ML023520113

Radiological Emergency Response Plan Implementing Procedures (Epips)

ML023520113
Person / Time
Site:	Kewaunee
Issue date:	12/06/2002
From:	Coutu T Nuclear Management Co
To:	Document Control Desk, Office of Nuclear Security and Incident Response
References
-RFPFR, NRC-02-104
Download: ML023520113 (63)

Text

Kewaunee Nuclear Power Plant Point Beach Nuclear Plant N490 Highway 42 6610 Nuclear Road Kewaunee, WI 54216-9511 Two Rivers, Wl 54241 920.388 2560 920 755.2321 NMC Committed to Nuclear Excellence~ Kewaunee / Point Beach Nuclear Operated by Nuclear Management Company, LLC NRC-02-104 December 6, 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 attachmenit is also submitted to the Kewaunee Nuclear Power Plant NRC Senior Resident Inspector.

Sincerely, Thomas Coutu Site Vice President SLC Attachment cc - US NRC Senior Resident Inspector, w/attach.

US NRC, Region 111 (2 copies), w/attach.

Electric Division, PSCW, w/o attach.

QA Vault, wo/attach.

DOCUMENT TRANSMITTAL S-7-KEWAUNEE NUCLEAR POWER PLANT -

FROM: , DIANE FENCL - KNPP -TRANSMrlTAL DATE: 11-26-2002 EMERGENCY PLAN IMPLEMENTING PROCEDURES TRANSMITTAL FORM OUTSIDE AGENCY COPIES (1-20) .

it es Krista Kappelman - PBNP - EP (10)*

S. C pn`n Craig Weiss - Alliant Energy (11)*

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

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

S. Campion - KNPP QA Vault (NRC Letter & Menio Onfly) (15)*

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

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

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

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

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

C. Sternitzky - ATF-2 (44)

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

-W. Galarneau - RAF (53)

- 'C. Grant - EOF (81)

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

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

XV. 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) Simulator/Communicator (117)

M. Fencl - Security (121)

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

S. Zutz - Security Building (120)

IV. Galarneau - SBF/EM Team (110, 111, 111A)

Ops Admin. (126)

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

S. Zutz - SBF/SEC (114) C. Grant - TSC Response Binder (Partial Distribution)

D. Krall - CR/Communicator (116)(Parthai Distribution) C. Grant - EOF Response Binder (Partial Distribution) I 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 1.

KEWAUNEE NUCLEAR POWER PLANT -

REVISION OF EMERGENCY PLAN IMPLEMENTING PROCEDURES Nove-mb-er26,2002.

the EPIPs, Please follow the directions listed below.' If you have any questions regarding changes made to please contact Dave Seebart at ext. 8719. ..

4444 .4 EPIP Index, dated 11-26-2002:

REMOVE -INSERT "EDURE REV PROCEDURE V

" EPIP-AD . j.. .. EPIP-AD-01 K S.... EPIP-AD-02 AD" EPIP-AD-02 AE EPIP-OSF-02 U- EPIP-OSF-02 V EPIP-SEC-03 AE EPIP-SEC-03 AF

. EPIP-TSC-08A . .N EPIP-TSC-08A I 4,4 d dated--copof this transmittal letter,awithinl0 days oftransmlttal date, to I44T4z 4*

--ir- a-:si,*ed the s&nder.If hanvee*

av3t uiyestions or co enntact Daveeeart at ext. 18*7.

I CERTIFY Copy No. - (WPSC No.) of the Kewaunee Nuclear Power Plant's EPIPs has been

-updated.

SIGNATURE DATE Please return this sheet to DIANE FENCL. -

U Diane Fencl 44 -.

Enclosure

. ý, i I, .

I j 01t-

. 1 .1; K,_)

2

EMERGENCY PLAN IMPLEMENTING PROCEDURES, ..

INDEX DATE.- 11-26-2002 PROC. NO. TITLE - REV.* DATE EP-AD ...-  :

EPIP-AD-01 Personnel Response to the Plant Emergency Siren K 11-26-2002

- EPIP-AD-02 -- -Emergency Class Determination - -- AE -.- 41-26-2002 -

EPIP-AD-03 KNPP Response to an Unusual Event AF 06-20-2002 EPIP-AD-04 KNPP Response to Alert or Higher AK 08-20-2002 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 Notificationof General Emergency- Deleted 04-27-87 EPIP-AD-1 1 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-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 Protective Action Guidelines R 11-07-2002 PAGE 1 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 11-26-2002 PRO C. NO. TITLE a EPIP-AD-20 KNPP Response to a Security-Threat EP-ENV

. EPIP-ENV:01 .,- Environmental Monitoring GQroup Organization W 0_8-20-2002 and Responsibilities EPIP-ENV-02 Environmental Monitoring Team Activation X 10-02-2001 EP-ENV-3A Environmental Protection Director Actions and Deleted 09-26-84 Directives EP-ENV-3B EM Team Actions Deleted 09-26-84 EPIP-ENV-03C Dose Projection Using RASCAL Version 2.2 W 08-20-2002 Software EP-ENV-3D Revision and Control of ISODOSE II Deleted 02-14-95 EP-ENV-3E Manual Determination of X/Q Deleted 04-24-87 EP-ENV-3F Manual Determination of X/Q (Green Bay Deleted 05-30-86 Meteorological Data)

EP-ENV-3G Manual Dose Projection Calculation Deleted 06-02-89 EP-ENV-3H Protective Action Recommendations Deleted 04-13-90 EPIP-ENV-04A Portable Survey Instrument Use T 08-20-2002 EPIP-ENV-04B Air Sampling and Analysis X 08-20-2002 EP-ENV-4C Environmental Monitoring Teams Deleted 04-13-90 EPIP-ENV-04C Ground Deposition Sampling and Analysis - - X 08-20-2002 EPIP-ENV-04D Plume Tracking for Environmental Monitoring 0 08-20-2002 Teams EP-ENV-5A LCS-1 Operation Deleted 04-14-86 EP-ENV-5B MS-3 Operation Deleted 04-14-86 EP-ENV-5C SAM IHOperation 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: 11-26-2002 PROC. NO. TITLE - - - REV. DATE EP-ENV-6 Data Analysis, Dose Projections and Protective Deleted 12-21-81 Action Recommendations EP-ENV-6 Alternate Sample Analysis and Relocation of EM Deleted 04-14-86

--Team EP-ENV-6A Relocation of Site Access Facility (Habitability) Deleted 03-23-84 EP-ENV-6B SAF Environmental Sample Analysis Relocation Deleted 03-23-84 EP-ENV-7 Site Access Facility Communications Deleted 09-26-84 EP-ENV-8 Total Population Dose Estimate Calculations Deleted 04-14-86 EP-EOF EP-EOF-1 Corporate Emergency Response Organization Deleted 03-11-94 EPIP-EOF-02 Emergency Operations Facility (EOF) Activation AA 08-06-2002 EPIP-EOF-03 EOF Staff Action for Unusual Event AC 02-06-2002 EPIP-EOF-04 EOF Staff Action for Alert or Higher AJ 08-06-2002 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 1 Internal Communication and Documentation V 11-07-2002 Flow EPIP-EOF-12 Media Center/Emergency Operation Facility/Joint Q 06-20-2002 Public Information Center Security PAGE 3 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 11-26-2002 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 V 11-26-2002 EPIP-OSF-03 Work Orders During an Emergency P 05-09-2002 EP-OSF-4 Operational Support Facility Communications Deleted 04-24-87 EPIP-OSF-04 Search and Rescue E 05-23-2002 EP-RET EP-RET-1 Radiation Emergency Team Organization Deleted 04-16-96 EPIP-RET-02 In-Plant Radiation Emergency Team V 05-23-2002 EPIP-RET-02A Radiation Protection Office/Radiological Analysis U 11-07-2002 Facility (RPO/RAF) Activation EPIP-RET-02B Gaseous Effluent Release Path, Radioactivity, and 5 08-06-2002 Release Rate Determination EP-RET-2C Containment Air Sampling and Analysis Deleted " 03-017-83 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: 11-26-2002 PRO C. 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

- _ t_______ _J!_____

i ______ - -

EP-RET-3E Post Accident Operation of High Rad Sample Deleted 08-27-85 Room Inline Multiported Count Cave EPIP-RET-04 SBF Activation T 10-17-2002 EP-RET-4A EOF Radiological Monitoring Deleted 03-10-83 EPIP-RET-04A SBF Operation/Relocation Deleted 10-02-2001 EP-RET-4B Radiological Controls at Site Access Facility Deleted 07-12-94 EP-RET-4C Site Radiological Monitoring Deleted 07-12-94 EP-RET-4D SAM-fl 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 Y 11-14-2002 EP-SEC-2A Manual Activation of Emergency Sirens Deleted 16-82 EPIP-SEC-03 Personnel Assembly and Accountability AF 11-26-2002 EPIP-SEC-04 Security Force Actions for Dosimetry Issue P 10-02-2001 PAGE 5 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES SINDEX DATE: 11-26-2002 PROC. NO. TITLE REV. DATE EP-SEC-5 Security Force Response to the EOF Deleted 07-28788 EPIP-SEC-05 Personnel Evacuation G 06-20-2002

________EP-TSC .. .

EPIP-TSC-01 Technical Support Center Organization and R 08-06-2002 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 Equipm ent EP-TSC-6 Assessment of Reactor Core Damage Deleted 09-30-86 EPIP-TSC-07 RV Head Venting Time Calculation J 06-20-2002 EPIP-TSC-08A Calculations for Steam Release from Steam 0 11-26-2002 Generators EPIP-TSC-08B* STMRLS Computer Program G 06-20-2002 EP-TSC-8C* See EP-TSC-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

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 11-26-2002 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-0o5 APPX-A-06-02 KNP Floor Plan A 10-31-2000

. . ... . Radiological Analysis EPIP-APPX-A-06 EP-FIG-008 APPX-A-06-01 Facility - KNP Floor Plan A 10-31-2000 EPIP-EOF-12 Division Office Building Form EPIPF-EOF-02-01 EP-FIG-009 EOF-12-01 (2nd Floor) Floor Plan B 10-24-2000 State/County Work Area EPIP-APPX-A-06 EP-FG-012 APPX-A-06-08 WPSC D2-1 Floor Plan C 10-31-2000 NRC Work Area EPIP-APPX-A-06 EP-FIG-013 APPX-A-06-09 WPSC D2-4 Floor Plan A 10-31-2000 Population Distribution by Geographical Sub EPIP-AD-19 EP-FIG-014 AD-19-01 Areas (with sectors) A 10-31-2000 EOF - WPSC D2-3 EPIP-APPX-A-06 EP-FIG-022 APPX-A-06-04 Floor Plan 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-----34 Briefing Center Deleted 08-04-98 General Office EPIP-EOF-12 Building - WPSC (1st EPIP-APPX-A-06 m-riE-o35 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*43 APPX-A-06-10 Area - WPSC D2-9 B 12-21-2001 JPIC - State and County Work Area EPIP-APPX-A-06 EP-FIG-044 APPX-A-06-07 WPSC D2-8 C 12-21-2001 JPIC - Utility Work EPIP-APPX-A-06 EP-FIG-045 APPX-A-06-05 Area - WPSC D2-7 C 12-21-2001 Aurora Medical Center RET-O8 Ev~na~o.* 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

............ ..I .

EMERGENCY PLAN IMPLEMENTING PROCEDURES

'INDEX DA TE: 11-26-2002 NUMBER TITLE REVISION DATE APPENDIX A APPX-A-1 Communication System Description AF 08-04-98 EPIP-APPX-A-02 Response Personnel Call List -. Deleted- 02-06-2002 EPIP-APPX-A-03 Off-Site Telephone Numbers Deleted 02-06-2002 EPIP-APPX-A-06 KNPP Emergency Response Facility Telephone AA 12-21-2001 Numbers PAGE 8 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 11-26-2002 FORM 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 B 08-06-2002 Iodide Distribution AD-18-02 Record of Known Allergy To or Voluntary Refusal to Take A 02-27-2002 Potassium Iodide EP-ENV ENV-01-01 Environmental Dispatch Area Activation Checklist D 10-31-2000 ENV-01-02 EMT Status B 10-31-2000 ENV-01-03 Meteorological and Plant Status Data C 12-14-2001 ENV-01-04 EMT Orders/Field Data B 10-31-2000 ENV-02-01 EMT Activation Checklist N 08-20-2002 EP-EOF EOF-02-01 EOF Activation Checklist T 08-06-2002 EOF-02-02 EOF Deactivation Checklist M 08-06-2002 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 G 11-07-2002 EOF-11-03 Environmental Status Board G 11-07-2002 EOF-12-01 I.D. Badge Registration Form G 10-24-2000 PAGE 9 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX- DATE: 11-26-2002 FORM EPIPF TITLE REV. DATE EP-OSF OSF 2.2 Maintenance Work in Progress Deleted 07-08-98 OSF-03-01 Operational Support Facility Team Briefing C 12-04-2001 EP-RET RET-02A-02 Emergency Sample Worksheet E 06-05-2001 RET-02B-01 Containment Stack Release (Grab Sample) D 08-06-2002 RET-02B-02 Auxiliary Building Stack (Grab Sample) D 08-06-2002 RET-02B-03 Auxiliary Building Stack (Sping Reading) D 08-06-2002 RET-02B-04 Containment Stack (Sping Reading) C 08-06-2002 RET-02B-05 Steam Release D 08-06-2002 RET-02B-06 Field Reading (Grab Sample) B 08-06-2002 RET-04-01 SAM-2 Counting Equipment Worksheet E 06-12-2001 RET 8.3 Hospital Survey 1 Deleted 06-05-2001 RET 8.4 Hospital Survey 2 Deleted 07-25-97 RET 8.5 Hospital Survey 3 Deleted 07-25-97 RET-08-06 Hospital Survey 4 Deleted 05-23-2002 RET-09-01 Post-Accident TLD Record Sheet D 04-16-2002 EP-SEC SEC-03.01 Emergency Accountability Log A 03-28-2000 SEC-04-01 Emergency Dosimeter Log G 06-20-2002 EP-TSC TSC-01.01 Plant Status Summary for SAM Implementation B 02-06-2002 TSC-01.02 Severe Accident Management Summary and Strategy B 02-06-2002 Recommendation TSC-01.03 Severe Accident Management-- Status B 02-06-2002 PAGE 10 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 11-26-2002 FORM EPIPF TITLE REV. DATE TSC-02-01 TSC and OSF Activation Checklist 0 09-27-2001 TSC 2.2 TSC Ventilation Checklist H 04-01-99 TSC-02-03 . Emergency Response Data System (ERDS)}Link Initiation _ G 05-04-2001 Checklist TSC-02-04 TSC Chart Recorder Operation Checklist D 01-30-2001 TSC-02-05 TSC and OSF De-activation Checklist A 10-09-2001 TSC-03-01 Plant System Status L 06-12-2001 TSC-03-02 Plant Equipment Status L 06-12-2001 TSC-03-03 Environmental Status Board J 06-12-2001 TSC-03-04 Radiation Monitors I 01-08-2002 TSC-04-01 Emergency Physical Change Request G 05-09-2002 TSC-04-02 Emergency Physical Change Safety Review Deleted 05-09-2002 TSC-04-03 Emergency Physical Change Index F 08-29-2000 TSC-07-01 Head Venting Calculation G 06-20-2002 TSC-08A-01 Steam Release Data Sheet (Energy Balance) H 12-14-2001 TSC-08A-02 Steam Release Calculation Sheet (Energy Balance) G 12-14-2001 TSC-08A-03 Steam Release Data/Calculation Sheet (Open Valve) E 12-14-2001 TSC-08A-04 Steam Release Data/Calculation Sheet (STMRLS Program) D 12-14-2001 TSC-09A-01 Core Exit Thermocouple Data D 05-16-2002 I 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

_zWISCONSlN PUBLIC SERVICE CORP. No . EPIP-AD-01 Rev. K

. 4 Title Personnel Response to the Plant

;Kewaunee Nuclear Power"Plant Emergency Siren Plan'IihplementingPocedure i K Date NOV 26 2002 Page 1 of 4 Reviewed By Dave Seebart1YsPORC Approved By W. L. Yarosz Nula -,[ es SRO Approval Of E] yes NuleartyYe Review -Temporary Related El No Required E] N90 Changes Required El No 1.0 Purpose 1.1 This procedure provides instruction for defining the initial actions to be taken in the event the plant emergency siren is sounded..

2.0 General Notes 2.1 The applicable content of this procedure shall be general knowledge for all personnel badged for unescorted access to KNPP and qualified Emergency Response Organization (ERO) responders.

2.2 When the plant emergency siren sounds, stop your work and listen for the plant page announcement for further information.

. 3.0 Precautions and Limitations 3.1 I approached by the media, THEN inform them that-the most accurate information concerning the emergency can be obtained at the Joint Public Information Center in the WPS Green Bay Division Office Building.

3.2 ONLY the scheduled Control Room staff, individuals specifically called to the Control Room (CR) by the ED or EOD, and the following individuals may report directly to the Control Room:

• Emergency Director (ED)

• Event Operations Director (EOD) e ERF Communicator - Control Room (ERFCM-CR)

• Notifier (SEC-N) 0 NRC Communicator (NRCCM)

• Control Room Support (SP-C)

• NRC Resident Inspector 9 CAS Operator

• Shift Technical Advisor (STA) 1\appdata\procpws\draft\epip\ead0l.doc-Christine Simmons/Christine Simmons-Jeanne Ferris REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. - No. EPIP-AD-01 Rev. K

.... ,--' - Title Personnel Response to the Plant

-'Kewaunee Nuclear Power Plant Emergency Siren

-'Emnie;gecyPlanlImplemnentingProcedure Date NOV 26 2002 Page 2 of 4 3.3 IF no Accountability Coordinator (AC) is available in an Assembly Area, THEN one of the first ERO members to arrive should implement Section 5.3 of EPIP-SEC-03, "Personnel Assembly and Accountability," until relieved by a designated Accountability Coordinator.

4.0 Initial Conditions 4.1 This procedure shall be implemented upon the sounding of the plant emergency siren accompanied by a plant page announcement of a Declared Emergency, or when directed by the Shift Manager (SM) or Emergency Director.

5.0 Procedure 5.1 When personnel within the Site Boundary hear the emergency siren and the page announcement of a declared emergency, they shall respond as follows:

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

a. ERO personnel inside the Radiologically Controlled Area (RCA) should pass through the RCA access'point near the Radiation Protection Office (RPO) on their way to their emergency duty location.

<2* b. ERO personnel who need to pass through the Security Building en-route to their emergency duty location should do-so promptly unless instructed to assemble elsewhere by Security.

c. The following are exceptions for ERO members reporting to identified duty locations:

0 Fire Brigade/Fire Team report to their turn out gear location and contact the Shift Manager (SM) or Event Operations Director (EOD) 0 On-Shift NAOs contact the SM or EOD

• Security Force personnel contact to the Shift Captain

• Dispatched emergency teams such as search and rescue or repair teams contact to the SM or Support Activities Director (SAD)

REFERENCE USE

W:ISCONSIN"PUBLIC SERVICE CORP. _ No. EPIP-AD-01 Rev. K Title Personnel Response to the Plant

• - :.'?;KeWaunnee Nuclear Power Plant -" .. ' , Emergency Siren Emiergency Plan Implementink Procedure Date NOV 26 2002 Page 3 of 4 5.1.2 Visitors, contractors, and non-ERO personnel on-site shall assemble in the nearest designated Assembly Area.

a. IF inside the Protected Area (PA), THEN report to one of the following areas:

"* Radiation Protection Office (RPO)

"* Administrative Training Facility (ATF) Lunchroom

"* Warehouse Annex Lunchroom

b. IF outside the PA, THEN report to one of the following areas:

"* Security Building Classroom C

"* Simulator Training Facility (STF) Lunchroom 5.2 While in transit to your duty location or assembly area and you observe:

5.2.1 An iniured person or vehicle accident - Report the event to the Radiation Protection Director in the TSC or the Shift Manager using the closest communication system available. Then, provide assistance to any victims to the best of your ability until help arrives and without causing bodily harm to yourself.

5.2.2 Any plant system or structural problem - Report your observation to the OSF as soon as possible after arriving at your duty location or assembly area.

5.3 When an evacuation is implemented, follow the instructions provided by Security and:

a. Exit the plant in an orderly fashion by the directed route.

b. IF reporting to a designated county relocation area, THEN proceed directly there, following all directions that may be provided for exiting the Emergency Planning Zone (EPZ) by county emergency government officials.

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 or it has been determined that accountability is no longer required.

7.0 References 7.1 EPIP-SEC-03, Personnel Assembly and Accountability 7.2 Figure EPIPFG-SEC-05-01, KNP Site Map and Evacuation Routes REFERENCE USE

W'ISCONSIN PUBLIC SERVICE CORP.. - No........ EPIP-AD-.01, Rev. K

, , Title -- Personnel Response to the Plant Kewaunee NuclearrPoiwe i Emergency Siren Emergency" Date NOV 26 2002 Page 4 of 4 8.0 Records 8.1 The following QA records and non-QA records are identified in this directive/procedure and are listed on the KNPP Records Retention Schedule. These records shall be maintained according to the KNPP Records Management Program.

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

WISCONSIN PUBLIC SERVICE CORP.. No. 7-EPIP-AD-02., Rev. AE

--- "Title Emergency Class Determinatin

,:,--,Kewaunee Nuciear PowerPlant .t.*

• .*2-Emergen cy Plan Implementing Procdure Date . NOV 26 2002. Page 1 of, Reviewed By Dave Seebart Approved By W. L. Yarosz Nuclear PORC SRO Approval Of Review Temporary 21 Yes Safety a Yes "1No Required 01 No Changes Required 0 No Related 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 accuracyprior 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.

j:\appdata\procpws\draft\epip\ead02.doc-Christine Simmons/Christine Simmons-Dave Lohman REFERENCE USE

IR'I,=RVIE CORP.-," No.' -

'IN -- EPIP-AD-02 IRev. AE' Kewaunee NucleaRI Power Plant '~~Title NO. -- IP-D02ReCas Determination Eifegec "A

"- meren Plan ImplementingiPrcedure :[ Date . NOV 26 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.

S....5.-4---D~f~n-mf-if ih'e -emerge~ncy-shTouildbei'F*classifii*d-d: -

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

".1 77 " 'WISCONSIN PUBLIC SERVICE CORP., :i-.,4NO.- -.EPIP-AD-02. -. . - Rev. AE Title Emergency&Class Determination Kewaunee Nucleariower Plant r

- -- I.

e P a

ý,..Eme Irgency Plan Inipl'eme&i -ProcAiedu ý Date -.- , NOV 26 2002 - ' Page 3 of 21 7.0 References

• S 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 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

, S..

42

2 The following charts are separated into different abnormal operating conditions *which may, depehiding upon

,.,,*SiteEmergency, 4,,.. .. . .. , .

Energency. . .

theirse eriL~v their severity, be classifiUed ,

asan eclassfied~z' Unusual

• Event,-Alert, or7General S, 1 CHAR'T 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. AE Date: NOV 26 2002 Page 4 of 21 REFERENCE USE

I CHARTA(1) -EFUN

---ABNORMAL RtADIOLOGICAL "EF-FLUENT KNPP INDICATION EMERENC CLASSASSIFIAATIO EMERGENCY CLASSIFICATIONTION CRITERIA A + ,....

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 . E meteorological" conditions.

Projected or measured dose rates to be provided Projected or measured in the environs P rajecediolialePoteo Dratetobpror d dose rates greater than 1 rem/hr whole GENERAL by the Radiological Protection Director or body or 5 rem/hr thyroid at the site EMERGENCY Environmental Monitoring Teams. 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.Rfor "adverse meteorology."

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

outside the site boundary.

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

a. Containment R-2 OR R-7 >_1.0OE+4 mr/hr, OR

b. Charging Area R-4 _ 1.0E+4 mr/hr, OR Radiation levels or airborne contamination which indicate a severe degradation in the control of ALERT

c. SFP Area R-5 _'1.0OE+4 mr/hi, 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 UINUSUAL EVENT (2) Liqiuid Releases: Notification by the exceeded.

Rad-Chem Group of violating .

ODCM 3.3.1 limits.

i Ut £ a Table 2-1 EPIP-AD-02 Rev. AE Date: NUV 6 20UU0 rage a of 41 REFERENCE USE

CHART.A(2)

-,GASEOUS EFFLUENTACTIONLEVELS- .

1. AUX BUILDING VENT RELEASES - WITH SIGNIFICANT CORE DAMAGE Instrument readings assutming'a post accident gas release AND C6ntainment High Rarige 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 (ADVMET) only when, 10m and 60m 'Wind speed < 5mph AND DeltM-TE>

(AVG MET).

2.4 degees F or Sigma Theta is < 3.01 degrees. All other cases are average meteorology 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 CPM (01-07) CPM (01-09) R-35 R.3E ..

PPCS PT G9086G PPCS PT G9088G MRE.

TOTAL NUMBER AVG MET ADV MET AVG MET ADV MET AVG ADV AVGMET ADV MET -,Y-,z, RUNNING MET MET AVG MET ADV MET I ** I.IE+4 6.5E+1 * ** 7.9E+2 1.27E+2 7.9E-1 2 8.8E+5 5.5E+3 3.25E+1 * ** 3.9E+2 6.35E+1 4 0E-1 GENERAL

• ** 2.6E+2 4.2E+1 2.6E-1 EMERG.

3 5.9E+5 3.7E+3 2 16E+1 4 - 4.4E+5 2.7E+3 .1.62E+1 - - -...

--.. ** 2.OE+2 3.175E+I- 2.0E-

- 1 1 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+0

• 3.1E+3 1.9E+1 3.1E+0

• SITE EMERG.

3 2.9E+4 1.8E+2 1.0E+0

• 2.1E+3 1.3E+I1 2.1E+O

• 4 2.2E+4 1.3E+2 *

• 1.5E+3 9.5E+0 1.5E+O

• 1 1.OE+3 6 2E+0 *

• 7.0E+1 * *

• 2 -5.OE+2 3.,IE+O * , * -3.5E+1 * * *A ALERT 3 3.3E+2 2 0E+0 *

• 2.3E+1 * *

• 4 2.5E+2 1.5E+O *

• 1.75E+1 * *

• I 1.0E+2 6.2E-1 *

• 7.OE+O * *

• 2 5 0E+1 3.IE-I * * .3.5E+0 * *

• UNUSUAL EVENT 3 3.3E+1 2.OE-1 *

• 2.3E+0 * *

• 4 2.5E+1 1.5E-1 *

• 1.7E+O * * *

• Offscale Low

• • Offscale High (Confirmation Only)

Table 2-1 EPIP-AD-02 Rev. AE Date: NOV 26 2002 S... ... age b OT;*

Page 6*OT Z1 REFERENCE USE

CHART-A(2)

".. GASEOUS EFFLUENT ACTION LEVELScontinued

2. AUX BUILDING VENT RELEASES WITHOUT CORE DAMAGE NOTE: 'Use, adverse meteorology conditions (ADV MET) only when, 10mnand 60m wind speed < 5mph'

,AND Delta-T > -+2.4 degrees F 'or Sigma Theta is < 3.01 degrees. All other cases are average meteorology (AyG MET).

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

SV & SFP A EMERG.

FANS AUX BLDG SPING MONITOR CLASS.

MID RANGE HIGH RANGE

• 2T TOTAL CPM (01-07) CPM (01-09)

NUMBER PPCS PT G9086G PPCS PT G9088G RUNNING 4 AVG MET ADV MET AVG MET ADV MET '-...

1 ** 9.4E+4 1.6E+4 1.0E+2 2 ** 4.7E+4 8.0E+3 5.OE+ I GENERAL 5.3E+3 3.3E+1 EMERG 3 ** 3.1E+4 4 ** 2.3E+4 4.OE+3 2.5+1 1 7.5E+5 4.6E+3 8.OE+2 5.OE+0 2 3.7E+5 2.3E+3 4.OE+2 2.5E+0 SITE J EMERG.

1.5+3 2.6E+2 1.6E+0 3 2.5E+5 4 1.8E+5 1.IE+3 2.OE+2 1.2E+0 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 4.3E+2 UNUSUAL EVENT 2.1E-2 2.8E+2 3

4 1.5E-2 2.IE+2

• • Offscale High (Confirmation Only) rage t VT I P'age 7 of 2 1 Table 2-1 EPIP-AD-02 Rev. AE Date: NOV 26 2002 REFERENCE USE

CHART A(2) _

.. --GASEOUS EFFLUENT ACTION .LEVELS continued - -

STEAM LINk KELkAk WIIfl I(vIVIrI(J4IVi tAII¶rIIM1Vi,4tVf!

3. STEAM LINE RELEASI* WIMH ,SLU81CPY I

• Instrumeni 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 within one-half hour of the accident.

S..... *'*' *'*-* *"Emergency Classification

..,,_,...**,- Steam Line Monitors Steam Line Monitors R-15 -R-31 R-32 R-33 R-34 *****: *--*:< -.*,

(cpm (mRlhr) (R/hr) ( lh) (R/hr)

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

• • 6.0E+1 -- 6.0E+1 -- Site Emergency

• • 1.5E-1 -- 1:5E-1 -- Alert 2.OE+05 .. .. . Unusual Event

• • Offscale High (Confirmation Only)

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

0 8 04 tdy 0 Ut £ I Table 2-1 EPIP-AD-02 Rev. AE Date: NOV 26 2U02 rage 8 ol.2 I REFERENCE USE

-CHART B r - -

FUEL DAMAGE INDICATION

' -" ""-* 'EMERGENCY

............CLASSIFICATION CRITERIA CLSIIAIN-

-KNPP INDICATION CRTERI CLCLSSIFCATIN I' -

(1) CET > 1,200 Degrees for greater than -15 minutes; OR' Plant conditions exist that make the

( R41> 1,000 rlhr, O -release of large amounts of GENERAL (2)" R4o . radioactivity in a short time period EMERGENCY (3) SACRG-1, Severe Accident Control Room Guideline possible.

SInitial 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-11.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 Bidg.

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

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

c. A dropped spent fuel assembly, OR

d. A loss of water level below spent fuel.

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

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

(1) Fuel Handling Accident in Containment Fuel damage accident with release ALERT confirming report, AND

a. A a.Acnimngrpr, of radioactivity auxiliary to containment or building.

ORR-12,

b. Alarm onR-11 OR (2) Fuel Handling Accident in Auxiliary Bldg. --

a. A confirming report, AND

b. Alarm onR-13 OR R-14.

(1) With RCS Temperature > 500'F,

_a. _ > 0.2 jICi/gram DOSE Equivalent 1-131 fora48 -sample.- ..... coolant activity High reactor UNUSUAL EVENT ...

hours, ORR

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

c. > 91/E iCilcc As determined by SP-37-065 (from T.S. 3. .c)

(1) R-9 is greater than 5.0 R/hr, AND Failed fuel monitor indicates greater UNUSUAL Sthan 0.1% equivalent fuel failures EVENT (2) Verified by RCS chemistry sample analysis. within 30 minutes.

Table 2-1 EPIP-AD-02 Rev. AE Date: NOV 26 2002 Page 9 oa 21 REFERENCE USE

CHART C.

.PRIMARYLEAK TO LOCA.

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

"EMERGENCYCAIAO KNPP INDICATION CLASSIFICATION CLASSIFICATION RT iA (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, O.R of 2 of 3 fission product barriers with a potential loss

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

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

a. Physical evidence of containment structure damage, OR

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

c. Containment hydrogen monitor indicates

> 10% hydrogen concentration, OR

d. Containment pressure exceeds 46 psig. -. ____,-__.....__...

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

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

(1) Initiation of reactor shutdown reguired 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. AE Date: NOV 26 2002 Page 10 of 21 REFERENCE USE

CHART D PRIMARY TO SECONDARY LEAK - .........-

W .

EMERGENCY ' "

"KNPPINDICATION

. ..., ... ...  : *' *--* *CLASSIFICATION CR ITE R IA ,-': - --CLASSIFICATION (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, ANDT (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 -generatortube 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.

UNUJSUAL EVENT Primary-to-secondary leakage > 150 gallons per Exceeding Primary-to-Secondary (1) 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.)

S.. .. . ... .. . .... .. . . .e.. . .. . . . ..

Table 2-1 EPIP-AD-02 Rev. AE Date: NOV 26 2002 Page 11 01f 21 REFERENCE USE

CHART E.

.. LOSS OF POWER --

EMERGENCY KNPP INDICATION, . .,.,CLASSIFICATION , CLASSIFICATION S.CRITERIA-.'

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

AC power,AND -EMERGENCY (2) Buses 1 through 6 are de-energized including the Total loss of auxiliary DIG supplies to buses 5 and 6, AND feedwater makeup capability for greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. (Loss (3) Loss of the turbine driven AFW pump, AND of power plus loss of all AFW would lead to clad failure and (4) Conditions exist for greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. potential containment failure.)

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

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

a. BRA 102 and BRB 102, ORm

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 wit internals removed.) .......

(1) Low voltage lockout OR de-energized condition on all safeguards DC'dis1tribution 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 104, OR

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

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

core is unloaded or cavity is flooded wit h internals removed.)

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

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

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

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

15 minutes.

Table 2-1 Table EPIP-AD-02 Rev.

2-1 EPIP-AD-02 AE Rev. AE Date: NUV b UU Date:REFERENCE NEV 26 2EUS ragje i2- ui --

USE

CHARTFF -. , :,,- , ,

ENGINEERED SAFETY FEATURE,ANOMALY

_EMERGENCY "KNPPINDICATION - CLASSIFICATION.-,,"- CLASSIFICATION CRITERIA .

(1) RCS > 20 0 'F with a loss of cooling capability Complete loss ofany function SITE or inventory control: needed when RCS > 200'F. EMERGENCY

a. Loss'of negative reactivity control, OR'

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

OR

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

d. Loss of RCS inventory control, OR

e. Loss of both trains of R-R, 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 Sink.") - -

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

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

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

. which brings the reactor subcritical.

(1) Loss of ESF function, required support function Inability to reach required UNUSUAL or required Tech Spec instruments OR shutdown within Tech Spec EVENT Exceeding Tech Spec Safety Limits, limits

-AND (2) upon discovery, inability or failure to take required shutdown or mode change actions within the required time.

(Total loss of AFW system when required (FR-H. 1 implemented) should be declared a UE regardless of Tech Spec action compliance.)

2-1PPAD0 e.AEDt:NU1b~U Table 2-1 EPIP-AD-02 Rev. Table~~~~~~~~~

AE Date: NOV 26 2USE REFERENCE USE Page 13 o

"CHARTG, '

• LOSS OF.INDICATION -*

-EMERGENCY -" L KNPP INDICATION , - CLASSIFICATION . CLASSIFICATION CRITERIA (1) Total loss of Annunciator System computer Most or allUalarms (annunciators) SITE alarms, and sequence of events recorder for lost and a plant transient initiated EMERGENCY greater than 15"minutes, AND or in progress., *

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

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

applicable when plant is at or below cold shutdown.)

(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.)

...CHART H .........

(DELETED) rage P'age 14 CT 1 14 OT ZI Table 2-1 EPIP-AD-02 Rev. AE Date: NOV 26 2002 REFERENCE USE

CHART I.. ..

"C 17 SECONDARYSIDE ANOMALY- ,

EMERGENCY KNPP INDICATION ,  % -CLASSIFICATION ,-- CLASSIFICATION CRITERIA (1) Main steam line break that results in a SI Steam line break, AND SITE actuation, AND

• ekEMERGENCY

-Pimmary-to-secondary leak (2) a. R-15 or R-19 reads offscale high with >50 GPM, AND confirmation by chemistry analysis, OR Indication of Fuel Damage.

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

b. CNTMT hydrogen monitor indicates> 1%

hydrogen concentration.

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

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

-normal, OR ..... .... . .

(Applies even if events occur in

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

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

(1) The uncontrolled depressurization of the Rapid depressurization of the UNUSUAL secondary system that results in an SI actuation. secondary side. EVENT Table 2-1 EPIP-AD-02 Rev. AE Date: NOV 26 2002 Page 15 of 21 REFERENCE USE

CHART J MISCELLANEOUS 'ABNORMAL PLANT CONDITIONS . ..

-" i EMERGENCY, - CA KNPP INDICATION ?,." . *,*. CLASSIFICATION CRITERIA, TcLAssIFICATION (1) Containment boundary failure or potential' Other plant conditions that make a GENERAL failure: I x ,- - , ..- release of large amounts of EMERGENCY

. radioactivity in a short time period

a. Containment pressure > 46 piig, 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

Ž 10% hydrogen concentration, 30 minutes without Safety Injection and Residual Heat AND Removal flow. Plus a containment failure is (2) Loss of core cooling capability: imminent.

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

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

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

(1) Evacuation of Control Room (E-O-06 event). Evacuationof controrolroom 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 lant Manager or his designate. This is to plant staff or state and/or local determine if conditions are applicable for authorities.

activating the E.P.

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

Table 2-1 EPIP-AD-02 Rev. AE Date: NOV 26 2002 Page it) of 2 1 REFERENCE USE

°CHARTXK*. ' -' * :

FIRE ANDFIRE PROTECTION . . .

...N.P6 I -DC"TIONEMERGENCY CLASSIFICATION

-P INDICATION,,-",, ":" CLASSIFICATION CRITERIA CLASSIFICATION (1) 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 redundant defeats causing thesafety trains required ESF to ESFofsystem equipment be inoperable.

(1) A fire within the Auxiliary Building, A fire potentially affecting safety ALERT Rooms,safeguards BatteryCenter, alley, systems.

DIG rooms,Support Technical 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 VNUSUAL more than 10 minutes. I more than 10 minutes. EVENT CHART L (DELETED) rage i i 01 Table 2-1 EPIP-AD-02 Rev. AE Date: NOV 26 2002 rage 1it of 2' 1 REFERENCE USE

CHARTM.- ,_ _ _

-EARTHQUAKE

- -- -EMERGENCY KNPP INDICATION CLASSIFICATION . CLASSIFICATION CRITERIA (1) Activation of seismic recorder with TRIGGER, An earthquake greater than SITE OBE, and DBE lightslit 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 damage or verification from University of Wisconsin Seis mc 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 I hour, AND design levels with plant not in EMERGENCY coldshutdown.

(2) Plant above cold shutdown condition. -I i iil --

(1) A tornado which strikes the facility, AND Any tornado striking facility. ALERT (2) Causes damage to render atnsingle l~'.rnnimnm~nt r~s-,ur~tlP1 train of h.innn~rr~hlh.

(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. AE Date: NOV 26 2002 P'age 18 or 2l REFERENCE USE

CHART.O SFL00D',LOW WATER, OR SEICHE -

S' EMERGENCY CLASSIFICATION "K-NkP INýDICATION CRITERIA CLASSIFICATION FOREBAY LEVEL Flood, low water, or Indicated for > 15 minutes - seiche near design ALERT 0 PUMPS 1 PIP 2 PUMPS CORRESPOND levels.

TO LAKE LEVEL NOTE3 NOTE1 >94%

• I 588 ft.

<50%

• NOTE5 NOTE5 < 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 0 PUMPS 1 PUMP 2 PUMPSTOLKLEL TO LAKE LEVEL NOTE2 > 98%* > 88%* > 586 ft.

< 53.1%* <46.9% NOTE5 < 569.5 ft.

NOTE 4 1 _

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

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

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

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

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

NOTE 5: The corresponding forebay level foi 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 toInternational Great Lakes Datum (IGLD), 1955 (IGLD 1955 = IGLD 1985 - 0.7 FEET) rage i. OT ei Table 2-1 EPIP-AD-02 Rev. AE Date: NOV 26 2002 Page 19 of 21 REFERENCE USE

CHART P, EXTERNAL EVENTS AND CHEMICAL SPILLS S . . .. - .. EMERGENCY KNPP INDICATION ,, CLASSIFICATION CLASSIFICATION, "P " "* .'-CRITERIA

"..Aircraft crashimpac affecting vital 'SITE (1) An aircraft crash intoplant b'uildings which causes I EMERGENCY_

strucures by i t a complete loss of an ESF function.

(1) A mie s s pSevere'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 (1) Release of flammable or toxic gas from a ruptured or flammable gas is confirmed EMERGENCY container, which causes or is likely to cause within vital area.

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

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

(1*)A missile strikes the facility A causes a sinle -Missile impact from .. whatever ALERT train of required ESF equipment to be inoperabte.

Uncontrolled release of toxic ALERT or flammable gas is confirmed (1) Release of toxic or flammable gas at life within the protected area.

threatening levels from a rupturedsafecontainer enter area AND impacts operation oft the protected 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 f6r 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.

NUV b ZUU Date: NOV 2R6 2EU ry u OH £ I Table 2-1 EPIP-AD-02 Rev.

2-1 EPIP-AD-02 Rev. AE AE Date:

REFERENCE USE raige 2ou o, z- I

sCICHARTQ

'SECURITY CONTNEC Jr-_7-

- EMERGENCY KN.PP.INDICATION..

S CLASSIFICATION - CLASSIFICATION P I -- ", .- CRITERIA (1) Physical attack on the plant that has resulted in', L6ss*ofphysidal control of the GENERAL unauthorized personnel occupying the control plant. EMERGENCY room or any other vital areas as described in r.

the Security Plan. -. _ ____

(1) Physical attack on the plant involving Imminent loss of physical SITE iminuent occupancy o6 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 Hevel 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.

F. E4 -'

rdyI Ut LI Table 2-1 EPIP-AD-02 Rev. AE Date: NOV 26 2002 I-age. I"oi ui- 1 REFERENCE USE

>11 . :ISONSIN PUBLIC SERVICECORP. A , No.

Title

-.;>,?EPIP-OSF-02 -, Rev. V

-,

Ojei-aiional Support Facility Operations t..:*.,kKewaunee Nuclear Power Plant ,

I

.Flrnerencv Plan -Ttlement n* Procedure Date ,,- ' -,,NOV-26 2002 ,,,Page" of Safety Reviewed .. By Dave Seebart . IApproved 0ByN TL. Yarosz W.O poroar _0 NReviewP Nuclear , -'PORC - Yes Temproval Of 0 Yes Related 0 No Required El.0 Changes Required No 1.0 Purpose 1.1 This procedure provides instruction for the Operational Support Facility (OSF) Staff when responding to an Alert, Site Emergency, or General Emergency.

2.0 General Notes 2.1 None 3.0 Precautions and Limitations 3.1 Ensure accountability of personnel and OSF Staff reporting to the OSF is maintained throughout the incident (See "Personnel Assembly and Accountability," EPIP-SEC-03) via the Technical Support Center (TSC) Area Accountability Coordinator.

3.2 A radiation survey of designated OSF assembly area or use of a portable radiation monitoring instrument for verification of habitability will be performed per "TSC and OSF Activation Checklist," Form EPIPF-TSC-02-01.

3.3 If it becomes necessary to evacuate the designated OSF assembly area, then a minimum staff will be maintained in the lower TSC. Additional OSF support personnel will be evacuated per "Personnel Evacuation," EPIP-SEC-05. .. . .. ..

3.4 If it becomes necessary to evacuate' or relocate the TSC and the OSF, then use the guidance in Section 5.5 to assist in relocating the personnel and functionality of the OSF.

4.0 Initial Conditions 4.1 This procedure shall be implemented upon declaration of an Alert, Slte Emergency, General Emergency, or when directed by the Shift Manager (SM) or Emergency Director (ED).

j.\appdata\procpws\draftVepip\eosfO2.doc-Chdstine Simmons/Christine Simmons-T-mn Dolski REFERENCE USE

.. ';WISCONSIN PUBLIC SERVICE'CORP. No:-`:* '-EPL-OSF02 Rev. V 7t-- -

. " Title Operational Support Facility Operations 4 , k. Kewaunee Nuclear Power Plant ,*:  %

E.m ergencyPlan Ithlementing'Procediure,p- Date .A ,NOV 26 2002  : Page 2 of 7 --

5.0 Procedure 5.1 Fire Team and Repair Team Accountability .

5.1.1 Fire Team

a. IF you have not been notified that a fire exists, THEN proceed to your assigned Turn Out Gear location.

" Report the team member names to the SM or Event Operations Director (EOD).

" Upon completion of initial accountability, if the Fire Team is not required, report to Accountability Location as follows:

1. Admin. Team to ATF-1 Accountability Location

2. Annex Team to Warehouse Accountability Location

b. IF you have been notified that a fire exists, THEN:

"* Upon hearing the plant siren, assemble and account at your Turn Out Gear Lockers (Admin. and Annex).

"* If time permits, one team member should locate the nearest Gai-tronics, telephone, or portable radio, and report the names and locations of the fire team members to the SM or EOD.

"* Respond to the fire keeping the SM or EOD informed of your actions.

c. During subsequent soundings of the plant alarm: -

IF you are in the field investigating or fighting a fire, THEN do NOT report to an Accountability Location.

• IF time permits, THEN one team member should locate the nearest Gai-tronics, telephone, or portable radio and report the names and locations of the team members to the SM or EOD.

• IF time does not permit, THEN proceed with your emergency duty regardless of accountability concerns.

R N

._ REFERENCE USE

- WISCONSIN PUBLIC SERVICECORP . No. EPIP-OSF-02 2 _ Rev. V-

, .- I Title Operational Supp6rt Facility" perations Isff Kewaunee Nuclear Power Plant -c.,'*;,

Zt - .

"/ "Emerhgency Plan mplementing Procedure- ... Date . - NOV 26 2002 'Page 3 of 7>--

5.1.2 ERO Repair Teams

a. IF you have not been contacted by the SM, Support Activity Director (SAD), or a Maintenance Supervisor in regards to performing an emergency duty, THEN proceed to the OSF upon hearing the plant siren.

b. IF you have been contacted by the SM, SAD, or Maintenance Supervisor and have been instructed to (1) perform an emergency duty, (2) report to the OSF, or (3) report to another area in response to the emergency (e.g., obtain equipment or tools), THEN:

", Upon hearing the plant siren,'locate the nearest Gai-tronics or telephone and contact the SM, SAD, or Maintenance Supervisor (whomever contacted you) to report your location.

"* IF you are continuing on to another area, THEN inform this person.

"* Continue with your emergency duty as instructed.

c. During subsequent soundings of the plant alarm, if you are in the field performing an emergency duty:

"* Do NOT report to an Accountability Area.

Note IF you are actually requiredto leave the area, THEN the OSF Coordinatorwill inform you.

"* Locate the nearest Gai-tronics or telephone and report your location to the OSF Coordinator.

5.2 OSF Coordinator "5.2.1' WHEN notified that an Emergency has been declared:

a. Report to the OSF.

b. IF an OSF Coordinator has been designated, until released, THEN assist the designated OSF Coordinator.

c. IF an OSF Coordinator has NOT been designated, THEN notify the SAD of your intent to assume the responsibilities of the OSF Coordinator and continue implementation of this procedure.

5.2.2 Notify the SAD of your assumption of the responsibilities of the OSF Coordinator.

5.2.3 Obtain the ERO Response binder from the "TSC Material Locker."

5.2.4 Verify an OSF Support Person is available to implement Step 5.3 of this procedure or assign another OSF staff member to this task.

REFERENCE USE

SERVICE CORK.

P.;,-ISCONSINPUBLIC 2 N60." -P EPIP-OSF-02 Rev.'V S...Title Operational Support Facility Operations -

-f"-.- Kewaunee Nuclear Power Pat,.

. EeeyPlImeeigPod- Date NOV,26 2002 '- ,Page 4 of,7 5.2.5 Direct an OSFAssembly:Area'Staff Member to: .:

a. Develop a list of OSF personnel resources by name and emergency duty position.

b. If required, serve as Accountability Coordinator to maintain personnel accountability.

c. Relay briefings during the course of the event.

5.2.6 Notify additional support personnel as needed, using the telephone numbers listed in the KPB Emergency Telephone Directory.

5.2.7 Obtain and maintain knowledge of "work in progress" and "work to be performed" upon arrival at the OSF and throughout the event.

Note Both the OSF and the TSC "High PriorityWork" status boardsmust be in unison.

a. Post the jobs actually in progress with the priority (No. 1-7) assigned by the ED on the "High Priority Work" status board.

b. Post the jobs awaiting team'assignment on the "Lower Priority Work" status board.

5.2.8 Provide updates to the OSF Support Person, SAD, and TSC Data Coordinator as needed, to maintain the "High Priority" and "Lower Priority" status boards current.

5.2.9 Brief the OSF Staff periodically on priority and pending work.

5.2.10 Ensure an OSFiEvent Log of all significant events and actions is maintained. Including as a minimum: . +,

a. Date

b. Time

c. Significant Event/Action

d. Name of person information was received from or sent to

e. Initials of person making log entry 5.2.11 Assist the SAD as required for evaluation of equipment and material necessary to support the emergency response organization.

5.2.12 Assist the SAD in the review of work requests and the planning and scheduling of K>, work as required.

REFERENCE USE

V

-:,.WISCONSIN PUBLIC SERYiCECORP. No. EPP-OSF-02 K-, Rev. V

.. ... .- .. Title

. Operational Support Facility Operations

-Kewu'nee Nuclear Power, Plant .

Date- - NOV 262002,. Page5 of7 5.2.13 Implement emergency repair and modifications on plant equipmenit and systems as

.. directed by the SAD in accordance with "Work Requests During an Emergency,"

EPIP-OSF-03_.

a. Ensure pre-job briefings are conducted using "Operational Support Facility Team Briefing," Form EPIPF-OSF-03-01.

5.2.14 Implement search 'and rescue operations as directed by the SAD in accordance with EPIP-OSF-04.

5.2.15 Provide manpower, equipment, and material necessary to support the emergency organization.

5.2.16 Support accountability of OSF staff members through the designated Accountability Coordinator in the TSC.

5.2.17 If appropriate, plan a shift relief for OSF Support Personnel per "Emergency Response Organization Shift Relief Guideline," EPIP-AD-05.

5.2.18 IF Final Conditions (Section 6.0) have NOT been met, THEN return to Step 5.2.7.

K-)

5.2.19 WHEN Final Conditions are met (Section 6.0):

a. Verify all work areas are returned to normal status and emergency procedures, forms, etc., are returned to their proper place.

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

5.3 OSF Support Person

-5.3.1 WHEN notified that an Emergency has been declared:

a. Report to the OSF.

b. IF an OSF Support Person has been designated, until released, THEN assist the designated OSF Support Person.

c. IF an OSF Support Person has NOT been designated, THEN notify the OSF Coordinator of your intent to assume the responsibilities of the OSF Coordinator and continue implementation of this procedure.

5.3.2 Ensure that copies of "Operational Support Facility Team Briefing,"

Form EPIP-OSF-03-01, are available.

5.3.3 Maintain OSF Status Boards as directed by the OSF Coordinator.

REFERENCE USE

"WISCONSIN PUBLIC SERVICE C0RP.-?.-' No.'-! '-,EPIP-OSF-02 Rev. 'V " .

. .. .. . -_'-,- Title Operational Support Facility Operations

,ý,Kewaunee NuclearPower Plant cyPlan niImeninProcedure ,:I Date - ,. -. NOV, 26 2002 Page 6 of 7 5.3.4 Maintain an "OSF Event Log" of significant events, announcements, and OSF Coordinator priorities.

5.3.5 Record incoming and outgoing ad hoc telephone messages on "Telephone Communications Log Sheet," Form EPIPF-EOF-04-02.

5.3.6 Inform the OSF Coordinator promptly of information received from maintenance teams in the field or other support organizations.

5.3.7 When requested, make document copies.

5.4 Operations Staff Support 5.4.1 Operations Staff reporting to the OSF may be needed to support the Control Room or the OSF. Priority should be given to the Control Room for the use of their time.

Note The dispatch of OperationsPersonnelfrom the OSF must be coordinated between the EOD and the ED to prevent conflicting or redundantassignments.

SROs in the OSF need to make sure that they do not compromise the decisions or prioritiesof the on shift Shift Manager.

5.4.2 Operations Staff in the OSF may be asked to provide support for:

a. Tag-out preparation.

b. System and component location information.

c. Work package preparation.

d. Direct assignment to maintenance repair teams.

5.5 --IF it becomes necessary to relocate or evacuate the"OSF/TSC', THEN the following guidance should be utilized to maintain the functionality of the OSF:

a. OSF Assembly Area personnel should be relocated with the guidance and direction of the Radiological Protection Director (RPD) and may be concurrent with the relocation of the Radiological Assessment Facility.

b. The OSF Coordinator should relocate with the OSF Assembly Area and establish and maintain communications with the Support Activities Director.

c. Team tracking and logging activities should be maintained and continued at the new OSF location in accordance with Section 5.2.

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

-ý'WISCONSIN PUBLIC SERVICE CORP.'*- No. '  %'.,v1,,EPlP-OSF-02 Rev. V,

.-e . : . Title Operational Support Fadility Operations-Kwaunee Nuclear' Poer Plant

Emergency

-- Plan Implementing Proceure. Date ,, r NOV 26.2002 Page 7of 7,z--:

7.0 References "

7.1. ,.Kew'aunee Nuclear Power Plant Emergency Plan t 7.2 EPIP Appendix A-i, Communication System Description 7.3 EPIPrAD-05, Emergency Response Organization Shift Relief Guideline 7.4 EPIP-OSF-03, Work Requests During an Emergency 7.5 EPIP-OSF-04, Search and Rescue 7.6 EPIP-SEC-03, Personnel Assembly and Accountability 7.7 EPIP-SEC-05, Personnel Evacuation 7.8 EPIP-TSC-02, Technical Support Center Activation 8.0 Records S 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

" OSF Event Log

"* Telephone Communications Log Sheet, Form EPIPF-EOF-04-02

"* Operational Support Facility Team Briefing, Form EPIPF-OSF-03-01 8.1.2 Non-GA Records None REFERENCE USE

-WISCONSIN PUBLIC SERVICE CORP *- No. EPIP-SEC-03, Rev. :AF ,

. Title- Personnel Assembly- nd Ac'c:muntability 2 *.; *:Kewaunee Nuclear Power Plant - '

i-u*megen-y Plan ImplementingkPrboedure .... . .Date *'X4 NOV26 2002 . Page 1 of 11-,'

Reviewed By Russ Kroening Approved By W. L. Yarosz Nuclear *1 " 'PORC SRO Approval Of Safety Review b Y" N Temporary "Y 21 No Required 0 o yl Changes Required No Related 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-01, "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) Lunchroom - 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 interiorrooms 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) j-\appdata\procpws\draft\epip\esec03.doc-Diane Fenc/Diane Fend-Jeanne Ferris REFERENCE USE

WISCONSIN PUBLIC'SERVICE RPi.z.7Z No.:'-:, -"EPIP-SEC-03" .". , Rev. AF

,. . . Title Personnel Assembly and Accountability

.. "~ :*,Kewaunee Nuclear Power Plant ;"' ; . . .. .

"EmergencyPlan Implementing'Procedure,..* Date -.:, NOV 26 2002 , . Page 2 of 11'1/4 3.0 Precautions and Limitations -'2,, - - - .

"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 "directedby 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 CORPIk No `",,EPJP-SEC-03 Rev. - AF Ttle Personnel Assembly and Accountability

-;---,,*-.Kewaunee Nuc -, P ant;.--;.,.

Power -

a -Im r ...... 'Plan r lementin-;Proceree-" _- Date ., : NOV'26 2002 ...-Pag 33 of 11 of -1....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. I 5.1.8 IF attempts fail to locate personnel who are unaccounted for, THEN direct the Central Alarm Station (CAS) or SecondaryAlarm 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:

"B"Attentionall 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 PUBLICQSERVICE'CORP-.

_- - ,EPIP-SE. No.-

N -- 3'..... Rev.

"" Title Personnel Assembly, and Accountability

-:1Kewaunee Nuclear Power Plant :. - '

' :,Eergency

--. ':.l P'Ia:ýni lmnepiM!-ening ,roceaure Date;,ý., -NOV26 2002', Pae 44 of Pa-ge" 11.....

of 11

""s 5.2 Master Accountability Coordinator (MAC) shall:,

5.2.1 WHEN accountability 'isrequired:

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 5.2.1.d.

5.2.2 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.

-5.2.3 Contact each Accountability Coordinator by phone to confirm visitor log.

Note CAS or SAS shall print the Emergency Report ten minutes after the Emergency Accountability Programhas started.

5.2.4 IF you have not received the Emergency Report, THEN contact CAS or SAS to obtain it.

5.2.5 Should attempts fail to locate personnel who are unaccounted for, direct the CAS or SAS to run a computer report on that person.

REFERENCE USE

"* ,*' WISCONSIN PUBLIC SERVICE CORP No., ýEPPWSEC-03*. "-:. , Rev., ,AF A

,., .. -Title Personnel Assembly and Accountability I....---Kewaunee Nuclear. Power Plant ,..

Emergzncy Plan IMplementing,Procedure .*.. Date..... NOV 26 2002, *_ Page 5 of 5.2.6 -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.

5.2.7 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.

5.2.8 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.

5.2.9 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.

5.2.10 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.

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

5.2.12 If appropriate, plan a shift relief for the MAC perEPIP-AD-05.

5.2.13 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.

REFERENCE USE

-WISCONSIN PUBLIC SERVICE CORP.:.-... . No. 'EPJP"SEC.0 Rev AF ,

~u ea Po Plan 'YTil Pers~finhel Assembly ind A6counitability

--Kewaunee Nuclear Power Plant Datenm;,0,, 'NOV,26 2002 . Page -;. C6of 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 listfor the MAC of FireBrigade Members, NAOs, and dispatched Emergency Teams that are accountabilityexempt.

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) - Lunchroom on the southwest wall near the Gai-tronics.

5.3.3 Locate yourself near the SMS accountability card reader... . .

Note Visitors have non-magnetic badges, so they should NOT swipe their key card in an accountabilitycard 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.

REFERENCE USE

.ISCONSINPRUBLICS ERVIC E;C.O P.,7" _`J` i No., EPIP-SEC-'03 ' Rev. 'AF i

Title Personnel Assembly and Accountability IKweeNuclear Power Plant "*

1___ 1 -.

• EmergencPlan Implemienting Procidure Date--,-, -NOV 26 2002, .I Page 7 of1l I V I I m

-5.3.5 IF a Director or Supervisor iotifies 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.

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

Acronym Area ForAnother Accountability Area CR Control Room RPO Radiation Protection Office TSC Technical Support Center WA Warehouse Annex Lunchroom ATF Administrative Training Facility Lunchroom ForRepair 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 REFERENCE USE

!i*:--- WISCONSIN PUBLIC SERVICE CORP7.': N No.?.. EPIP-SEC-03 - , Rev. AF '

Title Personnel Assembly and Accountability

-- K6 Nuclear Power Plint. <

Th:*:.*.EmIer encyMelaz er ea Date..... NOV ,26 2002 , . ,YPage 8,of ,1 > ,-.

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 nunibers 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.

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.

REFERENCE USE

-WISCONSIN'PUBLIC SERVICECORP No.~~PPSC~3 ~ Rv Title Personnel Assembly and'Acý0-o'nabit

&,2--,4 ý_W.-ew~au nee Nuclear~ Power, Plant

• 7.>-Emerken Ha Plan Iih-flemientinkProcur re

.Dae ,...NO 6 20 -,IZ 1V ag9o.1 agAfJ 5.3.1 IF Final Conditions (Section 6.0) are met, THEN -

Note , -

Flag any discrepanciesto emergency supplies that need corcin

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 MA:C to update'the accountability roster as necessary.

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

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 EPlP-SEC-04, "Security Force Actions for Dosimetry Issue."

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-Ol, 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 EPJP-SEC-04, Security Force Actions for Dosimetry Issue REFERENCE USE

-WISCONSIN PUBLIC SERVICE CORP... No' --k-"EPIP-SEC-03 I Rev., AF Title Personnel Assembly and Accountability

, Emerwauny PNuclearmoen "Pr i -

-Eirgnj~iýblyj~fn 26 2002, ,. Page 10 of 11,

- I Date' .... NOV,26 8.0 Records -

8.1 The following QA1recbrds 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-CA Records

• Emergency Accountability Log, Form EPIPF-SEC-03-01 REFERENCE USE

ACCOUNTABILITY AREAS,.,

(Inside the Protected Area)

LOCATION PHONE NUMBER.

"Conti6l Robi ... - 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 Trainine Facilitv (Basement) 6548 Warehouse Annex (Locker Room) 6454 ACCOUNTABILITY AREAS (Outside the Protected Area)

LOCATION PHONE NUMBER Security Building Classroom C 6548 Simulator Training Facility (Lunchroom) 6534 ALTERNATE LOCATION PHONE NUMBER Securitv Locker Room (Security Building) 8292 Simulator Training Facility (Simulator Control Room) 8607 ACCOUNTABILITY LEADERS tt' 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 r..44 II UIa44 El Table 1 EPIP-SEC-03 Rev. AF Date: NOV 26 2002 rage9 I I ol a I REFERENCE USE

-- %WISCONSIN PUBLIC SERVICE CORP.'- No EPIP-TSC-08A' >9.'.' Rev. '0

" ........ Title Calculations for Steam Release from Kewaunee Nuclear Power Plantn Steam'Generator's

,,,*.,',",*:Eme*'genc'y_*Plan Imp~~lementingPrcdue Date -, "* NV2 00 -- Page I of6*

-*:mi ":- ProcdiikJ.* Dat -;NOV 26 2002 '*D if Reviewed By John Helfenberger Approved '-By ~SRO W. L. Yarosz Approval Of [ e Nuclear 0 Yes' PORC -, - 0 Yes Apov0 Yes Safety , r Review Temporary .

Related 0l No Required - ,.t , 0 No Changes Required 111 No 1.0 Purpose 1.1 This procedure provides instruction for calculating the steam release rate in cc/sec to the environment from a faulted steam generator with a tube rupture in the same generator.

2.0 General Notes 2.1 The calculation for steam 'release may be performed using the PC Program STMIRLS or manually. Step 5.1 of this procedure is used when the computer calculation is performed.

Steps 5.2 or 5.3 are used when performing a manual calculation.

3.0 Precautions and Limitations 3.1 None 4.0 Initial Conditions 4.1 This procedure applies when the reactor is shutdown with or without reactor coolant pumps running. The core Delta-T and faulted steam generator pressure is relatively stable. The faulted steam generator is the only steam release path. The fault may be on any unisolated portion of the steam generator or steam line.

5.0 Procedure 5.1 Steam Release Calculation Using PC Program STMRLS Note IF steam release is due to an open steam generatorPORV or safety valve, THEN only Steps 5.1.1(a) and 5.1.1(g) need to be perforned.

5.1.1 Record the following data on Form EPIPF-TSC-08A-04:

a. Release due to open PORV or safety valve (YIN).

b. Reactor power prior to reactor shutdown (MWth).

c. Number of days that reactor was at power.

d. Time since reactor shutdown (min).

j:.appdata\procpws\draft~epip\etscO8a.doc-Christine Simmons/Christine Simmons-Ed Coen REFERENCE USE

_ ,_ :WISCONSIN PUBLIC SERVICE CORP. No EPJP-TSC-08A Rev. ,' O

. . ... Title Calculations for Steam Relea-e'froi*"

";IKewaunee Nuclear Power Plant,-, ' . Steam Generators .

Emergency Plan Implementing Procedure.,&V- Date , ' - NOV,26 2002- Page 2 of 6

e. Number of operating reactor coolant pumps. IF one or two reactor coolant pumps are running, THEN record RCS average temperature from loop with running reactor coolant pump. IF zero reactor coolant pumps are running, THEN record wide range hot leg and cold leg temperatures for each RCS loop.

f. RCS average pressure (psig).

g. Ruptured steam generator pressure (psig).

SIF ruptured steam generator pressure is approximately the saturation pressure for RCS average temperature, THEN a steam release projection is available.

h. Intact steam generator pressure (psig).

i. Safety injection flow rate (gpm).

j. Total auxiliary feedwater flow rate to intact steam generator (gpm).

Note Ensure that a PC and printerare set up in the lower Technical Support Center.

5.1.2 Log into the KNPP Network using your own Network ID and Password.

5.1.3 Click on the Steam Release Icon on the menu bar.

5.1.4 IF the network is unavailable, THEN:

a. Turn OFF the computer.

b. Retrieve the diskette labeled EPIP-TSC-08B, "STMRLS Computer Program," from the TSC emergency supply cabinet. (See EPIP-TSC-08B for alternate diskette locations.)

c. Insert the diskette into the PC's disk drive.

d. Turn the computer ON. After approximately 20 seconds, the computer will begin to execute the program.

Note A steam release "projection" is availableif rupturedsteam generatoris approximately equal to saturationpressurefor RCS average temperature.To enable the projection, enter "0 "for rupturedsteam generatorpressure. This tells the computer that the rupturedsteam generatoris saturatedat RCS temperature.

5.1.5 Input the data from Form EPIPF-TSC-08A-04 into the program. The program will prompt all required inputs.

REFERENCE USE

--WlscoNsPUBLIC SERVICE CORP...

• No. ,-. ;'*,EPlP-TSC-O8A, - Rev. - 0, Title Calculations for Steam Release from

1. ewaunee Nuclear Power-Plant *,,.-.

- Steam Generators Date;,, -,NO V.26 2002,,,

-I Page 3 of 6 V

• • 1

[ "Emergncy= .

Imlementin 5.1.6 -Record the steam release rate on Form EPIPF-TSC-08A-04.

5.1.7 IF a steam release projection is made, THEN note the general trend (increasing or decreasing) of the steam release. Do not use the projection release rates. The projection is for trending purposes only.

Note The letters under blanks on the calculationsheet match the letters on the data sheet.

Note IF steam release is due to an open PORV or safety valve, THEN perform Step 5.3.

5.2 Steam Release Calculation Using an Energy Balance Across RCS 5.2.1 Heat Input from the Reactor and Reactor Coolant Pumps 5.2.1.1 Record the following data on Form EPIPF-TSC-08A-01:

a. Time elapsed since reactor trip.

b. Decay heat using Reactor Data Manual, Section RD 11.2 or below tabulation (the Reactor Data Manual and table below assume 100%

power for 300 days prior to reactor trip).

RATE OF PRODUCTION OF DECAY HEAT FOLLOWING SHUTDOWN TIME AFTER SHUTDOWN  % OF FULL POWER 1 second 6.37 1 minute 12.69

.30 minutes 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 1.06 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 0.63 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 0.46 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 0.37

c. Number of reactor coolant pumps running.

5.2.1.2 Use Formula 1 on Form EPIPF-TSC-08A-02 to calculate the heat input in Btulsec.

REFERENCE USE

_=-WISCONSIN PUBLIC SERVICE CORP.,a-.-'ý. No.C Rev.,

- . . Title Calculations for Steam Release from

- .,Kewaunee Nuiclear Power Plant . Steam Generators I iikPddj~ Date -~ NOV 26 2002 Pae4o6 5.2.2 Heat Input from the Reactor Coolant System 5.2.2.1- -*Record the following data on Form EPIPF-TSC-08A-01:

a. With one or two RXCPs running, record Tare from loop with running reactor coolant pump.

b. With zero running, record RCS wide range hot and cold leg temperatures for each loop.

c. Reactor Coolant System pressure.

d. Using steam tables, calculate the Enthalpy (hf) at RCS temperature and pressure.

e. Using steam tables, calculate the Specific Volume (Vf) at RCS temperature and pressure.

f. Safety injection total flow using F8002G (FI-924) and FS001G (FI-925).

5.2.2.2 Use Formula 2 on Form EPIPF-TSC-08A-02 to calculate the heat input in Btulsec.

5.2.3 Heat Input from Auxiliary Feedwater Flow 5.2.3.1 Record the following data on Form EPIPF-TSC-08A-01:

a. Intact steam generator pressure.

b. Using steam tables, calculate the saturated liquid Enthalpy (hf) at intact steam generator pressure:

c. Auxiliary feedwater total flow using FI-18201 and FI-18202 (Control Room).

5.2.3.2 Use Formula 3 on Form EPIPF-TSC-08A-02 to calculate the heat input in Btu/sec.

REFERENCE USE

I PIIRI FRVICE CORP&iNoF .:'EPJP-TSC-O8A IRev. 0 ]

Title Calculations for Steam Release froifi

-*ewaee Nuclear Power Plant ,Steam Generators

Emergency PlanaImplementing Procedure 26 2002 Page 5 of 6

---

5.2.4 Steam Release Calculation 5.2.4.1 Record the following data on Form EPIPF-TSC-08A-01:

a. Faulted steam generator pressure.

b. Using steam tables, calculate the Latent Heat of Vaporization (hfg) at faulted steam generator pressure.

c. Using steam tables, calculate the Specific Volume (V,) at faulted steam generator pressure.

5.2.4.2 Use Formulas 4 and 5 on Form EPIPF-TSC-08A-02 to calculate the steam release in cc/sec.

5.3 Steam Release Calculation Due to Open PORV or Safety Valve 5.3.1 Steam Generator Parameters 5.3.1.1 Record the following data on Form EPIPF-TSC-08A-03:

a. Valve that is open (PORV or safety).

b. Discharge area for the open valve: PORV area is 0.0474 ft2 and for 2

the safety, the area is 0.0983 ft .

c. Faulted steam generator pressure.

d. Using steam tables, determine the saturation temperature.

5.3.2 Steam Release Calculation

a. Using Equation 1, determihe the steam velocity.

b. Using Equations 2 and 3, calculate the steam release rate.

6.0 Final Conditions 6.1 The emergency declaration is closed out, OR 6.2 The steam release is terminated, OR 6.3 The plant has been stabilized, recovery operations have been entered, and it has been determined that any steam release does not present a hazard to the public. (Projections indicate doses from a release are below Technical Specification Limits at the Site Boundary.)

REFERENCE USE

-wISCONSIN PUBLIC SERVICE CO;ORP-.:N '.' EPIP-TSC-08A°.:*:' -,*,"°,' : Rev.,.O--

• :- ,Kewaunee Nuclear Power Plant i Title Calculations for Steam Release from '"

Steam Generators . -

-NOV26,2002: -Page 6 of 6.,_ ,

• Emergency'Plan'Implem'en'tingProceduire*-]/-2 Date I I I 7.0 --References 7.1 - Reactor Data Manual, Section RD 11.2, Reactor Decay Heat 7.2 Startup Test 3.9, Reactor Coolant System Steam Rate Without Nuclear Heat 7.3 Steam Tables, Properties of Saturated and Superheated Steam 7.3.1 Table 1, Saturated Steam: Temperature Table 7.3.2 Table 2, Saturated Steam: Pressure Table 7.4 EPIP Appendix B, Forms 7.5 EPIP-TSC-08B, STMRLS Computer Program 7.6 COMTRAK 89-029 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

"* Steam Release Data Sheet (Energy Balance), Form EPIPF-TSC-08A-01

"* Steam Release Calculation Sheet (Energy Balance), Form EPIPF-TSC-08A-02

" Steam Release Data/Calculation Sheet -(Open Valve), Form EPIPF-TSC-OSA-03

• Steam Release Data/Calculation Sheet (STMRLS Program), Form EPIPF-TSC-08A-04 8.1.2 Non-QA Records None REFERENCE USE