 3.IE+0
  • SITE EMERG.

3 2.9E+4 1.8E+2 1.OE+0

  • 2.1E+3 I.3E+1 2.1E+0
  • 4 2.2E+4 1.3E+2 1.5E+3 9.5E+0 1.5E+0 I 1.0E+3 6.2E+0 *
  • 7.0E+1 * *
  • 2 5.OE+2 3.1E+0 *
  • 3.5E+I ALERT 3 3.3E+2 2.OE+0 *
  • 2.3E+ l * *
  • 4 2.5E+2 1.5E+0 *
  • 1.75E+1 * *
  • I 1.OE+2 6.2E-1 *
  • 7.0E+0 * *
  • 2 5.0E+I 3.1E-1 *
  • 3.5E+0 * *
  • UNUSUAL EVENT 3 3.3E+1 2.OE-1 *
  • 2.3E+0 * *
  • 4 l0 l 2.5E+1 1.5E-I * * .7E+0 * * *
  • Offscale Low
    • Offscale High (Confirmation Only)

Table 2-1 EPIP-AD-02 Rev. AG Date: MAY 5 2003 Page 6 of 21 REFERENCE USE

CHART A(2)

GASEOUS EFFLUENT ACTION LEVELS continued

2. AUX BUILDING VENT RELEASES WITHOUT CORE DAMAGE 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.

FANSFP AUX BLDG SPING MONITORS CLASS.

MID RANGE HIGH RANGE TOTAL CPM (01-07) CPM (01-09)

NUMBER PPCS PT G9086G PPCS PT G9088G RUNNING

________ AVG MET ADV MET AVG MET ADV MET 1 ** 9.4E+4 1.6E+4 1.0E+2 2 ** 4.7E+4 8.0E+3 5.0E+1 GENERAL 3 ** 3.1E+4 5.3E+3 3.3E+1 EMERG.

4 2.3E+4 4.0E+3 2.5+1 1 7.5E+5 4.6E+3 8.OE+2 5.OE+0 2 3.7E+5 2.3E+3 4.OE+2 2.5E+0 SITE EMERG.

3 2.5E+5 1.5+3 2.6E+2 1.6E+O 4 1.8E+5 1.1E+3 2.OE+2 1.2E+0 SV & SFP AUX BLDG SPING MONITORS FANS EMERG.

TOTAL LOW RANGE MID RANGE CLASS.

NUMBER Cl/cc (01-05) CPM (01-07)

RUNNING PPCS PT G9084G PPCS PT 9086G I ** 8.6E+3 2

  • 4.3E+3 ALERT 3 ** 1 2.8E+3 4 *2.11E+3 1 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 2.1E+2
    • Offscale High (Confirmation Only)

Table 2-1 EPIP-AD-02 Rev. AG Date: MAY 5 2003 Page 7 of 21 REFERENCE USE

CHART A(2)

GASEOUS EFFLUENT ACTION LEVELS continued

3. STEAM LINERELEASE WITH FIGNIFICANTCOREDAMAGE 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 (R-40) or 42600 (R-41) reads 1000 R/hr for > 2 minutes within one-half hour of the accident.

- - ~~~"All"B

- - - Steam Line Monitors Steam Line Monitors Emergenc Classification R-15 R-31 R-32 R-33 R-34 (cpm) (mRlhr) (R/hr) (mR/hr) (RIhr)

    • 1.3E+3 1.3E+0 1.3E+03 1.3E+0 General Emergency
    • 6.0E+1 6.0E+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)

Mid Range (cpm) High Range (cpm) -

1.3E+05 1.5E+2 General Emergency 6.7E+03 7.0E+0 Site Emergency 1.5E+1 Alert Unusual Event Table 2-1 EPIP-AD-02 Rev. AG Date: MAY 5 2003 Page 8 of 21 REFERENCE USE

CHART B FUEL DAMAGE INDICATION KNPP INDICATION EMERGENCY CLASSIFICATION CRITERIA CLASSIFICATION CASFCTO (1) CET > 1,200 Degrees for greater than 15 minutes, OR Plant conditions exist that make the (2) R40 or R41 > 1,000 RIhr, OR release of large amounts ofGE RA 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-I1ORR-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.

(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 auxiliary building.
b. Alarm on R-1 OR R-12, OR (2) Fuel Handline Accident in AuxiliaryBld.
a. A confirming report, AND
b. Alarm on R-13 OR R-14.

(I) With RCS Temperature > 500°F,

a. >10CrmDOEqiaet 31fr4 High reactor coolant activity UNUSUAL
a. > 1.0 lCi/gram DOSE Equivalent 1-131 for 48 sample. EVENTl hours, OR s
b. Exceeding 60 uCi/gram for Dose Equivalent 1-131,. OR
c. > 91/E pCi/cc As determined by SP-37-065 (from T.S. 3.l .c)

(1) R-9 is greater than 5.0 R/hr, AND Failed fuel monitor indicates greater UNUSUAL than 0.1% equivalent fuel failures l (2) Verified by RCS chemistry sample analysis. within 30 minutes. EVENT Table 2-1 EPIP-AD-02 Rev. AG Date: MAY 5 2003 Page 9 of 21 REFERENCE USE

CHART C PRIMARY LEAK TO LOCA

'-~~ NOTE: This chart does not apply when leakage from the Reactor Coolant System is caused by a Steam Generator tube rupture.

KNPP INDICATION CASFAT NCR 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

> 10% hydrogen concentration, OR

d. Containment pressure exceeds 46 psig.

(1) SI System is activated and RCS leakage Reactor Coolant System leakage SITE 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 ALERT an unisolable RCS leak > 50 gpm. greater than 50 GPM.

(1) Initiation of reactor shutdown required by Exceeding Reactor Coolant Technical Specification, Section T.S. 3.1.d. System leak rate, Technical 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. AG Date: MAY 5 2003 Page 10 of 21 REFERENCE USE

CHART D PRIMARY TO SECONDARY LEAK EMERGENCY KNPP INDICATION CLASSIFICATION CLASSIFICATION CRITERIA (I) 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.

(1) Entry into(1)

IPEOP E-3, E-, "Steam "Seam Generator ntryintoIPEO enertor Tube ube Rapid gross generator failure tube with of oneofsteam loss ALERT 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.

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 3.1 .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. AG Date: MAY 5 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 I 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 1 through 6 are de-energized including thEe Loss of off-site power, AND D/G supplies to buses 5 and 6 for longer than Ls fofst oe,ADST 15 minuites. (Does not apply when core is EMERGENCY unloaded or cavity is flooded with intemnals 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 mrinutes. power (for more than 15 EMERGENCY

a. BRA 102 and BRB 102, OR minutes).
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 DC distribution 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, OR minutes).
b. BRA 104 and BRB 104, OR
c. BRA 102 and BRB 104, OR
d. BRB 102 and BRA 104 CDoes not apply when core is unloaded or cavity is looded with 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 15 minutes. (Does not apply when less than 15 rninutes.)

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

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

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

15 minutes.

Table 2-1 EPIP-AD-02 Rev. AG Date: MAY 5 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 > 200°F. EMERGENCY

a. 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. Loss of RCS inventory control, OR
e. Loss of both trains of RHR, AND the inability to sustain either natural OR forced circulation with the steam generators (S 350°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.")

(Apply this criteria when the RCS is < 200°F.) Complete loss of any function ALERT needed when RCS S 200°F.

(I) Loss of both trains of RHR (Does not apply when core is unloaded OR cavity is flooded with intemals 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.)

Table 2-1 EPIP-AD-02 Rev. AG Date: MAY 5 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 15 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 snutdown.)

(1) Significant loss of ESF or Rx Protection Indications or alarms on process NUSUAL 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. AG Date: MAY 5 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 Rlhr, 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 Table 2-1 EPIP-AD-02 Rev. AG Date: MAY 5 2003 Page 15 of 21 REFERENCE USE

CHARTJ MISCELLANEOUS ABNORMAL PLANT CONDITIONS

. KNPP INDICATION KNPP INDICATION ~~EMERGENCY l 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

> 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: imminent.

a. Loss of SI and RHR flow, - Transient requiring the AND operation of shutdown systems with a failure of these (3) Failure of shutdown system when required: shutdown systems. In addition, 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 IFW 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 part 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. AG Date: MAY 5 2003 Page 16 of 21 REFERENCE USE

CHART K FIRE AND FIRE PROTECTION KNPP INDICATION EMERGENCY CLASSIFICATION CLASSIFICATION CRITERIA (1) A fire within the Auxiliary Building, A fire compronising 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.

D/G 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 ninutes. more than 10 minutes. EVENT CHART L (DELETED)

Table 2-1 EPIP-AD-02 Rev. AG Date: MAY 5 2003 Page 17 of 21 REFERENCE USE

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 RR159, 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 (OBE).

(2) Verification of a seisnic 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.

(1) A tornado which strikes the facility, AND Any tornado striking facility. ALERT (2) Causes damage to render a single train of required ES equipment 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. AG Date: MAY 5 2003 Page 18 of 21 REFERENCE USE

CHART 0 FLOOD, LOW WATER, OR SEICHE EMERGENCY CLASSIFICATION KNPP INDICATION CRITERIA CLASSIFICATION FOREBAY LEVEL Flood, low water, or Indicated for > 15 minutes seiche near design ALERT OPUMPS 1IPUMP 2 PUMPS CORRESPOND levels.

UMSTO LAKE LEVEL NOTE3 NOTE 2 94% 2588 ft.

<50%

  • NOTE5 NOTE 5 < 568.5 ft.

QR Deep water Wave 2 22.5 ft.

FOREBAY LEVEL 50-year flood, low Indicated for > 15 minutes water level or seiche UNUSUAL OPUMPS 1 PUMP 2 PUMPS CORRESPOND EVENT

______TO LAKE LEVEL NOTE2 298%* 2 88%* 2 586 ft.

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

_____ I NOTE 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. 1 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. AG Date: MAY 5 2003 Page 19 of 21 REFERENCE USE

CHART P EXTERNAL EVENTS AND CHEMICAL SPILLS EMERGENCY KNPP INDICATION CLASSIFICATION CLASSIFICATION CRITERIA Aircraft crash affecting vital SITE (1) An aircraft crash into plant buildings which causes structures by impact OR fire. EMERGENCY a complete loss of an ESF function.

.1 Astrikes missileplant buildings, OR Severe damage to safe SITE (1) A mssile strikes plant buildings, OR shutdown equipment from EMERGENCY missiles or expiosion.

(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 from a ruptured or flammable gas is confirmed EMERGENCY container, which causes or is liKely to cause within vital area.

evacuation of stations 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.

(1) An aircraft crashes into plant buildings AND Aircraft crash on facility. ALERT causes a single train of required ESF equipment to be inoperab e.

. . . .... . ~~~~~Missile impact from whatever ALERT (1) A missile strikes the facility AND causes a single Mssie impaciltf w train of required ESF equipment to be inoperable. source on facilty.

Uncontrolled release of toxic ALERT (1) Release of toxic or flammable gas at life Uorlale relasecofioxic threatening levels from a ruptured container enter or flammable gas is confirmed the protected area AND impacts safe operation of Within the protected area.

the plant.

(1) Self-explanatory. Known explosionplant facilt affecting damage to ALERT operation.

(1) Ancrash aircraft within thesiteboundary,Aircraft crash on-site or UNUSUAL (1) An arcraft crash wthin the ste boundary, OR unusual aircraft activity over EVENT facility.

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

Uncontrolled release of toxic UNUSUAL EVENT (I) Release of toxic or flammable gas from a ruptured or flammable gas is confirmed tank/truck on site, AND 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. AG Date: MAY 5 2003 Page 20 of 21 REFERENCE USE

CHART Q 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 imninent occupancy of 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 or of any vital areas as defined in the Security Plan, OR (2) Security safeguards contingency event that results in a site specific Hl eve] 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. AG Date: MAY 5 2003 Page 21 of 21 REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-TSC-03 Rev. W Title Plant Status Procedure Kewaunee Nuclear Power Plant Emergentcy Plan Implementing Procedure Date MAY 5 2003 Page 1 of 4 Reviewed By Jim Chadek Approved By Jerrie Morlino Nuclear O Yes PORC a Yes SRO Approval Of D Yes Safety Review Temporary Related 0 No Required El No Changes Required XNo 1.0 Purpose 1.1 This procedure provides instruction for the Data Coordinator or other Technical Support Center (TSC) staff members to maintain checklists for awareness of plant parameters, equipment availability, and radiological conditions.

2.0 General Notes 2.1 None 3.0 Precautions and Limitations 3.1 None 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 Start the trend recorders in the TSC (Safety Parameter Display System (SPDS) and meteorological) using instructions on Form EPIPF-TSC-02-04.

5.2 Ensure Technical Support Center (TSC) instrumentation and parameter displays are activated and functional.

5.2.1 IF a display is not functional, THEN contact the KNPP Computer Group.

5.3 Contact the Technical Support Center Director (TSCD) to determine if trends of critical parameters are needed.

5.4 If directed, initiate the following trends for the event in progress (i.e., LOCA: RWST Level versus Containment Sump Level):

5.4.1 Safety Assessment System 5.4.2 Digital Display (#3) 5.4.3 PPCS Computer Trend Recorders j:\appdata\procpws\draft\epip\etscO3.doc-Amy Kudick/Amy Kudick-Dick Eckert REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-TSC-03 Rev. W Title Plant Status Procedure Kewaunee Nuclear Power Plant Emnergentcy Plait Implementing Procedure Date MAY 5 2003 l Page 2 of 4 5.5 Obtain Data from the Plant Process Computer.

5.5.1 Call up GraphicDisplay #51, Plant System Status (Form EPIPF-TSC-03-01) on the system.

5.5.2 Obtain a hard copy by pressing the Print TSC Screen function key.

5.5.3 Call up GraphicDisplay #52, Environmental Status Board (Form EPIPF-TSC-03-03) on the PPCS Computer system.

5.5.4 Obtain a hard copy by pressing the Print TSC Screen function key.

5.5.5 Call up Grouip Outputs #45 and #46, Radiation Monitors on the System, and copy data onto Form EPIPF-TSC-03-04.

5.6 Direct the ERF Communicator - TSC to obtain the following information from the Control Room to complete Forms EPIPF-TSC-03-01 and EPIPF-TSC-03-02:

5.6.1 S/G PORV/STM Dump, A/B, Cond/ATM 5.6.2 SI Acc Level lA/B 5.6.3 Containment Humidity 5.6.4 RXCP Status A/B 5.7 Coordinate with the ERF Communicator - TSC to determine plant equipment status and record on Form EPIPF-TSC-03-02.

5.8 Data not available on the SPDS for Environmental Status Board (Form EPIPF-TSC-03-03) should be obtained and filled in by hand using the following guidelines:

a. Meteorological
1. Meteorological strip chart printers in the TSC
2. Point Beach Control Room
3. National Weather Service
b. Radiological Release
1. Radiological Protection Director (RPD)
2. Environmental Protection Director (EPD)

REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-TSC-03 I Rev. W Title Plant Status Procedure Kewaunee Nuclear Power Plant Emnergeicy Plan Inplementing Procedure Date MAY 5 2003 Page 3 of 4

c. Protective Action Recommendation
1. Emergency Director (ED)
2. Technical Support Center Director (TSCD) 5.9 Periodically update the status boards from the completed forms based upon:

5.9.1 The magnitude and pace of event.

5.9.2 When a significant change in parameters or equipment status occurs.

5.9.3 As a mean guide, update approximately every 15 minutes.

5.10 Review data for trends or significant changes.

5.11 Notify the ED or TSCD of any critical items.

5.12 Return to Step 5.4.

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 COMTRAK 84-177 7.2 COMTRAK 87-156 7.3 EPIP Appendix B, Forms REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-TSC-03 lRev. W Title Plant Status Procedure Kewaunee Nuclear Power Plant Emergenicy Plan Implemenzting Procedutre Date MAY 5 2003 l Page 4 of 4 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

  • TSC Chart Recorder Operation Checklist, Form EPIPF-TSC-02-04
  • Plant System Status, Form EPIPF-TSC-03-01
  • Plant Equipment Status, Form EPIPF-TSC-03-02
  • Environmental Status Board, Form EPIPF-TSC-03-03
  • Radiation Monitors, Form EPIPF-TSC-03-04 8.1.2 Non-OA Records None REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-TSC-09A Rev. K Title Core Damage Assessment Kewaunee Nuclear Power Plant Emergency Plan Implementing Procedure Date MAY 5 2003 T Page 1 of 11 Reviewed By John Helfenberger Approved By Jerrie Morlino Nuclear 1 Yes PORC El Yes SRO Approval Of 1 Yes Safety Review Temporary Related El No Required 0 No Changes Required 0 No 1.0 Purpose 1.1 This procedure provides instruction for assessing the degree of core damage during an accident. In addition, the guideline provides information for the assessment of the appropriate Emergency Action Level for off-site radiological protective actions based on the degree of core damage. Specifically, the information contained in this guideline relates to:

  • Determination of the degree of damage to the fuel rod cladding that results in the release of the fission product inventory in the fuel rod gap space
  • Determination of the degree of core overheating that results in the release of the fission product inventory in the fuel pellets
  • Determination of the appropriate Emergency Action Level for off-site radiological protective actions based on the degree of damage to the reactor core 2.0 General Notes 2.1 None 3.0 Precautions and Limitations 3.1 None 4.0 Initial Conditions 4.1 This guideline is to be used when Technical Support Center is activated and a Core Damage Assessment is requested.

j:\appdata\procpws\draft\epip\etscO9a.doc-Amy Kudick/Amy Kudick-Edward D. Coen REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-TSC-09A I Rev. K Title Core Damage Assessment Kewaunee Nuclear Power Plant Emergency Plan Implementtinig Procedrtre Date MAY 5 2003 Page 2 of 11 5.0 Procedure 5.1 Identify Current Plant Status 5.1.1 Complete Form EPIPF-TSC-09A-05 except for the last column.

5.1.2 Using the table below, determine the possible status of the reactor core.

5.1.3 Record status on Form EPIPF-TSC-09A-05.

5.1.4 Go to the appropriate section of this guideline as indicated from the table.

High Level Core Damage Assessment Plant Status Fuel Rod Fission Product Status Core Exit Thermocouple Temperature LESS THAN 700°F, AND No Core Damage Containment Radiation Continue to Monitor Plant Parameters Below Curve in Attachment A Core Exit Thermocouple Temperature Possible Fuel Rod LESS THAN 1800°F, AND Clad Damage Containment Radiation Below Curve in Attachment B Go to step 5.2 Core Exit Thermocouple Temperature GREATER THAN 1800 0 F OR Possible Fuel Contaiment Rdiatio Containment Radiation Overtemperature Damage Above Curve in Attachment B Go to step 5.3 5.2 Estimate Fuel Rod Clad Damage 5.2.1 Estimate fuel rod clad damage based on containment radiation levels.

5.2.1.1 Complete lines 1-4 of Form EPIPF-TSC-09A-02.

5.2.2 Estimate fuel rod clad damage based on core exit thermocouple readings.

5.2.2.1 Complete lines 5-10 of Form EPIPF-TSC-09A-02.

5.2.3 Verify reasonableness of clad damage estimates.

5.2.3.1 Complete lines 11-17 of Form EPIPF-TSC-09A-02.

REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-TSC-09A Rev. K Title Core Damage Assessment Kewaunee Nuclear Power Plant Erner ency Plan In: lementlin Procedure Date MAY 5 2003 l Page 3 of 11 5.2.3.2 IF expected response is not obtained, THEN determine if the deviation can be explained from the accident progression

  • injection of water to the RCS
  • bleed paths from the RCS
  • direct radiation to the containment radiation monitors, OR from conservatisms in the predictive model
  • fuel bumup
  • fission product retention in the RCS
  • fission product removal form containment 5.2.3.3 Record explanation of deviations on Form EPIPF-TSC-09A-02.

5.2.4 Report Findings.

5.2.4.1 Fill out Form EPIPF-TSC-09A-07 if level of damage has changed and give to Emergency Director.

5.2.5 Go to Step 5.1.

5.3 Estimate Fuel Overtemperature Damage 5.3.1 Estimate fuel overtemperature damage based on containment radiation levels.

5.3.1.1 Complete lines 14 of Form EPIPF-TSC-09A-03.

5.3.2 - Estimate fuel overtemperature damage based on core exit thermocouple readings.

5.3.2.1 Complete lines 5-7 of Form EPIPF-TSC-09A-03.

5.3.3 Estimate fuel overtemperature damage based on hydrogen concentration.

5.3.3.1 Complete lines 8-11 of Form EPIPF-TSC-09A-03.

5.3.4 Verify reasonableness of fuel overtemperature damage estimates.

5.3.4.1 Complete lines 12-18 of Form EPIPF-TSC-09A-03.

REFERENCE USE

WISCONSiN PUBLIC SERVICE CORP. No. EPIP-TSC-09A IRev. K Title Core Damage Assessment Kewaunee Nuclear Power Plant Emergency Plan Implementing Procedure Date MAY 5 2003 l Page 4 of 11 5.3.4.2 IF expected response is not obtained, THEN determine if the deviation can be explained from the accident progression

  • injection of water to the RCS
  • bleed paths from the RCS
  • direct radiation to the containment radiation monitors
  • hydrogen bum in containment or operation of hydrogen igniters, OR from conservatisms in the predictive model
  • fuel bumup
  • fission product retention in the RCS
  • fission product removal form containment 5.3.4.3 Record explanations of deviations on Form EPIPF-TSC-09A-03.

5.3.5 Report findings.

5.3.5.1 Fill out Form EPIPF-TSC-09A-07 if level of damage has changed and give to Emergency Director.

5.3.6 Go to Step 5.1.

6.0 Final Conditions 6.1 None 7.0 References 7.1 WCAP-14696-A Revision 1, "Westinghouse Owners Group, Core Damage Assessment Guidance," November 1999 7.2 Letter from John G. Lamb (NRC) to Mark Reddemann (NMC) transmitting the NRC SER for Amendment 160 to the Operating License allowing removal of Post Accident Sampling System from Technical Specifications, Letter No. K-02-006, Dated January 16, 2002 7.3 COMTRAK's89-026 and 89-027 7.4 Calculation Cl 1403, Determination of Setpoints for EPIP-TSC-09A 7.5 EPIP-EOF-04, EOF Staff Action for Alert or Higher REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-TSC-09A Rev. K Title Core Damage Assessment Kewaunee Nuclear Power Plant Emergency Plan Iplementing Procedure Date MAY 5 2003 l Page 5 of 11 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 OA Records

  • Fuel Rod Clad Damage Estimate, Form EPIPF-TSC-09A-02
  • Fuel Rod Overtemperature Damage Estimate, Form EPIPF-TSC-09A-03
  • Core Damage Assessment (Monitoring Data), Form EPIPF-TSC-09A-05
  • Core Damage Assessment Results, Form EPIPF-TSC-09A-07 8.1.2 Non-OA Records None REFERENCE USE

LIST OF ATTACHMENTS/FORMS ATTACHMENT TITLE Attachment A Containment Radiation Level vs. Time for RCS Release Attachment B Containment Radiation Level vs. Time for 1% Fuel Overtemperature Release Attachment C Containment Radiation Level vs. Time for 100% Clad Damage Release Attachment D Containment Radiation Level vs. Time for 100% Fuel Overtemperature Release Attachment E Hydrogen Concentration for 100% Core Overtemperature Damage FORM TITLE Form EPIPF-TSC-09A-01 Core Exit Thermocouple Data Form EPIPF-TSC-09A-02 Fuel Rod Clad Damage Estimate Form EPIPF-TSC-09A-03 Fuel Rod Overtemperature Damage Estimate Form EPIPF-TSC-09A-05 Core Damage Assessment (Monitoring Data)

Form EPIPF-TSC-09A-07 Core Damage Assessment Results Appendix A EPIP-TSC-09A Rev. K Date: MAY 5 2003 Page 6 of 11 REFERENCE USE

( (s ~~~~~~~~~~~~~~~~~

CONTAINMENT RADIATION LEVEL vs. TIME FOR RCS RELEASE 1.2E+01 - - i .

_- 1.OE+01 - _ X 0

(0 a:8.OE+00 -i 0

0 E

L) 0 6.OE+00 -

c. 4.0E+00 X-____ ______ _______

Q 2.0E+00 l_____ l_ __ _ _ _ _ _ _ __-_____l_

O.OE+00 - ... , , . . . .. . ., . . . . l.

0 5 10 15 20 25 30 35 40 45 50 Time (Hrs)

Attachment A EPIP-TSC-09A Rev. K Date: MAY 5 2003 Page 7 of 11 REFERENCE USE

(' ('

CONTAINMENT RADIATION LEVEL vs. TIME FOR 1% FUEL OVERTEMPERATURE RELEASE 1.E+05 r:

I.

c tl.E+04 0

E 0

'4-a, cc c) n ac.E+03 r-E 0

c0 C-)

l.E+02 0 5 10 15 20 25 30 35 40 45 50 Time Since Shutdown (Hrs)

- RCS Press < 1600 psig No ICS - RCS Press < 1600 psig, ICS Onl l'-RCS Press> 1600 psig No ICS - RCS Press> 1600 psig, ICS On Attachment B EPIP-TSC-09A Rev. K Date: MAY 5 2003 Page 8 of 11 REFERENCE USE

(.

CONTAINMENT RADIATION LEVEL vs. TIME FOR 100% CLAD DAMAGE RELEASE 1.E+04 I-co 17 0

0 E

0 L. 1.E+03 0

a:

En 0

D C

E c

C 0

l.E+02 0 5 10 15 20 25 30 35 40 45 50 Time Since Shutdown (Hrs)

I- RCS Press < 1600 psig No ICS - RCS Press < 1600 psig ICS On RCS Press > 1600 psig No ICS -RCS Press > 1600 psig ICS On Attacnment C EPIP-TSC-09A Rev. K Date: MAY 5 2003 Page 9 of 11 REFERENCE USE

(.

CONTAINMENT RADIATION LEVEL vs. TIME FOR 100% FUEL OVERTEMPERATURE RELEASE 1.E+07

_________________ 1_________________ F-- _________________ _________________ _________________ I _________________

L.

_____ _____ - I _____

I I

'a v-o 1.E+06 _______________ _______________ ______________ ______________ ______________ _______________ _______________

0 E ______________ ________________________________

_______________________________ 1 0

I-0 0) 0 a 1.E+05 E

._(U 0

l.E+04 0 5 10 15 20 25 30 35 40 45 50 Time Since Shutdown (Hrs) r l RCS Press < 1600 psig No ICS - RCS Press < 1600 psig ICS On - RCS Press > 1600 psig No ICS - RCS Press > 1600 psig ICS On Attachment D EPIP-TSC-09A Rev. K Date: MAY 5 2003 Page 10 of 11 REFERENCE USE

HYDROGEN CONCENTRATION FOR 100%

CORE OVERTEMPERATURE DAMAGE 12 10

.78 in p

0 I -6

  • 0 E

C r

4 2

0 0 10 20 30 40 50 60 70 80 Containment Pressure (psig)

A RCS Pressure < 1050 psig, core recovered B RCS Pressure > 1050 psig, core recovered C Core not recovered Attachment E EPIP-TSC-09A Rev. K Date: MAY 5 2003 Page 11 of 11

. REFERENCE USE

EVENT NOTICE Y NUCLEAR ACCIDENT REPORTING SYSTEM FORM (NARS)

ROLL-CALL State Warning Center I or 11 . .(Time) Kewaunee Co. _ _ (Time) Manitowoc Co. (Time)

"This is the (circle one) Ketvaunee/Point Beach Nuclear Site calling from the (circle one) CR/TSC/EOF/AEOF. An incident has occurred at our facility. Please record the following information on your Nuclear Accident Reporting System form." (Read below Box I hrough Box 12)

1. Reason For Call: Olnitial Report lEmereencv Classification Change [1PAR Change
2. STATUS 3. STATION/AFFECTED UNIT El [Al Actual Event El [S] Kewaunee (Check plant)

El [B] Drill El [T] Point Beach El Unit I El Unit 2 El Both (Check plant &unit)

4. ONSITE CLASSIFICATION 5. TINIE & DATE OF CLASSIFICATION / PAR CIIANGE / TERMINATION El [A] Unusual Event El [B] Alert El [A] Classification Time Date _ EAL# or Chart El [C] Site Area Emergency E [D] General Emergency E [B] Par Change Time Date .

E [E] Recovery El [Fl Terminated El [C] Recovery/Termination Time . . Date .

6. RELEASE STATUS 7. TYPF OF RELEASE

[A] Unusual Event or Alert: D [Al NOT APPLICABLE E [All NONE El [A2] OCCURRING El [A31 TERMINATED El [B] AIRBORNE

[B] Site Area Emergency or General Emergency: El [C] LIQUID El [BII POTENTIAL El [B21 OCCURRING El [B3] TERMINATED

8. WIND DIRECTION (15 minute average) 9. WIND SPEED & STABILITY CLASS FROM _______ DEGREES (Current 15 minute average.)

DOWNWINDSECTORS A B CD E FG H J K L M N P Q R MILES/HR.:

(Circle affected sectors.) STABILITY CLASS: A B C D E F G

_______________________________________________________________________ (Circle applicablestability class)
10. PROTECTIV'E ACTION RECOMMENDATIONS O[A] NONE (UNUSUAL EVENT, ALERT, SITE AREA EMERGENCY)

O[B] EVACUATE ALL SECTORS OUTTO _MILES (GENERAL EMERGENCY)

EVACUATE DOWNWIND SECTORS OUT TO MILES

11. ADDITIONA, INFORNIATION APPROVAL SIGNATURE DATE I TIME APPROVED /

(EMERGENCY DIRECTOR/EMERGENCY RESPONSE MANAGER)

12. EIERGENCY COMMUNICATOR /

(Print/sign)

1. "State Warning Center, please read back this message to verify accuracy." (Pause to allow message to be read back)
2. "llave all agencies received this messae?" (Iaitfor reply)
3. "Relay this information to Emergency anagement immediately. Have the appropriate personnel verify this message by placing a return phone call. The return phone number is (circle one) Kewaunee 920-388-0101 / Point Beach ."

NRC NOTIFICATION - Callback Verification Not Required Duty Officer Name Time Continuous phone link requested: No Yes NRC message transmitted by __from the Point Beach Site (Name) (CR/TSC/EOF/AEOF)

Form EPIPFGAD-07-01 Rev. Date: MAY 5 2003 Page 1 of 3

EVENT NOTICE NUCLEAR ACCIDENT REPORTING SYSTEM FORM (NARS)

NOTE:

R DO NOT FAX THIS PAGE TO STATE AND LOCAL AUTHORITIES DIRECTIONS FOR FILLING OUT THE FORM TABLE 1 Box #1 Reason For Call: Check appropriate. VIND DIRECTION AECTED DOWNWIND Box #2 Check appropriate status. (FROM) SECTORSI Box #3 Check affected plant and unit(s). For any wind direction, if ALL adverse meteorology Box #4 Classification being declared. IF this is a PAR Change (Use for block 10 "PAR" only) notification, THEN check the current classification.

>350.5 -9 HJK Box #5 Check the applicable events(s) and fill in the time and date.

If a classification, fill in EAL chart letter. >9-13 HJKL Box #6 Indicate whether a radioactive release is occurring. The >13-31.5 JKL definition of radioactive release is the release of radioactive >31.5-35.5 JKLM material to the environment attributable to the emergency

>35.5 -54 KLM event. At a minimum, a potential radioactive release always exists at a SE and General Emergency because of the >54-58 KLMN definition of SE and General Emergency. >58 -76.5 LMN Box #7 Indicate whether there is an airborne or liquid radioactive >76.5 -80.5 LMNP release in progress. IF there is no release in progress, THEN

>80.5 -99 MNP Check Not Applicable.

>99 -103 MNPQ Box #8 Use the current Primary 10-meter 15-minute average MET DATA if reliable; OTHERWISE, use the backup >103-121.5 NPQ 10 meter 15-minute average MET DATA or the Primary >121.5 -125.5 NPQR 60 meter 15-minute average MET DATA. >125.5-144 PQR

1. Fill the blank indicating the "From" wind direction.

>144-148 PQRA

2. Circle the appropriate downwind affected sectors using guidance of Table 1. >148-166.5 QRA

>166.5-170.5 QRAB Box #9 Use the current primary tower 10 meter 15-minute average MET DATA IF reliable: OTHERWISE, use the backup >170.5 -189 RAB tower 10 meter, or primary tower 60 meter data. >189-193 RABC

1. Fill the blank indicating the current wind speed. >193-211.5 ABC
2. IF available, Circle the appropriate stability class. Use >211.5-215.5 ABCD Delta-T for stability class IF reliable, OTHERWISE Primary or Backup Sigma Theta for stability class. >215.5 -234 BCD Stability class can be found on the Control Room ARTO >234-238 BCDE screen. Click on the "met data" icon in the bottom right

>238-256.5 CDE corner and the screen that pops up will have stability class. >256.5-260.5 CDEF Box #10 Indicate protective action recommendations. >260.5 -279 DEF

1. For a General Emergency, indicate a PAR as directed by >279-283 DEFG procedure EPIP-AD-03 or EPIP-AD-04 or EPIP-AD-19. >283-301.5 EFG
2. IF this is a PAR change, THEN include any previously >301.5 -305.5 EFGH chosen affected sectors to indicate all affected sectors.

>305.5 -324 FGH Box #11 1. IF classifying an event, THEN at a minimum describe

>324-328 FGHJ the EAL being implemented.

2. IE making a PAR change, THEN write "None", "PAR >328 -346.5 GHJ Change" or other applicable information related to the >346.5 -350.5 GHJK PAR.

Page 2 of 3 EPIPF-AD-07-O1 Rev.

Form EPIPF-AD-07-01 Rev. V V Date: MAY 55 2003 Date: MAY 2003 Page 2of 3

EVENT NOTICE TABLE 2 CONVERSION OF DELTA T AND SIGMA THETA STABILITY PASQUILL SIGMA THETA (O) 60M - IOM CLASSIFICATION CATEGORIES (DEGREES) DELTA T (F/50M)

Extremely Unstable A aO > 22.5 DELTA T -1.71 Moderately Unstable B 22.5 > aO 2 17.5 -1.71 < DELTA T S -1.53 Slightly Unstable C 17.5 > TO 2 12.5 -1.53 < DELTA T < -1.35 Neutral D 12.5 > crO Ž 7.5 -1.35 < DELTA T < -0.45 Slightly Stable E 7.5 > aO Ž 3.8 -0.45 < DELTA T < 1.35 Moderately Stable F 3.8 > c0Ž 2.1 1.35 < DELTA T < 3.60 Extremely Stable G 2.1 > aO 3.60 < DELTA T Rev. V Date: MAY 52003 Page 3 of 3 Form EPIPF-AD-07-O1 Form EPIPF-AD-07-01 Rev. Date: MAY 5 2003 Page 3 of 3

CORE DAMAGE ASSESSMENT RESULTS EI1 No Damage D Fuel Rod Clad Damage:

D Fuel Rod Overtemperature Damage:

Comments:

Core Hydraulics Engineer Date Form EPIPF-TSC-09A-07 Rev. A Date: MAY 5 2003 Page 1 of 1

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