ML012690151
| ML012690151 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee  |
| Issue date: | 09/18/2001 |
| From: | Webb T Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| -RFPFR, NRC-01-098 | |
| Download: ML012690151 (34) | |
Text
NRC-0 1-098 Kewaunee Nuclear Power Plant N490, State Highway 42 N m~ Kewaunee, WI 54216-9511 920-388-2560 Committed to Nuclear Excellence Operated by Nuclear Management Company, LLC September 18, 2001 10 CFR 50, App. E U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Ladies/Gentlemen:
DOCKET 50-305 OPERATING LICENSE DPR-43 KEWAUNEE NUCLEAR POWER PLANT RADIOLOGICAL EMERGENCY RESPONSE PLAN IMPLEMENTING PROCEDURES Pursuant to 10 CFR 50 Appendix E, attached is the latest revisions to the Kewaunee Nuclear Power Plant Radiological Emergency Response Plan Implementing Procedures (EPIPs). These revised procedures supersede the previously submitted procedures.
Pursuant to 10 CFR 50.4, two additional copies of this letter and attachment are hereby submitted to the Regional Administrator, U. S. Nuclear Regulatory Commission, Region III, Lisle, Illinois. As required, one copy of this letter and attachment is also submitted to the Kewaunee Nuclear Power Plant NRC Senior Resident Inspector.
Sincerely, Thomas J. Webb Site Licensing Director SLC Attachment cc - US NRC Senior Resident Inspector, w/attach.
US NRC, Region III (2 copies), w/attach.
Electric Division, PSCW, w/o attach.
QA Vault, w/attach.
KEWAUNEE NUCLEAR POWER PLANT September 18, 2001 EMERGENCY PLAN IMPLEMENTING PROCEDURES TRANSMITTAL FORM RETURN TO DIANE FENCL - KNPP OUTSIDE AGENCY COPIES (1-20)
T. Webb - NRC Document Control Desk (1)*" Bill Yarosz - Wisconsin Electric Power Co. (10)*
T. Webb - NRC Region 11 (2 & 3)* Craig Weiss - Wisconsin Power & Light (11)*
T. Webb - NRC Resident Inspector (4) (receives Appx. A phone numbers)*
T. Webb - State of Wisconsin (5)* Jim Holthaus - Nuclear Management Company (12)*
T. Webb - KNPP QA Vault w/NRC Letter (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. Mielke (35) H. Kocourek (13) K. Hoops (28)
D. Masarik (32) D. Seebart (24) B. Bartelme (34)
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.
STF (86, 87, 88) LOREB - STF (62, 66, 67, 68, 70, 72, 73, 74)
L. Welch - Fuel Services (65) STF Library (43)
NO Library - KNPP (59) Resource Center (82, 89, 94, 131)
C. Sternitzky - ATF-2 (44) D. Schrank - Maintenance Off. (41)
D. Braun - ATF-3 (45) D. Krall - CR/SS Office (51, 56)
P. Ehlen - I&C Office (42) P&FS Adm - GB-D2 (Nuclear Library) (84)
M. Daron - Security Building (46) H. Kocourek - TSC (50)
P&FS Adm - GB D2-3 (EOF) (81) W. Galarneau - RAF (53)
H. Kocourek - OSF (52) W. Galarneau - SBF/EMT (54)
C. Hutter - ATF-1 (64) T. Schmidli - RPO (55)
WORKING COPIES (101-199) These copies of procedures are kept in the areas designated for use in response to an emergency. These are not complete sets, but contain only those procedures that are used to implement activities in the location where they are kept. Please dispose of any sections distributed that are not tabbed in the indicated copy.
W. Galarneau - RAF/RPO (106, 107) D. Krall - CR/Communicator (I1 6 )(Paral Disitrbution)
W. Galarneau - SBF/ENV (108, 109) Simulator/Communicator (117)
W. Galarneau - SBF/EM Team (110, 111, 111A) J. Fletcher - Security (121)
W. Galarneau - Aurora Medical Center (118, 119) N. Deda - Security Building (120)
W. Flint - Cold Chem/HR Sample Room (113) S. VanderBloomen (125)
N. Deda - SBF/SEC (114) J. Stoeger (126)
Originals to KNPP QA Vault Please follow the directions when updating your EPIP Manual. WATCH FOR DELETIONS!!! These are controlled procedures and random checks may be made to ensure the manuals are kept up-to-date.
- THIS IS NOT A CONTROLLED COPY. IT IS A COPY FORINFORMATION ONLY.
1
KEWAUNEE NUCLEAR POWER PLANT REVISION OF EMERGENCY PLAN IMPLEMENTING PROCEDURES September 18, 2001 Please follow the directions listed below. If you have any questions regarding changes made to the EPIPs, please contact Dave Seebart at ext. 8719. If you are a controlled copy holder (see cover page), return this page to Diane Fenci by October 18, 2001, SIGNED AND DATED to serve as a record of revision.
EPIP Index, dated 09-18-2001.
I REMOVE INSERT PROCEDURE REV. PROCEDURE REV.
AA EPIP-AD-02 AB EPIP-AD-02 I CERTIFY Copy No.______ (WPSC No.) of the Kewaunee Nuclear Power Plant's EPIPs has been updated.
SIGNATURE DATE Please return this sheet to DIANE FENCL.
Diane Fend Enclosure 2
EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 09-18-2001 PROC. NO. TITLE REV. DATE EP-AD EPIP-AD-01 Personnel Response to the Plant Emergency H 09-10-2001 Siren EPIP-AD-02 Emergency Class Determination AB 09-18-2001 EPIP-AD-03 KNPP Response to an Unusual Event AB 03-20-2001 EPIP-AD-04 KNPP Response to Alert or Higher AC 03-20-2001 EP-AD-5 Site Emergency Deleted 04-27-87 EPIP-AD-05 Emergency Response Organization Shift Relief C 06-05-2001 Guideline EP-AD-6 General Emergency Deleted 04-24-87 EPIP-AD-07 Initial Emergency Notifications AM 01-30-2001 EP-AD-8 Notification of Alert or Higher Deleted 02-26-96 EP-AD-9 Notification of Site Emergency Deleted 04-27-87 EP-AD-10 Notification of General Emergency Deleted 04-27-87 EP-AD-1 1 Emergency Radiation Controls P 08-10-99 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 N 08-29-2000 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 0 06-05-2001 EPIP-AD- 19 Protective Action Guidelines P 10-31-2000 PAGE 1 OF 11
EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 09-18-2001 PROC. NO. TITLE REV. DATE EP-ENV EPIP-ENV-01 Environmental Monitoring Group Organization U 10-31-2000 and Responsibilities EPIP-ENV-02 Environmental Monitoring Team Activation W 06-15-2000 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 U 02-16-2000 Software EP-ENV-3D Revision and Control of ISODOSE II Deleted 02-14-95 EP-ENV-3E Manual Determination of X/Q Deleted 04-24-87 EP-ENV-3F Manual Determination of X/Q (Green Bay Deleted 05-30-86 Meteorological Data)
EP-ENV-3G Manual Dose Projection Calculation Deleted 06-02-89 EP-ENV-3H Protective Action Recommendations Deleted 04-13-90 EPIP-ENV-04A Portable Survey Instrument Use S 06-15-2000 EPIP-ENV-04B Air Sampling and Analysis V 09-12-2000 EP-ENV-4C Environmental Monitoring Teams Deleted 04-13-90 EPIP-ENV-04C Ground Deposition Sampling and Analysis V 09-12-2000 EPIP-ENV-04D Plume Tracking for Environmental Monitoring M 09-12-2000 Teams EP-ENV-5A LCS-1 Operation Deleted 04-14-86 EP-ENV-5B MS-3 Operation Deleted 04-14-86 EP-ENV-5C SAM II Operation Deleted 04-14-86 EP-ENV-5D PAC-4G (Alpha Counter) Operation Deleted 04-14-86 EP-ENV-5E Reuter-Stokes Operation Deleted 08-27-85 EP-ENV-6 Data Analysis, Dose Projections and Protective Deleted 12-21-81 Action Recommendations PAGE 2 OF 11
EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 09-18-2001 PROC. NO. TITLE REV. DATE 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-2 Emergency Operations Facility (EOF) Activation X 10-24-2000 EPIP-EOF-03 Corporate Action for Unusual Event Z 06-01-2000 EPIP-EOF-04 Corporate Action for Alert or Higher AF 06-01-2000 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 S 09-26-2000 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 T 06-01-2000 Flow EPIP-EOF-12 Media Center/Emergency Operation P 07-19-2001 Facility/Joint Public Information Center Security PAGE 3 OF 11
EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 09-18-2001 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 S 08-29-2000 EPIP-OSF-03 Work Requests During an Emergency N 09-12-2000 EP-OSF-4 Operational Support Facility Communications Deleted 04-24-87 EPIP-OSF-04 Search and Rescue D 09-12-2000 EP-RET EP-RET- 1 Radiation Emergency Team Organization Deleted 04-16-96 EPIP-RET-02 In-Plant Radiation Emergency Team S 06-05-2001 EPIP-RET-02A RPO - RAF Activation R 06-05-2001 EP-RET-2B Gaseous Effluent Sample and Analysis Q 03-03-98 EP-RET-2C Containment Air Sampling and Analysis Deleted 03-01-83 EPIP-RET-02D Emergency Radiation Entry Controls and M 06-12-2001 Implementation EP-RET-2E Handling of Injured Personnel Deleted 04-16-96 EP-RET-2F Personnel Decontamination Deleted 04-13-90 EPIP-RET-03 Chemistry Emergency Team 0 02-01-2000 EP-RET-3A Liquid Effluent Release Paths K 01-12-99 EP-RET-3B Post-Accident Reactor Coolant Alternate Deleted 01-25-88 Sampling Procedure EP-RET-3C Post Accident Operation of the High Radiation 0 01-18-2000 Sample Room PAGE 4 OF 11
EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 09-18-2001 PROC. NO. TITLE REV. DATE EP-RET-3D Containment Air Sampling Analysis Using M 01-18-2000 CASP EP-RET-3E Post Accident Operation of High Rad Sample Deleted 08-27-85 Room Inline Multiported Count Cave EPIP-RET-04 SBF Activation Q 06-12-2001 EP-RET-4A EOF Radiological Monitoring Deleted 03-10-83 EPIP-RET-04A SBF Operation/Relocation D 06-12-2001 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-f Operation Deleted 07-12-94 EP-RET-5 Plume Projection Deleted 09-26-84 EPIP-RET-05 Site Boundary Dose Rates During Controlled G 07-18-2000 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 0 06-15-2000 Center EPIP-RET-09 Post-Accident Population Dose K 08-29-2000 EP-SEC EP-SEC-1 Security Organization Deleted 04-24-87 EPIP-SEC-02 Security Force Response to Emergencies W 08-28-2001 EP-SEC-2A Manual Activation of Emergency Sirens Deleted 04-16-82 EPIP-SEC-03 Personnel Assembly and Accountability Z 09-10-2001 EPIP-SEC-04 Security Force Actions for Dosimetry Issue 0 02-16-2000 EP-SEC-5 Security Force Response to the EOF Deleted 07-28-88 EPIP-SEC-05 Personnel Evacuation F 07-05-2001 PAGE 5 OF 11
EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 09-18-2001 PROC. NO. TITLE REV. I DATE EP-TSC EP-TSC-l Technical Support Center Organization and 0 04-01-99 Responsibilities EPIP-TSC-02 Technical Support Center Activation R 07-18-2000 EPIP-TSC-03 Plant Status Procedure U 06-12-2001 EPIP-TSC-04 Emergency Physical Changes, Major Equipment L 08-29-2000 Repair EP-TSC-5 Technical Support Center Communications Deleted 04-24-87 Equipment EP-TSC-6 Assessment of Reactor Core Damage Deleted 09-30-86 EPIP-TSC-07 RV Head Venting Time Calculation H 03-07-2000 EPIP-TSC-08A Calculations for Steam Release from Steam M 03-07-2000 Generators EPIP-TSC-08B* STMRLS Computer Program E 03-07-2000 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 EP-TSC-9A* Core Damage Assessment I 02-23-99 EPIP-TSC-09B* CORE Computer Program I 03-07-2000 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.
EL-TS-10 1Technical Support for IPEOPs 1 03-20-2001 PAGE 6 OF 11
EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 09-18-2001 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 - A 10-31-2000 EPIP-APPX-A-06 EP-FIG-005 APPX-A-06-02 KNP Floor Plan A _10-31-200 Radiological Analysis Facility - KNP Floor EPIP-APPX-A-06 EP-FIG-oo0 APPX-A-06-01 Plan A 10-31-2000 EPIP-EOF- 12 Division Office Building EP-FIG-009 EOF-12-01 (2nd Floor) Floor Plan B 10-24-2000 Form EPIPF-EOF-02-01 Work State/County Area - WPSC D2-1 EP-FIG-012 APPX-A-06-08 Floor Plan C 10-31-2000 EPIP-APPX-A-06 NRC Work Area EPIP-APPX-A-06 APPX-A-06-09 VEP-FIG-013 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 B 10-31-2000 Map - Location of JPIC, EPIP-EOF-12 EP-FIG-024 EOF-12-02 MBC, GOB, DOB, etc. A 10-24-2000 EP-FIG-026 Site Map A 07-21-98 EP-SEC-5 Floor Plan - Media APPX-A-6 EP-FIG-034 Briefing Center DEL 08-04-98 General Office EPIP-EOF-12 Building - WPSC (lst EPIP-APPX-A-06 EP-FIG-035 APPX-A-06-06 Floor) Floor Plan C 10-24-2000 Floor Plan - Corporate EP-FIG-037 - - - Response Center DEL 08-04-98 APPX-A-6 EP-FIG-o38 - - - Floor Plan - JPIC DEL 08-04-98 APPX-A-6 EP-FIG-039 High Priority Work ORIG 07-08-98 EP-OSF-2 EP-FIG-039A Lower Priority Work ORIG 07-08-98 EP-OSF-2 JPIC - Federal Work EPIP-APPX-A-06 EP-FIG-043 APPX-A-06-10 Area - WPSC D2-9 A 10-31-2000 JPIC - State and County Work Area EPIP-APPX-A-06 EP-FIG-O44 APPX-A-06-07 WPSC D2-8 A 10-31-2000 JPIC - Utility Work EPIP-APPX-A-06 EP-FIG-045 APPX-A-06-05 Area - WPSC D2-7 A 10-31-2000 Aurora Medical Center RET-08 EP-FIG-046 RET-08-01 Location A 06-15-2000 APPX-A-02-01 ERO Call Tree A 01-30-2001 EPIP-APPX-A-02 ---
PAGE 7 OF 11
EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 09-18-2001 NUMBER TITLE REVISION DATE APPENDIX A APPX-A-1 Communication System Description AF 08-04-98 EPIP-APPX-A-02 Response Personnel Call List BK 07-19-2001 EPIP-APPX-A-03 Off-Site Telephone Numbers BM 07-20-2001 EPIP-APPX-A-06 WPSC Emergency Response Telephone Numbers Y 07-30-2001 PAGE 8 OF 11
EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 09-18-2001 FORM EPIPF TITLE REV. DATE APPENDIX B EP-AD AD 7.1 Event Notice (Wisconsin Nuclear Accident Reporting P 02-01-2000 Form)
AD 7.2 State Call-Back - Question Guideline B 04-16-96 AD 11.1 Emergency Radiation Work Permit F 04-16-96 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 B 10-31-2000 ENV-01-04 EMT Orders/Field Data B 10-31-2000 ENV-02-01 EMT Activation Checklist M 06-15-2000 EP-EOF EOF-02-01 EOF Activation Checklist R 10-24-2000 EOF-02-02 EOF Deactivation Checklist K 10-24-2000 EOF 4.1 SRCL Initial Action Checklist B 09-16-97 EOF 4.2 Telephone Communications Log Sheet ORIG 04-16-96 EOF 8.3 Fax for Emergency Declaration or Status Updates F 09-21-99 EOF 8.5 Plant Emergency Status Report ORIG 02-21-95 EOF 8.6 Radiological Status Report C 03-14-97 EOF 11.2 Operating Status E 02-14-95 EOF 11.3 Environmental Status Board E 07-31-95 EOF-12-01 I.D. Badge Registration Form G 10-24-2000 EP-OSF OSF 2.2 Maintenance Work in Progress Deleted 07-08-98 OSF-03-01 Operational Support Facility Team Briefing B 09-12-2000 PAGE 9 OF 11
EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 09-18-2001 FORM EPIPF TITLE REV. DATE EP-RET RET-02A-02 Emergency Sample Worksheet E 06-05-2001 RET 2B. 1 Containment Stack Release (Grab Sample) C 04-16-96 RET 2B.2 Auxiliary Building Stack (Grab Sample) C 04-16-96 RET 2B.3 Auxiliary Building Stack (Sping Reading) C 04-16-96 RET 2B.4 Containment Stack (Sping Reading) B 04-16-96 RET 2B.5 Steam Release C 04-16-96 RET 2B.6 Field Reading (Grab Sample) A 04-16-96 RET-04-01 SAM-2 Counting Equipment Worksheet E 06-12-2001 RET 8.3 Hospital Survey 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 F 06-15-2000 RET 9 Environmental TLD Record Sheet C 02-14-95 EP-SEC SEC-03.01 Emergency Accountability Log A 03-28-2000 SEC 4.1 Emergency Dosimeter Log F 02-16-2000 EP-TSC TSC 1.1 Plant Status Summary for SAM Implementation A 04-01-99 TSC 1.2 Severe Accident Management Summary and Strategy A 04-01-99 Recommendation TSC 1.3 Severe Accident Management - Status A 04-01-99 TSC 2.1 TSC and OSF Activation Checklist N 04-01-99 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 PAGE 10 OF 11
EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 09-18-2001 FORM EPIPF TITLE REV. DATE TSC-02-04 TSC Chart Recorder Operation Checklist D 01-30-2001 TSC 2.5 TSC and OSF De-activation Checklist ORIG 04-01-99 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 H 06-12-2001 TSC-04-01 Emergency Physical Change Request F 08-29-2000 TSC-04-02 Emergency Physical Change Safety Review F 08-29-2000 TSC-04-03 Emergency Physical Change Index F 08-29-2000 TSC-07-01 Head Venting Calculation F 10-31-2000 TSC 8A. 1 Steam Release Data Sheet (Energy Balance) G 02-14-95 TSC 8A.2 Steam Release Calculation Sheet (Energy Balance) F 02-14-95 TSC 8A.3 Steam Release Data/Calculation Sheet (Open Valve) D 02-14-95 TSC 8A.4 Steam Release Data/Calculation Sheet (STMRLS C 04-16-96 Program)
TSC 9A.1 Core Damage Based on Reactor Vessel Level & Fuel Rod C 02-14-95 Temp.
TSC 9A.2 Core Damage Based on Radiation Monitors C 02-14-95 TSC 9A.3 Cs-134 and Cs-137 PCF Determination D 04-16-96 TSC 9A.4 Core Damage Based on Activity Ratios C 02-14-95 TSC 9A.5 Core Damage Assessment (Monitoring Data) D 04-16-96 TSC 9A.6 Core Damage Summary C 02-14-95 PAGE 11 OF 11
1.0 1.1 Purpose This procedure provides instruction for determining proper emergency classification listed in from the Kewaunee Nuclear Power Plant order to activate the appropriate level of response off-site response organization.
emergency response organization and 2.0 General Notes 2.1 None 3.0 Precautions and Limitations exceeded emergency classification levels are being against 3.1 Plant monitors used to determine whether (e.g., compare to declaring an emergency class should be checked for accuracy prior sample channels, determine if consistent with system status, or verification by redundant analysis when required by Chart A(1).
4.0 Initial Conditions evolution that may result in an emergency 4.1 This procedure applies during any plant declaration.
5.0 Procedure referring to if a plant emergency exists during abnormal plant conditions by 5.1 Determine Chart 1, Emergency Action Level Charts.
the required actions of the appropriate 5.2 IF a plant emergency exists, THEN perform emergency procedure listed below:
Unusual Event 5.2.1 EPIP-AD-03, KNPP Response to an or Higher 5.2.2 EPIP-AD-04, KNPP Response to Alert Charts.
referring to the Emergency Action Level 5.3 As plant conditions change, continue be reclassified.
5.4 Determine if the emergency should to step 5.2.
5.5 IF the event is reclassified, THEN return FenclDiane Fend-Dave Lohman n:\nucdoc\procedures\draft\epip\ead02.doc-Diane
met, THEN return to step 5.3.
5.6 IF Final Conditions (Section 6.0) are not be suspended.
met, THEN use of this procedure may 5.7 IF Final Conditions (Section 6.0) are 6.0 Final Conditions Responsible or Recovery actions have begun and the 6.1 Plant Emergency has been Terminated Director has suspended the use of EPIPs.
7.0 References Plan 7.1 Kewaunee Nuclear Power Plant Emergency the Plant Emergency Siren 7.2 EPIP-AD-01, Personnel Response to Unusual Event 7.3 EPIP-AD-03, KNPP Response to an or Higher 7.4 EPIP-AD-04, KNPP Response to Alert Fires Chart G Report 88-11, Improve Guidance for 7.5 COMTRAK 89-001, NRC Inspection Chart P Report OE 2265, Improve Description of Unusual Aircraft Activity 7.6 OEA 87-246, on Acceptable Deviations to NUREG-0654 7.7 NRC Letter 07-11-94, Branch Position 8.0 Records and QA records and non-QA records are identified in this directive/procedure following 8.1 The Schedule. These records shall be maintained are listed on the KNPP Records Retention Program.
according to the KNPP Records Management 8.1.1 OARecords None 8.1.2 Non-QA Records None
EMERGENCY ACTION LEVEL CHARTS may, depending upon The following charts are separated into different abnormal operating conditions which General Emergency.
their severity, be classified as an Unusual Event, Alert, Site Emergency, or 0" Ný :_CHART PAGE A (1) 4 Abnormal Radiological Effluent A (2) 5-7 Gaseous Effluent Action Levels 8
B Fuel Damage Indication 9 C
Primary Leak to LOCA 10 D
Primary to Secondary Leak 11 E
Loss of Power 12 F
Engineered Safety Feature Anomaly 13 G
Loss of Indication 13 H
DELETED 14 I
Secondary Side Anomaly 15 Miscellaneous Abnormal Plant Conditions J 16 K
Fire and Fire Protection 16 L
DELETED 17 M
Earthquake 17 High Winds or Tornado N 18 0
Flood, Low Water, or Seiche 19 P
External Events and Chemical Spills 20 Security Contingency Q
. ... .. Page 3 of 20 w
Table 2-1 EPIP-AD-02 Rev. AB*
u wSEP 1 B 2001
CHART A(1)
ABNORMAL RADIOLOGICAL EFFLUENT KNPP INDICATION EMERGENCY CLASSIFICATION CLASSIFICATION CRITERIA Effluent monitors detect levels corresponding to greater than 1 rem/hr GENERAL SEE CHART A(2) whole body or 5 rem/hr thyroid at the EMERGENCY site boundary under "actual meteorological" conditions.
Projected or measured dose rates to be provided Projected or measured in the environs PytheRoj iologicaltect os Dirates odose rates greater than I 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) OR for "adverse meteorology."
At the site boundary, projected or measured dose rates greater than 50 Projected or measured dose rates to be provided mr/hr for 1/2 hours OR greater than 500 by the Radiological Protection Director or mr/hr for two minutes (or five times SITE EMERGENCY Environmental Monitoring Teams. these levels to the thyroid) or EPA PAGs are projected to be exceeded outside the site boundary.
SEE CHART A(2) than 10 Radiological effluents greaterlimits. ALERT times ODCM instantaneous
- b. Charging Area R-4 >_ .0E+4 mr/hr, OR contamination which indicate a severe degradation in the control of ALERT
- c. SFP Area R-5> 1.OE+4 mr/hr, OR radioactive materials (e.g., radiation levels suddenly increase by a factor of
- d. Plant area air sample indicates airborne 1000).
contamination> 1000 times the occupational DAC values.
(1) Gaseous Releases: See Chart A(2)
(2) Liguid Releases: Notification by the Rad- Off site Dose Calculation Manual UNUSUAL EVENT limits exceeded.
Chem Group of violating ODCM 3.3.1 limits.
Tal-- PPA-2Rv A ae E .8~U* ragei.* *gi z ut Table 2-1 EPIP-AD-02 Rev. AB Date: SEP 1 8 zoul r-age ,%of 20
CHART A(2)
GASEOUS EFFLUENT ACTION LEVELS
- 1. AUX BUILDING VENT RELEASES - WITH SIGNIFICANT CORE DAMAGE Instrument readings assuming a post accident gas release AND Containment High Range Radiation Monitors 42599 (R-40) and 42600 (R-41) reads 1000 R/hr within one-half hour of the accident.
NOTE: Use adverse meteorology conditions (ADV MET) only when, 10m and 60m wind speed < 5mph AND Delta-T > 2.4 degrees F. All other cases are average meteorology (AVG MET).
NOTE: R-13 and R-14 are expected to be off scale high during all events on this page.
1 8.8E+4 5.5E+2 3.OE+O
- 6.3E+3 3.9E+I 6.3E+O
- 2 4.4E+4 2.7E+2 1.5E+0
- 3.1E+3 1.9E+I 3.1E+O
- SITE 3 2.9E+4 1.8E+2 1.OE+O
- 2.1E+3 1.3E+l 2.1E+O
- EMERG.
4 2.2E+4 1.3E+2 *
- 1.5E+3 9.5E+0I 1.5E+O
- I 1.OE+3 6.2E+O *
- 7.0E+I * *
- 2 5.OE+2 3.1E+O *
- 3.5E+1 * * *ALERT 3 3.3E+2 2.OE+O *
- 2.3E+I * *
- 4 2.5E+2 1.5E+O *
- 1.75E+I * *
- I 1.OE+2 6.2E-1 *
- 7.OE+ * *
- 2 5.0E+1 3.E-I *
- 3.5E+ * *
- UNUSUAL 3 3.3E+I 2.OE-1 *
- 2.3E+O * * , EVENT 4 2.5E+1 1.5E-1 *
- 1.7E+O * * *
- Offscale Low
- --- ** Offscale High (Confirmation Only) rir-Au-IJ
-1 i'IJII-AIJU-U 8D18 2-1 KOV. Ab U-' 1 8 ZUW Page 5 of 20 I ableo KG(v. AB-Date: SEP 1 8 2001 Page 5 of 20
CHART A(2)
GASEOUS EFFLUENT ACTION LEVELS continued
- 2. AUX BUILDING VENT RELEASES WITHOUT CORE DAMAGE NOTE: Use adverse meteorology conditions (ADV MET) only when, 10m and 60m wind speed < 5mph AND Delta-T > 2.4 degrees F. All other cases are average meteorology (AVG MET).
NOTE: R-13 and R-14 are expected to be off scale high during all events on this page.
AUX BLDG SPING MONITORS FANS CLASS.
MID RANGE HIGH RANGE TOTAL CPM (01-07) CPM (01-09)
NUMBER PPCS PT G9086G PPCS PT G9088G RUNNING AVG MET ADV MET AVG MET ADV MET 1 ** 9.4E+4 1.6E+4 1.OE+2 2 ** 4.7E+4 8.OE+3 5.0E+1 GENERAL 3 ** 3.1E+4 5.3E+3 3.3E+1 EMERG.
4 2.3E+4 4.OE+3 2.5+1 1 7.5E+5 4.6E+3 8.OE+2 5.OE+O 2 3.7E+5 2.3E+3 4.OE+2 2.5E+O SITE 3 2.5E+5 1.5+3 2.6E+2 1.6E+0 EMERG.
4 1.8E+5 1.1E+3 2.OE+2 1.2E+O SV & SFP AUX BLDG SPING MONITORS FANS EMERG.
TOTAL LOW RANGE MID RANGE CLASS.
NUMBER Ci/cc (01-05) CPM (01-07)
RUNNING PPCS PT G9084G PPCS PT 9086G 1 ** 8.6E+3 2 ** 4.3E+3 ALERT 3 ** 2.8E+3 4 ** 2.1E+3 1 6.3E-2 8.6E+2 2 3.1E-2 4.3E+2 UNUSUAL 3 2.1E-2 2.8E+2 EVENT 4 1.5E-2 2.1E+2
- Offscale High (Confirmation Only)
Table 2-1 EPIP-AD-02 Rev. AB Date: SEP 1 8 Z001 Page 6 of 20
CHART A(2)
GASEOUS EFFLUENT ACTION LEVELS continued
- 3. STEAM LINE RELEASE WITH SIGNIFICANT CORE DAMAFGE Instrument readings assuming radioactive steam is releasing at a total of 1.4E+5 Rounds per hour to the atmosphere AND Containment High Range Radiation Monitor 42599 (R-40) or 42600 (R-41) reads 1000 R/hr within one-half hour of the accident.
"A" e "B" Steam Line Monitors Steam Line Monitors Emergency Classification r T R-15 R-31 R-32 R-33 R-34 (cpm) (mR/hr) (R/hr) (mR/hr) (Rihr) t - ----- 4 (mR/hr
4 (R/hr'
- 1.3E+3 E+0 1.3E+03 E+O General Emergency
- 6.0E+l -- 6.OE+l -- Site Emergency
- 1.5E-1 -- 1.5E-1 -- Alert 2.OE+05 -- Unusual Event
- Offscale High (Confirmation Only)
SHIELD BUILDING STACK RELEASE Instrument readings assuming SBV System is operating in the recirculation mode.
Reactor Bldg. Discharge Vent SPING Emergency Clas sifi cation [
PPCS PT G9077G PPCS PT G9079G I (02-07) (02-09)
Mid Range (cpm) High Range (epm) 1.5E+2 General Emergency 1.3E+05 6.7E+03 7.OE+O Site Emergency 1.5E+1 Alert
-- Unusual Event fl .4 . A - -- - - - a - - -
I a[gA £-I 'II'-AU-U, KeV. At$
Date: SEP 1 8 2001 Page 7 of 20
CHART B FUEL DAMAGE INDICATION EMERGENCY KNPP INDICATION CLASSIFICATION CLASSIFICATION CRITERIA Plant conditions exist that make the GENERAL SACRG-I, Severe Accident Control Room Guideline release of large amounts of EMERGENCY Initial Response has been implemented. radioactivity m a short time period possible.
SApplies when more than one spent fuel element is Major damage to spent fuel in SITE lamaged.) containment or auxiliary building. EMERGENCY (1) Fuel Handling accident in Containment Report of a large object dropped in Rx core OR dropped spent fuel assembly, AND Alarm on R- 11 OR R- 12 (2) Fuel Handling Accident in Auxiliary Bldg.
Report of:
- a. A large object dropped in spent fuel pool, OR
- b. A dropped spent fuel assembly, OR.
- c. A loss of water level below spent fuel, AND Alarm on R-13 or R-14.
R-9 indication is offscale high, AND Severe loss of fuel cladding ALERT 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 of radioactivity to containment or A confirming report, AND auxiliary building.
Alarm on R-11 OR R-12 (2) Fuel Handling Accident in Auxiliary Bldg.
A confirming report, AND Alarm on R-13 OR R-14.
With RCS Temperature > 5000 F, High reactor coolant activity UNUSUAL sample. EVENT
- a. > 0.2 pCi/gram DOSE Equivalent 1-131 for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, OR
- b. Exceeding T.S. figure 3.1-3 for Dose Equivalent 1-131, OR
- c. > 91/E p.Ci/cc As determined by SP-37-065 (from T.S. 3.1.c)
R-9 is greater than 5.0 R/hr, AND Failed fuel monitor indicates greater UNUSUAL than 0.1% equivalent fuel failures EVENT Verified by RCS chemistry sample analysis. within 30 minutes.
S. . . . .. . IF A* A el A f) r'age 8 of 2-0 Table 2-1 EPIP-AD-02 Rev. AB Talte: SEP 1e8 a001
CHART C PRIMARY LEAK TO LOCA NOTE: This chart does not apply when leakage from the Reactor Coolant System is caused by a Steam Generator tube rupture.
EMERGENCY CLASSIFICATION KNPP INDICATION CLASSIFICATION CRITERIA (1) LOCA is verified per IPEOP E-,1 "Loss of (1) Loss of coolant accident, GENERAL Reactor or Secondary Coolant," AIND AND EMERGENCY (2) ECCS failure is indicated by: (2) Initial or subsequent failure of ECCS, AND
- b. Verification of no flow to the reactor potential failure exists (loss vessel, OR of 2 of 3 fission product barriers with a potential loss
- c. Core exit thermocouples indicate greater of 3rd barrier).
than 1200'F, AND (3) Failure or potential failure of containment is indicated by:
- a. Physical evidence of containment structure damage, OR
- c. Containment hydrogen monitor indicates
_ 10% hydrogen concentration, OR
- d. Containment pressure exceeds 46 psig.
SI System is activated and RCS leakage exceeds Reactor Coolant System leakage SITE charging system capacity as verified by Control greater than make-up pump EMERGENCY Room indications or IPEOPs. capacity.
Char~i flow verses letdown flow indicates an Reactor Coolant System leak rate ALERT uniso ab e RCS leak > 50 gpm. greater than 50 GPM.
Initiation of reactor shutdown rguired by Exceeding Reactor Coolant UNUSUAL Technical Specification, SectionT...S.3.1.d. System leak rate, Technical EVENT Indicated leakage may be determined using Spiecifications, requiring reactor Reactor Coolant System mass balance calculations shutdown.
performed by SP-36-082.
Table 2-1 EPIP-AD-02 Rev. AB EPIP-AD-02 Rev. AB Date: SEP 1 8 ZUW rage 01 su r,,age v ol ew Date: SE.P 1 8 2001l
CHART D PRIMARY TO SECONDARY LEAK EMERGENCY KNPP INDICATION CLASSIFICATION CLASSIFICATION CRITERIA (1) Entry into IPEOP E-3, "Steam Generator Tube Rapid failure of steam generator SITE Rupture," is expected or has occurred, AND tubes with loss of off-site power. EMERGENCY (2) Primary-to-secondary flow > 800 GPM OR RCS pressure decreasing uncontrollably, AND (3) All three transformers Main Aux., Reserve Aux.,
and Tertiary Aux., are de-energized.
(1) Entry into IPEOP E-3, "Steam Generator Tube Rapid gross failure of one steam ALERT Rupture," is expected or has occurred, AND generator tube with loss of off-site power.
(2) Primary-to-secondary leak rate > 400 GPM, AND (3) All three transformers: Main Aux., Reserve Aux., and Tertiary Aux., are de-energized.
(1) Entry into IPEOP E-3, "Steam Generator Tube Rapid failure of multiple steam ALERT Rupture," is expected or has occurred, AND generator tubes.
(2) Primary-to-secondary leak rate greater than 800 GPM indicated by SI flow OR RWST level change.
Primary-to-secondary leakage > 150 gallons per day Exceeding Primary-to-Secondary UNUSUAL 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. EVENT Do not delay declaration if leakage suddenly increases above 150 gallons per day AND plant shutdown actions are initiated.
Table 2-1 Table Rev. AB EPIP-AD-02 Rev.
2-1 EPIP-AD-02 Date: SEP 182001 Page 10 of 20 AB Date: SEP 1 8 2001 Page 10 of 20
CHART E LOSS OF POWER N C EMERGENCY KNPP INDICATION CLASSIFICATION CRITERIA CLASSIFICATION (1) RCS is _> 350°F, AND Failure of off-site and on-site GENERAL AC power, AND EMERGENCY (2) Buses 1 through 6 are de-energized including the Total loss of auxiliary D/G supplies to buses 5 and 6, AND feedwater makeup capability for greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. (Loss (3) Loss of the turbine driven AFW pump, AND of power plus loss of all AeW 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.)
Buses 1 through 6 are de-energized including the D/G Loss of off-site power, AND SITE supplies to buses 5 and 6 for longer than 15 minutes. EMERGENCY (Does not apply when core is unloaded or cavity is Loss of on-site AC power (for flooded wit internals removed.) more than 15 minutes).
Low voltage lockout OR de-energized condition on Loss of all vital on-site DC all safeguards DC distribution cabinets for greater SITE power (for more than 15 EMERGENCY than 15 minutes. minutes).
- a. BRA 102 and BRB 102, OR
- b. BRA 104 and BRB 104,M
- c. BRA 102 and BRB 104, O
- d. BRB 102 and BRA 104 (Does not apply when core is unloaded or cavity is ooded wit internals removed.)
"Lowvoltage lockout OR de-energized condition on Loss of all vital on-site DC ALERT all safeguards DC distribution cabinets for less than power (for less than 15 15 minutes. minutes).
- a. BRA 102 and BRB 102, OR
- b. BRA 104 and BRB 104,:R
- c. BRA 102 and BRB 104,
- d. BRB 102 and BRA 104 (Does not apply when core is unloaded or cavity is flooded with internals removed.)
Buses 1 through 6 are de-energized, AND Loss of off-site power, AND ALERT the D/G supplies to buses 5 and 6 do not respond as Loss of on-site AC power (for designed. AC power is restored to bus 5 or 6 within less than 15 minutes.)
15 minutes. (Does not apply when core is unloaded or cavity is flooded with internals removed.)
With the Reactor Coolant System above cold Loss of off-site power, OR UNUSUAL shutdown condition: EVENT Loss of on-site power
- a. All three transformers: Main Aux., Reserve capability.
Aux., and Tertiary are de-energized, OR
- b. Both D/Gs unavailable (unable to supply bus 5 or 6 by any means).
Core is unloaded or reactor cavity is flooded with Loss of off-site power, AND UNUSUAL internals removed, AND EVENT Buses 1 through 6 are de-energized including the D/G Loss of on-site AC power (for more than 15 minutes).
supplies to buses 5 and 6 for longer than 15 minutes.
T~hln 9.1 gDID_.AI'tnf IDa,, AD * .s....
Tnhin 9.1 =DID-An n13 0 VV. A C2 uDat: SEP 1 8 2001 Page 11 of 20
CHART F ENGINEERED SAFETY FEATURE ANOMALY EMERGENCY KNPP INDICATION CLASSIFICATION CLASSIFICATION CRITERIA RCS > 200'F with a loss of cooling capability or Complete loss of any function SITE inventory control: needed when RCS > 200'F. EMERGENCY
- a. Loss of negative reactivity control, OR
- e. (1) Loss of both trains of RHR, AND (2) 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 0 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 ooded with internals removed.)
Failure of both Rx trip breakers to open upon receipt Failure of the Reactor ALERT of a valid signal. Applies even if IPEOP FR S. 1 is Protection System to initiate not entered. and complete a reactor trip which brings the reactor subcritical.
(1) Loss of ESF function, required support function Inability to reach required UNUSUAL or required Tech Spec instruments OR shutdown within Tech Spec EVENT Exceeding Tech Spec Safety Limits, AND limits (2) upon discovery, inability or failure to take required shut own or mode change actions within the required time.
NOTE: Total loss of AFW system when required (FR-H. 1 implemented) should be declared a UE regardless of Tech Spec action compliance.
Table EPIP-AD-02 Rev.
2-1 EPIP-AD-02 Table 2-1 Rev. AB AB Date:
Date:
1 UU1 W.L1 8 ZUU1 Page 12 of 20 Page 12 of 20
CHART G LOSS OF INDICATION EMERGENCY KNPP INDICATION CLASSIFICATION CLASSIFICATION CRITERIA (1) Total loss of Annunciator System computer Most or all alarms (annunciators) SITE alarms, and sequence of events recorder for lost and a plant transient initiated EMERGENCY greater than 15 minutes, AND or in progress.
(2) Uncontrolled plant transient in progress or initiated during the loss.
Total loss of Annunciator System, computer Most or all alarms (annunciators) ALERT alarms, and sequence of events recorder. (Not lost.
applicable shtdown.)when plant is at or below cold Significant loss of ESF or Rx Protection Indications or alarms on process UNUSUAL instrumentation. An Unusual Event should NOT be or effluent parameters not EVENT declared for a non-emergency Tech Spec functional in control room to an backdown when the affected parameter remains extent requiring plant shutdown monitorable. (Not applicable when plant is at or or other significant loss of below cold shutdown.) assessment capability.
CHART H (DELETED)
-1 E-IPiq-AD-02 flDI6 2-1 II able A icev. AB rIr-AU-UL Rev. Date: SEP18 20W Page 13 of2O Date: SEP 1 8 2001 Page 13 of 20
CHART I SECONDARY SIDE ANOMALY EMERGENCY KNPP INDICATION CLASSIFICATION CLASSIFICATION CRITERIA (1) Main steam line break that results in a SI Steam line break, AND SITE actuation, .AND EMERGENCY Primary-to-secondary leak (2) a. R-15 or R-19 reads offscale high with >50GPMAND confirmation by chemistry analysis, OR Indication of Fuel Damage.
> 50 gpm,
- b. Primary-to-secondary leakage 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.
Main steam line break that results in a SI actuation, Steam line break with ALERT AND significant (greater than 10 GPM) primary-to-secondary
- a. R-15 OR R-19 reads a factor of 1000 above leakage.
normal7)R (Applies even if events occur in
- b. Primary-to-secondary leakage > 10 gpm. opposite steam generators.)
Turbine trip and observation of penetration of casing. Turbine rotating component UNUSUAL failure causing rapid plant EVENT shutdown.
The uncontrolled depressurization of the secondary Rapid depressurization of the UNUSUAL system that results in an SI actuation. secondary side. EVENT EPIP-AD-02 Rev.
Table 2-1 EPIP-AD-02 AB Rev. AB Date: SEP 1 8 2001 Page 14 of 20 Date: SEP 1 8 2001 Page 14 of 20
CHARTJ MISCELLANEOUS ABNORMAL PLANT CONDITIONS KNPP INDICATION EMERGENCY CLASSIFICATION CRITERIA CLASSIFICATION (1) Containment boundary failure or potential Other plant conditions that make a GENERAL failure: release of large amounts of EMERGENCY radioactivity in a short time period
- a. Containment pressure > 46 psig, OR possible; e.g., any core melt situation.
- c. Containment hydrogen monitor systems for greater than 30
Ž 10% hydrogen concentration, AND minutes without Safe 7 Injection and Residua Heat (2) Loss of core cooling capability: Removal flow. Plus a containment failure is
(3) Failure of shutdown system when required: - Transient requiring the operation of shutdown
- a. Entry into IPEOP FR-S. l, "Response to systems with a failure of these Nuclear Power Generation/ATWS," OR shutdown systems. In addition, failure of SI and
- b. Loss of AFW for greater than 30 minutes RI-R and containment failure with loss of main FW and condensate, is imminent.
Evacuation of Control Room (E-O-06 event). Evacuation of control room and SITE control of shutdown systems EMERGENCY required from local stations.
Conditions that warrant increased awareness on part Other plant conditions that warrant UNUSUAL of the plant staff will be evaluated by the Plant increased awareness on the part of EVENT Manager or his designate. This is to determine if plant staff or state and/or local conditions are applicable for activating the E.P. authorities.
Example: Loss of AFW system when required validated upon implementation of Fk H. 1 "Responseto Loss of Secondary Heat Sink.'
Table 2-1 Table EPIP-AD-U2 Rev.Rev. AB Date: SEP 1 8 20W Page 15 of 20 2-1 EPIP-AD-02 AB Date: SEP 1 8 2001 Page 15 of 20
CHART K FIRE AND FIRE PROTECTION KNPP INDICATION EMERGENCY CLASSIFICATION CRITERIA CLASSIFICATION A fire within the Auxiliary Building Technical A fire compromising the functions SITE Support Center, safegards alley, -/G rooms, of safety systems. EMERGENCY Battery Rooms, or screenhouse that defeats redundant safety trains of ESF equipment causing the required ESF system to be inoperable.
A fire within the Auxiliary Building Technical A fire potentially affecting safety ALERT Support Center, safeguards alley D-/G rooms, systems.
Battery Rooms, or screenhouse that causes a single train of required ESF equipment to be inoperable.
A fire within the Administration Building, A fire within the plant lasting UNUSUAL Technical Support Center* Turbine Building, more than 10 minutes. EVENT Warehouse Annex Auxilhary Building, or Containment Building lasting more than 10 minutes.
CHART L (DELETED)
Table 2-1 EPIP-AD-02 AB Rev. AB EPIP-AD-02 Rev. Date: SEP 182001 Page 16 of 20 Page 16 of 20 Date: SEP 1 8 2001
CHART M EARTHQUAKE EMERGENCY KNPP INDICATION CLASSIFICATION CLASSIFICATION CRITERIA (1) Activation of seismic recorder with TRIGGER, An earthquake greater than SITE OBE, and DBE lights lit in relay room on Design Basis Earthquake (DBE). EMERGENCY RRl59, 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 RRI 59, 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 amage or verification from University of Wisconsin Seismic Center.)
NOTE: Telephone numbers for U of W - Milwaukee Seismic Center are in EPIP-APPX-A-03.
CHART N HIGH WINDS OR TORNADO EMERGENCY KNPP INDICATION CLASSIFICATION CLASSIFICATION CRITERIA (1) Winds in excess of 100 mph for greater than Sustained winds in excess of SITE 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, AND design levels with plant not in EMERGENCY cold shutdown.
(2) Plant above cold shutdown condition.
(1) A tornado which strikes the facility, AND Any tornado striking facility. ALERT (2) Causes damage to render a single train of required ESF-equipment to be inoperable.
A tornado observed on-site causing significant Any tornado on-site. UNUSUAL damage to the facility. EVENT Table 2-1 EPIP-AD-02 Rev.
2-1 EPIP-AD-02 Rev. AB AB Date: SEP 18 2001 Page 17 0? 20 Page 17 of 20 Date: SEP 1 8 2001
CHART 0 FLOOD, LOW WATER, OR SEICHE EMERGENCY CLASSIFICATION KNPP INDICATION CRITERIA CLASSIFICATION FOREBAY LEVEL Flood, low water, or Indicated for > 15 minutes seiche near design ALERT CORRESPOND levels.
I PUMP TORAELEVeL 2 PUMPS ITO LAKE LEVEL 0 PUMPS NOTE 3 NOTE 1 94% * > 588 ft.
< 50%
- NOTE 5 NOTE 5 < 568.5 ft.
OR Deep water Wave > 22.5 ft.
FOREBAY LEVEL 50-year flood, low Indicated for > 15 minutes water level or seiche UNUSUAL CORRESPOND EVENT 1 PUMP 2 PUMPS TOLAE LEVEL 0 PUMPS TO LAKE LEVEL NOTE2 >98%* 88%* > 586 ft.
< 53.1% <46.9%* NOTE5 < 569.5 ft.
NOTE 4 OR Deep water wave > 18 ft.
NOTE 1: Above the bottom of bar No. 1 painted on the south wall of the forebay.
NOTE 2: Above the bottom of bar No. 2 painted on the south wall of the forebay.
NOTE 3: Above the bottom of bar No. 3 painted on the south wall of the forebay.
NOTE 4: Applies to an uncontrollable decrease (cannot be restored by operator action. If the water box inlet valves are throttled, use other means to determine lake level per E-CW-04, "Loss of Circulating Water.")
NOTE 5: The corresponding forebay level for the associated lake level is below the circulating water pump trip setpoint of 42%. Therefore, this criterion will not be reached.
- Computer point for forebay level is L09075A and should be used because of its greater accuracy.
Plant elevations and lake elevations are referenced to International Great Lakes Datum (IGLD), 1955 (IGLD 1955 = IGLD 1985 - 0.7 FEET)
Table 2-1 EPIP-AD-02 Table Rev. AB EPIP-AD-02 Rev. Date: SEP 18 2001 Page 15 Ot 20 Page 18 of 20 Date: SEP 1 8 2001
CHART P EXTERNAL EVENTS AND CHEMICAL SPILLS EMERGENCY KNPP INDICATION CLASSIFICATION CLASSIFICATION CRITERIA An aircraft crash into plant buildings which causes a Aircraft crash affecting vital SITE complete loss of an ESF function. structures by impact (-R fire. EMERGENCY A missile strikes plant buildings OR explosion occurs Severe damage to safe SITE within a plant building, which causes a complete loss shutdown equipment from EMERGENCY of an ESF function. missiles or explosion.
Release of flammable or toxic gas from a ruptured Uncontrolled release of toxic SITE container, which causes or is likely to cause evacuation or flammable gas is confirmed EMERGENCY of stations necessary to control shutdown systems. within vital area.
Portable monitors indicate toxic or explosive concentrations of the gas at life threatening levels in those vital areas.
An aircraft crashes into plant buildings AND causes a Aircraft crash on facility. ALERT single train of required ESF equipment to be inoperable.
A missile strikes the facility AND causes a single train Missile impact from whatever ALERT of required ESF equipment to be inoperable, source on facility.
Release of toxic or flammable gas at life threatening Uncontrolled release of toxic ALERT levels from a ruptured container enter theprotected or flammable gas is confirmed area AND impacts safe operation of the plant. within the protected area.
Self-explanatory. Known explosion damage to ALERT facility affecting plant operation.
(1) An aircraft crash within the site boundary, OR Aircraft crash on-site or UNUSUAL unusual aircraft activity over EVENT (2) Unusual aircraft activity such as erratic flying, facility.
dropped unidentified object, or other hostile acts, whic threaten the plant or plant persornnel. (Any other persistent aircraft activity for which identification attempts through the FAA or other agencies have been unsuccessful.)
Release of toxic or flammable gas from a ruptured Uncontrolled release of toxic UNUSUAL EVENT tank/truck on site. Portable monitors indicate toxic or or flammable gas is confirmed explosive concentrations at life threatening levels of on site.
the gas near the spill area.
2001 Page 19 of 20 EPIP-AD-02 Rev.
Table 2-1 EPIP-AD-02 AB Rev. AB Date:
Date: SEP 18 SEP 1 8 2001 Page 19 of 20
CHART Q SECURITY CONTINGENCY
"'NC OEMERGENCY KNPP INDICATION CLASSIFICATION CRITERIA CLASSIFICATION Physical attack on the plant that has resulted in Loss of physical control of the GENERAL unauthorized personnel occupying the control room plant. EMERGENCY or any other vital areas as described in the Security Plan. _____________
Physical attack on the plant involving imminent Imminent loss of physical SITE occupancy of the control room, auxiliary shutdown control of the plant. EMERGENCY panels, or other vital areas as defined by the Security Plan.
Security safeguards contingency event that results Ongoing security compromise. ALERT in adversaries commandeering an area of the plant, but not control over shutdown capability or of any vital areas as defined in the Security Plan.
Examples: - Bomb threat accompanied by Security threat or attempted UNUSUAL interception of bomb materials, entry or attempted sabotage. EVENT
- Adversary intercepted in the protected area.
- Undetonated bomb found within the protected area.
NOTE: Security staff will not act as notifier during security events. Utilize Control Room staff for notifications.
a A fl*fl * - an - - - - -
I a le z-1 rI""r-AU-UZ Key. At$
Date: SEP 18 2001 Page 20 of 20