LIC-03-0087, Transmittal of Changes to Emergency Plan Implementing Procedures

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Transmittal of Changes to Emergency Plan Implementing Procedures
ML031820367
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 06/13/2003
From: Ridenoure R
Omaha Public Power District
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
LIC-03-0087
Download: ML031820367 (170)


Text

PF-Omha PubicPower Dst Fort Calhoun Station P.O. Box 550, Highway 75 Fort Calhoun, NE 68023-0550 June 13, 2003 LIC-03-0087 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Reference:

Docket No. 50-285

SUBJECT:

Transmittal of Changes to Emergency Plan Implementing Procedures (EPIP)

In accordance with 10 CFR 50.54(q), 10 CFR 50, Appendix E, Section V, and 10 CFR 50.4(b)(5), please find EPF change packages enclosed for the Document Control Desk (holder of Copy 165) and the NRC Region IV Plant Support Branch Secretary (holder of Copies 154 and 155).

The document update instructions and summary of changes are included on the Confirmation of Transmittal form (Form EP-1) attached to each controlled copy change package. Please return the Confirmation of Transmittal forms by July 25, 2003.

The revised documents included in the enclosed package are:

EPIP Index 3 pages issued 05/28/03 EPIP-EOF-6 R32a issued 01/23/02 EPIP-OSC-2 R42 issued 05/28/03 EPIP-OSC-15 R22 issued 10/24/00 EPIP-OSC-21 R12 issued 10/29/02 EPIP-RR-l 1 R14 issued 02/29/00 EPIP-RR-17 R15 issued 12/10/02 EPIP-RR-17A R20 issued 11/07/02 EPIP-RR-19A R6 issued 04/15/03 EPIP-RR-21 R12 issued 09/23/99 EPIP-RR-21A R4 issued 11/30/99 EPIP-RR-28 R8 issued 09/25/01 EPIP-RR-39 RO issued 03/27/01 EPIP-TSC-1 R23 issued 10/29/02 RERP Index page 1 of 2 issued 05/28/03 RERP Section J RI 8 issued 05/28/03 FC-EPF Index page 2 of 3 issued 06/03/03 FC-EPF-20 R2 issued 06/03/03 If you have any questions regarding the enclosed changes, please contact Mr. Carl Simmons at (402) 533-6430.

Sincerely, c: NRC Region IV Plant Support Branch Secretary (2 sets)

Alan Wang, NRC Project Manager (w/o enclosures)

J. G. Kramer, NRC Senior Resident Inspector (w/o enclosures)

Emerenc Plaining Department (w/o enclosures)

Employmnent withng mqalOgortunity p94 5

- e FORM EP-1 Rev. 6 (04129199)

OMAHA PUBLIC POWER DISTRICT Confirmation of Transmittal for Emergency Planning Documents/information g

Z Radilogicl EmegencyEmergency Plan Radiolog~icalaEm~e~rgEe~ncy Implementing Procedures z E Emergenc Planning gcy Response Plan (RERP) (EPIP) Forms (EPF) ii Emergency Planning Department Manual []i Other Emergency Planning Document(s)!

(EPDM) Information Transmitted to:

Name: Document Control Desk Copv No: 165 Date: __

Division of Reactor Safety CODy No: 154 Attn: Senior Emergency Preparedness Inspector Division of Reactor Safety CODy No: 155 Attn: Senior Emergency Preparedness Inspector The following document(s) i Information are forwarded for your manual:

REMOVE SECTION INSERT SECTION EPIP Index 3 pages Issued 05/15103 EPIP Index 3 pages Issued 05/28/03 EPIP-EOF-6 R32 issued 01/23/02 EPIP-EOF-6 R32a Issued 01/23/02 EPIP-OSC-2 R41 Issued 01/27/03 EPIP-OSC-2 R42 Issued 05128/03 EPIP-OSC-15 R22 Issued 10/24/00 EPIP-OSC-15 R22 Issued 10/24/00 EPIP-OSC-21 R12 Issued 10/29/02 EPIP-OSC-21 R12 Issued 10/29/02 EPIP-RR-1 1 R14 Issued 02/29/00 EPIP-RR-I1 R14 Issued 02129100 EPIP-RR-17 R15 Issued 12/10/02 EPIP-RR-17 R15 Issued 12/10/02 EPIP-RR-17A R20 Issued 11/07/02 EPIP-RR-17A R20 Issued 11/07/02 EPIP-RR-19A R6 issued 04/15/03 EPIP-RR-19A R6 Issued 04/15/03 EPIP-RR-21 R12 Issued 09/23/99 EPIP-RR-21 R12 Issued 09/23/99 EPIP-RR-21A R4 issued 11/30/99 EPIP-RR-21A R4 issued 11/30/99 EPIP-RR-28 R8 Issued 09/25/01 EPIP-RR-28 R8 issued 09/25/01 EPIP-RR-39 RO Issued 03/27/01 EPIP-RR-39 RO Issued 03/27/01 EPIP-TSC-1 R23 Issued 10/29/02 EPIP-TSC-1 R23 Issued 10/29/02 RERP Index page 1of 2 Issued 04/03/03 RERP Index page 1 of 2 Issued 05/28/03 RERP Section J RI 7 Issued 03/25/03 RERP Section J RI 8 Issued 05/28/03 FC-EPF Index page 2 of 3 Issued 10/08/02 FC-EPF Index page 2 of 3 Issued 06/03/03 FC-EPF 20 RI Issued 07/29/97 FC-EPF 20 R2 Issued 06/03/03

Summary of Changes:

EPIP-EOF-6 was revised adding note telling when to use fax, also to clarify instructions on how to use imminent release. EPIP-OSC-2 was revised to make changes to comply with new security card readers.

EPIP-OSC-1 5 was revised to change action steps about obtaining keys to a note, also to edit step(s) about EP Activation Booklet to clarify Intent. EPIP-OSC-21 was revised to delete step requiring synchronizing docks to the ERF since we now use atomic clocks. EPIP-RR-1 I was revised to update format, delete note, delete reference to Chemistry Liaison, and change ERMS operator to Site Directors Secretary and to change CID to ARs'. EPIP-RR-17 was revised to update format, to add instructions as required by users and to add instructions for actions to be taken upon event termination. EPIP-RR-1 7A was revised to add instructions for TSC Admin Logistics Coordinator to interface with the EOF Admin Logistics Manager to determine what special needs may be needed and to ensure that it is understood who performs these tasks. EPIP-RR-19A was revised to insert step in Attachment 6.2 to include tracking of EOP's and AOP's by TSC Ops Liaison. EPIP-RR-21 was revised to add ERMS operator to list of people needed for 24-hour staffing schedule and to remove step 5 of Att. 6.1 as this is redundant to EPIP-OSC-21 Aft. 6.2 step 4.b. EPIP-RR-21A was reformatted per Writers Guide. EPIP-RR-28 was revised per Writer's Guide and to delete reference to RP-604 and HIS-20 since they do not address emergency exposure. EPIP-RR-39 is a new procedure to provide guidance for Control Room Medical Responder.

EPIP-TSC-1 was revised to delete step requiring synchronizing clocks to the ERF since we now use atomic docks. RERP Section J was revised to make changes to comply with new security card readers.

/~/'{ Supervisor - Emergency Planning I hereby acknowledge receipt of the above documentslinformatlon and have Included them In my assigned manuals.

Signature: Date:_

Please sign above and return by 07125103 to: Beth Nagel Fort Calhoun Station, FC-2-1 Omaha Public Power District 444 South 16th Street Mall Omaha, NE 68102-2247 NOTE: If the document(s)/information contained in this transmittal Is no longer requested or needed by the recipient, or has been transferred to another individuals, please fill out the information below.

o Document(s)/Information No Longer Requested/Needed o Document(s)/Information Transferred to:

Name: Mailing Address:

Fort Calhoun Station Emergency Plan Implementing Procedure Index Page 1 of 3

£PIP Document Document Title Revision/Date EPIP-OSC-I Emergency Classification R35 05-02-02 EPIP-OSC-2 Command and Control Position Actions/Notifications R42 05-28-03 EPIP-OSC-9 Emergency Team Briefings R7 12-09-99 EPIP-OSC-15 Communicator Actions R22 10-24-OOa EPIP-OSC-21 Activation of the Operations Support Center R12 10-29-02a EPIP-TSC-1 Activation of the Technical Support Center R23 10-29-02a EPIP-TSC-2 Catastrophic Flooding Preparations R3 01-23-03 (RO 03-22-95) DELETED (05-09-95)

REINSTATED EPIP-TSC-8 Core Damage Assessment R14 01-19-01 EPIP-EOF-1 Activation of the Emergency Operations Facility R13 10-29-02 EPIP-EOF-3 Offsite Monitoring R18 11-12-02 EPIP-EOF-6 Dose Assessment R32 01-23-02a EPIP-EOF-7 Protective Action Guidelines R14 04-15-03 EPIP-EOF-10 Warehouse Personnel Decontamination Station RIO 01-13-OOa Operation EPIP-EOF-1 1 Dosimetry Records, Exposure Extensions and R19 04-03-03 Habitability May 28, 2003 10:08:32am

Fort Calhoun Station Emergency Plan Implementing Procedure Index Page 2 of 3 EPIP Document Document Title Revision/Date EPIP-EOF-19 Recovery Actions R7 09-30-98 EPIP-EOF-21 Potassium Iodide Issuance R4 11-07-00 EPIP-EOF-23 Emergency Response Message System R5 10-12-99 EPIP-EOF-24 EOF Backup Alert Notification System Activation R3 09-09-99 EPIP-RR-1 1 Technical Support Center Director Actions R14 02-29-OOa EPIP-RR-13 Reactor Safety Coordinator Actions R14 12-09-99a EPIP-RR-17 TSC Security Coordinator Actions R15 12-10-02a EPIP-RR-17A TSC Administrative Logistics Coordinator Actions R20 11 02a EPIP-RR-19A Operations Liaison Actions R6 04-15-03a EPIP-RR-21 Operations Support Center Director Actions R12 09-23-99a EPIP-RR-21A Maintenance Coordinator Actions R4 11-30-99a EPIP-RR-22 Protective Measures Coordinator/Manager Actions R22 05-15-03 EPIP-RR-22A Chemistry Coordinator Actions R6 12-07-01 EPIP-RR-25 EOF Dose Assessment Coordinator Actions R21 05-15-03 EPIP-RR-28 OSC Accountability and Dosimetry Technician Actions R8 09-25-01a May 28, 2003 10:08:32am

Fort Calhoun Station Emergency Plan Implementing Procedure Index Page 3 of 3 EPIP Document Document Title Revision/Date EPIP-RR-29 EOF Administrative Logistics Manager Actions R20 11-07-02 EPIP-RR-39 Control Room Medical Responder Actions RO 03-27-01 a EPIP-RR-63. EOF Dose Assessment Assistant Actions RIO 11-19-01 EPIP-RR-66 Communication Specialist Actions R8 08-31-99 EPIP-RR-72 Field Team Specialist Actions R13 07-09-02 EPIP-RR-87 Radiation Protection Coordinator Actions R7 08-24-00 EPIP-RR-90 EOF/TSC CHP Communication Actions RO 10-24-00 May 28, 2003 10:08:32am

WP10 Distribi Lation Authorized This procediire does not contain any propriet ary information, or Fort Calhoun Station such inform.ation has been Unit No.

No. 11 Unit censored.toTt his Issue may be

~released he public document room. Propr-letary information includes per sonnel names, company tellephone numbers, and any Info rmation, which could impede emei rgency response.

EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE

Title:

DOSE ASSESSMENT FC-68 Number: EC 28905 Reason for Change: Add note telling when to use fax. Clarify instructions on how to use imminent release. (CR 200103341)

Requestor: M. Reller Preparer: M. Reller Correction (a): Pages 4 and 8 (05-28-03) (Issue all pages)

ISSUED: 01-23-02 3:00 pm R32

FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 1 OF 31 DOSE ASSESSMENT NON-SAFETY RELATED

1. PURPOSE 1.1 This procedure provides instructions for performing dose assessment for Ventilation Stack releases, Main Steam Line/Condenser Off-Gas releases, Containment leakage and Radwaste Building releases. It also provides instruction for estimating unmonitored release rates, and performing liquid release assessment.
2. REFERENCES/COMMITMENT DOCUMENTS 2.1 EPIP-EOF-7, Protective Action Guidelines 2.2 Ol-ERFCS-1, Operation of the Emergency Response Facilities Computer System 2.3 CH-SMP-PA-0005, Monitoring of Gaseous Effluent Releases Via the Auxiliary Building Ventilation Duct Pathway 2.4 Technical Data Book TDB-IV.8, Area Monitor Setpoints 2.5 User's Guide for EAGLE 5.00 2.6 Engineering Analysis EA-FC-90-038, Manual Dose Assessment 2.7 Engineering Analysis EA-FC-90-105, Ingestion Pathway 2.8 Engineering Analysis EA-FC-90-035, EAGLE Radiological Parameters 2.9 Engineering Analysis EA-FC-93-066, EAGLE 4.0 Dose Calculation Methodology 2.10 Calculation FC-06179, TEDE and CDE conversion factors for offsite dose calculation 2.11 Commitments (other than Ongoing)
  • AR 10029, IER-89-24
  • AR 13302, IER-92-20
  • AR 17061, LIC-95-0049/LIC-95-0230 2.12 Protective Measure Basis Document, CHP-00-038, September 28, 2000 R32

FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 2 OF 31

3. DEFINITIONS 3.1 DELTA T (AT) TEMPERATURE - the temperature difference between 10 and 60 meters, in units of centigrade. The value displayed on the ERFCS equates to a 100AT[(T @ 60m - T @ 1On) x 2].

3.2 DURATION OF RELEASE - the time in hours the release is expected to continue.

3.3 DOSE - the amount of ionizing radiation that results from an amount of energy being absorbed in the human body, in units of Rem.

3.4 DOSE RATE - Dose per unit time, in units of Rem/hour.

3.5 ERFCS - Emergency Response Facility Computer System.

3.6 IMMINENT RELEASE - An impending release of the radioactive gas in Containment.

3.7 CDE - Committed Dose Equivalent.

3.8 TEDE - Total Effective Dose Equivalent.

3.9 COMMAND AND CONTROL POSITION: The position that is currently in charge of the emergency response, either the Shift Supervisor, Control Room Coordinator, Site Director or Emergency Director.

3.10 RELEASE RATE (Q) - the emission rate of the effluent in units of Curies per second from the release point.

4. PREREQUISITES 4.1 A radioactive release is suspected, imminent, or known to be in progress.
5. PROCEDURE NOTE: If on-site meteorological data is not available, contact the National Weather Service (number in the Emergency Phone Book), and request wind speed and direction. For night time (sunset to sunrise) with no precipitation, use a AT of +2.0 and a stability class F. For all other conditions, use a AT of -1.0 and a stability class D.

5.1 To perform dose assessments in the Control Room, use Attachment 6.1.

5.2 To perform dose assessments in the TSC, use Attachment 6.2.

5.3 To perform dose assessments in the EOF, use Attachment 6.3.

R32

FORT. CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 3 OF 31 5.4 When needed, perform dose assessments and updates to the states at least every 60 minutes. It is the goal of the Fort Calhoun Station to attempt to provide assessments and updates at 15 minute intervals. (AR 13302) 5.5 Retain all documentation (logs, assessments, etc.) generated or used during the emergency. At the termination, deliver all documentation to the TSC Administrative Logistics Coordinator in the TSC, or the EOF Administrative Logistics Manager in the EOF.

6. ATTACHMENTS 6.1 Dose Assessment in the Control Room 6.2 Dose Assessment in the TSC 6.3 Dose Assessment in the EOF 6.4 Computerized Dose Assessment 6.5 Unmonitored Release Assessments R32

FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 4'OF 31 Attachment 6.1 - Dose Assessment In The Control Room Page 1 of 4

1. Using information from the Control Room as needed and Al-33A, B and C or ERFCS pages 197, 360 and 361 evaluate and determine the release pathways for dose assessment as follows:

NOTE: The sample Control Module for RM-052 must be in the VENT position (monitoring the Auxiliary Building Vent Stack) in order to be used for dose assessment.

NOTE: RM-062/063 are the preferred process monitors to be used for dose assessment on the Auxiliary Building Vent Stack. RM-Q62 is normally in-service and RM-063 is normally in Standby. When RM-062 count rate exceeds 5.0 E+06 cpm or if RM-063 exceeds 5.0 E-3 jplcrcamwillomaticaifnRM-062 to RM-063 and the alarm URM-063 AUX BLDG VENT STACK IN SERVICE" will annunciate on Al-33C. When RM-063 radiation level drops below 5.0 E-3 pC/cc, sample flow will shift to RM-062 and RM-063 will shift to Standby.

1.1 Evaluate the Auxiliary Building Vent Stack release pathway using RM-052, RM-062 and RM-063.

1.1.1 If RM-052 or RM-062 is in High Alarm, determine the source of the release to the Auxiliary Building Vent Stack.

  • If the source of the release can be determined to be only from Condenser Off-gas (i.e. Off-gas is aligned to Auxiliary Building Vent Stack and there are no other release sources to the Auxiliary Building Vent Stack), then use an Iodine/Noble Gas Ratio of 0.003 for the Auxiliary Building Vent Stack release.
  • Otherwise, use the default Iodine/Noble Gas Ratio of 0.02.

1.2 Evaluate the Condenser/Main Steam release pathway using RM-057, RM-064 and whether or not a primary to secondary leak has been confirmed.

1.2.1 If RM-057 is in High Alarm or if a primary to secondary leak is confirmed, request that RM-064 be placed in service on the affected Main Steam Line.

1.2.2 If RM-057 is in High Alarm or if a primary to secondary leak is confirmed and if Condenser Off-gas is being vented directly to the atmosphere via the Turbine Building Roof, request that Condenser Off-gas be aligned to the Auxiliary Building Vent Stack.

. j~~~~

R32

FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE i PAGE 5 OF 31 Attachment 6.1 (continued) Page 2 of 4 1.2.3 If RM-057 is in High Alarm or if a primary to secondary leak is confirmed and Condenser Off-gas is being vented directly to the atmosphere via the Turbine Building Roof, perform dose assessment using Condenser Off-gas a release pathway, a flow rate of 340 scfm, and use an Iodine/Noble Gas Ratio of 0.003.

1.2.4 If a primary to secondary leak is confirmed and RM-057 is not operable or is over ranged, and Condenser Off-gas is not.aligned to the Auxiliary Building Vent Stack, this is an unmonitored release.

1.2.5 If there is a confirmed primary to secondary leak, and FW-1 0 is receiving steam from the affected Steam Generator, or the atmospheric Steam Dump Valve HCV-1 040 is OPEN or a Steam Safety is lifting on the affected side, and RM-064 count rate is above the back ground count rate as listed in TDB-IV.7, use an Iodine/Noble Gas Ratio of 0.003.

1.2.6 If there is a confirmed primary to secondary leak, and FW-1 0 is receiving steam from the affected Steam Generator, or the atmospheric Steam Dump Valve HCV-1 040 is OPEN or a Steam Safety is lifting,on the affected side, and RM-064 count rate is less than or equal to the background count rate as listed in TDB-IV.7, this is unmonitored release.

1.3 Evaluate the Containment Leakage release pathway using Containment Area Monitors.

NOTE: If containment leakage is suspected to be greater than designed Containment leakage of 1.5 scfm, and the leakage is from the Containment to the stack or from the Containment to Controlled Areas of the Auxiliary Building to the Auxiliary Building Vent Stack, consideration may be given not to count the release twice if dose assessment will be performed from the Auxiliary Building Vent Stack.

1.3.1 If Containment Area Monitors RM-070 through RM-075 are in High Alarm or RM-091A and B read 1.0 R/hr or higher, perform dose assessment using Containment leakage as a release pathway.

1.3.2 IF any area monitors indicate > 1000 times the background listed in TDB-IV.8, THEN inform the Command and Control position for classification information.

1.4 Evaluate the Radwaste Building Stack as a release pathway using RM-043 1.4.1 If RM-043 is in High Alarm, perform dose assessment using the Radiological Waste Building Vent Stack as a release pathway.

R32

I I FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 6 OF 31 Attachment 6.1 (continued) Page 3 of 4 1.5 Evaluate the liquid release pathways as follows:

1.5.1 If RM-055, Overboard Discharge Monitor is reading greater than the High Alarm Setpoint as listed in TDB-IV.7 and the overboard discharge flow is not isolated, then a liquid release assessment must be performed.

1.5.2 If either RM-054A or RM-054B Steam Generator Blowdown Monitors are reading greater than the High Alarm Setpoint as listed in TDB-IV.7 and blowdown flow is not isolated from the Steam Generator(s) with a primary to secondary leak, then a liquid release assessment must be performed.

1.6 Determine if there are any potentially unmonitored releases.

2. Perform dose assessment for monitored release pathways using Attachment 6.4 and for unmonitored release pathways per Attachment 6.5.
3. Review/Distribution NOTE: The PAR information generated by EAGLE is for OPPD decision maker's information only. Actual PARs are determined by the Command and Control position. The PAR Information Worksheet should be one of the tools used for guidance in determining PARs.

3.1 If Command and Control is in the Control Room 3.1.1 Have the Command and Control position review the PAR Information Worksheet and the Update Report to Offsite Authorities.

NOTE: If a dose assessment results in a change in classification or a PAR change, ensure that the states are notified by the CR Communicator using an approved Emergency Notification form (FC-1 188) prior to faxing the Update Report to Offsite Authorities.

NOTE: If the Network is down or faxing is slow consider using the stand-alone fax machine.

3.1.2 If the Command and Control position approves the assessment:

  • Click the "Fax/Distribute" button at the bottom of the Release Information Screen
  • Select the proper distribution list(s)
  • Click "OK" R32

FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE.7 OF 31 Attachment 6.1 (continued) Page 4 of 4 3.2 If Command and Control is in the TSC:

3.2.1 Fax unsigned PAR Information Worksheet and Update Report to State and County Authorities to the TSC.

3.2.2 Inform the TSC Protective Measures Coordinator of the transmittal.

3.2.3 Record transmittal time.

R32

FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 8 OF 31 Attachment 6.2 - Dose Assessment In The Technical Support Center Page 1 of 3 NOTE: Dose assessment will only be performed in the TSC in the event that the EAGLE equipment in the Control Room is unavailable or inoperable. The TSC EAGLE equipment may also be used as a backup to the equipment located at the EOF.

l

1. Inform the Protective Measures Coordinator that you will be performing dose assessment in the TSC.
2. Using information from the Control Room as needed and Al-33A, B and C or ERFCS pages 197, 360 and 361 evaluate and determine the release pathways for dose assessment as follows:

NOTE: The sample Control Module for RM-052 must be in the VENT position (monitoring the Auxiliary Building Vent Stack) in order to be used for dose assessment.

NOTE: RM-062/063 are the preferred process monitors to be used for dose assessment on the Auxiliary Building Vent Stack. RM-062 is normally in-service and RM-063 is normally in Standby. When RM-062 count rate exceeds 5.0 E+06 cpm or if RM-063 exceeds 5.0 E-3 pC/cc; sample flow will automatically shift from RM-062 to RM-063 and the alarm URM-063 AUX BLDG VENT STACK IN SERVICE" will annunciate on Al-33C. When RM-063 radiation level drops below 5.0 E-3 pC/cc, sample flow will shift to RM-062 and RM-063 will shift to Standby.

2.1 Evaluate the Auxiliary Building Vent Stack release pathway using RM-052, RM-062 and RM-063.

2.1.1 If RM-052 or RM-062 is in High Alarm, determine the source of the release to the Auxiliary Building Vent Stack.

  • IF the source of the release can be determined to be only from Condenser Off-gas (i.e. Off-gas is aligned to Auxiliary Building Vent Stack and there are no other release sources to the Auxiliary Building Vent Stack), THEN use an Iodine/Noble Gas Ratio of 0.003 for the Auxiliary Building Vent Stack release.
  • Otherwise, use the default Iodine/Noble Gas Ratio of 0.02.

2.2 Evaluate the Condenser/Main Steam release pathway using RM-057, RM-064 and whether or not a primary to secondary leak has been confirmed.

2.2.1 If RM-057 is in High Alarm or if a primary to secondary leak is confirmed, request that RM-064 be placed in service on the affected Main Steam Line.

R32

FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE . PAGE 9 OF 31 Attachment 6.2 (continued) Page 2 of 3 2.2.2 If RM-057 is in High Alarm or if a primary to secondary leak is confirmed and if Condenser Off-gas is being vented directly to the atmosphere via the Turbine Building Roof, request that Condenser Off-gas be aligned to the Auxiliary Building Vent Stack.

2.2.3 If RM-057 is in High Alarm or if a primary to secondary leak is confirmed and Condenser Off-gas is being vented directly to the atmosphere via the Turbine Building Roof, perform dose assessment using Condenser Off-gas a release pathway, a flow rate of 340 scfm, and use an Iodine/Noble Gas Ratio of 0.003.

2.2.4 If a primary to secondary leak is confirmed and RM-057 is not operable or is over ranged, and Condenser Off-gas is not aligned to the Auxiliary Building Vent Stack, this is an unmonitored release.

2.2.5 If there is a confirmed primary to secondary leak, and FW-1 0 is receiving steam from the affected .Steam.Generator, or the atmospheric Steam Dump Valve HCV-1040 is OPEN or a Steam Safety is lifting on the affected side, and RM-064 count rate is above the-back ground count rate as listed in TDB-IV.7, use an Iodine/Noble Gas Ratio of 0.003.

2.2.6 If there is a confirmed primary to secondary leak, and FW-10 is receiving steam from the affected Steam Generator, or the atmospheric Steam Dump Valve HCV-1040 is OPEN or a Steam Safety is lifting on the affected side, and RM-064 count rate is less than or equal to the background count rate as listed in TDB-IV.7, this is unmonitored release.

2.3 Evaluate the Containment Leakage release pathway using Containment Area Monitors NOTE: If containment leakage is suspected to be greater than designed Containment leakage of 1.5 scfm, and the leakage is from the Containment to the stack or from the Containment to Controlled Areas of the Auxiliary Building to the Auxiliary Building Vent Stack, consideration may be given not to count the release twice if dose assessment will be performed from the Auxiliary Building Vent Stack.

2.3.1 If Containment Area Monitors RM-070 through RM-075 are in High Alarm or RM-091A and B read 1.0 R/hr or higher, perform dose assessment using Containment leakage as a release pathway.

2.3.2 IF any area monitors indicate > 1000 times the background listed in TDB-IV.8, THEN inform the Command and Control position for classification information.

R32

FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 10 OF 31 Attachment 6.2 (continued) Page 3 of?

2.4 Evaluate the Radwaste Building Stack as a release pathway using RM-043 2.4.1 If RM-043 is in High Alarm, perform dose assessment using the Radiological Waste Building Vent Stack as a release pathway.

2.5 Evaluate the liquid release pathways as follows:

2.5.1 IF RM-055, Overboard Discharge Monitor is reading greater than the High Alarm Setpoint as listed in TDB-IV.7 and the overboard discharge flow is not isolated, then a liquid release assessment must be performed.

2.5.2 If either RM-054A or RM-054B Steam Generator Blowdown Monitors are reading greater than the High Alarm Setpoint as listed in TDB-IV.7 and blowdown flow is not isolated from the Steam Generator(s) with a primary to secondary leak, then a liquid release assessment must be performed.

2.6 Determine if there are any potentially unmonitored releases.

3. Perform dose assessment for monitored release pathways using Attachment 6.4 and for unmonitored release pathways per Attachment 6.5.
4. Review NOTE: The PAR information generated by EAGLE is for OPPD decision makers information only. Actual PARs are determined by the Command and Control position. The PAR Information Worksheet should be one of the tools used for guidance in determining PARs.

4.1 Obtain a printout of the PAR Information Worksheet and the Update Report to Offsite Authorities.

4.2 Forward printouts to the Protective Measures Coordinator.

5. Provide detailed briefing to oncoming shift relief of emergency conditions and dose assessment status.

R32

FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 11 OF 31 Attachment 6.3 - Dose Assessment in the Emergency Operation Facility Page 1 of 4

1. IF dose assessments are being performed in the Control Room, THEN contact the technician in the Control Room performing dose assessment and review all previous assessments using the fax copies.
2. IF dose assessments are being performed in the TSC, THEN contact the technician performing dose assessment in the TSC and review all previous assessments using the fax copies.
3. Standby to transfer dose assessment from the Control Room (or TSC) to the EOF, as directed by the Protective Measures Manager.
4. When directed to take over dose assessment, inform the technician in the Control Room (or TSC) of your actions.
5. Using information from the Control Room as needed and Al-33A, B and C or ERFCS pages 197, 360 and 361 evaluate and determine the release pathways for dose assessment as follows:

NOTE: The sample Control Module for RM-052 must be in the VENT position (monitoring the Auxiliary Building Vent Stack) in order to be used for dose assessment.

NOTE: RM-0621063 are the preferred process monitors to be used for dose assessment on the Auxiliary Building Vent Stack. RM-062 is normally in-service and RM-063 is normally in Standby. When RM-062 count rate exceeds 5.0 E+06 cpm or if RM-063 exceeds 5.0 E-3 pC/cc; sample flow will automatically shift from RM-062 to RM-063 and the alarm "RM-063 AUX BLDG VENT STACK IN SERVICE" will annunciate on Al-33C. When RM-063 radiation level drops below 5.0 E-3 pC/cc, sample flow will shift to RM-062 and RM-063 will shift to Standby.

5.1 Evaluate the Auxiliary Building Vent Stack release pathway using RM-052, RM-062 and RM-063.

5.1.1 If RM-052 or RM-062 is in High Alarm, determine the source of the release to the Auxiliary Building Vent Stack.

  • IF the source of the release can be determined to be only from Condenser Off-gas (i.e. Off-gas is aligned to Auxiliary Building Vent Stack and there are no other release sources to the Auxiliary Building Vent Stack), THEN use an Iodine/Noble Gas Ratio of 0.003 for the Auxiliary Building Vent Stack release.
  • Otherwise, use the default Iodine/Noble Gas Ratio of 0.02.

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FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 12 OF 31 Attachment 6.3 (continued) Page 2 of 4 5.2 Evaluate the Condenser/Main Steam release pathway using RM-057, RM-064 and whether or not a primary to secondary leak has been confirmed.

5.2.1 If RM-057 is in High Alarm or if a primary to secondary leak is confirmed, request that RM-064 be placed in service on the affected Main Steam Line.

5.2.2 If RM-057 is in High Alarm or if a primary to secondary leak is confirmed and if Condenser Off-gas is being vented directly to the atmosphere via the Turbine Building Roof, request that Condenser Off-gas be aligned to the Auxiliary Building Vent Stack.

5.2.3 If RM-057 is in High Alarm or if a primary to secondary leak is confirmed and Condenser Off-gas is being vented directly to the atmosphere via the.

Turbine Building Roof, perform dose assessment using Condenser Off-gas a release pathway, a flow rate of 340 scfm, and use an Iodine/Noble Gas -

Ratio of 0.003.

5.2.4 If a primary to secondary leak is confirmed and RM-057 is not operable or is over ranged, and Condenser Off-gas is not aligned to the Auxiliary Building Vent Stack, this is an unmonitored release.

5.2.5 If there is a confirmed primary to secondary leak, and FW-1 0 is receiving steam from the affected Steam Generator, or the atmospheric Steam Dump Valve HCV-1040 is OPEN or a Steam Safety is lifting on the affected side, and RM-064 count rate is above the back ground count rate as listed in TDB-IV.7, use an Iodine/Noble Gas Ratio of 0.003.

5.2.6 If there is a confirmed primary to secondary leak, and FW-1 0 is receiving steam from the affected Steam Generator, or the atmospheric Steam Dump Valve HCV-1 040 is OPEN or a Steam Safety is lifting on the affected side, and RM-064 count rate is less than or equal to the background count rate as listed in TDB-IV.7, this is unmonitored release.

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FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 13.OF 31 Attachment6.3 (continued) Page 3 of 4 5.3 Evaluate the Containment Leakage release pathway using Containment Area Monitors NOTE: If containment leakage is suspected to be greater than designed Containment leakage of 1.5 scfm, and the leakage is from the Containment to the stack or from the Containment to Controlled Areas of the Auxiliary Building to the Auxiliary Building Vent Stack, consideration may be given not to count the release twice if dose assessment will be performed from the Auxiliary Building Vent Stack.

5.3.1 If Containment Area Monitors RM-070 through RM-075 are in High Alarm or RM-091 A and B read 1.0 R/hr or higher, perform dose assessment using Containment leakage as a release pathway.

5.3.2 IF any area monitors indicate > 1000 times the background listed in TDB-IV.8, THEN inform the Command and Control position for classification information.

5.4 Evaluate the Radwaste Building Stack as a release pathway using RM-043 5.4.1 If RM-043 is in High Alarm, perform dose assessment using the Radiological Waste Building Vent Stack as a release pathway.

5.5 Evaluate the liquid release pathways as follows; 5.5.1 If RM-055, Overboard Discharge Monitor is reading greater than the High Alarm Setpoint as listed in TDB-IV.7 and the overboard discharge flow is not isolated, then a liquid release assessment must be performed.

5.5.2 If either RM-054A or RM-054B Steam Generator Blowdown Monitors are reading greater than the High Alarm Setpoint as listed in TDB-IV.7 and blowdown flow is not isolated from the Steam Generator(s) with a primary to secondary leak, then a liquid release assessment must be performed.

5.6 Determine if there are any potentially unmonitored releases.

6. Perform dose assessment for monitored release pathways using Attachment 6.4 and for unmonitored release pathways per Attachment 6.5.

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L- I I FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 14'OF 31 Attachment 6.3 (continued) Page 4 of al

7. Review NOTE: The PAR information generated by EAGLE is for OPPD decision makers information only. Actual PARs are determined by the Command and Control position. The PAR Information Worksheet should be one of the tools used for guidance in determining PARs.

7.1 Obtain a printout of the PAR Information Worksheet and the Update report to Offsite Authorities.

7.2 Forward printouts to the Dose Assessment Coordinator.

8. Provide detailed briefing to oncoming shift relief of emergency conditions and dose assessment status.

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FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 15 OF 31 Attachment 6.4 - Computerized Dose Assessment Page 1 of 8

1. Logging on to EAGLE 1.1 Is terminal on, with EAGLE Main Menu page showing?

1.1.1 YES Select operational mode (emergency, drill or test), proceed to Step 1.2.

NO Re-boot the system, user name for each terminal is on the monitor, password for all machines is 'eagle".

NOTE: If another terminal has network "Control" and is performing dose assessment, Coordinate the network synchronization accordingly. At the EOF work with the EOF Dose Assessment Coordinator to insure a smooth transfer of dose assessment responsibilities.

1.2 Verifying network status and control.

1.2.1 Click "View Network Status" a window will open showing the status of each EAGLE network terminal.

1.2.2 To take control of the network (with someone at other PC, preferred method):

  • Have person in control click the "Release Control" button
  • Click the "Take Control"
  • Click "Exit" 1.2.3 To take control when no one is at the other PC:
  • Click "Override Control"
  • Click "Refresh"
  • Click "Exit' 1.2.4 The blue lettering at the top of the EAGLE Main Menu screen should say "Network Mode/Control".

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FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 16 OF 31 Attachment 6.4 (continued) Page 2 of 8 CAUTION IF process monitor reading increases by 50% while performing an assessment, or the Command and Control position requests an immediate assessment, THEN complete the current assessment and immediately start another. [AR 10029]

2. Performing Dose Assessment NOTE: While EAGLE does have graphic capabilities, typically this function will only be performed at the EOF.

2.1 Click "Atmospheric Diffusion and Dose Calculations" button.

2.2 From the Change Plume Segment Number screen:

NOTE: It- is possible to redo a plume by selecting that number at this point. -All data for that plume and other sequential plumes will be lost.

2.2.1 Enter "1N to start new plume series or the next sequential number to continue the current series.

2.2.2 Click "OKr.

2.3 From the-EAGLE Screen select:

2.3.1 Click "Control Options" to select:

  • Run Mode (Normal Dose Projection, is the default)
  • Release Duration (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is the default) 2.3.2 Click 'OK".

2.3.3 If desired, click "Current Segment Time and Date" to gain another opportunity to change the plume number.

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FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE

  • PAGE 17OF 31 Attachment-6.4 (continued) Page 3 of 8 NOTE: There are four release points listed at this point. To simplify this procedure, guidance will only be given for the Auxiliary Building Stack. The method for doing other release paths is similar. Reference the EAGLE Help menu or the EAGLE 5.0 User Manual if you need assistance with these pathways.

NOTE: For Condenser Off-gas releases, use a condenser ejector flow-rate of 340 cfm.

NOTE: For Condenser Main Steam releases, use an Iodine/Noble Gas Ratio of 0.003.

2.3.4 Click 'Aux Bldg Stk" or appropriate button to enter release data:

  • Select the appropriate option (the method described here will use radiation monitor data)
  • Select the appropriate Rad Monitor.
  • Enter the current rad monitor value, click accept
  • Enter the current Auxiliary Building Vent Stack flow (default is 72500),

click "O"r

  • Click "Change Iodine/Noble Gas Ratio", if needed, enter desired value (default is 2 e-2), click "Accept;
  • If properly entered click "OK"

... * .Click"Return To Dose Calcs"-. --

2.3.5 Repeat Step 2.3.4 for each release path.

2.3.6 Click "Change Met Parameters" R32

FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 18 OF 31 Attachment 6.4 (continued) Page 4 of 8 NOTE: For early dose assessments use the defaults for Atmospheric Mixing Conditions and Atmospheric Stability Class Method. The Protective Measures Group in the EOF should review weather conditions and adjust assessments accordingly once the EOF has assumed command and control and dose assessment.

  • Select the appropriate Atmospheric Mixing Condition (Unlimited Mixing Conditions is Default), enter the Mixing Height in meters.
  • Select the appropriate Atmospheric Stability Class (Delta T Method is default). If you chose other than the default enter Sigma Theta in degrees Celsius.

NOTE: Use the most positive Delta-T and the slowest wind speed.

  • Enter wind speed and direction, the ambient temperature and the appropriate Delta-T in the spaces provided.
  • Once data is properly entered, click "OK" 2.4 Calculation 2.4.1 From the EAGLE screen click 'Calculate". A red box will appear confirming the plume number which is being calculated.

NOTE: When EAGLE is done calculating the "Output Menu" box will be operational.

2.5 Viewing Calculated Results 2.5.1 Click "Output Menu" R32

FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 19 OF 31 Attachment 6.4 (continued) Page 5 of 8 2.5.2 From the "EAGLE Output Menu" screen click on "Release/Dose Assessment Information"

  • The "Data Input" sub-page will appear allowing you to verify that the correct data was used for calculations (Click on the "Recommendations" sub-page to verify rad monitor inputs and flows)
  • Click on the "Projections" sub-page to get EAGLE Calculated results in TEDE and CDE at the Site Boundary, 2 miles, 5 miles and 10 miles.

(any "Projected Integrated Dose (REM)) that require protective actions per EPIP-EOF-7 will be highlighted in red)

  • Click on the "Recommendation" sub-page to view EAGLE recommended Protective Action Recommendations (PARs) 2.6 Printing 2.6.1 Click "Distribute" 2.6.2 Click "Print' after it is highlighted NOTE: A window will open and ask a "Dose Assessment Report', a PARs Worksheet" or "Both".

2.6.3 Click the option you prefer (normally both).

2.6.4 Go to the proper attachment in this procedure for your facility for distribution and approval guidance.

2.7 Follow-up Actions 2.7.1 To go to the next plume segment

  • Click "Return to Output Menu"
  • From the "EAGLE Output Menu" screen click "Go To Next Plume Segment"
  • Click "Run Next Segment"
  • Go to Step 2.3 and follow guidance as needed to change inputs, as conditions require R32

FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 20 OF 31 Attachment 6.4 (continued) Page 6 of 8

3. Imminent Release Assessment 3.1 Entering data 3.1.1 From the main menu click "Atmospheric Diffusion Assessment and Dose Calculations".

3.1.2 At the Plume Segment Number screen:

  • Enter the appropriate plume number
  • Click "OK" 3.1.3 At the EAGLE Screen select Control Options:
  • Select "Imminent Release Option"
  • Click "OK 3.1.4 At the Containment Imminent Release Screen, select:
  • Change Release Time; to change the time until release
  • Change Containment Flow; to change Containment Pressure
  • -- ChafgeRadolotgical-Datar to enter data from rad monitors or isotopes
  • Hours after accident
  • Click"OK" 3.1.5 Click 'Calculate Initial Release Rates", to get "Projected Release Rates" in Ci/sec.

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FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 21 OF 31 Attachment 6.4 (continued) Page 7 of 8 3.1.6 Click Perform Straight-line Gaussian Projection:

  • At the prompt select the release duration, click "OK'
  • Enter the meteorological information, click "OK"
  • The Plume Centerline Values Based on Straight-line Gaussian Diffusion Model will be displayed. Click "ok"
  • At the Imminent Release screen, click "Exit"
  • At the Dose Calculation screen the Straight Line Gaussian numbers calculated for the Imminent Release with a decayed source term will be displayed for Containment Leakage.
  • Click the "Change Met Parameters" button
  • The "Change Met Parameters' screen will appear with the values used for the Imminent Release Calculation
  • Click 'ok' to accept or change as desired.
  • You may now calculate plumes based on the Imminent Release parameters 3.1.7 To return EAGLE to the default spectrum after doing an Imminent Release Calculation
  • Click Contamn Leak"
  • From the Change Release Rate Screen
  • Click "No Release"
  • Click "Change Isotopic Spectrum"
  • Click "Reset All To Default Spectrum"
  • Click WOK"
  • You may now enter data based on the Default Spectrum.

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I I FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 22 OF 31 Attachment 6.4 (continued) Page 8 of 8

4. Liquid Release Assessment 4.1 Entering Data 4.1.1 From the Main EAGLE Menu Select 'Tabular Displays of Dose Calculations".

4.1.2 From that menu select the "Liquid Effluent Isotopic Activity Display".

4.1.3 At the "Projected Isotopic Activity at MUD Intake Structure Screen" enter:

  • Liquid flow rate (available from the Control Room)
  • River flow rate
  • The isotopic activity (obtain from Chemistry)
  • Click "Calculate Projected Activity" button 4.1.4 Hard copies of all EAGLE screens may be made by
  • With Microsoft Word open and minimized and the EAGLE window active
  • Simultaneously hit the "Alt" and "Print Screen" buttons
  • Maximize Microsoft Word
  • Click "Edit"
  • Click "Paste" 4.1.5 If the results exceed the EPA limits ensure that Command and Control position reports results to:
  • MUD dispatcher
5. Errors 5.1 If an error message should appear:

5.1.1 Follow the on screen instructions.

5.1.2 If errors cannot be corrected, or other problems arise, reboot the system.

5.1.3 If the problem is still not corrected, perform dose assessment on another EAGLE terminal.

5.1.4 If printer fails, manually record dose assessment results on a FC-1 188 form.

6. Graphic and Tabular displays and further guidance on dose assessment are explained in the EAGLE 5.0 User's Guide and the EAGLE help menu.

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FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 23 OF 31 Attachment 6.5 - Determining Unmonitored Release Rates Page 1 of 9 NOTE: For determining projected release rates from the Ventilation Stack when RM-062/52 and 63 are off-scale/not available, refer to CH-SMP-PA-0005.

NOTE: For determining projected release rates from the Main Steam/Condenser Off-gas system when RM-057/64 are off-scale/not available, use Section 1 NOTE: For determining projected release rates from Containment when RM-091 A/B and RM-070 through RM-075 are off-scale/not available, use Section 2.

NOTE: For determining actual release rates using Field Team data, use Section 3.

1. For unmonitored releases via Condenser Off-gas/Main Steam System:

1.1 If RM-057 is off-scale or is not operable, and Condenser Off-gas is vented to the atmosphere via the Turbine Building Roof, perform dose assessment using RM-064 and a main steam flow in Ibm/hr from the affected Steam Generator (ERFCS page 353) per the following criteria:

1.1.1 If RM-064 is reading at or below background, use one (1) net count per minute (NCPM) for the RM-064 reading, an Iodine/Noble Gas Ratio of 0.003 and Attachment 6.4 to perform dose assessment.

1.1.2 If RM-064 is reading above background, use the indicated reading on RM-064, and Iodine/Noble Gas Ratio of 0.003 and Attachment 6.4 to perform dose assessment.

1.1.3 If RM-064 is off-scale high or is not operable, go to Section 1.3 below.

1.2 For unmonitored releases via FW-10, the Atmospheric Dump Valve (HCV-1040) or a Main Steam Safety Valve, perform dose assessment per the following criteria:

1.2.1 If RM-064 is reading at or below background use one (1) net count per minute (NCPM) for the RM-064 reading, a flow rate as determined from EAGLE, an Iodine/Noble Gas Ratio of 0.003, and Attachment 6.4 to perform dose assessment.

1.2.2 If RM-064 is reading above background, use the indicated reading on RM-064, a flow rate as determined from EAGLE, an Iodine/Noble Gas Ratio of 0.003 and Attachment 6.4 to perform dose assessment.

1.2.3 If RM-064 is off-scale high or is not operable, go to Section 1.3 below.

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I I FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 24 OF 31 Attachment 6.5 (continued) Page 2 of 9 1.3 If RM-064 goes off-scale high or is otherwise known to be inoperable, perform the following:

1.3.1 Obtain direct radiation readings on the main steam lines in Room 81. Refer to Figure 6.5.1 for reading locations.

1.3.2 If the dose rate is between 0 and 100 mRem/hr, use the following equation to calculate the TEDE release rate:

QTEDE = (17.5) (Contact Dose Rate in mRemlhr) 1.3.3 If the dose rate is >100 mRem/hr, use the following equation to calculate the TEDE release rate:

QTEDE = (5) (Contact Dose Rate in mRem/hr) 1.3.4 Multiply the OTEDE from Step 1.3.2 or 1.3.3 by the following to obtain the Noble Gas, Iodine and Particulate release rate in Ci/sec:

(ATEDE) (0.981) = Noble Gas Release Rate in Ci/sec (ATEDE) (0.003) = Iodine Release Rate in Ci/sec (OTEDE) (0.009) = Particulate Release Rate in CVsec 1.3.5 Input the Noble Gas, Iodine and Particulate Release Rate into EAGLE dose assessment program to obtain the dose and dose rate results. (AR 17061)

2. Containment Leakage 2.1 If all Containment Area Radiation Monitors are off-scale or inoperable, perform the following:

2.1.1 Obtain direct radiation readings on containment penetrations C-2 or H-4.

Refer to Figures 6.5.2 and 6.5.3 for reading locations.

2.1.2 Multiply this penetration reading by the Containment Multiplication Factor (CMF) using Figure 6.5.4, to determine an equivalent area monitor reading.

2.1.3 Insert the area monitor reading into the EAGLE dose assessment procedure to obtain the dose and dose rate results.

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FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDt*IE .4' PAGE 25 OF 31 Attachment S.5 (continued) Page 3 of 9

3. Determining Actual Release Rates from Field Team Data NOTE: Field Teams must be dispatched, and data from the approximate plume centerline must be available in order to complete this procedure. The Field Team Specialist should be consulted for Field Team data.

3.1 Obtain FC-EPF-29 and collect the following data:

3.1.1 Date and time.

3.1.2 Downwind distance (in miles) to the sampling location.

3.1.3 Wind direction 3.1.4 Delta temperature (AT) 3.1.5 Wind speed 3.1.6 Diffusion factor (Xp/Q) - Using Figure 6.5.5, determine-the projected diffusion factor, based on time of day and downwind distance. During transitional periods, use the more conservative, or smaller, value.

3.1.7 Dose rate reported from the field team in Rem/hr.

3.1.8 Iodine air concentration reported from the field team in PCicc.

3.1.9 Particulate air concentration reported from the field team in pCi/cc.

3.1.10 Noble gas release rate from dose rate (ONG in CVsec) - Multiply the wind speed (Step 3.1.5) by the dose rate (Step 3.1.7) and by the factor provided, then divide the result by Xp/Q (Step 3.1.6).

3.1.11 Iodine release rate from ONG (in Ci/sec) - Multiply the noble gas release rate (Step 3.1.10) by the factor provided.

3.1.12 Iodine release rate from air sample data (in Ci/sec) -If desired, this method may be used if iodine air sample date is available from the Field Teams.

Multiply the wind speed (Step 3.1.5) by the iodine concentration (Step 3.1.8),

then divide the result by the XpJ/Q (Step 3.1.6).

3.1.13 Particulate release rate from air sample data (in Ci/sec) - Multiply the wind speed (Step 3.1.5) by the particulate concentration (Step 3.1.9), then divide the result by the xp/Q (Step 3.1.6).

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I __ I-A FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 26 OF 31 Attachment 6.5 (continued) Page 4 of 9 L 3.2 Input Of Results 3.2.1 Upon completion of the calculations, input the release rate data into the EAGLE dose assessment procedure to obtain any dose and dose rate data as needed.

3.3 Follow-up Actions 3.3.1 Sign the assessment form and indicate the time completed.

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FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 27 OF 31 Attachment 6.5 (continued) Page 5 of 9 Figure 6.5.1 - Main Steam Headers Radiation Dose Measurement Point Locations R32

FORT CALHOUN STATION - EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 28 OF 31 Attachment 6.5 (continued) Page 6 of 9 Figure 6.5.2 - Auxiliary Building - Plant Elevation 1007'-0" & 1013'-0

_I R32

FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE  ; PAGE 29 OF 31 Attachment 6.5 (continued) Page 7 of 9 Figure 6.5.3 - Auxiliary Building - Plant Elevation 1036'-O R32

FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 30 OF 31 Attachment 6.5 (continued) Page 8 of 9 Figure 6.5.4 - Containment Multiplication Factor (CMF)

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FORT CALHOUN STATION EPIP-EOF-6 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 31 OF 31 Attachment 6.5 (continued)> Page 9 of 9 Figure 6.5.5 - Diffusion Factors DIFFUSION FACTORS 1 00-02 x

SE 2 5 1*0l DOWNWIND DISTANCE (MILES)

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WP10 Distribution Authorized This procedure does not contain any proprietary information, or Fort Calhoun Station such Information has been Unit No. 1 censored. This Issue may bbe released to the public docurnent room. Proprietary Informati on includes personnel names, company telephone number and any Information, which could e.

EPIP-OSC-2. impede emergency respons EMERGENCY PLAN IMPLEMENTING PROCEDURE

Title:

COMMAND AND CONTROL POSITION ACTIONS/NOTIFICATIONS FC-68 Number EC 32041 Reason for Change: Make changes to comply with new security card readers.

Requestor: M. Reller Preparer: M. Reller ISSUED: 05-28-03 3:00 pmr R42

FORT CALHOUN STATION EPIP-OSC-2 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 1 OF 29 COMMAND AND CONTROL POSITION ACTIONS/NOTIFICATIONS NON-SAFETY RELATED

1. PURPOSE 1.1 This procedure provides guidance to the Command and Control position for implementing the Emergency Plan, making required notifications, transferring Command and Control, performing classification upgrades/downgrades and event terminations.
2. REFERENCES/COMMITMENT DOCUMENTS 2.1 SO-R-1, Reportability Determination 2.2 10 CFR 50.72, Immediate Notification Requirements for Operating Nuclear Power Reactors 2.3 EPIP-OSC-1, Emergency Classification 2.4 EPIP-OSC-1 5, Communicator Actions 2.5 EPIP-EOF-6, Dose Assessment 2.6 EPIP-EOF-7, Protective Action Guidelines 2.7 EPIP-EOF-1 1, Dosimetry Records, Exposure Extensions, and Habitability 2.8 EPIP-EOF-21, Potassium Iodide Issuance 2.9 EPIP-EOF-1 9, Recovery Actions 2.10 EPIP-TSC-1, Activation of the Technical Support Center 2.11 EPIP-EOF-1, Activation of the Emergency Operations Facility 2.12 Ol-ERFCS-1, Emergency Response Facility Computer System 2.13 FC-1 188, Emergency Notification Form 2.14 FC-EPF-38, Blair Industrial Park Co-Op, Event Notification Form 2.15 Emergency Telephone Book R42

~

______________ ~ ~ ~ ~ ~ ~ II I FORT CALHOUN STATION EPIP-OSC-2 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 2 OF 29 2.16 Commitments (other than Ongoing)

- AR 07071, LIC-88-0726 2.17 Ongoing Commitments

  • AR 30816, LIC-01 -01 89
3. DEFINITIONS 3.1 ANS - Alert Notification System' The system of sirens maintained in OPPD's designated EPZ (Emergency Planning Zone).

3.2 BLAIR INDUSTRIAL PARK CO-OP: NOTIFICATION SYSTEM - An organization of industries including Fort Calhoun Station that have banded together to form a warning system to notify member industries and the Washington County Dispatch Center of a potential or actual release of toxic chemicals and/or hazardous material from its facility.

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FORT CALHOUN STATION EPIP-OSC-2 EMERGENCY PLAN IMPLEMENTING PROCEDLRE PAGE 3 OF 29 3.3 CODE SYSTEM - A system devised by members of the Blair Industrial Park Co-Op to classify events that have occurred at the initiating facilities site. These codes are:

  • CODE BLUE: A minor emergency or problem such as a fire, explosion, gas or liquid release, unusual noise or odor, abnormal or extended flaring activity or other internal event has occurred which may be visible or detectable by off-site people, but which presents NO OFFSITE THREAT and requires no protective actions.

The situation is under control.

  • CODE GREEN: An emergency such as a fire, explosion, gas or liquid release or other event has occurred which affects plant operations and/or has the potential to escalate to a more serious emergency. THE SITUATION IS NOT UNDER CONTROL BUT POSES NO IMMEDIATE OFFSITE THREAT. The Washington County EOC may activate.
  • CODE YELLOW: A serious accident such as a fire, explosion, gas or liquid or other event has occurred or is imminent which seriously affects plant operations and/or poses a threat to residents or industries in the immediate vicinity of the affected industry. THE SITUATION IS NOT UNDER CONTROL AND ONSITE PROTECTIVE ACTIONS WILL BE NECESSARY. The Washington County EOC would activate.
  • CODE RED: A severe emergency such as fire, explosion, gas or liquid release or other event has occurred or is imminent which seriously affects plant operations and/or offsite areas well beyond site boundaries. THE SITUATION IS NOT UNDER CONTROL AND PROTECTIVE ACTIONS FOR NEIGHBORING INDUSTRIES AND RESIDENTS ARE NECESSARY. The Washington County EOC would fully activate at a safe location.

3.4 COMMAND AND CONTROL POSITION - The Shift Manager, Control Room Coordinator, Site Director or Emergency Director currently charged with the authorities and responsibilities for directing the emergency response.

3.5 EALs - 'Emergency Action Levels' 3.6 EAS - 'Emergency Alert System'. A mass-media system providing information and instructions to the general public in the event of a nuclear or other public emergency.

3.7 EOF - 'Emergency Operations Facility".

3.8 ERDS - 'Emergency Response Data System". The system that transmits selected plant parameter data to the NRC Operations Center.

3.9 ERF - 'Emergency Response Facility'. The Control Room, TSC, OSC and EOF maintained for emergency response.

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FORT CALHOUN STATION EPIP-OSC-2 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 4 OF 29 3.10 ERO - Emergency Response Organization".

3.11 FTS-ENS phones - NRC notification system phones, , FTS- "Federal Telecommunications System", ENS- "Emergency Notification System".

3.12 GE - "General Emergency".

3.13 KFAB - Designated Local Primary One (LP1) Emergency Alert Station located in Omaha, NE.

3.14 NOUE - "Notification of Unusual Event".

3.15 NRC - "Nuclear Regulatory Commission".

3.16 OSC - "Operations Support Center".

3.17 PARs - "Protective Action Recommendations".

3.18 RELEASE OF RADIOACTIVE MATERIAL - Any discharge of radioactive effluent to the environment that is a result of, or associated with, the emergency event.

3.19 SAE - "Site Area Emergency".

3.20 TSC - "Technical Support Center".

4. PREREQUISITES 4.1 An emergency has been declared or is to be reported per EPIP-OSC-1, Emergency Classification.
5. PROCEDURE NOTE: Once an event has been declared, notifications must be made within the time requirements of the applicable attachment.

5.1 IF no Emergency has been declared and conditions for a classification level occurred but no longer exist (per EPIP-OSC-1), THEN the event must be reported as follows:

5.1.1 Notify both states using the commercial line. Call Iowa at 1-515-281-3231 (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> #) and Nebraska at 1-402-471-7430 (normal hours) or 1-402-471-4545 (after hours).

5.1.2 Request that each state have the appropriate duty officer contact the Control Room at 1-402-533-6623 for a report on the event.

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FORT CALHOUN STATION EPIP-OSC-2 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 5 OF 29 5.1.3 Notify the NRC using the FTS-ENS phone (commercial line is a backup) per SO-R-1.

5.1.4 DO NOT complete an Attachment 6.1, but log information in the Control Room Log as necessary.

5.2 IF while in a declared emergency, conditions for a higher emergency classification were exceeded but have since been abated or otherwise been resolved prior to declaration, THEN the event must be reported as follows:

5.2.1 Perform the notifications described in Attachments 6.1, 6.2 or 6.3 for the states, counties and the NRC for the current classification.

5.2.2 Inform the states, counties and the NRC that a higher classification existed, but was not declared, what conditions existed that caused the emergency classification, and inform them of the time that the higher classification existed.

5.3 Record any additional documentation in FC-EPF-1 3, Emergency Response Organization Log Sheet, or the Control Room Log.

5.4 IN THE CONTROL ROOM: Perform notifications using Attachment 6.1.

5.5 IN THE TSC OR EOF: Perform notifications using Attachment 6.2 (TSC) or 6.3 (EOF).

5.6 IF an upgrade or downgrade of the emergency classification occurs prior to completion of the checklist, THEN perform the following:

5.6.1 Complete state/county notifications for the former classification.

5.6.2 Begin another Notification Attachment for the new classification.

5.7 Complete Attachment 6.7 when performing reliefs.

5.8 Retain all documentation (logs, calculation sheets, notes, etc.) generated or used during the emergency.

5.9 At the termination, deliver all documentation to the CR Communicator, or Admin Logistics position for your facility.

6. ATTACHMENTS 6.1 Notification Checklist for the Control Room R42

FORT CALHOUN STATION EPIP-OSC-2 EMERGENCY PLAN IMPLEMENTING PROCEDURIt- - PAGE 6 OF 29 6.2 Notification Checklist for the TSC 6.3 Notification Checklist for the EOF 6.4 ERO Activation Announcement 6.5 Classification Announcement 6.6 Emergency Tennination Guidelines 6.7 Relief Checklist 6.8 Command and Control Position Responsibilities 6.9 Classifying and Reporting events to the Blair Industrial Park Co-Op R42

FORT CALHOUN STATION EPIP-OSC-2 EMERGENCY PLAN IMPLEMENTING PROGEDURE PAGE 7 OF 29 Attachment 6.1 - Notification Checklist for the Control Room Page 1 of 5 Classification: 0 NOUE 0 Site Area Declared at /

Date Time 0 Alert 0 General EAL#

Command and Control:

Relief: (complete Attachment 6.7) Time NOTE: The following steps are ordered in a suggested sequence, but the Command and Control position may modify the sequence, if necessary.

NOTE: Fort Calhoun station made a commitment to place the TSC HVAC System in the FILTERED MODE with 30 minutes of a LOCA. Both the Shift Radiation Protection Technician and the Shift Chemistry Technician have been trained to place the TSC HVAC System in the FILTERED MODE.

/ TIME

1. Direct the:
  • Shift Communicator to report to the Control Room and perform Notifications
  • -Shift Chemistry-echnician to report to-ControlRoom for dose assessment, chemical and hazmat analysis and support.
  • Shift RP Technician for habitability, radiological support and backup dose assessment.

1.1 Ensure the TSC HVAC System was placed in FILTERED MODE by the Shift RP or Chemistry Technician enroute to the Control Room

[AR 30816].

2. Is ERO to be activated?

Yes 2.1 Instruct Communicator to activate the ERO.

2.2 Perform plant announcement per Attachment 6.4.

2.3 Go to Step 4.

No Go to Step 3.

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- -I I FORT CALHOUN STATION EPIP-OSC-2 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 8 OF 29 Attachment 6.1 Page 2 of 5

/ TIME

3. Is a Management Notification (NOUE only) desired?

Yes 3.1 Direct Communicator to do a Management notification.

3.2 Perform a plant announcement, using information from the Management Notification tab in the Emergency Planning Activation Instruction Booklet.

3.3 Have Communicator make the above announcement to Training Center and Administration Building.

No Go to Step 4.

NOTE: If the emergency classification changes prior to completion of this checklist, ensure the state and county notifications are initiated as a minimum before beginning another checklist.

4. Within 15 minutes of the emergency declaration you must:

4.1 Complete required sections of the Emergency Notification Form (FC-1 188) 4.2 Ensure the Communicator notifies the states and counties using the completed Emergency Notification Form.

5. Has the ERO been activated? [AR 10026]

Yes 5.1 Make a plant announcement for the current classification (if not done in Step 2) using Attachment 6.5.

5.2 Have Communicator make an announcement to Training Center and Administration Building (if not done in Step 2).

No Go to Step 6.

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FORT CALHOUN STATION EPIP-OSC-2 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 9 OF 29 Attachment 6.1 Page 3 of 5

/ TIME

6. Is a Site Evacuation to North Omaha necessary (required at General Emergency)? [AR 10026]

Yes 6.1 Perform a plant announcement per Attachment 6.5.

6.2 Have Communicator make an announcement to Training Center and Administration Building, using Evacuation Route checked.

No Go to Step 7.

7. Was a plant/site evacuation directed (plant evacuation at a minimum required at Alert or higher)? [AR 10026]

Yes 7.1 Assign a person to log personnel in/out of the Control Room until relieved by the Accountability Clerk.

No Go to Step 8.

' NOTE: NRC contact should be maintained from at least one facility. The FTS-ENS at the EOF can be patched in with the Control Room/TSC line if a request is made to the NRC.

8. Immediately (not later than one hour from declaration) after notification of the states and counties contact the NRC using the FTS-ENS phone (commercial phone is the backup) 8.1 Has NRC previously been notified?

Yes Then as a minimum report the classification, time and reason.

No First report to the NRC, use NRC Form 361 (SO-R-1).

8.2 Is classification an Alert or higher?

Yes Direct the STA to activate the ERDS system using Ol-ERFCS-1 A.

No Go to Step 9.

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I FORT CALHOUN STATION EPIP-OSC-2 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 10 OF 29 Attachment 6.1 Page 4 of 5

/ TIME

9. Use Attachment 6.9 to prepare the notification for the Blair Industrial Park Co-op.
10. Ensure the communicator updates the states and counties using an approved Emergency Notification Form (FC-1 188)
  • At least hourly (from the time of the last notification) and on an hourly basis until event termination
  • Within 15 minutes of a PAR change
11. Have the states requested that we activate the ANS (sirens)?

Yes 11.1 Contact the Emergency Director and request activation.

No Go to Step 12.

12. Has the state or county requested that Fort Calhoun Station activate the Emergency Alert System (EAS)?

Yes 12.1 Get the applicable EAS Message number from the state and county.

12.2 For the Primary message direct the Communicator to contact the National Weather Service using the Emergency Activations Booklet.

12.3 For all follow-up messages have the Communicator contact KFAB and give them the selected EAS message number for the requesting state.

No Go to Step 13.

13. Review conditions for upgrade or downgrade criteria.
14. Is emergency termination possible?

Yes 14.1 Review Attachment 6.6 for termination guidelines.

14.2 Complete and approve the termination Emergency Notification Form (FC-1 188).

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FORT CALHOUN STATION EPIP-OSC-2 EMERGENCY PLAN IMPLEMENTING PROGEDURE PAGE 11 OF 29 Attachment 6.1 - Page 5 of 5

/ TIME 14.3 Verify all data on the Emergency Notification Form is accurate.

14.4 Direct the Communicator to notify the states and counties using the Emergency Notification Form.

NOTE: If a Sub Area 1 evacuation was ordered Blair Industrial Park Co-Op facilities may not.be staffed.

14.5 Was the Blair Industrial Park Co-Op notified?

Yes Reactivate the system and inform Co-Op members of the event termination.

No Go to Step 14.6.

14.6 Notify the NRC using the FTS-ENS phone (commercial line is backup).

14.7 Announce Emergency termination using:

  • Plant Gai-Tronics
  • Facility PA system
  • MOP network for all other Emergency Response Facilities No Review this list and repeat applicable steps as required.

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FORT CALHOUN STATION EPIP-OSC-2 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 12 OF 29 Attachment 6.2 - Notification Checklist for the TSC Page 1 of 4 Classification: E NOUE El Site Area Declared at /

Date Time 0 Alert 0l General EAL#

Command and Control:

Relief: (complete Attachment 6.7) Time NOTE: The following steps are ordered in a suggested sequence, but the Command and Control position may modify the sequence, if necessary.

NOTE: If the emergency classification changes prior to completion of this checklist, ensure the state and county notifications are initiated as a minimum before beginning another checklist.

/ TIME

1. Within 15 minutes of the emergency declaration you must:

1.1 Complete required sections of the Emergency Notification Form (FC-1 188) 1.2 Ensure the COP Communicator notifies the states and counties using the completed Emergency Notification Form.

2. Is a Site Evacuation to North Omaha necessary (required at General Emergency)? [AR 10026]

Yes 2.1 Go to Attachment 6.5, to determine the evacuation route to be used, (primary or alternate) and the announcement to be made.

2.2 Direct the COP Communicator to make the evacuation announcement found in the Emergency Planning Activations Instruction Booklet to the Training Center and Administration Building.

No 2.3 Make a plant announcement per Attachment 6.5. [AR 10026]

2.4 Direct the COP Communicator to make the announcement for no site evacuation found in the Emergency Planning Activations Instruction Booklet to the Training Center and Administration Building.

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FORT CALHOUN STATION EPIP-OSC-2 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 13 OF 29 Attachment 6.2 Page 2 of 4

/ TIME

3. Has plant/site accountability been established?

Yes Go to Step 4.

No 3.1 Ensure CR/OSC/TSC Accountability Clerks are logging personnel in/out (if OSC/TSC are activated).

3.2 Ensure that the TSC Security Coordinator initiates the accountability procedure, if the TSC is activated.

3.3 Ensure the accountability completion time is documented in the Control Room Log.

NOTE: NRC contact should be maintained from at least one facility. The FTS-ENS at the EOF can be patched in with the Control Room/TSC line if a request is made to the NRC.

4. Immediately (not later than one hour from declaration) after notification of the states and counties ensure the NRC is contacted using the FTS-ENS phone (commercial phone is the backup) 4.1 As a minimum, report new classification time and reason.

4.2 Is new classification Alert or higher?

Yes Ensure the Control Room activated the ERDS using OI-ERFCS-1 A.

No Go to Step 5.

5. Direct the Control Room to use Attachment 6.9 to prepare the notification for the Blair Industrial Park Co-Op.
6. Ensure the COP Communicator updates the states and counties using an approved Emergency Notification Form (FC-1 188)
  • At least hourly (from the time of the last notification) and on an hourly basis thereafter
  • Within 15 minutes of a PAR change R42

I FORT CALHOUN STATION EPIP-QSC-2 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 14 OF 29 Attachment 6.2 Page 3 of 4

/ TIME

7. Have the states requested that we activate the ANS (sirens)?

Yes 7.1 Contact the EOF Emergency Director and request ANS activation.

No Go to Step 8.

8. Has a state or county requested that Fort Calhoun Station activate the Emergency Alert System (EAS)?

Yes 8.1 Get the applicable EAS Message number from the state and county.

8.2 For the preliminary message direct the COP Communicator to contact the National Weather Service using the Emergency Activations Booklet.

8.3 For all follow-up messages have the COP Communicator contact KFAB and give them the selected EAS message number for the requesting state.'

No Go to Step 9.

9. Periodically review conditions for event upgrade or downgrade criteria.
10. Is emergency termination possible?

Yes 10.1 Review Attachment 6.6 for termination guidelines.

10.2 Complete and approve the termination Emergency Notification Form (FC-1 188).

10.3 Verify that all Emergency Notification Form data is correct.

10.4 Direct the COP Communicator to notify the states and counties using the Emergency Notification Form.

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FORT CALHOUN STATION EPIP-OSC-2 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 15 OF 29 Attachment 6.2 Page 4 of 4

/ TIME NOTE: If a Sub Area 1 evacuation was ordered, Blair Industrial Park Co-Op facilities may not be staffed.

10.5 Was the Blair Industrial Park Co-Op notified?

Yes Have the Control Room inform Co-Op members of the event termination.

No Go to Step 10.6.

10.6 Notify the NRC using the FTS-ENS phone (commercial line is backup).

10.7 Announce Emergency termination using:

  • Plant Gai-Tronics
  • Facility PA system
  • MOP network for all other Emergency Response Facilities No Review this list and repeat applicable steps as required.

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I-- -J I FORT CALHOUN STATION EPIP-OSC-2 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 16 OF 29 Attachment 6.3 - Notification Checklist for the EOF Page 1 of 4 Classification: El NOUE 0 Site Area Declared at /

Date Time 0 Alert E General EAL#

Command and Control:

Relief: (complete Attachment 6.7) Time NOTE: The following steps are ordered in a suggested sequence, but the Command and Control position may modify the sequence, if necessary.

NOTE: If the emergency classification changes prior to completion of this checklist, ensure the state and county notifications are initiated as a minimum before beginning another checklist.

/ TIME

1. Within 15 minutes of the emergency declaration you must:

1.1 Complete required sections of the Emergency Notification Form.

1.2 Ensure the COP Communicator notifies the states and counties using the completed Emergency Notification Form. l

2. Is a Site Evacuation to North Omaha necessary (required at General Emergency)? [AR 10026]

Yes 2.1 Go to Attachment 6.5, to determine the evacuation route to be used, (primary or secondary) and the announcement to be made.

2.2 Direct the COP Communicator to make the evacuation announcement found in the Emergency Planning Activations Instructions Booklet to the Training Center/Administration Building.

No 2.3 Direct the Control Room to make plant announcement per Attachment 6.5. [AR 10026]

2.4 Direct the COP Communicator to make the announcement for no site evacuation found in the Emergency Planning Activations Instruction Booklet to the Training Center and Administration Building.

3. Has plant/site accountability been established? (AR 10026)

Yes Go to Step 4.

No 3.1 Direct Site Director to initiate personnel accountability.

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FORT CALHOUN STATION EPIP-OSC-2 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 17 OF 29 Attachment 6.3 Page 2 of 4 g$ TIME NOTE: NRC contact should be maintained from at least one facility. The FTS-ENS at the EOF can be patched in with the Control Room/TSC line if a request is made to the NRC.

4. Immediately (not later than one hour from declaration) after notification of the states and counties ensure the NRC is contacted using the FTS-ENS phone (commercial phone is the backup) 4.1 As a minimum, report new classification time and reason.

4.2 Is new classification Alert or higher?

Yes Ensure the Control Room activated the ERDS using Ol-ERFCS-1 A.

No Go to Step 5.

5. Direct the Control Room to use Attachment 6.9 to prepare the notification for the Blair Industrial Park Co-Op.
6. Ensure the COP Communicator updates the states and counties using an approved Emergency Notification Form (FC-1 188).
  • At least hourly (from the time of the last notification) and on an hourly basis thereafter until event termination
  • Within 15 minutes of a PAR change
7. Ensure that the staffs of each facility are given timely updates on any significant change in plant or release status, even if the emergency classification remains unchanged.

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FORT CALHOUN STATION EPIP-OSC-2 EMERGENCY PLAN IMPLEMENTING PiOCEdURE PAGE 18 OF 29 Attachment 6.3 Page 3 of 4

/ TIME

8. Have the states requested that we activate the ANS (sirens)?

Yes 8.1 Direct the Administrative Logistics Manager to activate the ANS activation.

No Go to Step 9.

9. Has a state or county requested that Fort Calhoun Station activate the Emergency Alert System (EAS)?

Yes 9.1 Get the applicable EAS Message number from the state or county.

9.2 For the preliminary message direct the COP Communicator to contact the National Weather Service using the Emergency Activations Booklet.

9.3 For all follow-up messages have the COP Communicator contact KFAB and give them the selected EAS message number for the requesting state.

No Go to Step 10.

10. Periodically review conditions for event upgrade or downgrade criteria.

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FORT CALHOUN STATION EPIP-OSC-2 EMERGENCY PLAN IMPLEMENTING -PROCEDURE PAGE 19 OF 29 Attachment 6.3 Page 4 of 4

/ TIME

11. Is emergency termination possible?

Yes 11.1 Review Attachment 6.6 for termination guidelines.

11.2 Verify that Emergency Notification Form (FC-1 188) data is correct.

11.3 Complete and approve the termination Emergency Notification Form.

11.4 Direct the COP Communicator to notify the states and counties using the Emergency Notification Form.

NOTE: If a Sub Area 1 evacuation was ordered, Blair Industrial Park Co-Op facilities may not be staffed.

11.5 Was the Blair Industrial Park Co-Op notified?

Yes Have the Control Room inform Co-Op members of the event termination.

No Go to Step 11.6.

11.6 Notify the NRC using the FTS-ENS phone (commercial line is backup).

11.7 Direct the Site Director to announce the emergency termination using:

  • Plant Gai-Tronics
  • Facility PA system
  • MOP network for all other Emergency Response Facilities No Review this list and repeat applicable steps as required.

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FORT CALHOUN STATION EPIP-OSC-2 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 20 OF 29 Attachment 6.4 - ERO Activation Announcement

1. Select from the options below, the information to be announced.
2. Notify Security if a plant/site evacuation is planned.
3. Sound the Emergency Alarm for approximately 30 seconds.
4. Read the selected announcement over the Gai-Tronics.
5. Again sound the Emergency Alarm for approximately 30 seconds.
6. Again read the selected announcement over the Gai-Tronics.

ANNOUNCEMENT "Attention all personnel..Attention all personnel...A(n) (Classification) has been declared, due to ... (state reason) ... All Emergency Response Organization personnel report to their assigned facility immediately...Personnel in the Radiation Controlled Area proceed to the RCA Access Point...No eating, drinking, smoking or chewing is allowed anywhere in THE OWNER CONTROLLED AREA until further notice...AII other personnel:

Opi tional: NOUE Continue with normal duties Optional: NOUE Evacuate to the Admin Building using the South Required: Alert Security Access Point Site Area Optional: Alert Evacuate to the North Omaha Power Station using the:

Site Area Required: General ___ PRIMARY Route. (No release, or release with wind direction >570 and <3040)

ALTERNATE Route. (wind direction from >304° or

<570 with known release) 1 R42

FORT CALHOUN STATION EPIP-OSC-2 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 21 OF 29 Attachment 6.5 - Classification Announcement NOTE: The Site Director and the Emergency Director should select the information to be announced and direct the Control Room to sound the Emergency Alarm and make the Gai-tronics announcements.

1. Select, from the options below, the information to be announced.
2. Notify Security if a plant/site evacuation is planned.
3. Sound the Emergency Alarm for approximately 30 seconds.
4. Read the selected announcement over the Gai-Tronics.
5. Sound the Emergency Alarm for approximately 30 seconds (second time).
6. Read the selected announcement over the Gai-Tronics (second time).
7. At the EOF, verify that the above steps have been completed using the Operations Liaison Circuit or other communication.

ANNOUNCEMENT "Attention all personnel...Attention all personnel...A(n) (Classification) has been declared, due to...(state reason)...No eating, drinking, smoking or chewing is allowed anywhere in THE OWNER CONTROLLED AREA until further notice"... (Continue only if a plant/site evacuation is required)

All Non-Emergency Response personnel must:

Optional: NOUE Evacuate to the Administration Building using the South Required: Alert Security Access Point Site Area Optional: Alert Evacuate to the North Omaha Power Station using the:

Site Area Required: General PRIMARY Route. (No release, or release with wind direction >570 and <304°)

ALTERNATE Route. (wind direction from Ž3040 or <570 with known release)

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I I FORT CALHOUN STATION . EPIP-OSC-2 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 22 OF 29 Attachment 6.6 - Emergency Termination Guidelines Page 1 of 2i NOTE: Prior to recommending establishment of recovery operations (if necessary) and termination of the Emergency Response Organization, the following conditions should be considered.

1. A Recovery Operations Manager has been designated per EPIP-EOF-19 if extensive recovery actions are needed to return the plant or environs to a pre-accident status.
2. Radiation Protection personnel are/have been monitoring access to any radiologically controlled areas of the plant necessary for recovery operations.

COMMENTS:

3. Off-site conditions allow access of personnel and needed support resources to the plant.

COMMENTS:

Planf status with respect to Technical Specifications has been evaluated by the Command 4.

4. Plant status with respect to Technical Specifications has been evaluated by the Command and Control position OR Technical Support personnel if ERO was activated.

COMMENTS:

Emergency termination recommendations have been discussed with the NRC Operations 5.

5. Emergency termination recommendations have been discussed with the NRC Operations Center.

COMMENTS:

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FORT CALHOUN STATION EPIP-OSC-2 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 23 OF 29 Attachment 6.6 Page 2 of 2

6. The states of Nebraska and Iowa and the counties have been notified of the pending termination.

COMMENTS:

7. The transition from Emergency to Recovery phase has been discussed with the designated Recovery Operations Manager and an initial recovery operations meeting has been scheduled, if needed.

COMMENTS:

Additional Discussions/Comments:

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FORT CALHOUN STATION EPIP-OSC-2 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 24 OF 29 Attachment 6.7 - Relief Checklist [AR 07071] Page 1 of 2 NOTE: Prior to assuming Command and Control of an emergency, Steps 1 through 8 of the following steps must be completed.

NOTE: By signing below the person assuming Command and Control of the emergency acknowledges that they have reviewed and accept the responsibilities contained in .8 of this procedure.

Command & Control Position/Time: /

Person Assuming Command & Control/Time: /

1. Review/Discuss cause of the emergency condition.
2. Review/Discuss current status of the emergency condition and classification level.
3. Review/Discuss current plant status.
4. Review/Discuss each step of current Notification Checklist (Attachments 6.1, 6.2 or 6.3), including any county/state/NRC notifications made and determine any steps NOT yet performed.
5. Review and discuss when next FC-1 188 should be sent to state/counties.
6. Determine activation status of the ERO and ERF facilities:

Control Room: 0 ERO Positions Activated TSC: o Activated o In Progress OSC: o Activated o In Progress EOF: o Activated o In Progress MRC: 0 Activated o In Progress o N/A

7. Determine current status of dose assessment, habitability checks, radiological surveys and other tasks being performed by the Emergency Response Organization.
8. Determine if position being relieved is ready to complete the transfer of Command and Control.
9. WHEN both positions are ready, THEN perform the transfer of Command and Control.

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FORT CALHOUN STATION EPIP-OSC-2 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 25 OF 29 Attachment 6.7 Page 2 of 2

10. Announce your name, and who has Command and Control to the lead personnel in the following facilities, if staffed:

Control Room, TSC, OSC, EOF and MRC.

11. Sign your name, title and the relief time in the 'Relief" space of the Notification Checklist. Initiate the appropriate Notification Checklist if transfer is between facilities.
12. Log relief information in the Command and Control position log.

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- l .

FORT CALHOUN STATION EPIPOSC-2 EMERGENCY PLAN IMPLEMENTING PA6FEi56#E PAGE 26 OF 29 Attachment 6.8 - Command and Control Position Responsibilities The following responsibilities CAN NOT BE DELEGATED by the Command and Control position. The responsibility of their completion rests with the Command and Control position until relieved by another qualified individual or the emergency is terminated. The Command and Control position may assign other personnel to assist in conducting the actions necessary.

1. Overall COMMAND AND CONTROL of the Emergency Response Organization.
2. Ensuring the proper CLASSIFICATION AND DECLARATION of the emergency situation is made in accordance with EPIP-OSC-1 and is periodically reviewed to determine if the classification should be upgraded, downgraded or terminated.
3. Ensuring all required NOTIFICATIONS are made to appropriate state, local and federal officials.
4. Ensuring any appropriate PROTECTIVE ACTION RECOMMENDATIONS (PARs) are provided to offsite officials.
5. Authorizing OPPD emergency worker exposure extensions beyond the Federal Radiation Protection Guidance.
6. Authorizing issuance of Potassium Iodide for OPPD emergency workers.

The Command and Control position also has the following responsibilities which may be delegated to other personnel, as necessary.

7. Request for assistance from federal agencies.
8. Authorizing any emergency information to be released to the media or the general public.
9. Coordinating the transfer of emergency information from the Emergency Response Organization (ERO) to other OPPD and outside organizations called upon to assist.
10. Ensuring a timely and complete turnover of information to any qualified relief.
11. Providing information to authorized representatives of the states of Nebraska, and Iowa, and associated local governments.
12. Ensuring plant operations are in compliance with Technical Specifications and other license conditions. If deviations are necessary to protect the public health and safety, they must be evaluated with respect to 10CFR50.54(x) and (y) and approved, as a minimum, by a senior licensed operator, prior to taking the action.

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FORT CALHOUN STATION EPIP-OSC-2 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 27 OF 29 Attachment 6.9 - Classifying and Reporting Events to the Blair Industrial Park Co-Op Page 1 of 3 NOTE: The purpose of this attachment is to keep members of the Blair Industrial Park Co-Op aware of significant events that have occurred at the Fort Calhoun Station. It is intended that the system be used for notification of situations which have or are anticipated to have visibility or impact beyond the Fort Calhoun station property lines. These situations may include, but are not limited to:

  • Any gas or chemical leaks of significant magnitude
  • Any radiation leaks of significant magnitude
  • Any news worthy information (such as major fires, explosions, large medical response, etc.) which could result in news media interviewing neighboring industries
  • Any plant evolutions resulting in large noises or having a visual impact which can be heard or seen by the public
1. INITIAL ASSESSMENT NOTE: FC-EPF-38 is designed to aid you in gathering data prior to contacting members of the Co-Op. Existing FC-1 188 and/or SO-R-1 can be used to provide the necessary information.

1.1 If notified of an onsite toxic chemical/hazardous material or radiological release, complete Sections 3, 5, 6 and 7 of FC-EPF-38. If all the information is not known, leave that section blank. DO NOT GIVE UNVERIFIED INFORMATION.

NOTE: Assistance in classification may be obtained from the Shift Chemist.

2. EVENT CLASSIFICATION 2.1 Report the event as classified (NOUE, ALERT, SITE AREA or GENERAL EMERGENCY) in Section 2 of FC-EPF-38.

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I A FORT CALHOUN STATION EPIP-OSC-2 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 28 OF 29 Attachment 6.9 Page 2 of ?

NOTE: If the involved chemical is not listed, or further information on chemicals is desired refer to SO-G-106, "Hazardous Material Chemical Assessment and Emergency Response Guidelines", the Material Safety Data Sheet, if available, or The North American Emergency Response Guidebook.

NOTE: If the involved chemical is not listed below, refer to the North American Emergency Response Guidebook for guidelines.

2.2 If the involved chemical is one of the following, consider it a SMALL HAZARD:

  • Acetylene
  • Amerzine
  • Chemtreat
  • Ethanolamine
  • Diesel Fuel
  • Hydrazine
  • Hydrogen 2.3 Use the guide below to classify the event class. The four codes are further defined in the definitions section of this procedure:

CODE HAZARD POTENTIAL CONDITIONS Blue Small or large Situation under control - NO offsite threat Green Small or large Situation NOT under control - No immediate offsite threat Yellow Large Situation NOT under control - Onsite protective actions will be needed Red Large Situation NOT under control - Protective actions for neighboring industries and residents needed R42

FORT CALHOUN STATION EPIP-OSC-2 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 29 OF 29 Attachment 6.9 Page 3 of 3 NOTE: All members of the Co-Op are staffed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day except Kelly Ryan and Blair Ag.

MACC may not have staff onsite on some weekends and/or holidays.

NOTE: Alternate emergency numbers and routine day to day contact numbers for all Co-Op members and other vital agencies may be found in the Emergency Phone Book under the Blair Industrial Co-Op tab.

NOTE: All Notifications to the Blair Industrial Park Co-Op should be made through the Control Room if possible.

3. NOTIFICATIONS 3.1 Obtain the instructions marked "Blair Industrial Park Co-Op Notification" from the Emergency Planning Activation Instructions Booklet.

3.2 Direct the Communicator to perform the Blair Industrial Park Co-Op Notifications.

3.3 If event is on-going, update the Blair Industrial Park Co-Op members as conditions warrant.

R42

WP10 Distribi ution Authorized This procediure does not contain any propriet ary information, or such information has been Fort Calhoun Station censored. I 'his issue may be released to I:he public document Unit No. 1 room. Propi rietary information includes per -sonnel names, company tel ephone numbers, and any infoUrmnation, which could impede eme rgency response.

EPIP-OSC-15 EMERGENCY PLAN IMPLEMENTING PROCEDURE

Title:

COMMUNICATOR ACTIONS FC-68 Number EC 25614 Reason for Change: Change action steps about obtaining keys to a note. Edit step(s) about EP Activation Booklet to clarify intent.

Requestor: Mark Reller Preparer Rhonda Hankins Correction (a): Page 5 (05-28-03) (Issue all pages)

ISSUED: 10-24-00 3:00 pm R22

FORT CALHOUN STATION EPIP-OSC-15 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 1 OF 6 COMMUNICATOR ACTIONS NON-SAFETY RELATED

1. PURPOSE 1.1 This procedure provides guidance to designated Communicators in the Control Room, TSC and EOF for making required notifications.
2. REFERENCES/COMMITMENT DOCUMENTS 2.1 SO-R-1, Reportability Determinations 2.2 FC-1 188, Emergency Notification Form 2.3 Emergency Planning Activation Instructions Booklet 2.4 Emergency Telephone Book 2.5 EPIP-OSC-2, Command and Control Position Actions/Notifications 2.6 Ongoing Commitment Documents
3. DEFINITIONS 3.1 ANS - "Alert Notification System". The system of sirens within OPPD's designated EPZ, used to provide public warning of a plant emergency event.

3.2 BLAIR INDUSTRIAL PARK CO-OP - Emergency Notification System. An organization of industries including the Fort Calhoun Station that have banded together to form a warning system to notify member industries and the Washington County Dispatch Center of a potential or actual release of toxic chemicals and/or hazardous material from its facility.

3.3 CODE SYSTEM - A system devised by members of the Blair Industrial Park Co-Op to classify events that have occurred at the initiating facility's site. These codes are:

3.3.1 CODE BLUE - A minor emergency or problem such as a fire, explosion, gas or liquid release, unusual noise or odor, abnormal or extended flaring activity or other internal event has occurred which may be visible or detectable by off-site people, but which presents NO OFF-SITE THREAT and requires no protective actions. The situation is under control.'

R22

. I I FORT CALHOUN STATION EPIP-OSC-15 EMERGENCY PLAN IMPLEMENTING F l- - - PAGE 2OF6 3.3.2 CODE GREEN - An emergency such as a fire, explosion, gas or liquid release or other event has occurred which effects plant operations and/or has the potential to escalate to a more serious emergency. THE SITUATION IS NOT UNDER CONTROL BUT POSES NO IMMEDIATE OFF-SITE THREAT. The Washington County EOC may activate.

3.3.3 CODE YELLOW - A serious accident such as a fire, explosion, gas or liquid release or other event has occurred or is imminent which seriously affects plant operations and/or poses a threat to residents or industries in the immediate vicinity of the affected industry. .THE SITUATION IS NOT UNDER CONTROL AND ON-SITE PROTECTIVE ACTIONS WILL BE NECESSARY. The Washington County EOC would activate.

3.3.4 CODE RED - A severe emergency such as fire, explosion, gas or liquid release or other event has occurred or is imminent which seriously affects plant operations and/or off-site areas well beyond site boundaries. THE SITUATION IS NOT UNDER CONTROL AND PROTECTIVE ACTIONS FOR NEIGHBORING INDUSTRIES AND RESIDENTS ARE NECESSARY.

The Washington County EOC would fully activate at a safe location.

3.4 COMMAND AND CONTROL POSITION - The Shift Manager, Control Room Coordinator, Site Director, or Emergency Director currently charged with the authorities and responsibilities for directing the emergency response.

3.5 COMMERCIAL LINE - OPPD installed phone system, for interplant and normal outside phone communication.

3.6 COMMUNICATOR - The Communicator position associated with the Command and Control position in charge. For the Shift Manager and Control Room Coordinator, it is the Control Room Communicator. For the Site Director, it is the TSC COP Communicator. For the Emergency Director, it is the EOF COP Communicator 3.7 COP - "Conference Operations Network". The phone system installed to provide rapid state and county notifications.

3.8 EAGLE - OPPD computerized dose assessment system - "Emergency Assessment of Gaseous and Liquid Effluents".

3.9 EAS - 'Emergency Alert System". The radio system providing announcements to the general public in the event of a nuclear or other public emergency.

3.10 ENS/FTS phone - NRC notification system phones, ENS - "Emergency Notification System", FTS - "Federal Telecommunications System".

R22

FORT CALHOUN STATION EPIP-OSC-15 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 3 OF 6 3.11 ERDS - Emergency Response Data System". The system that provides ERF data to the NRC Operations Center.

3.12 ERO - Emergency Response Organization'.

4. PREREQUISITES None
5. PROCEDURE 5.1 Upon activation of your position, use the applicable checklist listed to complete required actions:

Attachment 6.1 - Control Room Notifications Checklist Attachment 6.2 - TSC Notifications Checklist Attachment 6.3 - EOF Notifications Checklist 5.2 Review the procedure and checklist, and accomplish the applicable steps upon initial activation and when required thereafter.

5.3 Maintain a-log of notifications/other contacts made.

5.4 At the completion of the shift or at event termination, initial the steps which are completed.

5.5 Provide a detailed briefing to your shift relief of any actions taken and the current emergency and notification status.

5.6 Retain all documentation (logs, notes, etc.) generated or used during the emergency.

At the termination, deliver all documentation to the Administrative Logistics Coordinator in the TSC and/or the Administrative Logistics Manager in the EOF.

5.7 IF the ERO was not activated, THEN contact the Emergency Planning Contact Person to pickup all documentation associated with the event.

6. ATTACHMENTS 6.1 Control Room Notifications Checklist 6.2 TSC Notifications Checklist 6.3 EOF Notifications Checklist R22

FORT CALHOUN STATION EPIP-OSC-15 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 4 OF 6 Attachment 6.1 - Control Room Notifications Checklist Maintain a log of all key activities

/ INITIALS NOTE: Keys needed to unlock cabinets are in the lockbox on the cabinet doors. Keys to door 115 are in the lockboxes located near the door.

1. Obtain the "Emergency Planning Activation Instruction Booklet from the Shift Manager.

1.1 Don a position identification badge from the locker.

1.2 Maintain a log of emergency activities.

2. Using the Emergency Planning Activation Instruction Booklet perform notifications as requested by the Shift Manager or Command and Control Position.

NOTE: In the event that the ERFCS is not available in the TSC or EOF, you may be called to obtain necessary information.

3. Have Control Room Data Collector collect requested data using:
4. IF forced evacuation of the Control Room is necessary, and the TSC is not activated, THEN:

4.1 Follow the appropriate steps in the AOP's.

4.2 Perform your duties as directed from the COP work station in the TSC.

R22

FORT CALHOUN STATION EPIP-OSC-1 5 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 5 OF 6 Attachment 6.2 - TSC Notifications Checklist Maintain a log of all key activities

/ INITIALS

1. Upon arrival:

I 1.1 Put on position identification badge.

2. Using the Emergency Planning Activation Instruction Booklet:

2.1 Perform the actions and notification in this book as directed by the Command and Control Position.

NOTE: The Protective Measures Coordinator is your contact to obtain status board information.

3. Maintain the Radiological Status Board using data from Emergency Notification Forms (FC-1 188). [AR 13301]

R22

I \1 FORT CALHOUN STATION EPIP-OSC-1 5 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 6 OF 6

. .~~ . . . .

- Attachment 6.3 - EOF Notifications Checklist

.1 Maintain a log of all key activities

/ INITIALS

1. Upon arrival:

1.1 Sign in on Accountability Roster.

1.2 Put on position identification badge.

2. Using the Emergency Planning Activation Instruction Booklet:

2.1 Perform the actions and notifications in this book as directed by the Command and Control Position.

3. Maintain the PAR Status Board.

I R22

WP10

-- A!

- x-.i *- .-Distributiovi Authorized This procedure cdoes not contain any proprietary i nformation, or Fort Calhoun Station such Informatio:i has been issue may be Unit No. 1 censored. This I released to the Foublic document room. Proprieta ry Information Includes personi rnel names, company teleph4lne numbers, and any informaltion, which could impede emergenicy response.

EPIP-OSC-21 EMERGENCY PLAN IMPLEMENTING PROCEDURE

Title:

ACTIVATION OF THE OPERATIONS SUPPORT CENTER FC-68 Number: EC 31020 Reason for Change: Delete step requiring synchronizing clocks to the ERF since we now use atomic clocks.

Requestor: Rhonda Hankins Preparer Rhonda Hankins Correction (a): Page 4 (05-28-03) (Issue all pages)

ISSUED: 10-29-02 3:00 pm R12

FORT CALHOUN STATION EPIP-OSC-21 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 1 OF 13 ACTIVATION OF THE OPERATIONS SUPPORT CENTER NON-SAFETY RELATED

1. PURPOSE 1.1 This procedure provides instruction for the Operations Support Center (OSC) Director and other OSC personnel for activation and deactivation of the OSC. It also provides guidance for relocating the OSC to its alternate location should the need arise.
2. REFERENCES/COMMITMENT DOCUMENTS 2.1 EPIP-RR-21, Operations Support Center Director Actions 2.2 EPIP-EOF-1 1, Dosimetry Records, Exposure Extensions, and Habitability
3. DEFINITIONS 3.1 Activated - minimum staffing and basic setup requirements have been attained to allow the OSC to provide support to the Control Room.

3.2 Augmented - A facility is augmented when all augmenting and minimum staffing positions are filled.

4. PREREQUISITES None
5. PROCEDURE 5.1 Upon reporting to the OSC, activate the OSC using Attachment 6.1.

5.2 Should the need arise to relocate the OSC, use Attachments 6.5 and 6.6.

5.3 Upon event termination, restore the equipment in the OSC per Attachment 6.4.

6. ATTACHMENTS 6.1 Checklist for Activation of the OSC 6.2 Typical Floor Plan for the Operations Support Center 6.3 Typical Accountability Boundaries for the Operations Support Center 6.4 Checklist for Deactivation of the OSC R12

I FORT CALHOUN STATION EPIP-OSC-21 EMERGENCY PLAN IMPLEMENTING P i'dCEtd E - PAGE 2 OF 13 6.5 Guidelines for Setup of the Operations Support Center in an Alternate Location 6.6 Typical Location of Alternate Operations Support Center R12

FORT- CALHOUN STATION EPIP-OSC-21 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 3OF 13 Attachment 6.1 - Checklist for Activation of the OSC Page 1 of 3 NOTE: It is the goal of Omaha Public Power District (OPPD) to activate the OSC within one hour following declaration of an Alert or higher classification. In the event of adverse weather and/or other conditions that may limit or slow response, either manmade or natural, it is understood that staffing time may exceed this goal.

LL) INIT/TIME

1. Verify the following minimum staffing positions are available:
  • Radiation Protection Technician or Radiation Protection Coordinator
  • One other person to form a team I
2. Set up accountability boundaries per Attachment 6.3. l
3. Connect phone harness P10:
  • Storekeeper (ext 7055)
  • Maintenance Planner (ext 7057)
  • Maintenance Technicians (ext 7059)
  • Extra OSC phone (ext 7060) /
4. Connect phone harness W10:
  • OSC Director (ext 7051)
  • Radiation Protection Coordinator (ext 7052)
  • Chemistry Coordinator (ext 7053)
  • Maintenance Coordinator (ext 7054)
  • ERMS Operator (used only if ERMS is inoperable, ext 7056)
  • Conference Health Physics (CHP) Network Phone
  • Management Operations Phone (MOP) Network l
5. Connect PA microphone. l
6. Tum on power switch for:

0 Writeboard monitor 0 Document reader/printer l 1111 7. Adjust volume controls on Gaitronics units so announcements can be heard in the OSC. I R12

- l FORT CALHOUN STATION EPIP-OSC-21 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 4 OF 13 Attachment 6.1 - Checklist for Activation of the OSC Page 2 of 3I (I/ INIT/TIME

8. Prepare team tracking board for use. I
9. Post "NO EATING/DRINKING/SMOKING OR CHEWING" signs from the RP Coordinator's Kit in the following locations:
  • OSC - Conference Room Area
  • Access Control Area /
10. When Steps 1 through 9 are complete perform the following:

10.1 Make the following announcement on the OSC PA system:

"This is (INSERT NAME) . I have assumed the duties of OSC Director. The OSC is now activated. Eating, drinking, smoking or I chewing is NOT allowed."

10.2 Inform the Site Director the OSC is activated, ready to provide minimal support to the Control Room and who is filling the OSC i Director position.

l

11. Verify habitability per EPIP-EOF-1 1.
12. Set up a portable air monitoring system (AMS). I
13. Set up a portable area monitor with the alarm set at about 15 mr/hr.
14. Within one hour of initial emergency declaration, verify the following augmenting staff are present:
  • Chemistry Technician
  • Dosimetry Technician
  • Electrical Maintenance Technicians (2)
  • Maintenance Coordinator
  • Mechanical Maintenance or Steam Fitter Mechanic
  • Operations Liaison
  • Radiation Protection Technicians (6 of which one may be minimum staffing)
  • Radiation Protection Coordinator (if not counted for minimum staffing)

R12

FORT CALHOUN STATION EPIP-OSC-21 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 5 OF 13 Attachment 6.1 - Checklist for Activation of the OSC Page 3 of 3

(/) INIT/TIME

15. After one hour determine if any OSC positions are not filled.

15.1 If a position is not filled, based on the nature of the emergency determine if that position is required.

15.2 Request assistance from the TSC in contacting additional staff, as needed.

R12

FORT CALHOUN STATION EPIP-OSC-21 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 60F 13 Attachment 6.2 - Typical Floor Plan For The Operations Support Center i~D rW n II A. ERF Computer J. EGG Map S. Conference Area B. ERMS K. Procedure Rack T. Fax Machine C. OSC Base Radio L. Sign-In Board U. Procedures (Official Copy)

D. Dosimetry Issue Kit M. Gaitronics V. Team Status Board E. Copy Machine N. Radios/Protective Clothing W. ERMS Network Printer F. Respirators/Air Tanks 0. Kits, Phones, Admin. Supplies X. OSC OPS Liaison Network Phone G. SCBA's P. RP Instruments, Sample Y. Conference Health Physics Network Monitoring Kit Phone H. Writeboard Monitor 0. HIS-20 System Z. MOP Phone

1. Plant Maps R. Briefing Area
1. OSC DIRECTOR 7. OSC STOREKEEPER
2. OSC OPS LIAISON 8. OSC TECHNICIANS
3. OSC CHEMISTRY COORD. 9. OSC ACCT/DOSIMETRY CLERK
4. OSC RP COORD. 10. OSC ERMS OPERATOR
5. OSC MAINTENANCE COORD. 11. OSC RADIO OPERATOR
6. OSC MAINTENANCE PLANNER R12

FORLiALHOUN STATION ( EF( 03C-21 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 7 OF 13 Attachment 6.3 - Typical Accountability Boundaries for the Operations Support Center TYPICAL ACCOUNTABILITY BOUNDARIES FOR THE OPERATIONS SUPPORT CENTER I.11 A),In

,6

-'4 EPIP9206 EPIP-OSC-21 NOTE: OSC Boundaries are determined by the OSC Director.

--- Accountability Boundary X NO Exit - Use Southwest Staircase

  • DO NOT ENTER - Use Southwest Staircase R12

-- - I -j-FORT CALHOUN STATION EPIP-OSC-21 EMERGENCY PLAN IMPLEMENTING PFRtl'DUtiiME  :' PAGE 8 OF 13 Attachment 6.4 - Checklist for Deactivation of OSC Upon termination of emergency activities the following actions should be completed to restore the OSC.

INIT/TIME

1. Disconnect phone harnesses and store phones in the appropriate emergency gear locker. l
2. Disconnect the PA microphone and store in the appropriate emergency gear locker.
3. Place emergency kits in the appropriate emergency gear locker. /
4. Turn off all portable radios and place in their chargers.

/

5. Turn off RP instruments, return to the appropriate emergency gear locker and notify RP of any equipment that may have malfunctioned during use. /
6. Place the portable air monitor in the cage next to the copy machine and lock the cage.
7. Return respirators and air bottles to the appropriate location and notify I RP of equipment requiring recharging. /
8. Turn off the writeboard monitor. /
9. Turn in all logs, paperwork, procedures, etc. to the Administrative Logistics Coordinator in the TSC. /
10. Secure status boards for normal use. /
11. Remove accountability boundary signs from ropes and doors and place in the dosimetry issue kit cabinet. /
12. Place the EATING/DRINKING/SMOKING OR CHEWING signs in the RP Coordinator's kit. /

R12

FORT CALHOUN STATION EPIP-OSC-21 EMERGENCY PLAN IMPLEMENTING -PROGSEDIJE PAGE 9 OF 13 Attachment 6.5 - Guidelines for Setup of the Operations Support Center in An Alternate Location Page 1 of 4 NOTE: Continue to provide emergency support as practicable during relocation.

NOTE: The TSC is the preferred relocation facility.

(6 INIT/TIME

1. The OSC Director should:

1.1 Determine the location to which personnel will be relocated:

  • Ensure the receiving facility is safe and prepared to accept OSC personnel.
  • Determine that the chosen route to that facility is safe and free of unexpected obstacles.
  • Assign a Relocation Coordinator to direct Steps 1.2 through 2.2.
  • Promptly relocate himself to the facility to coordinate an orderly transfer.

1.2 The Relocation Coordinator shall make everyone aware of impending relocations including:

NOTE: A Site Announcement should be considered, but it shall not replace individual contact.

  • Teams that have been dispatched from the OSC
  • Control Room
  • Command and Control position

FORT CALHOUN STATION EPIP-OSC-21 EMERGENCY PLAN IMPLEMENTING PAGE 0 10 OF 13 Attachment 6.5 - Guidelines for Setup of the Operations Support Center in An Altemrate Location Page 2 of' LL1f INIT/TIME 1.3 The OSC Radiation Protection Coordinator should:

  • Determine the need for and if needed, establish radiological control points.
  • Authorize Issuance of dosimeters as conditions warrant.
  • If transferring to the TSC, coordinate with the TSC Protective Measures Coordinator to ensure the TSC is prepared to receive the OSC staff and equipment. Issues to be discussed should include:
  • Maintaining TSC Airlocks
  • Monitoring of personnel and equipment
  • Decontamination procedures
  • Where the OSC Staff should go
  • Coordinate the transfer of OSC RP Personnel and needed equipment.

1.4 The OSC Accountability/Dosimetry Technician should:

  • Issue dosimeters as directed by the RP Coordinator.
  • Take to the new facility:
  • Dosimeters
  • Dosimeter charger
  • Dosimetry records
  • Accountability rosters
  • Other records and logs
  • Verify accountability has been maintained as the OSC staff arrives.

R12

FORT CALHOUN STATION EPIP-OSC-21 EMERGENCY PLAN IMPLEMENTING RE PAGE 11 OF 13 Attachment 6.5 - Guidelines for Setup of the Operations Support Center in-An Alternate Location Page 3 of 4 (I INIT/TIME 1.5 The Maintenance Coordinator should ensure that needed equipment is prepared for transfer, including but not limited to:

  • Protective clothing
  • Respirators
  • Radios
  • Phone head sets, etc.
  • All logs and facility records
2. When all preparations are completed the Relocation Coordinator shall ensure that the rest of the entire OSC staff is aware of:

NOTE: The Coordinator for each position should coordinate relocation their staff and equipment to aid in maintaining accountability.

  • Where they are going
  • The route to taken
  • How the transfer will be made
  • The proper actions to follow upon arrival 2.1 The Relocation Coordinator shall call the alternate facility to inform them that transfer has begun.

2.2 The Relocation Coordinator and a Radiation Protection Technician shall remain in the OSC until informed that accountability has been verified in the new facility.

  • Upon confirmation of reestablished accountability the Relocation Coordinator and the RP Technician should proceed to the relocated facility.
  • If someone is not accounted for a search for that individual(s) shall be conducted.

R12

FORT CALHOUN STATION EPIP-OSC-21 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 12 OF 13 Attachment 6.5 - Guidelines for Setup of the Operations Support Center in An Alternate Location Page 4 of 4go (f2) INIT/TIME

3. Upon arrival of personnel in the new facility:

3.1 The OSC Director shall ensure:

  • The Accountability/Dosimetry Technician has verified accountability by ensuring those previously signed in on the roster with those arriving in the new facility.
  • Arrangements for personnel and equipment decon have been made.
  • The Operations Liaison has reestablished contact with other facilities Ops Liaisons.
  • The facility is set up in a reasonable manner to be reactivated.
  • The Radio Operator has reestablished the radio system and contact with dispatched teams, if applicable.
  • Sufficient phone service is established.
4. Report to the other facilities that the OSC has been relocated.

4.1 Make an announcement within the facility that the OSC has been reactivated. l R12

FOR1QALHOUN STATION ( EPC 3C-21 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 13 OF 13 Attachment 6.6 - Typical Location of Alternate Operations Support Center

.,I

I wI ;

.. `6 J.)

a-ACCOUNTABILITY BOUNDARY R12

WP10 -

Distribut ion Authorized This procedur e does not contain any proprietar y information, or Fort Calhoun Station such informat ion has been Unit No. 1 censored. Thiis Issue may be released to fth e public document room. Proprie!tary Information Includes pers4onnel names, company tele; )hone numbers, and any inforunation, which could ency response.

EPIP-RR-1 impede emerg EMERGENCY PLANT IMPLEMENTING PROCEDURE

Title:

TECHNICAL SUPPORT CENTER DIRECTOR ACTIONS FC-68 Number: 53204 Reason for Change: Revise Format, Delete Note, Delete reference to Chemistry Liaison.

Change ERMS operator to Site Directors Secretary. Change CID to ARs'.

Preparer. Mark Reller Correction (a): Page 3 (issue all pages) (05-28-03)

ISSUED: 02-29-00 3:00 pm R14

FORT CALHOUN STATION EPIP-RR-1 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 1 OF 5 TECHNICAL SUPPORT CENTER DIRECTOR ACTIONS NON-SAFETY RELATED

1. PURPOSE 1.1 The purpose of this procedure is to outline assignment and responsibilities of personnel in the Emergency Response Organization filling the position of Technical Support Center Director.
2. REFERENCES/COMMITMENT DOCUMENTS 2.1 EPIP-TSC-1, "Activation of the Technical Support Center" 2.2 EPIP-EOF-21, Potassium Iodide Issuance" 2.3 EPIP-OSC-1, "Emergency Classification" 2.4 EPIP-EOF-7, "Protective Action Guidelines" 2.5 EPIP-OSC-2, "Command and Control Position Actions/Notifications 2.6 Commitment Documents (other than Ongoing)
  • AR 11809, LIC-91-189
3. DEFINITIONS None
4. PREREQUISITES None
5. PROCEDURE 5.1 Use the Technical Support Center Director Checklist, Attachment 6.1, as an aid to completing required actions.

5.2 Review the procedure and checklist, and accomplish the applicable steps both upon initial activation and periodically, as required, thereafter.

R14

I I FORT CALHOUN STATION EPIP-RR-1 1 EMERGENCY PLAN IMPLEMENTING PA6@:itOR - PAGE 2 OF 5 5.3 Retain all docum entation (logs, calculation sheets, notes, etc.) generated or used during the emergency. At the termination, deliver all documentation to the TSC Administrative Logistics Coordinator position in the TSC.

6. ATTACHMENTS 6.1 Technical Support Center Director Checklist R14

FORT CALHOUN STATION EPIP-RR-1 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 3 OF 5 Attachment 6.1 - Technical Support Center Director Checklist

  • Maintain a log of all key activities * *

(I. INIT/TIME

1. Obtain worker packet and put on the Personnel Identification Badge. l I
2. If not yet completed, activate the TSC per EPIP-TSC-1.

NOTE: The TSC Administrative Logistics Coordinator is responsible for coordinating shift rotations and necessary notifications for call out l

personnel.

3. Working with your staff determine 24-hour staffing schedule for all TSC positions and provide to the TSC Administrative Logistics Coordinator.
4. Periodically review the following steps and perform, as required.

4.1 Maintain control of the TSC working area and keep noise levels down.

4.2 Coordinate the actions of the TSC Security Coordinator, the TSC Administrative Logistics Coordinator, the Reactor Safety Coordinator, Protective Measures Coordinator, and the TSC Operations Liaison. I 4.3 Keep the Site Director informed of operational and radiological analyses occurring as a result of the emergency.

4.4 Ensure only necessary personnel are in the TSC working area.

4.5 Review TSC support needed and have needed expertise called in.

4.6 If directed by the Site Director, approve information releases to the public (via available communications).

4.7 Ensure communications are maintained between the TSC, Control Room, OSC and the EOF.

4.8 When staffed, keep the Site Directors Secretary up to date with event chronology information for transmission to other ERMS locations.

R14

I I FORT CALHOUN STATION EPIP-RR-11 EMERGENCY PLAN IMPLEMENTING PRbCEDURE PAGE 4 OF 5 Attachment 6.1 - Technical Support Center Director Checklist

()INIT/TIME 4.9 If advised by the Protective Measures Coordinator that Potassium Iodide (KI) issuance is warranted, then refer to EPIP-EOF-21 and discuss with the Site Director.

4.10 If advised by the Protective Measures Coordinator that habitability conditions in the OSC have degraded, then consider and recommend to the Site Director the relocation of the OSC to an appropriate location. Possible alternatives are:

  • Training Center
  • Warehouse
  • Administration Building 4.11 Review status board information, and ensure status boards, including "priorities" listings, are kept up-to-date.

4.12 Whenever relieved by another qualified TSC Director, fully brief your relief on current emergency status, actions taken during shift, and actions in progress.

4.13 CLASSIFICATION: Assess the current emergency classification with the Site Director to determine whether it is still valid per EPIP-OSC-1.

4.14 PARs: Review with the Site Director, the need to authorize issuance of protective action recommendations to offsite authorities per EPI P-EOF-7.

4.15 NOTIFICATIONS: Assist the Site Director in ensuring that all notifications, including PARs are made per EPIP-OSC-2.

4.16 If directed by the Site Director, coordinate with the Shift Manager the sounding of the appropriate plant alarm and associated Gai-Tronics announcement for:

  • emergency classification upgrades
  • other imminent dangers (tomadoes, fires, etc.)

4.17 Ensure TSC personnel are performing necessary technical analyses of the emergency and providing alternative solutions to concerns.

R14

FORT CALHOUN STATION EPIP-RR-1 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 5 OF 5 Attachment 6.1 - Technical Support Center Director Checklist (W) INIT/TIME 4.18 Ensure the Reactor Safety Coordinator's group is performing core damage assessments, as needed.

4.19 If it is determined that an assessment team is .needed to verify if any radioactive release is in progress or to determine the source and release path of any release in progress, assign adequate personnel to assist with this task. They are to coordinate with and report any findings to the Protective Measures Coordinator. (AR 11089) 4.20 Coordinate with the Control Room Coordinator to identify approved procedures, or direct the TSC Staff to provide new procedures to which operators may transition from off-normal procedures when the event has been mitigated. /

5. Review EPIP-OSC-2 with the Site Director for guidelines when conditions warrant a downgrade or termination of an emergency classification.

Discuss proposed downgrades or termination with the Site Director. .. /

R14

WP10 Distribuition Authorized This procedu ire does not contain any proprieti iry Information, or Fort Calhoun Station such Informa ation has been his Issue may be Unit No. 1 censored. T1 released to t?ie public document room. Propri etary Information Includes pers;onnel names, company tele,phone numbers, and any Infor Tnation, which could Impede emer gency response.

EPIP-RR-17 EMERGENCY PLAN IMPLEMENTING PROCEDURE

Title:

TSC SECURITY COORDINATOR ACTIONS FC-68 Number: EC 28023 Reason for Change: Revise format. Add instructions as required by users. Add instructions for actions to be taken upon event termination.

Requestor: M. Reller Preparer M. Reller Correction (a): Page 2 (05-28-03) (Issue all pages)

ISSUED: 12-10-02 3:00 pm R15

FORT CALHOUN STATION EPIP-RR-1 7 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 1 OF 4 TSC SECURITY COORDINATOR ACTIONS NON-SAFETY RELATED

1. PURPOSE 1.1 This procedure details assignments and responsibilities of the TSC Security Coordinator.
2. REFERENCES/COMMITMENT DOCUMENTS None
3. DEFINITIONS None
4. PREREQUISITES None
5. PROCEDURE NOTE: The attached checklist is designed as a reminder of actions which are required to be performed during an emergency condition.

5.1 Review the procedure and checklist, and accomplish the applicable steps both upon initial activation and periodically, as required, thereafter.

5.2 At the completion of the shift or at event termination, initial the steps which are completed.

5.3 Retain all non-safeguards documentation (logs, calculations sheets, notes, etc.)

generated or used during the emergency. At the termination, deliver all non-safeguards documentation to the Administrative Logistics position in the TSC.

The TSC Security Coordinator will retain all safeguards documentation.

6. ATTACHMENTS 6.1 TSC Security Coordinator Checklist R15

FORT CALHOUN STATION EPIP-RR-1 7 EMERGENCY PLAN IMPLEMENTING gt-MA PAGE 2 OF 4 Attachment 6.1 - TSC Security Coordinator Checklist Page 1 of 3

  • Maintain a log of all key activities **

(I INITIALS NOTE: Actions may be performed out of sequence based on the judgement of the user.

1. Upon arrival:
  • Don Personnel Identification Badge
  • Obtain Worker Packet
  • Report your arrival to the TSC Director
  • Establish communication with Shift Security Supervisor (SSS)
  • Assist in the activation of the TSC per EPIP-TSC-1
2. Interface with:

2.1 The SSS to ensure: Contact Number

  • All onsite Security Force personnel have required Dosimetry I
  • The needs of the Security Force are met
  • The TSC is aware of any changes in location of Security Force personnel (ensure movements are coordinated through the OSC)
  • Security Force recall is initiated, if required
  • Coordination of 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> security staffing
  • The Security Force maintains plant security
  • Personal safety issues (haz-mat, fires, etc.) are discussed 2.2 The Protective Measures Coordinator to ensure:

2.2.1 The Security Force is located in areas to maintain personnel safety and their radiological dose ALARA. Consider

  • In-plant response
  • Wind direction
  • Radiological conditions 2.2.2 If relocation is required, personnel movement is coordinated with the OSC.

R15

FORT CALHOUN STATION EPIP-RR-17 EMERGENCY PLAN IMPLEMENTING PFROCEDFtE PAGE 3 OF 4 Attachment 6.1 - TSC Security Coordinator Checklist Page 2 of 3 0 INITIALS 2.3 Ensure the onsite Command and Control Position is kept abreast of all security issues and concerns.

3. Ensure support for accountability by:

NOTE: Since the TSC does not normally assume Command and Control, the accountability status report should go to the Shift Manager.

  • Providing adequate security personnel for the effort
  • Providing initial accountability status to the Shift Manager
  • Supporting search for any missing personnel
4. If a Site Evacuation is ordered or is imminent ensure:
  • Local Law Enforcement agencies are contacted
  • Traffic control is established on the plant assess road
  • The Administration Building and Training Center personnel are notified
  • The entire Owner Controlled and Protected Area are cleared of unnecessary personnel
  • Evacuees are aware of their destination, and the correct route to be taken
5. Determine what security contingency measures need to be initiated or terminated and ensure the NRC is aware of conditions, as required.
6. When relieved ensure:
  • Relief is aware of emergency conditions
  • Actions taken by your position (including status of these actions)
  • Review this checklist and provide extra copy for next shift
  • All paper work is retained until event terminations R15

FORT CALHOUN STATION EPIP-RR-1 7 EMERGENCY PLA'N IMPLEMENTING PROCEDURE PAGE 4 OF 4

- . Attachment 6.1 - TSC Security Coordinator Checklist Page 3 of 3 (LZ INITIALS

7. Upon event termination:
  • Inform SSS of termination and ensure the requirements of SECOP-28 are met
  • Provide assistance as requested by the Recovery Manager
  • Turn in all documentation generated by your position and the Security Department during the event to the TSC Administrative Logistics Coordinator R15

WP10 Distribution Auth orized This procedure does noot contain any proprietary info=im ation, or Fort Calhoun Station such information has t been Unit No. 1 censored. This issue rnay be released to the public i document room. Proprietary information Includes personnel nai mnes, company telephone numbers, and any information, w 'hich could ponse.

EPIP-RR-1 7A Impede emergency res EMERGENCY PLAN IMPLEMENTING PROCEDURE

Title:

TSC ADMINISTRATIVE LOGISTICS COORDINATOR ACTIONS FC-68 Number: EC 29517 Reason for Change: Add instructions for TSC Admin Logistics Coordinator to interface with the EOF Admin Logistics Manager to determine what special needs may be needed. To ensure that it is understood who performs these tasks.

Requestor: Mark Reller Preparer: Mark Reller Correction (a): Page 2 (05-28-03) (Issue all pages)

ISSUED: 11-07-02 3:00 pm R20

FORT CALHOUN STATION EPIP-RR-1 7A EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 1 OF 6 TSC ADMINISTRATIVE LOGISTICS COORDINATOR ACTIONS

1. PURPOSE 1.1 This procedure provides guidance to the TSC Administrative Logistics Coordinator in performing actions outlined in the Emergency Plan Implementing Procedures (EPIPs).
2. REFERENCES/COMMITMENT DOCUMENTS 2.1 Commitment Documents
3. DEFINITIONS None
4. PREREQUISITES None
5. PROCEDURE 5.1 Review the procedure and checklist, Attachment 6.1 and accomplish the applicable steps both upon initial activation and periodically, as required, thereafter.

5.2 At the completion of the shift or at event termination, check the steps which are completed.

5.3 Retain all documentation (logs, calculation sheets, notes, etc) generated or used during the emergency.

5.4 At event termination, collect all documentation from the TSC, OSC and CR.

5.4.1 Assemble all documentation for legal records and event analysis. Request the Emergency Planning Department to place in safe storage.

6. ATTACHMENTS 6.1 TSC Administrative Logistics Coordinator Checklist 6.2 Procurement or Addition of Diesel Fuel for Emergency Diesel Generators R20

I I FORT CALHOUN STATION EPIP-RR-1 7A EMERGENCY PLAN IMPLEMENTING PROCEDURE- PAGE 2 OF 6 Attachment 6.1 - TSC Administrative Logistics Coordinator Checklist Page 1 of 4

  • Maintain a log of all key activities *
  • LL) INIT/TIME
1. Upon arrival:
  • Obtain worker packet
  • Put on the Personnel Identification badge
  • Assist in activation of TSC per EPIP-TSC-1 I
2. Direct:

2.1 Site Director's Secretary to:

  • Maintain a log for the Site Director
  • Gather information for input to the ERMS.

2.2 Other Site Directors Secretary to operate the ERMS.

2.3 The COP Communicator to:

  • Perform required notifications on the COP Network
  • Maintain the Radiological Status Board [AR 13301]

2.4 The Status Board Keeper to obtain data from the ERFCS or Control Room to maintain the Status Board.

2.5 The Emergency Response Coordinator to assist other TSC positions.

2.6 Direct one Administrative Assistant to maintain the TSC Accountability Roster.

2.7 Direct the other Administrative Assistant to:

  • Perform copying duties in the TSC
  • Distribution duties in the TSC
  • Operate the fax machine R20

FORT CALHOUN STATION EPIP-RR-1 7A EMERGENCY PLAN IMPLEMENTING-PROCE-OURE PAGE 3 OF 6 Attachment 6.1 Page 2 of 4 (continued)

INIT/TIME

3. Secure access/egress to the TSC from the back (west) entrance using the following signs:
  • TSC IS ACTIVATED NO EXIT
  • TSC IS ACTIVATED AUTHORIZED PERSONNEL ONLY
  • WHEN TSC IS ACTIVATED DO NOT ENTER. USE EAST ENTRANCE
  • TSC IS ACTIVATED .
4. Establish 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> staffing:

4.1 Determine 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Staffing for:

TSC (assist the Site Director using FC-EPF1 0)

. Control Room (use FC-EPF-10)

OSC (request that OSC Director prepare using FC-EPF-9 and fax to you) 4.2 When you have all the staffing schedules:

0 Verify that all positions are filled S Verify that second shift positions are filled 0 Post shift schedules in the TSC 0 Fax shift schedules to the CR and OSC for posting Distribute shift schedules in the TSC 4.3 Notify personnel on the second shift to inform them of their work schedule (use other personnel to assist in this task as needed) I

5. Periodically review the following steps and perform them as required:

5.1 Prepare copies of the following and distribute them throughout the TSC and transmit to the OSC, as required.

  • Data sheets
  • Messages 5.2 Assist the Site and TSC Director, as needed.

R20

FORT CALHOUN STATION EPIP-RR-1 7A EMERGENCY PLAN IMPLEMENTING P4JIE " PAGE 4 OF 6 Attachment 6.1 Page 3 of 4 (continued)

INIT/TIME 5.3 Contact the EOF Administrative Logistics Managers when:

  • Evacuation of plant personnel to the North Omaha is ordered
  • Any person is injured, contaminated and requires off-site medical response 5.4 Working with the EOF Administrative Logistics Manager coordinate logistics support, including:

0 Transportation 0

Food Lodging 0

Special equipment Supplies /

NOTE: Step 6 may be performed by the EOF Administrative Logistics Manager.

6. Determine from the Control Room Coordinator the status of the emergency diesel generators.

6.1 If one or both are operating, within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> [AR 12110]:

NOTE: The phone number for the diesel fuel supplier can be found in the Emergency Phone Book in the "Off-Site Support Agencies' section.

  • Contact the diesel fuel supplier to arrange for the potential delivery of diesel fuel.
  • If Diesels are loaded arrange for continuous fuel deliveries to the site.

6.2 If diesel fuel can not be delivered to the site within 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> of the start of the diesels:

  • Request that the TSC or Site Director request an emergency work order to install the hardware for diesel fuel transfer described in Attachment 6.2. g i R20

FORT CALHOUN STATION EPIP-RR-1 7A EMERGENCY PLAN IMPLEMENTING:PROCEEIJRE PAGE 5 OF 6 Attachment 6.1 Page 4 of 4 (continued)

INIT/TIME

7. As required, provide a detailed briefing to your relief covering:

0 Emergency conditions 0 Actions taken (current status) l

8. At emergency termination:
  • Collect documentation and logs from all onsite facilities
  • Ensure that the TSC is placed back into a state of readiness
  • Review this checklist and ensure that special orders or supplies that were ordered are canceled
  • Ensure personnel on the shift roster are informed of status of emergency and whether or not to report for their shift _ ~~~~/

R20

FORT CALHOUN STATION EPIP-RR-17A EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 6 OF 6 Attachment 6.2 - Procurement or Addition of Diesel Fuel for Emergency Diesel Generators INITIALS

1. DIESEL FUEL TRANSFER FROM FO-10 TO FO-1 (Auxiliary Boiler Fuel Storage Tank to Diesel Generator Fuel Oil Storage Tank)

NOTE: At full rated power, each diesel generator consumes approximately 3 gallons per minute. FO-37 delivers approximately 6 gallons per minute. If only one diesel is in service, or if the diesels are running at less than rated load, the level in FO-1 will steadily increase when adding fuel oil to FO-1 from FO-10.

There are several possible methods to transfer diesel fuel from FO-1 0 to FO-1.

This method allows using installed equipment that will require a minimum amount of ntemporary" changes to accomplish the fuel transfer:

1.1 Connect a 1 inch hose from FO-201 "Auxiliary Feedwater Pump FW-54 Fuel Oil Transfer Pump FO-37 Discharge Drain Valve" to the 3 inch fill connection on FO-1. This will require approximately 400 feet of hose. The 1 inch hose may be run inside the 3 inch fill connection and duct taped in place. All mechanical joints should be stabilized with lock wires and taped to prevent leakage. Sleeves or blocks should be used around hoses that are run through doors to prevent damage to the hose. (Hose fittings and a hand pump are available in the warehouse stored under Stock Code Number 30869-2(fuel)).

1.2 The normal Auxiliary Feedwater Pump fuel oil system lineup in Ol-AFW-1 can be used, but HC-FO-37 must be placed in the "Hand" position, or it will automatically shut off when the Fuel Oil Day Tank FO-38 is full. Also, FO-1 96 must be closed or fuel will recirculate through FO-38 back to FO-10 if that is the path of least resistance.

FO-38 should be checked and refilled periodically; it contains an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> supply of fuel oil when full.

1.3 Continue to monitor LI-2107 and shut off the transfer pump when FO-1 level is approximately 17,500 gallons.

1.4 Upon completion of the fuel transfer evolution, drain and store hose properly to prevent possible fuel jelling in the hose.

R20

WP10 Distribu trion Authorized Fort Calhoun Station This procedu re does not contain Unit No. 1 any proprietairy information, or such Informa tion has been censored. Tt his Issue may be released to tt he public document room. Propri etary Information Includes pert sonnel names, company tele!phone numbers, infor 'matlon, which could EPIP-RR-1 9A and any emer!

impede gency response.

EMERGENCY PLAN IMPLEMENTING PROCEDURE

Title:

OPERATIONS LIAISON ACTIONS FC-68 Number: EC 31900 Reason for Change: Insert step in Attachment 6.2 to include tracking of EOP's and AOP's by TSC Ops Liaison.

Requestor: Mark Reller Preparer: Mark Reller Correction (a): Pages 3, 4 and 8 (Issue all pages) (05-28-03)

ISSUED: 04-15-03 3:00 pm R6

FORT CALHOUN STATION EPIP-RR-19A EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 1 OF 8 OPERATIONS LIAISON ACTIONS NON-SAFETY RELATED

1. PURPOSE 1.1 This procedure provides guidance to the Control Room, TSC, OSC and EOF Operations Liaisons in performing actions in response to an emergency at Fort Calhoun Station [AR 11390].
2. REFERENCES/COMMITMENT DOCUMENTS 2.1 EPIP-OSC-1, Emergency Classification 2.2 EPIP-EOF-7, Protective Action Guidelines 2.3 FCS Abnormal Operating Procedures (AOPs) 2.4 FCS Emergency Operating Procedures (EOPs) 2.5 Ongoing Commitments
  • AR 11390, LIC-91-065R
3. DEFINITIONS None
4. PREREQUISITES None
5. PROCEDURE NOTE: The attached checklist are designed as a reminder of actions which are required to be performed during an emergency condition.

5.1 The Control Room Operations Liaison will use Attachment 6.1 as an aid to completing required actions [AR 11390].

5.2 The TSC Operations Liaison will use Attachment 6.2 as an aid to completing required actions.

5.3 The EOF Operations Liaison will use Attachment 6.3 as an aid to completing required actions.

R6

FORT CALHOUN STATION EPIP-RR-1 9A EMERGENCY PLAN IMPLEMENTING  ; PAGE 2 OF 8 5.4 The OSC Operations Liaison will use Attachment 6.4 as an aid to completing required actions.

5.5 Review the procedure and appropriate checklist, and accomplish the applicable steps both upon initial activation and periodically, as required, thereafter.

5.6 At the completion of the shift or at event termination, initial the steps which have been completed.

5.7 Retain all documentation (logs, calculation sheets, notes, etc.) generated or used during the emergency. At the termination, deliver all documentation to the TSC Administrative Logistics Coordinator in the TSC, or the EOF Administrative Logistics Manager in the EOF.

6. ATTACHMENTS 6.1 Control Room Operations Liaison Checklist 6.2 TSC Operations Liaison Checklist 6.3 EOF Operations Liaison Checklist 6.4 OSC Operations Liaison Checklist I R6

FORT CALHOUN STATION EPIP-RR-1 9A EMERGENCY PLAN IMPLEMENTING-PROCEDURE PAGE 3 OF 8 Attachment 6.1 - Control Room Operations Liaison Checklist Page 1 of 1

  • Maintain a log of all key activities *
  • INIT/TIME
1. Obtain worker packet and put on Position Identification Badge. I
2. Interface with the Control Room Coordinator to receive a briefing on the following:

2.1 Plant status and actions taken; -~~~~~~

2.2 Current Classification; 2.3 Plant prognosis; 2.4 Status of AOPs; 2.5 Status of EOPs.

3. Stand by to establish a conference call with the TSC, OSC and EOF Operations Liaisons. The TSC and/or OSC and/or EOF will initiate this conference by calling the Control Room upon their arrival.
4. Periodically review the following steps and perform, as required. /

4.1 Provide updates of the information listed above to the TSC, OSC and EOF Operations Liaisons using the established communications link.

4.2 Provide a detailed briefing to your shift relief of any actions taken and the current emergency status.

R6

FORT-CALHOUN STATION EPIP-RR-1 9A EMERGENCY PLAN IMPLEMENTING PROCEDURE-- "' PAGE 4 OF 8 Attachment 6.2 - TSC Operations Liaison Checklist Page 1 of 2

  • Maintain a log of all key activities *
  • INIT/TIME
1. Obtain worker packet and put on the Personnel Identification I Badge. l
2. Using the Ops Liaison phone, perform the following:

2.1 Pick up the receiver and ask if the Control Room is on the line.

2.2 IF the Control Room is already on the line, THEN go to Step 3. Otherwise, continue.

2.3 Dial the Control Room number (listed on the pull-out template on the bottom of the phone) to access the Control Room Operations Liaison.

3. Interface with the Control Room Operations Liaison to receive a briefing on the following:

3.1 Plant status and actions taken; 3.2 Current Classification; l 3.3 Plant prognosis; 3.4 Status of AOP's; 3.5 Status of EOP's.

4. Brief the Site and TSC Director on operational status and review l status boards and ERFCS for accurate data.
5. Assist the Site Director in formulating an appropriate protective action recommendation based on plant parameters when necessary.

R6

FORT CALHOUN STATION EPIP-RR-1 9A EMERGENCY PLAN IMPLEMENTING IPOtIEDUtRE PAGE 5 OF 8 Attachment 6.2 - TSC Operations Liaison Checklist Page 2 of 2

  • Maintain a log of all key activities *
  • INIT/TIME
6. Periodically review the following steps and perform, as required:

6.1 Interface with the NRC Response Team and OPPD support personnel on technical and operational matters relating to the emergency.

6.2 Review EPIP-OSC-1 to determine if the current classification is valid.

6.3 Follow the status of EOPs and AOPs and report significant changes of problems to the-TSG Director. I-6.4 Provide a detailed briefing to your shift relief of any actions _ .

taken and the current emergency status.

l

.io R6

FORT CALHOUN STATION EPIP-RR-1 9A EMERGENCY PLAN IMPLEMENTING PROCIMUAE - PAGE 6 OF 8 Attachment 6.3 - EOF Operations Liaison Checklist Page 1 of 2

  • Maintain a log of all key activities *
  • INIT/TIME
1. Obtain and put on the Personnel Identification Badge. l
2. Using the Ops Liaison phone, perform the following:

2.1 Pick up the receiver and"ask if the Control Room is on the line.

2.2 IF the Control Room is already on the line, THEN go to Step 3. Otherwise, continue.

2.3 Dial the Control Room number (listed on the pull-out template on the bottom of the phone) to access the Control Room Operations Liaison.

3. Interface with the Control Room' Operations Liaison and the TSC Operations Liaison to receive a briefing on the following:

I 3.1 Plant status and actions taken; 3.2 Current Classification; 3.3 Plant prognosis;

4. Brief the Emergency Director on operational status and review status boards and ERFCS for accurate data.

l

5. Periodically review the following steps and perform, as required:

5.1 Interface with the NRC Response Team and OPPD support personnel on technical and operational matters relating to the emergency.

I 5.2 Assist the Emergency Director with staff and non-OPPD agency briefings.

5.3 Review EPIP-OSC-1 to determine if the current classification is valid and keep the Emergency Director informed.

R6

FORT CALHOUN STATION EPIP-RR-1 9A EMERGENCY PLAN IMPLEMENTING 1aOCEDURE PAGE 7 OF 8 Attachment 6.3 - EOF Operations Liaison Checklist Page 2 of 2

  • Maintain a log of all key activities *
  • INIT/TIME 5.4 Provide a detailed briefing to your shift relief of any actions taken and the current emergency status. /

R6

FORT CALHOUN STATION EPIP-RR-1 9A EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 8 OF 8

. Attachment 6.4 - OSC Operations Liaison Checklist Page 1of 1

-

  • Maintain a log of all key activities *
  • INIT/TIME
1. Obtain worker packet and put on the Personnel Identification Badge. /
2. Using the Ops Liaison phone, perform the following:

2.1 Pick up the receiver and ask if the Control Room is on the line.

2.2 IF the Control Room is already on the line, THEN go to Step 3. Otherwise, continue.

2.3 Dial the Control Room number (listed on the pull-out template on the bottom of the phone) to access the Control Room Operations Liaison. /

3. Interface with the Control Room Operations Uaison only when necessary to determine information applicable to OSC functions. 'I Brief the-OSC Director-when-necessary. So-me of these functions include:

3.1 Information concerning equipment/system status, especially when needed for team briefings. /

3.2 Operator dispatch directly to an affected area, so that the OSC personnel may be directed to assist if necessary. /

3.3 Operator dispatch to the OSC, so that the OSC may better prepare for necessary team briefing/dispatch process. /

4. Monitor the network to determine any other information that may impact the OSC, and inform the OSC Director. /
5. Periodically review the following steps, and perform, as required:

5.1 Provide a detailed briefing to your shift relief of any actions taken and the current emergency status. /

R6

WP1o0 .

Distributioni Authorized This Procedure dloes not contain Fort Calhoun Station any proprietary iiinformation, or Unit No. 1 such informationi has been censored. This I:ssue may be released to the p ublic document room. Proprietayy information Includes personr iel names, company telephcme numbers, and any informat ion, which could cy response.

-EPlP-RR-21 impede emergen EMERGENCY PLAN IMPLEMENTING PROCEDURE

Title:

OPERATIONS SUPPORT CENTER DIRECTOR ACTIONS FC-68 Number: DCR 10112 K>~Reason for Change: Add ERMS operator to list of people needed for 24-hour staffing schedule. Remove step 5 of Aft 6.1 as this is redundant to EPIP-OSC-21 Aft 6.2 step 4.b Initiator: D. Levine Preparer M. Reller Correction (a): Page 2 (issue all pages) (05-28-03)

ISSUED: 09-23-99 3:00 pm R12

FORT CALHOUN STATION EPIP-RR-21 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 1 OF 3 OPERATIONS SUPPORT CENTER DIRECTOR ACTIONS NON-SAFETY RELATED

1. PURPOSE 1.1 The purpose of this procedure is to provide guidance to the Operations Support Center (OSC) Director.
2. REFERENCES/COMMITMENT DOCUMENTS 2.1 EPIP-OSC-9, 'Emergency Team Briefings" 2.2 EPIP-OSC-21, "Activation of the Operations Support Center" 2.3 EPIP-EOF-1 1, "Dosimetry Records, Exposure Extensions, and Habitability"
3. DEFINITIONS None
4. PREREQUISITES None
5. PROCEDURE 5.1 Review the procedure and checklist, and accomplish the applicable steps both upon initial activation and periodically, as required, thereafter.

5.2 At the completion of the shift or at event termination, initial the steps which are completed.

5.3 Retain all documentation (logs, calculation sheets, notes, etc.) generated or used during the emergency. At the termination, deliver all documentation to the TSC Administrative Logistics Coordinator position in the TSC.

6. ATTACHMENTS 6.1 OSC Director's Checklist R12

EPIP-RR-21 FORT CALHOUN STATION i- EPIP-RR-21 EMERGENCY PLAN IMPLEMENTING 'tlJURES' -/ PAGE 2 OF 3 Attachment 6.1 - OSC Directors Checklist Page 1 of £r

  • Maintain a log of all key activities * *

(le INITfrIME

1. Obtain worker packet and put on the Personnel Identification Badge. I
2. Obtain current plant status from the TSC Director. If the TSC is not yet manned, obtain information from best available source (i.e., ERFCS, Control Room, OSC Operations Liaison, etc).
3. Activate the OSC per EPIP-OSC-21.
4. Brief the OSC personnel on initial plant conditions and events. /
5. Periodically review the following steps and perform, as required:

5.1 Coordinate the development of plans for required maintenance activities, and direct the emergency response functions of the OSC as necessary to assist the Site Director in mitigating the consequences of the accident.

5.2 Ensure the OSC is prepared to assemble, brief, and dispatch emergency teams as required per EPIP-OSC-9. - /

5.3 Consider the need for QA/QC coverage when dispatching teams but DO NOT delay dispatch of teams if QA/QC personnel are not available.

5.4 Ensure that accountability of the personnel in the OSC is maintained.

-5.s5-5(eep the ite-Directorupdatedonthesatusef-OSG-activities.

5.6 Ensure that accountability of the emergency teams dispatched from the OSC is maintained on the "Team Status Board."

5.7 Ensure that habitability checks are performed in the OSC and other occupied areas (Assembly Areas, Security Building, and the Warehouse) per EPIP-EOF-1 1.

5.8 Ensure the OSC status boards are maintained with current information.

R12

FORT CALHOUN STATION EPIP-RR-21 EMERGENCY PLAN IMPLEMENTINGTROCEDtRE PAGE 3 OF 3 Attachment 6.1 - OSC Director's Checklist Page 2 of 2

(& INIT/TIME

6. Ensure a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> work schedule for the following positions is prepared and provide a copy to the TSC Administrative Logistics Coordinator.

(use EPF-9, as necessary) 0 OSC Director 0 OSC Operations Liaison 0 Radiation Protection Coordinator 0 Chemistry Coordinator 0

Maintenance Coordinator ERMS Operator l

7. Provide a detailed briefing to your shift relief of any actions taken and the current emergency status.
8. When the emergency is terminated direct that all personnel restore their l emergency equipment and worker packets. Release the OSC personnel when complete.

R12

WP10 Distribuition Authorized This procedu ire does not contain any proprietairy Information, or Fort Calhoun Station such informaition has been Unit No. 1 censored. TIhis issue may be released to ttie public document room. Propri etary Information Includes peri ;onnel names, company tele,phone numbers, and any Infor mation, which could Impede emer gency response.

EPIP-RR-21A EMERGENCY PLAN IMPLEMENTING PROCEDURE

Title:

MAINTENANCE COORDINATOR ACTIONS FC-68 Number: DCR 10961 Reason for Change: Reformat per Writers Guide.

Initiator: Doug Levine Preparer: Mark Reller Correction (a): Page 2 (05-28-03) (Issue all pages)

ISSUED: 11-30-99 3:00pm R4

FORT CALHOUN STATION EPIP-RR-21 A EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 1 OF 2 MAINTENANCE COORDINATOR ACTIONS NON-SAFETY RELATED I

1. PURPOSE 1.1 The purpose of this procedure is to provide guidance to the Operations Support Center's Maintenance Coordinator.
2. REFERENCES/COMMITMENT DOCUMENTS 2.1 EPIP-OSC-9, Emergency Team Briefings 2.2 EPIP-OSC-21, Activation of the Operations Support Center 2.3 EPIP-EOF-1 1, Dosimetry Records, Exposure Extensions, and Habitability 2.4 EPIP-RR-21, OSC Director Actions
3. DEFINITIONS NONE
4. PREREQUISITES -

NONE

5. PROCEDURE NOTE: The attached checklist is designed as a reminder of actions which are required to I be performed during an emergency condition.

5.1 Review the procedure and checklist, and accomplish the applicable steps both upon initial activation and periodically, as required, thereafter.

5.2 At the completion of the shift or at event termination, initial the steps which are completed.

5.3 Retain all documentation (logs, calculation sheets, notes etc) generated or used during the emergency. At the termination, deliver all Maintenance group documentation to the TSC Administrative Logistics Coordinator in the TSC.

6. ATTACHMENTS 6.1 Maintenance Coordinator's Checklist R4

FORT CALHOUN STATION EPIP-RR-21A EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 2 OF 2 Attachment 6.1 - Maintenance Coordinator's Checklist

  • Maintain a log of all key activities * *

(f6 INIT/TIME

1. Obtain worker packet and put on the Personnel Identification Badge. I I
2. Coordinate setting up the OSC per EPIP-OSC-21. /
3. Update the OSC Personnel Assignment Board with the names of current shift of Maintenance group personnel. /
4. Periodically review the following steps and perform, as required:

4.1 Coordinate the maintenance and damage control activities of the Maintenance Coordinator group as necessary to mitigate the consequences of the accident and as directed by the OSC Director.

4.2 Assist the OSC Director in forming and briefing emergency teams for medical response, damage control, and accident mitigation.

4.3 Interface with the Radiation Protection Coordinator and Chemistry Coordinator as required to complete briefings for all teams dispatched from the OSC per EPIP-OSC-9.

4.4 Coordinate "Administrative Exposure Limit Increases" as necessary for the Maintenance Coordinator group per EPIP-EOF-1 1.

4.5 Coordinate the acquisition of repair parts and supplies as necessary to support emergency activities. /

5. Provide a detailed briefing to your shift relief of any actions taken and the current emergency status. /

R4

WP10 Distribution Authorized This procedure does not contain any proprietary information, or Fort Calhoun Station such information has been Unit No. 1 censored. This Issue may be released to the public docuir ient room. Proprietary informaticon Includes personnel names, company telephone numbers and any Information, which ccould Impede emergency response EPIP-RR-28 EMERGENCY PLAN IMPLEMENTING PROCEDURE

Title:

OSC ACCOUNTABILITY AND DOSIMETRY TECHNICIAN ACTIONS FC-68 Number EC 27778 Reason for Change: Revise per Writer's Guide. Delete reference to RP-604 and HIS-20 since they do not address emergency exposure.

Requestor: M. Reiter Preparer: M. Reller Correction (a): Page 2 (05-28-03) (Issue all pages)

ISSUED: 09-25-01 3:00 pm R8

FORT CALHOUN STATION EPIP-RR-28 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 1 OF 2 OSC ACCOUNTABILITY AND DOSIMETRY TECHNICIAN ACTIONS K> 1. PURPOSE This procedure provides instruction and guidance to the Operations Support Center's Accountability and Dosimetry Technician.

2. REFERENCES/COMMITMENT DOCUMENTS 2.1 RPI-6, Alternate Access Control of Radiologically Controlled Area 2.2 RP-602, Personnel Dosimetry Issue and Changeout 2.3 EPIP-OSC-21, Activation of the Operations Support Center 2.4 EPIP-EOF-11, Dosimetry Records, Exposure Extensions and Habitability
3. DEFINITIONS None
4. PREREQUISITES None
5. PROCEDURE 5.1 Use the OSC Accountability and Dosimetry Technician's Checklist, Attachment 6.1, as an aid to completing required actions.

NOTE: The attached checklist is designed as a reminder of actions which are required to be performed during an emergency condition.

5.2 Review the procedure and checklist, and accomplish the applicable steps both upon initial activation and periodically, as required, thereafter.

5.3 At the completion of the shift or at event termination, initial the steps which are completed.

5.4 Retain all documentation (logs, calculation sheets, note, etc.) generated or used during the emergency. At the termination, deliver all documentation to the Radiation Protection Coordinator.

6. ATTACHMENTS 6.1 OSC Accountability and Dosimetry Technician's Checklist R8

FORT CALHOUN STATION EPIP-RR-28 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 2 OF 2 Attachment 6.1 - OSC Accountability and Dosimetry Technician's Checklist Page 1 of 11

  • Maintain a log of all key activities * *

(Li INITIALS

1. Obtain worker packet and put on the Personnel Identification Badge.
2. Set up the accountability boundaries as described in EPIP-OSC-21.
3. Obtain the OSC Accountability Roster and maintain it at the access control point.
4. Assume access control duties for the radiologically control area per RPI-6 and EPIP-EOF-1 1.
5. Notify the Radiation Protection Coordinator that access control and accountability control has been established.
6. Periodically review the following steps and perform as required:

6.1 Maintain the OSC Accountability Roster by ensuring all personnel 1' sign in and out of the OSC.

6.2 If requested provide a copy of the current OSC Accountability Roster to Security Officers.

6.3 Issue TLDs as necessary.

7. Provide a detailed briefing to your shift relief of any action taken and the current emergency status.

R8

WP10 DistribLition Authorized This proceduire does not contain any propriet2try information, or Fort Calhoun Station such informaition has been Unit No. 1 censored. TIhs Issue may be released to tltie public document room. Propri ietary information Includes pen *onnel names, company tek ephone numbers, and any infoi mation, which could Impede emer rgency response.

EPIP-RR-39 EMERGENCY PLAN IMPLEMENTING PROCEDURE

Title:

CONTROL ROOM MEDICAL RESPONDER ACTIONS FC-68 Number: EC 26708 Reason for Change: New procedure to provide guidance for Control Room Medical Responder.

Requestor: Mark Reller Preparer: Rhonda Hankins Correction (a): Page 2 (05-28-03) (Issue all pages)

ISSUED: 03-27-01 3:00 pm RO

FORT CALHOUN STATION EPIP-RR-39 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 1 OF 2 CONTROL ROOM MEDICAL RESPONDER ACTIONS NON-SAFETY RELATED

1. PURPOSE 1.1 The purpose of this procedure is to provide guidance to the Control Room Emergency Medical Responder in performing actions in response to an emergency at Fort Calhoun Station.
2. REFERENCES/COMMITMENT DOCUMENTS None
3. DEFINITIONS None
4. PREREQUISITES None
5. PROCEDURE 5.1 Review the procedure and checklist, Attachment 1, and accomplish the applicable steps both upon initial activation and periodically, as required, thereafter.

5.2 At the completion of the shift or at event termination, initial the steps which are completed.

5.3 Retain all documentation (logs, calculations sheets, notes, etc.) generated or used during the emergency. At the termination, deliver all documentation to the Administrative Logistics position in the TSC.

6. ATTACHMENTS 6.1 Control Room Medical Responder Checklist I

RO

I-FORT CALHOUN STATION EPIP-RR-39 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 2 OF 2 Attachment 6.1 - Control Room Medical Responder Checklist

(/) INIT/TIME

1. Obtain and put on Position Identification Badge. I
2. Inform the Control Room Coordinator/Shift Manager of your arrival and position.
3. Obtain a 0-500 mR and a 0-50 R dosimeter from the gear locker.

3.1 Sign in on FC-RP-214-2, Manual RCA Access.

4. Ensure your First Aid kit is ready and accessible for immediate response.
5. Obtain a radio and conduct a radio check (outside the Control Room).
6. Standby to respond as directed by Control Room Coordinator/Shift Manager.

6.1 Request information on radiological and industrial safety hazards that may exist prior to responding.

6.2 Request any assistance needed in your response from the Control Room Coordinator/Shift Manager.

7. Provide detailed briefing to oncoming shift relief of emergency conditions and status of any actions taken. I RO

WP10 Distributilon Authorized This procedureedoes not contain any proprietary ( information, or Fort Calhoun Station such Informativ on has been s issue may be Unit No. 1 censored.

released to Thi.

theepublic document room. Proprieltary information includes perso nnel names, company telep hone numbers, and any informnation, which could impede emergeency response.

EPIP-TSC-1 EMERGENCY PLAN IMPLEMENTING PROCEDURE

Title:

ACTIVATION OF THE TECHNICAL SUPPORT CENTER FC-68 Number EC 31020 Reason for Change: Delete step requiring synchronizing clocks to the ERF since we now use atomic clocks.

Requestor: Rhonda Hankins Preparer: Rhonda Hankins Correction (a): Page 2 (05-28-03) (Issue all pages)

ISSUED: 10-29-02 3:00 pm R23

FORT CALHOUN STATION EPIP-TSC-1 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 1 OF 6 ACTIVATION OF THE TECHNICAL SUPPORT CENTER NON-SAFETY RELATED

1. PURPOSE 1.1 This procedure provides a checklist to provide guidance for activation and deactivation of the Technical Support Center (TSC).
2. REFERENCES/COMMITMENT DOCUMENTS None
3. DEFINITIONS 3.1 Activated - minimum staffing and basic setup requirements have been attained to allow the TSC to provide limited support to the Control Room.

3.2 Augmented - A facility is augmented when all augmenting and minimum staffing positions are filled.

4. PREREQUISITES None
5. PROCEDURE NOTE: The Site Director or TSC Director is responsible for completion of this procedure. They may assign this task to other members of the TSC staff.

5.1 Upon reporting to the TSC, activate the TSC using Attachment 6.1.

5.2 Upon event termination, deactivate the TSC per Attachment 6.2.

6. ATTACHMENTS 6.1 Checklist for Activation of the TSC 6.2 Checklist for Deactivation of the TSC 6.3 Activation/Deactivation of the TSC Air and Area Radiation Monitors 6.4 Operation of the TSC HVAC System R23

FORT CALHOUN STATION EPIP-TSC-1 EMERGENCY PLAN IMPLEMENTING P1RGUEEDURErV'V PAGE 2 OF 6 Attachment 6.1 - Checklist For Activation of the TSC Page 1 of 2 NOTE: It is the goal of Omaha Public Power District (OPPD) to activate the TSC within one hour following declaration of an Alert or higher classification. In the event of adverse weather and/or other conditions that may limit or slow response, either manmade or natural, it is understood that staffing time may exceed this goal.

(fL INIT/TIME

1. Contact the Control Room to determine if there is a toxic gas threat in the vicinity of Fort Calhoun Station.

1.1 If YES, secure the TSC HVAC system per Attachment 6.4, Step 3.

1.2 If NO, place the TSC HVAC System in the FILTERED MODE per Attachment 6.4, Step 1. - -~~ .1.

2. Verify the following minimum staffing positions are available.

0 Site Director Protective Measures Coordinator 0 TSC COP Communicator Reactor Safety Coordinator - I

3. Ensure that the volume buttons on both Gai-tronics are turned up. I
4. Using the Gai-Tronics, announce the following message:

4.1 "Attention all personnel....Attention all personnel....This is (insert name and position) 4.2 Repeat the message above. I

5. Open all TSC room doors. I
6. Post "NO EATING/DRINKING/SMOKING OR CHEWING" signs in the TSC Room 115 and near the entrance door. I
7. In Room 118, unlock the aperture card file using the key from the key box, and turn on the aperture card reader/printer. /

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FORT CALHOUN STATION EPIP-TSC-1 EMERGENCY PLAN IMPLEMENTING1GROOEIMJ E PAGE 3 OF 6 Attachment 6.1 (continued) Page 2 of 2 INIT/TIME

8. When Steps 2 through 7 are complete, make the following announcement on the TSC PA system:

This is (insert name and position) the TSC is activated.

Command and Control for the emergency is in the name of facility at this time. No eating, drinking, smoking or chewing is allowed in the TSC until further notice. /

9. Notify the Control Room, OSC and EOF that the TSC is activated.

/

10. Verify radiological habitability per EPIP-EOF-1 1.
11. Initiate operation of the TSC Air Monitor and Area Radiation Monitor per Attachment 6.3.
12. Within one hour of the initial emergency declaration, verify the following augmenting staff are present:

0 Field Teams (2 Technicians, 2 Drivers) 0 I&C/Electrical Systems Engineer S Operations Liaison 0 Primary System Engineer

13. After one hour determine TSC positions are filled.

13.1 If any positions are not filled, based on the nature of the emergency determine if that position is required.

13.2 Request assistance from the TSC staff in contacting additional staff. I R23

FORT CALHOUN STATION EPIP-TSC-1 EMERGENCY PLAN IMPLEMENTING #i~tEES;:;RE! § PAGE 4 OF 6 Attachment 6.2 - Checklist for Deactivation of the TSC Upon termination of emergency activities, the following actions should be completed to restore the TSC:

INIT/TIME

  • Place emergency kits inthe Emergency Gear Locker.
  • Properly restore all computer systems to their standby mode.

/

  • Turn off the writeboard system. l
  • Deactivate the TSC Air Monitor and Area Radiation Monitor per Attachment 6.3.
  • Place the TSC HVAC System in the NORMAL MODE per Attachment 6.4, Step 2.
  • Remove all posted signs within the TSC.
  • Turn in all logs, paperwork, procedures, etc. to the Administrative Logistics Coordinator. , 1
  • Turn off the aperture card reader/printer, and relock the aperture card file. /
  • Restock all Emergency Kits
  • Relock all room doors.

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FORT CALHOUN STATION EPIP-TSC-1 EMERGENCY PLAN IMPLEMENTING-PROCQGED14,E PAGE 5 OF 6 Attachment 6.3 - Activation/Deactivation of the TSC Air and Area Radiation Monitors (f) INIT/TIME

1. To activate the Air and Area Radiation Monitors, perform the following:

1.1 Enter Room 109 (the ERF computer system room).

1.2 Plug in and turn on the Area Radiation Monitor as necessary.

1.3 Plug in and turn on the PING Monitor as necessary.

1.4 Allow the PING to stabilize for several minutes, clearing the initial alarms as necessary.

1.5 Check both units on a routine basis during the emergency to ensure habitability is being maintained.

1.6 If either monitor alarms at any time during startup or operation, perform the following:

1.6.1 Reset the alarm by pressing the reset/acknowledge button.

1.6.2 If alarm resounds, read the affected meter and call a Radiation Protection Technician for further instructions. /

2. To deactivate the Air and Area Radiation Monitors, perform the following:

2.1 Obtain permission from the Radiological Operations Coordinator to secure this equipment.

2.2 If permission is granted, unplug both units.

2.3 If permission is not granted, leave equipment operating and inform the Control Room.

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I FORT CALHOUN STATION lEPIP-TSC-1 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 6 OF 6 Attachment 6.4 - Operation of the TSC HVAC System Page 1 of 1 W) INIT/TIME

1. Placing the TSC HVAC in the FILTERED MODE.

1.1 On panel Al-200A (in TSC Room 109) ensure the Air Handler, VA-107 is ON as indicated by the red light above the VA-1 07, TSC Ventilation Unit Fan Start/Stop Pushbuttons. If VA-107 is not ON, start VA-1 07 with the START push button.

1.2 Ensure the VA-109, Charcoal Filter Fan Selector Switch, HCNA-109, is in AUTO.

1.3 Place the TSC Ventilation Filtered Air Mode Switch, SSNA-109 is in the ON position.

2. Placing the TSC HVAC in the NORMAL MODE.

2.1 On panel Al-200A (in TSC Room 109), place the TSC Ventilation Filtered Air Mode Switch, SSNA-109 in OFF.

2.2 Verify VA-1 09, Charcoal Filter Fan Selector Switch, HCNA-109 is in AUTO and VA-107 in ON as indicated by red light above VA-1 07, TSC Ventilation Fan Unit Start/Stop Pushbuttons. -

3. Securing the TSC HVAC System.

3.1 On panel Al-200A (in TSC Room 109), ensure or place the TSC Ventilation Filtered Air Mode Switch, SSNA-109, in the OFF position.

3.2 Place the Air Handler, VA-1 07 in OFF by pushing the VA-1 07, TSC Ventilation Unit Fan Stop pushbutton AND verify the red light above the VA-107, TSC Ventilation Unit Fan Start/Stop pushbuttons is off.

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Fort Calhoun Station Radiological Emergency Response Plan Index Page I of 2 RERP

I f-, ^ ^ C

K> Document Document Title RevisionlDate RERP Definitions and Abbreviations Ri 6 03-20-03 RERP-SECTION A Assignment of Organizational Responsibility Ri I 02-27-97c (Organizational Control)

RERP-SECTION B Organizational Control of Emergencies R25 08-24-00 RERP-SECTION C Emergency Response Support and Resources R9 09-30-98a RERP-SECTION D Emergency Classification System R10 09-17-02 RERP-SECTION E Notification Methods and Procedures R23 08-24-OOa RERP-SECTION F Emergency Communications R15 08-24-00a RERP-SECTION G Public Education and Information RI 1 08-08-02 RERP-SECTION H Emergency Facilities and Equipment R30 08-08-02 RERP-SECTION I Accident Assessment R12 03-20-03 RERP-SECTION J Protective Response R18 05-28-03 RERP-SECTION K Radiological Exposure Control RI0 04-03-03 RERP-SECTION L Medical and Public Health Support RI1 01-27-00 RERP-SECTION M Recovery and ReEntry Planning and Post Accident R14 03-11-97b Operations May 28,2003 10:11 am

WP10 Distril bution Authorized This procedlure does not contain any proprie tary information, or Fort Calhoun Station such intFom iation has been Unit No. 1 censored. rhis issue may be released to the public document room. Propirietary information includes pe rsonnel names, company te lephone numbers, and any InfEFrmation, which could impede emr ergency response.

RERP-SECTION J RADIOLOGICAL EMERGENCY RESPONSE PLAN

Title:

PROTECTIVE RESPONSE FC-68 Number: EC 32383 Reason for Change: Make changes to comply with new security card readers.

Requestor Mark Reller Preparer: Mark Reller ISSUED: 05-28-03 3:00 pm R18

FORT CALHOUN STATION RERP-SECTION J RADIOLOGICAL EMERGENCY RESPONSE PLAN PAGE 1 OF 29 RADIOLOGICAL EMERGENCY RESPONSE PLAN RERP-J PROTECTIVE RESPONSE

1. PROTECTIVE RESPONSE FOR ONSITE PERSONNEL 1.1 Notification Onsite personnel are notified of a nuclear emergency via the emergency alarm. This alarm is identified by an intermittent howl and is distinguished from the fire alarm which is a continuous howl. Once the emergency alarm is sounded, the command and control position will give the emergency classification, with other pertinent information, using the intra-plant communication system (Gaitronics). If the owner-controlled area is to be evacuated, personnel will be notified by: 1) Gaitronics System, 2) Administration and Training Building paging systems, 3) Security Personnel, and/or 4) Alert Notification System, if used.

1.2 Evacuation If the emergency requires Protected Area evacuation, personnel not assigned specific emergency duties will normally proceed to the Administration Building. In the event the site must be evacuated, all non-essential personnel, will be given instructions by the command and control position. One of the two routes shown in Figures J-1 and J-2 will be used to proceed to the North Omaha Power Station.

Approximately 600 persons might be evacuated during normal work hours and operation; approximately 900 persons might be evacuated during a major outage.

During normal operating off-shift hours, no evacuation of onsite individuals is expected. Both OPPD and personal vehicles are used for site evacuation transportation. Agreements with the State of Nebraska and specifically the State Patrol guarantee professional handling and control of traffic. Normal travel time to North Omaha Station is 25 minutes at an average speed of 40 mph. RP personnel reporting to the EOF will coordinate personnel/vehicle monitoring and decontamination activities, if required.

Security and RP personnel inspect the owner controlled area after a site evacuation has taken place. If any persons other than emergency workers are in the owner controlled area during or after site evacuation, they will be given specific directions and/or escorted off-site.

R18

FORT CALHOUN STATION RERP-SECTION J RADIOLOGICAL EMERGENCY RESPOI4S9E'PIaN"- -'""'- PAGE 2'0F 29 1.3 Security and Accountability 1.3.1 Security The security program is designed to deter, delay and detect an intruder. The Security Area of the plant site is enclosed by an eight foot security fence topped by three strands of barbed wire. All gates to the fence are normally kept locked. An inner perimeter consists of personnel doors, roof hatches, and overhead doors equipped with magnetic alarm switches.

Personnel assigned by the Site Director to enter the plant must pass through the main gate which is guarded. It is extremely unlikely that any unauthorized person would be able to enter the site undetected even during an emergency condition.

1.3.2 Accountability If accountability of.onsitoe personnel is necessary, the onsite command and control position will notify personnel onsite by announcements on the Gaitronics System, and by sounding the Emergency Alarm (if required). At the completion of the notification(s), the accountability process begins, to be completed within 30 minutes.

Accountability is a process taking place in several areas:

A. Accountability of personnel reporting to the Control Room, TSC, or OSC for emergency response will be performed by personnel using the card readers at these locations.

B. Accountability of security force personnel will be accomplished using established security procedures.

C. Once initial accountability is complete, the command and control position, will be notified of the results.

D. Accountability is maintained by the use of rosters at the Control Room, OSC and TSC. Persons must sign in and out as they enter and leave.

These rosters will be compared to a list of personnel who accessed the protected area whenever necessary. Continuous accountability of security personnel is accomplished using established security procedures.

R18

FORT CALHOUN STATION RERP-SECTION J RADIOLOGICAL EMERGENCY RESPONSE'PLI-ANi- PAGE 3 OF 29 1.4 Protective Measures 1.4.1 It is the policy of OPPD to keep personnel radiation exposure within federal regulations, and station limits and guidelines, beyond that, to keep it As Low As Reasonably Achievable (ALARA). Every effort will be made to keep their exposures within the limits of 10 CFR 20.

1.4.2 Personnel monitoring devices are required for all personnel meeting the conditions specified in 10 CFR 20 Section 20.1502, Technical Specifications Section 5.11 and in Radiation Protection Procedures. During emergency conditions, implementing procedure EPIP-EOF-1 1 will be utilized.

Dosimeters and TLD's are typically located in each of the emergency lockers in the Control Room, EOF, OSC and the TSC. Additional dosimeters and TLD's may be obtained from the dosimetry group.

1.4.3 Clothing Protective clothing is a normal use item utilizing both washable and disposables. For entry into affected areas, the OSC has approximately 50 complete sets of protective clothing available. The Control Room has approximately 12 complete sets available. Additional sets are available at the Radiation Control Point. Approximately 2000 sets are maintained in the laundering cycle, and a large supply of washable and disposable coveralls is maintained in the warehouse and RP storage areas. Water-proof protective clothing is also a standard stock item.

R18

FORT CALHOUN STATION RERP-SECTION J RADIOLOGICAL EMERGENCY RESPOM PAGE 4OF 29 1.4.4 Respiratory Protection Respiratory protective devices may be required in any situation arising from plant operations where an airborne radioactivity condition is potential or existent. In such cases, the air will be monitored and the necessary protective devices specified according to the concentration and type of airborne contaminants present. Monitoring and issue of respiratory protection equipment will be conducted in accordance with Radiation Protection Manual Procedures. Precautions will be taken to keep airborne contamination to a minimum through the use of proper engineering controls and decontamination.

Limits for inhalation of radionuclides are established in Appendix B, Table 1 of 10CFR20. The Radiation Protection Manual establishes the station's administrative limits for inhalation which will be adhered to in emergencies if possible.

Types and recommended use for each type of respirator is specified in the Radiation Protection Manual.

Approximately 35 self contained breathing apparatus are maintained onsite.

Of these, a portiorn are maintained for fire brigade use, or normal use, and the remainder for emergency response . Spare bottles are also stored in some locations. The site has the capability to refill bottles with a compressor/air bank unit, with a cascade tank unit as a backup. Full-face

-- respirators are maintainedin some emergency gear lockers. Respirators are staged for use in plant radiation areas. The onsite Stores warehouse stocks approximately 150 full-face respirators for reserve supply.

1.4.5 Radioprotective Drugs The need for issuance of radioprotective drugs, specifically potassium-iodide, is determined using appropriate procedures.

Radioprotective drugs in the form of potassium iodide tablets are available in the Control Room, Technical Support Center, Operations Support Center, Emergency Operations Facility and the Field Team equipment lockers. Each bottle contains dosage supply for 14 days. Emergency workers are instructed on the advantages and disadvantages of taking the tablets to provide thyroid blockage. The final decision for use of the potassium iodide is made by the emergency worker.

R18

FORT CALHOUN STATION RERP-SECTION J RADIOLOGICAL EMERGENCY RESPON8Ei%-WL 1 PAGE 5 OF 29

2. PROTECTIVE RESPONSE FOR RESIDENTS WITHIN THE PLUME EXPOSURE PATHWAY 2.1 Protective Action Recommendations 2.1.1 OPPD Guidelines Fort Calhoun Station is designed and equipped with a series of safety systems engineered to meet all of 10 CFR 100 criteria for reactor safety.

OPPD recognizes that in any accident situation, it would be prudent and logical to make every effort to further reduce and minimize exposure to the public. OPPD management will recommend to appropriate State and local authorities that protective actions be initiated if any person is expected to receive an emergency exposure in excess of Environmental Protection Agency (EPA) guidelines.

Tables J-11 through J-4' provide some information and guidance on formulating Protective Action Recommendations (PAR's). Table J-1' summarizes the considerations for selecting the evacuation Protective Action Guides (PAG's). Table J-21 outlines the early (plume) phase PAG's due to exposure of airborne .and deposited radioactivity. Table J-3' summarizes the considerations for selecting relocation PAG's. Table J-41 outlines the immediate (relocation) phase PAG's due to exposure to deposited radioactivity.:

During the early (plume) phase of a radiological emergency, professional judgement will be required in the application of PAG's, due to varying characteristics, such as; plant conditions, evacuation time estimates, environmental conditions, affected population groups, etc. In all cases, the PAR's transmitted by OPPD to the states of Iowa and/or Nebraska are strictly recommendations. The respective government agencies in each state have the ultimate responsibility for implementing necessary protective actions for the general public.

Tables J-5 and J-6 provide information pertaining to emergency worker exposure limits and health risks associated with exposure to higher dose levels.

Taken from Manual of Protective Action Guides and Protective Actions for Nuclear Incidents. EPA-400-R-92-001, Revised May, 1992.

R18

FORT CALHOUN STATION RERP-SECTION J RADIOLOGICAL EMERGENCY RESPO['8 PLU.44r PAGE 6 OF 29 2.1.2 Initiation of Recommendations Recommendations will originate from an Emergency Response Facility based upon data derived from implementing procedure, EPIP-EOF-6. This procedure establishes a method for determining projected doses to the population-at-risk. Protective action recommendations based on radiological parameters or plant conditions are determined using EPIP-EOF-7. Total population exposure can be estimated using projected or known dose values and population densities.

2.2 Notification In the event public notification is required, both transient and resident population within the plume exposure pathway will be initially notified through the Alert Notification System (reference Section E) and as described in state and county radiological emergency plans. Information will be provided for transient and resident population as well as the general public outside the EPZ through the Emergency Alert System. Radio station KFAB-AM (1110 KHz) is the Local Primary One (LP1) information station for local emergencies.

Information brochures describing notification, protective actions and general radiological education are provided to residents by mail and by public service posting to transients within the EPZ. The States of Iowa and Nebraska will issue messages describing the incident and recommended public protective actions.

2.3 Evacuation 2.3.1 Evacuation Time Estimate Study Studies estimating the time required to evacuate the residents in the plume exposure pathway from the emergency planning zone were conducted in accordance with NUREG-0654, Rev. 1, Appendix 4 criteria. These studies are supporting documents to this Plan. Summaries of the Nebraska and Iowa evacuation time estimate studies are outlined in Figures J-3 and J-4, and Tables J-9 and J-1 0.

During normal weather conditions the maximum time to evacuate the approximately 4,365 residents of Iowa and the 13,138 Nebraska residents of the EPZ, is estimated at 170 minutes. In adverse conditions these times would increase to 175 minutes for Iowa and 185 Minutes for Nebraska.

R18

FORT CALHOUN STATION RERP-SECTION J RADIOLOGICAL EMERGENCY RESPONSE PL-AN, PAGE 7 OF 29 2.3.2 Evacuation of Areas within the EPZ The Governor (or Governor's Authorized Representative) of Nebraska can authorize the Nebraska State Patrol and Emergency Management Agency, based on recommendations of the State Health Department, to evacuate Nebraska residents to reception centers in Fremont and Bellevue, Nebraska.

The Governor (or Govemor's Authorized Representative) of Iowa can authorize the Iowa State Patrol and the Emergency Management Division to evacuate Iowa residents to Denison, Iowa, based upon recommendations of the Iowa Department of Public Health.

Normal evacuation routes within the EPZ are, on the Nebraska side of the river, people in Sub Area 1, Blair, North of Blair and North of U.S. Highway 30 (Sub Area 2) should go to the Fremont Reception Center. People south of Blair between the Missouri River and U.S. Highway 30 (Sub Areas 3, 4 and 5) should go to the Bellevue Reception Center. People in the Iowa portion of the EPZ should proceed to the Denison Reception Center. If alternate evacuation is necessary, directions will be given through the designated local primary one (LP1) Emergency Alert System radio station.

Figure J-5 shows the boundaries and highways leading to the Reception Centers.

The relocation centers for the host areas are as follows:

A. Bellevue First Baptist Church Activities Building Hancock Street and 23rd Avenue B. Fremont Fremont Senior High School 1750 N. Lincoln C. Denison Denison Community High School, North 16th R18

I I FORT CALHOUN STATION RERP-SECTION J RADIOLOGICAL EMERGENCY RESPON(tLW(-'m--' PAGE 8 OF 29 2.3.2 The ingestion planning zone (IPZY 'encompasses a 50 mile radius as illustrated in Figure J-6. Population for the IPZ is presented in Figure J-7 by.

sectors.

The plume exposure EPZ encompasses an approximate 10 mile radius as illustrated in Figure J-5. The EPZ includes portions of Harrison and Pottawattamie Counties in Iowa, Washington and Douglas Counties in Nebraska. The States of Iowa and Nebraska are separated by the Missouri River. Figure J-8 shows the total population within the EPZ, and population totals for each sector by ring miles (0-2, 2-5 and 5-10 miles) and total miles (0-2, 0-5 and 0-10 miles). Figure J-4 shows Sub Area population, including Estimated Transient population.

2.4 Protective Methods (Other than Evacuation) 2.4.1 Sheltering Remaining indoors during the passage of a radioactive cloud affords the dweller a reduction in the quantity of radionuclides inhaled, as well as providing shielding. Figure J-91 shows the ratio of the inhaled dose inside a shelter to that outside the shelter as a function of the ventilation rate. A ventilation rate survey showed a rate variance of 0.07 to 3.0 per hour. The ventilation rate is affected.by temperature-differentiali wind speed and direction, quality of construction and topographical setting.

Walls of buildings absorb and scatter gamma rays, thus providing a lower dose to the occupants. The shielding factor of a building is the ratio of the interior dose to the exterior dose. Shielding factor estimates applicable to residential housing units were made using the shielding technology by Z. G. Burson and A. E. Proflio (1975). Table J-72 summarizes shielding factors for designated structures/locations from a gamma cloud source.

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FORT CALHOUN STATION RERP-SECTION J RADIOLOGICAL EMERGENCY RESPONSEiPL-M. - PAGE 9 OF 29 1,2.3 2.4.1 Table J-83 summarizes the shielding factors for designated structures/locations from surface deposition of radioactive material. Burson and Profio proved that the fallout shielding technology developed via nuclear weapons tests could be directly applied to radioactivity deposited on surfaces after a reactor accident. The shielding factors listed in Table J-8 assumes uniform distribution of the radioactive fallout.

In each of the cases discussed, inhalation and shielding factors from a gamma cloud source and shielding factors from surface deposition of radioactive material, it is noted that the shielding factors using sheltering as a method of protection ranges from 0.6 to 0.005. Although the best protection seems to be the basement of large multi-structured buildings, the basement of any house has been proven to provide significant shelter from airborne and surface deposited radioactive material.

2.5 Radiological Environmental Monitoring In the event of an emergency, the permanent air particulate stations are first utilized for immediate data, concerning airborne releases. Background radiation stations (TLD's) provide short term, exposure data and are periodically replaced. See the specific Radiological Environmental Monitoring Surveillance Test for more information. TLD use can be increased during the longer term as the District maintains a TLD services contract with a off-site vendor. The environmental laboratory personnel perform accelerated collection and analysis of samples as their primary responsibility after an emergency occurs. Sampling requirements will be determined by the environmental laboratory personnel.

Sample analysis will be performed by the station and at offsite facilities as deemed necessary.

' Taken from WASH-1400(NUREG-75/014), October 1975, Figure VI.11-4.

2 Taken from WASH-1400(NUREG-75/014), October 1975, Figure VI-11-7.

3 Taken from WASH-1400(NUREG-75/014), October 1975, Figure. VI-11-8.

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FORT CALHOUN STATION RERP-SECTION J RADIOLOGICAL EMERGENCY RESPOJ'88EPEAtil' '- PAGE 10 OF 29 Table J Summary of Considerations for Selecting the Evacuation PAG's' DOSE Rem Consideration(s)

(mrem) 50 Rem Assumed threshold for acute health effects in adults.

(50000 mrem) 10 Rem Assumed threshold for acute health effects in the fetus.

(10000 mrem) 5 Rem ..Maximum acceptable dose for normal occupational exposure for (5000 mrem) adults.

5 Rem Maximum dose justified to average members of the population, (5000 mrem) based on the cost of evacuation.

0.5 Rem Maximum acceptable dose to the general population from all (500 mrem) sources from nonrecurring, non-accidental exposure.

0.5 Rem Minimum dose justified to average members of the population, (500 mrem) based on the cost of evacuation.

0.5 Rem Maximum acceptable dose2 to the to the fetus from occupational (500 mrem) exposure of the mother.

0.1 Rem Maximum acceptable dose to the general population from all (100 mrem) - sources from routine (chronic) non-accidental exposure.

0.03 Rem Dose that carries a risk assumed to be equal to or less than that (30 mrem) from evacuation.

1 Taken, in part, from Table C-8, *Manual of Protective Action Guides and Protective Actions for Nuclear Incidents," EPA-400-R-92-001, May, 1992.

2 This is also the dose to the 8- to 15-week-old fetus at which the risk of mental retardation is assumed to be equal to the risk of fatal cancer to adults from a dose of 5 rem.

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FORT CALHOUN STATION RERP-SECTION J RADIOLOGICAL EMERGENCY RESPONSE PLANP PAGE 11 OF 29 Table J Protective Action Recommendations Based on Dose Assessment/Field Team Radiological Data Early Phase (Plume Phase):

Projected Dose Protective Action Recommendation (PAR)

<1 rem TEDE None (NO PAR REQUIRED)

<5 rem CDE (thyroid) and continue to monitor radiological conditions

>1 rem TEDE Evacuate

Ž5 rem CDE (thyroid) Shelter, if it will provide protection equal to or greater than evacuation up to 10 rem (NOTE)

Ž50 rem SDE (skin) Evacuate NOTE: Sheltering may be preferable to evacuation as a protective action in some situations.

Because of the higher risk associated with evacuation of some special groups in the population (e.g. those who are not readily mobile), sheltering may be the preferred alternative for such groups as a protective action at projected doses up to 5 rem TEDE. In addition, under -

unusually hazardous environmental conditions, use of sheltering up to 5 rem TEDE to the general population (and up to 10 rem to special groups) may be justified.

For example, situations when evacuation may not be appropriate at 1 rem TEDE include:

(1) the presence of severe weather; (2) competing disasters; (3) institutionalized people who are not readily mobile; and (4) local physical factors which impede evacuation.

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FORT CALHOUN STATION RERP-SECTION J RADIOLOGICAL EMERGENCY RESP0I 13P & - PAGE 12 OF 29 Table J Summary of Considerations for Selecting PAG's for Relocation' DOSE Rem (mrem) Consideration(s) 50 Rem Assumed threshold for acute health effects in adults.

(50000 mrem) 10 Rem Assumed threshold for acute health effects in the fetus.

(10000 mrem) 6 Rem Maximum projected dose in first year to meet 0.5 Rem in the second (6000 mrem) year2.

5 Rem Maximum acceptable dose for normal occupational exposure for adults.

(5000 mrem) 5 Rem Minimum dose that must be avoided by one year relocation based on (5000 mrem) cost. _ -

3 Rem Minimum projected first-year dose corresponding to 5 Rem in 50 years2 .

(3000 mrem) 3 Rem Minimum projected first-year dose corresponding to 0.5 Rem in the (3000 mrem) second year2.

2 Rem Maximum dose in first year corresponding to 5 Rem in 50 years from a 4X200rnrem)- -reactor -incidentbased on radioactive decay and weathering only.

1.25 Rem Minimum dose in first year corresponding to 5 Rem in 50 years from a

-- (1250 mrem) reactor incident, based on' radioactive decay and weathering only.

0.5 Rem Maximum acceptable single-year dose to the general population from all (500 mrem) sources from non-recurring, non-incident exposure.

0.5 Rem Maximum acceptable dose to the fetus from occupational exposure of the (500 mrem) mother.

0.1 Rem Maximum acceptable annual dose to the general population from all (100 mrem) sources due to routine (chronic), non-incident, exposure.

0.03 Rem Dose that carries a risk assumed to be equal to or less than that from (30 mrem) relocation.

.a _nin pat .. o I abl. M anuai. . , roteci S-b ....... _ ... _ . ......... ....

Nuclaren, in pant, fromEabl -5, 'Manual of Protey9 yive Action Guides and Protective Actions for Nuclear Incidents," EPA-400-R-92-001, May, 1992.

2 Assumes the source term is from a reactor incident and that simple dose reduction methods are applied during the first month after the incident to reduce the dose to persons not relocated from contaminated areas.

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FORT CALHOUN STATION RERP-SECTION J RADIOLOGICAL EMERGENCY RESPON8EaPlaW-4 PAGE 13 OF 29 T-able J4 - Protective Action Guides for Exposure to Deposited Radioactivity' PAG Protective Action (projected dose Comments in first year)2 Relocate the general 2 2 Rem Beta dose to skin may be up to 50 times population. 3 (2 2000 mrem) higher.

Apply simple dose < 2 Rem These protective actions should be taken reduction techniques.4 (<2000 mrem) to reduce doses to as low as practicable levels.

' Taken, in part, from the WManual of Protective Action Guides and Protective Actions for Nuclear Incidents," EPA-400-R-92-001, May, 1992.

2 The projected sum of total effective dose equivalent (TEDE) from external gamma radiation and committed effective dose equivalent (CEDE) from inhalation of resuspended materials, from exposure or intake during the first year. Projected dose refers to the dose that would be received in the absence of shielding from structures or the application of dose reduction techniques. These PAG's may not provide adequate protection from some long-lived radionuclides.

3 Persons previously evacuated from areas outside the relocation zone defined by this PAG may return to occupy their residences. Cases involving relocation of persons at high risk from such action (e.g., patients under intensive care) should be evaluated individually.

4 Simple dose reduction techniques include scrubbing and/or flushing hard surfaces, soaking or plowing soil, minor removal of soil from spots where radioactive materials have concentrated, and spending more time than usual indoors or in other-low exposure rate areas.

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FORT CALHOUN STATION RERP-SECTION J RADIOLOGICAL EMERGENCY RESPOWITSPIEI -` PAGE 14 OF 29 Table J Emergency Worker Exposure Limits DOSE LIMIT ACTIVITY CONDITION(S)

  • 500 mrem All Activities Declared Pregnant Emergency Workers TEDE
  • 5 Rem TEDE All Activities Non-Pregnant Emergency Workers
  • 10 Rem TEDE Protecting Valuable Property A lower dose is not practicable
  • 25 Rem TEDE Life Saving or Protection of A lower dose is not practicable Large Populations

>25 Rem TEDE Life Saving or Protection of Only on a voluntary basis to persons Large Populations fully aware of the risks involved. (See Table J-6)

NOTE: Fort Calhoun Station has established separate administrative limits for use during normal operating conditions. These limits are outlined in various Radiation Protection procedures and policies.

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FORT CALHOUN STATION RERP-SECTION J RADIOLOGICAL EMERGENCY RESPONSE;,PLAN - PAGE 15 OF 29 Table J Summary of Risks Involved with Higher Dose Limits (taken form EPA 400_R-92-001, May, 1992)

Health Effects Associated with Whole-Body Absorbed Dosed Received Within a Few Hoursa Whole Body Early Whole Body Prodromal Absorbed Dose Fatalitiesb Absorbed Dose Effectsc (rad) (percent) (rad) (percent affected) 140 5 50 2 200 15 100 .15 300 50 150 50 400 -85 200 ---. 85 460 95 250 98 a Risks will be lower for protracted exposure periods.

b Supportive medical treatment may increase the dose at which these frequencies occur by approximately 50 percent.

c Forewarning symptoms of more serious health effects associated with large doses of radiation.

Approximate Cancer Risk to Average Individuals from 25 Rem Effective Dose Equivalent Delivered Promptly Age at Exposure Approximate Risk of Average Years of Life (years) Premature Death Lost in Premature Death (deaths per 1,000 Occurs (years) persons exposed) 20 to 30 9.1 24 30 to 40 7.2 19 40 to 50 5.3 15 50 to 60 3.5 11 R18

FORT CALHOUN STATION RERP-SECTION J RADIOLOGICAL EMERGENCY RESP% 9 p:tJPIW9? PAGE 16 OF 29 Table J Representative Shielding Factors from Gamma Cloud Source

', Ij 1"

Structure or Location Shielding Factor(a) Representative Range Outside 1.0 Vehicles 1.0 Wood - frame ( (no basement) 0.9 Basement of wood house 0.6 0.1 to 0.7 (c)

Masonry house (no basement) 0.6 0.4 to 0.7 (c)

Basement of masonry house 0.4 0.1 to 0.5 (c)

Large office or industrial building 0.2 0.1 to 0.3 (c)

(a) The ratio of the interior dose to the exterior dose.

(b) A wood frame house with brick or stone veneer is approximately equivalent to a masonry house for shielding purposes.

--- (Th-1s-ra-n-ge Is mainly due-to ifferent walt materials and different geometries.

{) The reduction factor depends on where the personnel are located within the building (e.g., the basement or an inside room).

NOTE: Consideration is limited to gamma radiation since beta and alpha particles cannot penetrate the walls of structures.

  • Taken from WASH-1400 (NUREG-75/104), October 1975.

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FORT CALHOUN STATION RERP-SECTION J RADIOLOGICAL EMERGENCY RESPONSE'PLAN, PAGE 170F29 Table J Representative Shielding Factors for Surface Deposition Structure or Location Representative (a)Shielding Representative Range Factor 1 m above an infinite smooth surface 1.00 1 m above ordinary ground 0.70 0.47 - 0.85 1 m above center of 50-ft roadways, 0.55 0.4 - 0.6 half contaminated Cars on 50-ft road:

Road fully contaminated 0.5 0.4 - 0.7 Road 50% decontaminated 0.5 0.4 - 0.6 Road fully decontaminated 0.25 0.2 - 0.5 Trains 0.40 0.3 - 0.5 One and two-story wood-frame house (no basement) 0.4 (b) 0.2 - 0.5 One and two-story block and brick house (no basement) 0.2 (b) 0.04 - 0.40 House basement, one or two walls fully exposed: 0.1 (b)0.03 - 0.15 One story, less than 2 ft of basement, walls exposed 0.3 (b) 0.03 - 0.07 Two stories, less than 2 ft of basement, walls exposed 0.3 (b).02 - 0.05 Three or four-story structures, 5,000 to 10,000 ft2 per floor:

First and second floor 0.05 (b) 0.01 - 0.08 Basement 0.01 (b) 0.001 - 0.07 Multistory structures, >10,000 ft2 per floor Upper floors 0.01 (b) 0.001 - 0.02 Basement 0.005 (b) 0.001 - 0.015 a The ratio of the interior dose to the exterior dose.

(b) Away from doors and windows.

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FORT LHOUN STATION RERP-S FfION J RADIOLOGICAL EMERGENCY RESPONSE PLAN PAGE 18 OF 29 Table J-9 STATE OF NEBRASKA EVACUATION TIME ANALYSIS Approximate distance from FCS, in miles 0-2 2-1 0 2-9 2-9 9-1 0 Permanent population  : 488 8972 2064 2767 353 Pemnanent population vehicles 197

.~~~~~~~~~~~~~~~f 3589 826 .~ 1107 142 Transient population 1110 1873 0 1678 0 Transient population vehicles :1110 1736 0 678 0 Persons without vehicles ^ 0 3105 0 610 0 Special vehicles 0 78 0 16 0 Notification Time 00:15 00:15 00:15 00:15 00:15

.Preparation time, permanent population 01:35 01:35 01:35 01:35 01 :35 Preparation time, transient population 00:45 00:45 00:45 00:45 00:45 Preparation time, special population ^ NA 2:00 NA 2:00 2:00 Evacuation time permanent population, normal conditions 2:40 2:55 2:55 2:50 2:40 permanent population, adverse conditions:2 Evacuation time, 3:55 0 3:55 3:20 2:40 Evacuation tm transient e, population, normal conditions:40 2:55 2:55 2:50 2:40 Evacuation time, transient population, adverse conditions 3:20 3:55 3:55 3:20 2:40 Evacuation time, special population, novmal conditions NA 2:55 2:55 2:50 NA Evacuation time, special population, adverse conditions NA 3:55 3:55 3:20 NA Conficmation Time

^ includes schools, nursing homes and transportation dependent R18

( (

RERP-SEC rON J FORT CALHOUN STATION RADIOLOGICAL EMERGENCY RESPONSE PLAN PAGE 19 OF 29 Table J-10 STATE OF IOWA EVACUATION TIME ANALYSIS

d. S AREAI; 0SUBAREAl I2 SUBAREA :SUbAREA:13 SUBA3E_14 Approximate distance from FCS, in miles 0-2 2-9 8-11 2-11 Permanent population 29 162 423 3023 142 Permanent population vehicles 12 65 170 1210 57 Transient population 5000 0 0 536 500 Transient population vehicles 1667 0 0 361 167 Persons without vehicles *0 0 0 1062 0 Special vehicles 0 0 0 29 0 Notification time 00:15 00:15 00:15 00:15 00:15 Preparation time, permanent population 02:30 02:30 02:30 02:30 02:30 Preparation time, transient population 00:60 00:60 00:60 00:60 00:60 Preparation time, special population
  • NA NA NA 2:15 NA Evacuation time, permanent population, normal 2:35 2:35 2:55 2:45 2:45 conditions Evacuation time, permanent population, adverse 2:40 2:40 3:05 2:50 2:50 conditions Evacuation time, transient population, normal conditions 2:35 NA 2:55 2:45 2:45 Evacuation time, transient population, adverse 2:40 NA NA 2:50 2:50 conditions Evacuation time, special population, normal conditions NA NA NA 2:50 NA Evacuation time, special population, adverse conditions NA NA NA 2:55 NA Confirmation time_
  • includes schools, nursing homes and transportation dependent R18

FORT CALHOUN STATION RERP-SECTION J RADIOLOGICAL EMERGENCY RESPO'IPLAVV^\`: PAGE'20 OF 29 Figure J Normal Evacuation Routes I'- ,; - = I-: P.

I -- 1~ I R18

FORT CALHOUN STATION RERP-SECTION J RADIOLOGICAL EMERGENCY RESPONSE PL1~*: PAGE 21 OF 29 Figure J Alternate Evacuation Route R18

FORT CALHOUN STATION RERP-SECTION J RADIOLOGICAL EMERGENCY RESPONSE .L1i . PAGE 22 OF 29 Figure J Evacuation Time Estimate Study Sub-area Designations I

I I

I I

I I

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FORT CALHOUN STATION RERP-SECTION J RADIOLOGICAL EMERGENCY RESPONSE PLAN PAGE 23 OF 29 Figure J Plume Exposure EPZ Population and Evacuation Times I

1N Nebraska Iowa Sub;; Population Evacuati Tmg:' EvtataE--abii;t'Tme Area.Ae MainmumiMaximum Norm AdeMn. mom Adv:fxerse...,

1 488 1598 2:40 3:10 10 29 5044 2:35 2:40 2 8972 13950 2:55 3:55 11 162 162 2:35 2:40 3 2064 2064 2:55 3:55 12 423 423 2:55 3:05 4 2767 3705 2:50 3:10 13 3023 4784 2:45 2:50 5 353 353 2:40 2:40 14 142 642 2:50 2:50 Total 14644 21670 2:50 3:10 Total 3779 11055 2:55 3:05 R18

FORT CALHOUN STATION RERP-SECTION J RADIOLOGICAL EMERGENCY RESPONt -t" o- PAGE 4 -OF29 Figure J Routesi to Relocation Centers R18

FORT CALHOUN STATION RERP-SECTION J RADIOLOGICAL EMERGENCY RESPONSE KANt PAGE 25 OF 29 Figure J Ingestion Pathway EPZ R18

FORT CALHOUN STATION RERP-SECTION J RADIOLOGICAL EMERGENCY RESPONS'EPLANk. PAGE 26 OF 29 Figure J Population Estimates Ingestion Pathway SPZ .

POPULATION DISTRIBUTION AS OF 1990 _II .

DISTANCE FROM FCS IN MILES OF SECTOR SEGMENT SECTOR OTOTO 1-S020 2 i T TTALS A 49 710 948 3720 1871 7298 B 393 499 1067 1578 3351 6888 C 114 703 2299 2369 1151 6636 D 2077 5092 1009 1903 7748 17829 E 102 696 2820 2615 2319 8552 F 120 893 1795 3699 2307 8814 G 879 5432 12296 3151 3012 24730 H 1961 107123 151221 13637 3801 277743 J 807 163724 82464 6740 4745 258480 K 1405 18269 23318 4452 6335 53779 L 420 2996 4534 5111 3176 16237 M 881 2263 22334 1672 1984 29134 N 516 1184 4030 2731 1693 10154 P

0 6361 1273 1085 1271 2060 740 5494 3437 2838 2492 17838 9213 1~

R 146 1085 2364 1356 3087 8038 TOTALS 17504 313025 315299 63665 51910 761403 CUMULATIVE 17504 330529 645828 709493 761403 761403 l R18

FORT CALHOUN STATION RERP-SECTION J RADIOLOGICAL EMERGENCY RESPON$.PPLAV.A,. PAGE 27 OF 29 Figure J Population Estimates Plume Exposures EPZ A

/ S I/x' IC1 LJ 2 ,'

I

  • / S~~~~~~~~~~24 32_

.4 9 -,~~~4 V ,a Population Totals Ring Miles Ring Population Total Miles Cumulative Population 0-2 267 0-2 267 2-5 9034 0-5 9301 5-10 9095 0-10 18396 R18

FORT CALHOUN STATION RERP-SECTION J RADIOLOGICAL EMERGENCY RESPON8E41tAbf*' W. PAGE 28 OF 29 Figure J Ratio of Inhaled Dose Insidb a Shelter to That Outside the Shelter as a Function of Ventilation Rates d ~ . . . . . ... . . . . . . . . . . . . . ... . . . . . . . .. .

U K: -------------- --------- - --------------- ..................

01 ........................

v 7 . .. . . ... . .. .. . . . .... . . . . .. .

G -) ................ ... .................. ...

3- .......... ---------- ... ...................... .....

Iti5 ---- -------- --------- -------- ---------

3.-

I-)4 ------------ -----------

U.-, ......... ..... --------------------------

u.2 ..............................................

tU .......... ............. 7 -----------------------------

A, U1 I - ,- ~4 5 1, I1 I ,J Exposure Time irsi I.E.

,F---- . L w - --

I - '

R18

FORT CALHOUN STATION RERP-SECTION J RADIOLOGICAL EMERGENCY RESPONEPLKAW PAGE 29 OF 29 Figure J Notification/Preparation/Mobilization Time Distributions r-V-

a In In 0

V.

E w

C 4-1 In 0 1 0.

,in 0

40 0 0 0 a M co co ItC 04 V.

swnavA3 el fiCulufiagO uojl!jndod lo % sAflUjnutn3 R18

Fort Calhoun Station Emergency Planning Forms Index Page 2 of 3 FC-EPF Document Document Title Revision/Date FC-EPF-15 Drill Exercise Comment Form R3 07-11-97a FC-EPF-17 Pager Response Follow Up Questionnaire R3 11-06-99 FC-EPF-19 Process and Area Monitor Locations R7 04-22-03 FC-EPF-20 Site Boundary/Owner Control Area R2 06-03-03 FC-EPF-21 Fort Calhoun Station Sector Map R2 05-15-97 FC-EPF-27 Onsite/Offsite Dose Comparison Data Record (Using Eagle Program) R3 11-07-00 FC-EPF-29 Estimation of Unmonitored Release Rates RI 12-30-93 FC-EPF-31 AT10O Stability Class Chart R2 03-14-02 FC-EPF-32 Area Monitor Trending RO 06-10-93 FC-EPF-33* Emergency Response Facility Computer System (ERFCS) RI 07-02-96 FC-EPF- ERFCS Function Key Mapping RO 10-08-02 33A FC-EPF-34 MRC Director Checklist RO 06-23-93 FC-EPF-35 Iowa EOC Route Map (double-sided) RO 06-21-94 FC-EPF-36 Briefing Guidelines R3 10-22-01 June 3,2003 8:06 am

Distribution Authorized This procedure does not contain any proprietary information, or such information has been censored. This issue may be released to the public document room. Proprietary information includes personnel names, company telephone numbers, and any information, which could impede emergency response.

ol - -- - -

FORT CALHOUN STATION FC-EPF-20 EMERGENCY PLAN FORM R2 SITE BOUNDARY/OWNER CONTROL AREA 281 . 750 258. 101. 250 o be 1 l l Il SCALE IN MILES SITE BOUNDARY/OWNER CONTROL AREA