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{{#Wiki_filter:E Design Criteria Ginna Station Spent Fuel Pool Cooling System Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649 ENR 1594 Revision 1 October 10, 1979 V Prepared by: Mechanical Engineer DATE Reviewed by: Quality Assurance/osz 7 DATE Approved by: Manag r, Mechanical Engineering DATE~Page i 80022 0< | {{#Wiki_filter:E Design Criteria Ginna Station Spent Fuel Pool Cooling System Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649 ENR 1594 Revision 1 October 10, 1979 V Prepared by: Mechanical Engineer DATE Reviewed by: Quality Assurance/osz 7 DATE Approved by: Manag r, Mechanical Engineering DATE~Page i 80022 0< | ||
0 Revision Status Sheet Page Latest Rev.Page Tables Latest Rev.0 Page Latest Rcv.3 4 0 0 0 0 II-1 II-2 III-1 IV-1 V-1 VI-1 0 0 0 0 0 0 0 0 10 0 14 15 0 16 17 0 0 Design Criteria EWR 1594 Page ii Revision Date lo/lo/79 42 9l 1.0 Summar Descr i tion of the Desi n Summary 1.1.1 In 1976, new high density fuel storage racks were in-stalled in the spent fuel pool to increase the number of spent fuel elements which can be stored on site.In order to effectively use the new racks it is necessary to increase the cooling capacity of the spent fuel pool cooling system (SFPCS).1.1.2 The existing SFPCS consists of a single installed pump and heat exchanger with a cooling capacity of 9.3 million Btu/hr.with a pool temperature of 150'F and a lake temperature of 80'F.Backup cooling is provided by hosing in a skid-mounted heat, exchanger and pump.The installed and skid-mounted systems can be operated in parallel to provide lower pool temperatures. | 0 Revision Status Sheet Page Latest Rev.Page Tables Latest Rev.0 Page Latest Rcv.3 4 0 0 0 0 II-1 II-2 III-1 IV-1 V-1 VI-1 0 0 0 0 0 0 0 0 10 0 14 15 0 16 17 0 0 Design Criteria EWR 1594 Page ii Revision Date lo/lo/79 42 9l | ||
===1.0 Summar=== | |||
Descr i tion of the Desi n Summary 1.1.1 In 1976, new high density fuel storage racks were in-stalled in the spent fuel pool to increase the number of spent fuel elements which can be stored on site.In order to effectively use the new racks it is necessary to increase the cooling capacity of the spent fuel pool cooling system (SFPCS).1.1.2 The existing SFPCS consists of a single installed pump and heat exchanger with a cooling capacity of 9.3 million Btu/hr.with a pool temperature of 150'F and a lake temperature of 80'F.Backup cooling is provided by hosing in a skid-mounted heat, exchanger and pump.The installed and skid-mounted systems can be operated in parallel to provide lower pool temperatures. | |||
1.1.3 1.1.4 1.2 To provide for effective use of the new spent, fuel pool rack capacity, and to provide a margin for future cool-ing requirements, a new 16 million Btu/hr cooling system will be installed. | 1.1.3 1.1.4 1.2 To provide for effective use of the new spent, fuel pool rack capacity, and to provide a margin for future cool-ing requirements, a new 16 million Btu/hr cooling system will be installed. | ||
The existing cooling system and backup system will serve as backup to the new system.The necessary modifications are shown schematically on the attached Figures 1 and 2.The general arrangement of equipment and piping is shown on Figure 3.Figure 4 provides a basic electrical one line diagram.Functions 1.2.1 The new spent fuel pool cooling system and component design parameters are given in attached Tables I and II respectively. | The existing cooling system and backup system will serve as backup to the new system.The necessary modifications are shown schematically on the attached Figures 1 and 2.The general arrangement of equipment and piping is shown on Figure 3.Figure 4 provides a basic electrical one line diagram.Functions 1.2.1 The new spent fuel pool cooling system and component design parameters are given in attached Tables I and II respectively. | ||
1.2.2 Spent Fuel Cooling Pumps 1.2.2.1 The new spent fuel pool pump (SFP P-2)shall provide 1004 of the design flow.It shall be a horizontal/ | |||
====1.2.2 Spent==== | |||
Fuel Cooling Pumps 1.2.2.1 The new spent fuel pool pump (SFP P-2)shall provide 1004 of the design flow.It shall be a horizontal/ | |||
centrifugal unit.All wetted surfaces shall be aus-tenitic stainless steel.1.2.2.2 The existing SFP pump (SFP P-1)and the skid mounted SFP backup pump (SFP P-3)are similar in capacity.Together they provide 100%of the flow required for backup cooling.These pumps are horizontal/centrifugal units.All wetted surfaces are austenitic stainless steel.1.2.2.3 The existing suction lines in the vicinity of the spent fuel pumps shall be modified so that two separate Design Criteria Revision 0 EHR 1594 Page 1 Date suction lines from the spent fuel pool combine into a common header from which the new pump, the existing pump and the skid mounted pump take suction.1.2.3 1.2.3.1 Spent Fuel Pool Cooling Heat Exchangers The new SFP heat exchanger (SFP HX-2)shall be the shell and U-tube type.SFP water will circulate through the tubes while service water will circulate through the shell.The SFP HX-2 shall be sized for 100 percent of the design heat load.1.2.3.2 The existing SFP heat exchanger (SFP HX-1)and the skid mounted SFP backup heat exchanger (SFP HX-3)are similar in capacity, and are the shell and U-tube type.SFP water circulates through the tubes while service water circulates through the shell.These two heat exchangers can remove more than 100%of the design heat load when operated in parallel.1.2.4 1.2.4.1 Spent Fuel Pool instrumentation Local pressure, temperature, and flow instrumentation is provided for testing and monitoring the performance of the pumps and heat exchangers. | centrifugal unit.All wetted surfaces shall be aus-tenitic stainless steel.1.2.2.2 The existing SFP pump (SFP P-1)and the skid mounted SFP backup pump (SFP P-3)are similar in capacity.Together they provide 100%of the flow required for backup cooling.These pumps are horizontal/centrifugal units.All wetted surfaces are austenitic stainless steel.1.2.2.3 The existing suction lines in the vicinity of the spent fuel pumps shall be modified so that two separate Design Criteria Revision 0 EHR 1594 Page 1 Date suction lines from the spent fuel pool combine into a common header from which the new pump, the existing pump and the skid mounted pump take suction.1.2.3 1.2.3.1 Spent Fuel Pool Cooling Heat Exchangers The new SFP heat exchanger (SFP HX-2)shall be the shell and U-tube type.SFP water will circulate through the tubes while service water will circulate through the shell.The SFP HX-2 shall be sized for 100 percent of the design heat load.1.2.3.2 The existing SFP heat exchanger (SFP HX-1)and the skid mounted SFP backup heat exchanger (SFP HX-3)are similar in capacity, and are the shell and U-tube type.SFP water circulates through the tubes while service water circulates through the shell.These two heat exchangers can remove more than 100%of the design heat load when operated in parallel.1.2.4 1.2.4.1 Spent Fuel Pool instrumentation Local pressure, temperature, and flow instrumentation is provided for testing and monitoring the performance of the pumps and heat exchangers. | ||
1.2.4.2 A new level switch shall be provided in the spent fuel pool which will trip the new SFP pump (SFP P-2)in the event of low water level in the spent fuel pool.1.2.4.3 A new, local, flow indicating switch shall be provided in the discharge piping of the new pump.This new flow switch shall include a control xoom annunciator that will alarm when SFP P-2 flow is low or when SFP P-2 is tripped;1.2.5 Spent, Fuel Pool Valves Manual valves are provided for throttling and isolation of the SFPCS components and to isolate the cleanup and makeup system from the cooling system.Check valves are, provided at the discharges of pumps SFP P-1 and SFP P-2 to prevent back flow.Valves are provided at the hose connections for the skid mounted backup components for reduced connection time.All valves in contact with SFP water are austenitic stainless steel.Design Criteria EWR 1594 Page 2 Revision DR(Q 5/23/79 1.2.6 1.2.6.1 Spent Fuel Pool Piping All piping in contact with SFP water shall be aus-tenitic stainless steel.The piping shall be of welded construction, except where flanged connections are re-quired to facilitate maintenance and installation. | 1.2.4.2 A new level switch shall be provided in the spent fuel pool which will trip the new SFP pump (SFP P-2)in the event of low water level in the spent fuel pool.1.2.4.3 A new, local, flow indicating switch shall be provided in the discharge piping of the new pump.This new flow switch shall include a control xoom annunciator that will alarm when SFP P-2 flow is low or when SFP P-2 is tripped;1.2.5 Spent, Fuel Pool Valves Manual valves are provided for throttling and isolation of the SFPCS components and to isolate the cleanup and makeup system from the cooling system.Check valves are, provided at the discharges of pumps SFP P-1 and SFP P-2 to prevent back flow.Valves are provided at the hose connections for the skid mounted backup components for reduced connection time.All valves in contact with SFP water are austenitic stainless steel.Design Criteria EWR 1594 Page 2 Revision DR(Q 5/23/79 1.2.6 1.2.6.1 Spent Fuel Pool Piping All piping in contact with SFP water shall be aus-tenitic stainless steel.The piping shall be of welded construction, except where flanged connections are re-quired to facilitate maintenance and installation. | ||
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In the event a full core is unloaded from the reactor and stored in the spent fuel pool, the new SFP P-2/SFP HX-2 loop will be operated alone.The SFP P-1/SFP HX-1 and SFP P-3/SFP HX-3 loops would be in place and available for backup cooling if required.1.5.3 Normally either the SFP P-1/SFP HX-1 loop or the SFP P-2/SFP HX-2 loop is operated alone to maintain desired pool temperatures. | In the event a full core is unloaded from the reactor and stored in the spent fuel pool, the new SFP P-2/SFP HX-2 loop will be operated alone.The SFP P-1/SFP HX-1 and SFP P-3/SFP HX-3 loops would be in place and available for backup cooling if required.1.5.3 Normally either the SFP P-1/SFP HX-1 loop or the SFP P-2/SFP HX-2 loop is operated alone to maintain desired pool temperatures. | ||
The SFP P-3/SFP HX-3 loop is connected and operated only when high heat loads are anticipated. | The SFP P-3/SFP HX-3 loop is connected and operated only when high heat loads are anticipated. | ||
1.5.4 Following a safety injection signal, the new spent fuel pool pump SFP P-2 shall be shed from bus 116.After termination of safety injection, SFP P-2 can be manu-ally started and powered from diesel generator No.1B.1.5.5 Following loss of offsite power coincident with safety injection, SFP P-1 sheds from bus 114.After termina-tion of safety injection, SFP P-1 can be manually started and powered from diesel generator No.1A.1.5.6 1.5.7 In the unlikely event of the spent.fuel pool pumps shedding, the cooling of the SFP water is interrupted. | |||
====1.5.4 Following==== | |||
a safety injection signal, the new spent fuel pool pump SFP P-2 shall be shed from bus 116.After termination of safety injection, SFP P-2 can be manu-ally started and powered from diesel generator No.1B.1.5.5 Following loss of offsite power coincident with safety injection, SFP P-1 sheds from bus 114.After termina-tion of safety injection, SFP P-1 can be manually started and powered from diesel generator No.1A.1.5.6 1.5.7 In the unlikely event of the spent.fuel pool pumps shedding, the cooling of the SFP water is interrupted. | |||
Consequently, the SFP water temperature increases, as specified in Table I, until approximately one hour after the safety injection when the SFP pumps can be manually started on the normal or standby power system.In the event of low water level in the spent fuel pool, a new level switch will trip SFP P-2 pump.2.0 Referenced Documents The following documents are referenced herein.Their applicability or requirements for design are as speci-fied in this criteria document.2.1 USNRC Regulatory Guides 2.1.1 No.1.26,"Quality Group Classifications and Standards for Water, Steam, and Radiowaste Containing Components for Nuclear Power Plants," Rev.3, February 1976.Design Criteria ENR 1594 5 1t Pape Revision Date 42-90 2.1.2 2.1.3 No.1.29,"Seismic Design Classification," Rev.3, September 1978.No.1.48,"Design Limits and Loading Combinations for Seismic Category I Fluid System Components," May 1973.2.1.4 No.1.60,"Design Response Spectra for Seismic Design of Nuclear Power Plants," Rev.1, December 1973.2.1.5 No.1.61,"Damp'ing Values for Seismic Design of Nuclear Power Plants," October 1973.2.1.6 No.1.92,"Combining Mod'al Responses and Spatial Com-ponents in Seismic Response Analysis,"Rev. | Consequently, the SFP water temperature increases, as specified in Table I, until approximately one hour after the safety injection when the SFP pumps can be manually started on the normal or standby power system.In the event of low water level in the spent fuel pool, a new level switch will trip SFP P-2 pump.2.0 Referenced Documents The following documents are referenced herein.Their applicability or requirements for design are as speci-fied in this criteria document.2.1 USNRC Regulatory Guides 2.1.1 No.1.26,"Quality Group Classifications and Standards for Water, Steam, and Radiowaste Containing Components for Nuclear Power Plants," Rev.3, February 1976.Design Criteria ENR 1594 5 1t Pape Revision Date 42-90 2.1.2 2.1.3 No.1.29,"Seismic Design Classification," Rev.3, September 1978.No.1.48,"Design Limits and Loading Combinations for Seismic Category I Fluid System Components," May 1973.2.1.4 No.1.60,"Design Response Spectra for Seismic Design of Nuclear Power Plants," Rev.1, December 1973.2.1.5 No.1.61,"Damp'ing Values for Seismic Design of Nuclear Power Plants," October 1973.2.1.6 No.1.92,"Combining Mod'al Responses and Spatial Com-ponents in Seismic Response Analysis,"Rev. | ||
1, February 1976: 2.1.7 No.1.100,"Seismic Qualification of Electric Equipment for Nuclear Power Plants, Rev.1, August 1977.2.2 American Society of Mechanical Engineers (ASME)Boiler and Pressure Vessel Code-1977 Edition with Addenda through Minter 1978.Section IIX-"Nuclear Power Plant Compents" Section XI-"In Service Inspection" 2.3 American National Standards Institute (ANSI)2.3.1 ANSI N45.2.1-1973,"Cleaning of Fluid Systems and Associated Components During Construction Phase of Nuclear Power Plants".2.3.2 ANSX N45 2 2 1 972 I"Packaging, Shipping, Receiving, Storage and Handling of Xtems for Nuclear Power Plants".2.3.3 ANSI N45.2.3-1973,"Housekeeping During the Construc-tion Phase of Nuclear Power Plants".2.3.4 ANSI N45.2.8-1975,"Supplemental Quality Assurance Requirements for Installation, Inspection, and Testing of Mechanical Equipment and Systems for the Construction Phase of Nuclear Power Plants".2.4 Institute of Electrical and Electronic Engineers (IEEE)2.4.1 IEEE-323-1974,"Standard for Qualifying Class IE Equip-ment for Nuclear Power Generating Stations". | 1, February 1976: 2.1.7 No.1.100,"Seismic Qualification of Electric Equipment for Nuclear Power Plants, Rev.1, August 1977.2.2 American Society of Mechanical Engineers (ASME)Boiler and Pressure Vessel Code-1977 Edition with Addenda through Minter 1978.Section IIX-"Nuclear Power Plant Compents" Section XI-"In Service Inspection" 2.3 American National Standards Institute (ANSI)2.3.1 ANSI N45.2.1-1973,"Cleaning of Fluid Systems and Associated Components During Construction Phase of Nuclear Power Plants".2.3.2 ANSX N45 2 2 1 972 I"Packaging, Shipping, Receiving, Storage and Handling of Xtems for Nuclear Power Plants".2.3.3 ANSI N45.2.3-1973,"Housekeeping During the Construc-tion Phase of Nuclear Power Plants".2.3.4 ANSI N45.2.8-1975,"Supplemental Quality Assurance Requirements for Installation, Inspection, and Testing of Mechanical Equipment and Systems for the Construction Phase of Nuclear Power Plants".2.4 Institute of Electrical and Electronic Engineers (IEEE)2.4.1 IEEE-323-1974,"Standard for Qualifying Class IE Equip-ment for Nuclear Power Generating Stations". | ||
| Line 46: | Line 53: | ||
FSAR Section 1.2.1).3.5 The SFP P-3/SFP HX-3 backup cooling loop is non-seismic. | FSAR Section 1.2.1).3.5 The SFP P-3/SFP HX-3 backup cooling loop is non-seismic. | ||
4.0 Qualit Grou Design Criteria ERR 15 94 Page 7 Revision Date 10/10/79 42.90.' | |||
===4.0 Qualit=== | |||
Grou Design Criteria ERR 15 94 Page 7 Revision Date 10/10/79 42.90.' | |||
~~ | ~~ | ||
~~~~4.1 Consistent with Regulatory Guide 1.26 the new spent fuel pool cooling system components are assigned the quality groups as shown in Table III.5.0 Code Class 5.1 The new spent fuel pool cooling system component ASME code classes are as shown in Table III.6.0 Codes Standards and Re ulator Re uirements 6.1 The following requirements shall apply to the design and installation of the new spent fuel pool cooling system including the modifications of the existing system as indicated on Figures 1 and 2.The design, materials, fabrication, installation, examination and testing of the Quality Group C com-ponents shall be in accordance with the requirements of ASME Section III, Subsection ND, except that code stamping and third party inspection is not required for field fabrication and installation. | ~~~~4.1 Consistent with Regulatory Guide 1.26 the new spent fuel pool cooling system components are assigned the quality groups as shown in Table III.5.0 Code Class 5.1 The new spent fuel pool cooling system component ASME code classes are as shown in Table III.6.0 Codes Standards and Re ulator Re uirements 6.1 The following requirements shall apply to the design and installation of the new spent fuel pool cooling system including the modifications of the existing system as indicated on Figures 1 and 2.The design, materials, fabrication, installation, examination and testing of the Quality Group C com-ponents shall be in accordance with the requirements of ASME Section III, Subsection ND, except that code stamping and third party inspection is not required for field fabrication and installation. | ||
| Line 86: | Line 95: | ||
27.3 Level B, C, and D requirements shall apply for other materials and equipment as indicated in ANSI N45.2.2.28.0 Public Safet Re uirements None.Design Criteria ELjR 1594 16 Page Revision Date 42.90 | 27.3 Level B, C, and D requirements shall apply for other materials and equipment as indicated in ANSI N45.2.2.28.0 Public Safet Re uirements None.Design Criteria ELjR 1594 16 Page Revision Date 42.90 | ||
~t~~29.0 A licabilit 30.0 None.Personnel Sachet Re uirements 31.0 None.Uni ue Re uirements None.Design Criteria ERR 1594 Page 17 Revision Date 0 5/23/79 42 90 | ~t~~29.0 A licabilit 30.0 None.Personnel Sachet Re uirements 31.0 None.Uni ue Re uirements None.Design Criteria ERR 1594 Page 17 Revision Date 0 5/23/79 42 90 | ||
~~~~TABLE 1 SPENT FUEL KOL COOLING SYSTEM DESIGN PARAMETERS 1.0 SFP storage capacity, assemblies 2.0 SFP water volume, ft 3 (water level 1'-4" fran top of pool)3.0 Design Heat Load Conditions 3.1 Initial decay heat, Btu/hr.3.2 Maximum pool temperature,'F 3.3 SFP heat up rate,'F/hr.(assumes no cooling)4.0 Service Water Requirements 4.1 SW temperature,'F 4.2 Max.SW temp.increase,'F 4.3 Si flow, gpn (approx.)Safet 16 x 10 150 7.7 80 20 1600 595 34,100 No 1 7.6 x 10 120 3.7 80 15 1000 Design Criteria EWR 1594 Page Revision Date 5/23/79 42.90 TABLE II SPENT FUEL POOL COOLING SYSTEM COMPONENTS DESIGN PAKQKTERS SFP P-2 (New)Quantity Design pressure, psig Design temperature,'F Design flow, gpm (approx.)NPSH available, Ft.(approx.)Design head, Ft.(approx.)Material Design Code Seismic Category SFP HX-2 (New)Quantity Design heat transfer, BTU/hr Design pressure, psig Design temperature,'F Design flew, gpn (Approx.)Inlet temperature,'F Outlet temperature,'F Fluid circulated Material Design Codes Seismic Category Design Criteria EHR 1594 Pnge 150 200 1,200 25 150 Austenitic Stainless Steel ASME Section III, Class 3 16 x 10 6 Shell 150 200 150 200 1600 1200 80 150 100 Max.Service Hater SFP Hater Revision 1 Dn/e 10/10/7 9 42.90 Carbon Steel Austenitic Stainless Steel ASME Section III, Class 2 and TEMA"E S nt Fuel Pool Hater Pi in/Valves (New)Design pressure, psig Design Temperature,'F Material Design Code Seismic Category 150 200 Austenitic Stainless Steel ASt4E Section III, Class 3 Service Water Pi in/Valves (New)Design pressure, psig Design temperature,'F Material Design Code Seismic Category 150 200 Carbon Steel ASME Section III, Class 3 Design Criteria EWR 1594 page II 2 Revision Date 5/23/79 | ~~~~TABLE 1 SPENT FUEL KOL COOLING SYSTEM DESIGN PARAMETERS 1.0 SFP storage capacity, assemblies 2.0 SFP water volume, ft 3 (water level 1'-4" fran top of pool)3.0 Design Heat Load Conditions | ||
===3.1 Initial=== | |||
decay heat, Btu/hr.3.2 Maximum pool temperature,'F 3.3 SFP heat up rate,'F/hr.(assumes no cooling)4.0 Service Water Requirements 4.1 SW temperature,'F 4.2 Max.SW temp.increase,'F 4.3 Si flow, gpn (approx.)Safet 16 x 10 150 7.7 80 20 1600 595 34,100 No 1 7.6 x 10 120 3.7 80 15 1000 Design Criteria EWR 1594 Page Revision Date 5/23/79 42.90 TABLE II SPENT FUEL POOL COOLING SYSTEM COMPONENTS DESIGN PAKQKTERS SFP P-2 (New)Quantity Design pressure, psig Design temperature,'F Design flow, gpm (approx.)NPSH available, Ft.(approx.)Design head, Ft.(approx.)Material Design Code Seismic Category SFP HX-2 (New)Quantity Design heat transfer, BTU/hr Design pressure, psig Design temperature,'F Design flew, gpn (Approx.)Inlet temperature,'F Outlet temperature,'F Fluid circulated Material Design Codes Seismic Category Design Criteria EHR 1594 Pnge 150 200 1,200 25 150 Austenitic Stainless Steel ASME Section III, Class 3 16 x 10 6 Shell 150 200 150 200 1600 1200 80 150 100 Max.Service Hater SFP Hater Revision 1 Dn/e 10/10/7 9 42.90 Carbon Steel Austenitic Stainless Steel ASME Section III, Class 2 and TEMA"E S nt Fuel Pool Hater Pi in/Valves (New)Design pressure, psig Design Temperature,'F Material Design Code Seismic Category 150 200 Austenitic Stainless Steel ASt4E Section III, Class 3 Service Water Pi in/Valves (New)Design pressure, psig Design temperature,'F Material Design Code Seismic Category 150 200 Carbon Steel ASME Section III, Class 3 Design Criteria EWR 1594 page II 2 Revision Date 5/23/79 | |||
~~TABLE III QUALITY GROUP, SEISMIC CATEGORY AND CODE CLASS SPENT FUEL HKL COOLING SYSTEM COMKJNENTS CQ1FONENT PUMP SFP P-2 HEAT EXCHANGER SFP HX-2 QUALITY GROUP SEISMIC CATEGORY ABIE CODE CLASS Section III, Class 3 Section XII, Class 3 bGTOR FOR SFP P-2, LOAD CENTER, CONTROL STATION, LEVEL SNITCH LOCAL HAND STATION PIPXNG, NBV AND MODIFIED.PIPING, NEW AND MODIFIED VALVES, NEN N/A Class XE N/A Section III, Class 3 Section III, Class 3 NH4 INSTRUMENTATION In-line Instrumentation C Section IXX, Class 3 Indicating Instrtmtenta-tion D Non-seismic Manufacturer.' | ~~TABLE III QUALITY GROUP, SEISMIC CATEGORY AND CODE CLASS SPENT FUEL HKL COOLING SYSTEM COMKJNENTS CQ1FONENT PUMP SFP P-2 HEAT EXCHANGER SFP HX-2 QUALITY GROUP SEISMIC CATEGORY ABIE CODE CLASS Section III, Class 3 Section XII, Class 3 bGTOR FOR SFP P-2, LOAD CENTER, CONTROL STATION, LEVEL SNITCH LOCAL HAND STATION PIPXNG, NBV AND MODIFIED.PIPING, NEW AND MODIFIED VALVES, NEN N/A Class XE N/A Section III, Class 3 Section III, Class 3 NH4 INSTRUMENTATION In-line Instrumentation C Section IXX, Class 3 Indicating Instrtmtenta-tion D Non-seismic Manufacturer.' | ||
Standards Design Criteria EWR 1594 V Page XIX-l Revision Date 5/23/79 42.90 a Ul 00 Vl O Q t5 Component Heat Exchanger Design PD+DW+ML TABLE IV LOAD COMBINATIONS Service Limits-Level A PD+DW+ML+TL Level B PD+DW+ML+HL+OBE Level C PD+DW+ML+HL+SSE Pump (Active)Valves (Active)PD+DW+ML PD+DW+ML PD+DW+ML+HL+OBE!PD+DW+ML+HL+OBE PD+DW+ML+HL+SSE PD+DW+ML+HL+SSE N.A.N.A.Valves (Non-Active) | Standards Design Criteria EWR 1594 V Page XIX-l Revision Date 5/23/79 42.90 a Ul 00 Vl O Q t5 Component Heat Exchanger Design PD+DW+ML TABLE IV LOAD COMBINATIONS Service Limits-Level A PD+DW+ML+TL Level B PD+DW+ML+HL+OBE Level C PD+DW+ML+HL+SSE Pump (Active)Valves (Active)PD+DW+ML PD+DW+ML PD+DW+ML+HL+OBE!PD+DW+ML+HL+OBE PD+DW+ML+HL+SSE PD+DW+ML+HL+SSE N.A.N.A.Valves (Non-Active) | ||
Revision as of 23:27, 8 October 2018
| ML17249A603 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 10/10/1979 |
| From: | EASTERBROOK K G, HUTTON J C, VOCI E K ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17249A600 | List: |
| References | |
| EWR-1594, EWR-1594-R1, NUDOCS 8002200549 | |
| Download: ML17249A603 (37) | |
Text
E Design Criteria Ginna Station Spent Fuel Pool Cooling System Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649 ENR 1594 Revision 1 October 10, 1979 V Prepared by: Mechanical Engineer DATE Reviewed by: Quality Assurance/osz 7 DATE Approved by: Manag r, Mechanical Engineering DATE~Page i 80022 0<
0 Revision Status Sheet Page Latest Rev.Page Tables Latest Rev.0 Page Latest Rcv.3 4 0 0 0 0 II-1 II-2 III-1 IV-1 V-1 VI-1 0 0 0 0 0 0 0 0 10 0 14 15 0 16 17 0 0 Design Criteria EWR 1594 Page ii Revision Date lo/lo/79 42 9l
1.0 Summar
Descr i tion of the Desi n Summary 1.1.1 In 1976, new high density fuel storage racks were in-stalled in the spent fuel pool to increase the number of spent fuel elements which can be stored on site.In order to effectively use the new racks it is necessary to increase the cooling capacity of the spent fuel pool cooling system (SFPCS).1.1.2 The existing SFPCS consists of a single installed pump and heat exchanger with a cooling capacity of 9.3 million Btu/hr.with a pool temperature of 150'F and a lake temperature of 80'F.Backup cooling is provided by hosing in a skid-mounted heat, exchanger and pump.The installed and skid-mounted systems can be operated in parallel to provide lower pool temperatures.
1.1.3 1.1.4 1.2 To provide for effective use of the new spent, fuel pool rack capacity, and to provide a margin for future cool-ing requirements, a new 16 million Btu/hr cooling system will be installed.
The existing cooling system and backup system will serve as backup to the new system.The necessary modifications are shown schematically on the attached Figures 1 and 2.The general arrangement of equipment and piping is shown on Figure 3.Figure 4 provides a basic electrical one line diagram.Functions 1.2.1 The new spent fuel pool cooling system and component design parameters are given in attached Tables I and II respectively.
1.2.2 Spent
Fuel Cooling Pumps 1.2.2.1 The new spent fuel pool pump (SFP P-2)shall provide 1004 of the design flow.It shall be a horizontal/
centrifugal unit.All wetted surfaces shall be aus-tenitic stainless steel.1.2.2.2 The existing SFP pump (SFP P-1)and the skid mounted SFP backup pump (SFP P-3)are similar in capacity.Together they provide 100%of the flow required for backup cooling.These pumps are horizontal/centrifugal units.All wetted surfaces are austenitic stainless steel.1.2.2.3 The existing suction lines in the vicinity of the spent fuel pumps shall be modified so that two separate Design Criteria Revision 0 EHR 1594 Page 1 Date suction lines from the spent fuel pool combine into a common header from which the new pump, the existing pump and the skid mounted pump take suction.1.2.3 1.2.3.1 Spent Fuel Pool Cooling Heat Exchangers The new SFP heat exchanger (SFP HX-2)shall be the shell and U-tube type.SFP water will circulate through the tubes while service water will circulate through the shell.The SFP HX-2 shall be sized for 100 percent of the design heat load.1.2.3.2 The existing SFP heat exchanger (SFP HX-1)and the skid mounted SFP backup heat exchanger (SFP HX-3)are similar in capacity, and are the shell and U-tube type.SFP water circulates through the tubes while service water circulates through the shell.These two heat exchangers can remove more than 100%of the design heat load when operated in parallel.1.2.4 1.2.4.1 Spent Fuel Pool instrumentation Local pressure, temperature, and flow instrumentation is provided for testing and monitoring the performance of the pumps and heat exchangers.
1.2.4.2 A new level switch shall be provided in the spent fuel pool which will trip the new SFP pump (SFP P-2)in the event of low water level in the spent fuel pool.1.2.4.3 A new, local, flow indicating switch shall be provided in the discharge piping of the new pump.This new flow switch shall include a control xoom annunciator that will alarm when SFP P-2 flow is low or when SFP P-2 is tripped;1.2.5 Spent, Fuel Pool Valves Manual valves are provided for throttling and isolation of the SFPCS components and to isolate the cleanup and makeup system from the cooling system.Check valves are, provided at the discharges of pumps SFP P-1 and SFP P-2 to prevent back flow.Valves are provided at the hose connections for the skid mounted backup components for reduced connection time.All valves in contact with SFP water are austenitic stainless steel.Design Criteria EWR 1594 Page 2 Revision DR(Q 5/23/79 1.2.6 1.2.6.1 Spent Fuel Pool Piping All piping in contact with SFP water shall be aus-tenitic stainless steel.The piping shall be of welded construction, except where flanged connections are re-quired to facilitate maintenance and installation.
1.2.6.2 Hoses for the skid mounted SFP backup pump and SFP backup heat exchanger are Styrene Butadine Rubber (SBR).Hoses are provided with aluminum couplings.
1.2.7 1.2.7.1 Service Water System Service water to the SFP HX-2 shall be supplied from the SH loop B supply header to the component cooling heat exchanger 1B (CC-HX-1B).
The service water from the SFP HX-2 shall be discharged into the common SN discharge header from CC HX-1A and CC HX-1B.1.2.7.2 Service water to SFP HX-1 and SFP HX-3 is supplied from the SH Loop A supply header to CC HX-1A.Service water from SFP HX-1 and SFP HX-3 is discharged into the common service water discharge header from CC HX-1A and CC HX-1B.1.2.7.3 Existing motor operated valves provide automatic and remote manual isolation of the service water supply lines to CC HX-1AI CC HX 1BI and SFP HX-1.These valves close automatically upon coincidence of safety injection and loss of offsite power.Handwheels for manual operation are also provided.1.2.7.4 A new air operated butterfly valve (AOV)shall provide automatic and remote manual isolation of the service water supply to SFP HX-2.This valve will close auto-matically in the event'of safeguards actuation (safety injection) signal.The new handswitch shall be pro-vided in the control room to remotely open or close the new AOV.A handwheel for manual operation shall be provided, and position indication both in the control room and locally shall be provided as well.1.2.7.5 Hose connections isolated by butterfly valves shall be provided on the service water supply and return piping to and from CC HX-1A for the service water to and from SFP HX-3.1.2.7.6 Local pressure, temperature, and flow instrumentation is provided for testing and monitoring the performance of the new SFP HX-2.Design Criteria EHR 1594 Page 3 Revision Da(e 5/23/7 9 42.90
~~l~1.2.7.7 Radiation detectors, alarms, and recorders are provided to detect radioactivity in the service water in the event that tube leaks occur in SFP HX-1 or SFP HX-2.1.3 Performance Re uirements 1.3.1 The new spent fuel pool cooling system design parameters are given in Table 1.The conditions indicated as"Safety" are design conditions used for safety evaluation of the cooling system.The conditions indicated as"Normal" are design conditions used to assure lower pool temperature conditions after normal refueling outages.1.3.2 1.3.3 The new spent fuel pool cooling system shall be designed to maintain the SFP water below 150'F with a"Safety" basis heat load of 16 x 10 Btu/hr.This heat load is based on storing fuel from all normal refuelings through 1998 plus a full core discharge at the end of 1999.The new spent fuel pool cooling system shall be designed to maintain the SFP water below 120'F with a"Normal" basis heat load of 7.6 x 10 Btu/hr.This heat load is based on storing fuel from all normal refuelings through 1998 plus a normal 1/3 core removal at the end of 1999.1.3.4 The SFP HX-2 shall be sized to remove the Safety and Normal basis heat loads using service water at 80'F.The temperature rise shall not exceed 20'F and 15'F respectively, for the Safety and Normal.basis heat loads.1.3.5 The SFP P-1/SFP HX-1 (existing) and SFP P-3/SFP HX-3 (backup)cooling loops when operated jn parallel are capable of'emoving more than 16 x 10 Btu/hr.with a pool temperature of 150'F and a service water temperature of 80'F.1.3.6 Both of the backup cooling loop were designed to remove 7.93 x 10 Btu/hr.with a pool temperature of 150'F and service water at 80'F.1.4 Control 1.4.1 Control for all pumps shall be from local control stations near the pumps.A mechanical interlock will be provided between the control stations of SFP P-2-and ,SFP P-i, to prevent simultaneous operation of both pumps with power supply from the safety buses.SFP P-3 is operated from a non-safety power source.Design Criteria EWR 1594 4 Page Revision Date 42.90
~~1'l~~%1.5 Modes of 0 eration 1.5.1 1.5.2 Operation of the spent fuel pool cooling system is manual and intermittent.
The system is started, oper-ated, and secured locally, as required, to maintain the SFP water temperature below 150'F.Normally the pool is maintained at, lower temperatures.
In the event a full core is unloaded from the reactor and stored in the spent fuel pool, the new SFP P-2/SFP HX-2 loop will be operated alone.The SFP P-1/SFP HX-1 and SFP P-3/SFP HX-3 loops would be in place and available for backup cooling if required.1.5.3 Normally either the SFP P-1/SFP HX-1 loop or the SFP P-2/SFP HX-2 loop is operated alone to maintain desired pool temperatures.
The SFP P-3/SFP HX-3 loop is connected and operated only when high heat loads are anticipated.
1.5.4 Following
a safety injection signal, the new spent fuel pool pump SFP P-2 shall be shed from bus 116.After termination of safety injection, SFP P-2 can be manu-ally started and powered from diesel generator No.1B.1.5.5 Following loss of offsite power coincident with safety injection, SFP P-1 sheds from bus 114.After termina-tion of safety injection, SFP P-1 can be manually started and powered from diesel generator No.1A.1.5.6 1.5.7 In the unlikely event of the spent.fuel pool pumps shedding, the cooling of the SFP water is interrupted.
Consequently, the SFP water temperature increases, as specified in Table I, until approximately one hour after the safety injection when the SFP pumps can be manually started on the normal or standby power system.In the event of low water level in the spent fuel pool, a new level switch will trip SFP P-2 pump.2.0 Referenced Documents The following documents are referenced herein.Their applicability or requirements for design are as speci-fied in this criteria document.2.1 USNRC Regulatory Guides 2.1.1 No.1.26,"Quality Group Classifications and Standards for Water, Steam, and Radiowaste Containing Components for Nuclear Power Plants," Rev.3, February 1976.Design Criteria ENR 1594 5 1t Pape Revision Date 42-90 2.1.2 2.1.3 No.1.29,"Seismic Design Classification," Rev.3, September 1978.No.1.48,"Design Limits and Loading Combinations for Seismic Category I Fluid System Components," May 1973.2.1.4 No.1.60,"Design Response Spectra for Seismic Design of Nuclear Power Plants," Rev.1, December 1973.2.1.5 No.1.61,"Damp'ing Values for Seismic Design of Nuclear Power Plants," October 1973.2.1.6 No.1.92,"Combining Mod'al Responses and Spatial Com-ponents in Seismic Response Analysis,"Rev.
1, February 1976: 2.1.7 No.1.100,"Seismic Qualification of Electric Equipment for Nuclear Power Plants, Rev.1, August 1977.2.2 American Society of Mechanical Engineers (ASME)Boiler and Pressure Vessel Code-1977 Edition with Addenda through Minter 1978.Section IIX-"Nuclear Power Plant Compents" Section XI-"In Service Inspection" 2.3 American National Standards Institute (ANSI)2.3.1 ANSI N45.2.1-1973,"Cleaning of Fluid Systems and Associated Components During Construction Phase of Nuclear Power Plants".2.3.2 ANSX N45 2 2 1 972 I"Packaging, Shipping, Receiving, Storage and Handling of Xtems for Nuclear Power Plants".2.3.3 ANSI N45.2.3-1973,"Housekeeping During the Construc-tion Phase of Nuclear Power Plants".2.3.4 ANSI N45.2.8-1975,"Supplemental Quality Assurance Requirements for Installation, Inspection, and Testing of Mechanical Equipment and Systems for the Construction Phase of Nuclear Power Plants".2.4 Institute of Electrical and Electronic Engineers (IEEE)2.4.1 IEEE-323-1974,"Standard for Qualifying Class IE Equip-ment for Nuclear Power Generating Stations".
2.4.2 IEEE-334-1974,"Standard for Type Tests of Continuous Duty Class XE Motor for Nuclear Power Generating Sta-tions".Design Criteria EHR 1594 Page 0 Revision Dnte 5/23/79 2.4.3 IEEE-336-1977,"Installation, Inspection and Testing Requirements for Instrumentation and Electric Equipment During the Construction of Nuclear Power Generating Stations".
2.4.4 IEEE-344-1975,"Recommended Practices for Seismic Qualification of Class IE Equipment for Nuclear Power Generating Stations".
2.4.5 ZEEE-383-1975,"Standard for Type Test of Class IE Electric Cables, Field Splices, and Connections for Nuclear Power Generating Stations".
2.4.6 IEEE-384-1977,"Criteria for Independence of Class IE Equipment and Circuits".
2.5 2.6 American Institute of Steel Construction (AISC)"Specification for the Design, Fabrication and Erection of Structural Steel.for Buildings," November 1, 1978.American Concrete Institute (ACI)ACI Standard 318-77, Building Code for Reinforced Concrete, 1977 Edition.2.7 Tubular Exchanger Manufacturer's Association (TEMA), TEMA Standards, 1978 Edition.2.8 2.9 Rochester Gas and Electric Fire Protection Evaluation, Gilbert Associates, Inc.Report 1936, March 1977.Ginna Station Final Facility Description and Safety Analysis Report (FSAR).3.0 3.1 3.2 Seismic Cate ory Consistent with Regulatory Guide 1.29 the new spent fuel pool cooling system is seismic category I.Seismic boundaries are shown in Figure 1 and 2.3.3 Table III defines the seismic categories of various components.
3.4 The existing spent fuel pool cooling loop is defined as seismic class II in the Ginna FSAR (
Reference:
FSAR Section 1.2.1).3.5 The SFP P-3/SFP HX-3 backup cooling loop is non-seismic.
4.0 Qualit
Grou Design Criteria ERR 15 94 Page 7 Revision Date 10/10/79 42.90.'
~~
~~~~4.1 Consistent with Regulatory Guide 1.26 the new spent fuel pool cooling system components are assigned the quality groups as shown in Table III.5.0 Code Class 5.1 The new spent fuel pool cooling system component ASME code classes are as shown in Table III.6.0 Codes Standards and Re ulator Re uirements 6.1 The following requirements shall apply to the design and installation of the new spent fuel pool cooling system including the modifications of the existing system as indicated on Figures 1 and 2.The design, materials, fabrication, installation, examination and testing of the Quality Group C com-ponents shall be in accordance with the requirements of ASME Section III, Subsection ND, except that code stamping and third party inspection is not required for field fabrication and installation.
6.2 In addition to ASME Section III requirements, SFP HX-2, fabrication shall be in accordance with TEMA"R" stan-dards.6.3 The design, materials, fabrication, installation, ex-amination and testing of seismic piping supports and anchors-pump supports, and heat exchanger supports shall be in accordance with the requirements of ASME Section III, Subsection NF, except that code stamping and third party inspection for field fabrication and installation is not required.6.4 6.5 The design, fabrication, and erection of structural steel modifications and additions not within the scope of ASME III Subsection NF shall be in accordance with the requirements of the AISC Specification.
Modifications and additions of concrete structures shall be designed and installed in accordance with the requirements of ACI 318.6.6 6.7 Cleaning of the spent fuel pool cooling system shall be in accordance with the piping requirements of ANSI N45.2.1 to the extent practical.
Housekeeping during construction shall be in accordance with the requirements of ANSI N45.2.3.Design Criteria EHR 1594 8 Page Revision D (5/23/79 42 90 I'
~~6.8 Installation of the new spent fuel pool cooling system shall be in accordance with Sections 2, 3, and 4 of ANSI N45.2.8.7.0 7.1 Desicen Parameters The new spent fuel pool cooling system design parame-ters are given in Table I.7.2 The new spent fuel pool cooling system component design parameters will be as given in Table II.7.3 The new spent.fuel pool cooling system (including the existing cooling and cleanup system)is shown in Figures 1 and 2.8.0 Load Conditions 8.1 The following requirements shall apply to the design of the new spent fuel pool cooling system and system com-ponents.The new spent fuel pool cooling system components and their supports shall be designed to sustain loads due to seismic accelerations and displacements, weight, pressure, and thermal expansion, as applicable.
8.2 Mechanical
and electrical components and their supports designated as seismic category I or class 1E shall be designed to remain functional following the SSE.8.3 The seismic ground response spectra shall be based on the requirements of USNRC Regulatory Guide 1.60 using peak accelerations of 0.2g for the SSE, and 0.08g for the OBE.8.4 Floor response curves and seismic analyses shall be based on the damping values required by USNRC Reg.Guide 1.61.8.5 The accelerations and displacements of the various modes determined during the seismic analyses (spectrum analyses)shall be combined as required by USNRC Reg.Guide 1.92.8.7 Design and service load combinations are as specified in Table IV.8.7.1 The stress limits as defined in ASME Section III shall be used for the load combinations in Table IV.8.7.2 The spent fuel pool pump and valves with operators are active components.
For these components, note no.11 of USNRC Reg.Guide 1.48 shall apply.Design Criteria Revts ton EHR 15 94 Page~Date 42.90 8.7.3 8.8 9.0 Manually operated valves and check valves are considered non-active components.
Seismic qualification of new Class 1E components shall be in accordance with IEEE-344 requirements, as amended by USNRC Regulatory Guide 1.100.Environmental Conditions 9.1 The new spent fuel pool cooling system shall be de-signed to withstand the following environmental con-ditions in the auxiliary building without impairment of operability.
Normal Accident Ambient Temperature,'F Ambient Pressure, psig Relative Humidity, Radioactivity 50-104*104 ATM.ATM.100 100 17.5 x 10 rads 9.2 Instrumentation and controls located in the control room shall be designed to withstand the following environmental conditions.
Normal Accident Ambient Temperature,'F Ambient Pressure, psig Relative Humidity, Radioactivity 50-90 ATM.5-90 None 50-90 ATM.5-90 None 10.0 10.1 10.2 Interface Re uirements The new spent fuel pooling cooling system shall be designed to be installed in parallel with the existing SFP cooling system without degradation of function of the existing SFP cooling system or service water systems.The function and adequacy of existing structures shall not be degraded by the installation of the new SFP cooling system.10.3 The existing electrical systems shall not be degraded by the addition of the new SFP cooling system.10.4 Interfaces between seismic category I and non-seismic piping systems shall be designed in a manner which will not degrade the required function of the seismic system.Design Criteria ENR 1594 Page 10 Revision Da(e 10/10/7 9 42.90
~~4 I 11.0 Material Re uirements Materials for the new spent fuel pool cooling system components will be as given in Table II.Component materials in contact with SFP water shall be austenitic stainless steel or an equivalent corrosion-resistant.
material.Component materials in contact with service water shall be carbon steel.12.0 Mechanical Re uirements The new spent fuel pool cooling system components shall be designed to minimize any hydraulically induced vibrations.
13.0 Structural Re uirements 13.1 Supports for the new, spent fuel pool pump, heat exchanger, and piping system shall be designed to ASME Section III, Subsection NF, for load combinations shown in Table IV.13.2 Supports'for the new electrical components and conduits shall be designed to conventional engineering design standards for loads due to weight and seismic events.13.3 Attachments or modifications to existing structures shall be reviewed to assure that they do not degrade the ability of the structures to perform their intended functions.
13.4 14.0 14.1 Any modifications to existing structural steel or concrete shall comply with applicable requirements of tne appropriate AISC or ACI code.H draulic Re uirements The new spent fuel pool pump and piping shall be de-signed to assure that adequate NPSH and cooling water flow are available for the removal of the design heat loads.14.2 14.3 For the"Safety" basis heat load, and the"normal" basis heat load, the NPSHA shall be determined at a pool temperature of 150'F and 120'F, respectively.
The NPSHA shall be based on the pool water level at the new level switch trip point for both heat loads.The service water piping to the new spent, fuel heat ex-changer shall be designed to provide adequate flow for the removal of the design heat loads.Design Criteria E3fR 1594 11 Pnge Revision 10/10/79 15.0 Water Chemistr Re uirements The water chemistry specifications for the spent fuel pool are given in Table V.16.0 16.1 Power supply for SFP P-2 shall be 480 V,'9, 60 Hz, from safety (essential) bus 16.To ensure that.bus 16 loading is minimized during an event that requires safety injection, SFP P-2 shall be shed on safety injection signal, and it shall be manually reloaded.16.2 16.3 A single line diagram for SFP P-2 isshown in Figure 4.Insulation for SFP P-2 motor cables shall be qualified in accordance with IEEE-383.16;4 The Class IE motor.for SFP P-2 shall be of totally enclosed construction.
17.0 0 erational Re uirements The SFP P-2 and SFP HX-2 shall be designed for continu-ous and intermittent operations.
18.0 Instrumentation and Control 18.1 The SFP P-2 shall be controlled by a local indicating switch.An interlock with the new level switch in the spent fuel pool will prevent the pump from operating when the pool water level is low.18.2 18.3 18.3.1 The control stations for SFP P-2 and SFP P-1 shall be mechanically interlocked to prevent running both pumps similtaneously.
Instrumentation The types and locations of instrumentation for the spent fuel pool cooling system will be as shown in Table VI.18.3.2 In-line instrumentation shall be seismic category I.The seismic category I boundary for indicating instru-mentation shall be the root valve.19.0 Access and Administrative Controls Not applicable.
Design Criteria EWR 1594 Page 12 Revision Date 5/23/7 9
'~gp~20.0 Redundanc , Diversit and Se aration Re uirements Spent Fuel Pool Cooling Water System 20.2 Redundant cooling capability shall be provided as shown in Figure 1.The existing and skid mounted systems when operated in parallel provide backup cooling capa-bility for the new cooling system.Spent Fuel Pool Service Water System As shown in Figure 2, the service water to SFP HX-2 shall be from service water loop B.The supply to SFP HX-1 and SFP HX-3 is from service water loop A.20.3 20.3.1 Electrical Separation Electrical separation between SFP P-2 and SFP P-1 motors and controls shall be maintained in accordance with IEEE-384 whenever existing plant design permits.20.3.2 20.3.3 Where separation between groups cannot meet IEEE-384 criteria, separation shall be maintained as described in 20.3.3 (Ref.: Ginna FSAR, Section 8.2.2, Page 8.2-6B,"Separation of Redundant Circuits".).
The minimum physical dimensions between redundant power, control and instrument cable trays shall be 5 inches vertical separation and 2 inches horizontal separation.
The minimum physical separation between redundant cables for power, control, and instrument systems shall be a galvanized sheet metal barrier in cable trays.21.0 21.1 21.1.1 21.1.2 Failure Effects Re uirements Pipe Break The design of the cooling system shall assure that the possibility of adverse effects resulting from steam environment, fluid jet impingement, and pipe whip caused by breaks in high and moderate energy piping in the Auxiliary Building does not prevent operation of the new cooling system.Appropriate modifications including shields, barriers, restraints, etc.shall be installed if postulated pipe breaks are found to be detrimental to system performance.
Design Criteria EWR 1594 Page 13 Revision Date 5/23/79 21.2 Tornado To minimize the damage due to potential tornado and ex-ternal missiles, only-the new spent fuel pool heat ex-changer and a limited amount of piping, valves, and instrumentation shall be located above the operating floor of the auxiliary building.21.3 Earthquake The new spent fuel pool cooling system shall be designed to remain operational after the SSE.21.4 Hurricane The effects of hurricane were not considered in the original plant design.21.5 21.5.1 llissiles-Internally Generated The new cooling system is a low energy system.No missles are postulated due to failure of pressurized components.
21.5.2 The new and existing SFP pumps and motors will be evaluated to determine the potential of failure resulting in unacceptable damage to each other or to other safety related components.
If necessary, barriers or other modifications shall be installed to prevent unacceptable damage.21.5.3 Potential missiles resulting from high and moderate energy piping components and valve failures and failures of rotating equipment shall be evaluated to determine the potential of unacceptable damage to the cooling system.Only components and equipment in the area of the new system shall be evaluated.
Barriers or other modifications shall be made, if practical, to protect the system from missiles.21.6 Floods ,Protection from flooding is provided by the design of the auxiliary building as described in Ginna FSAR, section 2.6.4"Floods and Low Hater", and Appendix 2C,"Probable blaximum Flood and Low Hater Conditions"".
Design Criteria EHR 1594 Page 14 Revision Date 5/23/79 21.7 21.7.1 Loss of Spent Fuel Pool Water To protect against the possibility of complete loss of water in the spent fuel'ool, the upper suction line penetrates the spent fuel pool near the top of the pool.The lower suction line penetrates the spent fuel pool approximately 5'-8" above the top of fuel to preclude the possibility of draining the pool and to assure a minimum water level of 5'-8" above the top of the fuel.21.7.2 The spent fuel pool cooling water return line, which terminates at the bottom of the spent fuel pool;con-tains a vent hole near the normal spent fuel pool water level, so that the pool water cannot be siphoned.21.7.3 Manual valves shall be provided,to isolate non-seismic category I piping systems connected to the spent fuel pool cooling system in the event non-seismic category I piping-systems fail.21.8 The load center, local control panel, conduit supports and new pump motor shall be designed such that failure of these components does not degrade the capability of the existing spent fuel pool cooling system.22.0 22.1 Test.Re uirements The new system shall be hydrostatical ly tested to the extent practical in accordance with ASME Section III.An initial service leak test will be made for those areas of the system and connecting piping where a hydro test is impractical.
22.2 The new system shall be functionally tested to verify that proper operation of the, cooling system is obtained.Test connections and instrumentation necessary to determine pressures, temperatures, and flows shall be prov).ded.
22.3 The SFP P-2 pump shall be tested by the manufacturer to determine actual head, horsepower, and efficiency curves with varying flow.22.4 The Motor Control Center and the local Class IE controls shall be qualified to the requirements of IEEE-323.The new SFP P-2 motor shall be qualified to the require-ments of IEEE 323 or IEEE-334.Revision/22.5 Functional testing of the new local control station, new-spent fuel pool level switch and new motor control center shall be in accordance with IEEE-336 require-ments.Design Criteria DTR 1594 Page 15 pal~10/10/7-9 42-90
~~23.0 Accessibility, Maintenance, Repair and Inservice Ins ection Re uirements 23.1 The new pump, motor, load center, heat exchanger, and valves shall be accessible for maintenance including heat exchanger tube bundle removal.23.2 23.3 Access to existing plant equipment for routine main-tenance and inspection shall not be adversely affected.The new cooling system and service water piping modifica-tions shall be designed to permit the performance of all tests and inspections required by ASME Section XI for Class 3 components.
24.0 24.1 25.0 Personnel Re uirements Not applicable.
Trans ortabilit Re uirements 26.0 26.1 None.Fire Protection Re uirements The design of the new spent fuel pool cooling system shall, as necessary, be compatible with the present fire protection requirements as outlined in GAI Report 1936.26.2 Cable used in this modification shall meet the flame spread requirements of IEEE-383-1974.
27.0 27.1 27.2 Handlin Re uirements The new system components and material to be used in seismic category I systems and structures shall be shipped, handled, and stored in accordance with the appropriate requirements of ANSI N45.2.2-1972.
Level B requirements of ANSI N45.2.2 shall apply for all new electrical components with the exception of the cables which shall meet Level D requirements.
27.3 Level B, C, and D requirements shall apply for other materials and equipment as indicated in ANSI N45.2.2.28.0 Public Safet Re uirements None.Design Criteria ELjR 1594 16 Page Revision Date 42.90
~t~~29.0 A licabilit 30.0 None.Personnel Sachet Re uirements 31.0 None.Uni ue Re uirements None.Design Criteria ERR 1594 Page 17 Revision Date 0 5/23/79 42 90
~~~~TABLE 1 SPENT FUEL KOL COOLING SYSTEM DESIGN PARAMETERS 1.0 SFP storage capacity, assemblies 2.0 SFP water volume, ft 3 (water level 1'-4" fran top of pool)3.0 Design Heat Load Conditions
3.1 Initial
decay heat, Btu/hr.3.2 Maximum pool temperature,'F 3.3 SFP heat up rate,'F/hr.(assumes no cooling)4.0 Service Water Requirements 4.1 SW temperature,'F 4.2 Max.SW temp.increase,'F 4.3 Si flow, gpn (approx.)Safet 16 x 10 150 7.7 80 20 1600 595 34,100 No 1 7.6 x 10 120 3.7 80 15 1000 Design Criteria EWR 1594 Page Revision Date 5/23/79 42.90 TABLE II SPENT FUEL POOL COOLING SYSTEM COMPONENTS DESIGN PAKQKTERS SFP P-2 (New)Quantity Design pressure, psig Design temperature,'F Design flow, gpm (approx.)NPSH available, Ft.(approx.)Design head, Ft.(approx.)Material Design Code Seismic Category SFP HX-2 (New)Quantity Design heat transfer, BTU/hr Design pressure, psig Design temperature,'F Design flew, gpn (Approx.)Inlet temperature,'F Outlet temperature,'F Fluid circulated Material Design Codes Seismic Category Design Criteria EHR 1594 Pnge 150 200 1,200 25 150 Austenitic Stainless Steel ASME Section III, Class 3 16 x 10 6 Shell 150 200 150 200 1600 1200 80 150 100 Max.Service Hater SFP Hater Revision 1 Dn/e 10/10/7 9 42.90 Carbon Steel Austenitic Stainless Steel ASME Section III, Class 2 and TEMA"E S nt Fuel Pool Hater Pi in/Valves (New)Design pressure, psig Design Temperature,'F Material Design Code Seismic Category 150 200 Austenitic Stainless Steel ASt4E Section III, Class 3 Service Water Pi in/Valves (New)Design pressure, psig Design temperature,'F Material Design Code Seismic Category 150 200 Carbon Steel ASME Section III, Class 3 Design Criteria EWR 1594 page II 2 Revision Date 5/23/79
~~TABLE III QUALITY GROUP, SEISMIC CATEGORY AND CODE CLASS SPENT FUEL HKL COOLING SYSTEM COMKJNENTS CQ1FONENT PUMP SFP P-2 HEAT EXCHANGER SFP HX-2 QUALITY GROUP SEISMIC CATEGORY ABIE CODE CLASS Section III, Class 3 Section XII, Class 3 bGTOR FOR SFP P-2, LOAD CENTER, CONTROL STATION, LEVEL SNITCH LOCAL HAND STATION PIPXNG, NBV AND MODIFIED.PIPING, NEW AND MODIFIED VALVES, NEN N/A Class XE N/A Section III, Class 3 Section III, Class 3 NH4 INSTRUMENTATION In-line Instrumentation C Section IXX, Class 3 Indicating Instrtmtenta-tion D Non-seismic Manufacturer.'
Standards Design Criteria EWR 1594 V Page XIX-l Revision Date 5/23/79 42.90 a Ul 00 Vl O Q t5 Component Heat Exchanger Design PD+DW+ML TABLE IV LOAD COMBINATIONS Service Limits-Level A PD+DW+ML+TL Level B PD+DW+ML+HL+OBE Level C PD+DW+ML+HL+SSE Pump (Active)Valves (Active)PD+DW+ML PD+DW+ML PD+DW+ML+HL+OBE!PD+DW+ML+HL+OBE PD+DW+ML+HL+SSE PD+DW+ML+HL+SSE N.A.N.A.Valves (Non-Active)
Piping PD+DW+ML PD+DW+ML PD+DW+ML+TL PD+DW+ML+TL PD+DW+ML+HL+OBE PD+DW+ML+HL+OBE PD+DW+ML+HL+SSE PD+DW+ML+HL+SSE H I A V)O DW ML HL TL OBE SSE PD Dead Weight Mechanical Loads Hydraulic Loads Thermal Loads Operating Basis Earthquake Safe Shutdown Earthquake Design Pressure Note: There ar no Level D service limits.
~~~~ir TABLE V SPENT FUEL POOL WATER CHEMISTRY SPECIFICATIONS Characteristics Normal Concentration Transient Limits (PPM)(PPM)Oxygen Chloride Fluoride Boron Acid Saturated 0.15 0.15 2500 boron Saturated 1.50 1.50 2500 boron Design Criteria EWR 1594 Page V-1 Revision 0 5/23/79 TABLE VI INSTRUMENTATION
-TYPE&LOCATION TYPE LOCATION FLOW PRESSURE TIZPERATURE POOL WATER LEVEL RADIOACTIVITY Pl&P, SFP P-1 Suction Discharge PUMP, SFP P-2 Suction Discharge PUMP, SFP P-3 Suction Discharge HEAT EXCHANGER, SFP HX-1 Inlet, SFP Water Outlet, SFP Water Inlet, Service Water Outlet, Service Water HEAT EXCHANGER, SFP HX-2 Inlet, SFP Water Outlet, SFP Water Inlet, Service Water Outlet, Service Water HEAT EXCHANGER, SFP HX-3 Inlet, SFP Water Outlet, SFP Water Inlet, Service Water Outlet, Service Water SPENT FUEL POOL WATER LEVEL L;A+L L L L L L L L L L L L L L L L L L L L L L L L L L,A A***I A, MCB**A, MCB**a m rt m V)0 L: Local Indication MCB: Main control board indication A: Alarm in control room*Tow flow annunciation
- Connected to the plant computer***New level switch in the pool interlocked with SFP P-2 NOTES-'"~hit NklR C 1 1 iECC'T T RC<<vkhl<<PUMP I I I I I I I I I I I I I I'I I I I J SE<MOXA 8~-~NCTE.I B Pl Pl~CP Cr-(SKIO MOUNTED)SEE I MOTE 5 0-,-)I I SEE uOTa Ji l~~SEE rl 5 MOTK I PI I NKW EXIST.C" SPP P I (EXIST)NEW T----~FIG.t~MX.S (9clO rr!rQ)PJ SPEND FUEL FIC<<.Z FI 6.X FI6.t F!G.X I.WHEN HOSK 15 DISCONNKCTKO VALVE IEEthhINS AND BLIND FLANGK 15 ADDKD.t.ALL NEW PIPING AND KOUIPMENT AEK SEISIAIC CATKGOIEY I TXECPT AS NOTKD.3.ALI.NEW PIPING AND KOUIPIAKNT 1XE ASIAE SECTIOH IQ s CLASS 3 EKCKPT AS NOTED..4.FOIE AUXILILIEY COOLANT SYSTEIA P 4 T DILGPhth KKFKK, TO F G t 8 DKAWING NO.'33013+3C.5.TIEIP ON SAFKTY INJECTION (BUS IC)6.TRIP OM BUS H UNDER YO'LTAGK COINC)DKNT WITH SAFET'f IMJ ECTION.T KEY XCCKIEI~CAROL SWATIOCIS AR KEXED ALIKE TO CrREVES"I SrrCCJLTAlltOCJS QPS~TION OF 8OTSI P CIHPS, d LKvEL SWCTCII'IIECPS PMP SSP P.E OM\C!rf SPENT CCJEL PC%LEVEL.p SKK HCTE I 4 FTHM>C~sw-ux-r EXIST EW'I%XI ST.%W 2IID LEVEL REVIEW COMPLETED FORM A IV I!IG!I DATE I I'p Sf~~r EK!ST NKW EXIST.OTE HAKE WATER PRCPh CCDT PIMPS TO~LING WATER STCSUGE TANK PI~FP BYPASS T~~REFIJELING TIATKTE ST<RAGE Thymi(NOTE r}FUJSH LPIc~LEGErI~W FIPIHO 4 EQVIPIBE"ii RXIr}T.PIPING$KXIUIPPAENT L----S}OSK$COCIPLQ4Cj
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ELEC TIEICRL SC4jrJAL IhtcsIAMIcll INTE!ELocK,!REACTOR HAKE UP NDTE 4~~GINNL STATION pcr cc Nor<<K loc<<cCrl~Crs~CCCC r CIC Cc<<r R'U'Q(A>ccr Lcw cwcc<<'rA<<cQ 0Ar<<0<<r<<9 vACVE Toe<~i vAcfr.4'lrrr>tA'L Ar spwT cJcL I boa Acerb r oTEstsa.aawsao cEflma.'NONE'aL g.PA'ILL'I<l FIGURE, I SPEN I FUEL POOl.COOLING SYSTEIA 5 F P WLTEIL P t I DILGR,LJA REV DCSCTCIPFION
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TO SW WESTCF COI4,A'NIIEIIT MOTE+UXII IS AUX.EQUIP.STAII'5~Ilg AIICÃW ga ILVP SIICTIOH OTE 4 (CLOSED)SEE MOIK C I I Ho STAIID IIX AUT FTI PII HP SJ C'T I 0'H OTE+I (CMSKO)SEK NOTE 4 I I P Qg-+.IDI(Nhw)'CLmng+SEa NOTE 1 CCW OTE 5 I (CLOSKD)E SKE MOTE C I I<<CW IOTE 5 CCW OTK 5 0~I I.WHEN HOSK 15 015CONNECTKD VALVE.F KMhlNS ANO bLIND FLANCK IS ADDED t.ALL NEW PIPIMG AMD EQUIPMENT hkE SKISMIC CATEGOKY T K'XCEPT h'5 NOTED.3.ALL NEW PIPING AND EQUIPMENT AIEE ASME SECTION j)E ICLASS 3 EXCEPT AS NOTED.4.FOE STATION SERVICE COOLING WATKX.PC T DIAGXhÃI IEKFKX.TO ILG 8 K DIhWING NO.35013-5E'I.S.FOR AUXILIAIEY COOLhNT SYSTKM PCI D)AGX.ANI kEFEF.TO X,G t K DRAWING NO.33OI3 435 AND 5501'5-+3C.4.IAOTOIC OPERATED l5OLhTION VALVES CLOSE AUTOMhTICAI.LY IN'THE EVKNT OF COINCIDENT SAFEGUAILOS ACTUAT)OII 51CNAL AND I.OSS OF OFFSITE POWKE 3 NEW AIR OP%RATIO ISCIIATIOal VALVE.ClDSE.S AQTCII4ATICALLY hl TH%, EVENT QF SAIECPhROS AC'b)ATIC31 SICTNhL HX-IA SW IO s, AUX.EQUIP.QP SW EAST<ÃCCaITAINIIIEMT NOTE 4 LOOP A (CLOSED)SEE NOTE (I CCW OTE 5~$(NOTE I)-~s.i+Kit)NTL)PI FIG.I SW TROIl AUX.KQUIP.I MOTE+I~NEW PFL~4 EQUI~-EXISTING PIPING f EQUIPMENT----ELECTRICAL SVqgL SFP H)bl S'-------V.OSLO CXPUVC FIG.I 6 2NO LEVEL AEVIEVl COMPLETEO FOA(14 FIG.I AEY ENGA OAIE a p'RE I'a FIG.I II ETUIE.N TO LhKE NOTE+NETUKN TO CIEEEIL MOTE 4~~CINNA STATION Ran cSIIa Ola~tuaaC Cc~.'A OI..J l t~'~a~~glaII RLI~01%.5 a Iaaf Ik I I~I~NONE II.PAT CL~I II 457 FIGURE SPENT FUEL POOL COOLENG SYSTEM SKFYICE WhTEF PCT DIAGR.hM g7 g Q O IZ I D W O aI cATA'LTTlc los IIR.3<TKC.
EWR.ISSUE 33015 7lEB
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~%5K'~RE~E%Qe CfKNKiD&~~RW-'<~~E~SSg~~~S'gHS@g r~Q+L PC.<i e.Existing Bus f/16 (480V, 38, 60Hz.)Bkr.17A (Exist.)I I I I New H.C.C.(480V, 38, 60Hz.)600A 100 New Spent Fuel hP Pool Pump (SFP P-2)FIGURE 4 SPENT FUEL POOL COOLING SYSTEM)ONE LINE DIAGRA.f