ML022280393
| ML022280393 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee  |
| Issue date: | 08/07/2002 |
| From: | Webb T Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Security and Incident Response |
| References | |
| NRC-02-073 | |
| Download: ML022280393 (83) | |
Text
Kewaunee Nuclear Power Plant Point Beach Nuclear Plant N490 Highway 42 6610 Nuclear Road Kewaunee, WI 54216-9511 Two Rivers, WI 54241 NM C 920.388.2560 920.755.2321 Committed to Nuclear Excellence Kewaunee / Point Beach Nuclear Operated by Nuclear Management Company, LLC NRC-02-073 August 7, 2002 10 CFR 50, App. E U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Ladies/Gentlemen:
Docket 50-305 Operating License DPR-43 Kewaunee Nuclear Power Plant Radiological Emergency Response Plan Implementing Procedures Pursuant to 10 CFR 50 Appendix E, attached is the latest revisions to the Kewaunee Nuclear Power Plant Radiological Emergency Response Plan Implementing Procedures (EPIPs). These revised procedures supersede the previously submitted procedures.
Pursuant to 10 CFR 50.4, two additional copies of this letter and attachment are hereby submitted to the Regional Administrator, U. S. Nuclear Regulatory Commission, Region III, Lisle, Illinois. As required, one copy of this letter and attachment is also submitted to the Kewaunee Nuclear Power Plant NRC Senior Resident Inspector.
Sincerely, Thomas J. Webb Regulatory Affairs Manager SLC Attachment cc -
US NRC Senior Resident Inspector, w/attach.
US NRC, Region III (2 copies), w/attach.
Electric Division, PSCW, w/o attach.
QA Vault, wo/attach.
/
DOCUMENT TRANSMITTAL KEWAUNEE NUCLEAR POWER PLANT FROM:
DIANE FENCL - KNPP TRANSMITTAL DATE 08-06-2002 EMERGENCY PLAN IMPLEMENTING PROCEDURES TRANSMITTAL FORM OUTSIDE AGENCY COPIES (1-20)
T. Webb - NRC Document Control Desk (1)*
Krista Kappelman - PBNP - EP (10)*
T. Webb - NRC Region I1I (2, 3)*
Craig Weiss - Alliant Energy (11)*
T. Webb - NRC Resident Inspector (4) (receives Appx. A phone numbers)*
T. Webb - State of Wisconsin (5)*
Jill Stern - Nuclear Management Company (12)*
T. Webb - KNPP QA Vault (NRC Letter & Memo Only) (15)*
PERSONAL COPIES (21-40) These copies are for the personal use of the listed individuals for reference or emergency response.
J. Bennett (33)
D. Seebart (24)
J. Ferris (13)
T. Coutu (28)
REFERENCE COPIES - CUSTODIAN (41-100) These copies are for general reference by anyone. They are distributed throughout the plant and corporate offices. The named individual is the responsible custodian for the procedures and shall insure they are properly maintained.
NO Library - KNPP (59)
C. Sternitzky - ATF-2 (44)
M. Daron - Security Building (46)
M. Lambert - EOF (81)
M. Lambert - OSF (52)
LOREB - STF (62, 66, 67, 68, 70, 72, 73, 74)
STF Library (43)
Resource Center - Training (82)
D. Krall - CR/SS Office (51, 56)
M. Lambert - TSC (50)
W. Galarneau - RAF (53)
W. Galarneau - SBF/EMT (54)
W. Galarneau - RPO (55)
STF (86, 87, 88)
WORKING COPIES (101-199) These copies of procedures are kept in the areas designated for use in response to an emergency.
W. Galarneau - RAF/RPO (106, 107)
W. Galarneau - SBF/ENV (108, 109)
W. Galarneau - SBF/EM Team (110, 111, IlA)
W. Flint - Cold ChemfHR Sample Room (113)
M. Kuether - SBF/SEC (114)
D. Krall - CR/Communicator (116)(parual Distribution)
Simulator/Communicator (117)
M. Fencl - Security (121)
M. Kuether - Security Building (120)
J. Stoeger (126)
Originals to KNPP QA Vault Please follow the directions when updating your EPIP Manual. WATCH FOR DELETIONS!!! These are controlled procedures and random checks may be made to ensure the manuals are kept up-to-date.
- THIS IS NOT A CONTROLLED COPY. IT IS A COPY FOR INFORMATION ONLY.
1
KEWAUNEE NUCLEAR POWER PLANT REVISION OF EMERGENCY PLAN IMPLEMENTING PROCEDURES August 06, 2002' Please follow the directions listed below. If you have any questions regarding changes made to the EPIPs, please contact Dave Seebart at ext. 8719.,
EPIP Index, dated 08-06-2002.
REMOVE PROCEDURE
-EIfPl -EOF-02 EPIP-EOF-04
-EPIP-RET-02B EPIP-TSC-01 Form EPIPF-AD-18-Of Form EPIF-EOF.,02-O1
.,Form EPIPF-EOF-02-02 EPIP FORM UET 2B. 1 "EPIPFORM RET 2B.4
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EPIP FORM RET 2B.5 EPIP FORM RET 2B.6 REV:
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REV.
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"INSERT PROCEDURE;
,, EPIP-EOF-02
-EPIP-EOF-04
,Clears TCI dated 05/28/2 002.
EPIP-RET-02B EPIP-TSC-01 "FormEPIPF-AD-1 8-01 Form EPIPF-EOF-02-01 "For-m EPIPF-EOF-02-02,.
-Form EPIPF-RET-02B-01 Form EPIPF-RET-02B-02
- -Form* EPIPF-1RET-02B3-03
"- Form-EPIPF-RET-02B-04 Form EPIPF-RET-02B-05" Form EPIPF-RE-T-02B-06 KJ, N
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~~~ave any uestos I CERTIFY Copy No.
(WPSC No.) of the
-Kewaunee Nuclear Power-Plant's EPIPs has been updated.
SIGNATURE DATE Please return this sheet to DIANE FENCL.
Diane Fencl Enclosure 2
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EMERGENCY PLAN IMPLEMENTING PROCEDURES
"" INDEX "
DATE: 08-06-2002 PROC. NO.
MMTIThE REV.
DATE EP-AD EjPIP-AD-01 Personnel Response to the PNant-Emergency 3J 01-08-2002 Siren EPIP-AD-02 Emergency Class Determination AD 07-19-2002 EPIP-AD-03 KNPP Response to an Unusual Event AF 06-20-2002 EPIP-AD-04 KNPP Response'toA Alert or Higher AJ.
06-20-2002 EP-AD-5 Site Emergency...
Deleted-04-27"87 EPIP-AD-05 Emergency Response Organization Shift Relief D
05-09-2002 Guideline.
EP-AD-6 General Emergency Dleted 04-24-87 EPIP-AD-07.
Iritial Emergency Notifications AR 20-2002 EP-AD-8 Notification of Alert or Higher Deleted 02-26-96 EP-AD-9 Notification of Site EmFfgeficy Deleted 04-27-§7 EP-AD-10 Notification of General Emergecy
-Deleted 04-27-e7 EPIP-AD-1 1 Emergency Radiation Controls R-04-11-2002 EP-AD-12 Pergonnel 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/EvacIation f.
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 andTermination 0
10-30-2001 EP-AD-16 Occupational Injuries or Vehicle Accidents Deleted 03-14-97 During Emergencies EP-AD-17 Communications Deleted 03-05-84 EPIP-AD-18 Potassium Iodide Distribution P
02-27-2002 EPIP-AD-19 Protective Action Guidelines Q
11-27-2001 PAGE 1 OF 11
EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 08-06-2002 PROC. NO.
TITLE REV.
DATE EPIP-AD-20 KNPP Response to a Security Threat C
05-23-2002 EP-ENV EPIP-ENV-01 Environmental Monitoring Group Organization V
10-02-2001 and Responsibilities EPIP-ENV-02 Environmental Monitoring Team Activation X
10-02-2001 EP-ENV-3A Environmental Protection Director Actions and Deleted 09-26-84 Directives EP-ENV-3B EM Team Actions Deleted 09-26-84 EPIP-ENV-03C Dose Projection Using RASCAL Version 2.2 V
10-09-2001 Software EP-ENV-3D Revision and Control of ISODOSE II Deleted 02-14-95 EP-ENV-3E Manual Determination of X/Q Deleted 04-24-87 EP-ENV-3F Manual Determination of X/Q (Green Bay Deleted 05-30-86 Meteorological Data)
EP-ENV-3G Manual Dose Projection Calculation Deleted 06-02-89 EP-ENV-3H Protective Action Recommendations Deleted 04-13-90 EPIP-ENV-04A Portable Survey Instrument Use S
06-15-2000 EPIP-ENV-04B Air Sampling and Analysis W
10-09-2001 EP-ENV-4C Environmental Monitoring Teams Deleted 04-13-90 EPIP-ENV-04C Ground Deposition Sampling and Analysis W
10-09-2001 EPI-P-ENV-04D Plume Tracking for Environmental Monitoring N
10-02-2001 Teams EP-ENV-5A LCS-1 Operation Deleted 04-14-86 EP-ENV-5B MS-3 Operation Deleted 04-14-86 EP-ENV-5C SAM II Operation Deleted 04-14-86 EP-ENV-5D PAC-4G (Alpha Counter) Operation Deleted 04-14-86 EP-ENV-5E Reuter-Stokes Operation Deleted 08-27-85 PAGE 2 OF 11
EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 08-06-2002 PROC. NO.
TITLE REV.
DATE EP-ENV-6 Data Analysis, Dose Projections and Protective Deleted 12-21-81 Action Recommendations EP-ENV-6 Alternate Sample Analysis and Relocation of Deleted 04-14-86 EM Team EP-ENV-6A Relocation of Site Access Facility (Habitability)
Deleted 03-23-84 EP-ENV-6B SAF Environmental Sample Analysis Relocation Deleted 03-23-84 EP-ENV-7 Site Access Facility Communications Deleted 09-26-84 EP-ENV-8 Total Population Dose Estimate Calculations Deleted 04-14-86 EP-EOF EP-EOF-1 Corporate Emergency Response Organization Deleted 03-11-94 EPIP-EOF-02 Emergency Operations Facility (EOF) Activation 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 U
11-15-2001 Flow EPIP-EOF-12 Media Center/Emergency Operation Q
06-20-2002 Facility/Joint Public Information Center Security PAGE 3 OF 11
EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 08-06-2002 PROC. NO.
TITLE REV.
DATE EP-OP EP-OP-1 Control Room Emergency Organization Deleted 04-24-87 EP-OP-2 Emergency Control Room Activation for Deleted 04-24-87 Emergency Response EP-OP-3 Control Room Communications Deleted 04-24-87 EP-OSF EP-OSF-1 Operation Support Facility Emergency Deleted 04-24-87 Organization EPIP-OSF-02 Operational Support Facility Operations U
02-06-2002 EPIP-OSF-03 Work Orders During an Emergency P
05-09-2002 EP-OSF-4 Operational Support Facility Communications Deleted 04-24-87 EPIP-OSF-04 Search and Rescue E
05-23-2002 EP-RET EP-RET-1 Radiation Emergency Team Organization Deleted 04-16-96 EPIP-RET-02 In-Plant Radiation Emergency Team V
05-23-2002 EPIP-RET-02A Radiation Protection Office/Radiological T
11-29-2001 Analysis Facility (RPO/RAF) Activation EPIP-RET-02B Gaseous Effluent Release Path, Radioactivity, S
08-06-2002 and Release Rate Determination EP-RET-2C Containment Air Sampling and Analysis Deleted 03-01-83 EPIP-RET-02D Emergency Radiation Entry Controls and M
06-12-2001 Implementation EP-RET-2E Handling of Injured Personnel Deleted 04-16-96 EP-RET-2F Personnel Decontamination Deleted 04-13-90 EPIP-RET-03 Chemistry Emergency Team 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: 08-06-2002 PROC. NO.
TITLE REV.
DATE EPIP-RET-03C Post Accident Operation of the High Radiation P
01-15-2002 Sample Room EPIP-RET-03D Containment Air Sampling Analysis Using N
01-15-2002 CASP EP-RET-3E Post Accident Operation of High Rad Sample Deleted 08-27-85 Room Inline Multiported Count Cave EPIP-RET-04 SBF Activation S
06-20-2002 EP-RET-4A EOF Radiological Monitoring Deleted 03-10-83 EPIP-RET-04A SBF Operation/Relocation Deleted 10-02-2001 EP-RET-4B Radiological Controls at Site Access Facility Deleted 07-12-94 EP-RET-4C Site Radiological Monitoring Deleted 07-12-94 EP-RET-4D SAM-Il Operation Deleted 07-12-94 EP-RET-5 Plume Projection Deleted 09-26-84 EPIP-RET-05 Site Boundary Dose Rates During Controlled H
10-09-2001 Plant Cooldown EP-RET-5A Plume Projection Deleted 04-27-87 EP-RET-6 Dose Projection Deleted 04-24-87 EP-RET-7 Radiological Analysis Facility/Radiation Deleted 04-24-87 Protection Office Communications EPIP-RET-08 Contamination Control of the Aurora Medical Deleted 05-23-2002 Center EPIP-RET-09 Post-Accident Population Dose L
04-16-2002 EP-SEC EP-SEC-1 Security Organization Deleted 04-24-87 EPIP-SEC-02 Security Force Response to Emergencies X
02-06-2002 EP-SEC-2A Manual Activation of Emergency Sirens Deleted 04-16-82 EPIP-SEC-03 Personnel Assembly and Accountability AE 07-19-2002 EPIP-SEC-04 Security Force Actions for Dosimetry Issue P
10-02-2001 PAGE 5 OF 11
EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 08-06-2002 PROC. NO.
TITLE REV.
DATE EP-SEC-5 Security Force Response to the EOF Deleted 07-28-88 EPIP-SEC-05 Personnel Evacuation G
06-20-2002 EP-TSC EPIP-TSC-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 Equipment EP-TSC-6 Assessment of Reactor Core Damage Deleted 09-30-86 EPIP-TSC-07 RV Head Venting Time Calculation J
06-20-2002 EPIP-TSC-08A Calculations for Steam Release from Steam N
12-14-2001 Generators EPIP-TSC-08B*
STMRLS Computer Program G
06-20-2002 EP-TSC-8C*
See EP-TSC-8B Deleted 04-16-92
- EP-TSC-8B was totally deleted; therefore, EP-TSC-8C was changed to EP-TSC-8B EP-TSC-9 Core Damage Assessment Using Released Deleted 09-30-86 Radionuclides EPIP-TSC-09A*
Core Damage Assessment J
05-16-2002 EPIP-TSC-09B*
CORE Computer Program Deleted 05-16-2002 EP-TSC-9C*
See EP-TSC-9B Deleted 04-16-92
- EP-TSC-9A, Rev. D was totally deleted; therefore, EP-TSC-9B became EP-TSC-9A. EP-TSC-9B was previously EP-TSC-9C.
EPIP-TSC-10 Technical Support for IPEOPs K
05-09-2002 PAGE 6 OF 11
EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 08-06-2002 FIGURES EPIP FIG #
Figure EPIPFG DESCRIPTION REV.
DATE EP-SEC-5 Technical Support EPIP-APPX-A-06 EP.FIG-O03 APPX-A-06-03 Center - KNP Floor Plan B
06-12-2001 Site Boundary Facility EPIP-APPX-A-06 EP-FIG-OOS APPX-A-06-02 KNP Floor Plan A
10-31-2000 Radiological Analysis Facility - KNP Floor EPIP-APPX-A-06 EP-FIG-O08 APPX-A-06-01 Plan A
10-31-2000 EPIP-EOF-12 Division Office Building Form EPIPF-EOF-02-01 EP-FIG-009 EOF-12-01 (2nd Floor) Floor Plan B
10-24-2000 State/County Work Area - WPSC D2-1 EPIP-APPX-A-06 EP-FIG-012 APPX-A-06-08 Floor Plan C
10-31-2000 NRC Work Area EPIP-APPX-A-06 EP-FIG-013 APPX-A-06-09 WPSC D2-4 Floor Plan A
10-31-2000 Population Distribution by Geographical Sub EPIP-AD-19 EP-FIG-014 AD-19-01 Areas (with sectors)
A 10-31-2000 EOF - WPSC D2-3 EPIP-APPX-A-06 EP-FIG-022 APPX-A-06-04 Floor Plan C
10-30-2001 Location of JPIC and Media Briefing Center EPIP-EOF-12 EP-FIG-O24 EOF-12-02 Map C
06-20-2002 KNP Site Map &
EP-SEC-5 EP-FIG-026 SEC-05-01 Evacuation Routes C
06-20-2002 Floor Plan - Media APPX-A-6 EP-FIG-034 Briefing Center Deleted 08-04-98 General Office EPIP-EOF-12 Building - WPSC (1st EPIP-APPX-A-06 EP-FIG-035 APPX-A-06-06 Floor) Floor Plan C
10-24-2000 Floor Plan - Corporate APPX-A-6 EP-FIG-037 Response Center Deleted 08-04-98 APPX-A-6 EP-FIG-038 Floor Plan - JPIC Deleted 08-04-98 EPIP-OSF-02 EP-FIG-039 OSF-02-01 High Priority Work A
10-02-2001 EPIP-OSF-02 EP-FIG-039A OSF-02-02 Lower Priority Work A
10-02-2001 JPIC - Federal Work EPIP-APPX-A-06 EP-FIG-043 APPX-A-06-10 Area - WPSC D2-9 B
12-21-2001 JPIC - State and County Work Area EPIP-APPX-A-06 EP-FIG-044 APPX-A-06-07 WPSC D2-8 C
12-21-2001 JPIC - Utility Work EPIP-APPX-A-06 EP-FIG-045 APPX-A-06-05 Area - WPSC D2-7 C
12-21-2001 Aurora Medical Center RET-08 EP-FIG-046 RET-08-01 Location Deleted 05-23-2002 EPIP-APPX-A-02 APPX-A-02-01 ERO Call Tree Deleted 12-04-2001 PAGE 7 OF 11
"EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 08-06-2002 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: 08-06-2002 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 A
02-27-2002 Take Potassium Iodide EP-ENV ENV-01-01 Environmental Dispatch Area Activation Checklist D
10-31-2000 ENV-01-02 EMT Status B
10-31-2000 ENV-01-03 Meteorological and Plant Status Data C
12-14-2001 ENV-01-04 EMT Orders/Field Data B
10-31-2000 ENV-02-01 EMT Activation Checklist M
06-15-2000 EP-EOF EOF-02-01 EOF Activation Checklist 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-11-02 Operating Status F
11-15-2001 EOF-11-03 Environmental Status Board F
11-15-2001 EOF-12-01 I.D. Badge Registration Form G
10-24-2000 PAGE 9 OF 11
EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 08-06-2002 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-0 1.03 Severe Accident Management - Status B
02-06-2002 TSC-02-01 TSC and OSF Activation Checklist 0
09-27-2001 PAGE 10 OF 11
EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 08-06-2002 FORM EPIPF TITLE REV.
DATE TSC 2.2 TSC Ventilation Checklist H
04-01-99 TSC-02-03 Emergency Response Data System (ERDS) Link Initiation G
05-04-2001 Checklist TSC-02-04 TSC Chart Recorder Operation Checklist D
01-30-2001 TSC-02-05 TSC and OSF De-activation Checklist A
10-09-2001 TSC-03-01 Plant System Status L
06-12-2001 TSC-03-02 Plant Equipment Status L
06-12-2001 TSC-03-03 Environmental Status Board 1
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 D
12-14-2001 Program)
TSC-09A-01 Core Exit Thermocouple Data D
05-16-2002 TSC-09A-02 Fuel Rod Clad Damage Estimate D
05-16-2002 TSC-09A-03 Fuel Rod Overtemperature Damage Estimate E
05-16-2002 TSC 9A.4 Core Damage Based on Activity Ratios Deleted 05-16-2002 TSC-09A-05 Core Damage Assessment (Monitoring Data)
E 05-16-2002 TSC 9A.6 Core Damage Summary Deleted 05-16-2002 PAGE 11 OF 11
1.0 Purpose 1.1 This procedure provides instruction for activating the Emergency Operations Facility (EOF).
2.0 General Notes 2.1 Telephone numbers and location of staff positions for the EOF are located in the KPB Emergency Telephone Directory.
2.2 A general description of communications equipment is contained in APPX-A-1, "Communication System Description," and may be helpful in resolving minor problems with the equipment.
3.0 Precautions and Limitations 3.1 If any of the actions on Form EPIPF-EOF-02-01, "EOF Activation Checklist,"
cannot be satisfied in a reasonable period of time, then the problem shall be noted on Form EPIPF-EOF-02-01 and an Action Request (AR) initiated at the next convenient opportunity. Consideration of activation should not be delayed for problems with individual actions on Form EPIPF-EOF-02-01.
3.2 The Emergency Response Manager (ERM) will make the decision whether the EOF can be activated prior to resolution of problems.
3.3 If it becomes necessary to evacuate or relocate the EOF, the ERM should utilize the guidance supplied in Section 5.2 to assist in transferring the functionality of the EOF to an alternate facility.
4.0 Initial Conditions 4.1 The EOF shall be activated for an Alert, Site Emergency, General Emergency, or at the discretion of the ERM.
4.2 Upon activation of the EOF, the Administrative and Logistics Director (ALD) shall assign and complete actions in accordance with this procedure.
n:.nucdoc~procedures\\draft\\epip\\eeof02.doc-Christine Simmons/Christine Simmons-Jeanne Ferris REFERENCE USE
- !., *;ý"-WISCONSIN PUBLI.ERVIC P
No.
EPIP-EOF-02 Rev.
AA STitle Emergency Operations Facility (EOF) ewau Nuclear Power Plant'.,,t Activation
- .*'Eniergency Plan Im'dlemening roceaure."'
Date AUG 6 2002 Page 1 of 3 Reviewed By Scott VanderBloomen Approved By Dave Seebart Nuclear PORC YeSRO Approval Of
[ Yes Safety
[ Yes Review Te SRo T
aproar Related E No Required
[]No Changes Required
[]No
5.0 Procedure 5.1 Activation 5.1.1 Complete Form EPIPF-EOF-02-01, "EOF Activation Checklist."
5.1.2 IF communications or PC equipment problems are identified, THEN contact WPSC Information Technology Services (ITS) OR Telecommunications as listed in the KPB Emergency Telephone Directory, Section ETD 04, AND state the following:
"* Telephone number or system with the problem
"* The nature of the problem
"* That emergency service is needed 5.1.3 WHEN Form EPIPF-EOF-02-01, "EOF Activation Checklist," (Items I through 4) is completed, give the form to the ERM for review and signature.
5.2 EOF Evacuation/Relocation 5.2.1 IF it becomes necessary to evacuate or relocate the EOF, THEN the ERM should consider the following in order to maintain the functionality of the EOF:
"* EOF Dose Assessment and Protective Action Recommendations may be formulated in the TSC
"* Command and control of Environmental Monitoring Teams may be transferred to the TSC
"* NRC and State and County communications may be handled from the TSC
"* The ERM may reposition to the TSC or the Point Beach EOF in the Point Beach Site Boundary Command Center 5.3 Deactivation 5.3.1 WHEN final conditions are met, complete Form EPIPF-EOF-02-02, "EOF Deactivation Checklist."
5.3.2 WHEN Form EPIPF-EOF-02-02 is completed, give the form to the ERM for review and signature.
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.
REFERENCE USE
LWISCONSIN PUBICERVICENo.
EPIP-EOF-02 Rev.
AA Title Emergency Operations Facility (EOF) n NActivation Date AUG 62002 Pate 3 of 3 7.0 References 7.1 Kewaunee Nuclear Power Plant Emergency Plan 7.2 APPX-A-1, Communication System Description 7.3 KPB Emergency Telephone Directory 7.4 COMTRAK 88-169, Title Markers for the EOF Staff 7.5 NAD-1 1.08, Action Request Process 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
- Form EPIPF-EOF-02-01, EOF Activation Checklist e
Form EPIPF-EOF-02-02, EOF Deactivation Checklist 8.1.2 Non-QA Records None REFERENCE USE
4
? * -
.zz'ZWISCONSIN PUBLIC-SERVICE CORP.,,-'."
No.
EPIP-EOF-04 Rev.
AJ Title EOF Staff Action for Alert or Higher
,Z'., *Kewaunee Nuclear Power Plant an Sz'-Emer ency Plan Implementtin Procedure '--1 Date AUG 6 Page 1 of 23 Reviewed By William Bartelme Approved By W. L. Yarosz Nuclear 0 Yes PORC 13 Yes SRO Approval Of 0 Yes Safety Review Temporary Related 0I No Required El No Changes Required El No 1.0 Purpose 1.1 This procedure provides instruction for the Emergency Response Manager and other initial response personnel for an appropriate response to an Alert, Site Emergency, or General Emergency, at the Emergency Operations Facility (EOF).
2.0 General Notes 2.1 Personnel on-site depart for the EOF promptly through the security building, unless instructed to assemble elsewhere by the Gai-tronics announcement or security personnel.
2.2 IF notified by radio-pager and the message is not understood, THEN emergency response personnel should confirm contact by telephoning Meridian Mail at 1-800-236-1588. A Meridian Mail voice message will indicate that the radio-pager activation was for an actual declared emergency and NOT a drill or exercise.
2.3 As more information becomes available, initial protective action recommendations should be adjusted in accordance with plant conditions, dose projections, time available to evacuate, estimated evacuation times, and meteorological conditions (EPIP-AD-19).
2.4 IF approached by the media during a declared emergency, THEN refer them to the Telephone Response Center at 920-433-1400 or 1-800-838-6192 and tell them that this is their most accurate source for information.
3.0 Precautions and Limitations 3.1 "Event Notice," Form EPIPF-AD-07-01, should be initiated and in progress to State and Local Emergency Governments within 15 minutes of the emergency level being declared or as soon as possible without further compromise to plant or public safety.
3.2 The Emergency Response Manager has the nondelegable responsibility for making protective action recommendations.
3.3 IF an emergency class escalation occurs during implementation of this procedure, THEN immediately reinitiate this procedure appropriate to the new emergency level declared.
n:\\nucdockproceduresdtraft\\epip\\eeofO4.doc-Chnstine Simmons/Chnstine Simmons-Jeanne Fernis REFERENCE USE
WISCONSIN PUBLIC SERVICE CORP.
No.
EPIP-EOF-04 Rev.
AJ Title EOF Staff Action for Alert or Higher
- ,Kewaunee Nuclear Power Plant
' *..ZEmergency Plan Implementimg ýPr~igcere2214=,i Date AUG 6 2002 Page 2 of 23 3.4 Only the following personnel may authorize support personnel without Kewaunee I.D. cards access to the EOF during a declared emergency:
3.4.1 Emergency Response Manager (ERM) 3.4.2 Administrative/Logistics Director (ALD) 3.4.3 Environmental Protection Director (EPD) 4.0 Initial Conditions 4.1 This procedure shall be implemented upon declaration of an Alert, Site Emergency, General Emergency, or when directed by the Emergency Response Manager.
5.0 Procedure Note It is the ERM's responsibility to provide overall direction and coordination of the KNPP emergency response activities, make protective action recommendations to government authorities, coordinate efforts with external organizations (governmental, industry, vendors, etc.), and support the plant's efforts to mitigate the accident by ensuring continuity of resources for long term operation of the emergency response organization.
5.1 Emergency Response Manager (ERM) shall:
5.1.1 WHEN notified that an Emergency has been declared,
- a. Report to the Emergency Operations Facility.
- b. IF an Emergency Response Manager has been designated, until released, THEN:
- 1. If appropriate, plan a shift relief per EPIP-AD-05, "Emergency Response Organization Shift Relief Guideline."
- 2. Assist the designated Emergency Response Manager.
- c. IF an Emergency Response Manager has NOT been designated, THEN assume the responsibilities of the Emergency Response Manager or continue implementation of this procedure.
Note Verbally inform the Emergency Director that you have accepted the PAR responsibilities.
5.1.2 Notify the Emergency Director of your arrival and assumption of the Emergency Response Manager duties.
REFERENCE USE
`rWISCONSIN PUBLIC SERVICE CORP.'"
No.
EPI-EOF-04 Rev.
AJ 1 -4 1 I 'Title EOF Staff Action for Alert or Higher Wt Kewaunee Nuclear,owe Plant c-:t
- EmergencPlan ImplementingProceditir ~
Date AUG 6 2002 Page 3 of 23 5.1.3 Accept formal turnover of the responsibility for PARs from the ED.
5.1.4 Ensure date and time is entered in the EOF log for turnover of responsibilities for PARs from the ED in the TSC.
5.1.5 When appropriate, direct the Off-Site Communicator in the EOF to take responsibility for off-site notifications from the TSC.
5.1.6 Verify a State Radiological Coordinator Liaison (SRCL) or the Radiological Protection Director (RPD) is prepared to transmit radiological related data and general plant conditions to the State Radiological Coordinator-in-the State Emergency Operations Center (Madison).
5.1.7 Verify engineering/licensing and communicator support are available in the EOF.
5.1.8 IF director(s) or supporting staff positions are not arriving at the EOF in a reasonable amount of time, THEN instruct the Off-Site Communicator to contact the individuals needed by telephone and/or by individual radio-pager codes.
5.1.9 IF a director position cannot be filled, THEN assign that director's duties to another director's position.
5.1.10 Ensure the ALD is completing EOF activation in accordance with "Emergency Operations Facility (EOF) Activation," EPIP-EOF-02.
5.1.11 Ensure the ALD is establishing security in accordance with "Media Center/Emergency Operation Facility/Joint Public Information Center Security," EPIP-EOF-12.
5.1.12 Establish Communications with the Technical Support Center and Control Room through the Darome Conference System.
5.1.13 Through the Emergency Response Facility Communicator - EOF, verify the status of off-site agency communications that have taken place from the Control Room.
REFERENCE USE
WISCONSIN PUBLIC SERVICE CORP.
No.
EPIP-EOF-04 Rev.
AJ Title EOF Staff Action for Alert or Higher
- ?.:*Kewaunee Nuclear Power Plant.-
- Eiiergen'cyPlani ~,imilemnentmg Procedure :2 Date AUG 6 2002 Page 4 of 23 Note The EOF can be activated for individual functions, i.e., off-site notifications prior to full activation of the facility.
5.1.14 WHEN confirmed with the Off-Site Communicator that the EOF is capable to assume off-site notification,
- a. Assume the responsibility for off-site notifications.
- b. Inform the ED of the transfer of this responsibility.
- c. Instruct the Off-Site Communicator to contact the State and County.EOCs (if active) and notify them that the EOF has the responsibility for 6ff-sit6 communications.
5.1.15 Contact and notify the JPIC Manager of the EOF activation status.
5.1.16 Ensure the KPB Nuclear Emergency Public Information Plan is being implemented for
.the declared emergency.
5.1.17 Ensure the EPD is taking steps to perform dose projections and provide assistance in making protective action recommendations.
5.1.18 Determine the emergency status by obtaining the following information from the emergency response organization in the EOF:
- a. Engineering/Licensing Support
"* Significant plant evolutions
"* NRC response team status and issues
- b. Environmental Protection Director
"* Status of Radiological Effluent Releases (potential off-site dose consequences)
"* Off-Site Dose Assessment Evaluation
"* Status of Environmental Monitoring Teams
"* Potassium Iodide Distribution e -Adequacy of the Protective Action Recommendations
- c. Administrative Logistics Director
- EOF Activation and Operational Status (EPIP-EOF-02) e EOF/JPIC Security Status (EPIP-EOF-12) 0 Status of ERO response REFERENCE USE
- Status of Information flow in the EOF
- Continuity of resources for long term operation of the emergency response organization
- d. State Radiological Coordinator Liaison
- Status of communications with the State of Wisconsin, State Radiological Coordinator
- e. Off-Site Communicator
- Off-Site Communications status
- Significant State and County concerns, priorities, and actions
- PAR implementation status 0 State or County requests for "Plant Emergency Status Report,"
Form EPIPF-EOF-08-05, or other information update
°It is NO__T required to de-escalate from an Emergency Action Level.
Termination or direct entry into recovery is preferable. However, there may be occasions when it is more appropriate to de-escalate.
EPIP-AD-02, "Emergency Class Determination, " and other EPIPs are NOT written to facilitate de-escalation. Therefore, any decision to de-escalate instead of entering recovery must be based on a thorough review of EPIP-AD-02 and careful use of appropriate procedures.
5.1.19 Review requirements for escalation and de-escalation situations with the Emergency Director (EPIP-AD-02).
5.1.20 As required, review the EALs and plant status to ensure the event classification is appropriate (EPIP-AD-02).
Note Off-site protective actions for the public are NOT required for events classified less than a general emergency.
5.1.21 As required, instruct the Environmental Protection Director to review off-site dose measurements and projections to ensure the event classification is appropriate.
5.1.22 Review current and potential protective action recommendations (EPIP-AD-19).
REFERENCE USE
SWiSCONSIN PUBLIC SERVICE CORP.
No.
EPIP-EOF-04 Rev.
AJ z, Title EOF Staff Action for Alert or Higher (Kewaunee Nuclear Power Plant
':A*Eernguffenc4 Pdn-IMplemenrgroceaure eu-*
Date AUG 6r2002 Page 6 of 23 5.1.23 IF time permits,.THEN contact Off-Site Authorities via the Dial Select to discuss potential changes in classification and/or appropriate PAR.
5.1.24 IF notified by the ED of any change in EALs, OR if there is a change in PARs, THEN:
- a. Ensure, with the assistance of the Engineering/Licensing Support Coordinator, an "Event Notice," Form EPIPF-AD-07-01, is complete.
- b. Review and sign all "Event Notice," Form EPIPF-AD-07-01, generated from the EOF.
- c. Direct the Off-Site Communicator to initiate notifications using the "Event Notice," Form EPIPF-AD-07-01.
- d. Verify that required notifications are made by the Off-Site Communicator (EPIP-AD-07, "Initial Emergency Notification," or EPIP-EOF-08, "Continuing Emergency Notifications").
Note The appropriate Government Agency contacts for the ERM are:
"* State of Wisconsin - Officer in Charge (OIC) @ Dial Select 83 or 608-242-3260/3261 e Kewaunee County - Emergency Government (Director) @ Dial Select 43 or 920-487-5257
"* Manitowoc County - Emergency Management Director @ Dial Select 53 or 920-683-4916/4918 5.1.25 WHEN contacted, or periodically, provide Off-Site Authorities with the following (Dial Select is the preferred communication link):
- a. Available information on the event status using "Plant Emergency Status Report," Form EPIPF-EOF-08-05, as a guide. This data can be provided by the Engineering/Licensing Coordinator.
- b. IF a hard copy of "Plant Emergency Status Report" is specifically requested by State or County Officials, THEN:
"* Direct the Engineering/Licensing Coordinator to provide written plant event summaries using "Plant Emergency Status Report,"
Form EPIPF-EOF-08-05.
"* Review and approve "Plant Emergency Status Report,"
Form EPIPF-EOF-08-05.
" Forward the approved 'Plant Emergency Status Report,"
Form EPIPF-EOF-08-05, to the Off-Site Communicator with direction to fax them to the State and County EOCs.
REFERENCE USE
5.1.26 WHEN a completed "Radiological Status Report," Form EPIPF-EOF-08-06, is received:
- a. Review,
- b. Approve, AND
- c. Return to the SRCL.
5.1.27 Contact the ED periodically to receive an update on:
"* Status of the plant
"* Material and Personnel support requirements
"* On-site or off-site radiological releases or potential releases and release paths
"* Priorities of tasks to minimize the impact of the accident on the public
"* Incidents of public interest (i.e., fires, spills, personnel contaminations/injuries) 5.1.28 Periodically inform the ED of:
State and County priorities
- State and County actions (i.e., protective actions, evacuations, traffic control, etc.)
- State and County areas of concern e Media areas of interest and any misinterpretations of the plant situation 5.1.29 Determine EOF priorities, evaluate activities in the following areas:
9 Logistical requirements to mitigate significant plant evolutions 0 Off-site dose consequences
- Protective action recommendations e
Protective actions implemented by the Counties 5.1.30 Periodically conduct briefings for the EOF Emergency Response Organization:
"* Status of the plant
"* Material and Personnel support requirements
"* On-site or off-site radiological releases or potential releases and release paths
"* Incidents of public interest (i.e., fires, spills, personnel contaminations/injuries)
"* State and County priorities REFERENCE USE
NwSCONSlN PUBLIC SERVICE CORP.
No.
EPIP-EOF-04 Rev.
AJ
-Title EOF Staff Action for Alert or Higher iKewaunee NucleaPerPoD6f rtrg:c IPan *Impfeimentdng Proedue 58 Date AUG 6 2002 Pagle 8of2
"* State and County actions (i.e., protective actions, evacuations, traffic control, etc.)
"* State and County areas of concern
"* Media areas of interest and any misinterpretations of the plant situation
"* EOF priorities 5.1.31 Ensure that the Spokesperson is informed. Forward plant status and public interest information to the Spokesperson for appropriate use in briefings to the:
"* Public
"* Media
"* WPSR Senior Management
"* Partners
"* Other financial stakeholders in KNPP or WPSR 5.1.32 If appropriate, plan for a shift relief per EPIP-AD-05.
5.1.33 IF plant conditions meet the requirements of Section 5.1 of EPIP-AD-15, "Recovery Planning and Termination," THEN recovery activities or termination can be implemented in accordance with EPIP-AD-15.
5.1.34 IF Final Conditions are NOT met (Section 6.0), THEN return to Step 5.1.15.
5.1.35 WHEN Final Conditions are met (Section 6.0),
- a. Ensure that termination or plant recovery Event Notifications have been initiated by the Off-Site Communicator.
- b. Verify all work areas are returned to normal status and emergency procedures, forms, etc., are returned to their proper place.
- c. Collect all completed forms, notes, and other documentation and give them to the ALD.
- d. Schedule a self-critique with all event participants in the EOF (all shifts) as soon as practical. The procedure "Drill and Exercise Critiques,"
EPMP-02.04, should be used as a guide.
REFERENCE USE
,h 6WISCONSIN PUBLIC SERVICE CORP.*C*C, No.
EPIP-EOF-04 Rev.
Al Title EOF Staff Action for Alert or Higher
,.)Kewau-ee Nuclear Power Pl nt
- 1. _
r'EniýeragyPlan implementing Procedure'"
Date AUG 6 2002 Page 9 of 23 5.2 Administrative Logistics Director (ALD) shall:
5.2.1 WHEN notified that an Emergency has been declared,
- a. Report to the Emergency Operations Facility immediately.
- b. IF an Administrative Logistics Director has been designated, until released, THEN:
- 1. If appropriate, plan a shift relief per EPIP-AD-05.
- 2. Assist the designated Administrative Logistics Director.
- c. IF an Administrative Logistics Director has NOT been designated,.THEN..
assume the responsibilities of the Administrative Logistics Director and continue implementation of this procedure.
5.2.2 Notify the Emergency Response Manager of your assumption of the responsibilities of the Administrative Logistics Director.
5.2.3 As directed by the ERM,
- a. Contact EOF administrative support personnel or others.
- b. Instruct them to report to the EOF immediately or to remain on standby for further instructions.
5.2.4 Support or implement the EOF activation process (EPIP-EOF-02).
5.2.5 Arrange for security support at the EOF, JPIC, and MC by implementing procedure EPIP-EOF-12.
5.2.6 As needed, assign EOF support personnel to provide administrative support as defined in EPIP-EOF-11, "Internal Communications and Documentation Flow," to:
- a. Maintain status boards and event sheets (Step 5.1).
- b. Ensure communications are properly distributed (Step 5.2).
- c. Ensure that a "Master Log" is established and maintained (Step 5.3).
5.2.7 Establish procedures for the long term storage of the documents, records, and logs generated by the event.
REFERENCE USE
5.2.8 Ensure that appropriate logs, records, and documents are maintained for the duration of the event. Those logs, records, and documents shall include as a minimum:
9 Ongoing plant status and conditions o Date and time of significant accident events
- Chronology of plant accident mitigation and repair priorities 0 All calculated, measured, or State provided radiological release data and information
- All event notification and status update documents generated o Any messages generated or recorded o All Honeywell computer printouts generated for status board maintenance or general information
- All logs maintained by EOF staff
- All news statements from the PIC 5.2.9 Monitor the flow of information in the EOF and correct any problems.
5.2.10 If required, arrange for communication system service repair (see EPIP-EOF-02, Step 5.1.3).
5.2.11 If required, develop a shift schedule to provide for 24-hour operation of the EOF and security staff per EPIP-AD-05.
5.2.12 Obtain purchasing support (see KPB Emergency Telephone Directory, ETD 04 for NMC contact) for assistance in the following:
- Material purchase and control contract negotiations, expense accounts 5.2.13 If needed, provide for the following manpower needs:
- Technical and craft disciplines through organizations such as Westinghouse Electric Corporation, Fluor Engineering, or INPO
- Labor relations' assistance 5.2.14 If needed, obtain the following logistical assistance for:
- Transportation of emergency response personnel e
Airline and hotel accommodations 9 Office supplies and furniture o Document reproduction e Food deliveries 9 Sanitation REFERENCE USE
WSCONSIN PUBIC SERVICE CO No.
EPIP-EOF-04 Rev.
AJ Title EOF Staff Action for Alert or Higher
,74ýý,'z,'Kewaunee Nuclear Power Plant V-..
Emergencj Plan Implementing Procedure `[Date AUG 6 2002 Page 11 of 23 5.2.15 IF Final Conditions are not met (Section 6.0), THEN return to Step 5.2.6.
5.2.16 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 records and logs as described in procedure "Declared Emergency Evaluation and Documentation," EPMP-02.01.
- c. Ensure "EOF Deactivation Checklist," Form EPIPF-EOF-02-02, is completed per EPIP-EOF-02.
5.3 Environmental Protection Director (EPD) shall:
5.3.1 WHEN notified that an Emergency has been declared,
- a. Report to the Emergency Operations Facility.
- b. IF an Environmental Protection Director has been designated, until released, THEN:
- 1. If appropriate, plan a shift relief per EPIP-AD-05.
- 2. Assist the designated Environmental Protection Director.
- c. IF an Environmental Protection Director has NOT been designated, THEN assume the responsibilities of the Environmental Protection Director and continue implementation of this procedure.
5.3.2 Notify the Emergency Response Manager of your assumption of the responsibilities of the Environmental Protection Director.
5.3.3 If necessary, establish the environmental team organization in accordance with EPIP-ENV-01, "Environmental Monitoring Group Organization and Responsibilities."
5.3.4 Ensure status boards are maintained along with a record of significant events, data reported, and directives given.
5.3.5 Provide overall direction to the Environmental Monitoring Group.
5.3.6 Prepare plant status updates for transmission to the Environmental Monitoring (EM)
Teams.
5.3.7 Direct the State Radiological Coordinator Liaison to provide available information to the State Radiological Coordinator using Form EPIPF-EOF-08-06 as a guide.
5.3.8 Inform the RPD when an EM Team member approaches administrative or legal radiological exposure limits.
REFERENCE USE
ZWIONSIN PUBLIC SERVICE.CORP.
No.
EPIP-EOF-04 Rev.
AJ Title EOF Staff Action for Alert or Higher Date AUG 6 2002 Page 12 of 23 5.3.9 Maintain an overall awareness of environmental conditions and the contributing factors for development of protective action recommendations in accordance with EPIP-AD-19.
5.3.10 Evaluate dose projections and field data.
5.3.11 Assist the Emergency Response Manager (ERM), the Emergency Director (ED), and the Radiological Protection Director (RPD) in determining protective action recommendations.
5.3.12 Communicate frequently with the Radiological Protection Director to confirm the accuracy of input data to the dose projection process.
5.3.13 As necessary, establish and maintain communication with other Emergency Response Organization Directors and Off-Site Authorities.
5.3.14 IF a radiological release has occurred or is imminent, THEN contact Environmental Inc. (Midwest Lab.) (see KPB Emergency Telephone Directory for phone number) and make arrangements for conducting soil/vegetation/water/snow deposition sampling and analysis.
- a. Identify locations where deposition sampling and analysis is needed using EMT field data and dose projection results.
- b. Perform sampling and analysis using the methodology described in the KNPP "Radiological Environmental Monitoring Manual (REMM)."
- c. Provide sample analysis results to the State Radiological Coordinator.
5.3.15 If appropriate, plan for a shift relief per EPIP-AD-05.
5.3.16 IF Final Conditions are NOT met (Section 6.0), THEN return to Step 5.3.4.
5.3.17 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 records, logs, forms, notes, and other documentation and give them to the ALD.
- c. Schedule a self-critique with all event participants in the environmental group (all shifts) as soon as possible. The procedure "Drill and Exercise Critiques," EPMP-02.04, should be used as a guide.
REFERENCE USE
,.?:*NWISCONSIN PUBLIC SERVICECR P.
No.
EPIP-EOF-04 Rev.
AJ S
5............... Title EOF Staff Action for Alert or Higher r>-
Kewaunee Nuclear Power Plant
-Q.'.
Emergency Plan Implementing Procedure Date AUG 6 2002 Page 13 of 23 5.4 State Radiological Coordinator Liaison (SRCL) shall:
5.4.1 WHEN notified that an Emergency has been declared:
- a. Report to the Emergency Operations Facility.
- b. IF a State Radiological Coordinator Liaison has been designated, until released, THEN
- 1. Assist in the activation of the EOF per EPIP-EOF-02.
- 2. If appropriate, plan a shift relief per EPIP-AD-05.
- 3. Assist the designated State Radiological Coordinator Liaison.
- c. IF a State Radiological Coordinator Liaison has NOT been designated, THEN assume the responsibilities of the State Radiological Coordinator Liaison and continue implementation of this procedure.
5.4.2 Notify the Environmental Protection Director of your assumption of the responsibilities of the State Radiological Coordinator Liaison.
5.4.3 Obtain and complete "SRCL Initial Action Checklist," Form EPIPF-EOF-04-01.
Note Assistance may be obtained from other environmental organization members or by requesting the ALD to provide EOF support staff.
5.4.4 Ensure radiological information provided by the State Radiological Coordinator is passed to the EPD.
5.4.5 Perform an initial core damage assessment.
5.4.5.1 Collect the following values from the plant process computer using Attachment A.
0 Core exit thermocouple reading - PPCS Graphic Display #4 Containment radiation monitor readings R-40 & R PPCS Point ID G0040G & G0041G Note It is not necessary to proceed to Step 5.2 or Step 5.3 of EPIP-TSC-09A.
Only the high level core damage assessment is required.
5.4.5.2 Go to Step 5.1.4 of EPIP-TSC-09A, "Core Damage Assessment," and determine the appropriate classification of fuel damage using all of the parameters collected in Step 5.4.5.1.
REFERENCE USE
- -?WISC0NSIN PUBLIC SERVICE-CORP.
No.
EPJP-EOF-04 Rev.
AJ S-.-'..-*
Title EOF Staff Action for Alert or Higher earPow-i" Pla nt
~-'~Eegecfl~irplmntnkPo ib~ZDate AG602Page 14of2 5.4.5.3 Provide fuel damage assessment results to the following positions:
"* Technical Support Center Director
"* Environmental Protection Director
"* Dose Projection Calculator 5.4.6 On a continual basis, collect available information using the following forms as a guideline:
"* "Plant Emergency Status Report," Form EPIPF-EOF-08-05 (from the Engineering/Licensing Coordinator)
"* "Radiological Status Report," Form EPIPF-EOF-08-06 (from the ENV Dose Calculator)
"* Other sources that would provide information to assist the SRC in making decisions concerning public health and safety 5.4.7 Transmit information to the SRC by phone as promptly as possible.
5.4.8 IF specifically requested by State or County Officials, THEN provide written radiological event summaries using Form EPIPF-EOF-08-06 for transmission to those officials by facsimile.
- a. Complete "Radiological Status Report," Form EPIPF-EOF-08-06.
- b. Forward the completed Form to the ERM for approval.
- c. Inform the EPD that you have completed "Radiological Status Report,"
Form EPIPF-EOF-08-06, to be transmitted by facsimile to State and County Officials.
Note If needed, use an extra SRCL to cover the HPN phone.
5.4.9 Respond to incoming calls from the NRC over the HPN phone.
5.4.10 Support the completion of "Event Notice," Form EPIPF-AD-07-01, and the development of protective action recommendations.
5.4.11 If appropriate, plan for shift relief per EPIP-AD-05.
5.4.12 IF Final Conditions are NOT met (Section 6.0), THEN return to Step 5.4.4.
REFERENCE USE
ON PUBLIC SERVICE CORP.9.J No.
EPP-EOF-04,Rev.
AJ S,-
Title EOF Staff Action for Alert or Higher 0,-ýtKewaunee Nuclear Power Plant
"<-7
-Emergency Plan Implementing Procedure rDate AUG 6 2002 Page 15 of 23 5.4.13 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 records, logs, notes, and other documentation and give them to the ALD.
5.5 Engineering/Licensing Support Coordinator shall:
5.5.1 WHEN notified that an Emergency has been declared,
- a. Report to the Emergency Operations Facility.
- b. IF an Engineering/Licensing Support Coordinator has been designated, until released, THEN
- 1. Assist in the activation of the EOF per EPIP-EOF-02.
- 2. If appropriate, plan a shift relief per EPIP-AD-05.
- 3. Assist the designated Engineering/Licensing Support Coordinator.
- c. IF an Engineering/Licensing Support Coordinator has NOT been "designated, THEN assume the responsibilities of the Engineering/Licensing Support Coordinator and continue implementation of this procedure.
5.5.2 Notify the Emergency Response Manager that you have assumed the responsibilities of the Engineering/Licensing Support Coordinator.
5.5.3 Monitor engineering, operational, and licensing events related to the event for the ERM.
Note Assistance may be obtained by requesting the ALD to provide EOF support staff.
5.5.4 Ensure status boards are maintained.
5.5.5 Review messages in the "IN" box and:
- a. Brief the ERM on significant changes, events, and information.
- b. IF the message should be placed on the status board or flip chart, THEN mark them as "POST location 0 Operations Status Board 0 Environmental Status Board Flip Chart
- c. Place the reviewed messages in the "OUT" box.
REFERENCE USE
5.5.6 WHEN required, provide the ERM:
- a. Review of the event classification (EPIP-AD-02).
- b. When directed by the ERM, complete "Event Notice," Form EPIPF-AD-07-01, for approval and transmittal to off-site agencies.
- c. Updated "Plant Emergency Status Report," Form EPIPF-EOF-08-05.
5.5.7 Perform liaison duties between the ERM and the NRC event response team in the EOF.
5.5.8 Coordinate the activities of the Emergency Response Facility Communicator - EOF for communications with other emergency facilities as appropriate.
5.5.9 If appropriate, plan for a shift relief, per EPIP-AD-05.
5.5.10 IF Final Conditions are not met (Section 6.0), THEN return to Step 5.5.3.
5.5.11 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 records, logs, forms, notes, and other documentation and give them to the ALD.
5.6 Off-Site Communicator shall:
5.6.1 WHEN notified that an Emergency has been declared during off-hours, THEN
- a. Report to the Emergency Operations Facility.
- b. IF an Off-Site Communicator has been designated, until released, THEN
- 1. Assist in the activation of the EOF.
- 2. If appropriate, plan a shift relief per EPIP-AD-05.
- 3. Assist the designated Off-Site Communicator.
- c. IF an Off-Site Communicator has NOT been designated, THEN assume the responsibilities of the Off-Site Communicator and continue implementation of this procedure.
5.6.2 Verify the phones needed for the Off-Site Communicator are properly located and functional.
REFERENCE USE
I -WISCONSIN PUBLIC SERVICE CORP. '---,*
No.
EPIP-EOF-04 Rev.
AJ Title EOF Staff Action for Alert or Higher Kewaunee Nuclear Power Plant "I Emergency Plan Implementing Procedure Date AUG 6 2002
[
Pale 17 of 23 Note Verbally inform the ERM that you have accepted the Off-Site Communicator responsibilities.
5.6.3 Notify the Emergency Response Manager of your arrival and availability to perform off-site communications.
5.6.4 When directed by the ERM, accept formal turnover of responsibilities for off-site communications from the TSC or Control Room.
5.6.5 When completed, notify the Emergency Response Manager that off-site communication responsibility has been accepted in the EOF.
5.6.6 Enter date and time in the EOF log for turnover of responsibilities for off-site communications from the TSC or Control Room.
Note Until turnover of off-site communications is complete, the Control Room or TSC has primary responsibility of the government verification lines. These lines should not be answered unless it is obvious that they are not being answered at the other facilities. IF the line is answered in the EOF prior to official turnover, THEN every effort should be made to reconnect the party on this line with the facility with primary responsibility and in the interim provide the best information available.
5.6.7 When directed by the ERM, start the transfer of off-site communications from the Control Room or TSC to the EOF.
- a. Contact the Event Operations Director (EOD in CR) or Off-Site Communicator (TSC), and obtain a briefing on the status of off-site notification.
Note Remind the EOD and/or Off-Site Communicator (TSC) to turn the bell switch on the Government Verification phone to the OFF position.
- b. WHEN mutually agreed upon, relieve the Control Room or TSC of off-site notification responsibilities.
- c. Ask the EOD or Off-Site Communicator (TSC) to fax a copy of all "Event Notice," Form EPIPF-AD-07-01, issued from the Control Room to the EOF at their earliest convenience.
5.6.8 Inform the ERM that the EOF now has responsibility for off-site notifications.
REFERENCE USE
SCONSIN PUBLIC SERVICECORP.
No EPIP-EOF-04 Rev.
AJ Y Title EOF Staff Action for Alert or Higher
\\ad'-AUG62 NUc0larw ePar-l Plaoft 23 n__
_In__
Date AUG 6 2002 Page 18 of 23 5.6.9 Enter the time and date in the log that responsibilities for off-site communications was accepted by the EOF from the TSC or CR.
5.6.10 Contact off-site EOC's and determine the status of their activation.
5.6.11 When activated, obtain the following information from the off-site EOCs:
"* Significant State or County concerns, priorities, and actions
"* If appropriate, PAR implementation status
"* Required reports or other information from KNPP -
5.6.12 Review current status board and chronological event sheet entries.
5.6.13 WHEN directed by the ERM, perform off-site notifications.
- a. IF off-site EOCs HAVE been activated, THEN Go To EPIP-EOF-08 and perform notifications.
- b. IF off-site EOCs have NOT been activated, THEN Go To EPIP-AD-07, Step 5.3 and perform notifications.
5.6.14 If requested by the ERM, fax hard copy status reports (Forms EPIPF-EOF-08-05 or EPIPF-EOF-08-06) to the State and County EOCs.
Note Assistance may be obtained by requesting the ALD to provide EOF support staff.
5.6.15 Ensure the EOF status board for off-site conditions is updated on a regular basis.
Assistance by the EOF support staff may be requested from the ALD.
5.6.16 If directed by the ERM, activate ERO pagers using EPIP-EOF-08 Step 5.3.
5.6.17 Record incoming and outgoing ad hoc telephone messages on "Telephone Communications Log Sheet," Form EPIPF-EOF-04-02.
5.6.18 WHEN requested, brief the ERM on off-site communications, include the following items:
, Off-site Communications status
- Significant State and County concerns, priorities, and actions
- PAR implementation status
- State or County requests for status reports (Form EPIPF-EOF-08-05) or other information updates REFERENCE USE
WISCONSIN PUBLIC SERVICE CORP..*'",
No.
EPIP-EOF-04 I Rev.
AJ Title EOF Staff Action for Alert or Higher Kewaunee Nuclear Power Plant
-:Emergency Plan Implementing Procedure Date AUG 62002 Page 19 of 23 5.6.19 Provide communication support as directed by the ERM.
5.6.20 If appropriate, plan for shift relief per EPIP-AD-05.
5.6.21 IF Final Conditions are not met (Section 6.0), THEN return to Step 5.6.6.
5.6.22 WHEN Final Conditions are met (Section 6.0),
- a. Ensure that termination or recovery communications are made as directed by the ERM in accordance with Step 5.6.6.
- b. Verify all work areas are returned to normal status and emergency procedures, forms, etc., are returned to their proper place.
- c. Collect all completed records, logs, forms, notes, and other documentation and give them to the ALD.
5.7 Emergency Response Facility (ERF) Communicator - Emergency Operations Facility (EOF) shall:
5.7.1 WHEN notified that an Emergency has been declared,
- a. Report to the Emergency Operations Facility.
- 1. Assist in the activation of the EOF.
- 2. If appropriate, plan a shift relief per EPIP-AD-05.
- c. IF an ERF Communicator - EOF has NOT been designated, THEN assume the responsibilities of the ERF Communicator - EOF and continue implementation of this procedure.
5.7.2 Notify the Engineering/Licensing Support Coordinator of your assumption of the responsibilities of the ERF Communicator - EOF.
5.7.3 Review the following items:
"* Master Log Sheets
"* Current Status Board listings
"* Current Chronological Event Sheet listing
"* Any News Statement that may have been generated 5.7.4 As directed by the Engineering/Licensing Support Coordinator, monitor the data presented on the Honeywell obtaining clarification from the plant, as necessary.
REFERENCE USE
5.7.5 Record incoming and outgoing ad hoc telephone messages on "Telephone Communications Log Sheet," Form EPIPF-EOF-04-02.
5.7.6 Enter the 4-Way Communication Link. The "dial in number" and "access number" are listed in the KPB Emergency Telephone Directory, ETD 03, "Emergency Response Facilities Telephone List."
5.7.7 Confer with the ERM and Engineering/Licensing Support Coordinator on key issues and events.
5.7.8 Ensure the ERM and Engineering/Licensing Support Coordinator are kept informed of all key issues/events at the plant. The items listed below are key-topics the ERF Communicator - EOF should be listening for:
"* Emergency Classification level declared
"* Events that caused the classification to be declared
"* Actions being taken by WPSC to mitigate the event
"* All incidents relating to personnel injury, contamination, or overexposure to radiation
"* Events happening outside the protected area of the plant (i.e., crashes, fires, tower or substation damage)
"* Outside assistance called in (i.e., ambulance, fire department, or Point Beach Nuclear Plant personnel or equipment) 5.7.9 If appropriate, plan for shift relief per EPIP-AD-05.
5.7.10 IF Final Conditions are not met (Section 6.0), THEN return to Step 5.7.3.
5.7.11 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 records, logs, forms, notes, and other documentation and give them to the ALD.
REFERENCE USE
Wo WISCONSIN PUBLIC SERVICE CORP.
No.
EPIP-EOF-04 Rev.
AJ Kewaunee*;:
Nucea Pwe Title EOF Staff Action for Alert or Higher
- .'-,:*:;kewaunee Nuclear Power Plant "",
Pluerec an mptementmng,rocedure~.
- Date AUG 62002 Page 21 of 23 5.8 EOF Support Staff shall:
5.8.1 WHEN notified that an Emergency has been declared,
- a. Report to the Emergency Operations Facility.
- b. Notify the Administrative Logistics Director of your availability to assume responsibilities of support staff and continue implementation of this procedure as directed by the Administrative Logistics Director.
5.8.2 Ensure the Honeywell terminal and printer are operating properly. Report problems to ALD.
5.8.3 Assist in activating the EOF in accordance with EPIP-EOF-02.
5.8.4 Perform the tasks described in EPIP-EOF-1 1.
5.8.5 WHEN directed by the ALD, provide general EOF support.
5.8.6 If appropriate, assist the ALD in plans for shift relief per EPIP-AD-05.
5.8.7 IF Final Conditions are not met (Section 6.0), THEN return to Step 5.8.4.
5.8.8 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 records, logs, forms, notes, and other documentation and give them to the ALD.
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.
REFERENCE USE
7.0 References 7.1 EPIP-AD-02, Emergency Class Determination 7.2 EPIP-AD-05, Emergency Response Organization Shift Relief Guideline 7.3 EPIP-AD-07, Initial Emergency Notifications 7.4 EPIP-AD-15, Recovery Planning and Termination 7.5 EPIP-AD-19, Protective Action Guidelines 7.6 EPIP-ENV-01, Environmental Monitoring Group Organization and Responsibilities 7.7 EPIP-EOF-02, Emergency Operations Facility (EOF) Activation 7.8 EPIP-EOF-03, EOF Staff Action for Unusual Event 7.9 EPIP-EOF-08, Continuing Emergency Notifications 7.10 EPIP-EOF-11, Internal Communication and Documentation Flow 7.11 EPIP-EOF-12, Media Center/Emergency Operation Facility/Joint Public Information Center Security 7.12 EPIP-APPX-A-1, Communication System Description 7.13 KPB Emergency Telephone Directory 7.14 EPMP-02.01, Declared Emergency Evaluation and Documentation 7.15 EPMP-02.04, Drill/Exercise Critique and Assessment 7.16 WPSC Nuclear Emergency Public Information Plan 7.17 Kewaunee Nuclear Power Plant Emergency Plan 7.18 NRC Inspection Report K-87-195 7.19 COMTRAK 91-187, Item 10 7.20 COMTRAK 96-163 REFERENCE USE
WISCONSIN PUBLIC SERVICE CORP.o, Rev.
AJ COR..,
INo.
EPIP-EOF-04{
e.*
Title EOF Staff Action for Alert or Higher
-,Kewaunee Nuclear Power Plant
""ergency"een o Date AUG 6 2002 Page 23 of 23 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
"* Event Notice, Form EPIPF-AD-07-01
"* EOF Activation Checklist, Form EPIPF-EOF-02-01
"* Plant Emergency Status Report, Form EPIPF-EOF-08-05
"* Radiological Status Report, Form EPIPF-EOF-08-06
"* SRCL Initial Action Checklist, Form EPIPF-EOF-04-01
"* Telephone Communications Log Sheet, Form EPIPF-EOF-04-02 8.1.2 Non-QA Records None REFERENCE USE
1
I,.
1.0 Purpose 1.1 This procedure provides instruction for identifying the release path of radioactive gaseous effluents, to ensure that appropriate effluent samples are taken and appropriate monitor readouts are recorded, in order to quantify the release and provide input data for plume projection calculations.
2.0 General Notes 2.1 This procedure is used whenever radiological data is required to perform computerized dose projections per EPIP-ENV-03C, "Dose Projection Using Rascal Version 2.2 Software."
2.2 The reference by BP effluent procedures to a four digit numeric value representing the SPING address and channel, directly relates to the address/channel numbers on the SPING CT unit. The first two digits refers to the address and the last two digits refer to the channel.
2.3 DNA (Distributed Network Architecture) is the name of the software used by RADSERV.
3.0 Precautions and Limitations 3.1 An Emergency Radiation Work Permit (ERWP) may be required as per EPIP-AD-1 1, "Emergency Radiation Controls" Step 4.1, for sampling within the Zone SV due to high airborne concentrations or other radiological concerns.
4.0 Initial Conditions 4.1 This procedure shall be implemented upon declaration of an Alert, Site Emergency, General Emergency, or when directed by the Shift Manager or Emergency Director.
n:\\nucdoc~procedures\\draft\\eplp\\eretO2b.doc-Chnstine SimmonslChristine Simmons--Jeanne Ferris REFERENCE USE
WISCONSIN PUBLIC SERVICE CORP.: '-'U' No.
EPIP-RET-02B Rev.
S Title Gaseous Effluent Release Path,
ý.*-*Kewaunee Nuclear Power Plant Radioactivity, and Release Rate
.Determination
. er
,a en rd
- ,Date
'AUG 62002 Page 2 of 16 5.0 Procedure Note Table 4 is a flow chart of the steps in this procedure.
5.1 IDENTIFY THE RELEASE PATH by monitoring the following indications:
5.1.1 Auxiliary Building Stack Release
- a. R-13 cpm
- b. R-14 cpm
- c. R-22 cpm
- d. R-35 mR/hr
- e. R-36 R/hr
- f. SPING 01
- 1.
01-05 *Ci/cc
- 2.
01-07 cpm
- 3.
01-09 cpm 5.1.2 Containment Stack Release
- a. R-11 cpm
- b. R-12 cpm
- c. R-21 cpm
- d. R-37 mR/hr
- e. R-38 R/hr
- f. SPING 02
- 1.
02-05 iiCi/cc
- 2.
02-07 cpm
- 3.
02-09 cpm 5.1.3 Steam Line Release
- a. R-15 cpm
- b. R-19 cpm
- e. 1A Steam Line
- 1.
R-31 mR/hr
- 2.
R-32 R/hr
- d. 1B Steam Line
- 1.
R-33niR/hr
- 2.
R-34 R/hr REFERENCE USE
-I-2¶.."
AUG 6 2002 "Paqe 3 of 16 5.2 DETERMINE THE APPROPRIATE SAMPLE POINT for the release path identified.
Note IF it is NO.T possible to obtain in-plant grab samples for any reason, THEN go directly to Step 5.7.
5.2.1 Auxiliary Building Stack Release
- a. R-13 orR-14 (657')- Step 5.4
- b. Auxiliary SPING (642') - Step 5.5 5.2.2 Containment Stack Release
- a. R-11/12 (657')- Step 5.4
- b. R-21 (657') - Step 5.4
- c. Cont. SPING (642') - Step 5.5 5.2.3 Steam Reliefs Release - go to Step 5.6 5.3 PRESAMPLE PREPARATION 5.3.1 Follow the instructions in Procedure EPIP-RET-02D, "Emergency Radiation Entry Controls and Implementation" for entries into the controlled area.
5.3.2 Obtain the following equipment:
- a. Marinelli Beaker
- b. Particulate Filter Papers
- c. Silver Zeolite Cartridges
- d. Gas Syringes (10 cc, 1 cc, 0.1 cc)
REFERENCE USE EPIP-RET-02B I Rev.
S Gaseous Effluent Release Path, Radioactivity, and Release Rate Determination -
I
/
WISCONSIN PUBLIC SERVICE CORP.
No.
EPIP-RET-02B Rev.
S "Title Gaseous Effluent Release Path,
- .,Kewaunee Nuclear Power Plant Radioactivity, and Release Rate "2Y"Enrec"a m
e r
Determination
' ~~~EnirgencyPlai m~p ementing r
~edu.'Dt AUG 6 2002 P
f1 IF radiation monitor R-35 reads greater than I000mR/hr, THEN discontinue sampling both the containment stack at R-11/12 or R-21 and the Auxiliary Building stack at the R-13 or R-14 sample locations on the 657'elevation of the Auxiliary Building.
Note Use Silver Zeolite filters for sampling for iodine radioisotopes.
5.4 OBTAIN AUXILIARY BUILDING OR CONTAINMENT STACK RELEASE DATA BY GRAB SAMPLE 5.4.1 Containment Stack Release
- a. If required, obtain grab sample from R-21 or R-11/12 for the determination of the effluent isotopic mixture.
- b. Record the sample analysis conditions and results on Form EPIPF-RET-02B-01.
- c. Calculate the total flow rate (cc/sec) by adding the operating fan flow rates at the top of Form EPIPF-RET-02B-01.
- d. Calculate the release rate (Ci/sec) for each isotope by multiplying the release concentration (ptCi/cc) by total fan flow rate (cc/sec)'and by 10"6 (Ci/tiCi). Record the results on Form EPIPF-RET-02B-01.
- e. Transmit completed Form EPIPF-RET-02B-01 to the Radiological Protection Director (RPD) or Environmental Protection Director (EPD) for review and/or input to dose projection using EPIP-ENV-03C.
5.4.2 IF grab samples are required from the Auxiliary Building stack for determination of the effluent isotopic mixture, THEN collect the samples at either the R-13 or R-14 sampler located on the 657' elevation of the Auxiliary Building. Use normal sampling procedures HP-05.004, "Radiation/Contamination Survey and Airborne Radioactivity Sampling Schedules," and HP-05.020, "Counting of High Activity Samples," for sampling the Auxiliary Building stack.
REFERENCE USE
5.4.3 Calculate a Radiological Release Rate for an Auxiliary Building Stack Release.
- a. Record the sampling analysis on Form EPIPF-RET-02B-02.
- b. Calculate the total flow (cc/sec) by adding the operating fan flow rates at the top of Form EPIPF-RET-02B-02.
Note Use back ofform for alternate methods of calculating the total fan flow rate for the Auxiliary Building.
- c. Calculate the release rate (Ci/sec) for each isotope by multiplying the release concentration (pCi/cc) by the total fan flow rate (ce/sec) and by 10-6 (Ci/liCi). Record the results on Form EPIPF-RET-02B-02.
5.4.4 Transmit completed Form EPIPF-RET-02B-02 to RPD or EPD for review and/or input to dose projection using EPIP-ENV-03C.
5.5 OBTAIN AUXILIARY BUILDING or CONTAINMENT STACK RELEASE DATA FROM SPING (if required).
Note SPING 01 designates Auxiliary Building Stack (See Form EPIPF-RET-02B-03).
SPING 02 designates Containment Stack (See Form EPIPF-RET-02B-04).
5.5.1 Calculate the Total Stack Flow Rate using Form EPIPF-RET-02B-03 and/or Form EPIPF-RET-02B-04.
5.5.2 Noble Gas Release
- a. View the current value of the Low, Medium, and High Range Gas channels (0105 or 0107 or 0109 for Auxiliary Building).
Gas channels (0205 or 0207 or 0209 for Containment).
- b. Select which channel to use based on the channel status information.
Do NOT use a channel in the "FAIL HI" condition.
- c. The Low Range Gas Channel (0105 or 0205) reads in gtCi/cc. iF this channel is used to determine the release, THEN go to Step 5.5.2.e to calculate the noble gas release rate.
- d. The mid (0107 or 0207) and high (0109 or 0209) range channels read out in cpm.
Convert the cpm reading obtained in "a" above to fCi/cc soup using the conversion tables attached to the SPING-4 consoles (See Table 3).
- e. Multiply the concentration in jtCi/cc by the stack flow rate in cc/sec and by 10-6 Ci/gCi to determine the NOBLE GAS RELEASE RATE (Ci/sec).
REFERENCE USE
WICNSNPUBLIC SRIECP.
N.
EPIP-RET-02B Rev.
S Title Gaseous Effluent Release Path, Kewaunee Nuclear Power Plant Radioactivity, and Release Rate
""*en ln e
rouDetermination Date AUG 62002 Pag e6 o~fl6 5.5.3 Iodine Release Data
- a. Identify the start of the release from the DNA history plot from the RADSERV control terminal.
Calculate the sample volume (X) x (Y) = Z X = Time from start of release to either present time or to knee of plateau (maximum printout value) in minutes.
Y = Flow of the sample pump (4.5E + 4 cc/min)
Z = Total volume in (cc)
- b. Enter this on Form EPIPF-RET-02B-03 or EPIPF-RET-02B-04.
- c. Determine iodine release concentration (gtCi/cc) by dividing the maximum value from the history printout (ItCi) by the sample volume in Step 5.5.3.a.
- d. Enter this on Form EPIPF-RET-02B-03 or EPIPF-RET-02B-04.
- e. Determine the iodine release rate (Ci/sec) by multiplying the iodine release concentration (gCi/cc) by the total flow rate (cc/sec) and by 10-6 Ci/JCi.
5.5.4 Calculate and record the total (gross) release rate (Ci/sec) by adding the Noble Gas Release Rate (5.5.2.e) and the Iodine Release Rate (5.5.3.e) on Form EPIPF-RET-02B-03 for Auxiliary Building and/or Form EPIPF-RET-02B-04 for containment.
5.5.5 Calculate and record the % Noble Gas and/or % Iodine by following equation:
Noble Gas or Iodine Release Rate x 100=%NGorI Total Release Rate 5.5.6 Transmit completed Form EPIPF-RET-02B-02 to the RPD or EPD for review and/or input to dose projection using EPIP-ENV-03C.
REFERENCE USE
WISCONSIN PUBLIC SERVICE CORP.
No.
EPIP-RET-02B Rev.
S
- Nuclear r PlantTitle Gaseous Effluent Release Path, U6w6e1 Radioactivity, and Release Rate
,-Determination
- ner9, InY zentinje Date AUG 6 2002 Page 7 of 16 5.6 OBTAIN STEAM LINE RELIEF VALVE RELEASE DATA 5.6.1 Contact the Technical Support Center for the release path (valves open). Determine the Steam Line Monitor readings. Record reading on Form EPIPF-RET-02B-05 (X value).
5.6.2 Select the proper calibration factor from Table 2, based on T=0 being the time of the reactor trip, to calculate the gross release concentration. Record calibration factor on Form EPIPF-RET-02B-05 (Y value).
5.6.3 Contact the Technical Support Center for steam release flow rate calculation results in cc/sec, per Form EPIPF-TSC-08A-04. Record'steam flow rate on Form EPIPF-RET-02B-05 (Z value).
5.6.4 Refer to EPIP-RET-05, "Site Boundary Dose Rates During Controlled Plant Shutdown" for additional information when the power operated relief valves are used for plant cooldown.
5.6.5 Calculate release rate (Ci/sec) using equation on Form EPIPF-RET-02B-05.
5.6.6 Transmit completed Form EPIPF-RET-02B-05 to RPD or EPD for review and/or input to dose projection using EPIP-ENV-03C.
5.7 OBTAIN FIELD SAMPLES (if required) 5.7.1 IF it is impossible or impractical to obtain in-plant grab samples as previously described, THEN actual grab samples in the field taken in the downwind plume will be required.
5.7.2 Inform the EPD of the need for field grab samples and to coordinate this task.
5.7.3 Field samples collected by the Environmental Monitoring (EM) Teams are ultimately delivered to the plant for counting and isotopic analysis.
5.7.4 Record field sample analysis results on Form EPIPF-RET-02B-06, and attach all sample results.
5.7.5 Transmit completed Form EPIPF-RET-02B-06 and attachments to RPD or EPD for review and/or input to dose projection using EPIP-ENV-03C.
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.
REFERENCE USE
I Rev.
S I
Gaseous Effluent Release Path, Radioactivity, and Release Rate Determination AUG 62002--' I -Page 8'of 16 7.0 References 7.1 COMTRAKS89-028, 89-207,89-208, and PLS84-005 7.2 EPIP-AD-1 1, Emergency Radiation Controls 7.3 EPIP-AD-18, Potassium Iodide Distribution 7.4 EPIP-ENV-03C, Dose Projection Using RASCAL Version 2.2 Software 7.5 EPIP-RET-02D, Emergency Radiation Entry Controls and Implementation 7.6 EPIP-RET-05, Site Boundary Dose Rates During Controlled Plant Cooldown 7.7 HP-05.004, Radiation/Contamination Survey and Airborne Radioactivity Sampling Schedules 7.8 HP-05.018, SPING-4 Filter Change-Post-Accident 7.9 HP-05.020, Counting of High Activity Samples 7.10 HP-05.017, RADSERV Control Terminal REFERENCE USE t
I l
W
i 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/Calculation Sheet (STMRLS Program),
Form EPIP-TSC-08A-04
"* Containment Stack Release (Grab Sample), Form EPIPF-RET-02B-01
"* Auxiliary Building Stack (Grab Sample), Form EPIPF-RET-02B-02
"* Auxiliary Building Stack (Sping Reading), Form EPIPF-RET-02B-03
"* Containment Stack (Sping Reading), Form EPIPF-RET-02B-04
"* Steam Release, Form EPIPF-RET-02B-05
"* Field Reading (Grab Sample), Form EPIPF-RET-02B-06 8.1.2 Non-QA Records None REFERENCE USE
IT Table I EPIP-RET-02B Rev. S Page 10 of 16 Date: AUG 6 2002 REFERENCE USE ISOTOPES TIME SINCE REACTOR TRIP 0.0 0.5 1.0 2.0 8.0 HOUR HOUR HOUR HOURS HOURS
- 1. KR-83M 0.0171 0.02340 0.02470 0.02130 0.00643 0.00010
-0
- 2. KR-85 0.0010 0.00148 0.00167 0.00148 0.00231 0.00280 0.00690 0.1230
- 3. KR-85M 0.0383 0.05460 0.05730 0.05330 0.02670 0.02650
-0
- 4. KR-87 0.0705 0.08580 0.07140 0.04550 0.00218
-0
- 5. KR-88 0.1010 0.13300 0.13200 0.11600 0.03280 0.00077
-0
- 6. KR-89 0.1210 0.00027
-0
- 7. XE-131M 0.0010 0.00156 0.00167 0.00184 0.00231 0.00280 0.00545 0.0350
- 8. XE-133 0.2670 0.41300 0.46700 0.51400 0.64300 0.75200 0.94400 0.8410
- 9. XE-133M 0.0408 0.06320 0.07140 0.07750 0.09350 0.09810 0.04360 0.0065
- 10.
XE-135 0.0605 0.09360 0.11500 0.13600 0.17000 0.11200
-0
- 11.
XE-135M 0.0554 0.04450 0.03610 0.03200 0.02060 0.00471
-0
- 12.
XE-138 0.2270 0.08580 0.02200 0.00126
-0 12 Y fi (DF) I 7.2400 4.26800 3.54200 2.93000 1.26800 0.57730 0.33040 0.2887 1=1 I
I I
I ISOTOPE NORMALIZATION FACTOR fi
GROSS RELEASE RATE DETERMINATION FOR STEAM RELEASES GROSS RELEASE RATE
-6 Ci 10"6xl w- =
Ci/sec WHERE:
X
= Steam Header Monitor Reading Y
=
Calibration Factor (g---cC)
( R ihr)
Z
= FlowIRateN c CALIBRATION FACTOR TABLE p*Ci/cc TIME (SINCE REACTOR TRIP)
R/br 14.5 1 HOUR 16.7 2 HOURS 20.3 4 HOURS 30.4 8 HOURS 67.9 1 DAY 887 1 WEEK 3.08 x 104 1 MONTH 1.93 x 104 Table 2 EPIP-RET-02B Rev. S Date: AUG 6 2002 rage ii OT 10 REFERENCE USE rage 1-t ot -,o
MID RANGE SPING MID-RANGE CPM TO pCI/cc SOUP TIME AFTER RX 0.0 HOUR 0.5 HOUR 1.0 HOUR 2.0 HOURS 8.0 HOURS 24 HOURS 1 WEEK 1 MONTH TRIP MD-RANGE iCi/cc pCi/cc pCi/cc pCi/cc pCi/cc pCi/cc pCi/cc pCi/cc CPM S....
,.^
O 930E*-03 I*
n A
m,,ql I 90E-01*
12 1 0OE+01 2.OE + 01 3 00E+01 4 COE + 01 5.0OE + 01 6 0OE + 01 7 COE + 01 SO0E+01 9 00E+01 1 COE + 02 2.OOE + 02 3 COE + 02 4 OE+ 02 50 CE + 02 6 0OE + 02 7 COE +02 8 COE + 02 9.COE + 02 1 COE +03 2 DOE + 03 3 COE + 03 4 COE +03 5.00E + 03 6 COE + 03 7.COE + 03 8 COE + 03 9.0OE + 03 1 COE + 04 200E+04 3 COE + 04 4 COE +04 5 COE +04 6 COE + 04 7.COE + 04 8.COE + 04 9 COE + 04 1 COE + 05 2 COE + 05 3.OOE + 05 4 COE + 05 5.00E + 05 6 COE + 05 7.COE + 05 8.00E + 05 9 COE + 05 I C0E+ 06 7.40E - 04 1.4IE- 03 2.22E - 03 2.96E - 03 3 70E - 03 4 44E -03 5.18E -03 5 92E - 03 6 66E -03 7.40E - 03 1.48E - 02 2.22E - 02 2 96E - 02 3.70E - 02 4 4"E-02 5 ISE-02 5.92E - 02 6 66E - 02 7.40E - 02 1 48E-01 2.22E -01 2 96E- 01 3 70E - 01 4444E-01 3.1BE-01 5.92E - 01 6 66E- 01 7.40E - 01 1.48E + 00 2.22E + O0 2.96E + 00 3.70E + 00 4 44E+00 5.18E + 00 5.92B + 00 6.66E + 00 7.40E + 00 1.48E + 01 222BE+01 2.96E + 0 I 3.70E + 01 4.44E + 01 5 19E+01 5 92E + 01 6.66E + 01 7.40E + 01 I
1.30E - 03 2.60E - 03 3 9OE -03 S.20E - 03 6 50E -03 7.80E -03 9.10E-03 1.04E -02 1.17E-02 1.30E - 02 2.60E - 02 3-90E - 02 S 20E - 02 6 50E - 02 7.80E -02 9.10E -02 1.04E-01 1.17E-01 1.30E-01 2 60E-01 3 90E-01 5 20E-Ol 6.50E-01 7.80E -01 9.10E - 01 I 04E + 00 1.17E + 00 1.30E + 00 2.60E + 00 3 90E + O0 5.20E + 00 6 SOE + 00 7.80E + 00 9.10E + 00 1.04E + 01 1.17E+01 1.30E + 01 2.60E + 01 390E+01 520E+01 650E+01 780E+01 9.10E + 01 1.04E + 02 1.17E+02 1.30E + 02 1.50E - 03 3 OOE-03 4 50E - 03 6 O0E- 03 7.50E- 03 9.00E - 03 1.5E - 02 1.20E - 02 1.35E -02 I 50E - 02 3 00E- 02 4 50E - 02 6 0OE -02 7.50E - 02 9 OBE-02 1.05E-01 1.20E - 01 1.35E - 01 1.50E -01 3 COE - 01 4 50E -o1 6 O0E- 01 7.50E-01 9.COE -01 1.OSE+ 00 1.20E + 00 1.35E + 0O 1.50E + 00 3 O0E + 00 450E+00 6 OE +00 7.50E + 00 9 OB + 00 1.OSE + 01 1.20E + 01 1.35E + 01
.SOE + 01 3.O0E + 01 4 50E + 01 600E+01 7.50E + 01 9.COE + 01 L.SE + 02 1.20E + 02 1.35E + 02
.S0E + 02 1.SUIE - 03 3 60E-03 5 40E - 03 7.20E - 03 9.OE - 03 1.0BE - 02 1.26E- 02 1.44E - 02 1.62E - 02 1.8E - 02 3.60E - 02 5 40E - 02 7.20E - 02 9.OBE - 02 1.0BE -01 1.26E - 0l 1.44E -O0 1.62E - 01 1.SE - 01 3 60E - 01 5.40E - 01 7.20B -01 9.COE - 01 1.0E + 00 1.26E + 00 1.44E + 00 1.62E + 00 1.80E + 00 3.60E + 00 5.40E + 00 7.20E + 00 9.OE + 00 1.08E+01 1.26E + 01 1.44E + 01 1.62E + 01 1.80E + 01 3.60E + 01 S.40E + 01 720E+01 9.COE + 01 1.0BE + 02 1.26E + 02 1.44E + 02 1.62E + 02 1.SOE + 02 4.2U0E -- 03 8.40E - 03 1.26E -02 1.68E - 02 2.1OE -02 2.25E - 02 294E-02 3.36E-02 3 7KE -02 4.20E - 02 5 40E-02 1.26E - 01 1.68E-01 2.10E-01 2.25E -01 2.94E - 01 336E-01 3.78E - 01 4.20E -01 8 40E -0l 1.26E + 00 1.68E + 00 2.10E + 00 2.25E + 00 2.94E+ 00 3.36E + 00 3.78E + 00 4.20E + 00 K 40E + 00 1.26E+01 1.68E + 01 2.10E+01 2.25E + 01 2.94E + 01 3.36E + 01 3.78E + 01 4.20E + 01 40E +01 1.26E + 02 1 6SE + 02 2 10E +02 2.25E + 02 2.94E + 02 3.36E + 02 3.78E + 02 4.20E + 02 1.86E - 02 2.79E - 02 3.72E - 02 4 65E -02 5.58E - 02 6.51E-02 7.44E - 02 8.37E - 02 9 30E - 02 1 86E-OI 2 79E - 01 3.72E- 01 4 65E -01 5.58E-01 6.51E - 01 7.44E - 01 8.37E - 01 9.30E -01 1.86E + 00 2.79E + 00 3.72E + 00 4 65E + 00 SSSE+00 651E+00 7.44E + 00 8 37E + 00 9.30E + 00 1.86E+01 2.79E+01 3.72E + 01 4.65E + 01 5.58E + 01 651E+01 7.44E + 01 8.37E + 01 930E+01 1.86E + 02 2.79E + 02 3.72E + 02 4.65E + 02 5.58E + 02 6.SIE + 02 7.44E + 02 8.37E + 02 930E+02 I_ 1 1
.1 3.20E-02 4 80E -02 6.40E - 02 8 COE- 02 9 60E - 02 1.12E-01 I 28E - 01 I 44E - 01 1 60E - 01 3 20E - 01 4 80E- 01 6 40E- 01 8 00E - 01 9.60E - 01 1.12E + 00 1.28E + 00 1.44E + 00 1 60E + 00 3.20E + 00 4 SOE + 00 6 40E + 00 8 COE + 00 9 60E+00 1.12E + 0l 1.28E + 01 1.44B + 01 1.60B + 01 3.20E + 01 4.80E + 01 6.40E + 01 8.00E + 01 960E+01 1.12E + 02 1.28E + 02 1.44E + 02 1.60E +02 3 20E+02 4 SOE + 02 6.40E + 02 S.COE + 02 9.60E + 02 1.12E + 03 1.28E + 03 1.44E + 03 1.60E + 03 3.80E - 02 S.70E - 02 7.60E - 02 9 50E- 02 1.14E-01 1.33E - 01 1.52E. 01 1.71E -01 1.90E - 01 3 SOE-C1 5 70E - 01 7.60E - 01 9.50E - 01 1.14E + 00 1 33E + 00 1.52E + 00 1.71E + 00 1.90E + O0 3.80E + O0 5.70B + O0 7.60B + O0 9.SOE + 00 1.14E + 01 1 33E + 01 1.52E + 01 1.71E + 01 1.90E + 01 3 SOE+01 5.70E + 01 760E+01 9 SOE + 01 1.14E + 02 1.33E+02 1.52E + 02 1.71E + 02 1.90E + 02 3 SOE + 02 5.70E + 02 7 60E+02 9 SOE + 02 1.14E + 03 1.33E + 03 1.52E + 03 1.71E+03 1.90E + 03
- a.
-.
D2na 49 nf IA Table 3 EPIP-RET-02B Rev. S Date: AUG6 002 I:UU REFERENCE USE w
On a 49cf46
HIGH RANGE SPING MID RANGE CPM TO pCi/cc SOUP TIME AFTER 0.0 HOUR 0.5 HOUR 1.0 HOUR 2.0 HOURS 8.0 HOURS 24 HOURS 1 WEEK 1 MONTH RX TRIP MED-RANGE P+/-Ccc ijCi/cc pCi/cc gCvcc PCi/cc pCi/c ACl/cc PCi/cc cpm 1.00E + 01 2001+01 3 00E+01 4 00E +01 500E+01 600E+01 7.00E + 01 8 00E+01 9.O0E + 01 1.00E + 02 2 00E + 02 3.00E + 02 4.00E + 02 5 00E+02 600E+02 7.OOE + 02 8 00E + 02 9.00E + 02 100E + 03 2.00E + 03 3 00E + 03 4.00E + 03 5 00E+03 6 00E + 03 7.00E + 03 8 00E+03 9 00E + 03 I.00E + 04 2.00E + 04 3 00E + 04 4 00E +04 5 00E +04 6 00E + 04 7.00E + 04 8 00E +04 9 0024+04 1.00E + 05 2 00E + 05 3 00E + 05 4 00E + 05 5 00E + 05 6 00E + 05 7.00E + 05 8.00E + 05 900E + 05 1.001 + 06 7 0E0-01 1.40E + 00 2.10E + 00 2.80E + 00 3 50E+ 00 4 20E + 00 4 90E + 00 5 60E+00 6 30E + 00 7.OOE + 00 1.40E + 01 2.102+01 2 8OE + 01 3.50E + 01 4.20E + 01 4.90E + 01 5 60E+ 01 6.30E + 01 7.00E + 01 1.40E + 02 2.10E + 02 2.80E + 02 3.50E + 02 4 20E + 02 490E + 02 5 60E + 02 6 30E + 02 7.00E + 02 1.40E + 03 2.10E + 03 2 80E+03 3.50E + 03 4.20E + 03 490E + 03 5 60E + 03 6 30E + 03 7.00E + 03 1.40E + 04 2.10E + 03 2.801 + 04 3 50E+04 4.20E + 04 4.90E + 04 5.60E + 04 6.30E + 04 7.00E + 04 1.1813+00 236E+00 3.54E + 00 4.72E + 00 5 90E+ 00 7.08E + 00 8.26E + 00 944E+00 1.06E + 01 I ISE+01 2 36E + 01 3.54E + 01 4.72E + 01 5.90E + 01 708E+01 8.26E+01 944E+01 1.06E + 02 1.18E + 02 2.36E + 02 3.54E + 02 4 72E + 02 5 90E+02 7.08E + 02 8 26E + 02 9.44E + 02 1.06E + 03 1 18E+03 2.36E + 03 3 54E + 03 4.72E + 03 5.90E + 03 7.08E + 03 8.26E + 03 9 44E + 03 1.06E + 04 1.18E+04 236E+04 3.54E + 04 4.72E + 04 5.90E + 04 7.08E + 04 826E+04 9.44E + 04 1.06E + 05 1.18E+05 1.43E + O00 2.86E + 00 4.29E + 00 5.72E + 00 7.15E + 00 8 58E+00 I O0E + 01 1.14E+01 1.29E +01 1.43E+01 286E+01 4.29E + 01 5.72E + 01 7 15E + 01 858E+01 I 00E + 02 1.14E + 02 1.29E + 02 1.43E + 02 2 86E+02 4 29E+02 5 72E+02 7.15E+02 8.58E + 02 1.00E + 03 1.14E + 03 1.29E + 03 1 43E + 03 2 86E + 03 4 29E + 03 5.72E + 03 7.15E + 03 8.58E + 03 1.00E + 04 1.14E + 04 1.29E + 04 1.43E + 04 2 86E + 04 4.29E + 04 5.72E + 04 7.15E + 04 8.58E + 04 1.00E + 05 1.14E+05 1.29E + 05 1.43E + 05 Table 3 EPIP-RET-02B Rev. S D..E. 42 if 4
Date: AUL b VU
REFERENCE USE 1.72E + 00 3.44E + 00 5.16E + 00 6 88E+00 8 60E + 00 1.03E+ 01 1.20E + 01 1.38E + 01 1.5E + 01 1.72E + 01 344E+01 5.16E + 01 6 88E+01 8 60E+01 1.03E + 02 1.20E + 02 1.38E + 02 1.55E + 02 1.72E+ 02 3 44E + 02 5.16E+02 6 88E + 02 8 60E + 02 I 03E + 03 1.20E + 03 1.38E+03 1.55E + 03 1.72E + 03 3.44E + 03 5.16E + 03 688E+03 8.60E + 03 1 03E + 04 1 20E+ 04 1.38E + 04 1.55E + 04 1.72E+ 04 3.44E + 04 5.16E + 04 688E+04 8 60E+04 1 03E+05 1.20E+05 1.38E + 05 1.55E + 05 1.72E + 05 7.96E + 00 1.19E+01 1.59E+01 1.99E + 01 239E+01 2.79E + 01 3.18E + 01 3.58E + 01 3.98E + 01 7.96E + 01 1.19E+02 1.59E + 02 1.99E + 02 239E+02 2.79E + 02 3.18E+ 02 3.58E + 02 3 98E+02 7.96E + 02 1.19E+03 1.59E + 03 1.99E + 03 2.39E + 03 2.79E + 03 3.18E+03 3.58E+03 3 98E + 03 7.96E + 03 1.19E + 04 1.59E + 04 1.99E + 04 2.39E+ 04 2.79E + 04 3.18E1+04 3.58E + 04 398E+04 7.96E + 04 1.19E + OS 1.59E + 05 1.99E + 05 2.39E + 05 2.79E + 05 3.18E+05 3.58E + 05 3.98E + 05 1.74E + 01 261E+01 3 48E + 01 435E+01 5.22E + 01 6.09E + 01 696E+01 7.83E + 01 8 70E + 01 1.74E + 02 261E+02 3 48E+02 4 35E+02 5 222 + 02 6 09E + 02 6.96E + 02 7.83E + 02 870E+02 1.74E + 03 2 61E+03 3.48E + 03 4.35E + 03 5.22E+03 6.09E + 03 6 96E+ 03 7.83E + 03 8.70E + 03 1.74E + 04 2.61E+04 3 48E + 04 4.35E + 04 5.22E + 04 6 09E + 04 6.96E + 04 7.83E + 04 8 70E + 04 1.74E + 05 261E+05 3 48E + 05 435E+05 5.22E + 05 609E+05 6.96E + 05 7.83 E + 05 8.70E + 05 3 08E + 01 4 62E+01 6 16E+01 7.70E + 01 9.24E + 01 1.08E + 02 1.23E + 02 1.39E + 02 1 54E + 02 3.08E + 02 4.62E + 02 6.16E + 02 7.70E + 02 9.24E + 02 1.08E + 03 1.23E + 03 1.39E + 03 1.54E + 03 3 08E + 03 4.62E + 03 6 16E + 03 7.70E + 03 9.24E + 03 1.08E + 04 1.23E + 04 1.39E + 04 1.54E + 04 3 08E + 04 4 62E + 04 6 16E+ 04 7.70E + 04 9.24E + 04 1.0E + 05 1.23E + 05 1.39E + 05 1.54E + 05 3 08E + 05 4.62E + 05 6 16E + 05 7.70E + 05 9.24E + 05 1 08E + 06 1.23E + 06 1.39E + 06 1.54E + 06 3.50E + 01 525E+01 7 00E + 01 8 75E + 01 1.05E + 02 1.23E + 02 1.40E + 02 1.58E + 02 1.75E + 02 3.50E + 02 5.25E + 02 7.00E + 02 8.75E + 02 1.05E + 03 1.23E + 03 1.40E + 03 1.58E + 03 1.75E+ 03 3 50E + 03 5.25E + 03 7.0OE + 03 8.75E + 03 1.05E + 04 1.23E + 04 1.40E + 04 1.58E + 04 1.75E + 04 3 5013+04 5.25E + 04 7.00E + 04 8.75E + 04 1.05E + 05 1.23E + 05 1.40E + 05 1.58E + 05 1.75E + 05 3.50E + 05 5.25E + 05 7.00E + 05 8.75E + 05 1.05E + 06 1.23E + 06 1.40E + 06 1.58E + 06 1.75E + 06 0
4'2 ^f 49 owu Date: AUG 6* 2002 I
PROCEDURAL FLOW CHART Identify Release Path:
\\
Verify By Monitoring These Indications Get Grab Samples At Determine Effluent Release Rate (cc/sec)
Transmit Obtained Data OR Perform Dose Projection Auxiliary Building Stack EPIP-ENV-03C EPIP-ENV-03C I
Steam Reliefs I
I R-13 cpm R-14 cpm R-22 cpm R-35 mR/hr R-36 R/hr SPING 01-05 jICi/cc 01-07 cpm 01-09 cpm I
Auxiliary SPING (642')
Field Samples R-13 (657')
R-14 (657')
ILA Auxiliary Exh.
1B Auxiliary Exh.
I AuZone SV 1B Zone SV 1A SFP 1B SFP EI FEPD, or EOF/RAF LiaionI Containment Stack I
R-11 cpm R-12 cpm R-21 cpm R-37 mR/hr R-38 R/hr SPING 02-05 IiCi/cc 02-07 cpm 02-09 cpm R-1 1/12 (657')
R-21 (657')
Cont. SPING (642')
Coordinate Field Sampling with EPD RBV IA SBV 1B SBV EPD or EOF/RAF Liaison Table 4 EPIP-RET-02B Rev. S Date: AUG 6 2002 rage i or io REFERENCE USE I
R-15 cpm R-19 cpm 1A Steam Line R-31 mR/hr R-32 R/hr lB Steam Line R-33 mR/hr R-34 R/hr
.Coordinate Field Sanipling with EPD Get From TSC, per Form TSC-08-02 EPD or EOF/RAF Liaison EPIP-ENV-03C I
Page -14 of -1
FOR EASE OF DATA RETRIEVAL, SEE:
Honeywell Graphic Output 12 - For All SPING Data Honeywell Graphic Output 17 and 18 -For Selected Non-SPING Data HONEYWELL MONITOR UNITS DESCRIPTION /LOCATION POINT NO.
NO.
GOOOG R-1 mR/hr Control Room G0002G R-2 mR/hr Containment, 649' G0004G R-4 mR/hr Charging Pump G0005G R-5 mR/hr Spent Fuel Pools, 649' G0006G R-6 mR/hr Sampling Room G0007G R-7 mR/hr Seal Table G0009G R-9 R/hr Letdown Line G0010G R-10 mR/hr New Fuel Pit G0011G R-11 cpm Containment Air Particulate G0012G R-12 cpm Containment Gas G0013G R-13 cpm Auxiliary Building Vent G0014G R-14 pm.
Auxiliary Building Vent Stack G0015G R-15 cpm Air Ejector G0016G R-16 cpm Containment Fan Coil Southwest Return G0017G R-17 cpm Component Cooling Southwest Return G0018G R-18 cpm Liquid Waste Disposal Line G0019G R-19 cpm S/G Blowdown G0020G R-20 cpm Service Water Standpipe G0031G R-31 mR/hr IA Steam Line - LO G0102G R-32 R/hr 1A Steam Line - HI G0105G R-33 mR/hr 1B Steam Line - LO G0104G R-34 R/hr 1B Steam Line - HI GO10IG R-35 mR/hr Auxiliary Building Vent Duct - LO GO10G R-36 R/hr Auxiliary Building Vent Duct - HI GOI 13G R-37 mR/hr Containment Vent Duct - LO GO 12G R-38 R/hr Containment Vent Duct - HI GO 14G R-40 R/hr 1A Containment HI-Range Monitor G0115G R-41 R/hr lB Containment HI-Range Monitor EBERLINE SPING AREA MONITORS G9041G 08-01 mR/hr 586' Sulfuric Acid Tank G9042G 08-02 R/hr 586' Containment Spray Pumps G9043G 03-01 R/hr 586' Waste Disposal Panel G9044G 03-02 mR/hr 586' Hi-Rad Sample Room G9045G 05-01 R/hr 586' RHR Pump Pit Area G9046G 05-02 mR/hr 586' Waste Compactor G9048G 08-03 mR/hr 606' Heating Boiler G9049G 04-01 mR/hr 606' Machine Shop G9050G 04-02 mR/hr 606' RPO/Laundry Room EBERLINE SPING AREA MONITORS (Continued on Page 2 of 2)
Pana l* nf 1I6 Table 5 EPIP-RET-02B Rev. S REFERENCE USE a) b)
Page 155 of 16 Date: AUG 2002UU
HONEYWELL MONITOR UNITS DESCRIPTION ] LOCATION POINT NO.
NO.
EBERLINE SPING AREA MONITORS (Continued)
G9051G 03-03 R/hr 606' Elevator/CC Heat Exchanger G9052G 05-03 mR/hr 606' Loading Dock G9053G 04-03 mR/hr 626' Makeup Demineralizer Area G9055G 04-04 mR/hr 626' I&C Shop - South G9056G 06-01 mR/hr 626' I&C Shop - North G9057G 06-02 R/hr 642' Shield Building Filter Area G9058G 06-03 mR/hr 642' Control Room A/C Room G9059G 06-04 R/hr 657' Containment Vent Filter Area G9060G 06-05 R/hr 657' Zone SV Filter Area G9061G 07-03 mR/hr 606' TSC Building Stairwell G9062G 07-01 mR/hr 586' RAF Count Room G9063G 07-02 mR/hr 586' Technical Support Center G9066G 07-04 cpm 586' Technical Support Center G9067G 03-04 cpm 586' Hi-Rad Sample Room G9069G 03-06 epm 586' Charging Pump Area G9070G 03-08 cpm 606' VCT Area CONTAINMENT STACK SPING G9071G 02-01 giCi Beta Particle G9072G 02-02 cpm Alpha Particulate G9073G 02-03 PCi Iodine G9074G 02-04 cpm Iodine Background G9075G 02-05 ACi/cc Low-Range Noble Gas G9076G 02-06 mR/hr Area Monitor - Gamma G9077G 02-07 epm Mid-Range Noble Gas G9078G 02-08 epm Background - Gas Channels G9079G 02-09 cpm Hi-Range Noble Gas AUXILIARY BUILDING STACK FLOW F700IG N/A cfm Auxiliary Building Stack Flow N/A 06-10 milli-amps Auxiliary Building Stack Flow (Form EPIPF-RET-02B-02)
AUXILIARY BUILDING STACK SPING G9080G 01-01 PCi Beta Particulate G9081G 01-02 epm Alpha Particulate G9082G 01-03 pCi Iodine G9083G 01-04 epm Iodine Background G9084G 01-05 piCi/cc Low-Range Noble Gas G9085G 01-06 mR/hr Area Monitor - Gamma G9086G 01-07 cpm Mid-Range Noble Gas G9087G 01-08 cpm Background - Gas Channels G9088G 01-09 cpm Hi-Range Noble Gas Table 5 EPIP-RET-02B Rev. S Date: AUG 6 20,UU2 REFERENCE USE n
.1a f4st raiux; s
,W e
-.7,,WISCONSINPUBLIC SERVICE CORP.,.-
No.
EPIP-TSC-O1 Rev.
R Title Technical Support Center Organization
ý'.:-Kewaunee Nuclear Power'Plant and Responsibilities
-.Emergen c": Plan Implementin" Proceure Date AUG 6 2002 Page 1 of 17 Reviewed By William Bartelme Approved By W. L. Yarosz Nuclear
[] Yes PORC 13 Yes SRO Approval Of 0] Yes Safety Review Temporary Related El No Required El
[No Changes Required
[]No 1.0 Purpose 1.1 This procedure provides instruction for establishing the emergency response organization for the Technical Support Center (TSC) and describes the responsibilities of the organizations members.
2.0 General Notes 2.1 None 3.0 Precautions and Limitations 3.1 If a declared emergency is initiated due to a low or high security threat, core damage assessment and severe accident management assessment may be performed in the Emergency Operating Facility (per revision 25 of the Emergency Plan, Section 6.2.5).
4.0 Initial Conditions 4.1 This procedure shall be implemented and the TSC staff formed during a Declared Emergency of Alert, Site Emerge ncy, General Emergency, or whenever the need arises to -activate the TSC.
I n:'nucdoc\\procedures\\draft\\epip\\etscOl.doc-Christtne Simmons/Christine Simmons-Jeanne Ferris REFERENCE USE
-4VrJSCONSIN PUBLIC SERVICE CORP.,;,
NO.
EPIP-TSC-O1 Rev.
R Title Technical Support Center Organization
- *ewauneeuclear Power Plant and Responsibilities
-it
,,'-egy hPlah ImIefnenientijgProcedure " Date AUG 6 2002 Page 2 of 17 5.0 Procedure 5.1 Technical Support Center Director (TSCD) shall:
5.1.1 Supervise and coordinate the TSC staff actions as stated in EPIP-AD-04, "KNPP Response to Alert or Higher," Step 5.9.
5.2 Severe Accident Management Team Leader (SAMTL) shall:
5.2.1 WHEN notified that an Emergency has been declared:
- a. Report to the Technical Support Center.
- b. IF a SAMTL has been designated, THEN until released,
- 1. Assist in the activation of the TSC.
- 2. If appropriate, plan a shift relief per EPIP-AD-05, "Emergency Response Organization Shift Relief Guideline."
- 3. Assist the designated SAM Operations person.
- c. IF a SAMTL has NOT been designated,.
notify the Technical Support Center Director (TSCD) of your intent to assume the responsibilities of the SAMTL and continue implementation of this procedure.
5.2.2 Obtain the SAMTL Response Binder from the TSC Material Locker.
Implementation of SAMGs from the TSC prior to full activation of the TSC is NOT recommended without careful analysis. Information flow into the TSC must be adequate to support the SAM Teams ability to develop recommendations and the Emergency Director should be available in the TSC to support the decision making process on SAM Team recommendations.
5.2.3 Ensure the following actions are completed prior to implementation of the SAM guidelines from the TSC:
- a.
The SAM Operations and SAM Core Hydraulics positions are filled.
- b.
The computers in the SAM Room are energized and signed on to the SAM data screens in accordance with Step 5.2.4 of this procedure.
REFERENCE USE
-ý,PJIBLIC SERVICE CORP.4.
No.
EPIP-TSC-01 Rev.
R T 1 Title Technical Support Center Organization
-l!Ki"Nucfear Power and Responsibilities
.mEergencyPlan'I iplemehtingProbeduie Date AUG 6 2002 Page 3 of 17 Note Obtain information needed in the next step from TSC status boards, Honeywell terminal, the Data Coordinator, and/or the Operations Communicator:
- c.
Using Form EPIPF-TSC-01-0l, "Plant Status Summary for SAM Implementation," obtain as complete a picture of plant status as possible.
5.2.4 SAM data screen access method:
- a. Log into the KNPP Network using one of the 2 terminals in the SAM Room.
- b. When the following message appears on the computer screen, "You have not logged on at this computer before. Would you like this computer to retain your individual settings for use when you log on here in the future,"
ALWAYS CLICK "NO".
Note The SAM DA TA Icon (shortcut) opens the Excelfile "N. 1Group Ep(242) lSam Hn wltopclSam.xls. "
- c. Select the SAM DATA Icon from the Program Menu.
5.2.5 Determine if the Control Room staff is implementing SAM guidelines:
- a. IF NO, THEN
- 1. Maintain plant status awareness using Form EPIPF-TSC-01-01, "Plant Status Summary for SAM Implementation," current with plant conditions.
- 2. Periodically check with the SAM Core Hydraulics and SAM Operations person to obtain knowledge of their individual activities.
- 3. Using Form EPIPF-TSC-01-03, "Severe Accident Management - Status,"
to determine potential SAM guideline application.
- 4. Offer assistance to the TSCD with tasks that will allow you to keep abreast of plant conditions.
- b. IF YES, THEN
- 1. Inform the SAM Core Hydraulics and SAM Operations person that they should go to the SAM Room and initiate a review of the Diagnostic Flow Chart (DFC) based on current plant conditions.
REFERENCE USE
KWISCONSIN PUBLIC SERVICE CORP.',:'
No.
EPIP-TSC-01 Rev.
R STitle Technical Support Center Organization ewa unee Nuclear Power Plant and Responsibilities ecyPlt Date AUG 6 2002 Pa e 4 of 17 Note Form EPIPF-TSC-OI-03 may be used as a tool during the analysis process.
- 4. Obtain and complete Form EPIPF-TSC-01-02, "Severe Accident Management Summary and Strategy Recommendation," for each SAM guideline analyzed that results in a needed strategy recommendation to the ED.
- 5. Interact with the TSC Directors to obtain information or alert them to pending anticipatory tasks.
- 6. Provide any or all strategy recommendation(s) to the ED using completed Form EPIPF-TSC-01-02 as soon as possible.
- 7. Ensure that the Severe Accident Management status board is maintained.
- 8. Ensure that the DFC is continuously monitored.
- 9. Ensure the Severe Challenge Status Tree (SCST) is monitored as appropriate for accident conditions.
- 10. Ensure Long Term Concerns are monitored per SAEG-1.
5.2.6 Review staffing requirements, AND
- a. Request additional assistance from the TSCD, O.R
- b. Release any assistance no longer required back to the TSCD.
5.2.7 If appropriate, plan a shift relief for SAM Team Leader per EPIP-AD-05.
5.2.8 IF Final Conditions (Section 6.0) have NO.T been met,.THEN return to Step 5.2.5.
5.2.9 WHEN Final Conditions (Section 6.0) are met:
- a. Verify the SAM Room is 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.
REFERENCE USE
5.3 Severe Accident Management Operations (SAMOP) shall:
5.3.1 WHEN notified that an Emergency has been declared:
- a. Report to the Technical Support Center.
- b.
IF a SAMOP person has been designated, THEN until released,
- 1. Assist in the activation of the TSC.
- 2. If appropriate, plan a shift relief per EPIP-AD-05.
- 3. Assist the designated SAMOP person.
- c. IF a SAMOP person has NOT been designated, THEN notify the Technical Support Center Director of your intent to assume the responsibilities of the SAMOP person and continue implementation of this procedure.
Note Pre-SAM activities should beperformedfrom the TSC Directors table at SAM Team Leader locations.
5.3.2 Initiate EPIP-TSC-10, "Technical Support for IPEOPs," and review against existing plant conditions, Control Room actions, and operating procedure implementation.
5.3.3 Advise the ED on the potential TSC actions and activities needed in support of operational situations and actions.
5.3.4 Inform the ED of any significant events.
5.3.5 Review staffing requirements with the SAM Team Leader, AND
- a. Request additional assistance from the TSCD, OR.
- b. Release any assistance no longer required back to the TSCD.
5.3.6 If appropriate, plan a shift relief for the SAMOP person per EPIP-AD-05.
5.3.7 IF informed by the SAM Team Leader that SAM guidelines need to be implemented:
- a. Secure use of procedure EPIP-TSC-10.
- b. Move to the SAM Room and initiate a review of the Diagnostic Flow Chart.
5.3.8 IF Final Conditions (Section 6.0) have NOT been met or SAM Guidelines have NOT been implemented, THEN return to Step 5.3.2.
REFERENCE USE
,WISCONSIN PUBLIC SERVICE CORP.J';I.`_* No.
EPIP-TSC-01 Rev.
R Title Technical Support Center Organization iJPower Plant.
and Responsibilities nmpi tingProcedire Date AUG 62002 Page 6 of 17 5.3.9 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 there proper place.
- b. Collect all completed forms, notes, and other documentation and give them to the TSCD.
5.4 Severe Accident Management Core Hydraulics (SAMCH) shall:
5.4.1 WHEN notified that an Emergency has been declared:
- a. IF on-site at the time of declaration, THEN report to the TSC and go to step e.
- b. Report to the Emergency Operations Facility.
- c. IF an SRCL person has NOT been designated, THEN notify the Emergency Protection Director and Technical Support Center Director of your intent to provide Core Damage Assessment until relieved by an SRCL.
- d. IF an SRCL has been designated, THEN report to the Technical Support Center.
- e. IF a SAMCH person has been designated, THEN until released,
- 1. Assist in the activation of the TSC.
- 2. If appropriate, plan a shift relief per EPIP-AD-05.
- 3. Assist the designated SAMCH person.
- f. IF a SAMCH person has NOT been designated, THEN notify the Technical Support Center Director of your intent to assume the responsibilities of the SAMCH person and continue implementation of this procedure.
5.4.2 Based on plant conditions, implement the following procedures:
- a. EPIP-TSC-07, "RV Head Venting Time Calculation"
- b. EPIP-TSC-08A, "Calculations for Steam Release from Steam Generators"
- c. EPIP-TSC-09A, "Core Damage Assessment" 5.4.3 Monitor core and reactor coolant parameters for indications of inadequate core cooling.
5.4.4 Assess for actual or potential reactor core damage.
5.4.5 Inform the TSCD of significant changes in core and reactor coolant parameters.
5.4.6 In conjunction with the SAM Team Leader, provide recommendations to the ED on mitigating actions that may be taken.
REFERENCE USE
5.4.7 Review staffing requirements with the SAM Team Leader, AND
- a.
Request additional assistance from the TSCD, OR
- b. Release any assistance no longer required back to the TSCD.
5.4.8 If appropriate, plan a shift relief for the SAMCH person per EPIP-AD-05.
5.4.9 IF informed by the SAM Team Leader that SAM guidelines need to be implemented:
EPIP-TSC-08A, and/or EPIP-TSC-09A as well as the SAGs and SCGs.
- a. Move to the SAM Room and initiate a review of the Diagnostic Flow Chart.
5.4.10 IF Final Conditions (Section 6.0) have NOT been met, THEN return to Step 5.4.2.
5.4.11 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 there proper place.
- b. Collect all completed forms, notes, and other documentation and give them to the TSCD.
5.5 Engineering Coordinator shall:
5.5.1 WHEN notified that an Emergency has been declared:
- a. Report to the Technical Support Center.
- b.
IF an Engineering Coordinator has been designated, THEN until released,
- 1. Assist in the activation of the TSC.
- 2. If appropriate, plan a shift relief per EPIP-AD-05.
- 3. Assist the designated Engineering Coordinator.
- c. IF an Engineering Coordinator has NOT been designated, THEN notify the Technical Support Center Director of your intent to assume the responsibilities of the Engineering Coordinator and continue implementation of this procedure.
5.5.2 Implement procedure EPIP-TSC-04, "Emergency Physical Changes, Major Equipment Repair."
REFERENCE USE
5.5.3 When required, develop and issue work requests.
5.5.4 When required, provide plant groups with revised and updated prints.
5.5.5 When requested, present emergency physical change information to the Plant Operations Review Committee (PORC).
5.5.6 When requested by the TSCD, coordinate engineering support.
5.5.7 When requested, provide engineering and technical assistance to the Support Activity
-Director.
5.5.8 Inform the TSCD of any significant events.
5.5.9 Review staffing requirements, AND
- a. Request additional assistance from the TSCD, OR
- b. Release any assistance no longer required back to the TSCD.
5.5.10 If appropriate, plan a shift relief for Engineering Coordinator per EPIP-AD-05.
5.5.11 IF Final Conditions (Section 6.0) have NOT been met, THEN return to Step 5.5.2.
5.5.12 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 there proper place.
- b. Collect all completed forms, notes, and other documentation and give them to the TSCD.
5.6 Quality Programs Coordinator shall:
5.6.1 WHEN notified that an Emergency has been declared:
- a. Report to the Technical Support Center.
- b. IE a Quality Programs Coordinator has been designated, THEN until
- released,
- 1. Assist in the activation of the TSC.
- 2. If appropriate, plan a shift relief per EPIP-AD-05.
- 3. Assist the designated Quality Programs Coordinator.
- c. IF a Quality Programs Coordinator has NOT been designated, THEN notify the Technical Support Center Director of your intent to assume the responsibilities of the Quality Programs Coordinator and continue implementation of this procedure.
REFERENCE USE
5.6.2 Alert the TSCD of any Quality Programs (QP) concerns which may impact any activity.
5.6.3 When appropriate, provide recommendations to the TSCD.
5.6.4 Maintain QP activities as close to normal as practical.
5.6.5 Coordinate necessary Warehouse activities for procurement and/or relative shipment of material.
5.6.6 Inform the TSCD of any significant events.
5.6.7 Review staffing requirements, AND
- a. Request additional assistance from the TSCD, O.R
- b. Release any assistance no longer required back to the TSCD.
5.6.8 If appropriate, plan a shift relief for Quality Programs Coordinator per EPIP-AD-05.
5.6.9 IF Final Conditions (Section 6.0) have NOT been met, THEN return to Step 5.6.2.
5.6.10 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 there proper place.
- b. Collect all completed forms, notes, and other documentation and give them to the TSCD.
5.7 Data Coordinator shall:
5.7.1 WHEN notified that an Emergency has been declared:
- a. Report to the Technical Support Center.
- b.
IF a Data Coordinator has been designated, THEN until released,
- 1. Assist in the activation of the TSC.
- 2. If appropriate, plan a shift relief per EPIP-AD-05.
- 3. Assist the designated Data Coordinator.
- c. IF a Data Coordinator has NOT been designated, THEN notify the Technical Support Center Director of your intent to assume the responsibilities of the Data Coordinator and continue implementation of this procedure.
5.7.2 Implement procedure EPIP-TSC-03, "Plant Status Procedure."
REFERENCE USE
- *V ISONSIN PUBLIC SERVICE CORP.
<* No.
EPIP-TSC-01 4°- e-'"- jne'e Nc...r'-
a..
""'"'Title Technical Support Center Organization ewaun"-:e-e-Nucea wer Plant and Responsibilities cy an.....
Date AUG 6 2002 Page 10 of 17 I,'Emergenc4y a 1I,pdementing"Procedure,:,,< ]Dt 5.7.3 Obtain information not available on the Honeywell from the ERF Communicator - TSC.
5.7.4 Alert the TSCD or ED of significant changes in plant parameters or system status changes.
5.7.5 Assist TSC staff members obtain plant data and information.
5.7.6 Ensures that data forms or messages are maintained for use in event analyses.
5.7.7 Inform the TSCD of any significant events.
5.7.8 Review staffing requirements, AND
- a. Request additional assistance from the TSCD, OR
- b. Release any assistance no longer required back to the TSCD.
5.7.9 If appropriate, plan a shift relief for Data Coordinator per EPIP-AD-05.
5.7.10 IF Final Conditions (Section 6.0) have NOT been met, THEN return to Step 5.7.2.
5.7.11 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 there proper place.
- b. Collect all completed forms, notes, and other documentation and give them to the TSCD.
5.8 Off-Site Communicator shall:
5.8.1 IF notified that an emergency has been declared during work-hours, THEN
- a.
Report to the TSC and ask for head-of-the-line privileges for accountability.
- b.
IF more than one off-site communicator arrives at the TSC, THEN promptly select one to stay in the TSC, others are to go to the EOF.
5.8.2 Verbally inform the TSCD or ED of your arrival and availability to perform off-site notifications.
5.8.3 If directed by the Emergency Director, accept formal turnover of responsibilities for off-site notifications from the Control Room.
5.8.4 When completed, verbally inform Emergency Director that off-site communication
.. responsibility has been accepted in the TSC.
REFERENCE USE
5.8.5 Direct TSC Support Personnel to enter date and time in the TSC log for turnover of responsibilities for off-site notifications from the Control Room.
5.8.6 Perform off-site notifications as directed by the ED in accordance with EPIP-AD-07.
Note Before contacting the Engineering/Licensing Coordinator, become familiar with off-site PAR and evacuation restrictions.
5.8.7 WHEN the EOF requests turnover of responsibility for off-site communication, THEN
- a.
Update the Off-Site Communicator in the EOF on status of off-site communications.
- b.
Formally release responsibility for off-site communications to the Off-Site Communicator in the EOF and note time.
- c.
Verbally inform the ED that off-site communication has been transferred to the EOF.
- d.
Direct the TSC support person to enter the date and time in the TSC log for turnover of responsibility for off-site notifications to the EOF.
- e.
Contact the Eng/Lic. Coordinator and ask how you can best support the EOF.
5.8.8 IF the EOF requests you to leave the site and PARs allow it, THEN inform the TSCD or ED you are leaving the site to follow EOF instructions.
5.8.9 WHEN Final Conditions are met (Step 6.0):
- a. IF off-site communications are being performed from the TSC, ensure that termination communications have been completed in accordance with EPIP-EOF-08.
- b. Verify that the bell switch on the emergency government verification line is in the ON position.
- c. Verify all work areas are returned to normal status and Emergency Procedures, Forms, etc., are returned to there proper place.
- d. Collect all completed Forms, Notes and Other Documentation and give them to the TSCD.
REFERENCE USE
5.9 NRC Communicator (NRCCM) shall:
5.9.1 WHEN notified that an Emergency has been declared:
- a.
Report to the Control Room.
- b.
IF a NRCCM has been designated, THEN until released,
- 1. Provide assistance to the designated NRCCM as required.
- 2. When appropriate, relocate to the TSC and monitor the communications of the NRCCM in the Control Room.
- 3. When the TSC is capable of supporting NRC communications, transfer NRC communications from the Control Room to the TSC.
- c. IF a NRC Communicator has NOT been designated, _THEN notify the Shift Technical Advisor (STA) or Event Operations Director of your intent to assume the responsibilities of the NRCCM and continue implementation of this procedure.
Note The Emergency Response Data System shall be activated within one hour of declaration of an Alert or higher.
- 1. Ensure the Emergency Response Data System has been activated per Form EPIPF-TSC-02-03.
- 2. Relieve the STA of NRC Communications responsibility.
- 3. Maintain a continuous line of communication with NRC headquarters.
- 4. WHEN the TSC is considered ready for activation, turn over NRC communications or relocate to the Technical Support Center.
5.9.2 Notify the TSCD that you have assumed responsibility for the NRC Communicator position.
REFERENCE USE
5.9.3 The following issues are of interest to the NRC:
- a.
Is there any change to the classification of the event? If so, what is the reason?
- b.
What is the ongoing/imminent damage to the facility, including affected equipment and safety features?
- c.
Have toxic or radiological releases occurred or been projected, including changes in the release rate? If so, what is the projected on-site and off-site releases, and what is the basis of assessment?
- d.
What are the health effect/consequences to on-site/off-site people?'
How may on-site/off-site people are/will be affected and to what extent?
- e.
Is the event under control? When was control established, or what is the planned action to bring the event under control? What is the mitigative action underway or planned?
- f.
What on-site protective measures have been taken or planned?
- g.
What off-site protective actions have been recommended to State/Local officials?
- h.
What is the status of State[Local/other Federal agencies' responses, if known?
- i.
If applicable, what is the status of public information activities,
'such as alarm, broadcast, or press releases (regulatee/State/Local/other Federal agencies)? Has a Joint Information Center been activated?
5.9.4 Continue to maintain a continuous line of communication with NRC headquarters.
5.9.5 Record all incoming and outgoing information on the Telephone Communications Log Sheet located in the TSC reference shelf.
5.9.6 Provide notifications and status updates to the NRC.
5.9.7 Notify the ED or TSCD of NRC concerns.
5.9.8 Inform the TSCD of any significant events.
5.9.9 Review staffing requirements, AND
- a. Request additional assistance from the TSCD, OR "b. Release any assistance no longer required back to the TSCD.
REFERENCE USE
I 5.9.10 If appropriate, plan a shift relief for NRC Communicator per EPIP-AD-05.
5.9.11 IF Final Conditions (Step 6.0) have NOT been met, THEN return to Step 5.9.3.
5.9.12 WHEN Final Conditions are met (Step 6.0):
- a. Verify all work areas are returned to normal status and emergency procedures, forms, etc., are returned to there proper place.
- b. Collect all completed Forms, Notes and Other Documentation and give them to the TSCD.
5.10 Emergency Response Facility (ERF) Communicator-Technical Support Center (TSC) shall:
5.10.1 WHEN notified that an Emergency has been declared:
- a.
Report to the Technical Support Center.
- 1. Assist in the activation of the TSC.
- 2. If appropriate, plan a shift relief per EPIP-AD-05.
- c. IF an ERF Communicator - TSC has NOT been designated, THEN notify the TSCD or ED of your intent to assume the responsibilities of the ERF Communicator - TSC and continue implementation of this procedure.
5.10.2 Enter the 4-Way Communication Link. The "dial in number" and "access number" are listed in the KPB Emergency Telephone Directory, ETD 03, "Emergency Facility Telephone List."
5.10.3 Record all incoming and outgoing ad hoc information on the Telephone Communications Log Sheet.
5.10.4 Obtain information and data from the Control Room that cannot be obtained from the Honeywell terminals.
5.10.5 Maintain Plant System Status, Form EPIPF-TSC-03-02. Use copies of Form EPIPF-TSC-03-01, "Plant System Status" and EPIP-TSC-03-02, "Plant Equipment Status," to keep track of changing plant conditions.
5.10.6 Inform the TSCD of any significant events.
REFERENCE USE
5.10.7 Review staffing requirements, AND
- a. Request additional assistance from the TSCD, O.R.
- b. Release any assistance no longer required back to the TSCD.
5.10.8 If appropriate, plan a shift relief for Operations Communicator per EPIP-AD-05.
5.10.9 IF Final Conditions (Step 6.0) have NOT been met, THEN return to Step 5.10.3.
5.10.10 WHEN Final Conditions are met (Step 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.
5.11 TSC Support Person shall:
5.11.1 WHEN notified that an Emergency has been declared:
- a. Report to the Technical Support Center.
- b. IF a TSC Support person has been designated, THEN until released,
- 1. Assist in the activation of the TSC.
- 2. If appropriate, plan a shift relief per EPIP-AD-05.
- 3. Assist the designated TSC Support person.
- c. IF a Recorder has NOT been designated, THEN notify the Technical Support Center Director of your intent to assume the responsibilities of the TSC Support person and continue implementation of this procedure.
5.11.2 Maintain a "Chronological TSC Log" of significant events, announcements, and TSCD priorities.
5.11.3 When requested, make document copies.
5.11.4 Inform the TSCD of any significant events.
5.11.5 Review staffing requirements, AND
- a. Request additional assistance from the TSCD, OR
- b. Release any assistance no longer required back to the TSCD.
5.11.6" If appropriate, plan a shift relief for the TSC Support person per EPIP-AD-05.
5.11.7 IF final conditions (Step 6.0) have NOT been met, THEN return to Step 5.11.2.
REFERENCE USE
-t C
-WISCONSIN PUBLIC SERVICE CORP.,.,"-7.' No.
EPIP-TSC-01 Rev.
R Nuc.e.r.Power Title Techiiical Support Center Organization Kewanee Nand Responsibilities
-- Elergen n
er 17 Date AUG 6 2002 Page 16 of 17 5.11.8 WHEN Final Conditions are met (Step 6.0):
- a.
Verify all work areas are returned to normal status and emergency procedures, forms, etc., are returned to there proper place.
- b. Collect all completed forms, notes, and other documentation and give them to the TSCD.
- c. Ensure documents and forms generated in the TSC during the event are retained according to the KNPP Records Retention Schedule.
6.0 Final Conditions 6.1 Plant Emergency has been terminated or Recovery actions have begun and the Emergency Response Manager has suspended the use of EPIPs.
7.0 References 7.1 EPIP-AD-04, KNPP Response to Alert or Higher 7.2 EPIP-AD-05, Emergency Response Organization Shift Relief Guideline 7.3 EPIP-AD-07, Initial Emergency Notifications 7.4 Kewaunee Nuclear Power Plant Emergency Plan 7.5 EPIP-EOF-08, Continuing Emergency Notifications 7.6 EPIP-TSC-03, Plant Status Procedure 7.7 EPIP-TSC-04, Emergency Physical Change, Major Equipment Repair 7.8 EPIP-TSC-07, RV Head Venting Time Calculation 7.9 EPIP-TSC-08A, Calculations for Steam Release from Steam Generators 7.10 EPIP-TSC-09A, Core Damage Assessment 7.11 EPIP-TSC-10, Technical Support for IPEOPs REFERENCE USE
S E -CE C R o.Rev.R
""WISCONSINSERVICE No.
EPIP-TSC-01 Z ~Title Technical Support Center Organization and Responsibilities "rn Date AUG 6 2002 Page 17 of 17 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
"* Telephone Communications Log Sheet, Form EPIPF-EOF-04-02
"* Chronological TSC Log
"* Severe Accident Management Summary and Strategy Recommendation, Form EPIPF-TSC-01-02 8.1.2 Non-QA Records
"* Plant Status Summary for SAM Implementation, Form EPIPF-TSC-01-01
"* Severe Accident Management - Status, Form EPIPF-TSC-01-03 REFERENCE USE
AIRBORNE RADIOIODINE DOSE ACCOUNTABILITY AND POTASSIUM IODIDE DISTRIBUTION TABLE 1 - THYROID DOSE RATE CALCULATION Location:
CONCENTRATION DOSE ESTIMATED ISOTRPO (3.()
CONVERSION (2) BREATHING RATE THYROID DOSE RATE SOP 1 CC FACTOR (rads!gCi)
(rads/hr) 1-131 1.480 rads/pCi 1-132 0.054 rads/gCi 1-133 0.400 rads/gCi 1-134 0.025 rads/pCi I-135 0.124 rads/iCi TOTAL DOSE RATE (rads/br)
TABLE 2 - THYROID DOSE FROM AIRBORNE RADIOIODINE AND POTASSIUM IODIDE DISTRIBUTION NAME EXPOSURE ESTIMATED TOTAL POTASSIUM IODIDE DURATION THYROID DOSE THYROID DOSE ISSUED LAST FIRST MI (hours)
RATE (rads/hr) (1)
(rads)
DATE TIME I
t t
T I
i t
I T
I-1-
t
- 4.
+
t t
1
+
1 4-
+
I I
- 4.
+
t 1
4-4
- 4.
4
+
- 4.
4
+
1 1
+
.t t
1
- 4.
+
1 t
1
- 4.
4 4
I I
- 4.
4 4
1 I
() From Table 1 (2) Short Exposure Times or Exposures While Working Assume 1.25E06 cc/hour. Long Exposure Times (Excess of Single Day) - Assume 8.35E05 cc/hour Recommended By:
Approved By:
() If NOT known, conservatively use the DCF for 1-131 (4) Record sample number(s) data is from, or how long airborne radioiodine concentration was derived:
Date / Time Radiological Protection Director Emergency Director Administering Director By:
Date / Time Date /Time
/
.4.14 ru I UI I Form EPIPF-AD-18-01 Rev. B Date: AUi 20U2 Vage~ 1 0I 1 Date: AUG 6 2002 Form EPIPF-AD-18B-01 Rev. B
EOF ACTIVATION CHECKLIST INITIAL WHEN ITEM ACTION COMPLETED S1 Position furniture and communications equipment in accordance with the floor plans attached to the containers listed below:
NOTE.
(1) Equipment boxes listed in order ofpriority.
(2) A dial tone should be heard each time a telephone is connected to the appropriate wall jack.
(3)
Title markers (name tents) should be placed in front of the chair where the individual with that title sits.
- a.
Box - A (SRCL/EPD Area)
- b.
Box - B (ALD Area)
- c.
Box - C (ENV Work Area)
- d.
Box - D (NRC Conference Room)
- e.
Box - E (State/County Conference Room)
- f.
Set out clipboards, name tags, baskets, and "Telephone Communication Log" pads.
- g.
IF full NRC response is anticipated, THEN clear AND set up Conference Room Gl-4 (See: Figure EPIPFG-APPX-06-06).
2 Establish security for the EOF/JPIC work area using Figure EPIPFG-EOF-12-01 attached to this checklist:
- a.
Station a person at Station 5 with the appropriate instructions and materials from procedure EPIP-EOF-12.
- b.
At all Figure locations marked "P" (Post), hang the "This Area Is Secured" signs.
NOTE: IF unauthorized personnel become a problem, _THE the doors marked "L " (Lockable) can be locked. Keys to those doors are hung inside the EOF storage closet door to be issued to EOF personnel as needed.
- c.
Ensure that all EOF/JPIC staff in the facility at the time are logged in on Form EPIPF-EOF-12-01 and issued an EOF/JPIC badge.
3 Communication System Checks:
- a.
EOF Telecopier: Send a test page of text to the Nuclear Telecopier at 5544 to verify the fax transmission capability.
- b.
Dial-Select: (Sta. 10) contact the TSC (ext. 33).
- c.
Env. Monitoring Group Communications Systems: Contact at least one EMT using radio or telephone.
- d.
Honeywell Computer: Call up graphic display screen #53.
I e.
Verify wall clocks in EOF have the same time as the Honeywell Computer.
D~na I nf 9 U
,i w
- v Date: AUU 0* ZUUZ Form EPIPF-EOF-02-01 Rev. T
EOF ACTIVATION CHECKLIST ERM SIGNATURE DATE TWIE Form EPIPF-EOF-02-01 Rev. T Date: AUG 6 2002 INITIAL WHEN ITEM ACTION COMPLETED 4
ERM Activation Actions
- a.
Verify capability for EOF to assume the following responsibilities:
(1) Off-site notification (2) Dose Assessment (3) PAR Determination (ERM)
- b.
Announce EOF activation and scope of responsibilities assumed.
(ERM)
- c.
Notify the ED AND inform him of the scope of EOF activation.
(ERM) n n!
9q c",dra
%0U
EOF DEACTIVATION CHECKLIST INITIAL WHEN ITEM ACTION COMPLETED 1
Termination notifications have been completed in accordance with EPIP-EOF-08 as appropriate.
2 Ensure the designated* emergency telephones are unplugged and returned to the blue storage containers in the EOF.
Remove ONLY the following phones AND store them in the EP storage closet in the storage box listed. All other phones shall remain permanently installed.
- SRCL/EPD Area (Storage Box A) - Phones 15, 16, 17, 18, and 22 (Fig. EPIPFG-APPX-A-06-04) 0 ALD/NRC Area (Storage Box B) - Phones 5 and 6 (Fig. EPIPFG-APPX-A-06-04)
- ENV Work Area (Storage Box C) - Phones 19,20, 21, and 23 (Fig. EPIPFG-APPX-A-06-04)
- NRC Conference Room (Storage Box D) - Phones 26, 27, 28, 29, and 30 (Fig. EPIPFG-APPX-A-06-09) 0 State/County Conference Room (Storage Box E) - Phones 32 and 33 (Fig. EPIPFG-APPX-A-06-08) 3 Ensure all work spaces are returned to their As-Found office configuration.
4 Ensure deactivation of security measures in accordance with EPIP-EOF-12.
5 Ensure EOF Inventory is performed per Form EPMPF-10.01-02, "EOF Inventory Checklist."
6 Notify Emergency Director that deactivation of the EOF is complete.
RM)
ERM SIGNATURE DATE TIME Form EPIPF-EOF-02-02 Rev. M Date: AUG 6 2002 Page 1 of I Page I of 1 Form EPIPF-EOF-02-02 Rev. M Date: AUG 6 2002
CONTAINMENT STACK RELEASE (GRAB SAMPLE)
Sample Date / Time:
OPERATING FANS cc/sec Reactor Building Vent ON / OFF 1.71E + 7 Shield Building Vent "A" ON / OFF 3.11E + 6 Shield Building Vent "B" ON / OFF 3.11E + 6 Total (Cont. Stack) Flow Rate (sum of fans on)
Isotopic Isotopic (Ci" Total 6
C_
Ci
=
Ci Release Rate =
Release X F x 10CC Conc ccc)
Flow Rate sec ISOTOPES tCi/cc Ci/sec ISOTOPES jiCi/cc Ci/sec ISOTOPES gtCi/ce Ci/sec H-3 Ru-106 Cs-134 P-32 Sb-127 Cs-136 S-35 Sb-129 Cs-137 Mn-54 Te-129m Ba-140 Co-58 Te-131m La-140 Co-60 Te-132 Ce-144 Kr-85 1-125 Pm-147 Kr-85m 1-131 Eu-155 Kr-87 1-132 Pu-210 Kr-88 1-133 Np-239 Sr-89 1-134 Pu-238 Sr-90 1-135 Pu-239 Sr-91 Xe-131m Am-241 Y-91 Xe-133 Cm-242 Mo-99 Xe-133m Cm-243 Tc-99m Xe-135 Cm-244 Ru-103 Xe-138 EPD or RPD Form EPIPF-RET-02B-O1 Rev. 0 Date: AUG 6 2002 Page 1 of I
' Form EPIPF-RET-02B-01 Rev. D Date: AUG 6 2002 Page I of 1
AUXILIARY BUILDING STACK (GRAB SAMPLE)
Sample Date / Time:
Total (Aux. Bldg. Stack) Flow Rate OR Auxiliary Building Stack Flow from Sping Channel 06-10 milliamps ( = X )
(X - 4) (7187.5) (2.83E + 4) 60
=
cc/sec OR
- Auxiliary Building Stack Flow from the Plant Process Computer Point F7001G CFM(= X)
(X) (2.83E + 4)
= c/sec 60 Isotopic Release Rate Isotopic (cp.i
=
Release Conc ccee)
Total (cc X Flow Rate (s-ec x 106 (i )
Ci sec ISOTOPES LCilcc Ci/sec ISOTOPES pCi/ce Ci/sec ISOTOPES Ci/cc Ci/sec H-3 Ru-106 Cs-134 P-32 Sb-127 Cs-136 S-35 Sb-129 Cs-137 Mn-54 Te-129m Ba-140 Co-58 Te-131m La-140 Co-60 Te-132 Ce-144 Kr-85 1-125 Pm-147 Kr-85m 1-131 Eu-155 Kr-87 1-132 Pu-210 Kr-88 1-133 Np-239 Sr-89 1-134 Pu-238 Sr-90 1-135 Pu-239 Sr-91 Xe-131m Am-241 Y-91 Xe-133 Cm-242 Mo-99 Xe-133m Cm-243 Tc-99m Xe-135 Cm-244 Ru-103 Xe-138 1
EPD or RPD
- Preferred method for determining Aux. Bldg. Stack Flow Rate.
OPERATING FANS cc/sec Auxiliary Building Vent "A" ON / OFF 1.87E + 7 Auxiliary Building Vent "B" ON / OFF 1.87E + 7 SV "A" ON / OFF 4.67E + 6 SV "B" ON / OFF 4.67E + 6 Spent Fuel Pool "A" ON / OFF 4.67E + 6 Spent Fuel Pool "B" ON / OFF 4.67E + 6 Page 1 of 1 Form EPIPF-RET-02B-02 Rev. D Date: AUG 6 2002
AUXILIARY BUILDING STACK (SPING READING)
Sping Reading Date / Time:
Total (Aux. Bldg. Stack) Flow Rate OR Auxiliary Building Stack Flow from Sping Channel 06-10 _
(X - 4) (7187.5) (2.83E + 4) 60 milliamps ( = X )
cc/sec OR
- Auxiliary Building Stack Flow From the Plant Process Computer Point F7001G CFM (= X)
(X) (2.83E + 4) 60
% I
=
I Release Rate (Iodine)
Total (Gross) Release Rate
%NG NG Release Rate
= __Total_(Gross) x 100 (Noble Gas)
Total (Gross) Release Rate Release Rate =
Release (jtCi Conc cc )
Total cc Flow Rate (Sec EPD or RPD Total (gross) Release Rate
"* Preferred method for determining Aux. Building Stack Flow Rate.
Form EPIPF-RET-02B-03 Rev. D Date: AUG 62002 Page 1 0? '1 OPERATING FANS cc/sec Aux. Building Vent "A" ON / OFF 1.87E + 7 Aux. Building Vent "B" ON / OFF 1.87E + 7 SV "A" ON / OFF 4.67E + 6 SV "B" ON / OFF 4.67E + 6 Spent Fuel Pool "A" ON / OFF 4.67E + 6 Spent Fuel Pool "B" ON / OFF 4.67E + 6 X 10, C6 Ci sec SPING RJEADINGS (Analysts Mix)~
RELEASE RELEASE SPING CHANNEL CONCEN.
RATE
_Ci/cc Ci/cc 01-05 Low-range gas 01-07 Mid-range gas =
- cpm, (use if 01-05 is off scale high) convert cpm reading to pCi/cc using conversion Table 3, EPIP-RET-02B 01-09 High-range gas =
- cpm, (use if 01-07 is off scale high) convert cpm reading to ltCi/cc using conversion Table 3, EPIP-RET-02B 01-03 (See: EPIP-RET-02B, 5.5.3)
Iodine ( ___
- Ci ) - ( __
cc ) =
- , Form EPIPF-RET-02B-03 Rev. D I
Page 1 of I Date: AUG 6 2002
CONTAINMENT STACK (SPING READING)
Sping Reading Date / Time:
Total (Cont. Stack) Flow Rate:
(sum of fans on)
%I !
I ReleaseRate X 100 (Iodine)
Total (Gross) Release Rate
%NG NG Release Rate (Noble Gas)
Total (Gross) Release Rate Release Rate =
Release (pCi )
Conc
( C Total R
cce Flow Rate (secJ Total (gross) Release Rate EPD or RPD:
Form EPIPF-RET-02B-04 Rev. C Date: AUG 6 2002 Page 1 ofl OPERATING FANS cc/sec Reactor Building Vent ON / OFF 1.71E + 7 Shield Building Vent "A" ON / OFF 3.11E+6 Shield Building Vent "B" ON / OFF 3.11E+6 Ci sec SPING READINGS RELEASE RELEASE SPING CHANNEL CONCEN.
RATE
_Ci/cc Ci/cc 02-05 Low-range gas 02-07 Mid-range gas =
- cpm, (use if 02-05 is off scale high) convert cpm reading to jtCi/cc (useif_0205_isoffcalehigh) using conversion Table 3, EPIP-RET-02B 02-09 High-range gas =
- cpm, (use if 02-07 is off scale high) convert cpm reading to gCi/cc (useif_0207_isoffcalehigh) using conversion Table 3, EPIP-RET-02B 02-03 (See: EPIP-RET-02B, 5.5.3)
Iodine (__
iCi) + ( __
cc ) =
X 10-6 Ci )(
pci Page I of 1 Form EPIPF-RET-02B-04 Rev. C Date: AUG 6 2002
STEAM RELEASE Time/Date of Reading:
Steam Line Monitor Reading(s):
HONEYWELL POINT NUMBERS R-31 G0103G R-33 G0105G R-32 G0102G R-34 G0104G IA Steam Line (Use R-32 when R-31 is offscale high)
R-31 (
mR/hr) (10-3) =
OR R-32 Steam Flow Rate (From EPIP-TSC-08B) 1B Steam Line (Use R-34 when R-33 is offscale high)
R/hr (= X)
R/hr (= X) cd/sec (= Z)
R-33 (
mR/hr) (10- 3 ) =
R/hr (= X)
OR R-34 Steam Flow Rate (From EPIP-TSC-08B)
R/hr (=X) cc/sec (= Z)
CALIBRATION FACTOR TABLE 10Ci/ce pICi/ec TIME (SINCE R/hr TIME (SINCE R/hr REACTOR TRIP)
(= Y)
(= Y) 0 14.5 8 HR 67.9 1 HR 16.7 1 DAY 887.0 2 FIR 20.3 1 WEEK 3.08 X 104 4 HR 30.4 1 MONTH 1.93 X 104 jtCi/cc R/hr (=Y)
R/hr X x Y x Z x 10_6 Ci )=
Ci ACi sec Gross Re lease Rate The results of the above equation may be entered as an analysts' mix in KRDose with 98% NG and 2% I, or 100% NG if no Iodine release is present.
EPD or RPD:
Form EPIPF.RET-02B-05 Rev. D Date: AUG 6 2002 Page 1 of I Note Note
- Form EPIPF.RET-02B-05 Rev. D Date
- AUG 6 2002 Page 1 of I
FIELD READING (GRAB SAMPLE)
Sample Date/Time:
Sample Location:
ISOTOPES p.Ci/cc ISOTOPES f
tCi/cc Kr 83m Xe 135m Kr 85 Xe 138 Kr 85m Ar 41 Kr 87 1130 Kr88 1131 Kr 89 1132 Xe 131m I 133 Xe 133 1 134 Xe 133m 1 135 Xe 135 EPD or RPD:
Form EPIPF-RET-02B-06 Rev. B Date: AUG 6 2002 Page 1 of I Page I of I Form EPIPF-RET-02B-06 Rev. B Date: AUG 6 2002