NRC-23-0063, Inservice Testing Program for Pumps and Valves - Part 12: IST Program Pump Basis Revision 1
| ML23283A035 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 10/09/2023 |
| From: | DTE Electric Company |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML23283A021 | List: |
| References | |
| NRC-23-0063 | |
| Download: ML23283A035 (1) | |
Text
DSN:IST Program Pump Basis, Rev.1, Page 1 of 111 FERMI 2 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES FERMI 2 FOURTH 10 YEAR INTERVAL - START DATE 02/17/2020 PART 12: IST PROGRAM PUMP BASIS REVISION 1 Revision Summary:
Revised per LCR 20-045-ISI QUAL Jeffrey D. Auler, e55603, see attached email. 1/8/21 Prepared: Date: PE-03 IST Program Manager Craig Shepherd, e55018, see attached email.
1/8/21 Reviewed: Date: PE-03 Qualified Program Engineer James Wines, e54431, see attached email. 1/12/21 Reviewed: Date: N/A Supervisor, Performance Engineering Randy Breymaier, e50801, see attached Approved: email. Date: 1/15/21 N/A Manager, Performance Engineering INFORMATION AND PROCEDURES DSN: IST Program Pump Basis Rev: 1 Date: 1/25/21 DTC: TM PLAN File: 1715.04 Recipient:
Date Approved: Release authorized by:
an -n r Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 2 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes C4103 North Standby Liquid Control Pump 5704/E-5 B 2 Reciprocating Positive C4103C001A Displacement P 2Y 24.139.02 TP-19 Q 2Y 24.139.02 TP-19 V 2Y 24. 139.02 Standard Code ISTB P Q 24.139.02 Q Q 24.139.02 V Q 24.139.02 Safety Function Basis: The major components of the SLCS consist of a storage tank, two positive displacement pumps, two explosive valves, and two check valves between the explosive valves and the reactor. The flow path is from the storage tank through the pumps, explosive valves, and check valves, and into the reactor to the bottom of the core plate. [UFSAR 7.1.2.1.21] The power supply to explosive valve F004A and injection pump C001A is from automatically restored MCC 72B-4C. The power supply to explosive valve F004B and injection pump C001B is from automatically restored MCC 72E-5B. [UFSAR 7.4.1.2.2] The SLCS has been reclassified to identify that it was not originally intended, procured, designed, or classified as safety related, but it will be maintained and tested as a safety-related system after completion of its preoperational tests. [UFSAR 7.4.1.2.1.2] The SLCS is manually initiated from the control room and receives no automatic initiation signals to ensure the system cannot be inadvertently initiated. [DBD C41-00 Section 4.2.6.6]The two SLCS pumps inject sodium pentaborate into the reactor core to shutdown the reactor. The system is capable of effecting a reactor shutdown from rated power operation to the cold subcritical condition, in the postulated event that the control rods cannot be inserted. [DBD C41-00 Section 1.0] Each pump is a positive displacement, triplex or quintuplex type pump rated at 100% capacity. The pump can deliver a rated flow of 43 gpm (41.2 gpm minimum) at 1215 psig of sodium pentaborate solution to the reactor vessel and is capable of pumping the entire contents of the storage tank which is held between 2560 and 3040 gallons in 62 to 74 minutes. [DBD C41-00 Section 4.1.2.8.9] The SLC pumps transfer borated water from the storage tank to the reactor pressure vessel (RPV). The borated solution is discharged near the bottom of the core shroud, where it then mixes with the cooling water rising through the core. The SLC system is manually initiated from the main control room, as directed by emergency operating procedures, if the operator believes the reactor cannot be shut down, or kept shut down, with the control rods. [TS B 3.1.7]
Function
Description:
Group B - This pump is in standby systems that are not operated routinely except for testing.The SLC System is designed to provide the capability of bringing the reactor, at any time in a fuel cycle, from full power and minimum control rod inventory (which is at the peak of the xenon transient) to a subcritical condition with the reactor in the most reactive, xenon free state without taking credit for control rod movement. The SLC System satisfies the requirements of 10 CFR 50.62 on anticipated transient without scram. The SLCS is a control system whose primary function is to provide an alternative method for the control of core reactivity in the event that the Control Rod Drive System is not available. The SLCS delivers a sufficient quantity of boron moderator to cause and maintain a safe shutdown of the reactor. This function is only required in the event that an adequate number of control rods cannot be inserted. A second function of the SLCS is to maintain suppression pool pH at or above 7 following a loss of coolant accident (LOCA) involving significant fission product releases. Maintaining suppression pool pH levels at or above 7 following an accident ensures that iodine will be retained in the suppression pool water. Maintaining the suppression pool at a pH above 7 ensures that iodine activity is retained in the suppression pool and offsite doses will remain within the 10CFR 50.67, Accident Source Term limits. [TS B 3.1.7] [DBD C41-00 Sections 2.1, 2.2]
Design Basis Limits: SR 3.1.7.7: Verify each SLC System pump develops a flow rate greater than or equal to 41.2 gpm at a discharge pressure greater than or equal to 1215 psig to ensure that the pump performance has not degraded during the fuel cycle. This minimum pump flow rate requirement ensures that, when combined with the sodium pentaborate solution concentration requirements, the rate of negative reactivity insertion from the SLC System will adequately compensate for the positive reactivity effects encountered during power reduction, cooldown of the moderator, and xenon decay. This test confirms one point on the pump design curve and is indicative of overall performance. Such inservice inspections confirm component OPERABILITY, trend performance, and detect incipient failures by indicating abnormal performance. The Frequency of this Surveillance is in accordance with the Inservice Testing Program.DCD C41-00 Section 4.2.3.1 Pump (proper) Design Parameters:Rated Capacity .......................... 43 GPMMinimum Flow............................41.2 GPMDesign Pressure .......................... 1400 PSIGDischarge Pressure ..................... 1215 PSIGDesign Temp...............................150OF Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 1 of 106
.70W an mFermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 3 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes Design
References:
TS 3.1.7 Standby Liquid Control (SLC) SystemTS B 3.1.7 Standby Liquid Control (SLC) SystemTS SR 3.1.7.7TS SR 3.1.7.8UFSAR 3.1.2.3.7 Criterion 26 - Reactivity Control System Redundancy and CapabilityUFSAR 5.2.1.1.9 Standby Liquid Control SystemUFSAR 7.1.2.1.21 Standby Liquid Control SystemUFSAR 7.4.1.2.2 Power SourcesUFSAR 7.4.1.2.1.2 ClassificationDBD C41-00 Rev. A, Standby Liquid Control System Appendix V Basis: OM Code Appendix V paragraph V-3000(a) Requirement: The Owner shall (a) identify those certain applicable pumps with specific design basis accident flow rates in the Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) for inclusion in this program.TS SR 3.1.7.7: Verify each SLC System pump develops a flow rate greater than or equal to 41.2 gpm at a discharge pressure greater than or equal to 1215 psigIn summary, to satisfy Appendix V, each SLC pump must be flow tested at a flow rate of greater than or equal to 41.2 gpm at a discharge pressure of greater than or equal to 1215 psig.
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 2 of 106
DTIE ergFermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 4 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes C4103 South Standby Liquid Control Pump 5704/D-5 B 2 Reciprocating Positive C4103C001B Displacement P 2Y 24.139.02 TP-19 Q 2Y 24.139.02 TP-19 V 2Y 24. 139.02 Standard Code ISTB P Q 24.139.02 Q Q 24.139.02 V Q 24.139.02 Safety Function Basis: The major components of the SLCS consist of a storage tank, two positive displacement pumps, two explosive valves, and two check valves between the explosive valves and the reactor. The flow path is from the storage tank through the pumps, explosive valves, and check valves, and into the reactor to the bottom of the core plate. [UFSAR 7.1.2.1.21] The power supply to explosive valve F004A and injection pump C001A is from automatically restored MCC 72B-4C. The power supply to explosive valve F004B and injection pump C001B is from automatically restored MCC 72E-5B. [UFSAR 7.4.1.2.2] The SLCS has been reclassified to identify that it was not originally intended, procured, designed, or classified as safety related, but it will be maintained and tested as a safety-related system after completion of its preoperational tests. [UFSAR 7.4.1.2.1.2] The SLCS is manually initiated from the control room and receives no automatic initiation signals to ensure the system cannot be inadvertently initiated. [DBD C41-00 Section 4.2.6.6]The two SLCS pumps inject sodium pentaborate into the reactor core to shutdown the reactor. The system is capable of effecting a reactor shutdown from rated power operation to the cold subcritical condition, in the postulated event that the control rods cannot be inserted. [DBD C41-00 Section 1.0] Each pump is a positive displacement, triplex or quintuplex type pump rated at 100% capacity. The pump can deliver a rated flow of 43 gpm (41.2 gpm minimum) at 1215 psig of sodium pentaborate solution to the reactor vessel and is capable of pumping the entire contents of the storage tank which is held between 2560 and 3040 gallons in 62 to 74 minutes. [DBD C41-00 Section 4.1.2.8.9] The SLC pumps transfer borated water from the storage tank to the reactor pressure vessel (RPV). The borated solution is discharged near the bottom of the core shroud, where it then mixes with the cooling water rising through the core. The SLC system is manually initiated from the main control room, as directed by emergency operating procedures, if the operator believes the reactor cannot be shut down, or kept shut down, with the control rods. [TS B 3.1.7]
Function
Description:
Group B - This pump is in standby systems that are not operated routinely except for testing.The SLC System is designed to provide the capability of bringing the reactor, at any time in a fuel cycle, from full power and minimum control rod inventory (which is at the peak of the xenon transient) to a subcritical condition with the reactor in the most reactive, xenon free state without taking credit for control rod movement. The SLC System satisfies the requirements of 10 CFR 50.62 on anticipated transient without scram. The SLCS is a control system whose primary function is to provide an alternative method for the control of core reactivity in the event that the Control Rod Drive System is not available. The SLCS delivers a sufficient quantity of boron moderator to cause and maintain a safe shutdown of the reactor. This function is only required in the event that an adequate number of control rods cannot be inserted. A second function of the SLCS is to maintain suppression pool pH at or above 7 following a loss of coolant accident (LOCA) involving significant fission product releases. Maintaining suppression pool pH levels at or above 7 following an accident ensures that iodine will be retained in the suppression pool water. Maintaining the suppression pool at a pH above 7 ensures that iodine activity is retained in the suppression pool and offsite doses will remain within the 10CFR 50.67, Accident Source Term limits. [TS B 3.1.7] [DBD C41-00 Sections 2.1, 2.2]
Design Basis Limits: SR 3.1.7.7: Verify each SLC System pump develops a flow rate greater than or equal to 41.2 gpm at a discharge pressure greater than or equal to 1215 psig to ensure that the pump performance has not degraded during the fuel cycle. This minimum pump flow rate requirement ensures that, when combined with the sodium pentaborate solution concentration requirements, the rate of negative reactivity insertion from the SLC System will adequately compensate for the positive reactivity effects encountered during power reduction, cooldown of the moderator, and xenon decay. This test confirms one point on the pump design curve and is indicative of overall performance. Such inservice inspections confirm component OPERABILITY, trend performance, and detect incipient failures by indicating abnormal performance. The Frequency of this Surveillance is in accordance with the Inservice Testing Program.DCD C41-00 Section 4.2.3.1 Pump (proper) Design Parameters:Rated Capacity .......................... 43 GPMMinimum Flow............................41.2 GPMDesign Pressure .......................... 1400 PSIGDischarge Pressure ..................... 1215 PSIGDesign Temp...............................150OF Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 3 of 106
Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 5 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes Design
References:
TS 3.1.7 Standby Liquid Control (SLC) SystemTS B 3.1.7 Standby Liquid Control (SLC) SystemTS SR 3.1.7.7TS SR 3.1.7.8UFSAR 3.1.2.3.7 Criterion 26 - Reactivity Control System Redundancy and CapabilityUFSAR 5.2.1.1.9 Standby Liquid Control SystemUFSAR 7.1.2.1.21 Standby Liquid Control SystemUFSAR 7.4.1.2.2 Power SourcesUFSAR 7.4.1.2.1.2 ClassificationDBD C41-00 Rev. A, Standby Liquid Control System Appendix V Basis: OM Code Appendix V paragraph V-3000(a) Requirement: The Owner shall (a) identify those certain applicable pumps with specific design basis accident flow rates in the Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) for inclusion in this program.TS SR 3.1.7.7: Verify each SLC System pump develops a flow rate greater than or equal to 41.2 gpm at a discharge pressure greater than or equal to 1215 psigIn summary, to satisfy Appendix V, each SLC pump must be flow tested at a flow rate of greater than or equal to 41.2 gpm at a discharge pressure of greater than or equal to 1215 psig.
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 4 of 106
Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 6 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes E1102C002A E1102 Residual Heat Removal Pump A 5706-2/B-6 A 2 Centrifugal dP 2Y 24.204.01 TP-19 Q 2Y 24.204.01 TP-19 V 2Y 24.204.01 PRR-001 Standard Code ISTB dP Q 24.204.01 Q Q 24.204.01 V Q 24.204.01 PRR-001 Safety Function Basis: The 4 RHR pumps are vertical, centrifugal pumps (with mechanical seals, cyclone separators and seal-cooling-heat exchangers) coupled with a vertical mounted squirrel cage, induction, constant speed, electric motor. The pumps take suction from the suppression pool and start automatically on a LPCI initiation signal. The pumps supply a minimum of 10,000 gpm flow each, at a TDH of 594 ft (256 psid) [DBD E11-00 Pump Data Sheet 4.2.1.1] and inject water into the RPV following a LOCA to restore reactor vessel level and provide core cooling. The pumps can be operated in the Emergency - Suppression Cooling Mode of operation to remove heat from the suppression pool to maintain pool temperatures within their required values. The RHR pumps also provide cooling water flow for the following: (a) Containment Spray Cooling of Drywell and Wetwell (b) Shutdown Cooling (c) Suppression Pool Cooling (Normal power operation) and (d) Fuel Pool Cooling Assist. [DBD E11-00 Section 4.1.1.1, Data Sheet 4.2.1.1] [UFSAR 5.5.7]In case of low water level in the reactor or high pressure in the containment drywell, the LPCI mode of operation of RHR system pumps water into the RPV in time to cool the core consistent with the design basis. Low-pressure coolant injection operation provides protection to the core for the case of a large break in the nuclear system when the feedwater pumps, the CRD pumps, and RCIC and HPCI systems are unable to maintain RPV water level. Protection provided by LPCI also extends to a small break in which the feedwater pumps, CRD pumps, and RCIC and HPCI systems are all unable to maintain RPV water level, and the ADS has operated to lower the reactor vessel pressure so that LPCI and core spray systems start to provide core cooling. In the event of a break in one of the two reactor recirculation system loops, logic is provided to sense the broken loop and to inject the LPCI flow into the unbroken loop. [UFSAR 6.3.2.2.4]LPCI is an independent operating mode of the RHR System. There are two LPCI subsystems [UFSAR Section 6.3.2.2.4] each consisting of two motor driven pumps and piping and valves to transfer water from the suppression pool to the RPV.
The two LPCI subsystems are interconnected via the RHR System cross-tie line. Logic is provided to sense which, if any, recirculation loop is broken and to inject the LPCI flow to an unbroken recirculation loop. The LPCI subsystems are designed to provide core cooling at low RPV pressure. Upon receipt of an initiation signal, all four LPCI pumps are automatically started. RHR System valves in the LPCI flow path are automatically positioned to ensure the proper flow path for water from the suppression pool to inject into the selected recirculation loop. When the RPV pressure drops sufficiently, the LPCI flow to the RPV, via the selected recirculation loop, begins. [TS B 3.5.1]
Function
Description:
Group A - This pump operates continuously or routinely during normal operation, cold shutdown, or refueling operations.The RHR system is designed for three modes of operation to satisfy all the objectives and bases. The main system pumps are sized for the flow required during LPCI operation, which is the subsystem that requires maximum flowrate.
The heat exchangers were originally sized on the basis of their required duty for the shutdown cooling function. The most limiting duty is that duty associated with the torus cooling mode.
The RHR system can be connected to the fuel pool cooling and cleanup system, so that RHR heat exchangers can assist fuel pool cooling during overload conditions. The shutdown cooling system is an integral part of the RHR system. It is operated during normal shutdown and cooldown. [UFSAR 5.5.7]For accident mitigation, the RHR pumps are used as Low Pressure Core Injection Pumps in the 'LPCI" mode to provide core cooling and maintain RPV level. LPCI is an independent operating mode of the RHR system. There at two LPCI subsystems, each consisting of two motor driven pumps and piping and valves to transfer water from the suppression pool to the RPV. The LPCI subsystems are designed to provide core cooling at low RPV pressure. Upon receipt of an initiation signal, all four LPCI pumps are automatically started. RHR system valves in the LPCI flow path are automatically positioned to ensure the proper flow path for water from the suppression pool to inject into the selected recirculation loop. When the RPV pressure drops sufficiently, the LPCI flow to the RPV, via the selected recirculation loop, begins. The water then enters the reactor through the jet pumps. [TS B 3.5.1]
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 5 of 106
- Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 7 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes Design Basis Limits: SR 3.6.2.3.2: Verify each required RHR pump develops a flow rate greater than or equal to 9,250 gpm through the associated heat exchanger while operating in the suppression pool cooling mode.SR 3.6.2.4.2: Verify each RHR pump develops a flow rate greater than or equal to 500 gpm through the heat exchanger and suppression pool spray sparger while operating in the suppression pool spray mode.SR 3.5.1.8 and SR 3.5.2.6: Verify the following ECCS pumps develop the specified flow rate against a system head corresponding to the specified reactor pressure.LPCI Flow Rate greater than or equal to 10,000 gpm System Head Corresponding to a Reactor Pressure of greater than or equal to 20 psig No. of pumps 1UFSAR Table 6.3-1Large leaks (accident condition)LPCI operates. Three of the four RHR main pumps take water from the suppression pool and delivers it to a recirculation loop. Signal: low reactor vessel level or high drywell pressure.Pumps and motors. Power from standby ac bus (30,000 gpm for 3 LPCI pumps plus 12,700 gpm for two core spray systems)[DBD E11-00 Section 4.1.1.1, Data Sheet 4.2.1.1]3 Pump LPCI operation equal to 11,325 gpm/pmp, with RX Pressure of 20 psid and a TDH of 398 ft 2 Pump LPCI operation equal to 11,676 gpm/pmp, with RX Pressure of 0 psid and a TDH of 379 ft Allowable continuous flow/pump equal to 12,500 gpmRated Shell Side Flow Rate SDC and (CC) - 10, 000 gpm (9250 gpm)Selected for the design rated flow because it is equal to the rated LPCI one pump flow rate (see DBD E11-00 paragraph 4.1.1.1.b) and thus does not impose any additional pumping requirements on the system. A flow of 9250 gpm (TS SR 3.6.2.3.2) is sufficient to provide an acceptable HX design. Per License Amendment 191, the TS SR 3.6.2.3.2 minimum test acceptance criterion is required to be greater than 9250 gpm to account for EDG under-frequency, test instrument accuracy, and differences in accident versus test conditions such as RHR pump suction strainer plugging. The minimum required test acceptance criterion necessary to ensure the ability to deliver greater than the 9250 gpm design minimum flow under accident is defined in DC-0367 Volume I. [DBD E11-00, Data Sheet 4.2.1.1, Section 6.0 Design Basis]
Design
References:
TS 3.5.1 ECCS-OperatingTS 3.5.2 ECCS-ShutdownTS 3.6.2.3 RHR Suppression Pool CoolingTS 3.6.2.4 RHR Suppression Pool SprayTS B 3.5 Emergency Core Cooling Systems (ECCS) And Reactor Core Isolation Cooling (RCIC) SystemTS SR 3.5.1.8 TS SR 3.5.2.6TS SR 3.6.2.3.2TS SR 3.6.2.4.2TS SR 3.5.2.6UFSAR 5.5.7 Residual Heat Removal SystemUFSAR 6.3.2.2.4 Low Pressure Coolant Injection SystemUFSAR 6.3.2.15.2 Calculation Procedure and ResultsUFSAR Table 6.2-1 Containment ParametersUFSAR Table 6.3-1 Shutdown Cooling and Emergency Core Cooling System OperationUFSAR 7.3.1 Emergency Core Cooling SystemDBD E11-00 Rev. F, Residual Heat Removal System (RHR)
Appendix V Basis: OM Code Appendix V paragraph V-3000(a) Requirement: The Owner shall (a) identify those certain applicable pumps with specific design basis accident flow rates in the Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) for inclusion in this program.SR 3.6.2.3.2: Verify each required RHR pump develops a flow rate greater than or equal to 9,250 gpm through the associated heat exchanger while operating in the suppression pool cooling mode.SR 3.6.2.4.2:
Verify each RHR pump develops a flow rate greater than or equal to 500 gpm through the heat exchanger and suppression pool spray sparger while operating in the suppression pool spray mode.SR 3.5.1.8 and SR 3.5.2.6: Verify the following ECCS pumps develop the specified flow rate against a system head corresponding to the specified reactor pressure.LPCI Flow Rate greater than or equal to 10,000 gpm System Head Corresponding to a Reactor Pressure of greater than or equal to 20 psigNo. of pumps 1UFSAR Table 6.3-1Large leaks (accident condition)
LPCI operates. Three of the four RHR main pumps take water from the suppression pool and delivers it to a recirculation loop. Signal: low reactor vessel level or high drywell pressure.Pumps and motors. Power from standby ac bus (30,000 gpm for 3 LPCI pumps plus 12,700 gpm for two core spray systems)In summary, to satisfy Appendix V, each RHR pump must be flow tested at a flow rate of greater than or equal to 10,000 gpm with system head corresponding to a Reactor Pressure of greater than or equal to 20 psig.
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 6 of 106
- D rFermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 8 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes E1102C002B E1102 Residual Heat Removal Pump B 5706-1/B-4 A 2 Centrifugal dP 2Y 24.204.06 TP-19 Q 2Y 24.204.06 TP-19 V 2Y 24.204.06 PRR-001 Standard Code ISTB dP Q 24.204.06 Q Q 24.204.06 V Q 24.204.06 PRR-001 Safety Function Basis: The 4 RHR pumps are vertical, centrifugal pumps (with mechanical seals, cyclone separators and seal-cooling-heat exchangers) coupled with a vertical mounted squirrel cage, induction, constant speed, electric motor. The pumps take suction from the suppression pool and start automatically on a LPCI initiation signal. The pumps supply a minimum of 10,000 gpm flow each, at a TDH of 594 ft (256 psid) [DBD E11-00 Pump Data Sheet 4.2.1.1] and inject water into the RPV following a LOCA to restore reactor vessel level and provide core cooling. The pumps can be operated in the Emergency - Suppression Cooling Mode of operation to remove heat from the suppression pool to maintain pool temperatures within their required values. The RHR pumps also provide cooling water flow for the following: (a) Containment Spray Cooling of Drywell and Wetwell (b) Shutdown Cooling (c) Suppression Pool Cooling (Normal power operation) and (d) Fuel Pool Cooling Assist. [DBD E11-00 Section 4.1.1.1, Data Sheet 4.2.1.1] [UFSAR 5.5.7]In case of low water level in the reactor or high pressure in the containment drywell, the LPCI mode of operation of RHR system pumps water into the RPV in time to cool the core consistent with the design basis. Low-pressure coolant injection operation provides protection to the core for the case of a large break in the nuclear system when the feedwater pumps, the CRD pumps, and RCIC and HPCI systems are unable to maintain RPV water level. Protection provided by LPCI also extends to a small break in which the feedwater pumps, CRD pumps, and RCIC and HPCI systems are all unable to maintain RPV water level, and the ADS has operated to lower the reactor vessel pressure so that LPCI and core spray systems start to provide core cooling. In the event of a break in one of the two reactor recirculation system loops, logic is provided to sense the broken loop and to inject the LPCI flow into the unbroken loop. [UFSAR 6.3.2.2.4]LPCI is an independent operating mode of the RHR System. There are two LPCI subsystems [UFSAR Section 6.3.2.2.4] each consisting of two motor driven pumps and piping and valves to transfer water from the suppression pool to the RPV.
The two LPCI subsystems are interconnected via the RHR System cross-tie line. Logic is provided to sense which, if any, recirculation loop is broken and to inject the LPCI flow to an unbroken recirculation loop. The LPCI subsystems are designed to provide core cooling at low RPV pressure. Upon receipt of an initiation signal, all four LPCI pumps are automatically started. RHR System valves in the LPCI flow path are automatically positioned to ensure the proper flow path for water from the suppression pool to inject into the selected recirculation loop. When the RPV pressure drops sufficiently, the LPCI flow to the RPV, via the selected recirculation loop, begins. [TS B 3.5.1]
Function
Description:
Group A - This pump operates continuously or routinely during normal operation, cold shutdown, or refueling operations.The RHR system is designed for three modes of operation to satisfy all the objectives and bases. The main system pumps are sized for the flow required during LPCI operation, which is the subsystem that requires maximum flowrate.
The heat exchangers were originally sized on the basis of their required duty for the shutdown cooling function. The most limiting duty is that duty associated with the torus cooling mode.
The RHR system can be connected to the fuel pool cooling and cleanup system, so that RHR heat exchangers can assist fuel pool cooling during overload conditions. The shutdown cooling system is an integral part of the RHR system. It is operated during normal shutdown and cooldown. [UFSAR 5.5.7]For accident mitigation, the RHR pumps are used as Low Pressure Core Injection Pumps in the 'LPCI" mode to provide core cooling and maintain RPV level. LPCI is an independent operating mode of the RHR system. There at two LPCI subsystems, each consisting of two motor driven pumps and piping and valves to transfer water from the suppression pool to the RPV. The LPCI subsystems are designed to provide core cooling at low RPV pressure. Upon receipt of an initiation signal, all four LPCI pumps are automatically started. RHR system valves in the LPCI flow path are automatically positioned to ensure the proper flow path for water from the suppression pool to inject into the selected recirculation loop. When the RPV pressure drops sufficiently, the LPCI flow to the RPV, via the selected recirculation loop, begins. The water then enters the reactor through the jet pumps. [TS B 3.5.1]
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 7 of 106
Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 9 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes Design Basis Limits: SR 3.6.2.3.2: Verify each required RHR pump develops a flow rate greater than or equal to 9,250 gpm through the associated heat exchanger while operating in the suppression pool cooling mode.SR 3.6.2.4.2: Verify each RHR pump develops a flow rate greater than or equal to 500 gpm through the heat exchanger and suppression pool spray sparger while operating in the suppression pool spray mode.SR 3.5.1.8 and SR 3.5.2.6: Verify the following ECCS pumps develop the specified flow rate against a system head corresponding to the specified reactor pressure.LPCI Flow Rate greater than or equal to 10,000 gpm System Head Corresponding to a Reactor Pressure of greater than or equal to 20 psig No. of pumps 1UFSAR Table 6.3-1Large leaks (accident condition)LPCI operates. Three of the four RHR main pumps take water from the suppression pool and delivers it to a recirculation loop. Signal: low reactor vessel level or high drywell pressure.Pumps and motors. Power from standby ac bus (30,000 gpm for 3 LPCI pumps plus 12,700 gpm for two core spray systems)[DBD E11-00 Section 4.1.1.1, Data Sheet 4.2.1.1]3 Pump LPCI operation equal to 11,325 gpm/pmp, with RX Pressure of 20 psid and a TDH of 398 ft 2 Pump LPCI operation equal to 11,676 gpm/pmp, with RX Pressure of 0 psid and a TDH of 379 ft Allowable continuous flow/pump equal to 12,500 gpmRated Shell Side Flow Rate SDC and (CC) - 10, 000 gpm (9250 gpm)Selected for the design rated flow because it is equal to the rated LPCI one pump flow rate (see DBD E11-00 paragraph 4.1.1.1.b) and thus does not impose any additional pumping requirements on the system. A flow of 9250 gpm (TS SR 3.6.2.3.2) is sufficient to provide an acceptable HX design. Per License Amendment 191, the TS SR 3.6.2.3.2 minimum test acceptance criterion is required to be greater than 9250 gpm to account for EDG under-frequency, test instrument accuracy, and differences in accident versus test conditions such as RHR pump suction strainer plugging. The minimum required test acceptance criterion necessary to ensure the ability to deliver greater than the 9250 gpm design minimum flow under accident is defined in DC-0367 Volume I. [DBD E11-00, Data Sheet 4.2.1.1, Section 6.0 Design Basis]
Design
References:
TS 3.5.1 ECCS-OperatingTS 3.5.2 ECCS-ShutdownTS 3.6.2.3 RHR Suppression Pool CoolingTS 3.6.2.4 RHR Suppression Pool SprayTS B 3.5 Emergency Core Cooling Systems (ECCS) And Reactor Core Isolation Cooling (RCIC) SystemTS SR 3.5.1.8 TS SR 3.5.2.6TS SR 3.6.2.3.2TS SR 3.6.2.4.2TS SR 3.5.2.6UFSAR 5.5.7 Residual Heat Removal SystemUFSAR 6.3.2.2.4 Low Pressure Coolant Injection SystemUFSAR 6.3.2.15.2 Calculation Procedure and ResultsUFSAR Table 6.2-1 Containment ParametersUFSAR Table 6.3-1 Shutdown Cooling and Emergency Core Cooling System OperationUFSAR 7.3.1 Emergency Core Cooling SystemDBD E11-00 Rev. F, Residual Heat Removal System (RHR)
Appendix V Basis: OM Code Appendix V paragraph V-3000(a) Requirement: The Owner shall (a) identify those certain applicable pumps with specific design basis accident flow rates in the Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) for inclusion in this program.SR 3.6.2.3.2: Verify each required RHR pump develops a flow rate greater than or equal to 9,250 gpm through the associated heat exchanger while operating in the suppression pool cooling mode.SR 3.6.2.4.2:
Verify each RHR pump develops a flow rate greater than or equal to 500 gpm through the heat exchanger and suppression pool spray sparger while operating in the suppression pool spray mode.SR 3.5.1.8 and SR 3.5.2.6: Verify the following ECCS pumps develop the specified flow rate against a system head corresponding to the specified reactor pressure.LPCI Flow Rate greater than or equal to 10,000 gpm System Head Corresponding to a Reactor Pressure of greater than or equal to 20 psigNo. of pumps 1UFSAR Table 6.3-1Large leaks (accident condition)
LPCI operates. Three of the four RHR main pumps take water from the suppression pool and delivers it to a recirculation loop. Signal: low reactor vessel level or high drywell pressure.Pumps and motors. Power from standby ac bus (30,000 gpm for 3 LPCI pumps plus 12,700 gpm for two core spray systems)In summary, to satisfy Appendix V, each RHR pump must be flow tested at a flow rate of greater than or equal to 10,000 gpm with system head corresponding to a Reactor Pressure of greater than or equal to 20 psig.
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 8 of 106
1M - Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 10 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes E1102C002C E1102 Residual Heat Removal Pump C 5706-2/B-8 A 2 Centrifugal dP 2Y 24.204.01 TP-19 Q 2Y 24.204.01 TP-19 V 2Y 24.204.01 PRR-001 Standard Code ISTB dP Q 24.204.01 Q Q 24.204.01 V Q 24.204.01 PRR-001 Safety Function Basis: The 4 RHR pumps are vertical, centrifugal pumps (with mechanical seals, cyclone separators and seal-cooling-heat exchangers) coupled with a vertical mounted squirrel cage, induction, constant speed, electric motor. The pumps take suction from the suppression pool and start automatically on a LPCI initiation signal. The pumps supply a minimum of 10,000 gpm flow each, at a TDH of 594 ft (256 psid) [DBD E11-00 Pump Data Sheet 4.2.1.1] and inject water into the RPV following a LOCA to restore reactor vessel level and provide core cooling. The pumps can be operated in the Emergency - Suppression Cooling Mode of operation to remove heat from the suppression pool to maintain pool temperatures within their required values. The RHR pumps also provide cooling water flow for the following: (a) Containment Spray Cooling of Drywell and Wetwell (b) Shutdown Cooling (c) Suppression Pool Cooling (Normal power operation) and (d) Fuel Pool Cooling Assist. [DBD E11-00 Section 4.1.1.1, Data Sheet 4.2.1.1] [UFSAR 5.5.7]In case of low water level in the reactor or high pressure in the containment drywell, the LPCI mode of operation of RHR system pumps water into the RPV in time to cool the core consistent with the design basis. Low-pressure coolant injection operation provides protection to the core for the case of a large break in the nuclear system when the feedwater pumps, the CRD pumps, and RCIC and HPCI systems are unable to maintain RPV water level. Protection provided by LPCI also extends to a small break in which the feedwater pumps, CRD pumps, and RCIC and HPCI systems are all unable to maintain RPV water level, and the ADS has operated to lower the reactor vessel pressure so that LPCI and core spray systems start to provide core cooling. In the event of a break in one of the two reactor recirculation system loops, logic is provided to sense the broken loop and to inject the LPCI flow into the unbroken loop. [UFSAR 6.3.2.2.4]LPCI is an independent operating mode of the RHR System. There are two LPCI subsystems [UFSAR Section 6.3.2.2.4] each consisting of two motor driven pumps and piping and valves to transfer water from the suppression pool to the RPV.
The two LPCI subsystems are interconnected via the RHR System cross-tie line. Logic is provided to sense which, if any, recirculation loop is broken and to inject the LPCI flow to an unbroken recirculation loop. The LPCI subsystems are designed to provide core cooling at low RPV pressure. Upon receipt of an initiation signal, all four LPCI pumps are automatically started. RHR System valves in the LPCI flow path are automatically positioned to ensure the proper flow path for water from the suppression pool to inject into the selected recirculation loop. When the RPV pressure drops sufficiently, the LPCI flow to the RPV, via the selected recirculation loop, begins. [TS B 3.5.1]
Function
Description:
Group A - This pump operates continuously or routinely during normal operation, cold shutdown, or refueling operations.The RHR system is designed for three modes of operation to satisfy all the objectives and bases. The main system pumps are sized for the flow required during LPCI operation, which is the subsystem that requires maximum flowrate.
The heat exchangers were originally sized on the basis of their required duty for the shutdown cooling function. The most limiting duty is that duty associated with the torus cooling mode.
The RHR system can be connected to the fuel pool cooling and cleanup system, so that RHR heat exchangers can assist fuel pool cooling during overload conditions. The shutdown cooling system is an integral part of the RHR system. It is operated during normal shutdown and cooldown. [UFSAR 5.5.7]For accident mitigation, the RHR pumps are used as Low Pressure Core Injection Pumps in the 'LPCI" mode to provide core cooling and maintain RPV level. LPCI is an independent operating mode of the RHR system. There at two LPCI subsystems, each consisting of two motor driven pumps and piping and valves to transfer water from the suppression pool to the RPV. The LPCI subsystems are designed to provide core cooling at low RPV pressure. Upon receipt of an initiation signal, all four LPCI pumps are automatically started. RHR system valves in the LPCI flow path are automatically positioned to ensure the proper flow path for water from the suppression pool to inject into the selected recirculation loop. When the RPV pressure drops sufficiently, the LPCI flow to the RPV, via the selected recirculation loop, begins. The water then enters the reactor through the jet pumps. [TS B 3.5.1]
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 9 of 106
Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 11 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes Design Basis Limits: SR 3.6.2.3.2: Verify each required RHR pump develops a flow rate greater than or equal to 9,250 gpm through the associated heat exchanger while operating in the suppression pool cooling mode.SR 3.6.2.4.2: Verify each RHR pump develops a flow rate greater than or equal to 500 gpm through the heat exchanger and suppression pool spray sparger while operating in the suppression pool spray mode.SR 3.5.1.8 and SR 3.5.2.6: Verify the following ECCS pumps develop the specified flow rate against a system head corresponding to the specified reactor pressure.LPCI Flow Rate greater than or equal to 10,000 gpm System Head Corresponding to a Reactor Pressure of greater than or equal to 20 psig No. of pumps 1UFSAR Table 6.3-1Large leaks (accident condition)LPCI operates. Three of the four RHR main pumps take water from the suppression pool and delivers it to a recirculation loop. Signal: low reactor vessel level or high drywell pressure.Pumps and motors. Power from standby ac bus (30,000 gpm for 3 LPCI pumps plus 12,700 gpm for two core spray systems)[DBD E11-00 Section 4.1.1.1, Data Sheet 4.2.1.1]3 Pump LPCI operation equal to 11,325 gpm/pmp, with RX Pressure of 20 psid and a TDH of 398 ft 2 Pump LPCI operation equal to 11,676 gpm/pmp, with RX Pressure of 0 psid and a TDH of 379 ft Allowable continuous flow/pump equal to 12,500 gpmRated Shell Side Flow Rate SDC and (CC) - 10, 000 gpm (9250 gpm)Selected for the design rated flow because it is equal to the rated LPCI one pump flow rate (see DBD E11-00 paragraph 4.1.1.1.b) and thus does not impose any additional pumping requirements on the system. A flow of 9250 gpm (TS SR 3.6.2.3.2) is sufficient to provide an acceptable HX design. Per License Amendment 191, the TS SR 3.6.2.3.2 minimum test acceptance criterion is required to be greater than 9250 gpm to account for EDG under-frequency, test instrument accuracy, and differences in accident versus test conditions such as RHR pump suction strainer plugging. The minimum required test acceptance criterion necessary to ensure the ability to deliver greater than the 9250 gpm design minimum flow under accident is defined in DC-0367 Volume I. [DBD E11-00, Data Sheet 4.2.1.1, Section 6.0 Design Basis]
Design
References:
TS 3.5.1 ECCS-OperatingTS 3.5.2 ECCS-ShutdownTS 3.6.2.3 RHR Suppression Pool CoolingTS 3.6.2.4 RHR Suppression Pool SprayTS B 3.5 Emergency Core Cooling Systems (ECCS) And Reactor Core Isolation Cooling (RCIC) SystemTS SR 3.5.1.8 TS SR 3.5.2.6TS SR 3.6.2.3.2TS SR 3.6.2.4.2TS SR 3.5.2.6UFSAR 5.5.7 Residual Heat Removal SystemUFSAR 6.3.2.2.4 Low Pressure Coolant Injection SystemUFSAR 6.3.2.15.2 Calculation Procedure and ResultsUFSAR Table 6.2-1 Containment ParametersUFSAR Table 6.3-1 Shutdown Cooling and Emergency Core Cooling System OperationUFSAR 7.3.1 Emergency Core Cooling SystemDBD E11-00 Rev. F, Residual Heat Removal System (RHR)
Appendix V Basis: OM Code Appendix V paragraph V-3000(a) Requirement: The Owner shall (a) identify those certain applicable pumps with specific design basis accident flow rates in the Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) for inclusion in this program.SR 3.6.2.3.2: Verify each required RHR pump develops a flow rate greater than or equal to 9,250 gpm through the associated heat exchanger while operating in the suppression pool cooling mode.SR 3.6.2.4.2:
Verify each RHR pump develops a flow rate greater than or equal to 500 gpm through the heat exchanger and suppression pool spray sparger while operating in the suppression pool spray mode.SR 3.5.1.8 and SR 3.5.2.6: Verify the following ECCS pumps develop the specified flow rate against a system head corresponding to the specified reactor pressure.LPCI Flow Rate greater than or equal to 10,000 gpm System Head Corresponding to a Reactor Pressure of greater than or equal to 20 psigNo. of pumps 1UFSAR Table 6.3-1Large leaks (accident condition)
LPCI operates. Three of the four RHR main pumps take water from the suppression pool and delivers it to a recirculation loop. Signal: low reactor vessel level or high drywell pressure.Pumps and motors. Power from standby ac bus (30,000 gpm for 3 LPCI pumps plus 12,700 gpm for two core spray systems)In summary, to satisfy Appendix V, each RHR pump must be flow tested at a flow rate of greater than or equal to 10,000 gpm with system head corresponding to a Reactor Pressure of greater than or equal to 20 psig.
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 10 of 106
DTIE E ergy-Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 12 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes E1102C002D E1102 Residual Heat Removal Pump D 5706-1/B-3 A 2 Centrifugal dP 2Y 24.204.06 TP-19 Q 2Y 24.204.06 TP-19 V 2Y 24.204.06 PRR-001 Standard Code ISTB dP Q 24.204.06 Q Q 24.204.06 V Q 24.204.06 PRR-001 Safety Function Basis: The 4 RHR pumps are vertical, centrifugal pumps (with mechanical seals, cyclone separators and seal-cooling-heat exchangers) coupled with a vertical mounted squirrel cage, induction, constant speed, electric motor. The pumps take suction from the suppression pool and start automatically on a LPCI initiation signal. The pumps supply a minimum of 10,000 gpm flow each, at a TDH of 594 ft (256 psid) [DBD E11-00 Pump Data Sheet 4.2.1.1] and inject water into the RPV following a LOCA to restore reactor vessel level and provide core cooling. The pumps can be operated in the Emergency - Suppression Cooling Mode of operation to remove heat from the suppression pool to maintain pool temperatures within their required values. The RHR pumps also provide cooling water flow for the following: (a) Containment Spray Cooling of Drywell and Wetwell (b) Shutdown Cooling (c) Suppression Pool Cooling (Normal power operation) and (d) Fuel Pool Cooling Assist. [DBD E11-00 Section 4.1.1.1, Data Sheet 4.2.1.1] [UFSAR 5.5.7]In case of low water level in the reactor or high pressure in the containment drywell, the LPCI mode of operation of RHR system pumps water into the RPV in time to cool the core consistent with the design basis. Low-pressure coolant injection operation provides protection to the core for the case of a large break in the nuclear system when the feedwater pumps, the CRD pumps, and RCIC and HPCI systems are unable to maintain RPV water level. Protection provided by LPCI also extends to a small break in which the feedwater pumps, CRD pumps, and RCIC and HPCI systems are all unable to maintain RPV water level, and the ADS has operated to lower the reactor vessel pressure so that LPCI and core spray systems start to provide core cooling. In the event of a break in one of the two reactor recirculation system loops, logic is provided to sense the broken loop and to inject the LPCI flow into the unbroken loop. [UFSAR 6.3.2.2.4]LPCI is an independent operating mode of the RHR System. There are two LPCI subsystems [UFSAR Section 6.3.2.2.4] each consisting of two motor driven pumps and piping and valves to transfer water from the suppression pool to the RPV.
The two LPCI subsystems are interconnected via the RHR System cross-tie line. Logic is provided to sense which, if any, recirculation loop is broken and to inject the LPCI flow to an unbroken recirculation loop. The LPCI subsystems are designed to provide core cooling at low RPV pressure. Upon receipt of an initiation signal, all four LPCI pumps are automatically started. RHR System valves in the LPCI flow path are automatically positioned to ensure the proper flow path for water from the suppression pool to inject into the selected recirculation loop. When the RPV pressure drops sufficiently, the LPCI flow to the RPV, via the selected recirculation loop, begins. [TS B 3.5.1]
Function
Description:
Group A - This pump operates continuously or routinely during normal operation, cold shutdown, or refueling operations.The RHR system is designed for three modes of operation to satisfy all the objectives and bases. The main system pumps are sized for the flow required during LPCI operation, which is the subsystem that requires maximum flowrate.
The heat exchangers were originally sized on the basis of their required duty for the shutdown cooling function. The most limiting duty is that duty associated with the torus cooling mode.
The RHR system can be connected to the fuel pool cooling and cleanup system, so that RHR heat exchangers can assist fuel pool cooling during overload conditions. The shutdown cooling system is an integral part of the RHR system. It is operated during normal shutdown and cooldown. [UFSAR 5.5.7]For accident mitigation, the RHR pumps are used as Low Pressure Core Injection Pumps in the 'LPCI" mode to provide core cooling and maintain RPV level. LPCI is an independent operating mode of the RHR system. There at two LPCI subsystems, each consisting of two motor driven pumps and piping and valves to transfer water from the suppression pool to the RPV. The LPCI subsystems are designed to provide core cooling at low RPV pressure. Upon receipt of an initiation signal, all four LPCI pumps are automatically started. RHR system valves in the LPCI flow path are automatically positioned to ensure the proper flow path for water from the suppression pool to inject into the selected recirculation loop. When the RPV pressure drops sufficiently, the LPCI flow to the RPV, via the selected recirculation loop, begins. The water then enters the reactor through the jet pumps. [TS B 3.5.1]
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 11 of 106
Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 13 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes Design Basis Limits: SR 3.6.2.3.2: Verify each required RHR pump develops a flow rate greater than or equal to 9,250 gpm through the associated heat exchanger while operating in the suppression pool cooling mode.SR 3.6.2.4.2: Verify each RHR pump develops a flow rate greater than or equal to 500 gpm through the heat exchanger and suppression pool spray sparger while operating in the suppression pool spray mode.SR 3.5.1.8 and SR 3.5.2.6: Verify the following ECCS pumps develop the specified flow rate against a system head corresponding to the specified reactor pressure.LPCI Flow Rate greater than or equal to 10,000 gpm System Head Corresponding to a Reactor Pressure of greater than or equal to 20 psig No. of pumps 1UFSAR Table 6.3-1Large leaks (accident condition)LPCI operates. Three of the four RHR main pumps take water from the suppression pool and delivers it to a recirculation loop. Signal: low reactor vessel level or high drywell pressure.Pumps and motors. Power from standby ac bus (30,000 gpm for 3 LPCI pumps plus 12,700 gpm for two core spray systems)[DBD E11-00 Section 4.1.1.1, Data Sheet 4.2.1.1]3 Pump LPCI operation equal to 11,325 gpm/pmp, with RX Pressure of 20 psid and a TDH of 398 ft 2 Pump LPCI operation equal to 11,676 gpm/pmp, with RX Pressure of 0 psid and a TDH of 379 ft Allowable continuous flow/pump equal to 12,500 gpmRated Shell Side Flow Rate SDC and (CC) - 10, 000 gpm (9250 gpm)Selected for the design rated flow because it is equal to the rated LPCI one pump flow rate (see DBD E11-00 paragraph 4.1.1.1.b) and thus does not impose any additional pumping requirements on the system. A flow of 9250 gpm (TS SR 3.6.2.3.2) is sufficient to provide an acceptable HX design. Per License Amendment 191, the TS SR 3.6.2.3.2 minimum test acceptance criterion is required to be greater than 9250 gpm to account for EDG under-frequency, test instrument accuracy, and differences in accident versus test conditions such as RHR pump suction strainer plugging. The minimum required test acceptance criterion necessary to ensure the ability to deliver greater than the 9250 gpm design minimum flow under accident is defined in DC-0367 Volume I. [DBD E11-00, Data Sheet 4.2.1.1, Section 6.0 Design Basis]
Design
References:
TS 3.5.1 ECCS-OperatingTS 3.5.2 ECCS-ShutdownTS 3.6.2.3 RHR Suppression Pool CoolingTS 3.6.2.4 RHR Suppression Pool SprayTS B 3.5 Emergency Core Cooling Systems (ECCS) And Reactor Core Isolation Cooling (RCIC) SystemTS SR 3.5.1.8 TS SR 3.5.2.6TS SR 3.6.2.3.2TS SR 3.6.2.4.2TS SR 3.5.2.6UFSAR 5.5.7 Residual Heat Removal SystemUFSAR 6.3.2.2.4 Low Pressure Coolant Injection SystemUFSAR 6.3.2.15.2 Calculation Procedure and ResultsUFSAR Table 6.2-1 Containment ParametersUFSAR Table 6.3-1 Shutdown Cooling and Emergency Core Cooling System OperationUFSAR 7.3.1 Emergency Core Cooling SystemDBD E11-00 Rev. F, Residual Heat Removal System (RHR)
Appendix V Basis: OM Code Appendix V paragraph V-3000(a) Requirement: The Owner shall (a) identify those certain applicable pumps with specific design basis accident flow rates in the Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) for inclusion in this program.SR 3.6.2.3.2: Verify each required RHR pump develops a flow rate greater than or equal to 9,250 gpm through the associated heat exchanger while operating in the suppression pool cooling mode.SR 3.6.2.4.2:
Verify each RHR pump develops a flow rate greater than or equal to 500 gpm through the heat exchanger and suppression pool spray sparger while operating in the suppression pool spray mode.SR 3.5.1.8 and SR 3.5.2.6: Verify the following ECCS pumps develop the specified flow rate against a system head corresponding to the specified reactor pressure.LPCI Flow Rate greater than or equal to 10,000 gpm System Head Corresponding to a Reactor Pressure of greater than or equal to 20 psigNo. of pumps 1UFSAR Table 6.3-1Large leaks (accident condition)
LPCI operates. Three of the four RHR main pumps take water from the suppression pool and delivers it to a recirculation loop. Signal: low reactor vessel level or high drywell pressure.Pumps and motors. Power from standby ac bus (30,000 gpm for 3 LPCI pumps plus 12,700 gpm for two core spray systems)In summary, to satisfy Appendix V, each RHR pump must be flow tested at a flow rate of greater than or equal to 10,000 gpm with system head corresponding to a Reactor Pressure of greater than or equal to 20 psig.
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 12 of 106
I VFermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 14 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes E1151C001A E1151 RHR Service Water Pump A 5706-3/G-4 A 3 Vertical Line Shaft dP 2Y 24.205.05 PRR-003, TP-19 Q 2Y 24.205.05 TP-19 V 2Y 24.205.05 PRR-002 Standard Code ISTB dP Q 24.205.05 PRR-003 Q Q 24.205.05 V Q 24.205.05 PRR-002 Safety Function Basis: The RHRSW System consists of two independent and redundant subsystems. Each subsystem is made up of a header, two pumps (with a combined nominal capacity of 9000 gpm), and suction source, valves, piping, heat exchanger, and associated instrumentation. Either of the two subsystems is capable of providing the required cooling capacity to maintain safe shutdown conditions. The two subsystems are separated from each other so that the failure of one subsystem will not affect the operability of the other subsystem. [TS Bases B 3.7.1] During normal and/or accident shutdown conditions, the function of the RHRSW and EESW systems is to remove decay heat from the RHR heat exchangers and the EECW heat exchangers, respectively. [UFSAR 3.8.4.1.2] Power for the main RHR and RHRSW pumps normally comes from an auxiliary ac power bus; but if offsite power is lost, power is made available from the standby ac power source to supply the RHR and RHRSW pumps. [UFSAR 5.5.7.3.4]Each of the four RHRSW pumps is a two-staged, motor-driven vertical pump. The RHRSW pumps are designed to supply a design minimum of 8,250 gpm and a design maximum of 10,430 gpm to the RHR heat exchanger in each division with two RHRSW pumps operating and normal RHR reservoir levels. The safety-related pumps are designated QA Level 1, seismic Category I, and are designed to ASME Section III, Class 3 requirements. The RHRSW pumps are located in the RHR complex and are not in a harsh environment. Design analysis indicates the "as-built" TDH requirement is 174 feet at 4500 gpm. Two pumps provide the minimum 8250 gpm required by the RHR heat exchanger. [DBD E11-XX Section 4.2.1] [UFSAR 7.3.9]Cooling water is pump by the RHRSW pumps from the RHR Reservoir through the tube side of the RHR heat exchangers, and discharges to the associated RHR Reservoir via the mechanical draft cooling towers or cooling tower bypass line during cold weather or testing. A minimum flow line from the pump discharge to the RHR Reservoir prevents the pump from overheating when pumping against closed flow path(s). However, the minimum flow protection is not assumed to function in an accident. The system is initiated manually from the control room. If operating during a loss of coolant accident (LOCA), the system is automatically tripped to allow the diesel generators to automatically power only that equipment necessary to flood the core. The system can be manually started if the LOCA signal is manually overridden or clears. [TS Bases B 3.7.1]The conditions assumed for calculating the peak suppression pool temperature and the available NPSH margin assume the temperature of the RHRSW reservoir varies linearly from 80 degrees F to 90 degrees F over 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and stabilizes at 90 degrees F. [UFSAR 6.3.2.14 Net Positive Suction Head]
Function
Description:
Group A - This pump operates continuously or routinely during normal operation, cold shutdown, or refueling operations.The RHRSW System is designed to provide cooling water for the Residual Heat Removal (RHR) System heat exchangers, required for a safe reactor shutdown following a Design Basis Accident (DBA) or transient. The RHR System is operated whenever the RHR heat exchangers are required to operate in the shutdown cooling mode, in the suppression pool cooling or in the fuel pool cooling assist modes of the RHR System. The RHRSW System also provides means to flood the Reactor Pressure Vessel or Primary Containment following a postulated Loss-of-Coolant Accident (LOCA). [TS Bases B 3.7.1]
The RHRSW System removes heat from the suppression pool to limit the suppression pool temperature and primary containment pressure following a LOCA. This ensures that the primary containment can perform its function of limiting the release of radioactive materials to the environment following a LOCA. [TS Bases B 3.7.1 Applicable Safety Analyses] The residual heat removal service water (RHRSW) system serves as the ultimate heat sink. Its design includes two 3,465,000-gal reservoirs. They are sized in accordance with the recommendations of Regulatory Guide 1.27. [UFSAR 6.3.2.6 Coolant Quantity]The RHRSW system is designed to; (a) with the RHR system, to remove decay heat and residual heat from the nuclear system to that refueling and nuclear system servicing can be performed; (b) with the RHR system, to supplement the fuel pool cooling system with additional cooling capacity; (c) with the RHR system, to remove decay heat and residual heat from the nuclear system by cooling the suppression pool water, following a postulated LOCA; (d) to provide a method to flood the reactor pressure vessel (RPV), acting as a backup in the extremely unlikely event that all RHR (low pressure coolant injection [LPCI[ mode) and core spray pumps fail to operate following a postulated LOCA; (e) to provide a method to flood primary containment so that the fuel can be removed from the RPV following a postulated LOCA. [UFAR 9.2.5.1 Design Basis] (a) and (b) above are not considered accident mitigating for the purposes of ISTA-1100.
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 13 of 106
- Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 15 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes Design Basis Limits: UFSAR Table 6.2-1 Containment ParametersHeat exchangers (RHR system)Flow of pumps, gpmShell-side 10,000* with one RHR pumpTube-side 9,000**Source of cooling water RHR service water* RHR heat exchanger performance maintained to assure credited overall heat transfer coefficient based on an RHR heat exchanger flow of 9250 gpm.** RHRSW pump flow reduces below 9,000 gpm with time due to the RHR reservoir evaporative and drift losses.Component Parameters [Nominal (nameplate) unless otherwise indicated. [DBD E11-XX Section 4.2.1]Pump:Capacity, gpm 4,500Minimum flow, gpm 500* Design analysis indicates the "as-built" TDH requirement is 174 feet at 4500 gpm. Two pumps provide the minimum 8250 gpm required by the RHR heat exchanger.Each of the four RHRSW pumps is a two-staged, motor-driven vertical pump. The RHRSW pumps are designed to supply a design minimum of 8,250 gpm and a design maximum of 10,430 gpm to the RHR heat exchanger in each division with two RHRSW pumps operating and normal RHR reservoir levels. The safety-related pumps are designated QA Level 1, seismic Category I, and are designed to ASME Section III, Class 3 requirements. The RHRSW pumps are located in the RHR complex and are not in a harsh environment. Design analysis indicates the "as-built" TDH requirement is 174 feet at 4500 gpm. Two pumps provide the minimum 8250 gpm required by the RHR heat exchanger. [DBD E11-XX Section 4.2.1] [UFSAR 7.3.9]The RHRSW pumps are started and stopped manually from the main control room. Each pair of pumps is capable of delivering 9000 gpm to the RHR heat exchangers and then to the cooling towers. In the flooding mode, the head of water is sufficient to fill 300,000 cubic feet of air space in the drywell in 1 week, at a rate of approximately 250 gpm. In the event of failure of all four of the 10,000-gpm RHR pumps, the RHRSW pumps in Division II will be capable of backup to the RHR pumps in the LPCI mode at a rate of 3250 gpm. [UFSAR 9.2.5.2.5 Pumps] The RHRSWS is designed to meet Category I requirements. [UFSAR 9.2.5.3.1.1 Earthquakes]
Design
References:
TS 3.7.1 Residual Heat Removal Service Water (RHRSW) System and associated BasesTS 3.7.2 Emergency Equipment Cooling Water (EECW/Emergency Equipment Service Water (EESW) System and Ultimate Heat Sink (UHS) and associated BasesUFSAR 3.8.4.1.2 Residual Heat Removal ComplexUFSAR 5.5.7.3.4 Low Pressure Coolant Injection SystemUFSAR 6.2.1.3.3 Recirculation Line Break Long Term ResponseUFSAR Table 6.2-1 Containment ParametersUFSAR 6.3.2.14 Net Positive Suction HeadUFSAR 6.3.2.6 Coolant QuantityUFSAR 7.3.9 Residual Heat Removal Service Water System Instrumentation and ControlUFSAR 9.2.5 Ultimate Heat SinkDBD E11-XX Rev. C, Residual Heat Removal Service Water (RHRSW) System Appendix V Basis: OM Code Appendix V paragraph V-3000(a) Requirement: The Owner shall (a) identify those certain applicable pumps with specific design basis accident flow rates in the Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) for inclusion in this program.UFSAR Table 6.2-1 Containment ParametersHeat exchangers (RHR system)Flow of pumps, gpmShell-side 10,000* with one RHR pumpTube-side 9,000**Source of cooling water RHR service water* RHR heat exchanger performance maintained to assure credited overall heat transfer coefficient based on an RHR heat exchanger flow of 9250 gpm.** RHRSW pump flow reduces below 9,000 gpm with time due to the RHR reservoir evaporative and drift losses.In summary, to satisfy Appendix V, each RHRSW pump must be flow tested at a flow rate of greater than or equal to 9000 gpm divided by 2, based on the design flow rates provided, which equates to 4500 gpm.
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 14 of 106
DI e-- Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 16 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes E1151C001B E1151 RHR Service Water Pump B 5706-3/G-5 A 3 Vertical Line Shaft dP 2Y 24.205.06 PRR-003, TP-19 Q 2Y 24.205.06 TP-19 V 2Y 24.205.06 PRR-002 Standard Code ISTB dP Q 24.205.06 PRR-003 Q Q 24.205.06 V Q 24.205.06 PRR-002 Safety Function Basis: The RHRSW System consists of two independent and redundant subsystems. Each subsystem is made up of a header, two pumps (with a combined nominal capacity of 9000 gpm), and suction source, valves, piping, heat exchanger, and associated instrumentation. Either of the two subsystems is capable of providing the required cooling capacity to maintain safe shutdown conditions. The two subsystems are separated from each other so that the failure of one subsystem will not affect the operability of the other subsystem. [TS Bases B 3.7.1] During normal and/or accident shutdown conditions, the function of the RHRSW and EESW systems is to remove decay heat from the RHR heat exchangers and the EECW heat exchangers, respectively. [UFSAR 3.8.4.1.2] Power for the main RHR and RHRSW pumps normally comes from an auxiliary ac power bus; but if offsite power is lost, power is made available from the standby ac power source to supply the RHR and RHRSW pumps. [UFSAR 5.5.7.3.4]Each of the four RHRSW pumps is a two-staged, motor-driven vertical pump. The RHRSW pumps are designed to supply a design minimum of 8,250 gpm and a design maximum of 10,430 gpm to the RHR heat exchanger in each division with two RHRSW pumps operating and normal RHR reservoir levels. The safety-related pumps are designated QA Level 1, seismic Category I, and are designed to ASME Section III, Class 3 requirements. The RHRSW pumps are located in the RHR complex and are not in a harsh environment. Design analysis indicates the "as-built" TDH requirement is 174 feet at 4500 gpm. Two pumps provide the minimum 8250 gpm required by the RHR heat exchanger. [DBD E11-XX Section 4.2.1] [UFSAR 7.3.9]Cooling water is pump by the RHRSW pumps from the RHR Reservoir through the tube side of the RHR heat exchangers, and discharges to the associated RHR Reservoir via the mechanical draft cooling towers or cooling tower bypass line during cold weather or testing. A minimum flow line from the pump discharge to the RHR Reservoir prevents the pump from overheating when pumping against closed flow path(s). However, the minimum flow protection is not assumed to function in an accident. The system is initiated manually from the control room. If operating during a loss of coolant accident (LOCA), the system is automatically tripped to allow the diesel generators to automatically power only that equipment necessary to flood the core. The system can be manually started if the LOCA signal is manually overridden or clears. [TS Bases B 3.7.1]The conditions assumed for calculating the peak suppression pool temperature and the available NPSH margin assume the temperature of the RHRSW reservoir varies linearly from 80 degrees F to 90 degrees F over 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and stabilizes at 90 degrees F. [UFSAR 6.3.2.14 Net Positive Suction Head]
Function
Description:
Group A - This pump operates continuously or routinely during normal operation, cold shutdown, or refueling operations.The RHRSW System is designed to provide cooling water for the Residual Heat Removal (RHR) System heat exchangers, required for a safe reactor shutdown following a Design Basis Accident (DBA) or transient. The RHR System is operated whenever the RHR heat exchangers are required to operate in the shutdown cooling mode, in the suppression pool cooling or in the fuel pool cooling assist modes of the RHR System. The RHRSW System also provides means to flood the Reactor Pressure Vessel or Primary Containment following a postulated Loss-of-Coolant Accident (LOCA). [TS Bases B 3.7.1]
The RHRSW System removes heat from the suppression pool to limit the suppression pool temperature and primary containment pressure following a LOCA. This ensures that the primary containment can perform its function of limiting the release of radioactive materials to the environment following a LOCA. [TS Bases B 3.7.1 Applicable Safety Analyses] The residual heat removal service water (RHRSW) system serves as the ultimate heat sink. Its design includes two 3,465,000-gal reservoirs. They are sized in accordance with the recommendations of Regulatory Guide 1.27. [UFSAR 6.3.2.6 Coolant Quantity]The RHRSW system is designed to; (a) with the RHR system, to remove decay heat and residual heat from the nuclear system to that refueling and nuclear system servicing can be performed; (b) with the RHR system, to supplement the fuel pool cooling system with additional cooling capacity; (c) with the RHR system, to remove decay heat and residual heat from the nuclear system by cooling the suppression pool water, following a postulated LOCA; (d) to provide a method to flood the reactor pressure vessel (RPV), acting as a backup in the extremely unlikely event that all RHR (low pressure coolant injection [LPCI[ mode) and core spray pumps fail to operate following a postulated LOCA; (e) to provide a method to flood primary containment so that the fuel can be removed from the RPV following a postulated LOCA. [UFAR 9.2.5.1 Design Basis] (a) and (b) above are not considered accident mitigating for the purposes of ISTA-1100.
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 15 of 106
Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 17 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes Design Basis Limits: UFSAR Table 6.2-1 Containment ParametersHeat exchangers (RHR system)Flow of pumps, gpmShell-side 10,000* with one RHR pumpTube-side 9,000**Source of cooling water RHR service water* RHR heat exchanger performance maintained to assure credited overall heat transfer coefficient based on an RHR heat exchanger flow of 9250 gpm.** RHRSW pump flow reduces below 9,000 gpm with time due to the RHR reservoir evaporative and drift losses.Component Parameters [Nominal (nameplate) unless otherwise indicated. [DBD E11-XX Section 4.2.1]Pump:Capacity, gpm 4,500Minimum flow, gpm 500* Design analysis indicates the "as-built" TDH requirement is 174 feet at 4500 gpm. Two pumps provide the minimum 8250 gpm required by the RHR heat exchanger.Each of the four RHRSW pumps is a two-staged, motor-driven vertical pump. The RHRSW pumps are designed to supply a design minimum of 8,250 gpm and a design maximum of 10,430 gpm to the RHR heat exchanger in each division with two RHRSW pumps operating and normal RHR reservoir levels. The safety-related pumps are designated QA Level 1, seismic Category I, and are designed to ASME Section III, Class 3 requirements. The RHRSW pumps are located in the RHR complex and are not in a harsh environment. Design analysis indicates the "as-built" TDH requirement is 174 feet at 4500 gpm. Two pumps provide the minimum 8250 gpm required by the RHR heat exchanger. [DBD E11-XX Section 4.2.1] [UFSAR 7.3.9]The RHRSW pumps are started and stopped manually from the main control room. Each pair of pumps is capable of delivering 9000 gpm to the RHR heat exchangers and then to the cooling towers. In the flooding mode, the head of water is sufficient to fill 300,000 cubic feet of air space in the drywell in 1 week, at a rate of approximately 250 gpm. In the event of failure of all four of the 10,000-gpm RHR pumps, the RHRSW pumps in Division II will be capable of backup to the RHR pumps in the LPCI mode at a rate of 3250 gpm. [UFSAR 9.2.5.2.5 Pumps] The RHRSWS is designed to meet Category I requirements. [UFSAR 9.2.5.3.1.1 Earthquakes]
Design
References:
TS 3.7.1 Residual Heat Removal Service Water (RHRSW) System and associated BasesTS 3.7.2 Emergency Equipment Cooling Water (EECW/Emergency Equipment Service Water (EESW) System and Ultimate Heat Sink (UHS) and associated BasesUFSAR 3.8.4.1.2 Residual Heat Removal ComplexUFSAR 5.5.7.3.4 Low Pressure Coolant Injection SystemUFSAR 6.2.1.3.3 Recirculation Line Break Long Term ResponseUFSAR Table 6.2-1 Containment ParametersUFSAR 6.3.2.14 Net Positive Suction HeadUFSAR 6.3.2.6 Coolant QuantityUFSAR 7.3.9 Residual Heat Removal Service Water System Instrumentation and ControlUFSAR 9.2.5 Ultimate Heat SinkDBD E11-XX Rev. C, Residual Heat Removal Service Water (RHRSW) System Appendix V Basis: OM Code Appendix V paragraph V-3000(a) Requirement: The Owner shall (a) identify those certain applicable pumps with specific design basis accident flow rates in the Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) for inclusion in this program.UFSAR Table 6.2-1 Containment ParametersHeat exchangers (RHR system)Flow of pumps, gpmShell-side 10,000* with one RHR pumpTube-side 9,000**Source of cooling water RHR service water* RHR heat exchanger performance maintained to assure credited overall heat transfer coefficient based on an RHR heat exchanger flow of 9250 gpm.** RHRSW pump flow reduces below 9,000 gpm with time due to the RHR reservoir evaporative and drift losses.In summary, to satisfy Appendix V, each RHRSW pump must be flow tested at a flow rate of greater than or equal to 9000 gpm divided by 2, based on the design flow rates provided, which equates to 4500 gpm.
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 16 of 106
an -n r Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 18 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes E1151C001C E1151 RHR Service Water Pump C 5706-3/G-4 A 3 Vertical Line Shaft dP 2Y 24.205.05 PRR-003, TP-19 Q 2Y 24.205.05 TP-19 V 2Y 24.205.05 PRR-002 Standard Code ISTB dP Q 24.205.05 PRR-003 Q Q 24.205.05 V Q 24.205.05 PRR-002 Safety Function Basis: The RHRSW System consists of two independent and redundant subsystems. Each subsystem is made up of a header, two pumps (with a combined nominal capacity of 9000 gpm), and suction source, valves, piping, heat exchanger, and associated instrumentation. Either of the two subsystems is capable of providing the required cooling capacity to maintain safe shutdown conditions. The two subsystems are separated from each other so that the failure of one subsystem will not affect the operability of the other subsystem. [TS Bases B 3.7.1] During normal and/or accident shutdown conditions, the function of the RHRSW and EESW systems is to remove decay heat from the RHR heat exchangers and the EECW heat exchangers, respectively. [UFSAR 3.8.4.1.2] Power for the main RHR and RHRSW pumps normally comes from an auxiliary ac power bus; but if offsite power is lost, power is made available from the standby ac power source to supply the RHR and RHRSW pumps. [UFSAR 5.5.7.3.4]Each of the four RHRSW pumps is a two-staged, motor-driven vertical pump. The RHRSW pumps are designed to supply a design minimum of 8,250 gpm and a design maximum of 10,430 gpm to the RHR heat exchanger in each division with two RHRSW pumps operating and normal RHR reservoir levels. The safety-related pumps are designated QA Level 1, seismic Category I, and are designed to ASME Section III, Class 3 requirements. The RHRSW pumps are located in the RHR complex and are not in a harsh environment. Design analysis indicates the "as-built" TDH requirement is 174 feet at 4500 gpm. Two pumps provide the minimum 8250 gpm required by the RHR heat exchanger. [DBD E11-XX Section 4.2.1] [UFSAR 7.3.9]Cooling water is pump by the RHRSW pumps from the RHR Reservoir through the tube side of the RHR heat exchangers, and discharges to the associated RHR Reservoir via the mechanical draft cooling towers or cooling tower bypass line during cold weather or testing. A minimum flow line from the pump discharge to the RHR Reservoir prevents the pump from overheating when pumping against closed flow path(s). However, the minimum flow protection is not assumed to function in an accident. The system is initiated manually from the control room. If operating during a loss of coolant accident (LOCA), the system is automatically tripped to allow the diesel generators to automatically power only that equipment necessary to flood the core. The system can be manually started if the LOCA signal is manually overridden or clears. [TS Bases B 3.7.1]The conditions assumed for calculating the peak suppression pool temperature and the available NPSH margin assume the temperature of the RHRSW reservoir varies linearly from 80 degrees F to 90 degrees F over 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and stabilizes at 90 degrees F. [UFSAR 6.3.2.14 Net Positive Suction Head]
Function
Description:
Group A - This pump operates continuously or routinely during normal operation, cold shutdown, or refueling operations.The RHRSW System is designed to provide cooling water for the Residual Heat Removal (RHR) System heat exchangers, required for a safe reactor shutdown following a Design Basis Accident (DBA) or transient. The RHR System is operated whenever the RHR heat exchangers are required to operate in the shutdown cooling mode, in the suppression pool cooling or in the fuel pool cooling assist modes of the RHR System. The RHRSW System also provides means to flood the Reactor Pressure Vessel or Primary Containment following a postulated Loss-of-Coolant Accident (LOCA). [TS Bases B 3.7.1]
The RHRSW System removes heat from the suppression pool to limit the suppression pool temperature and primary containment pressure following a LOCA. This ensures that the primary containment can perform its function of limiting the release of radioactive materials to the environment following a LOCA. [TS Bases B 3.7.1 Applicable Safety Analyses] The residual heat removal service water (RHRSW) system serves as the ultimate heat sink. Its design includes two 3,465,000-gal reservoirs. They are sized in accordance with the recommendations of Regulatory Guide 1.27. [UFSAR 6.3.2.6 Coolant Quantity]The RHRSW system is designed to; (a) with the RHR system, to remove decay heat and residual heat from the nuclear system to that refueling and nuclear system servicing can be performed; (b) with the RHR system, to supplement the fuel pool cooling system with additional cooling capacity; (c) with the RHR system, to remove decay heat and residual heat from the nuclear system by cooling the suppression pool water, following a postulated LOCA; (d) to provide a method to flood the reactor pressure vessel (RPV), acting as a backup in the extremely unlikely event that all RHR (low pressure coolant injection [LPCI[ mode) and core spray pumps fail to operate following a postulated LOCA; (e) to provide a method to flood primary containment so that the fuel can be removed from the RPV following a postulated LOCA. [UFAR 9.2.5.1 Design Basis] (a) and (b) above are not considered accident mitigating for the purposes of ISTA-1100.
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 17 of 106
.70W an mFermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 19 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes Design Basis Limits: UFSAR Table 6.2-1 Containment ParametersHeat exchangers (RHR system)Flow of pumps, gpmShell-side 10,000* with one RHR pumpTube-side 9,000**Source of cooling water RHR service water* RHR heat exchanger performance maintained to assure credited overall heat transfer coefficient based on an RHR heat exchanger flow of 9250 gpm.** RHRSW pump flow reduces below 9,000 gpm with time due to the RHR reservoir evaporative and drift losses.Component Parameters [Nominal (nameplate) unless otherwise indicated. [DBD E11-XX Section 4.2.1]Pump:Capacity, gpm 4,500Minimum flow, gpm 500* Design analysis indicates the "as-built" TDH requirement is 174 feet at 4500 gpm. Two pumps provide the minimum 8250 gpm required by the RHR heat exchanger.Each of the four RHRSW pumps is a two-staged, motor-driven vertical pump. The RHRSW pumps are designed to supply a design minimum of 8,250 gpm and a design maximum of 10,430 gpm to the RHR heat exchanger in each division with two RHRSW pumps operating and normal RHR reservoir levels. The safety-related pumps are designated QA Level 1, seismic Category I, and are designed to ASME Section III, Class 3 requirements. The RHRSW pumps are located in the RHR complex and are not in a harsh environment. Design analysis indicates the "as-built" TDH requirement is 174 feet at 4500 gpm. Two pumps provide the minimum 8250 gpm required by the RHR heat exchanger. [DBD E11-XX Section 4.2.1] [UFSAR 7.3.9]The RHRSW pumps are started and stopped manually from the main control room. Each pair of pumps is capable of delivering 9000 gpm to the RHR heat exchangers and then to the cooling towers. In the flooding mode, the head of water is sufficient to fill 300,000 cubic feet of air space in the drywell in 1 week, at a rate of approximately 250 gpm. In the event of failure of all four of the 10,000-gpm RHR pumps, the RHRSW pumps in Division II will be capable of backup to the RHR pumps in the LPCI mode at a rate of 3250 gpm. [UFSAR 9.2.5.2.5 Pumps] The RHRSWS is designed to meet Category I requirements. [UFSAR 9.2.5.3.1.1 Earthquakes]
Design
References:
TS 3.7.1 Residual Heat Removal Service Water (RHRSW) System and associated BasesTS 3.7.2 Emergency Equipment Cooling Water (EECW/Emergency Equipment Service Water (EESW) System and Ultimate Heat Sink (UHS) and associated BasesUFSAR 3.8.4.1.2 Residual Heat Removal ComplexUFSAR 5.5.7.3.4 Low Pressure Coolant Injection SystemUFSAR 6.2.1.3.3 Recirculation Line Break Long Term ResponseUFSAR Table 6.2-1 Containment ParametersUFSAR 6.3.2.14 Net Positive Suction HeadUFSAR 6.3.2.6 Coolant QuantityUFSAR 7.3.9 Residual Heat Removal Service Water System Instrumentation and ControlUFSAR 9.2.5 Ultimate Heat SinkDBD E11-XX Rev. C, Residual Heat Removal Service Water (RHRSW) System Appendix V Basis: OM Code Appendix V paragraph V-3000(a) Requirement: The Owner shall (a) identify those certain applicable pumps with specific design basis accident flow rates in the Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) for inclusion in this program.UFSAR Table 6.2-1 Containment ParametersHeat exchangers (RHR system)Flow of pumps, gpmShell-side 10,000* with one RHR pumpTube-side 9,000**Source of cooling water RHR service water* RHR heat exchanger performance maintained to assure credited overall heat transfer coefficient based on an RHR heat exchanger flow of 9250 gpm.** RHRSW pump flow reduces below 9,000 gpm with time due to the RHR reservoir evaporative and drift losses.In summary, to satisfy Appendix V, each RHRSW pump must be flow tested at a flow rate of greater than or equal to 9000 gpm divided by 2, based on the design flow rates provided, which equates to 4500 gpm.
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 18 of 106
DTIE ergFermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 20 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes E1151C001D E1151 RHR Service Water Pump D 5706-3/G-5 A 3 Vertical Line Shaft dP 2Y 24.205.06 PRR-003, TP-19 Q 2Y 24.205.06 TP-19 V 2Y 24.205.06 PRR-002 Standard Code ISTB dP Q 24.205.06 PRR-003 Q Q 24.205.06 V Q 24.205.06 PRR-002 Safety Function Basis: The RHRSW System consists of two independent and redundant subsystems. Each subsystem is made up of a header, two pumps (with a combined nominal capacity of 9000 gpm), and suction source, valves, piping, heat exchanger, and associated instrumentation. Either of the two subsystems is capable of providing the required cooling capacity to maintain safe shutdown conditions. The two subsystems are separated from each other so that the failure of one subsystem will not affect the operability of the other subsystem. [TS Bases B 3.7.1] During normal and/or accident shutdown conditions, the function of the RHRSW and EESW systems is to remove decay heat from the RHR heat exchangers and the EECW heat exchangers, respectively. [UFSAR 3.8.4.1.2] Power for the main RHR and RHRSW pumps normally comes from an auxiliary ac power bus; but if offsite power is lost, power is made available from the standby ac power source to supply the RHR and RHRSW pumps. [UFSAR 5.5.7.3.4]Each of the four RHRSW pumps is a two-staged, motor-driven vertical pump. The RHRSW pumps are designed to supply a design minimum of 8,250 gpm and a design maximum of 10,430 gpm to the RHR heat exchanger in each division with two RHRSW pumps operating and normal RHR reservoir levels. The safety-related pumps are designated QA Level 1, seismic Category I, and are designed to ASME Section III, Class 3 requirements. The RHRSW pumps are located in the RHR complex and are not in a harsh environment. Design analysis indicates the "as-built" TDH requirement is 174 feet at 4500 gpm. Two pumps provide the minimum 8250 gpm required by the RHR heat exchanger. [DBD E11-XX Section 4.2.1] [UFSAR 7.3.9]Cooling water is pump by the RHRSW pumps from the RHR Reservoir through the tube side of the RHR heat exchangers, and discharges to the associated RHR Reservoir via the mechanical draft cooling towers or cooling tower bypass line during cold weather or testing. A minimum flow line from the pump discharge to the RHR Reservoir prevents the pump from overheating when pumping against closed flow path(s). However, the minimum flow protection is not assumed to function in an accident. The system is initiated manually from the control room. If operating during a loss of coolant accident (LOCA), the system is automatically tripped to allow the diesel generators to automatically power only that equipment necessary to flood the core. The system can be manually started if the LOCA signal is manually overridden or clears. [TS Bases B 3.7.1]The conditions assumed for calculating the peak suppression pool temperature and the available NPSH margin assume the temperature of the RHRSW reservoir varies linearly from 80 degrees F to 90 degrees F over 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and stabilizes at 90 degrees F. [UFSAR 6.3.2.14 Net Positive Suction Head]
Function
Description:
Group A - This pump operates continuously or routinely during normal operation, cold shutdown, or refueling operations.The RHRSW System is designed to provide cooling water for the Residual Heat Removal (RHR) System heat exchangers, required for a safe reactor shutdown following a Design Basis Accident (DBA) or transient. The RHR System is operated whenever the RHR heat exchangers are required to operate in the shutdown cooling mode, in the suppression pool cooling or in the fuel pool cooling assist modes of the RHR System. The RHRSW System also provides means to flood the Reactor Pressure Vessel or Primary Containment following a postulated Loss-of-Coolant Accident (LOCA). [TS Bases B 3.7.1]
The RHRSW System removes heat from the suppression pool to limit the suppression pool temperature and primary containment pressure following a LOCA. This ensures that the primary containment can perform its function of limiting the release of radioactive materials to the environment following a LOCA. [TS Bases B 3.7.1 Applicable Safety Analyses] The residual heat removal service water (RHRSW) system serves as the ultimate heat sink. Its design includes two 3,465,000-gal reservoirs. They are sized in accordance with the recommendations of Regulatory Guide 1.27. [UFSAR 6.3.2.6 Coolant Quantity]The RHRSW system is designed to; (a) with the RHR system, to remove decay heat and residual heat from the nuclear system to that refueling and nuclear system servicing can be performed; (b) with the RHR system, to supplement the fuel pool cooling system with additional cooling capacity; (c) with the RHR system, to remove decay heat and residual heat from the nuclear system by cooling the suppression pool water, following a postulated LOCA; (d) to provide a method to flood the reactor pressure vessel (RPV), acting as a backup in the extremely unlikely event that all RHR (low pressure coolant injection [LPCI[ mode) and core spray pumps fail to operate following a postulated LOCA; (e) to provide a method to flood primary containment so that the fuel can be removed from the RPV following a postulated LOCA. [UFAR 9.2.5.1 Design Basis] (a) and (b) above are not considered accident mitigating for the purposes of ISTA-1100.
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 19 of 106
Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 21 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes Design Basis Limits: UFSAR Table 6.2-1 Containment ParametersHeat exchangers (RHR system)Flow of pumps, gpmShell-side 10,000* with one RHR pumpTube-side 9,000**Source of cooling water RHR service water* RHR heat exchanger performance maintained to assure credited overall heat transfer coefficient based on an RHR heat exchanger flow of 9250 gpm.** RHRSW pump flow reduces below 9,000 gpm with time due to the RHR reservoir evaporative and drift losses.Component Parameters [Nominal (nameplate) unless otherwise indicated. [DBD E11-XX Section 4.2.1]Pump:Capacity, gpm 4,500Minimum flow, gpm 500* Design analysis indicates the "as-built" TDH requirement is 174 feet at 4500 gpm. Two pumps provide the minimum 8250 gpm required by the RHR heat exchanger.Each of the four RHRSW pumps is a two-staged, motor-driven vertical pump. The RHRSW pumps are designed to supply a design minimum of 8,250 gpm and a design maximum of 10,430 gpm to the RHR heat exchanger in each division with two RHRSW pumps operating and normal RHR reservoir levels. The safety-related pumps are designated QA Level 1, seismic Category I, and are designed to ASME Section III, Class 3 requirements. The RHRSW pumps are located in the RHR complex and are not in a harsh environment. Design analysis indicates the "as-built" TDH requirement is 174 feet at 4500 gpm. Two pumps provide the minimum 8250 gpm required by the RHR heat exchanger. [DBD E11-XX Section 4.2.1] [UFSAR 7.3.9]The RHRSW pumps are started and stopped manually from the main control room. Each pair of pumps is capable of delivering 9000 gpm to the RHR heat exchangers and then to the cooling towers. In the flooding mode, the head of water is sufficient to fill 300,000 cubic feet of air space in the drywell in 1 week, at a rate of approximately 250 gpm. In the event of failure of all four of the 10,000-gpm RHR pumps, the RHRSW pumps in Division II will be capable of backup to the RHR pumps in the LPCI mode at a rate of 3250 gpm. [UFSAR 9.2.5.2.5 Pumps] The RHRSWS is designed to meet Category I requirements. [UFSAR 9.2.5.3.1.1 Earthquakes]
Design
References:
TS 3.7.1 Residual Heat Removal Service Water (RHRSW) System and associated BasesTS 3.7.2 Emergency Equipment Cooling Water (EECW/Emergency Equipment Service Water (EESW) System and Ultimate Heat Sink (UHS) and associated BasesUFSAR 3.8.4.1.2 Residual Heat Removal ComplexUFSAR 5.5.7.3.4 Low Pressure Coolant Injection SystemUFSAR 6.2.1.3.3 Recirculation Line Break Long Term ResponseUFSAR Table 6.2-1 Containment ParametersUFSAR 6.3.2.14 Net Positive Suction HeadUFSAR 6.3.2.6 Coolant QuantityUFSAR 7.3.9 Residual Heat Removal Service Water System Instrumentation and ControlUFSAR 9.2.5 Ultimate Heat SinkDBD E11-XX Rev. C, Residual Heat Removal Service Water (RHRSW) System Appendix V Basis: OM Code Appendix V paragraph V-3000(a) Requirement: The Owner shall (a) identify those certain applicable pumps with specific design basis accident flow rates in the Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) for inclusion in this program.UFSAR Table 6.2-1 Containment ParametersHeat exchangers (RHR system)Flow of pumps, gpmShell-side 10,000* with one RHR pumpTube-side 9,000**Source of cooling water RHR service water* RHR heat exchanger performance maintained to assure credited overall heat transfer coefficient based on an RHR heat exchanger flow of 9250 gpm.** RHRSW pump flow reduces below 9,000 gpm with time due to the RHR reservoir evaporative and drift losses.In summary, to satisfy Appendix V, each RHRSW pump must be flow tested at a flow rate of greater than or equal to 9000 gpm divided by 2, based on the design flow rates provided, which equates to 4500 gpm.
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 20 of 106
Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 22 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes E2101C001A E2101 Core Spray Pump A 5707/D-6 B 2 Centrifugal dP 2Y 24.203.02 TP-19 Q 2Y 24.203.02 TP-19 V 2Y 24.203.02 Standard Code ISTB dP Q 24.203.02 PRR-004 Q Q 24.203.02 PRR-004 V Q 24.203.02 PRR-004 Safety Function Basis: The CS System is designed to automatically supply water to the reactor core after the reactor pressure has been reduced to less than the CS System discharge pressure following a LOCA event, and to provide long term post-LOCA core cooling. [DBD E21-00 Section 2.2.2.1 Safety Related Functions] The CS System may be initiated by either automatic or manual means. Automatic initiation occurs for conditions of Reactor Vessel Water Level-Low Low Low, Level 1 or Drywell Pressure-High. [TS B 3.3.5.1]The Core Spray System is a subsystem of the Emergency Core Cooling System, and along with HPCI, LPCI and the ADS systems, in conjunction with the primary and secondary containment, to limit the release of radioactive materials to the environment following a loss of coolant accident (LOCA). The ECCS uses two independent methods (flooding and spraying) to cool the core during a LOCA. [TS B 3.5.1 ECCS - Operating]The CS System is composed of two independent subsystems. Each subsystem consists of two motor driven pumps, a spray sparger above the core, and piping and valves to transfer water from the suppression pool to the sparger. The CS system is designed to provide cooling to the reactor core when reactor pressure is low. Upon receipt of an initiation signal, the CS pumps in both subsystems are automatically started after a five second time delay on offsite AC power. In case offsite AC power is lost, the pumps start in sequence (with time delay) powered to the EDGs. When the RPV pressure drops sufficiently, CS system flow to the RPV begins. [TS B 3.5.1 ECCS - Operating]
Function
Description:
Group B - This pump is in standby systems that are not operated routinely except for testing.The Core Spray System is a subsystem of the Emergency Core Cooling System, and along with HPCI, LPCI and the ADS systems, in conjunction with the primary and secondary containment, to limit the release of radioactive materials to the environment following a loss of coolant accident (LOCA). The ECCS uses two independent methods (flooding and spraying) to cool the core during a LOCA. On receipt of an initiation signal, ECCS pumps automatically start; simultaneously, the system aligns and the pumps inject water, taken either from the CST or suppression pool, into the Reactor Coolant System (RCS) as RCS pressure is overcome by the discharge pressure of the ECCS pumps. Although the system is initiated, ADS action is delayed, allowing the operator to interrupt the timed sequence if the system is not needed. The HPCI pump discharge pressure almost immediately exceeds that of the RCS, and the pump injects coolant into the vessel to cool the core. If the break is small, the HPCI System will maintain coolant inventory as well as vessel level while the RCS is still pressurized. If HPCI fails, it is backed up by ADS in combination with LPCI and CS. In this event, the ADS timed sequence would be allowed to time out and open the selected safety/relief valves (SRVs) depressurizing the RCS, thus allowing the LPCI and CS to overcome RCS pressure and inject coolant into the vessel. If the break is large, RCS pressure initially drops rapidly and the LPCI and CS cool the core. [TS B 3.5.1 ECCS - Operating]The CS system is designed to operate in any of the five primary modes: standby, pump full flow test, Injection Flow Test and Minimum Flow Test and Minimum Flow Bypass during normal plant condition and Core Spray Injection Mode during emergency condition. The CS System is also evaluated for operating under an abnormal condition to provide alternate reactor coolant circulation and decay heat removal function in the event of loss of Shutdown Cooling Mode of RHR system. [DBD E21-00 Section 2.2.4 Operating Modes]
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 21 of 106
- Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 23 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes Design Basis Limits: SR 3.5.1.8 Verify 2 Core Spray pumps develop greater than or equal to 5725 gpm with reactor pressure greater than or equal to100 psig. Maximum Pump Flow equal to 3950 gpm (Based on 2 Pumps operating at 50% Capacity)Basis: Runout flow when the differential pressure between the reactor and the Suppression Pool is zero for nominal design conditions. Required Minimum Flow Head: Greater than or equal to 800 ft H20. Basis: The head rise is necessary in order to provide adequate pump head at minimum flow to provide beginning flow at 289 psi differential pressure between suction and discharge points at a water temperature of 130 degrees F.Minimum Pump Flow equal to 320 gpm Roughly 10% of rated flow, based on short- term operation of this type of pump.Data Sheet 4.3.1 Core Spray Pump E2101C001A,B,C,DCS pump is Safety Related, ASME B&PV Section III, Code Class II, QA Level 1 and Seismic Class I. The CS pumps have a rated flow of 3175 gpm per pump based on two 50 percent pumping units. This flowrate is based on the original required spray flow of 6250 gpm used in the original core cooling analyses. 100 gpm is added for leakage at the vessel nozzle thermal sleeve. The combined flow is 6350 gpm when taking suction from the pool and discharging from the CS spargers with a 100 psi differential between the Suppression Pool and the reactor. CS Pump has a Rated Total Dynamic Head (TDH) at rated flow of 665 ft.
Maximum Pump Flow is 3950 gpm based on 2 pumps operating at 50 percent capacity. The Required Minimum Flow Head is greater than or equal to 800 ft. The head rise is necessary in order to provide adequate pump head at minimum flow to provide beginning flow at 289 psi differential pressure between suction and discharge points at a water temperature of 130 degrees F. Minimum Pump Flow is 320 gpm which is roughly 10 percent of rated flow based on short term operation. The Required NPSH requires satisfactory operation at 3175 gpm with two pumps operating and with an available NPSH of 19.86 feet. See Subsection 4.1.1.1.4 for runout flow NPSH demand. Pump casing is carbon steel, shaft is stainless steel and impeller is stainless steel. CS Pump Temperature Rating is 40 degrees F to 212 degrees F. [DBD E21-00 Data Sheet 4.3.1]CS pumps shall start and be up to rated speed in 47 seconds, including time required to establish emergency power sources. The CS injection valves shall open in 15 seconds after an open signal is received. The system response time was originally specified at 30 seconds; (b) The CS System shall, as a minimum, start to deliver water from the suppression pool to the reactor vessel when the reactor pressure is equal to or greater than 280 psig. The beginning flow vessel pressure was originally specified at 289 psig; (c) Each CS System loop, with two pumps operating, shall provide a minimum rated CS flow of 5625 gpm to its spray sparger when the differential pressure between the reactor and the drywell is 100 psid. An additional 100 gpm is allowed for leakage of reactor internal piping for a total required reactor inlet flow requirement of 5725 gpm; (d) the active CS components shall be designed so that they will remain functional in the post-LOCA environment for 100 days. [DBD E21-00 Section 4.1.1.1.1]Pumps used for Core Cooling are Group B, ASME Code for Pumps and Valves for Nuclear Power, 1968 draft issue, Section 1. [DBD E21-00 Section 3.1.1 Mechanical Codes and Standards]The maximum runout flow of two CS pumps operating during the short term (less than or equal to 10 minutes after LOCA) core spray injection with the reactor pressure at 0 psid shall not exceed approximately 7900 gpm (i.e., 3950 gpm per pump) under nominal conditions. [DBD E21-00 Section 4.1.1.1.4 CS System Runout]
Design
References:
TS B 3.3.5.1 Emergency Core Cooling System (ECCS) InstrumentationTS B 3.5.1 ECCS - OperatingTS SR 3.5.1.8UFSAR 6.2.2 Primary Containment Heat Removal SystemUFSAR 6.3.2.2.2 Automatic Depressurization SystemUFSAR 6.3.2.2.3 Core Spray SystemUFSAR 6.3.2.2.5 Emergency Core Cooling System Discharge Line Fill SystemUFSAR 6.3.2.14 Net Positive Suction HeadUFSAR Table 6.3-2 Materials For The Principal Emergency Core Cooling System ComponentsUFSAR Table 8.3-2 Emergency Diesel Generator System Divisional Connected LoadsDBD E21-00 Rev E, Core Spray System Appendix V Basis: OM Code Appendix V paragraph V-3000(a) Requirement: The Owner shall (a) identify those certain applicable pumps with specific design basis accident flow rates in the Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) for inclusion in this program.SR 3.5.1.8 Verify 2 Core Spray pumps develop greater than or equal to 5725 gpm with reactor pressure greater than or equal to 100 psig. In summary, to satisfy Appendix V, each CS pump must be flow tested at a flow rate of greater than or equal to 5725 gpm divided by 2, based on the design flow rates provide, which equates to 2862.5 gpm.The pump meets the requirements of Appendix V, based on review of the single pump, comprehensive pump tests being permed and the data analysis within Design Calculation DC-0230 and Inservice Testing Evaluation IST-16-017.
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 22 of 106
- D rFermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 24 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes E2101C001B E2101 Core Spray Pump B 5707/D-3 B 2 Centrifugal dP 2Y 24.203.03 TP-19 Q 2Y 24.203.03 TP-19 V 2Y 24.203.03 Standard Code ISTB dP Q 24.203.03 PRR-004 Q Q 24.203.03 PRR-004 V Q 24.203.03 PRR-004 Safety Function Basis: The CS System is designed to automatically supply water to the reactor core after the reactor pressure has been reduced to less than the CS System discharge pressure following a LOCA event, and to provide long term post-LOCA core cooling. [DBD E21-00 Section 2.2.2.1 Safety Related Functions] The CS System may be initiated by either automatic or manual means. Automatic initiation occurs for conditions of Reactor Vessel Water Level-Low Low Low, Level 1 or Drywell Pressure-High. [TS B 3.3.5.1]The Core Spray System is a subsystem of the Emergency Core Cooling System, and along with HPCI, LPCI and the ADS systems, in conjunction with the primary and secondary containment, to limit the release of radioactive materials to the environment following a loss of coolant accident (LOCA). The ECCS uses two independent methods (flooding and spraying) to cool the core during a LOCA. [TS B 3.5.1 ECCS - Operating]The CS System is composed of two independent subsystems. Each subsystem consists of two motor driven pumps, a spray sparger above the core, and piping and valves to transfer water from the suppression pool to the sparger. The CS system is designed to provide cooling to the reactor core when reactor pressure is low. Upon receipt of an initiation signal, the CS pumps in both subsystems are automatically started after a five second time delay on offsite AC power. In case offsite AC power is lost, the pumps start in sequence (with time delay) powered to the EDGs. When the RPV pressure drops sufficiently, CS system flow to the RPV begins. [TS B 3.5.1 ECCS - Operating]
Function
Description:
Group B - This pump is in standby systems that are not operated routinely except for testing.The Core Spray System is a subsystem of the Emergency Core Cooling System, and along with HPCI, LPCI and the ADS systems, in conjunction with the primary and secondary containment, to limit the release of radioactive materials to the environment following a loss of coolant accident (LOCA). The ECCS uses two independent methods (flooding and spraying) to cool the core during a LOCA. On receipt of an initiation signal, ECCS pumps automatically start; simultaneously, the system aligns and the pumps inject water, taken either from the CST or suppression pool, into the Reactor Coolant System (RCS) as RCS pressure is overcome by the discharge pressure of the ECCS pumps. Although the system is initiated, ADS action is delayed, allowing the operator to interrupt the timed sequence if the system is not needed. The HPCI pump discharge pressure almost immediately exceeds that of the RCS, and the pump injects coolant into the vessel to cool the core. If the break is small, the HPCI System will maintain coolant inventory as well as vessel level while the RCS is still pressurized. If HPCI fails, it is backed up by ADS in combination with LPCI and CS. In this event, the ADS timed sequence would be allowed to time out and open the selected safety/relief valves (SRVs) depressurizing the RCS, thus allowing the LPCI and CS to overcome RCS pressure and inject coolant into the vessel. If the break is large, RCS pressure initially drops rapidly and the LPCI and CS cool the core. [TS B 3.5.1 ECCS - Operating]The CS system is designed to operate in any of the five primary modes: standby, pump full flow test, Injection Flow Test and Minimum Flow Test and Minimum Flow Bypass during normal plant condition and Core Spray Injection Mode during emergency condition. The CS System is also evaluated for operating under an abnormal condition to provide alternate reactor coolant circulation and decay heat removal function in the event of loss of Shutdown Cooling Mode of RHR system. [DBD E21-00 Section 2.2.4 Operating Modes]
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 23 of 106
Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 25 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes Design Basis Limits: SR 3.5.1.8 Verify 2 Core Spray pumps develop greater than or equal to 5725 gpm with reactor pressure greater than or equal to100 psig. Maximum Pump Flow equal to 3950 gpm (Based on 2 Pumps operating at 50% Capacity)Basis: Runout flow when the differential pressure between the reactor and the Suppression Pool is zero for nominal design conditions. Required Minimum Flow Head: Greater than or equal to 800 ft H20. Basis: The head rise is necessary in order to provide adequate pump head at minimum flow to provide beginning flow at 289 psi differential pressure between suction and discharge points at a water temperature of 130 degrees F.Minimum Pump Flow equal to 320 gpm Roughly 10% of rated flow, based on short- term operation of this type of pump.Data Sheet 4.3.1 Core Spray Pump E2101C001A,B,C,DCS pump is Safety Related, ASME B&PV Section III, Code Class II, QA Level 1 and Seismic Class I. The CS pumps have a rated flow of 3175 gpm per pump based on two 50 percent pumping units. This flowrate is based on the original required spray flow of 6250 gpm used in the original core cooling analyses. 100 gpm is added for leakage at the vessel nozzle thermal sleeve. The combined flow is 6350 gpm when taking suction from the pool and discharging from the CS spargers with a 100 psi differential between the Suppression Pool and the reactor. CS Pump has a Rated Total Dynamic Head (TDH) at rated flow of 665 ft.
Maximum Pump Flow is 3950 gpm based on 2 pumps operating at 50 percent capacity. The Required Minimum Flow Head is greater than or equal to 800 ft. The head rise is necessary in order to provide adequate pump head at minimum flow to provide beginning flow at 289 psi differential pressure between suction and discharge points at a water temperature of 130 degrees F. Minimum Pump Flow is 320 gpm which is roughly 10 percent of rated flow based on short term operation. The Required NPSH requires satisfactory operation at 3175 gpm with two pumps operating and with an available NPSH of 19.86 feet. See Subsection 4.1.1.1.4 for runout flow NPSH demand. Pump casing is carbon steel, shaft is stainless steel and impeller is stainless steel. CS Pump Temperature Rating is 40 degrees F to 212 degrees F. [DBD E21-00 Data Sheet 4.3.1]CS pumps shall start and be up to rated speed in 47 seconds, including time required to establish emergency power sources. The CS injection valves shall open in 15 seconds after an open signal is received. The system response time was originally specified at 30 seconds; (b) The CS System shall, as a minimum, start to deliver water from the suppression pool to the reactor vessel when the reactor pressure is equal to or greater than 280 psig. The beginning flow vessel pressure was originally specified at 289 psig; (c) Each CS System loop, with two pumps operating, shall provide a minimum rated CS flow of 5625 gpm to its spray sparger when the differential pressure between the reactor and the drywell is 100 psid. An additional 100 gpm is allowed for leakage of reactor internal piping for a total required reactor inlet flow requirement of 5725 gpm; (d) the active CS components shall be designed so that they will remain functional in the post-LOCA environment for 100 days. [DBD E21-00 Section 4.1.1.1.1]Pumps used for Core Cooling are Group B, ASME Code for Pumps and Valves for Nuclear Power, 1968 draft issue, Section 1. [DBD E21-00 Section 3.1.1 Mechanical Codes and Standards]The maximum runout flow of two CS pumps operating during the short term (less than or equal to 10 minutes after LOCA) core spray injection with the reactor pressure at 0 psid shall not exceed approximately 7900 gpm (i.e., 3950 gpm per pump) under nominal conditions. [DBD E21-00 Section 4.1.1.1.4 CS System Runout]
Design
References:
TS B 3.3.5.1 Emergency Core Cooling System (ECCS) InstrumentationTS B 3.5.1 ECCS - OperatingTS SR 3.5.1.8UFSAR 6.2.2 Primary Containment Heat Removal SystemUFSAR 6.3.2.2.2 Automatic Depressurization SystemUFSAR 6.3.2.2.3 Core Spray SystemUFSAR 6.3.2.2.5 Emergency Core Cooling System Discharge Line Fill SystemUFSAR 6.3.2.14 Net Positive Suction HeadUFSAR Table 6.3-2 Materials For The Principal Emergency Core Cooling System ComponentsUFSAR Table 8.3-2 Emergency Diesel Generator System Divisional Connected LoadsDBD E21-00 Rev E, Core Spray System Appendix V Basis: OM Code Appendix V paragraph V-3000(a) Requirement: The Owner shall (a) identify those certain applicable pumps with specific design basis accident flow rates in the Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) for inclusion in this program.SR 3.5.1.8 Verify 2 Core Spray pumps develop greater than or equal to 5725 gpm with reactor pressure greater than or equal to100 psig. In summary, to satisfy Appendix V, each CS pump must be flow tested at a flow rate of greater than or equal to 5725 gpm divided by 2, based on the design flow rates provide, which equates to 2862.5 gpm.The pump meets the requirements of Appendix V, based on review of the single pump, comprehensive pump tests being permed and the data analysis within Design Calculation DC-0230 and Inservice Testing Evaluation IST-16-017.
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 24 of 106
1M - Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 26 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes E2101C001C E2101 Core Spray Pump C 5707/D-4 B 2 Centrifugal dP 2Y 24.203.02 TP-19 Q 2Y 24.203.02 TP-19 V 2Y 24.203.02 Standard Code ISTB dP Q 24.203.02 PRR-004 Q Q 24.203.02 PRR-004 V Q 24.203.02 PRR-004 Safety Function Basis: The CS System is designed to automatically supply water to the reactor core after the reactor pressure has been reduced to less than the CS System discharge pressure following a LOCA event, and to provide long term post-LOCA core cooling. [DBD E21-00 Section 2.2.2.1 Safety Related Functions] The CS System may be initiated by either automatic or manual means. Automatic initiation occurs for conditions of Reactor Vessel Water Level-Low Low Low, Level 1 or Drywell Pressure-High. [TS B 3.3.5.1]The Core Spray System is a subsystem of the Emergency Core Cooling System, and along with HPCI, LPCI and the ADS systems, in conjunction with the primary and secondary containment, to limit the release of radioactive materials to the environment following a loss of coolant accident (LOCA). The ECCS uses two independent methods (flooding and spraying) to cool the core during a LOCA. [TS B 3.5.1 ECCS - Operating]The CS System is composed of two independent subsystems. Each subsystem consists of two motor driven pumps, a spray sparger above the core, and piping and valves to transfer water from the suppression pool to the sparger. The CS system is designed to provide cooling to the reactor core when reactor pressure is low. Upon receipt of an initiation signal, the CS pumps in both subsystems are automatically started after a five second time delay on offsite AC power. In case offsite AC power is lost, the pumps start in sequence (with time delay) powered to the EDGs. When the RPV pressure drops sufficiently, CS system flow to the RPV begins. [TS B 3.5.1 ECCS - Operating]
Function
Description:
Group B - This pump is in standby systems that are not operated routinely except for testing.The Core Spray System is a subsystem of the Emergency Core Cooling System, and along with HPCI, LPCI and the ADS systems, in conjunction with the primary and secondary containment, to limit the release of radioactive materials to the environment following a loss of coolant accident (LOCA). The ECCS uses two independent methods (flooding and spraying) to cool the core during a LOCA. On receipt of an initiation signal, ECCS pumps automatically start; simultaneously, the system aligns and the pumps inject water, taken either from the CST or suppression pool, into the Reactor Coolant System (RCS) as RCS pressure is overcome by the discharge pressure of the ECCS pumps. Although the system is initiated, ADS action is delayed, allowing the operator to interrupt the timed sequence if the system is not needed. The HPCI pump discharge pressure almost immediately exceeds that of the RCS, and the pump injects coolant into the vessel to cool the core. If the break is small, the HPCI System will maintain coolant inventory as well as vessel level while the RCS is still pressurized. If HPCI fails, it is backed up by ADS in combination with LPCI and CS. In this event, the ADS timed sequence would be allowed to time out and open the selected safety/relief valves (SRVs) depressurizing the RCS, thus allowing the LPCI and CS to overcome RCS pressure and inject coolant into the vessel. If the break is large, RCS pressure initially drops rapidly and the LPCI and CS cool the core. [TS B 3.5.1 ECCS - Operating]The CS system is designed to operate in any of the five primary modes: standby, pump full flow test, Injection Flow Test and Minimum Flow Test and Minimum Flow Bypass during normal plant condition and Core Spray Injection Mode during emergency condition. The CS System is also evaluated for operating under an abnormal condition to provide alternate reactor coolant circulation and decay heat removal function in the event of loss of Shutdown Cooling Mode of RHR system. [DBD E21-00 Section 2.2.4 Operating Modes]
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 25 of 106
Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 27 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes Design Basis Limits: SR 3.5.1.8 Verify 2 Core Spray pumps develop greater than or equal to 5725 gpm with reactor pressure greater than or equal to100 psig. Maximum Pump Flow equal to 3950 gpm (Based on 2 Pumps operating at 50% Capacity)Basis: Runout flow when the differential pressure between the reactor and the Suppression Pool is zero for nominal design conditions. Required Minimum Flow Head: Greater than or equal to 800 ft H20. Basis: The head rise is necessary in order to provide adequate pump head at minimum flow to provide beginning flow at 289 psi differential pressure between suction and discharge points at a water temperature of 130 degrees F.Minimum Pump Flow equal to 320 gpm Roughly 10% of rated flow, based on short- term operation of this type of pump.Data Sheet 4.3.1 Core Spray Pump E2101C001A,B,C,DCS pump is Safety Related, ASME B&PV Section III, Code Class II, QA Level 1 and Seismic Class I. The CS pumps have a rated flow of 3175 gpm per pump based on two 50 percent pumping units. This flowrate is based on the original required spray flow of 6250 gpm used in the original core cooling analyses. 100 gpm is added for leakage at the vessel nozzle thermal sleeve. The combined flow is 6350 gpm when taking suction from the pool and discharging from the CS spargers with a 100 psi differential between the Suppression Pool and the reactor. CS Pump has a Rated Total Dynamic Head (TDH) at rated flow of 665 ft.
Maximum Pump Flow is 3950 gpm based on 2 pumps operating at 50 percent capacity. The Required Minimum Flow Head is greater than or equal to 800 ft. The head rise is necessary in order to provide adequate pump head at minimum flow to provide beginning flow at 289 psi differential pressure between suction and discharge points at a water temperature of 130 degrees F. Minimum Pump Flow is 320 gpm which is roughly 10 percent of rated flow based on short term operation. The Required NPSH requires satisfactory operation at 3175 gpm with two pumps operating and with an available NPSH of 19.86 feet. See Subsection 4.1.1.1.4 for runout flow NPSH demand. Pump casing is carbon steel, shaft is stainless steel and impeller is stainless steel. CS Pump Temperature Rating is 40 degrees F to 212 degrees F. [DBD E21-00 Data Sheet 4.3.1]CS pumps shall start and be up to rated speed in 47 seconds, including time required to establish emergency power sources. The CS injection valves shall open in 15 seconds after an open signal is received. The system response time was originally specified at 30 seconds; (b) The CS System shall, as a minimum, start to deliver water from the suppression pool to the reactor vessel when the reactor pressure is equal to or greater than 280 psig. The beginning flow vessel pressure was originally specified at 289 psig; (c) Each CS System loop, with two pumps operating, shall provide a minimum rated CS flow of 5625 gpm to its spray sparger when the differential pressure between the reactor and the drywell is 100 psid. An additional 100 gpm is allowed for leakage of reactor internal piping for a total required reactor inlet flow requirement of 5725 gpm; (d) the active CS components shall be designed so that they will remain functional in the post-LOCA environment for 100 days. [DBD E21-00 Section 4.1.1.1.1]Pumps used for Core Cooling are Group B, ASME Code for Pumps and Valves for Nuclear Power, 1968 draft issue, Section 1. [DBD E21-00 Section 3.1.1 Mechanical Codes and Standards]The maximum runout flow of two CS pumps operating during the short term (less than or equal to 10 minutes after LOCA) core spray injection with the reactor pressure at 0 psid shall not exceed approximately 7900 gpm (i.e., 3950 gpm per pump) under nominal conditions. [DBD E21-00 Section 4.1.1.1.4 CS System Runout]
Design
References:
TS B 3.3.5.1 Emergency Core Cooling System (ECCS) InstrumentationTS B 3.5.1 ECCS - OperatingTS SR 3.5.1.8UFSAR 6.2.2 Primary Containment Heat Removal SystemUFSAR 6.3.2.2.2 Automatic Depressurization SystemUFSAR 6.3.2.2.3 Core Spray SystemUFSAR 6.3.2.2.5 Emergency Core Cooling System Discharge Line Fill SystemUFSAR 6.3.2.14 Net Positive Suction HeadUFSAR Table 6.3-2 Materials For The Principal Emergency Core Cooling System ComponentsUFSAR Table 8.3-2 Emergency Diesel Generator System Divisional Connected LoadsDBD E21-00 Rev E, Core Spray System Appendix V Basis: OM Code Appendix V paragraph V-3000(a) Requirement: The Owner shall (a) identify those certain applicable pumps with specific design basis accident flow rates in the Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) for inclusion in this program.SR 3.5.1.8 Verify 2 Core Spray pumps develop greater than or equal to 5725 gpm with reactor pressure greater than or equal to100 psig. In summary, to satisfy Appendix V, each CS pump must be flow tested at a flow rate of greater than or equal to 5725 gpm divided by 2, based on the design flow rates provide, which equates to 2862.5 gpm.The pump meets the requirements of Appendix V, based on review of the single pump, comprehensive pump tests being permed and the data analysis within Design Calculation DC-0230 and Inservice Testing Evaluation IST-16-017.
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DTIE E ergy-Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 28 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes E2101C001D E2101 Core Spray Pump D 5707/D-2 B 2 Centrifugal dP 2Y 24.203.03 TP-19 Q 2Y 24.203.03 TP-19 V 2Y 24.203.03 Standard Code ISTB dP Q 24.203.03 PRR-004 Q Q 24.203.03 PRR-004 V Q 24.203.03 PRR-004 Safety Function Basis: The CS System is designed to automatically supply water to the reactor core after the reactor pressure has been reduced to less than the CS System discharge pressure following a LOCA event, and to provide long term post-LOCA core cooling. [DBD E21-00 Section 2.2.2.1 Safety Related Functions] The CS System may be initiated by either automatic or manual means. Automatic initiation occurs for conditions of Reactor Vessel Water Level-Low Low Low, Level 1 or Drywell Pressure-High. [TS B 3.3.5.1]The Core Spray System is a subsystem of the Emergency Core Cooling System, and along with HPCI, LPCI and the ADS systems, in conjunction with the primary and secondary containment, to limit the release of radioactive materials to the environment following a loss of coolant accident (LOCA). The ECCS uses two independent methods (flooding and spraying) to cool the core during a LOCA. [TS B 3.5.1 ECCS - Operating]The CS System is composed of two independent subsystems. Each subsystem consists of two motor driven pumps, a spray sparger above the core, and piping and valves to transfer water from the suppression pool to the sparger. The CS system is designed to provide cooling to the reactor core when reactor pressure is low. Upon receipt of an initiation signal, the CS pumps in both subsystems are automatically started after a five second time delay on offsite AC power. In case offsite AC power is lost, the pumps start in sequence (with time delay) powered to the EDGs. When the RPV pressure drops sufficiently, CS system flow to the RPV begins. [TS B 3.5.1 ECCS - Operating]
Function
Description:
Group B - This pump is in standby systems that are not operated routinely except for testing.The Core Spray System is a subsystem of the Emergency Core Cooling System, and along with HPCI, LPCI and the ADS systems, in conjunction with the primary and secondary containment, to limit the release of radioactive materials to the environment following a loss of coolant accident (LOCA). The ECCS uses two independent methods (flooding and spraying) to cool the core during a LOCA. On receipt of an initiation signal, ECCS pumps automatically start; simultaneously, the system aligns and the pumps inject water, taken either from the CST or suppression pool, into the Reactor Coolant System (RCS) as RCS pressure is overcome by the discharge pressure of the ECCS pumps. Although the system is initiated, ADS action is delayed, allowing the operator to interrupt the timed sequence if the system is not needed. The HPCI pump discharge pressure almost immediately exceeds that of the RCS, and the pump injects coolant into the vessel to cool the core. If the break is small, the HPCI System will maintain coolant inventory as well as vessel level while the RCS is still pressurized. If HPCI fails, it is backed up by ADS in combination with LPCI and CS. In this event, the ADS timed sequence would be allowed to time out and open the selected safety/relief valves (SRVs) depressurizing the RCS, thus allowing the LPCI and CS to overcome RCS pressure and inject coolant into the vessel. If the break is large, RCS pressure initially drops rapidly and the LPCI and CS cool the core. [TS B 3.5.1 ECCS - Operating]The CS system is designed to operate in any of the five primary modes: standby, pump full flow test, Injection Flow Test and Minimum Flow Test and Minimum Flow Bypass during normal plant condition and Core Spray Injection Mode during emergency condition. The CS System is also evaluated for operating under an abnormal condition to provide alternate reactor coolant circulation and decay heat removal function in the event of loss of Shutdown Cooling Mode of RHR system. [DBD E21-00 Section 2.2.4 Operating Modes]
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Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 29 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes Design Basis Limits: SR 3.5.1.8 Verify 2 Core Spray pumps develop greater than or equal to 5725 gpm with reactor pressure greater than or equal to100 psig. Maximum Pump Flow equal to 3950 gpm (Based on 2 Pumps operating at 50% Capacity)Basis: Runout flow when the differential pressure between the reactor and the Suppression Pool is zero for nominal design conditions. Required Minimum Flow Head: Greater than or equal to 800 ft H20. Basis: The head rise is necessary in order to provide adequate pump head at minimum flow to provide beginning flow at 289 psi differential pressure between suction and discharge points at a water temperature of 130 degrees F.Minimum Pump Flow equal to 320 gpm Roughly 10% of rated flow, based on short- term operation of this type of pump.Data Sheet 4.3.1 Core Spray Pump E2101C001A,B,C,DCS pump is Safety Related, ASME B&PV Section III, Code Class II, QA Level 1 and Seismic Class I. The CS pumps have a rated flow of 3175 gpm per pump based on two 50 percent pumping units. This flowrate is based on the original required spray flow of 6250 gpm used in the original core cooling analyses. 100 gpm is added for leakage at the vessel nozzle thermal sleeve. The combined flow is 6350 gpm when taking suction from the pool and discharging from the CS spargers with a 100 psi differential between the Suppression Pool and the reactor. CS Pump has a Rated Total Dynamic Head (TDH) at rated flow of 665 ft.
Maximum Pump Flow is 3950 gpm based on 2 pumps operating at 50 percent capacity. The Required Minimum Flow Head is greater than or equal to 800 ft. The head rise is necessary in order to provide adequate pump head at minimum flow to provide beginning flow at 289 psi differential pressure between suction and discharge points at a water temperature of 130 degrees F. Minimum Pump Flow is 320 gpm which is roughly 10 percent of rated flow based on short term operation. The Required NPSH requires satisfactory operation at 3175 gpm with two pumps operating and with an available NPSH of 19.86 feet. See Subsection 4.1.1.1.4 for runout flow NPSH demand. Pump casing is carbon steel, shaft is stainless steel and impeller is stainless steel. CS Pump Temperature Rating is 40 degrees F to 212 degrees F. [DBD E21-00 Data Sheet 4.3.1]CS pumps shall start and be up to rated speed in 47 seconds, including time required to establish emergency power sources. The CS injection valves shall open in 15 seconds after an open signal is received. The system response time was originally specified at 30 seconds; (b) The CS System shall, as a minimum, start to deliver water from the suppression pool to the reactor vessel when the reactor pressure is equal to or greater than 280 psig. The beginning flow vessel pressure was originally specified at 289 psig; (c) Each CS System loop, with two pumps operating, shall provide a minimum rated CS flow of 5625 gpm to its spray sparger when the differential pressure between the reactor and the drywell is 100 psid. An additional 100 gpm is allowed for leakage of reactor internal piping for a total required reactor inlet flow requirement of 5725 gpm; (d) the active CS components shall be designed so that they will remain functional in the post-LOCA environment for 100 days. [DBD E21-00 Section 4.1.1.1.1]Pumps used for Core Cooling are Group B, ASME Code for Pumps and Valves for Nuclear Power, 1968 draft issue, Section 1. [DBD E21-00 Section 3.1.1 Mechanical Codes and Standards]The maximum runout flow of two CS pumps operating during the short term (less than or equal to 10 minutes after LOCA) core spray injection with the reactor pressure at 0 psid shall not exceed approximately 7900 gpm (i.e., 3950 gpm per pump) under nominal conditions. [DBD E21-00 Section 4.1.1.1.4 CS System Runout]
Design
References:
TS B 3.3.5.1 Emergency Core Cooling System (ECCS) InstrumentationTS B 3.5.1 ECCS - OperatingTS SR 3.5.1.8UFSAR 6.2.2 Primary Containment Heat Removal SystemUFSAR 6.3.2.2.2 Automatic Depressurization SystemUFSAR 6.3.2.2.3 Core Spray SystemUFSAR 6.3.2.2.5 Emergency Core Cooling System Discharge Line Fill SystemUFSAR 6.3.2.14 Net Positive Suction HeadUFSAR Table 6.3-2 Materials For The Principal Emergency Core Cooling System ComponentsUFSAR Table 8.3-2 Emergency Diesel Generator System Divisional Connected LoadsDBD E21-00 Rev E, Core Spray System Appendix V Basis: OM Code Appendix V paragraph V-3000(a) Requirement: The Owner shall (a) identify those certain applicable pumps with specific design basis accident flow rates in the Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) for inclusion in this program.SR 3.5.1.8 Verify 2 Core Spray pumps develop greater than or equal to 5725 gpm with reactor pressure greater than or equal to100 psig. In summary, to satisfy Appendix V, each CS pump must be flow tested at a flow rate of greater than or equal to 5725 gpm divided by 2, based on the design flow rates provide, which equates to 2862.5 gpm.The pump meets the requirements of Appendix V, based on review of the single pump, comprehensive pump tests being permed and the data analysis within Design Calculation DC-0230 and Inservice Testing Evaluation IST-16-017.
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I VFermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 30 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes E4101C001A E4101 HPCI - Main Pump 5708-1/E-3 B 2 Centrifugal dP 2Y 24.202.01 TP-19 N 2Y 24.202.01 Q 2Y 24.202.01 TP-19 V 2Y 24.202.01 Standard Code ISTB dP Q 24.202.01, 24.202.08 N Q 24.202.01, 24.202.08 Q Q 24.202.01, 24.202.08 V Q 24.202.01, 24.202.08 Safety Function Basis: The function of the high pressure coolant injection (HPCI) system is to provide high-pressure makeup to the RPV in the event of a small-break loss-of-coolant accident.
[UFSAR 5.2.1.1.12] The HPCI pump assembly consists of a two-stage main pump with high speed gear and a single-stage booster pump that are mounted on a common base and driven by a separately mounted steam turbine. The HPCI pump has a safety function to deliver 5000 gpm of makeup water to the reactor vessel in the event of a loss-of-coolant accident. [DBD E41-00 Section 4.2.2] The HPCI system ensures that the reactor core is adequately cooled to meet the design bases in the event of a small break in the nuclear system and loss of coolant that does not result in rapid depressurization of the RPV. The HPCI pump continues to operate until RPV pressure is below the maximum pressure at which LPCI operation or core spray system operation can maintain core cooling. The HPCI controls automatically start the system and bring it to design flow rate within 60 sec from receipt of a primary containment (drywell) high-pressure signal or an RPV low water level signal. [UFSAR 6.3.2.2.1]The HPCI pump assembly consists of a two-stage main pump with high speed gear and a single-stage booster pump that are mounted on a common base and driven by a separately mounted steam turbine. The HPCI pump has a safety function to deliver 5000 gpm of makeup water to the reactor vessel in the event of a loss-of-coolant accident. [DBD E41-00 Section 4.2.2] The safety-related pump assembly is designated QA Level 1, seismic Category I, and is designed to ASME Code Section III Class 2 requirements. Water for cooling the lube oil and barometric condenser is taken from between the main and booster pumps. The HPCI booster pump and main are not tested as individual units. Operation of the booster pump to pass its design flow of 5100 gpm is verified by the main pump producing a design flow of 5000 gpm. [DBD E41-00 Section 4.2.2] [UFSAR 6.3.2.2.1]
Function
Description:
Group B - This pump is in standby systems that are not operated routinely except for testing.The high pressure coolant injection (HPCI) system provides and maintains an adequate coolant inventory inside the RPV. This limits fuel cladding temperature, which may result from postulated small breaks in the nuclear system process barrier. A high-pressure system is needed for small breaks because the RPV depressurizes slowly, preventing low-pressure systems from injecting coolant. Also, the HPCI system reduces RPV pressure rapidly, permitting operation of the low-pressure systems. The HPCI system includes a turbine- driven pump powered by reactor steam. The system is designed to accomplish its function on a short-term basis, without reliance on plant auxiliary power supplies other than the dc power supply. The High Pressure Coolant Injection (HPCI) system forms a part of the Emergency Core Cooling System (ECCS) at Fermi 2 provided to protect the core against various sizes of postulated pipe breaks in accordance with General Design Criteria 35 of 10CFR50 Appendix A. The protection afforded by the ECCS systems meets the NRC criteria given in Appendix K of 10CFR50 and precludes exceeding the maximum fuel cladding temperature limit of 2200 degrees F and other requirements set forth in 10CFR50.46. The safety-related HPCI system provides emergency core cooling to the Reactor Pressure Vessel (RPV) for a wide range of reactor pressures in the event of an accident involving loss of coolant at a relatively low flow rate. This range of reactor pressures encompassing HPCI System Operation is 1169 psig max, based on the lowest SRV setting of 1135 psig +/- 3 percent, to 100 psig, which is the HPCI isolation setpoint based on Calculation DC-4575 Vol. I. [DBD E41-00 Section 2.1]The ECCS is designed, in conjunction with the primary and secondary containment, to limit the release of radioactive materials to the environment following a loss of coolant accident (LOCA). The ECCS uses two independent methods (flooding and spraying) to cool the core during a LOCA. The ECCS network consists of the High Pressure Coolant Injection (HPCI) System, the Core Spray (CS) System, the low pressure cooling injection (LPCI) mode of the Residual Heat Removal (RHR) System, and the Automatic Depressurization System (ADS). The suppression pool provides the required source of water for the ECCS. Although no credit is taken in the safety analyses for the condensate storage tank (CST), it is capable of providing a source of water for HPCI and CS systems. The HPCI pump discharge pressure almost immediately exceeds that of the RCS, and the pump injects coolant into the vessel to cool the core. If the break is small, the HPCI System will maintain coolant inventory as well as vessel level while the RCS is still pressurized. [TS Bases B 3.5.1]
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- Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 31 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes Design Basis Limits: SR 3.5.1.9 - Verify, with reactor pressure less than or equal to 1045 and greater than or equal to 945 psig, the HPCI pump can develop a flow rate of greater than or equal to 5000 gpm against a system head corresponding to reactor pressure. [In accordance with the Inservice Testing Program] Not required to be performed unit 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.SR 3.5.1.10 - Verify, with reactor pressure less than or equal to 215 psig, the HPCI pump can develop a flow rate of greater than or equal to 5000 gpm against a system head corresponding to reactor pressure. [In accordance with the Surveillance Frequency Control Program] Not required to be performed unit 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.UFSAR TABLE 6.3-6 ECCS ANALYSISSIGNIFICANT INPUT VARIABLES AND INITIAL CONDITIONHigh Pressure Coolant Injection (HPCI) SystemVessel Pressure at Which Flow May Commence psia 1135Minimum Rated Flow at Vessel Pressure of:psia 1135 to 165**gpm 5000** HPCI pump is designed to produce a flow of 5000 gpm at an RPV pressure of 1184 psia, which exceeds LOCA input.Greater than or equal 5000 gpm flow from main pump. [DBD E41-00 Section 4.2.2]Greater than or equal 5100 gpm flow from booster pump. [DBD E41-00 Section 4.2.2]Main Pump (E4101C001A)Flow Developed Head equal to 5000 gpm/2800 ft at 1135 psia (Reactor Pressure 525 feet at 165 psia Reactor Pressure)Water Temperature equal to 40 degrees F-140 degrees F*Design Temperature equal to 400 degrees F-212 degrees FDesign Pressure equal to 1500 psigShutoff Head equal to 3400 feetSpeed equal to 2100-4100 rpm Design
References:
TS 3.5.1 ECCS Operating, and associated BasesTS SR 3.5.1.9 TS SR 3.5.1.10UFSAR 1.2.2.9.11.1 High Pressure Coolant InjectionUFSAR 5.2.1.1.12 High Pressure Coolant Injection SystemUFSAR Table 6.3-2, Materials for the Principal Emergency Core Cooling System ComponentsUFSAR Table 6.3-6 ECCS AnalysisUFSAR 6.3.2.2.1 High Pressure Coolant Injection systemDBD E41-00 Rev F, High Pressure Coolant Injection System Appendix V Basis: OM Code Appendix V paragraph V-3000(a) Requirement: The Owner shall (a) identify those certain applicable pumps with specific design basis accident flow rates in the Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) for inclusion in this program.SR 3.5.1.9 - Verify, with reactor pressure less than or equal to 1045 and greater than or equal to 945 psig, the HPCI pump can develop a flow rate of greater than or equal to 5000 gpm against a system head corresponding to reactor pressure. [In accordance with the Inservice Testing Program] Not required to be performed unit 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.SR 3.5.10 - Verify, with reactor pressure less than or equal to 215 psig, the HPCI pump can develop a flow rate of greater than or equal to 5000 gpm against a system head corresponding to reactor pressure. [18 months] Not required to be performed unit 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.UFSAR TABLE 6.3-6 ECCS ANALYSISSIGNIFICANT INPUT VARIABLES AND INITIAL CONDITIONHigh Pressure Coolant Injection (HPCI) SystemVessel Pressure at Which Flow May Commence psia 1135Minimum Rated Flow at Vessel Pressure of:psia 1135 to 165**gpm 5000** HPCI pump is designed to produce a flow of 5000 gpm at an RPVpressure of 1184 psia, which exceeds LOCA input.In summary, to satisfy Appendix V, the HPCI pump must be flow tested with reactor pressure at greater than or equal to 945 psig and less than or equal to 1045 psig, at a flow rate of greater than or equal to 5,000 gpm with system head corresponding to reactor pressure.ANDIn summary, to satisfy Appendix V, the HPCI pump must be flow tested with reactor pressure at greater than or equal to 165 psig and less than or equal to 215 psig, at a flow rate of greater than or equal to 5,000 gpm with system head corresponding to reactor pressure.
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DI e-- Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 32 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes E4101C001B E4101 HPCI - Booster Pump 5708-1/E-4 Skid 2 Centrifugal Safety Function Basis: The HPCI Booster pump is not treated as an individual pump in IST scoping, but is tested as part of the main pump. It is considered a skid-mounted component of the main HPCI pump per ISTB-1200(c). The HPCI pump assembly consists of a two-stage main pump with high speed gear and a single-stage booster pump that are mounted on a common base and driven by the separately mounted HPCI steam turbine. The HPCI pumps deliver 5000 gpm of makeup water to the reactor vessel in the event of a loss-of-coolant accident and supply makeup water to the reactor vessel in the event of a loss of feedwater and failure of the Reactor Core Isolation Cooling system. The safety-related pump assembly is designated QA Level 1, seismic Category I, and is designed to ASME Code Section III Class 2 requirements. [DBD E41-00 Section 4.2.2] Surveillance testing of HPCI pump performance is representative of the performance of both pumps acting in series. Any evaluation or degradation may include the booster or main pump as a possible cause and maintenance activities would target either the booster pump or main pump depending on indications. [DBD E41-00 Section 4.2.2] [UFSAR 6.3.2.2.1]This pump is classified as a skid-mounted component. As such, testing of the major component can be credited as satisfactorily testing the skid-mounted component. This classification is consistent with ISTB-1200 and the discussion and NRC recommendation for skid-mounted components in NUREG 1482, Section 3.4, "Skid-Mounted Components and Component Subassemblies." Testing the HPCI Main Pump (major component) in accordance with 24.202.01 "HPCI Pump and Valve Operability Test at 1025 PSI" verifies operational readiness of the main and booster pumps. Specific to the HPCI Booster Pump, Table 2 provides expected and allowable test parameters specific to proper main and booster pump operations. Examples include; lube oil skid pressures and temperatures, pump discharge temperatures, bearing temperatures, turbine governor/coupling clearances, etc. 24.202.01 confirms E4100-F019, HPCI Booster Pump Suction Line From CST Check Valve, is sufficiently open by indication of at least 5150 gpm flow on E41-R613 which confirms proper operation of the Booster pump in addition to the IST procedurally required hydraulic and vibration test requirements.
Function
Description:
This pump is Skid-Mounted. The high pressure coolant injection (HPCI) system provides and maintains an adequate coolant inventory inside the RPV. This limits fuel cladding temperature, which may result from postulated small breaks in the nuclear system process barrier. A high-pressure system is needed for small breaks because the RPV depressurizes slowly, preventing low-pressure systems from injecting coolant. Also, the HPCI system reduces RPV pressure rapidly, permitting operation of the low-pressure systems. The HPCI system includes a turbine-driven pump powered by reactor steam. The system is designed to accomplish its function on a short-term basis, without reliance on plant auxiliary power supplies other than the dc power supply. The High Pressure Coolant Injection (HPCI) system forms a part of the Emergency Core Cooling System (ECCS) at Fermi 2 provided to protect the core against various sizes of postulated pipe breaks in accordance with General Design Criteria 35 of 10CFR50 Appendix A. The protection afforded by the ECCS systems meets the NRC criteria given in Appendix K of 10CFR50 and precludes exceeding the maximum fuel cladding temperature limit of 2200 degrees F and other requirements set forth in 10CFR50.46. The safety
-related HPCI system provides emergency core cooling to the Reactor Pressure Vessel (RPV) for a wide range of reactor pressures in the event of an accident involving loss of coolant at a relatively low flow rate. This range of reactor pressures encompassing HPCI System Operation is 1169 psig max, based on the lowest SRV setting of 1135 psig +/- 3 percent, to 100 psig, which is the HPCI isolation setpoint based on Calculation DC-4575 Vol. I. [DBD E41-00 Section 2.1 Summary] The function of the high pressure coolant injection (HPCI) system is to provide high-pressure makeup to the RPV in the event of a small-break loss-of-coolant accident. [UFSAR 5.2.1.1.12]
Design Basis Limits: DBD E41-00 Design ParametersBooster Pump (E4101C001B)Flow 5100 gpmWater Temperature Range equal to 40 degrees F -140 degrees F*Design Temperature equal to 40 degrees F - 212 degrees F Design Pressure 450 psig NPSH 21 feet required Booster Pump Bypass Flow equal to 70 gpm (minimum)Developed Pressure equal to 290 psi at 2000 rpmMaximum Suction Pressure equal to 65 psia Speed equal to 1050 - 2000 rpm Design
References:
TS 3.5.1 ECCS Operating, and associated BasesTS SR 3.5.1.9 TS SR 3.5.1.10UFSAR 1.2.2.9.11.1 High Pressure Coolant InjectionUFSAR 5.2.1.1.12 High Pressure Coolant Injection SystemUFSAR Table 6.3-2, Materials for the Principal Emergency Core Cooling System ComponentsUFSAR Table 6.3-6 ECCS AnalysisUFSAR 6.3.2.2.1 High Pressure Coolant Injection systemDBD E41-00 Rev F, High Pressure Coolant Injection System Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 31 of 106
Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 33 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes E5101C001 E5100 RCIC Pump 5709-1/E-4 B 2 Centrifugal dP 2Y 24.206.01 TP-19 N 2Y 24.206.01 Q 2Y 24.206.01 TP-19 V 2Y 24.206.01 Standard Code ISTB dP Q 24.206.01 N Q 24.206.01 Q Q 24.206.01 V Q 24.206.01 Safety Function Basis: The RCIC System is designed to perform the following safety-related functions: (a) ensure that adequate core cooling takes place to prevent the reactor fuel from overheating in the event of the reactor isolation is accompanied by loss of flow from the reactor feedwater system; (b) maintain sufficient water level in the reactor vessel to maintain adequate cooling of the reactor core on loss of feedwater or reactor isolation; (c) automatically initiate and provide sufficient flow in time to maintain sufficient coolant in the RPV so that the integrity of radioactive material barrier is not compromised; (d) meet Class I earthquake requirements and maintain pressure boundary requirements of the RPV boundaries. [DBD E51-00 Section 2.2.1 Safety Related Functions]The RCIC System meets the following safety design basis. (a) The system shall ensure that adequate core cooling takes place to prevent the reactor fuel from overheating in the event the reactor isolation is accomplished by loss of flow from the reactor feedwater system; (b) The system shall operate automatically in time to maintain sufficient coolant in the RPV so that the integrity of the radioactive material barrier is not compromised; (c) Piping and equipment, including support structures, shall be designed to withstand the effects of an earthquake without failure that could lead to a release of radioactivity in excess of the guideline values in published regulations. [UFSAR 5.5.6.1 Safety Design Basis]
Function
Description:
Group B - This pump is in standby systems that are not operated routinely except for testing.The RCIC pump provides 600 gpm injection flow at a discharge pressure of 1515 psia to maintain core cooling during reactor shutdown. The pump provides makeup water to the reactor pressure vessel (RPV) in case of a loss of flow from the main feedwater system in time to preclude conditions that lead to inadequate core cooling and initiation of low pressure ECCS due to decreasing RPV level. UFSAR 7.1.2.1.20 and Figure 7.1-1, state that RCIC is required for safe shutdown. [DBD E51-00 Data Sheet 4.2.1.1, UFSAR 7.4.1.1.1, 7.1.2.1.20, Figure 7.1-1]The Reactor Core Isolation Cooling (RCIC) System provides a source of high-pressure coolant to the reactor vessel to prevent the reactor core from overheating in the event of reactor isolation accompanied by loss of flow from the reactor feedwater system. The RCIC System consists of a noncondensing turbine driving a pump in an open loop system. The RCIC Turbine draws steam from the reactor upstream of the Main Steam Isolation Valves (MSIVs) and exhausts to the Suppression Pool. The RCIC turbine-driven pump takes suction from the Condensate Storage Tank (CST) or the Suppression Pool and delivers the makeup water to the reactor vessel via a feedwater line. The RCIC is automatically initiated when the Reactor Pressure Vessel (RPV) Level 2 is reached. [DBD E51-00 Section 2.1 Summary]
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 32 of 106
an -n r Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 34 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes Design Basis Limits: TS SR 3.5.3.4: Verify, with reactor pressure less than or equal to 200 psig, the RCIC pump can develop a flow rate of greater than or equal to 600 gpm against a system head corresponding to reactor pressure. [Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test] [18 months]TS SR 3.5.3.3: Verify, with reactor pressure less than or equal to 1045 and greater than or equal to 945 psig, the RCIC pump can develop a flow rate greater than or equal to 600 gpm against a system head corresponding to reactor pressure. [Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test] [92 days]RCIC Pump Operation (C001) Design Parameters [UFSAR 5.5.6.2.2 Design Parameters, DBD E51-00]Flow rate Injection flow 600 gpmCooling water flow 16 gpmTotal pump discharge 616 gpmWater temperature range 40OF to 140OFNPSH 20 ft minimumDeveloped head pressure 2915 ft at 1184-psia reactor pressure, 525 ft at 165-psia reactor pressureBHP (not to exceed) 700 HP at 2915-ft developed head, 100 HP at 525-ft developed headDesign pressure 1515 psiaDesign ambient 148 0F, maximum Total Developed Head (TDH) 3400 feetRCIC Turbine Operation (C002) High-Pressure Low-Pressure Condition ConditionReactor pressure (saturated temperature) 1184 psia 165 psiaSteam inlet pressure 1169 psia, minimum 150 psia, minimumTurbine exhaust pressure 25 psia, maximum 25 psia, maximumDesign inlet pressure 1250 psig at saturated temperatureDesign exhaust pressure 165 psig at saturation temperatureThe flow rate of water from the RCIC pump to the reactor vessel is 600 gpm, which is approximately equal to reactor boiloff rate 15 minutes after shutdown. This flow rate is sufficient to prevent the reactor vessel water level from dropping down to the top of the core. [UFSAR 5.5.6.3.2 Reactor Core Isolation Cooling Following Main Condenser Isolation]
Design
References:
TS 3.5.3 RCIC systemUFSAR 1.2.2.9.5 Reactor Core Isolation Cooling SystemUFSAR Table 3.6-6 Flow and Events Postulated for Feedwater BreakUFSAR 5.5.6 Reactor Core Isolation CoolingUFSAR 5.5.6.3.1 GeneralUFSAR Figure 7.1-1 PLANT INSTRUMENTATION AND CONTROL SYSTEMS CLASSIFICATIONUFSAR 7.1.2.1.20 Reactor Core Isolation Cooling SystemUFSAR 7.4.1.1.3.1 Initiating CircuitsUFSAR 7.4.1.1 Reactor Core Isolation Cooling System Instrumentation and ControlUFSAR TABLE 15.6.4.-1 TYPICAL SEQUENCE OF EVENTS FOR STEAM LINE BREAK OUTSIDE OF CONTAINMENTUFSAR 15.15.2 Analysis of Effects and ConsequencesDBD E51-00 Rev. E, Reactor Core Isolation Cooling Appendix V Basis: OM Code Appendix V paragraph V-3000(a) Requirement: The Owner shall (a) identify those certain applicable pumps with specific design basis accident flow rates in the Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) for inclusion in this program.TS SR 3.5.3.4: Verify, with reactor pressure less than or equal to 200 psig, the RCIC pump can develop a flow rate of greater than or equal to 600 gpm against a system head corresponding to reactor pressure. [Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test] [18 months]TS SR 3.5.3.3: Verify, with reactor pressure less than or equal to 1045 and greater than or equal to 945 psig, the RCIC pump can develop a flow rate greater than or equal to 600 gpm against a system head corresponding to reactor pressure. [Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test] [92 days]In summary, to satisfy Appendix V, the RCIC pump must be flow tested with reactor pressure at greater than or equal to 945 psig and less than or equal to 1045 psig, at a flow rate of greater than or equal to 600 gpm with system head corresponding to reactor pressure.ANDIn summary, to satisfy Appendix V, the HPCI pump must be flow tested with reactor pressure at greater than or equal to 150 psig and less than or equal to 200 psig, at a flow rate of greater than or equal to 600 gpm with system head corresponding to reactor pressure.
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 33 of 106
.70W an mFermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 35 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes P4400C001A P4400 Emergency Equip Cooling Water Div 1 Pump 5729-1/C-7 B 3 Centrifugal dP 2Y 24.207.08 Q 2Y 24.207.08 V 2Y 24.207.08 PRR-002 Standard Code ISTB dP Q 24.207.08 Q Q 24.207.08 V Q 24.207.08 Safety Function Basis: The EECW pumps are motor-driven, single stage, double suction, horizontal, centrifugal pumps. The pump has a safety function to supply cooling water to engineered safety feature (ESF) equipment in the event of a postulated design basis accident or safely shut down the plant concurrent with a loss of offsite power. The pump auto starts on high drywell pressure, loss of offsite electrical power, or mechanical (passive) failure of the RBCCW. The pump can be manually started if auto-initiation fails or following a HELB which does not result in loss of offsite power. (Note: This post-HELB safety-related function is not required if RBCCW is available.) The EECW pump in each division provides sufficient developed head to supply cooling water to all safety-related components during the emergency conditions described above. [DBD P44-00 Section 2.2, 3.2.1.1, Table 1-A & B] [UFSAR 9.2.2, 7.1.2.1.18]The EECWS may be manually initiated with the non-essential loads subsequently restored to facilitate RBCCW heat exchanger cleaning, to enhance drywell cooling during high lake water (GSW) temperature, for testing, or to provide RHR Reservoir freeze protection during extreme cold weather. The EECWS is designed to provide equipment cooling and ventilation space cooling for HPCI, RCIC, RHR and Core Spray systems. Each of the two supply and return cooling loops (Division I and Division II) consists of one circulating pump of sufficient capacity to circulate water through the system and return the cooling water to a full capacity heat exchanger. [UFSAR 6.3.2.2.6]The EECW/EESW System is designed to provide cooling water for the removal of heat from equipment, such as residual heat removal (RHR) and Core Spray (CS), pump coolers, and room coolers for Emergency Core Cooling System and other safety-related equipment, required for safe reactor shutdown following a Design Basis Accident (DBA) or transient. Components cooled by each EECW subsystem are normally cooled by the Reactor Building Closed Cooling Water (RBCCW) system, which cools various plant equipment primarily in the Reactor Building. An EECW subsystem contains a single 1775 gpm nominal capacity pump, a heat exchanger, a make-up tank, valves, piping, and associated instrumentation. A second 100 percent capacity heat exchanger is also provided as a backup. Upon activation, the EECW pump starts, the EECW loop isolates from the remainder of the RBCCW system, and other system valves reposition as needed to isolate non-essential loads and configure the system for emergency operation. [TS B 3.7.2]
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 34 of 106
DTIE ergFermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 36 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes Function
Description:
Group B - This pump is in standby systems that are not operated routinely except for testing.The safety-related EECW system consists of two independent and redundant cooling water flow trains, Division I and Division II, supplying cooling water to safety related equipment. Each division is equipped with a circulating EECW pump that circulates cooling water through the system piping and valves, the components served, and primary and backup plate and frame EECW heat exchangers. [DBD P44-00 Section 2.1] The EECW System is designed to perform the following safety related functions: (a) supply cooling water to engineered safety feature (ESF) equipment in the event of a postulated design basis accident or safely shut down the plant concurrent with the loss of offsite power; (b) transfer heat rejected by ESF components to the EESW; (c) automatically initiate on high drywell pressure, loss of offsite electrical power, or mechanical (passive) failure of the RBCCW; (d) manually initiate if auto-initiation fails or following a HELB which does not result in loss of offsite power [not required if RBCCW is available]; (e) provide an intermediate loop between potentially contaminated reactor auxiliaries and the EESW, assuring additional protection against radioactive water leakage into the environment. [DBD P44-00 Section 2.2.1] The basis for the emergency mode of operation is to assure safe plant shutdown utilizing the engineered safety feature EECW system in the event of a LOCA, loss of offsite power, or failure of the RBCCW. The non-safety-related RBCCW is isolated to prevent any potentially undesirable interactions with this system.
Cooling water flow to non-essential loads is isolated to preserve flow to essential loads. In addition, cooling water to the drywell is isolated during a LOCA since the EECW is not designed or required to accommodate drywell accident heat loads. [DBD P44-00 Section 2.2.3]LOCAIn the event of a postulated design basis accident [LOCA], both divisions of the EECW system are automatically initiated on high drywell pressure, which is indicative of a small, intermediate, or large coolant line break. Initiation of EECW starts the EECW and EESW pumps, closes EECW/RBCCW isolation valves F601A/B and F603A/B, isolating the non-essential RBCCW, and isolates several non-essential loads served by EECW. Upon closure of the divisional isolation valves (F601A/B and F603A/B), the EECW makeup tank isolation valves F602A/B automatically open. Simultaneously, the high drywell pressure signal isolates EECW cooling water flow to the drywell by closing valves F606A and F606B. Manual operation of EECW with the non-essential loads restored does not prevent the re-isolation of the non-essential loads in response to a high drywell pressure signal with or without a loss of offsite power. [DBD P44-00 Section 2.2.3]LOOPA loss of offsite power (LOOP) results in automatic initiation of EECW as described for LOCA event. Cooling water is supplied to the drywell if a high drywell pressure signal is not present (valves F606A and F606B do not close). Manual operation of EECW with the non-essential loads restored does not prevent the re-isolation of the non-essential loads in response to a loss of offsite power. [DBD P44-00 Section 2.2.3]MECHANICAL (PASSIVE) FAILURE OF RBCCWA low differential pressure across the RBCCW supply and return headers initiates EECW (with cooling water supplied to the drywell). Either Division I or Division II will start automatically, depending on which portion of RBCCW is affected by the break. The auto-start on low differential header pressure is not an ESF initiation; it is a design feature for dealing with abnormal operating occurrence, namely a loss of RBCCW supply flow to a division of EECW. [DBD P44-00 Section 2.2.3]
Design Basis Limits: TS B 3.7.2Components cooled by each EECW subsystem are normally cooled by the Reactor Building Closed Cooling Water (RBCCW) system, which cools various plant equipment primarily in the Reactor Building. An EECW subsystem contains a single 1775 gpm nominal capacity pump, a heat exchanger, a make-up tank, valves, piping, and associated instrumentation.DBD P44-00 EECW Pump ParametersPump: Capacity equal to 1775 gpmTDH (at capacity flow rate) equal to 167 ftNPSHA (at minimum makeup tank level and pressure)
- equal to 70 ftNPSHR (at maximum system flow rate of 1775 gpm) equal to 11.1 ftShutoff head equal to 200 ft(*) DC-5806 also evaluates NPSH requirements at 2400 gpm. The analysis demonstrates that the available NPSH of 37 ft exceeds a requirement of 25 ft.The EECW pumps are motor-driven, single stage, double suction, horizontal, centrifugal Goulds Model 3410, Size 6x8-14H. The EECW pump in each division provides sufficient developed head to supply cooling water to all safety-related components during emergency conditions (previously discussed in Sections 2 and 3.1). The safety-related pumps are designated QA Level 1, seismic Category I, and are designed to ASME Section III, Class 3 requirements. NUREG-0588 Appendix E safety category for these pumps is qualification category 2A. [DBD P44-00 Section 3.2.1.1, Table 1-A & B] [UFSAR 9.2.2, 7.1.2.1.18]Design Maximum Flow - The maximum allowed flow for the EECW heat exchanger is 4000 gpm which is well beyond the capability of the EECW pump. Maximum flow evaluated for EECW pump runout and minimum NPSH requirements is 2400 gpm. The ability to supply EECW water below a design maximum EECW supply temperature of 95 degrees F is based on maximum system flow of 1775 gpm. The limiting maximum value is, therefore, 1775 gpm. [DBD P44-00 Section 3.1.1 Process Design Requirements]
Design
References:
TS 3.7.2 Emergency Equipment Cooling Water (EECW)/Emergency Equipment Service Water (EESW) System and Ultimate Heat SinkTS B 3.7.2 Emergency Equipment Cooling Water (EECW)/Emergency Equipment Service Water (EESW) System and Ultimate Heat SinkUFSAR 6.3.2.2.6 Emergency Equipment Cooling Water SystemUFSAR 7.1.2.1.18 Emergency Equipment Cooling Water SystemUFSAR 9.2.2 Cooling System for Reactor AuxiliariesDBD P44-00 Rev G, Emergency Equipment Cooling Water (EECW) System Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 35 of 106
Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 37 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes Appendix V Basis: OM Code Appendix V paragraph V-3000(a) Requirement: The Owner shall (a) identify those certain applicable pumps with specific design basis accident flow rates in the Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) for inclusion in this program.This pump has been deemed not applicable to Appendix V. There are no specified TS or UFSAR requirements specific to pump design basis accident flow rates. There is one TS Bases reference. However, it refers to a nominal flow rate which is not a specific design basis accident flow rate.TS B 3.7.2Components cooled by each EECW subsystem are normally cooled by the Reactor Building Closed Cooling Water (RBCCW) system, which cools various plant equipment primarily in the Reactor Building. An EECW subsystem contains a single 1775 gpm nominal capacity pump, a heat exchanger, a make-up tank, valves, piping, and associated instrumentation.
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 36 of 106
Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 38 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes P4400C001B P4400 Emergency Equip Cooling Water Div 2 Pump 5729-2/F-7 B 3 Centrifugal dP 2Y 24.207.09 Q 2Y 24.207.09 V 2Y 24.207.09 PRR-002 Standard Code ISTB dP Q 24.207.09 Q Q 24.207.09 V Q 24.207.09 Safety Function Basis: The EECW pumps are motor-driven, single stage, double suction, horizontal, centrifugal pumps. The pump has a safety function to supply cooling water to engineered safety feature (ESF) equipment in the event of a postulated design basis accident or safely shut down the plant concurrent with a loss of offsite power. The pump auto starts on high drywell pressure, loss of offsite electrical power, or mechanical (passive) failure of the RBCCW. The pump can be manually started if auto-initiation fails or following a HELB which does not result in loss of offsite power. (Note: This post-HELB safety-related function is not required if RBCCW is available.) The EECW pump in each division provides sufficient developed head to supply cooling water to all safety-related components during the emergency conditions described above. [DBD P44-00 Section 2.2, 3.2.1.1, Table 1-A & B] [UFSAR 9.2.2, 7.1.2.1.18]The EECWS may be manually initiated with the non-essential loads subsequently restored to facilitate RBCCW heat exchanger cleaning, to enhance drywell cooling during high lake water (GSW) temperature, for testing, or to provide RHR Reservoir freeze protection during extreme cold weather. The EECWS is designed to provide equipment cooling and ventilation space cooling for HPCI, RCIC, RHR and Core Spray systems. Each of the two supply and return cooling loops (Division I and Division II) consists of one circulating pump of sufficient capacity to circulate water through the system and return the cooling water to a full capacity heat exchanger. [UFSAR 6.3.2.2.6]The EECW/EESW System is designed to provide cooling water for the removal of heat from equipment, such as residual heat removal (RHR) and Core Spray (CS), pump coolers, and room coolers for Emergency Core Cooling System and other safety-related equipment, required for safe reactor shutdown following a Design Basis Accident (DBA) or transient. Components cooled by each EECW subsystem are normally cooled by the Reactor Building Closed Cooling Water (RBCCW) system, which cools various plant equipment primarily in the Reactor Building. An EECW subsystem contains a single 1775 gpm nominal capacity pump, a heat exchanger, a make-up tank, valves, piping, and associated instrumentation. A second 100 percent capacity heat exchanger is also provided as a backup. Upon activation, the EECW pump starts, the EECW loop isolates from the remainder of the RBCCW system, and other system valves reposition as needed to isolate non-essential loads and configure the system for emergency operation. [TS B 3.7.2]
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 37 of 106
- Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 39 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes Function
Description:
Group B - This pump is in standby systems that are not operated routinely except for testing.The safety-related EECW system consists of two independent and redundant cooling water flow trains, Division I and Division II, supplying cooling water to safety related equipment. Each division is equipped with a circulating EECW pump that circulates cooling water through the system piping and valves, the components served, and primary and backup plate and frame EECW heat exchangers. [DBD P44-00 Section 2.1] The EECW System is designed to perform the following safety related functions: (a) supply cooling water to engineered safety feature (ESF) equipment in the event of a postulated design basis accident or safely shut down the plant concurrent with the loss of offsite power; (b) transfer heat rejected by ESF components to the EESW; (c) automatically initiate on high drywell pressure, loss of offsite electrical power, or mechanical (passive) failure of the RBCCW; (d) manually initiate if auto-initiation fails or following a HELB which does not result in loss of offsite power [not required if RBCCW is available]; (e) provide an intermediate loop between potentially contaminated reactor auxiliaries and the EESW, assuring additional protection against radioactive water leakage into the environment. [DBD P44-00 Section 2.2.1] The basis for the emergency mode of operation is to assure safe plant shutdown utilizing the engineered safety feature EECW system in the event of a LOCA, loss of offsite power, or failure of the RBCCW. The non-safety-related RBCCW is isolated to prevent any potentially undesirable interactions with this system.
Cooling water flow to non-essential loads is isolated to preserve flow to essential loads. In addition, cooling water to the drywell is isolated during a LOCA since the EECW is not designed or required to accommodate drywell accident heat loads. [DBD P44-00 Section 2.2.3]LOCAIn the event of a postulated design basis accident [LOCA], both divisions of the EECW system are automatically initiated on high drywell pressure, which is indicative of a small, intermediate, or large coolant line break. Initiation of EECW starts the EECW and EESW pumps, closes EECW/RBCCW isolation valves F601A/B and F603A/B, isolating the non-essential RBCCW, and isolates several non-essential loads served by EECW. Upon closure of the divisional isolation valves (F601A/B and F603A/B), the EECW makeup tank isolation valves F602A/B automatically open. Simultaneously, the high drywell pressure signal isolates EECW cooling water flow to the drywell by closing valves F606A and F606B. Manual operation of EECW with the non-essential loads restored does not prevent the re-isolation of the non-essential loads in response to a high drywell pressure signal with or without a loss of offsite power. [DBD P44-00 Section 2.2.3]LOOPA loss of offsite power (LOOP) results in automatic initiation of EECW as described for LOCA event. Cooling water is supplied to the drywell if a high drywell pressure signal is not present (valves F606A and F606B do not close). Manual operation of EECW with the non-essential loads restored does not prevent the re-isolation of the non-essential loads in response to a loss of offsite power. [DBD P44-00 Section 2.2.3]
Design Basis Limits: TS B 3.7.2Components cooled by each EECW subsystem are normally cooled by the Reactor Building Closed Cooling Water (RBCCW) system, which cools various plant equipment primarily in the Reactor Building. An EECW subsystem contains a single 1775 gpm nominal capacity pump, a heat exchanger, a make-up tank, valves, piping, and associated instrumentation.DBD P44-00 EECW Pump ParametersPump: Capacity equal to 1775 gpmTDH (at capacity flow rate) equal to 167 ftNPSHA (at minimum makeup tank level and pressure)
- equal to 70 ftNPSHR (at maximum system flow rate of 1775 gpm) equal to 11.1 ftShutoff head equal to 200 ft(*) DC-5806 also evaluates NPSH requirements at 2400 gpm. The analysis demonstrates that the available NPSH of 37 ft exceeds a requirement of 25 ft.The EECW pumps are motor-driven, single stage, double suction, horizontal, centrifugal Goulds Model 3410, Size 6x8-14H. The EECW pump in each division provides sufficient developed head to supply cooling water to all safety-related components during emergency conditions (previously discussed in Sections 2 and 3.1). The safety-related pumps are designated QA Level 1, seismic Category I, and are designed to ASME Section III, Class 3 requirements. NUREG-0588 Appendix E safety category for these pumps is qualification category 2A. [DBD P44-00 Section 3.2.1.1, Table 1-A & B] [UFSAR 9.2.2, 7.1.2.1.18]Design Maximum Flow - The maximum allowed flow for the EECW heat exchanger is 4000 gpm which is well beyond the capability of the EECW pump. Maximum flow evaluated for EECW pump runout and minimum NPSH requirements is 2400 gpm. The ability to supply EECW water below a design maximum EECW supply temperature of 95 degrees F is based on maximum system flow of 1775 gpm. The limiting maximum value is, therefore, 1775 gpm. [DBD P44-00 Section 3.1.1 Process Design Requirements]
Design
References:
TS 3.7.2 Emergency Equipment Cooling Water (EECW)/Emergency Equipment Service Water (EESW) System and Ultimate Heat SinkTS B 3.7.2 Emergency Equipment Cooling Water (EECW)/Emergency Equipment Service Water (EESW) System and Ultimate Heat SinkUFSAR 6.3.2.2.6 Emergency Equipment Cooling Water SystemUFSAR 7.1.2.1.18 Emergency Equipment Cooling Water SystemUFSAR 9.2.2 Cooling System for Reactor AuxiliariesDBD P44-00 Rev G, Emergency Equipment Cooling Water (EECW) System Appendix V Basis: OM Code Appendix V paragraph V-3000(a) Requirement: The Owner shall (a) identify those certain applicable pumps with specific design basis accident flow rates in the Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) for inclusion in this program.This pump has been deemed not applicable to Appendix V. There are no specified TS or UFSAR requirements specific to pump design basis accident flow rates. There is one TS Bases reference. However, it refers to a nominal flow rate which is not a specific design basis accident flow rate.TS B 3.7.2Components cooled by each EECW subsystem are normally cooled by the Reactor Building Closed Cooling Water (RBCCW) system, which cools various plant equipment primarily in the Reactor Building. An EECW subsystem contains a single 1775 gpm nominal capacity pump, a heat exchanger, a make-up tank, valves, piping, and associated instrumentation.
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 38 of 106
- D rFermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 40 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes P4400C002A P4400 EECW Makeup Div 1 Pump 5729-1/B-8 B 3 Centrifugal dP 2Y 24.208.02 Q 2Y 24.208.02 V 2Y 24.208.02 PRR-002 Standard Code ISTB dP Q 24.208.02 Q Q 24.208.02 V Q 24.208.02 Safety Function Basis: The EECW makeup pumps are motor-driven, single-stage, single-suction horizontal, centrifugal pumps, manufactured by FlowServe Corp. The EECW makeup pump in each division provides sufficient developed head to supply makeup water at a controlled pressure to its makeup tank during emergency conditions. This makeup system is initiated on either low makeup tank pressure or low makeup tank level when the makeup tank isolation valve is open, and normal pump suction pressure is achieved. [UFSAR 9.2.2.3] The EECW makeup tanks function to accommodate system coolant inventory variations and provide makeup water supplied by the demineralized water system via level control valves, F402A(B), and the EECW makeup line and its associated pump when level and/or pressure in the makeup tank cannot be maintained by normal means. [DBD P44-00 Section 3.2.3]The EECW system makeup tank is supplied via a crosstie line and a makeup pump from the EESW system to provide an alternate makeup supply for each division when the normal makeup supply to the tank is lost during and after the design basis accident. After EECW start, the EECW makeup tanks are replenished and pressurized by makeup pumps utilizing EESW water. The makeup pumps automatically start on makeup tank low pressure or low level, if the makeup tank isolation valve is open and normal makeup pump suction pressure is achieved. Instrumentation and controls are provided to automatically maintain EECW makeup tank pressure, and provide a source of safety-related water (EESW) during EECW system operation. [UFSAR 7.1.2.1.18]These safety-related pumps are designated QA Level 1, seismic Category I, and are designed to ASME Section III, Class 3 requirements. The NUREG- 0588 Appendix E safety category for these pumps is qualification category 2A. The makeup pump is powered from the same MCC that supplies power to the EECW isolation valves, and is local to each EECW division. The nominal pump capacity is 20 gpm at a total developed head of 60 feet. [DBD P44-00 Section 2.2, 3.2.1.2, 3.1.2.5, Table 1-A & B] [UFSAR 9.2.2, 7.1.2.1.18]
Function
Description:
Group B - This pump is in standby systems that are not operated routinely except for testing.The EECW section of the RBCCWS consists of two redundant full-capacity loops, each with two (2) 100 percent capacity heat exchangers, pump, and makeup pump and tank. The EECW (Division I and Division II) system makeup tank is connected with a makeup line to the EESW system to provide an alternate makeup supply for each division when the normal makeup supply to this tank is lost during and after the design basis accident. The isolation valves for the alternate makeup supply consist of a check valve and an air-operated valve which opens automatically on a makeup pump start, a loss of air or a loss of electrical power. Each makeup pump auto starts and provides the makeup water to the tank. [UFSAR 9.2.2.2] The EECW makeup pump in each division provides sufficient developed head to supply makeup water at a controlled pressure to its makeup tank during emergency conditions. [DBD P44-00 Section 3.2.1.2]An EECW/EESW subsystem is considered OPERABLE when it has an OPERABLE EECW pump, an OPERABLE EESW pump, and OPERABLE EECW/EESW heat exchanger, an OPERABLE EECW makeup tank, an OPERABLE EECW makeup pump, and OPERABLE flow paths to provide cooling water flow to the supported equipment and reject the heat to the division's RHR reservoir. [TS B 3.7.2]
Design Basis Limits: DBD P44-00 Section 3.2.1.2EECW Makeup Pump Parameters[Nominal (nameplate) unless otherwise indicated.]Pump:Capacity, gpm equal to 20TDH (at capacity flow rate), ft equal to 60NPSHA, ft equal to 97NPSHR, equal to 2Shutoff head, ft equal to 60Maximum allowable degradation, ft (10%) equal to 6Horsepower, hp equal to 3Speed, rpm equal to 1750Design pressure, psig equal to 120Design temperature, degree F equal to 125Material (pressure boundary) equal to Cast Carbon Steel (A216, WCB)Motor:Horsepower, hp equal to 3Design required horsepower at maximum system flow rate of 90 gpm, hp equal to 2.OSpeed, rpm equal to 1760Voltage, volts equal to 460Frame equal to 182TService factor equal to 1.15 Design
References:
TS 3.7.2 Emergency Equipment Cooling Water (EECW)/Emergency Equipment Service Water (EESW) System and Ultimate Heat SinkTS B 3.7.2 Emergency Equipment Cooling Water (EECW)/Emergency Equipment Service Water (EESW) System and Ultimate Heat SinkUFSAR 7.1.2.1.18 Emergency Equipment Cooling Water SystemUFSAR 9.2.2 Cooling System for Reactor AuxiliariesDBD P44-00, Rev G, Emergency Equipment Cooling Water (EECW) System Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 39 of 106
Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 41 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes Appendix V Basis: OM Code Appendix V paragraph V-3000(a) Requirement: The Owner shall (a) identify those certain applicable pumps with specific design basis accident flow rates in the Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) for inclusion in this program.This pump has been deemed not applicable to Appendix V. There are no specified TS or UFSAR requirements specific to pump design basis accident flow rates. DBD P44-00 refers to EECW Makeup Pump Parameters but states those values are nominal (nameplate) unless otherwise indicated.
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 40 of 106
1M - Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 42 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes P4400C002B P4400 EECW Makeup Div 2 Pump 5729-2/A-7 B 3 Centrifugal dP 2Y 24.208.03 Q 2Y 24.208.03 V 2Y 24.208.03 PRR-002 Standard Code ISTB dP Q 24.208.03 Q Q 24.208.03 V Q 24.208.03 Safety Function Basis: The EECW makeup pumps are motor-driven, single-stage, single-suction horizontal, centrifugal pumps, manufactured by FlowServe Corp. The EECW makeup pump in each division provides sufficient developed head to supply makeup water at a controlled pressure to its makeup tank during emergency conditions. This makeup system is initiated on either low makeup tank pressure or low makeup tank level when the makeup tank isolation valve is open, and normal pump suction pressure is achieved. [UFSAR 9.2.2.3] The EECW makeup tanks function to accommodate system coolant inventory variations and provide makeup water supplied by the demineralized water system via level control valves, F402A(B), and the EECW makeup line and its associated pump when level and/or pressure in the makeup tank cannot be maintained by normal means. [DBD P44-00 Section 3.2.3]The EECW system makeup tank is supplied via a crosstie line and a makeup pump from the EESW system to provide an alternate makeup supply for each division when the normal makeup supply to the tank is lost during and after the design basis accident. After EECW start, the EECW makeup tanks are replenished and pressurized by makeup pumps utilizing EESW water. The makeup pumps automatically start on makeup tank low pressure or low level, if the makeup tank isolation valve is open and normal makeup pump suction pressure is achieved. Instrumentation and controls are provided to automatically maintain EECW makeup tank pressure, and provide a source of safety-related water (EESW) during EECW system operation. [UFSAR 7.1.2.1.18]These safety-related pumps are designated QA Level 1, seismic Category I, and are designed to ASME Section III, Class 3 requirements. The NUREG- 0588 Appendix E safety category for these pumps is qualification category 2A. The makeup pump is powered from the same MCC that supplies power to the EECW isolation valves, and is local to each EECW division. The nominal pump capacity is 20 gpm at a total developed head of 60 feet. [DBD P44-00 Section 2.2, 3.2.1.2, 3.1.2.5, Table 1-A & B] [UFSAR 9.2.2, 7.1.2.1.18]
Function
Description:
Group B - This pump is in standby systems that are not operated routinely except for testing.The EECW section of the RBCCWS consists of two redundant full-capacity loops, each with two (2) 100 percent capacity heat exchangers, pump, and makeup pump and tank. The EECW (Division I and Division II) system makeup tank is connected with a makeup line to the EESW system to provide an alternate makeup supply for each division when the normal makeup supply to this tank is lost during and after the design basis accident. The isolation valves for the alternate makeup supply consist of a check valve and an air-operated valve which opens automatically on a makeup pump start, a loss of air or a loss of electrical power. Each makeup pump auto starts and provides the makeup water to the tank. [UFSAR 9.2.2.2] The EECW makeup pump in each division provides sufficient developed head to supply makeup water at a controlled pressure to its makeup tank during emergency conditions. [DBD P44-00 Section 3.2.1.2]An EECW/EESW subsystem is considered OPERABLE when it has an OPERABLE EECW pump, an OPERABLE EESW pump, and OPERABLE EECW/EESW heat exchanger, an OPERABLE EECW makeup tank, an OPERABLE EECW makeup pump, and OPERABLE flow paths to provide cooling water flow to the supported equipment and reject the heat to the division's RHR reservoir. [TS B 3.7.2]
Design Basis Limits: DBD P44-00 Section 3.2.1.2EECW Makeup Pump Parameters[Nominal (nameplate) unless otherwise indicated.]Pump:Capacity, gpm equal to 20TDH (at capacity flow rate), ft equal to 60NPSHA, ft equal to 97NPSHR, equal to 2Shutoff head, ft equal to 60Maximum allowable degradation, ft (10%) equal to 6Horsepower, hp equal to 3Speed, rpm equal to 1750Design pressure, psig equal to 120Design temperature, degree F equal to 125Material (pressure boundary) equal to Cast Carbon Steel (A216, WCB)Motor:Horsepower, hp equal to 3Design required horsepower at maximum system flow rate of 90 gpm, hp equal to 2.OSpeed, rpm equal to 1760Voltage, volts equal to 460Frame equal to 182TService factor equal to 1.15 Design
References:
TS 3.7.2 Emergency Equipment Cooling Water (EECW)/Emergency Equipment Service Water (EESW) System and Ultimate Heat SinkTS B 3.7.2 Emergency Equipment Cooling Water (EECW)/Emergency Equipment Service Water (EESW) System and Ultimate Heat SinkUFSAR 7.1.2.1.18 Emergency Equipment Cooling Water SystemUFSAR 9.2.2 Cooling System for Reactor AuxiliariesDBD P44-00, Rev G, Emergency Equipment Cooling Water (EECW) System Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 41 of 106
Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 43 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes Appendix V Basis: OM Code Appendix V paragraph V-3000(a) Requirement: The Owner shall (a) identify those certain applicable pumps with specific design basis accident flow rates in the Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) for inclusion in this program.This pump has been deemed not applicable to Appendix V. There are no specified TS or UFSAR requirements specific to pump design basis accident flow rates. DBD P44-00 refers to EECW Makeup Pump Parameters but states those values are nominal (nameplate) unless otherwise indicated.
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 42 of 106
DTIE E ergy-Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 44 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes P4500C002A P4500 Emergency Equip Service Water South Pump 5706-3/G-3 A 3 Vertical Line Shaft dP 2Y 24.208.02 PRR-003 Q 2Y 24.208.02 V 2Y 24.208.02 PRR-002 Standard Code ISTB dP Q 24.208.02 PRR-003 Q Q 24.208.02 V Q 24.208.02 PRR-002 Safety Function Basis: The EESWS pumps are two staged, motor-driven, vertical pumps. The pump has a safety function to provide a minimum of 1600 gpm flow at a design pressure of 125 psig to the EECW heat exchangers in the reactor building. EESWS is designed to provide a cooling water source for the EECWS. The system functions only during a loss of offsite power, high drywell pressure, or upon failure of the RBCCWS. The safety-related pumps are designated QA Level I, seismic Category I, and are designed to ASME Section III, Class 3 requirements. [DBD P45-00 Section 4.2.1] If the General Service Water (GWS) system becomes inoperative, the emergency equipment service water system (EESWS) takes over through the emergency equipment cooling water system (EECWS). [UFSAR 9.2.1.3]Sufficient water inventory is available for all UHS supported post LOCA cooling requirements for a 7 day period with no additional makeup water source available. The ability of the Ultimate Heat Sink and associated service/cooling water systems to support long term cooling of the reactor containment is assumed in evaluations of the equipment required for safe reactor shutdown. [TS B 3.7.2] The EECW/EESW System provides cooling water for the removal of heat from equipment, such as residual heat removal (RHR) and Core Spray (CS), pump coolers, and room coolers for Emergency Core Cooling System and other safety-related equipment, required for a safe reactor shutdown following a Design Basis Accident (DBA) or transient. One subsystem of EECW/EESW is required to provide the minimum heat removal capability assumed in the safety analysis for the system to which it supplies cooling water. [TS B 3.7.2] In the event of a mechanical failure of the RBCCWS, high drywell pressure, or upon loss of offsite electrical power, the EECWS with start automatically (or may be manually initiated) to cool equipment for reactor shutdown. In addition, the EESWS may be used to augment RBCCW for the purpose of assisting in equipment cooling. The EECWS is cooled by the EESWS which is supplied by the RHR reservoir. [UFSAR 9.2.2]The instrumentation and control of the emergency equipment cooling water (EECW) system is designed to initiate and maintain operation of the EECW system automatically when normal operation of the reactor building closed cooling water (RBCCW) system is impaired (as indicated by a low differential header pressure), high drywell pressure is experienced, or upon loss of offsite ac power. The controls are provided to start operation of the pumps of both loops to establish flow of the emergency equipment service water (EESW) system. [UFSAR 7.1.2.1.18]
Function
Description:
Group A - This pump operates continuously or routinely during normal operation, cold shutdown, or refueling operations.The EECW/EESW System is designed to provide cooling water for the removal of heat from equipment, such as residual heat removal (RHR) and Core Spray (CS), pump coolers, and room coolers for Emergency Core Cooling System and other safety-related equipment, required for a safe reactor shutdown following a Design Basis Accident (DBA) or transient. The EESW subsystem contains a single 1600 gpm nominal capacity pump that pumps from the division's RHR Reservoir through the EECW subsystem's heat exchanger and returns to the RHR Reservoir. Each EESW subsystem functions to cool the associated EECW subsystem. The EESW pump automatically starts on the same actuation signals as the EECW System. The two EECW/EESW subsystems are separated from each other so that failure of one subsystem will not affect the operability of the other subsystem. [TS B 3.7.2] The EESW system also provides an emergency source of water to the EECW makeup tanks for makeup and pressurization needs. [DBD P45-00 Section 2.2.1] The system functions only during a loss of offsite power, high drywell pressure, or upon failure of the RBCCWS.
[UFSAR 9.2.5.1]The ultimate heat sink is provided by the RHR complex, which contains the RHR service water (RHRSW) system, the EESWS, the diesel generator service water system, the mechanical draft cooling towers, the emergency ac power system (diesel generators), and the reservoir. [UFSAR 9.2.5]
Design Basis Limits: [DBD P45-00 Section 4.2.1]Component Parameters[Nominal (nameplate) unless otherwise indicated]Pump:Capacity equal to 1600 gpmMinimum flow equal to 200 gpm *
[K05026]TDH at capacity flow rate equal to 145 ftNPSHA at minimum RHR reservoir level (564 ft ASL) equal to 41.2 ftNPSHR at maximum system flow rate of 2263 gpm equal to 32.0 ftMinimum Submergence (rel. to 552.4 ft ASL datum) equal to 2.5 ft @ 1600 gpmShutoff head equal to 265 ftMaximum allowable pump degradation ft - See Discussion**Horsepower equal to 100 hpSpeed equal to 1775 rpmDesign pressure equal to 125 psigDesign temperature equal to 100 degrees FMaterial (pressure boundary) Carbon Steel* Refer to Section 4.1.2.4 of this Design Basis Document for discussion on minimum flow protection.** The EESW pump is required to supply greater than 1350 gpm during peak post-accident emergency modes of operation.
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 43 of 106
Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 45 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes Design
References:
TS 3.7.2 Emergency Equipment Cooling Water (EECW/Emergency Equipment Service Water (EESW) System and Ultimate Heat Sink (UHS)TS B 3.7.2 Emergency Equipment Cooling Water (EECW/Emergency Equipment Service Water (EESW) System and Ultimate Heat Sink (UHS)UFSAR 7.1.2.1.18 Emergency Equipment Cooling Water SystemUFSAR 9.2.5, Ultimate Heat SinkDBD P45-00, Rev. C, Emergency Equipment Service Water System Design Basis Document Appendix V Basis: OM Code Appendix V paragraph V-3000(a) Requirement: The Owner shall (a) identify those certain applicable pumps with specific design basis accident flow rates in the Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) for inclusion in this program.This pump has been deemed not applicable to Appendix V. There are no specified TS or UFSAR requirements specific to pump design basis accident flow rates. DBD P45-00 refers to EESW Pump Parameters but states those values are nominal (nameplate) unless otherwise indicated.
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 44 of 106
I VFermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 46 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes P4500C002B P4500 Emergency Equip Service Water North Pump 5706-3/G-6 A 3 Vertical Line Shaft dP 2Y 24.208.03 PRR-003 Q 2Y 24.208.03 V 2Y 24.208.03 PRR-002 Standard Code ISTB dP Q 24.208.03 PRR-003 Q Q 24.208.03 V Q 24.208.03 PRR-002 Safety Function Basis: The EESWS pumps are two staged, motor-driven, vertical pumps. The pump has a safety function to provide a minimum of 1600 gpm flow at a design pressure of 125 psig to the EECW heat exchangers in the reactor building. EESWS is designed to provide a cooling water source for the EECWS. The system functions only during a loss of offsite power, high drywell pressure, or upon failure of the RBCCWS. The safety-related pumps are designated QA Level I, seismic Category I, and are designed to ASME Section III, Class 3 requirements. [DBD P45-00 Section 4.2.1] If the General Service Water (GWS) system becomes inoperative, the emergency equipment service water system (EESWS) takes over through the emergency equipment cooling water system (EECWS). [UFSAR 9.2.1.3]Sufficient water inventory is available for all UHS supported post LOCA cooling requirements for a 7 day period with no additional makeup water source available. The ability of the Ultimate Heat Sink and associated service/cooling water systems to support long term cooling of the reactor containment is assumed in evaluations of the equipment required for safe reactor shutdown. [TS B 3.7.2] The EECW/EESW System provides cooling water for the removal of heat from equipment, such as residual heat removal (RHR) and Core Spray (CS), pump coolers, and room coolers for Emergency Core Cooling System and other safety-related equipment, required for a safe reactor shutdown following a Design Basis Accident (DBA) or transient. One subsystem of EECW/EESW is required to provide the minimum heat removal capability assumed in the safety analysis for the system to which it supplies cooling water. [TS B 3.7.2] In the event of a mechanical failure of the RBCCWS, high drywell pressure, or upon loss of offsite electrical power, the EECWS with start automatically (or may be manually initiated) to cool equipment for reactor shutdown. In addition, the EESWS may be used to augment RBCCW for the purpose of assisting in equipment cooling. The EECWS is cooled by the EESWS which is supplied by the RHR reservoir. [UFSAR 9.2.2]The instrumentation and control of the emergency equipment cooling water (EECW) system is designed to initiate and maintain operation of the EECW system automatically when normal operation of the reactor building closed cooling water (RBCCW) system is impaired (as indicated by a low differential header pressure), high drywell pressure is experienced, or upon loss of offsite ac power. The controls are provided to start operation of the pumps of both loops to establish flow of the emergency equipment service water (EESW) system. [UFSAR 7.1.2.1.18]
Function
Description:
Group A - This pump operates continuously or routinely during normal operation, cold shutdown, or refueling operations.The EECW/EESW System is designed to provide cooling water for the removal of heat from equipment, such as residual heat removal (RHR) and Core Spray (CS), pump coolers, and room coolers for Emergency Core Cooling System and other safety-related equipment, required for a safe reactor shutdown following a Design Basis Accident (DBA) or transient. The EESW subsystem contains a single 1600 gpm nominal capacity pump that pumps from the division's RHR Reservoir through the EECW subsystem's heat exchanger and returns to the RHR Reservoir. Each EESW subsystem functions to cool the associated EECW subsystem. The EESW pump automatically starts on the same actuation signals as the EECW System. The two EECW/EESW subsystems are separated from each other so that failure of one subsystem will not affect the operability of the other subsystem. [TS B 3.7.2] The EESW system also provides an emergency source of water to the EECW makeup tanks for makeup and pressurization needs. [DBD P45-00 Section 2.2.1] The system functions only during a loss of offsite power, high drywell pressure, or upon failure of the RBCCWS.
[UFSAR 9.2.5.1]The ultimate heat sink is provided by the RHR complex, which contains the RHR service water (RHRSW) system, the EESWS, the diesel generator service water system, the mechanical draft cooling towers, the emergency ac power system (diesel generators), and the reservoir. [UFSAR 9.2.5]
Design Basis Limits: [DBD P45-00 Section 4.2.1]Component Parameters[Nominal (nameplate) unless otherwise indicated]Pump:Capacity equal to 1600 gpmMinimum flow equal to 200 gpm *
[K05026]TDH at capacity flow rate equal to 145 ftNPSHA at minimum RHR reservoir level (564 ft ASL) equal to 41.2 ftNPSHR at maximum system flow rate of 2263 gpm equal to 32.0 ftMinimum Submergence (rel. to 552.4 ft ASL datum) equal to 2.5 ft @ 1600 gpmShutoff head equal to 265 ftMaximum allowable pump degradation ft - See Discussion**Horsepower equal to 100 hpSpeed equal to 1775 rpmDesign pressure equal to 125 psigDesign temperature equal to 100 degrees FMaterial (pressure boundary) Carbon Steel* Refer to Section 4.1.2.4 of this Design Basis Document for discussion on minimum flow protection.** The EESW pump is required to supply greater than 1350 gpm during peak post-accident emergency modes of operation.
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 45 of 106
-g a Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 47 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes Design
References:
TS 3.7.2 Emergency Equipment Cooling Water (EECW/Emergency Equipment Service Water (EESW) System and Ultimate Heat Sink (UHS)TS B 3.7.2 Emergency Equipment Cooling Water (EECW/Emergency Equipment Service Water (EESW) System and Ultimate Heat Sink (UHS)UFSAR 7.1.2.1.18 Emergency Equipment Cooling Water SystemUFSAR 9.2.5, Ultimate Heat SinkDBD P45-00, Rev. C, Emergency Equipment Service Water System Design Basis Document Appendix V Basis: OM Code Appendix V paragraph V-3000(a) Requirement: The Owner shall (a) identify those certain applicable pumps with specific design basis accident flow rates in the Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) for inclusion in this program.This pump has been deemed not applicable to Appendix V. There are no specified TS or UFSAR requirements specific to pump design basis accident flow rates. DBD P45-00 refers to EESW Pump Parameters but states those values are nominal (nameplate) unless otherwise indicated.
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 46 of 106
DI e-- Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 48 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3000C001 R3000 EDG 11 Diesel Fuel Oil Xfer Pump A 5734/F-8 B 3 Positive Displacement P 2Y 24.307.34 Q 2Y 24.307.34 V 2Y 24.307.34 PRR-002 Standard Code ISTB P Q 24.307.34 Q Q 24.307.34 V Q 24.307.34 PRR-002 Safety Function Basis: The diesel generator fuel-oil storage and transfer system is designed to perform its operational function automatically during emergency conditions. Each diesel generator is furnished with an individual fuel-oil storage tank. [UFSAR 9.5.4] The fuel oil transfer pumps operate automatically in order to maintain an adequate volume of fuel oil in the day tank during or following EDG testing. [TS B 3.8.1] A full day tank provides more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of fuel supply to each EDG. One transfer pump is started automatically when the respective EDG starts. The low level switch starts the second fuel oil transfer pump when the level is below the setpoint to maintain the minimum amount of fuel oil required by the Technical Specifications. [DBD R30-00 Section 4.1.7.2]Two redundant motor-driven fuel-oil transfer pumps deliver fuel to the day tank. Fuel flows by gravity from the day tank to the suction of the engine-driven fuel pump. The day tank is kept full, and, as required, one of the transfer pumps automatically operates (with the other pump in standby) to maintain the tank level. [UFSAR 9.5.4.2] Each transfer pump has a rated flow of 7.5 gpm (required flow to meet EDG fuel consumption requirement of 3.5 gpm). [DBD R30-00 Section 4.2.5.3]
Function
Description:
Group B - This pump is in standby systems that are not operated routinely except for testing.The diesel generator fuel-oil storage and transfer system is designed to perform its operational function automatically during emergency conditions. Each diesel generator is furnished with an individual fuel-oil storage tank. [UFSAR 9.5.4] The design of the fuel transfer systems is such that pumps operate automatically in order to maintain an adequate volume of fuel oil in the day tank during or following EDG testing. [TS B 3.8.1] The EDG Fuel Oil Subsystem associated with each EDG shall be operable with each EDG Fuel Oil Subsystem comprised of; (1) A separate day fuel tank containing a minimum of 210 gallons of fuel; (2) A separate fuel storage tank containing a minimum of 35,280 gallons of fuel, and (3) A separate fuel transfer pump. [DBD R30-00 Section 4.1.2.4 EDG Fuel Oil Subsystem]
Design Basis Limits: DBD R30-00 Section 4.2.5.3 Component RequirementsTransfer Pump Rated Flow (for each pump):7.5 GPM (Required flow to meet EDG fuel consumption requirement of 3.5 GPMPower Supply: 480V AC essential (for safety related FO Transfer Pumps, and non-safety related Standby pumps isolated from Class 1E MCCs that provide power)TS SR 3.8.1.6 -
Verify each fuel oil transfer system operates to automatically transfer fuel oil from storage tanks to the day tanks.This surveillance demonstrates that each required fuel oil transfer pump operates and transfers fuel oil from its associated storage tank to its associated day tank. It is required to support continuous operation of standby power sources. This surveillance provides assurance that the fuel oil transfer pump is operable, the fuel oil piping system is intact, the fuel delivery piping is not obstructed, and the controls and control systems for automatic fuel transfer systems is operable. The design of the fuel transfer systems is such that pumps operate automatically in order to maintain an adequate volume of fuel oil in the day tank during or following EDG testing. [TS B 3.8.1 Surveillance Requirements SR 3.8.1.6]Criterion 17 Conformance - The Fermi 2 onsite power system has four separate emergency diesel generators (EDGs), each of which supplies a separate bus. There are two independent and redundant divisions of ESF, each of which can be powered by a division pair of the EDGs through their associated buses. The diesel generators are of sufficient capacity to provide minimum essential emergency loads, including a single failure, such as the loss of a diesel generator or essential bus. The diesel generators are located in a Category I structure with fire-barrier separation between diesel generators. [UFSAR Section 3.1.2.2.8 Criterion 17 - Electric Power Systems]The system complies with Appendix B of ANSI Standard N195-1976, "Fuel Oil System for Standby Diesel Generators" and is designed to Category I requirements. The system piping and as much equipment as practicable are designed to either ASME B&PV Code Section III, Class 3 or the Diesel Manufacturers Association (DEMA) standards as shown in Figures 9.5-4, 9.5-5 and 9.5-6.
The diesel generator fuel-oil storage and transfer system for each diesel generator is separate and is located in separate compartments. The system is housed in the RHR complex, and, as such, is protected from flooding, tornado winds, and missiles. Adequate fire protection is provided and fire walls separate each compartment containing the individual diesel generator and its associated systems. [UFSAR 9.5.4.1 Design Basis]The diesel generator fuel oil system is classified as QA Level I and Seismic Category I. All off-skid piping and components of the fuel oil system are classified as Class 3 and are designed and constructed to Subsection ND of the ASME Code,Section III, and all addenda to and including Summer 1973, with the exception of the fuel oil transfer pumps. The fuel oil transfer pumps were upgraded to include hydrostatic tests with test reports and certificates of material conformance. [DBD R30-00 Section 2.3 Classification]
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 47 of 106
Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 49 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes Design
References:
TS 3.8.1 AC Sources - OperatingTS B 3.8.1 AC Sources - OperatingTS SR 3.8.1.6UFSAR 3.1.2.2.8 Criterion 17 - Electric Power SystemsUFSAR 9.5.4 Diesel Generator Fuel-Oil Storage and Transfer SystemDBD R30-00, Rev. H, Emergency Diesel Generator Appendix V Basis: OM Code Appendix V paragraph V-3000(a) Requirement: The Owner shall (a) identify those certain applicable pumps with specific design basis accident flow rates in the Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) for inclusion in this program.This pump has been deemed not applicable to Appendix V. There are no specified TS or UFSAR requirements specific to pump design basis accident flow rates. DBD R30-00 refers to a Transfer Pump rating of required 7.5 gpm flow to meet EDG fuel consumption requirement of 3.5 gpm. The NRC has stated that specific pump design basis values in other plant documents other than technical specifications, technical requirements program, or updated safety analysis report are not subject to Appendix V testing.
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 48 of 106
a n -n r Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 50 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3000C002 R3000 EDG 12 Diesel Fuel Oil Xfer Pump A 5734/F-8 B 3 Positive Displacement P 2Y 24.307.35 Q 2Y 24.307.35 V 2Y 24.307.35 PRR-002 Standard Code ISTB P Q 24.307.35 Q Q 24.307.35 V Q 24.307.35 PRR-002 Safety Function Basis: The diesel generator fuel-oil storage and transfer system is designed to perform its operational function automatically during emergency conditions. Each diesel generator is furnished with an individual fuel-oil storage tank. [UFSAR 9.5.4] The fuel oil transfer pumps operate automatically in order to maintain an adequate volume of fuel oil in the day tank during or following EDG testing. [TS B 3.8.1] A full day tank provides more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of fuel supply to each EDG. One transfer pump is started automatically when the respective EDG starts. The low level switch starts the second fuel oil transfer pump when the level is below the setpoint to maintain the minimum amount of fuel oil required by the Technical Specifications. [DBD R30-00 Section 4.1.7.2]Two redundant motor-driven fuel-oil transfer pumps deliver fuel to the day tank. Fuel flows by gravity from the day tank to the suction of the engine-driven fuel pump. The day tank is kept full, and, as required, one of the transfer pumps automatically operates (with the other pump in standby) to maintain the tank level. [UFSAR 9.5.4.2] Each transfer pump has a rated flow of 7.5 gpm (required flow to meet EDG fuel consumption requirement of 3.5 gpm). [DBD R30-00 Section 4.2.5.3]
Function
Description:
Group B - This pump is in standby systems that are not operated routinely except for testing.The diesel generator fuel-oil storage and transfer system is designed to perform its operational function automatically during emergency conditions. Each diesel generator is furnished with an individual fuel-oil storage tank. [UFSAR 9.5.4] The design of the fuel transfer systems is such that pumps operate automatically in order to maintain an adequate volume of fuel oil in the day tank during or following EDG testing. [TS B 3.8.1] The EDG Fuel Oil Subsystem associated with each EDG shall be operable with each EDG Fuel Oil Subsystem comprised of; (1) A separate day fuel tank containing a minimum of 210 gallons of fuel; (2) A separate fuel storage tank containing a minimum of 35,280 gallons of fuel, and (3) A separate fuel transfer pump. [DBD R30-00 Section 4.1.2.4 EDG Fuel Oil Subsystem]
Design Basis Limits: DBD R30-00 Section 4.2.5.3 Component RequirementsTransfer Pump Rated Flow (for each pump):7.5 GPM (Required flow to meet EDG fuel consumption requirement of 3.5 GPMPower Supply: 480V AC essential (for safety related FO Transfer Pumps, and non-safety related Standby pumps isolated from Class 1E MCCs that provide power)TS SR 3.8.1.6 -
Verify each fuel oil transfer system operates to automatically transfer fuel oil from storage tanks to the day tanks. This surveillance demonstrates that each required fuel oil transfer pump operates and transfers fuel oil from its associated storage tank to its associated day tank. It is required to support continuous operation of standby power sources. This surveillance provides assurance that the fuel oil transfer pump is operable, the fuel oil piping system is intact, the fuel delivery piping is not obstructed, and the controls and control systems for automatic fuel transfer systems is operable. The design of the fuel transfer systems is such that pumps operate automatically in order to maintain an adequate volume of fuel oil in the day tank during or following EDG testing. [TS B 3.8.1 Surveillance Requirements SR 3.8.1.6]Criterion 17 Conformance - The Fermi 2 onsite power system has four separate emergency diesel generators (EDGs), each of which supplies a separate bus. There are two independent and redundant divisions of ESF, each of which can be powered by a division pair of the EDGs through their associated buses. The diesel generators are of sufficient capacity to provide minimum essential emergency loads, including a single failure, such as the loss of a diesel generator or essential bus. The diesel generators are located in a Category I structure with fire-barrier separation between diesel generators. [UFSAR Section 3.1.2.2.8 Criterion 17 - Electric Power Systems]The system complies with Appendix B of ANSI Standard N195-1976, "Fuel Oil System for Standby Diesel Generators" and is designed to Category I requirements. The system piping and as much equipment as practicable are designed to either ASME B&PV Code Section III, Class 3 or the Diesel Manufacturers Association (DEMA) standards as shown in Figures 9.5-4, 9.5-5 and 9.5-6.
The diesel generator fuel-oil storage and transfer system for each diesel generator is separate and is located in separate compartments. The system is housed in the RHR complex, and, as such, is protected from flooding, tornado winds, and missiles. Adequate fire protection is provided and fire walls separate each compartment containing the individual diesel generator and its associated systems. [UFSAR 9.5.4.1 Design Basis]The diesel generator fuel oil system is classified as QA Level I and Seismic Category I. All off-skid piping and components of the fuel oil system are classified as Class 3 and are designed and constructed to Subsection ND of the ASME Code,Section III, and all addenda to and including Summer 1973, with the exception of the fuel oil transfer pumps. The fuel oil transfer pumps were upgraded to include hydrostatic tests with test reports and certificates of material conformance. [DBD R30-00 Section 2.3 Classification]
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 49 of 106
.70W an mFermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 51 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes Design
References:
TS 3.8.1 AC Sources - OperatingTS B 3.8.1 AC Sources - OperatingTS SR 3.8.1.6UFSAR 3.1.2.2.8 Criterion 17 - Electric Power SystemsUFSAR 9.5.4 Diesel Generator Fuel-Oil Storage and Transfer SystemDBD R30-00, Rev. H, Emergency Diesel Generator Appendix V Basis: OM Code Appendix V paragraph V-3000(a) Requirement: The Owner shall (a) identify those certain applicable pumps with specific design basis accident flow rates in the Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) for inclusion in this program.This pump has been deemed not applicable to Appendix V. There are no specified TS or UFSAR requirements specific to pump design basis accident flow rates. DBD R30-00 refers to a Transfer Pump rating of required 7.5 gpm flow to meet EDG fuel consumption requirement of 3.5 gpm. The NRC has stated that specific pump design basis values in other plant documents other than technical specifications, technical requirements program, or updated safety analysis report are not subject to Appendix V testing.
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 50 of 106
DTIE ergFermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 52 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3000C003 R3000 EDG 11 Diesel Fuel Oil Xfer Pump B 5734/E-8 B 3 Positive Displacement P 2Y 24.307.34 Q 2Y 24.307.34 V 2Y 24.307.34 PRR-002 Standard Code ISTB P Q 24.307.34 Q Q 24.307.34 V Q 24.307.34 PRR-002 Safety Function Basis: The diesel generator fuel-oil storage and transfer system is designed to perform its operational function automatically during emergency conditions. Each diesel generator is furnished with an individual fuel-oil storage tank. [UFSAR 9.5.4] The fuel oil transfer pumps operate automatically in order to maintain an adequate volume of fuel oil in the day tank during or following EDG testing. [TS B 3.8.1] A full day tank provides more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of fuel supply to each EDG. One transfer pump is started automatically when the respective EDG starts. The low level switch starts the second fuel oil transfer pump when the level is below the setpoint to maintain the minimum amount of fuel oil required by the Technical Specifications. [DBD R30-00 Section 4.1.7.2]Two redundant motor-driven fuel-oil transfer pumps deliver fuel to the day tank. Fuel flows by gravity from the day tank to the suction of the engine-driven fuel pump. The day tank is kept full, and, as required, one of the transfer pumps automatically operates (with the other pump in standby) to maintain the tank level. [UFSAR 9.5.4.2] Each transfer pump has a rated flow of 7.5 gpm (required flow to meet EDG fuel consumption requirement of 3.5 gpm). [DBD R30-00 Section 4.2.5.3]
Function
Description:
Group B - This pump is in standby systems that are not operated routinely except for testing.The diesel generator fuel-oil storage and transfer system is designed to perform its operational function automatically during emergency conditions. Each diesel generator is furnished with an individual fuel-oil storage tank. [UFSAR 9.5.4] The design of the fuel transfer systems is such that pumps operate automatically in order to maintain an adequate volume of fuel oil in the day tank during or following EDG testing. [TS B 3.8.1] The EDG Fuel Oil Subsystem associated with each EDG shall be operable with each EDG Fuel Oil Subsystem comprised of; (1) A separate day fuel tank containing a minimum of 210 gallons of fuel; (2) A separate fuel storage tank containing a minimum of 35,280 gallons of fuel, and (3) A separate fuel transfer pump. [DBD R30-00 Section 4.1.2.4 EDG Fuel Oil Subsystem]
Design Basis Limits: DBD R30-00 Section 4.2.5.3 Component RequirementsTransfer Pump Rated Flow (for each pump):7.5 GPM (Required flow to meet EDG fuel consumption requirement of 3.5 GPMPower Supply: 480V AC essential (for safety related FO Transfer Pumps, and non-safety related Standby pumps isolated from Class 1E MCCs that provide power)TS SR 3.8.1.6 -
Verify each fuel oil transfer system operates to automatically transfer fuel oil from storage tanks to the day tanks.. This surveillance demonstrates that each required fuel oil transfer pump operates and transfers fuel oil from its associated storage tank to its associated day tank. It is required to support continuous operation of standby power sources. This surveillance provides assurance that the fuel oil transfer pump is operable, the fuel oil piping system is intact, the fuel delivery piping is not obstructed, and the controls and control systems for automatic fuel transfer systems is operable. The design of the fuel transfer systems is such that pumps operate automatically in order to maintain an adequate volume of fuel oil in the day tank during or following EDG testing. [TS B 3.8.1 Surveillance Requirements SR 3.8.1.6]Criterion 17 Conformance - The Fermi 2 onsite power system has four separate emergency diesel generators (EDGs), each of which supplies a separate bus. There are two independent and redundant divisions of ESF, each of which can be powered by a division pair of the EDGs through their associated buses. The diesel generators are of sufficient capacity to provide minimum essential emergency loads, including a single failure, such as the loss of a diesel generator or essential bus. The diesel generators are located in a Category I structure with fire-barrier separation between diesel generators. [UFSAR Section 3.1.2.2.8 Criterion 17 - Electric Power Systems]The system complies with Appendix B of ANSI Standard N195-1976, "Fuel Oil System for Standby Diesel Generators" and is designed to Category I requirements. The system piping and as much equipment as practicable are designed to either ASME B&PV Code Section III, Class 3 or the Diesel Manufacturers Association (DEMA) standards as shown in Figures 9.5-4, 9.5-5 and 9.5-6.
The diesel generator fuel-oil storage and transfer system for each diesel generator is separate and is located in separate compartments. The system is housed in the RHR complex, and, as such, is protected from flooding, tornado winds, and missiles. Adequate fire protection is provided and fire walls separate each compartment containing the individual diesel generator and its associated systems. [UFSAR 9.5.4.1 Design Basis]The diesel generator fuel oil system is classified as QA Level I and Seismic Category I. All off-skid piping and components of the fuel oil system are classified as Class 3 and are designed and constructed to Subsection ND of the ASME Code,Section III, and all addenda to and including Summer 1973, with the exception of the fuel oil transfer pumps. The fuel oil transfer pumps were upgraded to include hydrostatic tests with test reports and certificates of material conformance. [DBD R30-00 Section 2.3 Classification]
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 51 of 106
Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 53 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes Design
References:
TS 3.8.1 AC Sources - OperatingTS B 3.8.1 AC Sources - OperatingTS SR 3.8.1.6UFSAR 3.1.2.2.8 Criterion 17 - Electric Power SystemsUFSAR 9.5.4 Diesel Generator Fuel-Oil Storage and Transfer SystemDBD R30-00, Rev. H, Emergency Diesel Generator Appendix V Basis: OM Code Appendix V paragraph V-3000(a) Requirement: The Owner shall (a) identify those certain applicable pumps with specific design basis accident flow rates in the Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) for inclusion in this program.This pump has been deemed not applicable to Appendix V. There are no specified TS or UFSAR requirements specific to pump design basis accident flow rates. DBD R30-00 refers to a Transfer Pump rating of required 7.5 gpm flow to meet EDG fuel consumption requirement of 3.5 gpm. The NRC has stated that specific pump design basis values in other plant documents other than technical specifications, technical requirements program, or updated safety analysis report are not subject to Appendix V testing.
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 52 of 106
Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 54 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3000C004 R3000 EDG 12 Diesel Fuel Oil Xfer Pump B 5734/E-8 B 3 Positive Displacement P 2Y 24.307.35 Q 2Y 24.307.35 V 2Y 24.307.35 PRR-002 Standard Code ISTB P Q 24.307.35 Q Q 24.307.35 V Q 24.307.35 PRR-002 Safety Function Basis: The diesel generator fuel-oil storage and transfer system is designed to perform its operational function automatically during emergency conditions. Each diesel generator is furnished with an individual fuel-oil storage tank. [UFSAR 9.5.4] The fuel oil transfer pumps operate automatically in order to maintain an adequate volume of fuel oil in the day tank during or following EDG testing. [TS B 3.8.1] A full day tank provides more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of fuel supply to each EDG. One transfer pump is started automatically when the respective EDG starts. The low level switch starts the second fuel oil transfer pump when the level is below the setpoint to maintain the minimum amount of fuel oil required by the Technical Specifications. [DBD R30-00 Section 4.1.7.2]Two redundant motor-driven fuel-oil transfer pumps deliver fuel to the day tank. Fuel flows by gravity from the day tank to the suction of the engine-driven fuel pump. The day tank is kept full, and, as required, one of the transfer pumps automatically operates (with the other pump in standby) to maintain the tank level. [UFSAR 9.5.4.2] Each transfer pump has a rated flow of 7.5 gpm (required flow to meet EDG fuel consumption requirement of 3.5 gpm). [DBD R30-00 Section 4.2.5.3]
Function
Description:
Group B - This pump is in standby systems that are not operated routinely except for testing.The diesel generator fuel-oil storage and transfer system is designed to perform its operational function automatically during emergency conditions. Each diesel generator is furnished with an individual fuel-oil storage tank. [UFSAR 9.5.4] The design of the fuel transfer systems is such that pumps operate automatically in order to maintain an adequate volume of fuel oil in the day tank during or following EDG testing. [TS B 3.8.1] The EDG Fuel Oil Subsystem associated with each EDG shall be operable with each EDG Fuel Oil Subsystem comprised of; (1) A separate day fuel tank containing a minimum of 210 gallons of fuel; (2) A separate fuel storage tank containing a minimum of 35,280 gallons of fuel, and (3) A separate fuel transfer pump. [DBD R30-00 Section 4.1.2.4 EDG Fuel Oil Subsystem]
Design Basis Limits: DBD R30-00 Section 4.2.5.3 Component RequirementsTransfer Pump Rated Flow (for each pump):7.5 GPM (Required flow to meet EDG fuel consumption requirement of 3.5 GPMPower Supply: 480V AC essential (for safety related FO Transfer Pumps, and non-safety related Standby pumps isolated from Class 1E MCCs that provide power)TS SR 3.8.1.6 -
Verify each fuel oil transfer system operates to automatically transfer fuel oil from storage tanks to the day tanks. This surveillance demonstrates that each required fuel oil transfer pump operates and transfers fuel oil from its associated storage tank to its associated day tank. It is required to support continuous operation of standby power sources. This surveillance provides assurance that the fuel oil transfer pump is operable, the fuel oil piping system is intact, the fuel delivery piping is not obstructed, and the controls and control systems for automatic fuel transfer systems is operable. The design of the fuel transfer systems is such that pumps operate automatically in order to maintain an adequate volume of fuel oil in the day tank during or following EDG testing. [TS B 3.8.1 Surveillance Requirements SR 3.8.1.6))Criterion 17 Conformance - The Fermi 2 onsite power system has four separate emergency diesel generators (EDGs), each of which supplies a separate bus. There are two independent and redundant divisions of ESF, each of which can be powered by a division pair of the EDGs through their associated buses. The diesel generators are of sufficient capacity to provide minimum essential emergency loads, including a single failure, such as the loss of a diesel generator or essential bus. The diesel generators are located in a Category I structure with fire-barrier separation between diesel generators. [UFSAR Section 3.1.2.2.8 Criterion 17 - Electric Power Systems]The system complies with Appendix B of ANSI Standard N195-1976, "Fuel Oil System for Standby Diesel Generators" and is designed to Category I requirements. The system piping and as much equipment as practicable are designed to either ASME B&PV Code Section III, Class 3 or the Diesel Manufacturers Association (DEMA) standards as shown in Figures 9.5-4, 9.5-5 and 9.5-6.
The diesel generator fuel-oil storage and transfer system for each diesel generator is separate and is located in separate compartments. The system is housed in the RHR complex, and, as such, is protected from flooding, tornado winds, and missiles. Adequate fire protection is provided and fire walls separate each compartment containing the individual diesel generator and its associated systems. [UFSAR 9.5.4.1 Design Basis]The diesel generator fuel oil system is classified as QA Level I and Seismic Category I. All off-skid piping and components of the fuel oil system are classified as Class 3 and are designed and constructed to Subsection ND of the ASME Code,Section III, and all addenda to and including Summer 1973, with the exception of the fuel oil transfer pumps. The fuel oil transfer pumps were upgraded to include hydrostatic tests with test reports and certificates of material conformance. [DBD R30-00 Section 2.3 Classification]
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 53 of 106
- Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 55 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes Design
References:
TS 3.8.1 AC Sources - OperatingTS B 3.8.1 AC Sources - OperatingTS SR 3.8.1.6UFSAR 3.1.2.2.8 Criterion 17 - Electric Power SystemsUFSAR 9.5.4 Diesel Generator Fuel-Oil Storage and Transfer SystemDBD R30-00, Rev. H, Emergency Diesel Generator Appendix V Basis: OM Code Appendix V paragraph V-3000(a) Requirement: The Owner shall (a) identify those certain applicable pumps with specific design basis accident flow rates in the Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) for inclusion in this program.This pump has been deemed not applicable to Appendix V. There are no specified TS or UFSAR requirements specific to pump design basis accident flow rates. DBD R30-00 refers to a Transfer Pump rating of required 7.5 gpm flow to meet EDG fuel consumption requirement of 3.5 gpm. The NRC has stated that specific pump design basis values in other plant documents other than technical specifications, technical requirements program, or updated safety analysis report are not subject to Appendix V testing.
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 54 of 106
- D rFermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 56 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3000C009 R3000 EDG 13 Diesel Fuel Oil Xfer Pump A 5734/F-8 B 3 Positive Displacement P 2Y 24.307.36 Q 2Y 24.307.36 V 2Y 24.307.36 PRR-002 Standard Code ISTB P Q 24.307.36 Q Q 24.307.36 V Q 24.307.36 PRR-002 Safety Function Basis: The diesel generator fuel-oil storage and transfer system is designed to perform its operational function automatically during emergency conditions. Each diesel generator is furnished with an individual fuel-oil storage tank. [UFSAR 9.5.4] The fuel oil transfer pumps operate automatically in order to maintain an adequate volume of fuel oil in the day tank during or following EDG testing. [TS B 3.8.1] A full day tank provides more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of fuel supply to each EDG. One transfer pump is started automatically when the respective EDG starts. The low level switch starts the second fuel oil transfer pump when the level is below the setpoint to maintain the minimum amount of fuel oil required by the Technical Specifications. [DBD R30-00 Section 4.1.7.2]Two redundant motor-driven fuel-oil transfer pumps deliver fuel to the day tank. Fuel flows by gravity from the day tank to the suction of the engine-driven fuel pump. The day tank is kept full, and, as required, one of the transfer pumps automatically operates (with the other pump in standby) to maintain the tank level. [UFSAR 9.5.4.2] Each transfer pump has a rated flow of 7.5 gpm (required flow to meet EDG fuel consumption requirement of 3.5 gpm). [DBD R30-00 Section 4.2.5.3]
Function
Description:
Group B - This pump is in standby systems that are not operated routinely except for testing.The diesel generator fuel-oil storage and transfer system is designed to perform its operational function automatically during emergency conditions. Each diesel generator is furnished with an individual fuel-oil storage tank. [UFSAR 9.5.4] The design of the fuel transfer systems is such that pumps operate automatically in order to maintain an adequate volume of fuel oil in the day tank during or following EDG testing. [TS B 3.8.1] The EDG Fuel Oil Subsystem associated with each EDG shall be operable with each EDG Fuel Oil Subsystem comprised of; (1) A separate day fuel tank containing a minimum of 210 gallons of fuel; (2) A separate fuel storage tank containing a minimum of 35,280 gallons of fuel, and (3) A separate fuel transfer pump. [DBD R30-00 Section 4.1.2.4 EDG Fuel Oil Subsystem]
Design Basis Limits: DBD R30-00 Section 4.2.5.3 Component RequirementsTransfer Pump Rated Flow (for each pump):7.5 GPM (Required flow to meet EDG fuel consumption requirement of 3.5 GPMPower Supply: 480V AC essential (for safety related FO Transfer Pumps, and non-safety related Standby pumps isolated from Class 1E MCCs that provide power)TS SR 3.8.1.6 -
Verify each fuel oil transfer system operates to automatically transfer fuel oil from storage tanks to the day tanks. This surveillance demonstrates that each required fuel oil transfer pump operates and transfers fuel oil from its associated storage tank to its associated day tank. It is required to support continuous operation of standby power sources. This surveillance provides assurance that the fuel oil transfer pump is operable, the fuel oil piping system is intact, the fuel delivery piping is not obstructed, and the controls and control systems for automatic fuel transfer systems is operable. The design of the fuel transfer systems is such that pumps operate automatically in order to maintain an adequate volume of fuel oil in the day tank during or following EDG testing. [TS B 3.8.1 Surveillance Requirements SR 3.8.1.6))Criterion 17 Conformance - The Fermi 2 onsite power system has four separate emergency diesel generators (EDGs), each of which supplies a separate bus. There are two independent and redundant divisions of ESF, each of which can be powered by a division pair of the EDGs through their associated buses. The diesel generators are of sufficient capacity to provide minimum essential emergency loads, including a single failure, such as the loss of a diesel generator or essential bus. The diesel generators are located in a Category I structure with fire-barrier separation between diesel generators. [UFSAR Section 3.1.2.2.8 Criterion 17 - Electric Power Systems]The system complies with Appendix B of ANSI Standard N195-1976, "Fuel Oil System for Standby Diesel Generators" and is designed to Category I requirements. The system piping and as much equipment as practicable are designed to either ASME B&PV Code Section III, Class 3 or the Diesel Manufacturers Association (DEMA) standards as shown in Figures 9.5-4, 9.5-5 and 9.5-6.
The diesel generator fuel-oil storage and transfer system for each diesel generator is separate and is located in separate compartments. The system is housed in the RHR complex, and, as such, is protected from flooding, tornado winds, and missiles. Adequate fire protection is provided and fire walls separate each compartment containing the individual diesel generator and its associated systems. [UFSAR 9.5.4.1 Design Basis]The diesel generator fuel oil system is classified as QA Level I and Seismic Category I. All off-skid piping and components of the fuel oil system are classified as Class 3 and are designed and constructed to Subsection ND of the ASME Code,Section III, and all addenda to and including Summer 1973, with the exception of the fuel oil transfer pumps. The fuel oil transfer pumps were upgraded to include hydrostatic tests with test reports and certificates of material conformance. [DBD R30-00 Section 2.3 Classification]
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 55 of 106
Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 57 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes Design
References:
TS 3.8.1 AC Sources - OperatingTS B 3.8.1 AC Sources - OperatingTS SR 3.8.1.6UFSAR 3.1.2.2.8 Criterion 17 - Electric Power SystemsUFSAR 9.5.4 Diesel Generator Fuel-Oil Storage and Transfer SystemDBD R30-00, Rev. H, Emergency Diesel Generator Appendix V Basis: OM Code Appendix V paragraph V-3000(a) Requirement: The Owner shall (a) identify those certain applicable pumps with specific design basis accident flow rates in the Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) for inclusion in this program.This pump has been deemed not applicable to Appendix V. There are no specified TS or UFSAR requirements specific to pump design basis accident flow rates. DBD R30-00 refers to a Transfer Pump rating of required 7.5 gpm flow to meet EDG fuel consumption requirement of 3.5 gpm. The NRC has stated that specific pump design basis values in other plant documents other than technical specifications, technical requirements program, or updated safety analysis report are not subject to Appendix V testing.
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 56 of 106
1M - Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 58 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3000C010 R3000 EDG 14 Diesel Fuel Oil Xfer Pump A 5734/F-8 B 3 Positive Displacement P 2Y 24.307.37 Q 2Y 24.307.37 V 2Y 24.307.37 PRR-002 Standard Code ISTB P Q 24.307.37 Q Q 24.307.37 V Q 24.307.37 PRR-002 Safety Function Basis: The diesel generator fuel-oil storage and transfer system is designed to perform its operational function automatically during emergency conditions. Each diesel generator is furnished with an individual fuel-oil storage tank. [UFSAR 9.5.4] The fuel oil transfer pumps operate automatically in order to maintain an adequate volume of fuel oil in the day tank during or following EDG testing. [TS B 3.8.1] A full day tank provides more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of fuel supply to each EDG. One transfer pump is started automatically when the respective EDG starts. The low level switch starts the second fuel oil transfer pump when the level is below the setpoint to maintain the minimum amount of fuel oil required by the Technical Specifications. [DBD R30-00 Section 4.1.7.2]Two redundant motor-driven fuel-oil transfer pumps deliver fuel to the day tank. Fuel flows by gravity from the day tank to the suction of the engine-driven fuel pump. The day tank is kept full, and, as required, one of the transfer pumps automatically operates (with the other pump in standby) to maintain the tank level. [UFSAR 9.5.4.2] Each transfer pump has a rated flow of 7.5 gpm (required flow to meet EDG fuel consumption requirement of 3.5 gpm). [DBD R30-00 Section 4.2.5.3]
Function
Description:
Group B - This pump is in standby systems that are not operated routinely except for testing.The diesel generator fuel-oil storage and transfer system is designed to perform its operational function automatically during emergency conditions. Each diesel generator is furnished with an individual fuel-oil storage tank. [UFSAR 9.5.4] The design of the fuel transfer systems is such that pumps operate automatically in order to maintain an adequate volume of fuel oil in the day tank during or following EDG testing. [TS B 3.8.1] The EDG Fuel Oil Subsystem associated with each EDG shall be operable with each EDG Fuel Oil Subsystem comprised of; (1) A separate day fuel tank containing a minimum of 210 gallons of fuel; (2) A separate fuel storage tank containing a minimum of 35,280 gallons of fuel, and (3) A separate fuel transfer pump. [DBD R30-00 Section 4.1.2.4 EDG Fuel Oil Subsystem]
Design Basis Limits: DBD R30-00 Section 4.2.5.3 Component RequirementsTransfer Pump Rated Flow (for each pump):7.5 GPM (Required flow to meet EDG fuel consumption requirement of 3.5 GPMPower Supply: 480V AC essential (for safety related FO Transfer Pumps, and non-safety related Standby pumps isolated from Class 1E MCCs that provide power)TS SR 3.8.1.6 -
Verify each fuel oil transfer system operates to automatically transfer fuel oil from storage tanks to the day tanks. This surveillance demonstrates that each required fuel oil transfer pump operates and transfers fuel oil from its associated storage tank to its associated day tank. It is required to support continuous operation of standby power sources. This surveillance provides assurance that the fuel oil transfer pump is operable, the fuel oil piping system is intact, the fuel delivery piping is not obstructed, and the controls and control systems for automatic fuel transfer systems is operable. The design of the fuel transfer systems is such that pumps operate automatically in order to maintain an adequate volume of fuel oil in the day tank during or following EDG testing. [TS B 3.8.1 Surveillance Requirements SR 3.8.1.6]Criterion 17 Conformance - The Fermi 2 onsite power system has four separate emergency diesel generators (EDGs), each of which supplies a separate bus. There are two independent and redundant divisions of ESF, each of which can be powered by a division pair of the EDGs through their associated buses. The diesel generators are of sufficient capacity to provide minimum essential emergency loads, including a single failure, such as the loss of a diesel generator or essential bus. The diesel generators are located in a Category I structure with fire-barrier separation between diesel generators. [UFSAR Section 3.1.2.2.8 Criterion 17 - Electric Power Systems]The system complies with Appendix B of ANSI Standard N195-1976, "Fuel Oil System for Standby Diesel Generators" and is designed to Category I requirements. The system piping and as much equipment as practicable are designed to either ASME B&PV Code Section III, Class 3 or the Diesel Manufacturers Association (DEMA) standards as shown in Figures 9.5-4, 9.5-5 and 9.5-6.
The diesel generator fuel-oil storage and transfer system for each diesel generator is separate and is located in separate compartments. The system is housed in the RHR complex, and, as such, is protected from flooding, tornado winds, and missiles. Adequate fire protection is provided and fire walls separate each compartment containing the individual diesel generator and its associated systems. [UFSAR 9.5.4.1 Design Basis]The diesel generator fuel oil system is classified as QA Level I and Seismic Category I. All off-skid piping and components of the fuel oil system are classified as Class 3 and are designed and constructed to Subsection ND of the ASME Code,Section III, and all addenda to and including Summer 1973, with the exception of the fuel oil transfer pumps. The fuel oil transfer pumps were upgraded to include hydrostatic tests with test reports and certificates of material conformance. [DBD R30-00 Section 2.3 Classification]
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 57 of 106
Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 59 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes Design
References:
TS 3.8.1 AC Sources - OperatingTS B 3.8.1 AC Sources - OperatingTS SR 3.8.1.6UFSAR 3.1.2.2.8 Criterion 17 - Electric Power SystemsUFSAR 9.5.4 Diesel Generator Fuel-Oil Storage and Transfer SystemDBD R30-00, Rev. H, Emergency Diesel Generator Appendix V Basis: OM Code Appendix V paragraph V-3000(a) Requirement: The Owner shall (a) identify those certain applicable pumps with specific design basis accident flow rates in the Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) for inclusion in this program.This pump has been deemed not applicable to Appendix V. There are no specified TS or UFSAR requirements specific to pump design basis accident flow rates. DBD R30-00 refers to a Transfer Pump rating of required 7.5 gpm flow to meet EDG fuel consumption requirement of 3.5 gpm. The NRC has stated that specific pump design basis values in other plant documents other than technical specifications, technical requirements program, or updated safety analysis report are not subject to Appendix V testing.
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 58 of 106
DTIE E ergy-Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 60 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3000C011 R3000 EDG 13 Diesel Fuel Oil Xfer Pump B 5734/E-8 B 3 Positive Displacement P 2Y 24.307.36 Q 2Y 24.307.36 V 2Y 24.307.36 PRR-002 Standard Code ISTB P Q 24.307.36 Q Q 24.307.36 V Q 24.307.36 PRR-002 Safety Function Basis: The diesel generator fuel-oil storage and transfer system is designed to perform its operational function automatically during emergency conditions. Each diesel generator is furnished with an individual fuel-oil storage tank. [UFSAR 9.5.4] The fuel oil transfer pumps operate automatically in order to maintain an adequate volume of fuel oil in the day tank during or following EDG testing. [TS B 3.8.1] A full day tank provides more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of fuel supply to each EDG. One transfer pump is started automatically when the respective EDG starts. The low level switch starts the second fuel oil transfer pump when the level is below the setpoint to maintain the minimum amount of fuel oil required by the Technical Specifications. [DBD R30-00 Section 4.1.7.2]Two redundant motor-driven fuel-oil transfer pumps deliver fuel to the day tank. Fuel flows by gravity from the day tank to the suction of the engine-driven fuel pump. The day tank is kept full, and, as required, one of the transfer pumps automatically operates (with the other pump in standby) to maintain the tank level. [UFSAR 9.5.4.2] Each transfer pump has a rated flow of 7.5 gpm (required flow to meet EDG fuel consumption requirement of 3.5 gpm). [DBD R30-00 Section 4.2.5.3]
Function
Description:
Group B - This pump is in standby systems that are not operated routinely except for testing.The diesel generator fuel-oil storage and transfer system is designed to perform its operational function automatically during emergency conditions. Each diesel generator is furnished with an individual fuel-oil storage tank. [UFSAR 9.5.4] The design of the fuel transfer systems is such that pumps operate automatically in order to maintain an adequate volume of fuel oil in the day tank during or following EDG testing. [TS B 3.8.1] The EDG Fuel Oil Subsystem associated with each EDG shall be operable with each EDG Fuel Oil Subsystem comprised of; (1) A separate day fuel tank containing a minimum of 210 gallons of fuel; (2) A separate fuel storage tank containing a minimum of 35,280 gallons of fuel, and (3) A separate fuel transfer pump. [DBD R30-00 Section 4.1.2.4 EDG Fuel Oil Subsystem]
Design Basis Limits: DBD R30-00 Section 4.2.5.3 Component RequirementsTransfer Pump Rated Flow (for each pump):7.5 GPM (Required flow to meet EDG fuel consumption requirement of 3.5 GPMPower Supply: 480V AC essential (for safety related FO Transfer Pumps, and non-safety related Standby pumps isolated from Class 1E MCCs that provide power)TS SR 3.8.1.6 -
Verify each fuel oil transfer system operates to automatically transfer fuel oil from storage tanks to the day tanks. This surveillance demonstrates that each required fuel oil transfer pump operates and transfers fuel oil from its associated storage tank to its associated day tank. It is required to support continuous operation of standby power sources. This surveillance provides assurance that the fuel oil transfer pump is operable, the fuel oil piping system is intact, the fuel delivery piping is not obstructed, and the controls and control systems for automatic fuel transfer systems is operable. The design of the fuel transfer systems is such that pumps operate automatically in order to maintain an adequate volume of fuel oil in the day tank during or following EDG testing. [TS B 3.8.1 Surveillance Requirements SR 3.8.1.6))Criterion 17 Conformance - The Fermi 2 onsite power system has four separate emergency diesel generators (EDGs), each of which supplies a separate bus. There are two independent and redundant divisions of ESF, each of which can be powered by a division pair of the EDGs through their associated buses. The diesel generators are of sufficient capacity to provide minimum essential emergency loads, including a single failure, such as the loss of a diesel generator or essential bus. The diesel generators are located in a Category I structure with fire-barrier separation between diesel generators. [UFSAR Section 3.1.2.2.8 Criterion 17 - Electric Power Systems]The system complies with Appendix B of ANSI Standard N195-1976, "Fuel Oil System for Standby Diesel Generators" and is designed to Category I requirements. The system piping and as much equipment as practicable are designed to either ASME B&PV Code Section III, Class 3 or the Diesel Manufacturers Association (DEMA) standards as shown in Figures 9.5-4, 9.5-5 and 9.5-6.
The diesel generator fuel-oil storage and transfer system for each diesel generator is separate and is located in separate compartments. The system is housed in the RHR complex, and, as such, is protected from flooding, tornado winds, and missiles. Adequate fire protection is provided and fire walls separate each compartment containing the individual diesel generator and its associated systems. [UFSAR 9.5.4.1 Design Basis]The diesel generator fuel oil system is classified as QA Level I and Seismic Category I. All off-skid piping and components of the fuel oil system are classified as Class 3 and are designed and constructed to Subsection ND of the ASME Code,Section III, and all addenda to and including Summer 1973, with the exception of the fuel oil transfer pumps. The fuel oil transfer pumps were upgraded to include hydrostatic tests with test reports and certificates of material conformance. [DBD R30-00 Section 2.3 Classification]
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 59 of 106
Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 61 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes Design
References:
TS 3.8.1 AC Sources - OperatingTS B 3.8.1 AC Sources - OperatingTS SR 3.8.1.6UFSAR 3.1.2.2.8 Criterion 17 - Electric Power SystemsUFSAR 9.5.4 Diesel Generator Fuel-Oil Storage and Transfer SystemDBD R30-00, Rev. H, Emergency Diesel Generator Appendix V Basis: OM Code Appendix V paragraph V-3000(a) Requirement: The Owner shall (a) identify those certain applicable pumps with specific design basis accident flow rates in the Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) for inclusion in this program.This pump has been deemed not applicable to Appendix V. There are no specified TS or UFSAR requirements specific to pump design basis accident flow rates. DBD R30-00 refers to a Transfer Pump rating of required 7.5 gpm flow to meet EDG fuel consumption requirement of 3.5 gpm. The NRC has stated that specific pump design basis values in other plant documents other than technical specifications, technical requirements program, or updated safety analysis report are not subject to Appendix V testing.
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 60 of 106
I VFermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 62 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3000C012 R3000 EDG 14 Diesel Fuel Oil Xfer Pump B 5734/E-8 B 3 Positive Displacement P 2Y 24.307.37 Q 2Y 24.307.37 V 2Y 24.307.37 PRR-002 Standard Code ISTB P Q 24.307.37 Q Q 24.307.37 V Q 24.307.37 PRR-002 Safety Function Basis: The diesel generator fuel-oil storage and transfer system is designed to perform its operational function automatically during emergency conditions. Each diesel generator is furnished with an individual fuel-oil storage tank. [UFSAR 9.5.4] The fuel oil transfer pumps operate automatically in order to maintain an adequate volume of fuel oil in the day tank during or following EDG testing. [TS B 3.8.1] A full day tank provides more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of fuel supply to each EDG. One transfer pump is started automatically when the respective EDG starts. The low level switch starts the second fuel oil transfer pump when the level is below the setpoint to maintain the minimum amount of fuel oil required by the Technical Specifications. [DBD R30-00 Section 4.1.7.2]Two redundant motor-driven fuel-oil transfer pumps deliver fuel to the day tank. Fuel flows by gravity from the day tank to the suction of the engine-driven fuel pump. The day tank is kept full, and, as required, one of the transfer pumps automatically operates (with the other pump in standby) to maintain the tank level. [UFSAR 9.5.4.2] Each transfer pump has a rated flow of 7.5 gpm (required flow to meet EDG fuel consumption requirement of 3.5 gpm). [DBD R30-00 Section 4.2.5.3]
Function
Description:
Group B - This pump is in standby systems that are not operated routinely except for testing.The diesel generator fuel-oil storage and transfer system is designed to perform its operational function automatically during emergency conditions. Each diesel generator is furnished with an individual fuel-oil storage tank. [UFSAR 9.5.4] The design of the fuel transfer systems is such that pumps operate automatically in order to maintain an adequate volume of fuel oil in the day tank during or following EDG testing. [TS B 3.8.1] The EDG Fuel Oil Subsystem associated with each EDG shall be operable with each EDG Fuel Oil Subsystem comprised of; (1) A separate day fuel tank containing a minimum of 210 gallons of fuel; (2) A separate fuel storage tank containing a minimum of 35,280 gallons of fuel, and (3) A separate fuel transfer pump. [DBD R30-00 Section 4.1.2.4 EDG Fuel Oil Subsystem]
Design Basis Limits: DBD R30-00 Section 4.2.5.3 Component RequirementsTransfer Pump Rated Flow (for each pump):7.5 GPM (Required flow to meet EDG fuel consumption requirement of 3.5 GPMPower Supply: 480V AC essential (for safety related FO Transfer Pumps, and non-safety related Standby pumps isolated from Class 1E MCCs that provide power)TS SR 3.8.1.6 -
Verify each fuel oil transfer system operates to automatically transfer fuel oil from storage tanks to the day tanks. This surveillance demonstrates that each required fuel oil transfer pump operates and transfers fuel oil from its associated storage tank to its associated day tank. It is required to support continuous operation of standby power sources. This surveillance provides assurance that the fuel oil transfer pump is operable, the fuel oil piping system is intact, the fuel delivery piping is not obstructed, and the controls and control systems for automatic fuel transfer systems is operable. The design of the fuel transfer systems is such that pumps operate automatically in order to maintain an adequate volume of fuel oil in the day tank during or following EDG testing. [TS B 3.8.1 Surveillance Requirements SR 3.8.1.6]Criterion 17 Conformance - The Fermi 2 onsite power system has four separate emergency diesel generators (EDGs), each of which supplies a separate bus. There are two independent and redundant divisions of ESF, each of which can be powered by a division pair of the EDGs through their associated buses. The diesel generators are of sufficient capacity to provide minimum essential emergency loads, including a single failure, such as the loss of a diesel generator or essential bus. The diesel generators are located in a Category I structure with fire-barrier separation between diesel generators. [UFSAR Section 3.1.2.2.8 Criterion 17 - Electric Power Systems]The system complies with Appendix B of ANSI Standard N195-1976, "Fuel Oil System for Standby Diesel Generators" and is designed to Category I requirements. The system piping and as much equipment as practicable are designed to either ASME B&PV Code Section III, Class 3 or the Diesel Manufacturers Association (DEMA) standards as shown in Figures 9.5-4, 9.5-5 and 9.5-6.
The diesel generator fuel-oil storage and transfer system for each diesel generator is separate and is located in separate compartments. The system is housed in the RHR complex, and, as such, is protected from flooding, tornado winds, and missiles. Adequate fire protection is provided and fire walls separate each compartment containing the individual diesel generator and its associated systems. [UFSAR 9.5.4.1 Design Basis]The diesel generator fuel oil system is classified as QA Level I and Seismic Category I. All off-skid piping and components of the fuel oil system are classified as Class 3 and are designed and constructed to Subsection ND of the ASME Code,Section III, and all addenda to and including Summer 1973, with the exception of the fuel oil transfer pumps. The fuel oil transfer pumps were upgraded to include hydrostatic tests with test reports and certificates of material conformance. [DBD R30-00 Section 2.3 Classification]
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 61 of 106
-g a Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 63 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes Design
References:
TS 3.8.1 AC Sources - OperatingTS B 3.8.1 AC Sources - OperatingTS SR 3.8.1.6UFSAR 3.1.2.2.8 Criterion 17 - Electric Power SystemsUFSAR 9.5.4 Diesel Generator Fuel-Oil Storage and Transfer SystemDBD R30-00, Rev. H, Emergency Diesel Generator Appendix V Basis: OM Code Appendix V paragraph V-3000(a) Requirement: The Owner shall (a) identify those certain applicable pumps with specific design basis accident flow rates in the Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) for inclusion in this program.This pump has been deemed not applicable to Appendix V. There are no specified TS or UFSAR requirements specific to pump design basis accident flow rates. DBD R30-00 refers to a Transfer Pump rating of required 7.5 gpm flow to meet EDG fuel consumption requirement of 3.5 gpm. The NRC has stated that specific pump design basis values in other plant documents other than technical specifications, technical requirements program, or updated safety analysis report are not subject to Appendix V testing.
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 62 of 106
DI e-- Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 64 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3001C005 R3001 EDG 11 DG Service Water Pump 5706-3/G-2 A 3 Vertical Line Shaft dP 2Y 24.307.34 PRR-003 Q 2Y 24.307.34 V 2Y 24.307.34 PRR-002 Standard Code ISTB dP Q 24.307.34 PRR-003 Q Q 24.307.34 V Q 24.307.34 PRR-002 Safety Function Basis: The safety related function of the EDG System is to provide an onsite standby source of AC electrical power to shutdown and maintain the reactor in a safe condition under all conditions including LOCA coincident with LOOP. [DBD R30-00 Section 2.2.1] The diesel generator service water system is designed to provide cooling water source for the emergency diesel generators (EDGs) during testing and emergency operation. [UFSAR 9.2.5.1] Diesel generator cooling water is supplied from the RHR reservoirs with each diesel generator supplied by its own pump. Supply lines are also independent for each diesel generator. The diesel generator service water pumps start and stop automatically in conjunction with the diesel generators. The diesel generator service water supplies cooling water to the lube oil heat exchanger, the engine inlet air cooler heat exchanger, and the engine jacket coolant heat exchanger. The diesel generator service water flows through the tube side of the three-stage heat exchanger. The first stage cools the inlet air coolant system, then the second stage cools the lube oil and finally the third stage cools the jacket coolant. [UFSAR 9.2.5.2.3] One 800-gpm diesel generator service water pump is provided for each of the four diesel generators.
[UFSAR 9.2.5.2.5]An individual loss of an EDGSW system will cause loss of only the particular EDG that it cools. The EDG loss will cause loss of only the loads for that particular generator because the Fermi 2 essential power system consists of four independent buses. The loss of the EESW system will cause loss of the emergency equipment cooling water (EECW) system in that division. This loss will cause the eventual loss of the ESF equipment in the particular division cooled by the EECW system. For a worst-case assumption, the EDGSW, EESW, and RHRSW systems are assumed to fail simultaneously in the same division coincident with the LOCA. [UFSAR 15.14.1.2]
Function
Description:
Group A - This pump operates continuously or routinely during normal operation, cold shutdown, or refueling operations.The DGSW System provides adequate cooling water to remove heat given off by three heat exchangers piped in series on the service water side. In order, the heat exchangers are the inlet coolant heat exchangers, lube oil coolers, and the jacket coolant heat exchangers. [DBD R30-00 Section 4.2.7.2] The DGSW Pumps provide an active safety function in support of EDG operability. They are not considered skid-mounted devices. [DBD R30-00 Section 4.2.7.3]The cooling water is provided from the RHR Service Water Reservoir. The EDG Jacket Cooling Water System is a closed loop system that removes heat from the engine and transfers it to the EDG Service Water System. The EDG Air Coolant System cools inlet combustion air during EDG operation and transfers heat to the EDG Service Water System. The EDG Lube Oil System lubricates and cools the engine during operation and keep the lube oil warm in standby mode to ensure a quick start. [DBD R30-00 Section 2.1]Each diesel generator has independent jacket coolant and service water systems. The jacket coolant system meets the single-failure criterion in that if the system prevents the operation of its associated diesel generator, the remaining diesel generators will provide adequate emergency power to meet safe-shutdown requirements of the plant. [UFSAR 9.5.5.3]
Design Basis Limits: TS SR 3.7.8.2 - Verify each EDGSW subsystem pump starts automatically when the associated EDG starts every 18 months. This SR (3.7.8.2) ensures that each EDGSW subsystem pump will automatically start to provide required cooling to the EDG when the EDG starts.One 800-gpm diesel generator service water pump is provided for each of the four diesel generators. [UFSAR 9.2.5.2.5]For the EDG System to perform its function or providing an onsite source of power under all conditions, the following process conditions are required; (1)
Service Water Inlet Temperature 89 Degrees F; (2) Service Water Operating Flow of 650 gpm; The basis for the service water inlet temperature is based on the design limit of RHRSW reservoir. The original design basis process requirement was for 89 degrees F service water supply temperature at a nominal flow rate of 800 gpm. A more recent analysis has concluded that with a degraded DGSW flow rate as low as 650 gpm is acceptable. DC-5804 provides flows (throttle valve controlled) for various system configurations that insures the design flow. [DBD R30-00 Section 4.1.5]DBD R30-00 Section 4.2.7.3 Component RequirementsComponent RequirementsDGSW Pump NPSHR (15ft)DGSW Pump NPSHA (41 Feet)NPSH based on 1008 gpm at 100 degrees FSystem Minimum Flow 650 gpm at 575 Ft reservoir elevationSystem Maximum Flow 1008 gpm (based on 8 ft/second max, 196 5/8 inch BWG18 tubes with 5 percent plugged)
Air Coolant HX Shell flow rate: 400 gpmLube Oil Heat ExchangersShell flow rate: 500 gpmJacket Coolant Heat ExchangersShell flow rate: 450 gpm Design
References:
TS 3.7.8 Emergency Diesel Generator Service Water (EDGSW) SystemTS SR 3.7.8.2TS B 3.7.8 Emergency Diesel Generator Service Water (EDGSW) System UFSAR 9.2.5 Ultimate Heat SinkUFSAR 9.2.5.2.3 Emergency Diesel GeneratorsUFSAR 15.14.1.2 Event DescriptionDBD R30-00, Rev. I, Emergency Diesel Generator Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 63 of 106
Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 65 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes Appendix V Basis: OM Code Appendix V paragraph V-3000(a) Requirement: The Owner shall (a) identify those certain applicable pumps with specific design basis accident flow rates in the Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) for inclusion in this program.This pump has been deemed not applicable to Appendix V. UFSAR 9.2.5.2.5 states that one 800-gpm diesel generator service water pump is provided for each of the four diesel generators. This 800-gpm flow rate is considered a nominal rating and not an Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) as defined in Appendix V.
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 64 of 106
an -n r Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 66 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3001C006 R3001 EDG 12 DG Service Water Pump 5706-3/G-3 A 3 Vertical Line Shaft dP 2Y 24.307.35 PRR-003 Q 2Y 24.307.35 V 2Y 24.307.35 PRR-002 Standard Code ISTB dP Q 24.307.35 PRR-003 Q Q 24.307.35 V Q 24.307.35 PRR-002 Safety Function Basis: The safety related function of the EDG System is to provide an onsite standby source of AC electrical power to shutdown and maintain the reactor in a safe condition under all conditions including LOCA coincident with LOOP. [DBD R30-00 Section 2.2.1] The diesel generator service water system is designed to provide cooling water source for the emergency diesel generators (EDGs) during testing and emergency operation. [UFSAR 9.2.5.1] Diesel generator cooling water is supplied from the RHR reservoirs with each diesel generator supplied by its own pump. Supply lines are also independent for each diesel generator. The diesel generator service water pumps start and stop automatically in conjunction with the diesel generators. The diesel generator service water supplies cooling water to the lube oil heat exchanger, the engine inlet air cooler heat exchanger, and the engine jacket coolant heat exchanger. The diesel generator service water flows through the tube side of the three-stage heat exchanger. The first stage cools the inlet air coolant system, then the second stage cools the lube oil and finally the third stage cools the jacket coolant. [UFSAR 9.2.5.2.3] One 800-gpm diesel generator service water pump is provided for each of the four diesel generators.
[UFSAR 9.2.5.2.5]An individual loss of an EDGSW system will cause loss of only the particular EDG that it cools. The EDG loss will cause loss of only the loads for that particular generator because the Fermi 2 essential power system consists of four independent buses. The loss of the EESW system will cause loss of the emergency equipment cooling water (EECW) system in that division. This loss will cause the eventual loss of the ESF equipment in the particular division cooled by the EECW system. For a worst-case assumption, the EDGSW, EESW, and RHRSW systems are assumed to fail simultaneously in the same division coincident with the LOCA. [UFSAR 15.14.1.2]
Function
Description:
Group A - This pump operates continuously or routinely during normal operation, cold shutdown, or refueling operations.The DGSW System provides adequate cooling water to remove heat given off by three heat exchangers piped in series on the service water side. In order, the heat exchangers are the inlet coolant heat exchangers, lube oil coolers, and the jacket coolant heat exchangers. [DBD R30-00 Section 4.2.7.2] The DGSW Pumps provide an active safety function in support of EDG operability. They are not considered skid-mounted devices. [DBD R30-00 Section 4.2.7.3]The cooling water is provided from the RHR Service Water Reservoir. The EDG Jacket Cooling Water System is a closed loop system that removes heat from the engine and transfers it to the EDG Service Water System. The EDG Air Coolant System cools inlet combustion air during EDG operation and transfers heat to the EDG Service Water System. The EDG Lube Oil System lubricates and cools the engine during operation and keep the lube oil warm in standby mode to ensure a quick start. [DBD R30-00 Section 2.1]Each diesel generator has independent jacket coolant and service water systems. The jacket coolant system meets the single-failure criterion in that if the system prevents the operation of its associated diesel generator, the remaining diesel generators will provide adequate emergency power to meet safe-shutdown requirements of the plant. [UFSAR 9.5.5.3]
Design Basis Limits: TS SR 3.7.8.2 - Verify each EDGSW subsystem pump starts automatically when the associated EDG starts every 18 months. This SR (3.7.8.2) ensures that each EDGSW subsystem pump will automatically start to provide required cooling to the EDG when the EDG starts.One 800-gpm diesel generator service water pump is provided for each of the four diesel generators. [UFSAR 9.2.5.2.5]For the EDG System to perform its function or providing an onsite source of power under all conditions, the following process conditions are required; (1)
Service Water Inlet Temperature 89 Degrees F; (2) Service Water Operating Flow of 650 gpm; The basis for the service water inlet temperature is based on the design limit of RHRSW reservoir. The original design basis process requirement was for 89 degrees F service water supply temperature at a nominal flow rate of 800 gpm. A more recent analysis has concluded that with a degraded DGSW flow rate as low as 650 gpm is acceptable. DC-5804 provides flows (throttle valve controlled) for various system configurations that insures the design flow. [DBD R30-00 Section 4.1.5]DBD R30-00 Section 4.2.7.3 Component RequirementsComponent RequirementsDGSW Pump NPSHR (15ft)DGSW Pump NPSHA (41 Feet)NPSH based on 1008 gpm at 100 degrees FSystem Minimum Flow 650 gpm at 575 Ft reservoir elevationSystem Maximum Flow 1008 gpm (based on 8 ft/second max, 196 5/8 inch BWG18 tubes with 5 percent plugged)
Air Coolant HX Shell flow rate: 400 gpmLube Oil Heat ExchangersShell flow rate: 500 gpmJacket Coolant Heat ExchangersShell flow rate: 450 gpm Design
References:
TS 3.7.8 Emergency Diesel Generator Service Water (EDGSW) SystemTS SR 3.7.8.2TS B 3.7.8 Emergency Diesel Generator Service Water (EDGSW) System UFSAR 9.2.5 Ultimate Heat SinkUFSAR 9.2.5.2.3 Emergency Diesel GeneratorsUFSAR 15.14.1.2 Event DescriptionDBD R30-00, Rev. I, Emergency Diesel Generator Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 65 of 106
.70W an mFermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 67 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes Appendix V Basis: OM Code Appendix V paragraph V-3000(a) Requirement: The Owner shall (a) identify those certain applicable pumps with specific design basis accident flow rates in the Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) for inclusion in this program.This pump has been deemed not applicable to Appendix V. UFSAR 9.2.5.2.5 states that one 800-gpm diesel generator service water pump is provided for each of the four diesel generators. This 800-gpm flow rate is considered a nominal rating and not an Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) as defined in Appendix V.
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 66 of 106
DTIE ergFermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 68 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3001C007 R3001 EDG 13 DG Service Water Pump 5706-3/G-6 A 3 Vertical Line Shaft dP 2Y 24.307.36 PRR-003 Q 2Y 24.307.36 V 2Y 24.307.36 PRR-002 Standard Code ISTB dP Q 24.307.36 PRR-003 Q Q 24.307.36 V Q 24.307.36 PRR-002 Safety Function Basis: The safety related function of the EDG System is to provide an onsite standby source of AC electrical power to shutdown and maintain the reactor in a safe condition under all conditions including LOCA coincident with LOOP. [DBD R30-00 Section 2.2.1] The diesel generator service water system is designed to provide cooling water source for the emergency diesel generators (EDGs) during testing and emergency operation. [UFSAR 9.2.5.1] Diesel generator cooling water is supplied from the RHR reservoirs with each diesel generator supplied by its own pump. Supply lines are also independent for each diesel generator. The diesel generator service water pumps start and stop automatically in conjunction with the diesel generators. The diesel generator service water supplies cooling water to the lube oil heat exchanger, the engine inlet air cooler heat exchanger, and the engine jacket coolant heat exchanger. The diesel generator service water flows through the tube side of the three-stage heat exchanger. The first stage cools the inlet air coolant system, then the second stage cools the lube oil and finally the third stage cools the jacket coolant. [UFSAR 9.2.5.2.3] One 800-gpm diesel generator service water pump is provided for each of the four diesel generators.
[UFSAR 9.2.5.2.5]An individual loss of an EDGSW system will cause loss of only the particular EDG that it cools. The EDG loss will cause loss of only the loads for that particular generator because the Fermi 2 essential power system consists of four independent buses. The loss of the EESW system will cause loss of the emergency equipment cooling water (EECW) system in that division. This loss will cause the eventual loss of the ESF equipment in the particular division cooled by the EECW system. For a worst-case assumption, the EDGSW, EESW, and RHRSW systems are assumed to fail simultaneously in the same division coincident with the LOCA. [UFSAR 15.14.1.2]
Function
Description:
Group A - This pump operates continuously or routinely during normal operation, cold shutdown, or refueling operations.The DGSW System provides adequate cooling water to remove heat given off by three heat exchangers piped in series on the service water side. In order, the heat exchangers are the inlet coolant heat exchangers, lube oil coolers, and the jacket coolant heat exchangers. [DBD R30-00 Section 4.2.7.2] The DGSW Pumps provide an active safety function in support of EDG operability. They are not considered skid-mounted devices. [DBD R30-00 Section 4.2.7.3]The cooling water is provided from the RHR Service Water Reservoir. The EDG Jacket Cooling Water System is a closed loop system that removes heat from the engine and transfers it to the EDG Service Water System. The EDG Air Coolant System cools inlet combustion air during EDG operation and transfers heat to the EDG Service Water System. The EDG Lube Oil System lubricates and cools the engine during operation and keep the lube oil warm in standby mode to ensure a quick start. [DBD R30-00 Section 2.1]Each diesel generator has independent jacket coolant and service water systems. The jacket coolant system meets the single-failure criterion in that if the system prevents the operation of its associated diesel generator, the remaining diesel generators will provide adequate emergency power to meet safe-shutdown requirements of the plant. [UFSAR 9.5.5.3]
Design Basis Limits: TS SR 3.7.8.2 - Verify each EDGSW subsystem pump starts automatically when the associated EDG starts every 18 months. This SR (3.7.8.2) ensures that each EDGSW subsystem pump will automatically start to provide required cooling to the EDG when the EDG starts.One 800-gpm diesel generator service water pump is provided for each of the four diesel generators. [UFSAR 9.2.5.2.5]For the EDG System to perform its function or providing an onsite source of power under all conditions, the following process conditions are required; (1)
Service Water Inlet Temperature 89 Degrees F; (2) Service Water Operating Flow of 650 gpm; The basis for the service water inlet temperature is based on the design limit of RHRSW reservoir. The original design basis process requirement was for 89 degrees F service water supply temperature at a nominal flow rate of 800 gpm. A more recent analysis has concluded that with a degraded DGSW flow rate as low as 650 gpm is acceptable. DC-5804 provides flows (throttle valve controlled) for various system configurations that insures the design flow. [DBD R30-00 Section 4.1.5]DBD R30-00 Section 4.2.7.3 Component RequirementsComponent RequirementsDGSW Pump NPSHR (15ft)DGSW Pump NPSHA (41 Feet)NPSH based on 1008 gpm at 100 degrees FSystem Minimum Flow 650 gpm at 575 Ft reservoir elevationSystem Maximum Flow 1008 gpm (based on 8 ft/second max, 196 5/8 inch BWG18 tubes with 5 percent plugged)
Air Coolant HX Shell flow rate: 400 gpmLube Oil Heat ExchangersShell flow rate: 500 gpmJacket Coolant Heat ExchangersShell flow rate: 450 gpm Design
References:
TS 3.7.8 Emergency Diesel Generator Service Water (EDGSW) SystemTS SR 3.7.8.2TS B 3.7.8 Emergency Diesel Generator Service Water (EDGSW) System UFSAR 9.2.5 Ultimate Heat SinkUFSAR 9.2.5.2.3 Emergency Diesel GeneratorsUFSAR 15.14.1.2 Event DescriptionDBD R30-00, Rev. I, Emergency Diesel Generator Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 67 of 106
Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 69 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes Appendix V Basis: OM Code Appendix V paragraph V-3000(a) Requirement: The Owner shall (a) identify those certain applicable pumps with specific design basis accident flow rates in the Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) for inclusion in this program.This pump has been deemed not applicable to Appendix V. UFSAR 9.2.5.2.5 states that one 800-gpm diesel generator service water pump is provided for each of the four diesel generators. This 800-gpm flow rate is considered a nominal rating and not an Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) as defined in Appendix V.
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 68 of 106
Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 70 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3001C008 R3001 EDG 14 DG Service Water Pump 5706-3/G-7 A 3 Vertical Line Shaft dP 2Y 24.307.37 PRR-003 Q 2Y 24.307.37 V 2Y 24.307.37 PRR-002 Standard Code ISTB dP Q 24.307.37 PRR-003 Q Q 24.307.37 V Q 24.307.37 PRR-002 Safety Function Basis: The safety related function of the EDG System is to provide an onsite standby source of AC electrical power to shutdown and maintain the reactor in a safe condition under all conditions including LOCA coincident with LOOP. [DBD R30-00 Section 2.2.1] The diesel generator service water system is designed to provide cooling water source for the emergency diesel generators (EDGs) during testing and emergency operation. [UFSAR 9.2.5.1] Diesel generator cooling water is supplied from the RHR reservoirs with each diesel generator supplied by its own pump. Supply lines are also independent for each diesel generator. The diesel generator service water pumps start and stop automatically in conjunction with the diesel generators. The diesel generator service water supplies cooling water to the lube oil heat exchanger, the engine inlet air cooler heat exchanger, and the engine jacket coolant heat exchanger. The diesel generator service water flows through the tube side of the three-stage heat exchanger. The first stage cools the inlet air coolant system, then the second stage cools the lube oil and finally the third stage cools the jacket coolant. [UFSAR 9.2.5.2.3] One 800-gpm diesel generator service water pump is provided for each of the four diesel generators.
[UFSAR 9.2.5.2.5]An individual loss of an EDGSW system will cause loss of only the particular EDG that it cools. The EDG loss will cause loss of only the loads for that particular generator because the Fermi 2 essential power system consists of four independent buses. The loss of the EESW system will cause loss of the emergency equipment cooling water (EECW) system in that division. This loss will cause the eventual loss of the ESF equipment in the particular division cooled by the EECW system. For a worst-case assumption, the EDGSW, EESW, and RHRSW systems are assumed to fail simultaneously in the same division coincident with the LOCA. [UFSAR 15.14.1.2]
Function
Description:
Group A - This pump operates continuously or routinely during normal operation, cold shutdown, or refueling operations.The DGSW System provides adequate cooling water to remove heat given off by three heat exchangers piped in series on the service water side. In order, the heat exchangers are the inlet coolant heat exchangers, lube oil coolers, and the jacket coolant heat exchangers. [DBD R30-00 Section 4.2.7.2] The DGSW Pumps provide an active safety function in support of EDG operability. They are not considered skid-mounted devices. [DBD R30-00 Section 4.2.7.3]The cooling water is provided from the RHR Service Water Reservoir. The EDG Jacket Cooling Water System is a closed loop system that removes heat from the engine and transfers it to the EDG Service Water System. The EDG Air Coolant System cools inlet combustion air during EDG operation and transfers heat to the EDG Service Water System. The EDG Lube Oil System lubricates and cools the engine during operation and keep the lube oil warm in standby mode to ensure a quick start. [DBD R30-00 Section 2.1]Each diesel generator has independent jacket coolant and service water systems. The jacket coolant system meets the single-failure criterion in that if the system prevents the operation of its associated diesel generator, the remaining diesel generators will provide adequate emergency power to meet safe-shutdown requirements of the plant. [UFSAR 9.5.5.3]
Design Basis Limits: TS SR 3.7.8.2 - Verify each EDGSW subsystem pump starts automatically when the associated EDG starts every 18 months. This SR (3.7.8.2) ensures that each EDGSW subsystem pump will automatically start to provide required cooling to the EDG when the EDG starts.One 800-gpm diesel generator service water pump is provided for each of the four diesel generators. [UFSAR 9.2.5.2.5]For the EDG System to perform its function or providing an onsite source of power under all conditions, the following process conditions are required; (1)
Service Water Inlet Temperature 89 Degrees F; (2) Service Water Operating Flow of 650 gpm; The basis for the service water inlet temperature is based on the design limit of RHRSW reservoir. The original design basis process requirement was for 89 degrees F service water supply temperature at a nominal flow rate of 800 gpm. A more recent analysis has concluded that with a degraded DGSW flow rate as low as 650 gpm is acceptable. DC-5804 provides flows (throttle valve controlled) for various system configurations that insures the design flow. [DBD R30-00 Section 4.1.5]DBD R30-00 Section 4.2.7.3 Component RequirementsComponent RequirementsDGSW Pump NPSHR (15ft)DGSW Pump NPSHA (41 Feet)NPSH based on 1008 gpm at 100 degrees FSystem Minimum Flow 650 gpm at 575 Ft reservoir elevationSystem Maximum Flow 1008 gpm (based on 8 ft/second max, 196 5/8 inch BWG18 tubes with 5 percent plugged)
Air Coolant HX Shell flow rate: 400 gpmLube Oil Heat ExchangersShell flow rate: 500 gpmJacket Coolant Heat ExchangersShell flow rate: 450 gpm Design
References:
TS 3.7.8 Emergency Diesel Generator Service Water (EDGSW) SystemTS SR 3.7.8.2TS B 3.7.8 Emergency Diesel Generator Service Water (EDGSW) System UFSAR 9.2.5 Ultimate Heat SinkUFSAR 9.2.5.2.3 Emergency Diesel GeneratorsUFSAR 15.14.1.2 Event DescriptionDBD R30-00, Rev. I, Emergency Diesel Generator Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 69 of 106
- Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 71 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes Appendix V Basis: OM Code Appendix V paragraph V-3000(a) Requirement: The Owner shall (a) identify those certain applicable pumps with specific design basis accident flow rates in the Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) for inclusion in this program.This pump has been deemed not applicable to Appendix V. UFSAR 9.2.5.2.5 states that one 800-gpm diesel generator service water pump is provided for each of the four diesel generators. This 800-gpm flow rate is considered a nominal rating and not an Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) as defined in Appendix V.
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 70 of 106
- D rFermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 72 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3001C013 R3000 EDG 11 Motor-driven LO Pre-Lube Pump M-5734/E-3 Skid NC Positive Displacement Safety Function Basis: A 2-hp motor-driven prelube pump, which can be manually operated from the remote panel, is provided for prelubricating the engine prior to nonemergency starts.
Prelubrication is not required on emergency starts. However, a vendor-supplied prelubrication piping modification is installed and eliminates the potential for dry starts. [UFSAR 9.5.7.2 System Description] The Diesel generator lubrication system is designed to provide adequate engine lubrication under all operating conditions, including immediate full-load operation after starting. [UFSAR 9.5.7.1 Design Basis]The EDG motor-driven LO pre-lube pumps are considered skid mounted devices and have no individual IST exams. Satisfactory engine operation during periodic testing provides assurance that this pump is operating satisfactorily. This pump is verified to work in procedure 34.307.001. Bearing checks done in 34.307.001 would indicate bearing damage if this pump were not working properly. System Engineers also check for proper operation of this pump when they observe surveillance testing of the EDGs (verify slight increase in upper header lube oil pressure).
Function
Description:
The EDG LO System provides adequate engine lubrication under all operating conditions and cools the engine during operation and keeps the Lube Oil warm in standby mode. The keep warm and pre-lube pumps keep the EDG in standby readiness but are not functionally required for operation of the EDG. It provides sufficient amount of lube oil on site for continuous operation of the EDG for 7 days without replenishment. [DBD R30-00 Section 4.2.6.2 Component Function]A 2-hp motor-driven prelube pump, which can be manually operated from the remote panel, is provided for prelubricating the engine prior to nonemergency starts. Prelubrication is not required on emergency starts. However, a vendor-supplied prelubrication piping modification is installed and eliminates the potential for dry starts. This piping routes the keep-warm system so that it discharges into the upstream side of the lube-oil strainer. This will provide continuous lube oil to the lower bearings and greatly reduce voids in the lube-oil system. The solid lube-oil system will provide faster lubrication of the upper bearings on the starting of the diesel and the engine-driven pump. [UFSAR 9.5.7.2 System Description]The EDG motor-driven LO pre-lube pumps are considered skid mounted devices and have no individual IST exams. Satisfactory engine operation during periodic testing provides assurance that this pump is operating satisfactorily. This pump is verified to work in procedure 34.307.001. Bearing checks done in 34.307.001 would indicate bearing damage if this pump were not working properly. System Engineers also check for proper operation of this pump when they observe surveillance testing of the EDGs (verify slight increase in upper header lube oil pressure).
Design Basis Limits: SR 3.8.1.2 - Note 1 - All EDG starts may be preceded by an engine prelube period and followed by a warmup period prior to loading.The Diesel generator lubrication system is designed to provide adequate engine lubrication under all operating conditions, including immediate full-load operation after starting. The system maintains the lube-oil temperature in the specified range under all loading conditions and ambient temperatures. The system is designed to Category I requirements and meets the DEMA or Quality Group D design and construction requirements except for the lube-oil cooler, which is designed and constructed in accordance with ASME B&PV Code Section III, Class 3 requirements. [UFSAR 9.5.7.1 Design Basis]
Design
References:
TS 3.8 Electrical Power Systems (SR 3.8.1.2 Note 1)UFSAR Table 3.2-1 Structures, Systems, And Components ClassificationUFSAR 9.5.7 Diesel Generator Lubrication SystemDBD R30-00 Rev I, Emergency Diesel Generator Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 71 of 106
Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 73 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3001C014 R3000 EDG 12 Motor-driven LO Pre-Lube Pump M-5734/E-3 Skid NC Positive Displacement Safety Function Basis: A 2-hp motor-driven prelube pump, which can be manually operated from the remote panel, is provided for prelubricating the engine prior to nonemergency starts.
Prelubrication is not required on emergency starts. However, a vendor-supplied prelubrication piping modification is installed and eliminates the potential for dry starts. [UFSAR 9.5.7.2 System Description] The Diesel generator lubrication system is designed to provide adequate engine lubrication under all operating conditions, including immediate full-load operation after starting. [UFSAR 9.5.7.1 Design Basis]The EDG motor-driven LO pre-lube pumps are considered skid mounted devices and have no individual IST exams. Satisfactory engine operation during periodic testing provides assurance that this pump is operating satisfactorily. This pump is verified to work in procedure 34.307.001. Bearing checks done in 34.307.001 would indicate bearing damage if this pump were not working properly. System Engineers also check for proper operation of this pump when they observe surveillance testing of the EDGs (verify slight increase in upper header lube oil pressure).
Function
Description:
The EDG LO System provides adequate engine lubrication under all operating conditions and cools the engine during operation and keeps the Lube Oil warm in standby mode. The keep warm and pre-lube pumps keep the EDG in standby readiness but are not functionally required for operation of the EDG. It provides sufficient amount of lube oil on site for continuous operation of the EDG for 7 days without replenishment. [DBD R30-00 Section 4.2.6.2 Component Function]A 2-hp motor-driven prelube pump, which can be manually operated from the remote panel, is provided for prelubricating the engine prior to nonemergency starts. Prelubrication is not required on emergency starts. However, a vendor-supplied prelubrication piping modification is installed and eliminates the potential for dry starts. This piping routes the keep-warm system so that it discharges into the upstream side of the lube-oil strainer. This will provide continuous lube oil to the lower bearings and greatly reduce voids in the lube-oil system. The solid lube-oil system will provide faster lubrication of the upper bearings on the starting of the diesel and the engine-driven pump. [UFSAR 9.5.7.2 System Description]The EDG motor-driven LO pre-lube pumps are considered skid mounted devices and have no individual IST exams. Satisfactory engine operation during periodic testing provides assurance that this pump is operating satisfactorily. This pump is verified to work in procedure 34.307.001. Bearing checks done in 34.307.001 would indicate bearing damage if this pump were not working properly. System Engineers also check for proper operation of this pump when they observe surveillance testing of the EDGs (verify slight increase in upper header lube oil pressure).
Design Basis Limits: SR 3.8.1.2 - Note 1 - All EDG starts may be preceded by an engine prelube period and followed by a warmup period prior to loading.The Diesel generator lubrication system is designed to provide adequate engine lubrication under all operating conditions, including immediate full-load operation after starting. The system maintains the lube-oil temperature in the specified range under all loading conditions and ambient temperatures. The system is designed to Category I requirements and meets the DEMA or Quality Group D design and construction requirements except for the lube-oil cooler, which is designed and constructed in accordance with ASME B&PV Code Section III, Class 3 requirements. [UFSAR 9.5.7.1 Design Basis]
Design
References:
Tech Specs 3.8 Electrical Power Systems (SR 3.8.1.2 Note 1)DBD R30-00 Rev H, Emergency Diesel GeneratorUFSAR Table 3.2-1 Structures, Systems, And Components ClassificationUFSAR 9.5.7 Diesel Generator Lubrication System Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 72 of 106
1M - Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 74 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3001C015 R3000 EDG 13 Motor-driven LO Pre-Lube Pump M-5734/E-3 Skid NC Positive Displacement Safety Function Basis: A 2-hp motor-driven prelube pump, which can be manually operated from the remote panel, is provided for prelubricating the engine prior to nonemergency starts.
Prelubrication is not required on emergency starts. However, a vendor-supplied prelubrication piping modification is installed and eliminates the potential for dry starts. [UFSAR 9.5.7.2 System Description] The Diesel generator lubrication system is designed to provide adequate engine lubrication under all operating conditions, including immediate full-load operation after starting. [UFSAR 9.5.7.1 Design Basis]The EDG motor-driven LO pre-lube pumps are considered skid mounted devices and have no individual IST exams. Satisfactory engine operation during periodic testing provides assurance that this pump is operating satisfactorily. This pump is verified to work in procedure 34.307.001. Bearing checks done in 34.307.001 would indicate bearing damage if this pump were not working properly. System Engineers also check for proper operation of this pump when they observe surveillance testing of the EDGs (verify slight increase in upper header lube oil pressure).
Function
Description:
The EDG LO System provides adequate engine lubrication under all operating conditions and cools the engine during operation and keeps the Lube Oil warm in standby mode. The keep warm and pre-lube pumps keep the EDG in standby readiness but are not functionally required for operation of the EDG. It provides sufficient amount of lube oil on site for continuous operation of the EDG for 7 days without replenishment. [DBD R30-00 Section 4.2.6.2 Component Function]A 2-hp motor-driven prelube pump, which can be manually operated from the remote panel, is provided for prelubricating the engine prior to nonemergency starts. Prelubrication is not required on emergency starts. However, a vendor-supplied prelubrication piping modification is installed and eliminates the potential for dry starts. This piping routes the keep-warm system so that it discharges into the upstream side of the lube-oil strainer. This will provide continuous lube oil to the lower bearings and greatly reduce voids in the lube-oil system. The solid lube-oil system will provide faster lubrication of the upper bearings on the starting of the diesel and the engine-driven pump. [UFSAR 9.5.7.2 System Description]The EDG motor-driven LO pre-lube pumps are considered skid mounted devices and have no individual IST exams. Satisfactory engine operation during periodic testing provides assurance that this pump is operating satisfactorily. This pump is verified to work in procedure 34.307.001. Bearing checks done in 34.307.001 would indicate bearing damage if this pump were not working properly. System Engineers also check for proper operation of this pump when they observe surveillance testing of the EDGs (verify slight increase in upper header lube oil pressure).
Design Basis Limits: SR 3.8.1.2 - Note 1 - All EDG starts may be preceded by an engine prelube period and followed by a warmup period prior to loading.The Diesel generator lubrication system is designed to provide adequate engine lubrication under all operating conditions, including immediate full-load operation after starting. The system maintains the lube-oil temperature in the specified range under all loading conditions and ambient temperatures. The system is designed to Category I requirements and meets the DEMA or Quality Group D design and construction requirements except for the lube-oil cooler, which is designed and constructed in accordance with ASME B&PV Code Section III, Class 3 requirements. [UFSAR 9.5.7.1 Design Basis]
Design
References:
Tech Specs 3.8 Electrical Power Systems (SR 3.8.1.2 Note 1)DBD R30-00 Rev H, Emergency Diesel GeneratorUFSAR Table 3.2-1 Structures, Systems, And Components ClassificationUFSAR 9.5.7 Diesel Generator Lubrication System Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 73 of 106
Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 75 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3001C016 R3000 EDG 14 Motor-driven LO Pre-Lube Pump M-5734/E-3 Skid NC Positive Displacement Safety Function Basis: A 2-hp motor-driven prelube pump, which can be manually operated from the remote panel, is provided for prelubricating the engine prior to nonemergency starts.
Prelubrication is not required on emergency starts. However, a vendor-supplied prelubrication piping modification is installed and eliminates the potential for dry starts. [UFSAR 9.5.7.2 System Description] The Diesel generator lubrication system is designed to provide adequate engine lubrication under all operating conditions, including immediate full-load operation after starting. [UFSAR 9.5.7.1 Design Basis]The EDG motor-driven LO pre-lube pumps are considered skid mounted devices and have no individual IST exams. Satisfactory engine operation during periodic testing provides assurance that this pump is operating satisfactorily. This pump is verified to work in procedure 34.307.001. Bearing checks done in 34.307.001 would indicate bearing damage if this pump were not working properly. System Engineers also check for proper operation of this pump when they observe surveillance testing of the EDGs (verify slight increase in upper header lube oil pressure).
Function
Description:
The EDG LO System provides adequate engine lubrication under all operating conditions and cools the engine during operation and keeps the Lube Oil warm in standby mode. The keep warm and pre-lube pumps keep the EDG in standby readiness but are not functionally required for operation of the EDG. It provides sufficient amount of lube oil on site for continuous operation of the EDG for 7 days without replenishment. [DBD R30-00 Section 4.2.6.2 Component Function]A 2-hp motor-driven prelube pump, which can be manually operated from the remote panel, is provided for prelubricating the engine prior to nonemergency starts. Prelubrication is not required on emergency starts. However, a vendor-supplied prelubrication piping modification is installed and eliminates the potential for dry starts. This piping routes the keep-warm system so that it discharges into the upstream side of the lube-oil strainer. This will provide continuous lube oil to the lower bearings and greatly reduce voids in the lube-oil system. The solid lube-oil system will provide faster lubrication of the upper bearings on the starting of the diesel and the engine-driven pump. [UFSAR 9.5.7.2 System Description]The EDG motor-driven LO pre-lube pumps are considered skid mounted devices and have no individual IST exams. Satisfactory engine operation during periodic testing provides assurance that this pump is operating satisfactorily. This pump is verified to work in procedure 34.307.001. Bearing checks done in 34.307.001 would indicate bearing damage if this pump were not working properly. System Engineers also check for proper operation of this pump when they observe surveillance testing of the EDGs (verify slight increase in upper header lube oil pressure).
Design Basis Limits: SR 3.8.1.2 - Note 1 - All EDG starts may be preceded by an engine prelube period and followed by a warmup period prior to loading.The Diesel generator lubrication system is designed to provide adequate engine lubrication under all operating conditions, including immediate full-load operation after starting. The system maintains the lube-oil temperature in the specified range under all loading conditions and ambient temperatures. The system is designed to Category I requirements and meets the DEMA or Quality Group D design and construction requirements except for the lube-oil cooler, which is designed and constructed in accordance with ASME B&PV Code Section III, Class 3 requirements. [UFSAR 9.5.7.1 Design Basis]
Design
References:
Tech Specs 3.8 Electrical Power Systems (SR 3.8.1.2 Note 1)DBD R30-00 Rev H, Emergency Diesel GeneratorUFSAR Table 3.2-1 Structures, Systems, And Components ClassificationUFSAR 9.5.7 Diesel Generator Lubrication System Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 74 of 106
DTIE E ergy-Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 76 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3001C017 R3000 EDG 11 Motor-driven Standby LO Pump M-5734/E-3 Skid NC Positive Displacement Safety Function Basis: The safety related function of the EDG System is to provide an onsite standby source of AC electrical power to shutdown and maintain the reactor in a safe condition under all conditions including LOCA coincident with LOOP. [DBD R30-00 Section 2.2.1 Safety Related Functions] The EDG Lube Oil System lubricates and cools the engine during operation and keeps the lube oil warm in standby mode to ensure quick start. [DBD R30-00 Section 2.1 Summary]
Function
Description:
A standby motor-driven circulation pump keeps the lube oil in the system warm (when the diesel is idle) by passing the oil over thermostatically controlled heater elements and returning the oil to the engine-driven pump discharge. [UFSAR 9.5.7.2 System Description]The lube-oil system, including lube-oil storage for each diesel generator, is completely independent of the lube-oil systems of the other diesel generators. Therefore, failure of one lube-oil system results in the loss of only one diesel generator in a division. The other diesel generator in the division, along with diesel generators in the second division, is adequate to meet the safe-shutdown requirements of the plant. [UFSAR 9.5.7.3 Safety Evaluation]The EDG LO System provides adequate engine lubrication under all operating conditions and cools the engine during operation and keeps the Lube Oil warm in standby mode. The keep warm system and pre-lube pumps keep the EDG in standby readiness but are not functionally required for operation of the EGD. It provides sufficient amount of lube oil on site for continuous operation of the EDG for 7 days without replenishment. [DBD R30-00 Section 4.2.6.2 Component Function]
Design Basis Limits: The lube-oil system is designed to Category I requirements. [UFSAR 9.5.7.3 Safety Evaluation]
Design
References:
Tech Specs 3.8 Electrical Power Systems DBD R30-00 Rev H, Emergency Diesel GeneratorUFSAR Table 3.2-1 Structures, Systems, And Components ClassificationUFSAR 9.5.7 Diesel Generator Lubrication System Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 75 of 106
Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 77 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3001C018 R3000 EDG 12 Motor-driven Standby LO Pump M-5734/E-3 Skid NC Positive Displacement Safety Function Basis: The safety related function of the EDG System is to provide an onsite standby source of AC electrical power to shutdown and maintain the reactor in a safe condition under all conditions including LOCA coincident with LOOP. [DBD R30-00 Section 2.2.1 Safety Related Functions] The EDG Lube Oil System lubricates and cools the engine during operation and keeps the lube oil warm in standby mode to ensure quick start. [DBD R30-00 Section 2.1 Summary]
Function
Description:
A standby motor-driven circulation pump keeps the lube oil in the system warm (when the diesel is idle) by passing the oil over thermostatically controlled heater elements and returning the oil to the engine-driven pump discharge. [UFSAR 9.5.7.2 System Description]The lube-oil system, including lube-oil storage for each diesel generator, is completely independent of the lube-oil systems of the other diesel generators. Therefore, failure of one lube-oil system results in the loss of only one diesel generator in a division. The other diesel generator in the division, along with diesel generators in the second division, is adequate to meet the safe-shutdown requirements of the plant. [UFSAR 9.5.7.3 Safety Evaluation]The EDG LO System provides adequate engine lubrication under all operating conditions and cools the engine during operation and keeps the Lube Oil warm in standby mode. The keep warm system and pre-lube pumps keep the EDG in standby readiness but are not functionally required for operation of the EGD. It provides sufficient amount of lube oil on site for continuous operation of the EDG for 7 days without replenishment. [DBD R30-00 Section 4.2.6.2 Component Function]
Design Basis Limits: The lube-oil system is designed to Category I requirements. [UFSAR 9.5.7.3 Safety Evaluation]
Design
References:
Tech Specs 3.8 Electrical Power Systems DBD R30-00 Rev H, Emergency Diesel GeneratorUFSAR Table 3.2-1 Structures, Systems, And Components ClassificationUFSAR 9.5.7 Diesel Generator Lubrication System Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 76 of 106
I VFermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 78 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3001C019 R3000 EDG 13 Motor-driven Standby LO Pump M-5734/E-3 Skid NC Positive Displacement Safety Function Basis: The safety related function of the EDG System is to provide an onsite standby source of AC electrical power to shutdown and maintain the reactor in a safe condition under all conditions including LOCA coincident with LOOP. [DBD R30-00 Section 2.2.1 Safety Related Functions] The EDG Lube Oil System lubricates and cools the engine during operation and keeps the lube oil warm in standby mode to ensure quick start. [DBD R30-00 Section 2.1 Summary]
Function
Description:
A standby motor-driven circulation pump keeps the lube oil in the system warm (when the diesel is idle) by passing the oil over thermostatically controlled heater elements and returning the oil to the engine-driven pump discharge. [UFSAR 9.5.7.2 System Description]The lube-oil system, including lube-oil storage for each diesel generator, is completely independent of the lube-oil systems of the other diesel generators. Therefore, failure of one lube-oil system results in the loss of only one diesel generator in a division. The other diesel generator in the division, along with diesel generators in the second division, is adequate to meet the safe-shutdown requirements of the plant. [UFSAR 9.5.7.3 Safety Evaluation]The EDG LO System provides adequate engine lubrication under all operating conditions and cools the engine during operation and keeps the Lube Oil warm in standby mode. The keep warm system and pre-lube pumps keep the EDG in standby readiness but are not functionally required for operation of the EGD. It provides sufficient amount of lube oil on site for continuous operation of the EDG for 7 days without replenishment. [DBD R30-00 Section 4.2.6.2 Component Function]
Design Basis Limits: The lube-oil system is designed to Category I requirements. [UFSAR 9.5.7.3 Safety Evaluation]
Design
References:
Tech Specs 3.8 Electrical Power Systems DBD R30-00 Rev H, Emergency Diesel GeneratorUFSAR Table 3.2-1 Structures, Systems, And Components ClassificationUFSAR 9.5.7 Diesel Generator Lubrication System Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 77 of 106
- Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 79 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3001C020 R3000 EDG 14 Motor-driven Standby LO Pump M-5734/E-3 Skid NC Positive Displacement Safety Function Basis: The safety related function of the EDG System is to provide an onsite standby source of AC electrical power to shutdown and maintain the reactor in a safe condition under all conditions including LOCA coincident with LOOP. [DBD R30-00 Section 2.2.1 Safety Related Functions] The EDG Lube Oil System lubricates and cools the engine during operation and keeps the lube oil warm in standby mode to ensure quick start. [DBD R30-00 Section 2.1 Summary]
Function
Description:
A standby motor-driven circulation pump keeps the lube oil in the system warm (when the diesel is idle) by passing the oil over thermostatically controlled heater elements and returning the oil to the engine-driven pump discharge. [UFSAR 9.5.7.2 System Description]The lube-oil system, including lube-oil storage for each diesel generator, is completely independent of the lube-oil systems of the other diesel generators. Therefore, failure of one lube-oil system results in the loss of only one diesel generator in a division. The other diesel generator in the division, along with diesel generators in the second division, is adequate to meet the safe-shutdown requirements of the plant. [UFSAR 9.5.7.3 Safety Evaluation]The EDG LO System provides adequate engine lubrication under all operating conditions and cools the engine during operation and keeps the Lube Oil warm in standby mode. The keep warm system and pre-lube pumps keep the EDG in standby readiness but are not functionally required for operation of the EGD. It provides sufficient amount of lube oil on site for continuous operation of the EDG for 7 days without replenishment. [DBD R30-00 Section 4.2.6.2 Component Function]
Design Basis Limits: The lube-oil system is designed to Category I requirements. [UFSAR 9.5.7.3 Safety Evaluation]
Design
References:
Tech Specs 3.8 Electrical Power Systems DBD R30-00 Rev H, Emergency Diesel GeneratorUFSAR Table 3.2-1 Structures, Systems, And Components ClassificationUFSAR 9.5.7 Diesel Generator Lubrication System Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 78 of 106
DI e-- Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 80 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3001C021 R3000 EDG 11 Motor-driven Fuel Oil Standby Pump M-5734/F-6 Skid 3 Positive Displacement Safety Function Basis: The safety related function of the EDG System is to provide an outside standby source of AC electrical power to shutdown and maintain the reactor in a safe condition under all conditions including LOCA coincident with LOOP. [DBD R30-00 Section 2.2.1 Safety Related Functions] The engine driven pump is safety related and required to operate in order to mitigate a design basis accident. An electric motor driven fuel pump is also provided to purge air from the fuel line following maintenance on the fuel oil system. The electric motor driven fuel pump will receive a start signal if a low pressure condition exists on the supply side of the duplex filter. Although the electric motor driven pump is not credited to operate during a design basis accident, it is considered to be a safety related pump. [UFSAR 9.5.4.2 System Description]The EDG motor-driven Standby FO pumps are considered skid-mounted components and have no individual IST exams. Satisfactory operation of the pump during various EDG testing provides assurance that this pump is operating satisfactory. Procedure 34.307.001 has steps for operations to run the motor-driven fuel pump until system pressure has stabilized greater than 25 psig.
Function
Description:
The engine driven pump is safety related and required to operate in order to mitigate a design basis accident. An electric motor driven fuel pump is also provided to purge air from the fuel line following maintenance on the fuel oil system. The electric motor driven fuel pump will receive a start signal if a low pressure condition exists on the supply side of the duplex filter. [UFSAR 9.5.4.2 System Description]The EDG motor-driven Standby FO pumps are considered skid-mounted components and have no individual IST exams. Satisfactory operation of the pump during various EDG testing provides assurance that this pump is operating satisfactory.
Design Basis Limits: Except for the fill vent and drain lines, the EDG Fuel Oil System, piping and components up to the diesel engine interface shall be designed to ASME Section III, Class 3 requirements as shown in UFSAR Figures 9.5-4, 9.5-5 and 9.5-6. The fill, vent and drain lines shall be designed to ANSI B31.1 requirements. [DBD R30-00 Section 4.1.8.2 Mechanical Codes and Standards]The EDG fuel oil fill, vent and drain lines, and exhaust piping downstream of the exhaust muffler shall be designed to Seismic Category II/I requirements. [DBD R30-00 Section 2.3 Classification]
Design
References:
DBD R30-00 Rev H, Emergency Diesel GeneratorUFSAR Table 3.2-1 Structures, Systems, And Components ClassificationUFSAR 9.5.4 Diesel Generator Fuel-Oil Storage and Transfer SystemTech Specs 3.8 Electrical Power Systems Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 79 of 106
Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 81 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3001C022 R3000 EDG 12 Motor-driven Fuel Oil Standby Pump M-5734/F-6 Skid 3 Positive Displacement Safety Function Basis: The safety related function of the EDG System is to provide an outside standby source of AC electrical power to shutdown and maintain the reactor in a safe condition under all conditions including LOCA coincident with LOOP. [DBD R30-00 Section 2.2.1 Safety Related Functions] The engine driven pump is safety related and required to operate in order to mitigate a design basis accident. An electric motor driven fuel pump is also provided to purge air from the fuel line following maintenance on the fuel oil system. The electric motor driven fuel pump will receive a start signal if a low pressure condition exists on the supply side of the duplex filter. Although the electric motor driven pump is not credited to operate during a design basis accident, it is considered to be a safety related pump. [UFSAR 9.5.4.2 System Description]The EDG motor-driven Standby FO pumps are considered skid-mounted components and have no individual IST exams. Satisfactory operation of the pump during various EDG testing provides assurance that this pump is operating satisfactory. Procedure 34.307.001 has steps for operations to run the motor-driven fuel pump until system pressure has stabilized greater than 25 psig.
Function
Description:
The engine driven pump is safety related and required to operate in order to mitigate a design basis accident. An electric motor driven fuel pump is also provided to purge air from the fuel line following maintenance on the fuel oil system. The electric motor driven fuel pump will receive a start signal if a low pressure condition exists on the supply side of the duplex filter. [UFSAR 9.5.4.2 System Description]The EDG motor-driven Standby FO pumps are considered skid-mounted components and have no individual IST exams. Satisfactory operation of the pump during various EDG testing provides assurance that this pump is operating satisfactory.
Design Basis Limits: Except for the fill vent and drain lines, the EDG Fuel Oil System, piping and components up to the diesel engine interface shall be designed to ASME Section III, Class 3 requirements as shown in UFSAR Figures 9.5-4, 9.5-5 and 9.5-6. The fill, vent and drain lines shall be designed to ANSI B31.1 requirements. [DBD R30-00 Section 4.1.8.2 Mechanical Codes and Standards]The EDG fuel oil fill, vent and drain lines, and exhaust piping downstream of the exhaust muffler shall be designed to Seismic Category II/I requirements. [DBD R30-00 Section 2.3 Classification]
Design
References:
DBD R30-00 Rev H, Emergency Diesel GeneratorUFSAR Table 3.2-1 Structures, Systems, And Components ClassificationUFSAR 9.5.4 Diesel Generator Fuel-Oil Storage and Transfer SystemTech Specs 3.8 Electrical Power Systems Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 80 of 106
an -n r Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 82 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3001C023 R3000 EDG 13 Motor-driven Fuel Oil Standby Pump M-5734/F-6 Skid 3 Positive Displacement Safety Function Basis: The safety related function of the EDG System is to provide an outside standby source of AC electrical power to shutdown and maintain the reactor in a safe condition under all conditions including LOCA coincident with LOOP. [DBD R30-00 Section 2.2.1 Safety Related Functions] The engine driven pump is safety related and required to operate in order to mitigate a design basis accident. An electric motor driven fuel pump is also provided to purge air from the fuel line following maintenance on the fuel oil system. The electric motor driven fuel pump will receive a start signal if a low pressure condition exists on the supply side of the duplex filter. Although the electric motor driven pump is not credited to operate during a design basis accident, it is considered to be a safety related pump. [UFSAR 9.5.4.2 System Description]The EDG motor-driven Standby FO pumps are considered skid-mounted components and have no individual IST exams. Satisfactory operation of the pump during various EDG testing provides assurance that this pump is operating satisfactory. Procedure 34.307.001 has steps for operations to run the motor-driven fuel pump until system pressure has stabilized greater than 25 psig.
Function
Description:
The engine driven pump is safety related and required to operate in order to mitigate a design basis accident. An electric motor driven fuel pump is also provided to purge air from the fuel line following maintenance on the fuel oil system. The electric motor driven fuel pump will receive a start signal if a low pressure condition exists on the supply side of the duplex filter. [UFSAR 9.5.4.2 System Description]The EDG motor-driven Standby FO pumps are considered skid-mounted components and have no individual IST exams. Satisfactory operation of the pump during various EDG testing provides assurance that this pump is operating satisfactory.
Design Basis Limits: Except for the fill vent and drain lines, the EDG Fuel Oil System, piping and components up to the diesel engine interface shall be designed to ASME Section III, Class 3 requirements as shown in UFSAR Figures 9.5-4, 9.5-5 and 9.5-6. The fill, vent and drain lines shall be designed to ANSI B31.1 requirements. [DBD R30-00 Section 4.1.8.2 Mechanical Codes and Standards]The EDG fuel oil fill, vent and drain lines, and exhaust piping downstream of the exhaust muffler shall be designed to Seismic Category II/I requirements. [DBD R30-00 Section 2.3 Classification]
Design
References:
DBD R30-00 Rev H, Emergency Diesel GeneratorUFSAR Table 3.2-1 Structures, Systems, And Components ClassificationUFSAR 9.5.4 Diesel Generator Fuel-Oil Storage and Transfer SystemTech Specs 3.8 Electrical Power Systems Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 81 of 106
.70W an mFermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 83 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3001C024 R3000 EDG 14 Motor-driven Fuel Oil Standby Pump M-5734/F-6 Skid 3 Positive Displacement Safety Function Basis: The safety related function of the EDG System is to provide an outside standby source of AC electrical power to shutdown and maintain the reactor in a safe condition under all conditions including LOCA coincident with LOOP. [DBD R30-00 Section 2.2.1 Safety Related Functions] The engine driven pump is safety related and required to operate in order to mitigate a design basis accident. An electric motor driven fuel pump is also provided to purge air from the fuel line following maintenance on the fuel oil system. The electric motor driven fuel pump will receive a start signal if a low pressure condition exists on the supply side of the duplex filter. Although the electric motor driven pump is not credited to operate during a design basis accident, it is considered to be a safety related pump. [UFSAR 9.5.4.2 System Description]The EDG motor-driven Standby FO pumps are considered skid-mounted components and have no individual IST exams. Satisfactory operation of the pump during various EDG testing provides assurance that this pump is operating satisfactory. Procedure 34.307.001 has steps for operations to run the motor-driven fuel pump until system pressure has stabilized greater than 25 psig.
Function
Description:
The engine driven pump is safety related and required to operate in order to mitigate a design basis accident. An electric motor driven fuel pump is also provided to purge air from the fuel line following maintenance on the fuel oil system. The electric motor driven fuel pump will receive a start signal if a low pressure condition exists on the supply side of the duplex filter. [UFSAR 9.5.4.2 System Description]The EDG motor-driven Standby FO pumps are considered skid-mounted components and have no individual IST exams. Satisfactory operation of the pump during various EDG testing provides assurance that this pump is operating satisfactory.
Design Basis Limits: Except for the fill vent and drain lines, the EDG Fuel Oil System, piping and components up to the diesel engine interface shall be designed to ASME Section III, Class 3 requirements as shown in UFSAR Figures 9.5-4, 9.5-5 and 9.5-6. The fill, vent and drain lines shall be designed to ANSI B31.1 requirements. [DBD R30-00 Section 4.1.8.2 Mechanical Codes and Standards]The EDG fuel oil fill, vent and drain lines, and exhaust piping downstream of the exhaust muffler shall be designed to Seismic Category II/I requirements. [DBD R30-00 Section 2.3 Classification]
Design
References:
DBD R30-00 Rev H, Emergency Diesel GeneratorUFSAR Table 3.2-1 Structures, Systems, And Components ClassificationUFSAR 9.5.4 Diesel Generator Fuel-Oil Storage and Transfer SystemTech Specs 3.8 Electrical Power Systems Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 82 of 106
DTIE ergFermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 84 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3001C025 R3000 EDG 11 Motor-driven Standby Coolant Pump M-5734/B-7 Skid NC Centrifugal Safety Function Basis: The diesel generator cooling system is designed to provide adequate cooling water to remove the heat given off by the lube-oil coolers, inlet air coolers, and the engine jacket coolant heat exchangers. The engine jacket coolant system, which is a closed loop system, removes heat from the engine and transfers it to the diesel generator service water system. [UFSAR 9.5.5.1 Design Basis]To ensure quick starts, a motor-driven standby circulating pump maintains the jacket coolant temperature at approximately 110 degrees F by pumping the coolant through a thermostat-controlled electric heater. [UFSAR 9.5.5.2 System Description]The EDG Jacket Cooling Water System is a closed loop system that removes heat from the engine and transfers it to the EDG Service Water System. It also maintains the Jacket Coolant System water warm in standby mode to ensure quick start. [DBD R30-00 Section 2.1 Summary]This pump is verified to work by jacket coolant temperature being maintained in standby. If the pump is not working, standby jacket coolant temperature will drop. Low jacket coolant temperature is alarmed. Standby jacket coolant temperature is recorded daily in Operator rounds. Standby jacket coolant temperature is trended by System Engineering. The system engineers EDG system monitoring plan contains additional details on data collection and analysis. [DBD R30-00 Section 4.2.8] [UFSAR 9.5.5]The EDG motor-driven Standby Coolant pumps are considered skid mounted devices and have no individual IST exams. Satisfactory engine operation during periodic testing provides assurance that this pump is operating satisfactorily, and this pump is operating when the engine is in the standby condition, and does not operate when the EDG is running.
Function
Description:
The EDG motor-driven Standby Coolant pumps are considered skid mounted devices and have no individual IST exams. Satisfactory engine operation during periodic testing provides assurance that this pump is operating satisfactorily. This pump is verified to work by jacket coolant temperature being maintained in standby. If the pump is not working, standby jacket coolant temperature will drop. Low jacket coolant temperature is alarmed. Standby jacket coolant temperature is recorded daily in Operator rounds. Standby jacket coolant temperature is trended by System Engineering. The system engineers EDG system monitoring plan contains additional details on data collection and analysis. The heaters keep the cooling water warm during standby operation. [DBD R30-00 Section 4.2.8] [UFSAR 9.5.5]
Design Basis Limits: The jacket coolant system is designed to Category I requirements and the system piping, valves, and heat exchangers meet either the requirements of the ASME B&PV Code Section III, Class 3, the DEMA standards, or Group D (ANSI B31.1), and are seismically supported. [UFSAR 9.5.5.1 Design Basis]All on-skid piping and components of Jacket Water and Air Coolant System are classified as QA Level 1 and Seismic Category I. All skid-mounted components and piping that are classified as Class 3 are constructed to Subsection ND of the ASME Code,Section III, and all addenda to and including Summer 1973. The off-skid vent and equalizing lines between the expansion tank and skid were analyzed and installed to Seismic Category I as a response to FSAR question 222.62d. Off-skid piping is non-Q designed to the Power Piping Code, ANSI B31.1.0. The off-skid expansion tank is non-ASME, Seismic Category I, QA Level 1. [DBD R30-00 Section 2.3 Classification]Except for the two jacket water system vent lines and the equalizing line to the expansion tank, EDG service water systems, piping and components up to the diesel engine interface shall be designed to the requirements of ASME Section III, Class 3 as shown in UFSAR Figures 9.2-6, 9.5-7, 9.5-8 and 9.5-9. [DBD R30-00 Section 4.1.8.2 Mechanical Codes and Standards]
Design
References:
DBD R30-00 Rev H, Emergency Diesel GeneratorUFSAR Table 3.2-1 Structures, Systems, And Components ClassificationUFSAR 9.5.5 Diesel Generator Cooling Water SystemUFSAR Figure 9.5-7 Diesel Generator Jacket Coolant SystemTech Specs 3.8 Electrical Power Systems Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 83 of 106
Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 85 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3001C026 R3000 EDG 12 Motor-driven Standby Coolant Pump M-5734/B-7 Skid NC Centrifugal Safety Function Basis: The diesel generator cooling system is designed to provide adequate cooling water to remove the heat given off by the lube-oil coolers, inlet air coolers, and the engine jacket coolant heat exchangers. The engine jacket coolant system, which is a closed loop system, removes heat from the engine and transfers it to the diesel generator service water system. [UFSAR 9.5.5.1 Design Basis]To ensure quick starts, a motor-driven standby circulating pump maintains the jacket coolant temperature at approximately 110 degrees F by pumping the coolant through a thermostat-controlled electric heater. [UFSAR 9.5.5.2 System Description]The EDG Jacket Cooling Water System is a closed loop system that removes heat from the engine and transfers it to the EDG Service Water System. It also maintains the Jacket Coolant System water warm in standby mode to ensure quick start. [DBD R30-00 Section 2.1 Summary]This pump is verified to work by jacket coolant temperature being maintained in standby. If the pump is not working, standby jacket coolant temperature will drop. Low jacket coolant temperature is alarmed. Standby jacket coolant temperature is recorded daily in Operator rounds. Standby jacket coolant temperature is trended by System Engineering. The system engineers EDG system monitoring plan contains additional details on data collection and analysis. [DBD R30-00 Section 4.2.8] [UFSAR 9.5.5]The EDG motor-driven Standby Coolant pumps are considered skid mounted devices and have no individual IST exams. Satisfactory engine operation during periodic testing provides assurance that this pump is operating satisfactorily, and this pump is operating when the engine is in the standby condition, and does not operate when the EDG is running.
Function
Description:
The EDG motor-driven Standby Coolant pumps are considered skid mounted devices and have no individual IST exams. Satisfactory engine operation during periodic testing provides assurance that this pump is operating satisfactorily. This pump is verified to work by jacket coolant temperature being maintained in standby. If the pump is not working, standby jacket coolant temperature will drop. Low jacket coolant temperature is alarmed. Standby jacket coolant temperature is recorded daily in Operator rounds. Standby jacket coolant temperature is trended by System Engineering. The system engineers EDG system monitoring plan contains additional details on data collection and analysis. The heaters keep the cooling water warm during standby operation. [DBD R30-00 Section 4.2.8] [UFSAR 9.5.5]
Design Basis Limits: The jacket coolant system is designed to Category I requirements and the system piping, valves, and heat exchangers meet either the requirements of the ASME B&PV Code Section III, Class 3, the DEMA standards, or Group D (ANSI B31.1), and are seismically supported. [UFSAR 9.5.5.1 Design Basis]All on-skid piping and components of Jacket Water and Air Coolant System are classified as QA Level 1 and Seismic Category I. All skid-mounted components and piping that are classified as Class 3 are constructed to Subsection ND of the ASME Code,Section III, and all addenda to and including Summer 1973. The off-skid vent and equalizing lines between the expansion tank and skid were analyzed and installed to Seismic Category I as a response to FSAR question 222.62d. Off-skid piping is non-Q designed to the Power Piping Code, ANSI B31.1.0. The off-skid expansion tank is non-ASME, Seismic Category I, QA Level 1. [DBD R30-00 Section 2.3 Classification]Except for the two jacket water system vent lines and the equalizing line to the expansion tank, EDG service water systems, piping and components up to the diesel engine interface shall be designed to the requirements of ASME Section III, Class 3 as shown in UFSAR Figures 9.2-6, 9.5-7, 9.5-8 and 9.5-9. [DBD R30-00 Section 4.1.8.2 Mechanical Codes and Standards]
Design
References:
DBD R30-00 Rev H, Emergency Diesel GeneratorUFSAR Table 3.2-1 Structures, Systems, And Components ClassificationUFSAR 9.5.5 Diesel Generator Cooling Water SystemUFSAR Figure 9.5-7 Diesel Generator Jacket Coolant SystemTech Specs 3.8 Electrical Power Systems Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 84 of 106
Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 86 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3001C027 R3000 EDG 13 Motor-driven Standby Coolant Pump M-5734/B-7 Skid NC Centrifugal Safety Function Basis: The diesel generator cooling system is designed to provide adequate cooling water to remove the heat given off by the lube-oil coolers, inlet air coolers, and the engine jacket coolant heat exchangers. The engine jacket coolant system, which is a closed loop system, removes heat from the engine and transfers it to the diesel generator service water system. [UFSAR 9.5.5.1 Design Basis]To ensure quick starts, a motor-driven standby circulating pump maintains the jacket coolant temperature at approximately 110 degrees F by pumping the coolant through a thermostat-controlled electric heater. [UFSAR 9.5.5.2 System Description]The EDG Jacket Cooling Water System is a closed loop system that removes heat from the engine and transfers it to the EDG Service Water System. It also maintains the Jacket Coolant System water warm in standby mode to ensure quick start. [DBD R30-00 Section 2.1 Summary]This pump is verified to work by jacket coolant temperature being maintained in standby. If the pump is not working, standby jacket coolant temperature will drop. Low jacket coolant temperature is alarmed. Standby jacket coolant temperature is recorded daily in Operator rounds. Standby jacket coolant temperature is trended by System Engineering. The system engineers EDG system monitoring plan contains additional details on data collection and analysis. [DBD R30-00 Section 4.2.8] [UFSAR 9.5.5]The EDG motor-driven Standby Coolant pumps are considered skid mounted devices and have no individual IST exams. Satisfactory engine operation during periodic testing provides assurance that this pump is operating satisfactorily, and this pump is operating when the engine is in the standby condition, and does not operate when the EDG is running.
Function
Description:
The EDG motor-driven Standby Coolant pumps are considered skid mounted devices and have no individual IST exams. Satisfactory engine operation during periodic testing provides assurance that this pump is operating satisfactorily. This pump is verified to work by jacket coolant temperature being maintained in standby. If the pump is not working, standby jacket coolant temperature will drop. Low jacket coolant temperature is alarmed. Standby jacket coolant temperature is recorded daily in Operator rounds. Standby jacket coolant temperature is trended by System Engineering. The system engineers EDG system monitoring plan contains additional details on data collection and analysis. The heaters keep the cooling water warm during standby operation. [DBD R30-00 Section 4.2.8] [UFSAR 9.5.5]
Design Basis Limits: The jacket coolant system is designed to Category I requirements and the system piping, valves, and heat exchangers meet either the requirements of the ASME B&PV Code Section III, Class 3, the DEMA standards, or Group D (ANSI B31.1), and are seismically supported. [UFSAR 9.5.5.1 Design Basis]All on-skid piping and components of Jacket Water and Air Coolant System are classified as QA Level 1 and Seismic Category I. All skid-mounted components and piping that are classified as Class 3 are constructed to Subsection ND of the ASME Code,Section III, and all addenda to and including Summer 1973. The off-skid vent and equalizing lines between the expansion tank and skid were analyzed and installed to Seismic Category I as a response to FSAR question 222.62d. Off-skid piping is non-Q designed to the Power Piping Code, ANSI B31.1.0. The off-skid expansion tank is non-ASME, Seismic Category I, QA Level 1. [DBD R30-00 Section 2.3 Classification]Except for the two jacket water system vent lines and the equalizing line to the expansion tank, EDG service water systems, piping and components up to the diesel engine interface shall be designed to the requirements of ASME Section III, Class 3 as shown in UFSAR Figures 9.2-6, 9.5-7, 9.5-8 and 9.5-9. [DBD R30-00 Section 4.1.8.2 Mechanical Codes and Standards]
Design
References:
DBD R30-00 Rev H, Emergency Diesel GeneratorUFSAR Table 3.2-1 Structures, Systems, And Components ClassificationUFSAR 9.5.5 Diesel Generator Cooling Water SystemUFSAR Figure 9.5-7 Diesel Generator Jacket Coolant SystemTech Specs 3.8 Electrical Power Systems Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 85 of 106
- Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 87 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3001C028 R3000 EDG 14 Motor-driven Standby Coolant Pump M-5734/B-7 Skid NC Centrifugal Safety Function Basis: The diesel generator cooling system is designed to provide adequate cooling water to remove the heat given off by the lube-oil coolers, inlet air coolers, and the engine jacket coolant heat exchangers. The engine jacket coolant system, which is a closed loop system, removes heat from the engine and transfers it to the diesel generator service water system. [UFSAR 9.5.5.1 Design Basis]To ensure quick starts, a motor-driven standby circulating pump maintains the jacket coolant temperature at approximately 110 degrees F by pumping the coolant through a thermostat-controlled electric heater. [UFSAR 9.5.5.2 System Description]The EDG Jacket Cooling Water System is a closed loop system that removes heat from the engine and transfers it to the EDG Service Water System. It also maintains the Jacket Coolant System water warm in standby mode to ensure quick start. [DBD R30-00 Section 2.1 Summary]This pump is verified to work by jacket coolant temperature being maintained in standby. If the pump is not working, standby jacket coolant temperature will drop. Low jacket coolant temperature is alarmed. Standby jacket coolant temperature is recorded daily in Operator rounds. Standby jacket coolant temperature is trended by System Engineering. The system engineers EDG system monitoring plan contains additional details on data collection and analysis. [DBD R30-00 Section 4.2.8] [UFSAR 9.5.5]The EDG motor-driven Standby Coolant pumps are considered skid mounted devices and have no individual IST exams. Satisfactory engine operation during periodic testing provides assurance that this pump is operating satisfactorily, and this pump is operating when the engine is in the standby condition, and does not operate when the EDG is running.
Function
Description:
The EDG motor-driven Standby Coolant pumps are considered skid mounted devices and have no individual IST exams. Satisfactory engine operation during periodic testing provides assurance that this pump is operating satisfactorily. This pump is verified to work by jacket coolant temperature being maintained in standby. If the pump is not working, standby jacket coolant temperature will drop. Low jacket coolant temperature is alarmed. Standby jacket coolant temperature is recorded daily in Operator rounds. Standby jacket coolant temperature is trended by System Engineering. The system engineers EDG system monitoring plan contains additional details on data collection and analysis. The heaters keep the cooling water warm during standby operation. [DBD R30-00 Section 4.2.8] [UFSAR 9.5.5]
Design Basis Limits: The jacket coolant system is designed to Category I requirements and the system piping, valves, and heat exchangers meet either the requirements of the ASME B&PV Code Section III, Class 3, the DEMA standards, or Group D (ANSI B31.1), and are seismically supported. [UFSAR 9.5.5.1 Design Basis]All on-skid piping and components of Jacket Water and Air Coolant System are classified as QA Level 1 and Seismic Category I. All skid-mounted components and piping that are classified as Class 3 are constructed to Subsection ND of the ASME Code,Section III, and all addenda to and including Summer 1973. The off-skid vent and equalizing lines between the expansion tank and skid were analyzed and installed to Seismic Category I as a response to FSAR question 222.62d. Off-skid piping is non-Q designed to the Power Piping Code, ANSI B31.1.0. The off-skid expansion tank is non-ASME, Seismic Category I, QA Level 1. [DBD R30-00 Section 2.3 Classification]Except for the two jacket water system vent lines and the equalizing line to the expansion tank, EDG service water systems, piping and components up to the diesel engine interface shall be designed to the requirements of ASME Section III, Class 3 as shown in UFSAR Figures 9.2-6, 9.5-7, 9.5-8 and 9.5-9. [DBD R30-00 Section 4.1.8.2 Mechanical Codes and Standards]
Design
References:
DBD R30-00 Rev H, Emergency Diesel GeneratorUFSAR Table 3.2-1 Structures, Systems, And Components ClassificationUFSAR 9.5.5 Diesel Generator Cooling Water SystemUFSAR Figure 9.5-7 Diesel Generator Jacket Coolant SystemTech Specs 3.8 Electrical Power Systems Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 86 of 106
SDrFermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 88 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3001C029 R3000 EDG 11 Engine-driven Fuel Oil Pump M-5734/F-5 Skid NC Positive Displacement Safety Function Basis: The safety related function of the EDG System is to provide an outside standby source of AC electrical power to shutdown and maintain the reactor in a safe condition under all conditions including LOCA coincident with LOOP. [DBD R30-00 Section 2.2.1 Safety Related Functions] The engine driven pump is safety related and required to operate in order to mitigate a design basis accident. An electric motor driven fuel pump is also provided to purge air from the fuel line following maintenance on the fuel oil system. The electric motor driven fuel pump will receive a start signal if a low pressure condition exists on the supply side of the duplex filter. Although the electric motor driven pump is not credited to operate during a design basis accident, it is considered to be a safety related pump. [UFSAR 9.5.4.2 System Description]The EDG motor-driven Standby FO pumps are considered skid-mounted components and have no individual IST exams. Satisfactory operation of the pump during various EDG testing provides assurance that this pump is operating satisfactory. Procedure 34.307.001 has steps for operations to run the motor-driven fuel pump until system pressure has stabilized greater than 25 psig.
Function
Description:
The engine driven Fuel Oil Pump is safety related and required to operate in order to mitigate a design basis accident. An electric motor driven fuel pump is also provided to purge air from the fuel line following maintenance on the fuel oil system. The electric motor driven fuel pump will receive a start signal if a low pressure condition exists on the supply side of the duplex filter. [UFSAR 9.5.4.2 System Description]The EDG engine-driven FO pumps are considered skid-mounted components and have no individual IST exams.
Satisfactory operation of the pump during various EDG testing provides assurance that this pump is operating satisfactory.
Design Basis Limits: Except for the fill vent and drain lines, the EDG Fuel Oil System, piping and components up to the diesel engine interface shall be designed to ASME Section III, Class 3 requirements as shown in UFSAR Figures 9.5-4, 9.5-5 and 9.5-6. The fill, vent and drain lines shall be designed to ANSI B31.1 requirements. [DBD R30-00 Section 4.1.8.2 Mechanical Codes and Standards]Pump discharges 9 gpm at 35 psig through a duplex fuel oil filter. [ST-OP-315-0065-001]The EDG fuel oil fill, vent and drain lines, and exhaust piping downstream of the exhaust muffler shall be designed to Seismic Category II/I requirements. [DBD R30-00 Section 2.3 Classification]
Design
References:
DBD R30-00 Rev H, Emergency Diesel GeneratorUFSAR Table 3.2-1 Structures, Systems, And Components ClassificationUFSAR 9.5.4 Diesel Generator Fuel-Oil Storage and Transfer SystemUFSAR Figure 9.5-6 Engine-Skid Mounted Diesel-Fuel-Oil SystemTS 3.8 Electrical Power SystemsST-OP-315-0065-001 Revision 30 Emergency Diesel Generator Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 87 of 106
Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 89 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3001C030 R3000 EDG 12 Engine-driven Fuel Oil Pump M-5734/F-5 Skid NC Positive Displacement Safety Function Basis: The safety related function of the EDG System is to provide an outside standby source of AC electrical power to shutdown and maintain the reactor in a safe condition under all conditions including LOCA coincident with LOOP. [DBD R30-00 Section 2.2.1 Safety Related Functions] The engine driven pump is safety related and required to operate in order to mitigate a design basis accident. An electric motor driven fuel pump is also provided to purge air from the fuel line following maintenance on the fuel oil system. The electric motor driven fuel pump will receive a start signal if a low pressure condition exists on the supply side of the duplex filter. Although the electric motor driven pump is not credited to operate during a design basis accident, it is considered to be a safety related pump. [UFSAR 9.5.4.2 System Description]The EDG motor-driven Standby FO pumps are considered skid-mounted components and have no individual IST exams. Satisfactory operation of the pump during various EDG testing provides assurance that this pump is operating satisfactory. Procedure 34.307.001 has steps for operations to run the motor-driven fuel pump until system pressure has stabilized greater than 25 psig.
Function
Description:
The engine driven Fuel Oil Pump is safety related and required to operate in order to mitigate a design basis accident. An electric motor driven fuel pump is also provided to purge air from the fuel line following maintenance on the fuel oil system. The electric motor driven fuel pump will receive a start signal if a low pressure condition exists on the supply side of the duplex filter. [UFSAR 9.5.4.2 System Description]The EDG engine-driven FO pumps are considered skid-mounted components and have no individual IST exams.
Satisfactory operation of the pump during various EDG testing provides assurance that this pump is operating satisfactory.
Design Basis Limits: Except for the fill vent and drain lines, the EDG Fuel Oil System, piping and components up to the diesel engine interface shall be designed to ASME Section III, Class 3 requirements as shown in UFSAR Figures 9.5-4, 9.5-5 and 9.5-6. The fill, vent and drain lines shall be designed to ANSI B31.1 requirements. [DBD R30-00 Section 4.1.8.2 Mechanical Codes and Standards]Pump discharges 9 gpm at 35 psig through a duplex fuel oil filter. [ST-OP-315-0065-001]The EDG fuel oil fill, vent and drain lines, and exhaust piping downstream of the exhaust muffler shall be designed to Seismic Category II/I requirements. [DBD R30-00 Section 2.3 Classification]
Design
References:
DBD R30-00 Rev H, Emergency Diesel GeneratorUFSAR Table 3.2-1 Structures, Systems, And Components ClassificationUFSAR 9.5.4 Diesel Generator Fuel-Oil Storage and Transfer SystemUFSAR Figure 9.5-6 Engine-Skid Mounted Diesel-Fuel-Oil SystemTS 3.8 Electrical Power SystemsST-OP-315-0065-001 Revision 30 Emergency Diesel Generator Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 88 of 106
1M - Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 90 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3001C031 R3000 EDG 13 Engine-driven Fuel Oil Pump M-5734/F-5 Skid NC Positive Displacement Safety Function Basis: The safety related function of the EDG System is to provide an outside standby source of AC electrical power to shutdown and maintain the reactor in a safe condition under all conditions including LOCA coincident with LOOP. [DBD R30-00 Section 2.2.1 Safety Related Functions] The engine driven pump is safety related and required to operate in order to mitigate a design basis accident. An electric motor driven fuel pump is also provided to purge air from the fuel line following maintenance on the fuel oil system. The electric motor driven fuel pump will receive a start signal if a low pressure condition exists on the supply side of the duplex filter. Although the electric motor driven pump is not credited to operate during a design basis accident, it is considered to be a safety related pump. [UFSAR 9.5.4.2 System Description]The EDG motor-driven Standby FO pumps are considered skid-mounted components and have no individual IST exams. Satisfactory operation of the pump during various EDG testing provides assurance that this pump is operating satisfactory. Procedure 34.307.001 has steps for operations to run the motor-driven fuel pump until system pressure has stabilized greater than 25 psig.
Function
Description:
The engine driven Fuel Oil Pump is safety related and required to operate in order to mitigate a design basis accident. An electric motor driven fuel pump is also provided to purge air from the fuel line following maintenance on the fuel oil system. The electric motor driven fuel pump will receive a start signal if a low pressure condition exists on the supply side of the duplex filter. [UFSAR 9.5.4.2 System Description]The EDG engine-driven FO pumps are considered skid-mounted components and have no individual IST exams.
Satisfactory operation of the pump during various EDG testing provides assurance that this pump is operating satisfactory.
Design Basis Limits: Except for the fill vent and drain lines, the EDG Fuel Oil System, piping and components up to the diesel engine interface shall be designed to ASME Section III, Class 3 requirements as shown in UFSAR Figures 9.5-4, 9.5-5 and 9.5-6. The fill, vent and drain lines shall be designed to ANSI B31.1 requirements. [DBD R30-00 Section 4.1.8.2 Mechanical Codes and Standards]Pump discharges 9 gpm at 35 psig through a duplex fuel oil filter. [ST-OP-315-0065-001]The EDG fuel oil fill, vent and drain lines, and exhaust piping downstream of the exhaust muffler shall be designed to Seismic Category II/I requirements. [DBD R30-00 Section 2.3 Classification]
Design
References:
DBD R30-00 Rev H, Emergency Diesel GeneratorUFSAR Table 3.2-1 Structures, Systems, And Components ClassificationUFSAR 9.5.4 Diesel Generator Fuel-Oil Storage and Transfer SystemUFSAR Figure 9.5-6 Engine-Skid Mounted Diesel-Fuel-Oil SystemTS 3.8 Electrical Power SystemsST-OP-315-0065-001 Revision 30 Emergency Diesel Generator Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 89 of 106
Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 91 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3001C032 R3000 EDG 14 Engine-driven Fuel Oil Pump M-5734/F-5 Skid NC Positive Displacement Safety Function Basis: The safety related function of the EDG System is to provide an outside standby source of AC electrical power to shutdown and maintain the reactor in a safe condition under all conditions including LOCA coincident with LOOP. [DBD R30-00 Section 2.2.1 Safety Related Functions] The engine driven pump is safety related and required to operate in order to mitigate a design basis accident. An electric motor driven fuel pump is also provided to purge air from the fuel line following maintenance on the fuel oil system. The electric motor driven fuel pump will receive a start signal if a low pressure condition exists on the supply side of the duplex filter. Although the electric motor driven pump is not credited to operate during a design basis accident, it is considered to be a safety related pump. [UFSAR 9.5.4.2 System Description]The EDG motor-driven Standby FO pumps are considered skid-mounted components and have no individual IST exams. Satisfactory operation of the pump during various EDG testing provides assurance that this pump is operating satisfactory. Procedure 34.307.001 has steps for operations to run the motor-driven fuel pump until system pressure has stabilized greater than 25 psig.
Function
Description:
The engine driven Fuel Oil Pump is safety related and required to operate in order to mitigate a design basis accident. An electric motor driven fuel pump is also provided to purge air from the fuel line following maintenance on the fuel oil system. The electric motor driven fuel pump will receive a start signal if a low pressure condition exists on the supply side of the duplex filter. [UFSAR 9.5.4.2 System Description]The EDG engine-driven FO pumps are considered skid-mounted components and have no individual IST exams.
Satisfactory operation of the pump during various EDG testing provides assurance that this pump is operating satisfactory.
Design Basis Limits: Except for the fill vent and drain lines, the EDG Fuel Oil System, piping and components up to the diesel engine interface shall be designed to ASME Section III, Class 3 requirements as shown in UFSAR Figures 9.5-4, 9.5-5 and 9.5-6. The fill, vent and drain lines shall be designed to ANSI B31.1 requirements. [DBD R30-00 Section 4.1.8.2 Mechanical Codes and Standards]Pump discharges 9 gpm at 35 psig through a duplex fuel oil filter. [ST-OP-315-0065-001]The EDG fuel oil fill, vent and drain lines, and exhaust piping downstream of the exhaust muffler shall be designed to Seismic Category II/I requirements. [DBD R30-00 Section 2.3 Classification]
Design
References:
DBD R30-00 Rev H, Emergency Diesel GeneratorUFSAR Table 3.2-1 Structures, Systems, And Components ClassificationUFSAR 9.5.4 Diesel Generator Fuel-Oil Storage and Transfer SystemUFSAR Figure 9.5-6 Engine-Skid Mounted Diesel-Fuel-Oil SystemTS 3.8 Electrical Power SystemsST-OP-315-0065-001 Revision 30 Emergency Diesel Generator Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 90 of 106
DTIE E ergy-Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 92 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3001C033 R3000 EDG 11 Engine-driven Jacket Coolant Pump M-5734/C-8 Skid 3 Centrifugal Safety Function Basis: The diesel generator cooling system is designed to provide adequate cooling water to remove the heat given off by the lube-oil coolers, inlet air coolers, and the engine jacket coolant heat exchangers. The engine jacket coolant system, which is a closed loop system, removes heat from the engine and transfers it to the diesel generator service water system. [UFSAR 9.5.5.1 Design Basis]To ensure quick starts, a motor-driven standby circulating pump maintains the jacket coolant temperature at approximately 110 degrees F by pumping the coolant through a thermostat-controlled electric heater. [UFSAR 9.5.5.2 System Description]The EDG Jacket Cooling Water System is a closed loop system that removes heat from the engine and transfers it to the EDG Service Water System. It also maintains the Jacket Coolant System water warm in standby mode to ensure quick start. [DBD R30-00 Section 2.1 Summary]This pump is verified to work by jacket coolant temperature being maintained in standby. If the pump is not working, standby jacket coolant temperature will drop. Low jacket coolant temperature is alarmed. Standby jacket coolant temperature is recorded daily in Operator rounds. Standby jacket coolant temperature is trended by System Engineering. The system engineers EDG system monitoring plan contains additional details on data collection and analysis. [DBD R30-00 Section 4.2.8] [UFSAR 9.5.5]The EDG motor-driven Standby Coolant pumps are considered skid mounted devices and have no individual IST exams. Satisfactory engine operation during periodic testing provides assurance that this pump is operating satisfactorily, and this pump is operating when the engine is in the standby condition, and does not operate when the EDG is running.
Function
Description:
The EDG engine-driven Jacket Coolant pumps are considered skid mounted devices and have no individual IST exams. Satisfactory engine operation during periodic testing provides assurance that this pump is operating satisfactorily. This pump is verified to work by jacket coolant temperature being maintained during diesel operation. If the pump is not working, standby jacket coolant temperature will rise. High jacket coolant temperature is alarmed. Jacket coolant temperature is trended by System Engineering. The system engineers EDG system monitoring plan contains additional details on data collection and analysis. [DBD R30-00 Section 4.2.8] [UFSAR 9.5.5]
Design Basis Limits: The jacket coolant system is designed to Category I requirements and the system piping, valves, and heat exchangers meet either the requirements of the ASME B&PV Code Section III, Class 3, the DEMA standards, or Group D (ANSI B31.1), and are seismically supported. [UFSAR 9.5.5.1 Design Basis]Engine-driven, single stage centrifugal pump, has a capacity of 400 gpm. [ST-OP-315-0065-001]All on-skid piping and components of Jacket Water and Air Coolant System are classified as QA Level 1 and Seismic Category I. All skid-mounted components and piping that are classified as Class 3 are constructed to Subsection ND of the ASME Code,Section III, and all addenda to and including Summer 1973. The off-skid vent and equalizing lines between the expansion tank and skid were analyzed and installed to Seismic Category I as a response to FSAR question 222.62d. Off-skid piping is non-Q designed to the Power Piping Code, ANSI B31.1.0. The off-skid expansion tank is non-ASME, Seismic Category I, QA Level 1. [DBD R30-00 Section 2.3 Classification]Except for the two jacket water system vent lines and the equalizing line to the expansion tank, EDG service water systems, piping and components up to the diesel engine interface shall be designed to the requirements of ASME Section III, Class 3 as shown in UFSAR Figures 9.2-6, 9.5-7, 9.5-8 and 9.5-9. [DBD R30-00 Section 4.1.8.2 Mechanical Codes and Standards]
Design
References:
DBD R30-00 Rev H, Emergency Diesel GeneratorUFSAR Table 3.2-1 Structures, Systems, And Components ClassificationUFSAR 9.5.5 Diesel Generator Cooling Water SystemUFSAR Figure 9.5-7 Diesel Generator Jacket Coolant SystemTS 3.8 Electrical Power Systems Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 91 of 106
Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 93 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3001C034 R3000 EDG 12 Engine-driven Jacket Coolant Pump M-5734/C-8 Skid 3 Centrifugal Safety Function Basis: The diesel generator cooling system is designed to provide adequate cooling water to remove the heat given off by the lube-oil coolers, inlet air coolers, and the engine jacket coolant heat exchangers. The engine jacket coolant system, which is a closed loop system, removes heat from the engine and transfers it to the diesel generator service water system. [UFSAR 9.5.5.1 Design Basis]To ensure quick starts, a motor-driven standby circulating pump maintains the jacket coolant temperature at approximately 110 degrees F by pumping the coolant through a thermostat-controlled electric heater. [UFSAR 9.5.5.2 System Description]The EDG Jacket Cooling Water System is a closed loop system that removes heat from the engine and transfers it to the EDG Service Water System. It also maintains the Jacket Coolant System water warm in standby mode to ensure quick start. [DBD R30-00 Section 2.1 Summary]This pump is verified to work by jacket coolant temperature being maintained in standby. If the pump is not working, standby jacket coolant temperature will drop. Low jacket coolant temperature is alarmed. Standby jacket coolant temperature is recorded daily in Operator rounds. Standby jacket coolant temperature is trended by System Engineering. The system engineers EDG system monitoring plan contains additional details on data collection and analysis. [DBD R30-00 Section 4.2.8] [UFSAR 9.5.5]The EDG motor-driven Standby Coolant pumps are considered skid mounted devices and have no individual IST exams. Satisfactory engine operation during periodic testing provides assurance that this pump is operating satisfactorily, and this pump is operating when the engine is in the standby condition, and does not operate when the EDG is running.
Function
Description:
The EDG engine-driven Jacket Coolant pumps are considered skid mounted devices and have no individual IST exams. Satisfactory engine operation during periodic testing provides assurance that this pump is operating satisfactorily. This pump is verified to work by jacket coolant temperature being maintained during diesel operation. If the pump is not working, standby jacket coolant temperature will rise. High jacket coolant temperature is alarmed. Jacket coolant temperature is trended by System Engineering. The system engineers EDG system monitoring plan contains additional details on data collection and analysis. [DBD R30-00 Section 4.2.8] [UFSAR 9.5.5]
Design Basis Limits: The jacket coolant system is designed to Category I requirements and the system piping, valves, and heat exchangers meet either the requirements of the ASME B&PV Code Section III, Class 3, the DEMA standards, or Group D (ANSI B31.1), and are seismically supported. [UFSAR 9.5.5.1 Design Basis]Engine-driven, single stage centrifugal pump, has a capacity of 400 gpm. [ST-OP-315-0065-001]All on-skid piping and components of Jacket Water and Air Coolant System are classified as QA Level 1 and Seismic Category I. All skid-mounted components and piping that are classified as Class 3 are constructed to Subsection ND of the ASME Code,Section III, and all addenda to and including Summer 1973. The off-skid vent and equalizing lines between the expansion tank and skid were analyzed and installed to Seismic Category I as a response to FSAR question 222.62d. Off-skid piping is non-Q designed to the Power Piping Code, ANSI B31.1.0. The off-skid expansion tank is non-ASME, Seismic Category I, QA Level 1. [DBD R30-00 Section 2.3 Classification]Except for the two jacket water system vent lines and the equalizing line to the expansion tank, EDG service water systems, piping and components up to the diesel engine interface shall be designed to the requirements of ASME Section III, Class 3 as shown in UFSAR Figures 9.2-6, 9.5-7, 9.5-8 and 9.5-9. [DBD R30-00 Section 4.1.8.2 Mechanical Codes and Standards]
Design
References:
DBD R30-00 Rev H, Emergency Diesel GeneratorUFSAR Table 3.2-1 Structures, Systems, And Components ClassificationUFSAR 9.5.5 Diesel Generator Cooling Water SystemUFSAR Figure 9.5-7 Diesel Generator Jacket Coolant SystemTS 3.8 Electrical Power Systems Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 92 of 106
I VFermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 94 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3001C035 R3000 EDG 13 Engine-driven Jacket Coolant Pump M-5734/C-8 Skid 3 Centrifugal Safety Function Basis: The diesel generator cooling system is designed to provide adequate cooling water to remove the heat given off by the lube-oil coolers, inlet air coolers, and the engine jacket coolant heat exchangers. The engine jacket coolant system, which is a closed loop system, removes heat from the engine and transfers it to the diesel generator service water system. [UFSAR 9.5.5.1 Design Basis]To ensure quick starts, a motor-driven standby circulating pump maintains the jacket coolant temperature at approximately 110 degrees F by pumping the coolant through a thermostat-controlled electric heater. [UFSAR 9.5.5.2 System Description]The EDG Jacket Cooling Water System is a closed loop system that removes heat from the engine and transfers it to the EDG Service Water System. It also maintains the Jacket Coolant System water warm in standby mode to ensure quick start. [DBD R30-00 Section 2.1 Summary]This pump is verified to work by jacket coolant temperature being maintained in standby. If the pump is not working, standby jacket coolant temperature will drop. Low jacket coolant temperature is alarmed. Standby jacket coolant temperature is recorded daily in Operator rounds. Standby jacket coolant temperature is trended by System Engineering. The system engineers EDG system monitoring plan contains additional details on data collection and analysis. [DBD R30-00 Section 4.2.8] [UFSAR 9.5.5]The EDG motor-driven Standby Coolant pumps are considered skid mounted devices and have no individual IST exams. Satisfactory engine operation during periodic testing provides assurance that this pump is operating satisfactorily, and this pump is operating when the engine is in the standby condition, and does not operate when the EDG is running.
Function
Description:
The EDG engine-driven Jacket Coolant pumps are considered skid mounted devices and have no individual IST exams. Satisfactory engine operation during periodic testing provides assurance that this pump is operating satisfactorily. This pump is verified to work by jacket coolant temperature being maintained during diesel operation. If the pump is not working, standby jacket coolant temperature will rise. High jacket coolant temperature is alarmed. Jacket coolant temperature is trended by System Engineering. The system engineers EDG system monitoring plan contains additional details on data collection and analysis. [DBD R30-00 Section 4.2.8] [UFSAR 9.5.5]
Design Basis Limits: The jacket coolant system is designed to Category I requirements and the system piping, valves, and heat exchangers meet either the requirements of the ASME B&PV Code Section III, Class 3, the DEMA standards, or Group D (ANSI B31.1), and are seismically supported. [UFSAR 9.5.5.1 Design Basis]Engine-driven, single stage centrifugal pump, has a capacity of 400 gpm. [ST-OP-315-0065-001]All on-skid piping and components of Jacket Water and Air Coolant System are classified as QA Level 1 and Seismic Category I. All skid-mounted components and piping that are classified as Class 3 are constructed to Subsection ND of the ASME Code,Section III, and all addenda to and including Summer 1973. The off-skid vent and equalizing lines between the expansion tank and skid were analyzed and installed to Seismic Category I as a response to FSAR question 222.62d. Off-skid piping is non-Q designed to the Power Piping Code, ANSI B31.1.0. The off-skid expansion tank is non-ASME, Seismic Category I, QA Level 1. [DBD R30-00 Section 2.3 Classification]Except for the two jacket water system vent lines and the equalizing line to the expansion tank, EDG service water systems, piping and components up to the diesel engine interface shall be designed to the requirements of ASME Section III, Class 3 as shown in UFSAR Figures 9.2-6, 9.5-7, 9.5-8 and 9.5-9. [DBD R30-00 Section 4.1.8.2 Mechanical Codes and Standards]
Design
References:
DBD R30-00 Rev H, Emergency Diesel GeneratorUFSAR Table 3.2-1 Structures, Systems, And Components ClassificationUFSAR 9.5.5 Diesel Generator Cooling Water SystemUFSAR Figure 9.5-7 Diesel Generator Jacket Coolant SystemTS 3.8 Electrical Power Systems Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 93 of 106
- Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 95 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3001C036 R3000 EDG 14 Engine-driven Jacket Coolant Pump M-5734/C-8 Skid 3 Centrifugal Safety Function Basis: The diesel generator cooling system is designed to provide adequate cooling water to remove the heat given off by the lube-oil coolers, inlet air coolers, and the engine jacket coolant heat exchangers. The engine jacket coolant system, which is a closed loop system, removes heat from the engine and transfers it to the diesel generator service water system. [UFSAR 9.5.5.1 Design Basis]To ensure quick starts, a motor-driven standby circulating pump maintains the jacket coolant temperature at approximately 110 degrees F by pumping the coolant through a thermostat-controlled electric heater. [UFSAR 9.5.5.2 System Description]The EDG Jacket Cooling Water System is a closed loop system that removes heat from the engine and transfers it to the EDG Service Water System. It also maintains the Jacket Coolant System water warm in standby mode to ensure quick start. [DBD R30-00 Section 2.1 Summary]This pump is verified to work by jacket coolant temperature being maintained in standby. If the pump is not working, standby jacket coolant temperature will drop. Low jacket coolant temperature is alarmed. Standby jacket coolant temperature is recorded daily in Operator rounds. Standby jacket coolant temperature is trended by System Engineering. The system engineers EDG system monitoring plan contains additional details on data collection and analysis. [DBD R30-00 Section 4.2.8] [UFSAR 9.5.5]The EDG motor-driven Standby Coolant pumps are considered skid mounted devices and have no individual IST exams. Satisfactory engine operation during periodic testing provides assurance that this pump is operating satisfactorily, and this pump is operating when the engine is in the standby condition, and does not operate when the EDG is running.
Function
Description:
The EDG engine-driven Jacket Coolant pumps are considered skid mounted devices and have no individual IST exams. Satisfactory engine operation during periodic testing provides assurance that this pump is operating satisfactorily. This pump is verified to work by jacket coolant temperature being maintained during diesel operation. If the pump is not working, standby jacket coolant temperature will rise. High jacket coolant temperature is alarmed. Jacket coolant temperature is trended by System Engineering. The system engineers EDG system monitoring plan contains additional details on data collection and analysis. [DBD R30-00 Section 4.2.8] [UFSAR 9.5.5]
Design Basis Limits: The jacket coolant system is designed to Category I requirements and the system piping, valves, and heat exchangers meet either the requirements of the ASME B&PV Code Section III, Class 3, the DEMA standards, or Group D (ANSI B31.1), and are seismically supported. [UFSAR 9.5.5.1 Design Basis]Engine-driven, single stage centrifugal pump, has a capacity of 400 gpm. [ST-OP-315-0065-001]All on-skid piping and components of Jacket Water and Air Coolant System are classified as QA Level 1 and Seismic Category I. All skid-mounted components and piping that are classified as Class 3 are constructed to Subsection ND of the ASME Code,Section III, and all addenda to and including Summer 1973. The off-skid vent and equalizing lines between the expansion tank and skid were analyzed and installed to Seismic Category I as a response to FSAR question 222.62d. Off-skid piping is non-Q designed to the Power Piping Code, ANSI B31.1.0. The off-skid expansion tank is non-ASME, Seismic Category I, QA Level 1. [DBD R30-00 Section 2.3 Classification]Except for the two jacket water system vent lines and the equalizing line to the expansion tank, EDG service water systems, piping and components up to the diesel engine interface shall be designed to the requirements of ASME Section III, Class 3 as shown in UFSAR Figures 9.2-6, 9.5-7, 9.5-8 and 9.5-9. [DBD R30-00 Section 4.1.8.2 Mechanical Codes and Standards]
Design
References:
DBD R30-00 Rev H, Emergency Diesel GeneratorUFSAR Table 3.2-1 Structures, Systems, And Components ClassificationUFSAR 9.5.5 Diesel Generator Cooling Water SystemUFSAR Figure 9.5-7 Diesel Generator Jacket Coolant SystemTS 3.8 Electrical Power Systems Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 94 of 106
DI e-- Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 96 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3001C037 R3000 EDG 11 Engine-Driven Air Coolant Pump M-5734/C-5 Skid NC Centrifugal Safety Function Basis: The diesel generator cooling system is designed to provide adequate cooling water to remove the heat given off by the lube-oil coolers, inlet air coolers, and the engine jacket coolant heat exchangers. The engine jacket coolant system, which is a closed loop system, removes heat from the engine and transfers it to the diesel generator service water system. [UFSAR 9.5.5.1 Design Basis]The EDG Jacket Cooling Water System is a closed loop system that removes heat from the engine and transfers it to the EDG Service Water System. It also maintains the Jacket Coolant System water warm in standby mode to ensure quick start. [DBD R30-00 Section 2.1 Summary]This pump is verified to work by air coolant temperature being maintained while operating. If the pump is not working, air coolant temperature will rise. High jacket coolant temperature is alarmed. Air coolant temperature is trended by System Engineering. The system engineers EDG system monitoring plan contains additional details on data collection and analysis. [DBD R30-00 Section 4.2.9] [UFSAR 9.5.5]The EDG engine-driven Air Coolant pumps are considered skid mounted devices and have no individual IST exams. Satisfactory engine operation during periodic testing provides assurance that this pump is operating satisfactorily.
Function
Description:
The EDG engine-driven Air Coolant pumps are considered skid mounted devices and have no individual IST exams. Satisfactory engine operation during periodic testing provides assurance that this pump is operating satisfactorily. This pump is verified to work by jacket coolant temperature being maintained during diesel operation. If the pump is not working, standby jacket coolant temperature will rise. High jacket coolant temperature is alarmed. Air coolant temperature is trended by System Engineering. The system engineers EDG system monitoring plan contains additional details on data collection and analysis. [DBD R30-00 Section 4.2.9] [UFSAR 9.5.5]
Design Basis Limits: The jacket coolant system is designed to Category I requirements and the system piping, valves, and heat exchangers meet either the requirements of the ASME B&PV Code Section III, Class 3, the DEMA standards, or Group D (ANSI B31.1), and are seismically supported. [UFSAR 9.5.5.1 Design Basis]All on-skid piping and components of Jacket Water and Air Coolant System are classified as QA Level 1 and Seismic Category I. All skid-mounted components and piping that are classified as Class 3 are constructed to Subsection ND of the ASME Code,Section III, and all addenda to and including Summer 1973. The off-skid vent and equalizing lines between the expansion tank and skid were analyzed and installed to Seismic Category I as a response to FSAR question 222.62d. Off-skid piping is non-Q designed to the Power Piping Code, ANSI B31.1.0. The off-skid expansion tank is non-ASME, Seismic Category I, QA Level 1. [DBD R30-00 Section 2.3 Classification]Except for the two jacket water system vent lines and the equalizing line to the expansion tank, EDG service water systems, piping and components up to the diesel engine interface shall be designed to the requirements of ASME Section III, Class 3 as shown in UFSAR Figures 9.2-6, 9.5-7, 9.5-8 and 9.5-9. [DBD R30-00 Section 4.1.8.2 Mechanical Codes and Standards]
Design
References:
DBD R30-00 Rev H, Emergency Diesel GeneratorUFSAR Table 3.2-1 Structures, Systems, And Components ClassificationUFSAR 9.5.5 Diesel Generator Cooling Water SystemUFSAR Figure 9.5-7 Diesel Generator Jacket Coolant SystemTS 3.8 Electrical Power Systems Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 95 of 106
Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 97 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3001C038 R3000 EDG 12 Engine-Driven Air Coolant Pump M-5734/C-5 Skid NC Centrifugal Safety Function Basis: The diesel generator cooling system is designed to provide adequate cooling water to remove the heat given off by the lube-oil coolers, inlet air coolers, and the engine jacket coolant heat exchangers. The engine jacket coolant system, which is a closed loop system, removes heat from the engine and transfers it to the diesel generator service water system. [UFSAR 9.5.5.1 Design Basis]The EDG Jacket Cooling Water System is a closed loop system that removes heat from the engine and transfers it to the EDG Service Water System. It also maintains the Jacket Coolant System water warm in standby mode to ensure quick start. [DBD R30-00 Section 2.1 Summary]This pump is verified to work by air coolant temperature being maintained while operating. If the pump is not working, air coolant temperature will rise. High jacket coolant temperature is alarmed. Air coolant temperature is trended by System Engineering. The system engineers EDG system monitoring plan contains additional details on data collection and analysis. [DBD R30-00 Section 4.2.9] [UFSAR 9.5.5]The EDG engine-driven Air Coolant pumps are considered skid mounted devices and have no individual IST exams. Satisfactory engine operation during periodic testing provides assurance that this pump is operating satisfactorily.
Function
Description:
The EDG engine-driven Air Coolant pumps are considered skid mounted devices and have no individual IST exams. Satisfactory engine operation during periodic testing provides assurance that this pump is operating satisfactorily. This pump is verified to work by jacket coolant temperature being maintained during diesel operation. If the pump is not working, standby jacket coolant temperature will rise. High jacket coolant temperature is alarmed. Air coolant temperature is trended by System Engineering. The system engineers EDG system monitoring plan contains additional details on data collection and analysis. [DBD R30-00 Section 4.2.9] [UFSAR 9.5.5]
Design Basis Limits: The jacket coolant system is designed to Category I requirements and the system piping, valves, and heat exchangers meet either the requirements of the ASME B&PV Code Section III, Class 3, the DEMA standards, or Group D (ANSI B31.1), and are seismically supported. [UFSAR 9.5.5.1 Design Basis]All on-skid piping and components of Jacket Water and Air Coolant System are classified as QA Level 1 and Seismic Category I. All skid-mounted components and piping that are classified as Class 3 are constructed to Subsection ND of the ASME Code,Section III, and all addenda to and including Summer 1973. The off-skid vent and equalizing lines between the expansion tank and skid were analyzed and installed to Seismic Category I as a response to FSAR question 222.62d. Off-skid piping is non-Q designed to the Power Piping Code, ANSI B31.1.0. The off-skid expansion tank is non-ASME, Seismic Category I, QA Level 1. [DBD R30-00 Section 2.3 Classification]Except for the two jacket water system vent lines and the equalizing line to the expansion tank, EDG service water systems, piping and components up to the diesel engine interface shall be designed to the requirements of ASME Section III, Class 3 as shown in UFSAR Figures 9.2-6, 9.5-7, 9.5-8 and 9.5-9. [DBD R30-00 Section 4.1.8.2 Mechanical Codes and Standards]
Design
References:
DBD R30-00 Rev H, Emergency Diesel GeneratorUFSAR Table 3.2-1 Structures, Systems, And Components ClassificationUFSAR 9.5.5 Diesel Generator Cooling Water SystemUFSAR Figure 9.5-7 Diesel Generator Jacket Coolant SystemTS 3.8 Electrical Power Systems Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 96 of 106
an -n r Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 98 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3001C039 R3000 EDG 13 Engine-Driven Air Coolant Pump M-5734/C-5 Skid NC Centrifugal Safety Function Basis: The diesel generator cooling system is designed to provide adequate cooling water to remove the heat given off by the lube-oil coolers, inlet air coolers, and the engine jacket coolant heat exchangers. The engine jacket coolant system, which is a closed loop system, removes heat from the engine and transfers it to the diesel generator service water system. [UFSAR 9.5.5.1 Design Basis]The EDG Jacket Cooling Water System is a closed loop system that removes heat from the engine and transfers it to the EDG Service Water System. It also maintains the Jacket Coolant System water warm in standby mode to ensure quick start. [DBD R30-00 Section 2.1 Summary]This pump is verified to work by air coolant temperature being maintained while operating. If the pump is not working, air coolant temperature will rise. High jacket coolant temperature is alarmed. Air coolant temperature is trended by System Engineering. The system engineers EDG system monitoring plan contains additional details on data collection and analysis. [DBD R30-00 Section 4.2.9] [UFSAR 9.5.5]The EDG engine-driven Air Coolant pumps are considered skid mounted devices and have no individual IST exams. Satisfactory engine operation during periodic testing provides assurance that this pump is operating satisfactorily.
Function
Description:
The EDG engine-driven Air Coolant pumps are considered skid mounted devices and have no individual IST exams. Satisfactory engine operation during periodic testing provides assurance that this pump is operating satisfactorily. This pump is verified to work by jacket coolant temperature being maintained during diesel operation. If the pump is not working, standby jacket coolant temperature will rise. High jacket coolant temperature is alarmed. Air coolant temperature is trended by System Engineering. The system engineers EDG system monitoring plan contains additional details on data collection and analysis. [DBD R30-00 Section 4.2.9] [UFSAR 9.5.5]
Design Basis Limits: The jacket coolant system is designed to Category I requirements and the system piping, valves, and heat exchangers meet either the requirements of the ASME B&PV Code Section III, Class 3, the DEMA standards, or Group D (ANSI B31.1), and are seismically supported. [UFSAR 9.5.5.1 Design Basis]All on-skid piping and components of Jacket Water and Air Coolant System are classified as QA Level 1 and Seismic Category I. All skid-mounted components and piping that are classified as Class 3 are constructed to Subsection ND of the ASME Code,Section III, and all addenda to and including Summer 1973. The off-skid vent and equalizing lines between the expansion tank and skid were analyzed and installed to Seismic Category I as a response to FSAR question 222.62d. Off-skid piping is non-Q designed to the Power Piping Code, ANSI B31.1.0. The off-skid expansion tank is non-ASME, Seismic Category I, QA Level 1. [DBD R30-00 Section 2.3 Classification]Except for the two jacket water system vent lines and the equalizing line to the expansion tank, EDG service water systems, piping and components up to the diesel engine interface shall be designed to the requirements of ASME Section III, Class 3 as shown in UFSAR Figures 9.2-6, 9.5-7, 9.5-8 and 9.5-9. [DBD R30-00 Section 4.1.8.2 Mechanical Codes and Standards]
Design
References:
DBD R30-00 Rev H, Emergency Diesel GeneratorUFSAR Table 3.2-1 Structures, Systems, And Components ClassificationUFSAR 9.5.5 Diesel Generator Cooling Water SystemUFSAR Figure 9.5-7 Diesel Generator Jacket Coolant SystemTS 3.8 Electrical Power Systems Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 97 of 106
.70W an mFermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 99 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3001C040 R3000 EDG 14 Engine-Driven Air Coolant Pump M-5734/C-5 Skid NC Centrifugal Safety Function Basis: The diesel generator cooling system is designed to provide adequate cooling water to remove the heat given off by the lube-oil coolers, inlet air coolers, and the engine jacket coolant heat exchangers. The engine jacket coolant system, which is a closed loop system, removes heat from the engine and transfers it to the diesel generator service water system. [UFSAR 9.5.5.1 Design Basis]The EDG Jacket Cooling Water System is a closed loop system that removes heat from the engine and transfers it to the EDG Service Water System. It also maintains the Jacket Coolant System water warm in standby mode to ensure quick start. [DBD R30-00 Section 2.1 Summary]This pump is verified to work by air coolant temperature being maintained while operating. If the pump is not working, air coolant temperature will rise. High jacket coolant temperature is alarmed. Air coolant temperature is trended by System Engineering. The system engineers EDG system monitoring plan contains additional details on data collection and analysis. [DBD R30-00 Section 4.2.9] [UFSAR 9.5.5]The EDG engine-driven Air Coolant pumps are considered skid mounted devices and have no individual IST exams. Satisfactory engine operation during periodic testing provides assurance that this pump is operating satisfactorily.
Function
Description:
The EDG engine-driven Air Coolant pumps are considered skid mounted devices and have no individual IST exams. Satisfactory engine operation during periodic testing provides assurance that this pump is operating satisfactorily. This pump is verified to work by jacket coolant temperature being maintained during diesel operation. If the pump is not working, standby jacket coolant temperature will rise. High jacket coolant temperature is alarmed. Air coolant temperature is trended by System Engineering. The system engineers EDG system monitoring plan contains additional details on data collection and analysis. [DBD R30-00 Section 4.2.9] [UFSAR 9.5.5]
Design Basis Limits: The jacket coolant system is designed to Category I requirements and the system piping, valves, and heat exchangers meet either the requirements of the ASME B&PV Code Section III, Class 3, the DEMA standards, or Group D (ANSI B31.1), and are seismically supported. [UFSAR 9.5.5.1 Design Basis]All on-skid piping and components of Jacket Water and Air Coolant System are classified as QA Level 1 and Seismic Category I. All skid-mounted components and piping that are classified as Class 3 are constructed to Subsection ND of the ASME Code,Section III, and all addenda to and including Summer 1973. The off-skid vent and equalizing lines between the expansion tank and skid were analyzed and installed to Seismic Category I as a response to FSAR question 222.62d. Off-skid piping is non-Q designed to the Power Piping Code, ANSI B31.1.0. The off-skid expansion tank is non-ASME, Seismic Category I, QA Level 1. [DBD R30-00 Section 2.3 Classification]Except for the two jacket water system vent lines and the equalizing line to the expansion tank, EDG service water systems, piping and components up to the diesel engine interface shall be designed to the requirements of ASME Section III, Class 3 as shown in UFSAR Figures 9.2-6, 9.5-7, 9.5-8 and 9.5-9. [DBD R30-00 Section 4.1.8.2 Mechanical Codes and Standards]
Design
References:
DBD R30-00 Rev H, Emergency Diesel GeneratorUFSAR Table 3.2-1 Structures, Systems, And Components ClassificationUFSAR 9.5.5 Diesel Generator Cooling Water SystemUFSAR Figure 9.5-7 Diesel Generator Jacket Coolant SystemTS 3.8 Electrical Power Systems Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 98 of 106
DTIE ergFermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 100 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3001C041 R3000 EDG 11 Engine-driven Lube Oil Pump M-5734/F-3 Skid NC Positive Displacement Safety Function Basis: The diesel generator lubrication system is designed to provide adequate engine lubrication under all operating conditions, including immediate full-load operation after starting. The system maintains the lube-oil temperature in the specified range under all loading conditions and ambient temperatures. [UFSAR 9.5.7.1]The safety related function of the EDG System is to provide an onsite standby source of AC electrical power to shutdown and maintain the reactor in a safe condition under all conditions including LOCA coincident with LOOP.
[DBD R30-00 Section 2.2.1 Safety Related Functions] The EDG Lube Oil System lubricates and cools the engine during operation and keeps the lube oil warm in standby mode to ensure quick start. [DBD R30-00 Section 2.1 Summary]
Function
Description:
A diesel engine-driven lube oil pump lubricates and cools engine components during diesel operation. [UFSAR 9.5.7.2 System Description]The lube-oil system, including lube-oil storage for each diesel generator, is completely independent of the lube-oil systems of the other diesel generators. Therefore, failure of one lube-oil system results in the loss of only one diesel generator in a division. The other diesel generator in the division, along with diesel generators in the second division, is adequate to meet the safe-shutdown requirements of the plant. [UFSAR 9.5.7.3 Safety Evaluation]The EDG LO System provides adequate engine lubrication under all operating conditions and cools the engine during operation and keeps the Lube Oil warm in standby mode. The keep warm system and pre-lube pumps keep the EDG in standby readiness but are not functionally required for operation of the EDG. It provides sufficient amount of lube oil on site for continuous operation of the EDG for 7 days without replenishment. [DBD R30-00 Section 4.2.6.2 Component Function]
Design Basis Limits: The lube-oil system is designed to Category I requirements. [UFSAR 9.5.7.3 Safety Evaluation]Rotary gear type positive displacement pump, with a capacity of 500 gpm.
The pump takes oil from the sump through a suction strainer and passes it through a full-flow filter. [ST-OP-315-0065-001 Design
References:
Tech Specs 3.8 Electrical Power Systems DBD R30-00 Rev H, Emergency Diesel GeneratorUFSAR Table 3.2-1 Structures, Systems, And Components ClassificationUFSAR 9.5.7 Diesel Generator Lubrication SystemST-OP-315-0065-001 Revision 30 Emergency Diesel Generator Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 99 of 106
Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 101 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3001C042 R3000 EDG 12 Engine-driven Lube Oil Pump M-5734/F-3 Skid NC Positive Displacement Safety Function Basis: The diesel generator lubrication system is designed to provide adequate engine lubrication under all operating conditions, including immediate full-load operation after starting. The system maintains the lube-oil temperature in the specified range under all loading conditions and ambient temperatures. [UFSAR 9.5.7.1]The safety related function of the EDG System is to provide an onsite standby source of AC electrical power to shutdown and maintain the reactor in a safe condition under all conditions including LOCA coincident with LOOP.
[DBD R30-00 Section 2.2.1 Safety Related Functions] The EDG Lube Oil System lubricates and cools the engine during operation and keeps the lube oil warm in standby mode to ensure quick start. [DBD R30-00 Section 2.1 Summary]
Function
Description:
A diesel engine-driven lube oil pump lubricates and cools engine components during diesel operation. [UFSAR 9.5.7.2 System Description]The lube-oil system, including lube-oil storage for each diesel generator, is completely independent of the lube-oil systems of the other diesel generators. Therefore, failure of one lube-oil system results in the loss of only one diesel generator in a division. The other diesel generator in the division, along with diesel generators in the second division, is adequate to meet the safe-shutdown requirements of the plant. [UFSAR 9.5.7.3 Safety Evaluation]The EDG LO System provides adequate engine lubrication under all operating conditions and cools the engine during operation and keeps the Lube Oil warm in standby mode. The keep warm system and pre-lube pumps keep the EDG in standby readiness but are not functionally required for operation of the EDG. It provides sufficient amount of lube oil on site for continuous operation of the EDG for 7 days without replenishment. [DBD R30-00 Section 4.2.6.2 Component Function]
Design Basis Limits: The lube-oil system is designed to Category I requirements. [UFSAR 9.5.7.3 Safety Evaluation]Rotary gear type positive displacement pump, with a capacity of 500 gpm.
The pump takes oil from the sump through a suction strainer and passes it through a full-flow filter. [ST-OP-315-0065-001 Design
References:
Tech Specs 3.8 Electrical Power Systems DBD R30-00 Rev H, Emergency Diesel GeneratorUFSAR Table 3.2-1 Structures, Systems, And Components ClassificationUFSAR 9.5.7 Diesel Generator Lubrication SystemST-OP-315-0065-001 Revision 30 Emergency Diesel Generator Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 100 of 106
Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 102 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3001C043 R3000 EDG 13 Engine-driven Lube Oil Pump M-5734/F-3 Skid NC Positive Displacement Safety Function Basis: The diesel generator lubrication system is designed to provide adequate engine lubrication under all operating conditions, including immediate full-load operation after starting. The system maintains the lube-oil temperature in the specified range under all loading conditions and ambient temperatures. [UFSAR 9.5.7.1]The safety related function of the EDG System is to provide an onsite standby source of AC electrical power to shutdown and maintain the reactor in a safe condition under all conditions including LOCA coincident with LOOP.
[DBD R30-00 Section 2.2.1 Safety Related Functions] The EDG Lube Oil System lubricates and cools the engine during operation and keeps the lube oil warm in standby mode to ensure quick start. [DBD R30-00 Section 2.1 Summary]
Function
Description:
A diesel engine-driven lube oil pump lubricates and cools engine components during diesel operation. [UFSAR 9.5.7.2 System Description]The lube-oil system, including lube-oil storage for each diesel generator, is completely independent of the lube-oil systems of the other diesel generators. Therefore, failure of one lube-oil system results in the loss of only one diesel generator in a division. The other diesel generator in the division, along with diesel generators in the second division, is adequate to meet the safe-shutdown requirements of the plant. [UFSAR 9.5.7.3 Safety Evaluation]The EDG LO System provides adequate engine lubrication under all operating conditions and cools the engine during operation and keeps the Lube Oil warm in standby mode. The keep warm system and pre-lube pumps keep the EDG in standby readiness but are not functionally required for operation of the EDG. It provides sufficient amount of lube oil on site for continuous operation of the EDG for 7 days without replenishment. [DBD R30-00 Section 4.2.6.2 Component Function]
Design Basis Limits: The lube-oil system is designed to Category I requirements. [UFSAR 9.5.7.3 Safety Evaluation]Rotary gear type positive displacement pump, with a capacity of 500 gpm.
The pump takes oil from the sump through a suction strainer and passes it through a full-flow filter. [ST-OP-315-0065-001 Design
References:
Tech Specs 3.8 Electrical Power Systems DBD R30-00 Rev H, Emergency Diesel GeneratorUFSAR Table 3.2-1 Structures, Systems, And Components ClassificationUFSAR 9.5.7 Diesel Generator Lubrication SystemST-OP-315-0065-001 Revision 30 Emergency Diesel Generator Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 101 of 106
- Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 103 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes R3001C044 R3000 EDG 14 Engine-driven Lube Oil Pump M-5734/F-3 Skid NC Positive Displacement Safety Function Basis: The diesel generator lubrication system is designed to provide adequate engine lubrication under all operating conditions, including immediate full-load operation after starting. The system maintains the lube-oil temperature in the specified range under all loading conditions and ambient temperatures. [UFSAR 9.5.7.1]The safety related function of the EDG System is to provide an onsite standby source of AC electrical power to shutdown and maintain the reactor in a safe condition under all conditions including LOCA coincident with LOOP.
[DBD R30-00 Section 2.2.1 Safety Related Functions] The EDG Lube Oil System lubricates and cools the engine during operation and keeps the lube oil warm in standby mode to ensure quick start. [DBD R30-00 Section 2.1 Summary]
Function
Description:
A diesel engine-driven lube oil pump lubricates and cools engine components during diesel operation. [UFSAR 9.5.7.2 System Description]The lube-oil system, including lube-oil storage for each diesel generator, is completely independent of the lube-oil systems of the other diesel generators. Therefore, failure of one lube-oil system results in the loss of only one diesel generator in a division. The other diesel generator in the division, along with diesel generators in the second division, is adequate to meet the safe-shutdown requirements of the plant. [UFSAR 9.5.7.3 Safety Evaluation]The EDG LO System provides adequate engine lubrication under all operating conditions and cools the engine during operation and keeps the Lube Oil warm in standby mode. The keep warm system and pre-lube pumps keep the EDG in standby readiness but are not functionally required for operation of the EDG. It provides sufficient amount of lube oil on site for continuous operation of the EDG for 7 days without replenishment. [DBD R30-00 Section 4.2.6.2 Component Function]
Design Basis Limits: The lube-oil system is designed to Category I requirements. [UFSAR 9.5.7.3 Safety Evaluation]Rotary gear type positive displacement pump, with a capacity of 500 gpm.
The pump takes oil from the sump through a suction strainer and passes it through a full-flow filter. [ST-OP-315-0065-001 Design
References:
Tech Specs 3.8 Electrical Power Systems DBD R30-00 Rev H, Emergency Diesel GeneratorUFSAR Table 3.2-1 Structures, Systems, And Components ClassificationUFSAR 9.5.7 Diesel Generator Lubrication SystemST-OP-315-0065-001 Revision 30 Emergency Diesel Generator Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 102 of 106
- D rFermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 104 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes T4100C040 T4100 South CCHVAC Chilled Water Pump 5736-2/F-3 A 3 Centrifugal dP 2Y 24.413.01 Q 2Y 24.413.01 V 2Y 24.413.01 PRR-002 Standard Code ISTB dP Q 24.413.01 Q Q 24.413.01 V Q 24.413.01 PRR-002 Safety Function Basis: The control center air conditioning system (CCACS) is designed to provide ventilation, heating, and cooling, and to limit the relative humidity in the control center envelope during normal operation and following a design-basis accident (DBA). [UFSAR 9.4.1] The chilled water pumps T4100C040 and T4100C041 are Division II and I respectively and provide cooling water for the Control Center Air Conditioning System in order to maintain the control room temperature less than or equal to 95 degrees F in accordance with TS SR 3.7.4.1.
Redundant components are powered by their corresponding redundant Division I and Division II engineered safety feature (ESF) buses. [UFSAR 9.4.1.1.d]During an emergency, the control center is isolated from all other areas of the plant. All air supplies to the standby gas treatment rooms and the normal operation of air intake and exhaust ducts are dampered closed. The multizone air-handling unit, the chiller, chilled water pump and the return air fan continue to operate as during normal operation. The return air damper assumes a full open position.
Condenser water is supplied from the EECWS. The fan in the mechanical equipment room fan-coil cooling unit is also energized under room thermostat control. Chilled-water flow through the cooling coil of the unit continues unimpeded as during normal operation. [UFSAR 9.4.1.2.3]This chilled water pump provides water for chilled water portion of the Control Center Air Conditioning Water Control to provide for temperature control of Cooling Coil T4100B007 (225 gpm), Chiller T4100B009 Compressor Motor (12 gpm), Oil Cooler (2 gpm), and Equipment Room Fan T4100B028 (10 gpm).[UFSAR Figure 9.4-3] The chilled water pump is designed for a 300 gpm flow at a dynamic head of 50 feet. [UFSAR Table 9.4-1 C]
Function
Description:
Group A - This pump operates continuously or routinely during normal operation, cold shutdown, or refueling operations.The CCHVAC system ensures that the Control Room will remain habitable for operating personnel during and following all design basis accident conditions. During a loss of coolant accident (LOCA), the CCHVAC System limits the radiation exposure to personnel within the control room based on the requirements of 10CFR50, Appendix A, General Design Criterion 19. [DBD T41-02 Section 2.2.3]The chilled water pump performs safety related functions during normal, recirculation, purge, and chlorine modes. Each chilled water pump provides the capability to supply chilled water from the evaporator of the chiller unit to the cooling coils of the multi-zone Air-Conditioning unit and the MER fan coil unit, and return the chilled water to the evaporator. Chilled water is also supplied to the chiller compressor motor, oil cooler, and the purge condenser. Chilled water is not required for the MER fan coil units during normal operation and purge modes; however, it is not isolated. The chilled water pump has sufficient flow capacity to circulate water to remove heat from the control center and-its associated chilled water circuits. The chilled water pump shall have sufficient head to overcome friction and dynamic losses in the piping, cooling coils, evaporator, and appurtenances in the chilled water circuits.[DBD T41-02 Section 4.2.4.2]
Design Basis Limits: TS SR 3.7.4.1 - Verify the control room air temperature is less than or equal to 95 degrees F every 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />sThis SR verifies that the heat removal capability of the system is sufficient to remove the control room heat load. The SR consists of a verification of control room temperature. [TS B SR 3.7.4.1]The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Frequency is appropriate since significant degradation of the Control Center AC System is not expected over this time period.UFSAR Table 9.4-1 Control Center HVAC System Major Components Descriptions and DBD T41-02 Section 4.2.4.3 Design RequirementsChilled Water PumpsType Centrifugal, vertically split casingTotal Dynamic head capacity 300 gpmTotal Dynamic head 50 ft water columnMotor 7 .5 horsepowerThe chilled water pump is required to operate at 249 gpm in all modes. [DBD T41-02 Section 4.2.4.3]
Design
References:
TS 3.7.4 Control Center Air Conditioning (AC) SystemUFSAR 6.4 Habitability Systems UFSAR 6.4.2.3 Air Conditioning SystemUFSAR 7.1.2.1.17 Control Center Atmospheric Control SystemUFSAR 9.4.1 Control Center Air Conditioning SystemUFSAR Table 9.4-1 Control Center HVAC System Major Components DescriptionsUFSAR Table 9.4-2 Main Control Room Air Conditioning System Single-Failure AnalysisUFSAR Figure 9.4-3 Control Center Air Conditioning Water Control Flow DiagramDBD T41-02, Rev F, Control Center Heating, Ventilating, and Air Conditioning (CCHVAC) System Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 103 of 106
Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 105 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes Appendix V Basis: OM Code Appendix V paragraph V-3000(a) Requirement: The Owner shall (a) identify those certain applicable pumps with specific design basis accident flow rates in the Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) for inclusion in this program.This pump has been deemed not applicable to Appendix V. UFSAR Table 9.4-1 lists a pump description for the chilled water pumps including a flow rate of 300 gpm with a total head of 50 feet. This 300 gpm flow rate is considered a nominal rating and not an Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) as defined in Appendix V.
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 104 of 106
1M - Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 106 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes T4100C041 T4100 North CCHVAC Chilled Water Pump 5736-2/F-3 A 3 Centrifugal dP 2Y 24.413.01 Q 2Y 24.413.01 V 2Y 24.413.01 PRR-002 Standard Code ISTB dP Q 24.413.01 Q Q 24.413.01 V Q 24.413.01 PRR-002 Safety Function Basis: The control center air conditioning system (CCACS) is designed to provide ventilation, heating, and cooling, and to limit the relative humidity in the control center envelope during normal operation and following a design-basis accident (DBA). [UFSAR 9.4.1] The chilled water pumps T4100C040 and T4100C041 are Division II and I respectively and provide cooling water for the Control Center Air Conditioning System in order to maintain the control room temperature less than or equal to 95 degrees F in accordance with TS SR 3.7.4.1.
Redundant components are powered by their corresponding redundant Division I and Division II engineered safety feature (ESF) buses. [UFSAR 9.4.1.1.d]During an emergency, the control center is isolated from all other areas of the plant. All air supplies to the standby gas treatment rooms and the normal operation of air intake and exhaust ducts are dampered closed. The multizone air-handling unit, the chiller, chilled water pump and the return air fan continue to operate as during normal operation. The return air damper assumes a full open position.
Condenser water is supplied from the EECWS. The fan in the mechanical equipment room fan-coil cooling unit is also energized under room thermostat control. Chilled-water flow through the cooling coil of the unit continues unimpeded as during normal operation. [UFSAR 9.4.1.2.3]This chilled water pump provides water for chilled water portion of the Control Center Air Conditioning Water Control to provide for temperature control of Cooling Coil T4100B007 (225 gpm), Chiller T4100B009 Compressor Motor (12 gpm), Oil Cooler (2 gpm), and Equipment Room Fan T4100B028 (10 gpm).[UFSAR Figure 9.4-3] The chilled water pump is designed for a 300 gpm flow at a dynamic head of 50 feet. [UFSAR Table 9.4-1 C]
Function
Description:
Group A - This pump operates continuously or routinely during normal operation, cold shutdown, or refueling operations.The CCHVAC system ensures that the Control Room will remain habitable for operating personnel during and following all design basis accident conditions. During a loss of coolant accident (LOCA), the CCHVAC System limits the radiation exposure to personnel within the control room based on the requirements of 10CFR50, Appendix A, General Design Criterion 19. [DBD T41-02 Section 2.2.3]The chilled water pump performs safety related functions during normal, recirculation, purge, and chlorine modes. Each chilled water pump provides the capability to supply chilled water from the evaporator of the chiller unit to the cooling coils of the multi-zone Air-Conditioning unit and the MER fan coil unit, and return the chilled water to the evaporator. Chilled water is also supplied to the chiller compressor motor, oil cooler, and the purge condenser. Chilled water is not required for the MER fan coil units during normal operation and purge modes; however, it is not isolated. The chilled water pump has sufficient flow capacity to circulate water to remove heat from the control center and-its associated chilled water circuits. The chilled water pump shall have sufficient head to overcome friction and dynamic losses in the piping, cooling coils, evaporator, and appurtenances in the chilled water circuits. [DBD T41-02 Section 4.2.4.2]
Design Basis Limits: TS SR 3.7.4.1 - Verify the control room air temperature is less than or equal to 95 degrees F every 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />sThis SR verifies that the heat removal capability of the system is sufficient to remove the control room heat load. The SR consists of a verification of control room temperature. [TS B SR 3.7.4.1]The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Frequency is appropriate since significant degradation of the Control Center AC System is not expected over this time period.UFSAR Table 9.4-1 Control Center HVAC System Major Components Descriptions and DBD T41-02 Section 4.2.4.3 Design RequirementsChilled Water PumpsType Centrifugal, vertically split casingTotal Dynamic head capacity 300 gpmTotal Dynamic head 50 ft water columnMotor 7 .5 horsepowerThe chilled water pump is required to operate at 249 gpm in all modes. [DBD T41-02 Section 4.2.4.3]
Design
References:
TS 3.7.4 Control Center Air Conditioning (AC) SystemUFSAR 6.4 Habitability Systems UFSAR 6.4.2.3 Air Conditioning SystemUFSAR 7.1.2.1.17 Control Center Atmospheric Control SystemUFSAR 9.4.1 Control Center Air Conditioning SystemUFSAR Table 9.4-1 Control Center HVAC System Major Components DescriptionsUFSAR Table 9.4-2 Main Control Room Air Conditioning System Single-Failure AnalysisUFSAR Figure 9.4-3 Control Center Air Conditioning Water Control Flow DiagramDBD T41-02, Rev F, Control Center Heating, Ventilating, and Air Conditioning (CCHVAC) System Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 105 of 106
Fermi Nuclear Plant DSN:IST Program Pump Basis, Rev.1, Page 107 of 111 Fermi Unit 2 4th Interval IST Program Manual Part 12 - IST Program Pump Basis Component ID System Description P&ID/Coor Group Class Type Program Plan Test Req Freq Procedure Notes Appendix V Basis: OM Code Appendix V paragraph V-3000(a) Requirement: The Owner shall (a) identify those certain applicable pumps with specific design basis accident flow rates in the Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) for inclusion in this program.This pump has been deemed not applicable to Appendix V. UFSAR Table 9.4-1 lists a pump description for the chilled water pumps including a flow rate of 300 gpm with a total head of 50 feet. This 300 gpm flow rate is considered a nominal rating and not an Owner's credited safety analysis (e.g., technical specifications, technical requirements program, or updated safety analysis report) as defined in Appendix V.
Jan 4, 2021 2:09 PM Iddeal Suite V. 9.35.2.1 Page 106 of 106
DSN:IST Program Pump Basis, Rev.1, Page 108 of 111 Jeffrey D Auler From: Craig E Shepherd Sent: Friday, January 8, 2021 12:38 PM To: Jeffrey D Auler
Subject:
Approvals, IST Program Pump Basis To: Jeff Auler, IST Program Manager I have reviewed and approved the following DTC DSN Revision Approval TMPLAN IST Program Pump 1 Reviewer:
Basis Craig Shepherd I also authorize any page renumbering required by inclusion of this email within the overall document as required per NSI P-20-0005.
Regards, Craig Shepherd 1
DSN:IST Program Pump Basis, Rev1, Page 109 of 111 Jeffrey D Auler From: Jeffrey D Auler Sent: Friday, January 8, 2021 1:19 PM To: Jeffrey D Auler
Subject:
IST Program Pump Basis I have prepared and app rove the following:
DTC DSN Revision Approval TM PLAN IST Program Pump 1 Preparer:
Basis Jeffrey D. Auler /s/
I also authorize any page renumbering required by inclusion of this email within the overall document as required per NSI P-20-0005.
Regards, Jeffrey D. Auler 1
DSN:IST Program Pump Basis, Rev.1, Page 110 of 111 Jeffrey D Auler From: James D Wines Sent: Tuesday, January 12, 2021 4:15 PM To: Jeffrey D Auler Cc: Randy D Breymaier
Subject:
Part 12 Pump basis Attachments: IST Program Plan Part 12.pdf I have reviewed and approve the following as the Supervisor, Engineering Programs DTC DSN Revision Approval TMPLAN IST Program Pump 1 Reviewer Basis James D Wines /s/
I also authorize any page renumbering required by inclusion of this email within the overall document as required per NSI P-20-0005.
James Wines I Supervisor - Nuclear Engineering (Programs)
Phone: 734.586.1701 1Text: 734.625.3154 1 Pager: 734.227.0076 1 eMail: James.Wines@dteenergy.com 1
DSN:IST Program Pump Basis, Rev.1, Page 111 of 111 Jeffrey D Auler From: Randy D Breymaier Sent: Friday, January 15, 2021 1:32 PM To: Jeffrey D Auler
Subject:
RE: Send this back to me (pump basis part 12)
I have reviewed and approve the following as the Manager, Engineering Programs DTC DSN Revision Approval TMPLAN IST Program Pump 1 Manager Approval Basis Randy Breymaier/s/
I also authorize any page renumbering required by inclusion of this email within the overall document as required per NSI P-20-0005.
Randy Breymaier Manager Performance Engineering 734 586-1811 1