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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 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) 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 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 6213 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 ML18036A4021991-10-0808 October 1991 Audit Rept Re Util Conformance w/10CFR50.4,50.59 & 50.71(e) Requirements Concerning Amend 8 to Facility Updated FSAR 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 ML20155B6241988-08-11011 August 1988 Rev 1 to Calculation ED-Q2268-87322, Thermal Overload Heater Calculations - 480V Reactor MOV Bd 2A ML20155B6291988-08-11011 August 1988 Rev 1 to Calculation ED-Q2268-87324, Thermal Overload Heater Calculations - 480V Reactor MOV Bd 2C ML20154Q8441988-05-19019 May 1988 Attachment 10 to Calculation ED-Q0281-88139 Re Fuse Program for Stated motor-operated Valve Boards 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 6213 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] |
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PSAT 04000U.04 i
PSAT Calculation 04011H.04
" Suppression Pool Scrubbing Efficiency (Including Pool Bypass)"
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CALCULATION TITLE:
" Suppression Pool Scrubbing Efficiency (Including Poc! Bypass)"
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Section EAgt Purpose 2
Methodology 2
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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.
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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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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.
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