WO 02-0048, Changes to Radiological Emergency Response Plan Implementing Procedure & Forms

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Changes to Radiological Emergency Response Plan Implementing Procedure & Forms
ML022750332
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 09/20/2002
From: Mckinney B
Wolf Creek
To:
Document Control Desk, Office of Nuclear Security and Incident Response
References
WO 02-0048
Download: ML022750332 (36)
v • d • e


Text

-WLF CREEK 'NUCLEAR OPERATING CORPORATION Britt T. McKinney Vice President Operations SEP20 2002 WO 02-0048 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington,- D. C. 20555

Subject:

Docket No. 50-482: Changes to Wolf Creek Generating Station (WCGS) Radiological Emergency Response Plan Implementing Procedure and Forms Gentlemen:

In accordance with 10 CFR 50, Appendix E, enclosed are revisions to a Wolf Creek

-Generating -Station (WCGS) Radiological Emergency- Response Plan implementing procedure and forms. The following is a list of the specific enclosures.

PROCEDURE--

"EffectiveAugust 26, 2002 EPP 06-012, Revision 5 (Corrected -copy)

FORMS Effective August 26, 2002 Effective Septemb&r 5, 2002 EPF 06-004-01, Revision 7 EPF 06-018-03, Revision 1 EPF 06-018-15, Revision 3 If you have -any questions concerning this submittal, -please contact me at (620) 364-4112, or Mr. K. A. (Tony) Harris at (620) 364-4038.

-Very truly yours, Britt T. McKinney -" 7J BTM/rlr Enclosures cc: J.-N. Donohew (NRC), w/e G.M. Good (NRC), w/e D. N. Graves (NRC), wo/e E.- W. Merschoff (NRC), w/e (2)

Senior Resident Inspector (NRC), wo/e RO Box 41-1 / Burlington, KS 66839/ Phone: (620) 364-8831 "An-Equal Opportunity Employer M/F/HCNET .

CORRECTED COPY 08/26/02 I-'

-p t.1 C)

C)

N C) NUCEAROPERATING CORPORATION t) a-EPP 06-012 DOSE ASSESSMENT Responsible Manager Manager Resource Protection Revision Number 5 Use Category Reference Administrative Controls Procedure No Infrequently Performed Procedure No Program Number 06 DC2 10/26/2001

Revision: 5 DOSE ASSESSMENT EPP 06-012 Reference Use Page 1 of 18 TA1BLE OF CONTENTS SECTION TITLE PAGE 1.0 PURPOSE 2 2.0 SCOPE 2

3.0 REFERENCES

AND COMMITMENTS 2 4.0 DEFINITIONS 3 C) 5.0 RESPONSIBILITIES 4 5

6.0 PRECAUTIONS/LIMITATIONS 6

7.0 PROCEDURE 6

7.1 Program Description 7.2 Program Use 9 7.3 Printer Use 14 8.0 INITIAL ACTIONS 15 9.0 SUBSEQUENT ACTIONS 15 10.0 RECORDS 15 11.0 FORMS 15 ATTACHMENT A NPIS SCREEN DISPLAYS 16 ATTACHMENT B RADIATION MONITOR INFORMATION 17

Revision: 5 DOSE ASSESSMENT EPP 06-012 Reference Use Page 2 of 18 rl 31.0 PURPOSE 1.1 This procedure provides guidance for determining release rates t*2 and for estimating off-site dose to the Whole Body and Thyroid.

C0 C, 2.0 SCOPE N, 2.1 The estimated release rate, total release values, off-site dose 0* rates, and integrated doses to the Whole Body and Thyroid, are used in conjunction with EPP 06-006, PROTECTIVE ACTION RECOMMENDATIONS, as one basis for determining off-site protective actions to be recommended to State and County o" Officials.

3.0 REFERENCES

AND COMMITMENTS 3.1 References 3.1.1 CHS AX-GO1, SAMPLING OF UNIT AND RADWASTE VENTS FOR RADIOACTIVE GAS AND TRITIUM 3.1.2 EPP 06-006, PROTECTIVE ACTION RECOMMENDATIONS 3.1.3 EPP 06-009, DRILLS AND EXERCISE REQUIREMENTS 3.1.4 EPP 06-011, EMERGENCY TEAM FORMATION AND CONTROL 3.1.5 EPP 06-013, EXPOSURE CONTROL AND PERSONNEL PROTECTION 3.1.6 Radiological Emergency Response Plan (RERP) 3.1.7 Regulatory Guide 1.109, Calculation Of Annual Doses To Man From Routine Release Of Reactor Effluents For The Purpose Of Evaluating Compliance With 10CFR50, Appendix I, (Rev. 1, October, 1977) 3.1.8 Regulatory Guide 1.111, Methods For Estimating Atmospheric Transport And Dispersion Of Gaseous Effluents In Routine Releases From Light Water Cooled Reactors, (Rev. 1, July 1977) 3.1.9 Regulatory Guide 1.145, Atmospheric Dispersion Models For Potential Accident Consequence Assessments At Nuclear Power Plants, (August, 1979) 3.1.10 Regulatory Guide 1.23, Meteorological Programs In Support Of Nuclear Power Plants, (September, 1980) 3.1.11 Regulatory Guide 1.4, Assumptions Used For Evaluating The Potential Radiological Consequences Of A Loss Of Coolant Accident For Pressurized Water Reactors, (Rev.

2, June 1974)

r Revision: 5 DOSE ASSESSMENT EPP 06-012

  • Reference Use Page 3 of 18 3.2 Commitments 3.2.1 ITIP 00101 (SOER 83-02, Recommendation R12), Ensure Estimates Of Dose Can Be Made For Two-Phase Or Liquid C) Releases Though S/G Safety And Relief Valves.

C)

H) 4.0 DEFINITIONS a

0l 4.1 Emergency Planning Zone (EPZ) 4.1.1 The area around WCGS in which emergency preparedness Mi planning is conducted. The plume exposure EPZ has a radius of approximately 10 miles. The ingestion exposure pathway EPZ has a radius of about 50 miles.

4.2 Exclusion Area 4.2.1 That area within a 1200-meter radius surrounding WCGS in which WCNOC has the authority to determine all activities including exclusion or removal of persons and property from the area.

4.3 Integrated Dose 4.3.1 The amount of ionizing radiation that has been received during a given period of time by a population or group.

4.4 Pasquill Atmospheric Stability Classifications 4.4.1 Are measures of the stability or instability of an air mass based upon the vertical temperature differential between two points.

4.5 Projected Dose 4.5.1 The amount of ionizing radiation that is likely to be received by a population or group if no protective action measures are implemented.

4.6 Projected Integrated Dose 4.6.1 The summation of the Integrated Dose (previous) and the Projected Dose (future).

4.7 Protective Actions 4.7.1 Those emergency measures taken to minimize or prevent radiological exposures to personnel.

4.8 Release Rate 4.8.1 The quantity of radioactive material released to the environment expressed in curies per second (Ci/sec).

1 Revision: 5 DOSE ASSESSMENT EPP 06-012 SReference Use Page 4 of 18.

ri 4.9 Source Term 4.9.1 The calculated quantity of radioactive material I*) available for or being released to the environment.

C)

C; 4.10 X/Q 4.10.1 A factor based on meteorological dispersion

0) characteristics which relates atmospheric radionuclide C' release rates to offsite air concentrations.

I 4.11 Nuclear Plant Instrument System (NPIS) 4.11.1 A plant monitoring tool designed to view critical systems and components during normal and accident conditions.

4.12 Dose Assessment Program 4.12.1 A computer program developed at Wolf Creek designed to use site-specific source terms in the performance of Dose Assessment during an accident condition.

5.0 RESPONSIBILITIES 5.1 Shift Manager 5.1.1 Prior to activation of the Emergency Operations Facility (EOF), assures the Shift Chemist implements this procedure.

5.2 Radiological Coordinator 5.2.1 IF vent monitor(s) are inoperable, THEN consider dispatching Plant Team(s) to collect appropriate samples.

5.3 Shift Chemist 5.3.1 At the declaration of an ALERT or higher emergency classification reports to the Control Room to perform emergency dose calculations in accordance with this procedure.

5.4 Dose Assessment Coordinator 5.4.2 Recommends that Offsite Monitoring Teams be dispatched to determine offsite dose rates in accordance with EPP 06-011, EMERGENCY TEAM FORMATION AND CONTROL.

5.4.3 Informs the appropriate TSC or EOF management of the dose rate and projected integrated TEDE and Thyroid doses.

H Revision: 5 DOSE ASSESSMENT EPP 06-012

- Reference Use Page 5 of 18 rl 5.5 Dose Assessment Technician 5.5.1 Performs emergency dose calculations in accordance with this procedure.

[0 0 6.0 PRECAUTIONS/LIMITATIONS 6.1 To confirm that the correct version of the Dose Assessment 0* Program is in use, open the Dose Assessment Program, then click (4 on 'Help' and 'Help About'. The correct version currently in use is Rev. 3.2. If the correct version is not loaded on your computer, it should be removed from your hard drive.

0" 6.2 Offsite dose projection calculations should be performed at least once per hour during the first eight hours after the accident unless it is determined that releases of airborne radioactivity from the plant have been terminated.

NOTE Use 15 minute MET data averages to determine if changes are in progress.

6.3 Offsite dose projection calculations may be updated anytime it is deemed necessary. Offsite dose projection calculations should be updated if any of the following conditions occur:

6.3.1 Release rate increases by more than 25 percent.

6.3.2 Wind direction changes by more than 22.50.

6.3.3 Atmospheric stability classification changes.

6.3.4 Wind speed changes by more than 50 percent.

6.3.5 Prior to any planned releases.

6.4 IF a radiological release is already in progress before a dose assessment calculation is performed, THEN be sure to look at historical release data / trend on the NPIS to determine the maximum release rate, monitor readings, and meteorological conditions.

6.4.1 IF this is not done THEN an under estimation of an emergency dose projection can occur.

-, Revision: 5 DOSE ASSESSMENT EPP 06-012 Reference Use Page 6 of 18 I

7.0 PROCEDURE 7.1 Program Description 03 NOTES C,

o Tab and Shift Tab key manipulations may be used to move through a Model Screen.

o Commonly practiced window manipulations may also be used to move through the program.

7.1.1 The following models may be selected by selecting the appropriate tab in the upper right hand corner of the program window.

1. Release Rate Model
2. Design Basis Accident (DBA)
3. SG Tube Rupture
4. Radiation Monitoring System
5. Field Team Data 7.1.2 Information
1. Selection of the INFORMATION heading on the tool bar allows access to the following screens:
a. Dose Projection Report/Dose by Subzone
b. Source Term
2. The Dose Projection Report/Dose by Subzone and Model Screen are two separate program windows and can both be visible at the same time, subject to limitations of screen resolution, and size.
a. The Model Screen includes:
1) MET data section
2) Release data section
3) Performed/Verified signature section
4) Release start time
5) Calculation result section:

H

-r Revision: 5 DOSE ASSESSMENT EPP 06-012 Reference Use Page 7 of 18 V1 a) Particulate, Noble Gas and Iodine release rates.

b) Projected Centerline Dose Segment - the results of the data entered above but not summed.

6) PAR section which is based on the Projected C) Dose Segment as well as the summed doses.

(4 a) Only evacuation recommended subzones are listed.

b. Dose Projection Report/Dose by Subzone Screen includes:
1) Dose Rate to the Whole Body and Thyroid for Exclusion Area Boundary (EAB), 2, 5, and 10 miles in Roentgen per hour (R/hr).
2) Plume arrival time in minutes for EAB, 2, 5, and 10 miles based on wind speed.
3) Estimated hours until evacuation necessary for EAB, 1 R TEDE or 5R thyroid.
4) A list of both TEDE and Thyroid Dose for each subzone.
3. The source term option allows manipulation of DCF information.
a. The source term enables the user to alter the distribution from the USAR Gap and default activities.
1) Selection of the Activity heading on the source term screen tool bar allows the user to zero all activities for manual entry or to return to USAR Gap activities.
2) Selection of the File heading on the source term screen tool bar allows for data file manipulation.

Revision: 5 DOSE ASSESSMENT EPP 06-012 Reference Use Page 8 of 18 NOTE If the containment spray is selected, the program will inquire C) whether the spray has been on for 30 minutes or more. If the spray has been on for 30 minutes or more, the filtration factor I) will be utilized; if not, the filtration factor will not be applied.

0

b. Two additional nuclide distribution factors are available on the source term screen, HEPA G" filters and Containment Spray.
1) A "Y" entry in the HEPA Filter Box reduces the Iodine Activity 90%. That is, 10% of the Iodine activity is released to the public.
2) A "Y" entry in the Containment Spray Box reduces the Iodine Activity available for release by 75%. That is, 25% of the Iodine activity is released to the public.
3) If both HEPA Filter and Containment Spray are answered "Yes", the Iodine Activity used in the offsite dose projections is reduced to 2.5% of its original activity level.
4) Prior to performing real time calculations, the user must remember to check the source term screen values to ensure projection source term values are appropriate.
4. PARs selection from the Information Menu Bar provides information for review of Protective Action Recommendations.

NOTE The notification form can only be printed if THE DOSE ASSESSMENT PROGRAM is running from the LAN.

5. The File Menu bar provides options to print the Notification form and calculation worksheet.

7.1.3 Data

1. Selection of Data from the Menu Bar allows selection of the following actions:
a. Sort Dose by Subzone

Revision: 5 DOSE ASSESSMENT EPP 06-012 Reference Use Page 9 of 18

b. Sum Dose
c. Perform Calculations
d. Long Range Calculations
2. The Sort Dose by Subzone and Sum Dose actions are self-explanatory.

7.1.4 Calculations

1. The offsite doses will be calculated using the data displayed on the Model Screen.

7.1.5 Long Range Calculations

1. The offsite doses, and farthest evacuation distance will be calculated using the data displayed on the Model Screen.

7.2 Program Use 7.2.1 The Dose Assessment Program will normally be operated from an Icon on the desktop. The program is also available at I:\Shared\EDCP\EDCP.EXE.

7.2.2 Select a Release Model from the tabs in the upper right hand corner of the program screen.

7.2.3 Dose calculations may now be performed. Menu items necessary for operation of the program are selected from the Menu Bar.

NOTE On a total lose of offsite power, certain radiation monitors are still available. See ATTACHMENT B for more information.

7.2.4 Obtain the following information:

1. Plant Status
2. MET data
3. Process Monitor data
4. Effluent Flow rate data

-OR

- 5. If no data is available perform a DESIGN BASIS RCS LOCA using:

Revision: 5 DOSE ASSESSMENT EPP 06-012 Reference Use Page 10 of 18 V a. DBA Release Rate

b. Unfiltered Release Pathway 0l c. Stability Class D for daytime or Stability Class C) F for night time N. -OR C)
d. If the accident is deemed to be outside of Design Basis and is rapidly escalating, t*J recommend to the Emergency Manager to use EPP a"06-006, PROTECTIVE ACTION RECOMMENDATIONS.

7.2.5 Dose Assessment Program MET Information

1. Wind speed can be input as mph, kph, or mps by double-clicking within the box surrounding the input description until the appropriate description is displayed.
2. Projected release duration and time since reactor trip can both be input as hrs., mins., or days by double-clicking within the box surrounding the input description until the appropriate description is displayed.
3. A Stability Class-Wind Speed/Weather Conditions Help Screen is available by double-clicking within the stability class input field.
a. The user may generate a stability class by selecting the appropriate weather condition and inputting the proper wind speed.
b. The generated stability class is returned to the Model Screen by selecting FILE EXIT.

7.2.6 Dose Assessment Program Model Operations

1. Steps 7.2.7 through 7.2.11 contain information regarding data entry specific to each model 7.2.7 Option One, Release Rate Model
1. This model allows the user to input Gaseous and Iodine release rates in Ci/sec.
2. The following instructions may be useful in operating the Release Rate Model:
a. Gaseous Release Rate may be changed to Total Release Rate by double-clicking within the box surrounding the Gaseous Release Rate.

Revision: 5 DOSE ASSESSMENT EPP 06-012 Reference Use Page 11 of 18 P1

1) Likewise, the display can be changed to Gaseous Release Rate from Total Release Rate by double-clicking within the box surrounding the total release rate.
b. Iodine Release Rate may be changed to a ratio by double-clicking within the box surrounding the Iodine Release Rate.
1) IF the ratio is known, THEN the value can be entered.
2) If the ratio is unknown, a Help Screen may be displayed by double-clicking within the input field for the iodine ratio.
3) Once the user selects the appropriate ratio from the list, FILE EXIT is used to return to the Model Page of the report.
4) The display may be changed back to Iodine Release Rate by double-clicking within the box surrounding Iodine/Noble Gas Ratio.
c. IF a leak rate (gal/min) and activity (pCi/cc) is known or can be estimated, THEN the following calculation could be used to determine a release rate:

SCC Dni 60si gal 1 pa galImin)3.785L)(1000cc L

a___

7.2.8 Option Two, Design Basis Accident (DBA) Model

1. This model allows the user to perform dose calculations based on USAR release rate data for various design accidents.
2. If this option is selected, the user may select from a list of nine DBAs:
a. Loss of Coolant
b. Main Steam Line Break
c. Loss of Offsite AC
d. Locked RCP Rotor
e. Waste Gas Decay Tank Rupture
f. CVCS Break

H Revision: 5 DOSE ASSESSMENT EPP 06-012

-J Reference Use Page 12 of 18

g. SG Tube Rupture
h. Fuel Handling Accident 0 i. Control Rod Ejection ci ti NOTE C, Use field team data whenever available to provide the most accurate dose estimations.

1 7.2.9 Option Three, Steam Generator Tube Rupture

1. The SG Tube Rupture Model allows the user to perform dose calculations based on a steam generator tube rupture utilizing steam flow and shine monitor readings.
2. The following instructions may be helpful when performing SG Tube Rupture calculations:
a. Steam generator monitor readings may be input in mR/hr for either a steaming steam generator or a full steam generator.
1) The input description is changed by double clicking within the box surrounding the input description.
2) Steam generator flow may be input in ibm/hr, thousands of Ibm/hr, gph or as a pressure entered by the user.

a) Gallons per hour (gph) should be selected if the steam generator is full of water.

This option represents a two-phase or liquid release from the steam generator.

[Commitment Step 3.2.11 b) The input description is changed by double-clicking within the box surrounding the input description.

3) A Steam Generator PORV/Auxiliary Feed Exhaust Help Screen is available by double clicking either the steam generator monitoring readings or steam generator flow input field.

H Revision: 5 DOSE ASSESSMENT EPP 06-012 Reference Use Page 13 of 18 ni a) Once the Help Screen is completed, the user can return the averaged flow and monitor readings to the Main Screen by selecting FILE EXIT.

C)

C) 7.2.10 Option Four, Radiation Monitoring System (RMS)

1. The RMS Model allows the user to input data from C the unit and/or radwaste vent monitor as well as the vent flow rates to perform offsite dose calculations.
2. The following instructions may be helpful when performing RMS calculations:
a. Gaseous Activity - May be changed to Total Activity by double-clicking within the box surrounding Gaseous Activity.
1) Likewise, if Total Activity is displayed it may be toggled back to Gaseous Activity by using the same technique.
b. Iodine Activity - May be changed to a ratio if necessary by entering the ratio value followed by double-clicking within the box surrounding the Iodine Activity. This is a toggle type of function and may be returned to an activity using the same technique.
1) If the ratio is unknown, the value may be entered.
2) If the ratio is unknown, once the display has been changed to a ratio input, double clicking on the associated data field will access a Help Screen.
3) Once the user selects the appropriate DBA ratio, FILE EXIT may be used to return the value to the Model Screen.
c. Vent Flow -- may be entered.
1) A Help Screen is available by double clicking the Vent Flow data box.
2) Enter the fan status for each fan by entering the status and then pressing Enter.
3) Select Vent Totals from the tool bar and total the flows required.

Revision: 5 DOSE ASSESSMENT EPP 06-012 Reference Use Page 14 of 18 E 4) Select FILE EXIT from the tool bar to forward the value to the Model Screen.

7.2.11 Option Five, Field Team Data Model C) 0 1. This model allows the user to input field team dose H) rates, iodine concentration, particulate concentration and distance information to back U* calculate the plant release rate and then ultimately the down field doses.

2. The following instructions may be helpful when performing the Field Team dose calculations:

NOTE The Particulate/Iodine ratio used throughout the Dose Assessment Program is 0.112. If the Particulate/Iodine ratio is selected, unless an entry is made, the value of 0.0 will be used. This option only pertains to the field team model.

a. Field Team Iodine Concentration may be changed to Iodine/Noble Gas Ratio by double-clicking in the box surrounding Field Team Iodine Concentration. This is a toggle-type function and may be changed back to concentration input using the same technique. By selecting Iodine/Noble Gas Ratio the particulate field will change to Particulate/Iodine Ratio.
1) If the ratio is known, the value may be entered.
2) If the ratio is unknown, once the display has been changed to a ratio input, double clicking on the associated data field will access a Help Screen.
3) Once the user selects the appropriate ratio, FILE EXIT may be used to return the value to the Model Screen.
b. Field Team Distance may be toggled between units of miles and kilometers by double-clicking in the box surrounding the Field Team Distance.

7.3 Printer Use 7.3.1 Selection of FILE and PRINT from the tool bar will allow the user to print to a Network printer.

H Revision: 5 DOSE ASSESSMENT EPP 06-012 Reference Use Page 15 of 18 NOTE There may be error messages received when printing the notification form. In most cases these are due to the PC C0 configuration and not the Dose Assessment Program program. If C) the program does not abort, then you should get printed output.

11 7.3.2 The notification form will only print if the PC is

(,) connected to the LAN and the user is logged into a server.

8.0 INITIAL ACTIONS 8.1 None.

9.0 SUBSEQUENT ACTIONS 9.1 None.

10.0 RECORDS 10.1 Printouts associated with this procedure are considered records.

10.2 Records generated by this procedure during an actual emergency are considered lifetime QA records and shall be forwarded to Emergency Planning at the termination of the emergency.

10.3 Records generated by this procedure during a drill or exercise are considered non-QA records and shall be forwarded to Emergency Planning at the termination of the drill or exercise.

11.0 FORMS 11.1 None

- END -

H Revision: 5 DOSE ASSESSMENT EPP 06-012 Reference Use Page 16 of 18 i-l ri 1 ATTACHMENT A (Page 1 of 1)

NPIS SCREEN DISPLAYS C)

C) 0 Group Menu - Touch Screen for E-Plan Menu C)

GI) E-Plan Menu - Touch Screen for one of the following CI- I STATUS BOARD II AREA RAD

1. RCS 1. Radiological Status
2. Steam Generators a.) MET Data a) Levels b) Radmonitors ACi/cc b) Pressures Press F2 Key
3. ECCS 2. Area Radmonitors mR/hr
4. Containment and CHARM R/hr a) Pressure 3. To exit press F6 Key b) Temperature c) H2 concentration d) CHARM R/hr Press F3 Key
5. Critical Parameters
6. To exit press Group Key III MET TOWER DATA IV GROUP DISPLAY
1. Stability Class I. SGCHEM 1
2. Wind Speed 2. SGCHEM 2
3. Wind Direction 3. SGCHEM 3
4. Vert Temp Difference OF 4. PORVMSIV, etc.

NOTE: To change to °C type NOTE: a) To trend press F4 Key GD MET and press b) For the New Group Enter Key Display press F5 Key S. To exit press Group Key 5. To exit press Group Key NOTE: Screen Display Color Code RED - Alarm YELLOW - Alert GREEN - Normal BLUE - Invalid Reading

- END -

-. Revision: 5 DOSE ASSESSMENT EPP 06-012 Reference Use Page 17 of 18 ATTACHMENT B (Page 1 of 2)

RADIATION MONITOR INFORMATION t[)

C)

C) On a total loss of off-site power the following radiation monitors

(') remain operable:

l*3 GHRT 10A Radwaste Building Vent - Part & Iodine GHRT 10B Radwaste Building Cent - WRGM GTRE 21A Unit Vent - Part & Iodine GTRE 21B Unit Vent - WRGM FCRT 385 Aux. Feedwater Turbine Discharge Monitor ABRT 111 Steam Line 'D" PORV Discharge Monitor ABRT 112 Steam Line "C" PORV Discharge Monitor AERT 113 Steam Line "B" PORV Discharge Monitor ABRT 114 Steam Line "AO PORV Discharge Monitor

1. These monitors have as their normal AC power SP02 which is supplied by AC power supply PG19GFF3 (480 Volt AC). This feeds or goes from PG19GFF3 to SP01 Inverter [an UPI] to SP02 to monitors.

H Revision: 5 DOSE ASSESSMENT EPP 06-012 Reference Use Page 18 of 18.

El ATTACHMENT B (Page 2 of 2)

RADIATION MONITOR INFORMATION (3

2. The SP01 Inverter is also fed by a 125 volt DC power PK0304 M] [plant batteries]. In the event of a loss of offsite power
i. occurs (PG19GFF3) then the inverter (UPI) SP01 still feeds the C; monitors via SP02.
3. If after a total loss of offsite power, the plant would regain I') one of the NB buses, then the radiation monitors that are fed from that bus would also be available if flow was restored to the monitor.

NOTE The Chemistry Technicians may have to remind the Control Room to restore flow to these monitors.

4. If the RM-1l is not available the flow to these monitors will have to be done from their RM-23's. (The RM-11 is not powered by NB bus).

- END -

EPF 06-004-01, Rev. 7 Page I of I PUBLIC INFORMATION ORGANIZATION ACTIVATION CHECKLIST ChompletedWhen ll steps required-Within each level Information Clearinghouse Activation WC PIO position staffed.

WC Public Information Manager position staffed.

(1) WC Technical Support position staffed.

News Writer position staffed.

IC telephones available with dial tone.

Fax, copier, computer or alternative capability operational.

Onsite PIC contacted for status update.

Clocks synchronized with Control Room.

Notify State PIO, 785-274-1192 I Information Clearinghouse Activation Date: I / Time:

Notify before continuing Site Emergency Manager 620-364-8831-5341 On-site PIC 620-364-4152 or ext. 5396 Off-site Emergency Manager 620-364-8831-5342 if available KGE/Westar Inc. (Pri) 785-575-1927, (Alt) 620-261-6209

_ KEPCO

_ (Pri) 785-271-4842, (Alt) 785-271-4802, (Alt) 785-271-4840 KCPL (Pri) 816-556-2653, (Alt) 816-556-2365

% P JjRumor Control will notify PIO/PIM when activated 11 SRumor Control (KCPL), 816-556-2269 Phone Team Activation Phone Team Manager position staffed Phone Team telephones available with dial tone 3 of 4 phone team members staffed Repeat notifications from IC Activation Level Phone Team Activation Date: / / Time:

Media Center Activation Media Center Manager or Media Liaison position staffed 1 of 2 Media Registrar staffed Media Registration setup Media Room setup Media Center operational

_Security posted

_Repeat notifications from IC Activation Level Media Center Activation Date: / / Time:

/Dt Public Information Manager Date Time

EPF 06-018-03. Rev. I Page 1 of 2 MEDIA MONITORING INVENTORY AND COMMUNICATIONS CHECKLIST REQUIREMENTS (REQ):

1. Inventory
2. Check seal quarterly/Inventory Annually
3. Operability Check Part I INVENTORY Quarter:I Date: Other:

I I Quantity Item REQ Required Present Comments Documents Rumor Control Coord. Manual (EM545) 1 1 Media Monitoring Team 1 3 Manual (EM225, EM542, EM543)

Radiological Emergency 1 1 set Procedures (EPPs) (EM196)

RETD (TD012, TD058) 1 2 Equipment Fax Machine (Found in 1 1 Governmental Affairs Office)

"TV 1,3 3 VCR 1,3 3 Radio 1,3 3 Telephone 1 2

  • Radio Headsets 1 3 Administrative Supplies Audio Cassette Tapes 1 15 Video Cassette Tapes 1 10
  • Spare Headphone Ear Pads 1 3 sets
  • Clipboard 1 1
  • Manila File Folder 1 15
  • Pens 1 10
  • Administrative Supplies Suggested Quantities

Paae 2 of 2 MEDIA MONITORING INVENTORY AND COMMUNICATIONS CHECKLIST Part II QUARTERLY COMMUNICATIONS CHECKS Quarter: I IDate: IOther:

Tester'sI Communications Circuits Initials Date Comments Rumor Control Coordinator T(816) 556-2269 1 Media Monitoring Team Fax Verification/Spare Phone Line (816) 654-1739 1 Media Conference Phone

a. (816) 556-2272 1 Fax Machine (816) 556-2924 SUBMITTED BY

[] Inventory has been completed and quantities noted. Communication checks are complete and corrective actions initiated for unsatisfactory checks. Other applicable information is provided in the Comments Section above.

Signature Print Name Ext. Date Part III REVIEW AND APPROVAL Quarter: Date: Other:

EMERGENCY PLANNING REVIEW El All identified discrepancies have been restocked and corrective actions complete or otherwise resolved as noted below. Other applicable information is provided in the Comments Section.

Comments:

Reviewer Signature Print Name Ext. Date EMERGENCY PLANNING APPROVAL El All reviews and appropriate actions are complete.

Comments:

Approval Signature Date

EPF 06-018-15, Rev. 3 Page I of 13 EMERGENCY PLANNING QUARTERLY COMMUNICATIONS CHECKLIST Part I I COMMUNICATION CHECKS TECHNICAL SUPPORT CENTER Communication Sat IUnsat Location Circuit (Check one) Date Comments NRC Conference Room Ext. 5324 Ext. 5365 Ext. 5389 Accountability Ext. 4050 1 1 Document Room Ext. 4509 1 1 1Ext. 5322 1 Maintenance Area Ext. 5713 1 NRC (Maintenance Area) 364-4231 or Ext. 4231 Engineering Area Ext. 5366 l Ext. 5310 Ext. 5711 General Use lExt. 5381 1 Fax Verification lExt. 4053 1 Fax Machine 364-4051 or Ext. 4051 TSC Communicator Ext. 5382 Ext. 5392 Team Communicator (Offsite) Ext. 5394 Dose Assessment Area lExt. 5353 1 1 133 FExt. 4332 Plant Status and Ext. 5346 Communications Area Ext. 5701 Ext. 5387 Ext. 4399 Public Information 364-4152 or Coordinator Ext. 5396 Administrative Coordinator Ext. 5375 1 Radiological Coordinator Ext. 5352 1

EPF 06-018-15, Rev. 3 Page 2 of 13 EMERGENCY PLANNING QUARTERLY COMMUNICATIONS CHECKLIST Part I I COMMUNICATION CHECKS TECHNICAL SUPPORT CENTER (Cont'd)

Communication Sat Unsat Location C3rcu.t (Check one) Date Comments Maintenance E 5 Coordinator Ext. 5347 Operations Coordinator Ext. 5345 Logkeeper (Multi-Line) Ext. 5344 Ext. 5358 Ext. 5364 Ext. 5370 I Ext. 5374 _

Ext. 5751 Site Emergency Manager (Multi-Line) Ext. 5341 Hotline NRC (Emergency 364-4230 or Management Area) Ext. 4230 Team Director -Ext.5361 Team Communicator I I (Onsite) Ext. 5359 Maintenance Assistant IExt. 5348 1 1 1 I OSC Seating Room Ext. 5360 1 I 1 1

Page 3 of 13 EMERGENCY PLANNING QUARTERLY COMMUNICATIONS CHECKLIST Part I I COMMUNICATION CHECKS CONTROL ROOM Communication Sat I Unsat Location Circuit (Check one) Date Coments Shift Manager Ext. 5340 Located in cabinet Located in Auxiliary Ext. 4817 Shutdown Panel Room Control Room I Supervisor IExt. 5379 1 Control Room Ext. 5343 _

(Multi-Line) Ext. 5350 Ext. 5357 Ext. 5363 Ext. 5369 Ext. 5373 Ext. 5752 Operations Communicator IExt. 5380 I I Fax Machine 1364-4018 1 1 1

EPF 06-018-15, Rev. 3 Page 4 of 13 EMERGENCY PLANNING QUARTERLY COMMUNICATIONS CHECKLIST Part I COMMUNICATION CHECKS EMERGENCY OPERATIONS FACILITY Communication Sat Unsat Location Circuit (Check one) Date Comments Team Director Ext. 5391, T Team Communicator Ext. 5128 1 1 1 Team Communicator (Multi-line) IExt. 5395 General Use Ext. 5071 1 NRC Engineering Ext. 5127 1 NRC PIO Ext. 5707 1 1 1 Operations Recorder Ext. 5704 1 1 1 EOF Communicator Ext. 5384 I Ext. 5393 Kansas State Rep. EP 364-8859 1 Ext. 5307 1 Kansas State Rep. 364-4237 or (Modem Line) Ext. 5104 NRC 364-4232 or Ext. 5301 Administrative I Coordinator IExt. 5378 1 Coffey County Rep. 364-8734 1 Operations CoordLinator Ext. 5368 1 1 1 NRC 364-4234 1 1 1 Off-Site Emergency Ext. 5342 Manager (Multi-line) Ext. 5349 Ext. 5354 Hotline NRC DSO 364-8243 1 1 I Logkeeper (Multi-line) Ext. 5125 1 General Use Ext. 5126 1

EPF 06-018-15, Rev. 3 Paqe 5 of 13 EMERGENCY PLANNING QUARTERLY COMMUNICATIONS CHECKLIST Part I COMMUNICATION CHECKS EMERGENCY OPERATIONS FACILITY (Cont'd)

Communicatmon Sat I Unsat Location Circuit (Check one) Date Comments Off-Site PIC Ext. 5372 1 NRC 364-4235 or Ext. 5304 Radiological Coordinator Ext. 5355 1o Ext. 5302 Kansas State Rep.- Rad 364-8282 1 1 130 Dose Assessment Area Ext. 5383 1 1 1 NRC (General use) 364-4236 or IExt. 5305 NRC Dose Projection Ext. 5706 1 1 1 FEMA Ext. 5705 1 1 I Dose Assessment Area Ext. 5825 1 1 1 Dose Assessment Coordinator Ext. 5356 EOF Conference Room Ext. 5710 (Multi-line) Ext. 5709 NRC Conference Room Ext. 5124 (Multi-line) Ext. 5130 Document Room Ext. 5111 NRC Mobile Lab Ext. 5300 1 1 1 Kit Room Ext. 5326 1 1 1 Fax Machine 364-4121 or Ext. 5101 Accountability lExt. 5822 1 1 1

EPF 06-018-15, Rev. 3 Page 6 of 13 EMERGENCY PLANNING QUARTERLY COMMUNICATIONS CHECKLIST Part I COMMUNICATION CHECKS EMERGENCY PLAN VEHICLES CommunLcation Sat Unsat Location Circuit (Check one) Date Comments Vehicle #1042 2-Way Radio Cellular Phone Vehicle #1043 1 2-Way Radio i I 1 Cellular Phone Vehicle #1094 12-Way Radi~o i Cellular Phone

EPF 06-018-15, Rev. 3 Page 7 of 13 EMERGENCY PLANNING QUARTERLY COMMUNICATIONS CHECKLIST Part I COMMUNICATION CHECKS

.INFORMATION CLEARINGHOUSE - WOLF CREEK Communication Sat I Unsat Location Circuit (Check one) Date Comments Public Information Ext. 5431 Manager Ext. 5432 Wolf Creek PIO Ext. 5430 1 News Writer/ I I Information Messenger Ext. 5429 1 KGE PIO Ext. 5420 1 KCPL PIO Ext. 5422 1 KPCo PIO Ext. 5421 1 1 1 NRC PIO Ext. 5427 1 FEMA PIO Ext. 5428 1 1 1 Kansas State PIO Ext. 5425 1 1 I Coffey County PIO Ext. 5423 1 Gov. Press Sec. Ext. 5426 1 1 I Part I COMMUNICATION CHECKS MEDIA CENTER - WOLF CREEK Communication Sat I Unsat Location Circuit (Check one) Date Comments Media Phones Ext. 5184 (Room 110) Ext. 5190 Ext. 5183 Ext. 5188 Ext. 5189 Ext. 5309 Ext. 5187 Ext. 5182 Ext. 5185 Ext. 5186 Ext. 5180 Ext. 5181 Conference Phone Line Ext. 5330 1

EPF 06-018-15, Rev. 3 Page 8 of 13 EMERGENCY PLANNING QUARTERLY COMMUNICATIONS CHECKLIST Part I I COMMUNICATION CHECKS PHONE TEAM - WOLF CREEK Communication Sat I Unsat Location Circuit (Check one) Date Conments Phone Team Manager Ext. 5312 Ext. 5308 364-4238 Phone Team Ext. 5313 Ext. 5314 Ext. 5315 Ext. 5316 Ext. 5317 Ext. 5318 Ext. 5319 Ext. 5320 Fax Machine 364-4122 or Ext. 5102

EPF 06-018-15, Rev. 3 Page 9 of 13 EMERGENCY PLANNING QUARTERLY COMMUNICATIONS CHECKLIST Part I COMMUNICATION CHECKS INFORMATION CLEARINGHOUSE - TOPEKA Communication Sat I Unsat Location Circuit (Check one) Date Comments Public Information Manager (785) 267-0651 Wolf Creek PIO (785) 267-0649 1 Technical Support (785) 267-3238 1 1 1 News Writer/

Information Messenger (785) 267-0603 IC Fax (785) 267-0742 1 1 1 WCNOC Owner PIO (785) 267-0725 1 1 1 WCNOC Owner PIO (785) 267-0748 1 1 NRC PlO (785) 267-0669 1 1 FEMA PIO 1(785) 267-0686 1 1 1 Kansas State PIO (785) 267-0627 1 1 1 Coffey County PIO (785) 267-0688 1 1 1 Gov. Press Sec. (785) 267-0612 1 1 1 Part I COMMUNICATION CHECKS PHONE TEAM ROOM - TOPEKA Communication Sat I Unsat Location Circuit (Check one) Date Comments Phone Team Manager (785) 267-0145 (785) 267-0397 (785) 267-1441 (785) 267-0662 (785) 267-0623 (785) 267-0509 (785) 267-0957 (78 5 ) 2 67 - 0 3 9 8 _ Pu li h e as Published as

____________(785) 267-0131 ____________1-800-354-3831

EPF 06-018-15, Rev. 3 Page 10 of 13 EMERGENCY PLANNING QUARTERLY COMMUNICATIONS CHECKLI ST Part I [-COM4MUNICATION CHECKS MEDIA CENTER - TOPEKA Communication Sat I Unsat Location Circuit (Check one) Date Comments Media Center i Auditorium (785) 267-9327 i Media Phones (785) 267-0399 (Armory Gym) (785) 267-0360 (785) 267-0434 (785) 267-0374 (785) 267-0481 (785) 267-0496 (785) 267-0468 (785) 267-0483 (785) 267-0457 (785) 267-0441 (785) 267-0465 1 1 1(785) 267-0450 1 1 Media Conference (785) 267-0295 1 Room (785) 267-0321 SUBMITTED BY jj Communication checks are complete and corrective actions initiated for unsatisfactory checks noted above.

Comments:

Signature Print Name Ext. Date

EPF 06-018-15, Rev. 3 Page 11 of 13 EMERGENCY PLANNING QUARTERLY COMMUNICATIONS CHECKLIST Part II COMMUNICATION DEVICES (OWNER CONTROLLED AREA)

Brick House Quantity Sat I Unsat Item Req. Present (Check one) Date Comments Tone Alert Radio 1 E-Plan Pager Number: 1 AA Batteries -4 n/a n/a Exp. Date:

Emergency Information 1 n/a n/a Card Posted Color:

Double-Wide House Quantity Sat Unsat Item Req. Present (Check one) Date Comments Tone Alert Radio 1 E-Plan Pager Number: 1 Emergency Information 1 n/a n/a Card Posted Color:

AA Batteries -4 n/a n/a Exp. Date:

Black Bear Bosun Shelter House Quantity Sat Unsat Item Req. Present (Check one) Date Comments Tone Alert Radio 1 SUBMITTED BY E] Communication checks are complete and corrective actions initiated for unsatisfactory checks noted above.

Comments:

Signature Print Name Ext. Date

EPF 06-018-15, Rev. 3 Page 12 of 13 Page 12 of 13 EPF 06-018-15, Rev. 3 EMERGENCY PLANNING QUARTERLY COMMUNICATIONS CHECKLIST Part III I ERDS TEST ERDS is tested on Tuesday of the eleventh full week of each quarter.

(If the Tuesday is a Federal holiday, the check will be performed on Friday that same week). Contact and testing shall be between the hours of 8 AM and 4 PM eastern time. ERDS data is to be transmitted for a two-hour period.

1.0 Contact the NRC Operations Center to arrange a time to conduct the test (refer to RETD,Section II, OFFSITE SUPPORT, for telephone number).

"o Test period scheduled at "o NRC Contact 2.0 Contact the Control Room and indicate that ERDS testing is commencing.

3.0 Activate ERDS using the NPIS Computer in the TSC Computer Room or as otherwise directed by Emergency Planning:

a. Select the E-Plan Menu, then touch the ERDS block on the screen OR Type the Turn-On code "ERDS" and press the "Return/Enter" key
b. Follow the prompts until the ERDS is activated.
c. ERDS activated at (time) 4.0 At the end of the two-hour testing period, contact the NRC:

4.1 Verify the time of reconnect upon loss of telephone connect.

Reconnect upon loss of telephone at 4.2 IF the ERDS connection has not been terminated by the NRC, THEN request permission to end the transmission.

4.3 IF directed by the NRC to perform the disconnect, THEN deactivate ERDS

a. Press the "F3" key on the NPIS computer
b. Follow the prompts until the ERDS is deactivated
c. Verify the ERDS connection has been terminated 4.4 Two-hour transmission complete at . (time)

SUBMITTED BY E] ERDS test is complete and corrective action initiated for unsatisfactory test.

Comments:

Signature Print Name Ext. Date

EPF 06-018-15, Rev. 3 Paqe 13 of 13 EMERGENCY PLANNING QUARTERLY COMMUNICATIONS CHECKLIST Part IV' REVIEW AND APPROVAL Quarter: Date: Other:

EMERGENCY PLANNING REVIEW E] Corrective actions complete or otherwise resolved as noted below.

Other applicable information is provided in the Comments Section.

Comments:

Reviewer Signature Print Name Ext. Date EMERGENCY PLANNING APPROVAL E] All reviews and appropriate actions are complete.

Comments:

Approval Signature Date

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