ML033230051

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Revision to Emergency Plan Implementing Procedures
ML033230051
Person / Time
Site: Ginna Constellation icon.png
Issue date: 11/07/2003
From: Watts R
Rochester Gas & Electric Corp
To: Clark R
Document Control Desk, NRC/NRR/DLPM/LPD1
References
Download: ML033230051 (15)
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Text

An Energy East Company ROCHESTER GAS AND ELECTRIC CORPORATION 89 EASTAVENUE, ROCHESTER, N.Y 14649-0001

  • 585 546-2700 www.wrge.com November 7, 2003 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn: Mr. Robert Clark (Mail Stop 0-8-E9)

Project Directorate 1-1

Subject:

Revision to Emergency Plan Implementing Procedures R.E. Ginna Nuclear Power Plant Docket No. 50-244 Gentlemen:

In accordance with 10 CFR 50.4(b)(5), enclosed is a revision to a Ginna Station Emergency Plan Implementing Procedure (EPIP).

We have determined, per the requirements of 10 CFR 50.54(q), that the procedure change does not decrease the effectiveness of our Nuclear Emergency Response Plan.

Very truly yours, Richard J. Watts Manager, Nuclear Training Department Enclosures xc: USNRC Region 1 (2 copies of letter and 2 copies of each procedure)

Resident Inspector, Ginna Station (1 copy of letter and 1 copy of each procedure)

RG&E Nuclear Safety and Licensing (1 copy of letter)

Dr. Robert C. Mecredy (2 copies of letter only)

RJW/jtw 5CQA

U.S. Nuclear Regulatory Commission November 7, 2003 Page 2 of 2 PROCEDURE REVISION NUMBER EPIP 2-5 15

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NPSP0200 Ginna Nuclear Power Plant Fri 11/7/2003 8:34:10 am WILLOUGHBYJ PROCEDURE INDE)( Page 1 of 2 INPUT PARAMETERS: TYPE: PREPP STATUSVALUE(S): EF I 5YEARS ONLY:

PREPIP EMERGENCY PLAN IMPLEMENTING PROCEDURE PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW - REVIEW- -

ST EPIP-1-0 GINNA STATION EVENT EVALUATION AND CLASSIFICATION 032 09/2212003 06/20/2003 06120/2008 2:

EF EPIP-1-1 UNUSUAL EVENT 004 05/23/2003 05/23/2003 05123/2008 EF EPIP-1-2 ALERT 004 11/02/2001 11/02/2001 11/02/2006 EF EPIP-1-3 SITE AREA EMERGENCY 005 12/09/1996 04/09/2003 04/09/2008 EF EPIP-1-4 GENERAL EMERGENCY 006 05/05/2003 05/05/2003 05/05/2008 EF EPIP-1-5 NOTIFICATIONS 056 09122/2003 09/22/2003 09/22/2008 EF-EPIP-1-6 SITE EVACUATION 017 06/20/2003 06/20/2003 06/20/2008 EF-EPIP-1-7 ACCOUNTABIULTY OF PERSONNEL 009 11/0212001 11/0212001 11/0212006 EF EPIP-1-8 SEARCH AND RESCUE OPERATION 006 05/23/2003 05/23/2003 05/23/2008 EF EPIP-1-9 TECHNICAL SUPPORT CENTER ACTIVATION 025 08/08/2003 08/08/2003 08/0812008 EF EPIP-1-10 OPERATIONAL SUPPORT CENTER (OSC) ACTIVATION 013 05/23/2003 05/23/2003 0512312008 EF EPIP-1-11 SURVEY CENTER ACTIVATION 029 02/25/2003 02/25/2003 02/25/2008 EF EPIP-1-12 REPAIR AND CORRECTIVE ACTION GUIDELINES DURING EMERGENCY SITUATIONS 009 12/20/2001 12/2012001 12/20/2006 EF EPIP-1-13 LOCAL RADIATION EMERGENCY 005 10/14/2003 10/14/2003 10/14/2008 EF EPIP-1-15 USE OF THE HEALTH PHYSICS NETWORK HPN 005 04124/1996 03/03/1999 03/03/2004 EF EPIP-1-16 RADIOACTIVE UQUID RELEASE TO LAKE ONTARIO OR DEER CREEK 005 02/25/2003 0225/2003 02/25/2008 EF EPIP-1-17 PLANNING FOR ADVERSE WEATHER 004 05/2312003 05/23/2003 05/23/2008 EF.

EPIP-1-18 DISCRETIONARY ACTIONS FOR EMERGENCY CONDONS. 006 05/05/2003 05/05/2003 05/05/2008 EF.

EPIP2-1 PROTECTIVE ACTION RECOMMENDATIONS 021 08/08/2003 08/08/2003 08/08/2008 EF EPIP-2-2 OBTAINING METEOROLOGICAL DATA AND FORECASTS AND THEIR USE INEMERGENCY DOSE AS 013 12/0312002: 12/03/2002 12/03/2007 EF EPIP-2-3 EMERGENCY RELEASE RATE DETERMINATION 015 07/01/2002 07/01/2002 07/01/2007 EF EPIP-2-4 EMERGENCY DOSE PROJECTIONS - MANUAL METHOD 014 08/08/2003 08/08/2003 08/08/2008 EF EPIP-2-5 EMERGENCY DOSE PROJECTIONS PERSONAL COMPUTER METHOD 015 11/07/2003 11/07/2003 1110712008 EF EPIP-2-6 EMERGENCY DOSE PROJECTIONS- MIDAS PROGRAM 013 10/0812003 10/08/2003 10/08/2008 EF EPIP-2-4 MANAGEMENT OF EMERGENCY SURVEY TEAMS 011 08/0912002 08/09/2002 08/09/2007 EF EPIP-2-8 VOLUNTARY ACCEPTANCE OF EMERGENCY RADIATION EXPOSURE 006 09/22/2003 09/22/2003 09/22/2008 EF EPIP-2-9 ADMINISTRATION OF POTASSIUM IODIDE (1a) 008 05/2312003 05/2312003 05/23/2008 EF EPIP-2-10 INPLANT RADIATION SURVEYS 004 08/0912002 08/09/2002 08/09/2007 EF EPIP-2-1I ONSITE SURVEYS 019 05/15/2002 05/1512002 05/15/2007 EF EPIP-2-12 OFFSITE SURVEYS 022 05/1512002 05/1512002 05/15/2007

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iV NPSP0200 Ginna Nuclear Power Plant Fri 1117/2003 8:34:10 am WILLOUGHBYJ PROCEDURE INDEX Page 2 of 2 INPUT PARAMETERS: TYPE: PREPIP STATUS VALUE(S): EF 5YEARS ONLY:

PREPIP EMERGENCY PLAN IMPLEMENTING PROCEDURE PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVEW ST EPIP-2-13 IODINE AND PARTICULATE ACTIVITY DETERMINATION FROM AIR SAMPLES 008 07/27/1999 07/27/1999 07/27/2004 EF EPIP-2-14 POST PLUME ENVIRONMENTAL SAMPLING 015 10/08/2002 10/08/2002 10/08/2007 EF EPIP-2-15 POST PLUME EVALUATION OF OFFSITE DOSES DUE TO DEPOSION 006 10/08/2002 10/08/2002 10/08/2007 EF EPIP-2.16 CORE DAMAGE ESTIMATION 013 12103/2002 12/03/2002 12103/2007 EF EPIP-2-17 HYPOTHETICAL (PRE-RELEASE) DOSE ESTIMATES 008 09/22/2003 09/22/2003 09/22/2008 EF EPIP-2-18 CONTROL ROOM DOSE ASSESSMENT 015 05/23/2003 05/23/2003 05/23/2008 EF EPIP-3-1 EMERGENCY OPERATIONS FACILITY (EOF) ACTIVATION AND OPERATIONS- 024 10/08/2003 1010812003 10/08/2008 EF EPIP-3-2 ENGINEERING SUPPORT CENTER (ESC) 010 08/09/2002 08/09/2002 08/09/2007 EF EPIP-3-3 IMMEDIATE ENTRY 010 08/08/2003 08/08/2003 08108/2008 EF EPIP-3-4 EMERGENCY TERMINATION AND RECOVERY 009 02/25/2003 02/25/2003 02/25/2008 EF EPIP-3-7 SECURITY DURING EMERGENCIES 010 10/08/2002 10/08/2002 10/08/2007 EF EPIP-4-1 PUBUC INFORMATION RESPONSE TO AN UNUSUAL EVENT 007 08/08/2003 08/08/2003 08/08/2008 EF EPIP-4-3 ACCIDENTAL ACTIVATION OF GINNA EMERGENCY NOTIFICATION SYSTEM SIRENS 013 08/08/2003 08/08/2003 08/08/2008 EF EPIP4-6 JOINT EMERGENCY NEWS CENTER ACTIVATION 009 08/31/2001 08/31/2001 08/31/2006 EF EPIP4-7 PUBUC INFORMATION ORGANIZATION STAFFING 023 05/23/2003 05/23/2063 05/23/2008 EF EPIP4-8 SILENT TESTING OF THE GINNA SIRENS FROM THE TECHNICAL SUPPORT CENTER 001 02/25/2003 02/25/2003 02/25/2008 EF EPIP49 ACTIVATION OF GINNA EMERGENCY SIRENS FROM THE TECHNICAL SUPPORT CENTER 002 05/08/2003 05t0812003 05/08/2008 EF EPIP4-10 SILENT TESTING OF THE GINNA SIRENS FROM THE COUNTY ACTIVATION POINTS 000 02/25/2003 02/25/2003 02/25/2008 EF EPIP4-11 ACTIVATION OF THE GINNA SIRENS FROM THE COUNTY ACTIVATION POINTS .001 05/08/2003 05/08/2003 05/08/2008 EF EPIP-5-1 OFFSITE EMERGENCY RESPONSE FACILTIES AND EQUIPMENT PERIODIC INVENTORY CHECKS AN 028 06/20/2003 06/20/2003 06/20/2008 EF EPIP-5-2 ONSITE EMERGENCY RESPONSE FACIUTlES AND EQUIPMENT PERIODIC INVENTORY CHECKS AND 031 06/20/2003 06/20/2003 06/20/2008. EF EPIP-5-5 CONDUCT OF DRILLS AND EXERCISES 015 05/23/2003 05/23/2003 05/23/2008 EF EPIP-5-6 ANNUAL REVIEW OF NUCLEAR EMERGENCY RESPONSE PLAN (NERP) 004 05/28/1999 05/28/1999 05/28/2004 EF EPIP-5-7 EMERGENCY ORGANIZATION 040 05/23/2003 05/23/2003 05/23/2008 EF EPIP-5-9 TESTING THE OFF HOURS CALL-IN PROCEDURE AND QUARTERLY TELEPHONE NUMBER CHECK 008 10/08/2003- 10/08/2003 10/08/2008 EF EPIP-5-10 EMERGENCY RESPONSE DATA SYSTEM (ERDS) 007 12/03/2002 12/03/2002 12/03/2007 EF NERP GINNA STATION NUCLEAR EMERGENCY RESPONSE PLAN . 022 07/3112003 07/31/2003 07/31/2005 EF PREPIP TOTAL 57 GRAND TOTAL: 57

ROCHESTER GAS AND ELECTRIC CORPORATION

  1. GINNA STATION CONTROLLED COPY NUMBER 37-5

.,I PROCEDURE NO. EPIP 2-5 REV. NO. 15 EMERGENCY DOSE PROJECTIONS - PERSONAL COMPUTER METHOD C--

RESPONSIBLE M R fl ikO-A EFFE6TIVE bATE '

Category 1.0 This procedure contains 10

EPIP 2-5:1 EPIP 2-5 EMERGENCY DOSE PROJECTIONS - PERSONAL COMPUTER METHOD 1.0 PURPOSE The purpose of this procedure is to provide a personal computer-based method for performing projections of downwind dose ratbs and doses. Such information is needed to decide upon protective actions to be recommended to limit the exposure of the general public and emergency workers.

2.0 RESPONSIBILITY The TSC or EOF Dose Assessment Manager is responsible for implementing this procedure.

3.0 REFERENCES

3.1 Developmental References 3.1.1 Nuclear Emergency Response Plan 3.1.2 EPA-400, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (1991) 3.1.3 Ginna UFSAR, Chapter 15 3.1.4 Regulatory Guide 1.109 3.1.5 Vertechs Corporation, EOF8. Estimated Offsite Dose Assessment Program Documentation Binder 3.2 Implementing References 3.2.1 EPIP 2-1, Protective Action Recommendations 3.2.2 EPIP 2-2, Obtaining Meteorological Data and Forecasts and Their Use in Emergency Dose Assessment 3.2.3 EPIP 2-3, Emergency Release Rate Determination 3.2.4 EPIP 2-4, Emergency Dose Projections - Manual Method 3.2.5 EPIP 1-0, Ginna Station Event Evaluation and Classification 3.2.6 EPIP 2-17, Hypothetical (Pre-Release) Dose Estimates 4.0 PRECAUTIONS None.

EPIP 2-5:2 5.0 PREREQUISITES 5.1 The following equipment and data sources are available for use in performing computerized dose projections:

5.1.1 Plant Process Computer System (PPCS) - EVENT 2 Report.

5.1.2 Personal Computer in TSC and EOF (for obtaining 15-minute meteorological data averages from Ginna primary weather tower).

5.1.3 Back-up wind speed and direction indicators at Station 13A (accessible from TSC or EOF Personal Computer) and National Weather Service.

5.1.4 Field readings from survey teams, including gamma dose rate and air sample measurements taken in the release plume.

5.1.5 Personal Computer for performing dose projection routines detailed in this procedure.

DOSE ASSESSMENT USE OF GINNA COMPUTER DATA NOTE: COMPARE ALL DOSE PROJECTIONS AGAINST EPIP 1-0, SECTION 5.2.

6.0 ACTIONS 6.1 Part "A" - Release Assessments 6.1.1 During a Ginna Refueling Outage, R12 could be an effluent monitor. Check with your technical support for this condition. If R12 is an effluent monitor and IS NOT on alarm or increasing, go to step 6.1.2. If R12 is an effluent monitor and IS on alarm or increasing, check:

Alarm EPIP 1-0 Section 5.1 and R1 2A5 - SPING Containment Vent LOW Range Gas Monitor a Yes 0 No R12A7 - SPING Containment Vent MID Range Gas Monitor o Yes 0 No R12A9 - SPING Containment Vent HIGH Range Gas Monitor D Yes o No Use the SPING sheet (Attachment 1) to determine which channel to use and enter the value in the DOWNCALC program (Go to step 6.1.2).

NOTE: R15 PROBLEMS USUALLY INDICATE THAT THERE IS A TUBE IN THE STEAM GENERATOR THAT IS LEAKING RADIOACTIVE REACTOR COOLANT SYSTEM WATER INTO THE NON-RADIOACTIVE STEAM PLANT WATER.

EPIP 2-5:3 6.1.2 Ri - Condenser Air Ejector Monitor. If Ri 5 IS NOT on alarm continue to Step 6.1.3. If Ri5 IS on alarm check:

Alarm EPIP 1-0 Section 5.1 and R15A5 - SPING Condenser Air Ejector LOW Range Gas Monitor o Yes No R15A7 - SPING Condenser Air Ejector MID Range Gas Monitor o Yes *mNo R15A9 - SPING Condenser Air Ejector HIGH Range Gas Monitor Yes o No Use the sping sheet (Attachment 1) to determine which channel to use and enter that value in the downcalc program. (Go to step 6.1.3).

NOTE: R14 PROBLEMS USUALLY INDICATE THAT THERE IS SOMETHING LEAKING IN THE AUXILIARY OR INTERMEDIATE BUILDINGS.

-6.1.3 R14 - Plant Vent Gas Monitor. If R14 IS NOT on alarm go to step 6.1.4 If R14 IS on alarm check:

Alarm EPIP 1-0 Section 5.1 and R14A5 - SPING Plant Vent LOW Range Gas Monitor o Yes o No R14A7 - SPING Plant Vent MID Range Gas Monitor o Yes o No R14A9 - SPING Plant Vent HIGH Range Gas Monitor o Yes o No Use the sping sheet (Attachment 1) to determine which channel to use and enter that value in the downcalc program. (Go to step 6.1.4).

NOTE: R31 AND R32 PROBLEMS USUALLY INDICATE THAT THERE IS A TUBE IN THE STEAM GENERATOR THAT IS LEAKING RADIOACTIVE REACTOR COOLANT SYSTEM WATER INTO THE NO-RADIOACTIVE STEAM PLANT WATER. AS LONG AS THE ARVS AND SAFETY VALVES ARE SHUT, THERE IS NO RELEASE.

6.1.4 R31 and R32 - "A" & "BN Steam Line Monitors. If R31 and R32 ARE NOT on alarm, go to step 6.2 for plant assessments. If R31 or R32 ARE on alarm, determine, from the event 2 printout, if any ARVs or Safety Valves are open. Also, compare R-31/32 readings to EPIP 1-0, Section 5.1. If the associated ARV or Safety Valve for the alarming monitor is open, enter the reading in the DOWNCALC program. (Go to step 6.3.) The event 2 report also lists a computer calculated .15 minute average of Ci/sec released. This can be directly entered into the DOWNCALC program also.

6.1.5 For unmonitored releases from containment, go to EPIP 2-17 to calculate the release rate.

6.2 Part "B" - Plant Assessments 6.2.1 Check R12 - Containment Gas Monitor. If R12 IS NOT on alarm or increasing then the containment atmosphere is clean of radioactivity. If R12 IS on alarm or increasing, then the Reactor Coolant System is leaking water out into the containment atmosphere. Go to step 6.2.2.

6.2.2 Check R9 - Letdown Monitor. If R9 IS on alarm or increasing then the Reactor Fuel is leaking into the Reactor Coolant System water. Go to Step 6.2.4.

EPIP 2-5:4 6.2.3 Ifyou have reached this step the plant and reactor, most probably, are in a stable condition and no release is occurring. Ifthe plant i in an outage, check with your Technical Group to learn about any unusual conditions that could pose special problems.

6.2.4 Check R29 and R30 - Containment HIGH Range Area Monitors.

Check and compare the readings. IfR29 or R30 read

>100 R/hr, declare a'Site Area Emergency (EAL#2.3.2). If R29 or R30 read >1000 R/hr, declare a General Emergency (EAL#2.3.3). Continue to check R29 and R30 for increases due to degraded plant conditions.

6.3 Dose Calculations Using Personal Computer 6.3.1 Ifusing the computers at RG&E, log in to corporate desktop using uUser: Ginna",

"Password: lakela".

6.3.1.1 Select the EOF8 icon to start session information.

6.3.1.2 Choose "new session".

6.3.1.3 Enter "session date" in MM/DDNYY format. Enter "session time" in HHMM format.

6.3.1.4 Enter your name.

6.3.1.5 Enter a short description of the event.

6.3.1.6 Enter a reactor shutdown date and time if the reactor is shutdown. Ifthe reactor is not shutdown, do not enter any data.

6.3.1.7 Select the "save" button. A message should appear in the upper right portion of the screen. Click anywhere on the screen to clear the "save" message.

6.3.2 Downwind dose calculations 6.3.2.1 Select the downcalc button along the left side of the screen.

6.3.2.2 Review the release flowrates. Contact Operations personnel to determine current flowrates. On the initial calculation, ifOperations is busy, use the normal flowrates in the program so the initial assessment is not delayed. Select the normal or emergency flowrates. Adjust the values as necessary. Select OK when done.

Ensure TSC/EOF Dose Assessment and offsite responders are using the same flowrates.

NOTE: TO SCROLL THROUGH FIELDS, PRESS THE TAB KEY.

6.3.2.3 Enter the shutdown date and time if the reactor is shutdown. Ifthe reactor is not shutdown, then press tab to scroll through these 2 fields.

6.3.2.4 Enter the calculation date and the calculation time.

6.3.2.5 To use the last saved values, click on the button labeled "use the last saved values".

Ifnew data is to be used, continue.

EPIP 2-5:5 6.3.2.6 Enter the temperature at 250 feet.

6.3.2.7 Enter the temperature at 33 feet.

NOTE: THE WIND SPEED INDICATOR AT THE 33 FOOT LEVEL IS DESIGNED TO MEASURE ONLY TO 50 MILES PER HOUR.

6.3.2.8 Enter the wind speed at 33 feet.

NOTE: IF "WHAT IF" CALCULATIONS ARE DESIRED, REFER TO EPIP 2-17.

6.3.2.9 If a radioiodine value for the containment vent (RiOA) or plant vent (RIOB) has been calculated using the "ventconc" program, enter the values for the appropriate monitor. If no value has been calculated, the program will use the default radioiodine release rate based on the noble gas concentration.

6.3.2.10 Enter the value (in mR/hr) if R-31 is in alarm condition and is a release path.

6.3.2.11 Enter the value in (in mR/hr) if R-32 is in alarm condition and is a release path.

6.3.2.12, Enter value (in uCicc from R-12A) if R-12 is in alarm condition and is a release path.

6.3.2.13 Enter value (in uCVcc from R-14A) if R-14 is in alarm condition.

6.3.2.14 Enter value (in uCi/cc from R-15A) if R-15 is in alarm condition and is a release path.

6.3.2.15 Enter date and time of data.

6.3.2.16 Enter exposure duration, if the release duration is known. If the release duration is unknown, enter the default of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

NOTE: THE SITE BOUNDARY IS 0.3 MILES FROM THE REACTOR.

6.3.2.17 Enter "X"miles to 5.0. If PARs have been issued, ensure that 5 miles is adequate for evacuation. This can be changed in later assessments for other areas of interest.

6.3.2.18 Select the "save and report" button on the bottom of the screen.

6.3.2.19 Review the file name and select OK.

6.3.2.20 Review the data, then print the report and exit.

CAUTION: DO NOT PRINT THE "EMERG DATA FORM" WITH N/A OR ZEROS (0) IN ALL OF THE RELEASE POINTS.

6.3.2.22 Select "emerg data form (part 11)". Report will print. Give this report to the Dose Assessment Manager. This report should be reviewed and faxed to RG&E, Wayne County, Monroe County and New York State.

EPIP 2-5:6 6.3.2.23 Return to step 6.3.2.2 for more downwind calculations. To perform other calculations, select "exit" from the top of the screen.

6.3.3 Survey Team Data Dose Projections 6.3.3.1 Select the sample button from the left hand side of the screen.

6.3.3.2 Enter the shutdown date and time if the reactor is shutdown. If the reactor is not shutdown, then press enter to scroll through these 2 fields.

6.3.3.3 Enter the calculation date and the calculation time.

6.3.3.4 Enter the team number, color or other identification.

6.3.3.5 Enter the team location where the sample was obtained.

6.3.3.6 Enter the date and time that the sample was started.

6.3.3.7 Enter the date and time that the sample was stopped.

6.3.3.8 Enter the units of measurement of the air sample.

6.3.3.9 Enter the air sample flow rate at the start of the sample.

6.3.3.10 Enter the air sample flow rate when the sample was stopped.

6.3.3.11 Enter the count rate (CPM) of the iodine cartridge.

6.3.3.12 Enter the count rate (CPM) of the particulate filter.

6.3.3.13 Enter the background count rate (CPM) in the area that the sample was counted.

(This should be performed outside of the plume).

6.3.3.14 The bottom right of the screen will show you:

- radioiodine concentration in the air (in uCVcc)

- radioactive particulate in the air (in uCVcc)

- the dose rate (in REM/hr) to a child's thyroid from the radioiodine concentration in the air.

6.3.3.15 Select the "save and report" button on the bottom of the screen.

6.3.3.16 Enter description of reason for calculation and select ok.

6.3.3.17 Review the data, then print the report and exit.

6.3.3.18 Select "exit" from the top of the screen.

6.3.3.19 Select the "backcalc" button along the left side of the screen.

6.3.3.20 Enter the shutdown date and time if the reactor is shutdown. If the reactor is not shutdown, then press enter to scroll through these 2 fields.

EPIP 2-5:7 6.3.3.21 Enter the calculation date and the calculation time.

6.3.3.22 Enter the temperature at 250 feet.

6.3.3.23 Enter the temperature at 33 feet.

NOTE: THE WIND SPEED INDICATOR AT THE 33 FOOT LEVEL IS DESIGNED TO MEASURE ONLY TO 50 MILES PER HOUR.

6.3.3.24 Enter the wind speed at 33 feet.

6.3.3.25 Enter the team number, color or other identification.

6.3.3.26 Enter the team location where the sample was obtained.

6.3.3.27 Enter the distance (in miles) away from the Ginna Plant.

6.3.3.28 Enter the sample date and sample time.

6.3.3.29 Enter the closed window dose rate that the survey team reported at the sample location. This dose rate will be in R/hr or mR/hr. (DO NOT use the background CPM value of the radioiodine analysis. That was a different screen that you have already completed.)

6.3.3.30 Enter the radioiodine concentration (in uCVcc) from the SAMPLE program printout.

6.3.3.31 Enter A & B points of interest.

6.3.3.32 You have now projected doses from the point where your survey team collected sample data.

6.3.3.33 Select the "save and report" button on the bottom of the screen.

6.3.3.34 Review the file name and select OK.

6.3.3.35 Review the data, then print the report and exit.

6.3.3.36 Select "report".

6.3.3.37 Select "emerg data form (part 11)". Report will print. Give this report to the Dose Assessment Manager. This report should be reviewed and faxed to RG&E, Wayne County, Monroe County and New York State.

6.3.3.38 Return to step 6.3.2 for more survey team calculations. To perform other calculations, select "exit" from the top of the screen.

6.4 Use of RASCAL for determination of exposure due to field samples.

6.4.1 Start RASCAL by clicking on the icon labeled. Select uSource Term to Dose Model".

Click OK.

6.4.2 Select "Event Type".

EPIP 2-5:8 6.4.2.1 Select "Nuclear Power Plant Reactor" then OK.

6.4.3 Select "Event Location".

I 6.4.3.1 Under Site Names select "Ginna". Modify the average the Reactor Power Level input, if appropriate, then select OK 6.4.4 Select "Source Term" 6.4.4.1 Select "Monitored Releases - mixtures" then OK.

6.4.4.2 Enter if Reactor is shutdown.

6.4.4.3 Enter sample ID.

6.4.4.4 Enter sample time.

1 6.4.4.5 Enter effluent monitor reading (usually in mCVcc).

6.4.4.6 Enter effluent flowrate.

1 6.4.4.7 Enter noble gas percentage as 99.999.

6.4.4.8 Enter halogen percentage as 0.001.

6.4.4.9 Select OK when all of the data has been entered.

6.4.4.10 Select "Release Path".

6.4.4.11 Select "not an isolated stack" and ensure release height is set at zero.

6.4.4.12 Enter the release start date and time.

1 6.4.4.13 Select "release duration" and set duration to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

6.4.5 Select "Meteorology".

6.4.5.1 Select "Actual Observations and Forecasts" then "Create New".

6.4.5.2 Ensure Station is "GINN" then select "Enter Data".

6.4.5.3 Enter the date, time, wind direction, wind speed, Stability, precipitation and 33 ft temp.

6.4.5.4 Select OK.

I 6.4.5.5 Select "Save and Process data".

I 6.4.5.6 Enter file name to save met data (name the file using Ginna then a number, i.e.,

1,2,3) then OK.

6.4.5.7 Select "Return".

EPIP 2-5:9 1 6.4.5.8 Select "OK".

6.4.6 Select "Calculate Doses" 6.4.6.1 Under Distance Calculations select 0 Close-in + out to 10 miles" 0 "Defaults" 6.4.6.2 Enter case description then OK.

6.4.7 Save the case using the button on the bottom left part of the screen.

6.4.8 Print Results by using the Print button on the right hand side of the screen.

7.0 ATTACHMENTS 7.1 SPING Functional Ranges

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SPING FUNCTIONAL RANGES 12 R-14A9 (High Range) 15 12 R-14A7 (Mid Range) 15 t g

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