ML042740522

CR X/Qs Using ARCON96 Code - Non-LOCA Releases

ML042740522
Person / Time
Site:	Salem, Hope Creek
Issue date:	09/22/2003
From:	Gita Patel NUCORE
To:	Office of Nuclear Reactor Regulation
References
LR-N04-0413 S-C-ZZ-MDC-1959, OIR1
Download: ML042740522 (69)

Text

• -

NC.DE-AP.ZZ-0002(Q)

FORM 1 Page 2 of 2 (Page 1 contains the instructions)

CALC NO.: S-C-ZZ-MDC-1959 CALCULATION COVER SHEET

• Page 1 of 66 REVISION: 01R1l CALC. TITLE:

CR x/Qs Using ARCON96 Code - Non-LOCA Releases

1. SHTS (CALC): l 66

1. ATT/ # SHTS: l 212

1. IDV/50.59 SHTS: l 2/3

1. TOTAL SHTS:

l73 CHECK ONE:

ED FINAL Z INTERIM (Proposed Plant Change)

El FINAL (Future Confirmation Req'd)

EA VOID SALEM OR HOPE CREEK:

D 0 - LIST 0D IMPORTANT TO SAFETY El NON-SAFETY RELATED HOPE CREEK ONLY:

[DO MQs ElOsh OF ER El STATION PROCEDURES IMPACTED, IF SO CONTACT RELIABILITY ENGINEER El CDs INCORPORATED (IF ANY):

DESCRIPTION OF CALCULATION REVISION (IF APPL.):

The XiQ values for Hope Creek CR air intake for Salem 2 plant vent release are calculated PURPOSE:

The purpose of this calculation is to determine the values of atmospheric dispersion factors (X/Qs) (relative concentrations) at the Salem Nuclear Generating Station (SNGS) control room (CR) air intakes, which are not exceeded more than 5.0 percent of the total hours in the meteorological data set (i.e., 95h percentile X/Qs). These XIQ values are determined for the following non-LOCA post-accident release points:

L-Units I & 2 Main Steam Safety Valve (MSSV) Set

2. Units I & 2 MSSV Set 2

3. Units I & 2 Penetration Area Pressure Relief Panels (PAPRPs)

4. Units I & 2 Smoke Hatches

5. SNGS Unit 2 Plant Vent Release (to the HCGS CR Air Intake)

The x1Qs developed in this calculation will be used in the design basis accident analyses to support the Licensing Change Request (LCR) S03-05.

CONCLUSIONS:

The 95h percentile atmospheric dispersion factors X/Qs values for post-accident releases through the MSSVs, PAPRPs, and smoke hatches are summarized in Sections 8.1 through 8.5. The applicable X/Qs should be used for the non-LOCA design basis accidents based on the appropriate release locations.

Printed Name / Sjigffajure/

1 Date ORIGINATOR/COMPANY NAME:

Gopal J. Patel/NUCORE 09/22/03 REVIEWER/COMPANY NAME:

N/A NIA VERIFIER/COMPANY NAME:

Mark Drucker/NUCORE o_

09/24/03 PSEG SUPERVISOR APPROVAL:

Paul LindsayIPSEG )

/

25 12 f

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CALCULATION CONTINUATION SHEET I SHEET 2 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker/NUCORE, REVIEWERNVERIFIER, DATE 09/24/03 REVISION HISTORY Revision Description OIRO Original Issue OIRI The X/Q values for Hope Creek CR air intake for a Salem 2 plant vent release are calculated

~.

7 Nuclear Common Revision 9

CALCULATION CONTINUATION SHEET SHEET 3 of66 CALC. NO.: S-C-ZZ-MDC-1959

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09/22/03 0

M. Drucker/NUCORE, REVIEWER/VERI Fl ER, DATE 09/24/03 PAGE REVISION INDEX PAGE REV PAGE REV I

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S CALCULATION CONTINUATION SHEET SHEET 4 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. DruckerfNUCORE, REVIEWER/VERIFIER, DATE 09/24/03 TABLE OF CONTENTS Section Cover Sheet Revision History Page Revision Index Table of Contents 1.0 Purpose

2.0 Background

3.0 Analytical Approach 4.0 Assumptions 5.0 Design Input Parameters 6.0 Methodology 7.0 Calculations 8.0 Results Summary 9.0 Conclusions 10.0 References I 1.0 Tables 12.0 Figures 13.0 Affected Documents 14.0 Attachments Sheet No.

1 2

3 4

5 5

5 1 0 1 5 19 20 38 43 44 47 51 66 66 Nuclear Common Revision 9

a-CALCULATION CONTINUATION SHEET SHEET 5 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker[NUCORE, REVIEEWER/VERI FI ER, DATE 09/24/03 1.0 PURPOSE The purpose of this calculation is to determine the values of atmospheric dispersion factors (x/Qs) (relative concentrations) at the Salem Nuclear Generating Station (SNGS) control room (CR) air intakes, which are not exceeded more than 5.0 percent of the total hours in the meteorological data set (i.e., 9 5 th percentile x/Qs).

These X/Q values are determined for the following post-accident release points:

I.

Units 1 & 2 Main Steam Safety Valve (MSSV) Set 1

2.

Units I & 2 MSSV Set 2

3.

Units 1 & 2 Penetration Area Pressure Relief Panels (PAPRPs)

4.

Units I & 2 Smoke Hatches In addition, this calculation determines the X/Q values for the following SNGS post-accident release path that could impact the Hope Creek Generating Station (HCGS):

5.

SNGS Unit 2 Plant Vent Release (to the HCGS CR Air Intake)

The x/Qs developed innthis calculation will bre-us&ed if the-de-sign b asi sa-ciddi-i nlyses -to support Licensi ng Change Request (LCR) S03-05.

2.0 BACKGROUND

The 9 5 th percentile yJQs at the SNGS control room intakes for the release points listed in Section 1.0 are calculated in Reference 10.17 using the ARCON95 computer code. The ARCON96 code user's manual (Ref.

10.2, Section 2.5.5) indicates that the ARCON96 X/Qs for the 2-hour to 8-hour averaging period are about a factor of 2 higher than the corresponding values calculated using ARCON95. For intervals in this range centerline x/Qs are averaged in ARCON96, whereas sector-average x/Qs were averaged in ARCON95.

Reference 10.3, Section 4, provides a set of equations for plume rise due to buoyancy and momentum, which are different than those used in Reference 10.17. The as-built vertical velocities of MSSV releases are considerably different than those used in Reference 10.17. Therefore, the existing x/Qs in Reference 10.17 are recalculated to comply with the latest regulatory guidance in Reference 10.3 using the as-built MSSV release data and ARCON96 code.

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CALCULATION CONTINUATION SHEET SHEET 6 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. DruckerfNUCORE, REVIEWERNVERIFIER, DATE 09/24/03 3.0 ANALYTICAL APPROACH The CR air intake X/Qs are calculated using the NRC-sponsored computer code ARCON96 (Refs. 10.2 and 10.13) and 7-years (1 988-1994) of SNGS plant specific meteorological data (Ref. 10.1). The recommendations provided in Regulatory Guide 1.194 (Ref. 10.3) for the use of ARCON96 dispersion model are incorporated.

The post-accident penetration area pressure relief panel and smoke hatch releases are assumed to be ground level point sources. The post-accident main steam safety valve release X/Qs are calculated as ground level releases, then reduced by a factor of five as allowed by RG 1.194 Section 6 for uncapped and vertically oriented high velocity releases. The Salem 1 & 2 plants have a combined control room (CCR) (Ref. 10.5.1), which is supplied with the outside air via Unit I and Unit 2 intakes (Ref. 10.4). The CR intake monitor allows for preferential alignment to side of the non-accident unit to provide less contaminated air intake (Ref. 10.15, Section 3.1). Therefore, each release point is analyzed to determine two sets of X/Qs, one set for each CR intake. The calculation is divided into the following four sections:

1.- -- - CR-X/Qs for Main SteameSafetyaValve lMSSV)rreleases-

2.

CR y/Qs for Penetration Area Pressure Relief Panel (PAPRP)

3.

CR yjQs for Smoke Hatch

4.

Hope Creek CR xJQs for Salem 2 Plant Vent Release 3.1 CR y/Qs for MSSV Releases There are four sets of MSSVs for each unit. Due to the clustering of the MSSVs within each set, each MSSV set can be represented by one release point. The locations of these MSSV release points are shown in Reference 10.1 1. The CR intakes are shown in Reference 10.4. Based on the proximity of the MSSV release points to the CR intakes, modeling ofjust the two MSSV sets located north of Salem Unit I and the two MSSV sets located south of Unit 2 are sufficient to conservatively establish the CR X/Qs. The steam releases from the faulted and intact steam generators can be respectively allocated to the MSSV Set 1 located near the containment centerline and to MSSV Set 2 located east of the containment centerline. The MSSV release point locations of interest are configured with respect to the CR air intakes in Figures 3 through 10 based on the dimensions given in various arrangement drawings (Refs. 10.4, 10.5, & 10.1 1). The cross-sectional area of containment building controls the Nuclear Common Revision 9

CALCULATION CONTINUATION SHEET SHEET 7 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker/NUCORE, REVIEWER/VERIFIER, DATE 09124/03 downwind distance of building-wake (see Figures 3 through 10) in prevailing wind direction for the MSSV releases. Various receptor data (Ref. 10.2, pages 15 & 16) and source data (Ref. 10.2, pages 17 & 18) required for the ARCON96 X/Q computations are established in Sections 7.1 through 7.8 based on the plant-specific configuration. The 7-years (1988-1994) meteorological data files were formatted per instructions given in Table A-I of Reference 10.3 and used as ARCON96 meteorological input. The required source/receptor input data are tabulated underneath Figures 3 through 10.

The MSSV release is a high velocity jet release, which creates additional plume rise due to buoyancy resulting from the expansion of effluent in the lower ambient temperature and pressure and momentum associated with the energetic release. Regulatory Guide 1.194, Section 6, allows a reduction of the ground level X/Q values calculated at the physical height of the release point by a factor of 5. This reduction may be taken if (1) the release point is uncapped and vertically oriented and (2) the time dependent vertical velocity exceeds the 95 th _

percentile wind speed (at the release point height) by a factor of 5. The MSSV releases are qualified for the

-allowable reduction as follows-:

-~

The MSSV vent pipes are uncapped and vertically oriented (Ref. 10.11).

a The 95th _ percentile wind speed at the lower measurement point of the met tower is 16.5 meter/sec (Ref. 10.1). The qualifying wind speed is 82.5 m/s (16.5 m/s x 5 = 82.5 m/s), which is 5 times the 9 5th percentile wind speed (Ref. 10.3).

The met tower lower measurement point is located 33 feet above the grade (Ref. 10.9), which is lower than the height of MSSV release point of 47'-6" (Section 7.1).

The vertical velocity of the MSSV is 448 m/s (Ref. 10.18, Section 3.1.2), which is considerably higher than 82.5 m/s.

The ground level X/Qs values calculated using ARCON96 and listed in Tables I & 2, are reduced by a factor 5 when reported in Sections 8.1 & 8.2.

3.2 CR x/Qs for Penetration Arca Pressure Relief Pan cl (PAPRP)

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CALCULATION CONTINUATION SHEET SHEET 8 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker/NUCORE, REVIEWER/VERIFIER, DATE 09/24/03 The Salem Units 1 & 2 PAPRPs are located east of the CR intakes (Refs. 10.5.1 & 10.12). The PAPRP framing details are shown in References 10.12.3 & 10.12.4. The PAPRPs are pressure-retaining barriers, which are expected to rupture when the pressure exceeds the design value. During the main steam line break accident (MSLB), the high energy steam released from the ruptured steam line will pressurize the PAPRPs above the design pressure and the post-MSLB activity will be released to the environment through the ruptured PAPRPs.

Since the orientation of the PAPRPs is horizontal facing east (Ref. 10.12.4), it does not meet the adjustment criterion for plume rise (see the discussion in Section 3.1 above). The PAPRP release point locations of interest are configured with respect to the CR air intakes in Figures 11 & 12 based on the dimensions given in various arrangement drawings (Refs. 10.4, 10.5.1, & 10.12). The cross-sectional area of the turbine building controls the downwind distance of building-wake (see Figures 11 & 12) in the prevailing wind direction from the east.

Various receptor data (Ref. 10.2, pages 15 & 16) and source data (Ref. 10.2, pages 17 & 18) required for the ARCON96 X/Q computations are established in Sections 7.9 through 7.12 based on the plant-specific

~-configuration;.The required source/receptbrfin-put data-are tab-ula-ted ufidereath Figures -l1&-2ia an the resulting X/Q values are shown in Table 3 and Section 8.3.

3.3 CR y/Qs for Smokc Hatch The Salem Units I & 2 Smoke Hatches are located on the roofs of the containment access to the fuel handling building (Ref. 10.16). The smoke hatches are pressure-retaining barriers, which are expected to rupture when the smoke related pressure exceeds the design value. A pressure inducing accident occurring in the penetration area will pressurize the smoke hatch above the design pressure and the post-accident activity will be released to environment through the ruptured smoke hatch barrier. The smoke hatch release point locations of interest are configured with respect to the CR air intakes in Figures 13 & 14 based on the dimensions given in various arrangement drawings (Refs. 10.16 & 10.19). The cross-sectional area of the fuel handling building (FHB) controls the downwind distance of building-wake (see Figures 13 & 14) in the prevailing wind direction from the west. Various receptor data (Ref. 10.2, pages 15 & 16) and source data (Ref. 10.2, pages 17 & 18) required for the ARCON96 X/Q computations are established in Sections 7.13 through 7.16 based on the plant-specific configuration. Although each smoke hatch is an area source of 5' x 5' (Refs. 10.16.1 & 10.16.3 Sections 11-11 Nuclear Common Revision 9

CALCULATION CONTINUATION SHEET SHEET 9 of 66 CALC. NO.: S-C-ZZ-MDC-1959

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09/22/03 0

M. Drucker/NUCORE, REVIEWER/VERIFIER, DATE 09/24/03

& 12-12), each is conservatively modeled as a point source. The required source/receptor input data are tabulated underneath Figures 13 & 14 and the resulting X/Q values are shown in Table 4 and Section 8.4.

3.4 Hope Creek CR y/Qs for Salem 2 Plant Vent Release The Hope Creek CR air intake is located to the northwest of the Salem 2 plant vent (Ref. 10.21). The plant vent release point of interest is configured with respect to the Hope Creek CR air intake in Figure 15 based on the dimensions given in arrangement drawings (Refs. 10.5 & 10.21). The cross-sectional area of the Salem 2 containment controls the downwind distance of building-wake (see Figure 15) in the prevailing wind direction from the southeast. Various receptor data (Ref. 10.2, pages 15 & 16) and source data (Ref. 10.2, pages 17 & 18) required for the ARCON96 X/Q computations are established in Section 7.17 based on the plant-specific configuration. The required source/receptor input data are tabulated underneath Figure 15 and the resulting X/Q values are shown in Section 8.5.

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CALCULATION CONTINUATION SHEET SHEET 10 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 l7 G. Patel/NUCORE, ORIGINATOR, DATE IREV:

09/22103 0

M. Drucker/NUCORE, REVIEWER/VERIFIER, DATE 09/24/03

4.0 ASSUMPTIONS

The regulatory requirements in Regulatory Guide 1.194 (Ref. 10.3) are adopted as assumptions in the following section, which are incorporated as design inputs along with other plant-specific as-built design parameters in Section 5.0 4.1 Metcorological Data Input General Considerations Design Input 5.1 - The 7-years of SNGS site-specific meteorological data (1988 through 1994) meet the following RG 1.194 RGP 3.1 requirements (Ref. 10.1)

The met data were obtained from the Artificial Island meteorological monitoring program, which provides the wind speed, wind direction, and other measured parameters to determine the.

atmospheric stability based on the guidance of Regulatory Guide 1.23 (Ref. 10.10).

The met data program includes quality assurance provisions consistent with Appendix B of 10

-CFR Part 50-(Ref.e0.16).

0' -

Data are presented as hourly averages as defined in RG 1.23 (Ref. 10.10).

Data are representative of overall site condition and are free from local effects such as building and cooling tower wakes, brush and vegetation, or terrain (Ref. 10.7).

The 7-years of data used in the X/Q assessment are more than sufficient to reflect long-term site-specific meteorological trends.

The near-ground atmosphere stability classifications for the ground level release are determined based on the vertical temperature difference (AT) measured between the lower measurement point at 33 feet and upper measurement point at 300 feet (Ref. 10. 17, page 8) and atmosphere stability classification criteria in ANSI/ANS-2.5 (Ref. 10.8).

The met data are formatted in the text data files using the format shown in Table A-I of RG-1.194.

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CALCULATION CONTINUATION SHEET SHEET 11 of66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker/NUCORE, REVIEWER/VERIFIER, DATE 09/24/03 4.2 Determination of Source Characteristics Design Input 5.2 - Source Data - based on RG 1.194, RGP 3.2.1, the post-accidental release through the Penetration Area Pressure Relief Panels (PAPRPs), Smoke Hatches, and the Plant Vent are qualified to be ground level point sources. The post-accident main steam safety valve release (MSSV) X/Qs are calculated as ground level releases, then reduced by a factor of five for the plume rise associated with the buoyancy and momentum with the vertically oriented high velocity MSSV release (Ref. 10.3, Section 6).

4.3 Determination of CR Intake (Receptor) Characteristics Design Input 5.3 - Receptor Data - meets the following RG 1.194 RGP 3.3 requirements:

1.

Ventilation System Outside Air Intake/ Dual Ventilation Outside Air Intakes RGPs 3.3.1 and 3.3.2 require that the CR ventilation system configuration with respect to accident response should be evaluated to identify the limiting and favorable intake with regard to their X/Q values. Because of the interplay of building wake, plume rise, wind direction frequency, intake flow rate, and other parameters, it may not be possible to identify the limiting or favorable intake by observation. The combined control room (CCR) draws makeup air from the environment by two separate air intakes (Ref. 10.4). Therefore, the X/Q values are calculated for each release source-receptor combination and the limiting and favorable intakes are identified based on the following requirements:

2.

Per RGP 3.3.2.1, the limiting and favorable x/Qs are not adjusted for dilution because both intakes are in the same wind direction window (See Figures 3 through 14).

3.

RGP 3.3.2.2 is not applicable to Salem I & 2 CCR design because the intakes can be automatically isolated by design and both intakes are in the same wind direction window.

4.

RGP 3.3.2.3 is not applicable to Salem I & 2 CCR design because the ventilation system design does not allow the operator to manually select the least contaminated outside air intake.

5.

The reduction of X/Q values in the RGP 3.3.2.4 cannot be credited for the Salem I & 2 CCR design because both intakes are in the same wind direction window.

Nuclear Common Revision 9

CALCULATION CONTINUATION SHEET SHEET 12 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

l M. Drucker/NUCORE, REVIEWER/VERIFIER, DATE 09/24103

6.

Infiltration Pathways The typical infiltration pathways that need to be considered in establishing CR intake x/Q values are listed in the RGP 3.3.3. The infiltration pathways listed in RGP 3.3.3 are reviewed for the assessment of CR X/Q values in this analysis for the potential releases from MSSVs, PAPRPs, and Smoke Hatches.

The potential infiltration is assumed to occur at the same location of CR emergency air intake (same location for normal and emergency intakes), therefore, no additional analysis required for infiltration X/Qs.

The single HCGS CR intake is the same intake modeled in the HCGS analysis that calculates CR X/Q values for HCGS events (Ref. 10.20).

4.4 Source-Receptor Distance Design Input 5.4 - Source-Receptor Distance - meets the RG 1.194 RGP 3.4 requirement as follows:

The source-to-receptor distance is the shortest horizontal distance between the release point and intake. -

The actual straight-line horizontal distances between the release points and intakes are used (See Figures 3 through 14).

4.5 Source-Receptor Direction Design Input 5.5 - Source-Receptor Direction - meets the RG 1.194 RGP 3.4 requirement as follows:

Wind direction data are recorded as the direction from which the wind blows (e.g. a wind blowing out of the west is recorded with a direction of 270 degrees). The plant north is 50-30'-01" west of true north (Ref. 10.7), therefore, the orientation of the release point with respect to receptor location is corrected accordingly.

4.6 Building Area ARCON96 uses the value of the building area in the high wind speed adjustment for ground level and vent release models (Ref. 10.3, Table A-2). The containment building vertical cross-sectional area, which is the area perpendicular to the prevailing wind direction, is used in Design Input 5.6 for the MSSV and Plant Vent releases. The turbine building cross-sectional area perpendicular to the prevailing wind direction is used in Design Input 5.6 for the PAPRP releases. The fuel handling building cross-Nuclear Common Revision 9

CALCULATION CONTINUATION SHEET SHEET 13 of 66 CALC. NO.: S-C-ZZ-MDC-1959

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M. Drucker/NUCORE, REVIEWER/VERIFIER, DATE 09/24/03 sectional area perpendicular to the prevailing wind direction is used in Design Input 5.6 for the smoke hatch releases.

4.7 Release Height ARCON96 uses the value of the release height to adjust wind speed for differences between the heights of the meteorological tower instrumentation and the release, to determine the slant path for ground level releases, and to correct the off-centerline data for elevated releases (Ref. 10.3, Table A-2). The actual release heights for the MSSVs, PAPRPs, smoke hatch, and Plant Vent are used in Design Input 5.7. The MSSV X/Qs are calculated as ground level releases, then reduced by a factor of five as allowed by RG 1.194 Section 6 for uncapped and vertically oriented high velocity releases.

4.8 Intake Height ARCON96 uses the value of the intake height to determine the slant path for ground level releases and to correct the off-centerline data for stack release models (Ref. 10.3, Table A-2). The actual CR intake centerline heights are used in Design Input 5.8 for this analysis.

4.9 Surface Roughness Length ARCON96 uses the value of this parameter in adjusting wind speeds to account for differences in meteorological instrumentation height and release height (Ref. 10.3, Table A-2). A value of 0.2 meters in lieu of the default value of 0.1 (Ref. 10.3, Table A-1) is used in Design Input 5.9.

4.10 Minimum WNind Speed ARCON96 uses the value of this parameter to identify calm wind conditions (Ref. 10.3, Table A-2). The code default wind speed of 0.5 m/s (Ref. 10.3, Table A-2) is used in Design Input 5.10. Consistent with RG 1. 1 94 Table A-2, use of the code default wind speed of 0.5 m/s is appropriate since the met tower anemometer is capable of documenting wind speeds of less than 0.6 m/s (i.e., wind speeds of less than 1.3 mph are documented in the meteorological data [Ref. 10.1]).

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CALCULATION CONTINUATION SHEET SHEET 14 of 66 CALC. NO.: S-C-ZZ-MDC-1959

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LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE V

0912203 0

M. Drucker/NUCORE, REVIEWERJVERIFIER, DATE 09124/03 4.11 Average Sector Wind Constant ARCON96 uses the value of this parameter to prevent inconsistency between the centerline and sector average X/Qs for wide plumes (Ref. 10.3, Table A-2). Although the code default value is 4.0, a value of 4.3 (Ref. 10.3, Table A-2) is used in Design Input 5.11.

4.12 Lower Measurement Height ARCON96 uses the value of this parameter to adjust the wind speeds for the differences between the heights of the meteorological tower instrumentation and the release (Ref. 10.3, Table A-2). The actual height of 33 feet (Ref. 10.9) is used for the lower instrumentation in Design Input 5.12.

4.13 Upper Measurement Height ARCON96 uses the value of this parameter to adjust the wind speeds for the differences between the heights of the meteorological tower instrumentation and the release (Ref. 10.3, Table A-2). The actual intermediate measurement height of 150 feet (Ref. 10.9) is conservatively used for the upper instrumentation in Design Input 5.13.

4.14 Wind Speed ARCON96 requires that wind speed be entered as miles per hour, meters per second or knots (Ref. 10.3, Table A-2). Wind speed in units of miles per hour (mph) is entered in Design Input 5.14 for consistency with the units of the wind speeds in the meteorological data files (Ref. 10.14).

Nuclear Common Revision 9

. N M-CALCULATION CONTINUATION SHEET SHEET 15 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker/NUCORE, REVIEWERVNERIFIER, DATE 09/24/03 5.0 DESIGN INPUT PARAMETERS Parameter Value Refcrence 5.1 Salem Metcorological Data 1988-1994 Meteorological Data Ref. 10.1 5.2 Source Release Category Salem 1 MSSV Set I Cluster Ground Level Point Source Sections 7.1 & 7.2 Salem I MSSV Set 2 Cluster Ground Level Point Source Sections 7.3 & 7.4 Salem 2 MSSV Set 1 Cluster Ground Level Point Source Sections 7.5 & 7.6 Salem 2 MSSV Set 2 Cluster Ground Level Point Source Sections 7.7 & 7.8 Salem I PAPRP Ground Level Point Source Sections 7.9 & 7.10 Salem 2 PAPRP Ground Level Point Source Sections 7.11 & 7.12 Salem 1 Smoke Hatch Ground Level Point Source Sections 7.13 & 7.14 Salem 2 Smoke Hatch Ground Level Point Source Sections 7.15 & 7.16 Salem 2 Plant Vent Ground Level Point Source Section 7.17 5.3.1 CR Characteristics Salem I MSSV Set I Cluster Dual CR Intakes Figures 3 & 4 Salem 1 MSSV Set 2 Cluster Dual CR Intakes Figures 5 & 6 Salem 2 MSSV Set 1 Cluster Dual CR Intakes Figures 7 & 8 Salem 2 MSSV Set 2 Cluster Dual CR Intakes Figures 9 & 10 Salem I PAPRP Dual CR Intakes Figure 11 Salem 2 PAPRP Dual CR Intakes Figure 12 Salem I Smoke Hatch Dual CR Intakes Figure 13 Salem 2 Smoke Hatch Dual CR Intakes Figure 14 Salem 2 Plant Vent Single (HCGS) CR Intake Figure 15 5.3.2 Dilution Credit Dilution Not Credited Salem I MSSV Set 1 Cluster Same Wind Direction Window Figures 3 & 4 Salem I MSSV Set 2 Cluster Same Wind Direction Window Figures 5 & 6 Salem 2 MSSV Set 1 Cluster Same Wind Direction Window Figures 7 & 8 Salem 2 MSSV Set 2 Cluster Same Wind Direction Window Figures 9 & 10 Salem I PAPRP Same Wind Direction Window Figure 11 Salem 2 PAPRP Same Wind Direction Window Figure 12 Salem I Smoke Hatch Same Wind Direction Window Figure 13 Salem 2 Smoke Hatch Same Wind Direction Window Figure 14 Salem 2 Plant Vent Same Wind Direction Window Figure 15 5.3.3 Reduction of x/Qs Reduction Not credited Salem I MSSV Set 1 Cluster Same Wind Direction Window Figures 3 & 4 Salem I MSSV Set 2 Cluster Same Wind Direction Window Figures 5 & 6 Salem 2 MSSV Set I Cluster Same Wind Direction Window Figures 7 & 8 Salem 2 MSSV Set 2 Cluster Same Wind Direction Window Figures 9 & 10 Salem I PAPRP Same Wind Direction Window Figure 11 Salem 2 PAPRP Same Wind Direction Window Figure 12 Nuclear Common Revision 9

• n CALCULATION CONTINUATION SHEET SHEET 16 of 66 CALC. NO.: S-C-ZZ-MDC-1959

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LCR S03-05 G. PateINUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker/NUCORE, REVIEWERNVERIFIER, DATE 09/24/03 Parameter Value Reference 5.3.3 Reduction of x/Qs (Cont'd)

Salem I Smoke Hatch Same Wind Direction Window Figure 13 Salem 2 Smoke Hatch Same Wind Direction Window Figure 14 Salem 2 Plant Vent Same Wind Direction Window Figure 15 5.3.4 Infiltration Pathways Same As CR Air Intakes 10.4 5.4 Source-Receptor Distance Salem I MSSV I To CR1 6.38 m Section 7.1 Salem I MSSV I To CR2 41.58 m Section 7.2 Salem 1 MSSV 2 To CR1 13.18 m Section 7.3 Salem 1 MSSV 2 To CR2 44.47 rn Section 7.4 Salem 2 MSSV 1 To CR2 6.38 m Section 7.5 Salem 2 MSSV I To CR1 41.58 m Section 7.6 Salem 2 MSSV 2 To CR2 13.18 m Section 7.7 Salem 2 MSSV 2 To CR1 44.47 m Section 7.8 Salem I PAPRP To CR1 29.77 m Section 7.9 Salem I PAPRP To CR2 54.03 m Section 7.10 Salem 2 PAPRP To CR2 29.77 m Section 7.11 Salem 2 PAPRP To CR1 54.03 m Section 7.12 Salem 1 Smoke Hatch To CR1 21.99 m Section 7.13 Salem 1 Smoke Hatch To CR2 55.61 m Section 7.14 Salem 2 Smoke Hatch To CR2 21.99 m Section 7.15 Salem 2 Smoke Hatch To CR1 55.61 m Section 7.16 Salem 2 Plant Vent To HCGS CR 427.99 m Section 7.17 5.5 Source-Receptor Direction Salem I MSSV I To CR1 113.490 Section 7.1 Salem I MSSV I To CR2 166.810 Section 7.2 Salem I MSSV 2 To CR1 105.000 Section 7.3 Salem I MSSV 2 To CR2 158.380 Section 7.4 Salem 2 MSSV 1 To CR2 55.510 Section 7.5 Salem 2 MSSV I To CR1 2.190 Section 7.6 Salem 2 MSSV 2 To CR2 64.000 Section 7.7 Salem 2 MSSV 2 To CR1 10.620 Section 7.8 Salem I PAPRP To CR1 99.340 Section 7.9 Salem I PAPRP To CR2 142.330 Section 7.10 Salem 2 PAPRP To CR2 69.660 Section 7.11 Salem 2 PAPRP To CR1 26.670 Section 7.12 Salem I Smoke Hatch To CR1 220.900 Section 7.13 Salem I Smoke Hatch To CR2 191.150 Section 7.14 Salem 2 Smoke Hatch To CR2 308.100 Section 7.15 Salem 2 Smoke Hatch To CR1 337.850 Section 7.16 Nuclear Common Revision 9

"i:1'::'-..

i:%:

. 7 I

CALCULATION CONTINUATION SHEET SHEET 17 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker/NUCORE, REVIEWER/VERIFIER, DATE 09/24/03 Parameter Value Rcfercnce 5.5 Source-Receptor Direction (Cont'd)

Salem 2 Plant Vent To HCGS CR 153.230 Section 7.17 5.6 Building Wake Area Salem I MSSV 1 To CRI 2,429.54 in2 Section 7.1 Salem 1 MSSV I To CR2 2,429.54 m2 Section 7.1 Salem I MSSV 2 To CRI 2,429.54 mi 2

Section 7.1 Salem 1 MSSV 2 To CR2 2,429.54 mi 2

Section 7.1 Salem 2 MSSV I To CR1 2,429.54 m2 Section 7.1 Salem 2 MSSV I To CR2 2,429.54 m2 Section 7.1 Salem 2 MSSV 2 To CR1 2,429.54 m2 Section 7.1 Salem 2 MSSV 2 To CR2 2,429.54 m2 Section 7.1 Salem I PAPRP To CR 775.49 m 2 Section 7.9 Salem I PAPRP To CR2 775.49 M2 Section 7.9 Salem 2 PAPRP To CR2 775.49 m 2 Section 7.9 Salem 2 PAPRP To CR1 775.49 m2 Section 7.9 Salem 1 Smoke Hatch To CR1 648.89 M2 Section 7.13 Salem 1 Smoke Hatch To CR2 648.89 m2 Section 7.13 Salem 2 Smoke Hatch To CR2 648.89 m 2

Section 7.13 Salem 2 Smoke Hatch To CR1 648.89 m 2 Section 7.13 Salem 2 Plant Vent To HCGS CR 2,429.54 m 2' Section 7.1 5.7 Release Height Salem I MSSV I To CR1 14.48 m Section 7.1 Salem I MSSV I To CR2 14.48 m Section 7.1 Salem I MSSV 2 To CR1 14.48 m Section 7.1 Salem 1 MSSV 2 To CR2 14.48 m Section 7.1 Salem 2 MSSV I To CR1 14.48 m Section 7.1 Salem 2 MSSV I To CR2 14.48 m.

Section 7.1 Salem 2 MSSV 2 To CR1 14.48 m Section 7.1 Salem 2 MSSV 2 To CR2 14.48 m Section 7.1 Salem I PAPRP To CR1 8.92 m Section 7.9 Salem I PAPRP To CR2 8.92 m Section 7.9 Salem 2 PAPRP To CR2 8.92 m Section 7.9 Salem 2 PAPRP To CR1 8.92 m Section 7.9 Salem I Smoke Hatch To CR1 12.96 m Section 7.13 Salem 1 Smoke Hatch To CR2 12.96 m Section 7.13 Salem 2 Smoke Hatch To CR2 12.96 m Section 7.13 Salem 2 Smoke Hatch To CRI 12.96 m Section 7.13 Salem 2 Plant Vent To HCGS CR 58.54 m Section 7.17 Nuclear Common Revision 9

CALCULATION CONTINUATION SHEET SHEET 18 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker/NUCORE, REVIEWER/VERIFIER, DATE 09124/03 Parameter Value Reference 5.8 Intake Height Unit I CRI 9.39 m Section 7.1 Unit 2 CR2 9.13 m Section 7.2 HCGS CR 17.05 m Section 7.17 5.9 Surface Roughness Length 0.2 m 10.3, Table A-I 5.10 Minimum Wind Speed 0.5 m/s 10.3, Table A-i 5.11 Averaging Sector Width 4.3 10.3, Table A-I Constant 5.12 Lower Measurement Height 33 feet (10.06 m) 10.9 for Met Data 5.13 Intermediate Measurement 150 feet (45.73 m) 10.9 Height for Met Data 5.14 Wind Speed Units for Met Mph 10.14 Data 5.15 Sigma Y value 1.448 m Section 7.9 5.16 SigmaZ Value 0.585 m Section 7.9 5.17 MSSV Vertical Velocity 448 m/s 10.18, Section 3.1.2 5.18 95"' - Percentile Wind Speed 16.5 m/s 10.1, Derived Note: The remaining default parameter values used by ARCON96 code are same as those in Reference 10.3, Table A-1.

'The MSSV X/Qs are calculated as ground level releases, then reduced by a factor of 5 as allowed in Reference 10.3, Section 6 for uncapped and vertically oriented high velocity releases.

Nuclear Common Revision 9

CALCULATION CONTINUATION SHEET SHEET 19 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE I REV:

09/22/03 0

l M. Drucker/NUCORE, REVIEWER/VERIFIER, DATE 09/24/03 6.0 METHODOLOGY The X/Q values for the MSSV, PAPRP, smoke hatch, and Salem 2 plant vent releases are developed in this calculation using the plant-specific as-built design input information (Ref. 10.18), the NRC sponsored ARCON96 computer code (Ref. 10.2), and line-by-line compliance with guidance in the RG 1.194 (Ref. 10.3).

The x/Qs values are calculated in a conservative manner to maximize their values. The X/Q values of MSSV releases are adjusted for the energetic plume rise by comparing a velocity equal to 5 times the 9 5 th - percentile wind speed at the MSSV release point height with the minimum vertical velocity resulting from the MSSV mass releases. The X/Q values for the PAPRP, smoke hatch, and Salem 2 plant vent are based on the ground level source point release and they are not adjusted for the plume rise. The smallest wake diffusion areas are considered based on the source/receptor geometries. The necessary ARCON96 input parameters are conservatively established in Section 7.0 and tabulated underneath Figures 3 through 15. The resulting X/Qs values are listed in Section 8.0.

Nuclear Common Revision 9

I CALCULATION CONTINUATION SHEET SHEET 20 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE I REV:

09/22/03 0

l l

M. Drucker/NUCORE, REVIEWER/VERIFIER, DATE 09/24/03 7.0 CALCULATIONS The source/receptor input parameters for ARCON96 code are calculated in the following sections based on geometry models shown in Figures 3 through 14 using the plant-specific as-built design information. In the following sections, the calculated numbers are rounded to nearest one-hundredth. A small variation in the rounded numbers may exist, which has no impact on the results of analyses. The dimensions in feet are converted into meters using a conversion factor of 1 meter = 3.28 feet.

CR Air Intake 7.1 Salem 1 MSSV Set 1 Releasc - Salem 1 CR1 Intake Yr/Qs The location of Salem I MSSV Set I with respect to CR1 air intake is shown in Figure 3 (Refs. 10.4.1, 10.11.1, 10.12.1, & 10.12.2). The Salem 1 MSSV Set I location with respect to CR1 air intake is such that the south wind will predominantly carry effluent from the MSSVs to the CR intake. The containment building cross-sectional area perpendicular to a south wind is considered for the wake diffusion.

Spring line elevation of cylindrical section of containment building = 218'-0" (Ref. 10.5.3)

Grade elevation= 99'-6" (Ref. 10.5.3)

Height of the containment building cylindrical section = 21 8'-O" - 99'-6" = 11 8'-6" Diameter of containment building cylindrical section = 2 x (70'-0" + 4'-6") = 149'-0" (Ref. 10.5.3)

Cross-sectional area of the containment building cylindrical section = diameter x height

= 149'-0" x 118'-6" = 17656.5 ft2 = 1641.18 m2 Top elevation of the containment building dome = 291 '-6" (Ref. 10.5.3)

Containment building dome height above spring line = 291 '-6" - 218'-0" = 73'-6" Containment building dome radius above spring line = 70'-0" + 3'-6" = 73'-6" (Ref. 10.5.3) Since the Containment Dome Radius is equivalent to the Containment Dome Height, the projected containment dome cross-sectional area is that of a semi-circle

= [(1/2) x 7t x Radius x Radius] = (3.14/2) x 73.5' x 73.5 = 8481.53 ft2 788.36 m2 Total cross-section area of the containment building cylindrical section and dome:

- 1641.18 m2 + 788.36 m2 = T2M9 T2Mi2 Nuclear Common Revision 9

CALCULATION CONTINUATION SHEET SHEET 21 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE IREV:

09/22/03 0

l l

M. Drucker/NUCORE, REVIEWERIVERI FI ER, DATE 09/24/03 This containment building wake area is used in the following Sections 7.1 through 7.8.

The MSSV Sets I & 2 north of Unit I and south of Unit 2 are analyzed for x/Qs due to their proximities to the Unit I & Unit 2 CR air intakes.

Top elevation of MSSV vent pipe = 147'-0" (Refs. 10.11.1 & 10.11.2)

Grade elevation = 99'-6" (Ref. 10.5.3)

Height of MSSV Sets I & 2 release = 147'-0" - 99'-6" =

.m. This release point height is typically applied to all MSSV release points in the following sections.

East-West Distance between centerlines of containment and CR1 Intake = East-west distance between containment centerline (Row FF) and Row GG (Ref. 10.12.5) - Distance between Row GG and centerline of CRI Intake (Ref. 10.4.1)

= 20'-0" - (1'- 7-1/2") = 18'-4-1/2" = 18.38' East-west distance between centerlines of containment and MSSV 15/16" (Ref. 10.11.1) = 0.078' East-west distance between centerlines of CRI intake and MSSV

= 18.38' - 0.078'= 18.30' North-south distance between CRI intake (Column 11.8) and containment centerline = 97'-6" (Ref. 10.11.1)

North-south distance between centerlines of containment and MSSV is approximately

84'- 2" + 3'-2-3/8" (Ref. 10.11.1) = 87'-4-3/8" North-south distance between CRI Intake and centerline of MSSV is approximately 97'-6" - 87'-4-3/8" = 10'-1-5/8" = 10.14' Straight line distance between MSSV Set 1 and CR1 intake = [(18.30 )2+ (1 0.14')2]In

Elevation of CR1 air intake = 128'-11" + 1'-4-1/2" (Ref. 10.12.5) = 130'- 3-1/2" = 130.29' Grade Elevation = 99'-6" (Ref. 10.5.3)

Height of CR1 air intake = 130.29' - 99.50' = Of =.9T9m This Unit I CR air intake height is typically used for CR1 X/Qs in the following sections.

MSSV Set I centerline direction with respect to CR1 intake Tan 0 = 18.30'/10.14' = 1.805, Therefore 0 = Tan' 1.805 = 61.010 Nuclear Common Revision 9

CALCULATION CONTINUATION SHEET SHEET 22 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. PatelINUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker/NUCORE, REVIEWERIVERIFIER, DATE 09i24/03 Orientation of MSSV Set 1 release with respect to CRI air intake, considering south wind 1800 and true north wind 3600 (Ref. 10.2, page 16), and that plant north is 50-30'-01" east of true north [with 60 minutes per degree]

(Ref. 10.7).

Orientation = I800 - 61.010 - 5.5°= :__

Unit I MSSV Set 1 X/Qs are calculated as ground level releases, then reduced by a factor of 5 as allowed by RG 1.194 Section 6 for uncapped and vertically oriented high velocity releases.

7.2 Salem 1 MSSV Set 1 Release - Salem 2 CR2 Intake y/Qs The location of Salem I MSSV Set 1 with respect to CR2 air intake is shown in Figure 4 (Refs. 10.4.2, 10.11.1, 10.12.1, & 10.12.2). The MSSV Set 1 location with respect to CR2 air intake is such that the south wind will predominantly carry effluent from the MSSV release to the CR2 intake. The containment building cross-sectional area perpendicular to a south wind is considered for the wake diffusion.

East-West Distance between centerlines of containment and CR2 Intake:

East-west distance between containment centerline (Row FF) and Row GG (Ref. 10.12.5) - Distance between Row GG and centerline of CR2 Intake (Ref. 10.4.2)

= 20'-0" -(1'- 7-1/2") = 18'-4-1/2" = 18.38' East-west distance between centerlines of containment and MSSV

= 15/16" (Ref. 10.11.2) = 0.078' East-west distance between centerlines of CR2 intake and MSSV

= 18.38'-0.078'= 18.30' North-south Distance between CR Intakes (CR1 and CR2) = Distance between Columns 11.5 and 16.2

= 2 x (13'-6" + 21 '-0" + 22'-0" + 6'-0") (Ref 10.5.1) = 2 x (62'-6") = 125'-0" North-south Distance between CR2 Intake and MSSV Set I = North-south distance between CR2 and CR1 intakes + distance between CR1 intake and centerline of MSSV Set I (per Section 7.1)

= 125'-0"+ 10'-l-5/8"= 135'-l-5/8"= 135.14' Straight line distance between MSSV Set I and CR2 intake = [(I8.30 )2+ (13 5.14')2]l =.3flT g}9 Elevation of CR2 air intake = 128'-0-3/4" + 1'-4-1/2" (Ref. 10.12.5) = 129'- 5-1/4" = 129.44' Grade elevation = 99'-6" (Ref. 10.5.1)

Nuclear Common Revision 9

I I CALCULATION CONTINUATION SHEET SHEET 23 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 l

~G. PateM/UCORE,_l ORIGINATOR, DATE J REV:

09/22/03 0

M. Drucker/NUCORE, REVIEWER/VERIFIER, DATE 09/24/03 Height of CR2 air intake = 129.44 - 99.50' = P This Unit 2 CR air intake height is typically used for CR2 x/Qs in the following sections.

Height of MSSV Set 1 release =

(Section 7.1)

MSSV Set I centerline direction with respect to CR2 intake Tan 0 = 18.30'/135.14' = 0.135, Therefore 0 = Tan-' 0.135 = 7.690 Orientation of MSSV Set 1 release with respect to CR2 air intake, considering south wind 1800 and true north wind 3600 (Ref. 10.2, page 16), and that plant north is 5°-30'-01" east of true north [with 60 minutes per degree]

(Ref. 10.7).

Orientation = 180° - 7.690 - 5.5°= =LM Unit 1 MSSV Set 1 x/Qs are calculated as ground level releases, then reduced by a factor of 5 as allowed by RG 1.194 Section 6 for uncapped and vertically oriented high velocity releases.

7.3 Salem I MSSV Set 2 Relcase - Salem 1 CR1 Intake y/Qs The location of Salem 1 MSSV Set 2 with respect to CR1 air intake is shown in Figure 5 (Refs. 10.4.1, 10.11.1, 10.12.1, & 10.12.2). The Salem 1 MSSV Set 2 location with respect to CR1 air intake is such that the south wind will predominantly carry effluent from the MSSVs to the CR intake.

North-south distance between CR1 intake (Column 11.8) and containment centerline = 97'-6" (Ref. 10.11.1)

North-south distance between containment and MSSV Set 2 centerline

= 79'-2" + 3'-2-3/8" (Ref. 10.11.1) = 82'-4-3/8" North-south distance between CR1 Intake and centerline of MSSV Set 2

= 97'-6" - 82'-4-3/8" = 15'-1-5/8" = 15.14' East-West Distance between centerlines of containment and CR1 Intake= 18.38' (Section 7.1)

East-west distance between centerlines of containment and MSSV Set 2

= 21 '-7-1/4" + 6-1/16" (Ref. 10.11.1) 22'-1-5/16" = 22.11' East-west distance between centerlines of CR1 intake and MSSV Set 2

= 18.38' + 22.11' =40.49' Straight line distance between MSSV Set 2 and CR1 intake = [(40.49 )2+ (15.14')2]1 =1 Height of CR1 air intake = [Nazi (Section 7.1)

Nuclear Common Revision 9

l CALCULATION CONTINUATION SHEET lSHEET 24of 66l CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker/NUCORE, REVIEWER/VERIFIER, DATE 09/24/03 Height of MSSV Set 2 release = p!'8;im (Section 7.1)

MSSV Set 2 centerline direction with respect to CR1 intake Tan 0 = 40.49'/15.14' = 2.674, Therefore 0 = Tan'l 2.674 = 69.50 Orientation of MSSV Set 2 release with respect to CR1 air intake, considering south wind 1800 and true north wind 3600 (Ref. 10.2, page 16), and that plant north is 50-30'-01" east of true north [with 60 minutes per degree]

(Ref. 10.7).

Orientation = 180° - 69.5° - 5.5°= R°T Unit 1 MSSV Set 2 yjQs are calculated as ground level releases, then reduced by a factor of 5 as allowed by RG 1.194 Section 6 for uncapped and vertically oriented high velocity releases.

7.4 Salem 1 MSSV Set 2 Release - Salem 2 CR2 Intake The location of Salem 1 MSSV Set 2 with respect to CR2 air intake is shown in Figure 6 (Refs. 10.4.2, 10.11.1, 10.12.1, & 10.12.2). The MSSV Set 2 location with respect to CR2 air intake is such that the south wind will predominantly carry effluent from the MSSV release to the CR2 intake.

CR2 air intake height = 9.13 m (Section 7.2)

East-West Distance between centerlines of containment and CR2 Intake = 18.38' (Section 7.2)

East-west distance between centerlines of containment and MSSV Set 2

= 21 '-7-1/4" + 6-1/16" (Ref. 10.11.2) = 22'-1-5/16" = 22.11' East-west distance between centerlines of CR2 intake and MSSV Set 2

= 18.38' +22.11' =40.49' North-south Distance between CR Intakes (CR1 and CR2) = 125'-0" (Section 7.2)

North-south distance between CR1 Intake and centerline of MSSV Set 2 = 15'-1-5/8" (Section 7.3)

North-south Distance between CR2 Intake and MSSV Set 2 = North-south distance between CR2 and CR1 intakes + north-south distance between CR1 intake and centerline of MSSV Set 2

= 125'-0" + 15'-1-5/8" = 140'-1-5/8" =140.14' Straight line distance between MSSV Set 2 and CR2 intake = [(40.49')2 + (140.14')2]Ii

=

R Height of CR2 air intake = [97' (Section 7.2)

Height of MSSV Set 2 release = r4 (Section 7.1)

Nuclear Common Revision 9

CALCULATION CONTINUATION SHEET SHEET 25 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. DruckerfNUCORE, REVIEWER/VERIFI ER, DATE 09/24/03 MSSV Set 2 centerline direction with respect to CR2 intake Tan 0 = 40.49'/140.14' = 0.289, Therefore 0 = Tan-' 0.289 = 16.120 Orientation of MSSV Set 2 cluster release with respect to CR2 air intake, considering south wind 1800 and true north wind 3600 (Ref. 10.2, page 16), and that plant north is 50-30'-01" east of true north [with 60 minutes per degree] (Ref. 10.7).

Orientation = 180° - 16.120 - 5.50 =f58;° Unit 1 MSSV Set 2 X/Qs are calculated as ground level releases, then reduced by a factor of 5 as allowed by RG 1.194 Section 6 for uncapped and vertically oriented high velocity releases.

7.5 Salem 2 MSSV Set 1 Rclease - Salem 2 CR2 Intake y/Qs The location of Salem 2 MSSV Set 1 with respect to CR2 air intake is shown in Figure 7 (Refs. 10.4.2, 10.11.2, 10.12.1, & 10.12.2). The Salem 2 MSSV Set 1 location with respect to CR2 air intake is such that the north wind will predominantly carry effluent from the MSSVs to the CR intake. Figure 7 is a mirror image of Figure 3 except for the source/receptor orientation. The distance to receptor, release point height, and wake area are the same as those tabulated underneath Figure 3 except for the CR intake height and the source/receptor orientation, which is calculated as follows:

Height of CR2 air intake = [LS5m (Section 7.2)

Height of MSSV Set I release =048- (Section 7.1)

Unit 2 MSSV Set I centerline direction with respect to CR2 intake Tan 0 = 18.30'/l0.14' = 1.805, Therefore 0 = Tan-' 1.805 = 61.010 Orientation of MSSV Set I release with respect to CR2 air intake, considering south wind 1800 and true north wind 3600 (Ref. 10.2, page 16), and that plant north is 50-30'-01" east of true north [with 60 minutes per degree]

(Ref. 10.7).

Orientation = 61.010 - 5.5=

Unit 2 MSSV Set I yJQs are calculated as ground level releases, then reduced by a factor of 5 as allowed by RG 1.194 Section 6 for uncapped and vertically oriented high velocity releases.

Nuclear Common Revision 9

CALCULATION CONTINUATION SHEET SHEET 26 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker/NUCORE, REVIEWVER/VERIFIER, DATE 09/24/03 7.6 Salem 2 MSSV Set 1 Release - Salem 1 CR1 Intake,/Qs The location of Salem 2 MSSV Set 1 with respect to CR1 air intake is shown in Figure 8 (Refs. 10.4.1, 10.11.2, 10.12. 1, & 10.12.2). The Salem 2 MSSV Set 1 location with respect to CR1 air intake is such that the north wind will predominantly carry effluent from the MSSVs to the CR intake. Figure 8 is a mirror image of Figure 4 except for the source/receptor orientation. The distance to receptor, release point height, and wake area are same as those tabulated underneath Figure 4 except for the CR intake height and the source/receptor orientation, which is calculated as follows:

Height of CR1 air intake [v9E (Section 7.1)

Height of MSSV Set I release=

(Section 7.1)

Unit 2 MSSV Set I centerline direction with respect to CR1 intake Tan 0 = 18.30'/135.14' = 0.135, Therefore 0 = Tan" 0.135 = 7.69° Orientation of Unit 2 MSSV Set 1 release with respect to CR1 air intake, considering south wind 1800 and true north wind 3600 (Ref. 10.2, page 16), and that plant north is 50-30'-01"? east of true north [with 60 minutes per degree] (Ref. 10.7).

Orientation = 7.690 - 5.50 =

t Unit 2 MSSV Set I X/Qs are calculated as ground level releases, then reduced by a factor of 5 as allowed by RG 1.194 Section 6 for uncapped and vertically oriented high velocity releases.

7.7 Salem 2 MSSV Set 2 Release - Salem 2 CR2 Intake ZIQs The location of Salem 2 MSSV Set 2 with respect to CR2 air intake is shown in Figure 9 (Refs. 10.4.2, 10.11.2,

10. 12. 1, & 10. 12.2). The Salem 2 MSSV Set 2 location with respect to CR2 air intake is such that the north wind will predominantly carry effluent from the MSSVs to the CR intake. Figure 9 is a mirror image of Figure 5 except for the source/receptor orientation. The distance to receptor, release point height, and wake area are same as those tabulated underneath Figure 5 except for the CR intake height and the source/receptor orientation, which is calculated as follows:

Height of CR2 air intake = Audi (Section 7.2)

Height of MSSV Set 2 release =.148m (Section 7.1)

Unit 2 MSSV Set 2 centerline direction with respect to CR2 intake Nuclear Common Revision 9

z CALCULATION CONTINUATION SHEET SHEET 27 of66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCRS03-05 G. Patel/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker/NUCORE, REVIEWERIVERIFI ER, DATE 09/24/03 Tan 0 = 40.49'/15.14' = 2.674, Therefore 0 = Tan"l 2.674 = 69.500 Orientation of Unit 2 MSSV Set 2 release with respect to CR2 air intake, considering south wind 1800 and true north wind 3600 (Ref. 10.2, page 16), and that plant north is 50-30'-01" east of true north [with 60 minutes per degree] (Ref. 10.7).

Orientation = 69.500 - 5.5° =4° Unit 2 MSSV Set 2 X/Qs are calculated as ground level releases, then reduced by a factor of 5 as allowed by RG 1.194 Section 6 for uncapped and vertically oriented high velocity releases.

7.8 Salem 2 MSSV Set 2 Release - Salem 1 CR1 Intake y/Qs The location of Salem 2 MSSV Set 2 with respect to CR1 air intake is shown in Figure 10 (Refs. 10.4.1,.

10.11.2, 10.12.1, & 10.12.2). The Salem 2 MSSV Set 2 location with respect to CR1 air intake is such that the north wind will predominantly carry effluent from the MSSVs to the CR intake. Figure 10 is a mirror image of Figure 6 except for the source/receptor orientation. The distance to receptor, release point height, and wake area are same as those tabulated underneath Figure 6, except for the CR intake height and the source/receptor orientation, which is calculated as follows:

Height of CR1 air intake = [93'q (Section 7.1)

Height of MSSV Set 2 release = EA`1 'iT (Section 7.1)

Unit 2 MSSV Set 2 centerline direction with respect to CR1 intake Tan 0 = 40.49'/140.14' = 0.289, Therefore 0 = Tan-' 0.289 = 16.120 Orientation of Unit 2 MSSV Set 2 cluster release with respect to CR1 air intake, considering south wind 1800 and true north wind 3600 (Ref. 10.2, page 16), and that plant north is 5°-30'-01 " east of true north [with 60 minutes per degree] (Ref. 10.7).

Orientation= 16.120 - 5.5° =

0.°L-62 Unit 2 MSSV Set 2 x/Qs are calculated as ground level releases, then reduced by a factor of 5 as allowed by RG 1.194 Section 6 for uncapped and vertically oriented high velocity releases.

Nuclear Common Revision 9

I CALCULATION CONTINUATION SHEET SHEET 28 of 66 l

I CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 gG.

Patel/NUCORE, ORIGINATOR, DATE IREV:

09/22/03 0

M. Drucker/NUCORE, REVI EWERIVERI FI ER, DATE 09/24/03 7.9 Salem 1 Penctration Area Pressure Relief Panel (PAPRP) Release - Salem 1 CR1 Intake y/Qs The locations of Salem Units 1 & 2 penetration area pressure relief panels (PAPRPs) with respect to CRI and CR2 air intakes are shown in Figures 11 and 12 (Refs. 10.4, 10.12.2 through 10.12.4). The locations of PAPRPs with respect to CR air intakes are such that the east wind will predominantly carry effluent from the PAPRPs to the CR intakes. The turbine building (TB) cross-sectional area perpendicular to east wind is considered for the wake diffusion.

The extreme north edge of the Unit 1 PAPRP is located at Column 10.2 (Refs. 10.5.1 & 10.12.4). The extreme south edge of the Unit 2 PAPRP is located at Column 17.8 (Refs. 10.5.1 & 10.12.4).

Width of TB between Columns 10.2 & 17.8 = 206.0' (Ref. 10.5.1)

Grade elevation = 99'-6" (Ref. 10.5.3)

Roof elevation of TB = 140'-0" (Ref. 10.5.3)

Height of TB = 140'-0" - 99'-6" = 40'-6" = 40.5' Cross-sectional area of TB contributing wake diffusion to PAPRP releases

= 206.0' x 40.5' = KK343 fi7.75 This wake area is used in the following Sections 7.9 through 7.12.

PAPRP size = 28'-6" x 1 1'-6" (Refs. 10.12.3 & 10.12.4)

East-west distance between centerlines of Units 1 and 2 containments and PAPRPs

= Distance between Rows FF and DC + Distance between Rows DC and BA

= 44'-6" (Ref. 10.12.2) + (8'-3" + 8'-3" + 15'-0") (Ref. 10.12.3) = 44'-6" + 31'-6" = 76'-0" East-West Distance between centerlines of Units 1 and 2 containment and CR1 Intake = 18.38' (Section 7.1)

East-west distance between centerlines of Unit 1 CR1 and PAPRPs

= Distance between centerlines of Units I and 2 containments and PAPRPs + Distance between centerlines of containment and CR1 intake

= 76'-0" + 18.38' = 94.38' North-south distance between centerlines of CR1 intake and PAPRP

= Distance between Columns 11.8 and 11.2 - Distance between Column 11.2 and north edge of PAPRP + 1/2 width of PAPRP

= 15-6" - 4'-9" + (28'-6")/2 (Ref. 10.12.3 & 10.12.4) = 25'-0" Nuclear Common Revision 9

CALCULATION CONTINUATION SHEET SHEET 29 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker/NUCORE, REVIEWER/VERIFIER, DATE 09/24/03 Straight line distance between PAPRP and CR1 intake = [(25.0')2 + (9 4.3 8g)]

Height of CRI air intake = Pi (Section 7.1)

Centerline elevation of PAPRP = 123'-0" + 1/2 (11 '-6") (Ref. 10.12.3) = 128.75' Grade elevation = 99'-6" (Ref. 10.5.3)

Height of PAPRP release point = 128.75 - 99.5' (10.5.3) =

This PAPRP release height is typically used in the following sections.

PAPRP direction with respect to CR1 intake Tan 0 = 94.38'/25' =3.775, Therefore 0 = Tan-' 3.775 = 75.16° Orientation of PAPRP release with respect to CR1 air intake, considering south wind 1800 and true north wind 3600 (Ref. 10.2, page 16), and that plant north is 50-30'-01" east of true north [with 60 minutes per degree] (Ref.

10.7).

Orientation = 1800 - 75.160 -

5° Effective height of PAPRP = 1 '-6" (Ref. 10.12.3) = 3.51 m Effective width of PAPRP = 28'-6" (Ref. 10.12.3) = 8.69 m Vertical diffusion coefficient a, = Effective height /6 (Ref. 10.3, Section 2.2.4.4) = 3.51 m /6

Horizontal diffusion coefficient cy = Effective width / 6 (Ref. 10.3, Section 2.2.4.4) = 8.69 m / 6 =E448m Unit I PAPRP release is assumed to be a ground level point source.

7.10 Salem 1 PAPRP Rclcase - Salem 2 CR2 Intake y/Qs The location of Salem I PAPRP with respect to CR2 air intake is shown in Figure 11 (Refs. 10.4.2, 10.12.2 through 10.12.4). The ARCON96 input parameters for the source/receptor geometry in Figure 11 are calculated as follows:

East-west distance between centerlines of Units I and 2 containments and PAPRPs = 76'-0" (Section 7.9)

East-West Distance between centerlines of Units I and 2 containment and CR2 Intake = 18.38' (Section 7.2)

East-west distance between centerlines of Unit 2 CR2 and PAPRPs

= Distance between centerlines of Units I and 2 containments and PAPRPs + Distance between centerlines of containment and CR2 intake

= 76'-0" + 18.38' = 94.38' Nuclear Common Revision 9

CALCULATION CONTINUATION SHEET SHEET 30 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 l

G. Patel/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker/NUCORE, REVIEWERVNERIFIER, DATE 09/24/03 North-south distance between centerlines of CR1 intake and PAPRP = 25'-0" (Section 7.9)

North-south distance between CR Intakes (CR1 and CR2) = 125'-0" (Section 7.2)

North-south distance between centerlines of CR2 intake and PAPRP

= Distance between centerlines of CR1 intake and PAPRP + Distance between centerlines of CR1 and CR2 intakes

=25'-0" + 125'-0" = 150'-0" Straight line distance between PAPRP and CR1 intake = [(94.38n)2+ (1 5 0.0)2fl2 =;

Height of CR2 air intake = A.*

(Section 7.2)

Height of PAPRP release =

(Section 7.9)

PAPRP direction with respect to CR2 intake Tan 0 = 94.38'/150' = 0.629, Therefore 0 = Tan-' 0.629 = 32.170 Orientation of PAPRP release with respect to CR2 air intake, considering south wind 1800 and true north wind 3600 (Ref. 10.2, page 16), and that plant north is 5

°-30'-0 east of true north [with 60 minutes per degree] (Ref.

10.7).

Orientation = 1800 - 32.170 - 5.50 =

Vertical diffusion coefficient a, =

(Section 7.9)

Horizontal diffusion coefficient ay = _8-im (Section 7.9)

Unit 1 PAPRP release is assumed to be a ground level point source.

7.11 Salem 2 PAPRP Release - Salem 2 CR2 Intake X/Qs The location of Salem 2 PAPRP with respect to CR2 air intake is shown in Figure 12 (Refs. 10.4.2, 10.12.2 through 10.12.4). The Salem 2 PAPRP location with respect to CR2 air intake is such that the east wind will predominantly carry effluent from the PAPRP to the CR intake. The source/receptor geometry for Unit 2 PAPRP/CR2 intake is a mirror image of the source/receptor geometry for Unit 1 PAPRP/CRI (see Figures 11 &

12). The distance to receptor, release point height, and wake area are same as those tabulated underneath Figure I I for Unit I PAPRP/CRI except for the CR intake height and the source/receptor orientation, which is calculated as follows:

Height of CR2 air intake =

-137M (Section 7.2)

Nuclear Common Revision 9

I CALCULATION CONTINUATION SHEET ISHEET 31 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker/NUCORE, REVIEWERNVERIFIER, DATE 09/24/03 Height of PAPRP release =

(Section 7.9)

PAPRP direction with respect to CR2 intake Tan 0 = 94.38'/25' =3.775, Therefore 0 = Tan-' 3.775 = 75.160 Orientation of PAPRP release with respect to CR2 air intake, considering south wind 1800 and true north wind 3600 (Ref. 10.2, page 16), and that plant north is 50-30'-01" east of true north [with 60 minutes per degree] (Ref.

10.7).

Orientation = 75.160 - 5.5° = By_

Vertical diffusion coefficient ca, =

(Section 7.9)

Horizontal diffusion coefficient ay =

(Section 7.9)

Unit 2 PAPRP release is assumed to be a ground level point source.

7.12 Salem 2 PAPRP Release - Salem 1 CR1 Intake y/Qs The location of Salem 2 PAPRP with respect to CR1 air intake is shown in Figure 12 (Refs. 10.4.1, 10.12.2 through 10.12.4). The Salem 2 PAPRP location with respect to CR1 air intake is such that the east wind will predominantly carry effluent from the PAPRP to the CR intake. The source/receptor geometry for Unit 2 PAPRP/CRI intake is a mirror image of the source/receptor geometry for Unit 1 PAPRP/CR2 (see Figures 11 &

12). The distance to receptor, release point height, and wake area are same as those tabulated underneath Figure 11 for Unit I PAPRP/CR2 except for the CR intake height and the source/receptor orientation, which is calculated as follows:

Height of CR2 air intake = T39 (Section 7.1)

Height of PAPRP release = E9m- (Section 7.9)

PAPRP direction with respect to CR1 intake Tan 0 = 94.38'/l 50' = 0.629, Therefore 0 = Tan-' 0.629 = 32.170 Orientation of PAPRP release with respect to CR1 air intake, considering south wind 1800 and true north wind 3600 (Ref. 10.2, page 16), and that plant north is 50-30'-01" east of true north [with 60 minutes per degree] (Ref.

10.7).

Orientation = 32.17° - 5.50 = V.L7'u Vertical diffusion coefficient a, =

8 (Section 7.9)

Nuclear Common Revision 9

CALCULATION CONTINUATION SHEET SHEET 32 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker/NUCORE, REVIEWER/VERIFIER, DATE 09/24/03 Horizontal diffusion coefficient ay = ;'448fn (Section 7.9)

Unit 2 PAPRP release is assumed to be a ground level point source.

7.13 Salem 1 Smoke Hatch Release-Salem 1 CR1 Intake y/Qs The locations of Salem Units 1 smoke hatch with respect to CR1 and CR2 air intakes are shown in Figure 13 (Refs. 10.4 & 10.16). The locations of the smoke hatches with respect to the CR air intakes are such that the west wind will predominantly carry effluent from the smoke hatches to the CR intakes. The fuel handling building (FHB) cross-sectional area perpendicular to a west wind is considered for the wake diffusion.

Width of FHB = 106'-7" = 106.58' (Refs. 10.19.1 & 10.19.3)

Minimum roof elevation of FHB = 165'-O" (Refs. 10.19.2 & 10.19.4)

Grade elevation = 99'-6" (Ref. 10.5.3)

Height of FHB = 165'-0" - 99'-6" = 65'-6" = 65.5' Cross-sectional area of FHB contributing wake diffusion to Smoke Hatch releases

= 106.58' x 65.5' = 6 This wake area is used in the following Sections 7.9 through 7.12.

Smoke hatch size =5'-O" x 5'-O" (Refs. 10.16.1 & 10.16.3 Sections 11-11 and 12-12)

East-west distance between centerlines of containment and Unit 1 smoke hatch

= Distance between Rows FF and KK - Distance between KK and west edge of roof over fuel bldg (FB) access

- Distance between west edge of FB access roof and centerline of smoke hatch

(4 x 20'-0") (Ref. 10.16.1) - 3'-6" (Ref. 10.16.1) - (3'-4-1/2" + [5'-0"]/2) (Ref. 10.16.3) = 70'- 7-1/2"

70.625' East-West Distance between centerlines of containment and CR1 Intake = 18.38' (Section 7.1)

East-west distance between centerlines of CR1 intake and Unit 1 smoke hatch

= Distance between centerlines of containment and Unit I smoke hatch - Distance between centerlines of containment and CR1 intake

= 70.625' - 18.38' = 52.245' North-south distance between centerlines of CR1 intake and smoke hatch Nuclear Common Revision 9

l_CALCULATION CONTINUATION SHEET SHEET 33 or 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 l

~G. Patel/NUCORE,l ORIGINATOR, DATE IREV:

09/22/03 O

M. Drucker/NUCORE, REVIEWER/VERIFIER, DATE 09/24/03

= Distance between Columns 11.8 and 10.4 - Distance between Columnl 0.4 and centerline of Unit 1 smoke hatch

(15'-6" + 18'-0") (Ref. 10.16.1) + (15'-3" + [5'-0"]/2 - 1 '-6") (Ref. 10.16.3) = 33'-6" + 16'-3" = 49'-9"

49.75' Straight line distance between Unit I smoke hatch and CR1 intake = [(52.245 )2 + (49.75 ')2]!I

EEfI 2 199YE.i Height of CR1 air intake

(Section 7.1)

Top elevation of Unit I and Unit 2 smoke hatches = 142'-0" (Ref. 10.16.3, Section F)

Grade elevation = 99'-6" (Ref. 10.5.3)

Height of smoke hatch release point = 142'-0" - 99.5' =

This smoke hatch release height is typically used in the following sections.

Unit 1 smoke hatch direction with respect to CR1 intake Tan 0 = 52.245'/49.75' = 1.05, Therefore 0 = Tan-' 1.05 = 46.400 Orientation of smoke hatch release with respect to CR1 air intake, considering south wind 1800 and true north wind 3600 (Ref. 10.2, page 16), and that plant north is 50-30'-01" east of true north [with 60 minutes per degree]

(Ref. 10.7).

Orientation = 1800 + 46.400 - 5.5 =

° Unit I smoke hatch release is assumed to be a ground level point source.

7.14 Salem 1 Smokc Hatch Rclease - Salem 2 CR2 Intakc y/Qs The location of Salem Unit 1 smoke hatch with respect to the CR2 air intake is shown in Figure 13 (Refs. 10.4.2

& 10.16) and a southwest wind will predominantly carry effluent from the Unit I smoke hatch to the CR2 intake. The ARCON96 input parameters for the source/receptor geometry in Figure 13 are calculated as follows:

East-west distance between centerlines of containment and Unit 1 smoke hatch = 70.625' (Section 7.13)

East-West Distance between centerlines of containment and CR2 Intake = 18.38' (Section 7.2)

East-west distance between centerlines of CR2 intake and Unit I smoke hatch Nuclear Common Revision 9

I CALCULATION CONTINUATION SHEET SHEET 33 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05

~G. Patel/NUCORE,.

ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker/NUCORE, REVIEWER/VERIFIER, DATE 09/24/03

Distance between Columns 11.8 and 10.4 - Distance between Column 10.4 and centerline of Unit 1 smoke hatch (I 5'-6" + 1 8'-0") (Ref. 10.16.1) + (15'-3" + [5'-0"]/2 - 1'-6") (Ref. 10.16.3) = 33'-6" + 16'-3" =49'-9"

49.752 Straight line distance between Unit 1 smoke hatch and CR1 intake = [(52.245')2 + (49.75X)2]1I2 Height of CR1 air intake =

(Section 7.1)

Top elevation of Unit 1 and Unit 2 smoke hatches = 142'-0" (Ref. 10.16.3, Section F)

Grade elevation = 99'-6" (Ref. 10.5.3)

Height of smoke hatch release point = 142'-0" - 99.5'==

This smoke hatch release height is typically used in the following sections.

Unit I smoke hatch direction with respect to CR1 intake Tan 0 = 52.245'/49.75' = 1.05, Therefore 0 = Tan-' 1.05 = 46.40° Orientation of smoke hatch release with respect to CR1 air intake, considering south wind 1800 and true north wind 3600 (Ref. 10.2, page 16), and that plant north is 50-30'-01" east of true north [with 60 minutes per degree]

(Ref. 10.7).

Orientation = 1800 + 46.400 - 5.50 =

Unit I smoke hatch release is assumed to be a ground level point source.

7.14 Salem 1 Smoke Hatch Release-Salem 2 CR2 Intake y/Qs The location of Salem Unit I smoke hatch with respect to the CR2 air intake is shown in Figure 13 (Refs. 10.4.2

& 10.16) and a southwest wind will predominantly carry effluent from the Unit 1 smoke hatch to the CR2 intake. The ARCON96 input parameters for the source/receptor geometry in Figure 13 are calculated as follows:

East-west distance between centerlines of containment and Unit I smoke hatch = 70.625' (Section 7.13)

East-West Distance between centerlines of containment and CR2 Intake = 18.38' (Section 7.2)

East-west distance between centerlines of CR2 intake and Unit I smoke hatch Nuclear Common Revision 9

X7 CALCULATION CONTINUATION SHEET SHEET 34 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE jREV:

09/22/030 M. Drucker/NUCORE, REVIEWER/VERIFIER, DATE 09/24/03 Distance between centerlines of containment and Unit 1 smoke hatch - Distance between centerlines of containment and CR2 intake

= 70.625' - 18.38' = 52.245' North-south distance between centerlines of CR2 intake and Unit 1 smoke hatch Distance between centerlines of CR1 intake and Unit 1 smoke hatch + Distance between centerlines of CR1 and CR2 intakes = 49.75' (Section 7.13) + 125.0' (Section 7.2) = 174.75' Straight line distance between Unit 1 smoke hatch and CR2 intake = [(52.245 )2 + 74.75')]

=J 5

Height of CR2 air intake =

3 (Section 7.2)

Height of smoke hatch release = A X62 (Section 7.13)

Unit 1 smoke hatch direction with respect to CR2 intake Tan 0 = 52.245'/174.75' = 0.299, Therefore 0 = Tan' 0.299 = 16.650 Orientation of Unit 1 smoke hatch release with respect to CR2 air intake, considering south wind 1800 and true north wind 3600 (Ref. 10.2, page 16), and that plant north is 50-30'-01" east of true north [with 60 minutes per degree] (Ref. 10.7).

Orientation = 1800 + 16.650 - 5.5 =

Unit I smoke hatch release is assumed to be a ground level point source.

7.15 Salem 2 Smoke Hatch Release - Salem 2 CR2 Intake y/Qs The location of the Salem 2 smoke hatch with respect to the CR2 air intake is shown in Figure 14 (Refs. 10.4.2

& 10.16). The Salem 2 smoke hatch location with respect to the CR2 air intake is such that the west wind will predominantly carry effluent from the Unit 2 smoke hatch to the CR2 intake. The source/receptor geometry for Unit 2 smoke hatch/CR2 intake is a mirror image of the source/receptor geometry for Unit 1 smoke hatch/CRI (see Figures 13 & 14). The distance to receptor, release point height, and wake area are the same as those tabulated underneath Figure 13 for Unit I smoke hatch/CR1 except for the CR intake height and the source/receptor orientation, which is calculated as follows:

Height of CR2 air intake = E1 -'3 (Section 7.2)

Height of smoke hatch release =

9 2

I (Section 7.13)

Nuclear Cnmmnn

CALCULATION CONTINUATION SHEET SHEET 35 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. PatelVNUCORE, ORIGINATOR, DATE REV:

09/22/03 l0 M. Drucker[NUCORE, REVIEWER/VERIFIER, DATE 09/24/03 Unit 2 smoke hatch direction with respect to CR2 intake Tan 0 = 52.245'/49.75' = 1.05, Therefore 0 = Tan-' 1.05 = 46.400 Orientation of Unit 2 smoke hatch release with respect to CR2 air intake, considering south wind 1800 and true north wind 3600 (Ref. 10.2, page 16), and that plant north is 50-30'-01" east of true north [with 60 minutes per degree] (Ref. 10.7).

Orientation = 3600 - 46.400 - 5.50 = --

ES Unit 2 smoke hatch release is assumed to be a ground level point source.

7.16 Salem 2 Smoke Hatch Release - Salem 1 CR1 Intake X/Qs The location of the Salem 2 smoke hatch with respect to the CR1 air intake is shown in Figure 14 (Refs. 10.4.1

& 10.16). The Salem 2 smoke hatch location with respect to the CR1 air intake is such that the northwest wind will predominantly carry effluent from the Unit 2 smoke hatch to the CR1 intake. The source/receptor geometry for Unit 2 smoke hatch/CRI intake is a mirror image of the source/receptor geometry for Unit I smoke hatch/CR2 (see Figures 13 & 14). The distance to receptor, release point height, and wake area are same as those tabulated underneath Figure 13 for Unit 1 smoke hatch/CR2 except for the CR intake height and the source/receptor orientation, which is calculated as follows:

Height of CR1 air intake = L9 mi (Section 7.1)

Height of smoke hatch release = Phi (Section 7.13)

Unit 2 smoke hatch direction with respect to CR1 intake Tan 0 = 52.245'/174.75' = 0.299, Therefore 0 = Tan' 0.299 = 16.650 Orientation of Unit 1 smoke hatch release with respect to CR2 air intake, considering south wind 1800 and true north wind 3600 (Ref. 10.2, page 16), and that plant north is 50-30'-01" east of true north [with 60 minutes per degree] (Ref. 10.7).

Orientation = 360° - 16.650 - 5.5°=' E 5

Unit 2 smoke hatch release is assumed to be a ground level point source.

Nuclear Common Revision 9

CALCULATION CONTINUATION SHEET SHEET 36 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker/NUCORE, REVIEWER/VERIFIER, DATE 09/24/03 7.17 Salem 2 Plant Vent Release - Hope Creek CR Intake yv/Qs The Salem 1 and 2 plant vents are on the same line-of-sight between the Salem and Hope Creek plants (Ref. 10.21). Salem 2 is closer to the HCGS plant, and an event that releases radioactivity to the environment from Salem 2 would have less dispersion to the Hope Creek air intake (and higher Hope Creek CR doses) than a similar event occurring at Salem 1. Therefore, this analysis conservatively calculates X/Q values for a Salem 2 plant vent release.

The location of the Salem 2 plant vent with respect to the HCGS CR air intake is shown in Figure 15 (Refs. 10.5

& 10.16). The Salem 2 plant vent location with respect to the HCGS CR air intake is such that the northwest wind will predominantly carry effluent from the Unit 2 plant vent to the HCGS CR intake. The ARCON96 input parameters for the source/receptor geometry in Figure 15 are calculated as follows:

Salem 2 containment building cross-sectional area perpendicular to a northwest wind is considered for the wake diffusion.

Wake diffusion area = 2429.54 m2 (Section 7.1)

The Salem 2 plant vent is centered atop the Salem 2 containment building. North-south distance between centerlines of Salem 2 and Hope Creek containment buildings

= N1037.5 (Ref. 10.21.2) + [S320 (Ref. 10.21.1) - (Distance between Columns 14 and 20.7) (Ref. 10.5.3)]

= 1037.5' + [320' - 160'-0"] = 1197.5' North-south distance between centerlines of HCGS containment and HCGS CR air intake

= I I0'-0" (Ref. 10.20, page 14)

North-south distance between centerlines of Salem 2 plant vent and HCGS CR air intake

= North-south distance between centerlines of Salem 2 and Hope Creek containment buildings + Distance between centerlines of HCGS containment and HCGS CR air intake = 1197.5' + 1 0'-0" = 1307.5' East-west distance between centerlines of Salem 2 & Hope Creek containment (Ref. 10.21.1)

= W500 -W120 = 500'-0" - 120'-0" = 380'-0" East-west distance between centerlines of HCGS containment and HCGS CR intake

= 129'-0" (Ref. 10.20, page 14)

East-west distance between centerlines of Salem 2 plant vent and HCGS CR air intake Nuclear Common Revision 9

d-CALCULATION CONTINUATION SHEET SHEET 37 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 l

l G. PateM/UCORE,_

ORIGINATOR, DATE REV:

0912/03 O

M. Drucker/NUCORE, REVIEWER/VERIFI ER, DATE 09/24/03

= East-west distance between centerlines of Salem 2 and Hope Creek containment buildings + Distance between centerlines of HCGS containment and HCGS CR air intake = 380'-0" + 129'-0" = 509'-0" Straight line distance between Salem 2 plant vent and HCGS CR intake

[(1307.5')2+ (509')2]12

=Lr-4'0 ET 8Ft27.-9771-m

= A Elevation of HCGS CR air intake = 155'-5" (Ref. 10.21, page 27)

Grade Elevation at Salem 2 containment = 99'-6" (Ref. 10.5.3)

Height of HCGS CR air intake = 155'-5" - 99'-6" = 55'-1 1" =

9 Elevation of Salem 2 plant vent = 291'-6" (Ref. 10.5.3)

Height of Salem 2 plant vent = 291 '-6" - 99'-6" =

Salem 2 plant vent direction with respect to HCGS CR intake Tan 0 = 509'/l 307.5' = 0.3893, Therefore 0 = Tan" 0.3893 = 21.270 Orientation of SNGS Unit 2 plant vent release with respect to HCGS CR air intake, considering south wind 1800 and true north wind 3600 (Ref. 10.2, page 16), and that plant north is 50-30'-01" east of true north [with 60 minutes per degree] (Ref. 10.7).

Orientation = 180° - 21.270 - 5.50

[f*3-3 0 Salem 2 plant vent release is assumed to be a ground level point source.

Nuclear Common Revision 9

'Y' I CALCULATION CONTINUATION SHEET SHEET 38 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patcl/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker/NUCORE, REVIEWERIVERIFIER, DATE 09/24/03 8.0 RESULTS

SUMMARY

8.1 CR Atmospheric Dispersion Factors (y/Qs) Due To Salem 1 MSSV Releases:

The CR x/Qs due to the post-accident releases from the Unit 1 MSSV Set I and Set 2 are summarized in the following Table:

Salem I & 2 CR X/Q Values Adjusted For Plume Rise Unit 1 MSSV Set 1 & Set 2 Releases Salem I & 2 CR Intake 95% Atmospheric Dispersion Factors (XIQs) (s/m3)

Time Unit 1 MSSV Set I Release Unit I MSSV Set 2 Release Interval Unit I Unit 2 Unit I Unit 2 (hr)

CR Intake CR Intake CR Intake CR Intake 0-2 1.57E-02 6.98E-04 5.38E-03 6.24E-04 2-8 1.13E-02 5.66E-04 3.72E-03 4.88E-04 8-24 4.24E-03 2.38E-04 1.40E-03 2.00E-04 24-96 3.08E-03 1.65E-04 9.64E-04 1.38E-04 96-720 2.26E-03 1.32E-04 7.34E-04

1. IE-04 ARCON96 IMSICRI IMSICR2 IMS2CRI IMS2CR2 Run No.

X The MSSV x/Qs are calculated as ground level releases, then reduced by a factor of 5 as allowed by RG 1.194 Section 6 for uncapped and vertically oriented high velocity releases.

Nuclear Common RPev~crn" Q

CALCULATION CONTINUATION SHEET SHEET 39 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker/NUCORE, REVIEWER/VERIFI ER, DATE 09/24/03 8.2 CR Atmospheric Dispersion Factors (y/Qs) Due To Salem 2 MSSV Releases:

The CR X/Qs due to the post-accidental releases from the Unit 2 MSSV Set 1 and Set 2 are summarized in the following Table:

Salem 1 & 2 CR X/Q Valucs Adjusted For Plume Rise Unit 2 MSSV Sct 1 & Set 2 Releases Salem 1 & 2 CR Intake 95% Atmospheric Dispersion Factors (X/Qs) (s/m 3)

Time Unit 2 MSSV Set I Release Unit 2 MSSV Set 2 Release Interval Unit I Unit 2 Unit I Unit 2 (hr)

CR Intake CR Intake CR Intake CR Intake 0-2 6.96E-04 1.45E-02 6.18E-04 5.02E-03 2-8 5.84E-04 1.19E-02 5.06E-04 4.12E-03 8-24 2.48E-04 5.10E-03 2.18E-04 1.73E-03 24-96 1.74E-04 3.06E-03 1.53E-04 1.03E-03 96-720 1.31E-04 1.93E-03 1.IOE-04 6.44E-04 ARCON96 2MSICRI 2MSICR2 2MS2CRI 2MS2CR2 Run No.

I The MSSV x/Qs are calculated as ground level releases, then reduced by a factor of 5 as allowed by RG 1.194 Section 6 for uncapped and vertically oriented high velocity releases.

Nuclear Common Revision 9

CALCULATION CONTINUATION SHEET SHEET 40 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. PateltNUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker/NUCORE, REVIEWER/VERIFIER, DATE 09/24/03 8.3 CR Atmospheric Dispersion Factors (y/Qs) Due To Salem 1 & 2 Penetration Area Pressure Relief Panel Releases:

The CR x/Qs due to the post-accident releases from the Unit I & 2 PAPRPs are summarized in the following Table:

Salem 1 & 2 CR Ground Level X/Q Values Units 1 & 2 Penetration Area Pressure Relief Panel Rclcases Salem I & 2 CR Intake 95% Atmospheric Dispersion Factors (X/Qs) (s/m 3)

Time Unit 1 PAPRP Release Unit 2 PAPRP Release Interval Unit 1 Unit 2 Unit I Unit 2 (fir)

CR Intake CR Intake CR Intake CR Intake 0-2 5.21E-03 1.96E-03 1.88E-03 4.88E-03 2-8 3.54E-03 1.53E-03 1.58E-03 4.05E-03 8-24 1.32E-03 6.08E-04 6.98E-04 1.60E-03 24-96 8.86E-04 4.23E-04 4.67E-04 9.59E-04 96-720 6.80E-04 3.19E-04 3.07E-04 6.22E-04 ARCON96 I PPRCR I IPPRCR2 2PPRCRI 2PPRCR2 Run No.

Nuclear Common Revision 9

CALCULATION CONTINUATION SHEET SHEET 41 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker/NUCORE, REVIEWERIVERIFIER, DATE 09/24103 8.4 CR Atmospheric Dispersion Factors (X/Qs) Due To Salem 1 & 2 Smoke Hatch Releases:

The CR X/Qs due to the post-accident releases from the Unit I & 2 Smoke Hatches are summarized in the following Table:

Salem I & 2 CR Ground Lcvel X/Q Values Units 1 & 2 Smoke Hatch Releases Salem I & 2 CR Intake 95% Atmospheric Dispersion Factors (X/Qs) (s/m3)

Time Unit I Smoke Hatch Release Unit 2 Smoke Hatch Release Interval Unit 1 Unit 2 Unit 1 Unit 2 (hr)

CR Intake CR Intake CR Intake CR Intake 0-2 1.15E-02 2.01 E-03 2.OOE-03 1.14E-02 2-8 9.28E-03 1.61 E-03 1.70E-03 9.24E-03 8-24 3.50E-03 6.51 E-04 6.98E-04 3.62E-03 24-96 2.49E-03 4.74E-04 4.68E-04 2.48E-03 96-720 2.02E-03 4.02E-04 3.61 E-04 2.07E-03 ARCON96 ISMKCRI ISMKCR2 2SMKCRI 2SMKCR2 Run No.

I Nuclear Common Revision 9

.jk l

CALCULATION CONTINUATION SHEET ISHEET 42 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker/NUCORE, REVIEWER/VERIFIER, DATE 09/24/03 8.5 Hope Creek CR Atmospheric Dispersion Factors (X/Qs) Due To Salem 2 Plant Vent Releases:

The Hope Creek CR yc/Qs due to the post-accident releases from the Salem 2 plant vent are summarized in the following Table:

Hope Creek CR Intake x/Qs Salem 2 Plant Vent Release Hope Creek CR Intake 95% Atmospheric Time Dispersion Factors Intenral (X/Qs)

(fir)

(slm3) 0-2 4.86E-05 2-8 3.35E-05 8-24 1.34E-05 24-96 9.59E-06 96-720 7.631E-06 ARCON96 SVEHCR Run No.

Nuclear Common Revision 9

I 4A

~,

sa l

CALCULATION CONTINUATION SHEET SHEET 43 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker/NUCORE, REVIEWER/VERIFIER, DATE 09/24/03

9.0 CONCLUSION

S:

The 9 5th percentile atmospheric dispersion factors X/Qs values for post-accident releases through the MSSVs, PAPRPs, smoke hatches, Salem 2 plant vent release are summarized in Sections 8.1 through 8.5. The applicable y/Qs should be used for the non-LOCA design basis accidents based on the appropriate release locations.

Nuclear Common Revision 9

CALCULATION CONTINUATION SHEET SHEET 44 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker/NUCORE, REVIEWER/VERIFIER, DATE 09/24/03

10.0 REFERENCES

1.

Hope Creek/Salem Generating Stations Meteorological Data Files for 1988 through 1994 (Attached CD).

2.

NUREG/CR-6331 PNNL-10521, Rev 1, Atmospheric Relative Concentrations in Building Wakes, May 1997.

3.

U.S. NRC Regulatory Guide 1.194, June 2003, "Atmospheric Relative Concentrations For Control Room Radiological Habitability Assessments At Nuclear Power Plants."

4.

SNGS Units 1 & 2 General Arrangement Mechanical Drawings:

1.

210488, Rev 6, No. 1 Unit - Auxiliary Building Control Area - Air Conditioning Equipment Room EL 122'-0".

2.

223540, Rev 6, No. 2 Unit - Auxiliary Building Control Area - Air Conditioning Equipment Room EL 122'-0".

5.

SNGS Units I & 2 General Arrangement Mechanical Drawings:

1.

204803, Rev 11, Auxiliary Building EL 122', Reactor Cont. & Fuel Handling Area EL 130'

2.

204805, Rev 6, Aux Bldg EL 84', Reactor Cont. 78' & 81 ' Fuel Handling Area EL 85'& 89'-6"

3.

204808, Rev 1, Auxiliary Building & Reactor Containment Section A-A

6.

E-mail From Robert F. Yewdall To John F. Duffy, Dated 04/12/02, NRP-02-0021,

Subject:

Artificial Island Meteorological Monitoring System Data Quality Documentation Compliance With 10CFR50 Appendix B (Attachment 14.2).

7.

SNGS Drawing No. 239584, Rev 2, Location of Meteorological Tower and Road Plan and Details.

8.

ANSI/ANS-2.5-1984, Standard for Determining Meteorological Information at Nuclear Power Sites (Reaffirmed August 1990).

9.

SNGS Electrical Arrangement Drawing No. 239850, Sheet 2, Rev 0, Meteorological Tower Conduits, Cathodic Prot, Grdg & Ltg.

CALCULATION CONTINUATION SHEET SHEET 45 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 I

G. Patel/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker/NUCORE, REVIEWERIVERIFIER, DATE 09/24/03

10.

U.S.NRC Regulatory Guide 1.23, February 1972, Onsite Meteorological Programs.

11.

SNGS Mechanical Arrangement Drawings:

1.

218249, Rev 8, No. 1 - Unit Reactor Containment Main Steam Safety Valve Vent Piping

2.

218299, Rev 3, No. 2 - Unit Reactor Containment Main Steam Safety Valve Vent Piping

12.

SNGS Steel Structural Drawings:

1.

204794, Rev 9, No. I & 2 Units - Auxiliary Building Misc. Steel - Penetration Area EL 140'-0",

Sheet I

2.

204795, Rev 4, Sheet 2, No.1 & 2 Units - Auxiliary Building Misc. Steel - Penetration Area EL 140'-0", Sheet 2

3.

206107, Rev 1, No.1 & 2 Units - Auxiliary Building Penetration Extension Above EL 120'-0"

4.

237302, Rev 7, No.1 & 2 Units - Penetration Area Pressure Relief Framing & Panels Above EL 120'-0"

5.

201303, Rev 5, No.1 & 2 Units - Auxiliary Building Misc. Steel - Penetration Area EL 120'-0",

Sheet 2

13.

Critical Software Package No. A-O-ZZ-MCS-0224, Sheet 2, Rev 0.

14.

Memorandum No. NRP-01-015, Dated 04/09/01, From Robert Yewdall to Gopal Patel,

Subject:

Design Input ARCON96 Meteorological Data, Calc H-I-ZZ-MDC-1979 (Attachment 14.3).

15.

Design Change Package (DCP) No. 1EC-3505, Package No. 13, Upgrade of Radiation Monitor Processor 2RIB Power Supply

16.

SNGS Architectural Drawings:

1.

207084, Rev 13, No. 1 Unit - Auxiliary Building Roof Plan EL 140'-0" & 141 '-0"

2.

207085, Rev 10, No. 2 Unit - Auxiliary Building Roof Plan EL 140'-0" & 141 '-0"

3.

207086, Rev 10, No. 1 & 2 Units - Auxiliary Building Roofs EL 130'-0" & 140'-0" Flashing Details Nuclear Common Rcvision 9

I CALCULATION CONTINUATION SHEET SHEET 46 or 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker/NUCORE, REVI EWERNVERI FI ER, DATE 09/24/03

17.

PSE&G Vendor Technical Document No. 321035, Rev 3, Accident X/Q Values At the Salem Generating Station Control Room Fresh Air Intakes, Exclusion Area Boundary And Low Population Zone

18.

SNGS Calculation No. S-C-ZZ-MDC-1987, Rev 0, Input Parameters for Salem AST Dose Calcs

19.

SNGS Architectural Drawings:

1.

207042, Rev 4, No. I Unit -Fuel Handling Area Floor Plans EL 84'-O", 1 00'-0", & 11 6'-0"

2.

207043, Rev 5, No. I Unit -Fuel Handling Area Floor Plan EL 130'-0" & Roof Plan

3.

207044, Rev 7, No. 2 Unit -Fuel Handling Area Floor Plans EL 84'-0", 100'-0", & 116'-0"

4.

207045, Rev 7, No. 2 Unit -Fuel Handling Area Floor Plan EL 130'-0" & Roof Plan

20.

HCGS Calculation No. H-1 -ZZ-MDC-1 879, Rev lIR0, Control Room & Technical Support Center X/Qs Using ARCON96 Code

21.

SNGS Drawings:

1.

HCGS Drawing No. C-0001-0, Rev 17, Site Plan

2.

HCGS Drawing No. C-0002-0, Rev 16, Plot Plan

3.

HCGS Drawing No. 205402, Sheet 1, Rev 33, Plot Plan

4.

HCGS Drawing No. 252312, Sheet 1, Rev 9, Yard Nuclear Common Revision 9

CALCULATION CONTINUATION SHEET SHEET 47 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. PateVNUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker/NUCORE, REVIEWER/VERIFIER, DATE 09/24/03 11.0 TABLES:

Table I Salem I & 2 CR Ground Level X/Q Values Unit 1 MSSV Set 1 & Set 2 Releases Salem 1 & 2 CR Intake 95% Atmospheric Dispersion Factors (X/Qs) (s/m3)

Time Unit 1 MSSV Set I Release Unit I MSSV Set 2 Release Interval Unit I Unit 2 Unit I Unit 2 (hr)

CR Intake CR Intake CR Intake CR Intake 0-2 7.84E-02 3.49E-03 2.69E-02 3.12E-03 2-8 5.66E-02 2.83E-03 1.86E-02 2.44E-03 8-24 2.12E-02 1.19E-03 7.01E-03 1.00E-03 24-96 1.54E-02 8.23E-04 4.82E-03 6.89E-04 96-720 1.13 E-02 6.61 E-04 3.67E-03 5.57E-04 ARCON96 IMSICRI IMSICR2 IMS2CRI IMS2CR2 Run No.

I Nuclear Common Revision 9

CALCULATION CONTINUATION SHEET SHEET 48 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE REV:

09122/03 0

M. Drucker/NUCORE, REVI EWERNVERI FIER, DATE 09/24/03 Table 2 Salem 1 & 2 CR Ground Level X/Q Valucs Unit 2 MSSV Set 1 & Set 2 Releases Salem I & 2 CR Intake 95% Atmospheric Dispersion Factors (X/Qs) (s/M3)

Time Unit 2 MSSV Set I Release Unit 2 MSSV Set 2 Release Interval Unit I Unit 2 Unit I Unit 2 (hr)

CR Intake CR Intake CR Intake CR Intake 0-2 3.48E-03 7.25E-02 3.09E-03 2.51 E-02 2-8 2.92E-03 5.96E-02 2.53E-03 2.06E-02 8-24 1.24E-03 2.55E-02 1.09E-03 8.65E-03 24-96 8.69E-04 1.53E-02 7.64E-04 5.15E-03 96-720 6.56E-04 9.66E-03 5.49E-04 3.22E-03 ARCON96 2MSICRI 2MSICR2 2MS2CRI 2MS2CR2 Run No.

I I

Nuclear Common Revision 9

• o CALCULATION CONTINUATION SHEET SHEET 49 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. PatetJNUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker/NUCORE, REVIEWER/VERIFIER, DATE 09/24/03 Table 3 Salem 1 & 2 CR Ground Level X/Q Values Units 1 & 2 Penetration Area Pressure Relief Panel Releases Salem I & 2 CR Intake 95% Atmospheric Dispersion Factors (X/Qs) (s/m3)

Time Unit 1 PAPRP Release Unit 2 PAPRP Release interval Unit I Unit 2 Unit I Unit 2 (hr)

CR Intake CR Intake CR Intake CR Intake 0-2 5.21E-03 1.96E-03 1.88E-03 4.88E-03 2-8 3.54E-03 1.53E-03 1.58E-03 4.0SE-03 8-24 1.32E-03 6.08E-04 6.98E-04 1.60E-03 24-96 8.86E-04 4.23E-04 4.67E-04 9.59E-04 96-720 6.80E-04 3.19E-04 3.07E-04 6.22E-04 ARCON96 IPPRCRI I PPRCR2 2PPRCRI 2PPRCR2 Run No.

Nuclear Common Revision 9

I !

I CALCULATION CONTINUATION SHEET SHEET 50 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. PatellNUCORE, ORIGINATOR, DATE

]REV:

09/22/03 0

M. Drucker/NUCORE, REVIEWER/VERIFIER, DATE 09/24/03 Table 4 Salem 1 & 2 CR Ground Level X/Q Values Units 1 & 2 Smoke Hatch Releases Salem 1 & 2 CR Intake 95% Atmospheric Dispersion Factors (X/Qs) (s/m3)

Timc Unit I Smoke Hatch Release Unit 2 Smoke Hatch Release Interval Unit I Unit 2 Unit I Unit 2 (hr)

CR Intake CR Intake CR Intake CR Intake 0-2 1.15E-02 2.011E-03 2.00E-03 1.14E-02 2-8 9.28E-03 1.61 E-03 1.70E-03 9.24E-03 8-24 3.50E-03 6.51 E-04 6.98E-04 3.62E-03 24-96 2.49E-03 4.74E-04 4.68E-04 2.48E-03 96-720 2.02E-03 4.02E-04 3.61 E-04 2.07E-03 ARCON96 I SMKCRI ISMKCR2 2SMKCRI 2SMKCR2 Run No.

CALCULATION CONTINUATION SHEET SHEET 51 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 l

G. Patel/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker/NUCORE, REVI EWER/VERIFI ER, DATE 09/24/03 12.0 FIGURES:

MSSV Set 2 Unit 2 Unit I Penetration Area Pressure Unit 2 Penetration Area Pressure Unit I o

= Release Points 0

= Receptors FIGURE 1: SNGS Source/Rcccptor Relationship Nuclear Common Revision 9

CALCULATION CONTINUATION SHEET SHEET 52 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. DruckerfNUCORE, REVIEWER/VERIFIER, DATE 09/24/03 MSSV Releases Salem Unit 2 Containment Bldg Salem Unit I Containment Bldg FIGURE 2: Limiting MSSV Release View Looking East Nuclear Common Revision 9

.
: Ir Plant North.

FIGURE 3: Unit 1 MSSV Set 1 Relcase - Unit 1 CR1 Air Intake Distance To Rclcasc Point Direction CR Rcleasc Rce ptor eight To Wake Intake Point Feet Meter Feet Meter Source Area Height Degree m2 Meter Unit I MSSV Set 1 20.92 6..38 47.5 14.48

• 113.49 2429.54 9.39 Unit I CRI Intake I I

Nuclear Common Revision 9

1.

,!--z 7-.S7.-

'7,'

Plant North Distance To Release Point Direction CR Release Reec tor ileight To Wake Intake Point Feet Meter Feet Meter Source Area Height Degree M2 Meter Unit I MSSV Set 1 136.37 41.58 47.5 14.48 166.81 2429.54 9.13 Unit 2 CR2 Intake

-_I Nuclear Common Revision 9

I CALCULATION CONTINUATION SHEET SHEET 55 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker/NUCORE, REVIEWERNVERIFIER, DATE 09/24/03 Plan~t North FIGURE 5: Unit 1 MSSV Set 2 Rcleasc - Unit 1 CR1 Air Intake Distance To Rclease Point Direction CR Relcase Rce Rptor I]cight To Wake Intake Point Fcet Meter Feet Meter Source Area Height Degree M___

Meter Unit I MSSV Set 2 43.23 13.18 47.5 14.48 105.00 2429.54 9.39 Unit _ CRI Intake I

I Nuclear Common Revision 9

7 CALCULATION CONTINUATION SHEET SHEET 56 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

l M. Drucker/NUCORE, REVIEWERIVERIFIER, DATE 09/24/03 Plant North FIGURE 6: Unit I MSSV Set 2 Release - Unit 2 CR2 Air Intake Distance To Rclcase Point Direction CR Relcase Rece tor eight To Wake Intake Point Feet Meter Feet Mcter Source Area Height Degree m2 Meter Unit 1 MSSV Set 2 145.87 44.47 47.5 14.48 158.38 2429.54 9.13 Unit 2 CR2 Intake

CALCULATION CONTINUATION SHEET SHEET 57 of 66 CA LC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker/NUCORE, REVI EWERtVERIFIER, DATE 09/24/03 Planlt North 97'-6" p

Salem Containn FF-i IUnit 2 ient Bldg 1

i I

[

/

Upit 2 MS' 10'-1-5/8" X g 15/16" SV set 18.38' 18.30' Intake 125'-O" i

Unit 2 CR

4 87'-2-1/2" FIGURE 7

Unit 2 MSSV Set 1 Rcleasc - Unit 2 CR2 Air Intake Distance To Release Point Direction CR Release Re_

_ ptor Height To Wake Intake Point Feet Metcr Feet Meter Source Area Height Dcgree M2 Meter Unit 2 MSSV Set 1 20.92 6.38 47.5 14.48 55.51 2429.54 9.13 Unit 2 CR2 Intake I

Nuclear Common Revision 9

CALCULATION CONTINUATION SHEET SHEET 58 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker/NUCORE, REVIEWERIVERIFIER, DATE 09/24/03 Pnt North FIGURE 8: Unit 2 MSSV Set 1 Release - Unit 1 CR1 Air Intake Distance To Release Point Direction CR Release Rece tor ight To Wake Intake Point Feet Meter Fect Meter Source Area Height

____Degree m 2 Meter Unit 2 MSSV Set 1 136.37 41.58 47.5 14.48 2.19 2429.54 9.39 Unit I CR1 Intake Nuclear Common Revision 9

'-.f4 I

CALCULATION CONTINUATION SHEET ISHEET 59 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE I REV:

09/22/03 0

M. DruckertNUCORE, REVIEWER/VERIFI ER, DATE 09/24/03 Plat North FIGURE 9: Unit 2 MSSV Set 2 Release - Unit 2 CR2 Air Intake Distance To Release Point Direction CR Release Rcce tor Hcight To Wake Intake Point Fcet Mctcr Fcet Meter Source Area Height Degree M2 Meter Unit 2 MSSV Set 2 43.23 13.18 47.5 14.48 64.00 2429.54 9.13 Unit 2 CR2 Intake

___I Nuclear Common Revision 9

CALCULATION CONTINUATION SHEET SHEET 60 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker/NUCORE, REVIEWER/VERIFIER, DATE 09/24/03 Plant North FIGURE 10: Unit 2 MSSV Sct 2 Relcase - Unit 1 CR1 Air Intake Distance To Release Point Direction CR Release Rece tor Height To Wake Intake Point Feet Meter Feet Meter Source Area Height Degree M2 Meter Unit 2 MSSV Set 2 145.87 44.47 47.5 14.48 10.62 2429.54 9.39 Unit 1 CRI Intake I

Nuclear Common Revision 9

CALCULATION CONTINUATION SHEET SHEET 61 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker/NUCORE, REVIEWER/VERIFIER, DATE 09/24/03 Plant North

.._4- - " --_._._._._._

FIGURE 11: Unit 1 Pcnetration Arca Pressure Relief Panel - Control Room Air Intakes Distance To Release Point Direction CR Sigma Sigma Release Rece tor Hci ght To Wake Intake Y

Z Point Feet Meter Feet Meter Source Area Height Value Value Degree M2 Meter Meter Meter Unit I PAPRP 97.63 29.77 29.25 8.92 99.34 775.49 9.39 1.448 0.585 CRI Intake Unit I PAPRP 177.22 54.03 29.25 8.92 142.33 775.49 9.13 1.448 0.585 CR2 Intake I

I I

I I

Nuclcar Common Revision 9

4 I 7.:.

CALCULATION CONTINUATION SHEET SHEET 62 of 66 CALC. NO.: S-C-ZZ-MDC-I 959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker/NUCORE, REVIEWER/VERIFIER, DATE 09/24/03 Plant North ietration Area

-essure Relief Panels Unit I CR Intake FIGURE 12: Unit 2 Pcnctration Area Prcssure Relief Panel - Control Room Air Intakes Distance To Rclease Point Direction CR Sigma Sigma Release Rccc tor Hci ght To Wake Intake Y

Z Point Feet Meter Feet Meter Source Area Height Value Value Degree M2 Meter Meter Meter Unit 2 PAPRP 97.63 29.77 29.25 8.92 69.66 775.49 9.13 1.448 0.585 CR2 Intake Unit 2 PAPRP 177.22 54.03 29.25 8.92 26.67 775.49 9.39 1.448 0.585 CRI Intake I

I I

I Nuclear Common Revision 9

..' kt' -

I CALCULATION CONTINUATION SHEET SHEET 63 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE REV:

09122103 O

1 M. Drucker/NUCORE, REVIEWER/VERIFIER, DATE 09124/03 Plant North 18.38' Hatch FIGURE 13: Unit I Smoke Hatch - Control Room Air Intakes Distance To Release Point Direction CR Release Rece tor Height To Wake Intake Point Feet Meter Feet Meter Source Area Height Degree M2 Meter Unit 1 Smoke Hatch 72.14 21.99 42.5 12.96 220.90 648.89 9.39 CR1 Intake Unit I Smoke Hatch 182.39 55.61 42.5 12.96 191.15 648.89 9.13 CR2 Intake II Nuclear Common Revision 9

CALCULATION CONTINUATION SHEET SHEET 64 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker/NUCORE, REVIEWERNVERIFIER, DATE 09/24/03 Plant North 70'-7-1 /2" Smoke Hatch FIGURE 14: Unit 2 Smoke Hatch - Control Room Air Intakes Distance To Release Point Direction CR Rclcase Rcec tor ight To Wake Intake Point Feet Meter Feet Meter Source Area Height Degree M 2 Meter Unit 2 Smoke Hatch 72.14 21.99 42.5 12.96 308.10 648.89 9.13 CR2 Intake Unit 2 Smoke Hatch 182.39 55.61 42.5 12.96 337.85 648.89 9.39 CR1 Intake Nuclear Common Revision 9

.. ~ ~

- - 1:I-

-P

.. -7.,

7y =-'

z CALCULATION CONTINUATION SHEET SHEET 65 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker/NUCORE, REVIEWER/VERIFIER, DATE 09/24/03 Plant North tr Figure: 15 Salem 2 Plant Vent - Hope Creek CR Air Intake Nuclear Common Revision 9

r..'

...

.N%445

.7.'.

4
x_

l CALCULATION CONTINUATION SHEET ISHEET 66 of 66 CALC. NO.: S-C-ZZ-MDC-1959

REFERENCE:

LCR S03-05 G. Patel/NUCORE, ORIGINATOR, DATE REV:

09/22/03 0

M. Drucker/NUCORE, REVIEWER/VERIFIER, DATE 09/24/03 13.0 AFFECTED DOCUMENTS:

Upon approval of Licensing Change Request LCR S03-05, the on-site x/Qs developed by Vendor Technical Document (VTD) No. 321035, Rev 3 will be superseded by those X/Qs developed in this calculation.

14.0 ATTACHMENTS:

14.1 Diskette with the following electronic files (1 page):

Diskette with the following electronic files:

Calculation No: S-C-ZZ-MDC-1959, Rev 0 Comment Resolution Form 2 - Mark Drucker Certification for Design Verification Form-I RCPD Form-i 14.2

[Reference 10.6] E-mail From Robert F. Yewdall To John F. Duffy, Dated 04/12/02, NRP-02-002,

Subject:

Artificial Island Meteorological Monitoring System Data Quality Documentation Compliance With 10CFR50 Nuclear Common Revision 9

S-C-ZZ-MDC-1959, Rev 0 4.1 Page: I of 1 I

I Diskette With Various Electronic Files Nuclcar Common Revision 9

b

..e>9z-l S-C-ZZ-MDGC1959, Rev 0 4.2 Page: 1 of I TO:

John F. Duffy Nuclear Engineering Design Gopal Patel NUCORE FROM:

Robert F. Yewdall Radiation Protection Support

SUBJECT:

Artificial Island Meteorological Monitoring System Data Quality Documentation Compliance With I OCFR50 Appendix B DATE:

April 12, 2002 NRP-02-0021 The purpose of this memorandum is to document compliance with I OCFR50, Appendix B. The requirement for this documentation is provided in Attachment I to this memo.

Commitment to a quality meteorological monitoring program is provided in our license documents, specifically section 17 to both the Salem and Hope Creek UFSARs. We are in compliance with the requirements of Technical Specification 6.8 and USNRC Regulatory Guide 1.33.

A quality programs is assured by strict implementation of approved stations procedures.

These procedures are:

> NC.RS-AP.MET-1201(Q) Meteorological Monitoring Program Administration Si NC.RS-SC.MET-1201(Q) Meteorological Monitoring System Calibration & Maintenance r

NC.RS-TI.MET-1201(Q) Meteorological Monitoring System Surveillance Instructions P NC.RS-TI.MET-1202(Q) Meteorological System Operation/ Interrogation r

NC.RS-TI.MET-1203(Q) Meteorological Monitoring System Data Collection

> NC.RS-TI.MET-1204(Q) Meteorological Monitoring System Data Validation The programs are monitored/ audited by the NRC during annual inspections as well as by QA assessments and self assessments.

If you have any questions with respect to data quality please contact me.

C B. Sebastian R. Gary K. O'Hare J. Nagle D. Kelly L. Clark F. Castelli J. Southers P. Bledsoe Nuclear Common Revision 9