Text

Revision 26 to EPIP-6, Activation & Operation of the Technical Support Center, and Revision 17 to EPIP-10, Medical Emergency Response.
	ML032550049
Person / Time
Site:	Watts Bar
Issue date:	09/05/2003
From:	Pace P; Tennessee Valley Authority
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML032550049 (113)
	v • d • e

_ I -

Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 SEP 5 2003 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) REVISION In accordance with the requirements of 10 CFR Part 50, Appendix E, Section V, the enclosure provides the EPIPs as listed below.

EPIP Rev Title Effective Date EPIP-6 26 Activation and Operation of 8-8-2003 the Technical Support Center EPIP-10 17 Medical Emergency Response 8-2 5-2 003 EPIP-13, Revision 9, "Initial Dose Assessment for Radiological Emergencies," was submitted to-NRC on July 2, 2003, in accordance with the requirements of 10 CFR 50, Appendix E, Section V. This EPIP is being reissued to correct typographical errors.

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

ly, P. 1A. Pace Manager, Site Licensing and Industry Affairs Enclosure Abq-5 cc: See Page 2

ZO~ ~ ~ ~~~ ~ ~ ~ ~ ~ - ~

U.S. Nuclear Regulatory Commission Page 2 SEP 0 5 2003 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

-4 FILING INSTRUCTIONS DOCUMENT NUMBER £P2R /;3 REMOVE REVISION INSERT REVISION -9 Fileinstr.doc

TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT EMERGENGY PLAN IMPLEMENTING PROCEDURE EPIP-1 3 INITIAL DOSE ASSESSMENT FOR RADIOLOGICAL EMERGENCIES Revision 9 Unit 0 PREPARED BY: James F. Hagy SPONSORING ORGANIZATION: Emergency Planning APPROVED BY: Frank L. Pavlechko Effective Date: 06/02/2003 LEVEL OF USE: REFERENCE NON-QUALITY RELATED

WBN INITIAL DOSEASSESSMENT EPIP-13 FOR RADIOLOGICAL EMERGENCIES REVISION LOG Revision Implementation Pages Description of Revision Number Date Affected 8 12/1612002 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 06/0212003 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.

PAGE 2 OF 26 REVISION 9

WBN INITIAL DOSE ASSESSMENTEPP 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 13 APPENDIX D - NOBLE GAS RELEASE RATE EVALUATION 14 APPENDIX E - STEAM LINE RELEASE EVALUATION 16 APPENDIX F - USE OF GRAB SAMPLES FOR GASEOUS EFFLUENT EVALUATION 18 APPENDIX G - TOTAL SITE NOBLE GAS RELEASE RATE 20 APPENDIX H - FLOW ESTIMATES 21 APPENDIX I - CECC LONG TERM DOSE ASSESSMENT 22 APPENDIX J - LOSS OF METEOROLOGICAL DATA 23 PAGE 3 OF 26 REVISION 9

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"

3. NUREG 1465, Accident Source Terms for Ught-Water Nuclear Power Plants X 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 ANSVANS-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 26 REVISION 9

WBN INITIAL DOSE ASSESSMENT FOR RADIOLOGICAL EMERGENCIES 2.3 Definitions/Acronyms 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., 1 REM TEDE, 5 REM Thyroid CDE).

REIRM 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.

XIQ: 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 26 REVISION 9

l WBN INITIAL DOSE ASSESSMENT EPIP-13 I I FOR RADIOLOGICAL EMERGENCIES l 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 SED/SM 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 CS 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 26 REVISION 9

WBN INITIALDOSE ASSESSMENT EPIP 3 FOR RADIOLOGICL EMERGENCIES -

APPENDIX A - "ICS"- DOSE ASSESSMENT (Page 1 of 1)

NOTE 1 Assessmentwind IJIETDATA, direction, and EFF1 information are also available from the Dose screen. See example of ICS Dose Assessment screen below.

IIt 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] RECALCULATE the Dose Assessment and print the worksheet.

[5] PROVIDE Dose Assessment information to the SM.

[61 IF ICS Dose Assessment is unavailable, THEN refer to the Appendix B of this procedure.

~~~W*~~~~~N~~~~OSEAS~~~~.. t$..5........... ....

,14-SEP-2001 14.041.39 -

,I _ _ Ai...u WBN' DOSE ASSESSWRET'

-DATE: '

TIME: -

1T :

.39.

INPUTS: VALUE UNITS QUALITY MET46A15 . EDS ETDATA 46M 15MIN AV8 WIND SPEED K-$$.1CM/HR fET46D15 * £0S ETDATA 46M 5MINAV WIND DIRECTION IffM OECGE IETSTCS2 .EDS .15MIN STABILITY CLASS. f O:

AD025 -ICS CALCULATED TOTAL NOBLE SAS RELEA.SE ME u./ 200D IODINE 0.016 ' TOTAL NO9LE lAS RELEASE RATE ijs4e uClFsM OUTPUT: HOURLY DOSE TEDE (Rem) THYROID CDE (Re.)

.1

...... .1. '.i..` .....

2L, oi',;

SITE BOUNDARY :.... .. ....

i% -.M 4 2 MILE: . I.. .-.11 5 MTLE: .4, 14 ., I

.., -,.-k ::7.., , tA R**'

PAGE 7 OF 26 REVISION 9

I WBN INITIAL DOSE ASSESSMENT rEPIP-13 FOR RADIOLOGICAL EMERGENCIES I EPIP-13 FIGURE A - SITE MAP (Page 1 of 1)

.11 PAGE 8 OF 26 REVISION 9

WBN I INITIAL DOSE ASSESSMENT FOR RADIOLOGICAL EMERGENCIES I EPIP-13 1 I I APPENDIX B - MANUAL ASSESSMENT OF MONITORED GASEOUS RELEASES (Page 1 of 4) pNOTE Appendix J may be referred to for additional help during periods when the Meteorological data is unavailable.

[1 OBTAIN Stability Class from the MET DATA screen on ICS or from the CECC 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<-1.24 B-1.11to-1.23 C-.98to-1.10 D-.33to-.97 E .97to-.32 F2.59to.98 G2 2.6

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

[4] CIRCLE the appropriate 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 TEDE Factors Stabilty >2.21 >4.4 >6.6 >8.8 >11 >13.2 >15.4 >17.6 >19.8 Class s2.21 s4.4 s6.6 S8.8 511 13.2 s15.4 517.6 s19.8 <22 nph mph mph mph mph mph mph mph mph mph A 1.6E-09 8.0E-10 6.4E-10 4.8E-10 3.2E-10 2.9E-10 2.5E-10 2.2E-10 1.9E-10 1.6E-10 B 7.5E-09 3.7E-09 3.OE-09 2.2E-09 1.4E-09 1.3E-09 1.2E-091 1.0E-09 8.9E-10 7.5E-10 C 2.2E-08 1.1 E-08 9.OE-09 6.7E-09 4.3E-09 3.9E-09 3.5E-09 3.OE-09 2.6E-09 2.2E-09 D 6.3E-08 3.2E-08 2.6E-08 1.9E-08 1.2E-08 1.1 E-08 1.OE-08 8.8E-09 7.5E-09 6.3E-09 E 1.1E-07 5.5E-08 4.4E-08 3.3E-08 2.2E-08 2.OE-08 1.8E-08 1.6E-08 1.3E-08 1.1 E-08 F 2.2E-07 I.OE-07 8.3E-08 6.3E-08 4.2E-08 3.8E-08 3.4E-08 3.OE-08 2.6E-08 2.2E-08 G 4.8E-07 2.3E-07 1.8E-07 1.4E-07 9.0E-08 8.1 E-08 7.2E-08 6.3E-08 5.4E-08 4.6E-08 5 Miles TEDE Factors Stabilt >2.21 >4.4 >6.6 >8.8 >11 >13.2 >16.4 >17.6 >19.8 Class s2.21 s4.4 s6.6 s8.8 s11 s13.2 S16.4 S17.6 S19.8 S22 mph mph mph mph mph mph mph mph mph A 7.5E-11 5.2E-11 5.2E-11 5.1E-11 5.1E-11 4.6E-11 4.OE-11 3.5E-11 3.OE-11 2.5E-11 8 9.9E-1 I 6.8E-1 I 6.7E-1 1 6.7E-1 I 6.6E-1 1 6.OE-11 5.3E-11 4.6E-11 4.OE-1 I 3.3E-11 C 1.9E-1 0 1.3E-1 0 1.3E-1 0 1.3E-1 0 1.3E-1 0 1.2E-1 0 1.1 E-1 0 9.3E-1 1 7.9E-1 1 6.5E-1 I D 8.3E-10 5.8E-10 5.7E-10 5.6E-10 5.6E-10 5.0E-10 4.5E-10 3.9E-10 3.4E-10 2.8E-10 1.SE-09 I 1.2E-09 I 1.2E-09 I 1.2E-09 I1.2E-09 I 1.1E-09 I9.BE-10 I 8.6E-10 7.3E-10 6.0E-10 F 4.6E-09 I 3.2E-09 3.IE-09 3.IE-09 I 3.OE-09 2.7E-09 2.4E-09 2.1E-09 1.8E-09 1.SE-09 1I G 1.1 E-08 7.5E-09 7.3E-09 7.2E-09 7.OE-09 6.3E-09 5.6E-09 4.9E-09 4.1 E-09 3.4E-09 PAGE 9 OF 26 REVISION 9

WBN INITIAL DOSE ASSESSMENT EPIP-13 FOR RADIOLOGICAL EMERGENCIES:

> APPENDIX B - MANUAL ASSESSMENT OF MONITORED GASEOUS RELEASES (Page 2 of 4)

NOTE TYPE I fuel damage should be used when the fuel damage Is unknown.

[51 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.

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

Release Paths Containment leak unfiltered or filtered SG Tube Rupture above or below the water CNTMT Bypass (e.g. RHR on shutdown cooling leaking in Aux. Bldg.)

Tvoe of Fuel Damace Type I Is normal reactor coolant Type 2 is fuel clad gap Type 3 is core damage (fuel over temp)

Type 4 is fuel melt 0.62 Miles TEDE Ratios

_ l~~Tpe Type 2 Type 3 lType 4 CNTMT (filtered) 0.5 1.0 1.0 1.2 X, CNTMT (unfiltered) or SGTR (below) 23 4.4 7.0 20 CNTMT Bypass 23 5.9 7.6 22 SGTR (above) 24 22 13 32 5 Miles TEDE Ratios Type Type 2 Type T3e4 CNTMT (filtered) 1.1 1.0 1.1 1.4 CNTMT (unfiltered) or SGTR (below) 55 9.1 16 49 CNTMT Bypass 55 13 17 52 SGTR (above) 58 48 29 75

[6] IF ICS is unavailable, THEN NOTIFY the SM that Appendix D must be performed by RADCONIChemistry personnel in TSC.

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

PAGE 10 OF 26 REVISION 9

WBN l INITIAL DOSE ASSESSMENT l P -1

. l WBN I FOR RADIOLOGICAL EMERGENCIES l l

\~Jo APPENDX B - MANUAL ASSESSMENT OF MONITORED GASEOUS RELEASES (page 3 of 4)

[8] COMPLETE the following TEDE 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 TEDE Factors determined in step [4].

[c) RECORD the TEDE Ratios determined in step [5].

INOTE A duration of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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.

[el CALCULATE the TEDE dose at .62 and 5 by multiplying the NG release rate x TEDE factor X TEDE ratio x Release duration = TEDE Dose.

TEDE DOSES Distance Noble Gas TEDE Factor . TEDE Ratio Release TEDE Dose Release Rate Duration (REM)

UCis hour(s) 0.62 5.0 PAGE 11 OF 26 REVISION 9

WBN INITIAL DOSE ASSESSMENT EPIP-1 3 FOR RADIOLOGICAL EMERGENCIES

\_APPENDIX B - MANUAL ASSESSMENT OF MONITORED GASEOUS RELEASES (Page 4 of 4)

I NOTE TYPE I fuel damage should be used when the fuel damage Is unknown. .1

[91 DETERMINE and CIRCLE the Thyroid CDE Ratio for the type of fuel damage and release path determined in step [51 in the table below.

Thyroid CDE Ratios I TypeI I Tpe2 Type3 Type4 CNTMT (filtered) 1.4E-02 1.1E-01 4.3E-02 7.2E-02 CNTMT (unfiltered) or SGTR (below) 3.3E-02 2.6E+00 6.4E-01 4.1E-01 CNTMT Bypass 1.1E-01 6.2E+00 2.OE+00 1.4E+00 SGTR (above) 7.8E-01 1.3E+01 8.3E+00 6.4E+00

[10] COMPLETE the following table as follows:

[a] RECORD the TEDE Dose in step [8].

[b) RECORD the Thyroid CDE Ratio in step [9].

[cJ CALCULATE the Thyroid CDE dose at 0.62 and 5 mile distance by multiplying the TEDE Dose x Thyroid CDEIrEDE Ratio.

Thyroid CDE Dose Distance TEDE Dose Thyroid/CDE Thyroid CDE 0.62___ (REM) Ratio (REM) 0.62 6.0

[111 PROVIDE this dose assessment to the SM as soon as possible. NG release rates may also used for event classification in EPIP-1.

Prepared by: Date: Time:

PAGE 12 OF 26 REVISION 9

WBN INITIAL DOSE ASSESSMENT FOR RADIOLOGICAL EMERGENCIES 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 I______________________________________________ _________(Hours) pCiIs LOCA - 100% Fuel Mett(>1200F) RCS Containment Tech Spec allowed leakage (0.25%124 hours) 24 1.16E+07 Containment Failure(1000/o/4 hours) 4 2.79E+1 0 LOCA - 100% Gap Activity RCS _

Containment Tech Spec allowed leakage(O.25%/24 hours) 24 6.34E+03 Containment Failure(100%14 hours) 4 1.52E+07 LOCA- Normal RCS X l Containment Tech Spec allowed leakage(O.25%/24 hours) 24 3.40E+01 Containment Failure(100%/4 hours) 4 8.15E+04 SG Tube Rupture l_

0-2 hours after the beginning of the release 2 3.87E+06 28 hours3.240741e-4 days 0.00778 hours 4.62963e-5 weeks 1.0654e-5 months after the beginning of the release 6 2.14E+00 Fuel Handling - One Bundle Damaged ccident inside Containment with Purge fans on 2 1.89E+05 Accident outside Containment with ABGTS on 0.25 1._ Eat6 Waste Gas Decay Tank Rupture _ I Reg. guide 1.24 analysis I j 2.09E+07 PAGE 13 OF 26 REVISION 9

WBN INITIALDOSE ASSESSMENT EPIP 3 l l ~FOR RADIOLOGICAL EMERGENCIES EP l1 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:ln columns A and B of this Appendix, the radiation monitor and panel number, along with the ICS or Ebedine computer points necessary to obtain the data, are listed. Monitors indicating uoffscale" (>106 cpm for monitors on panels 1 or 2-M-30) should be indicated as such.

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

INOTE:

t 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 14 OF 26 REVISION 9

FOR RADIOLOGICAL EMERGENCIES APPENDIX D - NOBLE GAS RELEASE RATE EVALUATION (Page 2 of 2)

-Monitor Noble Gas Release Point Effluent Noble Gas Effluent Flow Rate Conversion Release Rate Monitor Read' Monitor Reading (cfm) Factor (u+/-Cls) DatelTime A

____________ B C D AxBxC cpm 1.82E-05t Aux. Bldg. Vent 0-RM-90-IOIB O-PNL-90-L397 3 /

(0-M-12) R0020A F2704A (Min.141,000 cfm) cpm 1.82E-051 Service Building Vent 0-RM-90-132B 0-PNL-9o-L3993 /

(0-M-12) R0011A F2702A (Min.3,000 cfm) 4722 U1 Shield Building Vent u.Cicc 1-FI-90-400 uCi/s (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 jiCl/s U2 Shield Building Vent - uCicc 2-FI-90-400 (2M-9) 2-RI-90-400 /

(2-M30) 2-RI-90400 2-PNL-90-L396 (Low, Mid, High)

(EFF) F9015A R9102A

___________________ (M In.3300 cfm) _ i U1 Condenser Vacuum cpm 1.82E-05' Exhaust (CVE) 1-RM-90-119 1-FE-2-2/

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

NOTE: It *-RM-90-119 Is onscale, stop here. If monitor Is offscale, pr ceed to next row.

U1 Condenser Vacuum cpm From table Exhaust (CVE) 1-RM-90450 1-FE-2-256 below I (1-M-31) (Data) Channel 13-01 F2700A R9OS1A I (Min.21 cfm)

NOTE: If Channel 13-01 Is onscale, stop here. If onitor Is offscale, roceed to next rw U1 Condenser Vacuum _ cpm , From table Exhaust (CVE) 1-RM-90450 1-FE-2-2563 below (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 T=0 T=1 T=8 T=16 T=24 T=48 T=168 1-RM-90-450 (Channel 13-01) 5.48E-04 1.04E-03 2.75E-03 4.77E-03 I 1.60E-02 1.23E-02 1.81 E-02 1-RM-90450 (Channel 13-03 9.44E-01 2.02 5.33 9.16 1.23E+01 2.23E+01 3.14E+01 The monitor Xe4133 efficiency multiplied by a conversion factor (472 ccls/scfm).

\reConversion factor of 472 cc/slscfm.

3 No MCR indication (local indication only)

PAGE 15 OF 26 REVISION 9

WBN INITIAL DOSE ASSESSMENT EPIP-13 T l l FOR RADIOLOGICAL EMERGENCIESll APPENDIX E - STEAM LINE RELEASE EVALUATION (Page 1of 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 NOTE 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.

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

PAGE 16 OF 26 REVISION 9

WBN l INITIAL DOSE ASSESSMENT l P -1 FOR RADIOLOGICAL EMERGENCIES 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 Rates Factor2 Rate (mR/hr) (gClcc per mR/hr) (Ibm/hr) _ (cvs)

A B C D AxBxCxD Steam RM-9O-421B (1-M-30) 4.45 Generator I RR-90-268 Pt.01 (1-M-31)

R9055A Steam RM-90-422B (1-M-30) 4.45 Generator 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 4.45 Pump RM-90-421B (1-M-30) or Turbine RM-90-424B (1-M-30)

Total I This data is an internal ICS calculation.

2 4.45 = cc(steam)/0.0283 g] x g/2.205E-3 Ibm x hr/3600 see Main Steam Line Radiation Monitor Calibration Factors (CF) lime After Normal Spectrum Monitor DBA Spectrum Monitor Reading Shutdown (hrs) Reading < 1000 mR/hr > 1000 mR/hr or Suspected Fuel Damage (gCi/cc (gCicc per mR/hr) per mR/hr) 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 17 OF 26 REVISION 9

WBN INITIAL DOSE ASSESSMENTES FOR RADIOLOGICAL EMERGENCIES I PIP1 3 APPENDIX F - USE OF GRAB SAMPLES FOR GASEOUS EFFLUENT EVALUATION (Page 1 of 2)

[11 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 minimum value. I NOTE 2: Operations may be required to obtain flowrate for 1-FE-2-256, Condenser Vacuum

[3]

Exhaust.

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

I

[41 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 18 OF 26 REVISION 9

WBN INITIAL DOSE ASSESSMENT l EPIP-13 FOR RADIOLOGICAL EMERGENCIES l Q}g APPENDIX F - USE OF GRAB SAMPLES FOR GASEOUS EFFLUENT EVALUATION (Page 2 of 2)

Noble Gas Total Noble Gas Total Noble Release Point Sample Flow Rates Concentration Gas Release Date/Time cfm (gCilcc) Rate ( Cis)

A B C' DAxBxC 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)

UI Shield Building = 472 1-FI-90-400 1-PNL-90L398 EL 729, AE-5 (Min. 3,300 cfm)

U' field Building I _ 472 2-FI-90-400 2-PNL-90-L398 EL 727, AE-1 1 (Min. 3,300 cfm)

Condenser Vacuum / 472 Exhaust (Min.21 cfm)

Total 1 Conversion factor 472 cctslscfm.

Performed by: Date:

PAGE 19 OF 26 REVISION 9

I WBN I INITIAL DOSE ASSESSMENT FOR RADIOLOGICAL EMERGENCIES l I EPIP-1 3 I l

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.

[2J 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 1'Cis Steam Une and/or Auxiliary Feedwater Pump Turbine Noble Gas __ecus Release Rate Total Site Noble Gas Release Rate Ris Performed by Date PAGE 20 OF 26 REVISION 9

WBN INITIAL DOSE ASSESSMENT EPIP-13 FOR RADIOLOGICAL EMERGENCIESll APPENDIX H - FLOW ESTIMATES (Page 1 of 1)

NOTE: These values will be conservative.

11] 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 [I-M-9] and -PNL-90-L398 are inoperable)

Containment Purge air flow (Record 14,000 per operating fen) 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 (KMax.44,100) I I Shield Building - Unit 2 (If 2-FI-90-400 [2-M-9] and 2-PNL-90-L398 are inoperable) I

\9ABGTS Fan B-B in operation (Record 9,900 if operating) I cfm (Max. 9,900)

Auxiliary Building (if 0-PNL-90-L397 [no MCR Indication) is Inoperable)

Number of Auxiliary Building Exhaust Fans Operating x 84,000 11-M-9]1 I Number of Fuel Handling Area Exhaust Fans Operating x 60,000 [1-M-9] cfmI Total cfm (Max. 228,000) I Condenser Vacuum Exhaust - Unit 1 (If 1-FE-2-256 [no MCR Indication] is inoperable)

Obtain an estimate from Operations personnel (rotometer on pump) l cfm (Max. 100) I Service Building Exhaust (If O-PNL-L399 no MCR Indication] Is Inoperable)

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

PAGE 21 OF 26 REVISION 9

WBN INITIAL DOSE ASSESSMENT E-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.

13] COMPLETE and TRANSMIT Appendix I to the CECC.

1-131 Particulate Flow Rate (cfm) Concentration Concentration (RCVcc) (MCI/cc)

A B C Auxiliary Building Service Building U1 Shield Building U2 Shield Building _

Condenser Vacuum Exhaust Total Iodine and Particulate Release Fractions Noble Gas 1-131 Release 1-131 Fraction Particulate Particulate Release Rate Rate Release Rate Fraction (JLCiS) (1) (9Cl/s) (RCVs)

D E =A* B *472 E/D F=A C472 FID (1) From App. B or App. G Performed by: Date:

PAGE 22 OF 26 REVISION 9

l WBN INITIAL DOSE ASSESSMENT EPIP-13 FOR RADIOLOGICAL EMERGENCIESll 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 v 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 23 OF 26 REVISION 9

TV WBN

_ l INITIAL DOSEASSESSMENT FOR RADIOLOGICAL EMERGENCIES I EPlP-13 l a APPENDIX J (Page 2 of 4)

LOSS OF METEOROLOGICAL DATA NOTE I&C should be contacted to fix any problem associated vith 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.

[31 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 (843-7680) 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.

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

[c] CALL the Morristown National Weather Service at 9-1-(423)-586-8400 and 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 24 OF 26 REVISION 9

WBN INITIAL DOSE ASSESSMENT i EPIP-13

l l FOR RADIOLOGICAL EMERGENCIESll APPENDIX J (Page 3 of 4)

TSC CECC COMPUTER AND PRINTER USE

[1] ENSURE computer terminal is energized (switch is located in front). 3

[2] PRESS the "Return" key twice (repeat step if necessary). 3

[3] TYPE 'WBMET" at the "Usemame" prompt AND PRESS "Return". 0 NOTE The printer will print the MET data and log off the computer.

[4] TYPE 'TSC" at the "Password" prompt AND PRESS "Return". ;3

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

PAGE 25 OF 26 REVISION 9

WBN INITIAL DOSE ASSESSMENT EPIP-13 FOR RADIOL OGICAL EMERGENCIES 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) 1Oim 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 -0.9F*

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

Performers Initials -

SROs Initials PAGE 26 OF 26 REVISION 9

w TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT EMERGENGY PLAN IMPLEMENTING PROCEDURE EPIP-1 0 MEDICAL EMERGENCY RESPONSE Revision 17 Unit 0 PREPARED BY: James F. Hagy SPONSORING ORGANIZATION: Emergency Planning APPROVED BY: Frank L. Pavlechko Effective Date: 08/2512003 LEVEL OF USE: REFERENCE NON-QUALITY RELATED

i ._ t I WBN l MEDICAL EMERGENCY RESPONSE l EPIPI 0 l REVISION DESCRIPTION:

Revision Implementation Pages Desciption of Revision Number Date Affected 11 02/08/00 All Non-intent Changes. Revised phone numbers to McMinn Hospital and REACJTS. Revised map to McMinn Hospital using new State Route 305.

12 06/14/00 All Non Intent change. Phone number to Fire Protection revised.

Reference number revised. Typographical error corrected.

Physician's designee added to the procedure for EMS consultation on medical response. This revision resolves problems identified in WBN PER, 006394.

13 09125101 All Plan effectiveness determinations revisions Indicate the following revisions do not reduce the level of effectiveness of pg. 6, 10, 18 the procedure of REP:

Intent change. Procedure revised to Non-Quality related per requirements of NQAP & pending revision to SPP-2.2. The coversheet and records section of the procedure was revised to reflect this change.

Non-intent change. Removed reference to TVA Physician and replaced with Site Physician or designee 14 01124/02 All 7 Plan effectiveness determinations revisions indicate the following revisions do not reduce the level of effectiveness of pg. 3, 12 the procedure of REP:

Non-intent change. Added emergency room notification to Appendix D. -

15 06/05/02 All Plan effectiveness determinations on these changes indicate the following revisions do not reduce the level of effectiveness 3, 8, 10 11 & of the procedure or REP.

20 Non-intent change(s): Added location of the 911 phone in app.

B & C. Revised phone-number to Industrial Safety, RADCON and MCR. Removed zip codes from Appendix C. Added OSHA notification requirements within (8) hours after a catastrophic accident and corrected two typo(s) in the procedure.

16 03/31/2003 All Plan effectiveness determinations on these changes indicate the following revisions do not reduce the level of effectiveness of the procedure or REP.

Non-intent change(s): Updated format for intersite consistency.

Deleted Source Notes. Updated phone numbers.

17 08/25/2003 2,12 Plan effectiveness determinations on these changes indicate the following revisions do not reduce the level of effectiveness of the procedure or REP.

Non-intent change: Added ODS notification for SQPER 03-005656-000

-IPAGE2of 24 REVISION 17

__I l WBN l MEDICAL EMERGENCY RESPONSE EPIP-10 l Table of Contents Table of Contents ......................... 3

1.0 INTRODUCTION

......................... 4

2.0 REFERENCES

........................ 4 3.0 INSTRUCTIONS .. ........ 5 3.1 Initial Response ......................... 5 3.2 Control Room Response ................... -. 5 3.3 Shift Manager Response .................... 5 3.4 Incident Commander Response ..................................... 6 3.5 MERT Response ..................................... 6 3.6 Medical Services Nurse Response .................................... 6 3.7 RADCON Response ...... 6......6 3.8 Nuclear Security and Standby AUO Response ..................................... 6 3.9 Supplies ............... 6 4.0 RECORDS .7..........I....7 APPENDIX A Control Room Operator Medical Response Checklist .8 APPENDIX B Shift Manager (SM) Medical Response Checklist .9 APPENDIX C Notification List .11 APPENDIX D Hospital Notification Report .12 APPENDIX E Incident Commander - Designated US Medical Response Guidelines. 13 APPENDIX F EMS Leader/Emt Medical Response Guidelines .15 APPENDIX G Radiological Control (RADCON) Medical Response Guidelines .17 APPENDIX H Medical Services (Nurse) Medical Response Guidelines.19 APPENDIX I Nuclear Security/AUOs. (on Standby) Medical Response GUIDELINES . 20 APPENDIX J Transit Maps .21 APPENDIX K Blood Clean-Up at Watts Bar Nuclear Plant.24 PAGE 3 of 24 REVISION 17

i WBN I MEDICAL EMERGENCY RESPONSE J EPIP-10 1.0- INTRODUCTION At WBN the Medical Emergency Response Team (MERT) is an organized group of onsite personnel designated as the primary responders in a medical emergency. Emergency medical treatment involves treatment of a patient in areas other than the Medical Services facility. The MERT shall consist of the following list of personnel:

Operations (Designated Unit Supervisor (US) and available AUOs)

Fire Protection Section

Radiological Control (RADCON) Technicians

Medical Services - Nurse as requested

Nuclear Security This procedure outlines the actions to be followed during medical emergencies by the Medical Emergency Response Team (MERT) and other onsite support personnel. The Shift Manager (SM) and the MERT team members are primarily responsible to ensure that the actions outlined in this procedure are implemented.

2.0 REFERENCES

2.1 Source Documents

1. NUREG 0654, FEMA-REP-1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in support of Nuclear Power Plants

2. NUREG 0696, Functional Criteria for Emergency Response Facilities, Final Report 2.2 Interfacing Documents

1. NP Radiological Emergency Plan (REP)

2. WBN-EPIP-2 Notification of Unusual Event

3. WBN-EPIP-3 Alert

4. WBN-EPIP-4 Site Area Emergency

5. WBN-EPIP-5 General Emergency

6. WBN-EPIP-12, Emergency Equipment and Supplies

7. SPP-3.1 Corrective Action Program

8. SPP-3.5 Regulatory Reporting Requirements

9. ANSI Standard N.18.7-19762.0 PAGE 4 of 24 REVISION 17

I WBN MEDICAL EMERGENCY RESPONSE EPIP-1 0 3.0 INSTRUCTIONS 3.1 Initial Response Upon discovering an ill or injured person, ALL WBN personnel shall A. ADMINISTER immediate aid for any life threatening situation (IF TRAINED).

B. SUMMON assistance from available personnel in the immediate area.

C. NOTIFY the Control Room Ext. 3911 and state that a medical emergency has occurred and RESPOND to ALL Questions.

NOTE Individuals not involved in the emergency are to remain at their work stations, refrain from using the phone, portable radio, and elevators, and continue working unless called upon for assistance or told to move to another location.

CAUTION Patients known or suspected of being in medical distress shall not be allowed to walk, especially when the cause of distress may be aggravated by exertion.

3.2 Control Room Response Upon receipt of medical emergency notification, Control Room personnel shall perform APPENDIX A, Control Room Operator Medical Response Checklist.

3.3 Shift Manager Response Upon receipt of medical emergency notification, the Shift Manager shall perform APPENDIX B, Shift Manager (SM) Medical Response Checklist.

IF Offsite Hospital assistance is required, THEN the Shift Manager shall perform APPENDIX D, Hospital Notification Report.

PAGE 5 of 24 REVISION 17

I WBN MEDICAL EMERGENCY RESPONSE I EPIP-10 l 3.0 Instructions (continued) 3.4 Incident Commander Response Upon receipt of medical emergency notification, the Incident Commander (US) shall perform APPENDIX E, Incident Commander (US) Medical Response Guidelines.

3.5 MERT Response Upon receipt of medical emergency notification, the MERT shall perform APPENDIX F, EMS Leader/EMT Medical Response Guidelines.

3.6 Medical Services Nurse Response Upon receipt of medical emergency notification, the Medical Services Nurse shall perform APPENDIX H,Medical Services Nurse Medical Response Guidelines.

3.7 RADCON Response Upon receipt of medical emergency notification, RADCON shall perform APPENDIX G, Radiological Control (RADCON) Medical Response Guidelines.

3.8 Nuclear Security and Standby AUO Response Upon receipt of medical emergency notification, Nuplear Security and Standby AUO(s) shall perform APPENDIX I, Nuclear Security/AUOs (on Standby) Medical Response Guidelines.

3.9 Supplies Radiological Emergency Supply Cabinets are located at the agreement hospitals and are stocked in accordance with EPIP-12, Emergency Equipment And Supplies. Specialized replacement items can be obtained in coordination with the WBN EP Manager as required.

PAGE 6 of 24 REVISION 17

I WBN l MEDICAL EMERGENCY RESPONSE I EPIP-1 0 4.0 RECORDS 4.1 Records of Classified Emergencies The materials generated in support of key actions during an actual Medical 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 7 of 24 REVISION 17

WBN IMEDICAL EMERGENCY RESPONSE EPIP-1 0 APPENDIX A CONTROL ROOM OPERATOR MEDICAL RESPONSE CHECKLIST (Paqe of 1)

Control room personnel will USE the following checklist in their RESPONSE to an onsite medical emergency.

A. Obtain NAME of caller__

B. LOCATION (Bldg., Elev., Column) _3 C. Type of Medical Emergency_ 0 D. Number of Personnel Involved_ 0 E. Immediate Area Hazards (Radiological, Safety)

F. Telephone Number of Caller L 0 G. ALERT and DISPATCH MERT PERSONNEL __ 0 H. Make the following plant announcement with public address: 1 "ATTENTION ALL SITE PERSONNEL."

"ATTENTION ALL SITE PERSONNEL."

"A MEDICAL emergency has been reported. The MERT is to ACTIVATE and RESPOND to the following LOCATION:

I. CONFIRM that the Shift Manager (SM) has been notified. 0 J. CONFIRM that the Fire Protection Section Duty Shift 0 Supervisor (Fire Brigade Leader) was notified by:

Radio or Telephone (extension #3311 or #3355) and Pocket Pager #40566 K. CONFIRM/COORDINATE MERT response (via radio or phone) 0 until Incident Commander assumes control.

PAGE 8 of 24 REVISION 17

WBN I MEDICAL EMERGENCY RESPONSE l EPIP-10 l APPENDIX B SHIFT MANAGER (SM) MEDICAL RESPONSE CHECKLIST (Page 1 of 2)

SMs will use the following checklists in Appendix B in response to an onsite Medical Emergency:

INITIAL RESPONSE CHECKLIST A. ESTABLISH and MAINTAIN communications with the 3 designated Incident Commander.

B. ENSURE the Onsite Medical Services Personnel (if staffed) 0 have been notified to STANDBY. (#3254)

C. OBTAIN victim's name(s) and company or section. 0 Name Co. Section D. IF NEEDED, EXPEDITE offsite ambulance and hospital 0 support by immediately completing the Hospital Notification Report in Appendix D and going to steps in TRANSPORTING OFFSITE of this Appendix.

PAGE 9 of 24 REVISION 17

l WBN l MEDICAL EMERGENCY RESPONSE l EPIP-10 l APPENDIX B SHIFT MANAGER SM) MEDICAL RESPONSE CHECKLIST (Page 2 of 2)

TRANSPORTING OFFSITE A. OBTAIN medical transports, as requested by the Incident Commander, a Primary ambulance number 9-775-2141, back-up 911 (outside bell line on SM desk).

Life Force Helicopter 9-778-5433, contact radio frequency is 155.205.

IF Life Force is called, ALSO call Rhea County Ambulance for additional medical support.

B. ADVISE ambulance dispatcher of radiological conditions, type of a medical emergency, type of transport needed (emergency or non-emergency),

and point of site entry.

C. ENSURE the receiving hospital is notified, and has the information identified on D APPENDIX D.

NOTE 1 All WBN employees with service related traumatic injuries should be transported to an agreement facility. IF In shock or the condition is life threatening, he or she should be taken to the nearest facility, (Rhea Medical Center).

NOTE 2 IFthe patient is suspected or known to have been over exposed or contaminated with radioactive material, use an agreement hospital and ambulance IFuse of the WBN ambulance is not preferred.

D. NOTIFY Nuclear Security to escort the ambulance onsite or prepare the landing 0 zone and advise of its Estimated Time of Arrival (ETA).

FOLLOW-UP ACTIONS A. PERFORM reporting functions required by SPP-3.01 and SPP-3.5. 0 B. IFit is determined that the patient's "Emergency Contact" (located on the 3 employee's Form TVA 9880, Employee Status and Information Record) needs to be notified, ENSURE that Employee Relations & Development is contacted during regular hours and the employee's Supervisor Is contacted during off-hours.

C. IFthe victim was determined to be a non-TVA employee, ensure that their 0 supervision has been notified.

D. NOTIFY the site Physician (or designee) any time TVA personnel receive radiation 3 doses in excess of the TVA occupational dose limits at the first opportunity and as information becomes available. (#3254)

E. NOTIFY Industrial Safety (if on duty) (#3418) or at home if the medical emergency 0 has resulted in a fatality or catastrophic injury (i.e. three (3) or more hospitalized.

OSHA notification needs to be made within eight (8) hours after these types of accidents by the site Industrial Safety Manager or duty Plant Manager.

PAGE 10 of 24 REVISION 17

WBN I MEDICAL EMERGENCY RESPONSE I EPIP-1 0 APPENDIX C NOTIFICATION LIST (Page 1 of 1)

WATTS BAR ONSITE EMERGENCY CONTACTS Medical Emergency)TVA Ambulance -3911 Medical Office (WBN Training Center) -3254 Nuclear Security -8544 Shift Manager -7860 RADCON -7865, 1862 Fire Protection Section -3311 (3355, Back-up),

FPS Pocket Pager for Duty FPS/SS at 40586 Site Safety Manager -3418 AMBULANCE Pnimarv: Primary contact: 9-775-2141 (Dayton)

Rhea County Ambulance Service 911 (Backup, outside bell line SM Desk)

Highway 27, North Dayton, Tennessee Secondary contact: 9-365-9500 (Spring City)

Life Force Helicopter Primary contact: 9-778-5433 (Chattanooga)

RADIOLOGICAL AGREEMENT HOSPITALS Rhea Medical Center (Primary Hosp) Athens Reg. Med. Center (Secondary Hosp)

Highway 27, North 111 W. Madison Ave.

Dayton, Tennessee Athens, TN 9-775-1121 9-1-(423)-745-1411 9-775-8542 (ER) 9-1-(423)-744-3260 (ER) 9-775-8589 (ER) 9-1-(423)-744-3227 (ER)

RADIOLOGICAL/TRAUMA Erlanger Medical Center 975 E. Third St.

Chattanooga, TN 9-778-7296 (Emergency Room)

NOTE Erlanger provides Trauma/Radiological Backup services to TVA when directed by one of our Agreement Hospitals.

KtAATI b, UAK' tlVUfi I NNtb-tt 24-Hour Hospital Disaster Network Commercial 9-1-(865) 576-1005 PAGE 11 of 24 REVISION 17

I WBN I MEDICAL EMERGENCY RESPONSE I EPIP-10 I APPENDIX D HOSPITAL NOTIFICATION REPORT (Page 1 of 1)

(Non-QA Record)

The Shift Manager shall complete this form and NOTIFY the destination hospital as soon as the need for offsite transportation is determined by calling:

Primar, Rhea Medical Center (9-775-1121 or 9-775-8542), or Secondary, Athens Regional Medical Center (9-1-(423)-745-1411 or 9-1-(423)-744-3227).

wThis is the Shift Manager at the Watts Bar Nuclear Plant." (Connect me with the Emergency Room)

Date I I Time _ _ Hospital Person Contacted Title _

MESSAGE "Watts Bar Nuclear Plant will be sending _ (number) Injured person(s) to your hospital Emergency Department. The victim(s) is/are (names):

Patient Condition: (Check one)

O "NOT a Radiation Accident Victim(s). No radiological hazards."

O "Contaminated with radioactive material. (Extemalinternal)"

"Radiation overexposure only, no contamination" O "Contaminated and Overexposed" O 'Potentially Contaminated, Medical injuries prevent a complete body survey."

"Contamination Levels are:

O Unknown at this time O Counts Per Minute (Report as maximum level identified)

O Millirem/hour "

"Check appropriate type of radiation:

0 Alpha 0 Beta 3 Gamma REM exposure MREM exposure" "The nature of njury(ies) are:__

"The medical condition of the victim is: ___

"An Estimated rime of Arrival (ETA) will be provided by the ambulance EMT upon departure from Watts Bar."

"Please call me back at _to verify and confirm the validity of this medical emergency call."

(The SM should prepare to receive an Immediate confirmation call-back from the Hospital.)

ODS notified of any ambulance traffic to or from site Time:

PAGE 12 of 24 REVISION 17

1i WBN I MEDICAL EMERGENCY RESPONSE I EPIP-10 l APPENDIX E INCIDENT COMMANDER - DESIGNATED US MEDICAL RESPONSE GUIDELINES (Page 1 of 2)

Incident Commander's will UTILIZE the followina Guidelines in responding to an onsite Medical Emergency:

NOTE I The following steps may be performed in varying sequences as needed.

NOTE 2 If personnel contamination with injury has occurred, necessary medical treatment will take precedence over decontamination efforts.

INITIAL RESPONSE A ESTABLISH communications with the SM and EMS leader. 13 B. RESPOND to the incident and ESTABLISH a COMMAND POST.

C. DIRECT initial first-aid MERT efforts until the EMS Leader arrives.

D. DIRECT personnel in support of the medical response (i.e., RADCON, Nuclear Security, AUOs, Nurse).

0 E. ADVISE the SM of the victim's name and organization. 03 El F. ADVISE the SM on radiological conditions with the patient. 03 G. ADVISE the SM on which ambulance is required (per MERT Leader).

NOTE 3 Rhea County Ambulance is primary. TVA is secondary or for "load and I go" if Rhea County Ambulance has an unacceptable ETA.

PAGE 13 of 24 REVISION 17

[ WBN MEDICAL EMERGENCY RESPONSE EPIP-10 I APPENDIX E INCIDENT COMMANDER - DESIGNATED US MEDICAL RESPONSE GUIDELINES (Page 2 of 2)

H. ADVISE the EMS leader on access/egress routes. 0 I. IF radiological conditions with the patient are confirmed or suspected, a DIRECT RADCON to accompany the patient in the ambulance and provide Radiological Control assistance.

J. DIRECT on scene Security to address site access badging needs. 0 K. CONTROL access to the accident scene until all hazards are removed to 0 the extent that the area can be returned to unrestricted access (i.e., radiological, physical, or bio-hazard blood borne pathogens).

L. IF the emergency is at the onsite Health Station and the full MERT has 0 not been activated, then COORDINATE necessary support (i.e., standby notice to onsite EMTs, Security escorts for responding ambulances, and notifications).

PAGE 14 of 24 REVISION 17

WBN MEDICAL EMERGENCY RESPONSE I EPIP-10 APPENDIX F EMS LEADERIEMT MEDICAL RESPONSE GUIDELINES (Page 1 of 2)

INITIAL RESPONSE lNOTE 1 The following steps may be performed in varying sequences as needed.

A. ESTABLISH communications with the Incident Commander (US). 0 B. DIRECT the dispatch of EMTs and equipment to the scene. 3 C. RESPOND to the scene and ASSUME direction of the EMS response. 0 D. COORDINATE necessary support via the Incident Commander. 0 E. DETERMINE which ambulance (if any) is to be used. (ADVISE SM). 0 NOTE RHEA COUNTY AMBULANCE is the PRIMARY means of ground transport unless the medical emergency is life threatening and the ETA of the offsite ambulance is- unacceptable. LIFE FORCE helicopter may be utilized according to medical protocol. This includes transportation of contaminated and injured patients. IF Life Force is chosen, Rhea County Ambulance should also be called as a back up for medical support.

F. ADVISE the Incident Commander of the patient's destination (specific 0 hospital, site Health Station or decon room or no further TVA care).

G. IF the patient is contaminated, ENSURE the patient is wrapped in a linen 0 sheet to contain the contamination during movement.

H. IF the TVA ambulance is to be used, an EMT shall ride with the injured 0 person. REFER TO Appendix J, Transit Maps, for driving directions.

NOTE 3 One TVA EMT from the Fire Protection Section or a nurse shall remain onsite at all times, except in life-threatening situations as determined by the site Physician (or designee) or EMS Leader, in consultation with the SM.

PAGE 15 of 24 REVISION 17

WBN I MEDICAL EMERGENCY RESPONSE EPIP-10 APPENDIX F EMS LEADER/EMT MEDICAL RESPONSE GUIDELINES (Page 2 of 2)

The EMT shall CONTACT the receiving hospital from the 0 ambulance to provide an updated report and Estimated Time of Arrival.

J. OBTAIN SM concurrence if a TVA ambulance is to be taken offsite, 0 out-of-service, or when an employee treated by a TVA EMT is taken offsite for medical treatment due to service-related injury or illness.

K. ENSURE necessary actions are taken for blood-borne pathogen controls 0 at the accident scene. REFER TO Appendix K, Blood Cleanup at Watts Bar Nuclear Plant. Assistance may be available from siteHealth Services.

ADVISE the Incident Commander of clean-up status.

PAGE 16 of 24 REVISION 17

l WBN l MEDICAL EMERGENCY RESPONSE l EPIP-10 l APPENDIX G RADIOLOGICAL CONTROL (RADCON)

MEDICAL RESPONSE GUIDELINES (Page 1 of 2)

INITIAL RESPONSE A. ADVISE the MERT of radiological conditions and PROVIDE radiological support (monitoring, dosimetry, contamination control).

B. ESTABLISH contamination control zones to support the EMS effort. D C. COORDINATE the collection of isotopic samples for analysis. 03 D. ASSIST in onsite patient decontamination as indicated. E3 NOTE I Essential medical care takes priority over decontamination.

NOTE 2 If the person is severely injured, they will be transported directly to an agreement hospital. However, reasonable efforts should be made t 0 reduce the exposure level from contamination to less than 500 mrer nlhour at one foot. The patient shall be wrapped in a linen sheet to contaii 1n contamination. Avoid the use of plastics to prevent patient heat stre E. ACCOMPANY the patient in the ambulance (for radiological conditions). 0 355 F. ADVISE the SM if a REP Van needs to be dispatched to the hospital. 13 G. Upon arrival at the hospital, ADVISE the hospital team leader or 0o Radiation Safety Officer of your identity and offer assistance. 13 0o H. Unless directed otherwise, PROVIDE general radiological support (i.e., establish checkpoint, perform surveys of personnel and equipment).

PAGE 17 of 24 REVISION 17

I WBN I MEDICAL EMERGENCY RESPONSE I EPIP-10 I

- APPENDIX G RADIOLOGICAL CONTROL (RADCON)

MEDICAL RESPONSE GUIDELINES (Page 2 of 2)

I. FOLLOW-UP on TLD process and isotopic analysis data to the hospital. a J. COLLECT contaminated material from the hospital and take necessary 3 actions for disposal. Transport of material shall be in accordance with the TVA Radiological Material Shipping Manual.

K. Any personnel known or suspected of receiving radiation exposure in 3 excess of the TVA occupational dose limits should be reported by RADCON to the Site Physician (or designee) at the first opportunity and as information becomes available. (#3254) ° PAGE 18 of 24 REVISION 17

WBN IMEDICAL EMERGENCY RESPONSE I EPIP-10 I L

APPENDIX H MEDICAL SERVICES (NURSE)

MEDICAL RESPONSE GUIDELINES (Page 1 of 1)

A. PREPARE to assist with patient care if the patient is brought to the site 03 medical facility or onsite decontamination facility.

B. RESPOND to the accident scene when requested, (Nuclear Security will El provide an escort).

C. COORDINATE radiological decontamination efforts with RADCON while 0 onsite as the medical status permits.

D. ACCOMPANY the EMT in the ambulance if needed. 0 NOTE If an ambulance is to be used, an EMT shall ride with the injured pierson.

A nurse may accompany the EMT.

NOTE 2 One TVA EMT from the Fire Protection Section or a nurse shall re main onsite at all times, except in life-threatening situations as determineed by the site physician or EMS Leader, in consultation with the SM.

NOTE 3 Individuals who have received an acute whole body radiation expc)sure greater than 5 rem should have hematological studies performed t o detect chromosomal aberrations or other changes in blood constituents.

REACTS can provide this service and can be contacted at 9-1-865-576-3131 or 9-1-865-576-1005, by the attending physiciar I.

E. IF an emergency medical situation occurs at the Medical Station which 03 requires EMT or ambulance assistance, REQUEST assistance using extension 3911. IF the situation is not of an emergency nature, the SM may be notified directly using a non-emergency phone number.

PAGE 19 of 24 REVISION 17

l WBN l MEDICAL EMERGENCY RESPONSE EPIP-10 l APPENDIX I NUCLEAR SECURITYIAUOs (on Standby)

MEDICAL RESPONSE GUIDELINES (Page 1 of 1)

NUCLEAR SECURITY A. FACILITATE emergency personnel and equipment movement through 0 site areas, including control of the plant elevator as necessary.

B. PROVIDE crowd control (at accident scene and ambulance). 3 NOTE If helipad is to be used, stage a vehicle with emergency lights to aid in the identification of the landing area to the aircraft. DO NOT shine spotlights in the air at the aircraft and DO NOT approach the aircraft once landed. KEEP all bystanders away from aircraft. Flight crew will handle patient loading. If there is a nearby aerial obstruction (power line, power pole, illumination by spot light is recommended.

C. COORDINATE site access badging, TLD issuance, and escort needs with 0 MERT members, support staff, and offsite responders.

D. PROVIDE vehicle escorts for ambulances arriving and departing the site 0 as necessary.

E. PROVIDE escort for site Medical Services Staff from the Medical Station C to the accident scene as required.

ASSISTANT UNIT OPERATORS A. Available AUOs will report to the Service Building Fire Emergency Equipment Room, Elevation 729 and WAIT for instructions from the Incident Commander.

B. Anticipate the following needs:

Delivery of equipment and supplies to the MERT (stretchers, etc.).

Assistance on securingloperating elevators.

Assistance with plant equipment as related to the emergency response.

Prepare to dress-out if you may be used in the control zone or for aid in passing a contaminated patient onto an awaiting stretcher.

PAGE 20 of 24 REVISION 17

I l WBN l MEDICAL EMERGENCY RESPONSE EPIP-10 l

- APPENDIX J TRANSIT MAPS (Page 1 of 3)

WATTS BAR TO RHEA MEDICAL CENTER (5.9 Miles)

(0.7 miles)

(1 1.8 miles Total: 18.4 milesI 2-Lane Highway AI MEDICAL RHAt CNER,

" %% Contaminated Patient i &

%% Preparation I t me I .. "Alr 2 *I~ Ni >

/

PAGE 21 of 24 REVISION 17

4 L WBN l MEDICAL EMERGENCY RESPONSE l EPIP-10 l APPENDIX J TRANSIT MAPS (Page 2 of 3)

WATTS BAR TO ATHENS REGIONAL MEDICAL CENTER (SWEAZJI 3.7 MLES HYIn OMES t; X11.6 PALES 2.7 MILES Athens Regional Medical Center Contaminated Patient Praparation I

Total Miles to the Hospital:

26 Miles Via Hwy 305f1-75 PAGE 22 of 24 REVISION 17

WBN MEDICAL EMERGENCY RESPONSE EPIP-O I APPENDIX J TRANSIT MAPS

- (Page 3 of 3)

WATTS BAR TO ERLANGER MEDICAL CENTER AREA MCM EMERGENCY ROOM POLICE NTRANCE rx

= == = = = ~C== %S e HAMPTON RD.

Prinary Route is as FoEows:

Leave WBN Nudear Plant via Rt. 6 to Highway 27 (.2 wil"I Highway 27 to 4h Street irbnadately after Tennease River dge) to Eanger Hoepital v Lnag Stret to 3rd Street 10.6mes.

" Corridor" J

RED ANK 9

LIGHTS PAGE 23 of 24 REVISION 17

I WBN MEDICAL EMERGENCY RESPONSE l EPIP-10 l

APPENDIX K BLOOD CLEAN-UP AT WATTS BAR NUCLEAR PLANT (Page 1 of 1)

Fire Operations Personnel have the responsibilitv of cleaning up accidentally spilled blood on site.

The following methods are to be used in cleaning up spilled blood:

Accidentally spilled blood In plant (including Stainless Steel piping).

1. Wipe up blood, using damp cloth.

2. Wipe spill area with cloth fully saturated (wet) with O-SYL Disinfectant "USE CODE 11", diluted to proper strength solution (see O-SYL container for dilution ratio).

3. Let stand for ten (10) minutes, maintaining a damp surface.

4. Let area dry. Do not wipe up.

5. Place all clean-up materials in a '-'Bio-Hazard" marked disposable bag.

6. Take "Bio-Hazard" bag to Site Medical Services for disposal.

7. Notify Chem-Lab and have them do a swipe test per CEM-601.

(If blood spilled on Stainless Steel Piping)

8. If swipe test does not meet CEM-601 specs, re-do steps needed until acceptable limits are met.

PAGE 24 of 24 E REVISION 17

TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT EMERGENGY PLAN IMPLEMENTING PROCEDURE EPIP..6 ACTIVATION AND OPERATION OF THE TECHNICALSUPPORT CENTER (TSC)

Revision 26 Unit 0 PREPARED BY: James F. Hagy SPONSORING ORGANIZATION: Emergency Planning APPROVED BY: Frank L. Pavlechko Effective Date: 08108/2003 LEVEL OF USE: REFERENCE NON-QUALITY RELATED

WBN ACTIVATION AND OPERATION OF EPIP-6 TECHNICALRTHESUPPORT CENTER REVISION LOG ~.

Rev!ion Implementation Pages iDescription of Revision Number Date Affected 21 06/05/02 All Plan effectiveness determinations on these changes indicate the following revisions do not reduce the level of effectiveness of the 3,18.24, procedure or REP.

29 &61 Non-intent change(s): Clarified in App.B that the Site VP can assume the duties of the SED as necessary. Corrected typo In App. C and removed the reference to the 3 and 4 PARs. Added an operational responsibility to the TAM InApp.E. to coordinate WOG-99-064 (ERG) activities with the TAT Team. Added WOG-99-064 to the App.V reference list.

22 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 to revise instruction references. Updated format for intersite consistency. Deleted source notes. Added table of contents. Revised section numbering.

23 01/21/2003 2,60 Plan effectiveness determination reviews indicate the following revisions do not reduce the level of effectiveness of the procedure or REP:

Non-intent change to add loss of offsite power to App. X, for WBPER 03-00695-000.

24 03/31/2003 2, 4, 45, Plan effectiveness determination reviews indicate the following 65 revisions do not reduce the level of effectiveness of the procedure or REP:

Non-intent change to reflect training provided for Clerical Staff.

Editorial corrections. Added overtime restriction check to Appendix AA.

25 06/02/2003 2, 10, 33 Plan effectiveness determinations reviews indicate the following revisions do not reduce the level of effectiveness of the procedure or REP:

Non-intent change. Standardized record retention. Editorial corrections.

26 08/0812003 2-5, 47, Non-intent change. Relocated technical considerations 59-60 (Appendices W, X, Y, & Z) to TI-128, Post Accident Technical Considerations (TSC)." Added AOl's to interface documents.

Editorial corrections.

PAGE 2 OF 60 REVISION 26

WBN ACTIVATION AND OPERATION OF EPIP4 THE TECHNICAL SUPPORT CENTER Table of Contents Table of Contents ................................................ 3 1.0 PURPOSE ................................................ 4

2.0 REFERENCES

................................................ 5 3.0 INSTRUC TIONS . .............................................. 6 4.0 RECORDS.11...............................................1 APPENDIX A TSC Facility Layout Diagram ............................................... 12 APPENDIX B Site Vice President ............................................... 14 APPENDIX C Site Emergency Director ............................................... 16 APPENDIX D Operations Manager ................................................ 23 APPENDIX E Technical Assessment Manager ............................................... 25 APPENDIX F Maintenance Manager ............................................... 27 APPENDIX G Operations Communicator ............................................... 29 APPENDIX H Nuclear Security Manager ............................................... 31 APPENDIX I Radcon Manager ............................................... 33 APPENDIX J Chemistry Manager ............................................... 35 APPENDIX K NRC Coordinator ............................................... 37 APPENDIX L Control Room Communicator ............................................... 39 APPENDIX M EP Manager ............................................... 40 APPENDIX N Intentionally Deleted ............................................... 42 APPENDIX 0 TSC Logkeeper ............................................... 43 APPENDIX P TSC Clerical Staff .......... 44 APPENDIX Q Technical Assessment Team ......................................... 46 APPENDIX R Plant Parameter Data Sheets ......................................... 49 APPENDIX S Predictive Release Data Sheet ......................................... 55 APPENDIX T TSC Accident Assessment Summary Sheet ......................................... 56 APPENDIX U Protective Action Recommendation ......................................... 57 APPENDIX V Reference Materials and Equipment List......................................... 58 APPENDIX W Emergency Responder Notification Form ......................................... 59 APPENDIX X WBN TSC Sign-In Roster ......................................... 60 PAGE 3 OF 60 REVISION 26

WBN l ACTIVATION AND OPERATION OF EPIP-6 ITHE TECHNICAL SUPPORT CENTER 1.0 PURPOSE The purpose of this Procedure is to describe activation of Technical Support Center (TSC), describe the TSC organization, and provide for TSC operation once it has been staffed.

PAGE 4 OF 60 REVISION 26

WBN l ACTIVATION AND OPERATION OF - EPIP-6

_ WBN THE TECHNICAL SUPPORT CENTER ! I

2.0 REFERENCES

2.1 Source Documents:

1. Tennessee Valley Authority Nuclear Power Radiological Emergency Plan (REP)

2. SPP-1.2, Fitness For Duty

3. SPP-1.5, Overtime Restrictions (Regulatory)

4. Memo from J. B. Hosmer to R. J. Johnson dated 1/15188, RIMS No. B25 88011 5028

5. NUREG 0654, FEMA-REP-1, Rev. , Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in support of Nuclear Power Plants

6. NUREG 0696, Functional Criteria for Emergency Response Facilities, Final Report

7. ANSI Standard N 18.7-1976

8. CFR 20, Standards for Protection From Radiation

9. EPA 400-R-92-001, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents

10. NRC Generic Letter 96-06, Assurance of Equipment Operability and Containment Integrity During Design Basis Accident Condition

11. Response Technical Manual (RTM) 96 Vol. 1 Rev. 4.

2.2 Interface Documents

1. EPIP-1 Emergency Plan Classification Flowchart

2. EPIP-2 Notification of Unusual Event

3. EPIP-3 Alert

4. EPIP-4 Site Area Emergency

5. EPIP-5 General Emergency

6. EPIP-7 Activation and Operation of the Operations Support Center

7. EPIP-8 Personnel Accountability and Evacuation

8. EPIP-1 Security and Access Control

9. EPIP-1 3 Initial Dose Assessment for Radiological Emergencies

10. EPIP-15 Emergency Exposure Guidelines

11. EPIP-1 6 Termination of the Emergency and Recovery

12. AO1-6 Small Reactor Coolant System Leak

13. AO1-7.01 Maximum Probable Flood

14. AO1-8 Tornado Watch Or Warning

15. AOI-9 Earthquake

16. AOI-22 Break Of Downstream Dam

17. AOI-35 Loss Of Offsite Power

18. TI-1 28 Post Accident Technical Considerations (TSC)

19. CECC-EPIP-9 Emergency Environmental Radiological Monitoring Procedures

20. WBN FSAR

21. S01-30.06 Auxiliary Building Gas Treatment System (ABGTS)

22. SOI-67.01 Essential Raw Cooling Water System

23. Chemistry Manual, Chapter 13 (PASS)

24. ICS Users Manual

25. Watts Bar Nuclear Plant, Plant Lighting, N3-228-4003

26. SOI-14.03, Condensate Demineralizer Waste Disposal PAGE 5 OF 60 REVISION 26

4.~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

WBN ACTIVATION AND OPERATION OF EPIP-

~~~H ECHICL SUPR ENTE 3.0 INSTRUCTIONS 3.1 General The Shift Manager (SM), upon detection of an emergency condition, becomes the Site Emergency Director (SED), classifies the emergency, and declares the event. Upon arrival of the Plant Manager, or alternate defined in the Emergency Response Organization Call List, the SM will be relieved of the SED duties. The SED activates and operates the TSC (Appendix A) and oversees the operations of the Operations Support Center (OSC).

NOTE: In the event of plant inaccessibility, all references to the TSC (or OSC) are intended to refer to the alternate location selected for staffing, such as the staging area in Classroom 19 of the Watts Bar Training Center.

The TSC will provide the following functions:

A. Provide plant management and technical support to plant Operations personnel during emergency conditions.

B. Perform CECC functions for the Alert Emergency class, the Site Area Emergency class, and General Emergency class until the CECC is functional.

C. Help the reactor operators determine the plant safety status.

D. Relieve the reactor operators of peripheral duties and communications not directly related to reactor system manipulations.

E. Prevent congestion in the control room.

F. Provide assistance to the operators by technical personnel who have comprehensive plant data at their disposal.

G. Provide a coordinated emergency response by both technical and management personnel.

PAGE 6 OF 60 REVISION 26

I l :

I WBNl ACTIVATION AND OPERATION OF : EPIP-6 THE TECHNICAL SUPPORT CENTER

I 3.0 INSTRUCTIONS 3.1 General (continued)

H. Provide reliable communications between onsite and offsite emergency response personnel.

I. Provide a focal point for development of recommendations for offsite actions.

J. Provide relevant plant data to the NRC for its analysis of abnormal plant operating conditions.

3.2 Initiating Conditions This procedure shall be activated if an emergency has been declared and classified as ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY.

This procedure may be activated at any other time at the discretion of the SED.

3.3 Activation of the TSC 3.3.1 The SED will activate the TSC and announce the emergency condition by one or more of the following methods depending on time of day, etc:

A. Plant public address announcement.

JNOTE: The Radiological Emergency Response Organization Call List is handled in accordance with the Fitness for Duty, (SPP-1.2).

B. Shift personnel will normally activate the Emergency Paging System (EPS) or contact the persons designated on the Emergency Response Organization Call List.

C. TSC personnel can also contact additional responders/replacements by phone using the Emergency Response Organization Call List available in the TSC and Appendix W.

D. Target activation time for Minimum TSC staffing is approximately 60 minutes.

PAGE 7 OF 60 REVISION 26

I .1 I WBN WBN ITHE TECHNICAL SUPPORT CENTER ACTIVATION AND OPERATION OF EPIP-6 I

3.0 INSTRUCTIONS (continued) 3.3.2 Emergency Response Organization Call List The Site Emergency Preparedness (EP) Manager shall:

1. MAINTAIN an Emergency Response Call List listing all TSC (and other emergency) personnel by organizational title, name, home and work telephone numbers, and pager numbers.

2. UPDATE the Emergency Response Organization Call List quarterly with input by the appropriate organizations. Current copies of the list will be maintained in the TSC, OSC, Main Control Room, SM Office, and Nuclear Security. Each page will be dated for revision control.

NOTE: All TSC responders shall have unescorted protected area access and shall comply with fitness-for-duty policies while on-call.

3.3.3 Depending on the emergency conditions, personnel required for the TSC may vary. Listed below is the minimum staff required:

Site Emergency Director

Operations Manager or Operations Communicator

Technical Assessment Manager (TAM) or Technical Assessment Team Leader or TAT Team (Thermal Hydraulics, Mechanical, and Electrical)

Members

RADCON Manager PAGE 8 OF 60 REVISION 26

WBN ACTIVATION AND OPERATION OF EPIP-6 THE TECHNICAL SUPPORT CENTER 3.0 INSTRUCIONS (continued) 3.3.4 In addition, the following personnel should report to the TSC, or assigned TSC support location, upon announcement of an ALERT or higher emergency or at the direction of the SED:

Site Vice President (optional)

Operations Manager

Operations Communicator

TSC Maintenance Manager

Control Room Communicator (report to Control Room)

Nuclear Security Manager (can initially be the Nuclear Security Shift Supervisor)

Technical Assessment Team

Chemistry Manager

NRC Coordinator

Emergency Preparedness Manager

Media Relations Specialist (optional)

Westinghouse Representative

TSC Boardwriters Clerical Staff

Emergency Response Team Boardwriter PAGE 9 OF 60 REVISION 26

WBN I ACTIVATION AND OPERATION OF I EPIP-6 THE TECHNICAL SUPPORT CENTER 3.0 INSTRUCTIONS (continued) 3.A Required Actions For Activation and Operation of the TSC 3.4.1 TSC staff actions and responsibilities are described in their checklists (Appendices B-Q).

3.4.2 TSC responders will complete all of the applicable steps contained in the appropriate Appendix/Checklist for their position.

3.4.3 The Site Emergency Director or designee shall declare the TSC activated and inform the SM of the final transfer of responsibilities. A formal activation announcement shall be made plant wide to indicate the transfer of responsibility from the SM to the TSC SED.

3.6 Contingencies 3.5.1 If there is a loss of onsite to offsite telephone communications, cellular phone, radios or the satellite phone described in S01-100.01 will be used.

3.5.2 Ifthe TSC becomes uninhabitable, the SED will relocate the TSC to an alternate location based on RADCON/OPERATIONS advice.

3.5.3 Plant procedures should be followed whenever possible. Should a situation arise where normal procedures would be inappropriate, action will be performed as determined by the SED.

PAGE 10 OF 60 REVISION 26

7 4- :

I-I WBN WBN ACTIVATION AND OPERATION OF THETECHNICAL SUPPORT CENTER EPiP-6 I

3.0 INSTRUCTIONS (continued) 3.6 Long-Term Operation 3.6.1 Long-term operation will be put into effect during emergencies which are projected to exist for more than 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

3.6.2 The SED will notify the Central Emergency Control Center (CECC) of the decision to begin long-term operation.

3.6.3 Meals and arrangements for sleeping facilities will be made at the request of the SED. These arrangements may be made by the CECC.

3.6.4 Additional personnel will be called in at the request of the SED to provide coverage or to ensure 12-hour or shorter shifts in the TSC. The SED will coordinate these call-ins with Nuclear Security to facilitate site access.

3.6.5 The SED, through the OSC Manager, will establish 12-hour (or shorter) shifts for craft personnel onsite and call in additional personnel as necessary.

3.7 Termination and Deactivation 3.7.1 REFER TO EPIP-16, "Termination of the Emergency and Recovery," for activities associated with terminating emergencies, TSC deactivation, and post-accident recovery.

3.7.2 All equipment, supplies, and procedures will be replenished in the TSC following a drill, exercise or emergency by applicable groups as assigned in EPIP-12.

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 11 OF 60 REVISION 26

WBN l ACTIVATION AND OPERATION OF l EPIP-6 WBN ITHE TECHNICAL SUPPORT CENTER APPENDIX A TSC Facility Layout Diagram Page 1 of 2 NRC ENS U \\\\\ spplies NRC RMA Coordinator Draw ngs To the Main Control Room Watts Bar Nuclear Plant Il Procedurs Technical Support Center Elevation 755 I I Copier Plant Status Board Writer 8367 8612 Security Mgr.

8606,8608 To Relay Room Chemistry Mgr.

8607 NRC Office TAM 8605 HPN ENS Ops Mgr. SED TMCL 8603 8602 LAN PAGE 12 OF 60 REVISION 26

WBN I ACTIVATION AND OPERATION OF EPIP-6 WBN ITHE TECHNICAL SUPPORT CENTER APPENDIX A Page 2 of 2 Technical Support Center (TSC)

WBN EMERGENCY RESPONSE ORGANIZATION Director* I..... . IWestinghouse Representative Energency Preparedness

_ Manager

(*)Denotes minimum staffing position(s) per NUREG 0654.

PAGE 13 OF 60 REVISION 26

I ITHE WBN l ACTIVATION AND OPERATION OF WBN TECHNICAL SUPPORT CENTER EPIP-6 APPENDIX B SITE VICE PRESIDENT Page of 2 Initial Activation of the Technical Support Center Checklist Date:

Inits/Time ENTER badge into the TSC Accountability Card Reader.

SIGN INon the OrganizationaVStaffing Chart and PUT ON position badge.

NOTIFY SED of arrival.

/_ ESTABLISH a log of communications/events.

-/ ESTABLISH contact with the Media Relations Specialist.

/ ESTABLISH contact with the CECC Director.

_/ CHECK the status of emergency actions already in progress.

(Such as accountability, site evacuation or press inquiries.)

PAGE 14 OF 60 REVISION 26

4'-

ACTIVATION AND OPERATION OF I EPIP-6 I WBN I THE TECHNICAL SUPPORT CENTER I I-APPENDIX B SITE VICE PRESIDENT Page 2 of 2 Operational Resmonsibilities List

Provides TVA policy direction to the Site Emergency director (SED) and can assume the duties of the SED as necessary.

Provides support to other emergency centers as necessary.

Serves as the primary site representative to function as a TVA Spokesperson in the Local News Center (LNC) at the WBN Training Center (if activated).

Directs the site resources to support the SED in the accident mitigation activities.

Provides direct interface on overall site response activities with NRC, FEMA, other Federal organizations, the CECC Director, and onsite media.

Provides interfaces/briefings (as needed) at offsite locations on the overall site response activities with Federal, State and Local agencies.

PAGE 15 OF 60 REVISION 26

WBN l ACTIVATION AND OPERATION OF EPIP-6 WBN ITHE TECHNICAL SUPPORT CENTER APPENDX C SITE EMERGENCY DIRECTOR Pagel of 7 Initial Activation of the Technical Support Center Checklist Date:____

Inits/Time OBTAIN turnover briefing from SM/SED. Pages 5, 6 and 7 of Appendix C, SED Turnover Data Sheet may be used as a guide.

_ /_ REPORT to the TSC and ENTER badge into the TSC Accountability Card Reader.

/ SIGN IN on the staffing chart and PUT ON position badge.

ESTABLISH log of communicationslevents.

ESTABLISH initial contact with the CECC Director.

/_ CHECK the status of emergency actions already in effect such as emergency notifications (NRC, State, etc.) and accountability or site evacuation.

/_ REQUEST checklist completion status for required positions:

o Site Emergency Director o Operations Manager or Operations Communicator O TAM or TAT Leader or TAT Team (Thermal Hydraulics, Mechanical, and Electrical) members o RADCON Manager

/_ CONFIRM TSC staffed and Operational.

ASSUME role of SED from SM (confirmatory phone call to the SM).

PAGE 16 OF 60 REVISION 26

Of:

- t WBN l ACTIVATION AND OPERATION OF EPIP-6 THE TECHNICAL SUPPORT CENTER ! I APPENDIX C SITE EMERGENCY DIRECTOR Page 2 of 7 Initial TSC Activation Checklist (continued)

INFORM the CECC Director and OSC Manager that TSC is operational and that you have assumed responsibility of the SED and provide initial briefing.

MAKE a general plant-wide announcement regarding plant condition similar to the following:

ACCESS the Public Address System by dialing 487.

2. COVER the following points as a minimum:

a. "ATTENTION ALL SITE PERSONNEL ATTENTION ALL SITE PERSONNEL"

b. 3 "This is a drill, this is a drill." OR

c. 0 "This is a real emergency. This is a real emergency."

d. This is (name) Site Emergency Director. The TSC was activated at hours. Due to we have classified a (NOUE. Alert. Site Area Emergency. General Emergency).

Plant protective actions which we are implementing include: (Evacuations, assembly and accountability, etc.)

e. Radiological release points:

f. Our plan of action at this time is to -

9. The OSC (is, is not) activated. All emergency response teams will be dispatched from the OSC.

h. Any emergency response personnel who are fatigue and feel they can not perform their assigned duties, should notify the EP Manager in the TSC and the OCS Manager in the OSC.

i. 0 "This is a drill, this is a drill." OR 0 'This is a real emergency. This is a real emergency."

PAGE 17 OF 60 REVISION 26

I WBN ITHEACTIVATION AND OPERATION OF TECHNICAL SUPPORT CENTER IEPIP-6 I

APPENDIX C SITE EMERGENCY DIRECTOR Page 3 of 7 Operational Responsibilities

Determines the emergency classification and periodically reevaluates the classification.

Changes to the classification will be reported to the CECC Director and the NRC. THE CLASSIFICATION OF THE EVENT CANNOT BE DELEGATED. (See EPIP-1)

Approves or authorizes emergency doses that may exceed applicable NRC dose limits.

THIS RESPONSIBILITY CANNOT BE DELEGATED. (See EPIP-15)

Prior to the CECC being staffed, makes recommendations for protective actions to State and Local agencies through the Operations Duty Specialist. THIS RESPONSIBILITY CANNOT BE DELEGATED EXCEPT TO THE CECC DIRECTOR. Use Appendix U, Protective Action Recommendation Guidance Flowchart as a guide. (See EPIP-5)

Directs onsite emergency accident mitigation activities and periodically briefs the TSC/OSC staff on the current plant situation.

Ensures that general plant population is periodically briefed on the emergency conditions.

Periodically reviews priority of work operations of the OSC with the OSC Manager.

(See EPIP-7)

Directs activities of onsite emergency organizations.

Consults with the CECC Director and Site VP on important decisions. Use the CECC Ring-down Line to the CECC Director.

PAGE 18 OF 60 REVISION 26

1 -

lACTIVATION AND OPERATION OF lEPIP-6 I

VVBN l ! ~THE TECHNICAL SUPPORT CENTER!I APPENDIX C SITE EMERGENCY DIRECTOR Page 4 of 7 Operational Responsibilities (continued)

Coordinates emergency actions with onsite NRC.

Initiates onsite protective actions. (See EPIP-8)

Verifies the administration of Potassium Iodine (KI) to TVA personnel based on RADCON Manager's advice/direction. (See EPIP-14)

Establishes a RADCON checkpoint for site evacuation if conditions warrant. (See EPIP-8 and EPIP-14)

Initiates long-term 24 Hour/day operation.

Assumes responsibilities for the Severe Accident Management, when directed by the Main Control Room and the TSC is functional and the SAMG Evaluators are monitoring "TSC Diagnostic Flow Chart" (DFC). The TSC must have three SAMG Evaluators monitoring SAMGs to assume the accident responsibility.

Evaluates conditions and determines if emergency procedures should be implemented.

a. Emergency Environmental CECC-EPIP-9 Radiological Monitoring Procedures

b. Medical Emergency Response EPIP-10 C. Security Threat Physical Security Plan

d. Personnel Accountability EPIP-8 and Evacuation

e. Initial Dose Assessment for EPIP-13 Radiological Emergencies DEACTIVATION RESPONSIBILITIES Refer to EPIP-16.

PAGE 19 OF 60 REVISION 26

z -

WBN l ACTIVATION AND OPERATION OF EPIP-6 l WBN THE TECHNICAL SUPPORT CENTER !

APPENDIX C SITE EMERGENCY DIRECTOR Page 5 of 7 SED Turnover Datasheet

1. Current Emergency Classification:

UE O ALERT O SAE O GE 3 Time/Date Declared I

2. Event

Description:

3. Equipment Problems:

4. Site Radiological Problems _

5. Rad Release: Yes 0 No 03 Filtered 0 Unfiltered 03 Monitored 0 Unmonitored 0 Controlled 0 Uncontrolled 0 Projected Duration _I_ (hrs./min.)

PAGE 20 OF 60 REVISION 26

WBN ACTIVATION AND OPERATION OF EPIP-6 l~~~~H TEHIA SPOT CENTE APPENDIX C SITE EMERGENCY DIRECTOR Page 6 of 7 SED TURNOVER DATASHEET (continued)

Wind Speed mph Wind Direction FROM_

Projected Whole Body Dose _ mrem __ miles Projected Thyroid Dose _ mrem __miles

6. Protective Action Recommendations to Offsite Officials (use PAR Flowchart in App. U):

None 0 10 2 0

7. Onsite Protective Actions Taken: _

0 SITE EVACUATION 0 ACCOUNTABILITY 0 SPECIFIC AREA EVACUATIONS

8. Field Monitoring Vans Activated: Yes 0 No

9. SM/SED Notifications Made:

Time ODS notified: - (State and other notifications)

Time NRC Notified

10. Injured or contaminated persons status:

0 Rhea County Medical Center 0 Athens Regional Medical Center PAGE 21 OF 60 REVISION 26

l WBN ACTIVATION AND OPERATION OF

~~THE TECHNICAL SUPPORT CENTER.

APPENDIX C EPIP-6 III SITE EMERGENCY DIRECTOR Page 7 of 7 SED TURNOVER DATASHEET (continued)

11. Status of personnel in the field:

NAME LOCATION

12. SED Responsibility Transferred:

0 Physically in the TSC 0 TSC has minimum staffing 0 Call SM to see if conditions have changed.

0 Declares over the telephone, 'The TSC is staffed and activated. This is

-___- __ and I am now assuming the role of Site Emergency Director."

From 1:, to SM TSC/SED Time: Date:

PAGE 22 OF 60 REVISION 26

-q , -

WBN lACTIVATION AND OPERATION OF EPIP-6 THE TECHNICAL SUPPORT CENTER APPENDX D OPERATIONS MANAGER Page of 2

.Initial Activation of The Technical Support Center Checklist Date:

Inits/Time

/ ENTER badge into the TSC Accountability Card Reader.

_/ SIGN IN on the OrganizationaVStaffing Chart and PUT ON position badge.

ESTABLISH log of communicationslevents.

ESTABLISH contact with the OSC Operations Advisor and the CR Communicator in the MCR.

CHECK the status of onsite emergency actions already in effect such as Accountability or Evacuations.

_/ REPORT the status of inplant field activities (operations, repair, radiological, etc.) received from the OSC Operations Advisor, Maintenance Manager or SM.

VERIFY that notification of the NRC has been accomplished and inform SED and NRC Coordinator.

_/ DESIGNATES a person knowledgeable of the event to establish and maintain communications with the NRC via the phone as needed. This will be the NRC Coordinator when present. NOTIFY the SM that responsibility for NRC contact has been transferred to the TSC.

I_ PROVIDE this completed checklist to the SED or EP Manager.

PAGE 23 OF 60 REVISION 26

WBN ACTIVATION AND OPERATION OF EPIP-6 THE TECHNICAL SUPPORT CENTER .

APPENDIX D OPERATIONS MANAGER Page 2 of 2 Operational Resnonsibilities

Directs operational activities.

Informs the SED of plant status and operational problems.

Recommends solutions and mitigating action for operational problems.

Designates a SRO for the Technical Assessment Team, as needed.

Provides advice regarding Technical Specifications, system response, safety limits, etc.

Periodically reviews the emergency status with the control room. Reviews trended parameters, time history information, and status boards with the Control Room staff.

Ensures that the Control Room is aware of TSC accident assessments and OSC repair and response activities and priorities.

Ensures that adequate Operations staffing is currently in the Main Control Room and that oncoming control room staffing requirements are being met for the following positions (Appendix W, Emergency Responder Notification Form, may be used to document):

o Shift Manager o Unit Supervisor o Station Technical Advisor o 2 Reactor Operators o 5 AUOs (minimum tech specs staffing)

PAGE 24 OF 60 REVISION 26

t.z =

WBN lACTIVATION AND OPERATION OF EPIP-6 It WBN ITHE TECHNICAL SUPPORT CENTER ! I APPENDIX E TECHNICAL ASSESSMENT MANAGER Page 1 of 2 Initial Activation of The Technical Support Center Checklist Date:

Inits/Time ENTER badge into the TSC Accountability Badge Reader.

SIGN IN on the Organizational/Staffing Chart and PUT ON position badge.

/ ESTABLISH log of communications/events.

CHECK the status of emergency actions already in effect such as Accountability or Site Evacuation or Response Teams in the Plant.

/. PROVIDE this completed checklist to the SED or EP Manager.

PAGE 25 OF 60 REVISION 26

[ WBN ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER APPENDIX E EPIP-6 I

TECHNICAL ASSESSMENT MANAGER Page 2 of 2 Operational Responsibilities

Designates Technical Assessment Team Leader (if necessary).

Directs activities of the Technical Assessment Team.

Directs onsite effluent assessment.

Projects future plant status based on present plant conditions.

Keeps assessment team informed of plant status.

Provides information, evaluations, and projections to the SED.

Coordinates assessment activities with the CECC Plant Assessment team.

Establishes and maintains a status of significant plant problems.

If ICS is not operable, ensures information on Appendices R, S and T is sent to the CECC to be used in the predictive release rate model.

Coordinate with the Chemistry Manager to initiate a Post-Accident Sample (PASS) as needed for assessment of the containment atmosphere and/or fuel damage.

Provides for trending of significant parameters.

Coordinate support activities performed by the TAT Team in association with WOG-99-064 Emergency Response Guidelines (ERGs) Background Information.

Assumes SAMG responsibilities, when directed by the SED. The TSC must be functional and 3 SAMG Evaluators must be monitoring the TSC Diagnostic Flow Chart" (DFC) to assume SAMG responsibilities.

PAGE 26 OF 60 REVISION 26

I ,

WBN ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER EPIP-6 I

APPENDIX F MAINTENANCE MANAGER Page 1 of 2 Initial Activation of The Technical Sunport Center Checklist Date:

Inits/Time I_ ENTER badge into the TSC Accountability Badge Reader.

-I_- SIGN IN on the Organizational/Staffing Chart and PUT ON position badge.

I_ ESTABLISH log of communications/events.

I ESTABLISH contact with the OSC Manager and Asst. OSC Manager.

CHECK the status of emergency actions already in effect such as Accountability or Site Evacuation.

I_

CHECK status of deployed emergency response teams (Operations, Maintenance, Medical Emergency Response Teams, etc.)

I_

PROVIDE this completed checklist to the SED or EP Manager.

PAGE 27 OF 60 REVISION 26

WBN ACTIVATION AND OPERATION OF EPIP-6 THE TECHNICAL SUPPORT CENTER APPENDIX F MAINTENANCE MANAGER Page 2 of 2 Operational Responsibilities

Coordinates emergency response team assignment activities with the SED and the OSC.

Maintains cognizance of deployed OSC teams purpose and status.

Assists the SED and the OSC Manager in determining the relative priorities of maintenance/repair activities.

Ensures that damage assessment and repair priorities are coordinated with the OSC.

Maintains the Emergency Response Teams tracking board in the TSC.

PAGE 28 OF 60 REVISION 26

WBN ACTIVATION AND OPERATION OF EPIP-6 THE TECHNICAL SUPPORT CENTER . .

APPENDIX G OPERATIONS COMMUNICATOR Page 1 of 2 Initial Activation of The Technical SuPPort Center Checklist Date: _

InitslTime ENTER badge into the TSC Accountability Badge Reader.

SIGN IN on the OrganizationallStaffing Chart and PUT ON position badge.

/ OBTAIN headset and dial 4101.

I> / CHECK operability of the Integrated Computer System (ICS) system.

I PROVIDE this completed checklist to the SED or EP Manager.

PAGE 29 OF 60 REVISION 26

WBN ACTIVATION AND OPERATION OF EPIP-6 THE TECHNICAL SUPPORT CENTER APPENDIX G OPERATIONS COMMUNICATOR Page 2 of 2 ODerational Responsibilities

Provides operational knowledge as needed to status evaluations of plant systems.

Provides advise to the Operations Manager regarding Technical Specifications, Systems Response, and safety limits.

Assist Operations Manager in development of operations recommendations to problems.

Monitors the Control Room Communicator Party line.

Operates TSC ICS to obtain plant status and parameters.

Provides information from the Control Room to the Technical Support Center personnel.

Completes portions of plant parameter data sheets (Appendices R and S) as needed.

Monitors plant status boards.

Obtains supplemental data as needed by the TSC, OSC, or CECC.

Makes inquiries to the Control Room Communicator to obtain specific information as necessary.

Maintains the "Sequence of Events" board and "Main Problems" board.

PAGE 30 OF 60 REVISION 26

WBN0ACTIVATION AND OPERATION OF EPIP-6 THE TECHNICAL SUPPORT CENTER

. APPENDIX H NUCLEAR SECURITY MANAGER Page 1 of 2 Initial Activation of The Technical Support Center Checklist Date:

Inits/Time

-I- ENTER badge into the TSC Accountability Badge Reader.

I SIGN IN on the Organizational/Staffing Chart and PUT ON position badge.

I NOTIFY SED of arrival.

I ESTABLISH log of communications/events.

I ESTABLISH contact with the Central Alarm Station (CAS) and the Secondary Alarm Station (SAS).

I CHECK the status of emergency actions already in effect such as Accountability, Site Evacuation or site being closed to visitors.

I PROVIDE this completed checklist to the SED or EP Manager.

PAGE 31 OF 60 REVISION 26

WBN - 7 ACTIVATION AND OPERATION OF EPIP-6 THE TECHNICAL SUPPORT CENTER :

-APPENDIX H NUCLEAR SECURITYMANAGER Page 2 of 2 Operational Responsibilities

Directs activities of Nuclear Security personnel and mobilizes additional personnel as needed.

Reports on site accountability/evacuation as defined in EPIP-8.

Assists in establishing search teams, as required. (EPIP-8)

Provides status updates to Nuclear Security personnel.

Reports status of Security related events to the SED.

Remain cognizant of Plant Radiological Conditions and report location(s) of Security Personnel/Patrols (as needed) to the RADCON Manager and the SED.

Controls access to the site and the Main Control Room.

Advises incoming emergency response personnel at the gate house of any radiological, security, or environmental hazards enroute to the TSC/OSC.

PAGE 32 OF 60 REVISION 26

.N lACTIVATION AND OPERATION OF EPIP-6 THE TECHNICAL SUPPORT CENTER APPENDIX I RADCON MANAGER Page 1 of 2 Initial Activation of The Technical Support Center Checklist Date:

InitslTime I ENTER badge into the TSC Accountability Card Reader.

I SIGN IN on the OrganizationallStaffing Chart and PUT ON position badge.

I NOTIFY SED of arrival.

I ESTABLISH log of communications/events.

I ESTABLISH contact with the OSC RADCON Supervisor, the plant monitoring van (if dispatched), and the CECC Radiological Assessment Coordinator (RAC).

I CONTROL eating and drinking in the TSC until habitability has been established.

CHECK the status of offsite/onsite radiological conditions and emergency actions already in effect such as Accountability or Site Evacuation.

I_ PROVIDE this completed checklist to the SED or EP Manager.

PAGE 33 OF 60 REVISION 26

WBN l ACTIVATION AND OPERATION OF EPIP-6 ITHE TECHNICAL SUPPORT CENTER !

APPENDIX I RADCON MANAGER Page 2 of 2 Operational Responsibilities

Directs onsite Radcon activities.

IF the CECC is not staffed, utilize EPIP-13 to perform dose assessment. REPORT results to the SED.

Makes recommendations for protective actions for onsite personnel to the SED and for personnel entry into radiological hazardous environments.

Obtains MET data as needed by using ICS or CECC computer.

Directs the issue of KI by following EPIP-14 guidelines to onsite personnel after notifying the SED.

Remains cognizant of assessments of inplant and onsite radiological conditions from the OSC RADCON Supervisor.

Directs the radiological monitoring vans until the CECC assumes control (CECC EPIP-9).

Provides periodic status reports to the SED on radiological conditions.

Keeps the CECC RAC informed on site radiological conditions and Coordinates supplemental RADCON support.

Coordinates assessment of radiological conditions offsite with CECC RAM.

Maintains status maps of offsite radiological conditions and inplant Radiological Conditions status board (ensuring imes are posted next to radiological data).

Provides RADCON surveillance through the OSC to MET station personnel, if required by environmental releases.

Designates a qualified/knowledgeable person to provide inplant radiological data to the NRC via the Health Physics Network (HPN) upon request.

Ensures outlying emergency responders (i.e. line crews, warehouse) have dosimetry and are being protected during the emergency.

Provide radiological data to the OSC that must be obtained from the Main Control Room.

PAGE 34 OF 60 REVISION 26

, - I 1

r WBN ACTIVATION AND OPERATION OF EPIP-6 I THE TECHNICAL SUPPORT CENTER .

a APPENDIX J CHEMISTRY MANAGER Page 1 of 2 Initial Activation of The Technical Support Center Checklist Date:

InitslTime

-I- ENTER badge into the TSC Accountability Card Reader.

I SIGN IN on the Organizational/Staffing Chart and PUT ON position badge.

NOTIFY SED of arrival.

-/_I ESTABLISH log of communications/events.

ESTABLISH contact with the OSC Chemistry Advisor and the CECC Radiological Assessment Coordinator (RAC).

CHECK the status of emergency actions already in effect I_ such as chemistry sampling.

PROVIDE this completed checklist to the SED or EP Manager.

PAGE 35 OF 60 -REVISION 26

WBN l ACTIVATION AND OPERATION OF EPIP-6 THE TECHNICAL SUPPORT CENTER APPENDIX J CHEMISTRY MANAGER Page 2 of 2 Operational Responsibilities

Coordinates information and the assessment of radioactive effluents with the CECC.

Directs and remains cognizant of OSC Chemistry Advisor's Post-Accident Sampling Activities.

NOTE: From the time a decision Is made to take a PASS sample, the results must be obtained In three (3) hours. A PASS should not (normally) be requested until post-accident conditions are stable enough to provide for useful evaluation results.

Determines the impact of the incident on radwaste and various effluent treatment systems.

Assist the RADCON Manager in Dose Assessment Calculations using EPIP-1 3, Initial Dose Assessment For Radiological Emergencies.

Maintains the release rate portion on the Chemistry Status Board.

Completes portions of plant parameter data sheets (Appendices R and S) as needed.

Provides assistance to the SED and Technical Assessment Manager as needed.

PAGE 36 OF 60 REVISION 26

WBN ACTIVATION AND OPERATION OF EPIP-6 l THE TECHNICAL SUPPORT CENTER APPENDIX K NRC COORDINATOR Pagel of 2 Initial Activation of The Technical Support Center Checklist Date:

Inits/Time L ENTER badge into the TSC Accountability Card Reader.

I_ SIGN IN on the OrganizationallStaffing Chart and PUT ON position badge.

/ NOTIFY SED and OPS Manager of arrival.

L ESTABLISH log of communicationslevents.

CHECK the status of plant conditions and emergency actions already in effect such as Accountability or Site Evacuation.

I RELIEVE the Control Room of responsibility for maintaining contact with the NRC, (ENS).

CALL NRC to inform them that you have assumed responsibility for contact from the Control Room.

I PROVIDE this completed checklist to the SED or EP Manager.

PAGE 37 OF 60 REVISION 26

v :-

WBN ACTIVATION AND OPERATION OF EPIP-6 THE TECHNICAL SUPPORT CENTER APPENDIX K NRC COORDINATOR Page 2 of 2 Operational Responsibilities

Acts as primary liaison with onsite NRC personnel.

Remains fully cognizant of emergency and plant conditions.

Updates NRC personnel on plant status (use Appendix T-as a guide when ICS is unavailable).

Provides information requests from NRC to TSC personnel.

PAGE 38 OF 60 REVISION 26

WBN WlN I ACTIVATION AND OPERATION OF THE-TECHNICAL SUPPORT CENTER EPIP-6 APPENDIX L CONTROL ROOM COMMUNICATOR Page 1 of-1 Initial Activation of The Technical Supoort Center Checklist Date:

lnitslTime ENTER badge into the Accountability Card Reader.

_I/_ S;IGN IN on the Organizational/Staffing Chart and PUT ON position badge.

/_ NOTIFY SED of arrival.

/I REPORT to the TSC to obtain headset.

REPORT to Control Room and establish the Main Control Room "party

-~ line". Obtain headset/transmitter and activate amplifier at SM console - Dial 4101 for contact.

ESTABLISH contact with the Operations Manager and the other party line receivers (Status Board Writer, OSC OPS Advisor, TSC OPS Communicator).

/_ PROVIDE this completed checklist to the SED or EP Manager.

Operational Resoonsibilities

Serves as the control room - operations communications interface.

Provides key plant parameters and critical safety function conditions and other information as requested over the operations "party line" to various positions in the TSC, OSC, and CECC.

Provides operational knowledge for status evaluation of plant systems.

PAGE 39 OF 60 REVISION 26

WBN ACTIVATION AND OPERATION OF EPIP-6 THE TECHNICAL SUPPORT CENTER APPENDIX M EP MANAGER Page 1 of 2 Initial Activation of The Technical Support Center Checklist Date:

Inits/Time

/_ ENTER badge into the TSC Accountability Card Reader.

I SIGN IN on the Organizational/Staffing Chart and PUT ON position badge.

L NOTIFY SED of arrival.

ESTABLISH log of communications/events.

CHECK the status of emergency actions already in effect such as Accountability or Site Evacuation.

/_ ENSURE checklists are distributed and are being completed. INFORM SED when key staff are present.

/_ ENSURE all essential positions are filled by qualified responders who are fit for duty and checklists are returned.

CALL TSC Clerks to come to the TSC as necessary.

ENSURE all activation activities are proceeding normally.

ENSURE operability of backup communications.

/_ ENSURE that initial conditions data are transmitted to the CECC.

Data may include equipment status, core status, and a copy of the latest RCS coolant chemical analysis.

I_ ANNOUNCE activation of the TSC and provide SED (name) on the Plant PA and instruct AUOs in the plant to report to the OSC staging area once they have completed previous missions assigned by the Main Control Room.

PAGE 40 OF 60 REVISION 26

i :: i- .1i C WBN ACTIVATION AND OPERATION OF

. THE TECHNICAL SUPPORT CENTER APPENDIX M EPIP-6 I

EP MANAGER Page2of2 Operational Responsibilities

Advises the SED regarding the REP, use of EPIPs, emergency equipment use and availability, and coordination with the CECC.

Confirm completion of action steps in EPIPS 2 - 5.

Confirms TSC and OSC are operating properly.

Monitor fitness for duty (ie. fatigue) for the response team and make recommendations to the SED as needed.

Provides assistance to the SED as requested.

Coordinates food and lodging requirements for the ERO with the CECC.

Assist the SED by making PA announcements to update plant personnel of emergency status.

The EP Manager is authorized to activate the TSC if the incoming SED has been delayed. The SMSED will be notified that Emergency classifications, Protective Action Recommendations and Emergency Dose Authorizations will remain with the SMISED.

DEACTIVATION RESPONSIBILITIES Refer to EPIP-16.

PAGE 41 OF 60 REVISION 26

WBN ACTIVATION AND OPERATION OF EPIP-6

. WN ITHE TECHNICAL SUPPORT CENTER APPENDIX N I Intentionally Deleted Page 1 of 1 Nuclear Engineering personnel are available on the TAT Teams and do not require a separate and repetitive Activation Checklist.

This appendix will remain in its current state/position for future use.

PAGE 42 OF 60 REVISION 26

WBN l -ACTIVATION AND OPERATION OF EPIP-6 WBN ITHE TECHNICAL SUPPORT CENTER 0 APPENDIX 0 TSC LOGKEEPER Page 1 of 1 Initial Activation of The Technical SuDport Center Checklist Date:

Inits/Time

_/_ ENTER badge into the TSC Accountability Card Reader.

/_ SIGN IN on the Organizational/Staffing Chart and PUT ON position badge.

REPORT to the SED and begin a log of his/her activities.

_I_ RECORD significant information on the TSC Sequence of Events board.

PROVIDE this completed checklist to the SED or EP Manager.

Operational Responsibilities

Maintains official logs of the events and SED activities.

Initiates the shift turnover list as directed by the SED.

PAGE 43 OF 60 REVISION 26

WBN ACTIVATION AND OPERATION OF EPIP-6 THE TECHNICAL SUPPORT CENTER !

APPENDIX P TSC CLERICAL STAFF Page lof2 Initial Activation of The Technical Sunoort Center Checklist Date:

Inits/Time L ENTER badge into the TSC Accountability Card Reader.

I SIGN IN on the Organizational/Staffing Chart and PUT ON position badge.

/_ DISTRIBUTE manuals and TSC supplies and operate equipment as requested.

ENSURE that EPIPs are at the appropriate revision level.

/ ASSIST TSC personnel in obtaining their TLDs.

Deactivation of the TSC I COLLECT all logs, notes, and other materials from each TSC position and PROVIDE them to the EP Manager for documentation and storage.

ASSIST in the deactivation of the TSC by returning all equipment, supplies and manuals to the proper storage cabinets.

L PROVIDE this completed checklist to the SED or EP Manager.

PAGE 44 OF 60 REVISION 26

WBN lACTIVATION AND OPERATION OF lIEPIP-6

- THE TECHNICAL SUPPORT CENTERL]

APPENDIX P TSC CLERICAL STAFF Page 2 of 2 Operational Resionsibilities

Assist in the set up of the TSC.

Maintains accountability of TSC personnel and staff organization board.

Answers telephones.

Distributes plant parameter data sheets (Appendices R, S. & T), if ICS in unavailable.

Uses Emergency Response Call List to obtain staff for unfilled positions or replacement staff for shift turnover using Appendix W, "Emergency Responder Notification Form". Ensure that the following directions relative to call-in for unscheduled work per the "Fitness For Duty" (SPP-1.2) are followed: ASK responder the following questions:

1. "Have you consumed alcohol in the past five hours?"

2. "Are you fit for duty?"

If the first question is answered in the affirmative, call the next person on the call list unless the individual indicates that he is fit for duty in which case you should refer the determination to a supervisor.

Operates facsimile machines.

Operates CECC computer.

PAGE 45 OF 60 REVISION 26

A- ,- -- I l

WBN l ACTIVATION AND OPERATION OF I THE TECHNICAL SUPPORT CENTER l EPIP-6 I

APPENDIX Q TECHNICAL ASSESSMENT TEAM Page 1 of 3 Initial Activation of The Technical Support Center Checklist Date:

Inits/Time

_/_ ENTER badge into the TSC Accountability Card Reader.

/ SIGN IN on the Organizational/Staffing Chart and PUT ON position badge.

/ ESTABLISH log of communications/events.

j _/ ESTABLISH contact with the Technical Assessment Manager.

CHECK the status of emergency actions already in effect such as Accountability or Site Evacuation.

/ PROVIDE this completed checklist to the SED or EP Manager.

PAGE 46 OF 60 REVISION 26

l WBN ACTIVATION AND OPERATION OF I EPIP-6 APPENDIX Q TECHNICAL ASSESSMENT TEAM Page 2 of 3 Operational Resnonsibilities

Team Leader may designate TSC Logkeeper and Board Writer as directed by the TAM.

Prepares and provides current assessment on plant conditions and provides this information to the CECC Plant Assessment Team.

Reviews TI-128, Post Accident Technical Considerations (TSC)," for additional information which may be applicable to the ongoing events.

Project future status based on present plant conditions.

Provide technical support and recommendations to plant operations on mitigating the accident.

Determines the condition of the reactor and nuclear fuel.

If ICS is unavailable, prepares accident assessment form (Appendix T) for the TAM and NRC Communicator as warranted.

Provides Predictive Release Data Sheet (Appendix S) to the CECC as requested.

Performs trending of key plant parameters using ICS.

Assumes SAMG responsibilities, when directed by the TAM. The TSC must be functional and 3 SAMG Evaluators must be monitoring the "TSC Diagnostic Flow Chart" (DFC) to assume SAMG responsibilities.

PAGE 47 OF 60 REVISION 26

WBN rACTIVATION AND OPERATION OF EPIP-6 WBN ITHE TECHNICAL SUPPORT CENTER APPENDIX Q TECHNICAL ASSESSMENT TEAM Page 3 of 3 Operational Responsibilities (continued)

Verifies that all Aux. Bldg. Secondary Containment Enclosures (ABSCE) doors are closed. (SOI-30.06, Auxiliary Building Gas Treatment System, Checklist 3 or Fire Protection)

Identifies and tracks the status of current ABSCE breaches. (Contact HVAC System Engineer for Breaching Log status)

Verifies that all Emergency Control Room Pressurization Boundary (ECRPB) doors are closed.

Identifies and tracks the status of current ECRPB breaches.

PAGE 48 OF 60 REVISION 26

l BN

__WBN l ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER EPIP-6 I

APPENDIX R Plant Parameter Data Sheets Page 1 of 6 DATE: -TIME: UNIT:

NOTE: Unit status updates can be gained from the ICS computer utilizing the TSC Mimics and the following subgroups: REPI, REP2, 2PS1, 3MS1, 4S1, or SPDS.

Refer to the ICS System Users Guide for additional information. If the ICS is inoperable, utilize the sheets of this appendix to trend/track needed data.

1. CST LEVEL: (LI-2-230A)L. (LI-2-233A)_ GAL

2. SG HEAT SINK a CONDENSER ATMOSPHERE

3. AFW PUMPS RUNNING: A-A O B-B: TD

\,d 4. SG LEVELS: NR: (1) (2) (3) (4) %

(LI-3-39) (LI-3-52) (LI-3-94) (LI-3-107)

WR: (1) (2) (3) (4) %

(LI-3-43A) (LI-3-56A) (LI-3-98A) (Ll-3-111A)

5. SG PRESSURES: (I M_ _Zkl - (2j (3$ _ _ (4 9TT 2 PSIG PI-1-9A) 7;5

6. RVLIS: DYNAMIC RANGE % STATIC %

7. PZR LEVEL: (LI-68-335A) (LI-68-320) %

(COLD CAL) (HOT CAL)

8. PZR PRESSURE: (PI-68-342A) _(PI-68-340A) - PSIG

9. RCS PRESSURE: (LOOP 3 HOT LEG) (P1-68-64) PSIG

10. HL TEMP: WR (1) (2) -(3) _SZ3 (4j OF 41-68-1 (TI-694A) (1483 (TPUSZE)

1. CL TEMP: WR () (2) -:4 (3)1~ (4)=g °F ITIM8-767 ( l81 -1T80 1Z-PAGE 49 OF 60 REVISION 26

's _~-_Ri - :

.~~VNACIAIN AN OERATIO OF EPIP-6

THE TECHNICAL SUPPORT CENTER APPENDIX R Plant Parameter Data Sheets Page 2 of 6 DATE: TIME: UNIT:

12. RCS FLOW: RCP's RUNNING: 01 2 0 3 0l4 0 NATURAL CIRC

13. ECCS STATUS: STANDBY 0 INJECT O RECIRC 0 SPRAY

14. RWST LEVEL: (LI-63-50) GAL (LI-63-51) .GAL

15. CNTMT SUMP LEVEL: (LI-63-176) %

16. FLOWRATE: (FI-62-93) GPM (FI-63-170) - GPM CHARGING BIT

17. CNTMT PRESSURE: NR (P-30-44) (P-30-45) PSID

18. INCORE THERMOCOUPLES:

QUAD 1 - (1 of #41,28,24,56,55,29,6) °F QUAD 2-(1 of #44,22,58,21,16,63,64) °F QUAD 3 - (1 of #54,12,8,40,4,3,7) OF QUAD 4 - (1 of #60,9,45,6,46,42,36) °F

19. NIS SOURCE RANGE: (N-131) CPS (N-132) CPS

20. SUB COOLING MARGIN OF -OF (TI-68-105) (TI-68-1 15)

21. STATUS TREE INDICATING:

RED 0 REASON:

ORANGE 0 REASON:

DATA BY

PAGE 50 OF 60 REVISION 26

WBN ACTIVATION AND OPERATION OF EPIP-6 THE TECHNICAL SUPPORT CENTER .

APPENDIX R Plant Parameter Data Sheets Page 3 of 6 DATE: TIME: UNIT:

RADIATION MONITORS NOTE: UNIT STATUS UPDATE SHEETS (FOR USE WHEN TSCIICS COMPUTER IS INOPERABLE)

1. LOWER CNTMT (1-RE-90-106) (A) PARTICULATE __CPM O ISOLATED 0 TO LOWER (B) TOTAL GAS - CPM O TO UPPER

2. UPPER CNTMT (1-RE-90-112) (A) PARTICULATE CPM O ISOLATED 0 TO UPPER (B) TOTAL GAS CPM O TO LOWER (C) IODINE CPM

3. SHIELD BLDG VENT (1&2-RE-90-400) TOTAL GAS U1 U2 -. pCi/cc FLOW -CFM

4. AUXILIARY BLDG VENT (0-RE-90-101) (A) PARTICULATE_ CPM IJ ISOLATED (B) TOTALGAS - CPM FLOW CFM (C) IODINE CPM

5. CONDENSER EXHAUST (LR) CPM FLOW CFM (1-RE-90-119) (FT-2-256) lNOTE: ICS radiation monitor(s) RE identifications may be referenced as RM In the MCR.

PAGE 51 OF 60 REVISION 26

=F I

ACTIVATION AND OPERATION OF EPIP-6 WBN THE TECHNICAL SUPPORT CENTER I

-APPENDIX R Plant Parameter Data Sheets Page 4 of 6

6. STEAM LINE RAD MONITORS: 1-RE-90-421 mR/hr 1-RE-90-422 _ __mR/hr 1-RE-90-423 _ _ mR/hr 1-RE-90-424 rmR/hr STEAMFLOW (MCR) 1-Fl-1 -3A(3B) SG1 1bm/hr.

I-Fl-1-1 OA(I OB) SG2 ___1 bm/hr.

1-Fl-1 -21 A(21 B) 5G3 I bm/hr.

I-FI-1-28A(28B) SG4 1bm/hr.

7. SERVICE BLDG VENT _ CPM FLOW CFM 0-RE-90-132

8. SG BLOWDOWN: _______CPM CPM 1-RE-90-120 1-RE-90-121

9. ERCW DISCHARGE: HEADER A: _CPM CPM 0-RE-90-133 0-RE-90-140 HEADER B: _ CPM CPM 0-RE-90-134 0-RE-90-141

10. Additional monitors in alarm (trend as needed).

DATA BY:

PAGE 52 OF 60 REVISION 26

WBN l ACTIVATION AND OPERATION OF EPIP-6 THE TECHNICAL SUPPORT CENTER APPENDIX R Plant Parameter Data Sheets Page 5 of 6 DATE: TIME: UNIT:

POST-ACCIDENT RADIATION MONITORS NOTE: UNIT STATUS UPDATE (FOR USE WHEN TSC/ICS COMPUTER IS INOPERABLE)

1. UPPER CNTMT: (TOP OF #2 & #3 SG) I -RE-90-271: - R/hr (TOP OF #1 & #4 SG) 1-RE-90-272: R/hr

2. LOWER CNTMT: (BETWEEN #2 & #3 SG) 1-RE-90-273: R/hr (BETWEEN #1 & #4 SG) -RE-90-274:- R/hr

3. COND VAC EXHAUST: (mid.R/1-RE-90-404A)_(HR1-RE-90-404B)_CPM

4. Additional monitors in alarm (trend as needed):

DATA BY:

PAGE 53 OF 60 REVISION 26

sx - X WBN I ACTIVATION AND OPERATION OF EPIP6 THE TECHNICAL SUPPORT CENTER APPENDIX R Plant Parameter Data Sheets Page 6 of 6 INOTE: UNIT STATUS UPDATE (FOR USE WHEN TSC/iCS COMPUTER IS INOPERABLE)

DATE: _ TIME: - UNIT:

RADIOLOGICAL RELEASE DATA

1. RELEASE POINT: ---

2. RELEASE RATES: CIRCLE ONE: DECREASING STABLE INCREASING UNKNOWN

AIRBORNE------------LIQUID RELEASE ---------

ISO- CONCENTRATION FLOWRATE TOTAL-RELEASE RELEASES Ci/SEC TOPE VALUE UNITS VALUE UNITS VALUE UNITS NOBLE GAS_

IODINES PARTICULATE COMBINED RELEASE ISOTOPE RELEASE RATE

3. RELEASE BEGAN EXPECTED TO END _ EST/EDT. DURATION HR RELEASE POTENTIAL: .I Ci, IN VOLUME OF (CU FT OR GAL)

4. METEOROLOGICAL CONDITIONS: (IF REQUESTED DUE TO MET DATALINK INOPERABLE)

DATE TIME WIND SPEED DIRECTION ELEVATION TEMPERATURE (MPH or METERS) (DEGREES) (METERS) DIFFERENTIAL

5. REMARKS/COMMENTS:

DATA BY:

PAGE 54 OF 60 REVISION 26

WBN - ACTIVATION AND OPERATION OF EPIP-6 l WBN ITHE TECHNICAL SUPPORT CENTER ! I APPENDIX S Predictive Release Data Sheet Page 1 of I DATE: TIME: UNIT:

DATA NEEDED FOR CECC TO PERFORM PREDICTIVE RELEASE METHODOLOGY

1. PRIMARY COOLANT CONCENTRATION IN GAS IN LIQ ISOTOPE pCi/cc pCi/ml SAMPLE DATA I-131 DATE: TIME:

I-132 I-133 LOCATION:

I-134 I-135 TEMPERATURE:

CS-137 CS-138 PRESSURE PSIA KR-85m KR-85 GAS VOLUME: Cc KR-87 KR-88 WATER MASS: GRAM XE-133 XE-135 WATER LEVEL:

2. CONCENTRATION OF HYDROGEN IN CONTAINMENT ATMOSPHERE H2 CONC (MOLE %): _ DATE:

CNTMT TEMP: OF TIME: _

CNTMT PRESS PSI LOCATION:

3. OPERATING POWER HISTORY IF CECC/ICS DATALINK INOPERABLE)

DATE/TIME OF SHUTDOWN:

START END AVG POWER START END AVG POWER PERIOD PERIOD IN MWt PERIOD PERIOD IN MWt

4. CORE EXIT THERMOCOUPLE READINGS (IF CECC/ICS DATALINK INOPERABLE)

THERMOCOUPLE DATE TIME READING NOTES:

NUMBER (F)

5. REACTOR WATER LEVEL HISTORY (IF CECC/ICS DATALINK INOPERABLE)

DATE TIME READING RCS VOL NOTES:

(UNITS) (CU FT)

Send to: CECC Core Damage CECC RAC. DATA BY PAGE 55 OF 60 REVISION 26

WBN l ACTIVATIONAND OPERATION OF EPIP-6 THE TECHNICAL SUPPORT CENTER ! I APPENDIX T TSC Accident Assessment Summary Sheet Page 1 of 1 NOTE: This Status Update Sheet Is for use when the TSC ICSIERDS data systems are inoperable.

TO: Tech. Assmt. Mgr. & NRC Coordinator and CECC Plant Assessment Team FROM: WBN Tech. Assmt. Team 1.HEAT REMOVAL CAPABILITY (Core Cooling, Heat Sink, RSC Inventory):

Status Tree:

11. FUEL INTEGRITY (Subcriticality, RCS Radionuclide):

Ill. RADIOACTIVITY IN CONTAINMENT; IV. CONTAINMENT INTEGRITY:

Status Tree:

V. OVERALL ASSESSMENT & RECOMMENDATIONS:

Prepared by WBN EXT..

Time PAGE 56 OF 60 REVISION 26

WBN ACTIVATION AND OPERATION OF EPIP.6 WTHE TECHNICAL SUPPORT CENTER I APPENDIX U Protective Action Recommendation

-Page 1 of 1 INOTE: Ifconditionsareunknownutilizingtheflowchart,thenanswerNO. l aeneral Emergenc CONTINUE ASSESSMENT

Modify protective actions based on available plant and field monitoring information.

Locate and evaluate localized

_ hot spots. I-

/ At \ 4 or beyond 5 miles is the Projected NO or Measured Dose 4

Greater than FAG

\Table 1Liit/A p

E RECOMMENDATION 1 RECOMMENDATION 2 1'

EVACUATE 2 miles radius EVACUATE 2 mile radius and 10 miles downwind and 5 miles downwind AND AND SHELTER remainder of SHELTER remainder of 10 mile EPZ 10 mile EPZ I B TABLE I Drnt.63. .o A at;: r_..804^ei 9 I lL_ t1VU III..UUI I VWUIUt:

TYPE LIMIT Measured 3.9E-6 microCilcc of Iodine 131 or 1 REM/hr External Dose Projected 1 REM TEDE or 5 REM Thyroid CDE PAGE 57 OF 60 REVISION 26

WBN U ACTIVATION AND OPERATION OF EPIP-6 THE TECHNICAL SUPPORT CENTER APPENDIX V Reference Materials and Equipment List Page 1 of 1 The following reference materials are provided in the TSC:

1. Watts Bar Nuclear Plant FSAR.

2. Watts Bar Nuclear Plant Technical Specifications (Unit 1).

3. Surveillance Instructions (Selected). (Note Below)

4. Technical Instructions (Selected). (Note Below)

5. Radiological Control Instructions.

6. System Operating Instructions.

7. General Operating Instructions.

8. REP and WBN and CECC Emergency Plan Implementing Procedures

9. Plant Functional Drawings.

10. Abnormal Operating Instructions.

11. Emergency Operating Procedures.

12. Westinghouse Emergency Response Guidelines. (Note2 Below)

13. WOG, ERG Maintenance Direct Work Item DW-97-002 Response (Emergency Response Guidelines, Background Information).

14. Hand-held calculators.

15. Office supplies for use in the TSC.

NOTE: 1: Selection to be made by Technical Assessment Team Leader(s) or Technical Assessment Manager(s) and approved by the Emergency Preparedness Manager.

NOTE: 2: Obtain copy from Site Westinghouse Representative or Master Files.

PAGE 58 OF 60 REVISION 26

WBN l ACTIVATION AND OPERATION OF EPIP-6 WBN . THE TECHNICAL SUPPORT CENTER I APPENDIX W EMERGENCY RESPONDER NOTIFICATION FORM Page 1 of 1 Fitness for Duty Person Calling Date Department Name Time rime Alcohol 5 Hrs. Fit for Overtime Duty Called Needed to Prior to Report Duty restricted Official Report (YIN)_____ (1) Comments (1)REFER TO SPP-1.5, Overtime Restrictions (Regulatory)

PAGE 59 OF 60 REVISION 26

WBN WBN I 0lACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER EPIP-6 APPENDIX X WBN TSC Sign-In Roster Page1 of 1 NAMENAME (Print)

( Print) ~SociaNumber SecurtySintr Signature Replacement within12hoursIo Position/Role

0~~~~~~~~YsN

_ _ _ _ _ _ I

__ _ I _ _ _ _- I I Date of TSC Activation WBN EP Records Coordinator PAGE 60 OF 60 REVISION 26

ML032550049

Text

2.0 REFERENCES

2.0 REFERENCES

1.0 INTRODUCTION

2.0 REFERENCES

2.0 REFERENCES

2.0 REFERENCES

2.0 REFERENCES

Description:

Navigation menu

Search