ML20125A175

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ODCM: Dispersion Calculation Procedure and Source Term Inputs, Rev. 1
ML20125A175
Person / Time
Site: Beaver Valley
Issue date: 12/29/2006
From:
Energy Harbor Nuclear Corp
To:
Office of Nuclear Reactor Regulation
Shared Package
ML20125A185 List:
References
L-20-137
Download: ML20125A175 (12)
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RTL#: A9.621B Beaver Valley Power Station Unit 1/2 1/2-0DC-3.0l ODCM: Dispersion Calculation Procedure and Source Term Inputs Document Owner Manager, Nuclear Environmental & Chemistry Revision Number 1

Level Of Use General Skill Reference Safety Related Procedure Yes Effective Date 12/29/06

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Beaver Valley Power Station Procedure Number:

l/2-0DC-3.01

Title:

Unit:

Level Of Use:

1/2 General Skill Reference ODCM: Dispersion Calculation Procedure and Source Term Inputs Revision:

1 Page Number:

2 of 12 TABLE OF CONTENTS 1.0 PURPOSE.................................................................................................................................... 3 2.0 SCOPE..................................'....................................................................................................... 3 3.0 REFEFERENCES AND COMMITMENTS................................................................................. 3 3.1 References.......................................................................................................................... 3 3.2 Commitments..................................................................................................................... 4 4.0 RECORD,S AND FORMS....................-........................................................................................ 4 4.1 Records.............................................................................................................................. 4 4.2 Forms................................................................................................................................. 4, 5.0 PRECAUTIONS AND LIMITATIONS....................................................................................... 4 6.0 ACCEPTANCE CRITERIA......................................................................................................... 4 7.0 PREREQUISITES........................................................................................................................ 4 8.0 PROCEDURE.............................................................................................................................. 5 8.1 Summary of Dispersion and Deposition Methodology........................................................ 5 8.2 Summary of Source Term Inputs........................................................................................ 7 8.2.1 Liquid Source Term Inputs................................................................................. 7 8.2.2 Gaseous Source Term Inputs.............................................................................. 7 ATTACHMENT A BV-1 AND 2 RELEASE CONDITIONS............................................................ 8 ATTACHMENT B LIQUID SOURCE TERM INPUTS................................................................... 9 ATTACHMENT C GASEOUS SOURCE TERM INPUTS............................................................. 11 I L_ ___ _

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Beaver Valley Power Station Procedure Number:

1/2-0DC-3.0l

Title:

Unit:

Level Of Use:

1/2 General Skill Reference ODCM: Dispersion Calculation Procedure and Source Term Inputs Revision:

Page Number:

1 3 of 12 1.0 PURPOSE 1.1 This procedure contains the basic methodology that was used for calculating dispersion (rJQ) and deposition (D/Q).

1.1.1 Prior to issuance of this procedure, these items were located in Appendix A of the old ODCM.

1.2 Th.is procedure also contains the input parameters to the various computer codes used by the Licensee and its subcontractors for determination of the liquid and gaseous source term mixes:

1.2.1 Prior to issuance of this procedure, these items were located in Appendix B of the old ODCM.

2.0 SCOPE 2.1 This procedure is applicable to*all station personnel (including subcontractors) that are qualified to perform activities as described and referenced in this procedure.

3.0 REFEFERENCES AND COMMITMENTS 3.1 References 3.1.1 NUS-2173,Development Of Terrain Adjustment Factors For Use At the Beaver Valley Power Station, For the Straight-Line Atmospheric Dispersion Model, NUS Corporation, June 1978 3.1.2 NUREG/CR-2919, XOQDOQ: Computer Program For The Meteorological Evaluation Of Routine Effluent Releases At Nuclear Power Stations, September, 1982 3.1.3 Regulatory Guide 1.23, Meteorological Measurement Program for Nuclear Power Plants 3.1.4 Regulatory Guide 1.111, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents In Routine Releases From Light-Water-Coded Reactors, Revision 1, July 1977 3.1.5 NRC Gale Code, 3.1.6 SWEC LIQIBB Code, 3.1.7 SWEC GASIBB Code, 3.1.8 NUREG-1301, Offsite Dose Calculation Manual Guidance, Standard Radiological Effluent Controls for Pressurized Water Reactors (Generic Letter 89-01, Supplement No. 1) 3.1.9 1/2-ADM-1640, Control of the Offsite Dose Calculation Manual

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Beaver Valley Power Station Procedure Number:

l/2-0DC-3.01

Title:

Unit:

Level Of Use:

1/2 General Skill Reference ODCM: Dispersion Calculation Procedure and Source Term Inputs Revision:

1 Page Number:

4 of12 3.1.10 1/2-ADM-0100, Procedure Writer's Guide 3.1.11 1/2-ADM-0101, Review and Approval ofDocuments 3.1.12 CR 05-01169, Chemistry Action Plan for Transition ofRETS, REMP and ODCM.

CA-19, Revise procedure 1/2-0DC-3.0l to change document owner from Manager, Radiation Protection to Manager, Nuclear Environmental & Chemistry.

3.2 Commitments 3.2.1 None 4.0 RECORDS AND FORMS 4.1 Records 4.1.1 Any calculation supporting generation of dispersion, deposition, or source term mixes shall be documented, as appropriate, by a retrievable document (e.g.; letter or calculation package) with an appropriate RTL number.

4.2 Forms 4.2.1 None 5.0 5.1 PRECAUTIONS AND L'ITATIONS Thi~ procedure contains the information that was previously contained in Appendix A and Appendix B of the previous BV-1 and 2 Offsite Dose Calculation Manual.

5.1.1 In regards to this, the Tables that were transferred from Appendix A and Appendix B to the appropriate ATTACHMENTS of this procedure will still contain a prefix denoting an "A" or "B".

6.0 ACCEPTANCE CRITERIA 6.1 Any change to this procedure shall contain sufficient justification that the change will maintain the level. of radioactive effluent control required by 10 CFR 20.13 02, 40 CFR Part 190, 10 CFR 50.36a and Appendix I to 10 CFR 50, and not adversely impact the accuracy or reliability of effluent dose or setpoint calculation.

6.1.1 All changes to this procedure shall be prepared in accordance with 1/2-ADM-0100<3-l.lo) and 1/2-ADM-1640.<3*1.9) 6.1.2 All changes to this procedure shall be reviewed and approved in accordance with 1/2 ADM-0101<3*1.1 1> and 1/2-ADM-1640.<3.1.9) 7.0 PREREQUISITES 7.1 The user of this procedure shall be familiar with ODCM structure and content.

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Beaver Valley Power Station Procedure Number:

l/2-0DC-3.01

Title:

Unit:

Level Of Use:

1/2 General Skill Reference ODCM: Dispersion Calculation Procedure and Source Term Inputs Revision:

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5 of 12 8.0 PROCEDURE 8.1 Summary of Dispersion and Deposition Methodology 8.1.1 Annual average and grazing season average values of relative concentration (YJQ) and deposition (D/Q) were calculated for continuous and intermittent gaseous releases of activity from the site according to the straight-line airflow (Gaussian) model described in RG-l. ll l.c3.1.4) 8.1.1.1 8.1.1.2 8.1.1.3 8.1.1.4

  • 8.1.1.5 Undecayed and undepleted sector average x/Q and D/Q values were obtained for each of sixteen 22.5-degree sectors at the site boundary and maximum individual receptors.

For an elevated release, (i.e.; occurring at a height that is twice the height or more of a nearby structure) credit was taken for the effective release height which is comprised of the physical release height plus momentum plume rise minus the terrain height at a given receptor.

A building wake correction factor was used to adjust calculations for ground-level releases.

Airflow reversals were also accounted for by applying site-specific terrain recirculation factors for both ground and elevated releases at the site.c3*1.l)

The methodology employed in the calculation of intermittent release x/Q and D/Q

  • values is that described in NUREG/CR-2919.c3*1.2) 8.1.2 The site continuous gaseous release points that have been evaluated include the following:

8.1.2.1 8.1.2.2 8.1.2.3 8.1.2.4 8.1.2.5 8.1.2.6 8.1.2.7 PV-1/2: The Uni~ 1/2 Gaseous Waste/Process Vent attached to the Unit 1 natural draft cooling tower CV-I and CV-2: The Unit 1 Rx Containment/SLCRS Vented the Unit 2 SLCRS Filtered Pathway VV-1 and VV-2: The Unit 1 Ventilation Vent and the Unit 2 SLCRS Unfiltered Pathway TV-2: The Unit 2 Turbine Building Vent CB-2: The Unit 2 Condensate Polishing Building Vent DV-2: The Unit 2 Decontamination Building Vent WV-2: The Unit 2 Gaseous Waste Storage Tank Vault Vent 8.1.3 The intermittent releases are from PV-1/2, VV-1, VV~2, CV-I and CV-2.

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Beaver Valley Power Station Procedure Number:

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6 of12 8.1.4

  • Only PV-1/2 was considered to be an elevated release with all other release points being treated as ground level releases. A summary of the release characteristics and their locations is given in ATTACHMENT A 8.1.5 Onsite meteorological data for the period January 1, 1976 through December 31, 1980 were used as input for the annual-average calculations.

8.1.5.1 8.1.5.2 8.1.5.3 The grazing season was represented by a six-month period from May 1 through October 31 for each year of the 5-year meteorological data base. This grazing season corresponds reasonably well with the growing season.

The data were collected according to guidance in NRC RG-1.23<3*1.3) as described in Section 2.3 of the BVPS-2 FSAR.

The parameters used in the XIQ and D/Q calculations consist of wind speed, wind direction, and AT as an indicator of atmospheric stability. The lower level winds (35 ft) and AT (150-35 ft) were used for all release points except the Process Vent which required the use of 500 ft winds and AT (500-35 ft) which are representative of the release height (510 ft).

8.1.6 The annual average and grazing season XIQ and D/Q values for the continuous and intermittent radioactive releases were calculated at the site boundary, nearest resident, nearest vegetable garden, nearest milk cow, nearest milk goat, and nearest meat animal..

8.1.6.1 8.1.6.2 8.1.6.3 8.1.6.4 8.1.6.5 In the case of the Process Vent releases, several of each receptor type were evaluated in each downwind sector to determine the maximum Xf Q and D/Q values.

The distances of the limiting maximum individual receptors from the radioactive release points are given in ATTACHMENT E (Table 2.2-3) of l/2-0DC-2.02.

The continuous release annual average Xf Q values at the special locations for the Containment Vents, Ventilation Vents, Process Vent, Turbine Building Vents, Decontamination Building Vent, Waste Gas Storage Vault Vent; and Condensate Polishing Building Vent are given in ATTACHMENT F (Tables 2.2-4 through 2.2-10) of l/2-0DC-2.02. Continuous release annual average 'XIQ's for these same release points are also given at ten incremental downwind distances of0-5 miles.

Continuous release D/Q values for these same release points are given in ATTACHMENT K (Tables 2.3-21 through 2.3-27) of l/2-0DC-2.02 for the same 0-5 mile incremental distances, and in ATTACHMENT L (Tables 2.3-28 through 2.3-34) of l/2-0DC-2.02 for the special locations.

Due to their location adjacent to the Containment Building,/ the Decontamination Building and Gaseous Waste Storage Tank Vault XIQ's and D/Q's are the same as the Containment Vent XIQ's and D/Q's.

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1/2 General Skill Reference ODCM: Dispersion Calculation Procedure and Source Term Inputs Revision:

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7 of 12 8.1.6.6 Likewise, the Turbine Building Vent x/Q's and D/Q's apply to the Condensate Polishing Building as well due to its location adjacent to the Turbine Building.

  • 8.1.7 ATTACHMENT M (Tables 2.3-35 through 2.3-38) of l/2-0DC-2.02 contain short term x/Q values for batch releases originating from the Containment Vent, VentilationVent, and Process Vent releases respectively.

8.2 8.1.7.1 The values in these tables are based on 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> per year of Containment and Ventilation Vent purges and 74 hours8.564815e-4 days <br />0.0206 hours <br />1.223545e-4 weeks <br />2.8157e-5 months <br /> per year of Process Vent purges.

Summary of Source Term Inputs 8.2.1 Liquid Source Term Inputs 8.2.1.1 8.2.1.2 Inputs to the NRC Gale Code used for generation ofBV-1 Liquid Source Term Mixes are shown in ATTACHMENT B (Table B: la).

Inputs to the SWEC LIQIBB Code used for generation ofBV-2 Liquid Source Term Mixes are shown in ATTACHMENT B (Table B:lb) 8.2.2 Gaseous Source Term Inputs 8.2.2.1 8.2.2.2 Inputs to the SWEC GAS lBB Code for generation ofBV-1 Gaseous Source Term Mixes are shown in ATTACHMENT C (Table B:2a)

Inputs to the SWEC GASIBB Code for generation ofBV-2 Gaseous Source Term Mixes are shown in ATTACHMENT C (Table B:2b)

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1 8 of 12 ATTACHMENT A Page 1 of 1 BV-1 AND 2 RELEASE CONDITIONS TABIBAl VV-1 CV-I RX PV-1/2 GASEOUS TV-2 TURBINE VENTILATION CONTAINMENT/

WASTE/PROCESS BUILDING VENT VENT(PAB SLCRS VENT VENT EXHAUST)

VV-2 SLCRS CV-2RX UNFILTERED CONTAINMENT/

PATHWAY SLCRS FILTERED PATHWAY TYPE OF RELEASE GROUND LEVEL GROUND LEVEL ELEVATED GROUND LEVEL Long Term And Long Term And Long Term And Long Term And ShortTenn ShortTenn ShortTenn ShortTenn Release Point Height 26 47 155 33 (m)

Adjacan: Building 19 44 155 33 Height(m)

Relative Lora tion To E. Side OfPrimaiy Top CenterOf Atop Cooling Tower TUibineBuilding Adjacent Structures Auxiliaty Bldg Containment fume Exit Velocity(m'sec)

NA NA 9.4 NA Internal Stack NA NA 0.25 NA Diameter(m)

BuildingC~

1600 1600 NA NA Sectional Area(m2)

PwgeFmi_uency*

32 32 74 NA (hours/year)

PwgeDuration 8

8 NA NA (hrs/release)

  • Applied to Short Tenn calrulations only

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ATTACHMENT B Page I of2 LIQUID SOURCE TERM INPUTS TABLEB:la I

9 of12 INPUTS TO GALE CODE FOR GENERATION OF BV-1 LIQUID SOURCE TERM MIXES BV-1 PWR INPUTS Thermal Power Level (megawatts)

Plant Capacity Factor Mass Of Primary Coolant (thousand lbs)

Percent Fuel With Cladding Defects Primary System Letdown Rate (gpm)

Letdown Cation Demineralizer Flow Number Of Steam Generators Total Steam Flow (million lbs/hr)

Mass Of Steam In Each Steam Generator (thousand lbs)

Mass Of Liquid In Each Steam Generator (thousand lbs)

Total Mass Of Secondary Coolant (thousand lbs)

Mass Of Water In Steam Generator (thousand lbs)

Blowdown Rate (thousand lbs/hr)

Primary To Secondary Leak Rate (lbs/day)

Fission Product Carry-Over Fraction Halogen Carry-Over Fraction Condensate Demineralizer Flow Fraction Radwaste Dilution Flow (thousand gpm)

BV-1 LIQUID WASTE INPUTS COLLECTION FLOW RATE FRACTION FRACTION TIME STREAM (gal/day)

OFPCA DISCHARGE (days)

Shim Bleed 1.32E4 1.000 0.000 11.260 Rate Equipment 6.00E2 1.000 0.000 11.260 Drains Clean Waste 7.50El 1.000 1.000 0.071 Input Dirty Waste 1.35E3 0.035 1.000 0.071 Input Blowdown 9.75E4 1.000 0.071 Untreated 0.0 Blowdown DELAY TIME (days) 7.220 7.220 0.648 0.648 0.648 VALUE 2766.000

.800 345.000

.120 60.000 6.000 3.000 11.620 6.772 97.000 1296.000 291.000 33.900 100.000

.001

.010 0.000 22.500 DECONTAMINATION FACTORS I

Cs OTIIBRS IE7 IE7 IE7 IE7 IE7 IE7 IE5 2E4 1E5 IE5 2E4 1E5 IE5 2E4 IE5

/

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Beaver Valley Power Station

Title:

ODCM: Dispersion Calculation Procedure and Source Term Inputs ATTACHMENT B Page 2 of2 LIQUID SOURCE TERM INPUTS TABLEB:lb Procedure Number:

1/2-0DC-3.0l Unit:

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1/2 General Skill Reference Revision:

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1 10 of 12 INPUTS TO SWEC LIQlBB CODE FOR GENERATION OF BV-2 LIQUID SOURCE TERM MIXES BV-2 PWRINPUTS VALUE Thermal Power Level (megawatts)

Plant Capacity Factor Mass Of Primary Coolant (thousand lbs)

Percent Fuel With Cladding Defects Primary System Letdown Rate (gpm)

Letdown Cation Demineralizer Flow Number Of Steam Generators Total Steam Flow (million lbs/hr)

Mass Of Steam In Each Steam Generator (thousand lbs)

Mass Of Liquid In Each Steam Generator (thousand lbs)

Total Mass Of Secondary Coolant (thousand lbs)

Mass Of Water In Steam Generator (thousand lbs)

Blowdown Rate (thousand lbs/Irr)

Primary To Secondary Leak Rate (lbs/day)

Fission Product Carry-Over Fraction Halogen Carry-Over Fraction Condensate Demineralizer Flow Fraction Radwaste Dilution Flow (thousand gpm)

BV-2 LIQUID WASTE INPUTS COLLECTION DELAY FLOW RATE FRACTION FRACTION TIME TIME STREAM (gal/day)

OFPCA DISCHARGE (hrs)

(hrs)

Contaimnent 40 1.000 1.0 35.5 6.2 Sump Auxiliary 200 0.100 1.0 35.5 6.2 Building Sump Miscellaneous 700 0.010 1.0 35.5 6.2 Sources Rx Plant 35 1.000 1.0 35.5 6.2 Samples Lab Drains 400 0.002 1.0 35.5 6.2 Cond: Demin.

2685 I.IE-4 1.0 35.5 6.2 Rinse Water eves 60 1.0 1300 173 Turbine 7200 1.0 Bldg.Drains 2766.000

.800 385.000

.120 57.000 5.700 3.000 11.600 8.700 100.000 2000.000 298.000 22.300 100.000

.001

.010

.700 7.800 DECONTAMINATION FACTORS I

CsRb OTHERS 1E3 IE4 IE4 1E3 1E4 IE4 1E3 1E4 IE4 1E3 IE4 IE4 1E3 IE4 IE4 IE3 IE4 IE4 1E4 4E3 lE5

\\~

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Beaver Valley Power Station

Title:

ODCM: Dispersion Calculation Procedure and Source Term Inputs ATTACHMENTC Page 1 of2 GASEOUS _SOURCE TERM INPUTS TABLEB:2a Procedure Number:

l/2-0DC-3.01 Unit:

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1/2 General Skill Reference Revision:

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1 11 of12 INPUTS TO SWEC GASlBB CODE FOR GENERATION OF BV-1 GASEOUS SOURCE TERM MIXES BV-1 PWRINPUTS Thermal Power Level (megawatts)

Plant Capacity Factor Mass Of Primary Coolant (thousand lbs)

Percent Fuel With Cladding Defects Primary System Letdown Rate (gpm)

Letdown Cation Demineralizer Flow Number Of Steam Generators Total Steam Flow (million lbs/hr)

Mass Of Steam In Each Steam Generator (thousand lbs)

Mass Of Liquid In Each Steam Generator (thousand lbs)

Total Mass Of Secondary Coolant (thousand lbs)

Mass Of Water In Steam Generator (thousand lbs)

Blowdown Rate (thousand lbs/hr)

Primary To Secondary Leak Rate (lbs/day)

Fission Product Carry-Over Fraction Halogen Cany-Ovcr Fraction Condensate Demineralizer Flow Fraction Radwaste Dilution Flow (thousand gpm)

BV-1 GASEOUS WASTE INPUTS There ls Not Continuous Stripping Of Full Letdown Flow Hold Up Time For Xenon (days)

Hold Up Time For Krypton (days)

Primary Coolant Leak To Auxiliary Building (lb/day)

Auxiliary Building Leak Iodine Partition Factor Gas Waste System Particulate Release Fraction Auxiliary Building Charcoiodine Release Fraction Auxiliary Building Particulate Release Fraction Containment Volume (million cu-ft)

Frequency Of Primary Coolant Degassing (times/yr)

Primary To Secondary Leak Rate (lb/day)

There Is A Kidney Filter Containment Atmosphere Cleanup Rate (thousand cfm)

Purge Time Of Containment (hours)

There Is Not A Condensate Demineralizer Iodine Partition Factor (gasniq) In Steam Generator Frequency Of Containment Building High Vol Purge (times/yr)*

Containment Volume Purge Iodine Release Fraction Containment Volume Purge Particulate Release Fraction Steam Leak To Turbine Building (lbs/hr)

Fraction Iodine Released From Blowdown Tank Vent Fraction Iodine Released From Main Condensate Air Ejector There Is Not A Cryogenic Off Gas System

  • 2 cold and 2 hot purges VALUE 2766.000

.800 385.000

.120 57.000 5.700 3.000 Jl.600 8.700 100.000 2000.000 298.000 52.000 100.000

.001

.010 0.000 15.000 VALUE 39.000 2.000 160.000 7.5E-3 0.000 1.000 1.000 1.800 2.000 100.000 2.000 8.000 0.010 4.000 1.000 1.000 1700.000 0.000 0.440

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Beaver Valley Power Station

Title:

ODCM: Dispersion Calculation Procedure and Source Term Inputs ATTACHMENTC Page 2 of2 GASEOUS SOURCE TERM INPUTS TABLEB:2b Procedure Number:

l/2-0DC-3.01 Unit:

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1/2 General Skill Reference Revision:

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1 12 of 12 INPUTS TO SWEC GASlBB CODE FOR GENERATION OF BV-2 GASEOUS SOURCE TERM MIXES BV-2 PWR INPUTS Thermal Power Level (megawatts)

Plant Capacity Factor Mass Of Primary Coolant (thousand lbs)

Percent Fuel With Cladding Defects Primary System Letdown Rate (gpm)

Letdown Cation Demineralizer Flow Number Of Steam Generators Total Steam Flow (million lbs/hr)

Mass Of Steam In Each Steam Generator (thousand lbs)

Mass Of Liquid In Each Steam Generator (thousand lbs)

Total Mass Of Secondary Coolant (thousand lbs)

Mass Of Water In Steam Generator (thousand lbs)

Blowdown Rate (thousand lbs/hr)

Primary To Secondary Leak Rate (lbs/day)

Fission Product Carry-Over Fraction Halogen Carry-Over Fraction Condensate Demineralizer Flow Fraction Radwaste Dilution Flow (thousand gpm)

BV-2 GASEOUS WASTE INPUTS There Is Not Continuous Stripping OfFull Letdown Flow Hold Up Time For Xenon (days)

Hold Up Time For Krypton (days)

Primary Coolant Leak To Auxiliary Building (lb/day)

Auxiliary Building Leak Iodine Partition Factor Gas Waste System Particulate Release Fraction Auxiliary Building Charcoiodine Release Fraction Auxiliary Building Particulate Release Fraction Containment Volume (million cu-ft)

Frequency Of Primary Coolant Degassing (times/yr)

Primary To Secondary Leak Rate (lb/day)

There Is A Kidney Filter Containment Atmosphere Cleanup Rate (thousand cfm)

  • Purge Time Of Containment (hours)

There Is Not A Condensate Demineralizer Iodine Partition Factor (gas/liq) In Steam Generator Frequency Of Containment Building High Vol Purge (times/yr)*

Containment Volume Purge Iodine Release Fraction Containment Volume Purge Particulate Release Fraction SteamLeak To Turbine Building (lbs/hr)

Fraction Iodine Released From Blowdown Tanlc Vent Fraction Iodine Released From Main Condensate Air Ejector There Is Not A Czyogenic Off Gas System

  • 2 cold and 2 hot purges VALUE 2766.000

.800 385.000

.120 57.000 5.700 3.000 11.600 8.700 100.000 2000.000 298.000 22.300 100.000

.001

.010

.700 7.800 VALUE 45.800 2.570 160.000 7.5E-3 0.000 0.100 0.010 1.800 2.000 100.000 20.000 8.000 0.010 4.000 1.000 1.000 1700.000 0.000 0.270

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