ML020440560: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
 
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter: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-02-009 January 16, 2002 10 CFR 50, App. E U. S. Nuclear Regulatory Commission Attention:
{{#Wiki_filter:Kewaunee Nuclear Power Plant       Point Beach Nuclear Plant N490 Highway 42                 6610 Nuclear Road Kewaunee, WI 54216-9511           Two Rivers, WI 54241 920.755.2321 NM C Committed to Nuclear Excellence 920.388.2560 Kewaunee / Point Beach Nuclear Operated by Nuclear Management Company, LLC NRC-02-009 January 16, 2002                                                                     10 CFR 50, App. E U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Ladies/Gentlemen:
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.
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.
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.
As required, one copy of this letter and attachment is also submitted to the Kewaunee Nuclear Power Plant NRC Senior Resident Inspector.
Sincerely, Thomas J. Webb Site Licensing Director SLC Attachment cc -     US NRC Senior Resident Inspector, w/attach.
Sincerely, Thomas J. Webb Site Licensing Director SLC Attachment cc -US NRC Senior Resident Inspector, w/attach.
US NRC, Region III (2 copies), w/attach.
US NRC, Region III (2 copies), w/attach.
Electric Division, PSCW, w/o attach. QA Vault, w/attach.
Electric Division, PSCW, w/o attach.
A Cos DOCUMENT TRANSMITTAL KEWAUNEE NUCLEAR POWER PLANT FROM: DIANE FENCL -KNPP TRANSMITTAL DATE 01-15-2002"EMERGENCY PLAN IMPLEMENTING PROCEDURES TRANSMITTAL FORM OUTSIDE AGENCY COPIES (1-20) T. Webb -NRC Document Control Desk (1)* Krista Kappelman  
QA Vault, w/attach.
-PBNP -EP (10)* T. Webb -NRC Region m (2 & 3)* Craig Weiss -Wisconsin Power & Light (11)* T. Webb -NRC Resident Inspector (4) (receives Appx. A phone numbers)*
A Cos
T. Webb -State of Wisconsin (5)* Jim Holthaus -Nuclear Management Company (12)* T. Webb -KNPP QA Vault w/NRC Letter (15)* PERSONAL COPIES (21-40) These copies are for the personal use of the listed individuals for reference or emergency response.J. Bennett (33) D. Masarik (32)D. Mielke (35) D. Seebart (24)H. Kocourek (13) B. Bartelme (34)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.
 
STF (86, 87, 88) L. Welch -Fuel Services (65) NO Library -KNPP (59) C. Sternitzky
DOCUMENT TRANSMITTAL KEWAUNEE NUCLEAR POWER PLANT DIANE FENCL - KNPP                                     TRANSMITTAL DATE 01-15-2002 FROM:
-ATF-2 (44) D. Braun -ATF-3 (45) P. Ehlen -I&C Office (42) M. Daron -Security Building (46) P&FS Adm -GB D2-3 (EOF) (81) H.Kocourek
      "EMERGENCY PLAN IMPLEMENTING PROCEDURES TRANSMITTAL FORM OUTSIDE AGENCY COPIES (1-20)
-OSF (52) C. Hutter -ATF-1 (64)LOREB -STF (62, 66, 67, 68, 70, 72, 73, 74) STF Library (43) Resource Center -Training (82, 89, 94, 131) D. Schrank -Maintenance Off. (41) D. Krall -CR/SS Office (51, 56) P&FS Adm -GB-D2 (Nuclear Library) (84) H. Kocourek -TSC (50) W. Galarneau  
T. Webb - NRC Document Control Desk (1)*                   Krista Kappelman - PBNP - EP (10)*
-RAF (53) W. Galarneau  
T. Webb - NRC Region m (2 & 3)*                           Craig Weiss - Wisconsin Power & Light (11)*
-SBF/EMT (54) W. Galarneau  
T. Webb - NRC Resident Inspector (4) (receives     Appx. A phone numbers)*
-RPO (55)WORKING COPIES (101-199)
T. Webb - State of Wisconsin (5)*                         Jim   Holthaus - Nuclear Management Company (12)*
These copies of procedures are kept in the areas designated for use in response to an emergency.
T. Webb - KNPP QA Vault w/NRC Letter (15)*
These are not complete sets, but contain only those procedures that are used to implement activities in the location where they are kept. Please dispose of any sections distributed that are not tabbed in the indicated copy.W. Galarneau  
for reference or PERSONAL COPIES (21-40) These copies are for the personal use of the listed individuals emergency response.
-RAF/RPO (106, 107) W. Galarneau  
D. Mielke (35)                   H. Kocourek (13)               T. Coutu (28)
-SBF/ENV (108, 109) W. Galarneau  
J. Bennett (33)                                                 B. Bartelme (34)
-SBF/EM Team (110, 111, 1llA) W. Galarneau  
D. Masarik (32)                D. Seebart (24) by anyone. They are REFERENCE COPIES - CUSTODIAN (41-100) These copies are for general reference throughout the plant and corporate   offices. The   named individual is the responsible custodian for
-Aurora Medical Center (118, 119) W. Flint -Cold Chem/HR Sample Room (113) N. Deda -SBF/SEC (114)D. Krall -CR/Communicator (1 16)(Partial Distribution)
    -distributed the procedures and shall insure they   are properly maintained.
Simulator/Communicator (117) M. Fencl -Security (121) N. Deda -Security Building (120) S. VanderBloomen (125) J. Stoeger (126)Originals to KNPP QA Vault Please follow the directions when updating your EPIP Manual. WATCH FOR DELETIONS!!!
LOREB - STF (62, 66, 67, 68, 70, 72, 73, 74)
These are controlled procedures and random checks may be made to ensure the manuals are kept up-to-date.
STF (86, 87, 88)                                        STF Library (43)
*THIS IS NOT A CONTROLLED COPY. ITIS A COPYFOR INFORMATION ONLY.1 KEWAUNEE NUCLEAR POWER PLANT REVISION OF EMERGENCY PLAN IMPLEMENTING PROCEDURES January 15, 2C02 Please follow the directions listed below. If you have any questions regarding changes made to the EPIPs, please contact Dave Seebart at ext. 8719. If you are a controlled copy holder (see cover page), return this page to Diane Fencl by February 15, 2002, SIGNED AND DATED to serve as a record of revision.
L. Welch - Fuel Services (65)
Resource Center - Training (82, 89, 94, 131)
NO Library - KNPP (59)
D. Schrank - Maintenance Off. (41)
C. Sternitzky - ATF-2 (44)                              D. Krall - CR/SS Office (51, 56)
-*.. D. Braun - ATF-3 (45)
P&FS Adm - GB-D2 (Nuclear Library) (84)
P. Ehlen - I&C Office (42)
H. Kocourek - TSC (50)
M. Daron - Security Building (46)
W. Galarneau - RAF (53)
P&FS Adm - GB D2-3 (EOF) (81)
W. Galarneau - SBF/EMT (54)
H.Kocourek - OSF (52)                                  W. Galarneau - RPO (55)
C. Hutter - ATF-1 (64)
WORKING COPIES (101-199) These copies of procedures are kept in the areas designated for use in response to an emergency. These are not complete sets, but contain only those procedures that are used to that are implement activities in the location where they are kept. Please dispose of any sections distributed not tabbed in the indicated copy.
D. Krall - CR/Communicator (1 16)(Partial Distribution)
W. Galarneau - RAF/RPO (106, 107)
Simulator/Communicator (117)
W. Galarneau - SBF/ENV (108, 109)
M. Fencl - Security (121)
W. Galarneau - SBF/EM Team (110, 111, 1llA)
N. Deda - Security Building (120)
W. Galarneau - Aurora Medical Center (118, 119)
S. VanderBloomen (125)
W. Flint - Cold Chem/HR Sample Room (113)               J. Stoeger (126)
N. Deda - SBF/SEC (114)
Originals to KNPP QA Vault are Please follow the directions when updating your EPIP Manual. WATCH FOR DELETIONS!!! These controlled procedures and random checks may be made         to ensure the manuals   are kept up-to-date.
          *THIS IS NOT A CONTROLLED COPY. ITIS A COPYFOR INFORMATION ONLY.
1
 
KEWAUNEE NUCLEAR POWER PLANT REVISION OF EMERGENCY PLAN IMPLEMENTING PROCEDURES January 15, 2C02 to the EPIPs, Please follow the directions listed below. If you have any questions regarding changes made (see cover page), return this please contact Dave Seebart at ext. 8719. If you are a controlled copy holder page to Diane Fencl by February 15, 2002, SIGNED AND DATED           to serve as a record of revision.
EPIP Index, dated 01-15-2002.
EPIP Index, dated 01-15-2002.
REMOVE INSERT PROCEDURE RE
REMOVE                                                   INSERT REV.                    PROCEDURE                         REV.
PROCEDURE EP-RET-3C                        0                    EPIP-RET-03C                          P M                    EPIP-RET-03D                          N EP-RET-3D g
I I
Returnii a~signed and dated copy, of this transmittal letter, -within10 days of receipt, to the sender.
Ifyou have any questions or comments, please call Dave Seebart.                                                  I 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 end Enclosure 2
 
EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX                    DATE: 01-15-2002 PROC. N.                          TITLE                  REV.          DATE EP-AiD EPIP-AD-01    Personnel Response to the Plant-Emergency      J      01-08-2002 Siren EPIP-AD-02    Emergency Class Determination                AC        11-15-2001 EPIP-AD-03    KNPP Response to an Unusual Event            AD        12-14-2001 EPIP-AD-04    KNPP Response to Alert or Higher              AP      12-14-2001 EP-AD-5      Site Emergency                              Deleted      04-27-87 EPIP-AD-05    Emergency Response Organization Shift Relief  C        06-05-2001 Guideline EP-AD-6      General Emergency                            Deleted      04-24-87 EPIP-AD-07    Initial Emergency Notifications              AN        11-15-2001.
EP-AD-8      Notification of Alert or Higher              Deleted      02-26-96 EP-AD-9      Notification of Site Emergency              Deleted      04-27-87 EP-AD- 10    Notification of General Emergency            Deleted      04-27-87 EPIP-AD- 1I  Emergency Radiation Controls                    Q      09-27-2001 EP-AD-12    Personnel Assembly and Accountability        Deleted      03-26-94 EP-AD-13    Personnel Evacuation                        Deleted      04-25-94 EP-AD-13A    Limited Area Evacuation                      Deleted      03-01-83 EP-AD- 13B    Emergency Assembly/Evacuation                Deleted      03-01-83 EP-AD-13C      Site Evacuation                            Deleted      03-01-83 EP-AD-14      Search and Rescue                          Deleted      05-25-94 EPIP-AD-15    Recovery Planning and Termination              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                  0        06-05-2001 EPIP-AD-1 9    Protective Action Guidelines                  Q        11-27-2001 PAGE I OF 11
 
EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX                      DATE: 01-15-2002 PROC. NO.                          TITLE EPIP-AD-20    KNPP Response to a Security Threat EP-ENV EPIP-ENV-01    Environmental Monitoring Group Organization    V        10-02-2001 and Responsibilities EPIP-ENV-02    Environmental Monitoring Team Activation        X        10-02-2001 EP-ENV-3A    Environmental Protection Director Actions and Deleted      09-26-84 Directives EP-ENV-3B    EM Team Actions                              Deleted      09-26-84 EPIP-ENV-03C  Dose Projection Using RASCAL Version 2.2        V        10-09-2001 Software EP-ENV-3D    Revision and Control of ISODOSE II            Deleted      02-14-95 EP-ENV-3E    Manual Determination of X/Q                  Deleted      04-24-87 EP-ENV-3F    Manual Determination of X/Q (Green Bay        Deleted      05-30-86 Meteorological Data)
EP-ENV-3G    Manual Dose Projection Calculation            Deleted      06-02-89 EP-ENV-3H    Protective Action Recommendations            Deleted      04-13-90 EPIP-ENV-04A  Portable Survey Instrument Use                  S      06-15-2000 EPIP-ENV-04B  Air Sampling and Analysis                      W        10-09-2001 EP-ENV-4C    Environmental Monitoring Teams                Deleted      04-13-90 EPIP-ENV-04C  Ground Deposition Sampling and Analysis        W        10-09-2001 EPIP-ENV-04D  Plume Tracking for Environmental Monitoring      N        10-02-2001 Teams EP-ENV-5A    LCS-1 Operation                              Deleted      04-14-86 EP-ENV-5B    MS-3 Operation                                Deleted      04-14-86 EP-ENV-5C    SAM II Operation                              Deleted      04-14-86 EP-ENV-5D    PAC-4G (Alpha Counter) Operation              Deleted      04-14-86 EP-ENV-5E    Reuter-Stokes Operation                      Deleted      08-27-85 PAGE 2 OF 11
 
EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX                        DATE: 01-15-2002 PROC. NO.                            TITLE                        REV.          DATE EP-ENV-6    I Data Analysis, Dose Projections and Protective    Deleted      12-21-81 Action Recommendations EP-ENV-6      Alternate Sample Analysis and Relocation of        Deleted      04-14-86 EM Team EP-ENV-6A      Relocation of Site Access Facility (Habitability)  Deleted      03-23-84 EP-ENV-6B      SAF Environmental Sample Analysis Relocation      Deleted      03-23-84 EP-ENV-7      Site Access Facility Communications                Deleted      09-26-84 EP-ENV-8      Total Population Dose Estimate Calculations        Deleted      04-14-86 EP-EOF EP-EOF-1      Corporate Emergency Response Organization          Deleted      03-11-94 EPIP-EOF-02    Emergency Operations Facility (EOF) Activation        Z        11-29-2001 _
EPIP-EOF-03    EOF Staff Action for Unusual Event                  AB        12-14-2001 EPIP-EOF-04    EOF Staff Action for Alert or Higher                AH        12-14-2001 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                    T        11-27-2001 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- 1I    Internal Communication and Documentation            U        11-15-2001 Flow EPIP-EOF-12      Media Center/Emergency Operation                    P        07-19-2001 Facility/Joint Public Information Center Security PAGE 3 OF 11
 
EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX                  DATE: 01-15-2002 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        T      11-29-2001 EPIP-OSF-03  Work Requests During an Emergency              0      09-27-2001 EP-OSF-4    Operational Support Facility Communications Deleted    04-24-87-_
EPIP-OSF-04  Search and Rescue                              D      09-12-2000 EP-RET EP-RET- 1  Radiation Emergency Team Organization      Deleted    04-16-96 EPIP-RET-02  In-Plant Radiation Emergency Team            U        11-27-2001 EPIP-RET-02A  Radiation Protection Office/Radiological'      T      11-29-2001 Analysis Facility (RPO/RAF) Activation EP-RET-2B    Gaseous Effluent Sample and Analysis          Q        03-03-98 EP-RET-2C    Containment Air Sampling and Analysis      Deleted    03-01-83 EPIP-RET-02D  Emergency Radiation Entry Controls and        M        06-12-2001 Implementation EP-RET-2E  Handling of Injured Personnel                Deleted    04-16-96 EP-RET-2F  Personnel Decontamination                    Deleted    04-13-90 EPIP-RET-03  Chemistry Emergency Team                      0        02-01-2000 EPIP-RET-03A  Liquid Effluent Release Paths                  L        11-29-2001 EP-RET-3B  Post-Accident Reactor Coolant Alternate      Deleted    01-25-88 Sampling Procedure PAGE 4 OF 11
 
EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX                      DATE: 01-15-2002 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                                    R      10-02-2001 EP-RET-4A    EOF Radiological Monitoring                    Deleted      03-10-83 EPIP-RET-04A  SBF Operation/Relocation                      Deleted    10-02-2001 EP-RET-4B    Radiological Controls at Site Access Facility  Deleted      07-12-94 EP-RET-4C    Site Radiological Monitoring                  Deleted      07-12-94 EP-RET-4D    SAM-II Operation                              Deleted      07-12-94 EP-RET-5    Plume Projection                              Deleted      09-26-84 EPIP-RET-05    Site Boundary Dose Rates During Controlled        H        10-09-2001 Plant Cooldown EP-RET-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        P      10-30-2001 Center EPIP-RET-09  Post-Accident Population Dose                      K      08-29-2000 EP-SEC EP-SEC-1    Security Organization                          Deleted    04-24-87 EPIP-SEC-02  Security Force Response to Emergencies            W        08-28-2001 EP-SEC-2A    Manual Activation of Emergency Sirens          Deleted    04-16-82 EPIP-SEC-03  Personnel Assembly and Accountability            AC      12-14-2001 EPIP-SEC-04  Security Force Actions for Dosimetry Issue        P      10-02-2001 PAGE 5 OF 11
 
EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX                          DATE: 01-15-2002 PROC. NO.                            TITLE                          REV.          DATE EP-SEC-5      Security Force Response to the EOF                Deleted      07-28-88 EPIP-SEC-05      Personnel Evacuation                                    F      07-05-2001 EP-TSC EPIP-TSC-01      Technical Support Center Organization and              P        10-02-2001 Responsibilities EPIP-TSC-02      Technical Support Center Activation                    S      11-29-2001 EPIP-TSC-03      Plant Status Procedure                                V        10-09-2001 EPIP-TSC-04      Emergency Physical Changes, Major Equipment          M        10-02-2001 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                        I      10-19-2001 EPIP-TSC-08A      Calculations for Steam Release from Steam            N        12-14-2001 Generators EPIP-TSC-08B*    STMRLS Computer Program                                F        10-02-2001 EP-TSC-8C*      See EP-TSC-8B                                      Deleted      04-16-92
* EP-TSC-8B was totally deleted; therefore, EP-TSC-8C was changed to EP-TSC-8B EP-TSC-9      Core Damage Assessment Using Released              Deleted      09-30-86 Radionuclides EP-TSC-9A*      Core Damage Assessment                                I        02-23-99 EPIP-TSC-09B*      CORE Computer Program                                J        10-02-2001 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                          I        03-20-2001 PAGE 6 OF 11
 
EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX                            DATE: 01-15-2002 FIGURES EPIP              FIG #  1  Figure EPIPFG        DESCRIPTION            REV.      DATE EP-SEC-5                                              Technical Support EPIP-APPX-A-06        EP-FIG-003  APPX-A-06-03      Center - KNP Floor Plan      B    06-12-2001 Site Boundary Facility EPIP-APPX-A-06        EP-FIG-oos  APPX-A-06-02      KNP Floor Plan              A      10-31-2000 Radiological Analysis Facility - KNP Floor EPIP-APPX-A-06        EP-FIG-008  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 EPIP-APPX-A-06                                        Area - WPSC D2-1 EP-FIG-012  APPX-A-06-08        Floor Plan                  C    10-31-2000 EPIP-APPX-A-06                                        NRC Work Area EP-FIG-013  APPX-A-06-09        WPSC D2-4 Floor Plan        A    10-31-2000 Population Distribution EPIP-AD-19                                            by Geographical Sub EP-FIG-014  AD-19-01          Areas (with sectors)          A    10-31-2000 EPIP-APPX-A-06                                        EOF - WPSC D2-3 EP-FIG-022  APPX-A-06-04      Floor Plan                    C    10-30-2001 EPIP-EOF-12                                          Map - Location of JPIC, EP-FIG-024  EOF-12-02          MBC, GOB, DOB, etc.          B    09-27-2001 EP-SEC-5              EP-FIG-026  SEC-05-01          Site Map                    B    09-27-2001 Floor Plan - Media APPX-A-6              EP-FIG-034                      Briefing Center          Deleted    08-04-98 EPIP-EOF- 12                                          General Office Building  - WPSC (1st EPIP-APPX-A-06        EP-FIG-035  APPX-A-06-06      Floor) Floor Plan            C    10-24-2000 APPX-A-6                                              Floor Plan - Corporate EP-F-o37          - - -      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 EPIP-APPX-A-06                                        JPIC - Federal Work EP-FIG-043  APPX-A-06-10      Area - WPSC D2-9            B      12-21-2001 JPIC - State and County EPIP-APPX-A-06                                        Work Area EP-FIG-044  APPX-A-06-07      WPSC D2-8                    C    12-21-2001 EPIP-APPX-A-06                                      JPIC - Utility Work EP-FIG-045  APPX-A-06-05      Area - WPSC D2-7              C    12-21-2001 RET-08                                              Aurora Medical Center EP-FIG-046  RET-08-01        Location                      A    06-15-2000 EPIP-APPX-A-02          ---      APPX-A-02-01      ERO Call Tree              Deleted 12-04-2001 PAGE 7 OF 11
 
EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX            DATE: 01-15-2002 NUMBER                            TITLE APPENDIX A APPX-A-I    Communication System Description EPIP-APPX-A-02 Response Personnel Call List EPIP-APPX-A-03 Off-Site Telephone Numbers EPIP-APPX-A-06 KNPP Emergency Response Facility Telephone Numbers PAGE 8 OF 11


==V. PROCEDURE==
EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX                    DATE: 01-15-2002 FORM EPIPF                            TITLE                      REV.       DATE APPENDIX B EP-AD AD-07-01      Event Notice (Wisconsin Nuclear Accident Reporting    R      12-14-2001 Form)
AD-07-02      State Call-Back - Question Guideline                  C    11-15-2001 AD 11.1      Emergency Radiation Work Permit                        F      04-16-96 EP-ENV ENV-01-01    Environmental Dispatch Area Activation Checklist      D    10-31-2000 ENV-01-02    EMT Status                                            B    10-31-2000 ENV-01-03    Meteorological and Plant Status Data                  C    12-14-2001 ENV-01-04    EMT Orders/Field Data                                  B    10-31-2000 ENV-02-01    EMT Activation Checklist                              M    06-15-2000 EP-EOF EOF-02-01    EOF Activation Checklist                                S    10-30-2001 EOF-02-02    EOF Deactivation Checklist                            L    10-30-2001 EOF-04-01    SRCL Initial Action Checklist                          C    12-14-2001 EOF-04-02    Telephone Communications Log Sheet                    A    12-14-2001 EOF-08-03    Fax for Emergency Declaration or Status Updates        G    11-27-2001 EOF-08-05    Plant Emergency Status Report                          A    11-27-2001 EOF-08-06    Radiological Status Report                              D    11-27-2001 EOF- 11-02  Operating Status                                        F    11-15-2001 EOF-1 1-03  Environmental Status Board                              F    11-15-2001 EOF-12-01    I.D. Badge Registration Form                            G    10-24-2000 EP-OSF OSF 2.2      Maintenance Work in Progress                        Deleted  07-08-98 OSF-03-01    Operational Support Facility Team Briefing            C    12-04-2001 PAGE 9 OF 11


REV. EP-RET-3C 0 EPIP-RET-03C P EP-RET-3D M EPIP-RET-03D N Returnii a~signed and dated copy, of this transmittal letter, -within 10 days of receipt, to the sender. Ifyou have any questions or comments, please call Dave Seebart.Diane end Enclosure 2 I I CERTIFY Copy No.__ (WPSC No.) of the Kewaunee Nuclear Power Plant's EPIPs has been updated.
EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX                      DATE: 01-15-2002 FORM EPIPF                          TITLE                        REV. DATE EP-RET RET-02A-02  Emergency Sample Worksheet                              E    06-05-2001 RET 2B. 1  Containment Stack Release (Grab Sample)                C      04-16-96 RET 2B.2    Auxiliary Building Stack (Grab Sample)                  C      04-16-96 RET 2B.3    Auxiliary Building Stack (Sping Reading)                 C    04-16-96 RET 2B.4    Containment Stack (Sping Reading)                      B      04-16-96 RET 2B.5    Steam Release                                            C    04-16-96 RET 2B.6    Field Reading (Grab Sample)                            A      04-16-96 RET-04-01  SAM-2 Counting Equipment Worksheet                      E    06-12-2001 RET 8.3    Hospital Survey 1                                    Deleted 06-05-20Q1 RET 8.4    Hospital Survey 2                                    Deleted  07-25-97 RET 8.5     Hospital Survey 3                                    Deleted 07-25-97 RET-08-06   Hospital Survey 4                                        F    06-15-2000 RET 9      Environmental TLD Record Sheet                          C    02-14-95 EP-SEC SEC-03.01  Emergency Accountability Log                            A    03-28-2000 SEC 4.1    Emergency Dosimeter Log                                  F    02-16-2000 EP-TSC TSC 1.1    Plant Status Summary for SAM Implementation              A    04-01-99 TSC 1.2    Severe Accident Management Summary and Strategy          A    04-01-99 Recommendation TSC 1.3    Severe Accident Management - Status                      A    04-01-99 TSC-02-01  TSC and OSF Activation Checklist                        0    09-27-2001 TSC 2.2    TSC Ventilation Checklist                                H    04-01-99 TSC-02-03   Emergency Response Data System (ERDS) Link Initiation    G    05-04-2001 Checklist PAGE 10 OF 11
SIGNATURE DATE Please return this sheet to DIANE FENCL.g I I EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-15-2002 PROC. N. TITLE REV. DATE EP-AiD EPIP-AD-01 Personnel Response to the Plant-Emergency J 01-08-2002 Siren EPIP-AD-02 Emergency Class Determination AC 11-15-2001 EPIP-AD-03 KNPP Response to an Unusual Event AD 12-14-2001 EPIP-AD-04 KNPP Response to Alert or Higher AP 12-14-2001 EP-AD-5 Site Emergency Deleted 04-27-87 EPIP-AD-05 Emergency Response Organization Shift Relief C 06-05-2001 Guideline EP-AD-6 General Emergency Deleted 04-24-87 EPIP-AD-07 Initial Emergency Notifications AN 11-15-2001.
 
EP-AD-8 Notification of Alert or Higher Deleted 02-26-96 EP-AD-9 Notification of Site Emergency Deleted 04-27-87 EP-AD- 10 Notification of General Emergency Deleted 04-27-87 EPIP-AD- 1 I Emergency Radiation Controls Q 09-27-2001 EP-AD-12 Personnel Assembly and Accountability Deleted 03-26-94 EP-AD-13 Personnel Evacuation Deleted 04-25-94 EP-AD-13A Limited Area Evacuation Deleted 03-01-83 EP-AD- 13B Emergency Assembly/Evacuation Deleted 03-01-83 EP-AD-13C Site Evacuation Deleted 03-01-83 EP-AD-14 Search and Rescue Deleted 05-25-94 EPIP-AD-15 Recovery Planning and Termination 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 0 06-05-2001 EPIP-AD-1 9 Protective Action Guidelines Q 11-27-2001 PAGE I OF 11 EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX PROC. NO. TITLE EPIP-AD-20 KNPP Response to a Security Threat EP-ENV DATE: 01-15-2002 EPIP-ENV-01 Environmental Monitoring Group Organization V 10-02-2001 and Responsibilities EPIP-ENV-02 Environmental Monitoring Team Activation X 10-02-2001 EP-ENV-3A Environmental Protection Director Actions and Deleted 09-26-84 Directives EP-ENV-3B EM Team Actions Deleted 09-26-84 EPIP-ENV-03C Dose Projection Using RASCAL Version 2.2 V 10-09-2001 Software EP-ENV-3D Revision and Control of ISODOSE II Deleted 02-14-95 EP-ENV-3E Manual Determination of X/Q Deleted 04-24-87 EP-ENV-3F Manual Determination of X/Q (Green Bay Deleted 05-30-86 Meteorological Data) EP-ENV-3G Manual Dose Projection Calculation Deleted 06-02-89 EP-ENV-3H Protective Action Recommendations Deleted 04-13-90 EPIP-ENV-04A Portable Survey Instrument Use S 06-15-2000 EPIP-ENV-04B Air Sampling and Analysis W 10-09-2001 EP-ENV-4C Environmental Monitoring Teams Deleted 04-13-90 EPIP-ENV-04C Ground Deposition Sampling and Analysis W 10-09-2001 EPIP-ENV-04D Plume Tracking for Environmental Monitoring N 10-02-2001 Teams EP-ENV-5A LCS-1 Operation Deleted 04-14-86 EP-ENV-5B MS-3 Operation Deleted 04-14-86 EP-ENV-5C SAM II Operation Deleted 04-14-86 EP-ENV-5D PAC-4G (Alpha Counter) Operation Deleted 04-14-86 EP-ENV-5E Reuter-Stokes Operation Deleted 08-27-85 PAGE 2 OF 11 EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-15-2002 PROC. NO. TITLE REV. DATE EP-ENV-6 I 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)
EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX                      DATE: 01-15-2002 FORM EPIPF                          TITLE                      REV. DATE TSC-02-04  TSC Chart Recorder Operation Checklist                D    01-30-2001 TSC-02-05  TSC and OSF De-activation Checklist                  A    10-09-2001 TSC-03-01  Plant System Status                                  L    06-12-2001 TSC-03-02  Plant Equipment Status                                L    06-12-2001 TSC-03-03  Environmental Status Board                            J  06-12-2001 TSC-03-04  Radiation Monitors                                    I    01-08-2002 TSC-04-01   Emergency Physical Change Request                    F    08-29-2000 TSC-04-02   Emergency Physical Change Safety Review              F    08-29-2000 TSC-04-03  Emergency Physical Change Index                      F    08-29-2000 TSC-07-01  Head Venting Calculation                              F    10-31-2000 TSC-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)
Deleted 03-23-84 EP-ENV-6B SAF Environmental Sample Analysis Relocation Deleted 03-23-84 EP-ENV-7 Site Access Facility Communications Deleted 09-26-84 EP-ENV-8 Total Population Dose Estimate Calculations Deleted 04-14-86 EP-EOF EP-EOF-1 Corporate Emergency Response Organization Deleted 03-11-94 EPIP-EOF-02 Emergency Operations Facility (EOF) Activation Z 11-29-2001
TSC 9A. 1  Core Damage Based on Reactor Vessel Level & Fuel Rod  C      02-14-95 Temp.
_ EPIP-EOF-03 EOF Staff Action for Unusual Event AB 12-14-2001 EPIP-EOF-04 EOF Staff Action for Alert or Higher AH 12-14-2001 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 T 11-27-2001 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-1I Internal Communication and Documentation U 11-15-2001 Flow EPIP-EOF-12 Media Center/Emergency Operation P 07-19-2001 Facility/Joint Public Information Center Security PAGE 3 OF 11 EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-15-2002 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 T 11-29-2001 EPIP-OSF-03 Work Requests During an Emergency 0 09-27-2001 EP-OSF-4 Operational Support Facility Communications Deleted 04-24-87-_
TSC 9A.2    Core Damage Based on Radiation Monitors              C      02-14-95 TSC 9A.3    Cs-134 and Cs-137 PCF Determination                  D      04-16-96 TSC 9A.4    Core Damage Based on Activity Ratios                  C      02-14-95 TSC 9A.5    Core Damage Assessment (Monitoring Data)              D      04-16-96 TSC 9A.6    Core Damage Summary                                  C      02-14-95 PAGE 11 OF 11
EPIP-OSF-04 Search and Rescue D 09-12-2000 EP-RET EP-RET- 1 Radiation Emergency Team Organization Deleted 04-16-96 EPIP-RET-02 In-Plant Radiation Emergency Team U 11-27-2001 EPIP-RET-02A Radiation Protection Office/Radiological' T 11-29-2001 Analysis Facility (RPO/RAF)
 
Activation EP-RET-2B Gaseous Effluent Sample and Analysis Q 03-03-98 EP-RET-2C Containment Air Sampling and Analysis Deleted 03-01-83 EPIP-RET-02D Emergency Radiation Entry Controls and M 06-12-2001 Implementation EP-RET-2E Handling of Injured Personnel Deleted 04-16-96 EP-RET-2F Personnel Decontamination Deleted 04-13-90 EPIP-RET-03 Chemistry Emergency Team 0 02-01-2000 EPIP-RET-03A Liquid Effluent Release Paths L 11-29-2001 EP-RET-3B Post-Accident Reactor Coolant Alternate Deleted 01-25-88 Sampling Procedure PAGE 4 OF 11 EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-15-2002 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 R 10-02-2001 EP-RET-4A EOF Radiological Monitoring Deleted 03-10-83 EPIP-RET-04A SBF Operation/Relocation Deleted 10-02-2001 EP-RET-4B Radiological Controls at Site Access Facility Deleted 07-12-94 EP-RET-4C Site Radiological Monitoring Deleted 07-12-94 EP-RET-4D SAM-II Operation Deleted 07-12-94 EP-RET-5 Plume Projection Deleted 09-26-84 EPIP-RET-05 Site Boundary Dose Rates During Controlled H 10-09-2001 Plant Cooldown EP-RET-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 P 10-30-2001 Center EPIP-RET-09 Post-Accident Population Dose K 08-29-2000 EP-SEC EP-SEC-1 Security Organization Deleted 04-24-87 EPIP-SEC-02 Security Force Response to Emergencies W 08-28-2001 EP-SEC-2A Manual Activation of Emergency Sirens Deleted 04-16-82 EPIP-SEC-03 Personnel Assembly and Accountability AC 12-14-2001 EPIP-SEC-04 Security Force Actions for Dosimetry Issue P 10-02-2001 PAGE 5 OF 11 EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-15-2002 PROC. NO. TITLE REV. DATE EP-SEC-5 Security Force Response to the EOF Deleted 07-28-88 EPIP-SEC-05 Personnel Evacuation F 07-05-2001 EP-TSC EPIP-TSC-01 Technical Support Center Organization and P 10-02-2001 Responsibilities EPIP-TSC-02 Technical Support Center Activation S 11-29-2001 EPIP-TSC-03 Plant Status Procedure V 10-09-2001 EPIP-TSC-04 Emergency Physical Changes, Major Equipment M 10-02-2001 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 I 10-19-2001 EPIP-TSC-08A Calculations for Steam Release from Steam N 12-14-2001 Generators EPIP-TSC-08B*
WISCONSIN PUBLIC SERVICE CORP.                                  No.          EPIP-RET-03C            IRev. P Title        Post Accident Operation of the High Kewaunee Nuclear Power Plant                                            Radiation Sample Room Emergency Plan Implementing Procedure                            Date        JAN 15 2002              Page 1 of 34 Approved By        :Z ---- -'-,,
STMRLS Computer Program F 10-02-2001 EP-TSC-8C*
Reviewed Bv Nuclear                            [] Yes                              AORC            Yes_ SRO Approval Of          2 Yes Safety                                        Review                                        Temporary Related                            13 N        Reuired                              [] No  Changes Required        El No 1.0      Purpose 1.1      This procedure provides instruction for operation of the High Radiation Sample Room (HRSR) to obtain the following primary coolant samples under post accident conditions:
See EP-TSC-8B Deleted 04-16-92
: a. Diluted liquid sample of primary coolant for: (Step 5.1) 0 Boron analysis                                            0 Gamma isotopic analysis
* EP-TSC-8B was totally deleted; therefore, EP-TSC-8C was changed to EP-TSC-8B EP-TSC-9 Core Damage Assessment Using Released Deleted 09-30-86 Radionuclides EP-TSC-9A*
: b. An inline liquid sample for: (Step 5.2)
Core Damage Assessment I 02-23-99 EPIP-TSC-09B*
                    "* pH                                                       0   Oxygen
CORE Computer Program J 10-02-2001 EP-TSC-9C*
                    "* Conductivity
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 I 03-20-2001 PAGE 6 OF 11 EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-15-2002 FIGURES EPIP FIG # 1 Figure EPIPFG DESCRIPTION REV. DATE EP-SEC-5 Technical Support EPIP-APPX-A-06 EP-FIG-003 APPX-A-06-03 Center -KNP Floor Plan B 06-12-2001 Site Boundary Facility EPIP-APPX-A-06 EP-FIG-oos APPX-A-06-02 KNP Floor Plan A 10-31-2000 Radiological Analysis Facility -KNP Floor EPIP-APPX-A-06 EP-FIG-008 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 Map -Location of JPIC, EPIP-EOF-12 EP-FIG-024 EOF-12-02 MBC, GOB, DOB, etc. B 09-27-2001 EP-SEC-5 EP-FIG-026 SEC-05-01 Site Map B 09-27-2001 Floor Plan -Media APPX-A-6 EP-FIG-034 Briefing Center Deleted 08-04-98 EPIP-EOF-12 General Office 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-F-o37 ---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 A 06-15-2000 EPIP-APPX-A-02
--- APPX-A-02-01 ERO Call Tree Deleted 12-04-2001 PAGE 7 OF 11 EMERGENCY PLAN IMPLEMENTING PROCEDURES DATE: 01-15-2002 INDEX NUMBER TITLE APPENDIX A APPX-A-I Communication System Description EPIP-APPX-A-02 Response Personnel Call List EPIP-APPX-A-03 Off-Site Telephone Numbers EPIP-APPX-A-06 KNPP Emergency Response Facility Telephone Numbers PAGE 8 OF 11 EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-15-2002 FORM EPIPF TITLE REV. DATE APPENDIX B EP-AD AD-07-01 Event Notice (Wisconsin Nuclear Accident Reporting R 12-14-2001 Form) AD-07-02 State Call-Back
-Question Guideline C 11-15-2001 AD 11.1 Emergency Radiation Work Permit F 04-16-96 EP-ENV ENV-01-01 Environmental Dispatch Area Activation Checklist D 10-31-2000 ENV-01-02 EMT Status B 10-31-2000 ENV-01-03 Meteorological and Plant Status Data C 12-14-2001 ENV-01-04 EMT Orders/Field Data B 10-31-2000 ENV-02-01 EMT Activation Checklist M 06-15-2000 EP-EOF EOF-02-01 EOF Activation Checklist S 10-30-2001 EOF-02-02 EOF Deactivation Checklist L 10-30-2001 EOF-04-01 SRCL Initial Action Checklist C 12-14-2001 EOF-04-02 Telephone Communications Log Sheet A 12-14-2001 EOF-08-03 Fax for Emergency Declaration or Status Updates G 11-27-2001 EOF-08-05 Plant Emergency Status Report A 11-27-2001 EOF-08-06 Radiological Status Report D 11-27-2001 EOF- 11-02 Operating Status F 11-15-2001 EOF-1 1-03 Environmental Status Board F 11-15-2001 EOF-12-01 I.D. Badge Registration Form G 10-24-2000 EP-OSF OSF 2.2 Maintenance Work in Progress Deleted 07-08-98 OSF-03-01 Operational Support Facility Team Briefing C 12-04-2001 PAGE 9 OF 11 EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-15-2002 FORM EPIPF TITLE REV. DATE EP-RET RET-02A-02 Emergency Sample Worksheet E 06-05-2001 RET 2B. 1 Containment Stack Release (Grab Sample) C 04-16-96 RET 2B.2 Auxiliary Building Stack (Grab Sample) C 04-16-96 RET 2B.3 Auxiliary Building Stack (Sping Reading) C 04-16-96 RET 2B.4 Containment Stack (Sping Reading) B 04-16-96 RET 2B.5 Steam Release C 04-16-96 RET 2B.6 Field Reading (Grab Sample) A 04-16-96 RET-04-01 SAM-2 Counting Equipment Worksheet E 06-12-2001 RET 8.3 Hospital Survey 1 Deleted 06-05-20Q1 RET 8.4 Hospital Survey 2 Deleted 07-25-97 RET 8.5 Hospital Survey 3 Deleted 07-25-97 RET-08-06 Hospital Survey 4 F 06-15-2000 RET 9 Environmental TLD Record Sheet C 02-14-95 EP-SEC SEC-03.01 Emergency Accountability Log A 03-28-2000 SEC 4.1 Emergency Dosimeter Log F 02-16-2000 EP-TSC TSC 1.1 Plant Status Summary for SAM Implementation A 04-01-99 TSC 1.2 Severe Accident Management Summary and Strategy A 04-01-99 Recommendation TSC 1.3 Severe Accident Management
-Status A 04-01-99 TSC-02-01 TSC and OSF Activation Checklist 0 09-27-2001 TSC 2.2 TSC Ventilation Checklist H 04-01-99 TSC-02-03 Emergency Response Data System (ERDS) Link Initiation G 05-04-2001 Checklist PAGE 10 OF 11 EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-15-2002 FORM EPIPF TITLE REV. DATE TSC-02-04 TSC Chart Recorder Operation Checklist D 01-30-2001 TSC-02-05 TSC and OSF De-activation Checklist A 10-09-2001 TSC-03-01 Plant System Status L 06-12-2001 TSC-03-02 Plant Equipment Status L 06-12-2001 TSC-03-03 Environmental Status Board J 06-12-2001 TSC-03-04 Radiation Monitors I 01-08-2002 TSC-04-01 Emergency Physical Change Request F 08-29-2000 TSC-04-02 Emergency Physical Change Safety Review F 08-29-2000 TSC-04-03 Emergency Physical Change Index F 08-29-2000 TSC-07-01 Head Venting Calculation F 10-31-2000 TSC-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 9A. 1 Core Damage Based on Reactor Vessel Level & Fuel Rod C 02-14-95 Temp. TSC 9A.2 Core Damage Based on Radiation Monitors C 02-14-95 TSC 9A.3 Cs-134 and Cs-137 PCF Determination D 04-16-96 TSC 9A.4 Core Damage Based on Activity Ratios C 02-14-95 TSC 9A.5 Core Damage Assessment (Monitoring Data) D 04-16-96 TSC 9A.6 Core Damage Summary C 02-14-95 PAGE 11 OF 11 WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 2002 Page 1 of 34 Reviewed Bv Approved By ----:Z -'-,, Nuclear [] Yes AORC _ Yes SRO Approval Of 2 Yes Safety Review Temporary Related 13 N Reuired [] No Changes Required El No 1.0 Purpose 1.1 This procedure provides instruction for operation of the High Radiation Sample Room (HRSR) to obtain the following primary coolant samples under post accident conditions:
: a. Diluted liquid sample of primary coolant for: (Step 5.1)0 Boron analysis b. An inline liquid sample for: (Step 5.2)0 Gamma isotopic analysis"* pH 0 Oxygen "* Conductivity
* Chlorides
* Chlorides
: c. An inline undiluted gas sample for hydrogen analysis. (Step 5.3) d. A diluted gas sample for gamma isotopic analysis. (Step 5.3) e. An undiluted liquid sample for off-site analysis. (Step 5.4) f. Operation of IA and lB Hydrogen Analyzers for Containment. (Step 5.5) g. Flush of liquid sample lines. (Step 5.6) 2.0 General Notes 2.1 This procedure is designated CONTINUOUS USE. 2.2 The following is a list of acronyms that are used throughout this procedure:
: c. An inline undiluted gas sample for hydrogen analysis. (Step 5.3)
* CAP
: d. A diluted gas sample for gamma isotopic analysis. (Step 5.3)
* CASP
: e. An undiluted liquid sample for off-site analysis. (Step 5.4)
* CMP *DDT
: f. Operation of IA and lB Hydrogen Analyzers for Containment. (Step 5.5)
* HVAC/CCP
: g. Flush of liquid sample lines. (Step 5.6) 2.0       General Notes 2.1     This procedure is designated CONTINUOUS USE.
* HP/RPD
2.2     The following is a list of acronyms that are used throughout this procedure:
* HRSR
* CAP                 Chemical Analysis Panel
* LSP
* CASP                 Containment Air Sampling Panel
* RCHL
* CMP                  Chemical Analysis Monitor Panel
* SAP Chemical Analysis Panel Containment Air Sampling Panel Chemical Analysis Monitor Panel Deaerated Drain Tank HVAC/Containment Air Sample Control Panel Health Physics/Radiation Protection Director High Radiation Sample Room RCHL Liquid Sample Panel Reactor Coolant Hot Leg Sample Acquisition Panel n:\nucdoc\procedures\draft\epip\eret03c.doc-Bil HollingsworthlChrisfine Simmons-John Madden WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 2 of 34 3.0 Precautions and Limitations 3.1 Process an Emergency Radiation Work Permit per EPIP-AD-1 1, "Emergency Radiation Controls." 3.2 Contact Radiation Protection Group (HIP) for: 3.2.1 Proper personnel dosimetry 3.2.2 Proper radiation detection instrumentation 3.2.3 Personnel for continuous HIP coverage during sampling 3.2.4 Remote area monitor readings in area of HRSR 3.3 Utilize on-site communications with the HP/RPD, as necessary, during sampling.
              *DDT                      Deaerated Drain Tank
3.4 Containment sump pH should be adjusted to a pH > 7 within 48 hours following the initiation of recirculation during a small break loss of coolant accident.
* HVAC/CCP            HVAC/Containment Air Sample Control Panel
3.5 If the sample flow is lost during the performance of this procedure and the valve line-up is confirmed, a sample high temperature condition may exist.
* HP/RPD              Health Physics/Radiation Protection Director
* HRSR                High Radiation Sample Room RCHL
* LSP                  Liquid Sample Panel
* RCHL                Reactor Coolant Hot Leg
* SAP                  Sample Acquisition Panel n:\nucdoc\procedures\draft\epip\eret03c.doc-Bil HollingsworthlChrisfine Simmons-John Madden
 
WISCONSIN PUBLIC SERVICE CORP.                     No.         EPIP-RET-03C               Rev. P Title       Post Accident Operation of the High Kewaunee Nuclear Power Plant                               Radiation Sample Room Emergency Plan Implementing Procedure               Date       JAN 1 5 2002             Page 2 of 34 3.0     Precautions and Limitations 3.1     Process an Emergency Radiation Work Permit per EPIP-AD-1 1, "Emergency Radiation Controls."
3.2     Contact Radiation Protection Group (HIP) for:
3.2.1     Proper personnel dosimetry 3.2.2     Proper radiation detection instrumentation 3.2.3     Personnel for continuous HIP coverage during sampling 3.2.4     Remote area monitor readings in area of HRSR 3.3     Utilize on-site communications with the HP/RPD, as necessary, during sampling.
3.4       Containment sump pH should be adjusted to a pH > 7 within 48 hours following the initiation of recirculation during a small break loss of coolant accident.
3.5     If the sample flow is lost during the performance of this procedure and the valve line-up is confirmed, a sample high temperature condition may exist.
* No direct temperature indicator is available.
* No direct temperature indicator is available.
* Sample flow is automatically isolated when sample temperatures exceed 120°F and automatically resets when the temperatures are reduced.
* Sample flow is automatically isolated when sample temperatures exceed 120°F and automatically resets when the temperatures are reduced.
Line 86: Line 146:
* Such a high temperature condition may arise if the Component Cooling flow is isolated or Component Cooling temperatures are high. Component Cooling temperatures may be observed using the plant process computer.
* Such a high temperature condition may arise if the Component Cooling flow is isolated or Component Cooling temperatures are high. Component Cooling temperatures may be observed using the plant process computer.
High Component Cooling temperature may occur if Service Water temperatures are elevated.
High Component Cooling temperature may occur if Service Water temperatures are elevated.
3.6 IF the loss of sample flow is confirmed to be due to high Component Cooling temperatures, THEN discuss the concern with Operations or the Technical Support Center and discuss opportunities to reduce Service Water heat loads to allow for better performance of Component Cooling.
3.6     IF the loss of sample flow is confirmed to be due to high Component Cooling temperatures, THEN discuss the concern with Operations or the Technical Support Center and discuss opportunities to reduce Service Water heat loads to allow for better performance of Component Cooling.
3.7 Transit routes to and from the HRSR per HP/RPD recommendations.
3.7     Transit routes to and from the HRSR per HP/RPD recommendations.
3.8 Monitor radiation levels in the HRSR upon entry and during sample manipulations.
3.8     Monitor radiation levels in the HRSR upon entry and during sample manipulations.
CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C IRev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 2002 Page 3 of 34 3.9 Radiation level monitoring is required if accessing the maintenance areas behind the panels. 3.10 IF sufficient sample flow is not achieved, THEN extend the purge time as required to compensate for the reduced flow rates. 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.
CONTINUOUS USE
5.0 Procedure 5.1 Diluted Liquid Sample for Boron Analysis and Isotopic Analysis 5.1.1 In the HRSR check the following equipment available and operational:  
 
"* Drying oven on at 55°C to 60*C "* All material required to perform RCC-082, "Boron Analysis Curcumin Method." "* Multi-Channel Analyzer available for counting (Technical Support Center) " 2 -1 liter poly bottles "* Shielded aliquoter available  
WISCONSIN PUBLIC SERVICE CORP.                   No.       EPIP-RET-03C             IRev. P Title     Post Accident Operation of the High Kewaunee Nuclear Power Plant                             Radiation Sample Room Emergency Plan Implementing Procedure             Date       JAN 15 2002             Page 3 of 34 3.9     Radiation level monitoring is required if accessing the maintenance areas behind the panels.
"* New 60 ml diluted sample bottle (large bottle) "* Hand operated vacuum pump "* Lights on in diluted sample port of LSP "* LSP Sample Cask available with diluted sample bottle piston installed  
3.10   IF sufficient sample flow is not achieved, THEN extend the purge time as required to compensate for the reduced flow rates.
"* Reach Rod for remote valve operation CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C IRev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 4 of34 5.1.2 At the CASP perform the following:
4.0     Initial Conditions 4.1     This procedure shall be implemented upon declaration of an Alert, Site Emergency, General Emergency, or when directed by the Shift Manager or Emergency Director.
5.1.2.1 Verify ventilation is ON and mode control switches are in NORMAL position.
5.0     Procedure 5.1     Diluted Liquid Sample for Boron Analysis and Isotopic Analysis 5.1.1     In the HRSR check the following equipment available and operational:
5.1.2.2 Check High Vacuum Lights indicate NORMAL for the following:  
                  "* Drying oven on at 55°C to 60*C
"* LSP " CAP "* CASP 5.1.3 Perform valve lineup per Attachment A, "High Radiation Sample Valve Lineup Sheet." 5.1.4 Connect DI Water flush hose to LSP. 5.1.5 Open DI Water supply valve to LSP. 5.1.6 Evacuate the diluted sample bottle (60 ml, large bottle) to > 15 inches of vacuum. IF possible, THEN >20 inches of vacuum is recommended.
                  "* All material required to perform RCC-082, "Boron Analysis Curcumin Method."
5.1.6.1 Install sample bottle in sample cask. 5.1.6.2 Check cask for proper operation (large holder in cask). 5.1.7 At the LSP perform the following:
                  "* Multi-Channel Analyzer available for counting (Technical Support Center)
5.1.7.1 Inspect dilution water reservoir level. 5.1.7.2 IF necessary, THEN fill to full mark. 5.1.8 WHEN performing an RCHL sample, THEN request Control Room Operator perform the following:  
                  "   2 - 1 liter poly bottles
"* Open RC-422. "* Open RC-423.CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 2002 Page 5 of 5.1.9 At the SAP perform the following:
                  "* Shielded aliquoter available
5.1.9.1 WHEN performing an RCHL sample, THEN perform the following: " Open CC-314. "* Open RC-423-1.
                  "* New 60 ml diluted sample bottle (large bottle)
5.1.9.2 WHEN performing a Residual Heat Removal (RHR) sample, THEN perform the following:  
                  "* Hand operated vacuum pump
"* Open CC-316. "* WHEN sampling A RHR, THEN open RHR-81-A.
                  "* Lights on in diluted sample port of LSP
"* WHEN sampling B RHR, THEN open RHR-81-B.
                  "* LSP Sample Cask available with diluted sample bottle piston installed
5.1.9.3 Position RC-437-1 to DDT. 5.1.9.4 Position RC-437-2 to DDT. 5.1.10 At the LSP perform the following:
                  "* Reach Rod for remote valve operation CONTINUOUS USE
5.1.10.1 Open RC-V3. 5.1.10.2 WHEN performing a RCHL sample, THEN open RC-V-1.2.
 
5.1.10.3 WHEN performing a RHR sample, THEN open RC-V-1.1.
WISCONSIN PUBLIC SERVICE CORP.                     No.       EPIP-RET-03C             IRev. P Title     Post Accident Operation of the High Kewaunee Nuclear Power Plant                             Radiation Sample Room Emergency Plan Implementing Procedure               Date     JAN 1 5 2002             Page 4 of34 5.1.2     At the CASP perform the following:
Note Purge time may be varied based on actual purge flow rate obtained.
5.1.2.1     Verify ventilation is ON and mode control switches are in NORMAL position.
5.1.10.4 Throttle RC-VREL-1 until flow indicator RC-FI-1 indicates 1,900 to 2,000 cc/min. "* WHEN RCHL sample, THEN purge at least 12 minutes.
5.1.2.2     Check High Vacuum Lights indicate NORMAL for the following:
"* WHEN RHR sample, THEN purge at least 25 minutes.
                  "* LSP
5.1.10.5 IF unable to attain desired purge flow rate, THEN adjust purge time accordingly.
                  "   CAP
5.1.10.6 WHEN purge is complete, THEN perform the following:
                  "* CASP 5.1.3     Perform valve lineup per Attachment A, "High Radiation Sample Valve Lineup Sheet."
: a. Close RC-V-3. b. Open RC-V-8.2.
5.1.4     Connect DI Water flush hose to LSP.
5.1.5     Open DI Water supply valve to LSP.
5.1.6     Evacuate the diluted sample bottle (60 ml, large bottle) to > 15 inches of vacuum. IF possible, THEN >Ž20 inches of vacuum is recommended.
5.1.6.1     Install sample bottle in sample cask.
5.1.6.2     Check cask for proper operation (large holder in cask).
5.1.7     At the LSP perform the following:
5.1.7.1     Inspect dilution water reservoir level.
5.1.7.2     IF necessary, THEN fill to full mark.
5.1.8       WHEN performing an RCHL sample, THEN request Control Room Operator perform the following:
              "* Open RC-422.
              "* Open RC-423.
CONTINUOUS USE
 
WISCONSIN PUBLIC SERVICE CORP.                   No.         EPIP-RET-03C               Rev. P Title       Post Accident Operation of the High Kewaunee Nuclear Power Plant                               Radiation Sample Room Emergency Plan Implementing Procedure             Date         JAN 15 2002           Page 5 of 5.1.9     At the SAP perform the following:
5.1.9.1     WHEN performing an RCHL sample, THEN perform the following:
                  "   Open CC-314.
                  "* Open RC-423-1.
5.1.9.2     WHEN performing a Residual Heat Removal (RHR) sample, THEN perform the following:
                  "* Open CC-316.
                  "* WHEN sampling A RHR, THEN open RHR-81-A.
                  "* WHEN sampling B RHR, THEN open RHR-81-B.
5.1.9.3     Position RC-437-1 to DDT.
5.1.9.4     Position RC-437-2 to DDT.
5.1.10     At the LSP perform the following:
5.1.10.1   Open RC-V3.
5.1.10.2   WHEN performing a RCHL sample, THEN open RC-V-1.2.
5.1.10.3   WHEN performing a RHR sample, THEN open RC-V-1.1.
Note Purge time may be varied based on actualpurgeflow rate obtained.
5.1.10.4   Throttle RC-VREL-1 until flow indicator RC-FI-1 indicates 1,900 to 2,000 cc/min.
                  "* WHEN RCHL sample, THEN purge at least 12 minutes.
                  "* WHEN RHR sample, THEN purge at least 25 minutes.
5.1.10.5   IF unable to attain desired purge flow rate, THEN adjust purge time accordingly.
5.1.10.6   WHEN purge is complete, THEN perform the following:
: a. Close RC-V-3.
: b. Open RC-V-8.2.
: c. Open RC-V-8.1.
: c. Open RC-V-8.1.
: d. Open RC-V-2.CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 6 of 34 Note Purge time may be varied based on purge flow rate obtained.
: d. Open RC-V-2.
5.1.10.7 Throttle RC-VREL-2 until flow indicator RC-FI-2 indicates 180 to 220 cc/min. 5.1.10.8 Purge at least 3 minutes.
CONTINUOUS USE
5.1.10.9 IF unable to attain desired purge flow rate, THEN adjust purge time accordingly.
 
5.1.10.10 Verify diluted sample bottle (from Step 5.1.6) vacuum > 15 inches of vacuum. IF possible, THEN 20 inches of vacuum is recommended.
WISCONSIN PUBLIC SERVICE CORP.                 No.         EPIP-RET-03C             IRev. P Title       Post Accident Operation of the High Kewaunee Nuclear Power Plant                             Radiation Sample Room Emergency Plan Implementing Procedure           Date         JAN 1 5 2002           Page 6 of 34 Note Purgetime may be varied based on purgeflow rate obtained.
5.1.10.11 Install the sample cart under the diluted sample port. 5.1.10.12 Position the sample bottle up on the needles.
5.1.10.7   Throttle RC-VREL-2 until flow indicator RC-FI-2 indicates 180 to 220 cc/min.
5.1.10.8   Purge at least 3 minutes.
5.1.10.9   IF unable to attain desired purge flow rate, THEN adjust purge time accordingly.
5.1.10.10 Verify diluted sample bottle (from Step 5.1.6) vacuum > 15 inches of vacuum. IF possible, THEN Ž 20 inches of vacuum is recommended.
5.1.10.11 Install the sample cart under the diluted sample port.
5.1.10.12 Position the sample bottle up on the needles.
5.1.10.13 WHEN purge is complete, THEN perform the following:
5.1.10.13 WHEN purge is complete, THEN perform the following:
: a. Turn RC-DV-1 to SAMPLE position (6 o'clock).
: a. Turn RC-DV-1 to SAMPLE position (6 o'clock).
Line 124: Line 223:
: c. IF RHR sample, THEN close RC-V-1.1.
: c. IF RHR sample, THEN close RC-V-1.1.
5.1.10.14 Throttle open RC-V-21.
5.1.10.14 Throttle open RC-V-21.
5.1.10.15 Add 24 ml of DI Water to the sample bottle. 5.1.10.16 IF less than 24 ml of DI Water is used, THEN note sample volume. 5.1.10.17 Close RC-V-21.
5.1.10.15 Add 24 ml of DI Water to the sample bottle.
5.1.10.16 IF less than 24 ml of DI Water is used, THEN note sample volume.
5.1.10.17 Close RC-V-21.
5.1.10.18 Turn RC-DV-1 to BYPASS position (3 o'clock).
5.1.10.18 Turn RC-DV-1 to BYPASS position (3 o'clock).
5.1.10.19 Open RC-V-4. Note Flush time may be varied based on actual flush flow rate obtained.
5.1.10.19 Open RC-V-4.
5.1.10.20 Throttle RC-VEL-2 until flow indicator RC-FI-2 indicates 180 to 200 cc/min. 5.1.10.21 Flush for at least 3 minutes.
Note Flush time may be varied based on actualflushflow rate obtained.
5.1.10.20 Throttle RC-VEL-2 until flow indicator RC-FI-2 indicates 180 to 200 cc/min.
5.1.10.21 Flush for at least 3 minutes.
5.1.10.22 IF unable to attain desired flush flow rate, THEN adjust flush time accordingly.
5.1.10.22 IF unable to attain desired flush flow rate, THEN adjust flush time accordingly.
CONTINUOUS USE  
CONTINUOUS USE
~AIgr./4, NJi%.II 1 IR V IC~l, ~Fv ICF COR I .N.........  
 
.....C.ev. Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 2002 Page 7 of 34 Note The following step may be performed during the flush. 5.1.10.23 Lower the diluted sample bottle into the sample cask. "* Close the cask "* Place cask near fume hood "* Install auxiliary shield 5.1.10.24 Close RC-V-4. 5.1.10.25 Close RC-V-2. 5.1.10.26 Close RC-V-8.2.
No.                            I Rev. P
~AIgr./4,   NJi%.II 1 IR V   IC~l, ~Fv ICF COR.N......... I              ..... C.ev.
Title Post Accident Operation of the High Kewaunee Nuclear Power Plant                                 Radiation Sample Room Emergency Plan Implementing Procedure                       Date   JAN 15 2002             Page 7 of 34 Note The following step may be performed during theflush.
5.1.10.23 Lower the diluted sample bottle into the sample cask.
                        "* Close the cask
                        "* Place cask near fume hood
                        "* Install auxiliary shield 5.1.10.24 Close RC-V-4.
5.1.10.25 Close RC-V-2.
5.1.10.26 Close RC-V-8.2.
5.1.10.27 Close RC-V-8.1.
5.1.10.27 Close RC-V-8.1.
5.1.11 WHEN RCHL sample, THEN request Control Room Operator perform the following:  
5.1.11         WHEN RCHL sample, THEN request Control Room Operator perform the following:
"* Close RC-422. "* Close RC-423. 5.1.12 At the SAP perform the following:
                          "* Close RC-422.
5.1.12.1 WHEN RCHL sample, THEN perform the following:  
                          "* Close RC-423.
"* Close RC-423-1.
5.1.12         At the SAP perform the following:
"* Close CC-314. 5.1.12.2 WHEN RHR sample, THEN perform the following:  
5.1.12.1       WHEN RCHL sample, THEN perform the following:
"* IF opened, THEN close RHR-81A.
                          "* Close RC-423-1.
"* IF opened, THEN close RHR-81B.
                          "* Close CC-314.
"* Close CC-316. 5.1.12.3 Position RC-437-1 toVCT. 5.1.12.4 Position RC-437-2 to VCT. 5.1.12.5 Close DI Water supply valve. 5.1.12.6 Disconnect DI Water hose.CONTINUOUS USE I Rev. P No.
5.1.12.2       WHEN RHR sample, THEN perform the following:
WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 _ Page 8 of 34 Note Dilution factor correction is required ifsample was not diluted with 24 ml of DI Water Step 5.1.10.16.
                          "* IF opened, THEN close RHR-81A.
5.1.13 Perform the following post sample analyses preparations:
                          "* IF opened, THEN close RHR-81B.
Note For Boron analysis of< 2,000 ppm, an appropriately larger amount of sample shall be used. 5.1.13.1 WHEN analyzing for boron, THEN perform the following:
                          "* Close CC-316.
5.1.12.3       Position RC-437-1 toVCT.
5.1.12.4       Position RC-437-2 to VCT.
5.1.12.5       Close DI Water supply valve.
5.1.12.6       Disconnect DI Water hose.
CONTINUOUS USE
 
WISCONSIN PUBLIC SERVICE CORP.                     No.       EPIP-RET-03C                 Rev. P Title     Post Accident Operation of the High Kewaunee Nuclear Power Plant                             Radiation Sample Room Emergency Plan Implementing Procedure               Date     JAN 1 5 2002         _       Page 8 of 34 Note Dilutionfactor correction is requiredifsample was not diluted with 24 ml ofDI Water Step 5.1.10.16.
5.1.13     Perform the following post sample analyses preparations:
Note For Boron analysis of< 2,000 ppm, an appropriatelylargeramount of sample shall be used.
5.1.13.1   WHEN analyzing for boron, THEN perform the following:
: a. Transfer a 1.0 ml sample from the sample cask into a VYCOR evaporating dish using the shielded liquid aliquoter.
: a. Transfer a 1.0 ml sample from the sample cask into a VYCOR evaporating dish using the shielded liquid aliquoter.
: b. Continue the boron analysis per RCC-082, "Boron Analysis Curcumin -Method." 5.1.13.2 WHEN performing a Beta/Gamma analysis, THEN perform the following:
: b. Continue the boron analysis per RCC-082, "Boron Analysis Curcumin         -
Method."
5.1.13.2   WHEN performing a Beta/Gamma analysis, THEN perform the following:
: a. Transfer 1.0 ml of coolant from the cask to a 1 liter poly bottle using the shielded liquid aliquoter.
: a. Transfer 1.0 ml of coolant from the cask to a 1 liter poly bottle using the shielded liquid aliquoter.
: b. Dilute to 1 liter with DI Water. c. Transfer 10 ml of diluted sample to a second 1 liter poly bottle. d. Dilute to 1 liter with DI Water. Dilution factor = 108. e. Transfer sample to the multi-channel analyzer for counting.
: b. Dilute to 1 liter with DI Water.
5.2 Inline Sample for pH, Conductivity, 02 and Chloride Note Gas cylinders and their regulators are located outside the HRSR at the gas cylinder rack. 5.2.1 Align argon and helium as follows: 5.2.1.1 Verify open argon gas cylinder isolation.
: c. Transfer 10 ml of diluted sample to a second 1 liter poly bottle.
5.2.1.2 Verify argon cylinder pressure >_ 400 psi. 5.2.1.3 Adjust argon pressure regulator to obtain 150 psi (140 to 160 psi). 5.2.1.4 Verify open helium gas cylinder isolation.
: d. Dilute to 1 liter with DI Water. Dilution factor = 108.
CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 2002 Page 9 of 34 5.2.1.5 Verify helium cylinder pressure > 400 psi. 5.2.1.6 Adjust helium pressure regulator to obtain 70 psi (65 to 85 psi). 5.2.2 Verify reach rod is available for remote valve operation.
: e. Transfer sample to the multi-channel analyzer for counting.
5.2.3 Check HRSR Calibration Log for verification of latest performances.
5.2     Inline Sample for pH, Conductivity, 02 and Chloride Note Gas cylinders and their regulatorsare located outside the HRSR at the gas cylinder rack.
5.2.4 At the CASP perform the following:
5.2.1     Align argon and helium as follows:
5.2.4.1 Verify ventilation is ON and mode control switches are in NORMAL position.
5.2.1.1     Verify open argon gas cylinder isolation.
5.2.4.2 Check High Vacuum Lights indicate NORMAL for the following:
5.2.1.2     Verify argon cylinder pressure >_400 psi.
* LSP 0 CAP 0 CASP 5.2.5 At the CMP perform the following:
5.2.1.3     Adjust argon pressure regulator to obtain 150 psi (140 to 160 psi).
5.2.5.1 CMP Main Power switch ON. 5.2.5.2 Verify the YSI chart recorder is ON. 5.2.5.3 Verify the pH meter is ON. 5.2.5.4 Verify the conductivity meter is ON. 5.2.5.5 Start Ion Chromatograph (IC) in accordance with RCC-520, "DX-500 Startup and Shutdown Procedure." 5.2.6 Perform valve lineup per Attachment A, "High Radiation Sample Valve Lineup Sheet." 5.2.7 At the CAP, verify argon, helium, and air regulators set as follows: 5.2.7.1 Adjust argon pressure regulator to obtain 30 psi (30 to 32 psi). 5.2.7.2 Adjust helium pressure regulator to obtain 50 psi (50 to 55 psi). 5.2.7.3 Adjust air pressure regulator to obtain 75 psi (75 to 85 psi). 5.2.8 Connect DI Water flush hoses to LSP and CAP. 5.2.9 Open DI Water supply valve to LSP. CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Inmplementing Procedure Date AN 152002 Page 10 of 34 5.2.10 Open DI Water supply valve to CAP. 5.2.11 At the CAP perform the following:
5.2.1.4     Verify open helium gas cylinder isolation.
5.2.11.1 Position V-6 to LIQUID SAMPLE (9 o'clock).
CONTINUOUS USE
5.2.11.2 Position V-5 to LIQUID SAMPLE (9 o'clock).
 
5.2.12 WHEN RCHL sample, THEN request Control Room Operator perform the following:  
WISCONSIN PUBLIC SERVICE CORP.                     No.         EPIP-RET-03C             IRev. P Title       Post Accident Operation of the High Kewaunee Nuclear Power Plant                               Radiation Sample Room Emergency Plan Implementing Procedure               Date         JAN 15 2002           Page 9 of 34 5.2.1.5     Verify helium cylinder pressure > 400 psi.
"* Open RC-422. "* Open RC-423. 5.2.13 At the SAP perform the following:
5.2.1.6     Adjust helium pressure regulator to obtain 70 psi (65 to 85 psi).
5.2.13.1 WHEN performing an RCHL sample, THEN perform the following:  
5.2.2       Verify reach rod is available for remote valve operation.
"* Open CC-314. "* Open RC-423-1.
5.2.3       Check HRSR Calibration Log for verification of latest performances.
5.2.13.2 WHEN performing a RHR sample, THEN perform the following:  
5.2.4       At the CASP perform the following:
"* Open CC-316. "* WHEN sampling A RHR, THEN open RHR-81-A.
5.2.4.1     Verify ventilation is ON and mode control switches are in NORMAL position.
"* WHEN sampling B RI{R, THEN open RHR-8 1-B. 5.2.13.3 Position RC-437-1 to DDT. 5.2.13.4 Position RC-437-2 to DDT. 5.2.14 At the LSP perform the following:
5.2.4.2     Check High Vacuum Lights indicate NORMAL for the following:
5.2.14.1 Open RC-V3. 5.2.14.2 WHEN performing a RCHL sample, THEN open RC-V-1.2.
* LSP 0 CAP 0   CASP 5.2.5       At the CMP perform the following:
5.2.14.3 WHEN performing a RHR sample, THEN open RC-V-1.1.CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C -TRev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 2002 Page 11 of 34 Note Purge time may be varied based on actual purge flow rate obtained.
5.2.5.1     CMP Main Power switch ON.
5.2.14.4 Throttle RC-VREL- 1 until flow indicator RC-FI- 1 indicates 1,900 to 2,000 cc/min. "* WHEN RCHL sample, THEN purge at least 12 minutes.
5.2.5.2     Verify the YSI chart recorder is ON.
"* WHEN RHR sample, THEN purge at least 25 minutes.
5.2.5.3     Verify the pH meter is ON.
5.2.14.5 IF unable to attain desired purge flow rate, THEN adjust purge time accordingly.
5.2.5.4     Verify the conductivity meter is ON.
5.2.14.6 WHEN purge is complete, THEN perform the following:  
5.2.5.5     Start Ion Chromatograph (IC) in accordance with RCC-520, "DX-500 Startup and Shutdown Procedure."
"* Close RC-V-3. "* Open RC-V-2. "* Open RC-V-7. "* Position RC-V-22 to CHEM PANEL. Note Purge time may be varied based on actual purge flow rate obtained.
5.2.6     Perform valve lineup per Attachment A, "High Radiation Sample Valve Lineup Sheet."
5.2.14.7 Throttle RC-VREL-2 until flow indicator RC-FI-2 indicates 180 to 220 cc/min. 5.2.14.8 Purge at least 5 minutes.
5.2.7     At the CAP, verify argon, helium, and air regulators set as follows:
5.2.14.9 IF unable to attain desired purge flow rate, THEN adjust purge time accordingly.
5.2.7.1     Adjust argon pressure regulator to obtain 30 psi (30 to 32 psi).
5.2.15 At the CAP perform the following:
5.2.7.2     Adjust helium pressure regulator to obtain 50 psi (50 to 55 psi).
5.2.15.1 Verify adequate flow to the CAP by observing the red lights ON for both Oxygen and IC. 5.2.15.2 WHEN the YSI 02 meter chart reading has stabilized, THEN record the following on the Reactor Coolant Analysis Log (routine logsheet):
5.2.7.3     Adjust air pressure regulator to obtain 75 psi (75 to 85 psi).
5.2.8       Connect DI Water flush hoses to LSP and CAP.
5.2.9       Open DI Water supply valve to LSP.
CONTINUOUS USE
 
WISCONSIN PUBLIC SERVICE CORP.               No.     EPIP-RET-03C             IRev. P Title   Post Accident Operation of the High Kewaunee Nuclear Power Plant                       Radiation Sample Room Emergency Plan Inmplementing Procedure         Date     AN 152002               Page 10 of 34 5.2.10     Open DI Water supply valve to CAP.
5.2.11     At the CAP perform the following:
5.2.11.1   Position V-6 to LIQUID SAMPLE (9 o'clock).
5.2.11.2   Position V-5 to LIQUID SAMPLE (9 o'clock).
5.2.12     WHEN RCHL sample, THEN request Control Room Operator perform the following:
            "* Open RC-422.
            "* Open RC-423.
5.2.13     At the SAP perform the following:
5.2.13.1   WHEN performing an RCHL sample, THEN perform the following:
                  "* Open CC-314.
                  "* Open RC-423-1.
5.2.13.2   WHEN performing a RHR sample, THEN perform the following:
                  "* Open CC-316.
                  "* WHEN sampling A RHR, THEN open RHR-81-A.
                  "* WHEN sampling B RI{R, THEN open RHR-8 1-B.
5.2.13.3   Position RC-437-1 to DDT.
5.2.13.4   Position RC-437-2 to DDT.
5.2.14   At the LSP perform the following:
5.2.14.1   Open RC-V3.
5.2.14.2   WHEN performing a RCHL sample, THEN open RC-V-1.2.
5.2.14.3   WHEN performing a RHR sample, THEN open RC-V-1.1.
CONTINUOUS USE
 
WISCONSIN PUBLIC SERVICE CORP.                   No.         EPIP-RET-03C           -TRev. P Title       Post Accident Operation of the High Kewaunee Nuclear Power Plant                               Radiation Sample Room Emergency Plan Implementing Procedure             Date         JAN 15 2002           Page 11 of 34 Note Purge time may be varied based on actualpurgeflow rate obtained.
5.2.14.4   Throttle RC-VREL- 1 until flow indicator RC-FI- 1 indicates 1,900 to 2,000 cc/min.
                  "* WHEN RCHL sample, THEN purge at least 12 minutes.
                  "* WHEN RHR sample, THEN purge at least 25 minutes.
5.2.14.5   IF unable to attain desired purge flow rate, THEN adjust purge time accordingly.
5.2.14.6   WHEN purge is complete, THEN perform the following:
                  "* Close RC-V-3.
                  "* Open RC-V-2.
                  "* Open RC-V-7.
                  "* Position RC-V-22 to CHEM PANEL.
Note Purge time may be varied based on actualpurgeflow rate obtained.
5.2.14.7   Throttle RC-VREL-2 until flow indicator RC-FI-2 indicates 180 to 220 cc/min.
5.2.14.8   Purge at least 5 minutes.
5.2.14.9   IF unable to attain desired purge flow rate, THEN adjust purge time accordingly.
5.2.15     At the CAP perform the following:
5.2.15.1   Verify adequate flow to the CAP by observing the red lights ON for both Oxygen and IC.
5.2.15.2   WHEN the YSI 02 meter chart reading has stabilized, THEN record the following on the Reactor Coolant Analysis Log (routine logsheet):
* Conductivity reading
* Conductivity reading
* Temperature
* Temperature
* 02 reading CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C 1 Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 12 of 34 5.2.15.3 Inject sample on IC unit.
* 02 reading CONTINUOUS USE
 
WISCONSIN PUBLIC SERVICE CORP.                 No.         EPIP-RET-03C               1Rev. P Title       Post Accident Operation of the High Kewaunee Nuclear Power Plant                             Radiation Sample Room Emergency Plan Implementing Procedure           Date       JAN 1 5 2002               Page 12 of 34 5.2.15.3   Inject sample on IC unit.
* WHEN IC run complete, THEN record Chloride value on the Reactor Coolant Analysis Log (routine logsheet) and attach chart recorder printout.
* WHEN IC run complete, THEN record Chloride value on the Reactor Coolant Analysis Log (routine logsheet) and attach chart recorder printout.
5.2.16 At the LSP perform the following:
5.2.16   At the LSP perform the following:
5.2.16.1 Turn RC-V-22 to WASTE position (6 o'clock).
5.2.16.1   Turn RC-V-22 to WASTE position (6 o'clock).
5.2.16.2 WHEN RCHL sample, THEN close RC-V-1.2.
5.2.16.2   WHEN RCHL sample, THEN close RC-V-1.2.
5.2.16.3 WHEN RHR sample, THEN close RC-V-1.1.
5.2.16.3   WHEN RHR sample, THEN close RC-V-1.1.
5.2.16.4 Open RC-V-4. 5.2.16.5 Observe DI Water flush to waste as indicated on Flow Indicator RC-FI-2.
5.2.16.4   Open RC-V-4.
5.2.16.6 Flush for 2 minutes.
5.2.16.5   Observe DI Water flush to waste as indicated on Flow Indicator RC-FI-2.
5.2.16.7 Record pH reading on the Reactor Coolant Analysis Log (routine logsheet).
5.2.16.6   Flush for 2 minutes.
5.2.16.8 Turn RC-V-22 to CAP position (12 o'clock).
5.2.16.7   Record pH reading on the Reactor Coolant Analysis Log (routine logsheet).
5.2.16.9 Verify flush water flow by observing the lights ON for both 02 Flow and IC Flow. 5.2.16.10 Flush for at least 2 minutes.
5.2.16.8   Turn RC-V-22 to CAP position (12 o'clock).
5.2.16.9   Verify flush water flow by observing the lights ON for both 02 Flow and IC Flow.
5.2.16.10 Flush for at least 2 minutes.
5.2.16.11 Turn RC-V-22 to WASTE position (6 o'clock).
5.2.16.11 Turn RC-V-22 to WASTE position (6 o'clock).
5.2.16.12 Close RC-V-7. 5.2.16.13 Close RC-V-2. 5.2.16.14 Close RC-V-4. 5.2.17 At the CAP perform the following:
5.2.16.12 Close RC-V-7.
5.2.17.1 Position V-6 to 02 CAL (6 o'clock).
5.2.16.13 Close RC-V-2.
5.2.17.2 Close V-5 (6 o'clock).CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date AN1 5 2002 Page 13 of 34 5.2.18 WHEN RCHL sample, THEN request Control Room Operator perform the following:  
5.2.16.14 Close RC-V-4.
"* Close RC-422. "* Close RC-423. 5.2.19 At the SAP perform the following:
5.2.17     At the CAP perform the following:
5.2.19.1 WHEN RCHL sample, THEN perform the following:  
5.2.17.1     Position V-6 to 02 CAL (6 o'clock).
"* Close RC-423-1.
5.2.17.2     Close V-5 (6 o'clock).
"* Close CC-314. 5.2.19.2 WHEN RJ{R sample, THEN perform the following:  
CONTINUOUS USE
"* IF opened, THEN close RHR-81A.
 
"* IF opened, THEN close RHR-81B.
WISCONSIN PUBLIC SERVICE CORP.                   No.         EPIP-RET-03C             IRev. P Title       Post Accident Operation of the High Kewaunee Nuclear Power Plant                             Radiation Sample Room Emergency Plan Implementing Procedure             Date         AN1 5 2002             Page 13 of 34 5.2.18     WHEN RCHL sample, THEN request Control Room Operator perform the following:
"* Close CC-316. 5.2.19.3 Position RC-437-1 to VCT. 5.2.19.4 Position RC-437-2 to VCT. 5.2.19.5 Close DI Water supply valve. 5.2.19.6 Disconnect DI Water hose. 5.3 Inline Hydrogen and Gaseous Activity Grab Sample 5.3.1 Verify the multi-channel analyzer available for counting.
              "* Close RC-422.
Note Gas cylinders and their regulators are located outside the HRSR at the gas cylinder rack. 5.3.2 Align argon and helium as follows: 5.3.2.1 Verify open argon gas cylinder isolation.
              "* Close RC-423.
5.3.2.2 Verify argon cylinder pressure 400 psi. 5.3.2.3 Adjust argon pressure regulator to obtain 150 psi (140 to 160 psi). 5.3.2.4 Verify open helium gas cylinder isolation.
5.2.19     At the SAP perform the following:
CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 14 of 34 5.3.2.5 Verify helium cylinder pressure _> 400 psi. 5.3.2.6 Adjust helium pressure regulator to obtain 70 psi (65 to 85 psi). 5.3.3 At the CASP perform the following:
5.2.19.1   WHEN RCHL sample, THEN perform the following:
5.3.3.1 Verify ventilation is ON and mode control switches are in NORMAL position.
                    "* Close RC-423-1.
5.3.3.2 Check High Vacuum Lights indicate NORMAL for the following:  
                    "* Close CC-314.
"* LSP "* CA-P "* CASP 5.3.4 Verify the following equipment available and operational:
5.2.19.2   WHEN RJ{R sample, THEN perform the following:
                    "* IF opened, THEN close RHR-81A.
                    "* IF opened, THEN close RHR-81B.
                    "* Close CC-316.
5.2.19.3   Position RC-437-1 to VCT.
5.2.19.4   Position RC-437-2 to VCT.
5.2.19.5   Close DI Water supply valve.
5.2.19.6   Disconnect DI Water hose.
5.3     Inline Hydrogen and Gaseous Activity Grab Sample 5.3.1     Verify the multi-channel analyzer available for counting.
Note Gas cylinders and their regulatorsare locatedoutside the HRSR at the gas cylinder rack.
5.3.2     Align argon and helium as follows:
5.3.2.1     Verify open argon gas cylinder isolation.
5.3.2.2     Verify argon cylinder pressure &#x17d; 400 psi.
5.3.2.3     Adjust argon pressure regulator to obtain 150 psi (140 to 160 psi).
5.3.2.4     Verify open helium gas cylinder isolation.
CONTINUOUS USE
 
WISCONSIN PUBLIC SERVICE CORP.                   No.         EPIP-RET-03C               IRev. P Title       Post Accident Operation of the High Kewaunee Nuclear Power Plant                               Radiation Sample Room Emergency Plan Implementing Procedure             Date         JAN 1 5 2002             Page 14 of 34 5.3.2.5   Verify helium cylinder pressure _> 400 psi.
5.3.2.6   Adjust helium pressure regulator to obtain 70 psi (65 to 85 psi).
5.3.3     At the CASP perform the following:
5.3.3.1     Verify ventilation is ON and mode control switches are in NORMAL position.
5.3.3.2     Check High Vacuum Lights indicate NORMAL for the following:
                  "* LSP
                  "* CA-P
                  "* CASP 5.3.4     Verify the following equipment available and operational:
* Reach Rod for remote valve operation
* Reach Rod for remote valve operation
* 10 cc gas sample bottle, with septum, properly installed in face of LSP using the special handling tool 5.3.5 At the CMP perform the following:
* 10 cc gas sample bottle, with septum, properly installed in face of LSP using the special handling tool 5.3.5     At the CMP perform the following:
5.3.5.1 CMP Main Power switch ON. 5.3.5.2 Verify the program in Gas Chromatograph (GC) mini-computer.
5.3.5.1     CMP Main Power switch ON.
5.3.5.3 Check HRSR Calibration Log for verification of latest performances.
5.3.5.2     Verify the program in Gas Chromatograph (GC) mini-computer.
5.3.6 Perform valve lineup per Attachment A, "High Radiation Sample Valve Lineup Sheet." 5.3.7 At the CAP, verify Argon, Helium, and Air regulators set as follows: 5.3.7.1 Adjust Argon pressure regulator to obtain 30 psi (30 to 32 psi). 5.3.7.2 Adjust Helium pressure regulator to obtain 50 psi (50 to 55 psi). 5.3.7.3 Adjust Air pressure regulator to obtain 75 psi (75 to 85 psi). 5.3.8 Connect DI Water flush hoses to LSP and CAP. 5.3.9 Open DI Water supply valves.CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 20(2 Page 15 of 34 5.3.10 At the LSP, dry the expansion vessel as follows: 5.3.10.1 Turn RC-V-11 to ARGON position (3 o'clock).
5.3.5.3     Check HRSR Calibration Log for verification of latest performances.
5.3.10.2 Open RC-V-9. 5.3.10.3 Open RC-V-8.2.
5.3.6     Perform valve lineup per Attachment A, "High Radiation Sample Valve Lineup Sheet."
5.3.10.4 Open RC-V-10.
5.3.7     At the CAP, verify Argon, Helium, and Air regulators set as follows:
5.3.10.5 Regulate RC-VREL-2 to obtain 20 psi on RC-G-3. 5.3.10.6 Observe flow indication on RC-FI-2.
5.3.7.1     Adjust Argon pressure regulator to obtain 30 psi (30 to 32 psi).
5.3.10.7 Wait at least 1 minute. 5.3.10.8 Turn RC-V-1 1 counterclockwise to VACUUMISAMPLE position (9 o'clock).
5.3.7.2     Adjust Helium pressure regulator to obtain 50 psi (50 to 55 psi).
5.3.10.9 Close RC-V-9. 5.3.10.10 Close RC-V-8.2.
5.3.7.3     Adjust Air pressure regulator to obtain 75 psi (75 to 85 psi).
5.3.11 WHEN RCHL sample, THEN request Control Room Operator perform the following:  
5.3.8       Connect DI Water flush hoses to LSP and CAP.
"* Open RC-422. "* Open RC-423. 5.3.12 At the SAP perform the following:
5.3.9       Open DI Water supply valves.
5.3.12.1 WHEN performing an RCHL sample, THEN perform the following:  
CONTINUOUS USE
"* Open CC-314. "* Open RC-423-1.
 
5.3.12.2 WHEN performing a RHR sample, THEN perform the following:  
WISCONSIN PUBLIC SERVICE CORP.                 No.         EPIP-RET-03C             IRev. P Title       Post Accident Operation of the High Kewaunee Nuclear Power Plant                             Radiation Sample Room Emergency Plan Implementing Procedure           Date       JAN 15 20(2             Page 15 of 34 5.3.10   At the LSP, dry the expansion vessel as follows:
"* Open CC-316. "* WHEN sampling A RHR, THEN open RHR-81-A.
5.3.10.1   Turn RC-V-11 to ARGON position (3 o'clock).
"* WHEN sampling B RIR, THEN open RHR-81-B.
5.3.10.2   Open RC-V-9.
5.3.12.3 Position RC-437-1 to DDT. 5.3.12.4 Position RC-437-2 to DDT.CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 2002 Page 16 of 34 5.3.13 At the LSP perform the following:
5.3.10.3   Open RC-V-8.2.
5.3.13.1 Open RC-V3. 5.3.13.2 WHEN performing a RCHL sample, THEN open RC-V-1.2.
5.3.10.4   Open RC-V-10.
5.3.13.3 WHEN performing a RHR sample, THEN open RC-V- 1.1. Note Purge time may be varied based on actualpurge flow rate obtained.
5.3.10.5   Regulate RC-VREL-2 to obtain 20 psi on RC-G-3.
5.3.13.4 Throttle RC-VREL- 1 until flow indicator RC-FI- 1 indicates 1,900 to 2,000 cc/min. "* WHEN RCHL sample, THEN purge at least 12 minutes.
5.3.10.6   Observe flow indication on RC-FI-2.
"* WHEN RIR sample, THEN purge at least 25 minutes.
5.3.10.7   Wait at least 1 minute.
5.3.13.5 IF unable to attain desired purge flow rate, THEN adjust purge time accordingly.
5.3.10.8   Turn RC-V-1 1 counterclockwise to VACUUMISAMPLE position (9 o'clock).
Note The following, Steps 5.3.13.6 to 5.3.13.11, may be completed while waiting for the sample purge to be completed.
5.3.10.9   Close RC-V-9.
5.3.13.6 Evacuate the Gas Expansion Vessel, sample bottle, and tubing as follows: a. Open RC-V-13.
5.3.10.10 Close RC-V-8.2.
5.3.11   WHEN RCHL sample, THEN request Control Room Operator perform the following:
            "* Open RC-422.
            "* Open RC-423.
5.3.12   At the SAP perform the following:
5.3.12.1   WHEN performing an RCHL sample, THEN perform the following:
                "* Open CC-314.
                "* Open RC-423-1.
5.3.12.2   WHEN performing a RHR sample, THEN perform the following:
                "* Open CC-316.
                "* WHEN sampling A RHR, THEN open RHR-81-A.
                "* WHEN sampling B RIR, THEN open RHR-81-B.
5.3.12.3   Position RC-437-1 to DDT.
5.3.12.4   Position RC-437-2 to DDT.
CONTINUOUS USE
 
WISCONSIN PUBLIC SERVICE CORP.                   No.         EPIP-RET-03C             I Rev. P Title       Post Accident Operation of the High Kewaunee Nuclear Power Plant                             Radiation Sample Room Emergency Plan Implementing Procedure             Date         JAN 15 2002           Page 16 of 34 5.3.13   At the LSP perform the following:
5.3.13.1   Open RC-V3.
5.3.13.2   WHEN performing a RCHL sample, THEN open RC-V-1.2.
5.3.13.3   WHEN performing a RHR sample, THEN open RC-V- 1.1.
Note Purge time may be varied based on actualpurgeflow rate obtained.
5.3.13.4   Throttle RC-VREL- 1 until flow indicator RC-FI- 1 indicates 1,900 to 2,000 cc/min.
                "* WHEN RCHL sample, THEN purge at least 12 minutes.
                "* WHEN RIR sample, THEN purge at least 25 minutes.
5.3.13.5   IF unable to attain desired purge flow rate, THEN adjust purge time accordingly.
Note The following, Steps 5.3.13.6 to 5.3.13.11, may be completed while waitingfor the samplepurge to be completed.
5.3.13.6   Evacuate the Gas Expansion Vessel, sample bottle, and tubing as follows:
: a. Open RC-V-13.
: b. Open RC-V-15.
: b. Open RC-V-15.
: c. Turn RC-DV-2 to GAS SAMPLE position (12 o'clock).
: c. Turn RC-DV-2 to GAS SAMPLE position (12 o'clock).
: d. Open RC-V-12.
: d. Open RC-V-12.
5.3.13.7 WHEN vacuum on RC-G-2.2 > 22 inches vacuum, THEN turn RC-DV-2 to TO GC position (3 o'clock).
5.3.13.7   WHEN vacuum on RC-G-2.2 > 22 inches vacuum, THEN turn RC-DV-2 to TO GC position (3 o'clock).
5.3.13.8 WHEN vacuum on RC-G-2.1 > 22 inches of vacuum, THEN perform the following:
5.3.13.8   WHEN vacuum on RC-G-2.1 &#x17d;> 22 inches of vacuum, THEN perform the following:
: a. Close RC-V-15.
: a. Close RC-V-15.
: b. Close RC-V-13.
: b. Close RC-V-13.
: c. Close RC-V-10.
: c. Close RC-V-10.
: d. Turn RC-V-11 clockwise to CLOSE position (12 o'clock).
: d. Turn RC-V-11 clockwise to CLOSE position (12 o'clock).
: e. Close RC-V-12.CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C IRev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 17 of 34 5.3.13.9 Observe vacuum is holding steady on both gauges by performing the following:
: e. Close RC-V-12.
CONTINUOUS USE
 
WISCONSIN PUBLIC SERVICE CORP.                 No.         EPIP-RET-03C             IRev. P Title       Post Accident Operation of the High Kewaunee Nuclear Power Plant                           Radiation Sample Room Emergency Plan Implementing Procedure           Date       JAN 1 5 2002           Page 17 of 34 5.3.13.9 Observe vacuum is holding steady on both gauges by performing the following:
: a. Turn RC-DV-2 to 12 o'clock.
: a. Turn RC-DV-2 to 12 o'clock.
: b. Observe vacuum on RC-G-2.2 is holding steady. c. Turn RC-DV-2 to 3 o'clock.
: b. Observe vacuum on RC-G-2.2 is holding steady.
: c. Turn RC-DV-2 to 3 o'clock.
5.3.13.10 Open RC-V-14.
5.3.13.10 Open RC-V-14.
5.3.13.11 Observe RC-G-2.2 about 1.0 psi. Note Sample purge must be completed before proceeding.
5.3.13.11 Observe RC-G-2.2 about 1.0 psi.
5.3.13.12 Close RC-V-3. 5.3.13.13 Open RC-V-8.2.
Note Sample purge must be completed before proceeding.
5.3.13.12 Close RC-V-3.
5.3.13.13 Open RC-V-8.2.
5.3.13.14 Open RC-V-8.1.
5.3.13.14 Open RC-V-8.1.
5.3.13.15 Open RC-V-2. Note Purge time may be varied based on actual purge flow rate obtained.
5.3.13.15 Open RC-V-2.
5.3.13.16 Throttle RC-VREL-2 until flow indicator RC-FI-2 indicates 180 to 220 cc/min. 5.3.13.17 Purge at least 3 minutes.
Note Purgetime may be varied based on actualpurgeflow rate obtained.
5.3.13.16 Throttle RC-VREL-2 until flow indicator RC-FI-2 indicates 180 to 220 cc/min.
5.3.13.17 Purge at least 3 minutes.
5.3.13.18 IF unable to attain desired purge flow rate, THEN adjust purge time accordingly.
5.3.13.18 IF unable to attain desired purge flow rate, THEN adjust purge time accordingly.
5.3.13.19 Close RC-V-8.2.
5.3.13.19 Close RC-V-8.2.
Line 255: Line 485:
5.3.13.21 WHEN RCHL sample, THEN close RC-V-1.2.
5.3.13.21 WHEN RCHL sample, THEN close RC-V-1.2.
5.3.13.22 WHEN RHR sample, THEN close RC-V-1.1.
5.3.13.22 WHEN RHR sample, THEN close RC-V-1.1.
5.3.13.23 Open RC-V-9. 5.3.13.24 Open RC-V-16.
5.3.13.23 Open RC-V-9.
5.3.13.25 Wait 1 minute. 5.3.13.26 Close RC-V-16.CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 18 of 34 5.3.13.27 Close RC-V-9. 5.3.13.28 WHEN gas stripping complete, THEN flush the LSP as follows: a. Open RC-V-8.2.
5.3.13.24 Open RC-V-16.
5.3.13.25 Wait 1 minute.
5.3.13.26 Close RC-V-16.
CONTINUOUS USE
 
WISCONSIN PUBLIC SERVICE CORP.                   No.       EPIP-RET-03C             IRev. P Title       Post Accident Operation of the High Kewaunee Nuclear Power Plant                             Radiation Sample Room Emergency Plan Implementing Procedure             Date       JAN 1 5 2002             Page 18 of 34 5.3.13.27 Close RC-V-9.
5.3.13.28 WHEN gas stripping complete, THEN flush the LSP as follows:
: a. Open RC-V-8.2.
: b. Open RC-V-8.1.
: b. Open RC-V-8.1.
: c. Open RC-V-4. d. Turn RC-V- 11 counterclockwise to VACUUM/SAMPLE position (9 o'clock).
: c. Open RC-V-4.
5.3.13.29 Turn RC-DV-2 to GAS SAMPLE position (12 o'clock).
: d. Turn RC-V- 11 counterclockwise to VACUUM/SAMPLE position (9 o'clock).
To obtain the diluted gas sample. 5.3.13.30 Observe pressure gauge RC-G-2.2 stabilized at about 1 psi. 5.3.13.31 Turn RC-DV-2 to TO GC position (3 o'clock).
5.3.13.29 Turn RC-DV-2 to GAS SAMPLE position (12 o'clock). To obtain the diluted gas sample.
5.3.13.30 Observe pressure gauge RC-G-2.2 stabilized at about 1 psi.
5.3.13.31 Turn RC-DV-2 to TO GC position (3 o'clock).
5.3.13.32 Close RC-V-14.
5.3.13.32 Close RC-V-14.
5.3.13.33 Remove the diluted gas sample bottle from the LSP. 5.3.14 Place entire assembly in fume hood for later transport to multi-channel analyzer.
5.3.13.33 Remove the diluted gas sample bottle from the LSP.
5.3.15 At the CMP, operate the GC mini-computer to draw a vacuum on all 4 sample loops. 5.3.16 At the LSP, open RC-V-15 and allow the gas sample to transfer to the GC. 5.3.17 Operate the GC unit to obtain 4 samples for hydrogen determination.
5.3.14   Place entire assembly in fume hood for later transport to multi-channel analyzer.
By selective attenuation, starting with a high value, determine the hydrogen concentration.
5.3.15   At the CMP, operate the GC mini-computer to draw a vacuum on all 4 sample loops.
"* Cycle through the four loops. "* Stop at each loop at least 1 minute. Note Start attenuation selection with high values. "* Determine hydrogen concentration using selective attenuation.
5.3.16   At the LSP, open RC-V-15 and allow the gas sample to transfer to the GC.
"* Record information on the Reactor Coolant Analysis Log (routine logsheet).
5.3.17   Operate the GC unit to obtain 4 samples for hydrogen determination. By selective attenuation, starting with a high value, determine the hydrogen concentration.
CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 2002 Page 19 of 34 5.3.18 WHEN RCHL sample, THEN request Control Room Operator perform the following:  
            "* Cycle through the four loops.
"* Close RC-422. "* Close RC-423. 5.3.19 At the LSP perform the following:
            "* Stop at each loop at least 1 minute.
5.3.19.1 Close RC-V-4. 5.3.19.2 Close RC-V-2. 5.3.19.3 Close RC-V-8.1.
Note Start attenuationselection with high values.
5.3.19.4 Close RC-V-8.2.
            "* Determine hydrogen concentration using selective attenuation.
5.3.20 At the SAP perform the following:
            "* Record information on the Reactor Coolant Analysis Log (routine logsheet).
5.3.20.1 WHEN RCHL sample, THEN perform the following:  
CONTINUOUS USE
"* Close RC-423-1.
 
"* Close CC-314. 5.3.20.2 WHEN RHR sample, THEN perform the following:  
WISCONSIN PUBLIC SERVICE CORP.                 No.         EPIP-RET-03C             I Rev. P Title       Post Accident Operation of the High Kewaunee Nuclear Power Plant                           Radiation Sample Room Emergency Plan Implementing Procedure           Date         JAN 15 2002           Page 19 of 34 5.3.18   WHEN RCHL sample, THEN request Control Room Operator perform the following:
"* IF opened, THEN Close RHR-81A.
            "* Close RC-422.
"* IF opened, THEN close RHR-81B.
            "* Close RC-423.
"* Close CC-316. 5.3.20.3 Position RC-437-1 to VCT. 5.3.20.4 Position RC-437-2 to VCT. 5.3.21 At the LSP to flush the expansion vessel perform the following:
5.3.19   At the LSP perform the following:
5.3.21.1 Open RC-V-8.2.
5.3.19.1   Close RC-V-4.
5.3.21.2 Open RC-V-9. 5.3.21.3 Turn RC-V-11 to DI WATER position (6 o'clock).
5.3.19.2   Close RC-V-2.
5.3.21.4 Flush for at least 2 minutes.
5.3.19.3   Close RC-V-8.1.
5.3.21.5 Turn RC-V- 11 to ARGON position (3 o'clock).
5.3.19.4   Close RC-V-8.2.
5.3.21.6 Wait 2 minutes.
5.3.20   At the SAP perform the following:
CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 20 of 34 5.3.21.7 Turn RC-V-11 counterclockwise to CLOSE position (12 o'clock).
5.3.20.1   WHEN RCHL sample, THEN perform the following:
5.3.21.8 Close RC-V-9. 5.3.21.9 Close RC-V-8.2.
                "* Close RC-423-1.
5.3.22 To remove radioactive gases from the system perform the following:
                "* Close CC-314.
5.3.22.1 Open RC-V-10.
5.3.20.2   WHEN RHR sample, THEN perform the following:
5.3.22.2 Open RC-V-13.
                "* IF opened, THEN Close RHR-81A.
5.3.22.3 Open RC-V-15.
                "* IF opened, THEN close RHR-81B.
5.3.22.4 Turn RC-V- 11 to VACUUM/SAMPLE position (9 o'clock).
                "* Close CC-316.
5.3.22.5 Open RC-V-12.
5.3.20.3   Position RC-437-1 to VCT.
5.3.22.6 Evacuate system for at least 1 minute. 5.3.22.7 Close RC-V-12.
5.3.20.4   Position RC-437-2 to VCT.
5.3.22.8 Turn RC-V-1 1 clockwise to CLOSE position (12 o'clock).
5.3.21   At the LSP to flush the expansion vessel perform the following:
5.3.22.9 Close RC-V-15.
5.3.21.1   Open RC-V-8.2.
5.3.21.2   Open RC-V-9.
5.3.21.3   Turn RC-V-11 to DI WATER position (6 o'clock).
5.3.21.4   Flush for at least 2 minutes.
5.3.21.5   Turn RC-V- 11 to ARGON position (3 o'clock).
5.3.21.6   Wait 2 minutes.
CONTINUOUS USE
 
WISCONSIN PUBLIC SERVICE CORP.                   No.       EPIP-RET-03C                 Rev. P Title     Post Accident Operation of the High Kewaunee Nuclear Power Plant                             Radiation Sample Room Emergency Plan Implementing Procedure             Date       JAN 1 5 2002             Page 20 of 34 5.3.21.7   Turn RC-V-11 counterclockwise to CLOSE position (12 o'clock).
5.3.21.8   Close RC-V-9.
5.3.21.9   Close RC-V-8.2.
5.3.22   To remove radioactive gases from the system perform the following:
5.3.22.1   Open RC-V-10.
5.3.22.2   Open RC-V-13.
5.3.22.3   Open RC-V-15.
5.3.22.4   Turn RC-V- 11 to VACUUM/SAMPLE position (9 o'clock).
5.3.22.5   Open RC-V-12.
5.3.22.6   Evacuate system for at least 1 minute.
5.3.22.7   Close RC-V-12.
5.3.22.8   Turn RC-V-1 1 clockwise to CLOSE position (12 o'clock).
5.3.22.9   Close RC-V-15.
5.3.22.10 Close RC-V-13.
5.3.22.10 Close RC-V-13.
5.3.22.11 Close RC-V-10.
5.3.22.11   Close RC-V-10.
5.3.23 Transport diluted gas bottle to multi-channel analyzer for analysis in accordance with RCC-063, RCS Gaseous Activity." 5.4 Undiluted Liquid Grab Sample 5.4.1 In the HRSR check the following equipment available and operational:  
5.3.23   Transport diluted gas bottle to multi-channel analyzer for analysis in accordance with RCC-063, RCS Gaseous Activity."
"* Sample cask available with undiluted piston installed  
5.4     Undiluted Liquid Grab Sample 5.4.1     In the HRSR check the following equipment available and operational:
"* Two -15 ml undiluted sample bottle "* New undiluted liquid flush bottle "* Undiluted liquid sample flush bottle handling tool "* Lights ON in undiluted sample port of LSP "* Reach Rod for remote valve operation CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 21 of 34 5.4.2 At the CASP perform the following:
              "* Sample cask available with undiluted piston installed
5.4.2.1 Verify ventilation is ON and mode control switches are in NORMAL position.
              "* Two - 15 ml undiluted sample bottle
5.4.2.2 Check High Vacuum Lights indicate NORMAL for the following:  
              "* New undiluted liquid flush bottle
"* LSP "* CAP "* CASP 5.4.3 Perform valve lineup per Attachment A, "High Radiation Sample Valve Lineup Sheet." 5.4.4 Connect DI Water flush hoses to LSP. 5.4.5 Open DI Water supply valve to LSP. 5.4.6 Install undiluted sample bottle in sample cask. 5.4.7 Check cask for proper operation.
              "* Undiluted liquid sample flush bottle handling tool
5.4.8 Install the sample cask under the undiluted sample port. 5.4.9 Position the undiluted sample bottle up on the needles.
              "* Lights ON in undiluted sample port of LSP
5.4.10 WHEN performing an RCHL sample, THEN request Control Room Operator:
              "* Reach Rod for remote valve operation CONTINUOUS USE
9 Open RC-422. 0 Open RC-423. 5.4.11 At the SAP perform the following:
 
5.4.11.1 WHEN performing an RCHL sample, THEN perform the following:  
WISCONSIN PUBLIC SERVICE CORP.                   No.       EPIP-RET-03C             IRev. P Title     Post Accident Operation of the High Kewaunee Nuclear Power Plant                             Radiation Sample Room Emergency Plan Implementing Procedure             Date       JAN 1 5 2002           Page 21 of 34 5.4.2     At the CASP perform the following:
"* Open CC-314. "* Open RC-423-1.CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 2002 Page 22 of 34 5.4.11.2 WHEN performing a RHR sample, THEN perform the following:  
5.4.2.1     Verify ventilation is ON and mode control switches are in NORMAL position.
"* Open CC-316. "* WHEN sampling A RHR, THEN open RHR-81-A.
5.4.2.2     Check High Vacuum Lights indicate NORMAL for the following:
"* WHEN sampling B RHR, THEN open RHR-81-B.
                  "* LSP
5.4.11.3 Position RC-437-1 to DDT. 5.4.11.4 Position RC-437-2 to DDT. 5.4.12 At the LSP perform the following:
                  "* CAP
5.4.12.1 Open RC-V-3. 5.4.12.2 WHEN performing a RCHL sample, THEN open RC-V-1.2.
                  "* CASP 5.4.3     Perform valve lineup per Attachment A, "High Radiation Sample Valve Lineup Sheet."
5.4.12.3 WHEN performing a RHR sample, THEN open RC-V-1.1.
5.4.4     Connect DI Water flush hoses to LSP.
Note Purge time may be varied based on actual purge flow rate obtained.
5.4.5     Open DI Water supply valve to LSP.
5.4.12.4 Throttle RC-VREL-1 until flow indicator RC-FI-1 indicates 1,900 to 2,000 cc/min. "* WHEN RCHL sample, THEN purge at least 12 minutes.
5.4.6     Install undiluted sample bottle in sample cask.
"* WHEN RHR sample, THEN purge at least 25 minutes 5.4.12.5 IF unable to attain desired purge flow rate, THEN adjust purge time accordingly.
5.4.7     Check cask for proper operation.
5.4.12.6 WHEN purge is complete, THEN perform the following:
5.4.8     Install the sample cask under the undiluted sample port.
: a. Close RC-V-3. b. Open RC-V-2. c. Open RC-V-7. Note Purge time may be varied based on actual purge flow rate obtained.
5.4.9     Position the undiluted sample bottle up on the needles.
5.4.12.7 Throttle RC-VREL-2 until flow indicator RC-FI-2 indicates 180 to 220 cc/min. 5.4.12.8 Purge for at least 3 minutes.
5.4.10   WHEN performing an RCHL sample, THEN request Control Room Operator:
5.4.12.9 IF unable to attain desired purge flow rate, THEN adjust purge time accordingly.
9   Open RC-422.
CONTINUOUS USE 5.4.12.10 Turn RC-V-19 to SAMPLE position (3 o'clock).
0   Open RC-423.
5.4.12.11 Observe flow into undiluted sample bottle. 5.4.12.12 WHEN undiluted sample bottle is full, THEN position RC-V-19 to BYPASS position (12 o'clock).
5.4.11     At the SAP perform the following:
5.4.13 Remove undiluted sample bottle from the needles.
5.4.11.1     WHEN performing an RCHL sample, THEN perform the following:
5.4.14 Store the undiluted sample.  "* Return undiluted sample to cask. "* Close lead top. "* Install auxiliary shield. "* Remove cask from HRSR. 5.4.15 IF RCHL sample, THEN close RC-V-1.2.
                  "* Open CC-314.
5.4.16 IF RHR sample, THEN close RC-V-1.1.
                  "* Open RC-423-1.
5.4.17 Open RC-V-4. 5.4.18 Place new undiluted sample bottle in special handling tool. 5.4.19 Position tool and bottle up on undiluted sample needles in LSP. 5.4.20 Turn RC-V-19 to SAMPLE position (3 o'clock).
CONTINUOUS USE
5.4.21 Flush for at least 3 minutes.
 
5.4.22 Turn RC-V-19 to BYPASS position (12 o'clock).
WISCONSIN PUBLIC SERVICE CORP.                   No.         EPIP-RET-03C             IRev. P Title       Post Accident Operation of the High Kewaunee Nuclear Power Plant                             Radiation Sample Room Emergency Plan Implementing Procedure             Date       JAN 15 2002             Page 22 of 34 5.4.11.2   WHEN performing a RHR sample, THEN perform the following:
5.4.23 Close RC-V-7. 5.4.24 Close RC-V-2. 5.4.25 Close RC-V-4. 5.4.26 Remove undiluted flush bottle and handling tool. 5.4.27 WHEN RCHL sample, THEN request Control Room Operator perform the following:  
                "* Open CC-316.
"* Close RC-422. "* Close RC-423. CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C IRev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 2002 1 Page 23 of 34 WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 24 of 34 5.4.28 At the SAP perform the following:
                "* WHEN sampling A RHR, THEN open RHR-81-A.
5.4.28.1 WHEN RCHL sample, THEN perform the following:  
                "* WHEN sampling B RHR, THEN open RHR-81-B.
"* Close RC-423-1.
5.4.11.3   Position RC-437-1 to DDT.
"* Close CC-314. 5.4.28.2 WHEN RHR sample, THEN perform the following:  
5.4.11.4   Position RC-437-2 to DDT.
"* IF opened, THEN Close RHR-81A.
5.4.12   At the LSP perform the following:
"* IF opened, THEN close RHR-81B.
5.4.12.1   Open RC-V-3.
"* Close CC-316. 5.4.28.3 Position RC-437-1 to VCT. 5.4.28.4 Position RC-437-2 to VCT. 5.4.29 WHEN off-site shipment of an undiluted sample is required, THEN contact a Chemistry Supervisor.
5.4.12.2   WHEN performing a RCHL sample, THEN open RC-V-1.2.
5.5 Containment Hydrogen (H2) Monitor IA & 1B Operation Procedure 5.5.1 WHEN sampling the Containment for hydrogen, THEN perform the following:
5.4.12.3   WHEN performing a RHR sample, THEN open RC-V-1.1.
5.5.1.1 At the CASP perform the following:
Note Purgetime may be varied based on actualpurgeflow rate obtained.
5.5.1.1.1 Verify ventilation is ON and mode control switches are in NORMAL position.
5.4.12.4   Throttle RC-VREL-1 until flow indicator RC-FI-1 indicates 1,900 to 2,000 cc/min.
5.5.1.1.2 Check High Vacuum Lights indicate NORMAL for the following:
                "* WHEN RCHL sample, THEN purge at least 12 minutes.
* LSP 9 CAP
                "* WHEN RHR sample, THEN purge at least 25 minutes 5.4.12.5   IF unable to attain desired purge flow rate, THEN adjust purge time accordingly.
* CASP 5.5.1.2 Verify remote panels are in standby and have had 6 hours warm-up time. 5.5.1.3 Verify heat tracing is energized and operational.
5.4.12.6   WHEN purge is complete, THEN perform the following:
CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C IRev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 25 of 34 Note Due to ALARA considerations, both containment air sample trains will be lined up to preclude additional valve lineups.
: a. Close RC-V-3.
5.5.1.4 Contact the Control Room and perform the following:
: b. Open RC-V-2.
5.5.1.4.1 Verify that Containment Dome Fans IA and lB are operating.
: c. Open RC-V-7.
5.5.1.4.2 Inform the Control Room that both containment air sample trains will be lined up for sampling.
Note Purge time may be variedbased on actualpurgeflow rate obtained.
5.5.1.4.3 Request the Control Room perform the following valve lineup: "* Close SA 7010A. "* Open LOCA 2A. "* Open LOCA 1OA. "* Open SA 7003A. "* Close SA7010B.
5.4.12.7   Throttle RC-VREL-2 until flow indicator RC-FI-2 indicates 180 to 220 cc/min.
"* Position LOCA 2B LOCAL/REMOTE to LOCAL. "* Open LOCA 2B. "* Open LOCA 10B. "* Position SA 7003B LOCAL/REMOTE to LOCAL. "* Open SA 7003B. Note Damage to the Hydrogen Analyzer will result if CASP is monitoring the same Train. 5.5.1.5 WHEN H 2 Monitor 1A is to be used, THEN open AS-1 OA. 5.5.1.6 WHEN H 2 Monitor 1B is to be used, THEN open AS- 11OB. 5.5.1.7 Inform the Control Room that the H 2 Monitors are going to be started so that they can monitor their indication.
5.4.12.8   Purge for at least 3 minutes.
5.5.1.8 Switch selected analyzer to ANALYZE.
5.4.12.9   IF unable to attain desired purge flow rate, THEN adjust purge time accordingly.
5.5.1.9 Switch selected analyzer to SAMPLE MODE. 5.5.1.10 Push the remote selector pushbutton to gain control at the remote panel. CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 26 of 34 5.5.1.11 Allow at least 10 minutes for sample purge time. Note The Containment Hydrogen Monitors read out remotely in the Control Room. 5.5.1.12 IF desired, THEN record Hydrogen Monitor indication on the Reactor Coolant Analysis Log (routine logsheet).
CONTINUOUS USE
5.5.2 WHEN all Containment hydrogen sampling is complete, THEN perform the following:
 
5.5.2.1 Switch selected H 2 Monitor to STANDBY.
WISCONSIN PUBLIC SERVICE CORP.                   No.       EPIP-RET-03C            IRev. P Title      Post Accident Operation of the High Kewaunee Nuclear Power Plant                            Radiation Sample Room Emergency Plan Implementing Procedure              Date        JAN 15 2002        1  Page 23 of 34 5.4.12.10 Turn RC-V-19 to SAMPLE position (3 o'clock).
5.5.2.2 WHEN H 2 Monitor 1A was used, THEN close AS- 11OA. 5.5.2.3 WHEN H 2 Monitor lB was used, THEN close AS- I10B. 5.5.2.4 Request the Control Room perform the following valve lineup: "* Close LOCA 2A. "* Close LOCA 10A. "* Close SA 7003A. "* Open SA 7010A. "* Close LOCA 2B. "* Position LOCA 2B LOCAL/REMOTE to REMOTE. "* Close LOCA lOB. "* Close SA 7003B. "* Open SA 7010B. "* Position SA 7010B LOCAL/REMOTE to REMOTE.CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Paqe 27 of 34 5.6 Flush of Liquid Sample Lines Note The purpose of this section is to reduce radiation levels behind the liquid sample panel during post accident conditions.
5.4.12.11 Observe flow into undiluted sample bottle.
5.6.1 At the SAP perform the following:
5.4.12.12 WHEN undiluted sample bottle is full, THEN position RC-V-19 to BYPASS position (12 o'clock).
5.6.1.1 Position RC-437-1 to DDT. 5.6.1.2 Position RC-437-2 to DDT. 5.6.1.3 Open FPC-51. 5.6.1.4 WHEN performing an RCHL flush, THEN perform the following:  
5.4.13      Remove undiluted sample bottle from the needles.
"* Open FPC-51-14.
5.4.14      Store the undiluted sample.
"* Open CC-314. "* Open RC-423-1.
              "* Return undiluted sample to cask.
5.6.1.5 WHEN performing a RHR flush, THEN perform the following:  
              "* Close lead top.
"* Open FPC-51-41.
              "* Install auxiliary shield.
"* Open CC-316. 5.6.2 At the LSP perform the following:
              "* Remove cask from HRSR.
5.6.2.1 WHEN performing a RCHL flush, THEN open RC-V-1.2.
5.4.15    IF RCHL sample, THEN close RC-V-1.2.
5.6.2.2 WHEN performing a RHR flush, THEN open RC-V-1.1.
5.4.16    IF RHR sample, THEN close RC-V-1.1.
5.6.2.3 Open RC-V-2. 5.6.2.4 Open RC-V-7. Note Flush time may be varied based on actualflush flow rate obtained.
5.4.17     Open RC-V-4.
5.6.2.5 Throttle RC-VREL-2 until flow indicator RC-FI-2 indicates 180 to 220 cc/min. 5.6.2.6 Flush at least 45 minutes.
5.4.18     Place new undiluted sample bottle in special handling tool.
5.6.2.7 IF unable to attain desired flush flow rate, THEN adjust flush time accordingly.
5.4.19     Position tool and bottle up on undiluted sample needles in LSP.
CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 28 of 34 5.6.3 At the SAP perform the following:
5.4.20     Turn RC-V-19 to SAMPLE position (3 o'clock).
5.6.3.1 Close FPC-51. 5.6.3.2 WHEN RCHL line flush, THEN perform the following:
5.4.21     Flush for at least 3 minutes.
5.4.22     Turn RC-V-19 to BYPASS position (12 o'clock).
5.4.23     Close RC-V-7.
5.4.24     Close RC-V-2.
5.4.25     Close RC-V-4.
5.4.26     Remove undiluted flush bottle and handling tool.
5.4.27     WHEN RCHL sample, THEN request Control Room Operator perform the following:
            "* Close RC-422.
            "* Close RC-423.
CONTINUOUS USE
 
WISCONSIN PUBLIC SERVICE CORP.                     No.       EPIP-RET-03C             IRev. P Title     Post Accident Operation of the High Kewaunee Nuclear Power Plant                             Radiation Sample Room Emergency Plan Implementing Procedure               Date       JAN 1 5 2002           Page 24 of 34 5.4.28      At the SAP perform the following:
5.4.28.1   WHEN RCHL sample, THEN perform the following:
                    "* Close RC-423-1.
                    "* Close CC-314.
5.4.28.2   WHEN RHR sample, THEN perform the following:
                    "* IF opened, THEN Close RHR-81A.
                    "* IF opened, THEN close RHR-81B.
                    "* Close CC-316.
5.4.28.3   Position RC-437-1 to VCT.
5.4.28.4   Position RC-437-2 to VCT.
5.4.29     WHEN off-site shipment of an undiluted sample is required, THEN contact a Chemistry Supervisor.
5.5     Containment Hydrogen (H2) Monitor IA & 1B Operation Procedure 5.5.1       WHEN sampling the Containment for hydrogen, THEN perform the following:
5.5.1.1     At the CASP perform the following:
5.5.1.1.1   Verify ventilation is ON and mode control switches are in NORMAL position.
5.5.1.1.2   Check High Vacuum Lights indicate NORMAL for the following:
* LSP 9 CAP
* CASP 5.5.1.2     Verify remote panels are in standby and have had 6 hours warm-up time.
5.5.1.3     Verify heat tracing is energized and operational.
CONTINUOUS USE
 
WISCONSIN PUBLIC SERVICE CORP.                   No.       EPIP-RET-03C             IRev. P Title     Post Accident Operation of the High Kewaunee Nuclear Power Plant                             Radiation Sample Room Emergency Plan Implementing Procedure             Date     JAN 1 5 2002             Page 25 of 34 Note Due to ALARA considerations,both containment airsample trains will be lined up to preclude additionalvalve lineups.
5.5.1.4     Contact the Control Room and perform the following:
5.5.1.4.1     Verify that Containment Dome Fans IA and lB are operating.
5.5.1.4.2     Inform the Control Room that both containment air sample trains will be lined up for sampling.
5.5.1.4.3     Request the Control Room perform the following valve lineup:
                        "* Close SA 7010A.
                        "* Open LOCA 2A.
                        "* Open LOCA 1OA.
                        "* Open SA 7003A.
                        "* Close SA7010B.
                        "* Position LOCA 2B LOCAL/REMOTE to LOCAL.
                        "* Open LOCA 2B.
                        "* Open LOCA 10B.
                        "* Position SA 7003B LOCAL/REMOTE to LOCAL.
                        "* Open SA 7003B.
Note Damage to the Hydrogen Analyzer will result if CASP is monitoring the same Train.
5.5.1.5     WHEN H2 Monitor 1A is to be used, THEN open AS-1 OA.
5.5.1.6     WHEN H2 Monitor 1B is to be used, THEN open AS- 11OB.
5.5.1.7     Inform the Control Room that the H2 Monitors are going to be started so that they can monitor their indication.
5.5.1.8     Switch selected analyzer to ANALYZE.
5.5.1.9     Switch selected analyzer to SAMPLE MODE.
5.5.1.10   Push the remote selector pushbutton to gain control at the remote panel.
CONTINUOUS USE
 
WISCONSIN PUBLIC SERVICE CORP.                 No.       EPIP-RET-03C             IRev. P Title     Post Accident Operation of the High Kewaunee Nuclear Power Plant                           Radiation Sample Room Emergency Plan Implementing Procedure           Date       JAN 1 5 2002           Page 26 of 34 5.5.1.11 Allow at least 10 minutes for sample purge time.
Note The ContainmentHydrogen Monitors read out remotely in the Control Room.
5.5.1.12 IF desired, THEN record Hydrogen Monitor indication on the Reactor Coolant Analysis Log (routine logsheet).
5.5.2     WHEN all Containment hydrogen sampling is complete, THEN perform the following:
5.5.2.1   Switch selected H2 Monitor to STANDBY.
5.5.2.2   WHEN H2 Monitor 1A was used, THEN close AS- 11OA.
5.5.2.3   WHEN H2 Monitor lB was used, THEN close AS- I10B.
5.5.2.4   Request the Control Room perform the following valve lineup:
                "* Close LOCA 2A.
                "* Close LOCA 10A.
                "* Close SA 7003A.
                "* Open SA 7010A.
                "* Close LOCA 2B.
                "* Position LOCA 2B LOCAL/REMOTE to REMOTE.
                "* Close LOCA lOB.
                "* Close SA 7003B.
                "* Open SA 7010B.
                "* Position SA 7010B LOCAL/REMOTE to REMOTE.
CONTINUOUS USE
 
WISCONSIN PUBLIC SERVICE CORP.                       No.         EPIP-RET-03C             IRev. P Title       Post Accident Operation of the High Kewaunee Nuclear Power Plant                                 Radiation Sample Room Emergency Plan Implementing Procedure                 Date       JAN 1 5 2002             Paqe 27 of 34 5.6     Flush of Liquid Sample Lines Note The purpose of this section is to reduce radiationlevels behind the liquid sample panel duringpost accident conditions.
5.6.1     At the SAP perform the following:
5.6.1.1     Position RC-437-1 to DDT.
5.6.1.2     Position RC-437-2 to DDT.
5.6.1.3     Open FPC-51.
5.6.1.4     WHEN performing an RCHL flush, THEN perform the following:
                    "* Open FPC-51-14.
                    "* Open CC-314.
                    "* Open RC-423-1.
5.6.1.5     WHEN performing a RHR flush, THEN perform the following:
                    "* Open FPC-51-41.
                    "* Open CC-316.
5.6.2       At the LSP perform the following:
5.6.2.1     WHEN performing a RCHL flush, THEN open RC-V-1.2.
5.6.2.2     WHEN performing a RHR flush, THEN open RC-V-1.1.
5.6.2.3     Open RC-V-2.
5.6.2.4     Open RC-V-7.
Note Flush time may be varied based on actualflushflow rate obtained.
5.6.2.5     Throttle RC-VREL-2 until flow indicator RC-FI-2 indicates 180 to 220 cc/min.
5.6.2.6     Flush at least 45 minutes.
5.6.2.7     IF unable to attain desired flush flow rate, THEN adjust flush time accordingly.
CONTINUOUS USE
 
WISCONSIN PUBLIC SERVICE CORP.                 No.       EPIP-RET-03C               I Rev. P Title     Post Accident Operation of the High Kewaunee Nuclear Power Plant                           Radiation Sample Room Emergency Plan Implementing Procedure           Date       JAN 1 5 2002             Page 28 of 34 5.6.3     At the SAP perform the following:
5.6.3.1     Close FPC-51.
5.6.3.2     WHEN RCHL line flush, THEN perform the following:
: a. Close FPC-51-14.
: a. Close FPC-51-14.
: b. Close RC-423-1.
: b. Close RC-423-1.
: c. Close CC-314. 5.6.3.3 WHEN RHR line flush, THEN perform the following:
: c. Close CC-314.
5.6.3.3     WHEN RHR line flush, THEN perform the following:
: a. Close FCP-51-41.
: a. Close FCP-51-41.
: b. Close CC-316. c. Close RC-V-1.l.
: b. Close CC-316.
5.6.4 At the LSP perform the following:
: c. Close RC-V-1.l.
5.6.4.1 WHEN RCHL line flush, THEN close RC-V-1.2.
5.6.4      At the LSP perform the following:
5.6.4.2 WHEN RHR line flush, THEN close RC-V-.1.l.
5.6.4.1    WHEN RCHL line flush, THEN close RC-V-1.2.
5.6.4.3 Close RC-V-2. 5.6.4.4 Close RC-V-7. 5.6.4.5 Close RC-VREL-2, then open RC-VREL-2 approximately 1/2/2 turn. 5.6.4.6 Continue flush by opening RC-V-4. 5.6.4.7 Open RC-V-3. 5.6.4.8 Throttle RC-VREL-1 until positive indication of flow on RC-FI-1.
5.
Note Additional time may be required if radiation levels behind LSP have NOT stabilized.
5.6.4.9 Flush at least 15 minutes.
5.6.4.10 Close RC-V-3. 5.6.4.11 Close RC-V-4.
* Proper personnel dosimetry
* Proper personnel dosimetry
* Proper radiation detection instrumentation
* Proper radiation detection instrumentation
* Personnel for continuous HP coverage during sampling
* Personnel for continuous HP coverage during sampling
* Remote area monitor readings in area of High Radiation Sample Room (HRSR) 3.3 Utilize on-site communications with the RPD as necessary during sampling.
* Remote area monitor readings in area of High Radiation Sample Room (HRSR) 3.3     Utilize on-site communications with the RPD as necessary during sampling.
3.4 Any sample drawn from the post accident containment atmosphere should be assumed to contain specific activity of the following magnitude:
3.4     Any sample drawn from the post accident containment atmosphere should be assumed to contain specific activity of the following magnitude:
* Gas 5.0 Millicuries/cc
* Gas                   5.0               Millicuries/cc
* Iodine 0.2 Millicuries/cc 4.0 Initial Conditions 4.1 The site has declared an Alert, Site Emergency, General Emergency, or the Shift Manager or Emergency Director has implemented the use of this procedure.
* Iodine                 0.2               Millicuries/cc 4.0       Initial Conditions 4.1     The site has declared an Alert, Site Emergency, General Emergency, or the Shift Manager or Emergency Director has implemented the use of this procedure.
n.Nnucdoc\procedures\draft\epip\eret03d.doc-BilI HollingsworthUChristine Simmons-Darryl Holschbach 5.0 Procedure 5.1 Obtain all necessary equipment prior to beginning to sample the Containment atmosphere.
n.Nnucdoc\procedures\draft\epip\eret03d.doc-BilI HollingsworthUChristine Simmons-Darryl Holschbach
This equipment includes:
 
5.0     Procedure atmosphere.
5.1     Obtain all necessary equipment prior to beginning to sample the Containment This equipment includes:
* Operable CASP System with Inline Sample Chamber (ISC) Cart in Sample Station #1
* Operable CASP System with Inline Sample Chamber (ISC) Cart in Sample Station #1
* 5.0 microliter gas syringe (2)
* 5.0 microliter gas syringe (2)
Line 640: Line 812:
* Portable shields for transporting syringes
* Portable shields for transporting syringes
* Marinelli beaker (give to HIP to be counted prior to sample injection)
* Marinelli beaker (give to HIP to be counted prior to sample injection)
* Specially adapted 1 liter poly-bottle (for Gross Gas analysis) 5.2 WHEN preparing for CASP operation, THEN perform the following:
* Specially adapted 1 liter poly-bottle (for Gross Gas analysis) 5.2     WHEN preparing for CASP operation, THEN perform the following:
5.2.1 Proceed to HRSR per HP/RPD recommendations.
5.2.1     Proceed to HRSR per HP/RPD recommendations.
5.2.2 Determine radiation levels in HRSR and in maintenance area behind panels, if access is required.
if access is 5.2.2     Determine radiation levels in HRSR and in maintenance area behind panels, required.
5.2.3 Verify that heat tracing is ON. 5.2.4 Verify ventilation is ON and in NORMAL position and high vacuum lights indicate NORMAL for the Liquid Sample Panel (LSP), Chemical Analysis Panel (CAP), and CASP. 5.2.5 Verify that instrument air supply is available at >_ 70 psi. 5.2.6 Verify that CASP and CASP control panels are energized and operational.
5.2.3     Verify that heat tracing is ON.
5.2.7 Verify valve lineup per Attachment A, "Containment Air Sample Valve Lineup Sheet." CONTINUOUS USE Note The sample cart may be checked to verify it is properly locked in place by carefully pulling.
lights indicate 5.2.4     Verify ventilation is ON and in NORMAL position and high vacuum (CAP), and NORMAL for the Liquid Sample Panel (LSP), Chemical Analysis Panel CASP.
5.2.8 Verify the ISC in the #1 position is locked in place. Note Only Sample Station 1 shall be used for Iodine Analysis.
5.2.5     Verify that instrument air supply is available at >_70 psi.
Due to ALARA considerations, if available, both containment air sample trains should be aligned.
5.2.6     Verify that CASP and CASP control panels are energized and operational.
5.2.9 Contact the Control Room and verify Dome Fans 1A and lB are operational.
Sheet."
5.2.10 Request Operations perform the following valve lineup at the Post-LOCA Hydrogen Control Panel: "* Open LOCA 2A. "* Open LOCA 1OA. "* Open SA 7003A. "* Position LOCA 2B (Local/Remote) to LOCAL. "* Position SA 7003B (Local/Remote) to LOCAL. "* Open LOCA 2B. "* Open LOCA 1OB. "* Open SA 7003B. 5.2.11 Verify that one of the following conditions are in effect AND select a Sample Loop (A or B): a. The hydrogen monitor is NOT in operation, OR b. The sample loop selected is opposite that being used by H 2 monitor.
5.2.7     Verify valve lineup per Attachment A, "Containment Air Sample Valve Lineup CONTINUOUS USE
5.2.12 WHEN using Containment Air Sample Train 1A, THEN open AS 11A. 5.2.13 WHEN using Containment Air Sample Train IB, THEN open ASI 10B. 5.2.14 Open SV-10. 5.2.15 Open SV-6. 5.2.16 Open SV-5. 5.2.17 Verify flow monitor on CASP is indicating flow. CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03D Rev. N Title Containment Air Sampling Analysis Using Kewaunee Nuclear Power Plant CASP Emergency Plan Implementing Procedure Date JAN 15 202 Pa 4 5.2.18 Wait at least 2 minutes.
 
5.2.19 Open AV-1/SV 1.2. 5.2.20 Close SV-5. 5.2.21 Open AV-2. 5.2.22 Wait at least 3 minutes.
Note The sample cart may be checked to verify it is properly locked in place by carefullypulling.
5.2.23 Align the ISC Cart as follows: 5.2.23.1 Open V-4, Cart Inlet Valve. 5.2.23.2 Open V-6, Outlet Valve. 5.2.23.3 Close V-5, Bypass Valve. 5.2.23.4 Verify CASP flow monitor is indicating flow. 5.3 WHEN collecting a Containment Air sample, THEN perform the following:
5.2.8   Verify the ISC in the #1 position is locked in place.
5.3.1 Close SV-6. 5.3.2 Verify flow monitor on CASP indicates NO flow. Note An appropriate period for flow monitor pressure equalization is one minute. 5.3.3 Allow the flow monitor to equalize pressure for at least 1 minute. 5.3.4 WHEN pressure equalization period is complete, THEN obtain Containment atmosphere samples as follows: 5.3.4.1 Draw the following samples from the ISC. a. Two 5 microliter samples b. IF using the Baseline 1010A Gas Chromatograph, THEN obtain 2 -1.0 cc syringe samples.
Note Only Sample Station 1 shall be usedfor Iodine Analysis.
: c. IF using the SRI 8610 Gas Chromatograph, THEN obtain 1 -2.0 cc syringe sample.CONTINUOUS USE VlA ,ilq/ilft l r , I.RI,. ir"* ~rVi..a .i vvRN. ..........  
be Due to ALARA considerations,if available, both containment airsample trainsshould aligned.
...Re. N Title Containment Air Sampling Analysis Using Kewaunee Nuclear Power Plant CASP Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 5 of 10 5.3.4.2 IF the radiological condition of the syringes are NOT satisfactory, THEN perform the following:
5.2.9   Contact the Control Room and verify Dome Fans 1A and lB are operational.
5.3.4.2.1 Lock the tips. 5.3.4.2.2 Insert the needle of each syringe in a rubber stopper to prevent damage. 5.3.4.2.3 Place the syringes in a portable shield for transport.
5.2.10 Request Operations perform the following valve lineup at the Post-LOCA Hydrogen Control Panel:
5.3.5 Use the predetermined route to minimize personnel exposure while transporting the shielded syringes or samples for analysis.
        "* Open LOCA 2A.
5.4 WHEN shutting down and cleaning out the system, THEN perform the following:
        "* Open LOCA 1OA.
5.4.1 Close AS 11 OA OR AS 11 B, as appropriate.
        "* Open SA 7003A.
5.4.2 Open SV-6 and evacuate the ISC cart. 5.4.3 Wait at least 2 minutes.
        "* Position LOCA 2B (Local/Remote) to LOCAL.
5.4.4 Close V-4, Cart Inlet Valve. 5.4.5 Close V-6, Outlet Valve. 5.4.6 Open V-5, Bypass Valve. 5.4.7 Open AS 11OA OR AS 11GB, as appropriate.
        "* Position SA 7003B (Local/Remote) to LOCAL.
5.4.8 Close AV-2. 5.4.9 Verify flow monitor has flow. 5.4.10 Wait at least 2 minutes.
        "* Open LOCA 2B.
5.4.11 Open SV-5. 5.4.12 Close AV-1/SV1.2.
        "* Open LOCA 1OB.
5.4.13 Verify flow monitor has flow. 5.4.14 Wait at least 1 minute. 5.4.15 Close SV-10. 5.4.16 Close SV-6. 5.4.17 Close SV-5.CONTINUOUS USE I Rev. N WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03D I Rev. N Title Containment Air Sampling Analysis Using Kewaunee Nuclear Power Plant CASP Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 6 of 10 5.4.18 Close AS11 OA OR AS1 OB, as appropriate.
        "* Open SA 7003B.
5.4.19 Reset "Active/Inactive" indicator lights to INACTIVE.
5.2.11 Verify that one of the following conditions are in effect AND select a Sample Loop (A or B):
5.5 WHEN analyzing a sample for Iodine, THEN perform the following:
: a. The hydrogen monitor is NOT in operation, OR
5.5.1 Place a Silver Zeolite sample cartridge in a holder. 5.5.2 Attach a hose from the holder to a vacuum source in the HRSR Fume Hood. 5.5.3 Establish air flow through the filter cartridge.
: b. The sample loop selected is opposite that being used by H2 monitor.
5.5.4 Inject a 5.0 microliter gas sample upstream of the filter cartridge allowing the gas to flow through the Silver Zeolite cartridge.
5.2.12 WHEN using Containment Air Sample Train 1A, THEN open AS 11A.
5.5.5 Remove the Silver Zeolite cartridge from its holder and monitor it for radiation.  
5.2.13 WHEN using Containment Air Sample Train IB, THEN open ASI 10B.
-7 5.5.6 Transfer the Silver Zeolite cartridge to the Radiation Protection Group for counting.
5.2.14 Open SV-10.
Note Point Beach Nuclear Plant uses an identical geometry as Kewaunee for counting iodine samples.
5.2.15 Open SV-6.
5.5.7 IF the Count Room is NOT accessible OR the Multi-Channel Analyzer (MCA) is NOT operable, THEN the cartridge may be sent to Point Beach Nuclear Plant for analysis.
5.2.16   Open SV-5.
Note Further dilution may be necessary for counting.
5.2.17   Verify flow monitor on CASP is indicating flow.
5.6 WHEN analyzing a sample for Gross Gas activity, THEN perform the following:
CONTINUOUS USE
5.6.1 WHEN the Count Room is habitable AND the MCA is operable, THEN perform the following:
 
5.6.1.1 Inject a 5 microliter gas sample into a marinelli beaker that has been cleared for use by the Radiation Protection Group. 5.6.1.2 Return the sample to the Radiation Protection Group for counting.
WISCONSIN PUBLIC SERVICE CORP.                     No.         EPIP-RET-03D             Rev. N Title       Containment Air Sampling Analysis Using Kewaunee Nuclear Power Plant                             CASP Date       JAN 15 202             Pa   4 Emergency Plan Implementing Procedure 5.2.18     Wait at least 2 minutes.
5.6.2 IF the Count Room is NOT habitable OR the MCA is NOT operable, THEN perform the following:
5.2.19     Open AV-1/SV 1.2.
5.6.2.1 Inject a 5 microliter gas sample into the specially adapted 1.0 liter poly bottle. 5.6.2.2 Request Radiation Protection Group transfer the sample container to Point Beach Nuclear Plant for Gross Gas activity determination.
5.2.20     Close SV-5.
CONTINUOUS USE WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03D Rev. N Title Containment Air Sampling Analysis Using Kewaunee Nuclear Power Plant CASP Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 7 ofl1 5.7 WHEN analyzing a sample for Hydrogen and Oxygen, THEN perform the following:
5.2.21     Open AV-2.
5.7.1 Based on the gas chromatograph to be used, refer to the appropriate chemistry procedure for operating instructions as follows: RCC-080, "Gas Chromatograph, Baseline 1010A " Baseline 101OA Gas Operation Using a Chart Recorder" Chromatograph RCC-080D, "Operation of the Baseline 1010A Gas Chromatograph Using Computer Software" " SRI 8610 Gas Chromatograph RCC-080C, "Operation of the SRI 8610 Gas Chromatograph" 5.7.2 Verify that the gas chromatograph is: "* Turned on "* Operating properly "* Correctly calibrated 5.7.3 WHEN the gas chromatograph is verified operable, THEN perform the following:
5.2.22     Wait at least 3 minutes.
5.7.3.1 WHEN injecting the sample into the Baseline 1010A gas chromatograph, THEN inject the 1.0 cc gas sample into the gas partitioner and await results.
5.2.23     Align the ISC Cart as follows:
5.7.3.2 WHEN injecting the sample into the SRI 8610 gas chromatograph, THEN inject the 2 cc gas sample into the gas partitioner and await results.
5.2.23.1   Open V-4, Cart Inlet Valve.
5.7.4 Report all results obtained to the RPD.CONTINUOUS USE 5.8 WHEN the Containment Air sampling lineup is to be secured, THEN request Operations perform the following at the Post-LOCA Hydrogen Control Panel:
5.2.23.2   Open V-6, Outlet Valve.
5.2.23.3   Close V-5, Bypass Valve.
5.2.23.4   Verify CASP flow monitor is indicating flow.
5.3     WHEN collecting a Containment Air sample, THEN perform the following:
5.3.1     Close SV-6.
5.3.2     Verify flow monitor on CASP indicates NO flow.
Note An appropriateperiodforflow monitorpressure equalization is one minute.
5.3.3       Allow the flow monitor to equalize pressure for at least 1 minute.
5.3.4       WHEN pressure equalization period is complete, THEN obtain Containment atmosphere samples as follows:
5.3.4.1     Draw the following samples from the ISC.
: a. Two 5 microliter samples
: b. IF using the Baseline 1010A Gas Chromatograph, THEN obtain 2 - 1.0 cc syringe samples.
: c. IF using the SRI 8610 Gas Chromatograph, THEN obtain 1 - 2.0 cc syringe sample.
CONTINUOUS USE
 
I Rev. N VlA ,ilq/ilft *,,.CI11 lr , I.RI,. ir"*~rVi..a .i   vvRN. ..........                 ...                   Re. N Title     Containment Air Sampling Analysis Using Kewaunee Nuclear Power Plant                                               CASP Emergency Plan Implementing Procedure                                   Date     JAN 1 5 2002           Page 5 of 10 5.3.4.2             IF the radiological condition of the syringes are NOT satisfactory, THEN perform the following:
5.3.4.2.1             Lock the tips.
5.3.4.2.2             Insert the needle of each syringe in a rubber stopper to prevent damage.
5.3.4.2.3             Place the syringes in a portable shield for transport.
5.3.5           Use the predetermined route to minimize personnel exposure while transporting the shielded syringes or samples for analysis.
5.4       WHEN shutting down and cleaning out the system, THEN perform the following:
5.4.1           Close AS 11 OA OR AS 11 B, as appropriate.
5.4.2           Open SV-6 and evacuate the ISC cart.
5.4.3           Wait at least 2 minutes.
5.4.4           Close V-4, Cart Inlet Valve.
5.4.5           Close V-6, Outlet Valve.
5.4.6           Open V-5, Bypass Valve.
5.4.7           Open AS 11OA OR AS 11GB, as appropriate.
5.4.8           Close AV-2.
5.4.9           Verify flow monitor has flow.
5.4.10         Wait at least 2 minutes.
5.4.11         Open SV-5.
5.4.12         Close AV-1/SV1.2.
5.4.13         Verify flow monitor has flow.
5.4.14         Wait at least 1 minute.
5.4.15         Close SV-10.
5.4.16         Close SV-6.
5.4.17         Close SV-5.
CONTINUOUS USE
 
WISCONSIN PUBLIC SERVICE CORP.                     No.         EPIP-RET-03D               IRev. N Title       Containment Air Sampling Analysis Using Kewaunee Nuclear Power Plant                                 CASP Emergency Plan Implementing Procedure                 Date       JAN 1 5 2002               Page 6 of 10 5.4.18     Close AS11 OA OR AS1 OB, as appropriate.
5.4.19     Reset "Active/Inactive" indicator lights to INACTIVE.
5.5     WHEN analyzing a sample for Iodine, THEN perform the following:
5.5.1     Place a Silver Zeolite sample cartridge in a holder.
5.5.2     Attach a hose from the holder to a vacuum source in the HRSR Fume Hood.
5.5.3     Establish air flow through the filter cartridge.
5.5.4     Inject a 5.0 microliter gas sample upstream of the filter cartridge allowing the gas to flow through the Silver Zeolite cartridge.
5.5.5     Remove the Silver Zeolite cartridge from its holder and monitor it for radiation.       -7 5.5.6       Transfer the Silver Zeolite cartridge to the Radiation Protection Group for counting.
Note PointBeach NuclearPlant uses an identicalgeometry as Kewauneefor counting iodine samples.
5.5.7       IF the Count Room is NOT accessible OR the Multi-Channel Analyzer (MCA) is NOT operable, THEN the cartridge may be sent to Point Beach Nuclear Plant for analysis.
Note Furtherdilution may be necessaryfor counting.
5.6     WHEN analyzing a sample for Gross Gas activity, THEN perform the following:
5.6.1       WHEN the Count Room is habitable AND the MCA is operable, THEN perform the following:
5.6.1.1     Inject a 5 microliter gas sample into a marinelli beaker that has been cleared for use by the Radiation Protection Group.
5.6.1.2     Return the sample to the Radiation Protection Group for counting.
5.6.2       IF the Count Room is NOT habitable OR the MCA is NOT operable, THEN perform the following:
5.6.2.1     Inject a 5 microliter gas sample into the specially adapted 1.0 liter poly bottle.
5.6.2.2     Request Radiation Protection Group transfer the sample container to Point Beach Nuclear Plant for Gross Gas activity determination.
CONTINUOUS USE
 
WISCONSIN PUBLIC SERVICE CORP.                     No.       EPIP-RET-03D                 Rev. N Title       Containment Air Sampling     Analysis Using Kewaunee Nuclear Power Plant                               CASP Emergency Plan Implementing Procedure               Date       JAN 1 5 2002                 Page 7 ofl1 5.7     WHEN analyzing a sample for Hydrogen and Oxygen, THEN perform the following:
5.7.1     Based on the gas chromatograph to be used, refer to the appropriate chemistry procedure for operating instructions as follows:
RCC-080, "Gas Chromatograph, Baseline 1010A
                " Baseline 101OA Gas                 Operation Using a Chart Recorder" Chromatograph                     RCC-080D, "Operation of the Baseline 1010A Gas Chromatograph Using Computer Software"
                " SRI 8610 Gas Chromatograph RCC-080C, "Operation of the SRI 8610 Gas Chromatograph" 5.7.2       Verify that the gas chromatograph is:
                "* Turned on
                "* Operating properly
                "* Correctly calibrated 5.7.3       WHEN the gas chromatograph is verified operable, THEN perform the following:
5.7.3.1     WHEN injecting the sample into the Baseline 1010A gas chromatograph, THEN inject the 1.0 cc gas sample into the gas partitioner and await results.
5.7.3.2     WHEN injecting the sample into the SRI 8610 gas chromatograph, THEN inject the 2 cc gas sample into the gas partitioner and await results.
5.7.4     Report all results obtained to the RPD.
CONTINUOUS USE
 
5.8     WHEN the Containment Air sampling lineup is to be secured, THEN request Operations perform the following at the Post-LOCA Hydrogen Control Panel:
* Close LOCA 2A.
* Close LOCA 2A.
* Close LOCA 1OA.
* Close LOCA 1OA.
Line 690: Line 935:
* Close SA 7003B.
* Close SA 7003B.
* Position LOCA 2B (Local/Remote) to REMOTE.
* Position LOCA 2B (Local/Remote) to REMOTE.
* Position SA 7003B (Local/Remote) to REMOTE. 6.0 Final Conditions 6.1 This procedure is closed out when the 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 Sentry HRSS Operating and Maintenance Manual 7.2 EPIP-AD-1 1, Emergency Radiation Controls 7.3 RCC-080, Gas Chromatograph, Baseline 1010A Operation Using a Chart Recorder 7.4 RCC-080C, Operation of the SRI 8610 Gas Chromatograph 7.5 RCC-080D, Operation of the Baseline 1010A Gas Chromatograph Using Computer Software 7.6 TS 6.1 l.b.2 CONTINUOUS USE 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.
* Position SA 7003B (Local/Remote) to REMOTE.
These records shall be maintained according to the KNPP Records Management Program.
6.0     Final Conditions 6.1     This procedure is closed out when the Plant Emergency has been Terminated or Recovery EPIPs.
8.1.1 QA Records None 8.1.2 Non-QA Records None CONTINUOUS USE CONTAINMENT AIR SAMPLE VALVE LINEUP SHEET CASP CONTROL PANEL A V -1 / SV -1.2 ..................
actions have begun and the Emergency Response Manager has suspended the use of 7.0     References 7.1     Sentry HRSS Operating and Maintenance Manual 7.2     EPIP-AD-1 1, Emergency Radiation Controls 7.3     RCC-080, Gas Chromatograph, Baseline 1010A Operation Using a Chart Recorder 7.4     RCC-080C, Operation of the SRI 8610 Gas Chromatograph Software 7.5     RCC-080D, Operation of the Baseline 1010A Gas Chromatograph Using Computer 7.6     TS 6.1 l.b.2 CONTINUOUS USE
Sm pl Pos #1 Inlet / Outlet ................................................................
 
Close SV -2.1 / SV -2.2 ................
8.0     Records and 8.1     The following QA records and non-QA records are identified in this directive/procedure be maintained are listed on the KNPP Records Retention Schedule. These records shall according to the KNPP Records Management Program.
Sm pl Pos #2 Inlet / Outlet ................................................................
8.1.1     QA Records None 8.1.2     Non-QA Records None CONTINUOUS USE
Close SV -3.1 / SV -3.2 ................
 
Sm pl Pos #3 Inlet / Outlet ................................................................
CONTAINMENT AIR SAMPLE VALVE LINEUP SHEET CASP CONTROL PANEL Close AV -1 / SV -1.2 .................. Smpl Pos #1 Inlet / Outlet ................................................................
Close SV -4.1 / SV -4.2 ................
Close SV -2.1 / SV -2.2 ................ Smpl Pos #2 Inlet / Outlet ................................................................
Sm pl Pos #4 Inlet / Outlet ................................................................
Close SV-3.1 / SV -3.2 ................ Sm pl Pos #3 Inlet / Outlet ................................................................
Close SV -5 .................................
Close SV -4.1 / SV -4.2 ................ Smpl Pos #4 Inlet / Outlet ................................................................
Sm pl Bypass ....................................................................................
Smpl Bypass .................................................................................... Close SV -5 .................................
Close SV -10 ...............................
Instr. Air to Eductor ......................................................................... Close SV -10 ...............................
Instr. Air to Eductor .........................................................................
Return to Containm ent .....................................................................       Close_
Close AV -2 .................................
AV -2 .................................
Return to Containm ent .....................................................................
Eductor Suction Isol ......................................................................... Close SV -6 .................................
Close_ SV -6 .................................
SAMPLE ACQUISITION PANEL Cont Air Sm pl A Isol ....................................................................... Close A S 110A ............................
Eductor Suction Isol .........................................................................
Cont Air Sm pl B Isol ....................................................................... Close AS110B ............................
Close SAMPLE ACQUISITION PANEL A S 110A ............................
INLINE SAMPLE CHAMBER (SF1)
Cont Air Sm pl A Isol .......................................................................
Sam ple Inlet V alve ........................................................................... Close V-4 ....................................
Close A S110B ............................
Sam ple Bypass V alve ......................................................................     Open V -5 ....................................
Cont Air Sm pl B Isol .......................................................................
Sam ple Outlet V alve ........................................................................ Close V -6 ....................................
Close INLINE SAMPLE CHAMBER (SF1) V -4 ....................................
                                                            .. .           .. .. .     .     .. . . . .                                             Don  a fl nf  1j Attachment A EPIP-RET-03D Rev. N                                                      Cate:JAN       bU =1                                             ~*J w  i  l*
Sam ple Inlet V alve ...........................................................................
CONTINUOUS USE S------.........-......-.---.----.---}}
Close V -5 ....................................
Sam ple Bypass V alve ......................................................................
Open V -6 ....................................
Sam ple Outlet V alve ........................................................................
Close Attachment A EPIP-RET-03D Rev. N........ .......Do n a f l n f 1j Cate: JAN U b =1 CONTINUOUS USE w i}}

Latest revision as of 04:28, 24 November 2019

Radiological Emergency Response Plan Implementing Procedures
ML020440560
Person / Time
Site: Kewaunee Dominion icon.png
Issue date: 01/16/2002
From: Webb T
Nuclear Management Co
To:
Document Control Desk, Office of Nuclear Security and Incident Response
References
-RFPFR, NRC-02-009
Download: ML020440560 (58)
v • d • e


Text

Kewaunee Nuclear Power Plant Point Beach Nuclear Plant N490 Highway 42 6610 Nuclear Road Kewaunee, WI 54216-9511 Two Rivers, WI 54241 920.755.2321 NM C Committed to Nuclear Excellence 920.388.2560 Kewaunee / Point Beach Nuclear Operated by Nuclear Management Company, LLC NRC-02-009 January 16, 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 Site Licensing Director SLC Attachment cc - US NRC Senior Resident Inspector, w/attach.

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

Electric Division, PSCW, w/o attach.

QA Vault, w/attach.

A Cos

DOCUMENT TRANSMITTAL KEWAUNEE NUCLEAR POWER PLANT DIANE FENCL - KNPP TRANSMITTAL DATE 01-15-2002 FROM:

"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 m (2 & 3)* Craig Weiss - Wisconsin Power & Light (11)*

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

T. Webb - State of Wisconsin (5)* Jim Holthaus - Nuclear Management Company (12)*

T. Webb - KNPP QA Vault w/NRC Letter (15)*

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

D. Mielke (35) H. Kocourek (13) T. Coutu (28)

J. Bennett (33) B. Bartelme (34)

D. Masarik (32) D. Seebart (24) by anyone. They are REFERENCE COPIES - CUSTODIAN (41-100) These copies are for general reference throughout the plant and corporate offices. The named individual is the responsible custodian for

-distributed the procedures and shall insure they are properly maintained.

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

STF (86, 87, 88) STF Library (43)

L. Welch - Fuel Services (65)

Resource Center - Training (82, 89, 94, 131)

NO Library - KNPP (59)

D. Schrank - Maintenance Off. (41)

C. Sternitzky - ATF-2 (44) D. Krall - CR/SS Office (51, 56)

-*.. D. Braun - ATF-3 (45)

P&FS Adm - GB-D2 (Nuclear Library) (84)

P. Ehlen - I&C Office (42)

H. Kocourek - TSC (50)

M. Daron - Security Building (46)

W. Galarneau - RAF (53)

P&FS Adm - GB D2-3 (EOF) (81)

W. Galarneau - SBF/EMT (54)

H.Kocourek - OSF (52) W. Galarneau - RPO (55)

C. Hutter - ATF-1 (64)

WORKING COPIES (101-199) These copies of procedures are kept in the areas designated for use in response to an emergency. These are not complete sets, but contain only those procedures that are used to that are implement activities in the location where they are kept. Please dispose of any sections distributed not tabbed in the indicated copy.

D. Krall - CR/Communicator (1 16)(Partial Distribution)

W. Galarneau - RAF/RPO (106, 107)

Simulator/Communicator (117)

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

M. Fencl - Security (121)

W. Galarneau - SBF/EM Team (110, 111, 1llA)

N. Deda - Security Building (120)

W. Galarneau - Aurora Medical Center (118, 119)

S. VanderBloomen (125)

W. Flint - Cold Chem/HR Sample Room (113) J. Stoeger (126)

N. Deda - SBF/SEC (114)

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

  • THIS IS NOT A CONTROLLED COPY. ITIS A COPYFOR INFORMATION ONLY.

1

KEWAUNEE NUCLEAR POWER PLANT REVISION OF EMERGENCY PLAN IMPLEMENTING PROCEDURES January 15, 2C02 to the EPIPs, Please follow the directions listed below. If you have any questions regarding changes made (see cover page), return this please contact Dave Seebart at ext. 8719. If you are a controlled copy holder page to Diane Fencl by February 15, 2002, SIGNED AND DATED to serve as a record of revision.

EPIP Index, dated 01-15-2002.

REMOVE INSERT REV. PROCEDURE REV.

PROCEDURE EP-RET-3C 0 EPIP-RET-03C P M EPIP-RET-03D N EP-RET-3D g

I I

Returnii a~signed and dated copy, of this transmittal letter, -within10 days of receipt, to the sender.

Ifyou have any questions or comments, please call Dave Seebart. I 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 end Enclosure 2

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-15-2002 PROC. N. TITLE REV. DATE EP-AiD EPIP-AD-01 Personnel Response to the Plant-Emergency J 01-08-2002 Siren EPIP-AD-02 Emergency Class Determination AC 11-15-2001 EPIP-AD-03 KNPP Response to an Unusual Event AD 12-14-2001 EPIP-AD-04 KNPP Response to Alert or Higher AP 12-14-2001 EP-AD-5 Site Emergency Deleted 04-27-87 EPIP-AD-05 Emergency Response Organization Shift Relief C 06-05-2001 Guideline EP-AD-6 General Emergency Deleted 04-24-87 EPIP-AD-07 Initial Emergency Notifications AN 11-15-2001.

EP-AD-8 Notification of Alert or Higher Deleted 02-26-96 EP-AD-9 Notification of Site Emergency Deleted 04-27-87 EP-AD- 10 Notification of General Emergency Deleted 04-27-87 EPIP-AD- 1I Emergency Radiation Controls Q 09-27-2001 EP-AD-12 Personnel Assembly and Accountability Deleted 03-26-94 EP-AD-13 Personnel Evacuation Deleted 04-25-94 EP-AD-13A Limited Area Evacuation Deleted 03-01-83 EP-AD- 13B Emergency Assembly/Evacuation Deleted 03-01-83 EP-AD-13C Site Evacuation Deleted 03-01-83 EP-AD-14 Search and Rescue Deleted 05-25-94 EPIP-AD-15 Recovery Planning and Termination 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 0 06-05-2001 EPIP-AD-1 9 Protective Action Guidelines Q 11-27-2001 PAGE I OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-15-2002 PROC. NO. TITLE EPIP-AD-20 KNPP Response to a Security Threat EP-ENV EPIP-ENV-01 Environmental Monitoring Group Organization V 10-02-2001 and Responsibilities EPIP-ENV-02 Environmental Monitoring Team Activation X 10-02-2001 EP-ENV-3A Environmental Protection Director Actions and Deleted 09-26-84 Directives EP-ENV-3B EM Team Actions Deleted 09-26-84 EPIP-ENV-03C Dose Projection Using RASCAL Version 2.2 V 10-09-2001 Software EP-ENV-3D Revision and Control of ISODOSE II Deleted 02-14-95 EP-ENV-3E Manual Determination of X/Q Deleted 04-24-87 EP-ENV-3F Manual Determination of X/Q (Green Bay Deleted 05-30-86 Meteorological Data)

EP-ENV-3G Manual Dose Projection Calculation Deleted 06-02-89 EP-ENV-3H Protective Action Recommendations Deleted 04-13-90 EPIP-ENV-04A Portable Survey Instrument Use S 06-15-2000 EPIP-ENV-04B Air Sampling and Analysis W 10-09-2001 EP-ENV-4C Environmental Monitoring Teams Deleted 04-13-90 EPIP-ENV-04C Ground Deposition Sampling and Analysis W 10-09-2001 EPIP-ENV-04D Plume Tracking for Environmental Monitoring N 10-02-2001 Teams EP-ENV-5A LCS-1 Operation Deleted 04-14-86 EP-ENV-5B MS-3 Operation Deleted 04-14-86 EP-ENV-5C SAM II Operation Deleted 04-14-86 EP-ENV-5D PAC-4G (Alpha Counter) Operation Deleted 04-14-86 EP-ENV-5E Reuter-Stokes Operation Deleted 08-27-85 PAGE 2 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-15-2002 PROC. NO. TITLE REV. DATE EP-ENV-6 I Data Analysis, Dose Projections and Protective Deleted 12-21-81 Action Recommendations EP-ENV-6 Alternate Sample Analysis and Relocation of Deleted 04-14-86 EM Team EP-ENV-6A Relocation of Site Access Facility (Habitability) Deleted 03-23-84 EP-ENV-6B SAF Environmental Sample Analysis Relocation Deleted 03-23-84 EP-ENV-7 Site Access Facility Communications Deleted 09-26-84 EP-ENV-8 Total Population Dose Estimate Calculations Deleted 04-14-86 EP-EOF EP-EOF-1 Corporate Emergency Response Organization Deleted 03-11-94 EPIP-EOF-02 Emergency Operations Facility (EOF) Activation Z 11-29-2001 _

EPIP-EOF-03 EOF Staff Action for Unusual Event AB 12-14-2001 EPIP-EOF-04 EOF Staff Action for Alert or Higher AH 12-14-2001 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 T 11-27-2001 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- 1I Internal Communication and Documentation U 11-15-2001 Flow EPIP-EOF-12 Media Center/Emergency Operation P 07-19-2001 Facility/Joint Public Information Center Security PAGE 3 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-15-2002 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 T 11-29-2001 EPIP-OSF-03 Work Requests During an Emergency 0 09-27-2001 EP-OSF-4 Operational Support Facility Communications Deleted 04-24-87-_

EPIP-OSF-04 Search and Rescue D 09-12-2000 EP-RET EP-RET- 1 Radiation Emergency Team Organization Deleted 04-16-96 EPIP-RET-02 In-Plant Radiation Emergency Team U 11-27-2001 EPIP-RET-02A Radiation Protection Office/Radiological' T 11-29-2001 Analysis Facility (RPO/RAF) Activation EP-RET-2B Gaseous Effluent Sample and Analysis Q 03-03-98 EP-RET-2C Containment Air Sampling and Analysis Deleted 03-01-83 EPIP-RET-02D Emergency Radiation Entry Controls and M 06-12-2001 Implementation EP-RET-2E Handling of Injured Personnel Deleted 04-16-96 EP-RET-2F Personnel Decontamination Deleted 04-13-90 EPIP-RET-03 Chemistry Emergency Team 0 02-01-2000 EPIP-RET-03A Liquid Effluent Release Paths L 11-29-2001 EP-RET-3B Post-Accident Reactor Coolant Alternate Deleted 01-25-88 Sampling Procedure PAGE 4 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-15-2002 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 R 10-02-2001 EP-RET-4A EOF Radiological Monitoring Deleted 03-10-83 EPIP-RET-04A SBF Operation/Relocation Deleted 10-02-2001 EP-RET-4B Radiological Controls at Site Access Facility Deleted 07-12-94 EP-RET-4C Site Radiological Monitoring Deleted 07-12-94 EP-RET-4D SAM-II Operation Deleted 07-12-94 EP-RET-5 Plume Projection Deleted 09-26-84 EPIP-RET-05 Site Boundary Dose Rates During Controlled H 10-09-2001 Plant Cooldown EP-RET-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 P 10-30-2001 Center EPIP-RET-09 Post-Accident Population Dose K 08-29-2000 EP-SEC EP-SEC-1 Security Organization Deleted 04-24-87 EPIP-SEC-02 Security Force Response to Emergencies W 08-28-2001 EP-SEC-2A Manual Activation of Emergency Sirens Deleted 04-16-82 EPIP-SEC-03 Personnel Assembly and Accountability AC 12-14-2001 EPIP-SEC-04 Security Force Actions for Dosimetry Issue P 10-02-2001 PAGE 5 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-15-2002 PROC. NO. TITLE REV. DATE EP-SEC-5 Security Force Response to the EOF Deleted 07-28-88 EPIP-SEC-05 Personnel Evacuation F 07-05-2001 EP-TSC EPIP-TSC-01 Technical Support Center Organization and P 10-02-2001 Responsibilities EPIP-TSC-02 Technical Support Center Activation S 11-29-2001 EPIP-TSC-03 Plant Status Procedure V 10-09-2001 EPIP-TSC-04 Emergency Physical Changes, Major Equipment M 10-02-2001 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 I 10-19-2001 EPIP-TSC-08A Calculations for Steam Release from Steam N 12-14-2001 Generators EPIP-TSC-08B* STMRLS Computer Program F 10-02-2001 EP-TSC-8C* See EP-TSC-8B Deleted 04-16-92

  • EP-TSC-8B was totally deleted; therefore, EP-TSC-8C was changed to EP-TSC-8B EP-TSC-9 Core Damage Assessment Using Released Deleted 09-30-86 Radionuclides EP-TSC-9A* Core Damage Assessment I 02-23-99 EPIP-TSC-09B* CORE Computer Program J 10-02-2001 EP-TSC-9C* See EP-TSC-9B Deleted 04-16-92

EPIP-TSC- 10 Technical Support for IPEOPs I 03-20-2001 PAGE 6 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-15-2002 FIGURES EPIP FIG # 1 Figure EPIPFG DESCRIPTION REV. DATE EP-SEC-5 Technical Support EPIP-APPX-A-06 EP-FIG-003 APPX-A-06-03 Center - KNP Floor Plan B 06-12-2001 Site Boundary Facility EPIP-APPX-A-06 EP-FIG-oos APPX-A-06-02 KNP Floor Plan A 10-31-2000 Radiological Analysis Facility - KNP Floor EPIP-APPX-A-06 EP-FIG-008 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 EPIP-APPX-A-06 Area - WPSC D2-1 EP-FIG-012 APPX-A-06-08 Floor Plan C 10-31-2000 EPIP-APPX-A-06 NRC Work Area EP-FIG-013 APPX-A-06-09 WPSC D2-4 Floor Plan A 10-31-2000 Population Distribution EPIP-AD-19 by Geographical Sub EP-FIG-014 AD-19-01 Areas (with sectors) A 10-31-2000 EPIP-APPX-A-06 EOF - WPSC D2-3 EP-FIG-022 APPX-A-06-04 Floor Plan C 10-30-2001 EPIP-EOF-12 Map - Location of JPIC, EP-FIG-024 EOF-12-02 MBC, GOB, DOB, etc. B 09-27-2001 EP-SEC-5 EP-FIG-026 SEC-05-01 Site Map B 09-27-2001 Floor Plan - Media APPX-A-6 EP-FIG-034 Briefing Center Deleted 08-04-98 EPIP-EOF- 12 General Office Building - WPSC (1st EPIP-APPX-A-06 EP-FIG-035 APPX-A-06-06 Floor) Floor Plan C 10-24-2000 APPX-A-6 Floor Plan - Corporate EP-F-o37 - - - 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 EPIP-APPX-A-06 JPIC - Federal Work EP-FIG-043 APPX-A-06-10 Area - WPSC D2-9 B 12-21-2001 JPIC - State and County EPIP-APPX-A-06 Work Area EP-FIG-044 APPX-A-06-07 WPSC D2-8 C 12-21-2001 EPIP-APPX-A-06 JPIC - Utility Work EP-FIG-045 APPX-A-06-05 Area - WPSC D2-7 C 12-21-2001 RET-08 Aurora Medical Center EP-FIG-046 RET-08-01 Location A 06-15-2000 EPIP-APPX-A-02 --- APPX-A-02-01 ERO Call Tree Deleted 12-04-2001 PAGE 7 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-15-2002 NUMBER TITLE APPENDIX A APPX-A-I Communication System Description EPIP-APPX-A-02 Response Personnel Call List EPIP-APPX-A-03 Off-Site Telephone Numbers EPIP-APPX-A-06 KNPP Emergency Response Facility Telephone Numbers PAGE 8 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-15-2002 FORM EPIPF TITLE REV. DATE APPENDIX B EP-AD AD-07-01 Event Notice (Wisconsin Nuclear Accident Reporting R 12-14-2001 Form)

AD-07-02 State Call-Back - Question Guideline C 11-15-2001 AD 11.1 Emergency Radiation Work Permit F 04-16-96 EP-ENV ENV-01-01 Environmental Dispatch Area Activation Checklist D 10-31-2000 ENV-01-02 EMT Status B 10-31-2000 ENV-01-03 Meteorological and Plant Status Data C 12-14-2001 ENV-01-04 EMT Orders/Field Data B 10-31-2000 ENV-02-01 EMT Activation Checklist M 06-15-2000 EP-EOF EOF-02-01 EOF Activation Checklist S 10-30-2001 EOF-02-02 EOF Deactivation Checklist L 10-30-2001 EOF-04-01 SRCL Initial Action Checklist C 12-14-2001 EOF-04-02 Telephone Communications Log Sheet A 12-14-2001 EOF-08-03 Fax for Emergency Declaration or Status Updates G 11-27-2001 EOF-08-05 Plant Emergency Status Report A 11-27-2001 EOF-08-06 Radiological Status Report D 11-27-2001 EOF- 11-02 Operating Status F 11-15-2001 EOF-1 1-03 Environmental Status Board F 11-15-2001 EOF-12-01 I.D. Badge Registration Form G 10-24-2000 EP-OSF OSF 2.2 Maintenance Work in Progress Deleted 07-08-98 OSF-03-01 Operational Support Facility Team Briefing C 12-04-2001 PAGE 9 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-15-2002 FORM EPIPF TITLE REV. DATE EP-RET RET-02A-02 Emergency Sample Worksheet E 06-05-2001 RET 2B. 1 Containment Stack Release (Grab Sample) C 04-16-96 RET 2B.2 Auxiliary Building Stack (Grab Sample) C 04-16-96 RET 2B.3 Auxiliary Building Stack (Sping Reading) C 04-16-96 RET 2B.4 Containment Stack (Sping Reading) B 04-16-96 RET 2B.5 Steam Release C 04-16-96 RET 2B.6 Field Reading (Grab Sample) A 04-16-96 RET-04-01 SAM-2 Counting Equipment Worksheet E 06-12-2001 RET 8.3 Hospital Survey 1 Deleted 06-05-20Q1 RET 8.4 Hospital Survey 2 Deleted 07-25-97 RET 8.5 Hospital Survey 3 Deleted 07-25-97 RET-08-06 Hospital Survey 4 F 06-15-2000 RET 9 Environmental TLD Record Sheet C 02-14-95 EP-SEC SEC-03.01 Emergency Accountability Log A 03-28-2000 SEC 4.1 Emergency Dosimeter Log F 02-16-2000 EP-TSC TSC 1.1 Plant Status Summary for SAM Implementation A 04-01-99 TSC 1.2 Severe Accident Management Summary and Strategy A 04-01-99 Recommendation TSC 1.3 Severe Accident Management - Status A 04-01-99 TSC-02-01 TSC and OSF Activation Checklist 0 09-27-2001 TSC 2.2 TSC Ventilation Checklist H 04-01-99 TSC-02-03 Emergency Response Data System (ERDS) Link Initiation G 05-04-2001 Checklist PAGE 10 OF 11

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX DATE: 01-15-2002 FORM EPIPF TITLE REV. DATE TSC-02-04 TSC Chart Recorder Operation Checklist D 01-30-2001 TSC-02-05 TSC and OSF De-activation Checklist A 10-09-2001 TSC-03-01 Plant System Status L 06-12-2001 TSC-03-02 Plant Equipment Status L 06-12-2001 TSC-03-03 Environmental Status Board J 06-12-2001 TSC-03-04 Radiation Monitors I 01-08-2002 TSC-04-01 Emergency Physical Change Request F 08-29-2000 TSC-04-02 Emergency Physical Change Safety Review F 08-29-2000 TSC-04-03 Emergency Physical Change Index F 08-29-2000 TSC-07-01 Head Venting Calculation F 10-31-2000 TSC-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 9A. 1 Core Damage Based on Reactor Vessel Level & Fuel Rod C 02-14-95 Temp.

TSC 9A.2 Core Damage Based on Radiation Monitors C 02-14-95 TSC 9A.3 Cs-134 and Cs-137 PCF Determination D 04-16-96 TSC 9A.4 Core Damage Based on Activity Ratios C 02-14-95 TSC 9A.5 Core Damage Assessment (Monitoring Data) D 04-16-96 TSC 9A.6 Core Damage Summary C 02-14-95 PAGE 11 OF 11

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C IRev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 2002 Page 1 of 34 Approved By :Z ---- -'-,,

Reviewed Bv Nuclear [] Yes AORC Yes_ SRO Approval Of 2 Yes Safety Review Temporary Related 13 N Reuired [] No Changes Required El No 1.0 Purpose 1.1 This procedure provides instruction for operation of the High Radiation Sample Room (HRSR) to obtain the following primary coolant samples under post accident conditions:

a. Diluted liquid sample of primary coolant for: (Step 5.1) 0 Boron analysis 0 Gamma isotopic analysis
b. An inline liquid sample for: (Step 5.2)

"* pH 0 Oxygen

"* Conductivity

c. An inline undiluted gas sample for hydrogen analysis. (Step 5.3)
d. A diluted gas sample for gamma isotopic analysis. (Step 5.3)
e. An undiluted liquid sample for off-site analysis. (Step 5.4)
f. Operation of IA and lB Hydrogen Analyzers for Containment. (Step 5.5)
g. Flush of liquid sample lines. (Step 5.6) 2.0 General Notes 2.1 This procedure is designated CONTINUOUS USE.

2.2 The following is a list of acronyms that are used throughout this procedure:

  • CAP Chemical Analysis Panel
  • CASP Containment Air Sampling Panel
  • CMP Chemical Analysis Monitor Panel
  • DDT Deaerated Drain Tank
  • HVAC/CCP HVAC/Containment Air Sample Control Panel
  • HP/RPD Health Physics/Radiation Protection Director
  • HRSR High Radiation Sample Room RCHL
  • LSP Liquid Sample Panel
  • SAP Sample Acquisition Panel n:\nucdoc\procedures\draft\epip\eret03c.doc-Bil HollingsworthlChrisfine Simmons-John Madden

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 2 of 34 3.0 Precautions and Limitations 3.1 Process an Emergency Radiation Work Permit per EPIP-AD-1 1, "Emergency Radiation Controls."

3.2 Contact Radiation Protection Group (HIP) for:

3.2.1 Proper personnel dosimetry 3.2.2 Proper radiation detection instrumentation 3.2.3 Personnel for continuous HIP coverage during sampling 3.2.4 Remote area monitor readings in area of HRSR 3.3 Utilize on-site communications with the HP/RPD, as necessary, during sampling.

3.4 Containment sump pH should be adjusted to a pH > 7 within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> following the initiation of recirculation during a small break loss of coolant accident.

3.5 If the sample flow is lost during the performance of this procedure and the valve line-up is confirmed, a sample high temperature condition may exist.

  • No direct temperature indicator is available.
  • Sample flow is automatically isolated when sample temperatures exceed 120°F and automatically resets when the temperatures are reduced.
  • If sample flow is restored without having to take action, then high temperature isolation is confirmed.
  • Such a high temperature condition may arise if the Component Cooling flow is isolated or Component Cooling temperatures are high. Component Cooling temperatures may be observed using the plant process computer.

High Component Cooling temperature may occur if Service Water temperatures are elevated.

3.6 IF the loss of sample flow is confirmed to be due to high Component Cooling temperatures, THEN discuss the concern with Operations or the Technical Support Center and discuss opportunities to reduce Service Water heat loads to allow for better performance of Component Cooling.

3.7 Transit routes to and from the HRSR per HP/RPD recommendations.

3.8 Monitor radiation levels in the HRSR upon entry and during sample manipulations.

CONTINUOUS USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C IRev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 2002 Page 3 of 34 3.9 Radiation level monitoring is required if accessing the maintenance areas behind the panels.

3.10 IF sufficient sample flow is not achieved, THEN extend the purge time as required to compensate for the reduced flow rates.

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

5.0 Procedure 5.1 Diluted Liquid Sample for Boron Analysis and Isotopic Analysis 5.1.1 In the HRSR check the following equipment available and operational:

"* Drying oven on at 55°C to 60*C

"* All material required to perform RCC-082, "Boron Analysis Curcumin Method."

"* Multi-Channel Analyzer available for counting (Technical Support Center)

" 2 - 1 liter poly bottles

"* Shielded aliquoter available

"* New 60 ml diluted sample bottle (large bottle)

"* Hand operated vacuum pump

"* Lights on in diluted sample port of LSP

"* LSP Sample Cask available with diluted sample bottle piston installed

"* Reach Rod for remote valve operation CONTINUOUS USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C IRev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 4 of34 5.1.2 At the CASP perform the following:

5.1.2.1 Verify ventilation is ON and mode control switches are in NORMAL position.

5.1.2.2 Check High Vacuum Lights indicate NORMAL for the following:

"* LSP

" CAP

"* CASP 5.1.3 Perform valve lineup per Attachment A, "High Radiation Sample Valve Lineup Sheet."

5.1.4 Connect DI Water flush hose to LSP.

5.1.5 Open DI Water supply valve to LSP.

5.1.6 Evacuate the diluted sample bottle (60 ml, large bottle) to > 15 inches of vacuum. IF possible, THEN >Ž20 inches of vacuum is recommended.

5.1.6.1 Install sample bottle in sample cask.

5.1.6.2 Check cask for proper operation (large holder in cask).

5.1.7 At the LSP perform the following:

5.1.7.1 Inspect dilution water reservoir level.

5.1.7.2 IF necessary, THEN fill to full mark.

5.1.8 WHEN performing an RCHL sample, THEN request Control Room Operator perform the following:

"* Open RC-422.

"* Open RC-423.

CONTINUOUS USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 2002 Page 5 of 5.1.9 At the SAP perform the following:

5.1.9.1 WHEN performing an RCHL sample, THEN perform the following:

" Open CC-314.

"* Open RC-423-1.

5.1.9.2 WHEN performing a Residual Heat Removal (RHR) sample, THEN perform the following:

"* Open CC-316.

"* WHEN sampling A RHR, THEN open RHR-81-A.

"* WHEN sampling B RHR, THEN open RHR-81-B.

5.1.9.3 Position RC-437-1 to DDT.

5.1.9.4 Position RC-437-2 to DDT.

5.1.10 At the LSP perform the following:

5.1.10.1 Open RC-V3.

5.1.10.2 WHEN performing a RCHL sample, THEN open RC-V-1.2.

5.1.10.3 WHEN performing a RHR sample, THEN open RC-V-1.1.

Note Purge time may be varied based on actualpurgeflow rate obtained.

5.1.10.4 Throttle RC-VREL-1 until flow indicator RC-FI-1 indicates 1,900 to 2,000 cc/min.

"* WHEN RCHL sample, THEN purge at least 12 minutes.

"* WHEN RHR sample, THEN purge at least 25 minutes.

5.1.10.5 IF unable to attain desired purge flow rate, THEN adjust purge time accordingly.

5.1.10.6 WHEN purge is complete, THEN perform the following:

a. Close RC-V-3.
b. Open RC-V-8.2.
c. Open RC-V-8.1.
d. Open RC-V-2.

CONTINUOUS USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C IRev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 6 of 34 Note Purgetime may be varied based on purgeflow rate obtained.

5.1.10.7 Throttle RC-VREL-2 until flow indicator RC-FI-2 indicates 180 to 220 cc/min.

5.1.10.8 Purge at least 3 minutes.

5.1.10.9 IF unable to attain desired purge flow rate, THEN adjust purge time accordingly.

5.1.10.10 Verify diluted sample bottle (from Step 5.1.6) vacuum > 15 inches of vacuum. IF possible, THEN Ž 20 inches of vacuum is recommended.

5.1.10.11 Install the sample cart under the diluted sample port.

5.1.10.12 Position the sample bottle up on the needles.

5.1.10.13 WHEN purge is complete, THEN perform the following:

a. Turn RC-DV-1 to SAMPLE position (6 o'clock).
b. IF RCHL sample, THEN close RC-V-1.2.
c. IF RHR sample, THEN close RC-V-1.1.

5.1.10.14 Throttle open RC-V-21.

5.1.10.15 Add 24 ml of DI Water to the sample bottle.

5.1.10.16 IF less than 24 ml of DI Water is used, THEN note sample volume.

5.1.10.17 Close RC-V-21.

5.1.10.18 Turn RC-DV-1 to BYPASS position (3 o'clock).

5.1.10.19 Open RC-V-4.

Note Flush time may be varied based on actualflushflow rate obtained.

5.1.10.20 Throttle RC-VEL-2 until flow indicator RC-FI-2 indicates 180 to 200 cc/min.

5.1.10.21 Flush for at least 3 minutes.

5.1.10.22 IF unable to attain desired flush flow rate, THEN adjust flush time accordingly.

CONTINUOUS USE

No. I Rev. P

~AIgr./4, NJi%.II 1 IR V IC~l, ~Fv ICF COR.N......... I ..... C.ev.

Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 2002 Page 7 of 34 Note The following step may be performed during theflush.

5.1.10.23 Lower the diluted sample bottle into the sample cask.

"* Close the cask

"* Place cask near fume hood

"* Install auxiliary shield 5.1.10.24 Close RC-V-4.

5.1.10.25 Close RC-V-2.

5.1.10.26 Close RC-V-8.2.

5.1.10.27 Close RC-V-8.1.

5.1.11 WHEN RCHL sample, THEN request Control Room Operator perform the following:

"* Close RC-422.

"* Close RC-423.

5.1.12 At the SAP perform the following:

5.1.12.1 WHEN RCHL sample, THEN perform the following:

"* Close RC-423-1.

"* Close CC-314.

5.1.12.2 WHEN RHR sample, THEN perform the following:

"* IF opened, THEN close RHR-81A.

"* IF opened, THEN close RHR-81B.

"* Close CC-316.

5.1.12.3 Position RC-437-1 toVCT.

5.1.12.4 Position RC-437-2 to VCT.

5.1.12.5 Close DI Water supply valve.

5.1.12.6 Disconnect DI Water hose.

CONTINUOUS USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 _ Page 8 of 34 Note Dilutionfactor correction is requiredifsample was not diluted with 24 ml ofDI Water Step 5.1.10.16.

5.1.13 Perform the following post sample analyses preparations:

Note For Boron analysis of< 2,000 ppm, an appropriatelylargeramount of sample shall be used.

5.1.13.1 WHEN analyzing for boron, THEN perform the following:

a. Transfer a 1.0 ml sample from the sample cask into a VYCOR evaporating dish using the shielded liquid aliquoter.
b. Continue the boron analysis per RCC-082, "Boron Analysis Curcumin -

Method."

5.1.13.2 WHEN performing a Beta/Gamma analysis, THEN perform the following:

a. Transfer 1.0 ml of coolant from the cask to a 1 liter poly bottle using the shielded liquid aliquoter.
b. Dilute to 1 liter with DI Water.
c. Transfer 10 ml of diluted sample to a second 1 liter poly bottle.
d. Dilute to 1 liter with DI Water. Dilution factor = 108.
e. Transfer sample to the multi-channel analyzer for counting.

5.2 Inline Sample for pH, Conductivity, 02 and Chloride Note Gas cylinders and their regulatorsare located outside the HRSR at the gas cylinder rack.

5.2.1 Align argon and helium as follows:

5.2.1.1 Verify open argon gas cylinder isolation.

5.2.1.2 Verify argon cylinder pressure >_400 psi.

5.2.1.3 Adjust argon pressure regulator to obtain 150 psi (140 to 160 psi).

5.2.1.4 Verify open helium gas cylinder isolation.

CONTINUOUS USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C IRev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 2002 Page 9 of 34 5.2.1.5 Verify helium cylinder pressure > 400 psi.

5.2.1.6 Adjust helium pressure regulator to obtain 70 psi (65 to 85 psi).

5.2.2 Verify reach rod is available for remote valve operation.

5.2.3 Check HRSR Calibration Log for verification of latest performances.

5.2.4 At the CASP perform the following:

5.2.4.1 Verify ventilation is ON and mode control switches are in NORMAL position.

5.2.4.2 Check High Vacuum Lights indicate NORMAL for the following:

  • LSP 0 CAP 0 CASP 5.2.5 At the CMP perform the following:

5.2.5.1 CMP Main Power switch ON.

5.2.5.2 Verify the YSI chart recorder is ON.

5.2.5.3 Verify the pH meter is ON.

5.2.5.4 Verify the conductivity meter is ON.

5.2.5.5 Start Ion Chromatograph (IC) in accordance with RCC-520, "DX-500 Startup and Shutdown Procedure."

5.2.6 Perform valve lineup per Attachment A, "High Radiation Sample Valve Lineup Sheet."

5.2.7 At the CAP, verify argon, helium, and air regulators set as follows:

5.2.7.1 Adjust argon pressure regulator to obtain 30 psi (30 to 32 psi).

5.2.7.2 Adjust helium pressure regulator to obtain 50 psi (50 to 55 psi).

5.2.7.3 Adjust air pressure regulator to obtain 75 psi (75 to 85 psi).

5.2.8 Connect DI Water flush hoses to LSP and CAP.

5.2.9 Open DI Water supply valve to LSP.

CONTINUOUS USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C IRev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Inmplementing Procedure Date AN 152002 Page 10 of 34 5.2.10 Open DI Water supply valve to CAP.

5.2.11 At the CAP perform the following:

5.2.11.1 Position V-6 to LIQUID SAMPLE (9 o'clock).

5.2.11.2 Position V-5 to LIQUID SAMPLE (9 o'clock).

5.2.12 WHEN RCHL sample, THEN request Control Room Operator perform the following:

"* Open RC-422.

"* Open RC-423.

5.2.13 At the SAP perform the following:

5.2.13.1 WHEN performing an RCHL sample, THEN perform the following:

"* Open CC-314.

"* Open RC-423-1.

5.2.13.2 WHEN performing a RHR sample, THEN perform the following:

"* Open CC-316.

"* WHEN sampling A RHR, THEN open RHR-81-A.

"* WHEN sampling B RI{R, THEN open RHR-8 1-B.

5.2.13.3 Position RC-437-1 to DDT.

5.2.13.4 Position RC-437-2 to DDT.

5.2.14 At the LSP perform the following:

5.2.14.1 Open RC-V3.

5.2.14.2 WHEN performing a RCHL sample, THEN open RC-V-1.2.

5.2.14.3 WHEN performing a RHR sample, THEN open RC-V-1.1.

CONTINUOUS USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C -TRev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 2002 Page 11 of 34 Note Purge time may be varied based on actualpurgeflow rate obtained.

5.2.14.4 Throttle RC-VREL- 1 until flow indicator RC-FI- 1 indicates 1,900 to 2,000 cc/min.

"* WHEN RCHL sample, THEN purge at least 12 minutes.

"* WHEN RHR sample, THEN purge at least 25 minutes.

5.2.14.5 IF unable to attain desired purge flow rate, THEN adjust purge time accordingly.

5.2.14.6 WHEN purge is complete, THEN perform the following:

"* Close RC-V-3.

"* Open RC-V-2.

"* Open RC-V-7.

"* Position RC-V-22 to CHEM PANEL.

Note Purge time may be varied based on actualpurgeflow rate obtained.

5.2.14.7 Throttle RC-VREL-2 until flow indicator RC-FI-2 indicates 180 to 220 cc/min.

5.2.14.8 Purge at least 5 minutes.

5.2.14.9 IF unable to attain desired purge flow rate, THEN adjust purge time accordingly.

5.2.15 At the CAP perform the following:

5.2.15.1 Verify adequate flow to the CAP by observing the red lights ON for both Oxygen and IC.

5.2.15.2 WHEN the YSI 02 meter chart reading has stabilized, THEN record the following on the Reactor Coolant Analysis Log (routine logsheet):

  • Conductivity reading
  • Temperature
  • 02 reading CONTINUOUS USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C 1Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 12 of 34 5.2.15.3 Inject sample on IC unit.

  • WHEN IC run complete, THEN record Chloride value on the Reactor Coolant Analysis Log (routine logsheet) and attach chart recorder printout.

5.2.16 At the LSP perform the following:

5.2.16.1 Turn RC-V-22 to WASTE position (6 o'clock).

5.2.16.2 WHEN RCHL sample, THEN close RC-V-1.2.

5.2.16.3 WHEN RHR sample, THEN close RC-V-1.1.

5.2.16.4 Open RC-V-4.

5.2.16.5 Observe DI Water flush to waste as indicated on Flow Indicator RC-FI-2.

5.2.16.6 Flush for 2 minutes.

5.2.16.7 Record pH reading on the Reactor Coolant Analysis Log (routine logsheet).

5.2.16.8 Turn RC-V-22 to CAP position (12 o'clock).

5.2.16.9 Verify flush water flow by observing the lights ON for both 02 Flow and IC Flow.

5.2.16.10 Flush for at least 2 minutes.

5.2.16.11 Turn RC-V-22 to WASTE position (6 o'clock).

5.2.16.12 Close RC-V-7.

5.2.16.13 Close RC-V-2.

5.2.16.14 Close RC-V-4.

5.2.17 At the CAP perform the following:

5.2.17.1 Position V-6 to 02 CAL (6 o'clock).

5.2.17.2 Close V-5 (6 o'clock).

CONTINUOUS USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C IRev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date AN1 5 2002 Page 13 of 34 5.2.18 WHEN RCHL sample, THEN request Control Room Operator perform the following:

"* Close RC-422.

"* Close RC-423.

5.2.19 At the SAP perform the following:

5.2.19.1 WHEN RCHL sample, THEN perform the following:

"* Close RC-423-1.

"* Close CC-314.

5.2.19.2 WHEN RJ{R sample, THEN perform the following:

"* IF opened, THEN close RHR-81A.

"* IF opened, THEN close RHR-81B.

"* Close CC-316.

5.2.19.3 Position RC-437-1 to VCT.

5.2.19.4 Position RC-437-2 to VCT.

5.2.19.5 Close DI Water supply valve.

5.2.19.6 Disconnect DI Water hose.

5.3 Inline Hydrogen and Gaseous Activity Grab Sample 5.3.1 Verify the multi-channel analyzer available for counting.

Note Gas cylinders and their regulatorsare locatedoutside the HRSR at the gas cylinder rack.

5.3.2 Align argon and helium as follows:

5.3.2.1 Verify open argon gas cylinder isolation.

5.3.2.2 Verify argon cylinder pressure Ž 400 psi.

5.3.2.3 Adjust argon pressure regulator to obtain 150 psi (140 to 160 psi).

5.3.2.4 Verify open helium gas cylinder isolation.

CONTINUOUS USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C IRev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 14 of 34 5.3.2.5 Verify helium cylinder pressure _> 400 psi.

5.3.2.6 Adjust helium pressure regulator to obtain 70 psi (65 to 85 psi).

5.3.3 At the CASP perform the following:

5.3.3.1 Verify ventilation is ON and mode control switches are in NORMAL position.

5.3.3.2 Check High Vacuum Lights indicate NORMAL for the following:

"* LSP

"* CA-P

"* CASP 5.3.4 Verify the following equipment available and operational:

  • Reach Rod for remote valve operation
  • 10 cc gas sample bottle, with septum, properly installed in face of LSP using the special handling tool 5.3.5 At the CMP perform the following:

5.3.5.1 CMP Main Power switch ON.

5.3.5.2 Verify the program in Gas Chromatograph (GC) mini-computer.

5.3.5.3 Check HRSR Calibration Log for verification of latest performances.

5.3.6 Perform valve lineup per Attachment A, "High Radiation Sample Valve Lineup Sheet."

5.3.7 At the CAP, verify Argon, Helium, and Air regulators set as follows:

5.3.7.1 Adjust Argon pressure regulator to obtain 30 psi (30 to 32 psi).

5.3.7.2 Adjust Helium pressure regulator to obtain 50 psi (50 to 55 psi).

5.3.7.3 Adjust Air pressure regulator to obtain 75 psi (75 to 85 psi).

5.3.8 Connect DI Water flush hoses to LSP and CAP.

5.3.9 Open DI Water supply valves.

CONTINUOUS USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C IRev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 20(2 Page 15 of 34 5.3.10 At the LSP, dry the expansion vessel as follows:

5.3.10.1 Turn RC-V-11 to ARGON position (3 o'clock).

5.3.10.2 Open RC-V-9.

5.3.10.3 Open RC-V-8.2.

5.3.10.4 Open RC-V-10.

5.3.10.5 Regulate RC-VREL-2 to obtain 20 psi on RC-G-3.

5.3.10.6 Observe flow indication on RC-FI-2.

5.3.10.7 Wait at least 1 minute.

5.3.10.8 Turn RC-V-1 1 counterclockwise to VACUUMISAMPLE position (9 o'clock).

5.3.10.9 Close RC-V-9.

5.3.10.10 Close RC-V-8.2.

5.3.11 WHEN RCHL sample, THEN request Control Room Operator perform the following:

"* Open RC-422.

"* Open RC-423.

5.3.12 At the SAP perform the following:

5.3.12.1 WHEN performing an RCHL sample, THEN perform the following:

"* Open CC-314.

"* Open RC-423-1.

5.3.12.2 WHEN performing a RHR sample, THEN perform the following:

"* Open CC-316.

"* WHEN sampling A RHR, THEN open RHR-81-A.

"* WHEN sampling B RIR, THEN open RHR-81-B.

5.3.12.3 Position RC-437-1 to DDT.

5.3.12.4 Position RC-437-2 to DDT.

CONTINUOUS USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 2002 Page 16 of 34 5.3.13 At the LSP perform the following:

5.3.13.1 Open RC-V3.

5.3.13.2 WHEN performing a RCHL sample, THEN open RC-V-1.2.

5.3.13.3 WHEN performing a RHR sample, THEN open RC-V- 1.1.

Note Purge time may be varied based on actualpurgeflow rate obtained.

5.3.13.4 Throttle RC-VREL- 1 until flow indicator RC-FI- 1 indicates 1,900 to 2,000 cc/min.

"* WHEN RCHL sample, THEN purge at least 12 minutes.

"* WHEN RIR sample, THEN purge at least 25 minutes.

5.3.13.5 IF unable to attain desired purge flow rate, THEN adjust purge time accordingly.

Note The following, Steps 5.3.13.6 to 5.3.13.11, may be completed while waitingfor the samplepurge to be completed.

5.3.13.6 Evacuate the Gas Expansion Vessel, sample bottle, and tubing as follows:

a. Open RC-V-13.
b. Open RC-V-15.
c. Turn RC-DV-2 to GAS SAMPLE position (12 o'clock).
d. Open RC-V-12.

5.3.13.7 WHEN vacuum on RC-G-2.2 > 22 inches vacuum, THEN turn RC-DV-2 to TO GC position (3 o'clock).

5.3.13.8 WHEN vacuum on RC-G-2.1 Ž> 22 inches of vacuum, THEN perform the following:

a. Close RC-V-15.
b. Close RC-V-13.
c. Close RC-V-10.
d. Turn RC-V-11 clockwise to CLOSE position (12 o'clock).
e. Close RC-V-12.

CONTINUOUS USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C IRev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 17 of 34 5.3.13.9 Observe vacuum is holding steady on both gauges by performing the following:

a. Turn RC-DV-2 to 12 o'clock.
b. Observe vacuum on RC-G-2.2 is holding steady.
c. Turn RC-DV-2 to 3 o'clock.

5.3.13.10 Open RC-V-14.

5.3.13.11 Observe RC-G-2.2 about 1.0 psi.

Note Sample purge must be completed before proceeding.

5.3.13.12 Close RC-V-3.

5.3.13.13 Open RC-V-8.2.

5.3.13.14 Open RC-V-8.1.

5.3.13.15 Open RC-V-2.

Note Purgetime may be varied based on actualpurgeflow rate obtained.

5.3.13.16 Throttle RC-VREL-2 until flow indicator RC-FI-2 indicates 180 to 220 cc/min.

5.3.13.17 Purge at least 3 minutes.

5.3.13.18 IF unable to attain desired purge flow rate, THEN adjust purge time accordingly.

5.3.13.19 Close RC-V-8.2.

5.3.13.20 Close RC-V-8.1.

5.3.13.21 WHEN RCHL sample, THEN close RC-V-1.2.

5.3.13.22 WHEN RHR sample, THEN close RC-V-1.1.

5.3.13.23 Open RC-V-9.

5.3.13.24 Open RC-V-16.

5.3.13.25 Wait 1 minute.

5.3.13.26 Close RC-V-16.

CONTINUOUS USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C IRev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 18 of 34 5.3.13.27 Close RC-V-9.

5.3.13.28 WHEN gas stripping complete, THEN flush the LSP as follows:

a. Open RC-V-8.2.
b. Open RC-V-8.1.
c. Open RC-V-4.
d. Turn RC-V- 11 counterclockwise to VACUUM/SAMPLE position (9 o'clock).

5.3.13.29 Turn RC-DV-2 to GAS SAMPLE position (12 o'clock). To obtain the diluted gas sample.

5.3.13.30 Observe pressure gauge RC-G-2.2 stabilized at about 1 psi.

5.3.13.31 Turn RC-DV-2 to TO GC position (3 o'clock).

5.3.13.32 Close RC-V-14.

5.3.13.33 Remove the diluted gas sample bottle from the LSP.

5.3.14 Place entire assembly in fume hood for later transport to multi-channel analyzer.

5.3.15 At the CMP, operate the GC mini-computer to draw a vacuum on all 4 sample loops.

5.3.16 At the LSP, open RC-V-15 and allow the gas sample to transfer to the GC.

5.3.17 Operate the GC unit to obtain 4 samples for hydrogen determination. By selective attenuation, starting with a high value, determine the hydrogen concentration.

"* Cycle through the four loops.

"* Stop at each loop at least 1 minute.

Note Start attenuationselection with high values.

"* Determine hydrogen concentration using selective attenuation.

"* Record information on the Reactor Coolant Analysis Log (routine logsheet).

CONTINUOUS USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 2002 Page 19 of 34 5.3.18 WHEN RCHL sample, THEN request Control Room Operator perform the following:

"* Close RC-422.

"* Close RC-423.

5.3.19 At the LSP perform the following:

5.3.19.1 Close RC-V-4.

5.3.19.2 Close RC-V-2.

5.3.19.3 Close RC-V-8.1.

5.3.19.4 Close RC-V-8.2.

5.3.20 At the SAP perform the following:

5.3.20.1 WHEN RCHL sample, THEN perform the following:

"* Close RC-423-1.

"* Close CC-314.

5.3.20.2 WHEN RHR sample, THEN perform the following:

"* IF opened, THEN Close RHR-81A.

"* IF opened, THEN close RHR-81B.

"* Close CC-316.

5.3.20.3 Position RC-437-1 to VCT.

5.3.20.4 Position RC-437-2 to VCT.

5.3.21 At the LSP to flush the expansion vessel perform the following:

5.3.21.1 Open RC-V-8.2.

5.3.21.2 Open RC-V-9.

5.3.21.3 Turn RC-V-11 to DI WATER position (6 o'clock).

5.3.21.4 Flush for at least 2 minutes.

5.3.21.5 Turn RC-V- 11 to ARGON position (3 o'clock).

5.3.21.6 Wait 2 minutes.

CONTINUOUS USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 20 of 34 5.3.21.7 Turn RC-V-11 counterclockwise to CLOSE position (12 o'clock).

5.3.21.8 Close RC-V-9.

5.3.21.9 Close RC-V-8.2.

5.3.22 To remove radioactive gases from the system perform the following:

5.3.22.1 Open RC-V-10.

5.3.22.2 Open RC-V-13.

5.3.22.3 Open RC-V-15.

5.3.22.4 Turn RC-V- 11 to VACUUM/SAMPLE position (9 o'clock).

5.3.22.5 Open RC-V-12.

5.3.22.6 Evacuate system for at least 1 minute.

5.3.22.7 Close RC-V-12.

5.3.22.8 Turn RC-V-1 1 clockwise to CLOSE position (12 o'clock).

5.3.22.9 Close RC-V-15.

5.3.22.10 Close RC-V-13.

5.3.22.11 Close RC-V-10.

5.3.23 Transport diluted gas bottle to multi-channel analyzer for analysis in accordance with RCC-063, RCS Gaseous Activity."

5.4 Undiluted Liquid Grab Sample 5.4.1 In the HRSR check the following equipment available and operational:

"* Sample cask available with undiluted piston installed

"* Two - 15 ml undiluted sample bottle

"* New undiluted liquid flush bottle

"* Undiluted liquid sample flush bottle handling tool

"* Lights ON in undiluted sample port of LSP

"* Reach Rod for remote valve operation CONTINUOUS USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C IRev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 21 of 34 5.4.2 At the CASP perform the following:

5.4.2.1 Verify ventilation is ON and mode control switches are in NORMAL position.

5.4.2.2 Check High Vacuum Lights indicate NORMAL for the following:

"* LSP

"* CAP

"* CASP 5.4.3 Perform valve lineup per Attachment A, "High Radiation Sample Valve Lineup Sheet."

5.4.4 Connect DI Water flush hoses to LSP.

5.4.5 Open DI Water supply valve to LSP.

5.4.6 Install undiluted sample bottle in sample cask.

5.4.7 Check cask for proper operation.

5.4.8 Install the sample cask under the undiluted sample port.

5.4.9 Position the undiluted sample bottle up on the needles.

5.4.10 WHEN performing an RCHL sample, THEN request Control Room Operator:

9 Open RC-422.

0 Open RC-423.

5.4.11 At the SAP perform the following:

5.4.11.1 WHEN performing an RCHL sample, THEN perform the following:

"* Open CC-314.

"* Open RC-423-1.

CONTINUOUS USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C IRev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 2002 Page 22 of 34 5.4.11.2 WHEN performing a RHR sample, THEN perform the following:

"* Open CC-316.

"* WHEN sampling A RHR, THEN open RHR-81-A.

"* WHEN sampling B RHR, THEN open RHR-81-B.

5.4.11.3 Position RC-437-1 to DDT.

5.4.11.4 Position RC-437-2 to DDT.

5.4.12 At the LSP perform the following:

5.4.12.1 Open RC-V-3.

5.4.12.2 WHEN performing a RCHL sample, THEN open RC-V-1.2.

5.4.12.3 WHEN performing a RHR sample, THEN open RC-V-1.1.

Note Purgetime may be varied based on actualpurgeflow rate obtained.

5.4.12.4 Throttle RC-VREL-1 until flow indicator RC-FI-1 indicates 1,900 to 2,000 cc/min.

"* WHEN RCHL sample, THEN purge at least 12 minutes.

"* WHEN RHR sample, THEN purge at least 25 minutes 5.4.12.5 IF unable to attain desired purge flow rate, THEN adjust purge time accordingly.

5.4.12.6 WHEN purge is complete, THEN perform the following:

a. Close RC-V-3.
b. Open RC-V-2.
c. Open RC-V-7.

Note Purge time may be variedbased on actualpurgeflow rate obtained.

5.4.12.7 Throttle RC-VREL-2 until flow indicator RC-FI-2 indicates 180 to 220 cc/min.

5.4.12.8 Purge for at least 3 minutes.

5.4.12.9 IF unable to attain desired purge flow rate, THEN adjust purge time accordingly.

CONTINUOUS USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C IRev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 15 2002 1 Page 23 of 34 5.4.12.10 Turn RC-V-19 to SAMPLE position (3 o'clock).

5.4.12.11 Observe flow into undiluted sample bottle.

5.4.12.12 WHEN undiluted sample bottle is full, THEN position RC-V-19 to BYPASS position (12 o'clock).

5.4.13 Remove undiluted sample bottle from the needles.

5.4.14 Store the undiluted sample.

"* Return undiluted sample to cask.

"* Close lead top.

"* Install auxiliary shield.

"* Remove cask from HRSR.

5.4.15 IF RCHL sample, THEN close RC-V-1.2.

5.4.16 IF RHR sample, THEN close RC-V-1.1.

5.4.17 Open RC-V-4.

5.4.18 Place new undiluted sample bottle in special handling tool.

5.4.19 Position tool and bottle up on undiluted sample needles in LSP.

5.4.20 Turn RC-V-19 to SAMPLE position (3 o'clock).

5.4.21 Flush for at least 3 minutes.

5.4.22 Turn RC-V-19 to BYPASS position (12 o'clock).

5.4.23 Close RC-V-7.

5.4.24 Close RC-V-2.

5.4.25 Close RC-V-4.

5.4.26 Remove undiluted flush bottle and handling tool.

5.4.27 WHEN RCHL sample, THEN request Control Room Operator perform the following:

"* Close RC-422.

"* Close RC-423.

CONTINUOUS USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C IRev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 24 of 34 5.4.28 At the SAP perform the following:

5.4.28.1 WHEN RCHL sample, THEN perform the following:

"* Close RC-423-1.

"* Close CC-314.

5.4.28.2 WHEN RHR sample, THEN perform the following:

"* IF opened, THEN Close RHR-81A.

"* IF opened, THEN close RHR-81B.

"* Close CC-316.

5.4.28.3 Position RC-437-1 to VCT.

5.4.28.4 Position RC-437-2 to VCT.

5.4.29 WHEN off-site shipment of an undiluted sample is required, THEN contact a Chemistry Supervisor.

5.5 Containment Hydrogen (H2) Monitor IA & 1B Operation Procedure 5.5.1 WHEN sampling the Containment for hydrogen, THEN perform the following:

5.5.1.1 At the CASP perform the following:

5.5.1.1.1 Verify ventilation is ON and mode control switches are in NORMAL position.

5.5.1.1.2 Check High Vacuum Lights indicate NORMAL for the following:

  • CASP 5.5.1.2 Verify remote panels are in standby and have had 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> warm-up time.

5.5.1.3 Verify heat tracing is energized and operational.

CONTINUOUS USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C IRev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 25 of 34 Note Due to ALARA considerations,both containment airsample trains will be lined up to preclude additionalvalve lineups.

5.5.1.4 Contact the Control Room and perform the following:

5.5.1.4.1 Verify that Containment Dome Fans IA and lB are operating.

5.5.1.4.2 Inform the Control Room that both containment air sample trains will be lined up for sampling.

5.5.1.4.3 Request the Control Room perform the following valve lineup:

"* Close SA 7010A.

"* Open LOCA 2A.

"* Open LOCA 1OA.

"* Open SA 7003A.

"* Close SA7010B.

"* Position LOCA 2B LOCAL/REMOTE to LOCAL.

"* Open LOCA 2B.

"* Open LOCA 10B.

"* Position SA 7003B LOCAL/REMOTE to LOCAL.

"* Open SA 7003B.

Note Damage to the Hydrogen Analyzer will result if CASP is monitoring the same Train.

5.5.1.5 WHEN H2 Monitor 1A is to be used, THEN open AS-1 OA.

5.5.1.6 WHEN H2 Monitor 1B is to be used, THEN open AS- 11OB.

5.5.1.7 Inform the Control Room that the H2 Monitors are going to be started so that they can monitor their indication.

5.5.1.8 Switch selected analyzer to ANALYZE.

5.5.1.9 Switch selected analyzer to SAMPLE MODE.

5.5.1.10 Push the remote selector pushbutton to gain control at the remote panel.

CONTINUOUS USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C IRev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 26 of 34 5.5.1.11 Allow at least 10 minutes for sample purge time.

Note The ContainmentHydrogen Monitors read out remotely in the Control Room.

5.5.1.12 IF desired, THEN record Hydrogen Monitor indication on the Reactor Coolant Analysis Log (routine logsheet).

5.5.2 WHEN all Containment hydrogen sampling is complete, THEN perform the following:

5.5.2.1 Switch selected H2 Monitor to STANDBY.

5.5.2.2 WHEN H2 Monitor 1A was used, THEN close AS- 11OA.

5.5.2.3 WHEN H2 Monitor lB was used, THEN close AS- I10B.

5.5.2.4 Request the Control Room perform the following valve lineup:

"* Close LOCA 2A.

"* Close LOCA 10A.

"* Close SA 7003A.

"* Open SA 7010A.

"* Close LOCA 2B.

"* Position LOCA 2B LOCAL/REMOTE to REMOTE.

"* Close LOCA lOB.

"* Close SA 7003B.

"* Open SA 7010B.

"* Position SA 7010B LOCAL/REMOTE to REMOTE.

CONTINUOUS USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C IRev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Paqe 27 of 34 5.6 Flush of Liquid Sample Lines Note The purpose of this section is to reduce radiationlevels behind the liquid sample panel duringpost accident conditions.

5.6.1 At the SAP perform the following:

5.6.1.1 Position RC-437-1 to DDT.

5.6.1.2 Position RC-437-2 to DDT.

5.6.1.3 Open FPC-51.

5.6.1.4 WHEN performing an RCHL flush, THEN perform the following:

"* Open FPC-51-14.

"* Open CC-314.

"* Open RC-423-1.

5.6.1.5 WHEN performing a RHR flush, THEN perform the following:

"* Open FPC-51-41.

"* Open CC-316.

5.6.2 At the LSP perform the following:

5.6.2.1 WHEN performing a RCHL flush, THEN open RC-V-1.2.

5.6.2.2 WHEN performing a RHR flush, THEN open RC-V-1.1.

5.6.2.3 Open RC-V-2.

5.6.2.4 Open RC-V-7.

Note Flush time may be varied based on actualflushflow rate obtained.

5.6.2.5 Throttle RC-VREL-2 until flow indicator RC-FI-2 indicates 180 to 220 cc/min.

5.6.2.6 Flush at least 45 minutes.

5.6.2.7 IF unable to attain desired flush flow rate, THEN adjust flush time accordingly.

CONTINUOUS USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C I Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 28 of 34 5.6.3 At the SAP perform the following:

5.6.3.1 Close FPC-51.

5.6.3.2 WHEN RCHL line flush, THEN perform the following:

a. Close FPC-51-14.
b. Close RC-423-1.
c. Close CC-314.

5.6.3.3 WHEN RHR line flush, THEN perform the following:

a. Close FCP-51-41.
b. Close CC-316.
c. Close RC-V-1.l.

5.6.4 At the LSP perform the following:

5.6.4.1 WHEN RCHL line flush, THEN close RC-V-1.2.

5.6.4.2 WHEN RHR line flush, THEN close RC-V-.1.l.

5.6.4.3 Close RC-V-2.

5.6.4.4 Close RC-V-7.

5.6.4.5 Close RC-VREL-2, then open RC-VREL-2 approximately 1/2/2 turn.

5.6.4.6 Continue flush by opening RC-V-4.

5.6.4.7 Open RC-V-3.

5.6.4.8 Throttle RC-VREL-1 until positive indication of flow on RC-FI-1.

Note Additional time may be requiredif radiationlevels behind LSP have NOT stabilized.

5.6.4.9 Flush at least 15 minutes.

5.6.4.10 Close RC-V-3.

5.6.4.11 Close RC-V-4.

5.6.4.12 Close RC-VREL-1, then open RC-VREL-1 approximately /2 turn.

CONTINUOUS USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03C ]Rev. P Title Post Accident Operation of the High Kewaunee Nuclear Power Plant Radiation Sample Room Emergency Plan Implementing Procedure Date 152002 Page 29 of 34 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 Sentry HRSS Operating and Maintenance Manual 7.2 RCC-063, RCS Gaseous Activity 7.3 RCC-082, Boron Analysis Curcumin Method 7.4 RCC-201, HRSR Conductivity, YSI Dissolved Oxygen, and pH Analysis 7.5 RCC-202, Hydrogen - Gas Chromatography (G.C.) Analysis -

7.6 RCC-203, HRSR Post Accident Chloride-Ion Chromatography (IC) Analysis 7.7 RCC-520, DX-500 Startup and Shutdown Procedure 7.8 Commitment PLS-84-022 RQMT 2 - Step 5.3.14 (NOTE) 7.9 Commitment TEC-84-005, Step 5.1.13 and 5.1.14 7.10 EPIP-AD-11, Emergency Radiation Controls 7.11 OEA 93-160 7.12 KAP 1136, Corrective Action 2 8.0 Records 8.1 The following QA records and non-QA records are identified in this directive/procedure and are listed on the KNPP Records Retention Schedule. These records shall be maintained according to the KNPP Records Management Program.

8.1.1 QA Records None 8.1.2 Non-OA Records None CONTINUOUS USE

HIGH RADIATION SAMPLE VALVE LINEUP SHEET Page 1 of 5 Note Valves are listed as they appearon the panel, beginning in the top left hand corner working left to rightand top to bottom.

SAMPLE ACQUISITION PANEL FPC-51 ........................................ Sam ple Flush Line Iso ................................................ Closed RHR 81-B .................................... RHR Smpl Iso B Aux Cool .................. Closed FPC-51-41 ................................... RH R Sam ple Flush ..................................................... Closed RHR 81-A ................ RRR SMIPL Iso A Aux Cool ................. Closed R C-423-1 ..................................... R CHL Sm pl ................................................................ C losed CC-316 ................... RHR HRS HIx CC Flow .................... Closed FPC 51-14 ................................... RCHL Sm pl Flush ...................................................... Closed MGR-545-1 ............... VCT Gas Sp Smpl Iso B .................... Closed MGR-545 ................. VCT Gas Sp Smpl Iso A .................... Closed

- LD-75 .......................................... M /B D em in Inlet Smpl ............................................... Closed FPC-51-31 ................ M/B Demin Inlet Flush ..................... Closed LD -71 .......................................... M/B D emin Inlet Iso ................................................... Closed LD-85 ................... M/B Demin Outlet Smpl .................... Closed RC-437-1 ..................................... Sm pl Purge Divert A .................................................. V CT FPC-51-21 ................ M/B Demin Outlet Flush .................... Closed LD-81 .......................................... MfB Dem in Outlet Iso ................................................ Closed RC-437-2 ..................................... Smpl Purge D ivert B .................................................. V CT RC-403-1 ..................................... Przr Stm Sp Sm pl ........................................................ Closed FPC-51-12 ................ Pzr Stm Sp Smpl Flush ..................... Closed R C-413-1 ..................................... Pzr Liq Sp Smpl ......................................................... Closed FPC-51-13 ................ Pzr Liq Sp Smpl Flush ..................... Closed "CC-314 ........................................ Rx Cool HRS Hx CC Flow ......................................... Closed Attachment A EPIP-RET-03C Rev. P Date: JAN 1 5 2002 Page 30 of 34 CONTINUOUS USE

HIGH RADIATION SAMPLE VALVE LINEUP SHEET Page 2 of 5 Note Valves are listed as they appear on the panel, beginning in the top left hand corner working left to right and top to bottom.

LIQUID SAMPLE PANEL R C-V -12 ........................................ Argon to Eductor ......................................... Closed R C-V -15 ........................................ Gas Smpl to GC .......................................... Closed R C-V -14 ........................................ Argon Purge to Dil Gas Smpl ..................... Closed R C-V -13 ........................................ Dil Gas Smpl Vac ........................................ Closed RC-V -10 ........................................ Expansion Vessel Vacuum .......................... Closed R C-D V -2 ....................................... Diluted Gas Smpl ........................................ TO GC (3 o'clock)

R C-V -11 ........................................ Expansion Vessel Outlet ............................. CLOSED (12 o'clock)

R C-V -REL-1 ................................. RC Purge Throttle ....................................... Throttled RC-V -REL-2 ................................. RC Purge to Waste Tk ................................. Throttled RC-V -3 .......................................... RC Purge Stop ............................................. Closed R C-V -7 .......................................... Smpl Bomb Bypass ..................................... Closed R C-V -8.2 ....................................... Press Smpl Bomb Outlet ............................. Closed R C-V -9 .......................................... Expansion Vessel Inlet ................................ Closed R C-V -17 ........................................ Glove Box Grab Sample ............................. Closed R C-V -2 .......................................... RC Purge to Waste Stop .............................. Closed R C-V -18 ........................................ RC Purge/Backflush .................................... PURGE (6 o'clock)

R C-V -22 ........................................ RC Purge Waste/CAP ................................. WASTE (6 o'clock)

R C-V -6.2 ....................................... Rem Smpl Bomb Outlet .............................. Closed R C-V -5.2 ....................................... Rem Smpl Bomb Outlet Iso ........................ Closed R C-V -19 ........................................ Undiluted Liq Smpl ..................................... BYPASS (12 o'clock)

R C-D V -1 ....................................... Diluted Liquid Sample ................................ BYPASS (3 o'clock)

R C-V -1.1 ....................................... RHR Smpl Iso ............................................. Closed Attachment A EPIP-RET-03C Rev. P Date: JAN 15 2002 Page 31 of 34 CONTINUOUS USE

HIGH RADIATION SAMPLE VALVE LINEUP SHEET Page 3 of 5 Note Valves are listed as they appear on the panel, beginning in the top left hand cornerworking left to right and top to bottom.

LIOUID SAMPLE PANEL (continued)

RC-V-1.2 ....................................... RCHL/Pzr Smpl Iso ................................................... Closed RC-V-1.3 ....................................... (Spare) ........................................................................ Closed RC-V-1.4 ....................................... (Spare) ........................................................................ Closed RC-V-1.5 ....................................... VCT Gas Sp Smpl Iso ................................................ Closed RC-V-21 ........................................ Dilution H2 0 to Diluted Sample ................................ Closed RC-V-8.1 ....................................... Press Smpl Bomb Inlet ............................................... Closed RC-V-16 ........................................ Argon Gas Strip Purge ............................................... Closed RC-V-4 .......................................... DI W ater Flush Iso ..................................................... Closed --

RC-V-6.1 ....................................... Rem Smpl Bomb Inlet ................................................ Closed

"- RC-V-5.1 ....................................... Rem Smpl Bomb Inlet Iso .......................................... Closed LIOUID SAMPLE PANEL (Demin Section)

DM -V-l.1 ...................................... CVCS M/B Inlet ......................................................... Closed DM -V-1.2 ...................................... CVCS M/B Outlet ...................................................... Closed DM -V-1.3 ...................................... (Spare) ........................................................................ Closed DM -V-3 ......................................... DI Water Flush ........................................................... Closed RW -V-6 ......................................... Radwaste .................................................................... Closed DM -V-2.1 ...................................... CVCS Demin Inlet Smpl ............................................ Closed DM -V-2.2 ...................................... CVCS Dem in Outlet Smpl ......................................... Closed DM -V-2.3 ...................................... (Spare) ........................................................................ Closed Attachment A EPIP-RET-03C Rev. P Date: JAN 1 5 2002 Page 32 of 34 CONTINUOUS USE

HIGH RADIATION SAMPLE VALVE LINEUP SHEET Page 4 of 5 Note Valves are listed as they appear on the panel, beginningin the top left hand corner working left to right and top to bottom.

CHEMICAL ANALYTICAL PANEL V -10 ............................................... Inst Air Supply ......................................... Open V-12 ............. ......... Nitrogen Supply ....................................... Open V-14 ............................................... Argon Supply to GC ................................ Open V-13 ............................................... IC Inject Port ............................................ Closed (3 o'clock)

V-7 ....... ,.......... ........ o... 02 Analyzer Select ................................... YSI (6 o'clock)

V-8 .... . . .,....................... 02 Loop Outlet ......................................... Open V-6 .... . ............ ............. 02 Loop Select ......................................... 0 2 - Cal (6 o'clock)

V -5 ............... ....... ................. IC Loop Select .......................................... Closed (6 o'clock)

V -2 ..... ................ ................ IC Smpl Outlet ......................................... Open V-.1 .. .................................... GC Smpl Inlet .......................................... Open V -27 ............................................... pH Cal Tk 1 N2 Supply ............................ VENT (6 o'clock)

V -28 ............................................... pH Cal Tk 2 N2 Supply ............................ VENT (6 o'clock)

V -29 ............................................... Cal-3 N2 Supply ....................................... VE NT (6 o'clock)

V -1I ............................................... DI W ater Supply ...................................... Closed V -24 ............................................... 02 Cal Tk Fill ........................................... Closed V-17 ............................................... 02 Cal Tk Recirc ...................................... Closed V -9 ......... . . ..... .......... 02 Anal Cal Supply .................................. Closed V-26 ............................................... pH Cal Tk 1 Supply ................................. Closed V -16 ............................................... pH Cal Tk 2 Supply ................................. Closed V -15 ............................................... Cal-3 Supply ............................................ Closed V -30 ............................................... pH Cal Tk Select ...................................... CAL-1 V -25 ............................................... pH Cal Tk 1 Drain .................................... Closed V-20 ............................................... pH Cal Tk 2 Drain .................................... Closed V -19 ............................................... Cal-3 Drain ............................................... Closed V-18 ............................................... 02 Cal Tk Drain ....................................... Closed Attachment A EPIP-RET-03C Rev. P Date: JAN 1 5 2002 Page 33 of 34 CONTINUOUS USE

VALVE LINEUP SHEET Page 5 of 5 CASP CONTROL PANEL AV-1i/SV-1.2 .............. Smpl Pos #1 Inlet/Outlet ................................................................. Closed SV-2.1/SV-2.2 ............ Smpl Pos #2 Inlet/Outlet ................................................................. Closed SV-3.1/SV-3.2 ............ Smpl Pos #3 Inlet/Outlet ................................................................. Closed SV-4. 1/SV-4.2 ............ Smpl Pos #4 Inlet/Outlet ................................................................. Closed SV-5 ........................... Smpl Bypass .................................................................................... Closed SV-10 ......................... Air to Eductor .................................................................................. Closed AV-2 ........................... Return to Containm ent .................................................................... Closed SV-6 ........................... Eductor Suction Iso ......................................................................... Closed (At Sample Acquisition Panel)

AS110A ...................... Cont Air Smpl A Iso ....................................................................... Closed ASl10B ...................... Cont Air Smpl B Iso ....................................................................... Closed I.M.C.C. CONTROL PANEL HS-3 ........................... Dilution Water Bite Valve ................................................................ Off "HS-4 ........................... Air/W ater Flush Valve ...................................................................... Off HS-5 ........................... Pressurized Reactor Cool. To I.M .C.C ............................................. Off HS-6 ........................... Reactor Cool. Bite Valve ................................................................. Off HS-7 ........................... M ixing Chamber Flush/Vent Valve .................................................. Off HS-8 ........................... Undil. RX. Cool. Smpl Outlet Valve ................................................ Off HS-9 ........................... Undil. RX. Cool. Smpl/Divert Valve ................................................ Off I.M.C.C. CONTROL PANEL HS-10 ......................... M ixing Chamber Outlet Valve .......................................................... Off HS-11 ......................... Dil. RX. Cool. Smpl Outlet Valve .................................................... Off HS-12 ......................... Depressurized RX. Cool. to I.M .C.C ................................................ Off HS-13 ............. Degasifier Outlet/Flush Valve .................................................... Off HS-14 ......................... Dil. Wtr. Outlet Valve ....................................................................... Off HS-15 ......................... Air Flush to M ixing Chamber ........................................................... Off HS-16 ......................... Gas M arinelli Bypass Valve ............................................................. Off M ain Power Switch ............................................................................................................ On Attachment A EPIP-RET-03C Rev. P Page 34 of 34 Date: JAN 1 5 2002 CONTINUOUS USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03D Rev. N Title Containment Air Sampling Analysis Using Kewaunee Nuclear Power Plant CASP Emergency Plan Implementing Procedure Date JAN 15 2002 Page 1 of 10 Reviewed By (2_-ApprovedBy 0 Yes Nuclear 0 Yes PORC 0 Yes SRO Approval Of Safety Review Temporary 0 No Required El No Changes Required 0 No Related 1.0 Purpose 1.1 This procedure provides instruction for drawing and analyzing containment samples when directed by the Radiological Protection Director (RPD).

2.0 General Notes 2.1 This procedure is designated CONTINUOUS USE.

2.2 This procedure is to detail the requirements, considerations, and operations of the Containment Air Sample Panel (CASP) during a Post LOCA condition, to obtain a grab--

sample of Containment air for Gross Gas, Iodine, Hydrogen, and Oxygen analyses.

3.0 Precautions and Limitations 3.1 Process an Emergency Radiation Work Permit as needed per EPIP-AD-1 1, "Emergency Radiation Controls."

3.2 Contact the Radiation Protection (HP) Group and obtain the following:

  • Proper personnel dosimetry
  • Proper radiation detection instrumentation
  • Personnel for continuous HP coverage during sampling
  • Remote area monitor readings in area of High Radiation Sample Room (HRSR) 3.3 Utilize on-site communications with the RPD as necessary during sampling.

3.4 Any sample drawn from the post accident containment atmosphere should be assumed to contain specific activity of the following magnitude:

  • Gas 5.0 Millicuries/cc
  • Iodine 0.2 Millicuries/cc 4.0 Initial Conditions 4.1 The site has declared an Alert, Site Emergency, General Emergency, or the Shift Manager or Emergency Director has implemented the use of this procedure.

n.Nnucdoc\procedures\draft\epip\eret03d.doc-BilI HollingsworthUChristine Simmons-Darryl Holschbach

5.0 Procedure atmosphere.

5.1 Obtain all necessary equipment prior to beginning to sample the Containment This equipment includes:

  • Operable CASP System with Inline Sample Chamber (ISC) Cart in Sample Station #1
  • 5.0 microliter gas syringe (2)
  • 1.0 cc gas syringe or equivalent (2)
  • 2.0 cc gas syringe or equivalent (1)
  • An iodine cartridge holder (1)
  • Several small rubber stoppers (3 to 5)
  • Portable shields for transporting syringes
  • Marinelli beaker (give to HIP to be counted prior to sample injection)
  • Specially adapted 1 liter poly-bottle (for Gross Gas analysis) 5.2 WHEN preparing for CASP operation, THEN perform the following:

5.2.1 Proceed to HRSR per HP/RPD recommendations.

if access is 5.2.2 Determine radiation levels in HRSR and in maintenance area behind panels, required.

5.2.3 Verify that heat tracing is ON.

lights indicate 5.2.4 Verify ventilation is ON and in NORMAL position and high vacuum (CAP), and NORMAL for the Liquid Sample Panel (LSP), Chemical Analysis Panel CASP.

5.2.5 Verify that instrument air supply is available at >_70 psi.

5.2.6 Verify that CASP and CASP control panels are energized and operational.

Sheet."

5.2.7 Verify valve lineup per Attachment A, "Containment Air Sample Valve Lineup CONTINUOUS USE

Note The sample cart may be checked to verify it is properly locked in place by carefullypulling.

5.2.8 Verify the ISC in the #1 position is locked in place.

Note Only Sample Station 1 shall be usedfor Iodine Analysis.

be Due to ALARA considerations,if available, both containment airsample trainsshould aligned.

5.2.9 Contact the Control Room and verify Dome Fans 1A and lB are operational.

5.2.10 Request Operations perform the following valve lineup at the Post-LOCA Hydrogen Control Panel:

"* Open LOCA 2A.

"* Open LOCA 1OA.

"* Open SA 7003A.

"* Position LOCA 2B (Local/Remote) to LOCAL.

"* Position SA 7003B (Local/Remote) to LOCAL.

"* Open LOCA 2B.

"* Open LOCA 1OB.

"* Open SA 7003B.

5.2.11 Verify that one of the following conditions are in effect AND select a Sample Loop (A or B):

a. The hydrogen monitor is NOT in operation, OR
b. The sample loop selected is opposite that being used by H2 monitor.

5.2.12 WHEN using Containment Air Sample Train 1A, THEN open AS 11A.

5.2.13 WHEN using Containment Air Sample Train IB, THEN open ASI 10B.

5.2.14 Open SV-10.

5.2.15 Open SV-6.

5.2.16 Open SV-5.

5.2.17 Verify flow monitor on CASP is indicating flow.

CONTINUOUS USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03D Rev. N Title Containment Air Sampling Analysis Using Kewaunee Nuclear Power Plant CASP Date JAN 15 202 Pa 4 Emergency Plan Implementing Procedure 5.2.18 Wait at least 2 minutes.

5.2.19 Open AV-1/SV 1.2.

5.2.20 Close SV-5.

5.2.21 Open AV-2.

5.2.22 Wait at least 3 minutes.

5.2.23 Align the ISC Cart as follows:

5.2.23.1 Open V-4, Cart Inlet Valve.

5.2.23.2 Open V-6, Outlet Valve.

5.2.23.3 Close V-5, Bypass Valve.

5.2.23.4 Verify CASP flow monitor is indicating flow.

5.3 WHEN collecting a Containment Air sample, THEN perform the following:

5.3.1 Close SV-6.

5.3.2 Verify flow monitor on CASP indicates NO flow.

Note An appropriateperiodforflow monitorpressure equalization is one minute.

5.3.3 Allow the flow monitor to equalize pressure for at least 1 minute.

5.3.4 WHEN pressure equalization period is complete, THEN obtain Containment atmosphere samples as follows:

5.3.4.1 Draw the following samples from the ISC.

a. Two 5 microliter samples
b. IF using the Baseline 1010A Gas Chromatograph, THEN obtain 2 - 1.0 cc syringe samples.
c. IF using the SRI 8610 Gas Chromatograph, THEN obtain 1 - 2.0 cc syringe sample.

CONTINUOUS USE

I Rev. N VlA ,ilq/ilft *,,.CI11 lr , I.RI,. ir"*~rVi..a .i vvRN. .......... ... Re. N Title Containment Air Sampling Analysis Using Kewaunee Nuclear Power Plant CASP Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 5 of 10 5.3.4.2 IF the radiological condition of the syringes are NOT satisfactory, THEN perform the following:

5.3.4.2.1 Lock the tips.

5.3.4.2.2 Insert the needle of each syringe in a rubber stopper to prevent damage.

5.3.4.2.3 Place the syringes in a portable shield for transport.

5.3.5 Use the predetermined route to minimize personnel exposure while transporting the shielded syringes or samples for analysis.

5.4 WHEN shutting down and cleaning out the system, THEN perform the following:

5.4.1 Close AS 11 OA OR AS 11 B, as appropriate.

5.4.2 Open SV-6 and evacuate the ISC cart.

5.4.3 Wait at least 2 minutes.

5.4.4 Close V-4, Cart Inlet Valve.

5.4.5 Close V-6, Outlet Valve.

5.4.6 Open V-5, Bypass Valve.

5.4.7 Open AS 11OA OR AS 11GB, as appropriate.

5.4.8 Close AV-2.

5.4.9 Verify flow monitor has flow.

5.4.10 Wait at least 2 minutes.

5.4.11 Open SV-5.

5.4.12 Close AV-1/SV1.2.

5.4.13 Verify flow monitor has flow.

5.4.14 Wait at least 1 minute.

5.4.15 Close SV-10.

5.4.16 Close SV-6.

5.4.17 Close SV-5.

CONTINUOUS USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03D IRev. N Title Containment Air Sampling Analysis Using Kewaunee Nuclear Power Plant CASP Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 6 of 10 5.4.18 Close AS11 OA OR AS1 OB, as appropriate.

5.4.19 Reset "Active/Inactive" indicator lights to INACTIVE.

5.5 WHEN analyzing a sample for Iodine, THEN perform the following:

5.5.1 Place a Silver Zeolite sample cartridge in a holder.

5.5.2 Attach a hose from the holder to a vacuum source in the HRSR Fume Hood.

5.5.3 Establish air flow through the filter cartridge.

5.5.4 Inject a 5.0 microliter gas sample upstream of the filter cartridge allowing the gas to flow through the Silver Zeolite cartridge.

5.5.5 Remove the Silver Zeolite cartridge from its holder and monitor it for radiation. -7 5.5.6 Transfer the Silver Zeolite cartridge to the Radiation Protection Group for counting.

Note PointBeach NuclearPlant uses an identicalgeometry as Kewauneefor counting iodine samples.

5.5.7 IF the Count Room is NOT accessible OR the Multi-Channel Analyzer (MCA) is NOT operable, THEN the cartridge may be sent to Point Beach Nuclear Plant for analysis.

Note Furtherdilution may be necessaryfor counting.

5.6 WHEN analyzing a sample for Gross Gas activity, THEN perform the following:

5.6.1 WHEN the Count Room is habitable AND the MCA is operable, THEN perform the following:

5.6.1.1 Inject a 5 microliter gas sample into a marinelli beaker that has been cleared for use by the Radiation Protection Group.

5.6.1.2 Return the sample to the Radiation Protection Group for counting.

5.6.2 IF the Count Room is NOT habitable OR the MCA is NOT operable, THEN perform the following:

5.6.2.1 Inject a 5 microliter gas sample into the specially adapted 1.0 liter poly bottle.

5.6.2.2 Request Radiation Protection Group transfer the sample container to Point Beach Nuclear Plant for Gross Gas activity determination.

CONTINUOUS USE

WISCONSIN PUBLIC SERVICE CORP. No. EPIP-RET-03D Rev. N Title Containment Air Sampling Analysis Using Kewaunee Nuclear Power Plant CASP Emergency Plan Implementing Procedure Date JAN 1 5 2002 Page 7 ofl1 5.7 WHEN analyzing a sample for Hydrogen and Oxygen, THEN perform the following:

5.7.1 Based on the gas chromatograph to be used, refer to the appropriate chemistry procedure for operating instructions as follows:

RCC-080, "Gas Chromatograph, Baseline 1010A

" Baseline 101OA Gas Operation Using a Chart Recorder" Chromatograph RCC-080D, "Operation of the Baseline 1010A Gas Chromatograph Using Computer Software"

" SRI 8610 Gas Chromatograph RCC-080C, "Operation of the SRI 8610 Gas Chromatograph" 5.7.2 Verify that the gas chromatograph is:

"* Turned on

"* Operating properly

"* Correctly calibrated 5.7.3 WHEN the gas chromatograph is verified operable, THEN perform the following:

5.7.3.1 WHEN injecting the sample into the Baseline 1010A gas chromatograph, THEN inject the 1.0 cc gas sample into the gas partitioner and await results.

5.7.3.2 WHEN injecting the sample into the SRI 8610 gas chromatograph, THEN inject the 2 cc gas sample into the gas partitioner and await results.

5.7.4 Report all results obtained to the RPD.

CONTINUOUS USE

5.8 WHEN the Containment Air sampling lineup is to be secured, THEN request Operations perform the following at the Post-LOCA Hydrogen Control Panel:

  • Close SA 7003A.
  • Close SA 7003B.
  • Position LOCA 2B (Local/Remote) to REMOTE.
  • Position SA 7003B (Local/Remote) to REMOTE.

6.0 Final Conditions 6.1 This procedure is closed out when the Plant Emergency has been Terminated or Recovery EPIPs.

actions have begun and the Emergency Response Manager has suspended the use of 7.0 References 7.1 Sentry HRSS Operating and Maintenance Manual 7.2 EPIP-AD-1 1, Emergency Radiation Controls 7.3 RCC-080, Gas Chromatograph, Baseline 1010A Operation Using a Chart Recorder 7.4 RCC-080C, Operation of the SRI 8610 Gas Chromatograph Software 7.5 RCC-080D, Operation of the Baseline 1010A Gas Chromatograph Using Computer 7.6 TS 6.1 l.b.2 CONTINUOUS USE

8.0 Records and 8.1 The following QA records and non-QA records are identified in this directive/procedure be maintained are listed on the KNPP Records Retention Schedule. These records shall according to the KNPP Records Management Program.

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

CONTAINMENT AIR SAMPLE VALVE LINEUP SHEET CASP CONTROL PANEL Close AV -1 / SV -1.2 .................. Smpl Pos #1 Inlet / Outlet ................................................................

Close SV -2.1 / SV -2.2 ................ Smpl Pos #2 Inlet / Outlet ................................................................

Close SV-3.1 / SV -3.2 ................ Sm pl Pos #3 Inlet / Outlet ................................................................

Close SV -4.1 / SV -4.2 ................ Smpl Pos #4 Inlet / Outlet ................................................................

Smpl Bypass .................................................................................... Close SV -5 .................................

Instr. Air to Eductor ......................................................................... Close SV -10 ...............................

Return to Containm ent ..................................................................... Close_

AV -2 .................................

Eductor Suction Isol ......................................................................... Close SV -6 .................................

SAMPLE ACQUISITION PANEL Cont Air Sm pl A Isol ....................................................................... Close A S 110A ............................

Cont Air Sm pl B Isol ....................................................................... Close AS110B ............................

INLINE SAMPLE CHAMBER (SF1)

Sam ple Inlet V alve ........................................................................... Close V-4 ....................................

Sam ple Bypass V alve ...................................................................... Open V -5 ....................................

Sam ple Outlet V alve ........................................................................ Close V -6 ....................................

.. . .. .. . . .. . . . . Don a fl nf 1j Attachment A EPIP-RET-03D Rev. N Cate:JAN bU =1 ~*J w i l*

CONTINUOUS USE S------.........-......-.---.----.---

Retrieved from "https://kanterella.com/w/index.php?title=ML020440560&oldid=2202268"