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Category:ARCHIVE RECORDS
MONTHYEARML18039A6231998-11-18018 November 1998
Rev 0 to Calculation MD-Q0999-970046, NPSH Evaluation of Browns Ferry RHR & CS Pumps.
ML18039A6271998-11-10010 November 1998
Rev 1 to 50147-C-012, HCLPF Calculations for Selected Blockwalls.
ML18039A5571998-10-0404 October 1998
Rev 0 to CD-Q3068-980061, Evaluation of IGSCC Indication at Weld GR-3-63.
ML18039A5391998-09-0303 September 1998
Rev 1 to CD-Q0082-970020, Eqe Evaluation A-46 Outliers to DG Neutral Ground Transformers.
ML20217Q6921998-04-23023 April 1998
Rev R8 to Calculation ND-Q0031-920075, Control Room Doses
ML20217A5111998-03-24024 March 1998
Rev 4 to Calculation MD-Q-0999-920136, Post Accident Primary Containment Penetration Isolated Piping Over Pressure Analysis
ML18039A5341997-08-13013 August 1997
Rev 2 to CD-Q2999-940343, Qualification of Cable Tray & Conduit Systems by A-46 Program.
ML18039A5411996-12-0101 December 1996
Rev 0 to 50147-C-003, Outlier & HCLPF Evaluations for RHR Pump Anchorage.
ML20129C0761996-10-23023 October 1996
Press Release II-96-88, NRC Staff Issues Assessment of Performance at Browns Ferry Nuclear Power Plant in Al
ML20129D6391996-09-25025 September 1996
Rev 2 to Calculation Package for Application of Revised DBA Source Term to Browns Ferry Nuclear Power Plant
ML18039A5441996-08-0606 August 1996
Rev 0 to CD-Q3071-960089, Verification of Anchorage for Panel 3-25-31 to Resolve Outlier Identified by USI A-46 Evaluation (Ssel #39204).
ML18039A6261996-07-15015 July 1996
Rev 1 to 50147-C-011, HCLPF Calculations for Electrical Equipment on A-46 Safe Shutdown Equipment List.
ML20129D8441996-06-13013 June 1996
Rev 1 to Addl Radionuclide Data
ML20129D8191996-06-13013 June 1996
Rev 1 to Suppression Pool Scrubbing Efficency (Including Pool Bypass)
ML20129D8101996-06-13013 June 1996
Rev 1 to Max Elemental I Decontamination Factors
ML20129D7601996-06-13013 June 1996
Rev 2 to Volumetric Flowrate as Function of Time from Drywell to Torus (& Return)
ML20129D8911996-05-27027 May 1996
Rev 1 to Aerosol Decontamination Factor in Main Steam Lines & Condenser
ML18039A5331996-05-0303 May 1996
Rev 0 to 50147-C-004, Bfnd A-46/IPEEE Outlier Evaluation - RHR Heat Exchangers.
ML18039A5361996-04-15015 April 1996
Rev 6 to CD-Q0000-931227, Qualification of Cable Tray & Conduit Systems by A-46 Program.
ML18039A5381996-02-24024 February 1996
Rev 0 to 50147-C-006, GE 7700 MCC Seismic Capacity Vs Demand - Outlier Resolution.
ML20205K7891996-02-15015 February 1996
Press Release II-96-21, NRC Saff Proposed $80,000 Civil Penalty Against TVA for Alleged Discrimination at Browns Ferry
ML18038B6651996-02-0505 February 1996
Non-proprietary Calculations for Application of Revised DBA Source Term to Browns Ferry Nuclear Power Plant.
ML18039A6251995-10-16016 October 1995
Rev 1 to CD-Q0000-940339, Calculation of Basic Parameters for A46 & IPEEE Seismic Program.
ML18039A5431995-10-0101 October 1995
Rev 0 to 50147-C-002, MSIV Outlier Resolution.
ML18038B6661995-09-29029 September 1995
Non-proprietary Calculation of Containment Leakage Doses for Browns Ferry Nuclear Power Plant.
ML20129D8981995-09-28028 September 1995
Rev 0 to Elemental I Filter Efficiency in Main Steam Lines
ML20129D8741995-09-27027 September 1995
Rev 0 to Source Term for Use on Browns Ferry Application of NUREG-1465
ML20129D7371995-09-22022 September 1995
Rev 2 to Design Data Base for Application of Revised DBA Source Term to TVA Browns Ferry Nuclear Power Plant
ML20129D8831995-09-22022 September 1995
Rev 0 to Drywell Leakage Rate Direct to Environment Mimicking Case 2 Early Bypass of Sgts
ML20129D7861995-09-0101 September 1995
Rev 0 to Aerosol Decay Rates (Lambda) in Drywell
ML18039A5371995-03-23023 March 1995
Rev 2 to CD-Q0248-910431, Seismic Analysis of Battery Rack for Units 1 & 2 Battery Rooms A,B,C & D at El 621'3.
ML20093E4071994-02-0707 February 1994
Rev 0 to Calculation MD-Q3001-940005, Vessel Weld Flaw Evaluation for Browns Ferry Nuclear Plant Unit 3
ML20058N8251993-07-29029 July 1993
Package Consisting of Attachment to Employee Concerns Program
ML18036B1941992-05-26026 May 1992
Reactor Bldg Vents Radiation Monitoring Sys Drift Rate Calculation for TVA Browns Ferry Nuclear Plant.
ML20085M6321991-11-11011 November 1991
NUMARC Industry Survey in Support of License Renewal Rulemaking Aquatic Biology Dept Response to Aquatic Resource Questions
ML18036A3241991-08-14014 August 1991
Audit Rept on TVA Conformance W/Title 10 of Code of Federal Regulations Part 50.4,50.59,50.71(e) in Amend 7 of Browns Ferry Updated Fsar.
ML20059A4911990-08-13013 August 1990
Control Room Habitability Following Potential Barge Shipment Accident of Hazardous Chemicals
ML20085M6251990-07-0505 July 1990
DMR Summary for Plant & Specific Parameters Violated at Each Outfall
ML20059A4991990-05-29029 May 1990
Rev 0 to Frequency of Chlorine Concentration in Control Room in Excess of Toxicity Limit Due to Barge Accident
ML20059A4951990-05-23023 May 1990
Toxic Barge Study
ML20043B1131990-05-0303 May 1990
Rev 1 to ED-Q2000-87135, Cable Ampacity Calculation - V4 & V5 Safety-Related Trays for Unit 2 Operation.
ML18039A5311989-12-0202 December 1989
Rev 3 to CD-Q2253-883859, Center of Gravity for JBs 7193 & 7196.
ML18039A5301989-12-0202 December 1989
Rev 2 to CD-Q2253-883954, Seismic Qualification for Breakers in JB 7193 & 7196.
ML18039A5291989-09-21021 September 1989
Rev 1 to CD-Q2253-870722, Conduit Support.
ML18033A4851988-11-18018 November 1988
Sys Preoperability Checklist & Sys Plant Acceptance Evaluation Programs.
ML20154Q7921988-08-16016 August 1988
Rev 0 to Calculation ED-Q0268-88463, 480-Volt Reactor Motor-Operated Valve Boards 3A/B
ML20155B6291988-08-11011 August 1988
Rev 1 to Calculation ED-Q2268-87324, Thermal Overload Heater Calculations - 480V Reactor MOV Bd 2C
ML20155B6241988-08-11011 August 1988
Rev 1 to Calculation ED-Q2268-87322, Thermal Overload Heater Calculations - 480V Reactor MOV Bd 2A
ML20154Q8441988-05-19019 May 1988
Attachment 10 to Calculation ED-Q0281-88139 Re Fuse Program for Stated motor-operated Valve Boards
ML20154Q8251988-05-19019 May 1988
Rev 0 to Calculation ED-Q0281-88139, 250-Volt DC Reactor Motor-Operated Valve Boards 2A,2B & 2C
1998-09-03
[Table view]
Category:OPERATIONS SUPPORT-CALCULATIONS
MONTHYEARML18039A6231998-11-18018 November 1998
Rev 0 to Calculation MD-Q0999-970046, NPSH Evaluation of Browns Ferry RHR & CS Pumps.
ML18039A6271998-11-10010 November 1998
Rev 1 to 50147-C-012, HCLPF Calculations for Selected Blockwalls.
ML18039A5571998-10-0404 October 1998
Rev 0 to CD-Q3068-980061, Evaluation of IGSCC Indication at Weld GR-3-63.
ML18039A5391998-09-0303 September 1998
Rev 1 to CD-Q0082-970020, Eqe Evaluation A-46 Outliers to DG Neutral Ground Transformers.
ML20217Q6921998-04-23023 April 1998
Rev R8 to Calculation ND-Q0031-920075, Control Room Doses
ML20217A5111998-03-24024 March 1998
Rev 4 to Calculation MD-Q-0999-920136, Post Accident Primary Containment Penetration Isolated Piping Over Pressure Analysis
ML18039A5341997-08-13013 August 1997
Rev 2 to CD-Q2999-940343, Qualification of Cable Tray & Conduit Systems by A-46 Program.
ML18039A5411996-12-0101 December 1996
Rev 0 to 50147-C-003, Outlier & HCLPF Evaluations for RHR Pump Anchorage.
ML20129D6391996-09-25025 September 1996
Rev 2 to Calculation Package for Application of Revised DBA Source Term to Browns Ferry Nuclear Power Plant
ML18039A5441996-08-0606 August 1996
Rev 0 to CD-Q3071-960089, Verification of Anchorage for Panel 3-25-31 to Resolve Outlier Identified by USI A-46 Evaluation (Ssel #39204).
ML18039A6261996-07-15015 July 1996
Rev 1 to 50147-C-011, HCLPF Calculations for Electrical Equipment on A-46 Safe Shutdown Equipment List.
ML20129D7601996-06-13013 June 1996
Rev 2 to Volumetric Flowrate as Function of Time from Drywell to Torus (& Return)
ML20129D8101996-06-13013 June 1996
Rev 1 to Max Elemental I Decontamination Factors
ML20129D8191996-06-13013 June 1996
Rev 1 to Suppression Pool Scrubbing Efficency (Including Pool Bypass)
ML20129D8441996-06-13013 June 1996
Rev 1 to Addl Radionuclide Data
ML20129D8911996-05-27027 May 1996
Rev 1 to Aerosol Decontamination Factor in Main Steam Lines & Condenser
ML18039A5331996-05-0303 May 1996
Rev 0 to 50147-C-004, Bfnd A-46/IPEEE Outlier Evaluation - RHR Heat Exchangers.
ML18039A5361996-04-15015 April 1996
Rev 6 to CD-Q0000-931227, Qualification of Cable Tray & Conduit Systems by A-46 Program.
ML18039A5381996-02-24024 February 1996
Rev 0 to 50147-C-006, GE 7700 MCC Seismic Capacity Vs Demand - Outlier Resolution.
ML18038B6651996-02-0505 February 1996
Non-proprietary Calculations for Application of Revised DBA Source Term to Browns Ferry Nuclear Power Plant.
ML18039A6251995-10-16016 October 1995
Rev 1 to CD-Q0000-940339, Calculation of Basic Parameters for A46 & IPEEE Seismic Program.
ML18039A5431995-10-0101 October 1995
Rev 0 to 50147-C-002, MSIV Outlier Resolution.
ML18038B6661995-09-29029 September 1995
Non-proprietary Calculation of Containment Leakage Doses for Browns Ferry Nuclear Power Plant.
ML20129D8981995-09-28028 September 1995
Rev 0 to Elemental I Filter Efficiency in Main Steam Lines
ML20129D8741995-09-27027 September 1995
Rev 0 to Source Term for Use on Browns Ferry Application of NUREG-1465
ML20129D7371995-09-22022 September 1995
Rev 2 to Design Data Base for Application of Revised DBA Source Term to TVA Browns Ferry Nuclear Power Plant
ML20129D8831995-09-22022 September 1995
Rev 0 to Drywell Leakage Rate Direct to Environment Mimicking Case 2 Early Bypass of Sgts
ML20129D7861995-09-0101 September 1995
Rev 0 to Aerosol Decay Rates (Lambda) in Drywell
ML18039A5371995-03-23023 March 1995
Rev 2 to CD-Q0248-910431, Seismic Analysis of Battery Rack for Units 1 & 2 Battery Rooms A,B,C & D at El 621'3.
ML20093E4071994-02-0707 February 1994
Rev 0 to Calculation MD-Q3001-940005, Vessel Weld Flaw Evaluation for Browns Ferry Nuclear Plant Unit 3
ML18036B1941992-05-26026 May 1992
Reactor Bldg Vents Radiation Monitoring Sys Drift Rate Calculation for TVA Browns Ferry Nuclear Plant.
ML20059A4911990-08-13013 August 1990
Control Room Habitability Following Potential Barge Shipment Accident of Hazardous Chemicals
ML20059A4991990-05-29029 May 1990
Rev 0 to Frequency of Chlorine Concentration in Control Room in Excess of Toxicity Limit Due to Barge Accident
ML20059A4951990-05-23023 May 1990
Toxic Barge Study
ML20043B1131990-05-0303 May 1990
Rev 1 to ED-Q2000-87135, Cable Ampacity Calculation - V4 & V5 Safety-Related Trays for Unit 2 Operation.
ML18039A5301989-12-0202 December 1989
Rev 2 to CD-Q2253-883954, Seismic Qualification for Breakers in JB 7193 & 7196.
ML18039A5311989-12-0202 December 1989
Rev 3 to CD-Q2253-883859, Center of Gravity for JBs 7193 & 7196.
ML18039A5291989-09-21021 September 1989
Rev 1 to CD-Q2253-870722, Conduit Support.
ML20154Q7921988-08-16016 August 1988
Rev 0 to Calculation ED-Q0268-88463, 480-Volt Reactor Motor-Operated Valve Boards 3A/B
ML20155B6291988-08-11011 August 1988
Rev 1 to Calculation ED-Q2268-87324, Thermal Overload Heater Calculations - 480V Reactor MOV Bd 2C
ML20155B6241988-08-11011 August 1988
Rev 1 to Calculation ED-Q2268-87322, Thermal Overload Heater Calculations - 480V Reactor MOV Bd 2A
ML20154Q8251988-05-19019 May 1988
Rev 0 to Calculation ED-Q0281-88139, 250-Volt DC Reactor Motor-Operated Valve Boards 2A,2B & 2C
ML18039A5321986-11-19019 November 1986
Seismic Qualification of Conduit & Supports.
1998-09-03
[Table view] |
Text
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PSAT 04000U.04 i
Attachment 6 PSAT Calculation 04011H.04
" Suppression Pool Scrubbing Efficiency (Including Pool Bypass)"
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Page: 1 of 5 Rev: 0@2 3 4 CALCULATION TITLE PAGE CALCULATION NUMBER: PSAT 04011H.04 i
CALCULATION TITLE:
" Suppression Pool Scrubbing Efficiency (Including Poc! Bypass)"
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- Addition of pool DF calculation in accordance with References 2 and 5 2
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- PSAT 04011H.04 Page
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Table of Contents ,
i Section EAgt Purpose 2
Methodology 2 I
{ Assumptions 3
References 3
Calculation '
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Resulta 5
! Conclusions 5
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, Purpose The purpose of this calculation is to determine the maximum removal efBeiency that can be credited for the passage of particulates and of elemental iodine (including Te-132 which is being treated as elemental I-132 except for half-life) through (and around) the Browns Feny suppression pool for the purpose of applying the revised DB A source term ofReference 1.
Methodology The overall methodology is that ofReference 2 except for timing (which is specified in Reference
- 1) and the suppression pool DF which is explicitly calculated below (see Calculation section) in lieu ofusing the minimum value of 10 given as a " default" in Reference 2. (Per Reference 2, "in j the absence of detailed analysis, a [ suppression pod decontamination) factor of 10 [may be] used, j dthough this is likely to be significantly lower than what would be calculated"). To account for pool bypass, a steam mass flow corresponding to 10 times the drywel storus vacuum breaker surveillnace test acceptance value is used. It is compared to the mass flow out of the drywell during and immediately after the source tenn release (referred to as the slow drywell sweep and the fast drf wel' sweep, respectively) to determine the bypass fraction. No removal credit is taken - '
for the frada of the drywell sweep-out flow which bypasses the suppression pool. The overall pool DF (expressed as a " filter efBeiency") is calculated accordingly.
I y-. . '~-
PSAT 04011H.04 Page: 3 of 5 Rev: Oh 3 4 Assumptions Assumption 1: There is no dynamic pressure drop through the vent system during either the slow sweep or fast sweep of the drywell.
Justification: The fast sweep-out of the drywell occurs with a vent flow of about 32 lbm/sec (Reference 3). As was discussed in Reference 3, during the blowdown of the reactor vessel for a DBA recirc suction LOCA all coolant is released except for a portion in the lower reactor vessel. Ifit is estimated that: (1) the total coolant released is of the order of 400000 lbm, (2) about 40% of that flashes to steam (Reference 3 calculates 38%), and (3) the blowdown requires not more than 30 seconds (the start of the gap release in Reference 1). Thus, the average steam flow through the vent system is about 5300 lbm/sec. Considering that the vent system differential pressure would not be expected to exceed 30 psid for such an event, and further that pressure drop would be, at worst, linear with flow (and at best, proportional to flow velocity squared), the differential pressure for a flow ofonly 32 lbm/sec would be expected to be in the range of 0.001 to 0.2 psid. For a vent submergence of 3.5 ft (Reference 4, Item 8.14) the static differential pressure (to clear the vents) would be about 1.5 psid. Therefore, at worst, the dynamic pressure drop, even for the fast sweep-out flow of 32 lbm/sec, would be of the order of 10 percent of the static pressure difference and can therefore be neglected.
References Reference 1: Soffer, L., et al., " Accident Source Terms for Light-Water Nuclear Power Plants",
NUREG-1465, February 1995 Reference 2: Leaver, .9. E., et al., " Licensing Design Basis Source Term Update for the Evolutionary Advanced Light Water Reactor", DOE /ID-10298, September,1990 Reference 3: PSAT 0401IH.01, " Volumetric Flowrate as a Function of Time from Drywell to Torus (and Return)", Revision 0 Reference 4: PSAT 04000U.03, " Design Data Base for Application of the Revised DBA Source Term to the TVA Browns Feny Nuclear Power Plant", Revision 0 Reference 5: Powers, D. A., and Sprung, J. L., "A Simplined Model of Aerosol Scrubbing by a Water Pool Overlying Core Debris Interacting With Concrete", NUREG/CR-5901, November,1993 Reference 6: PSAT 04002H.09, " Elemental lodine Filter EfBeiency in Main Steam Lines",
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! PSAT 04011H.04 Page: 4 of 5 Rev: Oh2 3 4 ~
Revision 0 .
i Calculation I
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PSAT 04011H.04 Page: 5 of 5 Rev: 0 34 l
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1 Results
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The overall efHelency of the suppression pool as a filter for removing particulate and elemental iodine is 0.72 during the slow sweep-out (prior to 7230 second:) and 0.95 during the fast sweep-out (from 7230 seconds to 7890 seconds).
Conclusions Because of the relatively low flowrate conesponding to the slow sweep of the drywell, the pool bypass (which is not sensitive to flowrate since it depends only on the hydrostatic pressure difference needed to clear the vents) is relatively large during that pasiod leading to a relatively low overall efficiency. During the high flow of the fast sweep the pool bypass is correspondingly smaller and the efficiency correspondingly greater.
.
