ML040500275

Revision Aj to EPIP-AD-02, Emergency Class Determination and Revision T to EPIP-AD-11, Emergency Radiation Controls.

ML040500275
Person / Time
Site:	Kewaunee
Issue date:	02/09/2004
From:	Coutu T Nuclear Management Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NRC-04-014
Download: ML040500275 (55)

Text

I NMC Commifted to NuclearExcelnv . -

Kewaunee Nuclear Power Plant Operated by Nuclear Management Company, LLC February 09, 2004 NRC-04-014 10 CFR 50, App. E 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 are 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 Ill, Lisle, Illinois. As required, one copy of this letter and attachment is also submitted to the Kewaunee Nuclear Power Plant NRC Senior Resident Inspector.

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

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

Public Service Commission of Wisconsin, w/o enc.

QA Vault, w/o enc.

OL(S N490 Highway 42

• Kewaunee, Wisconsin 54216-9511 Telephone: 920.388.2560

DOCUMENT TRANSMITTAL KEWAUNEE NUCLEAR POWER PLANT FROM: DIANE FENCL - KNPP TRANSMITTAL DATE 01-28-2004 EMERGENCY PLAN IMPLEMENTING PROCEDURES TRANSMITTAL FORM OUTSIDE AGENCY COPIES (1-20)

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

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

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

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

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

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

J. Bennett (33) R. Johnson (24) P. Sunderland (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) D. Bradley - CR/SS Office (51, 56)

, C. Sternitzky - ATF-2 (44) C. Grant - TSC (50,95)

M. Daron - Security Building (46) W. Galarneau - RAF (53).

i C. Grant - EOF (81) W. Galarneau - SBF/EMT (54)

C. Grant - OSF (52,96) W. Galarneau - RPO (55)*

LOREB - STF (62, 66, 67, 68, 70, 72, 73, 74) STF (86,87,88)

STF Library (43)

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

WV. Galarneau - RAF/RPO (106, 107)(Partial Distribution) C. Grant - TSC Response Blue Binder (Piartal Distribution)

W. Galarneau - SBFIENV (108, 109)(Partial Distribution) C. Grant - TSC Response Red Binder (Partial Distribution)

W. Galarneau - SBFIEM Team (110,111, 111A)(Partial Distribution) -C-lratnt-TCPrd DI AJ:..roM5eN --

W. Flint - Cold Chem/HR Sample Room (113) C. Grant - EOF Response Binder (Partial Distribution)

S. Zutz - SBF/SEC (114) D. Bradley - CR Response Binder (Partial Distribution)

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

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

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

C. Grant (Liatson ?ianuals)EPIP-AD-02 and EOF.04 &APPXA-06 Figures only)

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

• THIS IS NOT A CONTROLLED COPY. IT IS A COPYFORINFORMATION ONLY.

1

KEWAUNEE NUCLEAR POWER PLANT.

REVISION OF EMERGENCY PLAN IMPLEMENTING PROCEDURES January 28, 2004 Please follow the directions listed below.

EPIP Index, dated 01-28-2004.

REMOVE INSERT _

PROCEDURE REV. PROCEDURE REV.

EPIP-AD-02 AI EPIP-AD-02 AJ

[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 Jerrie Coleman at 8719.

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

SIGNATURE DATE Please return this sheet to DIANE FENCL.

V 2

I EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-28-2004 PROC. NO. TITLE REV. DATE EP-AD EPIP-AD-01 Personnel Response to the Plant Emergency Siren L 09-09-2003 EPIP-AD-02 Emergency Class Determination AJ 01-28-2004 EPIP-AD-03 KNPP Response to an Unusual Event AJ .09-09-2003 EPIP-AD-04 KNPP Response to Alert or Higher AO 09-09-2003 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 Notifications AV 09-09-2003

.EP-AD-8 Notification of Alert or Higher Deleted 02-26-96 EP-AD-9 Notification of Site Emergency Deleted 04-27-87 EP-AD-10 Notification of General Emergency Deleted 04-27-87 EPIP-AD-1 1 Emergency Radiation Controls T 01-27-2004 EP-AD-12 Personnel Assembly and Accountability Deleted 03-26-94 EP-AD-13 Personnel Evacuation Deleted 04-25-94 EP-AD-13A Limited Area Evacuation Deleted 03-01-83 EP-AD-13B Emergency Assembly/Evacuation Deleted 03-01-83 EP-AD-13C Site Evacuation Deleted 03-01-83 EP-AD-14 Search and Rescue Deleted 05-25-94 EPIP-AD-15 Recovery Planning and Termination P 09-12-2002 EP-AD-16 Occupational Injuries or Vehicle Accidents Deleted 03-14-97 During Emergencies EP-AD-17 Communications Deleted 03-05-84 EPIP-AD-18 Potassium Iodide Distribution P 02-27-2002 EPIP-AD- 19 Determining Protective Action Recommendations T 09-19-2003 PAGE I OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-28-2004 PROC. NO. TITLE REV. JDATE EPIP-AD-20 KNPP Response to a Security Threat E 09-30-2003 EP-ENV EPIP-ENV-01 Environmental Monitoring Group Organization X 07-31-2003 and Responsibilities EPIP-ENV-02 Environmental Monitoring Team Activation Y 07-31-2003 EP-ENV-3A Environmental Protection Director Actions and Deleted 09-26-84 Directives EP-ENV-3B EM Team Actions Deleted 09-26-84 EPIP-ENV-03C Dose Projection Using RASCAL Software X 09-19-2003 EP-ENV-3D Revision and Control of ISODOSE II Deleted 02-14-95 EP-ENV-3E Manual Determnination of X/Q Deleted 04-24-87 EP-ENV-3F Manual Determination of X/Q (Green Bay Deleted 05-30-86 Meteorological Data)

EP-ENV-3G Manual Dose Projection Calculation Deleted 06-02-89 EP-ENV-3H Protective Action Recommendations Deleted 04-13-90 EPIP-ENV-04A Portable Survey Instrument Use U 07-31-2003 EPIP-ENV-04B Air Sampling and Analysis Y 07-31-2003

.EP-ENV-4C Environmental Monitorinig Teams Deleted 04-13-90 EPIP-ENV-04C Ground Deposition Sampling and Analysis Y 07-31-2003 EPIP-ENV-04D Plume Tracking for Environmental Monitoring P 07-31-2003 Teams EP-ENV-5A LCS-I 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: 01-28-2004 PROC. NO. TITLE REV. DATE EP-ENV-6 Data Analysis, Dose Projections and Protective Deleted 12-21-81 Action Recommendations EP-ENV-6 Alternate Sample Analysis and Relocation of EM Deleted 04-14-86 Team EP-ENV-6A Relocation of Site Access Facility (Habitability) Deleted 03-23-84 EP-ENV-6B SAF Environmental Sample Analysis Relocation Deleted 03-23-84 EP-ENV-7 Site Access Facility Communications Deleted 09-26-84 EP-ENV-8 Total Population Dose Estimate Calculations Deleted 04-14-86 EP-EOF EP-EOF-1 Corporate Emergency Response Organization Deleted 03-11-94 EPIP-EOF-02 Emergency Operations Facility (EOF) Activation AB 07-31-2003 EPIP-EOF-03 EOF Staff Action for Unusual Event AE 07-31-2003 EPIP-EOF-04 EOF Staff Action for Alert or Higher AL 07-31-2003 EP-EOF-5 Corporate Staff Action for Site Emergency Deleted 04-24-87 EP-EOF-6 Corporate Staff Action for General Emergency Deleted 04-24-87 EP-EOF-7 Notification of Unusual Event Deleted 04-06-94 EP-EOF-8 Relocation of EOF Deleted 03-01-83 EPIP-EOF-08 Continuing Emergency Notifications AA 07-31-2003 EP-EOF-9 Interface with Support Organizations Deleted 03-05-84 EP-EOF-9 Notification of Site Emergency Deleted 04-24-87 EP-EOF-10 Notification of General Emergency Deleted 04-24-87 EPIP-EOF-1 1 Internal Communication and Documentation W 07-31-2003 Flow EPIP-EOF-12 Media Center/Emergency Operation Facility/Joint R 06-19-2003 Public Information Center/Security PAGE 3 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-28-2004 PROC. NO. TITLE REV. DATE EP-OP EP-OP-1 Control Room Emergency Organization Deleted 04-24-87 EP-OP-2 Emergency Control Room Activation for Deleted 04-24-87 Emergency Response EP-OP-3 Control Room Communications Deleted 04-24-87 EP-OSF EP-OSF-1 Operation Support Facility Emergency Deleted 04-24-87 Organization EPIP-OSF-02 Operational Support Facility Operations V 11-04-2003 EPIP-OSF-03 Work Orders During an Emergency P 05-09-2002 EP-OSF4 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 X.07-31-2003 EPIP-RET-02A Radiation Protection Office/Radiological Analysis V 11-04-2003 Facility (RPO/RAF) Activation EPIP-RET-02B Gaseous Effluent Release Path, Radioactivity, and T 09-19-2003 Release Rate Determination EP-RET-2C Containment Air Sampling and Analysis Deleted 03-01-83 EPIP-RET-02D Emergency Radiation Entry Controls and M 06-12-2001 Implementation EP-RET-2E Handling of Injured Personnel Deleted 04-16-96 EP-RET-2F Personnel Decontamination Deleted 04-13-90 EPIP-RET-03 Chemistry Emergency Team P 02-18-2003 EPIP-RET-03A Liquid Effluent Release Paths L 11-29-2001 EP-RET-3B Post-Accident Reactor Coolant Alternate Deleted 01-25-88 Sampling Procedure PAGE 4 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-28-2004 PROC. NO. TITLE REV. DATE EPIP-RET-03C Post Accident Operation of the High Radiation P 01-15-2002 Sample Room EPIP-RET-03D Containment Air Sampling Analysis Using CASP N 01-15-2002 EP-RET-3E Post Accident Operation of High Rad Sample Deleted 08-27-85 Room Inline Multiported Count Cave EPIP-RET-04 SBF Activation U 06-19-2003 EP-RET-4A EOF Radiological Monitoring Deleted 03-10-83 EPIP-RET-04A SBF Operation/Relocation Deleted 10-02-2001 EP-RET-4B Radiological Controls at Site Access Facility Deleted 07-12-94 EP-RET-4C Site Radiological Monitoring Deleted 07-12-94 EP-RET-4D SAM-II Operation Deleted 07-12-94 EP-RET-5 Plume Projection Deleted 09-26-84 EPIP-RET-05 Site Boundary Dose Rates During Controlled I 07-31-2003 Plant Cooldown EP-RET-SA Plume Projection Deleted 04-27-87 EP-RET-6 Dose Projection Deleted 04-24-87 EP-RET-7 Radiological Analysis Facility/Radiation Deleted 04-24-87 Protection Office Communications EPIP-RET-08 Contamination Control of the Aurora Medical Deleted 05-23-2002 Center EPIP-RET-09 Post-Accident Population Dose Deleted 09-19-2003 EP-SEC EP-SEC-1 Security Organization Deleted 04-24-87 EPIP-SEC-02 Security Force Response to Emergencies Z 07-31-2003 EP-SEC-2A Manual Activation of Emergency Sirens Deleted 04-16-82 EPIP-SEC-03 Personnel Assembly and Accountability AG 05-20-2003 EPIP-SEC-04 Security Force Actions for Dosimetry Issue P 10-02-2001 PAGE5OF l

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-28-2004 PROC. NO. TITLE REV. DATE EP-SEC-5 Security Force Response to the EOF Deleted 07-28-88 EPIP-SEC-05 Personnel Evacuation G 06-20-2002 EP-TSC EPIP-TSC-01 Technical Support Center Organization and S 01-28-2003 Responsibilities EPIP-TSC-02 Technical Support Center Activation U 01-20-2003 EPIP-TSC-03 Plant Status Procedure W 05-05-2003 EPIP-TSC-04 Emergency Modifications 0 04-29-2003 EP-TSC-5 Technical Support Center Communications Deleted 04-24-87 Equipment EP-TSC-6 Assessment of Reactor Core Damage Deleted 09-30-86 EPIP-TSC-07 RV Head Venting Time Calculation J 06-20-2002 EPIP-TSC-08A Calculations for Steam Release from Steam P 09-02-2003 Generators EPIP-TSC-08B* STMRLS Computer Program H 07-31-2003 EP-TSC-8C* See EP-TSC-8B Deleted 04-16-92

• EP-TSC-8B was totally deleted; therefore, EP-TSC-8C was changed to EP-TSC-8B EP-TSC-9 Core Damage Assessment Using Released Deleted 09-30-86 Radionuclides EPIP-TSC-09A* Core Damage Assessment K 05-05-2003 EPIP-TSC-09B* CORE Computer Program Deleted 05-16-2002 EP-TSC-9C* See EP-TSC-9B Deleted 04-16-92

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

EPIP-TSC-10 TechnicalSupportforIPEOPs L l 07-31-2003 PAGE 6 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-28-2004 FIGIJRES EPIP l FG# Figure EPIPFG DESCRIPTION REV. DATE EPIP-SEC-05 Technical Support EPIP-APPX-A-06 EP-FG-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 EPFG-00S APPX-A-06-01 Facility - KNP Floor Plan A 10-31-2000 EPIP-EOF-12 Division Office Building Form EPIPF-EOF-02-01 EP-FIG-oo9 EOF-12-01 (2nd Floor) Floor Plan C 06-19-2003 State/County Work Area -

EPIP-APPX-A-06 EP-F1G-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-FIG4022 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 D 06-19-2003 KNP Site Map &

EPIP-SEC-05 EP-FG.026 SEC-05-01 Evacuation Routes E 09-19-2003 Floor Plan - Media APPX-A-6 EP-FIG-034 ___ Briefing Center Deleted 08-04-98 EPIP-EOF-12 EPIP-APPX-A-06 EP-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-FIG0-38 _ Floor Plan - JPIC Deleted 08-04-98 EPIP-OSF-02 EP-FG-039b OSF-02-01 High Priority Work B 07-31-2003 EPIP-OSF-02 EP-17G-039a OSF-02-02 Lower Priority Work B 07-31-2003 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 EP-FIG044 APPX-A-06-07 WPSC D2-8 D 04-29-2003 JPIC - Utility Work EPIP-APPX-A-06 EP-FIG-045 APPX-A-06-05 Area - WPSC D2-7 D 04-29-2003 Aurora Medical Center RET-08 EP-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: 01-28-2004 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: 01-28-2004 FORM 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 C 09-19-2003 AD-07-04 ERO Event Notification Deleted 07-31-2003 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 E 07-31-2003 ENV-01-02 EMT Status C 07-31-2003 ENV-01-03 Meteorological and Plant Status Data C 12-14-2001 ENV-01-04 EMT Orders/Field Data C 07-31-2003 ENV-02-01 EMT Activation Checklist 0 07-31-2003 EP-EOF EOF-02-01 EOF Activation Checklist V 09-19-2003 EOF-02-02 EOF Deactivation Checklist N 01-28-2003 EOF-04-01 SRCL Initial Action Checklist D 01-20-2003 EOF-04-02 Telephone Communications Log Sheet A 12-14-2001 EOF-08-03 Fax for Emergency Declaration or Status Updates H 01-20-2003 EOF-08-05 Plant Emergency Status Report A 11-27-2001 EOF-08-06 Radiological Status Report E 01-20-2003 EOF-1 1-02 Operating Status G 11-07-2002 PAGE 9 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-28-2004 FORM 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) E 09-19-2003 RET-02B-02 Auxiliary Building Stack Release (Grab Sample) E 09-19-2003 RET-02B-03 Auxiliary Building Stack Release (Sping Reading) E 09-19-2003 RET-02B-04 Containment Stack Release (Sping Reading) D 09-19-2003 RET-02B-05 Steam Release E 09-19-2003 RET-02B-06 Field Reading (Grab Sample) B 08-06-2002 RET-04-01 SAM-2 Counting Equipment Worksheet E 06-12-2001 RET 8.3 Hospital Survey I Deleted 06-05-2001 RET 8.4 Hospital Survey 2 Deleted 07-25-97 RET 8.5 Hospital Survey 3 Deleted 07-25-97 RET-08-06 Hospital Survey 4 Deleted 05-23-2002 RET-09-01 Post-Accident TLD Record Sheet Deleted 01-27-2004 EP-SEC SEC-03.01 Emergency Accountability Log A 03-28-2000 SEC-04-01 Emergency Dosimeter Log H 11-04-2003 EP-TSC TSC-01.01 Plant Status Summary for SAM Implementation C 01-28-2003 TSC-01.02 Severe Accident Management Summary and Strategy B 02-06-2002 Recommendation f~ . ..

PAGE 10 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-28-2004 FORM EPIPF TITLE REV. DATE TSC-01-03 Severe Accident Management - Status C 07-31-2003 TSC-02-01 TSC and OSF Activation Checklist P 01-20-2003 TSC-02-02 TSC Ventilation Checklist 3 09-19-2003 TSC-02-03 Emergency Response Data System (ERDS) Link Initiation H 01-20-2003 Checklist TSC-02-04 TSC Chart Recorder Operation Checklist E 01-20-2003 TSC-02-05 TSC and OSF De-Activation Checklist C 01-28-2003 TSC-03-01 Plant System Status L 06-12-2001 TSC-03-02 Plant Equipment Status L 06-12-2001 TSC-03-03 Environmental Status Board 1 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-07-0 1 Head Venting Calculation G 06-20-2002 TSC-08A-01 Steam Release Data Sheet (Energy Balance) H 12-14-2001 TSC-08A-02 Steam Release Calculation Sheet (Energy Balance) H 09-02-2003 TSC-08A-03 Steam Release Data/Calculation Sheet (Open Valve) E 12-14-2001 TSC-08A-04 Steam Release Data/Calculation Sheet (STMRLS Program) D 12-14-2001 TSC-09A-01 Core Exit Thermocouple Data D 05-16-2002 TSC-09A-02 Fuel Rod Clad Damage Estimate D 05-16-2002 TSC-09A-03 Fuel Rod Overtemperature Damage Estimate F 11-04-2003 TSC 9A.4 Core Damage Based on Activity Ratios Deleted 05-16-2002 TSC-09A-05 Core Damage Assessment (Monitoring Data) E 05-16-2002 TSC 9A.6 Core Damage Summary Deleted 05-16-2002 TSC-09A-07 Core Damage Assessment Results A 05-05-2003 PAGE 11 OF 11

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

: - . :t Title .;Emer . gency Class Determination Kewaunee Nuclear Power Plant Emergency Plan Implenting Procedure: Date JAN 28 2004 l Page 1 of 22 Reviewed By Paul Sunderland Approved By Kevin Davison Nuclear PORC SRO Approval Of Safety 0 Yes Review 0 Yes Temporary 0 Yes Related 03 NO Required 0 No Changes Required 0 No 1.0 Purpose 1.1 This procedure provides instruction for determining proper emergency classification listed in order to activate the appropriate level of response from the Kewaunee Nuclear Power Plant (KNPP) emergency response organization and off-site response orgariization.

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 deescalate.

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

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

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

J:\appdata\procpws\dratt\epip\eadO2.doc-Christine Simmons/Christine Simmons-John Egdorf REFERENCE USE

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

Emergenicy Plan nipleynenting Procedure. Date JAN 28 2004 l Page 2 of 22 5.0 Procedure 5.1 Determine if a plant emergency exists during abnormal plant conditions by referring to Table 2-1, Emergency Action Level Charts.

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

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

5.4 Determine if the emergency should be reclassified.

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

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

'..i 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. AJ

.-.- -.-- -: :: - - . - Title

~: E mergency Class Determination Kewaunee Nuclear Power Plant Emergency Plan Imple\enting Procedure Date JAN 28 2004 Page 3 of 22 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-OA 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.

• ,;'- a' ,YX Jo CHART -PAGE Abnormal Radiological Effluent A (1) 5 Gaseous Effluent Action Levels . A (2) 6- 8 Fuel Damage Indication B 9 Primary Leak to LOCA . C 10 Primary to Secondary Leak D 11 Loss of Power . E12 Engineered Safety Feature Anomaly F . .13 Loss of Indication G 14 DELETED H 14 Secondary Side Anomaly I 15 Miscellaneous Abnormal Plant Conditions - 16 Fire and Fire Protection K 18 DELETED L 18 Earthquake - M 19 High Winds or Tornado N 19 Flood, Low Water, or Seiche 0 -20 External Events and Chemical Spills P 21 Security Contingency Q 22 Table 2-1 EPIP-AD-02 Rev. AJ Date: JAN 28 2004 Page 4 of 22 REFERENCE USE

CHART A(1)

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

Projected l~ or

~ measured roeto dose rates or Dieco be provided by the Projected to Enviromenta dose rates or measured greater than in the environs 1 rem/hr whole GENERAL lI IRadiological Protection Director or Environmental..l Monitoring Teams. body or 5 rem/hr thyroid at the site EMERGENCY Monitoring Teams. boundary. ._l Effluent monitors detect levels corresponding to greater than 50 SEE CHART A(2) mr/hr for '/2 hour OR greater than 50 SITE EMERGENCYl mr/hr for two minutes (or five times these levels to the thyroid) OR for "adverse meteorology."

At the site boundary, projected or measured dose rates greater than 50 Projected or measured dose rates to be provided by the mr/hr for 1/2 hours OR greater than Radiological Protection Director or Environmental ti500 mr/hr for two minutes (or five SITE EMERGENCY Monitoring Teams.tiethsleesttetyrd)o EPA Prot&tive Action Guidelines are projected to be exceeded outside the site boundary.

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

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

b. Charging Area R-4 2 1,000 times baseline Radiation levels or airborne established in the Control Room, OR contamination which indicate a severe degradation in the control of ALERT

c. SFP Area R-5 2 1,000 times baseline established radioactive materials (e.g., radiation in the Control Room, OR - levels suddenly increase by a factor of 1,000).

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

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

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

Table 2-1 EPIP-AD-02 Rev. AJ Date: JAN 28 2004 Page 5 of 22 REFERENCE USE

CHART A(2)

GASEOUS EFFLUENT ACTION LEVELS i* 1. AUX BUILDING VENT RELEASES - WITHl SIGNIFIC.AANTMCORFlAAA GF Instrument readings assuming a post accident gas release AND Containment High Range Radiation Monitors 42599 (R140) and 42600 (R-41) 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.

SV & SFP AUX BLDG SPING MONITORS AUX BLDG STACK MONITORS F ANS _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

MID RANGE HIGH RANGE CPM (01-07) CPM (01.09) R-35 R/ll PPCS PT G9086G PPCS PT G9088G MIRIIR TOTAL NUMBER AVG -ADV RNNING AVG MET ADV MET AVG MET ADV MET MET MET AVG MET ADV MET 1 l .lE+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+1I 4.OE-I 3 5.9E+5 3.7E+3 2.16E+1 .

• 2.6E+2 4.2E+1 2.6E-I 4 4.4E+5 2.7E+3 1.62E+1 2.OE+2 3.175E+1 2.0E-1 I 8.81E+4 5.5E+2 3.0E+0

• 6.3E+3 3.9E+1 6.3E+0

• 2 4.4E+4 2.7E+2 I.5E+0 3. I E+3 1.9E+I 3.1 E+0 SITE 3 2.9E+4 1.8E+2 1.1OE+0

• 2.1 E+3 I.3E+1 2.1 E+0 EMERG.

.4 2.2E+4. 1.3E+2 - . 1.5E+3 9.5E3+0 1.5E+O

______ I.OE+3 6.2E+0

• l 7.0E+1 * *.

• 2 5.0E+2 3. I E+0 *

• 3.5E+1 *

• I ALERT.

. ll l l ~~~~~ALERT.

._3 3.3E+2 2.0E+0 *

• l2.3E+1 * *

• 2.5E+2 1.5E+0 l.75E+I I* * *

• I 1.OE+2 6.2E-1 *

• 7.OE+0 * *

• 2 5.0E+1 3.IE-1 *

• 3.5E+0 * *

• UNUSUAL EVENT 3 3.3E+1 2.02-1 *

• 2.3E+0 *

• l

• 4 ll 1 2.5E+1 1.5E-1 *

• 1.7E+0 * * *

• Offscale Low

• • Offscale High (Confirmation Only)

Table 2-1 EPIP-AD-02 Rev. AJ Date: JAN 28 2004 Page 6 of 22 REFERENCE USE

CHART A(2)

GASEOUS EFFLUENT ACTION LEVELS continued

.* 2. AUX BUILDING VENT RELEASES ITHOTCMOREDAA4AGE NOTE: Use adverse meteorology conditions (ADV MET) only when, 10m and 60m wind speed < 5mph AND Delta-T > +2.4 degrees F or Sigma Theta is < 3.01 degrees. All other cases are average meteorology (AVG MET).

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

SV & SFP AUX BLDG SPING MONITORS ECMEASRSG.

MID RANGE HIGH RANGE TOTAL CPM (01.07) CPM (01-09) -

NUMBER PPCS PT G9086G PPCS PT G9088G  :,,

RUNNING . 4A.nde AVG MET ADV IET AVG MET ADV MET

• 1** 9.4E+4 1.6E+4 1.0E+2

- 2 ** 4.7E+4 8.0E+3 5.0E+I GENERAL 3 ** 3.1E+4 5.3E+3 3.3E+I EMERG 4 ** 2.3E+4 4.0E+3 2.5+1 1 7.5E+5 4.6E+3 8.01E+2 5.0E+0 2 3.7E+5- 2.3E+3 4.OE+2 2.5E+0 SITE 3 2.5E+5 1.5+3 2.6E+2 1.6E+0 EMERG.

• 4 1.8E+5 1.12E+3 2.OE+2 1.2E+0 SV & SFP AUX BLDG SPING MONITORS FANS EMERG.

TOTAL LOW RANGE MID RANGE I NUMBER Ci/cc (01-05) CPM (01-07) CLASS.

RUNNING PPCS PT G9084G PPCS PT 9086G 8.6E+3 F 2 ** 4.32+3 ALERT 3 ** 2.8E+3 4 2.12+3 1 6.3E-2 8.6E+2 2 3.12-2 4.3E+2 UNUSUAL 3 2.12-2 2.8E+2 EVENT 4 1.52-2 . 2.1E+2

• • Offscale High (Confirmation Only)

Table 2-1 EPIP-AD-02 Rev. AJ Date: JAN 28 2004 Page 7 of 22 REFERENCE USE

CHART A(2)

GASEOUS EFFLUENT ACTION LEVELS continued

3. STEAM LINE RELEASE WATH 510 VIFICA NT CORE DA AGAGE 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.

-X~~~~e"A" B"~~~~~~~~Emergency Classification Steam Line Monitors Steam Line Monitors R-15 R-31 R-32 R-33 R-34 S (cpm) (mR/hr) (R/hr) (mR/hr) (R/hr) -S;____________l.___________i_

-** 1.3E+3 I.3E+0 1.3E+03 1.3E+0 General Emergency 6.0E+1 6.0E+1 Site Emergency

• • • .1.5E-1 .1.5E 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) e .;v*4;i?*n 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. AJ Date: JAN 28 2004 Page 8 of 22 REFERENCE USE

CHART B FUEL DAMAGE INDICATION KNPP INDICATION EMERGENCYTIO CLASSIFICATION CRITERIA CLASSIFICATION (1) CET > 1,200 Degrees for greater than 15 minutes, OR Plant conditions exist that make ihe (2) R40 or R41 > 1.000 R/hr OR release of large amounts of GENERAL radioactivity in a short time period EMERGENCY (3) SACRG-1, Severe Accident Control Room Guideline possible.

Initial Response has been implemented.

(Major damage is more than one spent fuel element -

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

a. Alarm on R-1 l OR R-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 assemblyOR .

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-l 1 OR R-12, OR (2) Fuel Handling Accident in Auxiliary Bldg.

a. A confirming report, AND

b. Alarm on R-13 OR R-14. ._._ll (1) With RCS Temperature > 500'F, UNSA High reactor coolant activity UNUSUAL

a. > 1.0 tiCi/gram DOSE Equivalent I-131 for 48 isample. EVENT hours, OR la.

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

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

(1) R-9 is greater than 5.0 R/hr, AND Failed fuel monitor indicates greater UNUSUAL than 0.1% equivalent fuel failures' (2) Verified by RCS chemistry sample analysis. within 30 minutes. EVENT Table 2-1 EPIP-AD-02 Rev. AJ Date: JAN 28 2004 Page 9 of 22 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 EMERGENCY CASFCTO CLASSIFICATION CRITERIAl 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 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 UNUSUAL Indicated leakage may be determined using Specifications, requiring reactor EVENT' Reactor Coolant System mass balance shutdown.

calculations performed by SP-36-082.

Table 2-1 EPIP-AD-02 Rev. AJ Date: JAN 28 2004 . Page 10 of 22 REFERENCE USE

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

and Tertiary Aux., are de-energized.

(1) Entry into IPEOP E-3, "Steam Generator Tube generator tube with loss of ALERT Rupture," is expected or has occurred, AND ogenertor t w (2) All three transformers: Main Aux., Reserve Aux., and Tertiary Aux., are de-energized. -_l Rapid failure of multiple steam ALERT (1) Entry into IPEOP E-3, "Steam Generator Tube generator tubes.

o Rupture," is expected or has occurred, AND g t (2) Primary-to-secondary leak rate greater than l 800 GPM indicated by SI flow OR RWST level change. l 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. AJ Date: JAN 28 2004 Page 11 of 22 REFERENCE USE

CHART E LOSS OF POWER EMERGENCY' KNPP INDICATION CLASSIFICATION CLASSIFICATION CRITERIA (1) Buses I through 6 are de-energized including the Failure of off-site and on-site GENERAL D/G supplies to buses 5 and 6, AND AC power, AND EMERGENCY Total loss of auxiliary (2) Loss of the turbine driven AFW pump, 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) 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 />. of power plus loss of all AFW would lead to clad failure and potential containment failure.) l (1) Buses I through 6 are de-energized including the D/G supplies to buses 5 and 6 for longer than Loss of off-site power, AND SITE 15 minutes. EMERGENCY Loss of on-site AC power (for more than 15 minutes). .

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

a. BRA 102 and BRB 102, OR

b. BRA 104 and BRB 104, OR

c. BRA 102 and BRB 104, OR

d. BRB 102 and BRA 104 (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-minutes).

a. BRA 102 and BRB 102, OR

b. BRA 104 and BRB 104, OR

c. BRA 102 and BRB 10.4 OR

d. BRB 102 and BRA 104 (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 Loss of on-site AC power (for respond as designed. AC power is restored to bus less than 15 minutes.)

5 or 6 within 15minutes.

(1) All three transformers: Main Aux., Reserve Aux., and Tertiary are de-energized, OR Loss of off-site power, OR UNUSUAL EVENT Loss of on-site power (2) Both D/Gs unavailable (unable to supply bus 5 or capability.

6 by any means). l (1) Core is unloaded or reactor cavity is flooded with ._I internals removed, AND Loss of off-site power, AND UNUSUAL EVENT Loss of on-site AC power (for (2) Buses 1 through 6 are de-energjzed including the more than 15 minutes).

D/G supplies to buses 5 and 6or longer than 15 minutes.

Table 2-1 EPIP-AD-02 Rev. AJ Date: JAN 28 2004 Page 12 of 22 REFERENCE USE

CHART F .

ENGINEERED SAFETY FEATURE ANOMALY EMERGENCY KNPP INDICATION CLASSIFICATION CLASSIFICATION.

CRITERIA (1) RCS > 2000 F with a loss of cooling capability Complete loss of any function SITE or inventory control: needed when RCS > 2000F. EMERGENCY

a. Sustained loss of negative reactivity control, OR

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

OR

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

d. Sustained loss of RCS inventory control,

-OR

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

(A Site Emergency should be declared upon the initiation of bleed and feed per FR1H. 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 <*2000 F.

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

(1) Failure of both Rx trip breakers to open upon Failure of the Reactor receipt of a valid signal. Applies even if Protection System to initiate IPEOP FR S. I 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 l 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. AJ Date: JAN 28 2004 Page 13 of 22 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, lost and a plant transient initiate EMERGENCY 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. lost.

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

CHART H (DELETED)

Table 2-1 EPIP-AD-02 Rev. AJ Date: JAN 28 2004 Page 14 of 22 REFERENCE USE

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

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

b. CNTMT hydrogen monitor indicates > 1%

hydrogen concentration.

(1) Main steam line break that results in a SI Steam line break with ALERT actuation, AND - significant (greater than.

10 GPM) primary-to-secondary

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

normal, OR (Applies even if events occur in

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

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

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

Table 2-1 EPIP-AD-02 Rev. AJ Date: JAN 28 2004 Page 15 of 22 REFERENCE USE

CHARTJ MISCELLANEOUS ABNORMAL PLANT CONDITIONS Note ChartJ is now a Avo page chart.

KNPP INDICATION EMERGEN CL.

CLASSIFICATION CRITERIA CLASSIFICATION (1) Containment boundary failure or potential Other plant conditions that make a GENERAL failure: release of large amounts'of - EMERGENCY radioactivity in a short time period

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

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

-Failure of main FW and AFW

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

a. Loss of SI and RHR flow, - Transient requiring the

• AND - ' operation systems withof shutdown' a failure of these (3) Failure of shutdown system when required: shutdown systems. In addition, failure of SI and

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

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

Two fission product barriers are lost with the Other plant conditions that make a GENERAL potential or probability of losing the third barrier. release of large amounts of EMERGENCY (At least one verified indication in each category radioactivity in a short'time period below.) possible; e.g., any core melt situation.

Indications:

Examples:

(1) Containment boundary potential failure: -Failure of main FW and AFW systems for greater than

a. Containment pressure > 46 psig, OR 30 minutes without Safety Injection and Residual Heat

b. Loss of all containment fan coil units and' Removal flow. Plus a both trains of ICS, OR containment failure is imminent.

c. Containment hydrogen monitor

> 10% hydrogen concentration. - Transient requiring the operation of shutdown (2) RCS Boundary: systems with a failure of these shutdown systems. In

a. Loss of RHR and SI flow OR addition, failure of SI and

._ R-HR and containment failure

b. LOCA is verified per IPEOP E-1. is imminent.

(3) Fuel Cladding:

a. R-9 > 10 R/hr, OR

b. RCS Chemistry Analysis _

Table 2-1 EPIP-AD-02 Rev. AJ Date: JAN 28 2004 Page 16 of 22 REFERENCE USE

CHART.J MISCELLANEOUS ABNORMAL PLANT CONDITIONS

,' I . ..

~~~EMRGNC KNPP INDICATION EMERGENCY CLASSIFICATION CLASSIFICATION CRITERIA (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 pa 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. I "Response to Loss of Secondary Heat Sink."

Table 2-1 EPIP-AD-02 Rev. AJ Date: JAN 28 2004 Page 17 of 22 REFERENCE USE

CHART K FIRE AND FIRE PROTECTION

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

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

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 minutes. EVENT CHART L (DELETED)

Table 2-1 EPIP-AD-02 Rev. AJ Date: JAN 28 2004 Page 18 of 22 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.

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

(1) Activation of seismic recorder with TRIGGER An earthquake felt in plant 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. -_l (1) A tornado which strikes the facility, AND Any tornado striking facility. ALERT (2) Causes damage that affects the continued safel operation of the plant.

(1) A tornado within sight of the plant which has Any tornado on-site. UNUSUAL caused the loss of at least one of the off-site EVENT transmission lines, OR (2) A tornado observed on-site.

Table 2-1 EPIP-AD-02 Rev. AJ Date: JAN 28 2004 Page 19 of 22 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 PUMPS1 PUMP__2PUMPS CORRESPOND levels.

UMSTO LAKE LEVEL NOTE3 NOTE I 2 94%* > 588 ft.

< 50% NOTE 5 NOTE5 < 568.5 ft.

PR Deep water Wave 2 22.5 ft.

FOREBAY LEVEL 50-year flood, low Indicated for > 15 minutes water level or seiche UNUSUAL CORRESPOND EVENT, OPUMPS 1 PUMP 2 PUMPS TO LAKE LEVEL NOTE2 > 98%* 88%* 586 ft.

< 53.1%

• NOTE*4 NOTE5 < 569.5 ft.

_ __ _ _ _ NOTE4 _ _ _ _ _ _ _

ORB Deep water wave 2 18 ft. (as confirmed by the U.S. Coast Guard, Two Rivers) l 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. AJ Date: JAN 28 2004 Page 20 of 22 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) Astrikesmissile plant buildings, OR Severe damage to safe SITE (1) A. missile strikes plant buildings, OR shutdown equipment from EMERGENCY missiles or explosion.

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

Uncontrolled release of toxic SITE (I) Release of flammable or toxic gas from a ruptured or flammable gas is confirmed EMERGENCYI container which enters a vital area. PortableH within vital grsi .

monitor detects explosive concentration of H2 in vital area.

Aircra'ft crash on'facility. ' -ALERT.

(1) An aircraft crashes into plant buildings OR A r switchyard which affects plant operation.

Missile source on impact from whatever facility- ALERT (1) A missile strikes the facility which affects plant operation. source-onfacility ,

(1) Release of toxic or flammable gas from a ruptured or flaolable gas is confirmed ALERT container such that the gases enter the plant witorflmmbe gasoiscconfirmed.

• protected area or buildings.. .

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

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ o p e ratio n . -_.

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

(2) Unusual aircraft activity such as erratic'flying, dropped unidentified object, or other hostile acts, which threaten the plant or plant personnel. (Any.

other persistent aircraft activity for which I identification attempts through the FAA or other agencies have been unsuccessful.)

Uncontrolled release of toxic UNUSUAL EVENT (I) Release of toxic or flammable gas on site, AND or flammable gas is confirmed on site.

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

Table 2-1 EPIP-AD-02 Rev. AJ Date: JAN 28 2004 Page 21 of 22 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. -_-_l (1) Physical attack on the plant involving Imminent loss of physical SITE imminent occupancy of the control room, control of the plant. EMERGENCY auxiliary shutdown panels, or other vital areas as defined by the Security Plan. I (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 HIlevel CREDIBLE threat as defined in the Security Plan.

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

area of the plant by a hostile force, OR (4) Security safeguards contingency event that results in undetonated bomb found within the protected area.

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

Table 2-1 EPIP-AD-02 Rev. AJ Date: JAN 28 2004 Page 22 of 22 REFERENCE USE

DOCUMENT TRANSMITTAL KEWAUNEE NUCLEAR POWER PLANT FROM: DIANE FENCL - KNPP TRANSMITTAL DATE 01-27-2004 EMERGENCY PLAN IMPLEMENTING PROCEDURES TRANSMITTAL FORM OUTSIDE AGENCY COPIES (1-20) 1~-S.Camipion TNRC Document Control Desk (1)* Krista Kappelman - PBNP - EP (10)*

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

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

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

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

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

J. Bennett (33) R. Johnson (24) P. Sunderland (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. Bradley - CR/SS Office (51, 56)

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

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

C. Grant - OSF (52, 96) W. Galarneau - SBF/EMT (54)

LOREB - STF (62,66,67,68,70,72,73,74) NV. 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)(Partial Distribution) C. Grant - TSC Response Blue Binder (Partial Distribution)

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

NV. Galarneau - SBF/EM Team (110,111, 111A)(Partial Distribution) --C--Grant--TSC4partwlsldibutlon-FOR-r ts ONLY-W'. Flint - Cold Chem/HR Sample Room (113) C. Grant - EOF Response Binder (Partial Distribution)

S. Zutz - SBF/SEC (114) -T-D-Brdley CR-Pesponse~. nder1paroaLDariwn-,tlo E. Gilson - Security (121) -K ;-Stangel---SGR-Response-Binder-artria Distributlon-S. Zutz - Security Building (120) D. Bradley - CR Tag Desk (Partial Distribution) -

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

Iint .HaaI)(P h' "0 r OF & )

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. IT IS A COPY FOR INFORMATION ONLY.

I'-

I

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-27-2004 PROC. NO. l TITLE REV. DATE EP-AD EPIP-AD-01 Personnel Response to the Plant Emergency Siren L 09-09-2003 EPIP-AD-02 Emergency Class Determination Al 12-04-2003 EPIP-AD-03 KNPP Response to an Unusual Event AJ 09-09-2003 EPIP-AD-04 KNPP Response to Alert or Higher AO 09-09-2003 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 Notifications AV 09-09-2003 EP-AD-8 Notification of Alert or Higher Deleted 02-26-96 EP-AD-9 Notification of Site Emergency Deleted 04-27-87 EP-AD-10 Notification of General Emergency Deleted 04-27-87 EPIP-AD-1 1 Emergency Radiation Controls T 01-27-2004 EP-AD-12 Personnel Assembly and Accountability Deleted 03-26-94 EP-AD-13 Personnel Evacuation Deleted 04-25-94 EP-AD-13A Limited Area Evacuation Deleted 03-01-83 EP-AD-13B Emergency Assembly/Evacuation Deleted 03-01-83 EP-AD-13C Site Evacuation Deleted 03-01-83 EP-AD-14 Search and Rescue Deleted 05-25-94 EPIP-AD-15 Recovery Planning and Termination P 09-12-2002 EP-AD-16 Occupational Injuries or Vehicle Accidents Deleted 03-14-97 During Emergencies EP-AD-17 Communications Deleted 03-05-84 EPIP-AD-18 Potassium Iodide Distribution P 02-27-2002 EPIP-AD-19 Determining Protective Action Recommendations T 09-19-2003 PAGE 1 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-27-2004 PROC. NO. TITLE EPIP-AD-20 KNPP Response to a Security Threat EP-ENV EPIP-ENV-01 Environmental Monitoring Group Organization X 07-31-2003 and Responsibilities EPIP-ENV-02 Environmental Monitoring Team Activation Y 07-31-2003 EP-ENV-3A Environmental Protection Director Actions and Deleted 09-26-84 Directives EP-ENV-3B EM Team Actions Deleted 09-26-84 EPIP-ENV-03C Dose Projection Using RASCAL Software X 09-19-2003 EP-ENV-3D Revision and Control of ISODOSE 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 U 07-31-2003 EPIP-ENV-04B Air Sampling and Analysis Y 07-31-2003 EP-ENV-4C Environmental Monitoring Teams Deleted 04-13-90 EPIP-ENV-04C Ground Deposition Sampling and Analysis Y 07-31-2003 EPIP-ENV-04D Plume Tracking for Environmental Monitoring P 07-31-2003 Teams EP-ENV-5A LCS-1 Operation Deleted 04-14-86 EP-ENV-5B MS-3 Operation Deleted 04-14-86 EP-ENV-5C SAM II Operation Deleted 04-14-86 EP-ENV-SD 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: 01-27-2004 PROC. NO. TITLE REV. DATE EP-ENV-6 Data Analysis, Dose Projections and Protective Deleted 12-21-81 Action Recommendations.

EP-ENV-6 Alternate Sample Analysis and Relocation of EM Deleted 04-14-86 Team EP-ENV-6A Relocation of Site Access Facility (Habitability) Deleted 03-23-84 EP-ENV-6B SAF Environmental Sample Analysis Relocation Deleted 03-23-84 EP-ENV-7 Site Access Facility Communications Deleted 09-26-84 EP-ENV-8 Total Population Dose Estimate Calculations Deleted 04-14-86 EP-EOF EP-EOF-1 Corporate Emergency Response Organization Deleted 03-11-94 EPIP-EOF-02 Emergency Operations Facility (EOF) Activation AB 07-31-2003 EPIP-EOF-03 EOF Staff Action for Unusual Event AE 07-31-2003 EPIP-EOF-04 EOF Staff Action for Alert or Higher AL 07-31-2003 EP-EOF-5 Corporate Staff Action for Site Emergency Deleted 04-24-87 EP-EOF-6. Corporate Staff Action for General Emergency Deleted 04-24-87 EP-EOF-7 Notification of Unusual Event Deleted 04-06-94 EP-EOF-8 Relocation of EOF Deleted 03-01-83 EPIP-EOF-08 Continuing Emergency Notifications AA 07-31-2003 EP-EOF-9 Interface with Support Organizations Deleted 03-05-84 EP-EOF-9 Notification of Site Emergency Deleted 04-24-87 EP-EOF-10 Notification of General Emergency Deleted 04-24-87 EPIP-EOF-1 1 Internal Communication and Documentation W 07-31-2003 Flow EPIP-EOF-12 Media Center/Emergency Operation Facility/Joint R 06-19-2003 Public Information Center/Security PAGE 3 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-27-2004 PROC. NO. TITLE REV. DATE EP-OP EP-OP-1 Control Room Emergency Organization Deleted 04-24-87 EP-OP-2 Emergency Control Room Activation for Deleted 04-24-87 Emergency Response EP-OP-3 Control Room Communications Deleted 04-24-87 EP-OSF EP-OSF-1 Operation Support Facility Emergency Deleted 04-24-87 Organization EPIP-OSF-02 Operational Support Facility Operations W 11-04-2003 EPIP-OSF-03 Work Orders During an Emergency P 05-09-2002 EP-OSF-4 Operational Support Facility Communications Deleted 04-24-87 EPIP-OSF-04 Search and Rescue E 05-23-2002 EP-RET EP-RET-1 Radiation Emergency Team Organization Deleted 04-16-96 EPIP-RET-02 In-Plant Radiation Emergency Team X 07-31-2003 EPIP-RET-02A Radiation Protection Office/Radiological Analysis V 11-04-2003 Facility (RPO/RAF) Activation EPIP-RET-02B Gaseous Effluent Release Path, Radioactivity, and T 09-19-2003 Release Rate Determination EP-RET-2C Containment Air Sampling and Analysis Deleted 03-01-83 EPIP-RET-02D Emergency Radiation Entry Controls and M 06-12-2001 Implementation EP-RET-2E Handling of Injured Personnel Deleted 04-16-96 EP-RET-2F Personnel Decontamination Deleted 04-13-90 EPIP-RET-03 Chemistry Emergency Team P 02-18-2003 EPIP-RET-03A Liquid Effluent Release Paths L 11-29-2001 EP-RET-3B Post-Accident Reactor Coolant Alternate Deleted 01-25-88 Sampling Procedure PAGE 4 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-27-2004 PROC. NO. TITLE REV. DATE EPIP-RET-03C Post Accident Operation of the High Radiation P 01-15-2002 Sample Room EPIP-RET-03D Containment Air Sampling Analysis Using CASP N 01-15-2002 EP-RET-3E Post Accident Operation of High Rad Sample Deleted 08-27-85 Room Inline Multiported Count Cave EPIP-RET-04 SBF Activation U 06-19-2003 EP-RET-4A EOF Radiological Monitoring Deleted 03-10-83 EPIP-RET-04A SBF OperationlRelocation Deleted .10-02-2001 EP-RET-4B Radiological Controls at Site Access Facility Deleted 07-12-94 EP-RET-4C Site Radiological Monitoring Deleted 07-12-94 EP-RET-4D SAM-II Operation Deleted 07-12-94 EP-RET-5 Plume Projection Deleted 09-26-84 EPIP-RET-05 Site Boundary Dose Rates During Controlled I 07-31-2003 Plant Cooldown EP-RET-SA Plume Projection Deleted 04-27-87 EP-RET-6 Dose Projection Deleted 04-24-87 EP-RET-7 Radiological Analysis Facility/Radiation Deleted 04-24-87 Protection Office Communications EPIP-RET-08 Contamination Control of the Aurora Medical Deleted 05-23-2002 Center EPIP-RET-09 Post-Accident Population Dose Deleted 09-19-2003 EP-SEC EP-SEC-1 Security Organization Deleted 04-24-87 EPIP-SEC-02 Security Force Response to Emergencies Z 07-31-2003 EP-SEC-2A Manual Activation of Emergency Sirens Deleted 04-16-82 EPIP-SEC-03 Personnel Assembly and Accountability AG 05-20-2003 EPIP-SEC-04 Security Force Actions for Dosimetry Issue P 10-02-2001 PAGE 5 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-27-2004 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 X 05-05-2003 EPIP-TSC-04 Emergency Modifications 0 04-29-2003 EP-TSC-5 Technical Support Center Communications Deleted 04-24-87 Equipment EP-TSC-6 Assessment of Reactor Core Damage Deleted 09-30-86 EPIP-TSC-07 RV Head Venting Time Calculation J 06-20-2002 EPIP-TSC-08A Calculations for Steam Release from Steam P 09-02-2003 Generators EPIP-TSC-08B* STMRLS Computer Program H 07-31-2003 EP-TSC-8C* See EP-TSC-8B Deleted 04-16-92

• EP-TSC-8B was totally deleted; therefore, EP-TSC-8C was changed to EP-TSC-8B EP-TSC-9 Core Damage Assessment Using Released Deleted 09-30-86 Radionuclides EPIP-TSC-09A* Core Damage Assessment K 05-05-2003 EPIP-TSC-09B* CORE Computer Program Deleted 05-16-2002 EP-TSC-9C* See EP-TSC-9B Deleted 04-16-92

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

EPIP-TSC-10 TechnicalSupportforIPEOPs L 07-31-2003 PAGE 6 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-27-2004 FIGURES EPIP l FIG Figure EPIPFG DESCRIPTION REV. DATE EPIP-SEC-05 Technical Support EPIP-APPX-A-06 EP-FIG403 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-09 EOF-12-01 (2nd Floor) Floor Plan C 06-19-2003 State/County Work Area -

EPIP-APPX-A-06 EP.IFIG-012 APPX-A-06-08 WPSC D2-1 Floor Plan C 10-31-2000 NRC Work Area -

EPIP-APPX-A-06 EP-FIG013 APPX-A-06-09 WPSC D24 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-FrG-022 APPX-A-06-04 Floor Plan D 04-29-2003 Location of JPIC and Media Briefing Center EPIP-EOF-12 EPFIGR024 EOF-12-02 Map D 06-19-2003 KNP Site Map &

EPIP-SEC-05 EP-FIG-026 SEC-05-01 Evacuation Routes E 09-19-2003 Floor Plan - Media APPX-A-6 EP-FrG-034 --- 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-039b OSF-02-01 High Priority Work B 07-31-2003 EPIP-OSF-02 EP-FIG-039a OSF-02-02 Lower Priority Work B 07-31-2003 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 EP-FIG-044 APPX-A-06-07 WPSC D2-8 D 04-29-2003 JPIC - Utility Work EPIP-APPX-A-06 EP.rG-04s APPX-A-06-05 Area - WPSC D2-7 D 04-29-2003 Aurora Medical Center RET-08 EP.F1G-O4W 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: 01-27-2004 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: 01-27-2004 FORM 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 C 09-19-2003 AD-07-04 ERO Event Notification Deleted 07-31-2003 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 E 07-31-2003 ENV-01-02 EMT Status C 07-31-2003 ENV-01-03 Meteorological and Plant Status Data C 12-14-2001 ENV-01-04 EMT Orders/Field Data C 07-31-2003 ENV-02-01 EMT Activation Checklist 0 07-31-2003 EP-EOF EOF-02-01 EOF Activation Checklist V 09-19-2003 EOF-02-02 EOF Deactivation Checklist N 01-28-2003 EOF-04-01 SRCL Initial Action Checklist D 01-20-2003 EOF-04-02 Telephone Communications Log Sheet A 12-14-2001 EOF-08-03 Fax for Emergency Declaration or Status Updates H 01-20-2003 EOF-08-05 Plant Emergency Status Report . A 11-27-2001 EOF-08-06 Radiological Status Report E 01-20-2003 EOF-1 1-02 Operating Status G 11-07-2002 PAGE 9 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-27-2004 FORMI 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) E 09-19-2003 RET-02B-02 Auxiliary Building Stack Release (Grab Sample) E 09-19-2003 RET-02B-03 Auxiliary Building Stack Release (Sping Reading) E 09-19-2003 RET-02B-04 Containment Stack Release (Sping Reading) D 09-19-2003 RET-02B-05 Steam Release E 09-19-2003 RET-02B-06 Field Reading (Grab Sample) B 08-06-2002 RET-04-01 SAM-2 Counting Equipment Worksheet E 06-12-2001 RET 8.3 Hospital Survey I Deleted 06-05-2001 RET 8.4 Hospital Survey 2 Deleted 07-25-97 RET 8.5 Hospital Survey 3 Deleted 07-25-97 RET-08-06 Hospital Survey 4 Deleted 05-23-2002 RET-09-01 Post-Accident TLD Record Sheet Deleted- 01-27-2004 EP-SEC SEC-03.01 Emergency Accountability Log A 03-28-2000 SEC-04-01 Emergency Dosimeter Log H 11-04-2003 EP-TSC TSC-01 .01 Plant Status Summary for SAM Implementation 4

TSC-01 .02 Severe Accident Management Summary and Strategy Recommendation PAGE 10 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-27-2004 FORMI EPIPF TITLE REV. DATE TSC-01 -03 Severe Accident Management - Status C 07-31-2003 TSC-02-01 TSC and OSF Activation Checklist P 01-20-2003 TSC-02-02 TSC Ventilation Checklist . 09-19-2003 TSC-02-03 Emergency Response Data System (ERDS) Link Initiation H 01-20-2003 Checklist TSC-02-04 TSC Chart Recorder Operation Checklist E 01-20-2003 TSC-02-05 TSC and OSF De-Activation Checklist C 01-28-2003 TSC-03-01 Plant System Status L 06-12-2001 TSC-03-02 Plant Equipment Status L 06-12-2001 TSC-03-03 Environmental Status Board J 06-12-2001 TSC-03-04 Radiation Monitors I 01-08-2002 TSC-04-01 Emergency Modification Request H 04-29-2003 TSC-04-02 Emergency Physical Change Safety Review Deleted 05-09-2002 TSC-04-03 Emergency Modification Index G 04-29-2003 TSC-07-01 Head Venting Calculation G 06-20-2002 TSC-08A-01 Steam Release Data Sheet (Energy Balance) H 12-14-2001 TSC-08A-02 Steam Release Calculation Sheet (Energy Balance) H 09-02-2003 TSC-08A-03 Steam Release Data/Calculation Sheet (Open Valve) E 12-14-2001 TSC-08A-04 Steam Release Data/Calculation Sheet (STMRLS Program) D 12-14-2001 TSC-09A-01 Core Exit Thermocouple Data D 05-16-2002 TSC-09A-02 Fuel Rod Clad Damage Estimate D 05-16-2002 TSC-09A-03 Fuel Rod Overtemperature Damage Estimate F 11-04-2003 TSC 9A.4 Core Damage Based on Activity Ratios Deleted 05-16-2002 TSC-09A-05 Core Damage Assessment (Monitoring Data) E 05-16-2002 TSC 9A.6 Core Damage Summary Deleted 05-16-2002 TSC-09A-07 Core Damage Assessment Results A 05-05-2003 PAGE 11 OF 11

[ WISCONSIN PUBLIC SERVICE CORP. No. EPIP-AD-I I I Rev. T Title Emergency Radiation Controls Kewaunee Nuclear Power Plant Emergency PlanImplementing Procedure Date JAN 27 2004 Page 1 of 7 Reviewed By Rick Adams Approved By Jerrie Coleman Nuclear O Yes PORC 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 maintaining exposure to emergency workers As Low As Reasonably Achievable (ALARA).

2.0 General Notes 2.1 Definitions 2.1.1 FEMA - Federal Emergency Management Agency 2.1.2 HP - Health Physics 2.1.3 PA - Protected Area 2.1.4 RCA - Radiologically Controlled Area 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 All emergency personnel are responsible for adhering to the requirements of this procedure.

5.1.1 The requirements of the Health Physics Procedures shall be applicable during all radiological emergencies, except as authorized by the Radiological Protection Director (RPD) or Emergency Director (ED).

5.1.2 For RCA entries, if any 10CFR20 dose limit is likely to be exceeded, an "Emergency Radiation Work Permit" (ERWP), Form EPIPF-AD-1 1-01, shall be completed.

Otherwise, use an existing Radiation Work Permit (RWP) or fill out a RWP in accordance with NAD-08.03, "Radiation Work Permit."

J:\appdata'procpws\draft\epip\eadl 1.doc-Amy Kudlck/Amy Kudick-Wayne Galameau REFERENCE USE

5.1.3 A PRIORITY ENTRY can be used for quick action to expedite the entry of emergency response personnel into the RCA in accordance with EPIP-RET-02D, "Emergency Radiation Entry Controls and Implementation" and should NOT exceed 10CFR20 dose limits.

Note Dose extensions beyond OCFR20 limits (see Table before Step 5.2) may be allowed within the dose guidelines specified by EPA-400 (see Table after Step 5.1.4).

5.1.4 For any entry where an exposure greater than 10CFR20 dose limits is likely, an Authorization For Increased Radiation Exposure (Form HPF-120) shall be completed in accordance with NAD-01.11, "Dosimetry and Personnel Monitoring." All exposures which could exceed 10CFR20 dose limits shall be approved by the ED.

IOCFR20 RADIATION DOSE LIMITS TEDE, ADULT ANNUAL 5 REM TODE, ADULT ANNUAL 50 REM LDE, ADULT ANNUAL 15 REM SDE, SKIN, ADULT ANNUAL 50 REM SDE, EXTREMITY, ADULT ANNUAL 50 REM DAC-HOUR, ADULT ANNUAL 2,000 DAC-HOURS REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-AD-11 Rev. T Title Emergency Radiation Controls Kewaunee Nuclear Power Plant Emergency Plan Implementing Procedure Date JAN 27 2004 Page 3 of 7 EPA RADIATION DOSE GUIDELINES (EPA-400)

Projected Dose (rem) to Action/Condition Comments Emergency Team Workers TEDE < 5 rem Control exposure of emergency workers to "All Other Organs" include:

these levels except for those instances listed Skin Extremities and Thyroid.

All Other Organs below. (Appropriate controls for emergency

< 50 rem TODE workers include time limitations, respirators, Stable iodine may be made and stable iodine.) available for use where predicted doses exceed 25 rem TEDE < 10 rem to the thyroid. Although Emergency workers' exposure should be respirators and stable iodine All Other Organs controlled below these levels when their should be used where effective

< 100 rem TODE mission involves protecting valuable property. to control dose to emergency I_________________ I____________________________

team workers, thyroid dose TEDE < 25 rem Emergency workers' exposure should be may not be a limiting factor controlled below these levels when their l All Other Organs mission involves life saving or protection of For Environmental/Monitoring

< 250 rem TODE large populations. Teams, refer to RASCAL "Maximum Doses at Selected TEDE > 25 rem Exposures above these levels to emergency Distances" output screen.

workers will be on a voluntary basis only to Check bone, lung, and thyroid All Other Organs persons fully aware of the risks involved. doses.

> 250 rem TODE 5.1.5 Understand the risks and benefits of taking Potassium Iodide (KI) orally when radioactive iodine levels warrant taking KI.

5.2 The Emergency Director (ED) is responsible for approving all requests for exposure in excess of 10CFR20 dose limits and the distribution of Potassium Iodide.

5.3 The Radiological Protection Director (RPD) has the overall responsibility for in-plant personnel monitoring and shall:

5.3.1 Ensure that personnel within the protected area are issued the appropriate dosimetry.

REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-AD-1I IRev. T ucler Poer PantTitle Kewanee Emergency Radiation Controls Kewaunee Nuclear Power Plant Emergency Plait Implementing Procedure Date JAN 27 2004 Page 4 of 7 5.3.2 Evaluate any potential exposure to radiation in excess of 10CFR20 dose limits for approval by the ED (Form HPF-110) in accordance with HP-05.001, "Survey and Sampling Techniques." In the absence of the RPD, the ED may authorize an overexposure after concurrence of the on-shift HP or an In-plant Radiation Emergency Team (IRET) member.

5.3.3 In accordance with EPIP-AD-18, "Potassium Iodide Distribution," advise the ED on the need to make thyroid blocking agent (Potassium Iodide, a stable iodine) available to Emergency Response Organization (ERO) members who may be subject to radioiodine intake.

5.3.4 Review all RWPs and ERWPs in use.

5.3.5 Establish control over radiation, high radiation or contamination areas discovered outside the normal RCA when levels are found to exceed the following:

• 2 mr/hr Direct Radiation

• 2,000 DPM/100 cm2 Beta-Gamma

• 200 DPM/100 cm 2 Alpha 5.3.5.1 This control may include:

a. Roping off and posting additional areas within the plant

b. Roping off and posting all doors to an entire building

c. Designating and posting the entire PA as RCA

d. Establishing roadblocks in conjunction with the ED and Site Protection Director (SPD), and designating the entire area within the roadblocks as RCA Note Emergency responsepersonnel reporting to the plant shall NOT be requiredto initial theirR WP priorto RCA entry when the RCA is expanded. 7he RWP shall be initialed priorto making entries at the Radiation Protection Office (RPO) or Radiological Access Facility(RAF). See Step 5.1, for Emergency RWVP (ERIWP) requirements.

5.4 The In-Plant Radiation Emergency Team (IRET) is responsible for performing those activities necessary to implement the purpose of this procedure.

5.4.1 Make radiological assessments of all in-plant areas requiring access during an emergency.

5.4.2 Report in-plant radiological conditions to the RPD.

REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-AD- I Rev. T Title Emergency Radiation Controls Kewaunee Nuclear Power Plant J 2 Emergency Plan Implementing Procedure Date JAN 27 2004 l Page 5 of 7 5.4.3 Determine the projected amount of time in-plant emergency workers will be allowed to remain in any radiation/contaminated area through pre-entry review of:

a. Projected route exposures

b. Measured dose rates and airborne concentrations

c. Personnel exposure history

d. Projected duration of task

e. Information on current plant conditions and the plant area under consideration 5.4.4 Provide radiation monitoring coverage for all continuously occupied areas.

5.4.5 Perform air sample surveys and direct radiation surveys as directed.

5.4.6 Control exposure to airborne radionuclides in accordance with the following:

a. Use only Self-Contained Breathing Apparatus (SCBA) pressure demand respirators when entering areas of unknown airborne concentrations.

b. Limit airborne particulate exposures to < 200 DAC-HOURS to the maximum extent possible.

c. Remove any worker from further emergency duties upon exceeding 2,000 DAC-HOURS.

d. Assess internal dose by performing whole body counts in accordance with procedure HP-03.008, "Evaluation of Inhalations or Ingestions."

Note For entry teams originatingfrom the OperationalSupport Facility(OSF),

document thze items below (Steps 5.4.7.a. through Step 5.4.7.Ih.) on Form EPIPF-OSF-03-01.

5.4.7 Review all planned entries with the entry team members and discuss the following:

a. Potential stress conditions and problems

b. Work methods, work location, and description of task

c. Number of personnel required and access routes inside the RCA

d. Allowable exposure limits, expected doses, stay times

e. Tools, equipment, and parts

f. Lighting

g. Communications requirements

h. Abort instructions REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-AD-11 Rev. T Title Emergency Radiation Controls Kewaunee Nuclear Power Plant Emergency Plan Implemenzting Procedure Date JAN 27 2004 Page 6 of 7 5.4.8 As directed, accompany any worker entering an area where radiological conditions are unknown.

5.4.9 Remove any individual who has exceeded IOCFR20 dose limits from work involving additional radiation exposure. The worker's exposure record shall be reviewed by the RPD and ED prior to further radiation work. Any further radiation work must be authorized by the ED.

5.4.10 As directed, store samples collected post accident in designated storage locations.

Liquid, air particulate, and halogen filter samples should be stored in the radioactive waste storage areas of the Auxiliary Building.

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 Kewaunee Nuclear Power Plant Emergency Plan 7.2 NUREG-0654/FEMA-REP-1, REV. 1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants (Nov. 1980) 7.3 EPA-400-R-92-001, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (Oct. 1991) 7.4 10CFR20, Standards for Protection Against Radiation 7.5 Kewaunee Nuclear Power Plant Health Physics Procedure Manual 7.6 KNPP Commitment Tracking System number 97-125, NRC Inspection Report 97-13, Repair Personnel 7.7 Implementing Procedures 7.7.1 EPIP-RET-02D, Emergency Radiation Entry Controls and Implementation 7.7.2 NAD-08.03, Radiation Work Permit 7.7.3 EPIP-AD-18, Potassium Iodide Distribution 7.7.4 EPIP Appendix B, Forms 7.7.5 HP-03.008, Evaluation of Inhalations or Ingestions REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-AD-1 1 Rev. T

.Title Emergency Radiation Controls Kewaunee Nuclear Power Plant Emergency Plan Implementing Procedure Date JAN 27 2004 l Page 7 of 7 7.7.6 NAD-01.11, Dosimetry and Personnel Monitoring 7.7.7 HP-05.001, Survey and Sampling Techniques 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 Emergency Radiation Work Permit, Form EPIPF-AD-11-01 8.1.2 Non-OA Records None REFERENCE USE