CNL-14-234, Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 1

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Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 1
ML14350B364
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 12/16/2014
From: James Shea
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
CNL-14-234
Download: ML14350B364 (74)
v • d • e


Text

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-14-234 December 16, 2014 10 CFR 50.90 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Sequoyah Nuclear Plant, Units 1 and 2 Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 50-328

Subject:

Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) Supplement 1

Reference:

TVA Letter to NRC, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10), dated November 22, 2013. (ADAMS Accession No. ML13329A717)

By letter dated November 22, 2013, the Tennessee Valley Authority (TVA) requested a license amendment to revise the current Technical Specifications for Sequoyah Nuclear Plant (SQN), Units 1 and 2, to the Improved Technical Specifications (ITS) consistent with the Improved Standard Technical Specifications described in NUREG-1431, Standard Technical Specifications - Westinghouse Plants, Revision 4.0 (Reference). The SQN ITS license amendment request (LAR), in part, proposed a change to the Applicability requirements of current Technical Specifications 3.3.3.1, 3.9.4, 3.9.9, and 3.9.12.

To facilitate the NRC staff review of these proposed changes, this supplemental information is being provided and is based on ongoing discussions with the NRC staff regarding the revised SQN fuel handling accident (FHA) radiological consequences analysis using alternative source term methodology.

The enclosure, Discussion of Changes Related to the Radiological Consequences Analysis of the Fuel Handling Accident for SQN, Units 1 and 2, provides background discussion of the revision to the SQN FHA radiological consequences analysis, revised input assumptions for the updated SQN FHA radiological consequences analysis, additional information consistent with NRC Regulatory Guide 1.183, and revised offsite and main control room radiation dose results.

U.S. Nuclear Regulatory Commission Page 2 December 16, 2014, LTR-CRA-02-219, Revision 2: Radiological Consequences of Fuel Handling Accidents for the Sequoyah Nuclear Plant Units 1 and 2, provides a copy of the revised Westinghouse report transmitting the updated SQN radiological consequences analysis associated with a design basis FHA., Fauske Report No. FAI/14-0989, Revision 2: Calculation of Atmospheric Dispersion Factors for Sequoyah Nuclear Plant, provides a copy of the calculation that determined the limiting atmospheric dispersion value for the SQN auxiliary building vent stack source location used in calculating the radiological consequences to personnel in the SQN main control room following a design basis FHA.

This correspondence contains no new regulatory commitments.

The information provided by this supplement to the ITS LAR does not change the intent or the justification for the requested ITS license amendment. TVA has further determined that this supplement does not affect the basis for concluding that the proposed license amendment does not involve a Significant Hazards Consideration. As such, the 10 CFR 50.92 evaluation provided in the November 22, 2013, ITS LAR remains valid. In addition, the ITS LAR, including this supplement, continues to be exempt from environmental review pursuant to the provisions of 10 CFR 51.22(c)(9).

The SQN Plant Operations Review Committee has reviewed this supplemental information and determined that operation of SQN in accordance with the Technical Specifications with an Applicability of, During movement of recently irradiated fuel assemblies, as proposed in the ITS LAR (Reference), will not endanger the health and safety of the public.

Additionally, in accordance with 10 CFR 50.91(b)(1), TVA is sending a copy of this letter and the enclosure to the Tennessee State Department of Environment and Conservation.

If there are any questions or if additional information is needed, please contact Tom Hess at 423-751-3487.

I declare under penalty of perjury that the foregoing is true and correct. Executed on this 16th day of December 2014.

Respectfully, J. W. Shea Vice President, Nuclear Licensing

Enclosure:

Discussion of Changes Related to the Radiological Consequences Analysis of the Fuel Handling Accident for SQN, Units 1 and 2 cc: See Page 3 J. W. Shea Digitally signed by J. W. Shea DN: cn=J. W. Shea, o=Tennessee Valley Authority, ou=Nuclear Licensing, email=jwshea@tva.gov, c=US Date: 2014.12.16 18:20:14 -05'00'

U.S. Nuclear Regulatory Commission Page 3 December 16, 2014 Enclosure cc (Enclosure):

NRC Regional Administrator - Region II NRC Senior Resident Inspector - Sequoyah Nuclear Plant Director, Division of Radiological Health - Tennessee State Department of Environment and Conservation

ENCLOSURE TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 Discussion of Changes Related to the Radiological Consequences Analysis of the Fuel Handling Accident for SQN, Units 1 and 2

E 1 of 5 Enclosure Discussion of Changes Related to the Radiological Consequences Analysis of the Fuel Handling Accident for SQN, Units 1 and 2

Background

By letter dated October 28, 2003 (Reference 1), the NRC issued Amendment No. 288 to Facility Operating License No. DPR-77 and Amendment No. 278 to Facility Operating License No. DPR-79 for Sequoyah Nuclear Plant (SQN) Units 1 and 2, respectively. These amendments modified the Applicability requirement associated with, movement of irradiated fuel, in Technical Specification 3.9.4, Containment Building Penetrations, by relaxing the Applicability requirement for the containment building equipment door. These amendments were in response to the Tennessee Valley Authority (TVA) alternative source term (AST) partial implementation license amendment request (LAR), which provided the SQN radiological consequences analysis performed for the design basis fuel handling accident (FHA) using an AST; Westinghouse Report LTR CRA-02-219, Revision 0 (Reference 2). In the NRC Safety Evaluation associated with SQN License Amendments 278 and 288, the NRC staff concluded, in part, that analysis methods and assumptions used were consistent with the conservative regulatory requirements and guidance, and that the change to replace the accident source term used in the previous design basis FHA within containment radiological consequences analyses with an AST was acceptable.

By letter dated November 22, 2013, TVA requested a license amendment to revise the current Technical Specifications (CTS) for SQN Units 1 and 2, to the Improved Technical Specifications (ITS) consistent with the Improved Standard Technical Specifications described in NUREG-1431, Standard Technical Specifications - Westinghouse Plants, Revision 4.0 (Reference 3). The SQN ITS LAR, in part, proposed a change to the Applicability requirements of several Technical Specifications to require these Technical Specifications, During movement of recently irradiated fuel assemblies; which, when a unit is not in Operational Mode 1, 2, 3, or 4, eliminates these requirements for fuel movements performed 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> following reactor shutdown. Specifically, the following Technical Specification Applicability requirements proposed to be modified are:

a. Radiation Monitoring Instrumentation - CTS 3.3.3.1, Table 3.3-6, Instrument 2.a, Process Monitors - Containment Purge Air, (ITS 3.3.6, Containment Ventilation Isolation Instrumentation, Table 3.3.6-1, Function 3, Containment Purge Air Radiation Monitor)

Mode 6 Applicable Mode requirement replaced with during movement of recently irradiated fuel assemblies within containment;

b. Containment Ventilation Isolation System - CTS 3.9.9 (ITS 3.3.6, Containment Ventilation Isolation Instrumentation) Applicability revised to during movement of recently irradiated fuel within the containment;
c. Radiation Monitoring Instrumentation - CTS 3.3.3.1, Table 3.3-6, Instrument 1.a, Area Monitor - Fuel Storage Pool Area, (ITS 3.3.8, Auxiliary Building Gas Treatment System (ABGTS) Actuation Instrumentation, Table 3.3.8-1, Function 2, Spent Fuel Pool Area Radiation Monitor) Applicable Mode
  • Note changed from, With fuel in the storage pool or building, to During movement of recently irradiated fuel assemblies in the auxiliary building;
d. Auxiliary Building Gas Treatment System - CTS 3.9.12 (ITS 3.7.12, Auxiliary Building Gas Treatment System (ABGTS)); Applicability changed from, Whenever irradiated fuel is in the storage pool, to During movement of recently irradiated fuel assemblies in the auxiliary building; and

E 2 of 5

e. Containment Building Penetrations - CTS 3.9.4 (ITS 3.9.4, Containment Penetrations)

Applicability associated with the containment building airlock doors and penetrations revised to during movement of recently irradiated fuel within the containment.

To facilitate the NRC staff review of these proposed changes, this supplemental information is being provided and is based on ongoing discussions with the NRC staff regarding the revised SQN FHA radiological consequence analysis using AST methodology., LTR-CRA-02-219, Revision 2: Radiological Consequences of Fuel Handling Accidents for the Sequoyah Nuclear Plant Units 1 and 2, provides a copy of the Westinghouse report transmitting the updated SQN radiological consequences analysis associated with a design basis FHA to support the elimination of specific Technical Specification requirements during fuel movements performed 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> following reactor shutdown., Fauske Report No. FAI/14-0989, Revision 2: Calculation of Atmospheric Dispersion Factors for Sequoyah Nuclear Plant, provides a copy of the calculation that determined the limiting atmospheric dispersion (/Q) value for the SQN auxiliary building (AB) vent stack source location used in calculating the radiological consequences to personnel in the SQN main control room (MCR) following a design basis FHA. This calculation was performed with the ARCON96 code, which is an NRC accepted code for determining /Q values in design basis evaluations of MCR radiological analyses. The input parameters to the ARCON96 code were prepared according to the guidance on the use of ARCON96 as discussed in NRC Regulatory Guide (RG) 1.194 (Reference 4).

Revised Input Assumptions for the Updated SQN FHA Radiological Consequences Analysis The input assumptions and methodology used in the SQN design basis FHA radiological consequences analysis using an AST are consistent with those described in RG 1.183 (Reference 5).

The following changes made to the input assumptions of the FHA radiological consequences analysis provided in LTR-CRA-02-219 are:

x revise the MCR /Q values to reflect an AB vent stack point release; x

delete the source term associated with tritium producing burnable absorber rods (TPBARs);

x application of a linear source term release rate for a FHA inside the containment; and x

establish a limiting containment purge isolation time by performing timing sensitivity evaluations.

Revised MCR /Q Values Although previous revisions of LTR-CRA-02-219 assumed the SQN AB vent stack as the point source radioactivity release, the MCR /Q value cited was based on a point release from the Unit 2 main steam valve vault. Therefore, the MCR /Q values for the 0-2 hour release outside containment and the purge isolation time-2 hour release inside containment were increased from 1.80E-3 sec/m3 to 2.56E-3 sec/m3 to accurately reflect the MCR /Q value associated with a radioactivity release from the AB vent stack. Based on a review of containment penetrations as potential point source release locations (e.g., equipment hatch,

E 3 of 5 access doors and containment pipe and cable penetrations), TVA established that the AB vent stack continues to be the limiting source location for calculation of dose to MCR personnel following a FHA inside the containment. Additionally, since the resulting /Q was determined to be higher at the MCR normal intake location than the MCR emergency intake location, the MCR normal intake is considered the limiting receptor location even though the Control Room Emergency Ventilation System (CREVS) is assumed to be in service within 5 minutes following event initiation.

TPBAR Source Term Deletion The source term associated with a fuel assembly containing TPBARs was eliminated from FHA radiological consequences analysis since the introduction of TPBARs was not implemented at SQN. On October 12, 2011, via electronic correspondence from R. Krich (TVA) to S. Lingam (NRC), TVA informed the NRC staff that: since the issuance of Facility Operating License Amendments 278 and 289 for SQN Unit 1 and Amendments 269 and 279 for SQN Unit 2, which authorized the use of TPBARs, changes have been made at SQN, Units 1 and 2, that materially change the bases for NRC approval of these amendments and TVA understands that it would need to request and receive NRC approval prior to introducing any TPBARs into either SQN unit. Based on the elimination of the tritium source term from the FHA radiological consequences analysis, the resulting dose values have decreased substantially for both offsite and MCR receptor locations.

Application of Linear Release in Containment For a FHA inside the containment, the containment mixing volume and purge flow rate assumptions have been deleted and the activity released from the damaged fuel not retained in the water pool is assumed to be released linearly from the pool to the environment within two hours. No credit is taken for mixing in the containment volume or filtration by the containment purge system.

Limiting Containment Purge Isolation Time To establish a limiting containment purge isolation time, timing sensitivity evaluations were performed considering a FHA inside containment with; 1) early isolation of the containment purge system, 2) delayed isolation of the containment purge system, and 3) no isolation of the containment purge system. The results of the evaluations showed that the dose to MCR personnel is more severe during a FHA inside containment with early isolation of the containment purge system. Early isolation of the containment purge system is conservative because there is less atmospheric dispersion from an activity release through the AB vent stack to the MCR and; thus, more severe MCR dose consequences than the MCR dose consequences from an activity release through the shield building exhaust vent. As such, there are no restrictions on the containment purge isolation timing. This allows containment penetrations to be open without closure or isolation requirements during fuel movement performed 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> following reactor shutdown.

Additional Information Consistent with RG 1.183 Limiting Single Active Failure Regulatory Position 5.1.2 of RG 1.183 states, in part: "The single active component failure that results in the most limiting radiological consequences should be assumed." At SQN, the only active engineered safety feature function that is credited in the FHA is the CREVS.

E 4 of 5 Therefore a failure of one train of the CREVS to actuate in the emergency mode is the most limiting single active failure for a design basis FHA assuming fuel movement 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> following reactor shutdown. The SQN ITS LAR is not altering the Applicability requirements of CTS 3.3.3.1, Radiation Monitoring Instrumentation, Table 3.3-6, Instrument 2.c, Process Monitors - Control Room Isolation, (ITS 3.3.7, Containment Ventilation Isolation Instrumentation, Table 3.3.7-1, Function 3, Control Room Radiation - Control Room Air Intakes) or CTS 3.7.7, Control Room Emergency Ventilation System (ITS 3.7.10, Control Room Emergency Ventilation System (CREVS)). These requirements will continue to be applicable in Modes 1, 2, 3, 4, 5, and 6, and during movement of irradiated fuel assemblies.

Internal Fuel Pressure As indicated in Table 2, Fuel Handling Assumptions, of Westinghouse Report LTR-CRA-02-219 (Attachment 1), an iodine decontamination factor (DF) of 200 was used for the determination of the radiological consequences. This is consistent with the guidance in Appendix B, Assumptions for Evaluating the Radiological Consequences of a Fuel Handling Accident, of RG 1.183 (Reference 5). The data, which determined an acceptable iodine DF value of 200 in Appendix B of RG 1.183, was developed in 1971 and based on fuel designs with an assumed internal fuel pressure of 1200 pounds force per square inch gage (psig).

As stated in the SQN Updated Final Safety Analysis Report, Section 15.5.6, the FHA assumes a maximum internal fuel rod pressure of 1200 psi.

Summary of FHA Dose Results Based on the changes to the input assumptions associated with the radiological consequences analysis for a FHA inside and outside the SQN Unit 1 and 2 containments, the analysis indicates that whether the FHA accident occurs inside the containment or in the AB, the dose results at the exclusion area boundary (EAB) and low population zone (LPZ) are the same because the accident occurring in these locations does not alter the activity released over the 2-hour period and the EAB and LPZ /Q values are not sensitive to the specific reactor building or AB release points. As indicated in Section 2.3, Results, of Westinghouse Report LTR-CRA-02-219 (Attachment 1), dose to individuals at the EAB is calculated to be 2.8 Roentgen equivalent man (rem) total effective dose equivalent (TEDE) and dose to individuals at the LPZ is calculated to be 0.5 rem TEDE, both of which are below the 10 CFR 50.67(b)(2)(i) and (ii) radiation dose criteria of 25 rem TEDE and the radiation dose criterion of 6.3 rem TEDE specified in Table 6, Accident Dose Criteria, of NRC RG 1.183 (Reference 5).

As indicated in Section 2.3, Results, of Westinghouse Report LTR-CRA-02-219 (Attachment 1), the worst-case FHA dose to personnel in the MCR is calculated to be 0.6 rem TEDE whether the FHA occurs in the AB or inside the containment and assumes an immediate isolation of the containment purge system, which has been determined to be more conservative than no containment purge isolation as described herein. The worst-case calculated FHA dose to the MCR is below the 10 CFR 50.67(b)(2)(iii) radiation dose criterion of 5 rem TEDE.

E 5 of 5 References

1.

Letter from NRC (M. Marshall) to TVA (J. Scalice), Sequoyah Nuclear Plant, Units 1 and 2 Issuance of Amendments Regarding Closure of the Containment Building Equipment Doors During Movement of Irradiated Fuel (TAC Nos. MB7238 and MB7239) (TS-02-08), dated October 28, 2003. (ADAMS Accession No. ML033030206)

2.

Letter from TVA (P. Salas) to NRC (Document Control Desk), Sequoyah Nuclear Plant (SQN) - Units 1 and 2 - Technical Specification (TS) Change 02-08, Partial Scope Implementation of the Alternate Source Term and Revision of Requirements for Closure of the Containment Building Equipment Door During Movement of Irradiated Fuel, dated January 14, 2003. (ADAMS Accession No. ML030160157)

3.

Letter from TVA (J. Shea) to NRC (Document Control Desk), Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10), dated November 22, 2013. (ADAMS Accession No. ML13329A717)

4.

NRC Regulatory Guide 1.194, Atmospheric Relative Concentrations for Control Room Radiological Habitability Assessments at Nuclear Power Plants, dated June 2003.

5.

NRC Regulatory Guide 1.183, Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors, dated July 2000.

ATTACHMENT 1 TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 LTR-CRA-02-219, Revision 2: Radiological Consequences of Fuel Handling Accidents for the Sequoyah Nuclear Plant Units 1 and 2

Westinghouse Non-Proprietary Class 3











Radiological Consequences of Fuel Handling Accidents for the Sequoyah Nuclear Plant Units 1 and 2 Addressing: 1) Control Room Atmospheric Dispersion Factor Update for Auxiliary Building Stack Release

2) Tritium Producing Burnable Absorber Rod (TPBAR) Deletion
3) Updated Source Term Release Rate for Fuel Handling Accident Inside Containment
4) Containment Purge Isolation Timing Sensitivity Document ID: LTR-CRA-02-219, Revision 2 Prepared for Tennessee Valley Authority by Westinghouse Electric Company December 9, 2014 2014 Westinghouse Electric Company

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2 1.0 USE OF ALTERNATE SOURCE TERM METHODOLOGY 1.1 Introduction The current Sequoyah fuel handling accident analysis (occurring either inside containment or outside containment) uses the alternate source term (AST) methodology described in Regulatory Guide 1.183 (Reference 1). The analysis in this report revises the current analysis to 1) update the control room atmospheric dispersion factor associated with the auxiliary building stack point release, 2) delete consideration of the source term associated with tritium producing burnable absorber rods (TPBARs), 3) apply a linear source term release rate for the fuel handling accident inside containment and 4) establish the limiting containment purge isolation time. With the use of the AST methodology and the input/assumption changes discussed above, it was demonstrated that handling of spent fuel assemblies and performing core alterations is acceptable with no containment closure/isolation requirements (auxiliary building stack release point is limiting for control room doses), no restrictions on containment purge isolation time (immediate purge isolation is limiting) and no requirements on Auxiliary Building Gas Treatment System (ABGTS) operation (no credit taken for filtration of releases).

The bases for these conclusions are discussed further in the following report.

1.2 Dose Models and Timing Doses are determined at the exclusion area boundary (EAB) and at the low population zone boundary (LPZ) for the two-hour interval over which releases are assumed to take place and in the control room for an extended period of time after termination of releases in order to address the continued presence of activity in the control room atmosphere.

The accident doses were calculated using the dose model consistent with the use of the alternate source term methodology (Regulatory Guide 1.183) and are reported as Total Effective Dose Equivalent (TEDE).

The TEDE dose is the sum of the Committed Effective Dose Equivalent (CEDE) and the Effective Dose Equivalent (EDE) which are calculated using the following equations:

DCEDE = (A)(X/Q)(BR)(DCFCEDE)

DEDE = (A)(X/Q)(DCFEDE) where: A = Activity of the nuclide released (Ci)

X/Q = atmospheric dispersion factor (sec/m3)

BR = breathing rate (m3/sec)

DCFCEDE = CEDE dose conversion factor (rem/Ci inhaled)

DCFEDE = EDE dose conversion factor (rem-m3/Ci-s)

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3 Nuclide data is provided in Table 1. The decay constants for the iodines and noble gases were provided by TVA. The dose conversion factors for the CEDE doses are taken from Table 2.1 of EPA Federal Guidance Report No. 11 (Reference 2). The dose conversion factors for the EDE doses are from Table III.1 of EPA Federal Guidance Report No. 12 (Reference 3).

2.0 FUEL HANDLING ACCIDENT ANALYSIS A fuel assembly is assumed to be dropped and damaged during refueling. Activity released from the damaged assembly is released to the outside atmosphere through either the containment purge system or the fuel-handling building ventilation system to the auxiliary building vent stack.

2.1 Input Parameters and Assumptions The analysis of the radiological consequences following a fuel handling accident (FHA) uses the methodology outlined in Regulatory Guide 1.183 (Reference 1). The major assumptions and parameters used in the analysis are itemized in Table 2.

It is assumed that all of the fuel rods in the equivalent of one fuel assembly are damaged to the extent that all the gap activity in the rods is released. Also, the assembly inventory is based on the assumption that the subject fuel assembly has been operated at 1.7 times core average power.

The damaged fuel assembly is assumed to be one without TPBARs (Tritium Producing Burnable Absorber Rods), as operation with TPBARs is currently outside of the Sequoyah licensing basis.

The decay time prior to the accident is 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />.

The analysis assumes that the iodine released from the fuel is 99.85% elemental and 0.15%

organic. This is consistent with Regulatory Guide 1.183. The water pool provides retention of a large portion of the elemental iodine but there is no retention of the organic iodine credited.

From Regulatory Guide 1.183, a decontamination factor (DF) of 200 specified is applied to the overall iodine inventory released to the pool. No retention in the water pool is assumed for noble gases (DF = 1.0).

For the FHA occurring outside of containment, all of the activity released from the damaged fuel and not retained in the water pool is assumed to be released linearly from the pool to the environment within two hours. No credit is taken for filtration of iodine in the release path.

This allows the Auxiliary Building Gas Treatment System to be out of service during spent fuel handling operations.

For the FHA occurring inside containment that includes scenarios with and without containment isolation, all of the activity released from the damaged fuel and not retained in the water pool is assumed to be released linearly from pool to the environment within two hours.

Prior to isolation of the containment, it is assumed that the activity release from the pool is

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4 drawn into the containment purge system as it is released. No credit is taken for mixing in the containment volume or filtration by the purge system. After isolation of the containment purge line, it is assumed that the activity release from the pool is directed through the auxiliary vent stack. Based on a review of all containment penetrations as potential point source release locations (i.e., equipment hatch, access doors and containment pipe/cable penetrations), TVA established that the auxiliary building vent stack is the limiting location for calculation of control room doses based on its proximity to the control room air intake locations. As the EAB and LPZ doses are not sensitive to the specific reactor building /auxiliary building release points, application of the auxiliary building stack as the release point for evaluation of control room doses will bound all other release points. This allows any of the other containment penetrations to be open without closure/isolation requirements during fuel movement.

2.2 Acceptance Criteria The offsite dose limit is defined in Regulatory Guide 1.183 to be 6.3 rem TEDE and, from 10CFR50.67, the dose limit for the control room (CR) is 5.0 rem TEDE.

2.3 Results Either FHA (occurring in containment or in the auxiliary building) will have the same offsite doses since the accident occurring in different locations does not change the amount of activity released over the two-hour period.

EAB 2.8 rem TEDE LPZ 0.5 rem TEDE By isolating the containment purge early, at the start of the event, the accident occurring in containment will have identical results to the accident occurring in the auxiliary building. Early isolation of containment purge is conservative since an activity release through the auxiliary building vent stack to the CR has less atmospheric dispersion and more severe CR dose consequences than a containment purge release of activity to the CR. As such, there are no restrictions on the containment purge isolation timing.

FHA Occurring in the Auxiliary Building FHA Occurring inside Primary Containment with Early Isolation of Containment Purge System FHA Occurring inside Primary Containment with Delayed Isolation of Containment Purge System FHA Occurring inside Primary Containment with No Isolation of Containment Purge System Control room 0.6 rem TEDE 0.6 rem TEDE 0.4 rem TEDE 0.2 rem TEDE The doses are all within the acceptance criteria.

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5

3.0 REFERENCES

1. Regulatory Guide 1.183, Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors, July 2000
2. EPA Federal Guidance Report No. 11, Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion, EPA-520/1-88-020, September 1988
3. EPA Federal Guidance Report No. 12, External Exposure to Radionuclides in Air, Water, and Soil, EPA 402-R-93-081, September 1993

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6 Table 1: Nuclide Data Nuclide Decay Constant (hr-1)

Committed Effective Dose Equivalent DCF from EPA Federal Guidance Report No. 11 (rem/Ci inhaled)

Effective Dose Equivalent DCF from EPA Federal Guidance Report No.12 (rem-m3/Ci-s)

I-131 3.5833E-3 3.29E4 6.734E-2 I-132 3.0401E-1 3.81E2 4.144E-1 I-133 3.3320E-2 5.85E3 1.088E-1 I-135 1.0486E-1 1.23E3 2.953E-1 Kr-85 7.3692E-6 N/A 4.403E-4 Xe-131m 2.4269E-3 N/A 1.439E-3 Xe-133m 1.2836E-2 N/A 5.069E-3 Xe-133 5.4594E-3 N/A 5.772E-3 Xe-135 7.5755E-2 N/A 4.403E-2

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7 Table 2: Fuel Handling Accident Assumptions Delay after shutdown before fuel movement 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> Average fuel assembly activity in Curies at shutdown (no decay)1 I-131 4.90E5 I-132 7.18E5 I-133 1.01E6 I-135 9.65E5 Kr-85 5.35E3 Xe-131m 5.43E3 Xe-133m 3.19E4 Xe-133 9.92E5 Xe-135 3.33E5 Te-131m 9.62E4 Te-132 7.05E5 Radial peaking factor 1.7 Fuel rod gap fraction2 I-131 0.08 Kr-85 0.10 Other iodines and noble gases 0.05 Fuel damaged One assembly without TPBARs Iodine species split Elemental 99.85%

Organic 0.15%

Pool scrubbing factor Iodine 200 Noble gases 1

Offsite Dose Analysis Parameters Breathing rate 3.5E-4 m3/sec 1 Only the iodines and noble gases having a significant presence after 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> are included in the list. The Te-131m and Te-132 are included since they produce I-131 and I-132 respectively as decay products.

2 These gap fractions are dependent on limiting the high burnup fuel rods (>54,000 MWD/Mtu) to a maximum linear heat generation rate of 6.3 kw/ft, peak rod average power.

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8 Table 2 (continued)

Atmospheric dispersion factor EAB 8.59E-4 sec/m3 LPZ outer boundary 1.39E-4 sec/m3 FHA Outside Containment Release path filter efficiency for iodines No credit assumed Isolation of release path None Duration of releases 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> FHA Inside Containment with Early Isolation of Containment Purge System Release path filter efficiency for iodines None Isolation of purge release path Immediately Duration of releases via auxiliary building vent 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> FHA Inside Containment with Delayed Isolation of Containment Purge System Release path filter efficiency for iodines None Isolation of purge release path 300 seconds Duration of releases via auxiliary building vent 300 sec - 2 hr FHA Inside Containment with No Isolation of Containment Purge System Release path filter efficiency for iodines None Isolation of purge release path None Duration of releases 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Control Room Dose Analysis Parameters Volume 2.6E5 cubic feet Normal operation inflow (unfiltered) 3200 cfm Air intake high radiation setpoint to actuate HVAC emergency mode 400 cpm Time to switch to emergency mode after signal 5 min Emergency mode filtered intake flow 1000 cfm Emergency mode filtered recirculation flow 2600 cfm Filter efficiency for iodine 95%

Unfiltered inleakage 51 cfm Atmospheric dispersion factor (X/Q)

FHA outside containment (0 - 2 hr) 2.56E-3 sec/m3 FHA inside containment 0 sec - Purge isolation time 5.63E-4 sec/m3 Purge isolation time - 2 hr 2.56E-3 sec/m3

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9 Occupancy factor 0 - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 1.0 24 - 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> 0.6 96 - 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> 0.4 Breathing rate 3.5E-4 m3/sec

ATTACHMENT 2 TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 Fauske Report No. FAI/14-0989, Revision 2: Calculation of Atmospheric Dispersion Factors for Sequoyah Nuclear Plant



16W070 83rd Street

  • Burr Ridge, Illinois 60527 (877) Fauske1 or (630) 323-8750
  • Fax: (630) 986-5481
  • E-mail: Info@Fauske.com











































  

Calculation of Atmospheric Dispersion Factors for Sequoyah Nuclear Plant Revision 2





Wison Luangdilok



Paul McMinn



Westinghouse Electric Company Cranberry Twp., PA December, 2014

FA II 14-0989 Rev. 2 CALCULATION NOTE COVER SHEET (Revision 1)

SECTION TO BE COMPLETED BY AUTHOR(S):

Page 2 of 54 December, 2014 Calc-Note Number:

F Al/14-0989 Revision Number:

2

Title:

Calculation of Atmospheric Dispersion Factors for Sequoyah Nuclear Plant Project Number Project/

Subject:

Sequoyah Nuclear Plant Or Shop Order:

W-Seguoyah

Purpose:

Determine X/Q's for control room intake Methods of Analysis*:

ARCON96 under RG 1.194 Acceptance Criteria*:

See Section 2.2 Results Summary:

See Section l.O

  • Can beN/ A and/or a reference to this information in the Design Analysis can be provided.

References of Resulting Reports, Letters, or Memoranda (Optional)

Author(s):

Name (Print or Type)

Signature:

~kb.

Wison Luangdilok SECTION TO BE COMPLETED BY VERIFIER(S):

Verifier(s):

Name (Print or Type)

Paul B. McMinn Method of Verification:

Design Review D

Signature:

Independent Review or Alternate Calculations Completion Date:

12115/2014 Completion Date:

12/15/2014 D

Testing 0

3-Pass Method IZJ Other (specify):

0 SECTION TO BE COMPLETED BY MANAGER:

Responsible Manager:

Name (Print or Type)

Approval Date:

Chan Y. Paik 12/15/2014

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79$B/2*

Program

Title:

ARCON96.

Developed For: U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Reactor Program Management Date: June 25, 1997 11:00 a.m.

NRC Contacts: J. Y. Lee Phone: (301) 415 1080 e-mail: jyl1@nrc.gov J. J. Hayes Phone: (301) 415 3167 e-mail: jjh@nrc.gov L. A Brown Phone: (301) 415 1232 e-mail: lab2@nrc.gov Code Developer: J. V. Ramsdell Phone: (509) 372 6316 e-mail: j_ramsdell@pnl.gov Code Documentation: NUREG/CR-6331 Rev. 1 The program was prepared for an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibilities for any third party's use, or the results of such use, of any portion of this program or represents that its use by such third party would not infringe privately owned rights.

Program Run 11/12/2014 at 08:25:01

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79$B/2*

              • ARCON INPUT **********

Number of Meteorological Data Files = 10 Meteorological Data File Names sqn2004.met sqn2005.met sqn2006.met sqn2007.met sqn2008.met sqn2009.met sqn2010.met sqn2011.met sqn2012.met sqn2013.met Height of lower wind instrument (m) = 9.7 Height of upper wind instrument (m) = 46.4 Wind speeds entered as miles per hour Ground-level release Release height (m) = 32.5 Building Area (m^2) = 1744.7 Effluent vertical velocity (m/s) = 0.00 Vent or stack flow (m^3/s) = 0.00 Vent or stack radius (m) = 0.00 Direction.. intake to source (deg) = 187 Wind direction sector width (deg) = 90 Wind direction window (deg) = 142 - 232 Distance to intake (m) = 45.4 Intake height (m) = 14.3 Terrain elevation difference (m) = 0.0 Output file names TVA_187.log

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TVA_187.cfd Minimum Wind Speed (m/s) = 0.5 Surface roughness length (m) = 0.20 Sector averaging constant = 4.3 Initial value of sigma y = 0.00 Initial value of sigma z = 0.00 Expanded output for code testing not selected Total number of hours of data processed = 87672 Hours of missing data = 1086 Hours direction in window = 33711 Hours elevated plume w/ dir. in window = 0 Hours of calm winds = 3480 Hours direction not in window or calm = 49395 DISTRIBUTION

SUMMARY

DATA BY AVERAGING INTERVAL AVER. PER. 1 2 4 8 12 24 96 168 360 720 UPPER LIM. 1.00E-02 1.00E-02 1.00E-02 1.00E-02 1.00E-02 1.00E-02 1.00E-02 1.00E-02 1.00E-02 1.00E-02 LOW LIM. 1.00E-06 1.00E-06 1.00E-06 1.00E-06 1.00E-06 1.00E-06 1.00E-06 1.00E-06 1.00E-06 1.00E-06 ABOVE RANGE 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.

IN RANGE 37191. 41990. 47718. 54466. 60486. 70175. 84153. 85227. 85735. 85855.

BELOW RANGE 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.

ZERO 49395. 44209. 37746. 29629. 24657. 14649. 662. 32. 0. 0.

TOTAL X/Qs 86586. 86199. 85464. 84095. 85143. 84824. 84815. 85259. 85735. 85855.

% NON ZERO 42.95 48.71 55.83 64.77 71.04 82.73 99.22 99.96 100.00 100.00 95th PERCENTILE X/Q VALUES 2.56E-03 2.49E-03 2.42E-03 2.29E-03 1.91E-03 1.46E-03 9.50E-04 8.20E-04 7.08E-04 6.47E-04 95% X/Q for standard averaging intervals 0 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 2.56E-03 2 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 2.20E-03

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8 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 1.04E-03 1 to 4 days 7.80E-04 4 to 30 days 6.01E-04 HOURLY VALUE RANGE MAX X/Q MIN X/Q CENTERLINE 3.31E-03 2.34E-04 SECTOR-AVERAGE 1.93E-03 1.37E-04 NORMAL PROGRAM COMPLETION









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79$B/2*

Program

Title:

ARCON96.

Developed For: U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Reactor Program Management Date: June 25, 1997 11:00 a.m.

NRC Contacts: J. Y. Lee Phone: (301) 415 1080 e-mail: jyl1@nrc.gov J. J. Hayes Phone: (301) 415 3167 e-mail: jjh@nrc.gov L. A Brown Phone: (301) 415 1232 e-mail: lab2@nrc.gov Code Developer: J. V. Ramsdell Phone: (509) 372 6316 e-mail: j_ramsdell@pnl.gov Code Documentation: NUREG/CR-6331 Rev. 1 The program was prepared for an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibilities for any third party's use, or the results of such use, of any portion of this program or represents that its use by such third party would not infringe privately owned rights.

Program Run 11/11/2014 at 10:46:04

              • ARCON INPUT **********

Number of Meteorological Data Files = 10 Meteorological Data File Names

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sqn2004.met sqn2005.met sqn2006.met sqn2007.met sqn2008.met sqn2009.met sqn2010.met sqn2011.met sqn2012.met sqn2013.met Height of lower wind instrument (m) = 9.7 Height of upper wind instrument (m) = 46.4 Wind speeds entered as miles per hour Ground-level release Release height (m) = 32.5 Building Area (m^2) = 1744.7 Effluent vertical velocity (m/s) = 0.00 Vent or stack flow (m^3/s) = 0.00 Vent or stack radius (m) = 0.00 Direction.. intake to source (deg) = 083 Wind direction sector width (deg) = 90 Wind direction window (deg) = 038 - 128 Distance to intake (m) = 37.9 Intake height (m) = 14.3 Terrain elevation difference (m) = 0.0 Output file names TVA_083.log TVA_083.cfd Minimum Wind Speed (m/s) = 0.5 Surface roughness length (m) = 0.20 Sector averaging constant = 4.3

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Initial value of sigma y = 0.00 Initial value of sigma z = 0.00 Expanded output for code testing not selected Total number of hours of data processed = 87672 Hours of missing data = 1086 Hours direction in window = 7383 Hours elevated plume w/ dir. in window = 0 Hours of calm winds = 3480 Hours direction not in window or calm = 75723 DISTRIBUTION

SUMMARY

DATA BY AVERAGING INTERVAL AVER. PER. 1 2 4 8 12 24 96 168 360 720 UPPER LIM. 1.00E-02 1.00E-02 1.00E-02 1.00E-02 1.00E-02 1.00E-02 1.00E-02 1.00E-02 1.00E-02 1.00E-02 LOW LIM. 1.00E-06 1.00E-06 1.00E-06 1.00E-06 1.00E-06 1.00E-06 1.00E-06 1.00E-06 1.00E-06 1.00E-06 ABOVE RANGE 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.

IN RANGE 10863. 16348. 24255. 35068. 43680. 59008. 82832. 85198. 85735. 85855.

BELOW RANGE 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.

ZERO 75723. 69851. 61209. 49027. 41463. 25816. 1983. 61. 0. 0.

TOTAL X/Qs 86586. 86199. 85464. 84095. 85143. 84824. 84815. 85259. 85735. 85855.

% NON ZERO 12.55 18.97 28.38 41.70 51.30 69.57 97.66 99.93 100.00 100.00 95th PERCENTILE X/Q VALUES 1.57E-03 1.27E-03 1.05E-03 8.75E-04 6.88E-04 4.67E-04 2.88E-04 2.47E-04 2.13E-04 1.91E-04 95% X/Q for standard averaging intervals 0 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 1.57E-03 2 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 6.45E-04 8 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 2.64E-04 1 to 4 days 2.28E-04 4 to 30 days 1.76E-04 HOURLY VALUE RANGE

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MAX X/Q MIN X/Q CENTERLINE 4.18E-03 3.72E-04 SECTOR-AVERAGE 2.44E-03 2.17E-04 NORMAL PROGRAM COMPLETION







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APPENDIX B:Software Installation and Validation 7KHH[DPSOHSUREOHPVSUHVHQWHGLQ5HIHUHQFHZKHUHUXQRQDORFDO3&DVGHVFULEHGLQ6HFWLRQ

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C:\\LIBRARY\\SEQUOYAH\\DOCUMENTATION\\SOFTWARE>DIR Volume in drive C is OSDisk Volume Serial Number is A077-018D Directory of C:\\LIBRARY\\SEQUOYAH\\DOCUMENTATION\\SOFTWARE 11/11/2014 11:02 AM <DIR>.

11/11/2014 11:02 AM <DIR>..

11/11/2014 11:00 AM <DIR> 1997 10/29/2014 01:10 PM 480 ARCON32.BAT 03/30/2004 09:44 AM 630,784 ARCON_WIN32.exe 04/01/1995 06:00 AM 324,120 EXAMPLE.MET 03/01/2004 12:53 PM 4,829 FAI1_96.log 10/29/2014 01:10 PM 11,168 FAI1_96_2014.cfd 10/29/2014 01:10 PM 4,829 FAI1_96_2014.log 10/29/2014 01:09 PM 408 FAI1_96_2014.RSF 10/29/2014 01:10 PM 11,168 FAI2_96_2014.cfd 10/29/2014 01:10 PM 4,829 FAI2_96_2014.log 10/29/2014 01:09 PM 408 FAI2_96_2014.RSF 10/29/2014 01:10 PM 11,168 FAI3_96_2014.cfd 10/29/2014 01:10 PM 4,829 FAI3_96_2014.log 10/29/2014 01:09 PM 408 FAI3_96_2014.RSF 10/29/2014 01:10 PM 11,168 FAI4_96_2014.cfd 10/29/2014 01:10 PM 4,834 FAI4_96_2014.log 10/29/2014 01:09 PM 408 FAI4_96_2014.RSF 10/29/2014 01:10 PM 11,168 FAI5a_96_2014.cfd 10/29/2014 01:10 PM 4,829 FAI5a_96_2014.log 10/29/2014 01:09 PM 408 FAI5A_96_2014.RSF 10/29/2014 01:10 PM 11,168 FAI5b_96_2014.cfd 10/29/2014 01:10 PM 4,829 FAI5b_96_2014.log 10/29/2014 01:09 PM 408 FAI5B_96_2014.RSF 10/29/2014 01:10 PM 11,168 FAI5c_96_2014.cfd 10/29/2014 01:10 PM 4,829 FAI5c_96_2014.log 10/29/2014 01:09 PM 408 FAI5C_96_2014.RSF 10/29/2014 01:10 PM 11,168 FAI5d_96_2014.cfd 10/29/2014 01:10 PM 4,829 FAI5d_96_2014.log 10/29/2014 01:09 PM 408 FAI5D_96_2014.RSF 10/29/2014 01:10 PM 11,168 FAI5e_96_2014.cfd

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10/29/2014 01:10 PM 4,829 FAI5e_96_2014.log 10/29/2014 01:09 PM 408 FAI5E_96_2014.RSF 10/29/2014 01:10 PM 11,168 FAI5f_96_2014.cfd 10/29/2014 01:10 PM 4,829 FAI5f_96_2014.log 10/29/2014 01:09 PM 408 FAI5F_96_2014.RSF 10/29/2014 01:19 PM 655 FC_ARCON32.BAT 11/11/2014 11:03 AM 467 FC_ARCON32_VV.BAT 11/11/2014 09:28 AM 123 OutputTest.bat 10/29/2014 01:10 PM 11,168 PI-11A_2014.cfd 10/29/2014 01:10 PM 5,034 PI-11A_2014.log 10/29/2014 01:09 PM 576 PI-11A_2014.RSF 10/29/2014 01:10 PM 11,168 PI-11b_2014.cfd 10/29/2014 01:10 PM 5,034 PI-11b_2014.log 10/29/2014 01:09 PM 1,418 PI-11B_2014.RSF 10/29/2014 01:10 PM 11,168 PI-12a_2014.cfd 10/29/2014 01:10 PM 5,034 PI-12a_2014.log 10/29/2014 01:09 PM 576 PI-12A_2014.RSF 03/31/2004 07:59 AM 398 PI-TEST2.RSF 09/14/2000 09:09 PM 332,880 Pi93.met 09/14/2000 09:08 PM 332,880 Pi94.met 09/14/2000 09:08 PM 332,880 Pi95.met 09/14/2000 09:08 PM 332,880 Pi96.met 09/14/2000 09:07 PM 332,880 Pi97.met 10/29/2014 01:07 PM <DIR> PREVIOUS 11/11/2014 09:29 AM 29,641 TestData.dat 11/11/2014 11:03 AM 0 Validation.dat 54 File(s) 2,871,128 bytes 4 Dir(s) 102,043,660,288 bytes free C:\\LIBRARY\\SEQUOYAH\\DOCUMENTATION\\SOFTWARE>FC FAI1_96_2014.LOG 1997\\EX1_96.LOG Comparing files FAI1_96_2014.log and 1997\\EX1_96.LOG

          • FAI1_96_2014.log Date: June 25, 1997 11:00 a.m.
          • 1997\\EX1_96.LOG Date: May 9, 1997 3:00 p.m.
          • FAI1_96_2014.log Program Run 10/29/2014 at 14:10:57
          • 1997\\EX1_96.LOG Program Run 5/ 9/1997 at 15:03:19

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          • FAI1_96_2014.log Ground-level release Release height (m) = 0.0 Building Area (m^2) = 1900.0 Effluent vertical velocity (m/s) = 0.00 Vent or stack flow (m^3/s) = 0.00 Vent or stack radius (m) = 0.00
          • 1997\\EX1_96.LOG Ground-level release Release height (m) =.0 Building Area (m^2) = 1900.0 Effluent vertical velocity (m/s) =.00 Vent or stack flow (m^3/s) =.00 Vent or stack radius (m) =.00
          • FAI1_96_2014.log Intake height (m) = 15.0 Terrain elevation difference (m) = 0.0
          • 1997\\EX1_96.LOG Intake height (m) = 15.0 Terrain elevation difference (m) =.0
          • FAI1_96_2014.log Output file names FAI1_96_2014.log FAI1_96_2014.cfd Minimum Wind Speed (m/s) = 0.5 Surface roughness length (m) = 0.10 Sector averaging constant = 4.0
          • 1997\\EX1_96.LOG Output file names ex1_96.log ex1_96.cfd Minimum Wind Speed (m/s) =.5 Surface roughness length (m) =.10 Sector averaging constant = 4.0
          • FAI1_96_2014.log Initial value of sigma y = 0.00 Initial value of sigma z = 0.00

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          • 1997\\EX1_96.LOG Initial value of sigma y =.00 Initial value of sigma z =.00 C:\\LIBRARY\\SEQUOYAH\\DOCUMENTATION\\SOFTWARE>FC FAI2_96_2014.LOG 1997\\EX2_96.LOG Comparing files FAI2_96_2014.log and 1997\\EX2_96.LOG
          • FAI2_96_2014.log Date: June 25, 1997 11:00 a.m.
          • 1997\\EX2_96.LOG Date: May 9, 1997 3:00 p.m.
          • FAI2_96_2014.log Program Run 10/29/2014 at 14:10:57
          • 1997\\EX2_96.LOG Program Run 5/ 9/1997 at 15:03:28
          • FAI2_96_2014.log Intake height (m) = 25.0 Terrain elevation difference (m) = 0.0
          • 1997\\EX2_96.LOG Intake height (m) = 25.0 Terrain elevation difference (m) =.0
          • FAI2_96_2014.log Output file names FAI2_96_2014.log FAI2_96_2014.cfd Minimum Wind Speed (m/s) = 0.5 Surface roughness length (m) = 0.10 Sector averaging constant = 4.0
          • 1997\\EX2_96.LOG Output file names ex2_96.log

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ex2_96.cfd Minimum Wind Speed (m/s) =.5 Surface roughness length (m) =.10 Sector averaging constant = 4.0

          • FAI2_96_2014.log Initial value of sigma y = 0.00 Initial value of sigma z = 0.00
          • 1997\\EX2_96.LOG Initial value of sigma y =.00 Initial value of sigma z =.00
          • FAI2_96_2014.log 95th PERCENTILE X/Q VALUES 1.94E-03 1.93E-03 1.87E-03 1.77E-03 1.52E-03 1.10E-03 6.79E-04 5.40E-04 4.28E-04 3.28E-04
          • 1997\\EX2_96.LOG 95th PERCENTILE X/Q VALUES 1.94E-03 1.93E-03 1.87E-03 1.76E-03 1.52E-03 1.10E-03 6.79E-04 5.40E-04 4.28E-04 3.28E-04 C:\\LIBRARY\\SEQUOYAH\\DOCUMENTATION\\SOFTWARE>FC FAI3_96_2014.LOG 1997\\EX3_96.LOG Comparing files FAI3_96_2014.log and 1997\\EX3_96.LOG
          • FAI3_96_2014.log Date: June 25, 1997 11:00 a.m.
          • 1997\\EX3_96.LOG Date: May 9, 1997 3:00 p.m.
          • FAI3_96_2014.log Program Run 10/29/2014 at 14:10:57
          • 1997\\EX3_96.LOG Program Run 5/ 9/1997 at 15:03:36

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          • FAI3_96_2014.log Building Area (m^2) = 1730.0 Effluent vertical velocity (m/s) = 0.00 Vent or stack flow (m^3/s) = 15.70
          • 1997\\EX3_96.LOG Building Area (m^2) = 1730.0 Effluent vertical velocity (m/s) =.00 Vent or stack flow (m^3/s) = 15.70
          • FAI3_96_2014.log Intake height (m) = 25.0 Terrain elevation difference (m) = 0.0
          • 1997\\EX3_96.LOG Intake height (m) = 25.0 Terrain elevation difference (m) =.0
          • FAI3_96_2014.log Output file names FAI3_96_2014.log FAI3_96_2014.cfd Minimum Wind Speed (m/s) = 0.5 Surface roughness length (m) = 0.10 Sector averaging constant = 4.0
          • 1997\\EX3_96.LOG Output file names ex3_96.log ex3_96.cfd Minimum Wind Speed (m/s) =.5 Surface roughness length (m) =.10 Sector averaging constant = 4.0
          • FAI3_96_2014.log Initial value of sigma y = 0.00 Initial value of sigma z = 0.00
          • 1997\\EX3_96.LOG Initial value of sigma y =.00 Initial value of sigma z =.00

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          • FAI3_96_2014.log 2 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 8.12E-03 8 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 4.01E-03 1 to 4 days 3.03E-03
          • 1997\\EX3_96.LOG 2 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 8.12E-03 8 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 4.00E-03 1 to 4 days 3.03E-03
          • FAI3_96_2014.log CENTERLINE 1.61E-02 3.99E-03 SECTOR-AVERAGE 1.12E-02 2.56E-03
          • 1997\\EX3_96.LOG CENTERLINE 1.61E-02 3.99E-03 SECTOR-AVERAGE 1.11E-02 2.56E-03 C:\\LIBRARY\\SEQUOYAH\\DOCUMENTATION\\SOFTWARE>FC FAI4_96_2014.LOG 1997\\EX4_96.LOG Comparing files FAI4_96_2014.log and 1997\\EX4_96.LOG
          • FAI4_96_2014.log Date: June 25, 1997 11:00 a.m.
          • 1997\\EX4_96.LOG Date: May 9, 1997 3:00 p.m.
          • FAI4_96_2014.log Program Run 10/29/2014 at 14:10:57
          • 1997\\EX4_96.LOG Program Run 5/ 9/1997 at 15:03:44
          • FAI4_96_2014.log Release height (m) = 65.0 Building Area (m^2) = 0.0 Effluent vertical velocity (m/s) = 10.00
          • 1997\\EX4_96.LOG Release height (m) = 65.0

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Building Area (m^2) =.0 Effluent vertical velocity (m/s) = 10.00

          • FAI4_96_2014.log Intake height (m) = 25.0 Terrain elevation difference (m) = 0.0
          • 1997\\EX4_96.LOG Intake height (m) = 25.0 Terrain elevation difference (m) =.0
          • FAI4_96_2014.log Output file names FAI4_96_2014.log FAI4_96_2014.cfd Minimum Wind Speed (m/s) = 0.5 Surface roughness length (m) = 0.10 Sector averaging constant = 4.0
          • 1997\\EX4_96.LOG Output file names ex4_96.log ex4_96.cfd Minimum Wind Speed (m/s) =.5 Surface roughness length (m) =.10 Sector averaging constant = 4.0
          • FAI4_96_2014.log Initial value of sigma y = 0.00 Initial value of sigma z = 0.00
          • 1997\\EX4_96.LOG Initial value of sigma y =.00 Initial value of sigma z =.00 C:\\LIBRARY\\SEQUOYAH\\DOCUMENTATION\\SOFTWARE>FC FAI5A_96_2014.LOG 1997\\EX5A_96.LOG Comparing files FAI5a_96_2014.log and 1997\\EX5A_96.LOG
          • FAI5a_96_2014.log Date: June 25, 1997 11:00 a.m.

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          • 1997\\EX5A_96.LOG Date: May 9, 1997 3:00 p.m.
          • FAI5a_96_2014.log Program Run 10/29/2014 at 14:10:57
          • 1997\\EX5A_96.LOG Program Run 5/ 9/1997 at 15:03:54
          • FAI5a_96_2014.log Building Area (m^2) = 1500.0 Effluent vertical velocity (m/s) = 0.00 Vent or stack flow (m^3/s) = 5.00 Vent or stack radius (m) = 0.50
          • 1997\\EX5A_96.LOG Building Area (m^2) = 1500.0 Effluent vertical velocity (m/s) =.00 Vent or stack flow (m^3/s) = 5.00 Vent or stack radius (m) =.50
          • FAI5a_96_2014.log Intake height (m) = 23.0 Terrain elevation difference (m) = 0.0
          • 1997\\EX5A_96.LOG Intake height (m) = 23.0 Terrain elevation difference (m) =.0
          • FAI5a_96_2014.log Output file names FAI5a_96_2014.log FAI5a_96_2014.cfd Minimum Wind Speed (m/s) = 0.5 Surface roughness length (m) = 0.10 Sector averaging constant = 4.0
          • 1997\\EX5A_96.LOG Output file names ex5a_96.log

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ex5a_96.cfd Minimum Wind Speed (m/s) =.5 Surface roughness length (m) =.10 Sector averaging constant = 4.0

          • FAI5a_96_2014.log Initial value of sigma y = 0.00 Initial value of sigma z = 0.00
          • 1997\\EX5A_96.LOG Initial value of sigma y =.00 Initial value of sigma z =.00 C:\\LIBRARY\\SEQUOYAH\\DOCUMENTATION\\SOFTWARE>FC FAI5B_96_2014.LOG 1997\\EX5B_96.LOG Comparing files FAI5b_96_2014.log and 1997\\EX5B_96.LOG
          • FAI5b_96_2014.log Date: June 25, 1997 11:00 a.m.
          • 1997\\EX5B_96.LOG Date: May 9, 1997 3:00 p.m.
          • FAI5b_96_2014.log Program Run 10/29/2014 at 14:10:57
          • 1997\\EX5B_96.LOG Program Run 5/ 9/1997 at 15:04:01
          • FAI5b_96_2014.log Building Area (m^2) = 1500.0 Effluent vertical velocity (m/s) = 0.00 Vent or stack flow (m^3/s) = 5.00 Vent or stack radius (m) = 0.50
          • 1997\\EX5B_96.LOG Building Area (m^2) = 1500.0 Effluent vertical velocity (m/s) =.00

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Vent or stack flow (m^3/s) = 5.00 Vent or stack radius (m) =.50

          • FAI5b_96_2014.log Intake height (m) = 23.0 Terrain elevation difference (m) = 0.0
          • 1997\\EX5B_96.LOG Intake height (m) = 23.0 Terrain elevation difference (m) =.0
          • FAI5b_96_2014.log Output file names FAI5b_96_2014.log FAI5b_96_2014.cfd Minimum Wind Speed (m/s) = 0.5 Surface roughness length (m) = 0.10 Sector averaging constant = 4.0
          • 1997\\EX5B_96.LOG Output file names ex5b_96.log ex5b_96.cfd Minimum Wind Speed (m/s) =.5 Surface roughness length (m) =.10 Sector averaging constant = 4.0
          • FAI5b_96_2014.log Initial value of sigma y = 0.00 Initial value of sigma z = 0.00
          • 1997\\EX5B_96.LOG Initial value of sigma y =.00 Initial value of sigma z =.00 C:\\LIBRARY\\SEQUOYAH\\DOCUMENTATION\\SOFTWARE>FC FAI5C_96_2014.LOG 1997\\EX5C_96.LOG Comparing files FAI5c_96_2014.log and 1997\\EX5C_96.LOG
          • FAI5c_96_2014.log Date: June 25, 1997 11:00 a.m.

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          • 1997\\EX5C_96.LOG Date: May 9, 1997 3:00 p.m.
          • FAI5c_96_2014.log Program Run 10/29/2014 at 14:10:57
          • 1997\\EX5C_96.LOG Program Run 5/ 9/1997 at 15:04:09
          • FAI5c_96_2014.log Building Area (m^2) = 1500.0 Effluent vertical velocity (m/s) = 0.00 Vent or stack flow (m^3/s) = 5.00 Vent or stack radius (m) = 0.50
          • 1997\\EX5C_96.LOG Building Area (m^2) = 1500.0 Effluent vertical velocity (m/s) =.00 Vent or stack flow (m^3/s) = 5.00 Vent or stack radius (m) =.50
          • FAI5c_96_2014.log Intake height (m) = 23.0 Terrain elevation difference (m) = 0.0
          • 1997\\EX5C_96.LOG Intake height (m) = 23.0 Terrain elevation difference (m) =.0
          • FAI5c_96_2014.log Output file names FAI5c_96_2014.log FAI5c_96_2014.cfd Minimum Wind Speed (m/s) = 0.5 Surface roughness length (m) = 0.10 Sector averaging constant = 4.0
          • 1997\\EX5C_96.LOG Output file names

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ex5c_96.log ex5c_96.cfd Minimum Wind Speed (m/s) =.5 Surface roughness length (m) =.10 Sector averaging constant = 4.0

          • FAI5c_96_2014.log Initial value of sigma y = 0.00 Initial value of sigma z = 0.00
          • 1997\\EX5C_96.LOG Initial value of sigma y =.00 Initial value of sigma z =.00 C:\\LIBRARY\\SEQUOYAH\\DOCUMENTATION\\SOFTWARE>FC FAI5D_96_2014.LOG 1997\\EX5D_96.LOG Comparing files FAI5d_96_2014.log and 1997\\EX5D_96.LOG
          • FAI5d_96_2014.log Date: June 25, 1997 11:00 a.m.
          • 1997\\EX5D_96.LOG Date: May 9, 1997 3:00 p.m.
          • FAI5d_96_2014.log Program Run 10/29/2014 at 14:10:58
          • 1997\\EX5D_96.LOG Program Run 5/ 9/1997 at 15:04:17
          • FAI5d_96_2014.log Building Area (m^2) = 1500.0 Effluent vertical velocity (m/s) = 0.00 Vent or stack flow (m^3/s) = 5.00 Vent or stack radius (m) = 0.50
          • 1997\\EX5D_96.LOG Building Area (m^2) = 1500.0

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Effluent vertical velocity (m/s) =.00 Vent or stack flow (m^3/s) = 5.00 Vent or stack radius (m) =.50

          • FAI5d_96_2014.log Intake height (m) = 23.0 Terrain elevation difference (m) = 0.0
          • 1997\\EX5D_96.LOG Intake height (m) = 23.0 Terrain elevation difference (m) =.0
          • FAI5d_96_2014.log Output file names FAI5d_96_2014.log FAI5d_96_2014.cfd Minimum Wind Speed (m/s) = 0.5 Surface roughness length (m) = 0.10 Sector averaging constant = 4.0
          • 1997\\EX5D_96.LOG Output file names ex5d_96.log ex5d_96.cfd Minimum Wind Speed (m/s) =.5 Surface roughness length (m) =.10 Sector averaging constant = 4.0
          • FAI5d_96_2014.log Initial value of sigma y = 0.00 Initial value of sigma z = 0.00
          • 1997\\EX5D_96.LOG Initial value of sigma y =.00 Initial value of sigma z =.00 C:\\LIBRARY\\SEQUOYAH\\DOCUMENTATION\\SOFTWARE>FC FAI5E_96_2014.LOG 1997\\EX5E_96.LOG Comparing files FAI5e_96_2014.log and 1997\\EX5E_96.LOG
          • FAI5e_96_2014.log

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Date: June 25, 1997 11:00 a.m.

          • 1997\\EX5E_96.LOG Date: May 9, 1997 3:00 p.m.
          • FAI5e_96_2014.log Program Run 10/29/2014 at 14:10:58
          • 1997\\EX5E_96.LOG Program Run 5/ 9/1997 at 15:04:23
          • FAI5e_96_2014.log Building Area (m^2) = 1500.0 Effluent vertical velocity (m/s) = 0.00 Vent or stack flow (m^3/s) = 60.00
          • 1997\\EX5E_96.LOG Building Area (m^2) = 1500.0 Effluent vertical velocity (m/s) =.00 Vent or stack flow (m^3/s) = 60.00
          • FAI5e_96_2014.log Intake height (m) = 23.0 Terrain elevation difference (m) = 0.0
          • 1997\\EX5E_96.LOG Intake height (m) = 23.0 Terrain elevation difference (m) =.0
          • FAI5e_96_2014.log Output file names FAI5e_96_2014.log FAI5e_96_2014.cfd Minimum Wind Speed (m/s) = 0.5 Surface roughness length (m) = 0.10 Sector averaging constant = 4.0
          • 1997\\EX5E_96.LOG Output file names ex5e_96.log ex5e_96.cfd

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Minimum Wind Speed (m/s) =.5 Surface roughness length (m) =.10 Sector averaging constant = 4.0 C:\\LIBRARY\\SEQUOYAH\\DOCUMENTATION\\SOFTWARE>FC FAI5E_96_2014.LOG 1997\\EX5E_96.LOG Comparing files FAI5e_96_2014.log and 1997\\EX5E_96.LOG

          • FAI5e_96_2014.log Date: June 25, 1997 11:00 a.m.
          • 1997\\EX5E_96.LOG Date: May 9, 1997 3:00 p.m.
          • FAI5e_96_2014.log Program Run 10/29/2014 at 14:10:58
          • 1997\\EX5E_96.LOG Program Run 5/ 9/1997 at 15:04:23
          • FAI5e_96_2014.log Building Area (m^2) = 1500.0 Effluent vertical velocity (m/s) = 0.00 Vent or stack flow (m^3/s) = 60.00
          • 1997\\EX5E_96.LOG Building Area (m^2) = 1500.0 Effluent vertical velocity (m/s) =.00 Vent or stack flow (m^3/s) = 60.00
          • FAI5e_96_2014.log Intake height (m) = 23.0 Terrain elevation difference (m) = 0.0
          • 1997\\EX5E_96.LOG Intake height (m) = 23.0 Terrain elevation difference (m) =.0
          • FAI5e_96_2014.log Output file names FAI5e_96_2014.log

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FAI5e_96_2014.cfd Minimum Wind Speed (m/s) = 0.5 Surface roughness length (m) = 0.10 Sector averaging constant = 4.0

          • 1997\\EX5E_96.LOG Output file names ex5e_96.log ex5e_96.cfd Minimum Wind Speed (m/s) =.5 Surface roughness length (m) =.10 Sector averaging constant = 4.0 C:\\LIBRARY\\SEQUOYAH\\DOCUMENTATION\\SOFTWARE>FC FAI5F_96_2014.LOG 1997\\EX5F_96.LOG Comparing files FAI5f_96_2014.log and 1997\\EX5F_96.LOG
          • FAI5f_96_2014.log Date: June 25, 1997 11:00 a.m.
          • 1997\\EX5F_96.LOG Date: May 9, 1997 3:00 p.m.
          • FAI5f_96_2014.log Program Run 10/29/2014 at 14:10:58
          • 1997\\EX5F_96.LOG Program Run 5/ 9/1997 at 15:04:32
          • FAI5f_96_2014.log Building Area (m^2) = 1500.0 Effluent vertical velocity (m/s) = 0.00 Vent or stack flow (m^3/s) = 20.00
          • 1997\\EX5F_96.LOG Building Area (m^2) = 1500.0 Effluent vertical velocity (m/s) =.00 Vent or stack flow (m^3/s) = 20.00
          • FAI5f_96_2014.log Intake height (m) = 23.0 Terrain elevation difference (m) = 0.0

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          • 1997\\EX5F_96.LOG Intake height (m) = 23.0 Terrain elevation difference (m) =.0
          • FAI5f_96_2014.log Output file names FAI5f_96_2014.log FAI5f_96_2014.cfd Minimum Wind Speed (m/s) = 0.5 Surface roughness length (m) = 0.10 Sector averaging constant = 4.0
          • 1997\\EX5F_96.LOG Output file names ex5f_96.log ex5f_96.cfd Minimum Wind Speed (m/s) =.5 Surface roughness length (m) =.10 Sector averaging constant = 4.0

















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