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{{#Wiki_filter:t liVD/AiVA8r MICHIGAN t
EIECYIIIC COMPANY DONALD C. COOK NUCLEAR PLANT PROCEDURE COVER SHEET Procedure NoPMP 2081 EPP. 023 Re~gIog No,  CANCELLED TITLE ACTIYATION AND OPERATIONS OF THE EMERGENCY CONTROL CENTER (ECC) (AN EMERGENCY OPERATIONS FACILITY)
SCOPE OF REVISION REASON FOR CANCELLATION:    SUPERSEDED  BY PMP 2081    EPP.022.
OCR JUg  P  71982 SIGNATURES ORIGINAL    CANCELLED            REV. 2        Rev. S PREPARED BY QUALITY ASSURANCE REVIEW                                          4,A.
INTERFACING DEPARIMENT HEAD CONCURRENCE                N.A.
DEPAR'IDENT HEAD APPROVAL                        N.A.          N PLANT NUCLEAR                                      A'.A.
SAFETY COMMITTEE PLANT MANAGER APPROVAL DATE OF ISSUE                  3-31-81 ram No. PN 2010.l - tv. s 82062S0009      820618 PDR'ADOCK 05000315'.
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PMP EPP INDEX INDIANA 5 MICHIGAN PONER COMPANY DONALD C. COOK HUCLm~"R PLANT PLANT MANAGER PROCEDURE Index Identification                  Ti tie                    Revision Nc.~          Comments Number                                                    And Oat PMP 2881 EPP.014  Off-Site  Dose Assessments              Revision  0    TP-1,2-25-82 Exp N/A 4-1-81 EPP.015  Sampling and Analysis        of        Revision  0 Waterborne Releases.
* 4-1-81 EPP.016  Collection  and Analysis of            Revision  0 Liquid and  Gaseous Samples              4-1-81 Interpretation of Liquid        'PP.017 Revision  0 and Gaseous    Samples                    4-1-81 EPP.018 'ransportation Accidents                  Revision 0 Involving Radioactive                    4-1-81 Material EPP.019  AEP  Emergency Response                  Revision  0 Organi za ti            ti on Acti va on and            4-1-8$
Management EPP.020  Activation    and Operation of          Revision  0    TP-1,11-16-81 Exp N/A the Technical Support Center              4-1-81      TP-2,3-12-82 Exp N/A (TSC)                                                  TP-3,3-12-82 Exp N/A EPP.021  Activation    and Operatio'n of          Revision  1 the Operations Staging Area                5-25-82 (OSA) and Personnel Accountability EPP.022  ActiVation    and Operation of          Revision  1 the Emergency Operations                6-4-82 Facility EPP.023  Activation    and Operation of          CANCELLED the Emergency Control Center              82.
(ECC) (An Emergency Operations    Facility)
EPP.024  Activation and Operation of Revision              0.
the Joint Public Information              4-1-81 Center (JPIC) (An Emergency Operations Facility)                                      ; ace.
Rev    Oat~ Q  7A
 
  ~ ~ ~
        ~ ~
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t liiDIAIVA8 MICHIGA EI.ECTBIG COMPANY DONALD C COOK NUCLEAR PLANT
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PROCEDURE COVER SHEET Paced<<e No    PMP 2081 EPP.022 Revision No.
TITLE ACTIYA'ZION.ANO'OPERATION.OF THE EMERGENCY qPERAT/ONS FACILITY SCOPE OF REVISION Rev. 1:      Revised the operation  of the  EOF  to  a single location as per NRC  reqUirements.
JUN 0 71982 SIGNATURES ORIGINAL        Rev. I            REV. 2        Rev, 3 PREPARED RY QUALITYASSURANCE REVIEW INTERFACING DEPARTMENT HEAD CONCURRENCE                      N.A.            gA DEPARTMENT HEAD APPROVAL                              N.A.          IV.A PLANT NUCLEAR SAFI'IY COMMIITEE PLANT MANAGER APPROVAL DATE OF ISSUE                        3-31-81 Fcan No. PSQ 2010 1- acv. s
 
~ ~ i t                        PMP-2081-EPP.022 LIST OF EFFECTIVE PAGES PAGE NUMBER                      REVISION NUMBER AND DATE Page  1 of  5                    Revision 1,  6 4 82 Page 2  of  5                    Revision 1,  6 4 82 Page  3  of  5                    Revision 1, 6 4 82 Page  4  of  5                    Revision 1; 6-4-82 Page  5  of  5                    Revision 1, 6-4-82 EXHIBIT A page  1  of 1                    Revision 1,  6 4-82 EXHIBIT B page  1  of 1                    Revision 1, 6-4-82 EXHIBIT  C Page  1  of 1                    Revision 1,  6 4 82 EXHIBIT  D Page  1  of 3                    Revision 1, 6-4-82 Page 2  of 3                    Revision 1, 6-4-82 Page 3  of 3                    Revision 1;  6 4-82 Page  1, of 1 Rev. 1;6482
 
MP-2081-EPP.022 INDIANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT ACTIVATION AND OPERATION OF THE EMERGENCY OPERATIONS  FACILITY 1.0 OBJECTIVE 1.1  This procedure defines the responsibilities of individuals in the Emergency Operations Facility (EOF);
the interfaces of the EOF with other centers and organizations; the operation of the EOF during short-term emergency response; and the staffing necessary to carry out these functions.
2.0 RESPONSIBILITIES AND FUNCTIONS 2.1  Responsibilities        See Exhibit  A for the  Emergency Operations      Facility Organization.
2.. 1 . 1      Radiation Control arid Waste Handling Manager (RCWHM): Assistant Plant Manager 2.1.2          Communications  Director: Production Supervisor, Technical 2.1.3          Communications Personnel:    Training Instructors, Performance Engineers, Operations Quality Control Implementation Coordinators 2.1.4          Radiological Assessment  Director:    R.P.
Performance Engineer 2.1.5          Radiation Protection Manager: Plant Radiation Protection Supervisor 2.2  Functions      The EOF,  upon activation, will assume responsibility for performing the following functions:
2.2.1          Management of overall IGM response 2.2.2          Coordination of radiological and environmental assessment 2.2.3          Determination of recommended public protective actions Page  1  of 5 Rev-  1,6~82
 
2.2.4      Coordination of emergency response activities with Berrien County, the State of Michigan, and the Federal Government.
2.3  The Emergency  Operations Facility is a support facility established for the purpose of performing the above functions. The EOF shall have appropriate technical data information and plant records to assist in the diagnosis of plant conditions to evaluate the potential or actual release of radioactive materials to the environment. An Assistant Plant Manager in this center shall organize and manage I&M support (dose assessment, communication, and radiation protection) resources to support the TSC and control room operators.
3.0 LIMITATIONS AND PRECAUTIONS 3.1  The Emergency    Operation  Facility shall be activated as necessary    for any emergency condition and specifically for Site  Emergencies and General Emergencies.        This procedure covers the operation of the EOF until establishment of the AEP Emergency Response Organization on-site and/or      until deactivation of    the EOF.
4.0 INSTRUCTIONS 4.1  Upon  recognition of the need for, or desirability of activating the EOF, the On-Site Emergency Coordinator shall direct the Communications Director to initiate PMP-2080-EPP.008, calling off-duty Plant personnel for the purpose of staffing the EOF.
4.2 The initial people to arrive in the EOF should prepare the facility for operation by performing the following:
4.2.1      Unlock the  EOF  equipment cabinet.      The key may be  obtained from the Shift Security Supervisor or from the Training Department secretary.
4.2.2      Turn on the radiation monitor.      Instructions are posted on the monitor.
4.2.3      Set up the communications/dose    assessment room and "command  center" for operation, as per Exhibit D.
4.2.3.1    Set up tables and chairs.
Page 2  of  5 Rev 1  ,  6-4-82
 
MP-2081-EPP.022 4.2.3.2    Set up telecopier.
4.2.3.3    Set out telephones.
4.2.3.4    Set out the headset    for the board writer.
4.2.4      Turn on Xerox machine.
4.3 The Radiation Control and Waste Handling Manager          shall manage I&M support activities (dose assessment, communications,      and radiation protection) from the and  interface with the On-Site Emergency Coordinator.EOFg Specifically, the RCWHM shall:
4.3.1        Oversee arrangement of the training building as the EOF. See Exhibit D.
4.3.2        Establish communications directly as needed, with the OSEC for the purpose of managing I&M response to the event.
4.3.3        Ensure the EOF assumes responsibility for communication with off-site organizations.
4.3.4      Ensure the    EOF assumes  dose assessment    and protective action decision-making responsibilities.
4.3.5      Coordinate I&M and Federal, State, and local response to the event via:
4.3.5.1      Information passed both ways through the communicators.
4.3.5.2      Establishing the    "command center",
as needed. See  Exhibit  D.
4.3.5.3      Establishing the NRC room, as needed. See Exhibit D.
4.3.5.4      Establishing the New York Emergency Response Organization room, as needed. See Exhibit D.
4.3.6      Complete the top portion of Exhibit C for use by the Radiological Assessment Director.
4.3.7      Ensure Exhibit C is normally developed every 15 minutes.      Approve Exhibit C upon completion and prior to release to off-site organizations.
Page 3  of 5 Rev. 1,6482
 
MP-2081-EPP.022 4.3.8      Remain cognizant. of the activi ~ - of the Radiation Protection Manager =:.". response to the emergency.
4.3.9      Direct the Shift Security Supervisor to establish security controls around the EOF building. These controls shall ensure that access is restricted to personnel assigned to the EOF.
4.4 The Communications    Director shall perform the following functions:
4.4.1      Establish    a chronological history log of events and make this log available to communications, dose assessment, radiation protection, and "command center" personnel.
4.4.2      Ensure  that detailed event data, Exhibit B, is  made  available regularly to communications, dose assessment and radiation protection personnel.                  this data will be provided every Normally fifteen minutes by telecopiert from the TSC.
4.4.3      Ensure the communicators,      dose assessment  and radiation protection personnel are brought up-to-date regarding event data and information required to perform their functions.
4~4~4      Establish communication with the Berrien County Sheriff's Department, Michigan State Pol~ice, Nuclear Regulatory Commission, American Electric Power Initial Assessment Group and  Public Affairs. Assume responsibility for this function from the TSC.
4.4.4.1    Exhibit  B  is to  be provided to  NRC and AEP, and    to the JPIC  and Westinghouse    as needed.
4.4.4.2    Exhibit C is to be provided to AEP, the JPIC, the Berrien County Sherif f ' Department, and the Michigan State Police. Exhibit C is also to be supplied to the NRC as needed.
Page 4 of  5 Rev. 1
 
MP-2081-EPP.022 4.4.5      Assume  responsibility for the dose assessment and  radiation protection functions from the TSC.
4.4.6      Communicate requests  from off-site  groups to the Technical Director.
4.5 The  Radiological Assessment Director is responsible for:
4.5.1.      Performing dose calculations for on-site and off-site areas and reporting these results to the Communications Director and Radiation Control and Waste Handling Manager.
4.5.2      Recommending protective actions    on-site  and off-site when appropriate.
4.6 The  Radiation Protection Manager is responsible for:
4.6.1      Implementing the emergency radiation protection program including personnel monitoring and decontamination.
4.6.2      Directing activities of Radiation Monitoring teams and reporting results to the Radiation Control and Waste Handling Manager.
4.6.3      Directing the activities of Re-entry and Rescue teams, as appropriate.
4.6.4      Coordinating first-aid activities.
Page 5 of 5 Rev. 1, 6-4-82
 
(OPERATIONS STAGING AREA)                                          (TECHNICAL SUPPORT CENTER)                                          (EMERGENCY OPERATIONS FACILITY)
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I AL INFORMATION SHEET                            PMP  2081.EPP.022 EXHIBIT B D. C. Cook      Unit No:        Data Taken By                                  Date                  Time RCS PARQKTER
: l.      RWST  I,evel                                                2. Containment Pressure                      PSIG 3~      Containment  Sump  Level                                  4. Containment Ievel                        0/
: 5.      BIT Flow              LP1                GPM    LP2            GPM LP3                GPM    LP4              GPM
: 6.      SI Flow            North                GPM    South              GPM
: 8.      RHR To CTS  Flow East                  GPM      West            GPM
: 9.      CTS                East (ON      OFF        )      West (ON        OFF      )
: 10. RCP  Status  LP1 .(ON  OFF    )    LP2 (ON        OFF    )  LP3    (ON    OFF    )    LP4 (ON    OFF        )
: 11. RCS  Press.              PSIG ~ 0      4                    12. PZR Ievel
: 13. PZR Liquid Temp.          F                                  14. PZR Steam Temp.              F
: 15. PZR Backup Htrs.    (ON    OFF      )                      16. PZR Cycling Htrs.        (ON    OFF    )
: 17. Charging Flow            GPM                                18. Ietdown Flow              GPM NSSS IOOP PARAMETERS                ~Leo        1          ~Leo  2            ~Loo  3            ~Leo    4
: 19. Wide Range T                                    OF                  op                  OF                  OF
: 20. Wide Range TC                                    OF                  OF                  OF                  OF
: 21. S/G Pressure                                    PSIG                PRIG                PSIG                PSIG w
22e    S/G N.R. I,evel                                  /
: 23. 3/0 S.R. Level
: 24. Steam Flow (pph K 100)
: 25. Feed Flow (pph K 10 )
: 26. Aex. Feed Flow(pph K 10 )
27      MSIV  Status                    (OP        CL      )    (OP    CI    )  (OP    CL    )      (OP  CL      )
      '8.
CST  Ievel                                                          Ft.
DOSE PARAMETERS                                                                  SPECIAL NOTES      OR DATA
: 29. R-2 Contain. Area                  R/Hr.
: 30. R-11 Contain. Part.                CPM
: 31. R-12 Contain. Gas                  CPM
: 32. R-33 Gland Exh. Vent                CPM
: 33. R-15 Air Ejector Vent              CPM
: 34. R-26 Vent Stack Gas                CPM
: 35. Vent Flow
: 36. GSLO Flow
: 37. SJAE Flow
: 38. Wind Speed                        MPH
: 39. Wind Direction                    4 (From)
: 40. Air Temp. bT                      oC Data    Verified  By Page    1  Of 1 Revision 1, 6-4-82
 
J ACCIDENT      ORMATION REPORTING DATA SHEE                    PMP  2081 EPP.022 EXHIBIT  C D.C. Cook Unit            Date Descriptioa of Event Prognosis For Terminatioa Or Worsening Classification:        Unusual Event        Alert      Site Emergency          General  Emergency Injured Personnel:    Yes, Number        , No        Radioactivity Contaminated:        Yes    No Estimated Duration of Release Basis for Projected    Dose Calculation Source Term  for Calculation                            Flow  for Calculation Monitor Readiag                                            Measurements Upper Limit of Moaitor Range                              Upper Limit on Containmeat Dose Rate 6" from Effluent Pipe                                    I,eak Rate Sample                                                      Time Plow Obtained Time Source Term Obtained I
Measured Dose Rate I
  ~ Iocation of FQ Time of Measurement Measurement Dose Rate Iodine Conc.
Meteorological Coaditions:      Wind Speed  (mph)
Wind  Direction:    From          To Stability Class:    AT          Pasqulll Cat.      A  D  C  D E Precipitation:      Yes          No Release Rate:    Total  Gas                    Ci/sec    Release Height: Ground Level Projected Dose At:                Site Boundary      2  Miles      5 Miles          10  Miles Dose Rate, Whole Body, R/hr
        -Integrated Dose,  Whole Body, R Dose Rate, Thyroid, R/hr
        -Integrated Dose, Thyroid,    R Sectors Affected
        -Iategrated from the time of    initial calculation  to ead of projected release.
Time  Calculation Performed                            Input Verified t Support Requested From State or County Agencies:
  ,'--.=                                                          Yes      No Type Recommended  Emergency Actioas For State    or County Agencies Page  1  Of 1 Revision 1,6-4-82
 
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Revision as of 06:37, 29 October 2019

Public Version of Notice of Cancellation of Emergency Plan Procedure PMP 2081 EPP.023 Re Activation & Operation of Emergency Control Ctr.Procedure Superseded by Procedure PMP 2081 EPP.022.Revised Index Encl
ML17319B391
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 06/07/1982
From:
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17319B389 List:
References
PROC-820607-01, NUDOCS 8206250009
Download: ML17319B391 (20)


Text

t liVD/AiVA8r MICHIGAN t

EIECYIIIC COMPANY DONALD C. COOK NUCLEAR PLANT PROCEDURE COVER SHEET Procedure NoPMP 2081 EPP. 023 Re~gIog No, CANCELLED TITLE ACTIYATION AND OPERATIONS OF THE EMERGENCY CONTROL CENTER (ECC) (AN EMERGENCY OPERATIONS FACILITY)

SCOPE OF REVISION REASON FOR CANCELLATION: SUPERSEDED BY PMP 2081 EPP.022.

OCR JUg P 71982 SIGNATURES ORIGINAL CANCELLED REV. 2 Rev. S PREPARED BY QUALITY ASSURANCE REVIEW 4,A.

INTERFACING DEPARIMENT HEAD CONCURRENCE N.A.

DEPAR'IDENT HEAD APPROVAL N.A. N PLANT NUCLEAR A'.A.

SAFETY COMMITTEE PLANT MANAGER APPROVAL DATE OF ISSUE 3-31-81 ram No. PN 2010.l - tv. s 82062S0009 820618 PDR'ADOCK 05000315'.

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PMP EPP INDEX INDIANA 5 MICHIGAN PONER COMPANY DONALD C. COOK HUCLm~"R PLANT PLANT MANAGER PROCEDURE Index Identification Ti tie Revision Nc.~ Comments Number And Oat PMP 2881 EPP.014 Off-Site Dose Assessments Revision 0 TP-1,2-25-82 Exp N/A 4-1-81 EPP.015 Sampling and Analysis of Revision 0 Waterborne Releases.

  • 4-1-81 EPP.016 Collection and Analysis of Revision 0 Liquid and Gaseous Samples 4-1-81 Interpretation of Liquid 'PP.017 Revision 0 and Gaseous Samples 4-1-81 EPP.018 'ransportation Accidents Revision 0 Involving Radioactive 4-1-81 Material EPP.019 AEP Emergency Response Revision 0 Organi za ti ti on Acti va on and 4-1-8$

Management EPP.020 Activation and Operation of Revision 0 TP-1,11-16-81 Exp N/A the Technical Support Center 4-1-81 TP-2,3-12-82 Exp N/A (TSC) TP-3,3-12-82 Exp N/A EPP.021 Activation and Operatio'n of Revision 1 the Operations Staging Area 5-25-82 (OSA) and Personnel Accountability EPP.022 ActiVation and Operation of Revision 1 the Emergency Operations 6-4-82 Facility EPP.023 Activation and Operation of CANCELLED the Emergency Control Center 82.

(ECC) (An Emergency Operations Facility)

EPP.024 Activation and Operation of Revision 0.

the Joint Public Information 4-1-81 Center (JPIC) (An Emergency Operations Facility)  ; ace.

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t liiDIAIVA8 MICHIGA EI.ECTBIG COMPANY DONALD C COOK NUCLEAR PLANT

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PROCEDURE COVER SHEET Paced<<e No PMP 2081 EPP.022 Revision No.

TITLE ACTIYA'ZION.ANO'OPERATION.OF THE EMERGENCY qPERAT/ONS FACILITY SCOPE OF REVISION Rev. 1: Revised the operation of the EOF to a single location as per NRC reqUirements.

JUN 0 71982 SIGNATURES ORIGINAL Rev. I REV. 2 Rev, 3 PREPARED RY QUALITYASSURANCE REVIEW INTERFACING DEPARTMENT HEAD CONCURRENCE N.A. gA DEPARTMENT HEAD APPROVAL N.A. IV.A PLANT NUCLEAR SAFI'IY COMMIITEE PLANT MANAGER APPROVAL DATE OF ISSUE 3-31-81 Fcan No. PSQ 2010 1- acv. s

~ ~ i t PMP-2081-EPP.022 LIST OF EFFECTIVE PAGES PAGE NUMBER REVISION NUMBER AND DATE Page 1 of 5 Revision 1, 6 4 82 Page 2 of 5 Revision 1, 6 4 82 Page 3 of 5 Revision 1, 6 4 82 Page 4 of 5 Revision 1; 6-4-82 Page 5 of 5 Revision 1, 6-4-82 EXHIBIT A page 1 of 1 Revision 1, 6 4-82 EXHIBIT B page 1 of 1 Revision 1, 6-4-82 EXHIBIT C Page 1 of 1 Revision 1, 6 4 82 EXHIBIT D Page 1 of 3 Revision 1, 6-4-82 Page 2 of 3 Revision 1, 6-4-82 Page 3 of 3 Revision 1; 6 4-82 Page 1, of 1 Rev. 1;6482

MP-2081-EPP.022 INDIANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT ACTIVATION AND OPERATION OF THE EMERGENCY OPERATIONS FACILITY 1.0 OBJECTIVE 1.1 This procedure defines the responsibilities of individuals in the Emergency Operations Facility (EOF);

the interfaces of the EOF with other centers and organizations; the operation of the EOF during short-term emergency response; and the staffing necessary to carry out these functions.

2.0 RESPONSIBILITIES AND FUNCTIONS 2.1 Responsibilities See Exhibit A for the Emergency Operations Facility Organization.

2.. 1 . 1 Radiation Control arid Waste Handling Manager (RCWHM): Assistant Plant Manager 2.1.2 Communications Director: Production Supervisor, Technical 2.1.3 Communications Personnel: Training Instructors, Performance Engineers, Operations Quality Control Implementation Coordinators 2.1.4 Radiological Assessment Director: R.P.

Performance Engineer 2.1.5 Radiation Protection Manager: Plant Radiation Protection Supervisor 2.2 Functions The EOF, upon activation, will assume responsibility for performing the following functions:

2.2.1 Management of overall IGM response 2.2.2 Coordination of radiological and environmental assessment 2.2.3 Determination of recommended public protective actions Page 1 of 5 Rev- 1,6~82

2.2.4 Coordination of emergency response activities with Berrien County, the State of Michigan, and the Federal Government.

2.3 The Emergency Operations Facility is a support facility established for the purpose of performing the above functions. The EOF shall have appropriate technical data information and plant records to assist in the diagnosis of plant conditions to evaluate the potential or actual release of radioactive materials to the environment. An Assistant Plant Manager in this center shall organize and manage I&M support (dose assessment, communication, and radiation protection) resources to support the TSC and control room operators.

3.0 LIMITATIONS AND PRECAUTIONS 3.1 The Emergency Operation Facility shall be activated as necessary for any emergency condition and specifically for Site Emergencies and General Emergencies. This procedure covers the operation of the EOF until establishment of the AEP Emergency Response Organization on-site and/or until deactivation of the EOF.

4.0 INSTRUCTIONS 4.1 Upon recognition of the need for, or desirability of activating the EOF, the On-Site Emergency Coordinator shall direct the Communications Director to initiate PMP-2080-EPP.008, calling off-duty Plant personnel for the purpose of staffing the EOF.

4.2 The initial people to arrive in the EOF should prepare the facility for operation by performing the following:

4.2.1 Unlock the EOF equipment cabinet. The key may be obtained from the Shift Security Supervisor or from the Training Department secretary.

4.2.2 Turn on the radiation monitor. Instructions are posted on the monitor.

4.2.3 Set up the communications/dose assessment room and "command center" for operation, as per Exhibit D.

4.2.3.1 Set up tables and chairs.

Page 2 of 5 Rev 1 , 6-4-82

MP-2081-EPP.022 4.2.3.2 Set up telecopier.

4.2.3.3 Set out telephones.

4.2.3.4 Set out the headset for the board writer.

4.2.4 Turn on Xerox machine.

4.3 The Radiation Control and Waste Handling Manager shall manage I&M support activities (dose assessment, communications, and radiation protection) from the and interface with the On-Site Emergency Coordinator.EOFg Specifically, the RCWHM shall:

4.3.1 Oversee arrangement of the training building as the EOF. See Exhibit D.

4.3.2 Establish communications directly as needed, with the OSEC for the purpose of managing I&M response to the event.

4.3.3 Ensure the EOF assumes responsibility for communication with off-site organizations.

4.3.4 Ensure the EOF assumes dose assessment and protective action decision-making responsibilities.

4.3.5 Coordinate I&M and Federal, State, and local response to the event via:

4.3.5.1 Information passed both ways through the communicators.

4.3.5.2 Establishing the "command center",

as needed. See Exhibit D.

4.3.5.3 Establishing the NRC room, as needed. See Exhibit D.

4.3.5.4 Establishing the New York Emergency Response Organization room, as needed. See Exhibit D.

4.3.6 Complete the top portion of Exhibit C for use by the Radiological Assessment Director.

4.3.7 Ensure Exhibit C is normally developed every 15 minutes. Approve Exhibit C upon completion and prior to release to off-site organizations.

Page 3 of 5 Rev. 1,6482

MP-2081-EPP.022 4.3.8 Remain cognizant. of the activi ~ - of the Radiation Protection Manager =:.". response to the emergency.

4.3.9 Direct the Shift Security Supervisor to establish security controls around the EOF building. These controls shall ensure that access is restricted to personnel assigned to the EOF.

4.4 The Communications Director shall perform the following functions:

4.4.1 Establish a chronological history log of events and make this log available to communications, dose assessment, radiation protection, and "command center" personnel.

4.4.2 Ensure that detailed event data, Exhibit B, is made available regularly to communications, dose assessment and radiation protection personnel. this data will be provided every Normally fifteen minutes by telecopiert from the TSC.

4.4.3 Ensure the communicators, dose assessment and radiation protection personnel are brought up-to-date regarding event data and information required to perform their functions.

4~4~4 Establish communication with the Berrien County Sheriff's Department, Michigan State Pol~ice, Nuclear Regulatory Commission, American Electric Power Initial Assessment Group and Public Affairs. Assume responsibility for this function from the TSC.

4.4.4.1 Exhibit B is to be provided to NRC and AEP, and to the JPIC and Westinghouse as needed.

4.4.4.2 Exhibit C is to be provided to AEP, the JPIC, the Berrien County Sherif f ' Department, and the Michigan State Police. Exhibit C is also to be supplied to the NRC as needed.

Page 4 of 5 Rev. 1

MP-2081-EPP.022 4.4.5 Assume responsibility for the dose assessment and radiation protection functions from the TSC.

4.4.6 Communicate requests from off-site groups to the Technical Director.

4.5 The Radiological Assessment Director is responsible for:

4.5.1. Performing dose calculations for on-site and off-site areas and reporting these results to the Communications Director and Radiation Control and Waste Handling Manager.

4.5.2 Recommending protective actions on-site and off-site when appropriate.

4.6 The Radiation Protection Manager is responsible for:

4.6.1 Implementing the emergency radiation protection program including personnel monitoring and decontamination.

4.6.2 Directing activities of Radiation Monitoring teams and reporting results to the Radiation Control and Waste Handling Manager.

4.6.3 Directing the activities of Re-entry and Rescue teams, as appropriate.

4.6.4 Coordinating first-aid activities.

Page 5 of 5 Rev. 1, 6-4-82

(OPERATIONS STAGING AREA) (TECHNICAL SUPPORT CENTER) (EMERGENCY OPERATIONS FACILITY)

ON-SITE EHERGENCY COORDINATOR I

I RADIATION CONTROL AND MASTE HANDLING HANAGER I

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l. RWST I,evel 2. Containment Pressure PSIG 3~ Containment Sump Level 4. Containment Ievel 0/
5. BIT Flow LP1 GPM LP2 GPM LP3 GPM LP4 GPM
6. SI Flow North GPM South GPM
8. RHR To CTS Flow East GPM West GPM
9. CTS East (ON OFF ) West (ON OFF )
10. RCP Status LP1 .(ON OFF ) LP2 (ON OFF ) LP3 (ON OFF ) LP4 (ON OFF )
11. RCS Press. PSIG ~ 0 4 12. PZR Ievel
13. PZR Liquid Temp. F 14. PZR Steam Temp. F
15. PZR Backup Htrs. (ON OFF ) 16. PZR Cycling Htrs. (ON OFF )
17. Charging Flow GPM 18. Ietdown Flow GPM NSSS IOOP PARAMETERS ~Leo 1 ~Leo 2 ~Loo 3 ~Leo 4
19. Wide Range T OF op OF OF
20. Wide Range TC OF OF OF OF
21. S/G Pressure PSIG PRIG PSIG PSIG w

22e S/G N.R. I,evel /

23. 3/0 S.R. Level
24. Steam Flow (pph K 100)
25. Feed Flow (pph K 10 )
26. Aex. Feed Flow(pph K 10 )

27 MSIV Status (OP CL ) (OP CI ) (OP CL ) (OP CL )

'8.

CST Ievel Ft.

DOSE PARAMETERS SPECIAL NOTES OR DATA

29. R-2 Contain. Area R/Hr.
30. R-11 Contain. Part. CPM
31. R-12 Contain. Gas CPM
32. R-33 Gland Exh. Vent CPM
33. R-15 Air Ejector Vent CPM
34. R-26 Vent Stack Gas CPM
35. Vent Flow
36. GSLO Flow
37. SJAE Flow
38. Wind Speed MPH
39. Wind Direction 4 (From)
40. Air Temp. bT oC Data Verified By Page 1 Of 1 Revision 1, 6-4-82

J ACCIDENT ORMATION REPORTING DATA SHEE PMP 2081 EPP.022 EXHIBIT C D.C. Cook Unit Date Descriptioa of Event Prognosis For Terminatioa Or Worsening Classification: Unusual Event Alert Site Emergency General Emergency Injured Personnel: Yes, Number , No Radioactivity Contaminated: Yes No Estimated Duration of Release Basis for Projected Dose Calculation Source Term for Calculation Flow for Calculation Monitor Readiag Measurements Upper Limit of Moaitor Range Upper Limit on Containmeat Dose Rate 6" from Effluent Pipe I,eak Rate Sample Time Plow Obtained Time Source Term Obtained I

Measured Dose Rate I

~ Iocation of FQ Time of Measurement Measurement Dose Rate Iodine Conc.

Meteorological Coaditions: Wind Speed (mph)

Wind Direction: From To Stability Class: AT Pasqulll Cat. A D C D E Precipitation: Yes No Release Rate: Total Gas Ci/sec Release Height: Ground Level Projected Dose At: Site Boundary 2 Miles 5 Miles 10 Miles Dose Rate, Whole Body, R/hr

-Integrated Dose, Whole Body, R Dose Rate, Thyroid, R/hr

-Integrated Dose, Thyroid, R Sectors Affected

-Iategrated from the time of initial calculation to ead of projected release.

Time Calculation Performed Input Verified t Support Requested From State or County Agencies:

,'--.= Yes No Type Recommended Emergency Actioas For State or County Agencies Page 1 Of 1 Revision 1,6-4-82

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