ML040850457

Revision 10 to EPIP-13, Initial Dose Assessment for Radiological Emergencies.

ML040850457
Person / Time
Site:	Watts Bar
Issue date:	03/19/2004
From:	Pace P Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Security and Incident Response
References
EPIP-13, Rev 10
Download: ML040850457 (32)

Text

Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 MAR 19 2004 10 CFR 50, App E.

U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:

In the Matter of ) Docket No. 50-390 Tennessee Valley Authority WATTS BAR NUCLEAR PLANT (WBN) - EMERGENCY PLAN IMPLEMENTING PROCEDURE (EPIP) REVISIONS In accordance with the requirements of 10 CFR Part 50, Appendix E, Section V, the enclosure provides the following EPIP.

EPIP Rev Title Effective Date EPIP-13 10 Initial Dose Assessment for 2-20-2004 Radiological Emergencies This EPIP contains a typographical error in Appendix B, Step [31.

The last three words of this step are unnecessary and are to be deleted in the next revision to this EPIP. Step [3] should read "DETERMINE the flow rate for the release path."

There are no regulatory commitments in this letter. If you should have any questions, please contact me at (423) 365-1824.

Sincerely, P. L. Pace Manager, Site Licensing and Industry Affairs Enclosure cc: See Page 2

U.S. Nuclear Regulatory Commission Page 2 MAR.1 9 2004 PLP:JES Enclosure cc (Enclosure):

NRC Resident Inspector (w/o Enclosure)

Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381 U.S. Nuclear Regulatory Commission (2 copies)

Region II Sam Nunn Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303

TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT EMERGENGY PLAN IMPLEMENTING PROCEDURE EPIP-13 INITIAL DOSE ASSESSMENT FOR RADIOLOGICAL EMERGENCIES Revision 10 Unit 0 PREPARED BY: George Crowley/Eddie Woods SPONSORING ORGANIZATION: Emergency Planning APPROVED BY: Frank L. Pavlechko Effective Date: 02/20/2004 LEVEL OF USE: REFERENCE NON-QUALITY RELATED

WBN INITIAL DOSE ASSESSMENT EPI P-I 3 FOR RADIOLOGICAL EMERGENCIES

-, ___REVISION LOG Revision Implementation Pages Description of Revision Number Date Affected 8 12/16/2002 All Plan effectiveness determination reviews indicate the following revisions do not reduce the level of effectiveness of the procedure or REP:

Non Intent change. Renumbered instruction for inter-site consistency, formerly EPIP-16. For historical data, source notes, etc., see EPIP-16, Revision 14. Editorial revisions. Deleted source notes, renumbered sections, corrected Appendix references.

9 06/02/2003 2, 4, 6,12, Plan effectiveness determination reviews 24 indicate the following revisions do not reduce the level of effectiveness of the procedure or REP:

Non Intent change. Standardized record retention. Editorial corrections. Revised SQN Control Room access phone number.

K 10 02/20/2004 All Intent change. Added steps in Appendix B to support Tritium (TPBAR's) in calculations.

Modified TEDE/CDE factors to support infinite cloud methodology to be consistent with CECC EPIP-8. General editorial changes, remove extraneous formatting.

PAGE 2 OF 30 REVISION 10

WBN INITIAL DOSE ASSESSMENT EPIP-1 3 FOR RADIOLOGICAL EMERGENCIES TABLE of CONTENTS Section Description Page 1.0 PURPOSE 4

2.0 REFERENCES

4 2.1 Interfacing Documents 4 2.2 Other Documents 4 2.3 Definitions/Acronyms 5 3.0 GENERAL INSTRUCTIONS 6 4.0 RECORDS 6 APPENDIX A - "ICS" DOSE ASSESSMENT 7 FIGURE A - SITE MAP 8 APPENDIX B - MANUAL ASSESSMENT OF MONITORED GASEOUS RELEASES 9 APPENDIX C - UNMONITORED RELEASES BASED ON ACCIDENT TYPES 17 APPENDIX D - NOBLE GAS RELEASE RATE EVALUATION 18 APPENDIX E - STEAM LINE RELEASE EVALUATION 20 APPENDIX F - USE OF GRAB SAMPLES FOR GASEOUS EFFLUENT EVALUATION 22 APPENDIX G - TOTAL SITE NOBLE GAS RELEASE RATE 24 APPENDIX H - FLOW ESTIMATES 25 APPENDIX I - CECC LONG TERM DOSE ASSESSMENT 26 APPENDIX J - LOSS OF METEOROLOGICAL DATA 27 PAGE 3 OF 30 REVISION 10

WBN INITIAL DOSE ASSESSMENT EPIP-13 FOR RADIOLOGICAL EMERGENCIES 1.0 PURPOSE This Procedure provides initial guidance to support site activities concerning dose assessment for airborne release situation(s).

2.0 REFERENCES

2.1 Interfacing Documents

1. CECC EPIP-8, "Dose Assessment Staff Activities During Nuclear Plant Radiological Emergencies"

2. WBN FSAR

3. ICS User's Manual

4. EPIP-1, "Emergency Plan Classification Flowchart" 2.2 Other Documents

1. TVA NP Radiological Emergency Plan

2. NUREG-0654/FEMA REP-1, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" K> 3. NUREG 1465, Accident Source Terms for Light-Water Nuclear Power Plants

4. NUREG 1228, Source Terms Estimated During Incident Response to Severe Nuclear Power Plant Accidents

5. Title 10, Code of Federal Regulations, Part 50, Appendix E

6. DCN 37910-A

7. EPA-400

8. Title 10, Code of Federal Regulations, Part 20

9. Letter, Eberline Instrument Co., to TVA (EEB820919007), 9/19/83 on (High Range Monitor Efficiencies)

10. EPIP-6, Activation and Operation of the Technical Support Center (TSC)

11. ODCM

12. NE Calculation Package, WBN TSR-008, WBNTSR-009, TI-RPS-162, WBN NAL 3-003R1, WBN APS 3-084

13. SPP-2.6, Computer Software Control

14. Watts Bar Nuclear Plant Environmental Data Station Manual.

15. Regulatory Guide 1.23, "Onsite Meteorological Programs."

16. American Nuclear Society Standard ANSI/ANS-3.11-2000, "Determining Meteorological Information at Nuclear Facilities."

17. Meteorological Data Print Program Users Manual.

18. Radiological Emergency Notification Directory (REND).

19. Watts Bar Nuclear Plant Nowcast Manual, October 1991.

20. ANSI N18.7-1976 PAGE 4 OF 30 REVISION 10

WBN INITIAL DOSE ASSESSMENT EPIP-13 FOR RADIOLOGICAL EMERGENCIES 2.3 DefinitionslAcronyms AIRBORNE RELEASE: Release of airborne radioactive material from the site into the environment.

CECC: Central Emergency Control Center.

EXCLUSION AREA BOUNDARY: The demarcation of the area (0.62 mile) surrounding the WBN units in which postulated FSAR accidents will not result in population doses exceeding the criteria of 10CFR Part 100. (See Figure A of this procedure).

ICS: Integrated Computer System.

PAG: Protective Action Guide. Specific levels of radiation dose control established by the Environment Protection Agency, (i.e., I REM TEDE, 5 REM Thyroid CDE).

RE/RM ICS references radiological elements (RE). The control room also has radiological monitors (RM) connected to these elements. For the purposes of this procedure these acronyms can be used interchangeably.

SITE BOUNDARY: The Site Boundary used here is consistent with the definition in the Offsite Dose Calculation Manual. (See Figure A of this procedure). The appropriate boundary between 'onsite" and "offsite".

SITE PERIMETER (SP): An area encompassing owner controlled areas in the immediate site environment. Measurements are taken at the 16 identified radiological monitoring points along the Site Perimeter. (See Figure A of this procedure).

STABILITY CLASS: An index (A-G) to represent the degree of mixing in the atmosphere.

TEDE: Total Effective Dose Equivalent. The TEDE dose is equivalent to the sum of the plume EDE, the inhalation EDE, and the ground EDE.

THYROID CDE: Thyroid Committed Dose Equivalent.

X/Q: The release dilution ratio between concentrations (X) at reception point (e.g., SP) to the source strength (Q) at a given release point. This dilution ratio is incorporated into the tables for Appendix B.

PAGE 5 OF 30 REVISION 10

WBN INITIAL DOSE ASSESSMENT EPI P-1 3 FOR RADIOLOGICAL EMERGENCIES 3.0 GENERAL INSTRUCTIONS 3.1 The onshift Radiological Control Group (RADCON) is responsible for completing this procedure should the CECC/TSC not be activated. This procedure will be performed as directed by the SEDISM when a dose assessment is necessary.

3.2 For initial dose assessment activities, COMPLETE the instructions found in Appendix A, "ICS, Dose Assessment."

3.3 Should ICS dose assessment be unavailable use the backup calculation method in Appendix B for the Site Boundary and five mile zones.

4.0 RECORDS 4.1 Records of Classified Emergencies The materials generated in support of key actions during an actual emergency are considered Lifetime retention Non-QA records. Materials shall be forwarded to the EP Manager who shall submit any records deemed necessary to demonstrate performance to the Corporate EP Manager for storage.

4.2 Drill and Exercise Records The materials deemed necessary to demonstrate performance of key actions during drills are considered Non-QA records. These records shall be forwarded to the EP Manager who shall retain records deemed necessary to demonstrate six-year plan performance for six years. The EP Manager shall retain other records in this category for three years.

PAGE 6 OF 30 REVISION 10

WBN INITIAL DOSE ASSESSMENT EPIP 13 FOR RADIOLOGICAL EMERGENCIES E APPENDIX A - "ICS" DOSE ASSESSMENT (Page 1 of 1)

NOTE 1: METDATA, wind direction, and EFF1 information are also available from the Dose l Assessment screen. See example of ICS Dose Assessment screen below.

[1] ACCESS the main WBN menu screen from an ICS terminal.

[2] ACCESS the TSC menu from the main WBN menu screen.

[3] ACCESS the Dose Assessment screen (DOSE) from the TSC menu.

[4] SELECT the appropriate appendix on the EPIP-13 Dose Assessment Calculator program.

[5] CALCULATE the Dose Assessment and print the Appendix.

[6] IF ICS Dose Assessment is unavailable or the incident involves TPBAR's, THEN REFER to the Appendix B of this procedure.

EPIP-13 Dose Assessment Calculator - Screen Example PAGE 7 OF 30 REVISION 10

WBN INITIAL DOSE ASSESSMENT EPI FOR RADIOLOGICAL EMERGENCIES P-13 FIGURE A - SITE MAP (Page 1 of 1)

PAGE 8 OF 30 REVISION 10

WBN INITIAL DOSE ASSESSMENT FOR RADIOLOGICAL EMERGENCIES E APPENDIX B - MANUAL ASSESSMENT OF MONITORED GASEOUS RELEASES (Page 1 of 8)

[1] IF the incident does not involve TPBAR, THEN GO TO step [11].

[2] REQUEST Chemistry to obtain a sample of the appropriate gaseous release for tritium.

NOTE Appendix F may be referred to during periods when ICS is unavailable to obtain release flow I rate.

[3] DETERMINE the flow rate for the release path that tritium being

[4] DETERMINE the tritium release rate by completing the following table.

A l B C D=AxBxC Tritium Release Conversion factor to Tritium Release Concentration Flowrate convert scfm to cc/s. Rate

[ICi/cc scfm __Ci/s 472 cc/s/scfm FNOTE Appendix J may be referred to during periods when the Meteorological data is unavailable. I

[5] OBTAIN Stability Class from the MET DATA screen on ICS or from SQN control room (843-7860) and CIRCLE the Stability Class in both tables below.

[6] IF the Stability Class cannot be obtained, THEN DETERMINE the stability class by subtracting the 10 meter from the 46 meter temperatures and CIRCLE the stability class in both tables below.

A* -1.24 B -1.1 I to -1.23 C -.98 to -1.1 0 D -.33 to -.97 E .97 to -.32 F 2.59 to .98 G 2 2.6

[7] OBTAIN the wind speed in mph from the 46 meter height and CIRCLE the appropriate range for the wind speed in both tables below.

PAGE 9 OF 30 REVISION 10

WBN INITIAL DOSE ASSESSMENT FOR RADIOLOGICAL EMERGENCIES E 3 K) APPENDIX B - MANUAL ASSESSMENT OF MONITORED GASEOUS RELEASES (Page 2 of 8)

[8] CIRCLE the appropriate Tritium TEDE factors for each distance in the tables below based on the wind speed and stability class obtained in the above steps.

0.62 Mile Tritium TEDE Factors Stability <2.2 >2.2 >4.4 >6.6 >8.8 >11 >13.2 >15.4 >17.6 >19.8 Class mph <=4.4 <=6.6 <=8.8 <=11 <=13.2 <=15.4 <=17.6 <=19.8 mph mph mmph p mph mph mph mph mph A 2.5E-10 1.3E-10 8.3E-11 6.3E-11 5.0E-1 1 4.2E-1 1 3.6E-1 1 3.1 E-11 2.8E-11 2.5E-1 1 B 1.2E-09 6.0E-10 4.0E-10 3.0E-10 2.4E-10 2.0E-10 1.7E-10 1.5E-10 1.3E-10 1.2E-10 C 3.5E-09 1.8E-09 1.2E-09 8.8E-10 7.0E-10 5.8E-10 5.0E-10 4.42-10 3.9E-10 3.5E-10 D 1.0E-08 5.0E-09 3.3E-09 2.5E-09 2.OE-09 1.7E-09 1.4E-09 1.3E-09 1.1E-09 1.OE-09 E 1.7E-08 8.5E-09 5.7E-09 4.3E-09 3.4E-09 2.8E-09 2.4E-09 2.1 E-09 1.9E-09 1.7E-09 F 3.3E-08 1.7E-08 1.1E-08 8.3E-09 6.6E-09 5.5E-09 4.7E-09 4.1 E-09 3.7E-09 3.3E-09 G 7.0E-08 3.5E-08 2.3E-08 1.82-08 1.4E-08 1.2E-08 1.OE-08 8.8E-09 7.8E-09 7.0E-09 5 Mile Tritium TEDE Factors Stability <2.2 >2.2 >4.4 >6.6 >8.8 >11 >13.2 >15.4 >17.6 >19.8 Class mph <=4.4 <=6.6 <=8.8 <=11 <=13.2 <=15.4 <=17.6 <=19.8 mph mph mph mph mph mph mph mph mph A 4.0E-11 2.0E-11 1.3E-11 1.0E-11 8.OE-12 6.7E-12 5.7E-12 5.0E-12 4.4E-12 4.OE-12 B 5.0E-11 2.5E-11 1.7E-11 1.3E-11 1.0E-11 8.3E-12 7.1E-12 6.3E-12 5.6E-12 5.0E-12 C 1.1E-10 5.5E-11 3.7E-11 2.8E-11 2.2E-11 1.8E-11 1.6E-11 1.4E-11 1.2E-11 1.1E-11 D 4.4E-10 2.2E-10 1.5E-10 1.1E-10 8.8E-11 7.3E-11 6.3E-11 5.5E-11 4.9E-11 4.4E-11 E 9.5E-10 4.8E-10 3.2E-10 2.4E-10 1.9E-10 1.6E-10 1.4E-10 1.2E-10 1.1E-10 9.5E-11 F 2.4E-09 1.2E-09 8.02-10 6.0E-10 4.8E-10 4.0E-10 3.4E-10 3.0E-10 2.7E-10 2.4E-10 G 5.5E-09 2.8E-09 1.8E-09 1.4E-09 1.1E-09 9.2E-10 7.9E-10 6.9E-10 6.1E-10 5.52-10 INOTE A duration of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> should be used when the release duration is unknown. l I

[9] OBTAIN and RECORD the estimated duration of the release in hours from the SM.

[10] CALCULATE the Tritium TEDE dose at .62 and 5 by multiplying the Tritium release rate x TEDE factor x Release duration = Tritium TEDE Dose.

Tritium TEDE DOSES Distance Tritium Tritium Release Tritium TEDE Release Rate TEDE Factor Duration Dose R+/-Ci/s - l hour(s) (REM) 0.62

[ 5.0 Prepared by:.

Date/Time:

PAGE 10 OF 30 REVISION 10

WBN INITIAL DOSE ASSESSMENT EPIP-13 FOR RADIOLOGICAL EMERGENCIES kd APPENDIX B - MANUAL ASSESSMENT OF MONITORED GASEOUS RELEASES (Page 3 of 8)

I NOTE Appendix J may be referred to during periods when the Meteorological data is unavailable.

[11] OBTAIN Stability Class from the MET DATA screen on ICS or from the SQN control room (843-7860) and CIRCLE the Stability Class in both tables below.

[12] IF the Stability Class cannot be obtained, THEN DETERMINE the stability class by subtracting the 10 meter from the 46 meter temperatures and CIRCLE the stability class in both tables below.

As-1.24 B-1.l1 to-1.23 C-.98to-1.10 D-.33to-.97 E .97to-.32 F2.59to.98 G22.6

[13] OBTAIN the wind speed in mph from the 46 meter height and CIRCLE the appropriate range for the wind speed in both tables below.

[14] CIRCLE the appropriate Noble Gas TEDE factors for each distance in the tables below based on the wind speed and stability class obtained in the above steps.

0.62 Miles Noble Gas TEDE Factors Stability <2.2 >2.2 >4.4 >6.6 >8.8 >11 >13.2 >15.4 >17.6 >19.8 Class mph <=4.4 <=6.6 <=8.8 <=11 <=13.2 <=15.4 <=17.6 <=19.8 mph mph mph mph mph mph mph mph mph . -

A 6.0E-10 3.0E-10 2.0E-10 1.5E-10 1.2E-10 1.OE-10 8.6E-11 7.5E-11 6.7E-11 6.OE-11 B 2.1 E-09 1.12-09 7.0E-10 5.3E-10 4.2E-10 3.5E-10 3.0E-10 2.6E-10 2.3E-10 2.1 E-10 C 4.6E-09 2.3E-09 1.5E-09 1.2E-09 9.2E-10 7.7E-10 6.6E-1 0 5.8E-10 5.1E-10 4.6E-10 D 9.5E-09 4.8E-09 3.2E-09 2.4E-09 1.9E-09 1.6E-09 1.4E-09 1.2E-09 1.1 E-09 9.5E-10 E 1.4E-08 7.0E-09 4.7E-09 3.5E-09 2.8E-09 2.3E-09 2.0E-09 1.8E-09 1.6E-09 1.4E-09 F 2.12-08 1.1E-08 7.0E-09 5.3E-09 4.2E-09 3.5E-09 3.0E-09 2.6E-09 2.3E-09 2.1E-09 G 3.5E-08 1.8E-08 1.2E-08 8.8E-09 7.0E-09 5.8E-09 5.0E-09 4.4E-09 3.92-09 3.5E-09 5 Miles Noble Gas TEDE Factors Stability <2.2 >2.2 >4.4 >6.6 >8.8 >11 >13.2 >15.4 >17.6 >19.8 Class mph <=4.4 <=6.6 <=8.8 <=11 <=13.2 <=15.4 <=17.6 <=19.8 mph mph mph mph mph mph mph mph mph A 9.5E-11 4.8E-11 3.2E-11 2.4E-11 1.9E-11 1.6E-11 1.4E-11 1.2E-11 1.1E-11 9.5E-12 B 1.5E-10 7.5E-11 5.0E-11 3.8E-11 3.0E-11 2.5E-11 2.1 E-11 1.9E-11 1.7E-11 1.5E-11 C 2.8E-10 1.4E-10 9.3E-11 7.0E-11 5.6E-11 4.7E-11 4.0E-11 3.5E-11 3.1E-11 2.8E-11 D 9.5E-10 4.8E-10 3.2E-10 2.4E-10 1.9E-10 1.6E-10 1.4E-10 1.2E-10 1.1E-10 9.5E-11 E 1.8E-09 9.0E-10 6.0E-10 4.5E-10 3.6E-10 3.0E-10 2.6E-10 2.3E-10 2.0E-10 1.8E-10 F 3.5E-09 1.82-09 1.2E-09 8.8E-10 7.0E-10 5.8E-10 5.0E-10 4.42-10 3.9E-10 3.5E-10 G 6.5E-09 3.3E-09 2.2E-09 1.62-09 1.3E-09 1.12-09 9.32-10 8.1E-10 7.2E-10 6.5E-10 PAGE 11 OF 30 REVISION 10

WBN INITIAL DOSE ASSESSMENT l FOR RADIOLOGICAL EMERGENCIES E 3

<_J APPENDIX B - MANUAL ASSESSMENT OF MONITORED GASEOUS RELEASES (Page 4 of 8)

LNOTE RCS fuel damage should be used when the fuel damage is unknown. I

[15] DETERMINE and CIRCLE the TEDE ratio based on the release path and type of fuel damage for both 0.62 and 5 mile distances using the table below.

I NOTE The SM may be able to assist in determining the release paths and type of fuel damage. I Release Paths Containment leak filtered Containment leak unfiltered or SGTR below the water Turbine, Reactor, or Auxiliary Building SGTR above the water Tvye of Fuel Damage Normal reactor coolant system Fuel clad gap Core damage (fuel over temp)

Fuel melt 0.62 Mile TEDE Ratios RCS Gap Core Fuel Damage Melt CNTMT (filtered) 3.7 1.0 0.9 1.0 CNTMT (unfiltered) or SGTR (below) 7.4 9.0 5.3 11 Turbine, Reactor, or Auxiliary Building 17 32 16 37 SGTR (above) 95 221 111 263 5 Miles TEDE Ratios RCS Gap Core Fuel Damage Melt CNTMT (filtered) 1.8 1.0 1.0 1.0 CNTMT (unfiltered) or SGTR (below) 3.5 4.9 2.9 5.8 Turbine, Reactor, or Auxiliary Building 7.4 15 7.9 17 SGTR (above) 43 100 51 116

[16] IF ICS is unavailable, THEN NOTIFY the SM that Appendix D must be performed by RADCON/Chemistry personnel in TSC.

[17] IF Radiation Monitor data is unavailable or the release is not monitored, THEN use Appendix C to determine the noble gas release rate.

PAGE 12 OF 30 REVISION 10

WBN INITIAL DOSE ASSESSMENT FOR RADIOLOGICAL EMERGENCIES E 3 K.) APPENDIX B - MANUAL ASSESSMENT OF MONITORED GASEOUS RELEASES (Page 5 of 8)

[18] COMPLETE the following NG TEDE Dose table for both 0.62 and 5 mile as follows:

[a] OBTAIN and RECORD the Noble Gas release rate from ICS EFF1 or appropriate appendix.

[bJ RECORD the NG TEDE Factors determined in step [14].

[c] RECORD the TEDE Ratios determined in step [15].

NOTE A duration of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> should be used when the release duration is unknown.

[d] OBTAIN and RECORD the estimated duration of the release in hours from the SM or if the release is unmonitored use release duration associated with accident type from Appendix C.

[e] CALCULATE the TEDE dose at .62 and 5 by multiplying the NG release rate x TEDE Factorx TEDE Ratio x Release Duration = NG TEDE Dose.

Noble Gas TEDE DOSES Distance Noble Gas Noble Gas TEDE Ratio Release Noble Gas Release Rate TEDE Factor Duration TEDE Dose x _ Ci/s hour(s) (REM) 0.62 5.0

[19] COMPLETE the following Total TEDE Dose table for both 0.62 and 5 mile as follows:

[a] OBTAIN and RECORD the tritium TEDE Dose (REM).

[b] OBTAIN and RECORD the noble gas TEDE Dose (REM).

[qJ ADD the Tritium and Noble Gaseous TEDE Doses.

TOTAL TEDE DOSES Distance Tritium TEDE Noble Gas Total Dose TEDE Dose TEDE (REM) (REM) (REM) 0.62 5.0 Prepared by:

Date/Time:-

PAGE 13 OF 30 REVISION 10

WBN INITIAL DOSE ASSESSMENT FOR RADIOLOGICAL EMERGENCIES E K\> APPENDIX B - MANUAL ASSESSMENT OF MONITORED GASEOUS RELEASES (Page 6 of 8)

I NOTE Appendix J may be referred to during periods when the Meteorological data is unavailable. I 120] OBTAIN Stability Class from the MET DATA screen on ICS or from the SON control room (843-7860) and CIRCLE the Stability Class in both tables below.

[21] IF the Stability Class cannot be obtained, THEN DETERMINE the stability class by subtracting the 10 meter from the 46 meter temperatures and CIRCLE the stability class in both tables below.

A*-i.24 B -1.1 1to -1.23 C:-.98 to -1.1 0 D. .33to-.97 E .971to -.32 F 2.59 to .98 G 22.6 122] OBTAIN the wind speed in mph from the 46 meter height and CIRCLE the appropriate range for the wind speed in both tables below.

[23] CIRCLE the appropriate CDE Factors for each distance in the tables below based on the wind speed and stability class obtained in the above steps.

0.62 Miles CDE Factors Stability <2.2 >2.2 >4.4 >6.6 >8.8 >11 >13.2 >15.4 >17.6 >19.8 Class mph <=4.4 <=6.6 <=8.8 <=11 <=13.2 <=15.4 <=17.6 <=19.8 mph mph mph mph mph mph mph mph mph A 1.2E-05 6.0E-06 4.0E-06 3.0E-06 2.4E-06 2.0E-06 1.7E-06 1.5E-06 1.3E-06 1.2E-06 B 5.8E-05 2.9E-05 1.9E-05 1.5E-05 1.2E-05 9.7E-06 8.3E-06 7.3E-06 6.4E-06 5.8E-06 C 1.7E-04 8.5E-05 5.7E-05 4.3E-05 3.4E-05 2.8E-05 2.4E-05 2.1 E-05 1.9E-05 1.7E-05 D 4.8E-04 2.4E-04 1.6E-04 1.2E-04 9.6E-05 8.0E-05 6.9E-05 6.0E-05 5.3E-05 4.8E-05 E 8.3E-04 4.2E-04 2.8E-04 2.1E-04 1.7E-04 1.4E-04 1.2E-04 1.OE-04 9.2E-05 8.3E-05 F 1.6E-03 8.0E-04 5.3E-04 4.0E-04 3.2E-04 2.7E-04 2.3E-04 2.OE-04 1.8E-04 1.6E-04 G 3.5E-03 1.8E-03 1.2E-03 8.8E-04 7.OE-04 5.8E-04 5.0E-04 4.4E-04 3.9E-04 3.5E-04 5 Miles CDE Factors Stability <2.2 >2.2 >4.4 >6.6 >8.8 >11 >13.2 >15.4 >17.6 >19.8 Class mph <=4.4 <=6.6 <=8.8 <=11 <=13.2 <=15.4 <=17.6 <=19.8 mph mph mph mph mph mph mph mph mph ___

A 2.OE-06 1.OE-06 6.7E-07 5.0E-07 4.OE-07 3.3E-07 2.9E-07 2.5E-07 2.2E-07 2.OE-07 B 2.5E-06 1.3E-06 8.3E-07 6.3E-07 5.0E-07 4.2E-07 3.6E-07 3.1 E-07 2.8E-07 2.5E-07 C 5.OE-06 2.5E-06 1.7E-06 1.3E-06 1.0E-06 8.3E-07 7.1 E-07 6.32-07 5.6E-07 5.0E-07 D 2.2E-05 1.1E-05 7.3E-06 5.5E-06 4.4E-06 3.7E-06 3.1 E-06 2.8E-06 2.4E-06 2.2E-06 E 4.7E-05 2.4E-05 1.6E-05 1.2E-05 9.4E-06 7.8E-06 6.7E-06 5.9E-06 5.2E-06 4.7E-06 F 1.2E-04 6.0E-05 4.0E-05 I3.0E-05 I2.4E-05 I2.0E-05 1.7E-05 1.5E-05 I1.3E-05 1.2E-05 G 2.7E-04 1.4E-04 I 9.0E-05 6.8E-05 5.4E-05 I 4.5E-05 I 3.9E-05 3A4-05 3.OE-05 2.7E-05 PAGE 14 OF 30 REVISION 10

WBN INITIAL DOSE ASSESSMENT EPIP 3 FOR RADIOLOGICAL EMERGENCIES E 3 Kj APPENDIX B - MANUAL ASSESSMENT OF MONITORED GASEOUS RELEASES (Page 7 of 8)

NOTE I RCS fuel damage should be used when the fuel damage is unknown.

NOTE 2 The SM may be able to assist in determining the release paths and type of fuel damage.

[24] DETERMINE and CIRCLE the Iodine to Noble Gas ratio based on the release path and type of fuel damage using the table below.

Release Paths Containment leak filtered Containment leak -ufiltered or SGTR below the water Turbine, Reactor, or Auxiliary Building SGTR above the water Tvpe of Fuel Damage Normal reactor coolant system Fuel clad gap Core damage (fuel over temp)

Fuel melt Iodine to NG Ratios RCS Gap Core Fuel Damage Melt CNTMT (filtered) 1.7E-06 3.OE-05 1.2E-05 2.2E-05 CNTMT (unfiltered) or SGTR (below) 1.7E-04 3.OE-03 1.2E-03 2.2E-03 Turbine, Reactor, or Auxiliary Building 5.8E-04 1.0E-02 4.1E-03 7.7E-03 SGTR (above) 4.2E-03 8.OE-02 3.0E-02 5.5E-02

[25] IF ICS is unavailable, THEN NOTIFY the SM that Appendix D must be performed by RADCON/Chemistry personnel in TSC.

[26] IF Radiation monitor data is unavailable or the release is not monitored, THEN Use Appendix C to determine the noble gas release rate.

PAGE 15 OF 30 REVISION 10

WBN INITIAL DOSE ASSESSMENT EPIP-1 3 FOR RADIOLOGICAL EMERGENCIES K-j APPENDIX B - MANUAL ASSESSMENT OF MONITORED GASEOUS RELEASES (Page 8 of 8)

[24] COMPLETE the following CDE Dose table for both 0.62 and 5 mile as follows:

[a] OBTAIN and RECORD the Noble Gas release rate from [CS EFF1 or appropriate appendix.

[b] RECORD the CDE Factors determined in step [23].

[c] RECORD the Iodine to NG Ratios determined in step [24].

INOTE A duration of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> should be used when the release duration is unknown. I

[d] OBTAIN and RECORD the estimated duration of the release in hours from the SM or if the release is unmonitored use release duration associated with accident type from Appendix C.

[e] CALCULATE the CDE dose at .62 and 5 by multiplying the NG Release Rate x CDE Factor x Iodine to NG Ratio x Release Duration = CDE Dose.

CDE DOSES Distance Noble Gas CDE Factor Iodine to NG Release CDE Dose Release Rate Ratio Duration (REM)

_Ci/s hour(s) 0.62 5.0 1 Prepared by:

Date/Time:_

PAGE 16 OF 30 REVISION 10

WBN INITIAL DOSE ASSESSMENT EPIP 13 FOR RADIOLOGICAL EMERGENCIES E-APPENDIX C - UNMONITORED RELEASES BASED ON ACCIDENT TYPES (Page 1 of 1)

Summary of Accident Types Duration of the Noble Gas Release Release (Consult with SM to determine the Accident type to use.) Rates (Hours) PCi/s LOCA - 100% Fuel Melt(>1200F) RCS Containment Tech Spec allowed leakage (0.25%/24 hours) 24 1.1 6E+07 Containment Failure(100%/4 hours) 4 2.79E+1O0 LOCA - 100% Gap Activity RCS l l _l Containment Tech Spec allowed leakage(0.25%/24 hours) 24 6.34E+03 Containment Failure(1 00%14 hours) 4 1.52E+07 LOCA - Normal RCS Containment Tech Spec allowed leakage(0.25%/24 hours) 24 3.40E+01 Containment Failure(100%14 hours) 4 8.15E+04 SG Tube Rupture 0-2 hours after the beginning of the release 2 3.87E+06 2-8 hours after the beginning of the release 6 2.14E+00 Fuel Handling - One Bundle Damaged l l Accident inside Containment with Purge fans on 2 1.89E+05 Accident outside Containment with ABGTS on 0.25 1.51 E+06 l Waste Gas Decay Tank Rupture l l _ _

lReg. guide 1.24 analysis I 2.09E+07 PAGE 17 OF 30 REVISION 10

l WBN INITIAL DOSE ASSESSMENT EPIP 3 l l FOR RADIOLOGICAL EMERGENCIES E 3 APPENDIX D - NOBLE GAS RELEASE RATE EVALUATION (Page 1 of 2)

NOTE 1: If ICS is not functional and time is not available due to the ongoing emergency event, wait for the TSC to activate prior to proceeding in this appendix. _

NOTE 2: In columns A and B of this Appendix, the radiation monitor and panel number, along with the ICS or Eberline computer oints necessary to obtain the data, are listed.

Monitors indicating "offscaleH (>10 cpm for monitors on panels 1 or 2-M-30) should be indicated as such.

[1] OBTAIN and RECORD the noble gas monitor readings on page 2 of this Appendix.

NOTE: Flow rates that are less than the minimum value indicated should be reported as the minimum value.

[2] RECORD the effluent flow rate(s) on page 2 of this Appendix.

[3] IF flow instrumentation is inoperable, THEN OBTAIN flow estimates using Appendix H.

)[4] CALCULATE the noble gas release rates on page 2 of this Appendix.

[5] SUM the noble gas release rates, AND RECORD the gaseous noble gas release rate total on page 2 of this Appendix.

[6] TRANSFER the gaseous noble gas release rate to Appendix G.

PAGE 18 OF 30 REVISION 10

WBN INITIAL DOSE ASSESSMENT EPIP 13 FOR RADIOLOGICAL EMERGENCIES APPENDIX D - NOBLE GAS RELEASE RATE EVALUATION (Page 2 of 2)

Monitor Noble Gas Release Point Effluent Noble Gas Effluent Flow Conversion Release Rate Monitor Read Monitor Reading Rate Factor (giCi/s) DatelTime (cfm)

A B C D =AxBxC __

cpm 1.82E-05' Aux Bldg. Vent O-RM-90-101B O-PNL-90-L39733 (O-M-12) R0020A F2704A (Min.141,000 cfm) cpm 1.82E-05' Service Building Vent 0-RM-90-132B O-PNL-90-L399 3 .

(O-M-12) R0011A F2702A (Min.3,000 cfm) 4722 U1 Shield Building Vent UCi/cc 1-FI-90-400 Us (1-M-30) 1-RI-90-400 (1-M-9) 1-RI-90-400 /

(EFF) 1-PNL-90-L398 (Low, Mid, High)

Y2203A R9101A (Min.3300 cfm) 4722 uCi/s U2 Shield Building Vent jiCi/cc 2-FI-90-400 (2-M- 2-RI-90-400 /

(2-M-30) 2-RI-90-400 9) (Low, Mid, High)

(EFF) 2-PNL-90-L398 R9102A F9015A (Min.3300 cfm)

U1 Condenser Vacuum cpm 1.82E-051 Exhaust (CVE) 1-RM-9D-119 1-FE-2-256 I_

(0-M-12) R0001A (low mg) F2700A (Min.21 cfm) _-

NOTE: If 1-RM-90-119 Is onscale, stop here. If monitor Is offscale, p oceed to next row.

U1 Condenser Vacuum Exhaust (CVE)

(1-M-31)

IE1-RM-902450 cpm (Data) Channel 13-01 F-2-56 F2700A From table below I R9061A (Min.21 cfm)

NOTE: If Channel 13.01 Is onscale, stop here. If monitor Is offscale, proceed to next row U1 Condenser cpm From table Vacuum Exhaust (CVE) 1-RM-90-450 -FE2-2-563 below I (1-M-31) (Data) Channel 13-03 F2700A R9062A (Min.21 cfm)

Total CVE Accident Monitor Calibration Factors x 472 cclslcfm for Various Times (T) Post-Accident T = Hours I T0 T=1 I T=8 I T16 T=24 I T=48 T=168 1-RM-90-450 (Channel 13-01) 5.48E-04 1.04E-03 2.75E-03 4.77E-03 1.60E-02 I1.23E-02 1.81 E-02 I-RM-90-450 (Channel 13-03) I 9.44E-01 I 2.02 I 5.33 I 9.16 I 1.23E+01 12.23E+01 I 3.14E+01 I The monitor Xe-1 33 efficiency multiplied by a conversion factor (472 cc/s/scfm).

2 Conversion factor of 472 cc/s/scfm.

3 No MCR indication (local indication only)

PAGE 19 OF 30 REVISION 10

WBN INITIAL DOSE ASSESSMENT FOR RADIOLOGICAL EMERGENCIES APPENDIX E - STEAM LINE RELEASE EVALUATION (Page 1 of 2)

[1] OBTAIN and RECORD the steam line radiation monitor readings on page 2 of this Appendix.

[2] DETERMINE and CIRCLE the appropriate calibration factor listed on page 2 of this Appendix AND RECORD the value on page 2 of this Appendix.

[NOTE Engineering may be consulted to determine the best estimate of steam flow during O periods when ICS steam flow is unavailable.

[3] OBTAIN and RECORD the steam mass flow rates on page 2 of this Appendix.

[4] CALCULATE the steam line release rates on page 2 of this Appendix.

[5] SUM the release rates for the steam lines, and RECORD the total steam line noble gas release rate on page 2 of this Appendix.

[6] TRANSFER the steam line noble gas release rate to Appendix G.

PAGE 20 OF 30 REVISION 10

WBN INITIAL DOSE ASSESSMENT FOR RADIOLOGICAL EMERGENCIES EI-APPENDIX E - STEAM LINE RELEASE EVALUATION (Page 2 of 2)

Steam Line Radiation Calibration Factor Steam Mass Conversion Release Monitor Reading (from table below) Flow Rate' Factor 2 Rate (mR/hr) (gCi/cc per mRlhr) (Ibm/hr) _ ( Cils)

A B C D AxBxCxD Steam Generator RM-90-4218 (1-M-30) 4.45 1 RR-90-268 Pt.01 (1-M-31)

R9055A Steam Generator RM-90-422B (1-M-30) 4.45 2 RR-90-268 Pt.02 (1-M-31)

R9056A Steam Generator 3 RM-90-423B (1-M-30) 4.45 RR-90-268 Pt.03 (1-M-31)

R9057A Steam Generator 4 RM-90-424B (1-M-30) 4.45 RR-90-268 Pt.04 (1-M-31)

R9058A Auxiliary . .

Feedwater Pump 4.45 Turbine RM-90-421B (1-M-30) or RM-90-424B (1-M-30)

Total 1 This data is an internal ICS calculation.

2 4.45 = [cc(steam)I0.0283 g] x g/2.205E-3 Ibm x hr13600 sec Main Steam Line Radiation Monitor Calibration Factors (CF)

Time After Shutdown Normal Spectrum Monitor DBA Spectrum Monitor Reading (hrs) Reading < 1000 mR/hr > 1000 mR/hr or Suspected Fuel

(,uCi/cc per mR/hr) Damage (g+/-Ci/cc per mRlhr) 0 3.OOE-3 9.88E-5 1 5.13E-3 7.79E-4 2 6.11 E-3 5.41 E-3 4 7.76E-3 6.86E-3 8 1.09E-2 9.63E-3 PAGE 21 OF 30 REVISION 10

WBN INITIAL DOSE ASSESSMENT FOR RADIOLOGICAL EMERGENCIES EPIP-1 3 APPENDIX F - USE OF GRAB SAMPLES FOR GASEOUS EFFLUENT EVALUATION (Page 1 of 2)

[1] IF sampling analysis is required to determine the site release rates, THEN REQUEST noble gas samples be obtained from applicable release points that have flow.

[2] RECORD sample date(s) and time(s) for applicable release point(s) on page 2 of this Appendix.

NOTE 1: Flow rates that are less than the minimum value indicated should be reported as the l minimum value.

NOTE 2: Operations may be required to obtain flowrate for 1-FE-2-256, Condenser Vacuum Exhaust.

[3] RECORD the effluent flow rate(s) on page 2 of this Appendix.

[4] IF flow instrumentation is inoperable, THEN OBTAIN flow estimates using Appendix H.

[5] RECORD the total noble gas concentration for applicable release point(s) on page 2 of this Appendix.

[6] CALCULATE the total noble gas release rate as indicated on page 2 of this Appendix

[7] SUM the noble gas release rates, AND RECORD the total gaseous noble gas release rate on page 2 of this Appendix.

[8] TRANSFER the gaseous noble gas release rate to Appendix G.

PAGE 22 OF 30 REVISION 10

WBN INITIAL DOSE ASSESSMENT EPIP-1 3 lFOR RADIOLOGICAL EMERGENCIES KJ APPENDIX F - USE OF GRAB SAMPLES FOR GASEOUS EFFLUENT EVALUATION (Page 2 of 2)

Noble Gas Total Noble Gas Total Noble Gas Release Point Sample Date/Time Flow Rates Concentration Release Rate cfm (RCi/cc) (4cifs)

A B C' D=AxBxC Auxiliary Building / 472 0-PNL-90-L397 EL 786, A8-V (Min.141,000 cfm)

Service Building / 472 0-PNL-90-L399 SN EL 751, S-5 (Min. 3000 cfm)

U1 Shield Building / 472 1-FI-90400 I-PNL-90-L398 EL 729, AE-5 (Min. 3,300 cfm)

U2 Shield Building I 472 2-FI-90-400 2-PNL-90-L398 EL 727, AE-1 I (Min. 3,300 cfm)

Condenser Vacuum / . 472 Exhaust (Min.21 cfm)

Total I Conversion factor: 472 cc/s/scfm.

Performed by: Date:

PAGE 23 OF 30 REVISION 10

WBN INITIAL DOSE ASSESSMENT EPIP 3 FOR RADIOLOGICAL EMERGENCIES E 3 APPENDIX G - TOTAL SITE NOBLE GAS RELEASE RATE (Page 1 of 1)

[1] SUM the values listed below to obtain the total site noble gas release rate.

[2] IF the CECC needs long term dose assessment THEN COMPLETE and TRANSMIT Appendix 1.

Total Site Noble Gas Release Rate Gaseous Noble Gas Release Rate l_pCi/s Steam Line and/or Auxiliary Feedwater Pump Turbine Noble Gas _pCi/s Release Rate Total Site Noble Gas Release Rate ~Li/s Performned by Date PAGE 24 OF 30 REVISION 10

WBN INITIAL DOSE ASSESSMENT FOR RADIOLOGICAL EMERGENCIES E 3 APPENDIX H - FLOW ESTIMATES (Page 1 of 1)

I NOTE: These values will be conservative.

[1] IF ventilation flow data is not readily obtainable, THEN the maximum values in cfm from Appendix C of the REP or from DBA analysis (shown in parentheses below) may be used in the Total Flow Rate Column below.

Shield Building - Unit I (If 1-FI-90-400 [1-M-9] and 1-PNL-90-L398 are inoperable)

Containment Purge air flow (Record 14,000 per operating fan) cfm EGTS air flow (Record 8,000 if operating) cfm ABGTS Fan A-A in operation. (Record 9,900 if operating) cfm PASF Ventilation (Record 2200 if operating) cfm Total cfm (Max. 48,100)

I Shield Building - Unit 2 (If 2-FI-90-400 [2-M-9] and 2-PNL-90-L398 are inoperable) l K- )ABGTS Fan B-B in operation I (Record 9,900 if operating) cfm (Max. 9,900)

Auxiliary Building (If O-PNL-90-L397 [no MCR indication] is inoperable)

Number of Auxiliary Building Exhaust Fans Operating x 84,000 [1-M-9] cfm Number of Fuel Handling Area Exhaust Fans Operating x 60,000 [1-M-9] cfm Total cfm (Max. 228,000)l Condenser Vacuum Exhaust - Unit I (If I-FE-2-256 [no MCR indication] is inoperable)

Obtain an estimate from Operations personnel (rotometer on pump) I cfm (Max. 100)

Service Building Exhaust (If O-PNL-L399 [no MCR indication] is inoperable)

Enter 10,500 SCFM for Service Building Exhaust cfm (Max. 10,500)

PAGE 25 OF 30 REVISION 10

WBN INITIAL DOSE ASSESSMENT EPIP-133 FOR RADIOLOGICAL EMERGENCIES APPENDIX I - CECC LONG TERM DOSE ASSESSMENT (Page 1 of 1)

Iodine and Particulate Release Concentrations

[1] IF site iodine and particulate concentrations are required, THEN REQUEST Chem Lab to obtain samples from applicable release points.

[2] RECORD the applicable information in the table below.

[3] COMPLETE and TRANSMIT Appendix I to the CECC.

1-131 Particulate Release Flow Rate (cfm) Concentration Concentration Point A(pCi/cc) (gCi/cc)

_ _ _ _A B C Auxiliary Building Service Building U1 Shield Buildingc U2 Shield Building .

Condenser Vacuum Exhaust Total Iodine and Particulate Release Fractions Noble Gas 1-131 Release I-1 31 Fraction Particulate Particulate Release Rate Rate Release Rate Fraction

(+/-'Ci/s) (1) (pCi/s) (eCis)

D E=A* B*472 E/D F=A* C*472 F/D (1)From App. B or App. G Performed by: Date:

PAGE 26 OF 30 REVISION 10

WBN INITIAL DOSE ASSESSMENT EPIP 13 FOR RADIOLOGICAL EMERGENCIES - 3 APPENDIX J - LOSS OF METEOROLOGICAL DATA (Page 1 of 4) 1.0 PURPOSE This Appendix provides instructions to ensure appropriate actions are taken by the Shift Manager (SM) for Main Control Room outages of onsite meteorological data.

2.0 RESPONSIBILITY Daily meteorological channel checks are performed by the SM to verify operability.

If an outage is detected, the SM shall take necessary actions to check backup displays, track the outage, and to initiate repair request.

Emergency Planning (EP) Field Support is responsible for operating the meteorological data system and for making the data signal available to the plant.

3.0 MINIMUM REQUIREMENTS A. The Offsite Dose Calculation Manual (ODCM) requires that two of three wind speed channels, two of three wind direction channels, and one of three air temperature differences be operable at all times to support estimation of routine and accident doses. A special report to the NRC is to be prepared for outages of more than seven (7) days.

B. Emergency action level event (5.2 tornado) and protective action decision making of the Radiological Emergency Plan (REP) require use of meteorological data.

C. R.G. 1.23 "Onsite Meteorological Programs" and ANSI/ANS Standard 3.11-2000 "Determining Meteorological Information at Nuclear Facilities" require a 90 percent annual joint data recovery rate of valid wind speed, wind direction and temperature difference.

PAGE 27 OF 30 REVISION 10

WBN INITIAL DOSE ASSESSMENT EPIP 3 FOR RADIOLOGICAL EMERGENCIES E 3 APPENDIX J (Page 2 of 4)

LOSS OF METEOROLOGICAL DATA NOTE l&C should be contacted to fix any problem associated with the ICS display.

[1] IF Met data is unavailable in the Main Control Room or from the ICS Terminals in the TSC and OSC (METDATA), THEN OBTAIN Met Data from the MET Tower using the CECC computer terminal in the TSC per Appendix J (page 3 of 4) of this Procedure.

[2] IF the minimum required data listed in Section 3.0 is not available from these methods, THEN DECLARE the system inoperable and begin appropriate tracking, AND NOTIFY EP Field Support (normal business hours or next working day, whichever is applicable) at x8450.

[3] IF specific Met data is still needed (i.e., EPIP-1, emergency action levels), THEN the remaining steps for obtaining data should be used in the following order:

[a] CALL the SQN Control Room (843-7860) and request the needed meteorological information.

[b] REQUEST the Operations Duty Specialist (ODS) to page the duty CECC Meteorologist. The CECC Meteorologist has backup procedures to estimate missing data using established relationships between onsite data and other sources of data.

NOTE This information obtained in step [c] will be from the 10 meter elevation but is still usable.

[c] CALL the Morristown National Weather Service at 9-1-(423)-586-8400and REQUEST the wind speed and wind direction.

[4] DOCUMENT the closure of any tracking initiated, AFTER notification that the Met Tower outage is completed.

PAGE 28 OF 30 REVISION 10

WBN INITIAL DOSE ASSESSMENT EPIP-1 3 FOR RADIOLOGICAL EMERGENCIES APPENDIX J (Page 3 of 4)

TSC CECC COMPUTER AND PRINTER USE

[1] ENSURE computer terminal is energized (switch is located in front). 1

[2] PRESS the "Return" key twice (repeat step if necessary). a3

[3] TYPE "WBMET' at the "Username" prompt AND PRESS "Return". 3 NOTE The printer will print the MET data and log off the computer.

[4] TYPE 'TSC" at the "Password" prompt AND PRESS "Return". D

[5] REPEAT step 2 through 4 for additional MET data as needed.

PAGE 29 OF 30 REVISION 10

WBN INITIAL DOSE ASSESSMENT EPIP-13 FOR RADIOLOGICAL EMERGENCIES I APPENDIX J (Page 4 of 4)

EXAMPLE REPORT WATTS BAR NUCLEAR PLANT METEORLOGICAL DATA DATE: 4-OCT-01 TIME: 11:30:48 (Central)

REF: 49 LOCATION: CECC COMPUTER DESCRIPTION INSTRUMENT TS LIMIT DATA (Last 15 min) 1Om Elevation Operable and 3.5 mph WIND SPEED 46m Elevation Channel Check 5.4 mph 91m Elevation 6.3 mph 1Om Elevation 233.7 deg WIND 46m Elevation 222.4 deg DIRECTION 91m Elevation 219.3 deg AIR 10 to 46m 1.1 F*

Delta T 10 to 91m 1.9 F*

46 to 91m 0.9 F*

To calculate Delta T, subtract the Lower elevation temperature value from the higher elevation temperature value (ex: (91m value) - (1lOm value)).

Performers Initials SROs Initials PAGE 30 OF 30 REVISION 10