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| {{#Wiki_filter:Attachment 3 to PLA-742 Page 1 of 1 WETWELL SPRAY TER'4INATION OF'PRESSURE INCREASE The NRC in Appendix I to SRP 6.2.1.1.C gives guidance that spray capacity be sufficient to accommodate a leakage area of the order of A/~K=0.05 ft Therefore, a calculation was performed to confirm that with the drywell at the design pressure and a leakage area of A//K=0.05 ft the drywell and wetwell pressure increase would be terminated when the wetwell sprays are initiated. | | {{#Wiki_filter:Attachment 3 to PLA-742 Page 1 of 1 WETWELL SPRAY TER'4INATION OF 'PRESSURE INCREASE The NRC in Appendix I to SRP 6.2.1.1.C gives guidance that spray capacity be sufficient to accommodate a leakage area of the order of A/ ~K = 0.05 ft Therefore, a calculation was performed to confirm that with the drywell at the design pressure and a leakage area of A// K = 0.05 ft the drywell and wetwell pressure increase would be terminated when the wetwell sprays are initiated. |
| The leakage rate is=0.05 2 X 32.2 X 144 X 5.18 6.406 m=4.3 ibm/sec The wetwell spray flow rate of one spray system is (reference"RHR Process Diagram".GE drawing 76IE792A Rev 5)750 gpm X 1=103 ibm/sec 7.48 X 60 X.016247 The condensation efficiency is calculated as eff=cond X evap m h h-h m (f spray X spray)This equation is used to calculate the minimum acceptable spray efficiency by substituting the bypass leakage rate of 4.3 ibm/sec into the equation for cond.'he wetwell sprays will terminate the pressure increase as long as they condense more steam than is leaking to the wetwell.The required spray efficiency for one RHR spray system as a function of spray temperature is given below.With two spray systems operating the required efficiency would be halved.The actual spray efficiency should be on the order of 0.7 and, hence, when a single system is in operation with its RHR heat exchanger, this termination of the pressure increase is assured.S ra Tem erature 130 F 150 F 170 F 190 F Required Efficiency of One Metwell S ra S stem.23.26.50.36}} | | The leakage rate is |
| | = 0.05 2 X 32.2 X 144 X 5.18 6.406 m = 4.3 ibm/sec The wetwell spray flow rate of one spray system is (reference "RHR Process Diagram". GE drawing 76IE792A Rev 5) 750 gpm X 1 = 103 ibm/sec 7.48 X 60 X .016247 The condensation efficiency is calculated as eff = m cond X h evap |
| | ( |
| | h f-h spray X m |
| | spray) |
| | This equation is used to calculate the minimum acceptable spray efficiency by substituting the bypass leakage rate of 4.3 ibm/sec into the equation for cond. 'he wetwell sprays will terminate the pressure increase as long as they condense more steam than is leaking to the wetwell. |
| | The required spray efficiency for one RHR spray system as a function of spray temperature is given below. With two spray systems operating the required efficiency would be halved. The actual spray efficiency should be on the order of 0.7 and, hence, when a single system is in operation with its RHR heat exchanger, this termination of the pressure increase is assured. |
| | Required Efficiency of One Metwell S ra Tem erature S ra S stem 130 F .23 150 F .26 170 F .50 190 F .36}} |
Latest revision as of 00:38, 22 October 2019
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML18040B2891999-03-12012 March 1999
Proposed Tech Specs Including Rev 0 to EMF-1997(P)(A) Into TS Section 5.6.5 & Including Revised MCPR Safety Limits in TS Section 2.1.1.2
ML18040B2881999-01-12012 January 1999
Proposed Tech Specs Re ANFB-10 Critical Power Correlation & MCPR Safety Limits
ML17164A6711998-07-0808 July 1998
Proposed Tech Specs,Implementing Improved Tech Specs of NUREG-1433.Page B3.8-1 of Incoming Submittal Not Included
ML17159A3261998-05-12012 May 1998
Proposed Tech Specs Re Removal of Fire Protection Program
ML20199C8741997-10-22022 October 1997
Rev 0 to NASI-00-507, Corrective Action Process Effectiveness Assessment
ML18026A4711997-02-11011 February 1997
Proposed Tech Specs Requesting Improved TSs LCO 3.10.3 & LCO 3.10.4 Be Approved for Use During Susquehanna Ses Unit 2 Eighth Refueling & Insp Outage Scheduled for 970315
ML17158C0321997-01-0808 January 1997
Rev 4, Solid Radwaste Pcp.
ML20129D7851996-09-23023 September 1996
Proposed Tech Specs Re MSIVs Leakage Testing
ML20116K3491996-08-0909 August 1996
Proposed Tech Specs Re Battery Load Profiles
ML17158B5581996-03-20020 March 1996
Proposed Tech Specs,Changing Open Logic for HPCI Suction Valve HV-155/255-F042 in Order to Eliminate HPCI Pump auto- Transfer on High Suppression Pool Level
ML20115A8211996-02-29029 February 1996
Proposed Tech Specs,Removing Rod Block Monitor Requirements from TS by Reducing Number of Rod Movements During Power Maneuvers
ML20115A8171996-02-29029 February 1996
Proposed Tech Specs,Relocating Spec 3/4.9.6, Refueling Platform to Document Which Is Controlled Under Requirements of 10CFR50.59
ML17158B1071996-02-12012 February 1996
Proposed Tech Specs to Implement 10CFR50,App J,Option B & Establish New Spec 6.8.5, Primary Containment Leakage Rate Testing Program.
ML17158A6821995-04-26026 April 1995
Rev 3 to Nuclear Dept Procedure ON-100-009, Control Room Evacuation.
ML17158A6841995-04-13013 April 1995
Rev 3 to Nuclear Dept Procedure ON-200-009, Control Room Evacuation.
ML20081L9151995-03-14014 March 1995
Rev 1 to NS-ST-002, Security Training & Crucial Security Task Certification
ML17164A5801995-02-10010 February 1995
Proposed Tech Specs for Aot/Sti Extensions
ML17164A5891995-01-20020 January 1995
Rev 2 to PP&L SSES Odcm.
ML17164A4351994-11-21021 November 1994
Proposed Tech Specs Increasing MSIV Leakage Rate & Deleting MSIV-LCS
ML17158A5441994-10-28028 October 1994
Proposed Tech Specs,Incorporating Administrative Changes
ML20058F8281993-11-24024 November 1993
Proposed Tech Specs Re Power Uprate W/Increased Flow
ML17157C3881993-05-31031 May 1993
Rev 8 to ISI-T-100.0, ISI Program Plan for Pump & Valve Operational Testing.
ML17157C3901993-05-31031 May 1993
Rev 5 to ISI-T-200.0, ISI Program Plan for Pump & Valve Operational Testing.
ML18017A2671993-04-20020 April 1993
Exercise Manual.
ML17157C2741993-04-0202 April 1993
Proposed TS 3.4.1.1.2 Re LCO for Recirculation Loops,Single Loop Operation
ML18017A2631992-05-0606 May 1992
Emergency Exercise Std for Conduct in Performance of 920219 NRC Graded Exercise
ML20113G9881992-02-19019 February 1992
Package Providing Basis for Conduct of Simulated Radiological Accident at Plant
ML17157B0101991-12-31031 December 1991
Rev 4 to ISI-T-200.0, Sses,Unit 2,ISI Program Plan for Pump & Valve Operational Testing, Per Generic Ltr 89-04
ML17157B0081991-12-31031 December 1991
Rev 7 to ISI-T-100.0, Sses,Unit 1,ISI Program Plan for Pump & Valve Operational Testing, Per Generic Ltr 89-04
ML18017A2591991-10-16016 October 1991
Exercise Manual, Approved by Util as Std for Conduct in Performance of 911016 NRC Graded Exercise
ML20082P1871991-09-0404 September 1991
Proposed Tech Specs for HPCI Sys Low Pressure Surveillance Test Acceptance Criteria
ML17157A3381990-09-30030 September 1990
Cycle 5 Reload Summary Rept.
ML17157A3371990-09-24024 September 1990
Proposed Tech Specs in Support of Facility Cycle 5 Reload
ML17157A2441990-07-0202 July 1990
Proposed Tech Specs to Support Cycle 6 Reload
ML17157A0891990-03-19019 March 1990
Rev 0 to Procedure MT-024-024, Diesel Engine Analysis & Load Balancing.
ML17157A0871990-03-19019 March 1990
Rev 0 to Procedure TP-024-087, Data Collection for E Diesel Generator Combustion Intake Air Temp Test.
ML20127B4271990-01-19019 January 1990
Rev 8 to Procedure MT-GE-008, 480 Volt & Under Circuit Breaker High Current Testing
ML19325D7491989-10-19019 October 1989
Proposed Tech Specs 3.2.2 Eliminating Certain Requirements on One Time Basis for 3 Months
ML20082C4101989-08-16016 August 1989
Spec Change Notice 7 to Rev 4 to TS F1000, TS for Design & Installation of Electrical Raceway Fire Barriers
ML17156B1101989-04-14014 April 1989
Proposed Tech Specs,Making Changes to Emergency Svc Water Sys,Per 10CFR50,App R
ML17156B0651989-03-31031 March 1989
Rev 6 to ISI-T-100.0, Pump & Valve Inservice Insp Testing Program.
ML17156B0671989-03-31031 March 1989
Rev 3 to ISI-T-200.0, Pump & Valve Inservice Insp Testing Program.
ML20082C4071989-03-23023 March 1989
Spec Change Notice 6 to Rev 4 to F1000, TS for Design & Installation of Electrical Raceway Fire Barriers
ML17156B1391989-02-22022 February 1989
Rev 12 to EO-100-009, Plant Shutdown from Outside Control Room.
ML20082B2771989-01-0404 January 1989
Rev 4 to TS F1000, TS for Design & Installation of Electrical Raceway Fire Barriers
ML20082C3731988-11-0707 November 1988
Spec Change Notice 5 to Rev 3 to TS F1000, TS for Design & Installation of Electrical Raceway Fire Barriers
ML20082C3711988-11-0101 November 1988
Spec Change Notice 4 to Rev 3 to TS F1000, TS for Design & Installation of Electrical Raceway Fire Barriers
ML20082C3641988-10-14014 October 1988
Spec Change Notice 3 to Rev 3 to TS F1000, TS for Design & Installation of Electrical Raceway Fire Barriers
ML17156A7291988-08-10010 August 1988
Proposed Tech Specs,Extending Operation During Cycle 4 W/ One Recirculation Loop Out of Svc
ML20082B2911988-07-11011 July 1988
Rev 3 to TS F1000, TS for Design & Installation of Electrical Raceway Fire Barriers
1999-03-12
[Table view]
Category:TEST REPORT
MONTHYEARML17157A3381990-09-30030 September 1990
Cycle 5 Reload Summary Rept.
ML20210B1791987-01-28028 January 1987
Suppl 1 to Susquehanna Unit 2 Cycle 2 Stability Test Results
PLA-2771, Cycle 2 Startup Test Summary1987-01-28028 January 1987
Cycle 2 Startup Test Summary
ML20211E2871986-09-16016 September 1986
Test Rept of 1/2 Inch Kwik-Bolt Software.Analyses of 1/2 Inch Bolt,Matl/Dimension,Concrete Mix Design,Tension Values & Safety Factor & Nuclear Power Plant Onsite Test Index Encl
ML20211E2251986-04-30030 April 1986
Hilti Kwik-Bolt Concrete Expansion Anchor Torque/Tension Test Performed for Dravo Const at Susquehanna Steam Electric Station in Berwick,Pa
ML20211E2381985-05-31031 May 1985
Hilti Kwik-Bolt Concrete Expansion Anchor Tension Test & Torque Vs Pretension Test Performed for Dravo Const in Berwick,Pa. Facility Test Data Analyses Encl
ML20133J1251985-05-0909 May 1985
Amended Startup Rept
ML17139B5871983-06-0909 June 1983
Startup Rept.
ML17139A9271982-08-31031 August 1982
Mark II Primary Containment Vacuum Relief Valve Test Program,Phase Iv,Revision 0.
ML20064N4241982-08-31031 August 1982
Primary Reactor Containment Integrated Leakage Rate Test, Final Rept
ML18031A3881982-08-25025 August 1982
Qualification Fire Test of Protective Envelope Sys.
ML17139A4531981-09-30030 September 1981
Protective Envelope Evaluation, Final Rept
ML18030A5331981-04-16016 April 1981
Wetwell Spray Termination of Pressure Increase Results
ML18030A0401981-04-0101 April 1981
Containment High Pressure Bypass Leakage Test.
ML18026A3441981-04-0101 April 1981
Containment Steam Bypass.
ML18030A5531981-03-25025 March 1981
Results of water,50F Subcooled Test Conducted on 810325
ML18030A5521981-03-25025 March 1981
Results of Steam Saturated Test Conducted on 810325
ML18030A5491981-03-24024 March 1981
Results of Steam Saturated Test Conducted on 810324
ML18030A5501981-03-24024 March 1981
Results of water,15F Subcooled Test Conducted on 810324
ML18030A5511981-03-24024 March 1981
Results of Steam Saturated Test Conducted on 810324
ML17138B7791980-10-30030 October 1980
Reactor Pressure Vessel Internals Vibration Test.
ML20151A3841980-07-28028 July 1980
Revision a to Electrical Wire & Cable Isolation Barrier Matls Test for Susquehanna Steam Electric Station,Units 1 & 2 for Bechtel Power Corp
ML17138B1971980-02-28028 February 1980
Submerged Structure Tests.
ML20195C6391978-02-28028 February 1978
Structural Integrity Test Rept Containment Structure Unit 1
ML20044G7941977-06-30030 June 1977
Structural Integrity Test Rept,Containment Structure,Unit 1.
ML17138A5451977-03-22022 March 1977
Rept Translated from German: Results of Non-Nuclear Hot Test W/Relief Sys in Philippsburg Nuclear Power Plant.
ML17138A5461976-09-30030 September 1976
Rept Translated from German:KKB-Nuclear Startup,Results of Tests W/Pressure Relief Sys.
ML17138A5411974-12-20020 December 1974
Rept Translated from German:Results of Non-Nuclear Hot Tests W/Relief Sys in Brunsbuttel Nuclear Power Plant.
1990-09-30
[Table view] |
Text
Attachment 3 to PLA-742 Page 1 of 1 WETWELL SPRAY TER'4INATION OF 'PRESSURE INCREASE The NRC in Appendix I to SRP 6.2.1.1.C gives guidance that spray capacity be sufficient to accommodate a leakage area of the order of A/ ~K = 0.05 ft Therefore, a calculation was performed to confirm that with the drywell at the design pressure and a leakage area of A// K = 0.05 ft the drywell and wetwell pressure increase would be terminated when the wetwell sprays are initiated.
The leakage rate is
= 0.05 2 X 32.2 X 144 X 5.18 6.406 m = 4.3 ibm/sec The wetwell spray flow rate of one spray system is (reference "RHR Process Diagram". GE drawing 76IE792A Rev 5) 750 gpm X 1 = 103 ibm/sec 7.48 X 60 X .016247 The condensation efficiency is calculated as eff = m cond X h evap
(
h f-h spray X m
spray)
This equation is used to calculate the minimum acceptable spray efficiency by substituting the bypass leakage rate of 4.3 ibm/sec into the equation for cond. 'he wetwell sprays will terminate the pressure increase as long as they condense more steam than is leaking to the wetwell.
The required spray efficiency for one RHR spray system as a function of spray temperature is given below. With two spray systems operating the required efficiency would be halved. The actual spray efficiency should be on the order of 0.7 and, hence, when a single system is in operation with its RHR heat exchanger, this termination of the pressure increase is assured.
Required Efficiency of One Metwell S ra Tem erature S ra S stem 130 F .23 150 F .26 170 F .50 190 F .36
