ML15141A053

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Enclosure 5, Revision 0 to EP-EALCALC-MNS-1401, MNS Radiological Effluent EAL Values
ML15141A053
Person / Time
Site: McGuire, Mcguire  
(NPF-009, NPF-017)
Issue date: 03/03/2015
From: Ingram C, Mccain S, Murray K
Duke Energy Carolinas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML15141A047 List:
References
MNS-15-018 EP-EALCALC-MNS-1401, Rev. 0
Download: ML15141A053 (29)
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Text

ENCLOSURE 5 MNS RADIOLOGICAL EFFLUENT EAL VALUES

~DUKE ENERGY.

McGuire Nuclear Station (MNS)

Radiological Effluent EAL Values EP-EALCALC-MNS-1401 Revision 0 Document Authc Technical Revie*

EPM Approval:

Document Author:

Scott McCain Technical Reviewer:

Caryl Ingram EPM Approval:

Kevin Murray r:

-02/26/15 wer 02/26/15 03/03/15

MNS EAL Technical Bases Calculations - Rxl Effluent Series Table of Contents 1.

P u rp o s e.................................................................................................................................

3

2. Development Methodology and Bases..............................................................................

4 2.1. Threshold Lim its...................................................................................................

4 2.2. Effluent Release Points...........................................................................................

6 2.3. Source Term.................................................................................................................

8 2.4. Release Duration..................................................................................................

.9 2.5. Meteorology..................................................................................................................

9

3. Design Inputs......................................................................................................................

11 3.1.

General Constants and Conversion Factors..........................................................

11 3.2. Liquid Effluent.............................................................................................................

11 3.3. Gaseous Effluent....................................................................................................

12

4. Calculations........................................................................................................................

14 4.1.

RU1.1 Liquid Release............................................................................................

14 4.2. RU1.1 Gaseous Release.......................................................................................

15 4.3. RA1.1, RS1.1 and RG1.1 Gaseous Release..........................................................

15

5. Conclusions........................................................................................................................

16

6. References..........................................................................................................................

17 ATTACHMENTS, Median W ind Speed and Stability Values Memo...........................................

18, RU1.1 Liquid Effluent EAL Calculations.........................................................

23, RU1.1 Gaseous Effluent EAL Calculations....................................................

24, RA1.1, RS1.1 and RG1.1 URI Gaseous Effluent EAL Calculations............... 25 EP-EALCALC-MNS-1401 Page 2 of 28 Rev 0

MNS EAL Technical Bases Calculations - Rxl Effluent Series

1.

Purpose The McGuire Nuclear Station (MNS) Emergency Action Level (EAL) Technical Bases Manual contains background information, event declaration thresholds, bases and references for the EAL and Fission Product Barrier (FPB) values used to implement the Nuclear Energy Institute (NEI) 99-01 Rev. 6 EAL guidance methodology. This calculation document provides additional technical detail specific to the derivation of the gaseous and liquid radiological effluent EAL values developed in accordance with the guidance in NEI 99-01 Rev. 6.

Documentation of the assumptions, calculations and results are provided for the MNS Rxl series EAL effluent monitor values associated the NEI 99-01 Rev 6 EALs listed below.

NEI EAL AU1.1 (gaseous and liquid)

NEI EAL AAI.1 (gaseous and liquid)

NEI EAL AS1.1 (gaseous)

NEI EAL AG1.1 (gaseous)

EP-EALCALC-MNS-1401 Page 3 of 28 Rev 0

MNS EAL Technical Bases Calculations - Rxl Effluent Series

2.

DEVELOPMENT METHODOLOGY AND BASES 2.1.

Threshold Limits 2.1.1. RUI.1 Liquid Threshold Limits Guidance Criteria The RU1 Initiating Condition (IC) addresses a release of gaseous or liquid radioactivity greater than 2 times the Offsite Dose Calculation Manual (ODCM) limits for 60 minutes or longer.

MNS Bases The ODCM Executive Summary section (with references to TS 5.5.5(a)(2) and SLC 16.11.1) limits for the concentration of radioactive liquid effluents released from the site to the unrestricted area are as follows:

0 10 times the effluent concentration (EC) levels of 10CFR20, Appendix B, Table 2 2.0E-04 pCi/ml for dissolved and entrained noble gases The RU1.1 liquid effluent EAL threshold values will equate to 2 times the ODCM limit.

2.1.2. RU1.1 Gaseous Threshold Limits Guidance Criteria The RU1 Initiating Condition (IC) addresses a release of gaseous or liquid radioactivity greater than 2 times the Offsite Dose Calculation Manual (ODCM) limits for 60 minutes or longer.

MNS Bases The ODCM Executive Summary section (with references to TS 5.5.5(a)(7) and SLC 16.11.6) limits for the concentration of radioactive gaseous effluents at the site boundary are as follows:

Less than or equal to 500 mrem/yr to the whole body (Noble Gasses)

Less than or equal to 3000 mrem/yr to the skin (Noble Gasses)

Less than or equal to 1500 mrem/yr to any organ (1-131, 1-133, tritium, and particulate with half-lives greater than 8 days)

Inhalation (internal organ) limits are not applicable for EAL threshold determination since the specified surveillance involves collection and analysis of composite samples. This after-the-fact assessment (individual uptake) could not be made in a timely manner conducive to accident classification.

The site specific RU1.1 gaseous effluent EAL threshold values will equate to 2 times the ODCM limit for the lesser of the whole body or skin exposure pathways.

EP-EALCALC-MNS-1401 Page 4 of 28 Rev 0

MNS EAL Technical Bases Calculations - Rxl Effluent Series 2.1.3. RAl.1 Liquid Threshold Limits Guidance Criteria The RA1 Initiating Condition (IC) addresses a release of radioactivity resulting in offsite dose greater than 10 mrem TEDE or 50 mrem thyroid CDE.

This is based on values at 1% of the EPA Protective Action Guides (PAGs).

Per NEI 99-01, the effluent monitor readings should correspond to the above dose limits at the "site-specific dose receptor point" (consistent with the calculation methodology employed) for one hour of exposure.

MNS Bases The liquid effluent limits are based on the water concentration values given in 10 CFR 20 Appendix B Table 2 Column 2 (see Section 2.1.1 above). The 10 CFR 20 values are equivalent to the radionuclide concentrations which, if ingested continuously over the course of a year, would produce a total effective dose equivalent of 0.05 rem (50 millirem). The EPA PAGs are based on a TEDE dose from immersion, inhalation and deposition. The 10 CFR 20 limits and the EPA limits do not represent the same type of exposure and thus cannot be compared on a one to one basis.

Additionally, significant dilution assumptions are incorporated in determining ODCM ingestion limits for liquid releases such that obtaining a dose of 10 mrem in one hour would require a discharge concentration above the effluent monitor threshold (ingestion of radioactivity from a liquid release at the site boundary is not practical).

Thus, the site specific EALs will not contain the RA1.1 liquid effluent monitor threshold value that equates to 1% of the EPA PAG. However, EALs RA1.3 and RA1.4 will remain applicable for liquid effluent releases that exceed the threshold based upon sample and field survey results.

2.1.4. RA1.1 Gaseous Threshold Limits Guidance Criteria The RA1 IC addresses a release of radioactivity resulting in offsite dose greater than 10 mrem TEDE or 50 mrem thyroid CDE.

Per NEI 99-01, the effluent monitor readings are based on values at 1% of the EPA Protective Action Guides (PAGs) at the "site-specific dose receptor point" (consistent with the calculation methodology employed) for one hour of exposure.

MNS Bases The gaseous effluent limits for RA1.1 are based on values that equate to an offsite dose greater than 10 mrem TEDE or 50 mrem CDE thyroid, which are 1% of the EPA PAGs.

EP-EALCALC-MNS-1401 Page 5 of 28 Rev 0

MNS EAL Technical Bases Calculations - Rxl Effluent Series 2.1.5. RSl.1 Gaseous Threshold Limits Guidance Criteria The RS1 IC addresses a release of radioactivity resulting in offsite dose greater than 100 mrem TEDE or 500 mrem thyroid CDE.

This is based on values at 10% of the EPA Protective Action Guides (PAGs) at the "site-specific dose receptor point" (consistent with the calculation methodology employed) for one hour of exposure.

MNS Bases The gaseous effluent limits for RSI.1 are based on values that equate to an offsite dose greater than 100 mrem TEDE or 500 mrem CDE thyroid, which are 10% of the EPA PAGs.

2.1.6. RG1.1 Gaseous Threshold Limits Guidance Criteria The RG1 IC addresses a release of radioactivity resulting in offsite dose greater than 1,000 mrem TEDE or 5,000 mrem thyroid CDE.

This is based on values at 100% of the EPA Protective Action Guides (PAGs) at the "site-specific dose receptor point" (consistent with the calculation methodology employed) for one hour of exposure.

MNS Bases The gaseous effluent limits for RG1.1 are based on values that equate to an offsite dose greater than 1,000 mrem TEDE or 5,000 mrem CDE thyroid, which are 100% of the EPA PAGs.

2.2.

Effluent Release Points Note - All effluent release points assume a background reading of zero to conservatively account for all modes of operation applicable to the EALs.

2.2.1. Liquid Release Points Guidance Criteria Per NEI 99-01, the RU1 IC addresses normally occurring continuous radioactivity releases from monitored gaseous or liquid effluent pathways (EAL #1) and planned batch releases from non-continuous release pathways (EAL #2).

Per NEI 99-01, the RA1 IC includes events or conditions involving a radiological release, whether gaseous or liquid, monitored or un-monitored. Classification based on effluent monitor readings assumes that a release path to the environment is established. If the effluent flow past an effluent monitor is known to have stopped due to actions to isolate the release path, then the effluent monitor reading is no longer valid for classification purposes.

EP-EALCALC-MNS-1401 Page 6 of 28 Rev 0

MNS EAL Technical Bases Calculations - Rxl Effluent Series The "site-specific monitor list and threshold values" should be determined with consideration of the selection of the appropriate installed gaseous and liquid effluent monitors.

MNS Bases There are two liquid radwaste discharge points to the environment at MNS (ODCM 2.0.1 and Figure 2.0-2):

1. The Condenser Cooling Water System (RC) discharges to Lake Norman.

EMF 49 for the Waste Monitor Tanks (WMT) 1/2EMF 44 for the Containment Ventilation Unit Condensate Drain Tank (CVUCDT)

There are 8 RC pumps with a flow rate of 2.50E+05 gpm each. Minimum dilution flow for this release pathway consists of one RC pump (ODCM 2.0.1.1).

2. The Conventional Waste Water System (WC) and Waste Water Collection Basin (WWCB) discharges to the Catawba River downstream of Cowan's Ford Dam - EMF 31.

Inputs to WC are normally held up in one of two WC Settling Ponds, then released as a batch. Inputs to WWCB are sent to the collection basin. It is assumed that no activity is present in the TBS/Condenser Drain (WU) effluent until indicated by EMF 31 at the TBS/WU output (ODCM 2.0.1.2), thus the WC and WWCB pathways do not meet the NEI 99-01 criteria for use as an EAL threshold.

2.2.2. Gaseous Release Points Guidance Criteria Per NEI 99-01, the RU1 IC addresses normally occurring continuous radioactivity releases from monitored gaseous or liquid effluent pathways (EAL #1) and planned batch releases from non-continuous release pathways (EAL #2).

Per NEI 99-01, the RA1 IC includes events or conditions involving a radiological release, whether gaseous or liquid, monitored or un-monitored. Classification based on effluent monitor readings assumes that a release path to the environment is established. If the effluent flow past an effluent monitor is known to have stopped due to actions to isolate the release path, then the effluent monitor reading is no longer valid for classification purposes.

Per NEI 99-01, the RS1 and RG1 ICs address monitored and un-monitored releases of gaseous radioactivity. Classification based on effluent monitor readings assumes that a release path to the environment is established. If the effluent flow past an effluent monitor is known to have stopped due to actions to isolate the release path, then the effluent monitor reading is no longer valid for classification purposes.

The "site-specific monitor list and threshold values" should include the effluent monitors described in emergency plan and emergency dose assessment procedures.

EP-EALCALC-MNS-1401 Page 7 of 28 Rev 0

MNS EAL Technical Bases Calculations - Rxl Effluent Series MNS Bases There are five gaseous effluent release points to the environment at MNS (ODCM 2.0.2 and Figure 2.0-4):

1. The two unit vents are the release points for waste gas decay tanks, containment building purges, auxiliary building ventilation, and the condenser air ejector -

1/2EMF 36.

2. The Waste Management Facility (WMF) - EMF 52.
3. The Waste Handling Area (WHA) - EMF 53.,
4. The Unit 2 Staging Building (2-SB) - 2EMF 59.

The WMF, WHA and 2-SB pathways are not sources for normally occurring continuous radioactivity releases or for planned batch releases from non-continuous release pathways, and available activity is extremely low. Thus these pathways do not meet the NEI 99-01 criteria for use as an EAL threshold.

2.3.

Source Term 2.3.1. RUl.1 Liquid Source Term Guidance Criteria NEI 99-01 does not provide specific guidance for AU1 liquid source term assumptions.

MNS Bases The source term used for liquid effluent releases is Cs-134. Cs-1 34 has been selected based on it being the lowest effluent concentration value for any detectable radionuclide not known to be absent from the liquid effluent (ODCM 3.0.1.2).

2.3.2. RU1.1 Gaseous Source Term Guidance Criteria NEI 99-01 does not provide specific guidance for AU1 gaseous source term assumptions.

MNS Bases The gaseous source term is based upon the NUREG-1 940 Table 1-6 noble gas fraction of activity available at shutdown.

EP-EALCALC-MNS-1401 Page 8 of 28 Rev 0

MNS EAL Technical Bases Calculations - Rxl Effluent Series 2.3.3. RA1.1, RS1.1 and RG1.1 Gaseous Source Terms Guidance Criteria NEI 99-01 specifies that the calculation of monitor readings will require use of an assumed release isotopic mix; the selected mix should be the same for ICs AA1, AS1 and AG1.

MNS Bases DEC utilizes a common RCS source term basis for fleet standardization. The source term utilized in the URI dose model provides the relative fractions and is taken from NUREG-1940 (referenced from URI Requirements Specification Appendix A Section A. 1) with the release path 'E' selected to model a LOCA type event with fuel clad damage.

Containment RCS HUT < 2 hrs Annulus VE Filter Unit Vent Env Sprays Off HUT < 2 hrs Working No Recirc No credit is taken for source term decay. The start of release time entered into URI is coincident with the time of reactor trip.

2.4.

Release Duration Guidance Criteria Per NEI 99-01, the effluent monitor readings for RA1.1, RS1.1 and RG1.1 gaseous EAL threshold values should correspond to a dose at the "site-specific dose receptor point" (consistent with the calculation methodology employed) for one hour of exposure.

MNS Bases The effluent monitor readings for RA1.1, RS1.1 and RG1.1 gaseous EAL threshold values are calculated for a release duration of one hour.

2.5.

Meteorology Guidance Criteria The effluent monitor readings should correspond to the applicable dose limit at the "site-specific dose receptor point." The "site-specific dose receptor point" is the distance(s) and/or locations used by the licensee to distinguish between on-site and offsite doses.

The selected distance(s) and/or locations should reflect the content of the emergency plan, and the procedural methodology used to determine offsite doses and protective action recommendations. This is typically the boundary of the Owner Controlled Area.

Monitor readings will be calculated using a set of assumed meteorological data or atmospheric dispersion factors; the data or factors selected for use should be the same for ICs AA1, ASI and AG1.

EP-EALCALC-MNS-1401 Page 9 of 28 Rev 0

MNS EAL Technical Bases Calculations - Rxl Effluent Series MNS Bases The site specific meteorology used for the calculation of monitor readings is based on selections and inputs for the URI dose assessment model as documented below.

2.5.1. Wind Speed and Stability Class (Median WS and stability memo - see Attachment 1)

M ed ian W ind S peed................................................................................................

6 m ph S tability C lass (A -G )..................................................................................................

.. D 2.5.2. Wind Direction (ODCM 2.0.2.1 and Figure 6.0-1: UFSAR Figure 2-5)

The boundary for establishing gaseous effluent release limits is the exclusion area boundary (EAB), which is considered the site boundary.

The EAB is defined as a 2500-ft. (-0.5 mile) radius from the station center. The highest ODCM calculated annual average dispersion parameter for any area at or beyond the site boundary is the NNE (wind direction from 2030) sector at 0.5 mile.

2.5.3. Other Parameters No precipitation is assumed to occur for the duration of the release and plume transport across the EPZ.

EP-EALCALC-MNS-1401 Page 10 of 28 Rev 0

MNS EAL Technical Bases Calculations - Rxl Effluent Series

3.

DESIGN INPUTS 3.1.

General Constants and Conversion Factors 3.1.1. 472 cc/sec per cfm 3.1.2. 106 pCi per Ci 3.2.

Liquid Effluent 3.2.1. Liquid Effluent Monitor Ranges (UFSAR Table 11-27)

EMF 9(L......10-107 cpm E M F 49(L)................................

.............................. 10 1-10 7 cpm E M F 4 9 (H )....................................................................................................

10 1_10 6 cpm E M F 44 (L)....................................................................................................

10 1-107 cpm E M F 44 (H )....................................................................................................

10 1_10 6 cpm 3.2.2. Liquid Effluent Dilution Flow (F)

Liquid Effluent Dilution Flow (ODCM 2.0.1.1)..............................................

2.50E+05 gpm 3.2.3. Liquid Effluent Source Flow (f)

WMT pump (HP/0/B/1003/008 Enclosure 5.1 Section 0)....................................

120 gpm CVUCDT pum p (O DCM 3.0.1.2)............................................................................

60 gpm 3.2.4. Recirculation Factor (o)

The recirculation factor accounts for the fraction of discharged water reused by the station. The recirculation factor equals 2.26 (ODCM 2.0.1.1).

3.2.5. 10CFR20 Source Term Limit (ECA)

The 10CFR20 Appendix B, Table 2, Column 2 limit is as follows:

C s-1 34.......................................................................................................

9.O E -07 ýiC i/m l 3.2.6. Cs-137 to Cs-1 34 Equivalency Factor (Eq1 )

Liquid radiation monitors are calibrated to Cs-1 37. The Cs-1 37 equivalence factor accounts for the different gamma energies and abundance of isotopes other than Cs-137. The equivalency factor is applied to the Cs-1 34 source term isotope as follows:

A ll EM F (O DC M Table 3.0-1)..................................................................................

2.5843 EP-EALCALC-MNS-1401 Page 11 of 28 Rev 0

MNS EAL Technical Bases Calculations - Rxl Effluent Series 3.2.7. Cs-137 Correlation Factor (CFi)

The liquid effluent monitor Cs-1 37 correlation factor converts the release concentration in pCi/ml to effluent monitor to cpm. The Cs-1 37 correlation factor is as follows:

EMF 49(L) (ODCM 3.0.1.1).............................................................

3.42E+08 cpm/jiCi/ml EMF 49(H) (HP/O/B/1003/008)........................................................

5.00E+03 cpm/ýtCi/ml EMF 44(L) (ODCM 3.0.1.2).............................................................

3.42E+08 cpm/gCi/ml EMF 44(H) (HP/O/B/1003/008)........................................................

5.00E+03 cpm/p.Ci/ml 3.3.

Gaseous Effluent 3.3.1. Gaseous Effluent Monitor Ranges (UFSAR Table 11-28)

U nit V ent - EM F 36(L)..................................................................................

101-107 cpm Unit Vent - EMF 36(H)...............................................................................

10-1_0 6 cpm 3.3.2. Gaseous Effluent Source Flow ()

Unit Vent (ODCM 3.0.2.2)............................................................................

1.20E+05 cfm 3.3.3. RU1.1 Dispersion Factor (X/Q)

Dispersion Factor (ODCM 3.0.2)...........................................................

7.611 E-05 sec/m 3 3.3.4. RU1.1 Source Term Fraction (Si)

NUREG-1 940 Table 1-6 noble gas fraction of activity available at shutdown.

Isotopic Fraction I

Si (unitless)

Kr-83m 1.83E-02 Kr-85 1.70E-03 Kr-85m 3.71 E-02 Kr-87 7.40E-02 Kr-88 1.02E-01 Xe-131m 2.20E-03 Xe-133 3.26E-01 Xe-133m 1.03E-02 Xe-1 35 8.54E-02 Xe-135m 6.90E-02 Xe-138 2.74E-01 1.OOE+00 EP-EALCALC-MNS-1401 Page 12 of 28 Rev 0

MNS EAL Technical Bases Calculations - Rxl Effluent Series 3.3.5. ODCM Dose Factors (Requlatorv Guide 1.109 Table B-i)

Note - RG1.109 values converted from mRem/yr per pCi/m 3 to mRem/yr per pCi/m 3.

SE (f0 U.6.

U0 4)

IM-E-U-.,

0 00 E.

EU Kr-83m 7.56E-02 0.OOE+00 1.93E+01 Kr-85 1.61E+01 1.34E+03 1.72E+01 Kr-85m 1.17E+03 1.46E+03 1.23E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 Kr-88 1.47E+04 2.37E+03 1.52E+04 Xe-131m 9.15E+01 4.76E+02 1.56E+02 Xe-133 2.94E+02 3.06E+02 3.53E+02 Xe-133m 2.51E+02 9.94E+02 3.27E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 Xe-138 8.83E+03 4.13E+03 9.21E+03 3.3.6. Xe-133 Equivalency Factor (Eqi)

Gaseous radiation monitors are calibrated to Xe-1 33. The Xe-1 33 equivalence factor accounts for the different gamma energies and abundance of isotopes other than Xe-133.The equivalency factors are applied to the source term isotopes as follows:

ODCM Table 3.0-2 EMF 36 Kr-83m 0.00 Kr-85 2.56 Kr-85m 2.48 Kr-87 2.93 Kr-88 2.78 Xe-131m 1.69 Xe-133 1.00 Xe-133m 1.99 Xe-135 2.63 Xe-135m 0.83 Xe-138 2.93 3.3.7. Xe-133 Correlation Factor (CFi)

The gaseous effluent monitor Xe-1 33 correlation factor converts the release concentration in pCi/ml to effluent monitor to cpm.

EMF 36(L) Xe-1 33 Correlation Factor (ODCM 3.0.2.2).................... 2.60E+07 cpm/liCi/ml EP-EALCALC-MNS-1401 Page 13 of 28 Rev 0

MNS EAL Technical Bases Calculations - Rxl Effluent Series

4.

Calculations 4.1.

RU1.1 Liquid Release 4.1.1. ODCM Liquid Release Limit C1 < (F +f) x (lOx ECi) crxf SP

  • Y (C, xEqi xCFcs-137) + bkg i

Where:

Ci concentration of radionuclide T' in the liquid effluent (pCi/ml) - this is considered the ODCM limit for EAL purposes F

dilution flow (gpm) f undiluted flow from the source of the release (gpm) 10 TS multiplier - component of ODCM Limit (see definition)

EC, concentration of radionuclide T from 10CFR20, Appendix B, Table 2, Column 2 (pCi/ml) u most restrictive recirculation factor at equilibrium (unitless)

SP radiation monitor setpoint equivalent to the ODCM limit (cpm)

Eqi Cs-1 37 equivalence factor for radionuclide 'i' (unitless)

CFcs-137 radiation monitor correlation factor for Cs-1 37 (cpm per pCi/ml) bkg background reading for the radiation monitor (cpm) 4.1.2. RU1.1 Liquid Release EAL Threshold RU1.1 =2( I (Ci xEqi xCFcs - 37) ) + bkg See Attachment 2 for the spreadsheet calculations that develop the RUI.1 liquid effluent EAL threshold values for each applicable monitor.

EP-EALCALC-MNS-1401 Page 14 of 28 Rev 0

MNS EAL Technical Bases Calculations - Rxl Effluent Series 4.2.

RU1.1 Gaseous Release 4.2.1. ODCM Gaseous Release Limit 500 Sptotaibody (cpm) =50 Si x Ki

+ bkg 472xfx x,*

Q CFV_-133 xEqi SPskin (cpm) =

3000

+

[472xf x XZ SiX(Li+_1.I+M)

Q CFVe 133 xEqi Where:

500/3000 ODCM Limit - 500 total body or 3000 skin (mrem/yr) 472 conversion factor (cc/ft3 per sec/min) f vent flow (cfm)

X/Q annual average meteorological dispersion to the controlling site boundary location (sec/m3)

Si isotopic fraction of the mix activity released (unitless)

Ki total body dose factor (mrem/yr per pCi/m 3)

Li + 1.1Mi skin dose factor (mrem/yr per pCi/m 3)

Eq, Xe-1 33 equivalence factor for radionuclide T' (unitless)

CFxe.-133 radiation monitor correlation factor for Xe-1 33 (cpm per pCi/ml) bkg background reading for the radiation monitor (cpm) 4.2.2. RU1.1 Gaseous Release EAL Threshold RU1.1 is two times the lesser of the calculated total body or skin value plus background.

See Attachment 3 for the spreadsheet calculations that develop the RU 1.1 gaseous effluent EAL threshold values for each applicable monitor.

4.3.

RA1.1, RS1.1 and RG1.1 Gaseous Release The RA1.1, RS1.1 and RG1.1 gaseous release EAL threshold are developed using the URI site specific dose assessment models with the inputs described in Section 2 above.

Note - URI calculations were performed for each unit. There was no difference in results between units.

Refer to Attachment 4 for the results of the URI gaseous effluent EAL threshold calculations.

EP-EALCALC-MNS-1401 Page 15 of 28 Rev 0

MNS EAL Technical Bases Calculations - Rxl Effluent Series

5.

Conclusions Release Point Monitor GE SAE Alert UE 2.61E+4 2.61E+3 2.70E+2 U1/2 Plant Vent 1/2EMF 36(H) 2.61 Ec4 2.61 N/A

{.(cpm)

(cpm)

(cpm)

(.94.86E+6 3.10E+3 U1/2 Plant Vent 1/2EMF 36(L)

N/A N/A 4.pm) 3.pm)

(cpm)

(cpm)

Waste Monitor Tanks 2.15E+2 (WMT)

EMF 49(H)

N/A N/A N/A (cpm)

.3 Cont Vent Unit Cond 4.29E+2 Drain Tank (CVUCDT)

EMF 44(H)

N/A N/A N/A (cpm)

EP-EALCALC-MNS-1401 Page 16 of 28 Rev 0

MNS EAL Technical Bases Calculations - Rxl Effluent Series

6.

References 6.1.

NEI 99-01 R6, Methodology for Development of Emergency Action Levels, November 2012 6.2.

NUREG-1 940, RASCAL 4: Description of Models and Methods, December 2012 6.3.

McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM), Revision 54 6.4.

Unified RASCAL Interface Requirements Specification, McGuire, Version 2 6.5.

HP/0/B/1003/008, Determination Of Radiation Monitor Setpoints (EMFs), Revision 41 6.6.

Memo: Median Wind Speed and Stability Values at Duke Energy Nuclear Sites, 06/19/14 EP-EALCALC-MNS-1401 Page 17 of 28 Rev 0

Attachment I Median Wind Speed and Stability Values Memo Date:

June 19,2014 To:

Caryl Ingram, NGO-EP From: Stanton Lanham, Meteorology - Environmental Services Marsha Kinley, Meteorology - Environmental Services

Subject:

Median Wind Speed and Stability Values at Duke Energy Nuclear Sites 1.0 Overview Data from the most recent full five years (2009-2013) was used to calculate the median wind speed (WS), vertical temperature gradient (Delta-T), and stability class at each of the Duke Energy nuclear sites in the Carolinas. Upper level winds were used at Brunswick. All other sites use the lower level.

Singular median values for WS, Delta-T, and stability class from all wind direction sectors are given in Table 1. NEI 99-01 Rev. 6 does not provide any guidance on selection of default meteorological conditions.

These median values are irrespective of season or time of day, so the difference between the median values and actual meteorological conditions could be large.

Also note that the median Delta-T values are in normalized units of (deg C/100m), and would need to be converted to reflect actual sensor separation distance on a tower, if needed.

Table 2.1 through Table 2.6 contains sector-specific median values of Wind Speed, Delta-T and Stability Class for each of the 16 directional sectors. This information provides more site-specific characteristics, similar to what would have been evaluated for the previous Rev. 4 of NEI-99-01 guidance. In addition, the most frequent sector from which the wind is blowing at each site for the five year period is also indicated in these tables-Table I Median Values from Years 2009-2013 Median Median Delta-Stability WS (mph)

T (C/lOOm) **

Class DEC Sites CNS 4.8

-0.7 D

MNS 6

-0.9 D

ONS 3.7

-0.78 D

DEP Sites BNP*

13.4

-0.71 D

HNP 3.5

-0.51 D

RNP 4.4

-0.84 D

Upper level winds are used at BNP. All other sites use lower level winds.

  • Note: Delta-T values listed are in degs C/100 m. The units may need to be converted if actual delta-T based on tower-specific separation distances are required.

EP-EALCALC-MNS-1401 Page 18 of 28 Rev 0

Attachment I Median Wind Speed and Stability Values Memo 2.0 Data The data presented represents the median of the entire five-year span at each site (Table 1), as well as the overall medians broken down by directional sector (Tables 2.1 - 2.6). Each value represents the middle of the dataset, with 50% of values above the median, and 50% of values below the median.

Data for the Legacy Duke Energy sites was obtained from the Duke's Environmental Monitoring "Ambient Administration" archive, which contains validated hourly meteorological data. Data for the Legacy Progress sites was obtained from hourly meteorological data files provided by the vendor (Murray and Trettel), and has undergone their data review/QA process. The five-year analysis results presented here were determined independently of previous studies, however comparison to the Annual Effluent reports (2013 MET) for all sites showed good agreement with the values presented in Table I.

The sector-specific median values (Tables 2.1 through 2.6) had not been investigated previously.

Legacv Duke Sites (DEC:

Table 2.1 Catawba Nuclear: 5-year Lower Level Medians by Sector Median Median Delta-Stability Sector WS (mph)

T (C/lOOm)

Class N

7.4

-1.08 D

NNE 8.7

-1.3 D

NE 9

-1.2 D

ENE 6.1

-1.06 D

E 4.6

-0.94 D

ESE 4.4

-0.9 D

SE 4.8

-08 D

SSE 4.4

-0.76 D

S*

3.9

-0.36 E

SSW 4.1

-0.66 D

SW 3.8

-0.7 D

WSW 3.4

-0.4 E

W 3.6 0

E WNW 4

0 E

NW 4.4 0

E NNW 5.1 0

E

  • Most frequent CNS wind direction (2009-2013): from South 2

EP-EALCALC-MNS-1401 Page 19 of 28 Rev 0

Attachment I Median Wind Speed and Stability Values Memo Table 2.2 McGuire Nuclear: 5-year Lower Level Medians by Sector Median Median Delta-Stability Sector WS (mph)

T (C/l00m) class N

6.9

-1.18 D

NNE 7

-1.16 D

NE 7.8

-1.C6 D

ENE 6.6

-1.C2 D

E 5.2

-0.28 D

ESE 5.5

-0.28 D

SE 5.1

-0.E8 D

SSE 4.2

-0.42 E

S 4.b

-g.12 1

SSW 5

-0.14 E

SW*

6.3

-0U2 D

WSW 5.2

-0.74 D

W 4.9

-0.76 D

WNW 6.3

-0.c2 D

NW 8.5

-1.C6 D

NNW 9.1

-1.16 D

Most frequent MNS wind direction (2009-2013): from SW Table 2.3 Oconee Nuclear: 5-year Lower Level Medians Median Median Delta-Stability Sector WS (mph)

T (C/t00m) dass N

2.5

-0.44 E

NNE 2.8

-0.58 D

.NE 3.9

-0.14 D

ENE 4.6

-0.28 D

E 3.7

-0.J2 D

ESE 3.2

-0.4 E

SE 3.3

-0.42 E

SSE 3.3

-0.5 D

S 3.4

-0.E8 D

SSW 4-6

-1.2 D

SW*

5

-1.32 D

WSW 4.8

-1.05 D

W 3.6

-0.8 D

WNW 2.8

-0.46 E

NW 2.7

-0.2 E

NNW 2.5

-0.42 E

by Sector

[',IL A t

  • VVUfl 05 4U[L e

%en isuUJ ircuIIUiol om vyOI LtS VJ.H~l 3

EP-EALCALC-MNS-1401 Page 20 of 28 Rev 0

Attachment I Median Wind Speed and Stability Values Memo Legacy Progress Sites (DEP):

Table 2.4 Brunswick Nuclear: 5-year Upper Level Medians by Sector Median Median Delta-Stability Sector WS (mph)

T(C/100m)

Class N

14

-0.71 D

NNE 14.7

-0.68 D

NE 14.2

-0.69 D

ENE 13.6

-0.81 D

E 11.2

-0.79 D

ESE 9.5

-0.635 D

SE 9

-0.67 D

SSE 9.5 46 E

S 11-4

-0.34 E

SSW 13.6

-0.79 D

SW*

16.2

-0.95 D

WSW 14.2

-0.74 D

W 9.6

-0.24 E

WNW 14.3

-0.28 E

NW 14.4

-0.44 E

NNW 15

-0.7 D

  • Most frequent BNP wAnd direction (2009-2013): from SW Table 2.5 Harris Nuclear: 5-year Lower Level Medians by $*

Median Median Delta-Stability Sector WS {mph)

T {C/10Om)

Class N

33

-0.35 E

NNE*

3.1

-0.26 E

NE 1.6 0-92 E

ENE 2.1 0.26 E

E 2.2

-0.07 E.

ESE 2.6

-0.39 E

SE 2.9

-0.49 E

SSE 3-4

-0.59 D

S 4.2

-0.64 D

SSW 47

-0.58 D

SW 4.7

-0.64 D

WSW 4.6

-0.86 D

W 3.7

-0.68 D

WNW 4.2

-0.74 D

NW 4.1

-0.805 D

NNW 3.5

-0.55 D

ector MOSt frequent HNP wino direction (20]09-2U13):. from NNE 4

EP-EALCALC-MNS-1401 Page 21 of 28 Rev 0

Attachment I Median Wind Speed and Stability Values Memo Table 2.6 Robinson Nuclear: 5-year Lower Level Medians by Sector Median Median Delta-Stability Sector WS (mph)

T (C/loom)

Class N*

5.8

-1.03 D

NNE 5.2

-1.09 D

NE 4

-1.11 D

ENE 3.8

-1.14 D

E 3.6

-1.2 D

ESE 3.3

-1.28 D

SE 3.5

-1.12 D

SSE 4.2

-0.69 D

S 4.7

-0.6 D

SSW 4.6

-0.68 D

SW 4.6

-0.83 D

WSW 4

-0.71 D

W 3.9

-0.59 D

WNW 3.9

-0.47 E

NW 4.1 0.28 E

NNW 4.7 0.31 E

  • Most frequent RNP wind direction (2009-2013): from North 3.0 Discussion and Conclusion The median wind speed data presented in Table I compared to Tables 2.1 through 2.6 indicates typically varying conditions, depending on the directional sectors at each site. The overall median wind speed at a site (3-6 mph) is in the middle of the wider range of the sector-specific medians (1-9 mph).

The singular median values sometime match well with the sector-specific median conditions of the most frequent directional sector, but can also be entirely different from the median of the most frequent wind direction sector. These differences span from potentially lower wind speeds which would be conservative for dose (i.e. Brunswick), to potentially higher wind speeds which would be non-conservative for dose (i.e Catawba).

Thus, the median values of wind speed should only be used for dose assessment as a last resort, when actual meteorological data is not available, or dose calculation is for some reason impaired.

The median Stability Class is generally neutral (class D), but varies between D and E (slightly more stable) in the sector-specific tables (Tables 2.1 through 2.6). These median values are typical of daytime conditions, with a thermally mixed boundary layer.

Thus, the median stability dass should only be used when there is no concem about actual time of day, seasonal variances, or extreme weather events.

EP-EALCALC-MNS-1401 Page 22 of 28 Rev 0 RUI.1 Liquid Effluent EAL Calculations RUI.1 Liquid Effluent EAL Calculations Cs-134 10CFR20 Limit - ECi (pCi/ml):

I TS Multiplier t1OE+O1 Background (cpm):

EP-EALCALC-MNS-1401 Page 23 of 28 Rev 0 RU1.1 Gaseous Effluent EAL Calculations RUI.1 Gaseous Effluent EAL Calculations Xe-133 Correlation Factor (pCi/ml/cpm): [.0+07 Vent Flow (cfm):

Unit Conersion Factor (cc/ft3 per sec/min):

42 XNQ (sec/m3):

Total Body Dose Rate Limit (mRem/yr): [

500 ODCM Limit for Total Body (cpm):

Skin Dose Rate Limit (mRem/yr):

0 ODCM Limit for Skin (cpm):

Background (cpm):

2x ODCM Limit (cpm):

EP-EALCALC-MNS-1401 Page 24 of 28 Rev 0 RA1.1, RS1.1 and RG1.1 URI Gaseous Effluent EAL Calculations RAI.1, RSI.1 and RGI.1 URI Gaseous Effluent EAL Calculations Dose Assessment MCoeire Monday, Febnmry 16, 215 16:19 Medhod: Detaled Assessment - Moni=tomd Release Release Paftwa (E) <RCS> <Cotainmerw t <Anus> <VE Fber> <Uni Vent> <Fiw>

PRF: 8.00E-04 Colainment HUT: = < 2 Hours Cont Sprays: = OFF Purge Filter = N/A Ie Cond Status: = No Ream Aen/Am*-Fuel HUT: = < 2 Hours Ann/AuirlFuel Filter = Wokldg Steam Gen: = N/A Turb Bldg HUT: = N/A Soum'e Tam: Reaclor Core Accdeft - Clad Upper Tome After S/ID (hhimm): 0.00 Wind: From 203" @ 6 mph Release Duration (hh:rnm): 1.00 ETE (hh:mm). I,/A ]

Slabty Class: D Pmoti Nore Mondto EMF36L Readings-486E+06 CPM Flowrate: 120000 CFM lK S.B.

1.30E+01 8.86E+00) 6-29E-01 5.49E-01 1.00E+01 1-16E+01, 0.5 1.20E+01 i8.12E-+00 5-96E-01 5-89E-01 9.30E-H00 1.0(E+01 0.7 8.36E+O0 5.52E+00 4.60E-01 5,49E-01 6.53E+00 620E+00 1.0 520E+00 3.37E+00 325E-01 4.26E-01 4.12E+00 3.5ME+00 1.5 2-76E+00 1.78E+00 1.90E-01 2.42E-01 2-21E+00 1.90E+00 N

A 20 1.92E+00 1.26E+00 1.18E-01 1.35E-01 1.51E+00 1.22EH)0 3-0 1-39E+00 9.30E-01 0.OOE+00 0-00E+00 9.30E-01 624E-01 Q

4.0 152E00 1.00E-41O O.00E-H10 0_000E+00 1.00E+00 6.95E-01 510 1-18E+00 7171E-01 OOOE.00 0.0E*-00 7-71E-01 5.87E-01 7.0 7.OOE-01 4-48E-01 0.00E+00 OIXIEW0 4A48-01 4.UOE-O1RD 10.0 4.84E-01 3.03E-01

_0.00E400 0_E+00 3.0E-1

_ 3.33E-01 IF AssessmeriDatRoub IW-Saved ID Film McGuire tOMbs Monitored Release 02162015 161951-URI7 Re e 5.B6E-03y(0.1%)

Reviewed By-Noble Gas 4.89E-00 (99.9%X)

Page 1 of 3 Mcfuire I17..0O.1 EP-EALCALC-MNS-1 401 Page 25 of 28 Rev 0 EP-EALCALC-MNS-1401 Page 25 of 28 Rev 0 RA1.1, RS1.1 and RG1.1 URI Gaseous Effluent EAL Calculations RAI.1, RSI.1 and RGI.1 URI Gaseous Effluent EAL Calculations rlnit A-4t-Q&-4L-4tm nt McGuire Monday, January 12, 2015 11:12 Mef.ld Doeailed Assessment - Monitored Release Release Pallhwa (E) <RCS> <Contaimnent> <Am Wlus>

<E Frler> <Unit Vent> <Env>

PRF: 8-ODE-04 Conkaiwnent HUT: = <2 Hours Cant Sprays: = OFF Purge File = N/A Ice Cond Status: = No Recire AnnlAdFuel HUT: = < 2 Hours AnnVAudFuet Filer = Wodring Steam Gen: = N/A Turb Bldg HUT: = N/A Source Term: Reactor Care Accident - Clad Upper Tine After S/ID (h-.:mm): 0-10 Wind: From 203 @ 6 mph Relemse Duvution (hh:nmm): 1-00 ETE (hh:mm): IN/A I Stabity Class: D Recioon: None Monitor. EMF36H Reaings: 2.70E+02 CPM Flowate: 120000 CFM S.B.

1.30E+01 8 86E+00 6.2WE-01 5-49E-01 1.00E+01 1.16E+01 1I 0.5 1.20+01 8.12E+00 5.96E-01 5.88E-01 9.30E+00 1.()E401*

1 0.7

&36E+00 5.52E+00 480E-01 5.49E-01 6.53E+00 6.20E+00 H

1.0 5.206+00 3.37E+00 325E-01 415E-01 4.12E+00 3.57E+00 1-5 2176E+00 1.78E+00 1.90E-01 2-42E-01 2.21E+00 1.90E+00 N

A 2-0 1.92E+00 1-26E+00 1.18E-01 1.35E-01 1.51E+00 122E00 3.0 1.39E+00 9.30E-01 0.00E+00 0.00E+00 9.30E-01 624E-01 L*

4.0 1.52E+00 9.99E-01 0.00E+00 0.10E+00 9.99E-01 6.95E-01 5.0 1.18E_00 770E-01 0.006*00 0.00E*00 7.70E-01 5.87E-01 7_0 7.OOE-01 4.48E-01 O.O0E+00 0.00E+00 4.48E-01 4.OOE-01 R

D 10.0 4.84E-01 3.03E-01 O.000E+0 0.0OE+00 3.03E-01 3.33E-01 F

Asses5ient Data ReSUts SaVed ID FW.e:

McGuie lOMides Monillord Release 01122015 111224-URI7 R ee y _ _ _ _._-03__0_1%_

Reviewed By:.

Noble Gas 4.89E+00 (99.9%)

Page 1 of 3 V77c7u77 12.0.0.

EP-EALCALC-MNS-1 401 Page 26 of 28 Rev 0 EP-EALCALC-MNS-1401 Page 26 of 28 Rev 0 RA1.1, RSIA and RG1.1 URI Gaseous Effluent EAL Calculations RAI.1, RSI.1 and RGI.1 URI Gaseous Effluent EAL Calculations Dose Assessment MCUlr Monday, January 12 2015 11:14 Method: Detaled Assessment - Monitored Release Release PahW. (E) <RCS> <Containment> <Annulus> <VE Filter> <Unit Vent> <Env>

PRF: 8.00E-04 Contaiunent HUT:

< 2 Hoaws Cont Sprays- = OFF Purge Filer = WA Ice Cond Status: = No Recirc AnJdAuXdFuel HUT:

< 2 Hours Ann/AuxmFuel Filer = Woing Steam Gen: = NA Turb Bldg HUT:

WA Souce Tenm: Reactor Core Ackdent - Clad Upper Tine After SID (htrmm): 0.10 Wind: From 203 @ 6 mph Release Durati (hh:mm): 1-00 ETE (hh:mm): IN/A I SW y Class: D Precitatio-n: None Monitor EMF36H Rea:i.gs: 2.61E+03 CPM Flowrate: 12D000 CFM

,,S.B-1-30E+02 8.86E+01 6.29E+00 5AG9E+00 1.0QE+02 1-16E+02 0.5 1.20E+02 8.12E+01 5.96E-H00 5.88E+00 9.30E+01 1.00E+02 0.7 8.36E+01 5.52E+01 4.60E+00 5.49E+00 6-53E+01 62DE+01 1.0 5.20E+01 3-37E+01 325E+00 425E+00 4-12E+01 3.57E+01 1.5 Z76E+01 1.78E+01 1.90E+00 2.42Et00 2.21E+01 1.90E+01 2-0 1.92E401 1.26E+01 1-18E-00 1.35E-00 1.51E+01 122E+01 3.0 1.39E.O1 9.30E+00 6-12E-01 7.56E-01 1.07E+01 6-24E+00 4.0 1.52E+01 9.99E+00 6.88E-01 8.32E-01 1.15E+01 6.95E+00 5.0 1.18EbO1 7.70E400 578E-01 6.50E-01 8.92E+00 5.87E+00 7.0 7.00-O00 4.48E-00 3.70E-01 356E-01 5.20E+00 4.00E-R0D 10.0 4.84E400 3.03E+00 2-74E-01

_08E-01 3.51E+00 3.33E00 F

Assessment Data Resultsave to Rle:

S McGuire 11Miges Monilted Release 01122015 111415.UR!7 R w y __ _ _ _ 2.43E-0 (0.0%)

iodine5-9WE-02 (0.1%)

Reviewed By-Noble Gas 1

4.89E-H01 (99.9%)

Page I of 3 M~Ck31,relz*0.1 EP-EALCALC-MNS-1401 Page 27 of 28 Rev 0 EP-EALCALC-MNS-1401 Page 27 of 28 Rev 0 RAI.1, RSI.1 and RGI.1 URI Gaseous Effluent EAL Calculations Dose Assessment MCGuire Monday, January 12, 2015 11:15 Method: Detaled Assessmenm - Mantored Release Rekease Paway: (E) <RCS> <Contaiwnenk' <Annulus> <VE Fiber> <Unit Vent> <Env>

PRF: 8.00E-04 Contahment HUT: = < 2 Horns Cont Sprays: = OFF Purge Filer = WA Ice Cond Status: = No Recire Ann/AuX/FUM HUT: = < 2 Hours Ann/AuFuel Fer = Workng Steam Gen: = WA Turb Bldg HUT: = WA Souce Term: F4eaclor Core Accident - Clad Time After SAD(hh:mm): 0.00 Release DOration (hhtmm): 1-00 ETE (hh:mm): [WA I Upper Wind: From 203" @ 6 mph Stabily Class: D PRecoa: None Monitor EMF36H Readings: 2-61 E+04 CPM Fkwate. 120000 CFM McGuire 10INs Monisored Release 01 122015 111514.UR!7 I~~~~~~~~

Ciisf-iin Gee i

mrec EP-EALCALC-MNS-1401 Page 28 of 28 Rev 0

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