ML022130477

Transmittal of Revisions to Kewaunee Nuclear Power Plant Radiological Emergency Response Plan Implementing Procedures EPIP-AD-02 (Rev AD) & EPIP-SEC-03 (Rev Ae)

ML022130477
Person / Time
Site:	Kewaunee
Issue date:	07/24/2002
From:	Webb T Nuclear Management Co
To:	Document Control Desk, Office of Nuclear Security and Incident Response
References
NRC-02-068
Download: ML022130477 (58)

Text

Kewaunee Nuclear Power Plant N490 Highway 42 Kewaunee, WI 54216-9511 920.388.2560 Point Beach Nuclear Plant 6610 Nuclear Road Two Rivers, Wl 54241 920.755.2321 Kewaunee / Point Beach Nuclear Operated by Nuclear Management Company, LLC NRC-02-068 July 24, 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.

Committed to Nuclear Excellence

DOCUMENT TRANSMITTAL KEWAUNEE NUCLEAR POWER PLANT FROM:

DIANE FENCL - KNPP TRANSMITTAL DATE 07-19-2002 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 1I (2, 3)*

Craig Weiss - Alliant Energy (11)*

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

T. Webb - State of Wisconsin (5)*

Jill Stern - Nuclear Management Company (12)*

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

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

J. Bennett (33)

D. Seebart (24)

J. Ferris (13)

T. Coutu (28)

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

NO Library - KNPP (59)

C. Sternitzky - ATF-2 (44)

M. Daron - Security Building (46)

M. Lambert - EOF (81)

M. Lambert - OSF (52)

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

STF Library (43)

Resource Center - Training (82)

D. Krall - CR/SS Office (51, 56)

M. Lambert - TSC (50)

W. Galarneau - RAF (53)

W. Galarneau - SBF/EMT (54)

W. Galarneau - RPO (55)

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)

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

W. Galarneau - SBF/EM Team (110, 111, lllA)

W. Flint - Cold Chem/HR Sample Room (113)

M. Kuether - SBF/SEC (114)

D. Krall - CR/Communicator (116)(Prtial Dstribudon)

Simulator/Communicator (117)

M. Fend - Security (121)

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. IT IS A COPY FOR INFORMATION ONLY.

I

KEWAUNEE NUCLEAR POWER PLANT REVISION OF EMERGENCY PLAN IMPLEMENTING PROCEDURES July 19, 2002 Please follow the directions listed below. If you have.ny questions regarding changes made to the EPIPs, please contact Dave Seebart at ext. 8719.

EPIP Index, dated 07-19-2002.

'Retum a signed anddated copy-of this tiansmittal letter, within 10days of transmittal date, to the sender. Ifyou have any questions 'or comments, please contact Dave Seebart at ext. 8719.

Diane Fencl Enclosure 2

REMOVE INSERT PROCEDURE REV.

PROCEDURE REV.

EPIP-AD-02 AC EPIP-AD-02 AD EPIP-SEC-03 AD EPIP-SEC-03 AE i -

i I CERTIFY Copy No._

((WPSC No.) of the Kewaunce Nuclear Power Plant's EPIPs has been updated.

SIGNATURE DATE Please return this sheet to DIANE FENCL.

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 07-19-2002 PROC. NO.

TITLE REV.

DATE EP-AD EPIP-AD-01 Personnel Response to the Plant Emergency J

01-08-2002 Siren EPIP-AD-02 Emergency Class Determination AD 07-19-2002 EPIP-AD-03 KNPP Response to an Unusual Event AF 06-20-2002 EPIP-AD-04 KNPP Response to Alert or Higher AJ 06-20-2002 EP-AD-5 Site Emergency Deleted 04-27-87 EPIP-AD-05 Emergency Response Organization Shift Relief D

05-09-2002 Guideline EP-AD-6 General Emergency Deleted 04-24-87 EPIP-AD-07 Initial Emergency Notifications AR 06-20-2002 EP-AD-8 Notification of Alert or Higher Deleted 02-26-96 EP-AD-9 Notification of Site Emergency Deleted 04-27-87 EP-AD-10 Notification of General Emergency Deleted 04-27-87 EPIP-AD-11 Emergency Radiation Controls R

04-11-2002 EP-AD-12 Personnel Assembly and Accountability Deleted 03-26-94 EP-AD-13 Personnel Evacuation Deleted 04-25-94 EP-AD-13A Limited Area Evacuation Deleted 03-01-83 EP-AD-13 B Emergency Assembly/Evacuation Deleted 03-01-83 EP-AD-13C Site Evacuation Deleted 03-01-83 EP-AD-14 Search and Rescue Deleted 05-25-94 EPIP-AD-15 Recovery Planning and Termination 0

10-30-2001 EP-AD-16 Occupational Injuries or Vehicle Accidents Deleted 03-14-97 During Emergencies EP-AD-17 Communications Deleted 03-05-84 EPIP-AD-18 Potassium Iodide Distribution P

02-27-2002 EPIP-AD-19 Protective Action Guidelines Q

11-27-2001 PAGE 1 OF 11 4

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 07-19-2002 PROC. NO.

TITLE REV.

DATE EPIP-AD-20 KNPP Response to a Security Threat C

05-23-2002 "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 4

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 07-19-2002 PROC. NO.

TITLE REV.

DATE EP-ENV-6 Data Analysis, Dose Projections and Protective Deleted 12-21-81 Action Recommendations EP-ENV-6 Alternate Sample Analysis and Relocation of Deleted 04-14-86 EM Team EP-ENV-6A Relocation of Site Access Facility (Habitability)

Deleted 03-23-84 EP-ENV-6B SAF Environmental Sample Analysis Relocation Deleted 03-23-84 EP-ENV-7 Site Access Facility Communications Deleted 09-26-84 EP-ENV-8 Total Population Dose Estimate Calculations Deleted 04-14-86 EP-EOF EP-EOF-1 Corporate Emergency Response Organization Deleted 03-11-94 EPIP-EOF-02 Emergency Operations Facility (EOF) Activation 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 Al 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 X

06-20-2002 EP-EOF-9 Interface with Support Organizations Deleted 03-05-84 EP-EOF-9 Notification of Site Emergency Deleted 04-24-87 EP-EOF-10 Notification of General Emergency Deleted 04-24-87 EPIP-EOF-1 I Internal Communication and Documentation U

11-15-2001 Flow EPIP-EOF-12 Media Center/Emergency Operation Q

06-20-2002 Facility/Joint Public Information Center Security PAGE 3 OF 11 4

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 07-19-2002 PROC. NO.

TITLE REV.

DATE EP-OP EP-OP-1 Control Room Emergency Organization Deleted 04-24-87 EP-OP-2 Emergency Control Room Activation for Deleted 04-24-87 Emergency Response EP-OP-3 Control Room Communications Deleted 04-24-87 EP-OSF EP-OSF-1 Operation Support Facility Emergency Deleted 04-24-87 Organization EPIP-OSF-02 Operational Support Facility Operations U

02-06-2002 EPEP-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-I Radiation Emergency Team Organization Deleted 04-16-96 EPIP-RET-02 In-Plant Radiation Emergency Team V

05-23-2002 EPIP-RET-02A Radiation Protection Office/Radiological T

11-29-2001 Analysis Facility (RPO/RAF) Activation EPIP-RET-02B Gaseous Effluent 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 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 In

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 07-19-2002 PROC. NO.

TITLE REV.

DATE EPIP-RET-03C Post Accident Operation of the High Radiation P

01-15-2002 Sample Room EPIP-RET-03D Containment Air Sampling Analysis Using N

01-15-2002 CASP EP-RET-3E Post Accident Operation of High Rad Sample Deleted 08-27-85 Room Inline Multiported Count Cave EPIP-RET-04 SBF Activation S

06-20-2002 EP-RET-4A EOF Radiological Monitoring Deleted 03-10-83 EPIP-RET-04A SBF Operation/Relocation Deleted 10-02-2001 EP-RET-4B Radiological Controls at Site Access Facility Deleted 07-12-94 EP-RET-4C Site Radiological Monitoring Deleted 07-12-94 EP-RET-4D SAM-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-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 L

04-16-2002 EP-SEC EP-SEC-1 Security Organization Deleted 04-24-87 EPIP-SEC-02 Security Force Response to Emergencies X

02-06-2002 EP-SEC-2A Manual Activation of Emergency Sirens Deleted 04-16-82 EPIP-SEC-03 Personnel Assembly and Accountability AE 07-19-2002 EPIP-SEC-04 Security Force Actions for Dosimetry Issue P

10-02-2001 PAGE 5 OF 11 41

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 07-19-2002 PROC. NO.

TITLE REV.

DATE EP-SEC-5 Security Force Response to the EOF Deleted 07-28-88 EPIP-SEC-05 Personnel Evacuation G

06-20-2002 EP-TSC EPIP-TSC-0 1 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 J

06-20-2002 EPIP-TSC-08A Calculations for Steam Release from Steam N

12-14-2001 Generators EPIP-TSC-08B*

STMRLS Computer Program G

06-20-2002 EP-TSC-8C*

See EP-TSC-8B Deleted 04-16-92

• EP-TSC-8B was totally deleted; therefore, EP-TSC-8C was changed to EP-TSC-8B EP-TSC-9 Core Damage Assessment Using Released Deleted 09-30-86 Radionuclides EPIP-TSC-09A*

Core Damage Assessment J

05-16-2002 EP1P-TSC-09B*

CORE Computer Program Deleted 05-16-2002 EP-TSC-9C*

See EP-TSC-9B Deleted 04-16-92

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

EPIP-TSC-10 Technical Support for IPEOPs K

05-09-2002 PAGE 6 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 07-19-2002 FIGURES EPIP FIG #

Figure EPIPFG DESCRIPTION REV.

DATE EP-SEC-5 Technical Support EPIP-APPX-A-06 EP-FIG-003 APPX-A-06-03 Center - KNP Floor Plan B

06-12-2001 Site Boundary Facility EPIP-APPX-A-06 EP-FIG-005 APPX-A-06-02 KNIP Floor Plan A

10-31-2000 Radiological Analysis Facility - K.NP Floor EPIP-APPX-A-06 EP-FIG-OOS 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 Location of JPIC and Media Briefing Center EPIP-EOF-12 EP-FIG-024 EOF-12-02 Map C

06-20-2002 KNP Site Map &

EP-SEC-5 EP-FIG-026 SEC-05-01 Evacuation Routes C

06-20-2002 Floor Plan - Media APPX-A-6 EP-FIG-034 Briefing Center Deleted 08-04-98 General Office EPIP-EOF-12 Building - WPSC (1 st 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-038 Floor Plan - JPIC Deleted 08-04-98 EPIP-OSF-02 EP-FIG-039 OSF-02-01 High Priority Work A

10-02-2001 EPIP-OSF-02 EP-FIG-039A OSF-02-02 Lower Priority Work A

10-02-2001 JPIC - Federal Work EPIP-APPX-A-06 EP-FIG-043 APPX-A-06-10 Area - WPSC D2-9 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-45 APPX-A-06-05 Area - WPSC D2-7 C

12-21-2001 Aurora Medical Center RET-08 EP-FIG-046 RET-08-01 Location Deleted 05-23-2002 EPIP-APPX-A-02 APPX-A-02-01 ERO Call Tree Deleted 12-04-2001 PAGE 7 OF 11 4

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 07-19-2002 14 PAGE 8 OF 11 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

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 07-19-2002 FORUM EPIPF TITLE REV.

DATE APPENDIX B EP-AD AD-07-01 Event Notice (Wisconsin Nuclear Accident Reporting Form)

S 05-23-2002 AD-07-02 State Call-Back - Question Guideline C

11-15-2001 AD-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-0 1-01 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-0 1-04 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-1 1-02 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

-4

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 07-19-2002 FORM EPIPF TITLE REV.

DATE EP-OSF OSF 2.2 Maintenance Workin 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 RET 8.3 Hospital Survey I Deleted 06-05-2001 RET 8.4 Hospital Survey 2 Deleted 07-25-97 RET 8.5 Hospital Survey 3 Deleted 07-25-97 RET-08-06 Hospital Survey 4 Deleted 05-23-2002 RET-09-01 Post-Accident TLD Record Sheet D

04-16-2002 EP-SEC SEC-03.01 Emergency Accountability Log A

03-28-2000 SEC-04-01 Emergency Dosimeter Log G

06-20-2002 EP-TSC TSC-0 1.01 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-0 1.03 Severe Accident Management - Status B

02-06-2002 TSC-02-01 TSC and OSF Activation Checklist 0

09-27-2001 PAGE 10 OF 11 4

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 07-19-2002 FOR.M 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 1

01-08-2002 TSC-04-01 Emergency Physical Change Request G

05-09-2002 TSC-04-02 Emergency Physical Change Safety Review Deleted 05-09-2002 TSC-04-03 Emergency Physical Change Index F

08-29-2000 TSC-07-01 Head Venting Calculation G

06-20-2002 TSC-08A-01 Steam Release Data Sheet (Energy Balance)

H 12-14-2001 TSC-08A-02 Steam Release Calculation Sheet (Energy Balance)

G 12-14-2001 TSC-08A-03 Steam Release Data/Calculation Sheet (Open Valve)

E 12-14-2001 TSC-08A-04 Steam Release Data/Calculation Sheet (STMRLS D

12-14-2001 Program)

TSC-09A-01 Core Exit Thermocouple Data D

05-16-2002 TSC-09A-02 Fuel Rod Clad Damage Estimate D

05-16-2002 TSC-09A-03 Fuel Rod Overtemperature Damage Estimate E

05-16-2002 TSC 9A.4 Core Damage Based on Activity Ratios Deleted 05-16-2002 TSC-09A-05 Core Damage Assessment (Monitoring Data)

E 05-16-2002 TSC 9A.6 Core Damage Summary Deleted 05-16-2002 PAGE 11 OF 11 4

WISCONSIN PUBLIC SERVICE CORP.

No.

EPIP-AD-02 JRev.

AD Title Emergency Class Determination Kewaunee Nuclear Power Plant Emergency Plan Implementing Procedure Date JUL 19 2002 Page 1 of 21 Reviewed By Dave Lohman Approved By William Yarosz Nuclear 0Ys PORC0 S.'RO Approval Of Ye Safety 0 Yes Review Temporary Yes Related 0 No Required 0 No Changes Required 0 No 1.0 Purpose 1.1 This procedure provides instruction for determining proper emergency classification listed in order to activate the appropriate level of response from the Kewaunee Nuclear Power Plant (KNPP) emergency response organization and off-site response organization.

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

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

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

"* Plant Trip

"* SI Initiation

"* Entry into an orange or red path

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

n:\\nucdoc\\procedures\\draftxepip\\ead02.doc-Diane Fend/Diane Fend--Jeanne Ferris REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP.

No.

EPIP-AD-02 Rev.

AD Title Emergency Class Determination Kewaunee Nuclear Power Plant Emergency Plan Implementing Procedure Date JUL 19 2002 Page 2 of 21 4.0 Initial Conditions 4.1 This procedure applies during any plant evolution that may result in an emergency declaration.

5.0 Procedure 5.1 Determine if a plant emergency exists during abnormal plant conditions by referring to Table 2-1, Emergency Action Level Charts.

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

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

5.4 Determine if the emergency should be reclassified.

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

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

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

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

REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP.

No.

EPIP-AD-02 TRev.

AD Title Emergency Class Determination Kewaunee Nuclear Power Plant Emergency Plan Implementing Procedure Date JUL 19 2002 Page 3 of 21 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 NUTREG-0654 8.0 Records 8.1 The following QA records and non-QA records are identified in this directive/procedure and are listed on the KNPP Records Retention Schedule. These records shall be maintained according to the KNPP Records Management Program.

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

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

CHART PAGE Abnormal Radiological Effluent A (1) 5 Gaseous Effluent Action Levels A (2) 6-8 Fuel Damage Indication B

9 Primary Leak to LOCA C

10 Primary to Secondary Leak D

11 Loss of Power E

12 Engineered Safety Feature Anomaly F

13 Loss of Indication G

14 DELETED H

14 Secondary Side Anomaly I

15 Miscellaneous Abnormal Plant Conditions J

16 Fire and Fire Protection K

17 DELETED L

17 Earthquake M

18 High Winds or Tornado N

18 Flood, Low Water, or Seiche 0

19 External Events and Chemical Spills P

20 Security Contingency Q

21 Table 2-1 EPIP-AD-02 Rev. AD Date: JUL 19 2002 Page 4 of 21 REFERENCE USE

CHART A(1)

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

Projected or measured dose rates to be provided Projected or measured in the environs by the Radiological Protection Director or dose rates greater than 1 rem/hr whole GENERAL Environmental Monitoring Teams.

body or 5 rem/hr thyroid at the site EMERGENCY boundary.

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

At the site boundary, projected or measured dose rates greater than 50 Projected or measured dose rates to be provided mr/hr for 1/2 hours OR greater than 500 by the Radiological Protection Director or mr/hr for two minutes (or five times SITE EMERGENCY Environmental Monitoring Teams.

these levels to the thyroid) or EPA PAGs are projected to be exceeded outside the site boundary.

SEE CHART A(2)

Radiological effluents greater than 10 ALERT times ODCM instantaneous limits.

a.

Containment R-2 OR R-7 _> I.OE+4 mr/hr, OR Radiation levels or airborne

b.

Charging Area R-4 _> 1.OE+4 mr/hr, OR contamination which indicate a severe degradation in the control of ALERT

c.

SFP Area R-5 > 1.0E+4 mr/hr, OR radioactive materials (e.g., radiation 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)

Offsite Dose Calculation Manual limits UNUSUAL EVENT (2)

Liquid Releases: Notification by the exceeded.

Rad-Chem Group of violating ODCM 3.3.1 limits.

Table 2-1 EPIP-AD-02 Rev. AD Date: JUL 19 2002 Page 5 of 21 REFERENCE USE

CHART A(2)

GASEOUS EFFLUENT ACTION LEVELS

1.

AUX BUILDING VENT RELEASES - WITH SIGNIFICANT CORE DAMAGE Instrument readings assuming a post accident gas release AND Containment High Range Radiation Monitors 42599 (R-40) and 42600 (R-41) reads 1000 R/hr 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 EMERG.

FANS CLASS.

MID RANGE HIGH RANGE R-36 CPM (01-07)

CPM (01-09)

R-35 R-HR PPCS PT G9086G PPCS PT G9088G MR/HR

[TOTAL AVG ADV AVG METADV ME NUMBER AVG MET ADV MET AVG MET ADV MET ET ET AVG MET ADV MET RUNN ING 1

I.IE+4 6.5E+I 7.9E-,-2 1.27E+2 7.9E-1 2

8.8E+5 5.5E+3 3.25E+1 3.9E+2 6.35E+1 4.OE-I GENERAL 3

5.9E+5 3.7E+3 2.16E+1 2.6E+2 4.2E+1 2.6E-I EMERG.

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

8.8E+4 5.5E+2 3.OE+O 6.3E+3 3.9E+1 6.3E+O 2

4.4E+4 2.7E+2 1.5E+O

3. 1E+3 I.9E+I 3.1E+O SITE 3

2.9E+4 I.8E+2 I.OE+O

2. i E+3 1.3E+1 2.1E+O EMERG.

4 2.2E+4 1.3E+2 1.5E+3 9.5E+O I.5E+0 I

I.OE+3 6.2E+O 7.0E+1 2

5.OE+2 3.1E+O 3.5E+1 ALERT 3

3.3E+2 2.OE+O 2.3E+I 4

2.5E+2 1.5E+O I.75E+I I

1.OE+2 6.2E-1 7.OE+0 2

5.0E+I 3.IE-I 3.5E+O UNUSUAL 3

3.3E+1 2.OE-1 2.3E+O

• EVENT 4

2.5E+1 I1.5E-I 1.7E+O Offscale Low

• • Offscale High (Confirmation Only)

Table 2-1 EPIP-AD-02 Rev. AD Date: JUL 19 2002 REFERENCE USE Page a oWTIz

CHART A(2)

GASEOUS EFFLUENT ACTION LEVELS continued

2.

AUX BUILDING VENT RELEASES WITHOUT CORE DAMAGE NOTE:

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

NOTE:

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

SV SFPEMERG.

SV & SFP AUX BLDG SPING MONITORS CLASS.

FANS CAS MID RANGE HIGH RANGE TOTAL CPM (01-07)

CPM (01-09)

NUMBER PPCS PT G9086G PPCS PT G9088G RUNNING AVG MET ADV MET AVG MET ADV MET 1

9.4E-4 1.6E+4 1.OE+2 2

4.7E+4 8.0E-3 5.0E+1 GENERAL 3

3.1 E+4 5.3E+3 3.3E+1 EMERG.

4 2.3E+4 4.OE+3 2.5+1 1

7.5E+5 4.6E+3 8.OE+2 5.OE+O 2

3.7E+5 2.3E+3 4.OE+2 2.5E+O SITE 3

2.5E+5 1.5+3 2.6E+2 1.6E+0 EMERG.

4 1.8E+5 L.IE+3 2.OE+2 1.2E+O SV & SFP AUX BLDG SPING MONITORS FANS EMERG.

TOTAL LOW RANGE MID RANGE CLASS.

NUMBER Ci/cc (01-05)

CPM (01-07)

RUNNING PPCS PT G9084G PPCS PT 9086G 1**

8.6E+3 2**

4.3E+3 ALERT 3**

2.8E+3 4**

2.1E+3 1

6.3E-2 8.6E+2 2

3.1E-2 4.3 E+2 UNUSUAL EVENT 3

2.1E-2 2.8E+2 4

1.5E-2 2.1E+2

• • Offscale High (Confirmation Only) fIt /

f 1

Table 2-1 EPIP-AD-02 Rev. AD REFERENCE USE V~*=*

Date: JUL *1V UUZ

CHART A(2)

GASEOUS EFFLUENT ACTION LEVELS continued

3.

STEAM LINE RELEASE WITH SIGNIFICANT CORE DAMAGE Instrument readings assuming radioactive steam is releasing at a total of 1.4E+5 Rounds per hour to the atmosphere AND Containment High Range Radiation Monitor 42599 (R-40) or 42600 (R-41) reads 1000 R/hr within one-half hour of the accident.

"A" "B"

Steam Line Monitors Steam Line Monitors Emergency Classification R-15 R-31 R-32 R-33 R-34 (cpm)

(mR/hr)

(R/hr)

(mR/hr)

(R/hr) 1.3E+3 1.3E+0 1.3E+03 1.3E+0 General Emergency 6.0E+1 6.OE+ 1 Site Emergency 1.5E-1 1.5E-1 Alert 2.OE+05 Unusual Event Offscale High (Confirmation Only)

4.

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

Reactor Bldg. Discharge Vent SPING Emergency Classification PPCS PT G9077G PPCS PT G9079G (02-07)

(02-09)

Mid Range (cpm)

High Range (cpm) 1.3E+05 1.5E+2 General Emergency 6.7E+03 7.OE+0 Site Emergency 1.5E+1 Alert Unusual Event Table 2-1 EPIP-AD-02 Rev. AD Page 8 of 21 Date: JUL 19 2002 REFERENCE USE

CHART B FUEL DAMAGE INDICATION EMERGENCY K.NPP INDICATION CLASSIFICATION CLASSIFICATION CRITERIA (1)

CET > 1,200 Degrees for greater than 15 minutes, OR (2)

R40 or R41 > 1,000 r/lr, OR (3)

SACRG-1, Severe Accident Control Room Guideline Initial Response has been implemented.

(Major damage is more than one spent fuel element

'araged.)

(1)

Fuel Handling accident in Containment

a.

Alarm on R-l1 OR R-1 2, AND

b.

Dropped spent fuel assembly, O.R

c.

Re ort of a large object dropped ir O l Rx core, (2)

Fuel Handling Accident in Auxiliary Bldg.

a.

Alarm on R-13 or R-14, AND

b.

A large object dropped in spent fuel pool, OR

c.

A dropped spent fuel assembly, OR

d.

A loss of water level below spent fuel.

(1)

R-9 indication is offscale high, AND (2)

Laboratory analysis confirms RCS activity levels comparable to USAR Appendix D, Table D.4-1.

Plant conditions exist that make the release of large amounts of radioactivity m a short time period possible.

Major damage to spent fuel in containment or auxiliary building.

Severe loss of fuel cladding

a. Very high coolant activity sample

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

GENERAL EMERGENCY SITE EMERGENCY ALERT (1) Fuel Handling Accident in Containment Fuel damage accident with release ALERI

a.

A confirming report, AND of radioactivity to containment or

b.

Alarm on R-11 OR R-12, OR auxiliary building.

(2)

Fuel Handling Accident in Auxiliary Bldg.

a.

A confirming report, AND

b.

Alarm on R-13 OR R-14.

(1) With RCS Temperature > 500F,

a.

> 0.2 p.Ci/gram DOSE Equivalent 1-131 for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, O.R

b.

Exceeding T.S. Figure 3.1-3 for Dose Equivalent 1-131, QB.

c.

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

(1)

R-9 is greater than 5.0 R/hr, AND (2)

Verified by RCS chemistry sample analysis.

High reactor coolant activity sample.

Failed fuel monitor indicates greater than 0. 1% equivalent fuel failures within 30 minutes.

UNUSUAL EVENT UNUSUAL EVENT

• .

dff-

Pane9of2l uare: JUL I Luu

REFERENCE USE Table 2-1 EPIP-AD-02 Rev. AD Pane 9 of 21 Date: JUL I U uue I

I

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 CLASSIFCATION CLASSIFICATION CRITERIA (1) LOCA is verified per IPEOP E-l, "Loss of (1) Loss of coolant accident, GENERAL R-actor 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.

Reactor Coolant System leakage SITE (1) SI System is activated and RCS leakage greater than make-up pump EMERGENCY exceeds charging system capacity as verified capacity.

by Control Room indications or IPEOPs.

(1) Charging flow verses letdown flow indicates Reactor Coolant System leak rate ALERT an unisolable RCS leak > 50 gpm.

greater than 50 GPM.

Exceeding Reactor Coolant UNUSUAL (1) Initiation of reactor shutdown required by System leak rate, Technical EVENT Technical Specification, Section T.S. 3.1.d.

Sfpecifications, requiring reactor Indicated leakage may be determined using shutdown.

Reactor Coolant System mass balance calculations performed by SP-36-082.

Table 2-1 EPIP-AD-02 Rev. AD Date: JUL 19 2002 Page 10 of 21 REFERENCE USE

CHART D PRIMARY TO SECONDARY LEAK Table 2-1 EPIP-AD-02 Rev. AD Date: JUL 19 2002 44~

II 1K L

REFERENCE USE 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.

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

(2)

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

Rapid failure of multiple steam ALERT (1) Entry into IPEOP E-3, "Steam Generator Tube generator tubes.

Rupture," is expected or has occurred, AND (2)

Primary-to-secondary leak rate greater than 800 GPM indicated by SI flow OR RWST level change.

UNUSUAL (1)

Primary-to-secondary leakage > 150 gallons per Exceeding Primary-to-Secondary EVENT day for more than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (TS 3.1.d.2).

leak rate Technical Specification.

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

rageu V.iL,

CHART E LOSS OF POWER EMERGENCY KNPP INDICATION CLASSIFICATION CLASSIFICATION CRITERIA

)RCS is 350'F, AND Failure of off-site and on-site GENERAL (1)

AC power, AND EMERGENCY (2)

Buses I through 6 are de-energized including the Total loss of auxiliary D/G supplies to buses 5 and 6, AND feedwater makeup capability for greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. (Loss (3) Loss of the turbine driven AFW pump, AND of power plus loss of all AFW would lead to clad failure and (4) Conditions exist for greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

potential containment failure.)

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

(

removed.)

more than 15 minutes).

(1) Low voltage lockout OR de-energized condition Loss of all vital on-site DC SITE on all safeguards DC ditribution cabinets for Loss of a ol tan DC greater than 15 minutes.

power (for more than 15 EMERGENCY

a. BRA 102 and BRB 102, OR minutes).

b. BRA 104 and BRB 104, OR

c. BRA 102 and BRB 104, OR

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

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

power (for less than 15

a. BRA 102 and BRB 102, OR minutes).

b. BRA 104 and BRB 104, OR

c. BRA 102 and BRB 104, OR

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

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

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

(1) With the Reactor Coolant System above cold shutdown condition:

Loss of off-site power, OR UNUSUAL

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

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

(1) Core is unloaded or reactor cavity is flooded with Loss of off-site power, A EN T internals removed,A UNUSUAL (2)

Buses 1 through 6 are de-energized including the Loss of on-site AC power (for D/G supplies to buses 5 and 6 for longer than more than 15 minutes).

15 minutes.

Table 2-1 EPIP-AD-02 Rev. AD Date: JUL 19 2002 REFERENCE USE vaget j

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

needed when RCS > 2000F.

EMERGENCY

a.

Loss of negative reactivity control, OR

b.

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

OR

c.

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

d.

Loss of RCS inventory control, OR

e.

Loss of both trains of RHR, AND the inability to sustain either natural OR forced circulation with the steam generators (< 350°F).

(A Site Emergency should be declared upon the initiation of bleed and feed per FR H. 1, Response to Loss of Secondary Heat Sin (Apply this criteria when the RCS is _ 200'F.)

Complete loss of any function ALERT needed when RCS _* 2000F.

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

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

and complete a reactor trip which brings the reactor subcritical.

(1) Loss of ESF function, required support function Inability to reach required UNUSUAL or required Tech Spec instruments OR shutdown within Tech Spec EVENT Exceeding Tech Spec Safety Limits, AND limits (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. AD Date: JUL 19 2UU2

.rw 4A ^f 1I4 REFERENCE USE r*W17 l*

CHART G LOSS OF INDICATION CHART H (DELETED)

Table 2-1 EPIP-AD-02 Rev. AD Date: JUL 19 2002 rage i'i OT 

I REFERENCE USE EMERGENCY KNPP INDICATION CLASSIFICATION CLASSIFICATION CRITERIA (1) Total loss of Annunciator System computer Most or all alarms (annunciators, SITE alarms, and sequence of events recortler for lost and a plant transient initiated EMERGENCY greater than 15 minutes, AND or in progress.

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

(1) Total loss of Annunciator System, computer Most or all alarms (annunciators)

ALERT alarms, and sequence of events recorder. (Not lost.

applicable when plant is at or below cold shutdown.)U (1) Significant loss of ESF or Rx Protection Indications or alarms on process UNUSUAL instrumentation. An Unusual Event should or effluent parameters not EVENT NOT be declared for a non-emergency Tech functional in control room to an Spec backdown, when the affected parameter extent requiring plant shutdown remains monitorable.

or other significant loss of assessment capability.

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

r'age -14T of°1

CHART I SECONDARY SIDE ANOMALY EMERGENCY KNPP INDICATION CLASSIFICATION CLASSIFICATION CRITERIA (1) Main steam line break that results in a SI Steam line break, AND SITE actuation, AND EMERGENCY Primary-to-secondary leak (2) a. R-15 or R-19 reads offscale high with

>50 GPM, AND confirmation by chemistry analysis, OR Indication of Fuel Damage.

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

b. CNTMT hydrogen monitor indicates > 1%

hydrogen concentration.

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

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

norma--, ORR (Applies even if events occur in

b. Primary-to-secondary leakage > 10 gpm.

opposite steam generators.)

(1) Turbine trip and observation of penetration of Turbine rotating component VNUSUAL casing.

failure causing rapid plant EVENT shutdown.

(1) The uncontrolled depressurization of the Rapid depressurization of the UNUSUAL secondary system that results in an SI actuation.

secondary side.

EVENT Table 2-1 EPIP-AD-02 Rev. AD Date: JUL 19 2002 REFERENCE USE rage -i=of A" I

CHARTJ MISCELLANEOUS ABNORMAL PLANT CONDITIONS Table 2-1 EPIP-AD-02 Rev. AD Date: JUL 19 2002 r'ge i 01 £ I REFERENCE USE KNPP INDICATION EMERGENCY CLASSIFICATION CLASSIFICATION CRITERIA (1) Containment boundary failure or potential Other plant conditions that make a GENERAL failure:

release of large amounts of EMERGENCY radioactivity in a short time period

a.

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

b.

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

Failure of main FW and AFW

c.

Containment hydrogen monitor systems for greater than

> 10% hydrogen concentration, AND 30 minutes without Safety Injection and Residual Heat (2)

Loss of core cooling capability:

Removal flow. Plus a containment failure is

a.

Loss of SI and RHR flow, AND imminent.

(3)

Failure of shutdown system when required:

Transient requiring the operation of shutdown

a.

Entry into IPEOP FR-S. 1, "Response to systems with a failure of these Nuclear Power Generation/ATWS," OR shutdown systems. In addition, failure of SI and

b.

Loss of AFW for greater than 30 minutes RHR and containment failure with loss of main FW and condensate.

is imminent.

(1)

Evacuation of Control Room (E-O-06 event).

Evacuation of control room and SITE control of shutdown systems EMERGENCY required from local stations.

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

activating the E.P.

Example:

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

ri.age [Dt)OI A I

CHART K FIRE AND FIRE PROTECTION CHART L (DELETED)

Table 2-1 EPIP-AD-02 Rev. AD Date: JUL 19 2002 Page 17 of 21 REFERENCE USE KNPP INDICATION EMERGENCY CLASSIFICATION CLASSIFICATION CRITERIA (I) A fire within the Auxiliary Building A fire compromising the functions SITE Technical Support Center, safeguards alley, of safety systems.

EMERGENCY DiG 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.

more than 10 minutes.

EVENT

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

EMERGENCY RR159, AND (2)

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

(1) Activation of seismic recorder with TRIGGER, An earthquake greater than ALERT and OBE lights lit in relay room on RR159, Operational Basis Earthquake AND (OBE).

(2) Verification of a 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 mage or verification from University of Wisconsin Seismic Center.)

NOTE:

Telephone numbers for U of W - Milwaukee Seismic Center are in the KPPB Emergency Telephone Directory, ETD 02.

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 I hour, AND design levels with plant not in EMERGENCY cold-shutdown.

(2)

Plant above cold shutdown condition.

(1) A tornado which strikes the facility, AND Any tornado striking facility.

ALERT (2)

Causes damage to render a single train of required ESF-equipment to be inoperable.

(1) A tornado observed on-site causing significant Any tornado on-site.

UNUSUAL damage to the facility.

EVENT Table 2-1 EPIP-AD-02 Rev. AD Date: JUL 19 2002 rage i or i REFERENCE USE Page 1 i or Ti

CHART 0 FLOOD, LOW WATER, OR SEICHE 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. AD Date: JUL 19 2002 REFERENCE USE Page 19 of 21 EMERGENCY CLASSIFICATION KNPP INDICATION CRITERIA CLASSIFICATION FOREBAY LEVEL Flood, low water, or Indicated for > 15 minutes seiche near design ALERT CORRESPOND levels.

0 PUMPS 1 PUMP 2 PUMPSTOLKLEL TO LAKE LEVEL NOTE3 NOTE1

> 94%*

> 588 ft.

< 50%

• NOTE 5 NOTE 5

< 568.5 ft.

OR Deep water Wave > 22.5 ft.

FOREBAY LEVEL 50-year flood, low Indicated for > 15 minutes water level or seiche UNUSUAL CORRESPOND EVENT o PUMPS 1 PUMP 2 PUMPSTOL ELVL TO LAKE LEVEL NOTE2

> 98%*

> 88% *

> 586 ft.

< 53.1%

<46.9%*

NOTE5

< 569.5 ft.

NOTE 4 OR Deep water wave > 18 ft. (as confirmed by the U.S. Coast Guard, Two Rivers)

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 impactiR fire.

EMERGENCY a complete loss of an ESF function.

m (1) A missile strikes plant buildings, O Severe damage to safe SITE 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 (1) Release of flammable or toxic gas from a ruptured or flammable gas isconfirmed EMERGENCY container, which causes or is likely to cause within vital area.

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

Airrat cas onfailiy.ALERT (1) An aircraft crashes into plant buildings AND Aircraft crash on facility.

causes a single train of required ESF equipment to be inoperable.t Missile impact from whatever ALERT (I) A missile strikes the facility AND causes a sinle source on facility.

tram of required ESF equipmnent to be inoperable.

Uncntoled elas oftoicALERT (1) Release of toxic or flammable gas at life Uncontrolled release of toxic threatening levels from a ruptured container enter within the protected area.

the protected area AND impacts safe operation of the plant.

Known explosion damage to ALERT (1) Self-explanatory.

facility affecting plant operation.

Aircraft crash on-site or UNUSUAL (1) An aircraft crash within the site boundary, _R unusual aircraft activity over EVENT 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 identification attempts through the FAA or other agencies have been unsuccessful.)

Uncontrolled release of toxic UNUSUAL EVENT (1) Release of toxic or flammable gas from a ruptured or flammable gas is confirmed tank/truck on site, AND on site.

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

Table 2-1 EPIP-AD-02 Rev. AD Date: JUL 19 2002 REFERENCE USE P-age 2u Or zI

CHART Q SECURITY CONTINGENCY EMERGENCY IKNPP INDICATION CLASSIFICATION CLASSIFICATION CRITERIA (1) Physical attack on the plant that has resulted in Loss of physical control of the GENERAL unauthorized personnel occupying the control plant.

EMERGENCY room or any other vital areas as described in the Security Plan.

(1) Physical attack on the plant involving Imminent loss of physical SITE imminent occupancy of the control room, control of the plant.

EMERGENCY auxiliary shutdown panels, or other vital areas as defined by the Security Plan.

(1) Security safeguards contingency event that Ongoing security compromise.

ALERT results in a hostile force entering the protected area of the plant, but not gaining control over shutdown capability or of any vital areas as defined in the Security Plan, OR (2) Security safeguards contingency event that results in a site specific HI level 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. AD Date: JUL 19 2002 Page 21 of 21 REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP.

No.

EPIP-SEC-03 TRev.

AE Title Personnel Assembly and Accountability Kewaunee Nuclear Power Plant Emergency Plan Implementing Procedure Date JUL 19 2002 Page 1 of 11 Reviewed By Dave Seebart Approved By William Yarosz Nuclear I PORC SRO Approval Of Safety

[ Yes Review 0 Yes Temporary 0 Yes Related 0] No J Required 0 No Changes Required 0 No 1.0 Purpose 1.1 This procedure provides instruction for establishing and maintaining personnel accountability within the Protected Area (PA) of the plant.

2.0 General Notes 2.1 When initial assembly and accountability are in progress, certain individuals (as designated in EPIP-AD-0 1, "Personnel Response to the Plant Emergency Siren") will be allowed to move in, out, and about the PA before initial accountability is complete.

2.2 Emergency Response Organization (ERO) staff shall report to their duty locations.

2.3 Visitors, Contractors, and non-ERO personnel on-site should assemble in the nearest designated Assembly Area.

2.4 Severe Weather 2.4.1 Several of the Assembly Areas are NOT appropriate for severe weather safety.

a. Warehouse Annex Lunchroom - relocate to the locker room.

b. Administrative Training Facility (ATF) Lunchroom - relocate to the ATF Basement.

c. Simulator Training Facility (STF) Lobby - relocate to the Simulator Control Room away from the glass partition along the west wall close to the floor.

d. Classroom C Security Building - relocate to the Security Building locker room.

Note IF unable to relocate as stated above, personnel should relocate on lower levels of buildings in interior rooms away from all windows.

2.4.2 The following locations are adequate during severe weather:

a. Control Room (CR)

b. Radiation Protection Office (RPO)

c. Technical Support Center (TSC) n:\\nucdoc\\procedures\\draft\\epip\\esecO3.doc-Oiane Fend/Diane Fenc--Jeanne Ferris REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP.

No.

EPIP-SEC-03 FRev.

AE Title Personnel Assembly and Accountability Kewaunee Nuclear Power Plant Emergency Plan Implementing Procedure Date JUL 19 2002 Page 2 of 11 3.0 Precautions and Limitations, 3.1 Initial accountability starts from the site announcement (siren sounding/public address message) and needs to be completed within 30 minutes.

a. The SMS Emergency Accountability Program will begin 2 minutes after site announcement. This allows for personnel to exit areas that are not their normal emergency work area (i.e., Control Room).

b. The first report should be generated after 5 minutes.

c. After 10 minutes, print a report or review the computer screen every minute until the number of unaccounted for personnel plateaus.

d. When the number of unaccounted for personnel plateaus, accountability is complete.

3.2 Allow prompt movement of ERO personnel into and out of the Protected Area when the Site Protection Director has determined there is no personnel hazard restricting such movement.

3.3 Adhere to the radiation control policies and requirements outlined in EPIP-AD-1 1, "Emergency Radiation Controls," and EPIP-RET-02D, "Emergency Radiation Entry Controls and Implementation."

3.4 Personnel who are in the Control Room when the Emergency Accountability Program is started are accounted for by the SMS.

3.5 Security Force Members, Fire Brigade Members, NAOs, and dispatched Emergency Teams are exempt from the SMS Emergency Accountability Program. They will be accounted for as defined in EPIP-AD-01, Step 5. 1.1.c.

4.0 Initial Conditions 4.1 Personnel assembly is required whenever the plant emergency siren is sounded.

Accountability will be required upon assembly unless otherwise directed by the Shift Manager/Emergency Director.

5.0 Procedure 5.1 Site Protection Director (SPD) or Designee shall:

5.1.1 IF a designated Master Accountability Coordinator (MAC) is not available, THEN direct the Security Shift Captain to perform accountability functions.

5.1.2 Contact the Emergency Director (ED) or Radiological Protection Director (RPD) to determine the location of any personnel hazards on-site or off-site and continue to monitor conditions.

REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP.

No.

EPIP-SEC-03 FRev.

AE Title Personnel Assembly and Accountability Kewaunee Nuclear Power Plant Emergency Plan Implementing Procedure Date JUL 19 2002 Page 3 of 1 5.1.3 IF conditions warrant, THEN direct the Security Force to hold exiting personnel in the Security Building until the RPD determines a safe evacuation route.

5.1.4 Advise the MAC of all hazardous areas and/or severe weather.

5.1.5 Advise on-site directors of hazardous areas or severe weather conditions.

5.1.6 Direct Security Force personnel to make a tour through the Owner Controlled Area (OCA), sewage plant, exterior warehouses, exterior substation, and Met Tower to inform personnel to assemble in the STF or Security Building, or to leave the site, as appropriate.

5.1.7 Ensure attempts are made by any available means to contact all personnel who are unaccounted for.

5.1.8 IF attempts fail to locate personnel who are unaccounted for, THEN direct the Central Alarm Station (CAS) or Secondary Alarm Station (SAS) operator to run a computer report for that person(s).

5.1.9 Provide the Support Activities Director (SAD) and the RPD with information regarding all personnel who are unaccounted for based upon last known locations obtained from the computer report.

5.1.10 Keep the ED informed of the status of personnel accountability.

5.1.11 When initial accountability is complete, ensure the following message is announced over the Gai-tronics:

"I"Attention all personnel. Initial accountability is complete. Personnel may relocate to other areas but shall maintain accountability."

5.1.12 Maintain cognizance of all personnel outside the PA who remain on-site.

5.1.13 Continue to provide the MAC with updates on any location determined to be a personnel hazard including areas outside the PA.

REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP.

No.

EPIP-SEC-03 I Rev.

AE Title Personnel Assembly and Accountability Kewaunee Nuclear Power Plant Emergency Plan Implementing Procedure Date JUL 19 2002 Page 4 5.2 Master Accountability Coordinator (MAC) shall:

5.2.1 WHEN accountability is required:

a. Report to the Security Building.

b. IF a MAC has been designated and UNTIL they are released,

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

2. Help the designated MAC.

c. IF a MAC has NOT been designated, notify the Site Protection Director (SPD) of your intent to assume the responsibilities of the MAC and continue implementation of this procedure.

d. Assign an Accountability Coordinator to the South Security Building Visitor's Desk.

1. Inform this Accountability Coordinator to complete Form EPIPF-SEC-03.01, "Emergency Accountability Log," for ERO members entering the Protected Area.

2. Implement Step 5.3.8 of this procedure.

e. IF there is no Accountability Coordinator available for the Security Visitor's Desk, THEN assign a plant staff or security staff member to perform Step 5.2.l.d.

5.2.2 After the sound of the plant emergency siren:

a. Contact CAS to ensure SAS/CAS has started the "Emergency Accountability Program" on the SMS.

b. Make a public address announcement that the program has been activated and personnel in accountability areas should now swipe.

5.2.3 Contact Security to verify there is NOT a hard copy visitor list. If this list is available, pick up the KNPP Protected Area Visitor and Non-Designated Vehicle log (SIP 20.02-1) at the Registration Desk.

5.2.4 Contact each Visitor's Escort via Gai-tronics to ensure accountability of their Visitor, place a check mark next to the Visitor's name as reported by the Escort.

5.2.5 Four minutes after siren activation for a declared emergency, make a public address announcement that personnel who have not swiped a card reader must do so immediately.

5.2.6 Five minutes after the SMS Emergency Program has been started, obtain an Emergency Report from CAS or SAS.

REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP.

No.

EPIP-SEC-03 Rev.

AE Title Personnel Assembly and Accountability Kewaunee Nuclear Power Plant Emergency Plait Implementing Procedure Date JUL 19 2002 Page 5 of II 5.2.7 Should attempts fail to locate personnel who are unaccounted for, direct the CAS or SAS to run a computer report on that person.

5.2.8 Review the Emergency Report

a. Contact the Control Room and strike any names from the list that have been positively accounted for (individual is in the Control Room or is accounted for on their "Emergency Accountability Log").

b. Contact the Technical Support Center (TSC) and strike any names from the list that have been positively accounted for (individual is in the TSC or is accounted for on their "Emergency Accountability Log").

c. Contact all names remaining on the list by any possible means.

5.2.9 WHEN all personnel have been contacted or reasonable attempts to contact have failed, record the names of individuals not accounted for and their last known location and provide this information to the SPD.

5.2.10 Contact the Accountability Areas outside the PA (per Table 1) to determine the number and location of personnel on-site but not within the Protected Area.

5.2.11 Report to the SPD the number and location of personnel on-site but outside the PA and obtain an update regarding personnel hazards and/or severe weather.

5.2.12 IF the plant emergency siren sounds after initial accountability, THEN return to Step 5.2.2.

5.2.13 Provide Accountability Coordinators (AC) with information regarding personnel hazards and/or severe weather provided by the SPD and continue to do so on a periodic basis.

5.2.14 Brief the SPD on any change in accountability status or new problems (i.e., groups or individuals overdue in assembly areas).

5.2.15 If appropriate, plan a shift relief for the MAC per EPIP-AD-05.

5.2.16 IF Final Conditions (Section 6.0) have NOT been met, THEN return to Step 5.2.12.

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WISCONSIN PUBLIC SERVICE CORP.

No.

EPIP-SEC-03 Rev.

AE Title Personnel Assembly and Accountability Kewaunee Nuclear Power Plant Emergency Plan Implementing Procedure Date JUL 19 2002 Page 6 of 11 5.2.17 WHEN Final Conditions (Section 6.0) are met,

a. Return your work area to normal status and return emergency procedures, forms, etc. to there proper place.

b. Record any discrepancies to emergency supplies that need correction and report them to the SPD.

c. Collect all completed forms, notes, and other documentation and give them to the SPD.

5.3 Accountability Coordinator (AC) shall:

5.3.1 WHEN accountability is required:

a. Report to your assigned assembly area.

b. IF an AC has NOT been designated, THEN notify a Facility Director or MAC of your intent to assume the responsibilities of the AC in the assembly area and continue implementation of this procedure.

c. IF an AC has been designated and UNTIL they are released,

1. Help in facility activation.

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

3. Help the designated AC.

5.3.2 Obtain Accountability packet located in the assembly areas in the following locations:

a. Control Room (CR) - On the wall behind the Control Room Supervisor's desk.

Note Make a list for the MAC of Fire Brigade Members, NAOs, and dispatched Emergency Teams that are accountability exempt.

b. Technical Support Center (TSC) - On the desk near the entrance door (No. 410).

c. Radiation Protection Office (RPO) - Next to the entrance door (No. 55).

d. Administrative Training Facility (ATF) - Lunchroom southwest comer, above the phone and Gai-tronics.

e. Warehouse Annex - Lunchroom west wall, above the phone and Gai-tronics.

f. Security Building - Room "C" on the wall by the phone and Gai-tronics.

g. Site Training Facility (STF) - Lobby on the wall by the Gai-tronics.

REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP.

No.

EPEP-SEC-03 FRev.

AE Title Personnel Assembly and Accountability Kewaunee Nuclear Power Plant Emergency Plan Implementing Procedure Date JUL 19 2002 Page 7 of I1 5.3.3 Locate yourself near the SMS accountability card reader.

Note Visitors have non-magnetic badges, so they should NOTswipe their key card in an accountability card reader. Log visitors and report their information to the MAC.

5.3.4 WHEN the Gai-tronics announcement is made that emergency accountability has been initiated, ensure that all badged personnel located in the area swipe their Security key card in the accountability reader and receive a green light.

5.3.5 IF a Director or Supervisor notifies you of individuals who will NOT assemble, THEN record them as if they were leaving the facility per Step 5.3.8.

5.3.6 During accountability, demand quiet and cooperation. Maintain accountability of personnel assembled there.

5.3.7 WHEN provided by the MAC, inform personnel in your assembly area of information on hazardous areas.

Note Only address the teams or individuals you logged out.

5.3.8 WHEN an individual elects to move to another area, log their departure on "Emergency Accountability Log," Form EPIPF-SEC-03-01, as follows:

Note This includes visitors also.

a. In the "Name" column: Enter the name of the individual leaving the area.

b. In the "Card" column: Enter the individual's security card number.

REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP.

No.

EPIP-SEC-03 Rev.

AE Title Personnel Assembly and Accountability Kewaunee Nuclear Power Plant Emergency Plan Implementing Procedure Date JUL 19 2002 Page 8 o

c. In the "Destination"' column: Enter the location to which the individual is heading.

Acronym Area For Another Accountability Area CR Control Room RPO Radiation Protection Office TSC Technical Support Center WA Warehouse Annex Lunchroom ATF Administrative Training Facility Lunchroom For Repair Team Activity LPA Leaving the Protected Area PA Outside the Buildings but inside the Protected Area ADMN Administrative Buildings TURB Turbine Building AUX Auxiliary Building CNTM Containment Building WRHS Warehouse or Shop Area

d. In the "Departure Time" column: Enter the time the individual departed the area.

e. In the "Return/Arrive Time" column: Enter the time the individual returns to the area or the time you are informed they arrive at another Assembly Area by the Accountability Coordinator in that area.

5.3.9 IF an individual arrives in your area who did not log out of your area and is not immediately returning to the area he checked out of, THEN contact the area he departed and notify them of the individual's arrival time and intent to stay.

5.3.10 IF moving the entire group of assembled personnel to another area, THEN:

a. Contact the MAC to inform them of the intended move.

b. Record badge numbers of people moving.

c. Instruct personnel in your area to proceed directly to the new destination, staying in a group until head count can be verified.

REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP.

No.

EPIP-SEC-03 I Rev.

AE Title Personnel Assembly and Accountability Kewaunee Nuclear Power Plant Emergency Plan Implementing Procedure Date JUL 19 2002 Page9of 11

d. Verify the badge numbers upon arrival at the new location.

e. Contact the MAC to verify arrival and to provide a phone number at the new location.

5.3.11 IF the plant siren is sounded following the initial accountability, THEN initiate contacts to all individuals listed as NOT "Returned or Arrived" on your Form EPIPF-SEC-03-01:

a. WHEN contacted, give them any information you know about the siren sounding.

b. IF instructed by a Facility Director, instruct the individual to come back to an assembly area.

c. Note the individuals that were contacted and notify the MAC of individuals logged out of your area and whether you were able to contact them.

d. Return to Step 5.3.4.

5.3.12 If appropriate, plan a shift relief for the area AC per EPIP-AD-05.

5.3.13 IF Final Conditions (Section 6.0) have NOT been met, THEN return to Step 5.3.7.

5.3.14 IF Final Conditions (Section 6.0) are met, THEN Note Flag any discrepancies to emergency supplies that need correction.

a. Return your work area to normal status and return emergency procedures, forms, etc. to there proper place.

b. Collect all completed forms, notes, and other documentation and give them to the SPD.

5.4 Security Force shall:

5.4.1 WHEN accountability is required and the SMS system is offline, manually maintain a log of personnel entering/exiting the PA to enable the MAC to update the accountability roster as necessary.

5.4.2 Guide PA ingress/exit in accordance with EPIP-SEC-02, "Security Force Response to Emergencies."

5.4.3 Patrolling Security Officers shall:

a. Verify their locations by portable radio to the Shift Captain for accountability.

b. Obtain personal dosimetry to take with them on patrol in accordance with EPIP-SEC-04, "Security Force Actions for Dosimetry Issue."

REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP.

No.

EPIP-SEC-03 Rev.

AE Title Personnel Assembly and Accountability Kewaunee Nuclear Power Plant Emergency Plan Implementing Procedure Date JUL 19 2002 Page 10 6.0 Final Conditions 6.1 Plant Emergency has been Terminated or Recovery actions have begun and the Emergency Director has suspended the use of EPIPs or it has been determined emergency accountability is no longer required.

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-05, Emergency Response Organization Shift Relief Guideline 7.4 EPIP-AD-1 1, Emergency Radiation Controls 7.5 EPIP-RET-02D, Emergency Radiation Entry Controls and Implementation 7.6 EPIP-SEC-02, Security Force Response to Emergencies 7.7 EPIP-SEC-04, Security Force Actions for Dosimetry Issue 8.0 Records 8.1 The following QA records and non-QA records are identified in this directive/procedure and are listed on the KNPP Records Retention Schedule. These records shall be maintained according to the KNPP Records Management Program.

8.1.1 QA Records None 8.1.2 Non-QA Records 0 Emergency Accountability Log, Form EPIPF-SEC-03-01 REFERENCE USE

ACCOUNTABILITY AREAS (Inside the Protected Area)

LOCATION PHONE NUMBER Control Room 8207 Radiation Protection Office 8451 Technical Support Center (Included OSF and RAF) 8353 Administrative Training Facility (Lunchroom) 6480 Warehouse Annex (Lunchroom) 6452 ALTERNATE LOCATION PHONE NUMBER Administrative Training Facility (Basement) 6548 Warehouse Annex (Locker Room) 6454 ACCOUNTABILITY AREAS (Outside the Protected Area)

LOCATION PHONE NUMBER Security Building Classroom C 6548 Simulator Training Facility (Lobby) 8427 ALTERNATE LOCATION PHONE NUMBER Security Locker Room (Security Building) 8292 Simulator Training Facility (Simulator Control Room) 8607 ACCOUNTABILITY LEADERS LEADER PHONE NUMBER Master Accountability Coordinator (Security Building) 8509 Accountability Coordinator (Sec. Bldg. Visitor's Desk) 8289 Site Protection Director (Sec. Bldg.)

8418 (TSC)

PBX 8591 Kew. Ex. 388-0459 Table I EPIP-SEC-03 Rev. AE Date: JUL 19 2002 rage 11 orii REFERENCE USE Page 11 OT" 11

Friday, July 19, 2002 Attention:

NRC Document Control Desk The purpose of this letter is to inform you that we have not yet received the Document Transmittal Sheet for revisions of procedures made in your copy of the Emergency Plan Implementing Procedures (EPIP) manual.

We are currently performing an audit for all manuals that are distributed from Document Control at Kewaunee Nuclear Power Plant. Since we have not received receipts from you in some time, we are enclosing an index of the Emergency Plan Implementing Procedures (EPIP) Manual. Please use this index to ensure that your manual is up to date. If you find any discrepancies in this manual, please contact me, Laura Ihlenfeldt at (920)-388.-8881, or Yvonne Elsen at (920)-388-8'_36 and we will ensure that you receive the correct updates.

Please complete this audit and sign, date, and return this to me within 30 days, or your manuals will be cancelled.

Thank you in advance for your help!

Yvonne Elsen Document Control Supervisor 388-8136 Laura Ihlenfeldt 388-8881 Signature:

Date:

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 07-19-2002 PROC. NO.

TITLE REV.

DATE EP-AD EPIP-AD-0I Personnel Response to the Plant Emergency J

01-08-2002 Siren EPIP-AD-02 Emergency Class Determination AD 07-19-2002 EPIP-AD-03 KNPP Response to an Unusual Event AF 06-20-2002 EPIP-AD-04 KNPP Response to Alert or Higher AJ 06-20-2002 EP-AD-5 Site Emergency Deleted 04-27-87 EPIP-AD-05 Emergency Response Organization Shift Relief D

05-09-2002 Guideline EP-AD-6 General Emergency Deleted 04-24-87 EPIP-AD-07 Initial Emergency Noatdions AR 06-20-2002 EP-AD-8 Notification of Alert or Higher Deleted 02-26-96 EP-AD-9 Notification of Site Emergency Deleted 04-27-87 EP-AD-C10 Notification of General Emergency Deleted 04-27-87 EPIP-AD-11 Emergency Radiation Controls R

04-11-2002 EP-AD-12 Personnel Assembly and Accountability Deleted 03-26-94 EP-AD-13 Personnel Evacuation Deleted 04-25-94 EP-AD-613A Limited Area Evacuation Deleted 03-01-83 EP-AD-13B Emergency Assembly/Evacuation Deleted 03-01-83 EP-AD-13C Site Evacuation Deleted 03-01-83 EP-AD-14 Search and Rescue Deleted 05-25-94 EPIP-AD-15 Recovery Planning and Termination 0

10-30-2001l EP-AD-16 Occupational Injuries or Vehicle Accidents Deleted 03-14-97 During Emergencies EP-AD-17 Communications Deleted 03-05-84 EPIP-AD-18 Potassium Iodide Distribution P

02-27-2002 EPIP-AD-19 Protective Action Guidelines Q

11-27-2001 PAGE 1 OF 11 Q

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 07-19-2002 TITLE REV.

DATE KNPP Response to a Security Threat C

05-23-2002 E P-EN-V 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-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 q

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 07-19-2002 PROC. NO.

TITLE REV.

I 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 X

06-20-2002 EP-EOF-9 Interface with Support Organizations Deleted 03-05-84 EP-EOF-9 Notification of Site Emergency Deleted 04-24-87 EP-EOF-10 Notification of General Emergency Deleted 04-24-87 EPIP-EOF-11 Internal Communication and Documentation U

11-15-2001 Flow EPIP-EOF-12 Media Center/Emergency Operation Q

06-20-2002 Facility/Joint Public Information Center Security PAGE 3 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 07-19-2002 PROC. NO.

TITLE REV.

DATE EP-OP EP-OP-I Control Room Emergency Organization Deleted 04-24-87 EP-OP-2 Emergency Control Room Activation for Deleted 04-24-87 Emergency Response EP-OP-3 Control Room Communications Deleted 04-24-87 EP-OSF EP-OSF-1 Operation Support Facility Emergency Deleted 04-24-87 Organization EPIP-OSF-02 Operational Support Facility Operations U

02-06-2002 EPIP-OSF-03 Work Orders During an Emergency P

05-09-2002 EP-OSF-4 Operational Support Facility Communications Deleted 04-24-87 EPIP-OSF-04 Search and Rescue E

05-23-2002 EP-RET EP-RET-1 Radiation Emergency Team Organization Deleted 04-16-96 EPIP-RET-02 In-Plant Radiation Emergency Team V

05-23-2002 EPIP-RET-02A Radiation Protection Office/Radiological T

11-29-2001 Analysis Facility (RPO/RAF) Activation EPIP-RET-02B Gaseous Effluent 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 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: 07-19-2002 PROC. NO.

TITLE REV.

DATE EPIP-RET-03C Post Accident Operation of the High Radiation P

01-15-2002 Sample Room EPIP-RET-03D Containment Air Sampling Analysis Using N

01-15-2002 CASP EP-RET-3E Post Accident Operation of High Rad Sample Deleted 08-27-85 Room Inline Multiported Count Cave EPIP-RET-04 SBF Activation S

06-20-2002 EP-RET-4A EOF Radiological Monitoring Deleted 03-10-83 EPIP-RET-04A SBF Operation/Relocation Deleted 10-02-2001 EP-RET-4B Radiological Controls at Site Access Facility Deleted 07-12-94 EP-RET-4C Site Radiological Monitoring Deleted 07-12-94 EP-RET-4D SAM-I Operation Deleted 07-12-94 EP-RET-5 Plume Projection Deleted 09-26-84 EPIP-RET-05 Site Boundary Dose Rates During Controlled H

10-09-2001 Plant Cooldown EP-RET-5A Plume Projection Deleted 04-27-87 EP-RET-6 Dose Projection Deleted 04-24-87 EP-RET-7 Radiological Analysis Facility/Radiation Deleted 04-24-87 Protection Office Communications EPIP-RET-08 Contamination Control of the Aurora Medical Deleted 05-23-2002 Center EPIP-RET-09 Post-Accident Population Dose L

04-16-2002 EP-SEC EP-SEC-1 Security Organization Deleted 04-24-87 EPIP-SEC-02 Security Force Response to Emergencies X

02-06-2002 EP-SEC-2A Manual Activation of Emergency Sirens Deleted 04-16-82 EPIP-SEC-03 Personnel Assembly and Accountability AE 07-19-2002 EPIP-SEC-04 Security Force Actions for Dosimetry Issue P

10-02-2001 PAGE 5 OF 11 It

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 07-19-2002 PROC. NO.

TITLE REV.

DATE EP-SEC-5 Security Force Response to the EOF Deleted 07-28-88 EPIP-SEC-05 Personnel Evacuation G

06-20-2002 EP-TSC EPIP-TSC-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 J

06-20-2002 EPIP-TSC-08A Calculations for Steam Release from Steam N

12-14-2001 Generators EPIP-TSC-08B*

STMRLS Computer Program G

06-20-2002 EP-TSC-8C*

See EP-TSC-8B Deleted 04-16-92

• EP-TSC-8B was totally deleted; therefore, EP-TSC-8C was changed to EP-TSC-8B EP-TSC-9 Core Damage Assessment Using Released Deleted 09-30-86 Radionuclides EPIP-TSC-09A*

Core Damage Assessment J

05-16-2002 EPIP-TSC-09B*

CORE Computer Program Deleted 05-16-2002 EP-TSC-9C*

See EP-TSC-9B Deleted 04-16-92

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

EPIP-TSC-10 Technical Support for IPEOPs K

05-09-2002 PAGE 6 OF 11 4

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 07-19-2002 FIGURES EPIP FiG Figure EPIPFG DESCRIPTION REV.

DATE EP-SEC-5 Technical Support EPIP-APPX-A-06 EP-FIG-003

.APPX-A-06-03 Center - KNP Floor Plan B

06-12-2001 Site Boundary Facility EPIP-APPX-A-06 EP-FIG-O05 APPX-A-06-02 ICNP Floor Plan A

10-31-2000 Radiological Analysis Facility - KNP Floor EPIP-APPX-A-06 EP-FIG-OO8 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 Location of JPIC and Media Briefing Center EPIP-EOF-12 EP-FIG-024 EOF-12-02 Map C

06-20-2002 KNP Site Map &

EP-SEC-5 EP-FIG-026 SEC-05-01 Evacuation Routes C

06-20-2002 Floor Plan - Media APPX-A-6 EP-FIG-034 Briefing Center Deleted 08-04-98 General Office EPIP-EOF-12 Building - WPSC (1 st 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-FtG-038 Floor Plan - JPIC Deleted 08-04-98 EPIP-OSF-02 EP-FIG-039 OSF-02-01 High Priority Work A

10-02-2001 EPIP-OSF-02 EP-FIG-039A OSF-02-02 Lower Priority Work A

10-02-2001 JPIC - Federal Work EPIP-APPX-A-06 EP-FIG-043 APPX-A-06-10 Area - WPSC D2-9 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-04S APPX-A-06-05 Area - WPSC D2-7 C

12-21-2001 Aurora Medical Center RET-08 EP-FIG-046 RET-08-01 Location Deleted 05-23-2002 EPIP-APPX-A-02 APPX-A-02-01 ERO Call Tree Deleted 12-04-2001 PAGE 7 OF 11 Q

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 07-19-2002 41 PAGE 8 OF 11 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

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 07-19-2002 FORM EPIPF TITLE REV.

DATE APPENDLX B "EP-AD ENV-01-01 Event Notice (Wisconsin Nuclear Accident Reporting Form)

S 05-23-2002 State Call-Back - Question Guideline C

11-15-2001 Emergency Radiation Work Permit G

04-11-2002 Airborne Radioiodine Dose Accountability and Potassium A

02-27-2002 Iodide Distribution Record of Known Allergy To or Voluntary Refusal to A

02-27-2002 Take Potassium Iodide EP-ENV Environmental Dispatch Area Activation Checklist D

10-31-2000 ENV-01-02 EMT Status B

10-31-2000 ENV-0 1-03 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-1 1-02 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 4

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 07-19-2002 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 Briefimg C

12-04-2001 EP-RET RET-02A-02 Emergency Sample Worksheet E

06-05-2001 RET 2B. I 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 RET 8.3 Hospital Survey 1 Deleted 06-05-2001 RET 8.4 Hospital Survey 2 Deleted 07-25-97 RET 8.5 Hospital Survey 3 Deleted 07-25-97 RET-08-06 Hospital Survey 4 Deleted 05-23-2002 RET-09-01 Post-Accident TLD Record Sheet D

04-16-2002 EP-SEC SEC-03.01 Emergency Accountability Log A

03-28-2000 SEC-04-01 Emergency Dosimeter Log G

06-20-2002 EP-TSC TSC-01.01 Plant Status Summary for SAM Implementation B

02-06-2002 TSC-01.02 Severe Accident Management Summary and Strategy B

02-06-2002 Recommendation TSC-0 1.03 Severe Accident Management - Status B

02-06-2002 TSC-02-01 TSC and OSF ActiYation Checklist 0

09-27-2001 PAGE 10 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX FORM EPIPF TITLE REV.

DATE TSC 2.2 TSC-02-03 TSC-02-04 TSC-02-05 TSC-03-01 TSC-03-02 TSC-03-03 TSC-03-04 TSC-04-01 TSC-04-02 TSC Ventilation Checklist Emergency Response Data System (ERDS) Link Initiation Checklist TSC Chart Recorder Operation Checklist TSC and OSF De-activation Checklist Plant System Status Plant Equipment Status Environmental Status Board Radiation Monitors Emergency Physical Change Request Emergency Physical Change Safety Review TSC-04-03 Emergency Physical Change Index TSC-07-01 Head Venting Calculation TSC-08A-01 Steam Release Data Sheet (Energy Balance)

TSC-08A-02 Steam Release Calculation Sheet (Energy Balance)

TSC-08A-03 Steam Release Data/Calculation Sheet (Open Valve)

TSC-08A-04 Steam Release Data/Calculation Sheet (STMRLS Program)

TSC-09A-01 Core Exit Thermocouple Data TSC-09A-02 4

TSC-09A-03 TSC 9A.4 TSC-09A-05 Fuel Rod Clad Damage Estimate Fuel Rod Overtemperature Damage Estimate Core Damage Based on Activity Ratios Core Damage Assessment (Monitoring Data)

I__

I41 Core Damage Summary PAGE 11 OF 11 DATE: 07-19-2002 H

G D

A L

L J

I G

Deleted F

G H

G E

D D

D E

I Deleted 04-01-99 05-04-2001 01-30-2001 10-09-2001 06-12-2001 06-12-2001 06-12-2001 01-08-2002 05-09-2002 05-09-2002 08-29-2000 06-20-2002 12-14-2001 12-14-2001 12-14-2001 12-14-2001 05-16-2002 05-16-2002 05-16-2002 05-16-2002 05-16-2002 05-16-2002 TSC 9A.6 E

Deleted 4

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