ML21127A149

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ODCM: Dispersion Calculation Procedure and Source Term Inputs
ML21127A149
Person / Time
Site: Beaver Valley
Issue date: 12/29/2006
From:
Energy Harbor Nuclear Corp
To:
Office of Nuclear Reactor Regulation
Shared Package
ML21127A168 List:
References
L-21-135
Download: ML21127A149 (12)
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Text

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

Beaver Valley Power Station

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TABLE OF CONTENTS 1.0 PURPOSE.................................................................................................................................... 3 2.0 SCOPE......................................................................................................................................... 3 3.0 REFEFEREN"CES AND COMWTMEN"TS................................................................................. 3 3.1 References.......................................................................................................................... 3 3.2 Commitments..................................................................................................................... 4 4.0 RECORDS AND FORMS............................................................................................................ 4 4.1 Records.............................................................................................................................. 4 4.2 Forms................................................................................................................................. 4

- 5.0 PRECAUTIONS AND ~ATIONS....................................................................................... 4 6.0 ACCEPTmCE 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 Somce Term Inputs.............................................................................. 7 ATTACHMENT A BV-1 AND 2 RELEASE CONDffiONS............................................................ 8 ATTACHMENT B LIQUID SOURCE TERM INPUTS................................................................... 9 ATTACHMENT C GASEOUS SOURCE TERM INPUTS............................................................. 11

Beaver Valley Power Station

Title:

OOCM: Dispersion Calculation Procedure and Source Term Inputs 1.0 PURPOSE Procedure Nomber:

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1 3 nfl2 1.1 This procedure contains the basic methodology that was used for calculating dispersion (:;JQ) 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 This 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 nuxes.

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

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

3.0 REFEFERENCES AND COMMITMENTS

3. I 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 GASlBB Code, 3.1. 8 NUREG-1301, Off site Dose Calculation Manual Guidance, Standard Radiological Effluent Controls for Pressurized Water Reactors (Generic Letter 89-01, Supplement No. I) 3.1.9 l/2-ADM-1640, Control of the Offsite Dose Calculation Manual

Beaver Valley Power Station TIiie:

Prooedure Number.

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3.1.10 1/2-ADM-0100, Procedure Writer's Guide 3.1.11 1/2-ADM-0101, Review and Approval of Documents 3.1.12 CR 05-01169, Chemistry Action Plan for Transition ofRETS, REMP and ODCM CA-19, Revise procedure l/2-0DC-3.01 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 PRECAUTIONS AND LIMITATIONS 5.1 This procedure contains the information that was previously contained in Appendix A and Appendix B of the previous BV-1 and 2 Off site 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 A1ly change to this procedure shall contain sufficient justification that the change will maintain the level of radioactive efiluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a and Appendix I to 10 CFR 50, and not adversely impact the accuracy or reliability of efiluent dose or setpoint calculation.

6.1.1 All changes to this procedure shall be prepared in accordance with 1/2-ADM-0100<3,1.1o) and 1/2-ADM-1640.(3.t.9) 6.1.2 All changes to this procedure shall be reviewed and approved in accordance with 1/2 ADM-0101(3.1.11) and 1/2-ADM-1640.<3*1.9) 1.0 PREREQUISITES 7.1 The user of this procedure shall be familiar with ODCM structure and content.

Beaver Valley Power Station Prooedore Number:

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5 nf12 8.0 PROCEDURE 8.1 Summary of DiS]ersion and Qewsition Methodology 8.1.1 Annual average and grazing season average values of relative concentration (XIQ) 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-1.111.(3.1.4) 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.(3.1.1)

The methodology employed in the calculation of intermittent release X/Q and D/Q values is that described in NUREG/CR-2919.<3*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 Unit 1/2 Gaseous Waste/Process Vent attached to the Unit 1 natural draft cooling tower CV-1 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 fromPV-1/2, VV-1, VV-2, CV-1 and CV-2.

Beaver Valley Power Station

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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-I3 ) 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 XIQ 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 XIQ 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-ODC-2.02. Continuous release annual average x/Q's for these same release points are also given at ten incremental downwind distances of 0-5 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-ODC-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 Vauh XIQ's and D/Q's are the same as the Containment Vent XIQ's and D/Q's.

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7 nf12 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-ODC-2.02 contain short term x/Q values for batch releases originating from the Containment Vent, Ventilation Vent, and Process Vent releases respectively.

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.

8.2 Sumnuuy of Source Term Inputs 8.2.1 Liqyid Sow:ce 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 LIQlBB Code used for generation ofBV-2 Liquid Source Term Mixes are shown in ATTACHMENT B (Table B:lb) 8.2.2 Gaseous Source Tenn uwuts 8.2.2.1 8.2.2.2 Inputs to the SWEC GASlBB Code for generation ofBV-1 Gaseous Source Term Mixes are shown in ATTACHMENT C (Table B:2a)

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

Beaver Valley Power Station Procedure Number:

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I 8 nfl2 ATTACHMENT A Page I of I BV-1 AND 2 RELEASE CONDmONS TABIEA:1 W-1 CV-lRX PV-1/2 GASEOUS TV-2 TURBINE VENTILATION CONTAINMENf/

W ASIB/PROCESS BUILDING VENT VENT(PAB SLCRSVENT VENT EXHAUS1)

W-2 SLCRS CV-2RX UNFILTERED CONTAINMENI'/

PATHWAY SLCRS FILTERED PATHWAY TYPE OF RELEASE GROUND LEVEL GROUND LEVEL FLEVA1ED GROUND LEVEL LoogTennAm LoogTenn.Am LoogTenn.Am

~TennAm SlutTenn Slut:Tenn SlutTenn ShnTenn R.eleaePootff3glt 26 47 155 33 (m)

~Buldiog 19 44 155 33 He;glt(m)

Relativel..oca tm To E Side OfPrimary Tq,Cam-Of Aiq)~T<Mtr

~Bi nlctir-g

~Strucnre; Auxilimy Bklg Ccnainumlbre

&it Vooat)(m'sec)

NA NA 9.4 NA Irtaml.Snd NA NA 0.25 NA Dianrter(m)

BuiktingG\\Er Sectinll Area(nf)

}(JOO 1(00 NA NA Purge~

32 32 74 NA (b::uwyear)

I\\JgeUmim 8

8 NA NA (m'release)

  • Awfied 1o Sh:11:Tmn ca1a daricm crly

Beaver Valley Power Station

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ODCM: Dispersion Calculation Procedure and Source Term Inputs ATTACHMENT B Page 1 of2 LIQUID SOURCE TERM INPUTS TABLEB:la Prooedmc Number.

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1 9 of 12 INPUTS TO GALE CODE FOR GENERATION OF BV-1 LIQUID SOURCE TERM MIXES BV-1 PWRINPUfS VALUE Thermal Power Level (megawatts) 2766.000 Plant Capacity Factor

.800 Mass Of Primary Coolant (thousand lbs) 345.000 Percent Fuel With Cladding Defects

.120 Primary System Letdown Rate {gpm) 60.000 Letdown Cation Demineralizer Flow 6.000 Number Of Steam Generators 3.000 Total Steam Flow (million lbs/hr) 11.620 Mass Of Steam In &ch Steam Generator (thousand lbs) 6.772 Mass Of Liquid In &ch Steam Generator (thousand lbs) 97.000 Total Mass Of Secondary Coolant (thousand lbs) 1296.000 Mass Of Water In Steam Generator (thousand lbs) 291.000 Blowdown Rate (thousand lbs/hr) 33.900 Primary To Secondary Leak Rate (lbs/day) 100.000 Fission Product Carry-Over Fraction

.001 Halogen Carry-Over Fraction

.010 Condensate Demineralizer Flow Fraction 0.000 Radwaste Dilution Flow (thousand gpm) 22.500 BV-1 LIQUID WASIB INPUTS COLLECTION DELAY DECONTAMINATION FLOWRAIB FRACTION FRACTION TIME TIME FACTORS S1REAM (ga]/day)

OFPCA DISCHARGE (days)

(days)

I Cs OTHERS Shim Bleed 1.32E4 1.000 0.000 11.260 7.220 1E7 1E7 1E7 Rate Equipment 6.00E2 1.000 0.000 11.260 7.220 1E7 1E7 1E7 Drains Clean Waste 7.50El 1.000 1.000 0.071 0.648 1E5 2E4 1E5 Input Dirty Waste 1.35E3 0.035 1.000 0.071 0.648 1E5 2E4 1E5 Input Blowdown 9.75E4 1.000 0.071 0.648 1E5 2E4 1E5 Untreated 0.0 Blowdown

Beaver Valley Power Station

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ODCM: Dispersion Calculation Procedure and Source Term Inputs ATTACHMENTB Page2 of2 LIQUID SOURCE TERM INPUTS TABLEB:lb Procedure Number.

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IO nf12 INPUTS TO SWEC LIQ lBB CODE FOR GENERATION OF BV-2 LIQUID SOURCE TERM MIXES BV-2 PWR INPUTS V AWE Thermal Power Level (megawat1s)

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 Ibs/1rr)

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 Demineralizcr Flow Fraction Radwaste Dilution Flow (thou.sand gpm)

BV-2 LIQUID WASIB INPUTS COLLECTION DELAY FWWRATE FRACTION FRACTION TIME TIME STREAM (gal/day)

OFPCA DISCHARGE (hrs)

(hrs)

Cn:ntaimnent 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 Somces Rx Plant 35 1.000 1.0 35.5 6.2 Samples LabDrains 400 0.002 1.0 35.5 6.2 Cond. Demin.

2685 1.IB-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 lE4 lE4 IE3 1E4 1E4 lE3 lE4 lE4 1E3 1E4 1E4 1E3 1E4 1E4 1E3 lE4 lE4 1E4 4E3 1E5

Beaver Valley Power Station

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ODCM: Dispersion Calculation Procedure and Source Term Inputs

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ATTACHMENT C Page 1 of2 GASEOUS SOURCE TERM INPUTS TAB1EB:2a ProoedureNumb<<:

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11 nf 12 INPUTS TO SWEC GASIBB CODE FOR GENERATION OF BV-1 GASEOUS SOURCE TERM MIXES BV-1 PWRINPUTS Thenna1 Power Level (megawatts)

Plant Capacity Factor Mass Of Primary Coolant (thousand lbs)

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

Letdown Cation Demincra1izer F1ow Number Of Steam Generators Total Steam Flow (million lbs/hr)

Mass Of Steam In F.ach Steam Generator (thousand lbs)

Mass Of Liquid In F.ach Steam Gcnerntor (thousand lbs)

Total Mass Of Secondary Coolant (thousand lbs)

Mass OfWate:r In Steam Generator (thousand lbs)

Blowdown Rate (thousand lbs/hr)

Primary To Secondary Leak Rate (lbs/day)

Fission Product Carry-Over Fraction Halogen Cany-Over Fraction Condensate Deminerali7.er Flow Fraction Radwaste Dilution Flow (thousand gpm)

BV-1 GASEOUS WASIBINPUTS There Is Not Qwtjnrnms St;riwing OfFull Letdown Flow Hold Up Time For Xenon (days)

Hold Up Time For Krypton (days)

Primmy Coolant Leak To Auxiliary Building (lb/day)

Anxiliary Building Leak Iodine Partition Factor Gas Waste System Particulate Release Fraction Auxiliary Building Charcoiodine Rele.ase Fraction Auxiliary Building Particu1ate 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 Oeannp Rate (thousand cfm)

Purge Time Of Containment (homs)

There 1s Not A ComJenwe Deminemlizef Iodine Partition Factor (gas/liq) In Steam Generator Frequency Of Omtaimnent Building High Vol Purge (times/yr)*

C<mtainment Volume Purge Iodine Release Fraction Ccmtain:ment Volume Purge Particulate Release Fraction Steam Leak To Turbine Building (lbslhr)

Fraction Iodine Released From Blowdown Tank Vent Fraction Iodine Released From Main Condensate Air Eje.ctor There Is Not A C.CVogenic 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 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

Beaver Valley Power Station Thie:

ODCM: Dispersion Calculation Procedure and Source Term Inputs ATTACHMENT C Page 2 of2 GASEOUS SOURCE TERM INPUTS TABLEB:2b Prooedore Numb<<:

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1 12 nf 12 INPUTS TO SWEC GASIBB 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 Primaiy System Letdown Rate (gpm)

Letdown Cation Deminera1iz.er Flow Number Of Steam Generators Total Steam Flow (million lbs/hr)

Mass Of Steam In F.ach Steam Generator (thousand lbs)

Mass Of Llquid In Each Steam Generator (thousand lbs)

Total Mass Of Secondmy 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 Cany-Over Fraction Halogen Cany;C)ver Fraction Condensate Deminera1iz.er Flow Fraction Radwaste Dilution Flow (thousand gpm)

BV-2 GASEOUS WASIBINPUTS There Is Not ()mtjnuoos 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 Auxilimy Building Owcoiocline 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 ls Not A Condensate pernjoe.ralirer Iodine Partition Factor (gas/liq) In Steam Generator Frequency Of Containment Building High Vol Purge (times/yr)*

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

Fraction Iodine Released From Blowdown Tank Vent Fraction Iodine Released From Main C'.ondensate 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 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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