|
|
Line 17: |
Line 17: |
|
| |
|
| =Text= | | =Text= |
| {{#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 01:38, 22 October 2019
|
---|
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 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 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 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 ML17156B0671989-03-31031 March 1989 Rev 3 to ISI-T-200.0, Pump & Valve Inservice Insp Testing Program. ML17156B0651989-03-31031 March 1989 Rev 6 to ISI-T-100.0, 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