ML021570015

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Radiological Emergency Response Plan Implementing Procedures
ML021570015
Person / Time
Site: Kewaunee Dominion icon.png
Issue date: 05/16/2002
From: Webb T
Nuclear Management Co
To:
Document Control Desk, Office of Nuclear Security and Incident Response
References
NRC-02-047
Download: ML021570015 (29)
v • d • e


Text

Kewaunee Nuclear Power Plant Point Beach Nuclear Plant N490 Highway 42 6610 Nuclear Road Kewaunee, WI 54216-9511 Two Rivers, WI 54241 920.388.2560 920.755.2321 Committed to NuclearExcellen '> Kewaunee / Point Beach Nuclear Operated by Nuclear Management Company, LLC NRC-02-047 May 16, 2002 10 CFR 50, App. E U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Ladies/Gentlemen:

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

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

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

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

Electric Division, PSCW, w/o attach.

QA Vault, wo/attach.

ý N6

DOCUMENT TRANSMITTAL KEWAUNEE NUCLEAR POWER PLANT FROM: DIANE FENCL - KNPP TRANSMITTAL DATE 05-16-2002 EMERGENCY PLAN IMPLEMENTING PROCEDURES TRANSMITTAL FORM OUTSIDE AGENCY COPIES (1-20)

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

T. Webb - NRC Region 111 (2, 3)* - Craig Weiss - Alliant Energy (11)*

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

T. Webb - State of Wisconsin (5)* Jim Holthaus - Nuclear Management Company (12)*

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

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

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

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

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

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

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

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

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

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

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

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

W. Galarneau - RAF/RPO (106, 107) M. Kuether - SBF/SEC (114) 6 W. Galarneau - SBF/ENV (108, 109) D. Krall - CR/Communicator (11 )(Partial Distribution)

W. Galarneau - SBFIEM Team (110, 111, l1lA) Simulator/Communicator (117)

W. Galarneau - Aurora Medical Center (118, 119) M. Fencl - Security (121)

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

J. Stoeger (126)

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

  • THIS IS NOT A CONTROLLED COPY. ITIS A COPY FOR INFORMATION ONLY.

I

KEWAUNEE NUCLEAR POWER PLANT REVISION OF EMERGENCY PLAN IMPLEMENTING PROCEDURES May 16, 2002 Please follow the directions listed below. If you have any questions regarding changes made to the EPIPs, please cintact Dave Seebart at ext. 8719.

EPIP Index, dated 05-16-2002.

REMOVE INSERT PROCEDURE REV. PROCEDURE REV.

EPIP-TSC-9A I EPIP-TSC-09A J EPIP-TSC-09B J DELETED EPIP FORM TSC 9A. 1 C Form EPIPF-TSC-09A-01 D EPIP FORM TSC 9A.2 C Form EPIPF-TSC-09A-02 D EPIP FORM TSC 9A.3 D Form EPIPF-TSC-09A-03 E EPIP FORM TSC 9A.4 C DELETED --

EPIP FORM TSC 9A.5 D Form EPIPF-TSC-09A-05 E EPIP FORM TSC 9A.6 C DELETED Return a. signed and dated copy of this transmittal letter, within 10 days of transmittal date, to the sender. If you have any questions or comments, please contact Dave Seebart at ext. 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.

Diane Fencl Enclosure 2

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 05-16-2002 PROC. NO. TITLE REV. DATE EP-AD EPIP-AD-01 Personnel Response to the Plant Emergency J 01-08-2002 Siren 11-15-2001 EPIP-AD-02 Emergency Class Determination AC AE 02-06-2002 EPIP-AD-03 KNPP Response to an Unusual Event AH 02-27-2002 EPIP-AD-04 KNPP Response to Alert or Higher

+ Deleted 04-27-87 EP-AD-5 Site Emergency D 05-09-2002 EPIP-AD-05 Emergency Response Organization Shift Relief Guideline 04-24-87 EP-AD-6 General Emergency Deleted AP 02-27-2002 EPIP-AD-07 Initial Emergency Notifications 02-26-96 EP-AD-8 Notification of Alert or Higher Deleted Deleted 04-27-87 EP-AD-9 Notification of Site Emergency Deleted 04-27-87 EP-AD-10 Notification of General Emergency R 04-11-2002 EPIP-AD- 11 Emergency Radiation Controls Deleted 03-26-94 EP-AD-12 Personnel Assembly and Accountability Deleted 04-25-94 EP-AD- 13 Personnel Evacuation Deleted 03-01-83 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 05-25-94 EP-AD- 14 Search and Rescue 0 10-30-2001 EPIP-AD- 15 Recovery Planning and Termination Occupational Injuries or Vehicle Accidents Deleted 03-14-97 EP-AD-16 During Emergencies Deleted 03-05-84 EP-AD-17 Communications P 02-27-2002 EPIP-AD-18 Potassium Iodide Distribution Q 11-27-2001 EPIP-AD-19 Protective Action Guidelines I --

PAGE 1 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 05-16-2002 PROC. NO. TITLE EPIP-AD-20 KNPP Response to a Security Threat EP-ENV EPIP-ENV-01 Environmental Monitoring Group Organization V 10-02-2001 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 V 10-09-2001 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 S 06-15-2000 EPIP-ENV-04B Air Sampling and Analysis W 10-09-2001 EP-ENV-4C Environmental Monitoring Teams Deleted 04-13-90 EPIP-ENV-04C Ground Deposition Sampling and Analysis W 10-09-2001 EPIP-ENV-04D Plume Tracking for Environmental Monitoring N 10-02-2001 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: 05-16-2002 PROC. NO. TITLE REV. DATE EP-ENV-6 Data Analysis, Dose Projections and Protective Deleted 12-21-81 Action Recommendations EP-ENV-6 Alternate Sample Analysis and Relocation of 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 Z 11-29-2001 EPIP-EOF-03 EOF Staff Action for Unusual Event AC 02-06-2002 EPIP-EOF-04 EOF Staff Action for Alert or Higher AI 02-06-2002 EP-EOF-5 Corporate Staff Action for Site Emergency Deleted 04-24-87 EP-EOF-6 Corporate Staff Action for General Emergency Deleted 04-24-87 EP-EOF-7 Notification of Unusual Event Deleted 04-06-94 EP-EOF-8 Relocation of EOF Deleted 03-01-83 EPIP-EOF-08 Continuing Emergency Notifications V 02-27-2002 EP-EOF-9 Interface with Support Organizations Deleted 03-05-84 EP-EOF-9 Notification of Site Emergency Deleted 04-24-87 EP-EOF-10 Notification of General Emergency Deleted 04-24-87 EPIP-EOF- I1 Internal Communication and Documentation U 11-15-2001 Flow EPIP-EOF-12 Media Center/Emergency Operation P 07-19-2001 Facility/Joint Public Information Center Security PAGE 3 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 05-16-2002 PROC. NO. TITLE REV. DATE EP-OP EP-OP-l Control Room Emergency Organization Deleted 04-24-87 EP-OP-2 Emergency Control Room Activation for Deleted 04-24-87 Emergency Response EP-OP-3 Control Room Communications Deleted 04-24-87 EP-OSF EP-OSF-1 Operation Support Facility Emergency Deleted 04-24-87 Organization EPIP-OSF-02 Operational Support Facility Operations U 02-06-2002 EPIP-OSF-03 Work Orders During an Emergency P 05-09-2002 EP-OSF-4 Operational Support Facility Communications Deleted 04-24-87 Search and Rescue D 09-12-2000 EPIP-OSF-04 EP-RET EP-RET-l Radiation Emergency Team Organization Deleted 04-16-96 EPIP-RET-02 In-Plant Radiation Emergency Team U 11-27-2001 Radiation Protection Office/Radiological T 11-29-2001 EPIP-RET-02A Analysis Facility (RPO/RAF) Activation EPIP-RET-02B Gaseous Effluent Sample and Analysis R 04-11-2002 EP-RET-2C Containment Air Sampling and Analysis Deleted 03-01-83 EPIP-RET-02D Emergency Radiation Entry Controls and M 06-12-2001 Implementation EP-RET-2E Handling of Injured Personnel Deleted 04-16-96 EP-RET-2F Personnel Decontamination Deleted 04-13-90 EPIP-RET-03 Chemistry Emergency Team 0 02-01-2000 Liquid Effluent Release Paths L 11-29-2001 EPIP-RET-03A EP-RET-3B Post-Accident Reactor Coolant Alternate Deleted 01-25-88 Sampling Procedure PAGE 4 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 05-16-2002 PROC. NO. TITLE REV. DATE EPIP-RET-03C Post Accident Operation of the High Radiation P 01-15-2002 Sample Room EPIP-RET-03D Containment Air Sampling Analysis Using N 01-15-2002 CASP EP-RET-3E Post Accident Operation of High Rad Sample Deleted 08-27-85 Room Inline Multiported Count Cave EPIP-RET-04 SBF Activation R 10-02-2001 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 H 10-09-2001 Plant Cooldown EP-RET-5A Plume Projection Deleted 04-27-87 EP-RET-6 Dose Projection Deleted 04-24-87 EP-RET-7 Radiological Analysis Facility/Radiation Deleted 04-24-87 Protection Office Communications EPIP-RET-08 Contamination Control of the Aurora Medical P 10-30-2001 Center EPIP-RET-09 Post-Accident Population Dose L 04-16-2002 EP-SEC EP-SEC-1 Security Organization Deleted 04-24-87 EPIP-SEC-02 Security Force Response to Emergencies X 02-06-2002 Deleted 04-16-82 EP-SEC-2A Manual Activation of Emergency Sirens EPIP-SEC-03 Personnel Assembly and Accountability AD 04-25-2002 EPIP-SEC-04 Security Force Actions for Dosimetry Issue P 10-02-2001 PAGE 5 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 05-16-2002 PROC. NO. TITLE REV. DATE EP-SEC-5 Security Force Response to the EOF Deleted 07-28-88 EPIP-SEC-05 Personnel Evacuation F 07-05-2001 EP-TSC EPIP-TSC-0 I Technical Support Center Organization and Q 02-06-2002 Responsibilities EPIP-TSC-02 Technical Support Center Activation T 02-06-2002 EPIP-TSC-03 Plant Status Procedure V 10-09-2001 EPIP-TSC-04 Emergency Physical Changes, Major Equipment N 05-09-2002 Repair EP-TSC-5 Technical Support Center Communications Deleted 04-24-87 Equipment EP-TSC-6 Assessment of Reactor Core Damage Deleted 09-30-86 EPIP-TSC-07 RV Head Venting Time Calculation I 10-19-2001 EPIP-TSC-08A Calculations for Steam Release from Steam N 12-14-2001 Generators EPIP-TSC-08B* STMRLS Computer Program F 10-02-2001 EP-TSC-8C* See EP-TSC-8B Deleted 04-16-92

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

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

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 05-16-2002 FIGURES EPIP FIG # Figure EPIPFG DESCRIPTION REV. t DATE EP-SEC-5 Technical Support EPLP-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-OO5 APPX-A-06-02 KNP Floor Plan A 10-31-2000 Radiological Analysis Facility - KNP Floor EPIP-APPX-A-06 EP-FIG-00 APPX-A-06-01 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 - WPSC D2-1 EPIP-APPX-A-06 EP-FIG-012 APPX-A-06-08 Floor Plan C 10-31-2000 NRC Work Area EPIP-APPX-A-06 EP-FIG-013 APPX-A-06-09 WPSC D2-4 Floor Plan A 10-31-2000 Population Distribution by Geographical Sub EPIP-AD-19 EP-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 C 10-30-2001 Map - Location of JPIC, EPIP-EOF- 12 EP-FIG-024 EOF-12-02 MBC, GOB, DOB, etc. B 09-27-2001 EP-SEC-5 EP-FIG-026 SEC-05-01 Site Map B 09-27-2001 Floor Plan - Media APPX-A-6 EP-FIG-034 --- Briefing Center Deleted 08-04-98 General Office EPIP-EOF-12 Building - WPSC (1st EPIP-APPX-A-06 EP-FIG-035 APPX-A-06-06 Floor) Floor Plan C 10-24-2000 Floor Plan - Corporate APPX-A-6 EP-FIG-037 --- Response Center Deleted 08-04-98 APPX-A-6 EP-FIG -- 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 B 12-21-2001 JPIC - State and County Work Area EPIP-APPX-A-06 EP-FIG-044 APPX-A-06-07 WPSC D2-8 C 12-21-2001 JPIC - Utility Work EPIP-APPX-A-06 EP-FIG-045 APPX-A-06-05 Area - WPSC D2-7 C 12-21-2001 Aurora Medical Center RET-08 EP-FIG-046 RET-08-01 Location A 06-15-2000 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: 05-16-2002 NUMBER TITLE REVISION DATE APPENDIX A APPX-A-1 Communication System Description AF 08-04-98 EPIP-APPX-A-02 Response Personnel Call List Deleted 02-06-2002 EPIP-APPX-A-03 Off-Site Telephone Numbers Deleted 02-06-2002 EPIP-APPX-A-06 KNPP Emergency Response Facility Telephone AA 12-21-2001 Numbers PAGE 8 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 05-16-2002 FORM EPIPF TITLE REV. DATE APPENDIX B EP-AD AD-07-01 Event Notice (Wisconsin Nuclear Accident Reporting R 12-14-2001 Form)

AD-07-02 State Call-Back - Question Guideline C 11-15-2001 AD- 11-01 Emergency Radiation Work Permit G 04-11-2002 AD-18-01 Airborne Radioiodine Dose Accountability and Potassium A 02-27-2002 Iodide Distribution AD-18-02 Record of Known Allergy To or Voluntary Refusal to A 02-27-2002 Take Potassium Iodide EP-ENV ENV-01-01 Environmental Dispatch Area Activation Checklist D 10-31-2000 ENV-01-02 EMT Status B 10-31-2000 ENV-01-03 Meteorological and Plant Status Data C 12-14-2001 ENV-01-04 EMT Orders/Field Data B 10-31-2000 ENV-02-01 EMT Activation Checklist M 06-15-2000 EP-EOF EOF-02-01 EOF Activation Checklist S 10-30-2001 EOF-02-02 EOF Deactivation Checklist L 10-30-2001 EOF-04-01 SRCL Initial Action Checklist C 12-14-2001 EOF-04-02 Telephone Communications Log Sheet A 12-14-2001 EOF-08-03 Fax for Emergency Declaration or Status Updates G 11-27-2001 EOF-08-05 Plant Emergency Status Report A 11-27-2001 EOF-08-06 Radiological Status Report D 11-27-2001 EOF- 11-02 Operating Status F 11-15-2001 EOF- 11-03 Environmental Status Board F 11-15-2001 EOF-12-01 I.D. Badge Registration Form G 10-24-2000 PAGE 9 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 05-16-2002 FORM EPIPF TITLE REV. DATE 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 2B. 1 Containment Stack Release (Grab Sample) C 04-16-96 RET 2B.2 Auxiliary Building Stack (Grab Sample) C 04-16-96 RET 2B.3 Auxiliary Building Stack (Sping Reading) C 04-16-96 RET 2B.4 Containment Stack (Sping Reading) B 04-16-96 RET 2B.5 Steam Release C 04-16-96 RET 2B.6 Field Reading (Grab Sample) A 04-16-96 RET-04-01 SAM-2 Counting Equipment Worksheet E 06-12-2001 Deleted 06-05-2001 RET 8.3 Hospital Survey 1 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 F 06-15-2000 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 4.1 Emergency Dosimeter Log F 02-16-2000 EP-TSC TSC-01.01 Plant Status Summary for SAM Implementation B 02-06-2002 TSC-0 1.02 Severe Accident Management Summary and Strategy B 02-06-2002 Recommendation TSC-01.03 Severe Accident Management - Status B 02-06-2002 TSC-02-01 TSC and OSF Activation Checklist 0 09-27-2001 PAGE 10 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 05-16-2002 FORM EPIPF TITLE REV. DATE TSC 2.2 TSC Ventilation Checklist H 04-01-99 TSC-02-03 Emergency Response Data System (ERDS) Link Initiation G 05-04-2001 Checklist TSC-02-04 TSC Chart Recorder Operation Checklist D 01-30-2001 TSC-02-05 TSC and OSF De-activation Checklist A 10-09-2001 TSC-03-01 Plant System Status L 06-12-2001 TSC-03-02 Plant Equipment Status L 06-12-2001 TSC-03-03 Environmental Status Board J 06-12-2001 TSC-03-04 Radiation Monitors I 01-08-2002 TSC-04-01 Emergency Physical Change Request G 05-09-2002 TSC-04-02 Emergency Physical Change Safety Review Deleted 05-09-2002 TSC-04-03 Emergency Physical Change Index F 08-29-2000 TSC-07-01 Head Venting Calculation F 10-31-2000 TSC-08A-01 Steam Release Data Sheet (Energy Balance) H 12-14-2001 TSC-08A-02 Steam Release Calculation Sheet (Energy Balance) G 12-14-2001 TSC-08A-03 Steam Release Data/Calculation Sheet (Open Valve) E 12-14-2001 TSC-08A-04 Steam Release Data/Calculation Sheet (STMRLS D 12-14-2001 Program)

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

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-TSC-09A FRev. J Title Core Damage Assessment Kewaunee Nuclear Power Plant Emergency Plan Implementing Procedure Date MAY 16 2002 Page I of 11 Reviewed By William Yarosz Approved By Tom Coutu Nuclear 0 Yes POR 0 Yes SRO Approval Of 0 Yes Safety Review Temporary Related 0 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.

n:\nucdoc\procedures\draft\epip\etscO9a.doc-Chdstine Simmons/Christine Simmons-Edward Coen REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-TSC-09A -Rev. J Title Core Damage Assessment Kewaunee Nuclear Power Plant Emergency Plan Implementing Procedure Date MAY 16 2002 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 Fuel Rod Plant Status Fission Product Status Core Exit Thermocouple Temperature LESS THAN 700-F, AND No Core Damage Containment Radiation Continue to Monitor Plant Parameters LESS THAN Figure EPIPFG-TSC-09A-01 Rad/hr Core Exit Thermocouple Temperature Possible Fuel Rod LESS THAN 1800°F, AND Clad Damage Containment Radiation Go to step 5.2 LESS THAN Figure EPIPFG-TSC-09A-02 Rad/hr Core Exit Thermocouple Temperature Possible Fuel GREATER THAN 1800-F, OR Overtemperature Damage Containment Radiation Go to step 5.3 GREATER THAN Figure EPIPFG-TSC-09A-02 Rad/hr 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. J Title Core Damage Assessment Kewaunee Nuclear Power Plant Emergency Plan Implementing Procedure Date MAY 16 2002 Page 3 of I1 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 Report clad damage estimate 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 1-4 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 -Rev. J Title Core Damage Assessment Kewaunee Nuclear Power Plant Emergency Plan Implementing Procedure Date MAY 16 2002 I 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 burn 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 Report fuel overtemperature estimate 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 REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-TSC-09A IRev. J Title Core Damage Assessment Kewaunee Nuclear Power Plant Emergency Plan Implementing Procedure Date MAY 16 2002 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 QA Records

"* Core Exit Thermocouple Data, Form EPIPF-TSC-09A-01

"* 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 8.1.2 Non-QA 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 I 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)

Appendix A EPIP-TSC-09A Rev. J Date: MAY 16 2002 Page 6 of 11 REFERENCE USE

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

  • 1.OE+01

-r V

" 8.0E+0O 0

E

, 6.0E+00 0

a)

E 0

2.0E+00 0 5 10 15 20 25 30 35 40 45 50 Time (Hrs)

Attachment A EPIP-TSC-09A Rev. J Date: MAY 16 2002 Page 7 of 11 REFERENCE USE

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

ý5.E+04 Q

E 0

0.E÷03 E

0 0

1 .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 On

"----RCS Press > 1600 psig No ICS -RCS Press > 1600 psig, ICS On rage P'age d0 OT OT ii Attachment B EPIP-TSC-09A Rev. J Date: MAY 16 2002 II REFERENCE USE

CONTAINMENT RADIATION LEVEL vs. TIME FOR 100% CLAD DAMAGE RELEASE 1.E+04 C

"0 (U

0 E

0 1.E+03 4) 0 (I,,

0u 0

o 1 E0 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 Attachment C EPIP-TSC-09A Rev. J Date: MAY 16 2002 Page 9 of 11 REFERENCE USE

CONTAINMENT RADIATION LEVEL vs. TIME FOR 100% FUEL OVERTEMPERATURE RELEASE l.E+07 0

E\

1.E+06 0

4 1.E+05 o 1.E +04 . . .. ._i_____I __.. [ I I I I I 1 I I I 5 10 15 20 25 30 35 40 45 50 0

Time Since Shutdown (Hrs)

-RCS Press < 1600 psig No ICS -- RCS Press < 1600 psig ICS On - RCS Press > 1600 psig No ICS -- RCS Press > 1600 psig ICS On S.

. . .IF'l

. . ... . . __-- A n* .,1 A Attachment D EPIP-TSC-09A Rev. J Date: MAY 16 2002 r-age -10 of I I REFERENCE USE

HYDROGEN CONCENTRATION FOR 100%

CORE OVERTEMPERATURE DAMAGE 12 10 8

6 E

0 0 4 2

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

A RCS Pressure < 1050 psig, core recovered B RCS Pressure > 1050 psig, core recovered C Core not recovered rage ii or ii Attachment E EPIP-TSC-09A Rev. J Date: MAY 16 2002 P-age 1 OT I-1 REFERENCE USE

CORE EXIT THERMOCOUPLE DATA Core Exit Thermocouple Temperatures (°F):

Number of CETs operable Number of CETs readings GREATER THAN 1200°F Number of CETs readings GREATER THAN 1400°F Number of CETs readings GREATER THAN 1800°F Core Hydraulics Engineer Date Form EPIPF-TSC-09A-01 Rev. D Date: MAY 16 2002 Page 1 of I INFORMATION USE

FUEL ROD CLAD DAMAGE ESTIMATE

1. Time since reactor shutdown (hrs.) from Form EPIPF-TSC-09A-05
2. Radiation level (Rad/hr) for 100% clad damage from Figure 3 EPIP-TSC-09A
3. Containment high range radiation level (Radihr) from Form EPIPF-TSC-09A-05
4. %Clad Dmgc Damagec. ==.%Ca Containment High Range Radiation Level x 100% =

Containment Radiation Level for 100% Clad Damage

5. RCS pressure (psig) from Form EPIPF-TSC-09A-05
6. Number of CETs > 1400°F from Form EPIPF-TSC-09A-02
7. Number of CETs > 1200°F from Form EPIPF-TSC-09A-02
8. Number of operable CETs from Form EPIPF-TSC-09A-02
9. IF RCS pressure GREATER THAN 1600 psig, THEN:

% Clad Damagec* - Number of CETs > 1400OF xl100%=

Number of Operable CETs

10. IF RCS pressure LESS THAN 1600 psig, THEN:

% Clad DamageCE - Number of CETs > 1200°F x100% =

Number of Operable CETs

11. RCS pressure (psig) from Form EPIPF-TSC-09A-05
12. Saturation temperature (0F) (RCS pressure +15) from Steam Tables
13. Containment H2 concentration (from Form EPIPF-TSC-09A-05) LESS THAN 0.2% YES / NO
14. RVLIS level (from Form EPIPF-TSC-09A-05) at 0%

(Circle no if one or more Reactor Coolant Pump is on) YES / NO

15. Hot leg RTD temperature GREATER THAN saturation temperature and LESS THAN 650°F YES / NO
16. Source range monitor GREATER THAN 200 COUNTS PER SECOND YES / NO

%Clad Damagec, -% Clad Damagec.r LESSTHAN50%

17.  % Clad Damagec.

YES/NO Explanation of Deviations:

Clad Damage Estimate:  %

Core Hydraulics Engineer Date Form EPIPF-TSC-09A-02 Rev. D Date: MAY 16 2002 Page I of I INFORMATION USE

FUEL ROD OVERTEMPERATURE DAMAGE ESTIMATE

1. Time since reactor shutdown (hrs) from Form EPIPF-TSC-09A-05
2. Radiation level (Rad/hr) for 100% core overtemperature damage from Figure 4 EPIP-TSC-09A
3. Containment high range radiation level (Rad/hr) from Form EPIPF-TSC-09A-05
4. %Core Damagec* = Containment High Range Radiation Level x 100%=

Containment Radiation Level for 100% Overtemperature Damage

5. Number of CETs > 1500'F from Form EPIPF-TSC-09A-02
6. Number of operable CETs from Form EPIPF-TSC-09A-02
7.  % Core Damagec - Number of CETs > 1800'F xl100%=

Number of Operable CETs

8. Hydrogen concentration in containment (%) from Form EPIPF-TSC-09A-05
9. Containment pressure (psig) from Form EPIPF-TSC-09A-05
10. H2 concentration (%) at 100% overtemperature damage from Figure 5 EPIP-TSC-09A
11.  % Core DamageH - Hydrogen Concentration in Containment x100%=

H2 Concentration at 100% Overtemperature

12. RCS pressure (psig) from Form EPIPF-TSC-09A-05
13. RVLIS level (from Form EPIPF-TSC-09A-05) at 0%

(Circle no if one or both Reactor Coolant Pump is on) YES /NO

14. Hot leg RTD temperature GREATER THAN 650°F YES / NO
15. Source range monitor GREATER THAN 200 COUNTS PER SECOND YES / NO
16.  % Core Damage. -% Core DamagecEr x 100% LESSTHAN 50%

% Core Damagec, YES / NO

17. 1%Core Damagec, -% Core Damager,, LESS THAN 25%

YES / NO

18. 1%Core Damage.- -%CoreDamage.1 LESS THAN 25% YES/NO Explanation of Deviations:

Core Damage Estimate:  %

Core Hydraulics Engineer Date Form EPIPF-TSC-09A-03 Rev. E Date: MAY 16 2002 Page 1 of I INFORMATION USE

CORE DAMAGE ASSESSMENT (MONITORING DATA)

RYIC RCS C PEAK EK CNTMT CNTMT CNTMT HI-RANGE FUEL FISO ROD HOT LEG CET PRESSURE CNCTNMT FISSION RVLIS RCS TIME LEVEL# PRESSURE TEMP. TEMP. H, CONC. PRESSURE RAD PRODUCT STATUS*

4 F I- t t t 4 F F + F t 4 F F + F -t 4 F F 4- F F + t 4 F 4- F F + F

__ I __ I ___ I __ 1 1

__ ___ .1 ___ ___ 1 4 F 4 4 F + +/- t 4 F 4 4 F + t 4 F 4 4 F + +/-

4 4 - 1* r

________ .1. __________ 4 ____________ .1. ___________ __________ ____________ .,. ____________ ..- ____________ - ___________

Time of Reactor Shutdown #Enter N/A if one or both Reactor Coolant Pump is on

  • Use ND for No Damage CD for possible Clad Damage FD for possible Fuel Overtemperature Damage Core Hydraulics Engineer Date Form EPIPF-TSC-09A-05 Rev. E Date: MAY 16 2002 Page I of 1 INFORMATION USE
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