Text

Emergency Plan Implementing Procedure Change
	ML022480167
Person / Time
Site:	Vermont Yankee
Issue date:	08/20/2002
From:	Tkaczyk L; Entergy Nuclear Northeast, Entergy Nuclear Operations
To:	; Document Control Desk, Office of Nuclear Security and Incident Response
References
	BVY 02-63
	Download: ML022480167 (101)
	v • d • e

Entergy Nuclear Northeast Entergy Nuclear Operations, Inc S Entergy Vermont Yankee 185 Old Ferry Rd PO Box 500 Brattleboro, VT 05302 Tel 802-257-5271 August 20, 2002 BVY 02-63 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Subject:

Vermont Yankee Nuclear Power Station License No. DPR-28 (Docket No. 50-271)

Vermont Yankee Emergency Plan Implementing Procedure Change In accordance with 10 CFR 5 0.54(q), enclosed is the latest changes to the Vermont Yankee Emergency Plan Implementing Procedures, the change memos and the 10 CFR 50.54(q) Evaluation Checklists for the following:

OP 3513, Rev. 21 OP 3505, LPC#1, Rev. 24 OP 3544, Rev. 2 OP 3504, LPC#2, Rev. 34 OP 3546, LPC#2, Rev. 1 These changes were determined to not need prior NRC review and approval.

If you have any questions, please contact Audra Williams, Emergency Planning Coordinator, in our Brattleboro office at (802) 258-4177.

Sincerely, ENTERGY NUCLEAR NORTHEAST VERMONT YANKEE

-1/

Emergency Planning Manager Attachments cc: USNRC Region 1 Administrator USNRC Resident Inspector - VYNPS USNRC Project Manager - VYNPS David M. Silk, Senior Emergency Preparedness Specialist, USNRC Region 1 Vermont Department of Public Service

,4o4S

Vermont Yankee Emergency Plan Implemeniting Procedures Table of Contents August 20, 2002 Emergency Plan Classification and Action Level Scheme AP 3125 Rev. 18 "R" Emergency Communications OP 3504 Rev. 34 "R" OP 3505 Rev. 24 'TI Emergency Preparedness Exercises and Drills Emergency Equipment Readiness Check OP 3506 Rev. 41 "R" Emergency Radiation Exposure Control OP 3507 Rev. 29 "R" On-Site Medical Emergency Procedure OP 3508 Rev. 23 "R" Environmental Sample Collection During an Emergency OP 3509 Rev. 17 "R" Off-Site and Site Boundary Monitoring OP 3510 Rev. 26 "R'"

Off-Site Protective Action Recommendations OP 3511 Rev. 11 "R" Evaluation of Off-Site Radiological Conditions OP 3513 Rev. 21 "R" Emergency Actions to Ensure Accountability and Security Response OP 3524 Rev. 19 "R" Radiological Coordination OP 3525 Rev. 9 "R" Emergency Call-In Method OP 3531 Rev. 15 "R" AP 3532 Rev. 10 "I" Emergency Preparedness Organization OP 3533 Rev. 5 "C" Post Accident Sampling of Reactor Coolant OP 3534 Rev. 3 "Cit Post Accident Sampling of Plant Stack Gaseous Releases OP 3535 Rev. 4 "C" Post Accident Sampling and Analysis of Primary Containment OP 3536 Rev. 1 "C" In Plant Air Sample Analysis with Abnormal Condition Control Room Actions During an Emergency OP 3540 Rev. 1 "R" Activation of the Technical Support Center OP 3541 Rev. 1 "R" OP 3542 Rev. 1 "R" Operation of the Technical Support Center Operation of the Operations Support Center OP 3544 Rev. 2 "R" OP 3545 Rev. 1 "R" Activation of the Emergency Operations Facility/Recovery Center Operation of the Emergency Operations Facility/Recovery Center OP 3546 Rev. I "R" Security Actions During an Emergency OP 3547 Rev. 1 "R" OP 3712 Rev. 16 "I" Emergency Plan Training

VERMONT YANKEE NUCLEAR POWER STATION

OPERATING'RO CEDURE-

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OP 3513 REVISION 21 EVALUATIONS OF OFF-SITE RADIOLOGICAL CONDITIONS USE CLASSIFICATION: REFERENCE LPC Effective No. Date Affected Pages Implementation Statement: N/A Issue Date: 08/20/2002 OP 3513 Rev. 21 Page 1 of 9

TABLE OF CONTENTS 3

D ISCU SSIO N .....................................................................................................................................................

ATTAC IMEN TS ..............................................................................................................................................

REFERENCES ANT) COMMITMENTS ...........................................................................

PRECAIJTIONSILJM]TATIONS....................................................................................

RESPONSIBILIIES................................................................................................. 6 6

PR O CED U REN .............................................................................................................................................

Initial EvaluationM ...... ...................................................................................................... 6 RE C 7

I. Subsequent Evaluation ...............................................................................................................

9 FIN A L C ONDIT IO N SS ......................................................................................................................................

OP 3513 Rev. 21 Page 2 of 9

PURPOSE To specify the methodology utilized to evaluate the off-site radiological consequences involving an elevated (stack) or ground level release of radioactivity during accident conditions.

DISCUSSION This procedure consists of two sections as follows:

SECTION TITLE RESPONSIBILITY METHODS I Initial Evaluation CONTROL ROOM - Shift ODPS (Off-Site Dose Supervisor/Plant Emergency Projection System), Off-Site Director (SS/PED) Dose Nomogram, or Measured Site Boundary Dose Rate EOF Radiological Assistant METPAC Computer II Subsequent (Primary), ODPS (Backup),

Evaluation or Off-Site Dose Nomogram (Backup)

During the initial stages of an emergency where an actual release of radioactivity has occurred, the SS/PED will be responsible to perform the initial evaluation of off-site radiological conditions. For other emergencies involving a potential release of radioactivity, (e.g., high level activity in containment, but no actual release), the Radiological Assistant will be responsible to perform the initial evaluation of off-site radiological conditions should an actual release occur.

The initial evaluation of off-site radiological conditions will be accomplished by utilizing the Off-Site Dose Projection System (ODPS), the Off-Site Dose Nomogram or Measured Site Boundary Dose Rate (refer to Section I of this procedure).

Following the initial evaluation and upon activation of the EOF, a subsequent method to further evaluate and refine the initial off-site dose projections will be performed by appropriate personnel located at the EOF. The METPAC Computer System and field-data monitoring information will be utilized to perform subsequent evaluation of off-site radiological conditions (refer to Section II of this procedure).

OP 3513 Rev. 21 Page 3 of 9

In order to help qualitatively define plume width, a transparent overlay has been prepared for the area base map. This transparency consists of three colored angles as follows:

Blue For all unstable meteorological classes (Stability Class A, B, or C)

Red For neutral meteorology (Stability Class D)

Orange For all stable meteorological classes (Stability Class E, F, or G) of Included within each angle are areas lateral to the plume centerline having I131 concentrations angles over the at least 5% of the plume centerline value. Centering the stability-dependent appropriate downwind direction on the area base map will help qualitatively define the plume can width. Using the sector/zone designation appropriate to the plume width, Vermont Yankee dose provide State officials with the affected area and corresponding off-site radiological projections out to ten miles.

Off-site protective action recommendations shall be made based on the guidelines established in OP 3511.

In accordance with AP 6002, Preparing 50.59 Evaluations, the results of an Applicability changes provided the Determination (AD) has determined that an AD is not required for future The basis scope of the procedure or program is not revised to include a different type of activity.

Implementing Procedure and is subject for this conclusion is that this document is an Emergency Emergency Plan to 10CFR50.54(q) to determine if the changes decrease the effectiveness of the and the and if they have the potential to affect our ability to meet the standards of 10CFR50.47(b) requirements of 10CFR50 Appendix E.

ATTACHMENTS

1. Table 1 Deleted

2. Table II VY Primary and Backup Towers AT/Stability Criteria

3. Table IIl Air Sample Codes for 1-131 Air Concentrations

4. VYOPF 3513.01 Dose Assessment Status Form

5. VYOPF 3513.02 Isotopic Analysis

6. VYOPF 3513.03 Field Data Status Log

7. VYOPF 3513.04 Doses at Selected Locations

8. VYOPF 3513.05 Deleted

9. Figure I Initial Dose Assessment & PAR Sequence

10. Figure I1 Vermont Yankee Emergency Dose Rate Nomogram

11. Figure IlI Field Sample Thyroid Dose Nomogram

12. Appendix A Deleted

13. Appendix B Off-Site Dose Projection Methodology When ODPS is Inoperable

14. Appendix C Field Data Monitoring

15. Appendix D METPAC Computer Input Sequence and Instructions

16. Appendix E Description of METPAC Options and Operational Features

17. Appendix F Deleted

18. Appendix G Off-Site Dose Projection System (ODPS) Input Sequence and Format

19. Appendix H Manual Source Term Data Acquisition

20. Appendix I Manual Meteorological Data Acquisition OP 3513 Rev. 21 Page 4 of 9

21. Appendix J Multiple Release Assessment

22. Appendix K Guidelines for "What If" Projection of Potential Radioactive Material Releases REFERENCES AND COMMITMENTS

1. Technical Specifications

a. None

2. Codes, Standards, and Regulations

a. 10 CFR 50, Appendix E

3. Commitments

a. None

4. Supplemental References

a. VY Meteorology System Manual

b. METPAC, Technical Reference Manual

c. DP 0530, Report #51

d. OP 2611, Stack Effluent Sampling and Analysis

e. AP 3125, Emergency Plan Classification and Action Level Scheme

f. OP 3510, Off-Site and Site Boundary Monitoring

g. OP 3511, Off-Site Protective Action Recommendations

h. AP 6807, Collection, Temporary Storage and Retrieval of QA Records PRECAUTIONS/LIMITATIONS

1. Since significant changes in meteorological, plant radiological, and plant status conditions can occur, frequent checks on conditions are important.

2. Meteorological data obtained from Met Data History 1 and 2 on ERFIS are data averaged over 15-minute intervals, presented over the past six hours. A separate screen, METPAC PARAMETERS (MPP), represents instantaneous readings at the designated time.

3. The Off-Site Dose Nomogram method will conservatively provide higher dose predictions at the site boundary than the ODPS or METPAC method due to model sophistication involving the effective stack height and formulation of meteorological parameters. The Off-Site Dose Nomogram basic purpose is to initially scope the magnitude of the release rather than provide a precise site boundary dose rate.

OP 3513 Rev. 21 Page 5 of 9

4. Comparison between dose projection methods and off-site monitoring measurements should be reviewed carefully. The user should realize that dose projection methods use meteorological conditions that reflect a 15-minute average condition. However, wide variation in wind speed and direction can occur during that time interval which real-time off-site monitoring measurements would reflect.

5. Accurate reported locations of off-site monitoring team data are necessary, given the significance of these data in the evaluation of off-site radiological conditions.

6. To run ODPS for an unmonitored (ground) release, a site boundary dose rate and the estimated time of release are necessary input.

RESPONSIBILITIES

1. Shift Supervisor/Plant Emergency Director (SS/PED):

Responsible for performing the initial dose calculations within this procedure until relieved by the appropriate personnel at the Emergency Operations Facility (EOF).

2. Radiological Assistant:

Responsible for performing the subsequent dose calculations and evaluations within this procedure.

PROCEDURE I. Initial Evaluation A. Immediate Action by the SS/PED or Designated Plant Staff Member

1. Upon receiving an indication of a significant release of radioactivity is occurring and the EOF has not been activated, initiate or assign a qualified individual to perform the appropriate calculations in this procedure to evaluate the off-site radiological conditions.

NOTE Figure I is a flow chart available to assist in the identification of dose assessment activities to be considered and implemented.

2. For an actual ground release, dispatch a Site Boundary Team to obtain a whole body dose rate reading at the fence line in the downwind direction of the release in accordance with OP 3510, and record field data on VYOPF 3513.03.

OP 3513 Rev. 21 Page 6 of 9

3. If the Stack High Range Monitor equals or exceeds 20 mR/hr, request the Chemistry Technician to obtain a silver zeolite cartridge air sample from the main stack sample point for an iodine release rate determination.

4. If ODPS is operable, then implement Appendix G to access off-site dose projection information from ODPS.

5. If ODPS is inoperable, then implement Appendix B to perform the applicable off-site dose projections.

B. Subsequent Actions

1. If significant changes occur in meteorological or radiological conditions, repeat applicable steps in Section L.A to re-evaluate off-site radiological conditions.

2. Upon activation of the EOF, the TSC Coordinator or designated individual will forward applicable dose assessment results and data to the Radiological Assistant if necessary or required.

IT. Subsequent Evaluation A. Actions by the Radiological Assistant or Designated Qualified Individual

1. If release has started before EOF activation, determine the status of actions performed in Section I of this procedure from the TSC Coordinator or designated individual.

NOTE Appendix H and Appendix I provide methods to acquire radiological (source term) and meteorological data, respectively.

2. Obtain information on radiological (source term) and meteorological data to evaluate off-site radiological conditions to include as needed the following information (refer to VYOPF 3513.01):

a. Time and date of the reactor scram.

b. Time and date of start of any release(s).

C. Type of any release(s).

d. Duration of any release(s).

OP 3513 Rev. 21 Page 7 of 9

e. Stack High Range Monitor reading, stack flow rate, and site boundary dose rate.

f. Quarter-hour meteorological data from the beginning of any release(s).

g. Latest estimated projected doses and plume arrival time at the site boundary, 2, 5, 10 miles.

h. In-plant chemistry sample information (if available) to include reactor coolant, drywell, and plant stack sample results.

i. Containment High Range Monitor readings, in-plant area and process rad monitor readings, and SBGTS status information.

j. Protective Action Recommendation(s) if any were made to state authorities.

3. Based on plant conditions and information obtained from radiological and meteorological data, coordinate the assessment of off-site dose projections and calculations by using one or more of the following methods:

a. METPAC (Primary) - Refer to Appendix D.

b. ODPS - Refer to Appendix G.

c. Nomogram - Refer to Appendix B.

d. Field Data Monitoring Results - Refer to Appendix C.

e. Multiple Release Assessment - Refer to Appendix J.

f. Guidelines for "What If' Projection of Potential Radioactive Material Releases - Refer to Appendix K.

4. Review dose assessment calculation results and dose calculation parameters/assumptions utilized.

OP 3513 Rev. 21 Page 8 of 9

5. As dose projection information becomes available, perform the following actions:

a. Implement Section HIof OP 3511 to formulate Protective Action Recommendations for that state's authorities.

b. Review AP 3125 to evaluate the emergency classification based on site boundary radiological dose conditions and immediately inform the EOF Coordinator if site boundary radiological dose condition EALs have been reached or exceeded.

c. Forward applicable information on VYOPF 3513.01.

d. Post appropriate dose assessment information on status boards.

e. Maintain a file of printouts and completed input data forms.

6. Contact the Chemistry Manager for status of in-plant chemistry sample information to include isotopic breakdown of reactor coolant, drywell air, and effluent release data (e.g., plant stack), and utilize the results of these samples to determine source term release rate information as needed.

7. Periodically brief the EOF Coordinator on off-site dose assessment results and pertinent changes, especially updates regarding protective action recommendations.

8. Brief the Radiological Assistant staff periodically on the status of plant conditions, meteorological changes, plant radiological effluent conditions and dose assessment results.

9. As new or additional information becomes available, ensure that status boards and forms are updated and the updated information is forwarded to the EOF Coordinator for distribution.

10. Continue to update and evaluate off-site dose projections as required.

FINAL CONDITIONS

1. Turn in all data log sheets, calculations, and printouts to the Emergency Plan Coordinator for proper filing in accordance with AP 6807.

OP 3513 Rev. 21 Page 9 of 9

TABLE II VY PRIMARY AND BACKUP TOWERS AT/STABILITY CRITERIA PRIMARY TOWER AT(oF)

Stability Ground Release Elevated Release Class Stability Category Use Angle AT <-1.72 AT <-2.74 A Extremely Unstable Blue

-1.71 <AT <_-1.54 -2.73 _AT _<-2.45 B Moderately Unstable Blue

-1.53 _<AT <-1.36 -2.44 <AT <-2.16 C Slightly Unstable Blue

-1.35 <AT <-0.46 -2.15 <AT <-0.72 D Neutral Red

-0.45 _AT -+1.35 -0.71 <AT <+2.15 E Slightly Stable Orange

+1.36 _AT <+3.62 +2.16 <AT <+5.74 F Moderately Stable Orange

+3.63 _AT +5.75 <AT G Extremely Stable Orange BACKUP TOWER (33 ft. - 135 ft.)

AT (-F)

RANGE CLASS METPAC LOWER AT* METPAC UPPER AT*

AT <-1.07 A -2.0 -3.0

-1.06 <AT <-0.96 B -1.6 -2.5

-0.95 <AT <-0.84 C -1.4 -2.2

-0.83 _<AT <-0.28 D -1.0 -1.0

-0.27 <AT <+0.83 E +1.0 +1.0

+0.84 <AT <+2.23 F +2.0 +3.0

+2.24 <AT G +4.0 +6.0

Input this number into missing delta temperature field to obtain appropriate stability class.

Table II OP 3513 Rev. 21 Page 1 of 1

TABLE Il AIR SAMPLE CODES FOR 1-131 AIR CONCENTRATIONS

1-131 Air *1-131 Air Air Net Concentration Air Net Concentration

[LCi/cc Code CPM RtCi/cc Code CPM 0 <40 N/A 24 1750 1.11E-06 40 2.55E-08 25 2000 1.27E-06 1

2 60 3.82E-08 26 2250 1.43E-06 3 80 5.09E-08 27 2500 1.59E-06 4 100 6.37E-08 28 2750 1.75E-06 5 125 7.96E-08 29 3000 1.91E-06 6 150 9.55E-08 30 3250 2.07E-06 7 175 1.11E-07 31 3500 2.23E-06 8 200 1.27E-07 32 3750 2.39E-06 9 225 1.43E-07 33 4000 2.55E-06 10 250 1.59E-07 34 4250 2.71E-06 11 275 1.75E-07 35 4500 2.87E-06 12 300 1.91E-07 36 5000 3.18E-06 325 2.07E-07 37 7500 4.78E-06 13 14 350 2.23E-07 38 10000 6.37E-06 15 375 2.39E-07 39 12500 7.96E-06 16 400 2.55E-07 40 15000 9.55E-06 425 2.71E-07 41 17500 1.L1E-05 17 18 450 2.87E-07 42 20000 1.27E-05 19 500 3.18E-07 43 25000 1.59E-05 20 750 4.78E-07 44 30000 1.91E-05 1000 6.37E-07 45 35000 2.23E-05 21 22 1250 7.96E-07 46 40000 2.55E-05 1500 9.55E-07 47 50000 3.18E-05 23 air sample has

These 1-131 air concentration values are only to be used when a "standard" to count the been taken (i.e., flow rate = 1CFM;; collection time = 10 min.; RM-14 used will be for all other air samples silver zeolite cartridges). The 1-131 air concentration values calculated by using the equation in Method 2 of Appendix C.

Table IE OP 3513 Rev. 21 Page 1 of 1

DOSE ASSESSMENT STATUS FORM Time of Shutdown: Form Prepared By:

v-' RELEASE INFORMATION Date: Time:

Ground: Combination:

Stack:

hr Anticipated: hr Release Started At:

Estimated Release Duration: hrs SBGT: -] On [L- Off CLASSIFICATION LI Unusual Event 0I Alert [] Site Area E] General Date: Time:

METEOROLOGICAL/STACK/DATA AT:

PARAMETER UPPER LOWER (15 MIN. AVE.) UNITS (for Stack Release) (for Ground Release)

Wind Speed mph Wind Direction deg Delta T deg (F)

A,B,C = Blue Angle Stability Class D Red Angle E,F,G = Orange Angle Precipitation in/15 min.

Stack High Range mR/hr (Use instantaneous reading.)

Stack Flow (use instantaneous) scfm Site Boundary Dose Rate mR/hr (Measured)

Sample Analysis Performed? LI YES [] NO Weather Forecast:

CALCULATED DOSE OR DOSE ASSESSMENT RESULTS ATTACHED: EL ODPS l METPAC ELEVATED GROUND COMBINATION CDE CDE CDE PLUMB TEDE THYROID TEDE THYROID TEDE THYROID ARRIVAL TIME (R) (R) (R) (R) (R) (R)

DISTANCE At 0.35-Mile At 2-Mile At 5-Mile At 10-trifle

-1ivIIe I I I___I_____ .1_________

Reviewed By Rad Assistant (Print/Sign)

I Rad. Ass't to EOF Coord., EOF States' Reps VYOPF 3513.01 DISTRIBUTION OP 3513 Rev. 21 EOF Coord. to SRM Page 1 of 1 SRM to NRC, ESC and NMC

ISOTOPIC ANALYSIS A. SAMPLE DESCRIPTION Sample Location:

Sample Time:

Sample Date:

B. ISOTOPIC SAMPLE RESULTS jCi/cc Xe' 33 ____ ____ __ jCi/cc I_131 Xe 135 ____ ____ ___ tCi/cc 1i132 fiCi/cc jzCi/cc Xe135m _____________ P i/cc

_133 1I134 __ Ci/cc 1_135 _tCi/cc Other Isotopes:

C. DOSE ASSESSMENT RESULTS Dose Projections Attached? E YES [7 NO Comments:

Performed By !:

Reviewed By:

(Print/Sign)

I Rad. Ass't to EOF Coordinator VYOPF 3513.02 DISTRIBUTION OP 3513 Rev. 21 EOF Coordinator to SRM Page 1 of 1 SRM to EOF States' Reps., NRC, ESC, and NMC

FIELD DATA STATUS LOG INFO Current at: Time Date Team Name:

Sample Location:

A. WHOLE BODY DOSE RATE RESULTS

1. Dose Rate Readings:

a. Waist Height Fl RM-14 LI PIC-6

b. 2" Above Ground El RM-14 El PIC-6 NOTE To ensure that the Radiological Assistant receives the whole body dose rate results expeditiously, forward whole body dose rate results to Radiological Coordinator in EOF before an air sample is taken.

B. AIR SAMPLE RESULTS

1. "Standard" Air Sample:

a. Air Code

b. Sample Collection Time

c. 1-131 Concentration (Table III) jtCi/cc OR

2. "Non-Standard" Air Sample:

a. Air Sample "Time ON"

b. Air Sample "Flow ON" [] LPM [E CFM or Total minutes C. Air Sample "Time OFF" _

d. Air Sample "Flow OFF" ZI LPM [E CFM

e. Air Sample "NET cprnm"

______ ____ .Cicc

f. 1-131 Concentration (Appendix C - Method 2)

C. FIELD SAMPLE THYROID DOSE NOMO GRAM RESULTS iiCi/cc

1. 1-131 Concentration hours

2. Inhalation Time REM

3. Adult Thyroid CDE (Figure III)

Perforr aed By:. Reviewed By:

(Print/Sign)

I VYOPF 3513.03 Copies Distributed To: Radiological Coordinator OP 3513 Rev. 21 Page 1 of I

C (

DOSES AT SELECTED LOCATIONS Gamma Dose Rate 113 Conc.

(mR/hr) (ItCi/cc) Sample Storage Location Initials Date Time Sample Location VYOPF 3513.04 OP 3513 Rev. 21 Page 1 of 1

FIGURE I INITIAL DOSE ASSESSMENT & PAR SEQUENCE G) Perform stack analysis IfStack Gas I or 2 Is Alarming In Alert.

(Q) If dose projection results not available, Implement PA1~s on plant conditions.

Obtain applicable meteorological data (wind direction and/or wind speed) and source term data.

' Separate Path Recommendations are required.

I Figure I OP 3513 Rev. 21 Page 1 of 1

( C FIGURE IH VERMONT YANKEE EMERGENCY DOSE RATE NOMOGRAM OFFSITE DOSE RATE AT 113 MILE (mrem/hr) 1C' 101 10 10 10 .. 10 10 10 .0 I

I REDV: 05 DATE: 0013/94 101~~ - - - - J~SCFML 1 fI 1 LU1'.L

-VYC-1220 REV 1 1:' _____ 1__

FANCAPACITIES IN SCFM EACHFAR MAX 10¸ I I RAO WASTE EX RW* IA 6"100 12,200 In 6s100 IURBINE BLO TEF 19 72,000 73,000 1A 72;000 MAINEXHAUST TURBINE 910 TEF TEF 25.00 60.000 76 26;000 OP FLOOR EX 10 RXLDF-X (NORMAL)

RXOLDEX REF REF 1A 65.800 55.300 16 641(00 2A 100 3.000 4 ri i i' (SOOTS) 26 1.600 1010, .n . I I . . . . - -

AOQ EXHAUST AOQEXHAUST 11,600 11.600 11,600

'O

,VJ//VVI SERVICEBL9 EXHAUST SEF 2A 20 2,400 2,400 2.400 I/X/bX/*XI 7Y7/J-'~I NOBLE GAS RELEASE RATE -In 6 Q (RCVSOC)

TI JL17/

iYJ'i/YA/X 4 11I1I-iJi-I I

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I- I- I - I -1" WfINDSPEEDL

!I1-A-K I I RELEASE mim kttTltMRATE,

/" I IYIRIY AIY /1/ AIY AIX YIJ I STACK H1GH MONITOR RANGE: iO'to10'mR/hr I STACK FLOW MONITOR RANGE, 0 to 20,000 SCFM

~2 104". .'X I RELEASE RATE FUNCTION a .J(t) MLrahrW.' NOBLE GAS 0

J (t) ý

I OFFSITE DOSE RATE FUNCTION n- - , NOBLE GAS

- I OFFSITE MONITOR DOSE RATE STACK HIGH(RA1,EpEMONITOR FUNCTION I WIND SPEED TIMES GAMMA DIFFUSION FACTOR AT13 MILE = 2.0 x 104 motor' 0.1 1.0 10 100 1,000 (INDEPENDENT OF STABILITY CLASS)

TIME AFTER SHUTDOWN (HOURS)

Figure II OP 3513 Rev. 21 Page 1 of I

FIGURE III FIELD SAMPLE THYROID DOSE NOMOGRAM 100000 100 HR 10000 50 HR 20 HR o

8 HR 1000 4 HR S2HR I 1HR 100 U,

U' D

Ca 10

cl 1

0.1 0.01 0.001 T 1.00E-09 1.00E-08 1.00E-07 1.00E-06 1.00E-05 1.00E-04 1-131 Air Concentration (uCUcc)

Figure UI OP 3513 Rev. 21 Page 1 of 1

APPENDIX B OFF-SITE DOSE PROJECTION METHODOLOGY WHEN ODPS IS INOPERABLE Obtain the necessary off-site dose projection information for stack and ground release as follows:

a. IF A STACK RELEASE IS OCCURRING: (NOMOGRAM METHOD - FIGURE 11)

1) Obtain and record input data as follows:

a) Date/Time I b) Elapsed time following reactor shutdown hrs NOTES For elevated release use upper wind speed and direction, or as directed if necessary by Appendix I.

Wind direction and stability class are used in OP 3511 to determine towns affected by possible Protective Action Recommendation.

mph c) Upper Wind Speed (Use 15 min avg data from MET DATA HISTORY-1 or use alternate methods on Appendix I) 0 d) Upper Wind Direction (Use 15 min avg data from MET DATA HISTORY-1 or use alternate methods on Appendix I) e) Assume Stability Class is as follows: A (Unstable)

NOTE Appendix H provides alternate methods to obtain source term data.

f) Stack High Range Monitor _mRlhr (Use instantaneous data from METPAC PARAMETERS (MTPP) orRM 17-155 on CRP 9-2) scfm g) Stack Flow (Use instantaneous data from METPAC PARAMETERS (MPP) or FI-108-22 on CRP 9-2)

Appendix B OP 3513 Rev. 21 Page 1 of 3

APPENDIX B (Continued)

2) Use full scale Nomogram (if available) with appropriate input data information from above to determine the Site Boundary Dose Rate (.35 miles) and record below Stack Site Boundary Dose Rate.

Stack Site Boundary Dose Rate: mR/hr NOTE Unless a more definitive number is available for the release duration, a value of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months will be used.

3) Calculate the Stack Site Boundary Dose (R) and record below as follows:

Dose (R) = Stack Site Boundary Dose Rate in mR/hr x Release Duration in Hours 1000 R

Stack Site Boundary Dose: R

4) If no ground release is occurring, skip Appendix B, Step 1.b and then continue with Appendix B, Step 2.

b. IF A GROUND RELEASE IS OCCURRING: (MEASURED SITE BOUNDARY DOSE RATE)

1) Obtain and record input data as follows:

NOTES For ground release, use lower wind direction.

Wind direction and stability class are used in OP 3511 to determine towns affected by possible Protective Action Recommendation.

0 a) Lower Wind Direction (Use 15 min avg data from MET DATA HISTORY-1 or use alternate methods on Appendix I) b) Assume Stability Class is as follows: A (Unstable)

Appendix B OP 3513 Rev. 21 Page 2 of 3

APPENDIX B (Continued) c) Obtain and record below the Whole Body Dose Rate (waist height reading) from the Site Boundary Team.

Whole Body Dose Rate: mR/hr NOTE Unless a more definitive number is available for the release duration, a value of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months will be used.

2) Calculate the Ground Site Boundary Dose (R) and record below as follows:

(R) =Site Boundary Whole Body DoseDoeR= 1I~xDose Rate in mR/hr Release Duration in Hours 1000-mR R

Ground Site Boundary Dose: _ R

3) Continue with Appendix B, Step 2.

2. Use the applicable meteorological data (wind direction and stability class) and Site Boundary Dose results from above to do the following:

a. If multiple release points exist (stack and ground), then analyze information using Appendix J, "Multiple Release Assessment."

b. If only one release point exists(stack or ground), then continue with the following actions:

1) Implement OP 3511 Section II, Step A.2 to formulate Protective Action Recommendations for State authorities.

2) Review AP 3125 to determine whether site boundary radiological dose EALs have been reached or exceeded.

3) Forward results to the SS/PED and TSC Coordinator.

-'* Appendix B OP 3513 Rev. 21 Page 3 of 3

APPENDIX C FIELD DATA MONITORING K Receipt and Logging of Field Data Information

1. As monitoring teams report air sample and dose rate information, the Rad Assistant's radio operator will record this information on VYOPF 3513.03 and forward to the Rad Coordinator.

2. The Rad Coordinator will interpret the "Air Code" numbers into air concentration by one of the following methods:

a. Method 1:

If a "standard" air sample was taken, use Table M to determine the corresponding air concentration.

NOTE Unless otherwise specified, a "standard" sample is as follows:

Counting efficiency (RM-14) = 0.25%

Flow rate = 1CFM Collection Time = 10 minutes

b. Method 2:

If a "non-standard" air sample was taken, use the following equation to calculate air concentration:

Conc (ptCi/cc) CxCF ExVxT Where: C Net cpm from air sample CF= Conversion Factor (4.5 x 10-1 [tCi-Iidpm-cc for flow rate in LPM or 1.6 x 1011 p.Ci-ft3/dpm-cc for flow rate in CFM)

E = Efficiency (0.0025 for RM-14)

V = Flow rate of sample in LPM or CFM T - Sample collection time in minutes

c. Record results on VYOPF 3513.03.

3. Proceed to Figure III to determine thyroid dose at the sample location and record results on VYOPF 3513.03.

4. Ensure that field monitoring information on dose rates and 1-131 concentrations are recorded on VYOPF 3513.04.

Appendix C OP 3513 Rev. 21 Page 1 of 1

APPENDIX D METPAC COMPUTER INPUT SEQUENCE AND INSTRUCTIONS A. Initial Start-up and Operation I. Turn on the computer, line printer, and monitor.

NOTES The computer will boot-up by executing a RAM memory test and loading appropriate start-up files and mouse driver. When the computer has completed its booting process, the monitor screen will be at the DOS prompt (i.e., C:\>).

MM = current month, DD = current day, YY = current year, HH

= current hour, mm = current minutes.

"(Enter)" indicates that user inputs are entered by depressing the "Enter" key.

2. Type "Date" (Enter). Enter current date in format MM-DD-YY (Enter).

3. Type "Time" (Enter). Enter the current time in format: HH:mm (Enter).

4. Type "METPAC" (Enter) to start program.

NOTES

The current analysis condition and Main Menu will be displayed on the screen at this time.

Refer to Appendix E for information on METPAC options and operational features of the program.

5. Select the desired option from the Main Menu (as shown below) by typing the number (letter) or using the cursor control (arrow) keys, then (Enter).

1 START NEW ACCIDENT 2 CONTINUE ACCIDENT 3 ELIMINATE LAST 1/4 HOUR ANALYSIS 4 OBTAIN OUTPUT 5 BATCH EXECUTION Q QUIT Appendix D OP 3513 Rev. 21 Page I of 9

APPENDIX D (Continued)

NOTE If the "START NEW ACCIDENT" is selected, the program will respond with: Are You Sure? If Y is entered, a new accident analysis will be initiated and the previous data base will be deleted. If N is entered, the program will return to the Main Menu screen to allow user to select another option.

6. Type and enter a "1" if starting a new analysis, or a "2" if continuing an analysis.

7. Upon entering the desired option (1 or 2), the date screen will be displayed. Enter appropriate information on date and time of reactor shutdown and date and time of release occurring, as necessary.

NOTES METPAC does not use a negative value for time-after-shutdown.

Any time-after-shutdown which is negative is reassigned the value of zero. Time-after-shutdown is calculated as the difference between the end time of analysis and the time of shutdown.

The program accepts only 2 characters. Backspace may be used to edit input.

With the exception of exiting from the displayed screen, it is not necessary to press the "Enter" key; moving the cursor to next location makes the previous input value accepted.

If there are errors with the input, the terminal will beep, a message will appear above the input screen, and the cursor will automatically move to the input location that is in error. The corrected values must be inputted and followed by a RETURN.

If this is the start of a new analysis and there are both a ground and an elevated release, then the hour and minute of both releases must be in the same fifteen-minute period.

8. Using arrow keys, move the cursor to "RAD SCREEN" (Enter). The radiological data input screen will appear (only input for the designated release paths will be displayed).

Appendix D OP 3513 Rev. 21 Page 2 of 9

APPENDIX D (Continued)

9. Using arrow keys, position the cursor and enter the following appropriate radiological data using information from VYOPF 3513.01, Dose Assessment Status Form, or as directed by the Radiological Assistant:

a. Stack high range monitor (mR/hr), if release is from the stack, or measured field data (i.e., centerline dose rate, 1-131 air concentration, and location of measurement), if release is from an unmonitored pathway.

b. Stack flow rate (scfm), if release is from the stack.

c. If requested and available, enter isotopic data for the release pathway using information obtained from in-plant samples, and implement the following steps:

1) Type and enter "Y" at the "ISOTOPICS" prompt.

2) Position the cursor and input data for detected isotopes.

3) Record isotopic information used in program on VYOPF 3513.02 or print out the METPAC isotopic report after running dose calculation by accessing the report function key Fl.

4) Move the cursor to "EXIT" (Enter) to return to Rad Screen.

10. Move the cursor to "MET SCREEN" (Enter). The meteorological data input screen will appear.

Appendix D OP 3513 Rev. 21 Page 3 of 9

APPENDIX D (Continued)

11. Using arrow keys, position the cursor and enter the following meteorological data using information from VYOPF 3513.01, Dose Assessment Status Form, or as directed by the Radiological Assistant.

a. Enter upper or lower wind speed (mph), depending on release pathway selected.

b. Enter upper or lower wind direction (deg. from), depending on release pathway selected.

c. Enter upper or lower AT (deg. F), depending on release pathway selected.

d. Enter amount of precipitation (inches/quarter hr) or if no precipitation, then enter zero.

12. Ensure that the release condition for release pathway is correct (0 = release stopped, 1 = release continuing).

13. Move cursor to "RUN" (Enter).

Appendix D OP 3513 Rev. 21 Page 4 of 9

APPENDIX D (Continued)

NOTES The dose rates indicated are projected rates at the end of a 15 minute period located at ground level relative to the plume centerline. The outside boundaries of the plume parallel to the centerline are the 1% projected dose rates.

After the dispersion and dose projection calculations are completed, a color background map with the plume and a function key menu will appear on the monitor.

The description of the function keys are as follows:

F1 - Allows user to obtain METPAC reports. Selecting this option brings up the following menu.

F1 - Tracking Report F2 - PAG Comparison Report F3 - TID and other reports. Selecting this option brings up the following menu:

F1 - total dose (TEDE and thyroid CDE) accumulated since start of release.

F2 - dose (EDE) rate due to accumulated ground deposition.

F3 - total accumulated ground deposition (ptCi/m2) report.

F4 - accumulated ground deposition by isotope report.

F5 - accumulated external dose (EDE) due to plume.

F6 - accumulated dose (EDE) due to inhalation.

F7 - accumulated dose (EDE) due to ground deposition.

F8 - TEDE and thyroid CDE for last 15 min.

time period.

F9 - all of the above reports.

F10- exit to previous menu.

F4 - Isotopic Report F5 through F9 - No function F10 - Exit to previous menu.

(NOTE Continued on Next Page)

Appendix D OP 3513 Rev. 21 Page 5 of 9

APPENDIX D (Continued)

(NOTE Continued from Previous Page)

F2 - Displays the ground plume.

F3 - Displays the elevated plume.

F4 - No function.

F5 - No function.

F6 - Provides the following options for modifying the plume plot:

F1 - Draws/removes 5 and 10 mile radius circles and 16 cardinal direction sectors.

F2 - Draws/removes evacuation roads.

F3 - Displays/removes locations for points of interest.

Utilize Table I for additional points of interest.

Depress Return to exit.

F4 - Displays/removes town names.

FS - Zooms in on a specified area of the map.

F6 - Toggles between the boundaries legend and the plume legend.

F7 - Displays/removes TID plot.

F8 - Provides dose rates at selected points on the plume plot and ground deposition plot, and doses at selected points on the TID plot.

a. Move and click the mouse to the point of interest to obtain:

1) distance from site,

2) angle in degrees from site.

b. Repeat for other points.

c. To exit, move mouse to EXIT location and click on Exit.

F9 - Displays/removes the ground deposition plot.

F10 - Exit to previous menu.

(NOTE Continued on Next Page)

Appendix D OP 3513 Rev. 21 Page 6 of 9

APPENDIX D (Continued)

(NOTE Continued from Previous Page)

F7 - Displays summary table for plume points. Selecting this feature brings up the following menu:

F1 - allows user to obtain METPAC reports (see F1 above).

F2 - displays summary table for ground level release.

F3 - displays summary table for elevated release.

F4 through F6 - no function.

F7 - return to plume plot (exit to previous menu).

F8 and F9 - no function.

F10 - exit graphics program to Main Menu.

F8 - Allows user to obtain a dose rate for a location of interest on the map (see F8 description under plot modifying feature above).

F9 - Makes a hard copy of the graphics screen.

F10 - Exit to Main Menu.

Space bar - user to switch plume display between TEDE and thyroid CDE.

14. From the displayed function key menu on monitor, select the specific function desired by pressing the appropriate function key on keyboard.

15. Repeat above data entry steps for each 15 minute interval to the current time period if needed.

NOTE Line printer must be on-line now.

16. Print out appropriate reports and graphic plume plots as directed by the Radiological Assistant.

17. As METPAC dose projection information becomes available, provide the dose projection printouts and associated data to the Radiological Assistant for evaluation.

Appendix D OP 3513 Rev. 21 Page 7 of 9

APPENDIX D (Continued)

NOTE METPAC is intended to run on a real time basis and analysis should be updated and run at 15 minute intervals if possible.

18. Continue to update METPAC dose projections as information becomes available, especially for the next quarter hour analysis.

NOTE The total integrated dose feature automatically calculates and accumulates doses and ground deposition during each quarter hour analysis. TID reports can be obtained from the function menu option.

Also, since the TID estimates are dependent on METPAC input data, they are subject to the same conservatisms and assumptions that apply to dose rate projections.

B. Batch Execution Mode

1. If requested to run the METPAC Batch Execution mode, implement the following steps:

a. Select option 5 from the Main Menu, then press (Enter).

b. Select the appropriate batch option displayed (refer to Appendix E for option descriptions).

c. Enter the following, depending on selected batch option:

1) Dates and time for shutdown and release.

2) Number of quarter hours to project.

3) Radiological and meteorological data.

NOTE Upon entry of last data, the program begins dispersion and dose calculations, followed by the display of the plume plot for the batch execution.

d. Depress the F10 key when ready to exit the plot.

Appendix D OP 3513 Rev. 21 Page 8 of 9

APPENDIX D (Continued)

e. Enter "Y" if the batch execution is to be saved as part of the current analysis, or "N" if it is not.

C. METPAC Termination NOTE METPAC should be terminated by returning to the Main Menu screen to prevent loss of data files.

1. Select "Q" from the Main Menu, then press (Enter) (The program will terminate with the data files being saved for future use).

Appendix D OP 3513 Rev. 21 Page 9 of 9

APPENDIX E DESCRIPTION OF METPAC OPTIONS AND OPERATIONAL FEATURES METPAC OPTIONS A. Continuing an Accident To continue the analysis of the accident and obtain a new printout of protective action guideline comparisons, the user must enter a 2 (Enter) in response to the Main Menu (Screen 1). This allows the user to update the release based on the next 15-minute radiological and meteorological data.

The second screen, the Date Screen, appears with the time of shutdown and the time of the chosen release path displayed at the top. An inactive release pathway and the date and time of analysis appears in the middle of the screen. The date and time of analysis is filled in, and the time is already incremented by 15 minutes. To continue, hit "Enter" key.

The third screen, the Rad Screen, appears with the data fields filled in from the previous quarter hour input. If the data has not changed, hit "Enter" key. If new data must be entered, the data can be modified, as in the previous section. Position the cursor to "MET SCREEN" and hit "Enter" key. The fourth screen, the Met Screen, appears with all data fields filled in from the previous quarter hour input. If the data have not changed, hit "Enter" key. If new data must be entered, the data can be modified, as in the previous section. Position the cursor to "RUN" and hit "Enter" key. The program calculates dispersion and dose and display the graphics, as in the previous section.

B. Eliminate Last Quarter Hour Starting at Main Menu, to eliminate a quarter hour analysis, the user should type "3" (Enter). The Main Menu Screen updates with the "END TIME OF ANALYSIS" reduced by 15 minutes. This option eliminates the last 15-minute database record from the database file.

C. Viewing a Plot and Obtaining a Printout Starting from the Main Menu, to view a plot or obtain an output report from a previous time period, the user should type "4" (Enter). At the bottom of the Main Menu, the user is asked to enter the time of interest. If the user does not wish to execute this option, hit "Enter" key. If a valid time is entered followed by a (Enter), the program displays the requested plot. Valid times are between the start time of analysis and the end of time of analysis.

The user can now design the plot screen or obtain the desired report as in Appendix D.

To exit, depress the F10 key. This returns the user to the Main Menu.

Appendix E OP 3513 Rev. 21 Page 1 of 7

APPENDIX E (Continued)

D. Editing Data To edit a mistake in a previous quarter hour data record, the user proceeds through the Main Menu as if continuing an accident. When the Date Screen is presented, the user enters the quarter hour that the error occurred in the time of analysis input line. This is done by entering the hour and the minute on the "EDIT QUARTER HR" line. When the time has been edited, the user moves the cursor to "RAD SCREEN" and hits the "Enter" key.

The user may change any value on the Rad Screen by moving the cursor to the error location and typing the corrected value. After all editing has been completed, move the cursor to "MET SCREEN" and hit "Enter" key. The fourth screen is displayed. The user may edit any value by moving the cursor to the error location, and entering the correct value. After editing has been completed, position the cursor to "RUN", and hit "Enter" key. Since the program uses persistence when continuing an analysis, the program may have continued that the error in subsequent quarter hours. To verify subsequent quarter hours, position the cursor on "NEXT QTR HR" rather than on "RUN". The program presents the Rad Screen, then the Met Screen for the subsequent quarter hours, but does not change the field that was corrected. If the user finds that the error persists, it can be corrected at this time. The program does this for all quarter hours from the time of the error to the last time analyzed.

After the last quarter hour has been verified, the program continues as in Appendix D.

All quarter hours from the time of the error to the last analysis time are reanalyzed, but only the last quarter hour is displayed. Hit the "F10" key to continue.

E. Viewing Input To view a previous quarter hour input screen, the user proceeds through the Main Menu as if continuing an accident. When the Date Screen is presented, the user enters the quarter hour that is desired in the time of analysis input line. The user moves the cursor to "RAD SCREEN" and hits "Enter" key. The Rad Screen appears for review. After reviewing the rad data, verify that the cursor is positioned on "MET SCREEN", then hit "Enter" key. When the user is done reviewing the Met Screen, move the cursor to "DATE SCREEN" and hit "Enter" key. This brings the user back to the second screen.

At this time, the user may continue the accident, edit data, view another input screen or return to the Main Menu.

Appendix E OP 3513 Rev. 21 Page 2 of 7

APPENDIX E (Continued)

F. Starting Another Release Path I To start a second release path, the user proceeds through the Main Menu as if continuing an accident. When the Date Screen is presented, the user moves the cursor to the line on which entry of the release path date and time occurs. The user can then enter the data for the date and time, as is done in Appendix D. This date and time must be after the date and time of the first release and before the date and time of the current analysis. The user moves the cursor to "RAD SCREEN" and hit "Enter" key.

When the Rad Screen appears, it contains data for the first time of analysis in which the release started. The user may update this record to contain the appropriate radiological measures, then choose "MET SCREEN". The meteorological data values can be updated appropriately. Once this has been done and the "RUN" option has been chosen, the program displays the input screen for the next time of analysis. This continues until the user has had a chance to update all input screens up to the current time of analysis.

After the last quarter hour has been updated, the program continues as in Appendix D.

All quarter hours from the time of the start of the new release path to the current analysis time are reanalyzed, but only the last quarter is displayed. Hit "F10" key to continue.

G. Batch Execution To execute the batch feature, the user selects option 5 from the Main Menu and hits "Enter" key. This action brings up the Batch Menu Input Screen, which allows the user to specify one of three ways the batch execution will take place.

Batch option 1 is chosen when the user wishes to add quarter hours which are exactly the same as the last quarter hour to an existing accident. After the number of quarter hours to be projected has been entered, the program performs the dispersion and dose calculations, then displays the plume plot. The operator can now modify the plot screen, print the plot, or go to report processing. To exit, hit the "F10" key. The program asks the operator whether or not to save the batch generated data. Entering "Y" saves the batch data.

Entering "N" keeps the accident analysis as it was before batch execution.

Appendix E OP 3513 Rev. 21 Page 3 of 7

APPENDIX E (Continued)

Batch option 2 is used to add quarter hours with different data from the last quarter hour of the current analysis. After entering the number of quarter hours to be projected, the radiological and meteorological screens are presented. Data values for these screens can remain the same or be modified as described above. After the operator enters the data values for the Met Screen, "NEXT QTR HR" must be selected to enter data for the subsequent time period. This selection must be made for all subsequent time periods in order to enter different values. The Met Screen for the last quarter hour period in a batch execution does not display "NEXT QTR HR". If the operator wishes to use current values for all remaining quarter hour periods in a batch execution, the "RUN" option on the Met Screen can be selected. After positioning the cursor on "RUN" in the final quarter hour and hitting the "Enter" key, the dispersion and dose calculations are performed, followed by the display of the plume plot. The operator can now modify the plot screen, print the plot, or go to report processing. To exit, hit the "F10" key. The program asks the operator whether or not to save the batch generated data. Entering "Y" saves the batch data. Entering "N" keeps the accident analysis as it was before batch execution.

Batch option 3 is selected when an entirely different analysis, separate from the current accident, is to be performed. Selection of this option results in the display of the Date Screen which requires the user to enter the dates and times of reactor shutdown and release. After the dates and times have been entered, the user is requested to enter the number of quarter hours over which the projection is to occur. Next, the Rad and Met Screens are presented in the same manner as continuing an accident. After entering data for the first quarter hour, the operator selects "NEXT QTR HR" if data values differ for subsequent quarter hour time periods, or "RUN" if the data values are to remain the same in subsequent time periods. After positioning the cursor on "RUN" in the final quarter hour of the batch execution and hitting the "Enter" key, the dispersion and dose calculations are performed and the Output Main Menu is displayed. The operator can now modify the plot, print the plot, or go to report processing.

The program asks the operator whether or not to save the batch generated data. Entering "Y" saves the batch data. Entering "N" keeps the accident analysis as it was before batch execution.

Appendix E OP 3513 Rev. 21 Page 4 of 7

APPENDIX E (Continued)

UI. METPAC OPERATIONAL FEATURES A. Stack Release Pathway For the stack release pathway, METPAC allows the user to define whether the program should use a default isotopic mix (monitor reading) or user-defined mix (isotopic input) for calculating the release rate. The stack release rate options with the define flag settings are as follows:

1. Entering Stack Monitor Reading and Stack Flow Rate (Flag Setting of 0 Assumed)

(User-defined stack monitor reading and stack flow rate is used. User-defined isotopic mixture in the isotopic input screen is not used or included).

METPAC uses the stack monitor reading and stack flow rate to calculate the release rate for determining the TEDE and CDE to the thyroid.

2. Entering Stack Monitor Reading and Measured Stack Iodine Isotopic Data with Stack Flow Rate (Flag Setting of 1 - Combo)

(User-defined stack monitor reading and measured stack iodine isotopic data with stack flow rate is used. User-defined isotopic mixture in the isotopic input screen includes only iodine).

METPAC uses the default noble gas isotopic mixture based on the stack monitor reading to calculate the release rate for determining its contribution to the TEDE.

METPAC also uses the user-defined iodine mixture in the isotopic input screen to calculate the iodine release rate for determining its contribution to the TEDE and CDE to the thyroid.

3. Entering Measured Stack Isotopic Data with Stack Flow Rate (Flag Setting of 2 Measure)

(User-defined measured stack isotopic data with stack flow rate is used.

User-defined isotopic mixture includes noble gas or particulate radionuclides in the isotopic input screen).

METPAC uses the user-defined isotopic mixture to calculate the release rate for determining the TEDE and CDE to the thyroid. However, if no iodine isotopic mixture is included in the isotopic screen, then the 1-131 dose equivalent to noble gas ratio is used in order to calculate the iodine release rate for determining the CDE to the thyroid. This 1-131 dose equivalent release rate is based on the user-defined total noble gas isotopic mixture (concentration).

Appendix E OP 3513 Rev. 21 Page 5 of 7

APPENDIX E (Continued)

B. Unmonitored Release Pathway For the unmonitored release pathway, METPAC allows the user to define whether the program should use field measurements (dose rate/I-131 conc., distance and sector) or user-defined mix (isotopic input) from the release point for calculating the release rate.

The unmonitored release rate options with the define flag settings are as follows:

NOTE User must enter a dose rate, distance, and sector to run the unmonitored release option. The "Sector" is the compass direction where the field sample was taken and defined as a number. The compass "Sector" number designations are as follows:

N=1, NNE=2, NE=3, ENE=4, E=5, ESE=6, SE=7, SSE=8, S=9, SSW=I0, SW=11, WSW=12, W=13, WNW=14, NW=15, and NNW=16.

The limitation of this feature is that the field measurements must be taken at or beyond site boundary. Field measurements as input are treated as centerline values by the model.

Only one dose rate measurement and one airborne 1-131 measurement is accepted by model during a quarter hour period.

1. Entering Field Team Data (Flag Setting of 0 - Field)

(User-defined dose rate meter reading, distance and sector is used with the option to enter 1-131 concentration, distance and sector).

METPAC uses the dose rate reading, distance, and sector to back-calculate the noble gas release rate for determining the TEDE. If an 1-131 concentration is entered, then METPAC back-calculates the iodine release rate for determining its contribution to the TEDE and CDE to the thyroid.

2. Entering Field Team Dose Rate Data and Measured Iodine Isotopic Data with Estimated Flow Rate From Release Point (Flag Setting of 1 - Combo)

(User-defined dose rate meter reading, distance and sector is used and also the user-defined iodine isotopic mixture and estimated flow rate is used.

MVIETAC uses the dose rate meter reading, distance and sector to back-calculate the noble gas release rate for determining its contribution to the TEDE. METPAC also uses the user-defined iodine mixture in the isotopic input screen to calculate the iodine release rate for determining its contribution to the TEDE and CDE to the thyroid.

Appendix E OP 3513 Rev. 21 Page 6 of 7

APPENDIX E (Continued)

3. Entering Measured Isotopic and Estimated Flow Rate Data from Release Point (Flag Setting of 2 - Isotopic)

(User-defined isotopic mixture and estimated flow rate from the measured isotopic concentrations at the release point is used).

METPAC uses the user-defined isotopic mixture to calculate the release rate for determining the TEDE and CDE to the thyroid. If the iodine mixture in the isotopic input screen is entered, then METPAC uses the iodine mixture for determining its contribution to the TEDE and CDE to the thyroid.

Appendix E OP 3513 Rev. 21 Page 7 of 7

APPENDIX G OFF-SITE DOSE PROJECTION SYSTEM (ODPS) INPUT SEQUENCE AND FORMAT Obtain the necessary off-site dose projection information for stack and ground release as follows:

a. IF A STACK RELEASE IS OCCURRING:

NOTE Meteorological and source term data are automatically input to model.

Manual input of data is not necessary.

1) Press the "ODPS" ERFIS terminal key to access the "ODPS Menu" screen.

2) Click on the "SOURCE TERM DATA" box to display screen.

NOTE ERFIS Printer must be on-line now.

3) Click on the PRINTER icon to obtain record of stack release projection information (Reactor Trip Status and Stack).

4) Press the "ODPS" ERFIS terminal key to return to the "ODPS Menu" screen.

5) Click on the "PROTECTIVE ACTION RECOMMENDATIONS LIVE STACK MIR/HR" box to display screen.

6) If ODPS aborts due to bad input (as indicated on screen display), refer to Appendix G - Table G.1.

7) When "PROTECTIVE ACTION RECOMMENDATION" screen is displayed, click on the PRINTER icon to obtain stack release off-site dose projection information.

8) Press the "ODPS" ERFIS terminal key to return to the "ODPS Menu" screen.

9) If no ground release is occurring, skip Appendix G, Step 1.b for ground release and then continue with Appendix G, Step 2.

Appendix G OP 3513 Rev. 21 Page 1 of 4

APPENDIX G (Continued)

b. IF A GROUND RELEASE IS OCCURRING:

1) Press the "ODPS" ERFIS terminal key to access the "ODPS Menu" screen.

2) Click on the "INPUT SITE BOUNDARY MR/HR (UNMONITORED)" box which will display the password entry screen.

3) Leave the User Name entry field blank then type the password currently designated for Control Room use and click on OK.

I 4) Enter the appropriate site boundary dose rate (IR/HR) reading from the Site Boundary Team (team dispatched per OP 3510) in field space provided.

5) Next, enter the estimated time that the release started in field spaces provided (Format in HH and MM).

NOTE ERFIS Printer must be on-line now.

6) Click on the PRINTER icon to obtain record of input data.

7) Press the "Enter" button on the display to update the input data.

8) When "ODPS MENU" screen is displayed, click on "PROTECTIVE ACTION RECOMMENDATIONS BOUNDARY MRJHR" box to display screen.

9) If ODPS aborts due to bad input (as indicated on screen display), refer to Appendix G- Table G.1.

Appendix G OP 3513 Rev. 21 Page 2 of 4

APPENDIX G (Continued)

10) When "PROTECTIVE ACTION RECOMMENDATIONS" screen is displayed, click on the PRINTER icon to obtain ground release off-site dose projection information.

NOTE "ADULT THY" values are not calculated for a ground release.

11) Press the "ODPS" ERRIS terminal key to return to the "ODPS Menu" screen.

12) Continue with Appendix G, Step 2 below.

2. Use printed screen information from above to do the following:

a. If multiple release points exist (stack and ground), then analyze information using Appendix J, "Multiple Release Assessment."

b. If only one release point exists (stack or ground), then continue with the following actions:

1) Implement OP 3511 Section HI,Step A.2 to formulate Protective Action Recommendations for State authorities.

2) Review AP 3125 to determine whether site boundary radiological dose EALs have been reached or exceeded.

3) Forward results to SS/PED and TSC Coordinator.

Appendix G OP 3513 Rev. 21 Page 3 of 4

APPENDIX G (Continued)

TABLE G. 1 S/ If ODPS aborts due to bad input (as indicated by screen display), do the following:

1. Press the "CAW" key which will bring up the password entry screen.

2. Leave the User Name entry field blank.

3. Type the password currently designated for Control Room use and click on OK.

4. Use the "Tab" key to tab to the PTID input field, then press the "Enter" key.

5. Type the PTID (See below) of the point to be overridden into the Point Search Text field.

Release Type PTID Description U014 Stack Gas III Monitor High Range C198 Average Stack Flow FT-108-22 Stack C179 Upper Wind Speed (15 min. ave.)

C187 Upper Wind Direction (15 mrin. ave.)

C181 Upper Delta T (15 min. ave.)

C192 Precipitation (15 min. total)

C178 Lower Wind Speed (15 min. ave.)

K> C186 Lower Wind Direction (15 min. ave.)

C180 Lower Delta T (15 nin. ave.)

C192 Precipitation (15 min. total)

6. Click on "FIND/FIND NEXT" until the point is found, then click on OK.

7. Use the "Tab" key to tab to the SCAN STATUS toggle field.

8. Press the "ENTER" key to toggle from ACTIVE to INACTIVE.

9. Use the "Tab" key to tab to the VALUE input field.

10. Type in the override value to be used and press the "ENTER" key.

a. To manually access back-up meteorological data, refer to Appendix I, Step 2.

b. To manually access back-up source term data, refer to Appendix H, Step 5.

11. Press the "ODPS" key, go back to Appendix G, Step 1.

K Appendix G OP 3513 Rev. 21 Page 4 of 4

APPENDIX H MANUAL SOURCE TERM DATA ACQUISITION record To determine the source term data for dose assessment, perform the following steps and applicable data (refer to VYOPF 3513.01):

1. Obtain and record the time and date of reactor shutdown.

2. Determine and record the type of release(s) (i.e., stack, ground, or combination).

3. Determine and record the time and date of the identified release(s).

4. Determine and record the release duration of the identified release(s).

NOTE Unless a more definitive number is available for release duration, a value of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months duration will be used.

5. Obtain and record release pathway monitoring data as delineated below:

a. FOR ELEVATED RELEASE (stack)

NOTE The stack high range monitor is a Victoreen ion chamber which measures the radiation in the base of the stack. The monitor has a readout in the Control Room on CRP 9-2 with a range from 0.1 mR/hr to 1 x W07 mR/hr.

CAUTION Use instantaneous reading, not the 15 minute average.

1) Stack High Range Monitoring Reading (mR/hr) from one of the following:

a) Control Room Panel (RM 17-155 on CRP 9-2), or b) METPAC PARAMETERS display on ERFIS monitor (depress "ODPS" key, then select METPAC PARAMETERS (MPP) poke box).

Appendix H OP 3513 Rev. 21 Page 1 of 2

APPENDIX H (Continued)

2) Stack Flow Rate (scfm) from one of the following:

a) Control Room panel (FI-108-22 on CRP 9-2), or b) Local readout in the stack monitoring room, or c) ERFIS Data Point C198 (15-minute average), or d) METPAC PARAMETERS display on ERFIS monitor (depress "ODPS" key, then select METPAC PARAMETERS (MPP) poke box), or e) OP 2611, Section entitled, "Determine Stack Flow Rate".

b. FOR GROUND RELEASE

1) Site boundary whole body dose rate (mR/hr) at the fence line downwind location.

6. If the Stack High Range Monitor equals or exceeds 20 mR/hr, request the Chemistry Technician to obtain a silver zeolite cartridge air sample from the main stack sample point for an iodine release rate determination.

7. If available, obtain and utilize stack sample analysis or field data monitoring information.

Record isotopic information on VYOPF 3513.02 and field data on VYOPF 3513.03.

K1Appendix H OP 3513 Rev. 21 Page 2 of 2

APPENDIX I MANUAL METEOROLOGICAL DATA ACQUISITION To determine the meteorological data for dose assessment, obtain and record applicable information as delineated below:

NOTES FOR ELEVATED RELEASE (stack), ensure that upper meteorological values are obtained and utilized.

FOR GROUND RELEASE, ensure that the lower meteorological values are obtained and utilized.

CAUTION Use 15 minute average met data, not the instantaneous data.

1. Access MET DATA HISTORY-i display on ERFIS monitor by depressing the "ODPS" key and then selecting the MH1 poke box.

2. If the primary meteorological tower instrumentation is not functioning, but ERFIS is operable, obtain meteorological data from the secondary tower. Access MET DATA HISTORY-2 display on the ERFIS monitor by depressing the "ODPS" key and then selecting the MI2 poke box.

3. If the primary meteorological tower instrumentation is functioning, but the MET DATA HISTORY-1 display on the ERFIS monitor is not available, determine the required meteorological data from the video graphic recorders in the Relay House.

4. If the primary meteorological tower instrumentation is not functioning, and the MET DATA HI-STORY-1 and MET DATA HISTORY-2 displays on the ERFIS monitor are not available, obtain readouts of wind speed, wind direction, ambient temperature, and one value of delta T from the secondary (backup) tower from CRP 9-48.

5. If primary and secondary meteorological tower instrumentation is not available, consult Albany National Weather Service Station (Tel. No.'s 800-833-9880 [Primary] or 518-435-9574

[Backup], and ask for "Public Forecaster") regarding meteorological observations.

Appendix I OP 3513 Rev. 21 Page 1 of 2

APPENDIX I (Continued)

6. Stability Class can be determined from one of the following:

a. If a delta T value was obtained from either the primary or back-up tower, use the appropriate section of Table II.

b. If a delta T value is not available from either the primary or back-up tower, a generalized determination of atmospheric stability may be made by observing the cloud cover as follows:

B = Clear sky in daytime D = Heavy overcast day or night F = Clear sky at night

c. Obtain from ODPS or METPAC printout.

Appendix I OP 3513 Rev. 21 Page 2 of 2

APPENDIX J MULTIPLE RELEASE ASSESSMENT NOTE Wind direction and stability class are used in OP 3511 to determine towns affected by possible Protective Action Recommendation.

A. COMBINED ASSESSMENT (USE THIS SECTION IF THE DIFFERENCE BETWEEN I THE UPPER & LOWER WIND DIRECTION IS <450, IF >450 PROCEED WITH SECTION B)

1. Average the upper and lower wind directions to determine the wind direction applicable for the combined release pathway and record below.

0 Average Wind Direction for Combined Release Pathway:

A (Unstable)

2. Assume Stability Class for the combined release pathway is as follows:

3. Add doses from each pathway (stack and ground) to calculate the cumulative dose at the designated downwind distances and record information as indicated below:

NOTE If Appendix B was used to calculate doses, assume the Site Boundary dose results are applicable out to 5 miles.

COMBINED DOSE CALCULATION RESULTS CUMULATIVE DOSES (STACK & GROUND)

DISTANCE TEDE (REM) CDE THYROID (REM)

At Site Boundary (0.35 miles)

At 2 Miles At 5 Miles At 10 Miles Appendix J OP 3513 Rev. 21 Page 1 of 3

APPENDIX J (Continued)

4. Use the applicable meteorological data (wind direction and stability class) and dose calculation results recorded above to continue with the following actions:

a. Implement OP 3511 Section If to formulate Protective Action Recommendations for State authorities.

b. Review AP 3125 to determine whether site boundary radiological dose EALs have been reached or exceeded.

c. Forward results to SS/PED and TSC Coordinator.

B. INDEPENDENT ASSESSMENT (USE THIS SECTION IF THE DIFFERENCE BETWEEN THE UPPER & LOWER WIND DIRECTION IS >450)

1. Record the independent wind direction and stability class from each release pathway (stack and ground) as indicated below:

Release Pathway Wind Directions (deg°) Stability Class*

Stack Ground

A, B, C, D, E, F, or G NOTE If Appendix B was used to calculate doses, assume the Site Boundary dose results are applicable out to 5 miles.

2. Record the independent dose information from each release pathway at the designated downwind distances (stack and ground) as indicated below:

INDEPENDENT DOSE CALCULATION RESULTS r

.*TAC'T" GROUND CDE CDE TEDE THYROID TEDE THYROID DISTANCE (REM) (REM) (REM) (REM)

At Site Boundary (0.35-Miles)

At 2-Miles At 5-Miles At 10-Miles Appendix J OP 3513 Rev. 21 Page 2 of 3

APPENDIX J (Continued)

3. Use the applicable meteorological data (wind direction and stability class) and dose calculation results recorded above to continue with the following actions:

a. Implement OP 3511 Section II to formulate Protective Action Recommendations for State authorities.

b. Review AP 3125 to determine whether site boundary radiological dose EALs have been reached or exceeded.

c. Forward results to SS/PED and TSC Coordinator.

Appendix J OP 3513 Rev. 21 Page 3 of 3

APPENDIX K GUIDELINES FOR "WHAT IF" PROJECTION OF POTENTIAL RADIOACTIVE MATERIAL RELEASES NOTE The following series of calculations is one example of obtaining data for release projections. It is acceptable to use other methods as necessary based on the emergency situation.

1. Determine available source term by making an assumption of fuel conditions based on plant conditions.

NOTE Figure 5.2 from the Core Damage Methodology Assessment [part of Severe Accident Management (SAM) Guideline] may be helpful in determining extent of fuel conditions.

Source Term (ST) - iiCi Clad Failure Fuel Overheat Fuel Melt Noble Gas 1E12 5E13 1E14 1-131 4E9 2E13 2E13 Particulate (Cs137 ) 4E8 2E12 2E12 Clad failure assumes a 1% noble gas, 0.01% iodine and particulate release. Fuel overheat assumes a 50% noble gas, iodine and particulate release. Fuel melt assumes a 100% noble gas, 50% iodine and particulate release. The available source term is assumed to be 1E14 [tCi noble gas, 4E13 glCi i 13 1 and 4E12 particulate (Cs 137 ).

2. Calculate the containment concentration (CC).

CC(pgCi/cc) = ST([tCi)_ ST([tCi) _ iCi/cc CV(cc) 6.7E9 cc CV = Containment Volume which is 6.7E9 cc for combined Drywell and Torus Gas. See volumes list in information fact sheet for additional numbers.

Appendix K OP 3513 Rev. 21 Page 1 of 5

APPENDIX K (Continued)

3. Postulate a release mechanism.

NOTE Containment leakage is a percentage of the Design Containment Leakage. Containment leakage may be obtained from the TSC or an estimate may be obtained from the ESC.

a. Slow containment leakage (<10%/day) to stack via Reactor Building (Elevated Release).

b. Fast containment leakage (Ž_10%/day) to stack via Reactor Building (Elevated Release).

c. Containment failure to environment via Reactor Building blowout panels (Ground Level Release).

4. Calculate Metpac/Nomogram input values.

a. Slow containment leakage (<10%/day) to stack via Reactor Building (Elevated).

Assumes Stack Release Rate (SRR) is equal to the containment release rate.

SRR(gCi/sec) = CC(gCi/cc) x CLR(cc/sec) x F = __ Ci/sec CLR = Containment release rate. The design containment release rate is 7.8E2 cc/sec.

See information fact sheet for additional information.

F= SBGT retention values.

F = 1, SBGT not in use F = 1, SBGT noble gas retention F = 0.05, SBGT iodine and particulate retention Appendix K OP 3513 Rev. 21 Page 2 of 5

APPENDIX K (Continued)

b. Fast containment leakage (_10%Iday) to stack via Reactor Building (Elevated). Assumes immediate uniform mixing in the Reactor Building.

SRR(.Cifsec) CC(R.Ci/cc) x CV(cc) x RBFR(cc/sec) x F RV(cc) + CV(cc)

CC(jCi/cc) x RBFR(cc/sec) x F Ci!

5.2 RV = Reactor Building volume which is 2.8El0 cc.

RBFR = Reactor Building Flow Rate which depends upon a combination of SBGT and Reactor Building ventilation alignment. Ventilation alignment and number of fans may be obtained from the TSC. Flow rates are listed below and on the Nomogram.

F= SBGT retention values.

F = 1, SBGT not in use F = 1, SBGT noble gas retention F = 0.05, SBGT iodine and particulate retention

c. Fast or slow containment leakage when Reactor Building Air Concentrations are known.

SRR([.Ci/sec) = RBC(RCi/cc) x RBFR(cc/sec) x F = _gCi/sec RBC = Reactor Building air concentration.

d. Containment failure to environment via Reactor Building blowout panels (Ground Level).

Assumes immediate uniform mixing of the Reactor Building with Containment and 50%

of the Reactor Building volume is released to the environment in 15 minutes.

GLRR = Ground Level release rate is 1.6E7 cc/sec assuming 50% of the Reactor Building volume is released in 15 minutes.

RBQ~C(1 i/cc) = CC([Ci/cc) x CV(cc) CC(liCi/cc) - 9Cicc RV(cc) + CV(cc) 5.2

5. If Elevated release, obtain Stack High Range Monitor reading SHRM from Nomogram for elevated release using SRR value calculated earlier.

SHRM= mR/hr Appendix K OP 3513 Rev. 21 Page 3 of 5

APPENDIX K (Continued)

6. If requested, Stack air concentrations can be calculated using the following formula:

SRR(liCi/sec)

Stack Air Concentration([tCi/cc) =

Stack Flow Rate(cc/sec)

7. Insert previously calculated values into Metpac or Nomogram as appropriate to complete release projection.

8. All "what if" dose projections must be clearly marked with appropriate stamp or label. "What if' dose projection stamp is available in the EOF Emergency Cabinet #3.

Appendix K OP 3513 Rev. 21 Page 4 of 5

APPENDIX K (Continued)

INFORMATION FACT SHEET

'.- VOLUMES:

Primary System (Liquid) 7,700ft3 2.2E8cc Primary System (Gas) 6,300ft3 1.8E8cc Drywell (Gas) 131,850ftW 3

3.7E9cc Torus (Liquid) 70,000ft 3 2.0E9cc Torus (Gas) 106,250ft 3

3.OE9cc Reactor Building (Gas) 1E6ft 2.8E10cc FLOW RATES:

Reactor Building Ventilation 55,800 cfm 2.6E7 cc/sec Standby Gas Treatment 3,000 cfm 1.4E6 cc/sec (2 fans running)

Turbine Building Ventilation 122,000 cfm 5.8E7 cc/sec (TEFlA or 1B and TEF 6 & 7)

Radwaste Ventilation 12,200 cfm 5.8E6 cc/sec (2 fans running)

AOG Building Ventilation 11,500 cfm 5.4E6 cc/sec Stack with Normal Ventilation 206,000 cfm 9.7E7 cc/sec MISCELLANEOUS FACTS:

Design Containment Leakage 1% of the radioactive inventory/day 2.4E3ft3/day = 6.7E7 cc/day = 7.8E2 cc/sec RB Air Turnover Rate Using SBGT - 1/day If blowout panel goes, assume 1/2 RB volume is released CONVERSION FACTORS:

472 cc/sec/cfm 3

28,300 cc/ft Appendix K OP 3513 Rev. 21 Page 5 of 5

10 CFR 50.54(q) Evaluation Checklist List of Emergency Plan Section(s)/Emergency Plan Implementing Procedure(s) or any other document to be evaluated. (Include Title and Revision No.):

OP 3513 Rev. 21, Evaluation of Off-site Radiological Conditions A. Screening Evaluation Based on a review of the following questions, determine if the change has the potential to affect our ability to meet the standards of 10 CFR 50.47(b) and the requirements of Appendix E to 10 CFR 50.

A "YES" answer to any part of the questions requires that a written evaluation be done to determine whether the effectiveness of the Emergency Plan was decreased as specified in Section B of this checklist.

A "NO" answer to all questions requires no written evaluation as specified in Section B of this checklist.

1. Could the proposed change affect our ability to meet the following standards of 10 CFR 50.47(b):

(1) Assignment of Emergency Response Organization responsibiliti G NO (2) Assignment of on-shift Emergency Response Organization persopNO and Resources (3) Arrangements for Emergency Response Support YES ON (4) Emergency Classification and Action levels, including facility system and effluent parameters YES6 (5) Notification Methods and Procedures (6) Emergency Communications among principal response organizations the public YES (7) Public Education and Information YES N (8) Adequacy of Emergency Facilities and Equipment YES (10) Plume exposure pathway EPZ protective actions YES (11) Emergency Worker Radiological Exposure Control injured individuals (12) Medical Services for contaminated YES (13) Recovery and Reentry Plans YES~

(14) Emergency response periodic drills and exercises YES(2 (15) Radiological Emergency Response Training (16) Plan development, review and distribution YES VYAPF 3532.01 AP 3532 Rev. 10 Page 1 of 3 RT No. 10.E06.171

10 CFR 50.54(q) Evaluation Checklist (Continued) affect our ability to meet the following requirements of

2. Could the change Appendix E to 10 CFR 50.

(1) Section IV. A - Organization YES (2) Section IV. B - Assessment Actions Organizations YSN (3) Section IV. C - Activation of Emergency YES (4) Section IV. D - Notification ProceduresSection IV. E - Emergency Facilities and Equipment YES (5) YES (6) Section IV. F - TrainingYE (7) Section IV. G - Maintaining Emergency Preparedness H - Re overyYES (8)Section IV. H - Recovery YESS NO B. Effectiveness Determination For each applicable (i.e., a "yes" answer specified) standardAtoabove, 10 CFR 50.47(b) and Appendix E to 10 CFR 50 identified from Section the change decreases complete the evaluation form below to determine whether continues Emergency Plan and whether it to meet the the effectiveness of the stated applicable standard or requirement.

and attached to A facsimile of the evaluation form may be used as needed this checklist.

For applicable item 10 CFR 50.47(b) (1), (2), Appendix E,Section IV.A of Section A above, this change (DOES/DOES NOT) decrease the effectiveness of the Emergency Plan and (DOES/DOES NOT) continue to meet the stated applicable standard or requirement.

BASIS FOR ANSWER:

Site Boundary The change made to the Security Site Boundary Team becoming BVY-2002-015.

Team is in response to the Security ICM communicated in this duty This addresses the issue of collateral duties and this transfers effectiveness of from Security to Plant Staff. This does not decrease the the Emergency Plan and continues to meet the requirements.

VYAPF 3532.01 Rev. 10 AP 3532 Page 2 of 3

10 CFR 50.54(q) Evaluation Checklist (continued)

C. Conclusion (Fill out appropriate information)

Ef The changes made do not decrease the effectiveness of the Emergency Plan and continue to meet the standards of 10 CFR 50.47(b) and the requirements of Appendix E to 10 CFR 50.

The changes made do decrease the effectiveness of the Emergency Plan 0 of 10 CFR 50.47(b) and and decrease our ability to meet the standards CFR 50. The following course of the requirements of Appendix E to 10 action is recommended:

"o Revise proposed changes to meet applicable standards and requirements.

"O cancel the proposed changes.

El Process proposed changes for NRC approval prior to implementation in accordance with 10 CFR 50.54(q).

D. Impact on Other Documents (TRM, Tech Specs)

Keywords used in search: Site Boundary Teams, Security 0 This change does not affect any other documents.

[3 This change does affect other documents.

Document(s) affected:

Section(s) affected:

E. Impact on the Updated FSAR existing Use AP 6036 to determine if the proposed E-Plan change modifies information and UFSAR information or requires the addition of new UFSAR initiate UFSAR change(s) as required.

Site Boundary Teams, Security Keywords used in UFSAR search:

Additional Comments:

Measures These changes are in response to the Interim Compensatory communicated in BVY-2002-015 Date: 7/26/02 Prepared By: Audra S( WilliamsPrint/S gn )

Reviewed By: O* 1" Date:

(Emergency Plan Coord na *o) (Print Si VYAPF 3532.01 AP 3532 Rev. 10 Page 3 of 3 a

VERMONT YANKEE NUCLEAR POWER STATION 4 "

4+:'OPER.A.TII%4G.

)-

PROCEDIJRE OP 3544 REVISION 2 OPERATION OF THE OPERATIONS SUPPORT CENTER (OSC)

USE CLASSIFICATION: REFERENCE LPC Effective Affected Pages No. Date Implementation Statement: N/A [

Issue Date: 08/20/2032 OP 3544 Rev. 2 Page 1 of 11

TABLE OF CONTENTS

-PURPOSE .......................................................................................................................................................... 3 D ISCUSSION .................................................................................................................................................... 3 AT rACHM E T .S............................................................................................................................................. 4 REFEREN CES AN D COMM FTM ENTS ..................................................................................................... 5 PRECAU TION S/LIM ITATION S ................................................................................................... 5 PRO CEDURE .................................................................................................................................................... 6 1.0 Imm ediate A ctions .......................................................................................................... 6 2.0 Subsequent Actions ............................................................................................................ 10 FINAL COND ITION S .................................................................................................................................... 11 OP 3544 Rev. 2 Page 2 of 11

PURPOSE To outline the operation of the Operations Support Center (OSC).

DISCUSSION There are four emergency classifications, Unusual Event, Alert, Site Area Emergency, and General Emergency. The decision to make an immediate initial declaration rests with the Shift Supervisor/Plant Emergency Director, who, in turn, instructs Control Room personnel to activate the notification system. Notification of State authorities must be initiated within 15 minutes after the event has been classified. The NRC must be notified immediately after the States' notification, but not later than one (1) hour after the event has been classified.

An Unusual Event is defined as any plant-related event which indicates a potential degradation of plant safety margins which is not likely to affect personnel on-site or the public off-site or result in radioactive releases requiring off-site monitoring. Unusual Event conditions will not have caused serious damage to the plant and may not require a change in operation status.

The basic shift complement is able to deal with Unusual Event conditions. On-duty personnel are assigned to functions as required. Additional members of the plant organization, including top management, are notified by Plant Security, and augment on-duty personnel as necessary. The Duty On Call Officer who is available on an on-call basis must report to the site and will assume the role of the TSC Coordinator. Dissemination of public information and closure or escalation to a more severe classification will occur as conditions warrant.

An Alert event is defined as an indication of a substantial degradation of plant safety margins which could affect on-site personnel safety, could require off-site impact assessment, but is not likely to require off-site protective action.

An Alert event requires action beyond the normal capability of the basic shift complement. Plant response and off-site notification associated with this event classification ensure that sufficient emergency response personnel are mobilized to activate the Technical Support Center (TSC) and the Operations Support Center (OSC). The Emergency Operations Facility/Recovery Center (EOF/RC) is activated with the Site Recovery Manager (SRM), the EOF Coordinator and other EOF/RC staff members. Sufficient emergency assistance personnel to assess off-site radiological impact are assigned if the Alert event is producing releases off-site.

Actual releases of radioactivity which substantially exceed Technical Specification limits may be involved and thus radiation monitoring and dose projection may be an integral portion of the emergency response required. Prompt notification is made to State authorities and follow-up information is provided as needed to off-site emergency organizations.

A Site Area Emergency indicates an event which involves likely or actual major failures of plant functions needed for the protection of the public. The possibility does exist for some releases of radioactive material and response to this event emphasizes the ability to monitor the releases and to provide action recommendations to State authorities and follow-up information as needed to off-site emergency organizations.

OP 3544 Rev. 2 Page 3 of 11

Plant resources are ahiicipated to be sufficient to cope with a Site Area Emergency.

Outside resources, however, are mobilized and selected members are dispatched to the site. All emergency centers are activated following declaration of a Site Area Emergency. All non-essential personnel are evacuated from the site. Representatives from adjoining States are dispatched to the Emergency Operations Facility. Assessment of plant conditions and off-site radiological parameters determine the type of protective measures necessary for protection of the public sector. The public is notified of the event by local media facilities and periodic updates of information are released to ensure uniform, adequate response to real conditions.

A General Emergency is declared when substantial core degradation or melting has occurred, with a potential for loss of containment integrity. The possibility does exist for releases of radioactive material and response to this event emphasizes the ability to monitor the releases and to provide for protective action recommendations to State authorities.

Contracted service organizations, sponsor utilities, and other industry resources are alerted and requested to render assistance as appropriate. In addition, Federal resources are called upon for assistance. Assessment of plant conditions and off-site radiological parameters determine the type of protective action recommendations.

Plant representatives closeout or escalate the emergency classification, or move to recovery as conditions warrant. Written summaries of the event are provided to off-site authorities and other affected agencies.

The Operations Support Center Coordinator (OSCC) is responsible for initiating this procedure following appointment by the Technical Support Center Coordinator.

In accordance with AP 6002, Preparing 50.59 Evaluations, the results of an Applicability Determination (AD) has determined that an AD is not required for future changes provided the scope of the procedure or program is not revised to include a different type of activity. The basis for this conclusion is that this document is an Emergency Implementing Procedure and is subject to 10CFR50.54(q) to determine if the changes decrease the effectiveness of the Emergency Plan and if they have the potential to affect our ability to meet the standards of 10CFR50.47(b) and the requirements of 10CFR50 Appendix E.

ATTACHMENTS

1. Appendix A Radiological Habitability Assessment

2. Appendix B On-Site Assistance Team Checklist

3. Appendix C OSC Staff Responsibilities

4. Table 1 Personnel Assignment List

5. VYOPF 3544.01 Emergency Conditions Radiological Assessment Form

6. VYOPF 3544.02 OSC Team Work Status Form OP 3544 Rev. 2 Page 4 of 11

REFERENCES AND COMMITMENTS

1. Technical Specifications and Site Documents

a. Vermont Yankee Nuclear Power Station Emergency Plan

2. Codes, Standards and Regulations

a. None

3. Commitments

a. EPEX86RP1

b. EPEX8803CPE1

c. INS9007CPE3

4. Supplemental References

a. AP 0009, Event Reports

b. AP 0010, Situational Reporting Requirements

c. AP 0021, Work Orders

d. AP 0140, Vermont Yankee Local Control Switching Rules

e. AP 0156, Notification of Significant Events

f. AP 0864, Fitness for Duty

g. AP 3125, Emergency Plan Classification and Action Level Scheme

h. OP 3504, Emergency Communications

i. OP 3507, Emergency Radiation Exposure Control

j. OP 3508, On-Site Medical Emergency Procedure

k. OP 3510, Off-Site and Site Boundary Monitoring

1. OP 3531, Emergency Call-In Method

m. OP 3540, Control Room Actions During an Emergency

n. OP 3541, Activation of the Technical Support Center (TSC)

o. OP 3542, Operation of the Technical Support Center (TSC)

p. OP 3545, Activation of the Emergency Operations Facility/Recovery Center (EOF/RC)

q. OP 3546, Operation of the Emergency Operations Facility/Recovery Center (EOF/RC)

r. OP 3547, Security Actions During an Emergency

s. AP 6807, Collection, Temporary Storage and Retrieval of QA Records PRECAUTIONS/LI MITATIONS

1. Refer to OP 3504 for alternate methods of communication in the event that primary methods fail.

OP 3544 Rev. 2 Page 5 of 11

PROCEDURE NOTES The responsible individual may assign actions required to other personnel as appropriate. The designated individual, however, has the overall responsibility for the execution of the checklist.

Record time and initials as required.

Steps may be performed concurrently or out of sequence.

Some steps have multiple signature lines, based on event level.

The step should be initialed for each event level it is completed for. If an event escalates, each step with that event level designator should be rechecked to ensure no further action is required.

OSC Coordinator Name (print): Date:

Time/Date Initials 1.0 Immediate Actions 1.1. Provide support to the Control Room as A /

requested. S /

G I 1.2. Assist in coordination of Operations relief A /

planning. S /

G I 1.3. Ensure that Operations Support Center (circle one)

(OSC) Staff is in place. (Complete A S G Table 1)

I/________

1.4. Assign an OSC Coordinator Assistant:

Name: /

1.5. IF there are indications that a stack release A /

is in progress, THEN have OSC personnel obtain a stack sample immediately. S /

(EPEX86RP1) G /

OP 3544 Rev. 2 Page 6 of 11

Time/Date Initials 1.6. IF there is no indication of a stack release, A /

THEN perform stack sampling as required. S /

G /

1.7. Ensure that the names of personnel (circle one) stationed at the OSC are reported to A S G Security as soon as possible.

(VYOPF 3524.02) 1.8. Assign a qualified individual to implement (circle one)

Appendix A, Radiological Habitability Assessment. A S G Name:

1.9. Designate a qualified individual (Ops.

SRO/Control Authority Qualified) to be (circle one)

Switching and Tagging Coordinator (see Appendix C). A S G Name: I ___________________

1.10. Utilizing white board located in OSC hallway, designate qualified personnel to implement the following emergency team assignments as applicable and as they become available:

1.10.1. Governor Hunt House Monitoring Team Names: _(Leader)

I _________________

The Team Leader or designee opens the GHH Monitoring Kit located at the OSC, obtains the clipboard and follows instructions per OP 3510.

(EPEX8803CPE1)

OP 3544 Rev. 2 Page 7 of 11

Time/Date Initials 1.10.2. Site Boundary Survey Team Names: (Leader)

The Team Leader or designee opens the Site Boundary Kit located at the OSC, obtains the clipboard and follows instructions per OP 3510.

1.10.3. Off-Site Green Team Names: _(Leader)

The Team Leader or designee opens one Off-Site Monitoring Kit located at the OSC, obtains the clipboard and follows instructions per OP 3510.

1.10.4. Off-Site Blue Team Names: (Leader)

The Team Leader or designee opens one Off-Site Monitoring Kit located at the OSC, obtains the clipboard and follows instructions per OP 3510.

1.10.5. Off-Site Black Team NOTE This additional off-site team may be deployed at the discretion of the Radiological Coordinator.

Names: _(Leader)

The Team Leader or designee opens one Off-Site Monitoring Kit located at the OSC, obtains the clipboard and follows instructions per OP 3510.

OP 3544 Rev. 2 Page 8 of 11

Time/Date Initials NOTE All work assignments from the TSC to the OSC should be made through the phone to the Communicator. Do not use the ring down phone or Gaitronics.

1.11. Coordinate the implementation of on-site assistance team activities with the TSC Coordinator as follows:

NOTE Depending on the nature of the task, teams will be assembled as appropriate. When more than one member is involved, a Work Coordinator will be assigned. The Work Coordinator or assigned individual has total responsibility for all work associated with the job.

1.11.1. Designate a Work Coordinator (if applicable) and team members based on job task requirements and conditions.

1.11.2. Maintain a continuous accountability of OSC on-site assistance team assignments and tasks as follows:

1.11.2.1. Complete the appropriate sections of VYOPF 3544.02, OSC Team Work Status Form. / _________________

NOTE Work Status forms (VYOPF 3544.02) are posted in the OSC hallway.

1.11.2.2.To help identify for OSC personnel the mission of the OSC Teams, ensure that VYOPF 3544.02, OSC Team Work Status Form is posted and updated in the OSC.

(INS9007CPE3) I _________________

OP 3544 Rev. 2 Page 9 of 11

Time/Date Initials 1.11.3. For tasks involving on-site repair activities, instruct the Work Coordinator or assigned individual to implement Appendix B, On-Site Assistance Team Checklist. I __________________

1.11.4. For tasks involving injured personnel of search and rescue activities, instruct the team members to implement applicable steps in Appendix B, On-Site Assistance Team Checklist, and OP 3508, On-Site Medical Emergency Procedure. / ___________________

1.11.5. Provide teams with the necessary instructions and pertinent plant status conditions to initiate and conduct job tasks. I __________________

1.11.6. When On-Site Assistance/Rescue Teams return from their assignments, ensure that the close out of the work effort is completed and documented. / ___________________

2.0 Subsequent Actions 2.1. Assist in the coordination of recovery A _

efforts as requested by the TSC. S /

G /

2.2. Coordinate the implementation of post accident sampling, and prioritize the assignment of desired samples to be collected and analyzed with the Radiation Protection Coordinator (or designated A _

alternate) at the TSC, as conditions S /

warrant. G _

OP 3544 Rev. 2 Page 10 of 11

Time/Date Initials 2.3. Periodically ensure that radiological assessment is performed according to Appendix A for the OSC, TSC, Control Room and Gates 1 and 2. / __________________

2.4. Ensure that unassigned OSC personnel remain within the OSC. / _________________

2.5. Periodically assess the personnel situation at the OSC, dispatch extra reserves to the EOF/RC as directed by the TSC Coordinator. / ___________________

2.6. Report findings to and receive instruction from the Shift Supervisor/Plant Emergency Director and/or the TSC Coordinator.

NOTE The OSC Coordinator will base his operations in the OSC but may find it necessary to go to the TSC from time to time.

2.7. If deemed necessary, assign as individual (circle one) to the TSC who will remain in contact with the OSC. A S G Name: / __________________

2.8. Periodically brief OSC personnel on current plant conditions and significant developments. I __________________

FINAL CONDITIONS

1. Ensure the OSC is returned to pre-emergency status.

2. Submit completed copies of this procedure to the TSC Coordinator.

3. Send all dosimetry and records to the Radiological Assistant for evaluation.

OP 3544 Rev. 2 Page 11 of 11

APPENDIX A RADIOLOGICAL HABITABIITY ASSESSMENT

1. Obtain a copy of OP 3507, Emergency Radiation Exposure Control.

2. Obtain a RM-14/20, a PIC-6, or other suitable dose rate instrument and a low volume air sampler. Perform the necessary function checks on the instrumentation.

3. If no multichannel analysis of the sample is available, utilize silver zeolite cartridges for quantitative iodine results.

4. Monitor conditions in the area(s) assigned:

NOTE Security at Gatehouse 2 do not routinely wear dosimetry. The habitability technician will inform Security when to don dosimetry.

OSC Responsibility OSC TSC Control Room Gate 1, 2 Other Areas:

5. Ensure the placement of two (2) high range ion chamber or electronic dosimeters in a representative location for the assessment of total exposure for each of the above locations.

6. Relative to KI usage, implement OP 3507.

7. Report findings and recommendations on VYOPF 3544.01 and submit to the TSC Coordinator or EOF Coordinator (if applicable).

NOTE Additional information, such as area surveys, should be recorded on the reverse side of VYOPF 3544.01.

Appendix A OP 3544 Rev. 2 Page 1 of 1

APPENDIX B ON-SITE ASSISTANCE TEAM CHECKLIST NOTE The Work Coordinator or assigned individual has total responsibility for all work associated with the job. Work Control process defined in AP 0021, Work Orders, must be used as appropriate.

1. Determine appropriate work controls, necessary equipment, spare parts, and services and their availability.

2. Receive status update and instructions from the OSC Coordinator or designated assistant.

3. Obtain appropriate radiation protection information and plant radiological conditions.

4. Ensure that a dose commitment for the job task is established in accordance with OP 3507, "Emergency Radiation Exposure Control".

5. Prior to team deployment, ensure that team members are briefed on the specific work controls and radiation protection controls to be followed for the job task.

6. Provide periodic updates on work effort status and other significant information to the OSC Coordinator or designated assistant especially area radiation levels and accrued exposure values.

7. Upon job completion, ensure that appropriate close out of the work effort is completed (i.e., job status notification, team debriefing, and work effort documentation).

Appendix B OP 3544 Rev. 2 Page 1 of 1

APPENDIX C osC STAFF RESPONSIBILITIES SWITCHING & TAGGING COORDINATOR (Control Authority):

NOTE The Control Authority will perform the following Tagging evolutions from the OSC using a manual process or by computer from the Tagging Desk if assigned by the OSC Coordinator.

Use current revision of AP 0140 for all Switching & Tagging requests.

Maintain Equipment Status Index using VYAPF 0140.05.

Use VYAPF 0140.01 to write tagging orders on which will be used by Switchman.

Handwrite information on tags for Switchman and fill out VYAPF 0140.03 for Tagging Order.

Issue Tagging Order to Switchman; have tags second verified by assigned Switchman.

Once tags are hung, update Equipment Status Index, VYAPF 0140.05, and notify Work Party Leader that tags are hung.

Sign Work Party Leader onto Tagging Order per telecom or in person per Control Authority discretion.

0 Authorize Work Party Leader to commence work.

& Work Party Leader notifies Control Authority that work is complete by telecom or in person.

0 Control Authority uses VYAPF 0140.03 to issue tags off restoration to Switchman.

Control Authority has second Switchman perform verification of Tagging restoration.

0 Control Authority updates Equipment Status Index, VYAPF 0140.05.

Appendix C OP 3544 Rev. 2 Page 1 of 1

TABLE 1 PERSONNEL ASSIGNMENT LIST Required for Activation Personnel OSC Coordinator Positions to be Staffed (not required for acti OSC Coordinator's Assistant Switching and Tagging Coordinator Radiological Habitability Assessment Work Coordinator Table I OP 3544 Rev. 2 Page 1 of 1

EMERGENCY CONDITIONS RADIOLOGICAL ASSESSMENT FORM DATE TIME LOCATION OF SAMPLING DATA Maximum Dose Rate (W.B.)

Average Dose Rate (W.B.)

Air Sample Results (silver zeolite cartridge? ["] YES LR NO).

RECOMMENDED ACTION (From sampling information and specifications in Appendices A and B of OP 3507, Emergency Radiation Exposure Control)

COMMENTS NOTE Additional information, such as area surveys, should be recorded on the reverse side of this form.

I Surveyor (print/sign) Date VYOPF 3544.01 OP 3544 Rev. 2 Page I of 1

OSC TEAM WORK STATUS FORM JOB NO. JOB LOCATION BRIEF JOB DESCRIPTION:

NAME OF OSC TEAM MEMBERS Work Coordinator (if applicable)

Team Members:

EMERGENCY DOSE COMMITMENT REQUIRED? (VYOPF 3507.02 ATTACHED)

[M YES [M NO RAD PROTECTION INITIALS:

TIME TEAM DISPATCHED: TIME TEAM RETURNED:

DISPOSITION OF JOB:

OSC COORDINATOR'S FINAL INITIALS:

[Copy and post in OSC hallway] VYOPF 3544.02 OP 3544 Rev. 2 Page 1 of I

10 CFR 50.54(q) Evaluation checklist List of Emergency Plan Section(s)/Emergency Plan Implementing Procedure(s) or any other document to be evaluated. (Include Title and Revision No.):

OP 3544, Rev. 2, Operation of the Operations Support Center (OSC)

A. Screening Evaluation Based on a review of the following questions, determine if the change has the potential to affect our ability to meet the standards of 10 CFR 50.47(b) and the requirements of Appendix E to 10 CFR 50.

A "YES" answer to any part of the questions requires that a written evaluation be done to determine whether the effectiveness of the Emergency Plan was decreased as specified in Section B of this checklist.

A "NO" answer to all questions requires no written evaluation as specified in Section B of this checklist.

1. Could the proposed change affect our ability to meet the following standards of 10 CFR 50.47(b):

(1) Assignment of Emergency Response Organization responsibilities 0 personnel (2) Assignment of on-shift Emergency Response organization YES NO (3) Arrangements for Emergency Response Support and Resources (4) Emergency Classification and Action levels, including facilitySy system and effluent parameters YES (5) Notification Methods and Procedures (6) Emergency Communications among principal response organizations the public YES NO (7) Public Education and Information YES NO (8) Adequacy of Emergency Facilities and Equipment YES NO (9) Adequacy of Accident Assessment methods, systems and equipment YES NO (10) Plume exposure pathway EPZ protective actions YES 0NO (11) Emergency Worker Radiological Exposure Control YES NO (12) Medical Services for contaminated injured individuals YES NO (13) Recovery and Reentry Plans YES NO (14) Emergency response periodic drills and exercises YES NO (15) Radiological Emergency Response Training YES NO (16) Plan development, review and distribution YES NO VYAPF 3532.01 AP 3532 Rev. 10 Page 1 of 3 RT No. 10.E06.171

10 CFR 50.54(q) Evaluation Checklist (Continued)

2. Could the change affect our ability to meet the following requirements of Appendix E to 10 CFR 50.

(1)Section IV. A - Organization YES (2)Section IV. B - Assessment Actions (3)Section IV. C - Activation of Emergency Organizations YES 0 (4)Section IV. D - Notification Procedures YES (5)Section IV. E - Emergency Facilities and Equipment YES 0 (6)Section IV. F - Training YES NO (7)Section IV. G - Maintaining Emergency Preparedness YES N (8)Section IV. H - Recovery YES NO B. Effectiveness Determination For each applicable (i.e., a "yes" answer specified) standard to 10 CFR 50.47(b) and Appendix E to 10 CFR 50 identified from Section A above, complete the evaluation form below to determine whether the change decreases the effectiveness of the Emergency Plan and whether it continues to meet the stated applicable standard or requirement.

A facsimile of the evaluation form may be used as needed and attached to this checklist.

For applicable item 10 CFR 50 n/a of Section A above, this change (DOES-QS decrease the effectiveness of the Emergency Plan and

j DOES NOT) continue to meet the stated applicable standard or requirement.

BASIS FOR ANSWER: Items added were enhancements and formalization of existing processes. These items do not decrease the effectiveness of the Eplan and continues to meet all requirements.

VYAPF 3532.01 AP 3532 Rev. 10 Page 2 of 3

10 CFR 50.54(q) Evaluation Checklist (Continued)

C. Conclusion (Fill out appropriate information)

E0 The changes made do not decrease the effectiveness of the Emergency Plan and continue to meet the standards of 10 CFR 50.47(b) and the requirements of Appendix E to 10 CFR 50.

0 The changes made do decrease the effectiveness of the Emergency Plan and decrease our ability to meet the standards of 10 CFR 50.47(b) and the requirements of Appendix E to 10 CFR 50. The following course of action is recommended:

[ Revise proposed changes to meet applicable standards and requirements.

0J Cancel the proposed changes.

[I Process proposed changes for NRC approval prior to implementation in accordance with 10 CFR 50.54(q).

D. Impact on Other Documents (TRM, Tech Specs)

Keywords used in search: SNi+th!iOIC.

0 This change does not affect any other documents.

0 This change does affect other documents.

Document(s) affected:

Section(s) affected:

E. Impact on the Updated FSAR Use AP 6036 to determine if the proposed E-Plan change modifies existing UFSAR information or requires the addition of new UFSAR information and initiate UFSAR change(s) as required.

Keywords used in UFSAR search: Swfthl!2 Ar Additional Comments:

Items added addressed formality.

Prepared By: Audra Williams Date: 7/25/02 Reviewed By: f- ' 4 C_2 f& -19 Date:

(Emergency Plan Coordinator)(PrinV/ ign)

VYAPF 3532.01 AP 3532 Rev. 10 Page 3 of 3

VERMONT YANKEE NUCLEAR POWER STATION OP 3504 REVISION 34 EMERGENCY COMMUNICATIONS USE CLASSIFICATION: REFERENCE I Implementation Statement: N/A Issue Date: 04/02/02 OP 3504 Rev. 34 Page 1 of 22

APPENDIX B OFF-SITE EMERGENCY TELEPHONE NUMBER LIST (In Alphabetical Order)

TELEPHONE NUMBER 860-561-3433 American Nuclear Insurers (ANI) 800-4l3* rommt 4)

AT&T (NOAA radio phone lines to Ames Hill)

Brattleboro Memorial Hospital Emergency Room (Ref. OP 3508) 802-257-8222 800-9921M CAN - Operations Manager (Ref. OP 3531) to verify 800-552-W or 877-786 wM operator and callback #s 800-739-MU(in-dial) 800-794 ~in-dial) 518-862.4MAdmin.)

Central Vermont Communications (Ref. OP 353 1) 800-696-6474 802-7754i*0(pager)

Consultation:

Dave E. Drum, MD, Radiation Safety Officer 617-732-l 'age 11161 (Ref. OP 3508) 781-23540 (home) 617-3234*5939 Voice Mail Department of Energy (DOE) Radiological Assistance, Brookhaven Lab 631-344-2200 Duke Engineering & Services, Marlborough, MA (Main switchboard)

(Ref. OP 3504, OP 3510, OP 3531) 508-229-2100 DE&S Pag;ers (Ref. OP 3531) 800-366 Franklin Medical Center (Ref. OP 3508) 413-772-0211 GE Emergency Support Assistance 408-971-1038 INPO Main Switchboard 770-644-8000 Emergency Network Telephone 800-321.M ISO - New England (Ref. OP 3504, OP 3506) 413-535-4384 Keene Dispatch (Ref. OP 3506) 603-352-1100 (Primary) 603-352-1291 (Backup)

Maine Yankee - Wiscasset (Ref. OP 3504) 207-882-6321 Massachusetts Emergency Management Agency - (State EOC) 508-820-2075 (Direct Line)

(Ref. OP 3504, OP 3506. OP 3540, OP 3546) 508-820-2000 (Switchboard)

Massachusetts State Police - Troop B, Northampton 413-586-3166 (Ref. OP 3504, OP 3540, OP 3542, OP 3546) 413-586-3166 800-833-9880 (Primary)

National Weather Service, Albany, NY 518-435-9574 (Backup)

(Ref. OP 3504, OP 3513, OP 3540) 508-389-2000 National Grid - Westboro (Ref. OP 3504) 508-389-2104 MUX Room (Ref. OP 3506) 603-223-3662 (Direct Line)

LPC. New Hampshire Office of Emergency Management - (State EOC) 603-271-2231 (Switchboard)

"(Ref.OP 3504. OP 3506, OP 3540, OP 3546)

Appendix B 34 OP 3504 Rev.

Page 1 of 2 LPC#2

APPENDIX B (Continued)

TELEPHONE NUMBER New Hampshire State Police 603-271-3636

\.) (Ref. OP 3504, OP 3540. OP 3542)

North Atlantic Energy Services Company - Seabrook (Ref. OP 3504) 603-474-9521 Lfc.. New York State Emergency Management Coordination 518-457-2200 or 518.457-2201 518-457-6811 (Backup)

Ctr. (Ref. OP 3506) 301-816-5100 NRC Operations Center (24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ), Rockville, MD 301-951-0550 (Backup)

(Ref. OP 3504, OP 3506, OP 3540) 301-415-0550 (Backup) 301-816-5151 (Fax)

NRC. Region I 800-432-1156 or LC.l 610-337-5000 Public Service of New Hampshire - Manchester 603-669-4000 (Ref. OP 3504)

Radiation Overexposure Treatment Assistance (Ref. OP 3508) 615-662-W (home)

Aaron B. Brill, MD 615-343-7152 (work)

U Mass Medical Center or Vanerbilt 615-322-3190 (work)

(NIAT Physician) 617-727-6214 (work)

Mr. Robert Hallisey 781-729-.(home) b (MDPH)

Mr. Robert Gallagher 617-727-6214 (work) 781-899-10 (home, M-F) 413-339-4 (home, Sat. & Sun.)

617-727-6214 (work)

Mr. Thomas Matthews 781-3961=(home)

(MDPH) 802-254-2010 or 911 Rescue Inc. (Ref. OP 3508) 413-625-8200 Shelburne Dispatch (Ref. OP 3506) 603-352-1100 or 603-352-1291 Southwest Mutual Fire Aid 413-625-8200 Tri-State Mutual Fire Aid 802-862-9883 National Weather Service (Burlington, VT) Forecasts 802-773-9161 (Switchboard)

VELCO Dispatcher (Rutland Office notification) 802-770-6261 (Dispatch) 802-865-7730 Vermont Department of Health 802-241-5476 (Direct Line)

WI Vermont Emergency Management Agency - (State EOC) 802-244-8721 (Switchboard)

(Ref. OP 3504, OP 3506, OP 3540, OP 3546) 800-347-0488 Vermont State Police 802-244-8727 (Ref. OP 3504, OP 3540, OP 3542, OP 3546)

VY Physician (Ref. OP 3508)

George Idelkope, MD 603-336-5948 (Work) 603-3634O(Home) 802-291-8000 Vernon Hydro (Wilder Station) (Ref. OP 3547) 413.424-5261 Yankee Rowe (Ref. OP 3504)

Appendix B 34 OP 3504 Rev.

Page 2of2 LPC #2

10 CFR 50.54(q) Evaluation Checklist List of Emergency Plan Section(s)/Emergency Plan Implementing Procedure(s) or any other document to be evaluated. (Include Title and Revision No.):

OP 3504, Rev. 34, Emergency Communications A. Screening Evaluation Based on a review of the following questions, determine if the change has the potential to affect our ability to meet the standards of 10 CFR 50.47(b) and the requirements of Appendix E to 10 CFR 50.

A "YES" answer to any part of the questions requires that a written evaluation be done to determine whether the effectiveness of the Emergency Plan was decreased as specified in Section B of this checklist.

A "NO" answer to all questions requires no written evaluation as specified in Section B of this checklist.

1. Could the proposed change affect our ability to meet the following standards of 10 CFR 50.47(b):

(1) Assignment of Emergency Response Organization responsibilities YES NO (2) Assignment of on-shift Emergency Response Organization personneP YES N (3) Arrangements for Emergency Response Support and Resources r YES &N (4) Emergency Classification and Action levels, including facility system and effluent parameters YES (5) Notification Methods and Procedures YES (6) Emergency Communications among principal response organizations d the public YES NO (7) Public Education and Information YES NO (8) Adequacy of Emergency Facilities and Equipment YES NO (9) Adequacy of Accident Assessment methods, systems and equipment YES No (10) Plume exposure pathway EPZ protective actions YES N (11) Emergency Worker Radiological Exposure Control YES NO (12) Medical Services for contaminated injured individuals YES NO (13) Recovery and Reentry Plans YES NO (14) Emergency response periodic drills and exercises YES (15) Radiological Emergency Response Training YES N (16) Plan development, review and distribution YES 0 VYAPF 3532.01 AP 3532 Rev. 10 Page 1 of 3 RT No. 10.E06.171

10 CFR 50.54(q) Evaluation Checklist (Continued)

2. Could the change affect our ability to meet the following requirements of Appendix E to 10 CFR 50.

(1)Section IV. A - Organization YES 0 (2)Section IV. B - Assessment Actions (3)Section IV. C - Activation of Emergency Organizations Procedures (4)Section IV. D - Notification YES YES (5)Section IV. E - Emergency Facilities and Equipment (6)Section IV. F - Training YES 0 (7)Section IV. G - Maintaining Emergency Preparedness (8)Section IV. H - Recovery YES NO B. Effectiveness Determination For each applicable (i.e., a "yes" answer specified) standard to 10 CFR 50.47(b) and Appendix E to 10 CFR 50 identified from Section A above, complete the evaluation form below to determine whether the change decreases the effectiveness of the Emergency Plan and whether it continues to meet the stated applicable standard or requirement.

A facsimile of the evaluation form may be used as needed and attached to this checklist.

For ap l beebI-,,item 10 CFR 50 _rii of Section A above, this change S/IS NOT9 decrease the effe ctiveness of the Emergency Plan and DOES DOES KDT) continue to meet the stated applicable standard or ftrqtrirement.

BASIS FOR ANSWER.A4 12 0I 4 CCU~r~

fiy-Pt C

D~c TJeiQvn O F 1Wfi4ffre i o v&'f-1~4rd MO s~- in Spztw VYAPF 3532.01 AP 3532 Rev. 10 Page 2 of 3

10 CFR 50.54 (q) Evaluation Checklist (Continued)

C. Conclusion (Fill out appropriate information)

Ef The changes made do not decrease the effectiveness of the Emergency Plan and continue to meet the standards of 10 CFR 50.47(b) and the requirements of Appendix E to 10 CFR 50.

0 The changes made do decrease the effectiveness of the Emergency Plan and decrease our ability to meet the standards of 10 CFR 50.47(b) and the requirements of Appendix E to 10 CFR 50. The following course of action is recommended:

o Revise proposed changes to meet applicable standards and requirements.

0 Cancel the proposed changes.

E3 Process proposed changes for NRC approval prior to implementation in accordance with 10 CFR 50.54(q).

D. Impact on Other Documents (TRM, Tech Specs)

Keywords used in search:

E This change does not affect any other documents.

O This change does affect other documents.

Document(s) affected:_

Section(s) affected:

E. Impact on the Updated FSAR Use AP 6036 to determine if the proposed E-Plan change modifies existing UFSAR information or requires the addition of new UFSAR information and initiate UFSAR change(s) as required.

Keywords used in UFSAR search:

Additional Comments:

a4vvia C5("aVe Wi Prepared By: Date: ____ ____ ___

" ~(Print/Sion)

Reviewed By: Date: g"i\o.

(Emergency Plan C~ordinator) (Print/tign)

VYAPF 3532.01 AP 3532 Rev. 10 Page 3 of 3

VERMONT YANKEE NUCLEAR POWER STATION OP 3505 REVISION 24 EMERGENCY PREPAREDNESS EXERCISES AND DRILLS USE CLASSIFICATION: INFORMATION, except for Appendix A, which is classified as CONTINUOUS LPC Effective Affected Pages No. Date 1 07/26/02 114 of 17; VYOPF 3505.01 Pg 4 of 4 I I Implementation Statement: N/A Issue Date: 06/06/02 OP 3505 Rev. 24 Page 1 of 17

e. Prior to the drill, the EPDETC ensures the following are notified:

1) Director of Public Affairs & Human Resources

2) Radiation Protection Manager

3) Operations Manager

4) Security Manager

5) NRC Resident Inspector

6) Safety Coordinator

f. The EPDETC briefs controllers on the drill and issues Emergency Exercise/Drill Controller's Evaluation Form, VYOPF 3505.02.

g. The EPDETC conducts a critique for controllers and participants to present their observations and comments. All weaknesses and deficiencies are documented and resolved as outlined in Section C.

h. All Emergency Exercise/Drill Controller's Evaluation Forms are collected by the EPDETC at the conclusion of the critique.

2. Health Physics Drills

a. A drill is conducted semi-annually which involves response to and analysis of, simulated elevated in-plant airborne and liquid samples, and I*r direct radiation measurements in the environment (inside plant or outside of plant). The semi-annual Health Physics Drills are conducted as follows:

1) One of the drills may be performed as part of the required Emergency Preparedness Exercise/Drill.

2) One of the drills is performed separately, and following the guidelines outlined in this procedure.

3) One of the drills should include use of the post-accident sampling system.

NOTE Time frame to conduct the drill should allow enough time for obtaining and counting planned drill chemistry samples.

b. In conjunction with the Chemistry Manager and the Radiation Protection Manager, the EPDETC directs the development of a drill scenario utilizing the Health Physics Drill Planning Form, VYOPF 3505.05.

c. The EPDETC briefs controllers on the drill and distributes Emergency Exercise/Drill Controller's Evaluation Form, VYOPF 3505.02.

OP 3505 Rev. 24 Page 14 of 17 LPC#1

EMERGENCY PREPAREDNESS EXERCISE/DRILL PLANNING FORM (Continued)

ý* C, / P. Gouger's Market & Deli Person Contacted: Date:

Degree of Participation (if required)/Contract Valid:

Initials:

Q. Brattleboro Fire Department Date:

Person Contacted:

Degree of Participation (if required)/Agreement Letter Valid:

Initials:

R. Town of Vernon Persdn Contacted: Date:

Degree of Participation (if required)/Agreement Letter Valid:

Initials:

S. Institute of Nuclear Power Operations Date:

Person Contacted:

Degree of Participation (if required)fAgreement Letter Valid:

Initials:

T. Yankee Nuclear Power Station Person Contacted: Date:

Degree of Participation (if required)/Agreement Letter Valid:

Initials:

U. Department of Energy Date:

Person Contacted:

Degree of Participation (if required)fAgreement Letter Valid: Initials:

V. Framnatome ANP DE&S (TLD Lab)

P_1 I Date:

Person Contacted:

Degree of Participation (if required)/Agreement Letter Valid:

Initials:

Initials:______

VYOPF 3505.01 OP 3505 Rev. 24 Page 4 of 4 LPC#1

10 CFR 50.54(q) Evaluation Checklist List of Emergency Plan Section(s)/Emergency Plan Implementing Procedure(s) or any other document to be evaluated. (Include Title and Revision No.):

OP 3505, Rev. 24, LPC #1, Emergency Preparedness Exercises & Drills A. Screening Evaluation Based on a review of the following questions, determine if the change has the potential to affect our ability to meet the standards of 10 CFR 50.47(b) and the requirements of Appendix E to 10 CFR 50.

A "YES" answer to any part of the questions requires that a written evaluation be done to determine whether the effectiveness of the Emergency Plan was decreased as specified in Section B of this checklist.

A "NO" answer to all questions requires no written evaluation as specified in Section B of this checklist.

1. Could the proposed change affect our ability to meet'the following standards of 10 CFR 50.47(b):.

(1) Assignment of Emergency Response Organization responsibilities YES N (2) Assignment of on-shift Emergency Response Organization personnel YES N (3) Arrangements for Emergency Response Support and Resources a (4) Emergency Classification and Action levels, including facility system and effluent parameters (5) Notification Methods and Procedures . YES N (6) Emergency Communications among principal response organizations the public YES § (7) Public Education and Information (8) Adequacy of Emergency Facilities and Equipment YES 0 (9) Adequacy of Accident Assessment methods, systems and equipment

( YES (10) Plume exposure pathway EPZ protective actions YES (11) Emergency Worker Radiological Exposure ControlYs injured individuals (12) Medical Services for contaminated (13) Recovery and Reentry PlansYE YES (14) Emergency response periodic drills and exercises YEs YES (15) Radiological Emergency Response Training YES (16) Plan development, review and distribution VYAPF 3532.01 AP 3532 Rev. 10 Page I of 3 RT No. 10.EO6.171

10 CFR 50.54(q) Evaluation Checklist (Continued)

2. Could the change affect our ability to meet the following requirements of Appendix E to 10 CFR 50.

(1)Section IV. A - Organization YES (2) Section IV. B - Assessment Actions (3) Section IV. C - Activation of Emergency Organizations (4) Section IV. D - Notification Procedures (5) Section IV. E - Emergency Facilities and Equipment YES (6) Section IV. F - Training YES (7) Section IV. G - Maintaining Emergency Preparedness YESN (8) Section IV. H - Recovery YES I B. Effectiveness Determination For each applicable (i.e., a "yes" answer specified) standard to 10 CFR 50.47(b) and Appendix E to 10 CFR 50 identified from Section A above, complete the evaluation form below to determine whether the change decreases the effectiveness of the Emergency Plan and whether it continues to meet the stated applicable standard or requirement.

A facsimile of the evaluation form may be used as needed and attached to this checklist.

For applicable item 10 CFR 50 n of Section A above, this change (DOES/DOES NOT) decrease the effectiveness of the Emergency Plan and (DOES/DOES NOT) continue to meet the stated applicable standard or requirement.

BASIS FOR ANSWER: Wording was added to clarify and correspond with the Emergency Plan to specify that simulated elevated airborne samples are in-plant and direct radiation measurements are in the environment (inside plant or outside of plant) . rde!d Wodi=9 tw -Eitf a W1ILtUL xa..r. .%

-I-wr,,1A "" '-"-plct aftzr rill J Jzzr wa.. a rorma.i.K 1

fl ~enu~+/- as tnis was aireacy'beiLIY Gt. Editorial vendor name changes to VYOPF 3505.01 Form. None of the changes decrease the effectiveness of the Eplan and continues to meet the requirements.

VYAPF 3532.01 AP 3532 Rev. 10 Page 2 of 3

10 CFR 50.54(q) Evaluation Checklist (Continued)

C. Conclusion (Fill out appropriate information)

Ef The changes made do not decrease the effectiveness of the Emergency Plan and continue to meet the standards of 10 CFR 50.47(b) and the requirements of Appendix E to 10 CFR 50.

[3 The changes made do decrease the effectiveness of the Emergency Plan and decrease our ability to meet the standards of 10 CFR 50.47(b) and the requirements of Appendix E to 10 CFR 50. The following course of action is recommended:

o] Revise proposed changes to meet applicable standards and requirements.

o Cancel the proposed changes.

o Process proposed changes for NRC approval prior to implementation in accordance with 10 CFR 50.54(q).

D. Impact on Other Documents (TRM, Tech Specs)

Keywords used in search: airborne samples, environment

[l This change does not affect any other documents.

[3 This change does affect other documents.

Document(s) affected:

Section(s) affected:

E. Impact on the Updated FSAR Use AP 6036 to determine if the proposed E-Plan change modifies existing UPSAR information or requires the addition of new UFSAR information and initiate UFSAR change(s) as required.

Keywords used in UFSAR search: airborne samples, environment Additional Comments:

These changes are formality of practices already being performed.

Prepared By: Audra William*_

(Prin -t/Sign, (L n T*Date: 7/26/02

-/?

Reviewed By: k("mer kcd*cy Pa rnate: Dria (Emergency Plan Cordi fator)'(rit n VYAPF 3532.01 AP 3532 Rev. 10 Page 3 of 3

VERMONT YANKEE NUCLEAR POWER STATION

-E J

OP 3546 REVISION 1 OPERATION OF THE EMERGENCY OPERATIONS FACILITY/RECOVERY CENTER (EOF/RC)

USE CLASSIFICATION: REFERENCE LPC Effective Affected Pages No. Date 1 07/24/02 6 & ADDED 6A of 6 2 07/31/02 5 of 6; App. A Pgs 4 & 7 of 7; ADDED TABLE 2 PG 1 OF 1 Implementation Statement: N/A I Issue Date: 06/06/02 OP 3546 Rev. 1 Page 1 of 6

8. Appendix H EOF Engineering Support Group Assistant

9. Appendix I Recovery Manager Staff Responsibilities

10. Appendix J Respi6fise Check of RM-14/Frisker Prob6

11. Appendix K EOF Engineering Equipment Locations

12. VYOPF 3546.01 Plant Status Briefing Form

13. VYOPF 3546.02 Emergency Classification and PAR Notification Form

14. VYOPF 3546.03 Instructions to Personnel Prior to Being Released from the Assembly Area

15. VYOPF 3546.04 Technical Representative Escalation Checklist/Script

16. Table 1 Radiological Assistant's Organization PLFC n 17. Table 2 White Plains Recovery Support Group Corporate Call List REFERENCES AND COMMITMENTS

1. Technical Specifications and Site Documents

a. Vermont Yankee Nuclear Power Station Emergency Plan

2. Codes, Standards and Regulations

a. None

3. Commitments

a. INS8722-01

b. E_Drill-98EOF3

c. LAI-801

d. EPEX97TSC-2

4. Supplemental References

a. AP 0009, Event Reports

b. AP 0010, Situational Reporting Requirements

c. AP 0021, Work Orders

d. AP 0156, Notification of Significant Events

e. AP 0864, Fitness for Duty

f. AP 3125, Emergency Plan Classification and Action Level Scheme

g. OP 3504, Emergency Communications

h. OP 3507, Emergency Radiation Exposure Control

i. OP 3508, On-Site Medical Emergency Procedure

j. OP 3509, Environmental Sample Collection During an Emergency

k. OP 3510, Off-Site and Site Boundary Monitoring

1. OP 3511, Off-Site Protective Action Recommendations

m. OP 3513, Evaluation of Off-Site Radiological Conditions

n. OP 3531, Emergency Call-In Method

o. OP 3540, Control Room Actions During an Emergency

p. OP 3541, Activation of the Technical Support Center (TSC)

q. OP 3542, Operation of the Technical Support Center (TSC)

r. OP 3544, Operation of the Operations Support Center (OSC)

OP 3546 Rev. 1 Page 5 of 6 LPC #2

s. OP 3545, Activation of the Emergency Operations Facility/Recovery Center (EOF/RC)

t. OP 3547, Security Actions During an Emergency

u. AP 6807, Collection, Temporary Storage and Retrieval of QA Records Sv. PP 7019, Severe Accident Management Program PRECAUTIONS/LIMITATIONS

1. Refer to OP 3504 for alternate methods of communication in the event that primary methods fail.

PROCEDURE NOTE With the exception of authorizir ig Protective Action Recommendations and classifications, actions requJired in each appendix may be assigned by the responsible individual to other personnel as appropriate. The the designated individual, however, has the overall responsibility for execution of the appendix.

1. Select the appropriate appendix:

a. Appendix A, Site Recovery Manager

b. Appendix B, Emergency Operations Facility Coordinator C. Appendix C, Emergency Operations Facility Coordinator Assistant

d. Appendix D, Personnel & Equipment Monitoring Team

e. Appendix E, Communications Assistant

f. Appendix F, Radiological Assistant

g. Appendix G, Manpower & Planning Assistant NOTES Some spaces have multiple signature lines, based on event level.

The step should be initialed for each event level it is completed for.

If an event escalates, each step with that designator should be rechecked to ensure no further action is required.

0 Steps may be performed concurrently or out of sequence.

2. Complete the appropriate appendix and record time and initials as required.

OP 3546 Rev. 1 Page 6 of 6 LPC #1

3. Alternate Assembly and Staging Area

a. If a Code Red Security Event occurs during off-hours, the Emergency Operations Facility will be used as an alternate assembly and staging area for personnel who o, would normally report to emergency response facilities at the plant site. A pager code of "777" and a Community Alert Message notifies personnel to report to the EOF in an off-hours Code Red Security Event.

b. The warehouse (News Media Center) will be used for the alternate assembly and staging area. The News Media Center will be relocated in a Code Red Security Event occurring after hours.

c. EOF staff will activate the EOF per procedure. TSC/OSC personnel arriving at the EOF will be directed to the alternate assembly and staging area. Personnel will sign in at the assembly area to provide an available manpower list.

d. The TSC Coordinator and OSC Coordinator will organize response teams based L on the nature of the emergency and release second shift personnel.

FINAL CONDITIONS

1. Return all completed Appendices and forms to the Emergency Plan Coordinator for filing per AP 6807.

OP 3546 Rev. 1 Page 6A of 6 LPC #1

APPENDIX A (Continued)

Time/Date Initials NOTE States' notification must be initiated within 15 minutes of emergency classification declaration.

16.3. Ensure that the notification of the VT/NH/MA State EOCs is being implemented per I VYOPF 3546.02, Emergency Classification and PAR Notification Form. (Compliance Advisor) G _

16.4. If any State EOC is not manned, and the EOF/RC State representative is not present, notify the appropriate State Police agency per S /

I VYOPF 3546.02. (Compliance Advisor) G /

16.5. Inform each EOF/RC State representative of the transition on the emergency class and the condition A /

producing the change. (SRM State Advisor) S /

A /

16.6. After completion of the State's notification, SRM I acknowledges that the States' notification has been S

completed.

16.7. Notify White Plains Recovery Support Group A I L, C.a Managers of escalation per Table 2. S /

Q ý/

(circle one) 17.0 IF the State of Vermont issues an evacuation order for S G Brattleboro, THEN contact the Nuclear Information Director and discuss impact on the News Media Center (NMC).

(circle one) 18.0 IF a decision is made to evacuate the NMC, THEN announce that, as a precautionary measure, all declared S G pregnant staff should evacuate the EOF.

(EDrill-98EOF3) 19.0 Ensure VYOPF 3546.01 is faxed to the TSC to update the TSC Coordinator of any protective actions the States may be implementing. (Media Advisor Assistant)

Appendix A OP 3546 Rev. 1 Page 4 of 7 LPC #2

APPENDIX A (Continued)

Time/Date Initials

5. Provide a verbal close-out of the event with off-site authorities and agencies as follows:

a. NRC /

/

b. State of Vermont I

c. State of New Hampshire

/

d. Commonwealth of Massachusetts

6. Site Recovery Manager will notify White Plains Recovery Managers of de-escalation to a recovery /

phase per Table 2.

7. Initiate an Event Report per AP 0009 for the event I that resulted in the declaration of the emergency.

NOTE Emergency Planning will sign off step 8.

8. When a written report is generated, ensure a copy is forwarded to the Emergency Plan Coordinator for the following off-site authorities:

II a. Director of Vermont Emergency Management, State of VT

b. Director of Massachusetts Emergency Management, Commonwealth of MA I c. Director of New Hampshire Emergency Management, State of NIH I

Appendix A OP 3546 Rev. 1 Page 7 of 7 LPC #2

TABLE 2

?~C, WHITE PLAINS RECOVERY SUPPORT GROUP CORPORATE CALL LIST RECOVERY SUPPORT GROUP MANAGERS (For notification of escalation)

" A "f*l'* T-T AMVI* PT-TflNTff IWORK PHONE I PAGEL{# I G. Wilverding (203) 938-0540 (914) 272-3375 718-3375*

M. Karasulu (914) 245-0525 (914) 272-3442 718-3442*

0. Canavan (212) 989-0449 (914) 272-3440 718-3440*

Rorke (516) 767-7587 (914) 272-3428 718-3428* SG.

RECOVERY MANAGERS (For notification of de-escalation to a recovery phase)

NAME HOME PHONE WORK PHONE PAGER #

H. Salmon (914) 734-7690 (914) 272-3220 800-734-9140 D. Robson (914) 686-7284 (914) 272-3452 800-844-8084 Pin: 1487471 T. Dougherty (718) 961-1907 (914) 272-3451 718-3451*

J. Kelly (845) 947-2095 (914) 272-3370 888-593-5942 L

1-800-436-2732 Table 2 OP 3546 Rev. 1 Page I of 1 LPC #2

10 CFR 50.54(q) Evaluation Checklist List of Emergency Plan Section(s)/Emergency Plan Implementing Procedure(s) or any other document to be evaluated. (Include Title and Revision No.):

OP 3546, Rev. l,LPC 1, Operation of the Emergency Operations Facility/Recovery Center (EOF/RC)

A. Screening Evaluation Based on a review of the following questions, determine if the change has the potential to affect our ability to meet the standards of 10 CFR 50.47(b) and the requirements of Appendix E to 10 CFR 50.

A "YES" answer to any part of the questions requires that a written evaluation be done to determine whether the effectiveness of the Emergency Plan was decreased as specified in Section B of this checklist.

A "NO" answer to all questions requires no written evaluation as specified in Section B of this checklist.

I. Could the proposed change affect our ability to meet the following standards of 10 CFR 50.47(b):

(1) Assignment of Emergency Response Organization responsibilitil "YE NO Assignment of on-shift Emergency Response Organization personnel (2)

(3) Arrangements for Emergency Response Support and Resources 0 S NO (4) Emergency Classification and Action levels, including facility system and effluent parameters YES (5) Notification Methods and Procedures

NO (6) Emergency Communications among principal response organizat and the public and Information (7) Public Education YES (8) Adequacy of Emergency Facilities and Equipment (9) Adequacy of Accident Assessment methods, systems and equipment YES~

(10) Plume exposure pathway EPZ protective actions (BSNO (11) Emergency Worker Radiological Exposure Control YE 0 (12) Medical Services for contaminated injured individuals YES (13) Recovery and Reentry Plans YES (14) Emergency response periodic drills and exercises YES (o)

(15) Radiological Emergency Response Training YES (16) Plan development, review and distribution YES VYAPF 3532.01 AP 3532 Rev. 10 Page 1 of 3 RT No. I0.E06.171

10 CFR 50.54(q) Evaluation Checklist (Continued)

2. Could the change affect our ability to meet the following requirements of Appendix E to 10 CFR 50.

(1)Section IV. A - Organization Section IV. B Assessment Actions E NO (2) -

YES 0 (3) Section IV. C - Activation of Emergency Organizations NO (4) Section IV. D - Notification Procedures YSNO (5) Section IV. E - Emergency Facilities and Equipment YES~

(6) Section IV. F - Training YES~

(7) Section IV. G - Maintaining Emergency Preparedness YESg (8) Section IV. H - Recovery.

YES B. Effectiveness Determination For each applicable (i.e., a "yes" answer specified) standard to 10 CFR 50.47(b) and Appendix E to 10 CFR 50 identified from Section A above, complete the evaluation form below to determine whether the change decreases the effectiveness of the Emergency Plan and whether it continues to meet the stated applicable standard or requirement.

A facsimile of the evaluation form may be used as needed and attached to this checklist.

For applicable item 10 CFR 50.47(b) (1), (3), (5) (10) & App E.IV.A,C&D of Section A above, this chane (DOEStDES NO, decrease the effectiveness of the Emergency Plan and NOT)

NODOES continue to meet the stated applicable standard or requirement.

BASIS FOR ANSWER:

This revision includes considerations from the NRC Security Order. This includes having an alternate assembly &.staging area if it is not prudent to staff the Technical Support Center (TSC). This does not decrease the effectiveness of the E-Plan. 10 CFR 50.47(b) (10) requires development of a range of protective actions for emergency workers. When an emergency is declared due to a security condition, staffing the TSC may put personnel at risk. Using an alternate assembly and staging area under these circumstances is a protective action for the emergency worker. This protective action precludes activation of the on-site emergency facilities, however, the Emergency Operations Facility would be staffed and assume the duties normally performed by on-site individuals.

VYAPF 3532.01 AP 3532 Rev. 10 Page 2 of 3

10 CFR 50.54(q) Evaluation Checklist (Continued)

C. Conclusion (Fill out appropriate information)

W The changes made do not decrease the effectiveness of the Emergency Plan and continue to meet the standards of 10 CFR 50.47(b) and the requirements of Appendix E to 10 CFR 50.

0 The changes made do decrease the effectiveness of the Emergency Plan and decrease our ability to meet the standards of 10 CFR 50.47(b) and the requirements of Appendix E to 10 CFR 50. The following course of action is recommended:

0 Revise proposed changes to meet applicable standards and requirements.

O] Cancel the proposed changes.

o Process proposed changes for NRC approval prior to implementation in accordance with 10 CFR 50.54(q).

D. Impact on Other Documents (TRM, Tech Specs)

Keywords used in search: emergency, staffing, communications V This change does not affect any other documents.

0 This change does affect other documents.

Document(s) affected:

Section(s) affected:

E. Impact on the Updated FSAR Use AP 6036 to determine if the proposed E-Plan change modifies existing UFSAR information or requires the addition of new UFSAR information and initiate UFSAR change(s) as required.

Keywords used in UFSAR search: emergency, staffing, communications Additional Comments:

Prepared By: Audm WilIY's ju&aL k & 1 Date: 1-2.5O2 (Print/Sign)

Reviewed By: L..o A.exIv-ac ,,4r-

-n-)

Date: 1Ai~

(Emergency Plan Coordinator) (Print/S VYAPF 3532.01 AP 3532 Rev. 10 Page 3 of 3

ML022480167

Text

Subject:

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