ML24128A105

Updated Safety Analysis Report (Usar), Revision 38, Section 9, Plant Radioactive Waste Control Systems

ML24128A105
Person / Time
Site:	Prairie Island
Issue date:	04/30/2024
From:	Northern States Power Company, Minnesota, Xcel Energy
To:	Office of Nuclear Reactor Regulation
Shared Package
ML24128A092	List: L-PI-24-010, Revisions 255 Through 264 for Technical Specification Bases ML24128A088 ML24128A098 ML24128A099 ML24128A100 ML24128A101 ML24128A102 ML24128A103 ML24128A104 ML24128A105 ML24128A106 ML24128A107 ML24128A108 ML24128A109 ML24128A110 ML24128A111 ML24128A112 ML24128A113 ML24128A114 ML24128A115 ML24128A116 ML24128A117 ML24128A118 ML24128A119 ML24128A120
References
L-PI-24-010
Download: ML24128A105 (1)

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{{#Wiki_filter:PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 37 Page i SECTION 9 PLANT RADIOACTIVE WASTE CONTROL SYSTEMS TABLE OF CONTENTS Page 9.1

SUMMARY

DESCRIPTION....................................................................9.1-1 9.1.1 General Systems Description...................................................9.1-1 9.1.2 Component Design Considerations..........................................9.1-3 9.2 LIQUID RADWASTE SYSTEM...............................................................9.2-1 9.2.1 Design Basis............................................................................9.2-1 9.2.2 Description...............................................................................9.2-2 9.2.3 Performance Analysis..............................................................9.2-9 9.3 GASEOUS RADWASTE SYSTEM.........................................................9.3-1 9.3.1 Design Basis............................................................................9.3-1 9.3.2 Description...............................................................................9.3-2 9.3.3 Performance Analysis..............................................................9.3-5 9.4 SOLID RADWASTE SYSTEM................................................................9.4-1 9.4.1 Design Basis............................................................................9.4-1 9.4.2 Description...............................................................................9.4-1 9.4.3 Performance Analysis..............................................................9.4-1

9.5 REFERENCES

........................................................................................9.5-1

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 37 Page ii TABLE OF CONTENTS [Continued] LIST OF TABLES TABLE 9.1-1 WASTE DISPOSAL SYSTEM PERFORMANCE DATA TABLE 9.1-2 WASTE DISPOSAL COMPONENTS CODE REQUIREMENTS TABLE 9.1-3 COMPONENT

SUMMARY

DATA TABLE 9.2-1 PERFORMANCE DATA AND SERVICE REQUIREMENTS TABLE 9.2-2 PERFORMANCE DATA AND SERVICE REQUIREMENTS TABLE 9.2-3 LIQUID SOURCE TERMS FROM THE PRAIRIE ISLAND PLANT (PER UNIT) TABLE 9.2-4 PRAIRIE ISLAND LIQUID RADWASTE SYSTEM TABLE 9.3-1 GASEOUS SOURCE TERMS FROM THE PRAIRIE ISLAND PLANT (PER UNIT) TABLE 9.3-2 PRAIRIE ISLAND - HIGH LEVEL LOOP PROCESS CONDITIONS AND MAXIMUM ISOTOPIC CONCENTRATIONS TABLE 9.3-3 PRAIRIE ISLAND - LOW LEVEL LOOP PROCESS CONDITIONS AND MAXIMUM ISOTOPIC CONCENTRATIONS

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 37 Page iii TABLE OF CONTENTS [Continued] LIST OF DRAWINGS FIGURE 9.1-1 FLOW DIAGRAM - WASTE DISPOSAL SYSTEM FIGURE 9.1-2 FLOW DIAGRAM - AUXILIARY & REACTOR BUILDING FLOOR & EQUIPMENT DRAIN SYSTEMS FIGURE 9.1-3 FLOW DIAGRAM - STEAM GENERATOR BLOWDOWN SYSTEM FIGURE 9.1-4 FLOW DIAGRAM - STEAM GENERATOR BLOWDOWN SYSTEM FIGURE 9.1-5 FLOW DIAGRAM - STEAM GENERATOR BLOWDOWN SYSTEM FIGURE 9.1-6 FLOW DIAGRAM - WASTE DISPOSAL SYSTEM FIGURE 9.1-7 FLOW DIAGRAM - WASTE DISPOSAL SYSTEM FIGURE 9.1-8 FLOW DIAGRAM - WASTE DISPOSAL SYSTEM FIGURE 9.1-9 FLOW DIAGRAM - MISCELLANEOUS GAS SYSTEM FIGURE 9.1-10 FLOW DIAGRAM - RADWASTE BUILDING LIQUID WASTE DISPOSAL AND WASTE SOLIDIFICATION SYSTEMS

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PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 23 Page 9.1-1 SECTION 9 PLANT RADIOACTIVE WASTE CONTROL SYSTEMS 9.1

SUMMARY

DESCRIPTION 9.1.1 General Systems Description Radioactive fluids entering the Waste Disposal System are collected in intermediate holding tanks for determination of subsequent treatment. They may be sampled and analyzed to determine the quantity of radioactivity, with an isotopic analysis if necessary. The liquid wastes are then processed as required for reuse or released under controlled conditions and in accordance with applicable limits of 10CFR20 and the design objectives of Appendix I to 10CFR50. The bulk of the radioactive liquid drained from the Reactor Coolant System is processed by the Chemical and Volume Control System recycle train and retained inside the plant. This minimizes liquid input to the Waste Disposal System which processes relatively small quantities of generally low activity level wastes. The processed water from the waste disposal system, from which the majority of the radioactive material has been removed may be reused in plant or released through a monitored line to the canal downstream of the cooling towers. Waste gases are processed by one of two interconnected equipment trains. The low level loop, provides sufficient storage capacity for cover gases from the nitrogen blanketing system to minimize the need to vent gases which accumulate as a result of load follow operations. Discharges of fission gases from the system are limited to maintenance vents, unavoidable equipment leaks, and infrequent gas decay tank releases to dispose of gases accumulated by inflows from shutdown operations and miscellaneous vents. Controls are provided to regulate the rate of release from these tanks through the monitored plant vent. The high level loop was designed to accumulate, concentrate and contain fission gases at high activity concentrations from continuous purging of the volume control tanks gas space. It would provide continuous removal of fission gases from the letdown coolant to maintain the coolant fission gas concentrations at a low residual level. This loop can perform these functions and/or be used for reserve holdup capacity of low level loop gas. The spent resins from demineralizers, filter cartridges and concentrates from the evaporators are packaged and stored onsite until shipment offsite for processing and disposal. 01-082 01-081 01-081 01-082

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 23 Page 9.1-2 The Waste Disposal System Process Flow Diagrams are shown in Figures 9.1-1 through 9.1-10 and Performance Data are given in Table 9.1-1. With the exception of the SGB system, containment building sumps and pumps, reactor coolant drain tanks and drain tank pumps, and associated piping and valves, the Waste Disposal System is common to Units 1 and 2. The Waste Disposal System collects and processes all potentially radioactive reactor plant wastes for removal from the plant site well within limitations established by regulations. Fluid wastes are collected, sampled and analyzed to determine the quantity of radioactivity, with an isotopic analysis if necessary. Depending on the results of the analysis, these wastes are processed as required and reused in the plant or released to the environment. If the wastes are to be released from the plant site, they are released under controlled conditions. Radiation monitors are provided to maintain surveillance over the release operation, and a permanent record of activity released is provided by radiochemical analysis of the known quantities of waste and substantiated by plant recording instruments. The system is capable of processing all wastes generated during continuous operation of the primary system, assuming that fission products escape to the reactor coolant by diffusion through defects in the cladding of no more than one percent of the fuel rods. At least two valves must be manually opened to permit discharge of liquid or gaseous waste from the Waste Disposal System. One of these valves is normally locked closed. An additional control valve will trip closed on a high effluent radioactivity level signal to prevent discharge to the environment. As secondary functions, system components supply hydrogen and nitrogen to primary system components as required during normal operation, and provide facilities to transfer fluids from the containment to other systems outside the containment. The system is controlled from local control panels in the auxiliary building and the radwaste building. Malfunctions of the system are locally alarmed in the auxiliary and radwaste buildings, as well as being annunciated in the control room. All system equipment is located in the radwaste building, the auxiliary building, or the reactor containment buildings. The design basis for the radwaste building is described in Section 12.2.1.4.3.2, Structural Design Basis for Class I* Structures. 01-082 01-082 01-082 01-082

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 23 Page 9.1-3 The radwaste building is supplied with outside air which can be preheated by heating coils in the air-handling unit. Exhaust flow is directed through charcoal adsorber beds and a HEPA filter prior to release to the surroundings. The cement dust filter fan exhaust is not directed through the adsorber bed or the HEPA filter. All releases are monitored by the Radwaste Building Radiation Monitor Channel R-35 as described in Table 7.5-1. In addition, unit heaters are provided throughout the radwaste building for heating in the winter. Adjacent to the Radwaste Building is the resin disposal building which receives, dewaters and handles spent resins from the condensate polishing system (See Section 11.8.) 9.1.2 Component Design Considerations Codes applying to components of the Waste Disposal System are shown in Table 9.1-2. Component summary data are shown in Table 9.1-3. The wetted surfaces of all pumps are stainless steel or other materials of equivalent corrosion resistance. Piping carrying liquid wastes is stainless steel or fiberglass while gas piping is carbon or stainless steel. Steel piping connections are welded except where flanged connections are necessary to facilitate equipment maintenance. Valves exposed to gases are carbon or stainless steel. Those exposed to liquids are stainless steel. Globe valves are installed with flow over the seats when such an arrangement reduces the possibility of leakage. Isolation valves are provided to isolate equipment for maintenance, to direct the flow of waste through the system, and to isolate storage tanks for radioactive decay. Relief valves are provided for tanks containing radioactive wastes if the tanks might be overpressurized by improper operation or component malfunction. Tanks containing wastes which are normally free of gaseous activity are vented locally. Outleakage from the system is minimized by using diaphragm valves, bellows seals, self contained pressure regulators and soft-seated packless valves throughout the radioactive portions of the system. 01-082 01-081 01-081 01-081

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 23 Page 9.1-4 THIS PAGE IS LEFT INTENTIONALLY BLANK

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 36 Page 9.2-1 9.2 LIQUID RADWASTE SYSTEM 9.2.1 Design Basis Criterion: The facility design shall include those means necessary to maintain control over the plant radioactive effluents, whether gaseous, liquid, or solid. Appropriate holdup capability shall be provided for retention of gaseous, liquid, or solid effluents, particularly where unfavorable environmental conditions can be expected to require operational limitations upon the release of radioactive effluents to the environment. In all cases, the design for radioactivity control must be justified (a) on the basis of 10CFR20 requirements, for both normal operations and for any transient situation that might reasonably be anticipated to occur and (b) on the basis of 10CFR100 dosage level guidelines for potential reactor accidents of exceedingly low probability of occurrence. (GDC70) Liquid, gaseous, and solid waste disposal facilities are designed so that discharge of effluents and off-site shipments are a small percentage of the applicable governmental regulations. The liquid radwaste systems design objective is to have the capability of processing the discharge of radioactive material under normal operating conditions so as to approach essentially zero (i.e., actual river background) and to ensure that activity released under design basis conditions will be a small fraction of the applicable limits in 10CFR20. 9.2.1.1 Liquid Radwaste The liquid radwaste system is designed to collect, process and dispose of all radioactive liquid wastes generated in the operation of the plant. The system is designed to accommodate the radioactive input resulting from the design basis maximum fuel leakage condition. The radioactive waste system has been shown to meet the requirements of Appendix I to 10CFR50. The radwaste systems reduce the activity released to acceptable levels. 9.2.1.2 Monitoring Radioactive Releases Criterion: Means shall be provided for monitoring the containment atmosphere and the facility effluent discharge paths for radioactivity released from normal operations, from anticipated transients, and from accident conditions. An environmental program shall be maintained to confirm that radioactivity releases to the environs of the plant have not been excessive. (GDC 17).

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 36 Page 9.2-2 The containment atmosphere, the shield building vent, the auxiliary building vent, the control room ventilation system, the spent fuel pool exhaust, the RHR cubicle ventilation exhaust, the condenser air ejector exhaust, the circulating water discharge, the containment fan coolers cooling water discharge, blowdown from the steam generators, the component cooling water, and the Waste Disposal System liquid effluent are monitored for radioactivity concentration during normal operations, anticipated transients, and accident conditions. High radiation in any of these is indicated and alarmed in the control room. All gaseous effluent from possible sources of accidental radioactive release external to the reactor containment (e.g., the spent fuel pool and waste handling equipment) will be exhausted from an auxiliary building vent, which is monitored. Leaks from piping carrying radioactive liquids are contained within the reactor containment buildings, radwaste building, or auxiliary building. Any contaminated liquid effluent released to the condenser circulating water is monitored. For any leakage from the reactor containment under accident conditions, the plant radiation monitoring system supplemented by portable survey equipment provides adequate monitoring of radioactivity release. 9.2.2 Description The waste disposal system collects, processes, stores and disposes of radioactive liquid waste originating in the plant. The subsystems comprising the Liquid Radioactive Waste Disposal System are: Reactor Coolant Drain (RCD), Auxiliary and Reactor Building Drain (ARD), Steam Generator Blowdown Treatment (SGBT), Non-Aerated Drain, and Aerated Drains Treatment (ADT). The system has the capability of storing 60,000 gallons. The major sources of liquid waste are: Reactor Coolant System drains and leaks Chemical and Volume Control System drains and leaks Non-aerated equipment drains and leaks Aerated equipment drains and leaks Chemical laboratory drains Decontamination area drains Radiochemical laboratory drains Sampling System Steam Generator Blowdown Auxiliary Coolant System drains To facilitate storage, processing and disposal, the system is designed to segregate various waste streams at their point of collection into the following categories: Non-aerated waste Aerated waste Chemical drains Steam Generator Blowdown

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 36 Page 9.2-3 Resin waste Non-aerated waste is primarily from Reactor Coolant System drainage which is collected from the following sources and transferred directly to the Chemical and Volume Control System (CVCS) holdup tanks, or the waste holdup tank (depending on fluid composition) for processing:

a.

Reactor coolant loops

b.

Pressurizer relief tank

c.

Reactor coolant pump secondary seals

d.

Excess letdown (during startup)

e.

Accumulators

f.

Reactor vessel flange leakoffs Fluid directed to the reactor coolant drain tanks is pumped to the CVCS holdup tanks, the waste holdup tank, or the refueling water storage tanks by the reactor coolant drain tank pumps. There is one reactor coolant drain tank with two reactor coolant drain tank pumps located inside of each reactor containment building. The remaining non-aerated liquid waste originates in the Chemical and Volume Control System charging and letdown paths and the gas decay tank drains. These liquid waste streams are collected and handled in an anaerobic manner to minimize the hydrogen explosion hazard and prevent the escape of gaseous radioactivity. This is accomplished by collecting non-aerated waste in a closed piping system that drains to a non-aerated sump tank. The non-aerated sump tank is isolated from the atmosphere by a flexible diaphram type seal. Normally non-aerated waste is transferred to the CVCS holdup tanks for processing. (see Section 10.2.3) If the water is not suitable or it is not desirable to send the non-aerated waste to the CVCS holdup tanks, the water can be pumped to the waste holdup tank. Aerated waste originates primarily from the floor drains, aerated equipment drains and leaks, the laundry equipment drains, and the decontamination area drains. Where possible, aerated waste is collected by gravity drainage to the aerated sump tank. In other cases, aerated waste is drained to local sumps from where it is pumped to the aerated sump tank. From the aerated sump tank, aerated waste can be pumped to the two aerated monitor tanks, the ADT collection tanks or the waste holdup tank. Normally the discharge from the aerated sump tank pump is aligned to the waste holdup tank due to its capacity and shielded location. When enough water has been collected in the waste holdup tank for processing purposes, the waste holdup tank is gravity drained to the aerated sump tank, which is pumped to the ADT collection tanks.

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 36 Page 9.2-4 Waste water in the ADT Collection tanks is normally processed through the ADT Cartridge Filters. The filtrate is collected in the ADT Condensate Receiver Tanks, and then processed through the ADT Ion Exchangers and collected in the ADT Monitor Tanks. The ADT Monitor Tanks are analyzed, and based on the analysis, may be released or reprocessed. Waste from the hot sampling station and hot chemical laboratory is collected in the chemical drain tank. Periodically this waste is neutralized, if needed, then pumped to the aerated sump tank. Waste water from the resin disposal building sump is pumped to the miscellaneous drains collection tank or the waste holdup tank. Waste water from the truck loading enclosure sump is pumped to the aerated sump tank. Control of radioactivity of the laundry and hot shower wastes is gained by using disposable clothing in areas of known high contamination. The laundry and hot shower waste liquid is directed to the aerated sump tank through the floor drain system. The laundry and hot shower liquid waste is then processed through the ADT system. Steam Generator Blowdown is discharged to a flash tank shared by both steam generators of a unit. The blowdown line from each steam generator is equipped with two motor-operated containment isolation valves, one inside and one outside of containment. As shown in Tables 5.2-1 Part A (U1) and Part B (U2) only the outside valve is credited for Containment Isolation. The other redundant barrier is the Steam Generator (see Appendix G). Flow into the flash tank from each steam generator is controlled by a single control valve. Flow rate from each steam generator is manually controlled from the control room. The steam generator blowdown motor operated isolation valves are designed to close upon receipt of a containment isolation signal. The SGB flow control valves are designed to trip closed if one of the following conditions occur:

1.

Either Auxiliary Feedwater Pump for the associated unit starts.

2.

High activity is detected in the associated steam generator blowdown radiation monitor (R19).

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 36 Page 9.2-5 Normally steam generator blowdown from the flash tank is directed to the SGB Holdup Tanks from which it is pumped through a filter and ion exchanger to the respective condenser. This is called reclaim. Occasionally, to control steam generator chemistry, blowdown is released to the circulating water canal via a radiation monitor. Such is the case during unit startup. In the event that radioactivity exceeds the setpoint of the SGB Radiation Monitor, the discharge valve to the river automatically closes thus securing the release. The steam from the blowdown flash tank is normally routed to the extraction steam inlet to Feedwater Heater No. 3. Steam can also be routed to the main condenser or to the atmosphere. The noncondensible gases removed from the condenser (by an air ejector) pass through a radiation monitor at all times, however the radiation monitor for the air ejector discharge is not considered an effluent monitor. The air ejector discharge monitor alarm set point is based on monitoring primary to secondary leakage and not based on monitoring effluent release. The air ejector discharge is directed to Auxiliary Building Ventilation. Auxiliary Building Ventilation is equipped with monitoring for effluents. Auxiliary Building Ventilation Monitoring provides alarm and trip functions. SGB Monitor Tank liquid releases are made based on radiochemical batch analysis of the tank contents and are monitored by the waste disposal system liquid effluent monitor. Information on concentrations in these effluents that are below the functional alarm levels are provided by the routine radiochemistry analysis and continuous ERCS monitor. 9.2.2.1 Components 9.2.2.1.1 Laundry and Hot Shower Tanks The laundry and hot shower tanks are constructed of welded stainless steel. The inlets to these tanks have been closed off. Laundry and hot shower waste is now directed to the floor drain system. 9.2.2.1.2 Chemical Drain Tank The chemical drain tank is stainless steel and collects drainage from the chemistry laboratory. After analysis, the tank contents are treated as aerated waste. 9.2.2.1.3 Reactor Coolant Drain Tanks The reactor coolant drain tanks are right circular cylinders with spherically dished heads. The tanks, which are all welded stainless steel, serve as a drain collecting point for the Reactor Coolant System drains and other equipment located inside the reactor containments. The tank contents can be discharged to the CVCS, waste holdup tank, or to the refueling water storage tanks.

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 36 Page 9.2-6 9.2.2.1.4 Waste Holdup Tank The waste holdup tank receives radioactive liquids from various aerated plant systems and drains. Various non-aerated equipment can also be aligned to the waste holdup tank. The tank is constructed of welded stainless steel and can be drained to the aerated sump tank or pumped to either the waste evaporator or the waste condensate tanks. 9.2.2.1.5 Aerated Sump Tank and Pumps The aerated sump tank serves as a collecting point for auxiliary building floor drains and various aerated equipment system drains. A horizontal centrifugal sump pump or shared backup pump are used to transfer the tank contents to the waste holdup tank, ADT collection tanks, or the aerated monitor tanks. All wetted parts of the pumps are stainless steel. The aerated sump tank is constructed of welded stainless steel. 9.2.2.1.6 Non-Aerated Sump Tank The non-aerated sump tank serves as a collecting point for waste water from the charging pump seal water, gas decay tank drains, demineralizer drains, and other various non-aerated equipment drains. A horizontal centrifugal pump or shared backup pump transfers this collected liquid normally to the CVCS holdup tank, but can be aligned to transfer the contents to the waste holdup tank. The tank is constructed of welded stainless steel with a diaphragm seal to prevent entrained gases from escaping to the atmosphere. This tank can be vented to the waste gas compressor suction. 9.2.2.1.7 Aerated Drains Treatment (ADT) Monitor Tanks The ADT monitor tanks are constructed of welded stainless steel and can receive water from the ADT ion exchangers and the SGB monitor tanks. The tanks serve as a final collection point for water which has been processed through the liquid radwaste treatment system. Depending upon chemical analysis, the water in the ADT monitor tanks can be released to the environment, reprocessed, or returned to the waste holdup tank or SGB monitor tanks, for decay. 9.2.2.1.8 Aerated Drains Treatment (ADT) Collection Tanks The aerated drains treatment collection tanks can receive liquid from the aerated sump tank, the miscellaneous drains collection tank, the ADT monitor tanks, or the SGB system for processing in the radwaste building. The ADT collection tank water is normally processed through the ADT cartridge filters, but can be directed to the waste holdup tank for additional decay. The ADT collection tanks are constructed of welded stainless steel.

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 36 Page 9.2-7 9.2.2.1.9 Aerated Drains Treatment (ADT) Ion-Exchangers The ADT system uses three flushable ion-exchangers that can be operated in parallel or series and are shared by Units 1 and 2. Each ion exchanger contains approximately 35 cu. ft. of resin. Each vessel is constructed of stainless steel, with a stainless steel retention screen. 9.2.2.1.10 Miscellaneous Drains Collection Tank The miscellaneous drains collection tank receives liquids from floor drains of the radwaste building and from the resin disposal building sump. It can be used as excess storage in series with the ADT collection tanks. The miscellaneous drains collection tank is constructed of welded stainless steel. 9.2.2.1.11 SGB Monitor Tanks The SGB monitor tanks are constructed of welded stainless steel and can serve as a collecting point for the SGB ion exchanger outlet. The tanks are occasionally used for ADT water waiting reprocessing. 9.2.2.1.12 SGB Ion Exchanger Two flushable ion exchangers, operated in parallel, are shared by Units 1 and 2. Each ion exchanger contains approximately 37 cu. ft. of resin. Each vessel is constructed of stainless steel, with a stainless steel resin retention screen. 9.2.2.1.13 Waste Evaporators Equipment not used. 9.2.2.1.13.1 2 GPM Radwaste Evaporator Equipment not used. 9.2.2.1.13.2 Waste Feed Equipment not used. 9.2.2.1.13.3 Steam Supply Equipment not used.

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 36 Page 9.2-8 9.2.2.1.13.4 Cooling Water Supply Equipment not used. 9.2.2.1.13.5 Distillate System Equipment not used. 9.2.2.1.13.6 Concentration Level Equipment not used. 9.2.2.1.13.7 Nitrogen Blanketing Equipment not used. 9.2.2.1.14 ADT Evaporator (5 GPM) Equipment not used. 9.2.2.1.14.1 Evaporator Equipment not used. 9.2.2.1.14.2 Vapor Condenser Equipment not used. 9.2.2.1.14.3 Concentrate Cooler Equipment not used. 9.2.2.1.14.4 Recirculation Pump Equipment not used. 9.2.2.1.14.5 Distillate Cooler Equipment not used.

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 36 Page 9.2-9 9.2.2.1.14.6 Vent Cooler Equipment not used. 9.2.2.1.15 Waste Condensate Tanks The waste condensate tanks are constructed of welded stainless steel and are used for excess holdup capacity for liquids awaiting processing. 9.2.2.1.16 ADT Condensate Receiver Tanks The ADT condensate receiver tanks are constructed of welded stainless steel and serve as an intermediate holding point for radwaste water processing. 9.2.2.1.17 Aerated Monitor Tanks The aerated monitor tanks are constructed of welded stainless steel and are available for holdup of excess waste liquid awaiting processing via the liquid radwaste system. 9.2.2.1.18 Waste Liquid Discharge Header The waste liquid discharge header begins below grade just outside of the auxiliary building and travels to the circulating water distribution basin discharge structure at the head of the circulating water discharge canal. The header then enters the discharge canal and travels along the canals bottom terminating in a mixing diffuser just upstream of the circulating water canal discharge structure at the Mississippi River. The buried portion of the header is a polypropylene dual wall containment system with leak detection. Adjacent to the circulating water distribution basin discharge structure the header terminates into a sump system which allows sampling for leakage. The portion of the header within the discharge canal is single wall polypropylene pipe. (References 2,3) 9.2.3 Performance Analysis Liquid wastes are generated primarily by plant maintenance and unit operation. Under normal conditions, these wastes are treated as necessary to meet release requirements and discharged to the environment. The Liquid Radwaste System was analyzed and evaluated to show plant capability to meet the design objectives of Appendix I to 10CFR50. See Reference 1 for details. The liquid source terms were calculated using the GALE code and are presented in Table 9.2-3. The following assumptions were used in the analysis.

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 36 Page 9.2-10

a.

Part of the reactor coolant letdown stream (called shim bleed) is diverted to the Chemical Volume Control System (CVCS) hold up tank. After further processing, it was assumed that the entire shim bleed is released to the circulating water discharge canal.

b.

Equipment and clean wastes, which are collected in the reactor coolant drain tank and the nonaerated drain sump tank, respectively, are processed together with the shim bleed. In the analysis, it was assumed that all the wastes treated were released to the discharge canal downstream of the cooling towers.

c.

Dirty wastes originating from the aerated drain system are usually collected in the aerated drain treatment (ADT) collection tank. Following processing, the wastes were assumed processed through two ADT ion exchangers in series and the entire content was discharged to the circulating water discharge canal.

d.

Steam generator blowdown is normally processed through the steam generator blowdown (SGB) ion exchanger and then discharged to the condenser. Blowdown is released to the circulating water discharge canal approximately 5 days a month with no processing. For the analysis, it was assumed that the blowdown was continuously processed through the SGB ion exchanger (mixed bed) and pumped to the SGB monitor tank where the entire contents are released to the discharge canal.

e.

Detergent wastes which originate from the laundry and hot shower drains are collected in the laundry and hot shower tanks. For the analysis, it was assumed that the wastes were discharged through the laundry tank strainer to the discharge canal without treatment. In addition, the amount of detergent wastes was assumed to be 450 gal/day as indicated in NUREG-0017. Table 9.2-4 contains information pertinent to the above liquid radwastes. The results of the analysis demonstrated the plants capability of keeping the levels of radioactivity in effluents as low as reasonably achievable. Maximum offsite dose from all possible pathways was shown to be well within the design objectives of Appendix I of 10CFR50. Tritium exists as a gas or combined in water. In the presence of water the majority of the tritium will remain with the water and not appear as a gas. The tritium release rates in the plant offgases and liquid radwaste discharges result in concentration well below the 10 CFR 20 limits. The dose rate to the environs due to tritium is negligible and therefore not considered significant in the radioactive waste systems.

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 36 Page 9.2-11 However, as a further means of lowering the potential for tritium to enter local groundwater, the discharge point of liquid radwaste and steam generator blowdown was extended from its original point of discharge at the head of the circulating water discharge canal to just upstream of the circulating water canal discharge structure at the Mississippi River. The extended discharge header ensures that any tritium that may be present in the liquid release is not retained within the discharge canal as it travels down its entire length but is mixed into the circulating water discharge immediately before it enters the river (Reference 3). The extension effectively bypasses the Circulating Water Monitor (R-21). This is discussed in USAR Section 7.5.2. Protection against accident and/or off standard releases of wastes is provided by appropriate system interlocks; detection instrumentation alarms on off standard conditions and automatically closes the discharge valve. All radwaste tankage, filters and equipment are either contained in a Class I* portion of the plant or specially constructed areas to provide a substantial degree of control of the wastes. These arrangements are provided to assure that in the event of a failure of the liquid waste systems or errors in operation of the system the potential for inadvertent release of liquids is minimal. This assures control and containment of any leaks, spills, or overflows from the equipment. The liquid waste system components are found in the containment, auxiliary, and radwaste buildings. In addition, all vessels which are used for waste storage are located inside structures such as sumps, dikes or vaults which will retain any spilled liquid. The reactor coolant drain tank is located at the ground floor of the containment and can be pumped to the liquid waste system. The Miscellaneous Drains Collection Tank, ADT Collection Tanks, ADT Condensate Receiver Tanks, ADT Monitor Tanks, ADT evaporator and waste concentrates tank (located in the radwaste building) were designed Class III*. The waste concentrates tank is in a vaulted room that holds its entire volume. The rest of the tanks are located either in rooms with dikes or drain directly to the radwaste building sump. The radwaste system was designed to permit operation of the rest of the plant for extended periods without requiring its being continually operable. The CVCS holdup tanks are also equipped with safety pressure relief valves and designed to withstand the established seismic forces at the site. Liquids in the Chemical and Volume Control System flowing into and out of these tanks are controlled by manual operation and governed by prescribed administrative procedures.

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 36 Page 9.2-12 The volume control tank design philosophy is similar in many respects to that applied for the CVCS holdup tanks. Level alarms, pressure relief valves and tank isolation and valve control assure that a safe condition is maintained during system operation. Excess letdown flow is directed either to the CVCS holdup tanks via the reactor coolant drain or the volume control tank. The waste holdup tank is a horizontal tank which is continuously maintained at atmospheric pressure. Its vent is routed to the auxiliary building exhaust ducts. Should a complete failure of any tank containing radioactive liquid wastes occur its contents will be retained. The potential hazard from these processes or waste liquid releases is derived only from the volatilized components. The potential for accidental release is summarized in Section 14.5.2. All radioactive liquid waste processed through the radioactive waste collection and treatment systems is discharged to the circulating water discharge channel. The probability of unmonitored releases to the discharge channel is exceedingly small because at least two barriers must be abridged to permit release; e.g. steam generator tubes and condenser tubes or residual heat exchanger and component cooling heat exchanger. In addition the pressure differential, in essentially all operating modes, opposes leakage into the discharge and the Circulating Water Monitor would indicate abnormal radiation levels. After waste disposal system liquid has been sampled for radiochemical batch analysis and is determined acceptable for release, the liquid is transferred through a radiation trip valve to the auxiliary building standpipe, then on to the waste liquid discharge header. Periodic samples are taken from the discharge channel before it enters the river for radiation monitoring to further confirm proper operation of the circulating water monitor. Although the radiochemical analysis establishes the basis for releases, the radiation monitors provide surveillance over the release operation and automatically close the discharge valve if the liquid activity release rate would exceed the limits of 10CFR20. The most severe airborne radioactivity concentrations which might be postulated to result from open cycle cooling tower operation was investigated and was compared with the concentration limits specified in Table II of 10CFR20. It was observed that even though the basic assumptions relating to the composition of activity and the associated release rates are factors of 10 to 1000 greater than what might be experienced under any conceivable abnormal situation, the airborne concentrations in the cooling tower vapor at the site boundary would still be well below of the 10CFR20 limits. Periodic sampling of the intake water for radioactivity and appropriate environs monitoring are performed as a further precaution that no unforeseen abnormal condition results in undesirable radiological effects. 604000000354

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 37 Page 9.3-1 9.3 GASEOUS RADWASTE SYSTEM 9.3.1 Design Basis 9.3.1.1 Gaseous Radwaste System The gaseous radwaste system is designed to process and control the release of gaseous radioactive effluents to the site environs so that the offsite radiation dose rate does not exceed the limits specified in 10CFR20 and the design objectives of Appendix I to 10CFR50 are met. 9.3.1.2 Monitoring Fuel and Waste Storage Areas Criterion: Monitoring and alarm instrumentation shall be provided for fuel and waste storage and associated handling areas for conditions that might result in loss of capability to remove decay heat and to detect excessive radiation levels. (GDC 18) Monitoring and alarm instrumentation is provided for fuel and waste storage and handling areas to detect deviation from normal water level, inadequate cooling and excessive radiation levels. Radiation monitors are provided to maintain surveillance over the release of radioactive gases and liquids, and the permanent record of activity releases is provided by radiochemical analysis of known quantities of waste. A controlled ventilation system removes gaseous radioactivity from the atmosphere of the fuel storage and waste treating areas of the auxiliary building and discharges it to the atmosphere via the auxiliary building vent. Radiation monitors are in continuous service in these areas to actuate high-radiation alarms on the control board annunciator, as described in Section 7.5.3. 9.3.1.3 Protection Against Radioactivity Release from Spent Fuel and Waste Storage Areas Criterion: Provisions shall be made in the design of fuel and waste storage facilities such that no undue risk to the health and safety of the public could result from an accidental release of radioactivity. (GDC 69) All waste handling and storage facilities are contained and equipment is designed so that accidental releases directly to the atmosphere are monitored and will not exceed the guidelines of 10CFR100, as described in Sections 9.1.2, 14.5.2, and 14.5.3.

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 37 Page 9.3-2 9.3.2 Description During plant operation, potentially radioactive gases are received mainly from the following sources:

a.

Displacement of cover gases as liquids accumulate in various tanks.

b.

Miscellaneous equipment vents and relief tanks.

c.

Sampling operations and automatic gas analysis for hydrogen and oxygen in cover gases.

d.

Nitrogen stripping of reactor coolant to remove hydrogen during shutdown operations. The waste gas system consists of two interconnected process loops. A low level loop and a high level loop. The waste gas system is very similar to the Westinghouse Environmental Assurance System with the exception of the volume of a gas decay tank which is slightly smaller than the EAS. The low level loop is designed to contain and process influent gases from sources a through d above. It is also used to process and contain fission gases resulting from occasional hydrogen stripping of the reactor coolant. Gases vented into the low level loop vent header flow to the waste gas compressor suction header. One of two compressors is in continuous operation with the second unit instrumented to act as backup for peak load conditions or failure of the first unit. Under normal operating conditions, the gas flow from the compressor is split through the hydrogen recombiner and to the decay tanks. Outlet flow from the gas decay tanks is varied to maintain proper pressure in the vent header and holdup tank header. When the tank in service becomes pressurized to approximately 110 psig, a pressure transmitter automatically closes the inlet valve to that tank, opens the inlet valve to the backup tank and sounds an alarm to alert the operator so a new backup tank may be selected. Pressure indicators are provided to aid the operator in selecting the backup tank. Any net flow into or out of the loop accumulates in, or is made up from, the gas decay tanks. A backup supply of gas is provided from the nitrogen header in the event that return flow from the gas decay tanks to the CVCS holdup tanks is not available.

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 37 Page 9.3-3 Most of the gas received by the low level loop during normal operation is cover gas displaced from the Chemical and Volume Control System holdup tanks as they fill with liquid. This gas is primarily nitrogen, but it also contains hydrogen originally dissolved in the letdown coolant. As the gas circulates around the loop, hydrogen is oxidized to water vapor and condensed in the recombiner. The gas decay tank capacity is adequate for storing all of the holdup tank cover gas when those tanks are filled with liquid. There is normally no need to vent the system to atmosphere, although an occasional discharge will be required to dispose of gases accumulated from shutdown operations and inflows from miscellaneous vents. The high level waste gas loop was designed to process and contain gases with high activity received during infrequent hydrogen stripping of the reactor coolant to remove fission gases. Since reactor coolant fission gas is usually at a low activity level, the high level waste gas loop is normally not used. The high level loop compressor is normally aligned to the low level loop and is used during times of high demand. The high level gas decay tanks are normally used for reserve holdup capacity of low level loop gas. This helps to minimize the frequency of gas decay tank releases. When a low level loop gas decay tank must be discharged to the environment, its contents are sampled and analyzed to determine and record the activity to be released, and then will be discharged to the auxiliary building vent at a controlled rate. The isolation valve in the discharge line is closed automatically by a high activity level indication in the auxiliary building vent. During operation, gas samples are drawn automatically from the in service low level loop gas decay tank, and the various tanks vented to the low level waste gas system. The sample stream is automatically analyzed to determine the hydrogen and oxygen content. There should be no significant oxygen concentration in any of the tanks. An alarm will warn the operator if any sample shows two percent or higher of oxygen by volume. The nitrogen and hydrogen supply systems shown on Figure 9.1-6 are designed to provide a supply of gas to various NSSS components. Operation is identical for both systems. Each system consists essentially of multiple banks of gas cylinders, dual manifolds, each with pressure regulator, and branch line to the various pieces of equipment. Each branch line has a shut off valve and a pressure control valve. Two independent manifolds are provided for each system, one for normal operation and one spare. Each manifold has a pressure regulator, pressure indicator, a common pressure switch and a common alarm. When the gas cylinder banks supplying the operating manifold are low in pressure, an alarm sounds. The exhausted gas cylinders are removed from service and another group of cylinders are placed in service.

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 37 Page 9.3-4 9.3.2.1 Components 9.3.2.1.1 Gas Decay Tanks Fifteen welded carbon steel tanks are provided to accumulate and contain radioactive gases. Nine tanks are supplied in the low level loop to store cover gases displaced from various tanks until they are returned to the tanks. The remaining six tanks are supplied in the high level loop. 9.3.2.1.2 Compressors Three compressors are provided to circulate gases around the two process loops. These compressors are water-sealed centrifugal machines. All three compressors are available for use in the low level loop. One compressor is normally in service on the low level loop with a second compressor in standby. Operation of two compressors in the low level loop is controlled by the vent header pressure. Two of the compressors are available for use on the high level loop if needed. Construction is primarily carbon steel. A mechanical seal is provided in each of the three units to minimize leakage of seal water. 9.3.2.1.3 Recombiners One recombiner is provided in each of the two waste gas system process loops but the high level recombiner is not used. The units are skid mounted packages complete with separate control panels for remote installation. Instrumentation provided in the recombiner will control oxygen addition to maintain effluent hydrogen concentration. The catalyst is palladium on kaolin beads approximately one-eighth inch in diameter. 9.3.2.1.4 Nitrogen Manifold Nitrogen is supplied at a nominal pressure of 100 psig to purge the vapor spaces of various NSSS components. Purging reduces the hydrogen concentration or replaces the fluid that has been removed. Each of the dual manifolds are provided with gas supply connections from a nitrogen storage facility. 9.3.2.1.5 Hydrogen Manifold Hydrogen is supplied at a nominal pressure of 100 psig to the main generators, volume control tanks and to other various NSSS components from a central storage facility. Hydrogen is used as the heat transfer medium to cool the main generators and for reducing the oxygen concentration in the volume control tank to less than 5% by volume. Hydrogen is supplied to the plant systems by a remote hydrogen storage facility outside of the turbine building, installed under modification EC12191 (Ref. 5). 604000000356

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 37 Page 9.3-5 The remote hydrogen storage facility consists of three permanent tube banks connected to a common header. On each of the three banks, the individual tubes are joined together by a manifold. Each of the three banks can be isolated from the common header individually by a single isolation valve between the tube bank manifold and the header. Only one tube bank is placed into service at a given time, in order to limit the volume of hydrogen being supplied to the header. The tube banks are refilled on site by a delivery tube trailer. The design criteria for the storage facility were selected in accordance with the Electrical Power Research Institute report NP-5283-SR-A, Guidelines for Permanent BWR Hydrogen Water Chemistry Installations - 1987 Revision (Ref. 4), and associated NRC Safety Evaluation Report, dated July 1987. The hydrogen storage facility meets the design criteria as prescribed within the aforementioned documents. 9.3.2.1.6 Gas Analyzer An automatic gas analyzer is provided to monitor the concentrations of oxygen and hydrogen in the cover gas of tanks and vessels which might accumulate a hazardous mixture of the two gases. 9.3.3 Performance Analysis Gaseous wastes consist primarily of hydrogen stripped from coolant discharged to the CVCS holdup tanks during boron dilution, nitrogen and hydrogen gases purged from the volume control tank, and nitrogen from the closed gas blanketing system. Hydrogen is removed by oxidation and condensation in the recombiners. Nitrogen from the gas blanketing system is stored and reused. The majority of gas discharged from the system is nitrogen received as a result of shutdown operations and miscellaneous vents. The gaseous waste process flow diagram is shown on Tables 9.3-2 and 9.3-3. These tables illustrate flow rates, temperatures, pressures, and specific isotope radioactivity. No minimum holdup time is specified. The design of the high level loop provides for indefinite holdup. Gaseous source terms were calculated using the GALE code and are presented in Table 9.3-1. Detailed assumptions and methodology used in the calculation are discussed in Reference 1. Maximum offsite dose from all possible pathways was shown to be well within the Design Objectives of Appendix I to 10CFR50. The releases are described and their effects are summarized in Section 14.5.3.1.

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 37 Page 9.3-6 THIS PAGE IS LEFT INTENTIONALLY BLANK

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 13 Page 9.4-1 9.4 SOLID RADWASTE SYSTEM 9.4.1 Design Basis The solid radwaste system is designed to package, store and provide shielded storage facilities for solid wastes and to allow temporary storage prior to shipment from the plant for offsite processing or disposal. The system is designed to meet the requirements of 10CFR20, 10CFR71, and 49CFR170-189. 9.4.2 Description Solid wastes consist mainly of dry active waste (DAW) such as contaminated paper, plastic, wood, etc., contaminated metals and spent resin. DAW may be compacted for disposal or storage or may be sent off-site for further processing, such as sorting or incineration. The by-product of such off-site processing, for example, incinerator ash, may be returned to the plant site for storage if no disposal site is available. Contaminated metals may be compacted on-site for storage or disposal. Contaminated metals may also be sent off-site for processing such as decontamination or metal melting. Spent resin originates in any of several system ion exchangers. Spent resin is flushed to a resin shipping liner for disposal or off-site processing. Alternatively, resin may be placed in on-site storage if a disposal site is not available. 9.4.3 Performance Analysis Solid wastes received at disposal sites must meet the requirements of 10CFR61 relating to waste form and classification as well as disposal site-specific regulations. Annual generation of DAW is estimated at approximately 50,000 lbs. Annual generation of spent bead resin is estimated at approximately 500 cu. ft. 95130

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 13 Page 9.4-2 THIS PAGE IS LEFT INTENTIONALLY BLANK

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 31 Page 9.5-1

9.5 REFERENCES

1.

Letter, L O Mayer (NSP) to D. L. Ziemann (NRC), Appendix I Submittals, June 4, 1976 and July 21, 1976. (10501/1800) (10501/2070)

2.

Prairie Island Modification 92L377, Waste Liquid Discharge Header Replacement.

3.

Prairie Island Modification 89Y065, Waste Liquid Discharge Line Extension.

4.

EPRI NP-5283-SR-A, Guidelines for Permanent BWR Hydrogen Water Chemistry Installations - 1987 Revision, September 1987.

5.

Passport Engineering Change #12191, Hydrogen Storage System. 01145513

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PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 32 TABLE 9.1-1 WASTE DISPOSAL SYSTEM PERFORMANCE DATA Original Plant Design Life 40 years Normal process capacity, liquids 2 gpm Estimated Annual liquid input to Radwaste System(*) Volume (2 units) 531,240 gal. Activity (2) Tritium Design Value (2 units) 5.2 x 103 curies Tritium, Expected Value (2 units) 8.2 x 102 curies Other (2 units) 8.04 curies Annual gaseous release Activity (2 units) 1278 curies/year Annual generation of Dry Active Waste (2 units) 50,000 lbs Annual generation of spent resin 500 ft3 (*) estimated based on FSAR Table 11.1-4, equilibrium cycle 01-082 01353916

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 23 TABLE 9.1-2 WASTE DISPOSAL COMPONENTS CODE REQUIREMENTS Component Code Chemical Drain Tank No code Reactor Coolant Drain Tank ASME III, (1) Class C Sump Tanks No code Monitor Tanks No code Waste Holdup Tanks No code Collection Tanks No code Waste Condensate Tank No code Ion-Exchange Shells No code Laundry and Hot Shower Tank No code Waste Filter ASME III, (1) Class C Piping and Valves USAS-B31.1 (2) Section 1 Gas Decay Tank ASME III, (1) Class C Recombiner ASME III, (1) Class C (1) ASME III - American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section III, Nuclear Vessels (2) USAS-B31.1 - Code for pressure piping American Standards Association and special nuclear casses where applicable. 01-082 01-082

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 28 TABLE 9.1-3 COMPONENT

SUMMARY

DATA (Page 1 of 4) Tanks Qty Type Volume Design Pressure psig Design Temp F Material(1) Reactor Coolant Drain (per unit) 1 Horiz 350 gal 25 267 ss Laundry & Hot Shower 2* Vert 700 gal Atm 180 ss Chemical Drain 1* Vert 600 gal Atm 180 ss Aerated Sump 1* Vert 600 gal Atm 180 ss Non-Aerated Sump 1* Vert 300 gal Atm 125 ss Waste Holdup 1* Horiz 24,490 gal Atm 180 ss Waste Condensate 2* Vert 1,000 gal Atm 180 ss Gas Decay 15* Vert 470 ft3 150 150 cs SGB Flash (per unit) 1 Vert 2,000 gal 100 325 cs Aerated Drains Monitor 2* Vert 1,000 gal Atm 125 ss SGB Holdup (per unit) 2 Vert 10,000 gal Atm 135 ss SGB Monitor (per unit) 2 Vert 10,000 gal Atm 135 ss ADT Collection 2* Vert 3,000 gal Atm 180 ss Misc. Drains Collection 1* Vert 3,000 gal Atm 180 ss Laundry Sludge 1* Vert 800 gal Atm 180 ss Coagulation 1* Vert 900 gal Atm 180 ss ADT Condensate 2* Vert 2,400 gal Atm 180 ss ADT Monitor 2* Vert 5,000 gal Atm 180 ss Spent Resin 1* Vert 2,200 gal 30 180 ss Waste Concentrate 1* Vert 1,700 gal 33 180 ss (1) Material contacting fluid (2) Mechanical seal provided Shared by Units 1 and 2 05-054 05-054

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 28 TABLE 9.1-3 COMPONENT

SUMMARY

DATA (Page 2 of 4) Pumps Qty Type Flow gpm Head ft Design Pressure psig Design Temp F Material(1) 11 Reactor Coolant Drain Tank (per unit) 1 Horiz cent(2) 60 200 150 267 ss 12 Reactor Coolant Drain Tank (per unit) 1 Horiz cent(2) 200 200 150 267 ss Chemical Drain Tank 1* Horiz cent(2) 20 100 375 150 ss Laundry 2* Horiz cent(2) 20 100 150 150 ss SGB Flash Tank Transfer (per unit) 1 Horiz cent(2) 120 130 150 140 ss 11 SGB Holdup Tank (per unit) 1 Horiz cent(2) 120 310 150 140 ss 12 SGB Holdup Drain Tk (per unit) 1 Horiz cent(2) 60 125 150 140 ss SGB Monitor Drain Tk (per unit) 1 Horiz cent(2) 60 125 150 125 ss Aerated Drains Monitor Tank 1* Horiz cent(2) 60 150 150 125 ss Non-Aerated Sump Tank 1* Horiz cent(2) 60 80 150 125 ss Laundry & Hot Shower Tank 2* Horiz cent(2) 60 100 150 125 ss Aerated Sump Tank 1* Horiz cent(2) 20 100 150 150 ss Backup Sump Tank 1* Horiz cent(2) 20 100 150 150 ss Waste Evaporator Feed 1* Horiz cent(2) 20 100 150 150 ss Waste Condensate Tank 2* Horiz cent(2) 20 100 150 150 ss (1) Material contacting fluid (2) Mechanical seal provided Shared by Units 1 and 2 05-054

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 28 TABLE 9.1-3 COMPONENT

SUMMARY

DATA (Page 3 of 4) Pumps Qty Type Flow gpm Head ft Design Pressure psig Design Temp F Material(1) ADT Collection Tank 2* Horiz cent(2) 20 110 150 200 ss Misc. Collection Tank 2* Vert cent(2) 60 100 150 200 ss Coagulation Tank 1* Horiz cent(2) 20 80 150 125 ss Laundry Sludge Tank 1* Horiz cent(2) 30 115 150 125 ss ADT Condensate Receiver Tank 2* Horiz cent(2) 60 100 150 200 ss ADT Monitor Tank 2* Horiz cent(2) 60 100 150 200 ss 121 Spent Resin 1* Horiz cent(2) 30 145 150 125 ss 122 Spent Resin 1* Horiz diaphragm 20 200 150 125 ss Waste Concentrate Tank 1* Horiz diaphragm 20 200 150 125 ss Heat Exchangers Qty (per unit) Type Shell Flow (lb/hr) Tube Flow (lb/hr) Btu/hr Shell Design Press/ Temp (psi)/(F) Tube Design Press/ Temp (psi)/(F) Shell Matl. Tube Matl. SGB Heat Exch. 11 1 Shell & Tube 75,000 6,900** 1,159,200 150/130 150/130 cs ss SGB Heat Exch. 12 1 Shell & Tube 57,776 2,481,862 10,377,000 150/130 600/150 cs ss This is a maximum blowdown liquid capacity as a result of blowdown system modifications. This corresponds to a blowdown rate of approximately 15 gpm per steam generator. (1) Material contacting fluid (2) Mechanical seal provided Shared by Units 1 and 2 05-054

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 28 TABLE 9.1-3 COMPONENT

SUMMARY

DATA (Page 4 of 4) Strainer and Filter Qty Flow gpm Design Pressure psig Design Temp F Housing Material Filters SGB Reclaim 2 20 150 125 cs Aerated Drain 1* 20 150 125 ss Non-Aerated Drain 1* 20 150 125 ss 123/124 ADT 2* 40 150 125 ss 123 ADT IX 1* 20 150 125 ss 121/122 ADT 2* 20 150 125 ss Strainers SGB Ion Exchanger 2 60 150 125 ss Miscellaneous Qty Capacity Type Waste Gas Compressors 3* 40 CFM Horiz (2) cent ADT Ion Exchanger 3* 60 gpm (1) Material contacting fluid (2) Mechanical seal provided

• Shared by Units 1 and 2

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 23 TABLE 9.2-1 PERFORMANCE DATA AND SERVICE REQUIREMENTS (2 GPM Waste Evaporator) Equipment not used. 01-082

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 23 TABLE 9.2-2 PERFORMANCE DATA AND SERVICE REQUIREMENTS (5 GPM ADT Evaporator) Equipment not used. 01-082

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 23 TABLE 9.2-3 LIQUID SOURCE TERMS FROM THE PRAIRIE ISLAND PLANT (PER UNIT) Page 1 of 2 ANNUAL RELEASES TO DISCHARGE CANAL Coolant Concentrations Adjusted Detergent Total Nuclide Half-Life Primary Secondary Boron RS Misc. Wastes Secondary Turb Bldg Total LWS Total Wastes (Days) (Micro CI/ML) (Micro CI/ML) (Curies) (Curies) (Curies) (Curies) (Curies) (CI/YR) (CI/YR) (CI/YR) CORROSION AND ACTIVATION PRODUCTS CR 51 2.78E+01 1.72E-05 2.27E-07 .00001 .00016 .00027 .00000 .00044 .00054 0.00000 .00054 MN 54 3.03E+02 2.80E-04 5.43E-08 .00000 .00001 .00006 .00000 .00009 .00011 .00100 .00110 FE 55 9.50E+02 1.44E-03 1.90E-07 .00001 .00014 .00023 .00000 .00038 .00046 0.00000 .00046 FE 59 4.50E+01 9.03E-04 1.39E-07 .00000 .00009 .00017 .00000 .00026 .00031 0.00000 .00031 CO 58 7.13E+01 1.44E-02 1.93E-06 .00009 .00139 .00230 .00002 .00379 .00459 .00400 .00460 CO 60 1.92E+03 1.80E-03 2.44E-07 .00001 .00017 .00029 .00000 .00048 .00058 .00870 .00930 NP239 2.35E+00 1.12E-03 1.27E-07 .00000 .00009 .00015 .00000 .00024 .00029 0.00000 .00029 FISSION PRODUCTS BR 83 1.00E-01 5.28E-03 2.90E-07 .00000 .00002 .00024 .00001 .00026 .00032 0.00000 .00032 BR 84 2.21E-02 2.97E-03 5.51E-08 0.00000 .00000 .00001 .00000 .00001 .00001 0.00000 .00001 RB 86 1.87E+01 8.05E-05 1.21E-08 .00000 .00038 .00014 .00000 .00052 .00063 0.00000 .00063 RB 88 1.24E-02 2.30E-01 2.34E-06 0.00000 .00000 .00133 .00000 .00133 .00160 0.00000 .00160 SR 89 5.20E+01 3.16E-04 5.55E-08 .00000 .00003 .00007 .00000 .00010 .00012 0.00000 .00012 SR 91 4.03E-01 6.65E-04 6.04E-08 .00000 .00002 .00007 .00000 .00009 .00010 0.00000 .00010 Y 91M 3.47E-02 4.08E-04 7.75E-08 .00000 .00001 .00006 .00000 .00007 .00009 0.00000 .00009 Y 91 5.88E+01 5.78E-05 6.30E-09 .00000 .00001 .00001 .00000 .00002 .00002 0.00000 .00002 ZR 95 6.50E+01 5.42E-05 8.28E-09 .00000 .00001 .00001 .00000 .00002 .00002 0.00000 .00002 NB 95 3.50E+01 4.52E-05 8.43E-09 .00000 .00000 .00001 .00000 .00001 .00002 0.00000 .00002 MO 99 2.79E+00 7.82E-02 1.20E-05 .00004 .00626 .01415 .00011 .02057 .02488 0.00000 .02500 TC 99M 2.50E-01 5.05E-02 3.91E-05 .00000 .00557 .04190 .00025 .04775 .05776 0.00000 .05800 RU 103 3.96E+01 4.07E-05 5.60E-09 .00000 .00000 .00001 .00000 .00001 .00001 .00014 .00015 RM 103M 3.96E-02 5.09E-05 5.04E-08 .00000 .00000 .00003 .00000 .00003 .00004 0.00000 .00004 TE 127M 1.09E+02 2.53E-04 2.46E-08 .00000 .00002 .00003 .00000 .00006 .00007 0.00000 .00007 TE 127 3.92E-01 8.71E-04 2.05E-07 .00000 .00004 .00022 .00000 .00027 .00033 0.00000 .00033 TE 129M 3.40E+01 1.27E-03 1.69E-07 .00001 .00012 .00020 .00000 .00035 .00040 0.00000 .00040 TE 129 4.79E-02 1.80E-05 1.45E-06 .00000 .00008 .00086 .00000 .00094 .00114 0.00000 .00110 I 130 5.17E-01 2.11E-03 2.18E-07 .00000 .00008 .00024 .00002 .00034 .00041 0.00000 .00041 01-082 01-082 01-082 01-082

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 23 TABLE 9.2-3 LIQUID SOURCE TERMS FROM THE PRAIRIE ISLAND PLANT (PER UNIT) Page 2 of 2 ANNUAL RELEASES TO DISCHARGE CANAL Coolant Concentrations Adjusted Detergent Total Nuclide Half-Life Primary Secondary Boron RS Misc. Wastes Secondary Turb Bldg Total LWS Total Wastes (Days) (Micro CI/ML) (Micro CI/ML) (Curies) (Curies) (Curies) (Curies) (Curies) (CI/YR) (CI/YR) (CI/YR) TE 131M 1.25E+00 2.40E-03 2.75E-07 .00000 .00015 .00032 .00000 .00047 .00057 0.00000 .00057 TE 131 1.74E-02 1.26E-03 1.41E-06 .00000 .00008 .00024 .00000 .00027 .00033 0.00000 .00033 I 131 8.05E+00 2.45E-01 3.46E-05 .00508 .02216 .04110 .00337 .07171 .00675 .00006 .08700 TE 132 3.25E+00 2.50E-02 3.06E-06 .00002 .00206 .00341 .00003 .00572 .00691 0.00000 .00690 I 132 9.58E-02 1.10E-01 2.19E-05 .00002 .00244 .01880 .00038 .02163 .02617 0.00000 .02600 I 133 8.75E-01 3.70E-01 4.25E-05 .00016 .02002 .04856 .00347 .07221 .08735 0.00000 .08700 I 134 3.67E-02 5.32E-02 1.46E-06 .00000 .00001 .00062 .00000 .00063 .00076 0.00000 .00076 CS 134 7.49E+02 2.35E-02 3.39E-06 .00035 .11364 .04047 .00003 .15449 .18688 .01300 .20000 I 135 2.79E-01 1.98E-01 1.72E-05 .00000 .00392 .01792 .00092 .02276 .02753 0.00000 .02000 CS 136 1.30E+01 1.24E-02 1.56E-06 .00008 .05733 .01862 .00002 .07605 .09199 0.00000 .09200 CS 137 1.10E+04 1.69E-02 2.26E-06 .00025 .08186 .02693 .00002 .10907 .13193 .02400 .16000 BA 137M 1.77E-03 1.85E-02 2.48E-05 .00024 .07654 .02518 .00002 .10198 .12336 0.00000 .12000 BA 140 1.28E+01 2.00E-04 2.70E-08 .00000 .00002 .00003 .00000 .00005 .00006 0.00000 .00006 LA 140 1.68E+00 1.42E-04 3.86E-08 .00000 .00002 .00005 .00000 .00006 .00007 0.00000 .00007 CE 141 3.24E+01 6.33E-05 8.46E-09 .00000 .00001 .00001 .00000 .00002 .00002 0.00000 .00002 PR 143 1.37E+01 4.54E-05 5.95E-09 .00000 .00000 .00001 .00000 .00001 .00001 0.00000 .00001 CE 144 2.84E+02 2.98E-05 5.43E-09 .00000 .00000 .00001 .00000 .00001 .00001 .00520 .00520 PR 144 1.20E-02 3.79E-05 5.83E-08 .00000 .00000 .00001 .00000 .00001 .00001 0.00000 .00002 ALL OTHERS 4.76E-08 3.09E-08 .00000 .00001 .00002 .00000 .00003 .00003 0.0 .00003 TOTAL (EXCEPT TRITIUM) 1.47E+00 2.14E-04 .00642 .39494 .30556 .00868 .71561 .86561 .06234 .93000 TRITIUM RELEASE 330 CURIES PER YEAR 01-082 01-082

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 23 TABLE 9.2-4 PRAIRIE ISLAND LIQUID RADWASTE SYSTEM SHIM BLEED EQUIPMENT DRAINS & CLEAN WASTE DIRTY WASTES BLOWDOWN WASTES DETERGENT WASTES

1.

Sources Reactor Coolant Letdown Non-Aerated Drain System & Reactor Coolant Drain Tank Aerated Darin System Blowdown from Steam Generator Laundry and Hot Shower Drains

2.

Flow Rate (gpd) 1,440 362 1,000 86,300 450

3.

Activity (FPCA) 1.0 1.0 0.07

4.

Collection Tank Volume (gal) 65,830 65,830 3,000 2,000 600

5.

Collection Rate (gpd) 1,802* 1,802* 1,000 86,300 450

6.

Collection Time (days) 29.2 29.2 1.2 0.009 1.07

7.

Processing Rate (gpm) 15 15 20 20 20

8.

Processing Time (days) 2.44 2.44 0.042 0.028 0.017

9.

Discharge Tank Volume (gal) 10,000 10,000 5,000 10,000 Same as Collection Tank

10.

Discharge Rate (gpm) 100 100 60 60 Same as Collection Tank

11.

Discharge Time (days) 0.055 0.055 0.023 0.046 Same as Collection Tank

12.

Fraction of Processed Stream Released 1.0 1.0 1.0 1.0 1.0 2 Evaporator Feed Ion Exchangers (cation) Evaporator condensate Demineralizer (anion) 2 ADT Ion Exchangers (Mixed Bed) SGBT Ion Exchanger (Mixed Bed)

13.

DFs Iodine 1(1) 102 102 (10) 102

14.

Cs, Rb 10(10) 1 2 (10) 10

15.

Others 10(10) 1 102 (10) 102

16.

Regenerant Time (days) Not Not Not Not NA

17.

Regenerant Volume (gal) Regenerated Regenerated Regenerated Regenerated

18.

Regenerant Activity

19.

Fraction of Regenerants Discharged

20.

Treatment of Regenerants

21.

Source Terms See Table 9.2-3 See Table 9.2-3 See Table 9.2-3 See Table 9.2-3 See Table 9.2-3

• Sum of Shim Bleed, Equipment Wastes, and Clean Waste input flows.

01-082 01-082

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 23 TABLE 9.3-1 GASEOUS SOURCE TERMS FROM THE PRAIRIE ISLAND PLANT (PER UNIT) Page 1 of 2 GASEOUS RELEASE RATE - CURIES PER YEAR Gas Stripping Building Ventilation PRIMARY COOLANT (MICROCI/GM) SECONDARY COOLANT (MICROCI/GM) SHUTDOWN CONTINUOUS REACTOR AUXILIARY TURBINE BLOWDOWN VENT OFF GAS AIR EJECTOR EXHAUST TOTAL KR-83M 2.418E-02 1.415E-08 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 KR-85M 1.26E-01 7.529E-08 0.0 0.0 0.0 3.0E+00 0.0 0.0 2.0E+00 5.0E+00 KR-85 7.313E-02 4.338E-08 1.5E+01 1.4E+02 2.2E+01 2.0E+00 0.0 0.0 0.0 1.8E+02 KR-87 6.917E-02 3.908E-08 0.0 0.0 0.0 1.0E+00 0.0 0.0 0.0 1.0E+00 KR-88 2.299E-01 1.340E-07 0.0 0.0 1.0E+00 5.0E+00 0.0 0.0 3.0E+00 9.0E+00 KR-89 5.776E-03 3.427E-09 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 XE-131M 9.248E-02 5.522E-08 0.0 0.0 2.1E+01 2.0E+00 0.0 0.0 1.0E+00 2.4E+01 XE-133M 2.328E-01 1.390E-07 0.0 0.0 2.0E+01 5.0E+00 0.0 0.0 3.0E+00 2.8E+01 XE-133 1.738E+01 1.023E-05 0.0 0.0 2.7E+03 3.7E+02 0.0 0.0 2.3E+02 3.3E+03 XE-135M 1.501E-02 8.808E-09 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 XE-135 3.978E-01 2.336E-07 0.0 0.0 6.0E+00 8.0E+00 0.0 0.0 5.0E+00 1.9E+01 XE-137 1.040E-02 6.119E-09 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 XE-138 5.081E-02 2.936E-08 0.0 0.0 0.0 1.0E+00 0.0 0.0 0.0 1.0E+00 TOTAL NOBLE GASES 3.6E+03 I-131 2.449E-01 3.838E-05 0.0 0.0 5.5E-04 3.9E-02 2.1E-03 0.0 2.4E-02 6.6E-02 I-133 3.697E-01 4.643E-05 0.0 0.0 3.0E-04 5.9E-02 2.5E-03 0.0 3.7E-02 9.9E-02 TRITIUM GASEOUS RELEASE 330 CURIES/YR 0.0 appearing in the table indicates release is less than 1.0 Ci/yr for noble gas, 0.0001 Ci/yr for Iodine. 01-081

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 23 TABLE 9.3-1 GASEOUS SOURCE TERMS FROM THE PRAIRIE ISLND PLANT (PER UNIT) Page 2 of 2 AIRBORNE PARTICULATE RELEASE RATE-CURIES PER YEAR NUCLIDE WASTE GAS SYSTEM BUILDING VENTILATION REACTOR AUXILIARY TOTAL MN-54 4.5E-05 2.0E-05 1.8E-02 1.8E-02 FE-59 1.5E-05 6.7E-06 6.0E-03 6.0E-03 CO-58 1.5E-04 6.7E-05 6.0E-02 6.0E-02 CO-60 7.0E-05 3.0E-05 2.7E-02 2.7E-02 SR-89 3.3E-06 1.5E-06 1.3E-03 1.3E-03 SR-90 6.0E-07 2.7E-07 2.4E-04 2.4E-04 CS-134 4.5E-05 2.0E-05 1.4E-02 1.8E-02 CS-137 7.5E-05 3.4E-05 3.0E-02 3.0E-02 01-081

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 23 TABLE 9.3-2 PRAIRIE ISLAND - HIGH LEVEL LOOP PROCESS CONDITIONS AND MAXIMUM ISOTOPIC CONCENTRATIONS 01-081 01-081

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 23 TABLE 9.3-3 PRAIRIE ISLAND - LOW LEVEL LOOP PROCESS CONDITIONS AND MAXIMUM ISOTOPIC CONCENTRATIONS 01-081 01-081

PRAIRIE ISLAND UPDATED SAFETY ANALYSIS REPORT USAR Section 9 Revision 23 THIS PAGE IS LEFT INTENTIONALLY BLANK

A B C D E F G H 1 2 3 4 HI 470120603 110E005{H{AW.1-71 REACTOR NORMALLY CAPPED. \\ CONNECT FOR VENT TD CDNTA{NMENT ATMOSPHERE 760" ELEV. FLANGE DRAIN DOWN ~ITT ACCUMULATOR LEAKDFF{RCS/ IB III C R ---'"en*---'-- 3/8-WD-2505R 1, / (3/8-WL -1) .l l -B032 {3-WL -1) l-------,-..=3_-W;;;L:;.-..;1 ____ ---< i DRAIN (S.I.Sl 1-W -151R LOOP 'A' ~**:',---..:..-"-=....:.;;.:;.;_~ w' ' "' 110E033 SH 1 {1-8823AI NSR III ,;, ~ {H{AW.1-441 TYGON HOSE Cl IA I -, CONNECT{ON INS{ E REACTOR CONTAINMENT UN{T I

• IWL 31-1 1 Ji,*

I ~ NSR~II,:, VENT, &l J :;~~ ~ FROM LOOP A Cl IA Al -X42 l" _ _._,.,,~xH-(-38 I H T LEG I RC 8 11 ' * \\ DRAINS {RCS! 1 3"X2" E-9 {XH-1-71 E-6 110E005 ---':e:1----!.....:-:e:*:-.-cl-..!--', MAKE-UP WATER {XH-1-7) F-11 IR~:1: 21 I RC- ; -11*I V /':,,, FOR RCDT FROM AUX o-1--.,...-t't':t-XH-1-38 ~ [XH-l-3B) SPRAY LINE.,._--[~J------: >j<: LJ E-5 {XH-l-7 ) - 5 !RC-(9-1! !RC-19-2!I ~ LOOP 8 -- -':e:1- ____ **:e:*:.,..:,-;::..:..>,L_J DRAINS (RCSl ~ I ~ ~ I ~ 2-WD-151R {2-WL-ll I I {XH-1-7) H-3 !RC-(-4] IRQ-3III I '85"

• 11 SUMP C >---~

{NF-392481 1* IA I III 3-W -151R {-WD-151R {3-WL-11 rl {l-WL-1) EXCESS LETDOWN HEAT EXCHANGER VACUUM BREAKER I IWL-35-23I ~ IB 111 c1 NSR C2 NSR VENT L .l (CVCSl """'._ __ -*,kr u~h0:51-~~-1 -. {1-8146) ACCUMULATOR L~'.J DRAIN (SIS) 1 E!: LOOP *s*- - * -i:*~.---"-'---+-,-1 VCT ~ 110E033 SH.! {1-882381 (HIAW.1-44) _W_L __ _9- {-X42D {-WD-151R {1-WL-11 o:i= (Zj 53021 6 IWG-22-12f--- /0/ 3/4-WD-151R,2020~ ~ I { 2-w/ 1:\\4 {.I / HI =,_:,. ~=.i WL-57-25 1 _915\\n 101114 1-RV52EN 1/4 VENTm., l-WD-151R NSR C2 3/4-X420 III IB \\ N TE IWL-95-ll NSR C2 Ill IB OUTSIDE REACTOR CONTAINMENT 1-C36 WL-42-1 WL-41-1 ((-X32 I 5 6 1-WD-152R-6 /{3/4-WL-5Bl (1/4"-WL-117) (l-WL-109) ' '7WL-29-26I {1-WL-6Al .....1-----D'::J- - - Nz ~ l 1-PCV-10(4 -WD-151R-7 {3-WL-71 OPEN SIGHT7 DRA{N \\,. ,/ :4* FL.EL. 697'-6' 1 I I I t TD CONTA{NMENT SUMP "A" CONT. SEE NF-39248 1 2-C58 3/4-~{2-WL-981 I" '~151""'-.... I 7 ¥ ,.,,~ L..--<'SE-'1-.....; Af\\. ~~DRAIN & 1-9(66B 3/4"X1/2,,{TEM, WDAPRB ~ 3-X4ZD.,., RE'ACTDR COOLANT ,?-~ RA{N TANK PUMPS WL-3(-22 {Il{/3) {]-WL-(08) I-X420 WL-31-2{ 3/4"-X42 1-9160A 3-0A32R ff 31434 7 a J 1i I ~ '1 tf! {-9160B 3-DA32R = C2 1B NSR Ill {l-WL-6BI 1-RA32ROB 110E067-SH.3 {H!AW,1 -1251 TO LETDOWN HEAT EXCHANGER FDR CONT. SEE X-H{AW-1-38 FLUSH 2-T58 '--IWL-40-2I {2-VC-1991

• {NOICATES UNIT N0.2 VALVES USED IN UNIT NO.I INSIDE REACTOR __ OUTSIDE REACTOR _

CONTAINMENT CONTAINMENT I { ,,J., 2-T58 [;~ '-10 PATH TRANSFER UN{T 2 ,,,..,,.---- 3/4" TUBING DRAIN / {3/8"-WL-329I 3 I ,,,---suMP C 4 5 6 7 I-W0-!52R-6 {1-2WL-68) NSR III OUTSIDE REACTOR CONTAINMENT C2 1B 1-C36 2WL-42-1 ZWL-41-1 1-X32D {1-2WL-6AI N2 -

~;:,!:JI---...IJ4'-H:::Jl<:h NSR C2 FILTERS 2-PCV-1014 1-RA32ROB 110E067 -

SH.3 {H!AW.1-125) III 2-91608 {-OA32R = TO LETDOWN HEAT EXCHANGER FDR CONT. SEE X-H{AW-1001-4 l '-,) 1B T FC 2-9160A t-DA32R ~ = v Cl z B " CD 0 _, w 'i' "' \\ {2-2VC-1991 f' ) 2 WL-40 ~~R C2 ~ 2-T58 _I_II __ I_B.,.. 3-WD-151R-10 ~- {3-2WL-108) T FOR CONT. SEE OWG.NF-39250 1-X42D C2 NSR ZWL-31-41 {1-2WL-64I 1B Ill .. INO{CATES UNIT NO.! VALVES USED IN UN{T N0.2 I I I I I 8 {NSIDE REACTOR CONTAINMENT UNIT 2 C2 NSR 1B Ill 3-WD-151R-10 {3-2WL-10I 2-WD-!51R-9 C2-2WL-9C) 9 10 11 475120603 HI 2-TJA = <18 ~ B = 110E013 3/8-W0-2505R ~ REACTOR 3 8 2 1 1,. 4 FLANGE { / - WL-I 2 -8032 LEAKDFF {RCS) TYGON HOSE {X-H{AW-(001-31 CONNECTIDN, {RCSI l ~II NSR ~ r---- .,85. N~

IA Cl /

2WL-35-23I 2-RC-250IR-!1 ~ 12 REVIS{ONS 81 AS BUil T-REMVE SECONDARY SEAL REFERENCE.CAPPED 2-2WL-l LINE, ADDED CONTJNUATION ZONES. PER ORR Pl-14-002 OWN: KJF 1-15-14 CHK'D: JKR 1-2\\-\\4 MOD", EC-21789 APP' = CMR 1-21-14 82 ISSUED FOR CONSTRUCTION REMOVED SECONDARY SEAL REFERENCE.CAPPED 2-WL-t LINE, ADDED CONTJNUATION ZONES

• OWN= JMB 1-23-14 CHK'D: FJH 01-31-14 01-31-14 I

~R I {2-2WL-1) ~ { I ~ "21 SUMP C {NF-39248) ,s;;+-,..-,,..**1- -.!. - - -*-~- -4

• LOOP A DRAINS (RCS) 3-W-151R 3X2 j1 z~c-1-1 I I2~c-;_2 I 110rn13 {XH-1001-3> 0-11 MOD": EC-21790 REVIEWED= RW PE CERT:

PE* 03-07-14 (3-2WL-1) >'

~ J------{ ~ J- --* SPRAY LINE (RCS>

\\ ~..._ I * {XH-1001-3) C-5 l2RC-I9-2I I 2RC-I9-I I 2-WD-!5IR .,_,_ - - - - -':e:'-

• LOOP 8 DRAINS {RCS)

{2-2WL-{J C2 NSR !ZRC-l-3 ! !2RC-l-4 ! 110C013 {XH-100(-31 H-3 APP' = TM ISSUED FOR CONSTRUCTION REMOVED,REPLACED & CHANGED POSH IONS OF WL-34-19 & WL-43-1, --..----, 2-WD-151R {1-2WL-11 OWN= FJH 09-12-14 CHK'D1 JMB 9-16-14 2WL-95-1 l.52fil; 3/4-WD-15{R {3/4-2WL-71/ 2WL-30-5 2WL-31-!7 1-X42D 2WL-30-6 1B Ill .__ ___ (({ = 2-9163 2-DA42R 2-WD-151R-8 (2-2WL-8) \\ ACCUMULATOR ORA{NS {5151 110E034 SHEET I {X-H{AW-(001-61 C2 NSR ls I ui LEGEND CLASS BREAK QA TYPE MOD": EC-21790 REVIEWED= RW PE CERT: 9-16-14 APP' : TM PE* 9-]7-14 AS BUILT-lNCORPRATED A/E',. REV. 82 PER ORR Pl-15-050 CERTJFIED REV. 82, TRANSFERRED TO RECORD TRACING. DWN1 MEA 4-17-15 CHK'D: RSA 6-1-15 MOD11: EC-21790 APP' = KJW 6-1-15 83 ISSUED FOR CONSTRUCTION DEL.NOTE 2 FROM 2WL-43 MOVE 2WL-36-B WNSTREAM OF 2WL-43-I &. CHANGE 10 BALL VAL VE, DWN1 JEK 5-4-15 CHK'D: MOD": EC-25250 REVIEWED= RSA 5-12-15 PE CERT1 APP' = TL PE" 6-24-15 AS BUILT-lNCDRPRATED A/E',. REV. 83 PER ORR Pl-15-178 CERTJFIED REV. 83, TRANSFERRED TO RECORD TRACING. OWN, MEA 11-24-15 CHK'D= JLS 11-24-15 MOD": EC-25250 APP' = KJW 11-24-15 84 AS BUil T-lLT (& 2L T) -1003 FISHER TRANSMITTER 23. PER ORR Pl-18-118 OWN: PB 11-28-18 CHK'D: TEO 12-lll3-IB MOD": 6EOVENG27135 APP', DB 12-04-18 85 AS BUil T-ADDEO LINE NUMBERS 2-RC-94 & 2-2RC-94. PER ORR PI-l'l-079 OWN: JEK 4--9-19 CHK' = ERN 4-10-19 M D"1 6DC00021909 APP' = DB 4-tl-19 Cl - SAFETY-RELATED; ISi CLASS 1 C2 - SAFETY-RELATED; ISI CLASS 2 C3 - SAFETY-RELATED; ISi CLASS 3 SR - SAFETY-RELATED FLUID BOUNDARY; NON-CODE CLASS NSR - NON-SAFETY-RELATED IA,IB,IC,l!A,IIB & III DENOTES PIPING QA TYPES.

NOTES,

1. 3/4' PIPE BY3/4" TUBE INSERT REO'D.

12wfu-21 2-T58 {3/4-2WL-531 l2WL 27 7rJ {2- ~WL -9B> 1--~-./. / ~ 3/4"X1/2" 1 PEN SIGHT I DRAIN 2.LOCATE CHECK VALVE IN A HORIZ.RUN OF P{PING NEAR THE RCDT.

3. LOCATE CONN.AS CLOSE TO DRAIN TANK AS POSS{BLE 2WL-31-22

\\_{1-2WL-45) l '/\\ ' D 1ll"s 2 C5B f {TEM,WOAPRB _/ REACTOR COOLANT ~ DRAIN TANK PUMPS 3/4 X420 ((( {/3) {3/4-2WL-5]) 2-T58 ,,.........-(0 PATH TRANSFER UN{T 2-91668 3-X42D ,. ~., y4" 1 r FL.EL. 697'-0" I I I t TD CONTAINMENT SUMP 'A' FOR CONT.SEE NF-39248 4 *.J.,__ DENOTES CATEGORY { T VENTILATION ZONE

5. NUMBERS IN PARENTHESIS DENOTE PS & E LINE NUMBERS.

6. {!((131 DENOTES E U{P QA TYPE/

DESIGN CLASS

7. ALL PIPING QA TYPE III UNLESS OTHER W{SE NOTED OUTSIDE REACTOR_, *-

INSIDE REACTOR_, ./3/4,' TUB{NG DRAIN /{3/8-2WL-56)

8. "W" DENOTES FURNISHED BY WESTING-HOUSE CORP.

7 CONTA{NMENT CONTAINMENT

9.

FOR VALVE POSITIONS SEE OPS MANUAL C PROCEDURE CHECKLIST. / SUMP C L_~

10.

FOR SYMBOLS SEE XH-1-105, NF-39214.

11. C2 BOUNDARIES END AT CNTMT PENT.

THIS WESTINGHOUSE DIAGRAM REPLACES DWG.NO. 110E067 SH.1 REV.11 8 9 REFERENCE DRAWINGS

1. LEGEND {))0El51{X-H{AW-l-!05)

2. LINE LIST (206C928HX-HIAW 786) 3.PHYS{CAL NF-39328-2, NF-39325-2

& NF-39309-2 10 REF NF-38398-2 {U-11 NF-38398-8 {U-21. Thli m.., f documem Ii a 1001 to ""5&1:employeeo In !he perlarmance o1111elr Jd:13. Yoor P"""'nsl salety I* plG'llded !er t,y LJSllg smaty prar!lll9B, proo,,,tlu... BM "'1Llpm9nl!IB <IOSl!IIM<I In sal"'V training prngr:arn*. manuats an~ SPAA'I. DWN FJH DAlE 09-12-\\4 81c:tllRCNITNO. 8630 ]&2 M430 9010 CHECl<ED PROJECTNO. EC-21790 REV.! APP' il,CERT WASTE DISPOSAL SYSTEM FLOW DIAGRAM Fl.ME NORTHERN STATES POWER COMPANY 11-*- PRAIRIE ISLAND NUCLEAR GENERATING PLANT RED WING, MINNESOTA SCALE NTS REV 85 X-HIAW-1-123 841210 XH-1-123, G" j NSP GENERATION CNJ j 12 B C D E F H FIGURE 9.1-1 REV. 37 CAD FILE: U09101.DGN N It) 0 0 0 0 0 0 ~ 0 co

A B C D E F G H 1 !3/4AC HCA[;, VEN? TO /. TM []PAIN 4" 4" 4" 4" 4" I 4" 4" 4" l.._ TO RC DR TK PUr.f>S X-HIAW-1-123 { 1l [2.i t -~ ~ ! 4-WL-367----,, 2 1N':l1DE CON.TA.INMEt,l\\ VE"~~E\\.. UNIT*l 4** f"l'l COll. UNtT r-- M~N!PUL....._"'T~ ( RA.NE AAILS J.!TI _ J4 "" ~ loeo1 ++ ~ ~ 4" WMOV-1 r:, '-( SPOOL REMOVED I---- CAPPED It ABANDONED DRAIN (I. PRESSURE TEST 1 I 2 3 OUT51DE CONT~Ni\\'IE.Ni VE'_SSE.L. RESIN DISPOSAL BLOG. SUMP 'B" I 3 I 4 =3/4'... -. F~01") $[fl,j_ i1--Ji\\TE.R 1-:; 1 *.. 1c:: '\\. H1P.w-1-3~ \\. ~" F ROl"'I NO\\IAE.RA>t:.D DAA!N FIL-,.i:::~ NF -2,4'2.--t'? 4 \\; 5 I 5 I 6 1 r 7 8 9 OVTSID!t CONT,A.1Nt1~Nr V{SS'!:; 1 1 159 DRNSA-3 THl5DWG,. -*------ !~2"' 125C:.DRN SC.-3,Hl5DWq. - ~-..._=-__ _. FROM LEAK. 0ETECT10N S.Et. DWG NF -.39.!.l8-I NE.W ~fJE.L. P-L., EL. 73a*. 7 ** ~ ~** FROM LEAK. Of.T!.CT!ON ------ SE.E OWCii. NF="-393.! I 4** 4** ") -- '---7'.,. ---1/2---- ti) F_PlPE C.HA.$E. FL. E.L. TZf.._,.., _L_ 2" FROM MIXED BED DEMIN. X-HIAW-1001-5* Z"FRO"' OESORATING I \\ ",UB'NC CROM o ALVE 2VC-38-4 2" FROM SEAL WATER w HIAW-1001-5 HT, EXCH. X-HIAW71001-5 ~ 2" F"ROM CATION BED OEMIN X-HIAW-1007-5 ~ ~ ~ I ~ _ i} *WL* 3<oS ~.,,. ~~ ME:.l.i..Fl t:.L 115'-o:z____ z** 2N o* 2" FROM EVAPOR. COND - 2" FROM SPENT FUEL PIT DEi.iN. X-HIAW-1-29 -~ ~~ f DEMIN. *11 S. 21 X-HIAW-1-40 nWL-47-1 4" 4" 4" 4" 4" 4" 4" ~"" riWL-45-2 (1) m ~1) (JJ (1) (7) I)~- -/ - - JU \\ f-2" FROM RESIN DISPOSAL SUMP "8" THIS DWG. AT LDC. H-3 10 11 12 REVISIONS ~ AS BUil T-A fN5 t DE CONIA.!NMt.N T ve:,,_-s~ REVISEO UNE NUMBERS l-WL-18 TO 1-WL-12. 3-WL-83 TO 3-WL-85 & LOCATION OF 3-WL-544. ADDEO LN NOS,3-WL-41114 & 3-2WL-404.SAFETY CLASS FLAGS AT PENET 26 UNIT 1 & UNIT 2. SAFETY CLASS LEGEND & NOTES & IB TO ORIGINAL LEGENO, UNIT-2 Fl\\t-.1 COIL \\JNrT REACTOR HEAfl VENT TO An.I DRAIN REFUE ,NC CAAAL O.,AIN - ~1r 04NS15 PER ORR Pl-10-145 OWN: JEK 9-17-10 CHK'D: DB 9-20-10 M00"1 EC-15902 APP' : CMR 9-21-10 ~ AS BUILT-CHANGED LEVEL ALARMS FROM 16881 TO 16880 AND FROM 16878 TO 16879 AT COORDINATES E2 ANO E3, PER ORR PI-11-120 OWN: KJF 7-1-ll CHK'D1 SES 7-12-11 MOO": EC-1611145 APP' : CMR 7-13-ll l.§.!j AS BUil T-REV' LEVEL INDICATOR lU-1125 TO READ lLl-725 AT F-1 LDC. PER ORR PI-11-21115 OWN: DB 11-3-11 CHK'D: TJT 11-7-11 MOO": EC-18805 APP' : CMR 11-14-11 ~ AS BUILT-RELOCATED DRNS WL-36-57, WL-36-58, 2WL-36-57 &. 2WL-36-58 ON RHR SUMP DISCHARGE LINES. PER ORR PI-12-233 OWN: JEK 12-5-12 CHK'D: AP 12-7-12 MO "* EC-20808 APP'O: CMR 12-10-12 l§] AS BUILT-REV'D VLV NO WL-38-54 TO READ WL-36-54 a LOCATION E-2. PER ORR PI-15-053 OWN: DB 4-21-15 CHK'D: RLM 4-21-15 MO "= EC-25565 APP'O: KJW 4-21-15 ~ AS BUILT-VALVE NO'S FOR 11 ANNULUS SUMP PUMP & 11 ANNULUS BACK-UP SUMP PUMP WERE FLIPPED.CORRECTEO LAYOUT 4" 4" 4

• l4" 4., PER AS-BUILT.

PER ORR Pl-19-271 OWN: LAS 12-3-19 CHK'D1 RM 12-3-19 M00":600C00027634 APP' : OB 12-3-19 ~ AS BUil T-REPLACED 121 AUX BLOG SUMP PUMP MOTOR 291-4 &. f--- B C D 121 AUX BLDG BACK-UP SUMP~ PUMP MOTOR 191-45. 2"><11/4" ~ RED'S REMOVED TO MATCH NEW MOTORS DISCHARGE. PER ORR PI-21-054 OWN: LAB lEl-16-21 CHK'D: AMS 10-19-21 LA A 4 " " 4" ~" 4" MOO": 601000003292 16894........ ~~~Li / APP' : OB 10-20-21 LA PUMP HI LEVEL _,, l/ 16810

• .q CONT, 4-2WL-48:7

--FROl,I RC DRAIN TANK PUl,IP SEE X-HIAW-1-123 4-21,/L-75 1 E ~ AJINULUS SUM LA BACK-UP -~c::::----:::::=t--11~n--TO RC DRAIN TANK PUt,1> (11[/3! j 16892.. q PUMP Plf,F' SEE X-HIAW-1-12~ CONT,_4 I ~6L:91 '--1 2w~\\~ ,.---- -f!:':- -{l-J--t.1.. .rouT..... 6 t 7 I 8 I 9 I LEVEL 10 l COPEN SIGHT

~~~~.. EL.

I" J J DRAIN P~P ....o __ ") i--t~ ___ y:~u m !~1(".,- CONT. BACK-UP .... ~*~*£---~ r PUMP r-- CONT. 4* ,-4*2WL*72 ~ ,.,. t-,-" ::,-4-2WL*78 r./-" .a :- ~ ~ ~ SPOOL REMl::NED -

J:

~1-2WL-14 l.,---4*2WL-71 ,...--4-2WL-75 ~ CAPPED &. )~ rt ABANDONED 4,* ~ A LEYf;L_ 47i;i16 0304 STARTS PUMP ~ SD-3-2 1 LEGEND F CX] '<I-N CJ' (Y) J_ z ~ H NF-39248 I NF-39248, G" j NSP GENERATION CNJ j 12 FIGURE 9.1-2 REV. 37 CAD FILE: U09102,DGN N It) 0 0 0 0 0 0 ~ 0 co

A B C D E F G H 1 FROM LALiNORY ---'2'-"--, SERVICE

• I SJNI(

FILTER BARREL _j FLO()R DR.I\\Jo\\J wu.-,1 '3/'f*WL-~11 !Well-6il fi 2 TO SC,,8.HOLD UP TA NKJ.1' 11 TO SG.8 HOLD tl P TA MK#j 2 1 FOR CONT, SEE. D W6. NF-8874121 (0-ll) I FO O NF-887 0 10-101 2 3 2" I 3 I 4 VENT ALT. DISCH. TO LAND-LOCKED DRAINAGE CONT. ON NF-39250 4 I 5 6 2LA-l4*8-ll2L1'.-14-7 2L.:H7-ll 5,G.B. 110Ml'TOR iA.NK

• 21

5. G.E,.

HOLi~- U~ TANK I WL-52-4 -,----~ fu,. "-.--- I""' IWL-52-3 ,3, -WL-IOB - ~ ~ I I I'"* -. I L-c,::~ 1..1~::, I L. J TU~lNt BLOC,, SUMP UNIT -itJ 1 r 7 TO NO. II ;.j, 12 5,6. B. HOLO-UP TA NK CONT~OL

80-12-9 SJ-17-4 TO SUB MDN (TCR TANKS

• u & *21. SEE owe.

NF*88741i! !E*3! "W"DENOTES F"URN15HED B Y WESTl>JGHOUSE <:ORF'. AS DESIGNATED 01-J FLOW DIAG~M X-I-\\IAW 123' t

• OENOTES LIMITS OF Q,A.TYPeS.

IA I le,, IC,,TIB'ic1ll DcNDTE5 TH!" PIPING, Q.A.TYPES Q oeNOTES CONT>-INMENT l'EHE.TR1'T\\ON NUMSEP. CAT, l f DENOTES CATEGOR'w' l VE:NTlLAT ION ZONE (:Dr/3J DENOTES EQUIPMENT Q.A,/ DESIGN C.L1'SS P - O E:NO""T 'E. '$ PUR'=\\E. C.Ot.JN, V - DE.NOTES VEl'JT CON.N. C.- DE.1'.IOTE& OR,6,,,,\\N CONN. ALL P 1P1w6 i"O BE QA,'/PE: III \\JNLE:S5 OIHE:R..W\\C:,E NOi'ED 5 I 6 t 7 8 9 NORTH I 8 I 9 I 10 INTERLOC~ LOGIC 11 FROM NON-t1.E'RP,,TEO - ORJ\\IN 5"'{STEM FOR C.ONTl... VAT\\ON SEE. DWG NF-3,q21.t-S 12 REVISIONS ~ A Cj, 8WIL""'\\"- IU';;:iT,1~L LE D tJ~W f:"T - r0~"-1 f' l O'-"" TQ'P.u S M\\ I IE.tl PER. C~~ Pt-.,z.. 111 W I.J. f'~ ! ~ j /,i ! -:;'j,? c '"' k *.. JI.IM ~ - 5'- ~2 MCD.e.' ~ -:'J 1. 1 '22. 0 'L M E D. GG7 _j/;6) ~ AS BUJLT-REV'D, DWG. CONT, TO READ NF*JCJ216* 2 PER ORR Pl 123 OWN: DB CHK'D, PAS B-31-'lS MOO**~ FlLME01.,.6.-,5 ~ AS &JILT* REV'O OWG. TO SHOW STRAINER J:;S-li!'71, ?ER [)RR PJ-qq.13 OWN: BMS J-25. qq CHK'D1 PAS 4/6/')9 MOO*: "reTOOI FILMED fqq ~ AS BUil T - ADDEO HOSE STATJCJ,1 VALVE Sl AS SHOWN. PER DRR Pl-11.10-185 WN1 MPP 10/26/00 CHK'D1 CMR ll-8-00 MOO*: q7WL0I FILMED 1\\/00 ~ AS BUIL T-l"IDDED STD CONTROL Vl"ILVE SVM80L FOR C'r'-31256 PER OAR PHHl-185 OWN: VLS 03/21/05 CHK'D1 Ct-IA 03/28/05 MOO*:,,...._ FILMED 05105 ~ AS BUILT-l"IDDEO CONHNUATION llWU REF. NO. PER EC*l4 <172. WN: Ll'IB J leJ CHK'D: JMC 4*2'H0 AS Bu!LT-CORRECTED LOCATI~ OF CATEQORY, I VENT ZOIIIE. PER ORR Pl-0'H05 OWN, LAB 3-12-10 CHl<'01 JMC 4*2"H0 M00*1 EC-11687 f"IPP'O: CMR 4*2Ci:*10 ~ AS BUILT-AOOED ROOT VALVES WL-165-63 l 64 a LOCATION C-8. PER OAR Pl-12*2l5 OWN, [18 Ll-13-12 CHK'D1 AP 11-1-4-12 MOO*: EC-20672 l"IPP'O: CMR 11-15*12 lZ!!J tiS 8UIL T-REMOVE STRAINER, Ctif' BOTH Et>OS WITH CAP ANO BLANI( FLN.IGE. Tll"'"l'/- *-1D-~ ln ""'~lll-jm,. Y<o--_,- p,awka!l,r .... LMICl~pc-,pr,:,codu.vnloq.....,cM-tl~~-,.,.,_andSPM'1. DR.Aw1Nec. No, lMN sAB ID<<TE s-2a-q5 ss30 I I 100 L__J 1 I N~-40~~1 ~ t-lF*4075 I ~~~a~::::'.::'.':::'.::'.'.'.~==;~i====+/-:;=:+/-:::,:=t:~1:::~j~~*~o*~*~tt::'12~12j F012.UN\\T~l4'2..~ (ftllp I 1 1

1~14 1 ~1a.1e ACCOUN"T NO.

40-50-1-84 (l.NIT

• ll 41-50-2-8-1 (UNIT *2) li:H59-l -6'J (I.NIT *JJ 41-sq-1-aq <UNIT *IJ

'111-5'!*2-69 CUNIT

• 21 10 N'll't>,,r;srr.

FLOW DIAGRAM LIQUID WASTE DISPOSAL - STEAM GEN. BLOWOOWN SYSTEM - UNITS 1 AND 2 NORTHERN STATES POWER COMP.-.NY fJ,11DM"""W -.., NONE I ~ 78 PRAIRJE ISLAND NUCLEAR GENERATING PLANT NF-39249 RfOWlr<<l MINIE:SOT/\\ 'UtUSSTT(IE.IUU 1USISTDATESUHI ,unnnOEs.10NF I L,nssnn I, HUSERNAl£U I 12 A B C D E F (J' '<j-N (J' C') J z H FIGURE 9.1-3 REV. 35 CAD FILE: U09103.DGN 'I"' (f) (f) 'I"' 0 0 0 0 0 (f) 0 U)

A B C D E F G H 1 12 SG 2 INSIDE SHIELD WALL INSIDE CNTMT VESSEL 3 OUTSIDE SHIELD WALL OUTSIDE CNTMT VESSEL cs 43027 03 ' t- - ---C CONT 4 5 CONTROL CV-39087 CV-31616 6 CONTROL CONTROL 7 8 9 LEAK DETECTION SYS MON UNIT [28600] 10 11 FROM RAO MNTR RE-18 NF-39249 G-B 12 REVISIONS 77 AS BUILT REDRAWN PER SYSTEM WALKDOWN,INCORPORATED SAFETY CLASS DESIGNATIONS, 04NS15 SEE NOTE 10--._ GRPH DSPL 58350 y

r 8' AUX BLDG STD PIPE TO DISCH CNL DISCH 1-------'-----------,Q- '--------~--~==---~

PER ORR PHJB-097 OWN: MAW 6-12-06 CHK'D: JEK 9-1Hl9 2-SB-2 BD-1-1 ~ II SG 2-SB-2 I SM-13-4 ~ BD-\\-2 I C2 NSR 18 I II L._ ___ _J I PO 48121 CV 31415 SV-33607 V i CV 31414 NF-3924 7 G-12 SV-33606 BD-6-1 ATM I 27-1 '- "( CONT ( SV-37616 ) 6-5B-7 6-SB-39 A 470tt 0605 HIGH I ~LEVEL L _ 5.§1~ 12 1' t TO STM TRAP "25 NF-39233 F-7 CONT CV-31519 CV-31609 A 4 7011 0605 I ~ SB-20-1 _ l.. _ ~8_11~ LOW 22 LEVEL X, cNT 1ss-1s-2~ V ~ lrn-,1-3 I f-H----"6-_,,5,,_B-_e:3Be__-=-- 1-----1 f- __ TO FWH VNT TO ATMOS NF-39224 t MAIN CDSR IA NF-39233 E-7 SB-20-2 V ~ rss:f8] \\ SB-15-8 3/4" "83" 21/2-SB-48 C-3 STRAINER TRAP TO DRAIN CONT VENT I TO FLOOR

==~ 21/2-SB-58 =-= ~--"-'"-'"-'"'----- f----1-----, CONT TS 17710 CNL H[ TEMP 6' PRDC PIPE 10' CNTMT PIPE WITH LK ET GRPH OSPL 58350 2-5B-5121 FROM "21 RAD MNTR NF-39250 F-11 T 3-SB-15 LC-26856 21/2-SB-50 ~ 'f' SB-12-4 OPS 17667 121 SGB RAD MNTR FLTR 21/2-SB-51 lss-b-51 4-5B-15 3-SB-15 REVIEWED: WJI 9-11-09 ~ MOD11: EC-13379 u FILMED: 10-09 ADDED STRA[NER ANO TRAP TO DRAIN AT LOCATION 8-7. PER ORR PI-09-163 OWN: KJF 5-5-10 CHK'D: JBS 10-13-10 MOD": EC-14472 APP' : CMR 10-18-10 79 AS BUILT-ADDED VALVE SB-15-9 TO SB CHEMISTRY SAMPLE LINE l-SB-24. PER ORR PI-12-110 WN1 LAB 5-22-12 CHK'D1 AP 5-25-12 MOD*: EC-17061 APP' : CMR 5-29-12 80 AS BUil T-REV' PIPE ROUTE TO/FROM 12 SGS HX SWITCHING 16' SEE NOTE l0------......... TD HOT SMPL RM (SM-36) NF-3923B A-5 I cs 7 ffi m ~ SV MANUAL LN TO SHELL INLET/OUTLET & 21/2",4' TO TUBE INLET/ OUTLET.RELOC VENT/ORN TO TUBE SIDE. I B0-\\-3 f-d, '{' 2-5B-1 I 2-SB-1 ~ B0-1-4 I CONT I I ~ : ~--: I I I I I I I ~ ~ I r --ScNT I I I I ~ ~ ~ I /2;~~4\\ z 17, 7 ~ L 43i'l27 01 1-SB-51

l D

!SB-\\4-1! f-3/4,,_-Se,B'---"5--1><1-........ NF-3924 7 SB-3-HZI G-12 5GB HX (I[J/31 SV-37502 21/2-SB-53 A/S 3/4-SB-46 lsB-15-5r w 0 2-WL-62 NF-39220 D-10 CONT 0 ~ 0 SV-37507 SB-15-9 CV / 31523 \\ -j SB-26-4 I \\ BY-PASSrcV=A~LicVE~~D-'7_,,,I-CONT I sB-13-3 r -j SB-32-1 I w 0 0 \\ LC-26856 ..--ls-Cf--------~r-CON; & CONT'-'=~~ 2-SB-55 ,--<c;--- - - NF-39249 - G-1 2' NOTE 7 F NOTE 7 PER ORR PI-13-108 OWN: DB 7-23-13 CHK'O: AP 7-29-13 MOD*, EC-21898 APP' : CMR 7-30-13 81 AS BUil T-REV' ANNUNClATORS 53100 FROM 033 TO 0105, ANO FROM 021 TO 0205. PER ORR PI-14-192 OWN: MEA 1-6-15 CHK'D1 RM 1-7-15 N ~ 0 2-SB-3 lt1]; Ulr,~!"""UI ~."i" / 2-SB - (;' ~936 AIR VOLUME \\ CHAMBER ,Pr 1-.: MNL OADIN PNL UNIT I CON IA !B0-13-13f-ct' T3/4* 3-WL-** r SGB SMPLPNL SEE XH-248-1-1 LOC. G-2 MOD*: EC-24452 APP' : CMR 1-7-15 82 AS BUil T- ,l 12 SGB HUT a, ~ ill ~ ~ ~ '*c2~NS~ 18 III V lwL-75-Jr s IB 10r-- 'j ( SV-37525~ CV 31525 c~: J 10,000 G*L (I[J/3) II SGS HUT 10,000 GAL (111/3) AOOE VALVE SB-28-4 ANO 3"xl' REDUCER. ~ ~ SM-13-1 I ~ 'I s~.~-~3-~B~r* 'I ~SCCB_-c,cc_1C7r 320~0\\ I SB-34-1""" --jWL-91-11 A/S POS 1 sM-13-2 r$ I TO HOT SMPL RM (SM-351 NF-39238 A-5 ( SV-37539 l w D AIR VOLUME CHAMBER PC ~ MNL 26140 '--~,,--,,-~~,,--,,----< OA IN 5 PNL A/S POS A/S UNIT 2 CON 2A 5 lzwL-75-4f--- 12wL-75-2 BY-PASS .~* SV MANUAL { SV-37340 ) i VAL VE _J 1/2* 1/2" ~ ,'---1!--,----'---=2~-2,cWe,L~--"3~95~--{:'f']----- c!c: ~ 2WL 31 /2;i ---~ PI V CV l2WL-83-1h 11937 171 =~~~ 31840 l2wL-93_1 I i.l

-jwL-36-231 I 

~3/4-WL-307 12wlL-9,0-3I 2-WL-42 NF-39249lA f-M'-J ~ 3/4-WL-306 G-7 CV SAMPLE TD 3/4I' lzwL-,75-11 1/2" lwL-36-481 3l603 ~=-- w / 4-2WL -395 --- l-- _ _,2c:-!!.WLcc-:,4ce2_--ll_----7 2-WL-54 V n s' s ~ J 3 ~ 4-WL-395 ~ s TO COLO CHEM LAB IWL-75-zr 1/2" 1/2" ~ 2-WL-395 SV MANUAL BY-PASS VALVE _J 'r 'i' II 2 SGB ION IW~L~-,=o~-4~r EXGR FLTR r-,.. (]II/3) Pl 1766B 1 wL-70-3r c-",.'-1.,.._,a - I

~-1/2I

3/4-WL-50 3 1 3/4' f~ --jWL-36-211 ~ z IWL-85-51 lwL I vi:: \\J ~ _.., 3-WL-394 --'----..-;--.,j-;J;i I IWL-85-4 I 3-WL-3931 F II 7 ~ ~ J 3 IBD-13-271 lwL-38-341 IWL-38-32l..._\\.j,.I IWL-38-331 ,,iB0-13-261 CONT Li2'-"~== CONT 4,1/ I~ 'f-~-61<i'~~~=(ci,:S7ia,;;-, ry [ SV-37605 J,- _, ~SV-37606) r ~ 1 l:J, r ~ ( SV-37528 ) s i cv:,:< cv s' 3/4* II 3/4' ! ~"'~,, ~=,.> ~ IWL-94-11~ 31605 31606 ....1 lwL-165-65f- -w /YI ~ ~I 3 SGB ION ID W/ ~Ii ~ ~ 1/2' [- EXCH STRNR

J1/2' ~

]:---J:k;'.}---J:'<f----,~l~-711,g-,~

• t

  1e-

  ~.ll~==:1

..i -jwL-36-501 lwL-JS-t7I 3 r'"'-3/4-WL-403 ~ V[ 3/4-2WL-400 I l2WL-9t-t I s --~- <IIIIJJ ~ coNT~ IB-14-111 ls-t 4 - 12 I l2wL-94-tl / OPS II IBD-13-17 \\J./' 3/4-WL-52 L!J IWL-36-451 CONT c,,.,, 'cNT D 17894 v i:::ctil,._-"-""--"--1 o ~~1'--~-------_:_ --,'t~-~Tr_:*v:_'__:':_ ___.:,.-_____ -,---';}r--::==::---E---=2"-W"Lcc-:,5e,2_--I----(;---;:------'--- _____ 1 7 21/2-2WL-395 --'--=::-::-'--1---'!:-1"1c.::s--__':)-_I'~ ~ C. -~ M @- ( I 3-WL-66

i w

~

f -jWL-36-181 NOTE 7 C:O~T

~ ....1 7

t:'

,.,_i., ~ i:si TDRAOMNTR I II ~ RESIN FILL NF-39249 V IWL-36-20f.-t 1 ~3/4-WL-401 SGB MNTR TNK 10,000 GAL (111/3) g 6 ""\\J7 ,l WL 36 49VJI N C 1/2' ~ 3/4' ~ WD,S DISCH l:L-36-19~~~ @-_1_ WL-165-50 ..__+/-:

-;=-1 B-20-1 I G-9

~ 0 ~ ~3-WL-56 s A I B0-114~L _____ -i BD-18-3 I t1/2-WL-6] /41;~7\\ 3/4 I B0-16-2 I-T ..-.2-WL-1B5 a I r-.J:-- 1-wL-62 ~ -3

---

js-iJ-Jil I B-13-5 I I I (11 ~ :11-<--i-o>------'2'--_,,W,cL-_,6,,_l __ __J" 4--J-WL-185 0

iwL-92-3 r~ >-__,J ~ v 12wL-36-211 ~ ~ = J_ -'+' "' I IB IBI -:'-1, IBD-13-19 2-WL-53 11 SGS ION EXGR Ul[/3! ~ p -r',,i 2WL-36-181 ~ 2-WL-392 ~\\} f AND XH-248-1-2 LDC. F-10 ,:,1-------,--~-:==:---------..-E--f::-J-4-WL-45 ~... (~S~V--3~7~5~3~0 _ _,__) 1 I S-~~T 1!,4-~-2--W-L---17-6 ~°'.--"r-=c-cc--cc7 I BD-1k-[ I ~ /31~;0\\ r ... 7 B-13-11 I ~ 1530 ~

--j BD-13-10 I '<t 

=f' IBD-14-81 \\, "' ~* w '-".' ~-1/2-WL-174 l1/2-WL-44.___ 3N 7 'j' 'j' _.,.-_ ~r-, ;,, ---,;-, e---- i-:,.-t-WL-176.,- IB0-13-8 f- -,+-:;; ~r I WL-89-2 I L!J N 1-WL-175 r 3/4-WL-~Bj 1*-b-,1 _.J ~2.,. 0 ~ ls-la-2r-- ~ 1-wL-48 w 2-WL-50 £~ CONT N W O,~,._ _ _,,..f-1/2-WL -172 IWL-66-31 5GB HUT PMPS (111/3) 1/2" 1B0-13-61 /I -WL-l47 'i' '-1'/ 1'4-~~ 2-WL-390 ,H>-,, ~'

11) \\

" "w ~"'-c A~--.i14-~ao ~-WL-171_.J" I WL-66-2 I

E-

,-~~-f 0 f,.iL-~9-~ 2-WL-43 I I BD-14-3 I -j B0-13-9 I 3/4-WL-402 I WL-36-14 I PER ORR PI-16-142 OWN: JEK 5-13-16 CHK'D: PMB 5-20-16 M00"1 EC-23444 APP' : DB 5-20-16 83 AS BUil T-CORRECTED RELIEF VALVE SB-19-1 ATTACHMENT P INT FROM 16 INCH LINE TO 21/2-SB-48 AT GRID C-7. PER ORR Pl-lB-043 OWN: JEK 5-11-18 CHK'D: BNS 5-17-18 MOO": 6DOCEDI28113 APP' : DB 5-17-18 { SV-37526 ) I WL-92-2 1-~ L--/f\\-----------' Tf------------------l-------~2~-~W~L--3~9~\\-1' >------------~ ~@ I I SV-37531 ) ~ 1 t CONT lwL-36-15r ~ TD WST HUT L-~-----~-"----------------1>, . 1'1-,- - NF-39248 i.--3/4-WL-4'9 IWL-16-891 E-7 3/4-WL-49..... I I I 3 :--jWL-36-461 I 1 wL-16-ss r~ V LEGEND CLASS BREAK QA TYPE Cl - SAFETY-RELATED; ISI CLASS C2 C3 SR SAFETY-RELATED; ISI CLASS 2 SAFETY-RELATED, ISi CLASS 3 SAFETY-RELATED FLUID BOUNDARY, NON-CODE CLASS NSR - NON-SAFETY-RELATED IA,IB,IC,IIA,IIB & III DENOTES PIPING QA TYPES NOTES: STG:K ~~TPR ~ ~ ~ ~ 01: '-V 3/4 WL 181 r.i/ rS:PS 63 ...J ....1 ....1 _J I ~ 17896 m1131 ~ )I: ): ~ lwL-36-221 V N N N 21 1/2-WL-350.... ~ '1/2['-' SGEBXC[HON -J .~ 1 wL-66-1 r* ~ ~.- CONT s-; STRNR _.,1/2*

TDAOT, FLG I

IJ./ CLN ouTI 1 1 lwL-29-301 IJ./ 2-WL-55 I IBD-13-141 RESIN FILL 7 CONT ~ 9 ~ I JO NF-39236 E-B j ---12wL-36-40I 3/4-2WL-401 ____.., ~ ~I 3/4-WL-178 ,J.,, 6 lwL-36-161 ~--__[~__L-=::.'.W'.:LC:-5:'.1'-{;;t:'.]'+' _ __,;;t:'.]_L_~L--------------------'2'---"W=-L-_,5,,_1 _________ ~ FROM SGB HUT PMPS "21 & "22 NF-39250 H-5 L FOR VALVE POSITIONS SEE OPS MANUAL C PROCEDURE CHECKLIST.

2. UNLESS OTHERWISE SHOWN.CLASS BOUNDARIES STOP AT VENT AND DRAIN VALVES WITH DOWNSTREAM ITEMS (e.g., PIPE, CAPS, ETC.l CLASSED AS NON-SAFETY-RELATED.

CONT [)

i

(]II/3) "' w, 3/4"1,cl I3/4" w SYS t.. 2-WL-221 NF-39236 1-9-,~',-=-, A-7 N J ~ CONT rl IB 291 "-' I~~ !WL-36-65f-E-{ w 0 -"~ CV ~ 31843 J ~ N 2-WL -221 I BD-14-141 ( SV-376~1 I CV 31601 (' "'-i., CONT)tt \\JI~ I CONT I, ,I- /\\ 1* ~ ! B 13 ! ~-WL-399 1/21 -1'"f---,~, Sl----t-><l--"'--'-"--'-'--'----'---t--, -.-1~-t<l;f-_.-, T-D " 7"~1 \\ ,, t1/2-WL-63 2-WL-63 '1-, ,,l-"c:.,-="'°'-<:J-'--=--""---1:,;, :J-----_J CONT~,,....,' 12wL-92-3r~ SGBMNTR IB-13-331 BD-13-28 3/4-WL-182 W I :JD IZWL-36-50 I 21 3-WL-66 SGB MNTR TNK 10,000 GAL (IJ]/3) ~2-WL-186 1 so-13-32 r ~ i:..-t-WL-1B6 o --jBo-1J-1sl lwL-29-31~ ~ 2-WL-57 2-WL-233\\ _,_ ,_.1 \\J-/ '+I 2-WL -59 NF-39236 Ca<! :J-_l_--t>f<. 1 :J-._.'=-"-'_J E-B IWL-29-321 IB0-13-231 2' 1- - NF-39242 D-6 2[ SGB ION EXGR ([11/3) .'t'. r ,., "'-._, B0-13-221 1~ I B 20 I I IB0-13-241 ~ CV l SV-37532 7 31532 ORN TD (rcs"vc-;,3"7s"o"2,-~,/ ~1 t-" 1/2-WL-351 TNK PMP 12wL-36-4lf-f L __________________ - w:;T~JA CV 11601 ..,-i 2WL-66-1 I {lII/31 FLR ORN 316.2 3/4-WL-64____.., "-1-' L_:;::::::_--11 ___ JDL __________ _;2t-::,<W!cL:'-6,'.41_ _____ L _________________________________ ~~;! -~1~~~:---------::;._~*,:,;_ -;_;:;------=T-~ 3/4-WL-64 \\ I BD-13-12 I I B0-14-9 I 3/4* '1-ir-2~W~L~-3"6'-"5"~ lzwL-36-42r ~ 3/4u 0 0 1 2 3 4 5 6 7 REFERENCE DWGS NF-39216 CL SYSTEM FLOW DIA. UNIT I NF-39220 - CO SYSTEM FLOW DIA. UNIT I NF-39224 - BL SYSTEM FLOW DIA. UNIT I NF-39233 - TO SYSTEM FLOW DIA. UNIT I NF-39236 - WS SYSTEM FLOW DIA, UNIT 1 & 2 8 9 NF-39238 - SM SYSTEM FLOW DIA. UNIT 1 & 2 NF-39242 - RM SYSTEM FLOW OJA. UNIT I & 2 NF-39247 - CG SYSTEM FLOW DIA. UNIT l & 2 NF-39248 - MO SYSTEM FLOW DIA. UNIT 1 & 2 NF-39249 - WL SYSTEM FLOW DIA. UNIT 1 & 2 NF-39250 - SB SYSTEM FLOW DIA. UNIT l & 2 10 DWN MAW DAlE 6-12-06

3. +- DENOTES CATEGORY I VENTILATION ZONE 4,

FOR SYMBOLS SEE XH-1-105, NF-39214. 5, 1/1 DENOTES EQUIPMENT QA TYPE/ DESIGN CLASS.

6. P-DENOTES PURGE CONN.

7. FOR LEVEL CONTROL & ALARM PIPING SEE NF-39249 (A-61

8. S-DENOTES SAMPLE CONN.

9, 0 DENOTES CONTAINMENT PEN NUMBER

10. SHELL SIDE C2 TUBE SIDE Cl.

11.

ALL PIPING TD BE QA TYPE III UNLESS OTHERWISE NOTED. Thli m.., f documem Ii a 1001 to ""5&1:employeeo In !he perlarmance o!lhelr Jd:13. Yoor P"""'""' salety I* plG'llded !er t,y LJSllg smaty prar!lll9B,,,,,,.,,.,iu... BM "'1Llpm9nl!IB _,,,.IM<I In sal"'V training prngr:arn*. manual!! an~ SPAA'I. 81c:tllRCNITNO. 8630 750 1&2 440~ 4212 '"~~-"-------t===-""'=~==:::J=::,:=l:::::;:::::t::::,:::J::::,=t:'E:t~ecl:~E::j PROJECT NO APP' il,CERT FLOW DIAGRAM STEAM GENERATOR BLOWDOWN SYSTEM ,w,"----.an=,.;,c/=""""""""°',----'U"-N'-'-1-'-T S=rl~&"-::::2:':::--_-,----,,.,-------, NORTHERNSTATESPO\\rVERCOMPANY SCALE NONE REV 83 11-*- PRAIRIE ISLAND NUCLEAR GENERATING PLANT RED WING, MINNESOTA $$USERNAWE$$ $$$$$$5 YT I t.£ $$$$$.$$$$$5 YDA TE$$$$$$ $$$$$$$$$DES !CNF IL$$$$$$$$$ NF-88740 NF-8B740, G" INSRP rLIIERIJ/OJI CJilj 12 A B C D E F (Sl -st-r-- OJ OJ J_ z H FIGURE 9.1-4 REV. 37 CAD FILE: U09104.DGN N an " 0 0 0 0 0 0 ~ 0 co

A B C D E F G H 1 UNIT 2 COMPOSITE SAMPLER SEE TECH MANUAL XH*6CJ* 8 2 3 fZWL-52'*41 GRAB

W*2111L*17 I

,-=~~--,-11-------lSAMPLE ~M-131-1 1 r I I I I I I 2WL *52*3 I- -,- - - 7 3/4' I - 7 I - 7 14;=,:J~=,J LJ LJ UNIT 2 TURBINE BLOG SMP CONN I

• H~L-551LJ 4-WL- !'1!'52 j ALT DISCH TO LC!NOLOCK ORAINACiE

--j 21<-JO-l I I 2WL + l l----- TO CL RETURN NF-3'1217*1 TO '5GB HU TNKS

• 11 & *t2... -

2..::_W..l:_-~- NF - 392-19 0- 7 r-SPOOL PC 3/4*WL-308 r -~----j.,,.f-J V I 4 RTD LOOP B 1 -rl --------, Ll~~~:-21Z-c1 2-80018 XH-lei!l -3 G-3

!<1 I

RES[DUAI.. HEAT OUT] lLOOP *A') Z-l~ -1 XH 1001-e Cl Cl-I RT LQOP'A' \\ "'T Cl~ _\\_,__.._,, z.~* 2-8001A )(H 1001-J F-11

!<1 I

l~ - DJ XH-U!liU-8 H-1 1/2,-2WL-30 1/2

• 2WL -31 MV 32232 2-B7028 5

J* ~ESIOUAL ~ HEAT CUT !LOOP"8') Cl SPRAY LINE I >*L*7* I 1/2-2WL* 26 LSE~0~01:~. \\ 9

• 2WL-2q

~ - \\ ~ '--------"1/2,:*<_2W"'Lc:*"_2<>_B ____ ---~ _/ VALVE STEM LEAK-OFF Cl CV UNI T N0,2 --1/2:*2WL* 40 [ I 2WL-6*H I 1/2*2WL* El [ \\ 1/2-2WL -0 1/2-2WL-40 1/2-2WL-40 lWL-64-8 ~ -~ I I C 1/2 - 2WL-40 1/2*2\\i!'L-421 1/2*2WL-40 1/4-2WL-*10 31228 TO RC DRN TNK PMPS .f ;i. 6 7 !2wL-~:H2I 1/2-2Wl...-40 I 1/2-2WL-35 [Ml 1- - -,, 6' - - --i XH-lli:li!ll -6 \\_C2 o-1/2-2\\il -2WL*36 ~ 2*6701A l 2wL - 6 1-10 I ~ _a~ _ I! ' -~ ~l~(z 1/2*2WL*40 1/2*2WL*39 XH-111101-B G-2 "'-'-'-;:~f=-:-=~"=:1 10' 2WL-53*13 ~ --C- - - - -i XM-1001-B Cl+ c"2 E-I PRESSURIZER RELIEF TANK INSIDE SHIELD WALL OUTSIDE SHTELO lr{Al..L xH-01~5*-ac-,-£ -= ** ** 2PC'l-31A XM-H23._ - - -- Et- ----t::l(}-------~~-----~ Ell ~ INSIDE. C tffAINt-ENT VESSEL OUTSIDE CONTA[NMENT VESSEL ATMOS °42SB-l6*JI CONT CV 3~088 12s8-10-2 1 °-11 SEE NOTE 10, 22 SG ABANDON FE 71"2 GR?M OSPL 8350 ~1* 2SM-13*3 I 2SM -t3- ~ TO HOT SMPL RM I ISM-23Sl ---- - NF -39238 A-II SEE NOTE 10-.., 21 SG I 2ss -4 ~, 258-1-3 CO"IT C:DNT (i) 25M-IJ-1 ~ 0 TO HOT SMPL AM ISM-235) NF-Jq235 A-II --j 2SB-13-2 I 21 10,000 GALS J-2WL-21 '1-2WL-2i!I SGB HUTS (![l/JJ 7 2ss-J-u I I 2S8-L -2 ~ u D 258-3-"3 u D [cs7 ~ I CONT~ -I I I I I I I 2-25B-1 1259-4-1 ~ 2S8-3-4-2 C2 NSR 1B Ill [cs:] ~ CONT I 't I I L_ I I I L @7 "oa=rH77 I DSPL 583521 ABANOON FE 271'11 I 2se-21-4.._ 2*2SB-5 C2 NSR NF-39247 F-12 12se-J -!i ~ ~ -I 2s8-21 J I z FE 27112 ~ ')' "1258-3-10 I 258-34-1 0 1B Ill I 2ss-J-a._ CV 31594 22 10,000 GALS D 2-258-16 t.lOTE: FOR LEVEL CONTROL ALARM PIP'[NG SE:E DETAIL AT RIGHT SV-37496 NF-Jq247 F-12 2-2WL*392 r.~ -L;o.. il~~--'4---------J e------~ I 2WL-J7-16 I Z-25B-35 'f j 2WL -~1-2 I 2-258-30 21 SGB FLASH TANK (111/J) 00 s '\\' m ~ ~ 2LA-2-':18 2l A-15-5 ~ tzsa-22 -1 I ~2~*~*-'l2'?:2-'j2~ Ll 2LA-1'5-6 SY MANUAL 8'1"-PilllSS VALYE 3-258 -l I ' l~2SB-28*1 3/4-ZSB-12 12S8-1&5*l I 2LA-4-1 CONT CV*3ct068 CV-3161~ ~J~-Z~S8~*-<0c--,,._I.:_ NF' - 3'}23 E-7 CONT 2T0-1* 3 H~*~-:,*_., MAIN COSR Nf-3qz34 F-B TO FWH VNT TO ATMOS NF-39225 0-3 ~-2S8-7 V ~ 12sa-15-2 r !zsB-20-1 ~ 21 SGS HX 1111/Jl CV-31S73 NF-39217-2 A-7 BD-7-6 CV 39510 SV-37510 21/2-2S8-53 D ,---f 2S8-15-3 j 0 UNIT

• 2 NF- ]~221 D-10 STEAM GE~BLOWDOWN ZLA-1 -l!i 21.A-l -loll 2LA-14-21 21.A-18-7 I ZLA-p-3 I I ZLA-117-5 I 2LA-1"
• 1'9 l2u1-1e-ej 2LA-L-4-17 I 2t.A-l8-1I I 8

9 10 11 12 REVISIONS 7 9 AS BUILT-ADD SAFETY CLASS I WL-6'4-1 j [ - C2 DESIGNATIONS FOR YALVE STEM LEAKDFF MA[N LINES. A .. l WL-65*3 'GLOBE SS (LOOP 8) (TYP) r-..... --:.a,., t-EAT OUT:} :,,1

,1

B' f- - - -l XH 31 SPROY Lll'iE SCOOP CCt.O LEO?OOP"B" s~?" / 1tJ:,0v H-1 Cl E-5 ~ PCV-43lB r IWL-64-2 I I-WL-I03 1-WL -1'°'3 I- - -,, WL-53*"1 _§" ~ XH-1-44 o-* ~ - -;::,I J!'_ - - ~*- ~ XH-1-JL a + * : G-2 Cl C2 1 1/2*WL-103-f-'L....V)=="-'---< I I I I I I I 0"4NSl5 PER DRR Pl * ""! - 23 DWN1 JEK l-18-li:I CH!C'D1 DB 2-1s-rn MOO*, EC-1-45!'.Sl APP'01 CMR 2-16-10 80 AS BUILT-REV'D LOCATION OF VENT 'IALYE 2WL 50 OOVNSTREAM OF 2WL*"46-oll I LOC 0-10. PER DRR Pl 030 DWN1 OB 2-2* 12 CHK'D1 AP 2* Z'M2 M00* 1 EC-IC!084 APP'01 CMR 2* 29-12 81 AS BUILT-AOQEO VALVE 25B-15-"I TD RTD LOOP *A* ] RC 1 1-8001-A -cl XH+Jt ~-- --t::i - ~*- 1 H-2 a +

• MY 32il65 1* 8B03B MY 32066 S8 Ct£MISTAY SAMPLE LINE B 3/4*2S8-3.

? 3' ---c,I Cl .L.H-\\-7 F-lB p I BD-12-8 ~ -WL-95 1/2-WL-93 1/2* WL

• 92 I/ -WL-91 RESIDUAL MEAT OUT J ~I

[; (LOOP A) t--l XH-1-3.1' 7£ """~ G-2 MV Cl 32 16 1*8702A REACTOR BUJLOING YAL'IE STEM b[A!C QFF I-WL-103 1-WL-Il1l3 I WL-53-121 Cl C2 1/2-wL-103 I Y.i-wL-rnt ~ I t'. XI-I-I -~ - l o-* C2 PRESSUAIZEA RELIEF TANK 'i' 1-Wl-103 2n ~ -~~-------.---, I CY JIJZJ UNJI ND I TO RC ORN TN!C PMPS XI-H-123 E-1

!<1 C--i 1*8703

~ - -c.-1 1.l!i:_ ~ XH Jl Cl~C~ E-2 PEA ORA PI 110 OWN! LAB

> 12 Ct,I(*~ AP 5*25-12 M00* 1 EC-17061 r.PP*O: CMR 6*2'1-12 82 AS BU[LT-ll:UTEO LEAK OFF LINE FOR MV-32066, LINE NOS.

1/2-WL-102, llll3, RDCR &. VL'I WL-'5J-lJ, ADDEO CAPS. PER ORR Pl-12-IC!6 D'WN; DB 10*26*12 CHK'Oi AP 10- 30-12 MOO* :EC-20<171 APP'D1 CMR llll 12 83 AS BUILT-AOOEO c.--Ps TO MV-3216"4 LEAKOFF LINE THAT WERE MI SSED ON REV 76, PER ORR Pl-12-213 0.1% JEK. ll-I2-12 CHK'Oi AP U -13*12 MOO* : EC*20'176 APP'O; CMR lHS-12 84 AS BUILT-XH-1-123 F-7 D I -i eo I REY'O PIPE ROUTE TO/FROM 22 SGS MX SWITCHING !6' LN TO SHELL INLET /OUTLET & 2~',' TO TUBE INLET/ OOTLET.AELOC VENT/DR~ TO nm: SIOE. 2LA-18-17 21 REACTOR COOLANT ORMN FILTER llll/3) I BD-l2-t0 I 3*2WL-10C I 80-11~2 I 1-2WL*65 2\\i/L J 0 V 12wL-31-45r --l2W-L *Jl-2 1 -j 2WL-27-2 I PER ORR Pl-13-108 OWN: OB 7-23*13 CHK'D1 AP' 7-29-13 M00*1 EC-218~8 i'lfP*O, CMR 7*30*13 85 flS 8UILT-f-----~3'-*,c2Wc,L'-*-"10c,C'------RW~T_ ~- - - XH-111!101*7 RfMOV~O STEilllM GEl'i BLOWOOWN ORA[N LINES 1-25B-1 l 1-25B-2 & ASSOC YALYES 2SB-2*1 8,; zse-2-2. PER ORR Pl-1-4-036 V ~ I 2~,~.~-,~*~-J~f-- I j 258-12*1 I 116' ' ~-39221 0-10 CONT I 2SB-l2*2 I ~ 2~*2S8-4B Ill l(l j 25B-IS-6 f-.: 0 2*2SB-t6 ZLA*l4*22 --j 2S1-17--4 j 2*2S1*98 CONT FROM REYERSE OSMOSJS CV 3'=!512 SV-375!2 CONT 25B-17-l CONT t1/2* 1';1£;<, J:'::';::ce.""~:rL~ A'Pf7T..t.,:J""-2ee*ee*""-1~0r l2SB- !2-JI 5GB " TRANSFER 21 SGB RAO M NlTOR ~ PUMP (1] 1/3)

1.

j 25B-15-n-- NOTES: FOR VALVE PDSlTIONS SEE OPS MANUAL C PROCEOURE CHECKL[S T, MH-IT TEMP

2. UNLESS OTHERW[SE SHOWN.CLASS BOUNOAR! ES STOP AT VENT ANO DRAIN VALVES WITH DOWNSTREAM ITEMS lo.g.* PIPE, CAPS, ETC.}

CLASSEO AS NN - SAFETY - RE LATEO. 3, +- DENOTES CATEGORY [ YENTJLAT!ON ZONE B-8 lY 2SB-10*6 ORPH OSPL 58350 2-2S8*15 z m N DWN1 LAB 2-5-H CHK'Di TLL 2-5-1'4 MOO*, EC-16807 APP'O; CMR 2-5-1 86 AS 8UIL T-ADDEO VAL.VE 2S8*28-4 AND 3°><1' REDUCER, PER ORR Pl-16-1-42 WN1 JEK 5-13-16, CHK'D, PMB '!i-2"-16 MOO*, EC-234 4 I t-'.... --trr---;l;,,la;2,eSB;.-~,~.-~,H- -,l2SB-28*3I CONT FROM LC - 26957 APP'D1 DB 5*2iH6 87 AS BUILT-REMOVE STRAINER, CAP 1 zss-32-l I 1 2se-1s-q I HI TEMP I ZSB-13-3 f-c ~ SV-33328 --j 2SB 2 I~ ~ CV 3!S07 -, 258-12*5 I I ' NF-88740 B-HI REFERENCE I BOTH ENOS WITH BLANK FLAMCES. coNT PER ORR Pl-12-22'3 OWN: PB B-l!!-16 CHK'D: ASA B-23-16, MOO* : EC-17185 APP'= 06 8* 2J*l6 DWGS XH-l RC SYSTEM FLOW OJA, UNIT I XH 31

• RH SYSTEM FL OW DIA. UNIT 1 XH-1 VC SYSTEM FLOW IA. UNIT I XH*l-40
• VC SYSTEM FLOW OJA. UNIT I & 2 XH*l-44
• SI SYSTEM FLOW OJA, UNIT 1 XH-1-123 - WL SYSTEM FLOW O!A. UNIT I & 2 XH-1001 RC SYS TEM FLOW DIA. UNJT 2 XH-1001*6 SI SYSTEM FLOW DIA. UNJT 2 XH-1001*7 SI SYSTEM FLOW OJA. UN[T 2 XH-1001*8 RH SYSTEM FLOW OlA, UNIT 2 NF-39217* 1
• CL SYSTEM FLOW DIA, UNIT 2 NF-39217*2
• CL STSTEM FLOW OJA. UNIT 2 NF *3922l
• CD SYSTEM FLOW OlA, UNJT 2 NF-39225 BL SYSTEM FLOW DIA. UNIT 2 NF *39234 TD SYS TEM FLOW DIA. UNIT 2 NF-39238 SM SYSTEM FLOW

!A, UNIT I & 2 NF-39247 CG SYSTEM FLOW DIA, UNIT l & 2 NF-39248 MO SYSTEM FLOW DIA, UNlT I & 2 NF-39249 WL SYSTEM FLOW DIA. UNIT l & 2 NF-88740 SB SYSTEM FLOW DIA. UNIT 1 &. 2 LEGEND C D E F l 2WL-J8-18f-m ID N /.. -j2wL-JB-1sj I lzLA-IB-'91 j 2LA-1'a-12 I j2LA

• H
• 2i!I ~

21 SGS HUT 22 see HUT 2UH-4-27 I 2LA-ls-15 I I 2LA.~1B-IB I 4, FOR SYMBOLS SEE XH*l-105. NF-39214, CLASS BREAK A TYPE Cl

• SAFETY* RELATED, [SI CLASS ISl lO N

(J" (") i1. 1 2*2WL-3o:i0 I 2WL 3 j 2*2WL*l8 ! 2wL-B9-1 I I 2WL-6S-2 f-. 0 l2WL-8ct-2 j (111/3) 2 SGB HUT PMP 1111/Jl 0 2-2WL-'3<tl 3 !2wL-J1-11H NF *J 'l2"4B - E-7 4 IZWL-38*32I 2'1tt.. *85-S 2WL-38-3J j 2wL-10-J I 2*WL*51 Pl 17669 21 SGB ION EXCR FILTER illl/31 2Wl.

• 7i!I -

5 l'E"-8B740 F-10 6 21 & 22 SGB ltJT PMP CONT SGB HOLD-UP TANKS LE\\/EL CONT & ALARM PIPING 7 j 2LA-\\8-t6 j l-1i2:i;L~A-jl!*-:12~5 LEYEL 8

5. 1/1 DENOTES EQUIPMENT A TYPE/

DESIGN CLASS,

6. ALL PIPING TO BE A TYPE II[ UNLESS OTHERWISE NOTED.

7. S-DENOTES SAMPLE CONN.

8, P-OENOTES PURGE CONN, 9, 0 DENOTES CONTAINMENT PEN NUMBER 10, SHELL SIDE C2 TUBE SIDE Cl, 9 10 AP!"CICEAT. IM'Q: 4*)6*07 C2 C3 SR SAFETY* RELATEO; ISi CLASS 2 SAFETY-RELATED; IS! CLASS 3 SAFE TY-RELATED FL U [ BOUNOARY, NON-CODE CLASS NSR

• NON-SAFETY-RELATED IA,18,IC,llA,llB & llI DENOTES PIPING DA TYPES Tllill.-.,td<n.--.i0a-1D..-~h.,_p,,,btNroo<tl'hrtt-,.l'lU~....... lo pr-.Jb" tr,,lll'.rQllif"'ll'prlOl:.,..,IIIQCedJJMlllld........ 11<1H<d>odhllftffn'l,i,g-lll&'UlllllldSFWlil.

LlOUID 8630 100 FLOW DIAGRAM WASTE DISPOSAL SGB UNITS I & 2 "1011 4212 SYSTEM NOITTHEml STATES POitEll COMPANY ee....r. NONE ir:r 87 11"""""""' PRAIRIE ISLAND NUCLEAR GENERATING PLANT NF-39250 FEl~.r.MIESOT.O. 'isUSERNAloEU SUHSS1'TIIEUSlttltH1SSYDATEHUU USHOHOES IONF l L$$$UHH NF-Jq2511l,DC" I ffe it¥f.Wiov ¢¢ I 12 z H FIGURE 9.1-5 REV. 35 CAD FILE: U09105.DGN 'I"' (W) (W) 'I"' 0 0 0 0 0 (W) 0 U)

A B C D E F G H 1 C2 NSR UNIT 111 CONTAINMENT !X-HIAW-1-123) I I

1.

~'1_"').( 1-9160A .J *,..... I I 'L',i. 1B ~ r!-, 1-91s0s III 2 i- ~ NH~C (::1'E.l'-l I X*... A...,1. 1-123 I I I I I _.J REACTOR 0 HOT 1 ----- SAMPLE ~- - SYSTEM ~/,i' (NF-39238) . OE.O~CI $M,1 ( 1-1.lAIN 1* '\\CJ HOI.DUP TA.MKS (cvCS.) 3/4-X42D WG-35-4 I s.s. 1 c.s. !3/4-WG-30! 'I I. r *---f',J-I

• ~:

I I ~ I ~ GA 4csH. 3 LOCl-7) I I I I I',. I I I I I I FROM BORJC ACID GAS STRIPPER VENT CONDENSER UNIT *1 FOR CONT. SEE WO. X-HIAW-I-405 !CONN. No. 10) 1 UNIT M2 CONTAINMENT !X-H]AW 1-123l 2 POC E, 2~ ~--._.,--* 53038 I 2WG-43-I 3 3/4-X32D . '.!J 3/4 I ! - 'NO - l52K.*.Y~, r1 ~we !>~* E:)_, 2-W -152R {2-WG-321 . '-v lwG-1s-2a IWG-8-61 3 REACTOR I-- MAKEUP WATER <NF-39242) 4 5 6 7 8 9 10 11 12 REVISIONS '"123 COMPRESSOR (2-WG-38) '..i '2'" 7 6 AS BUil T-X-HIAW-550-1 (LDC. J-4) \\ 4 1<,El_ll,J"~-----:::r-----T-----------....,.------------:===--i----------~iis~::=:==~==~~~:'iir... ~1"-~--------*

• W s~ D Ir I

'{"121 CTL TC HZ RC'"BR"' s1,KID... z O*l '-'""" WC.,,-1-3 ,-x,,o --~

• a0**

~1" r'/,G ~), I(, ""TC,-.OL O ;. -P -~.:,...Nk.. V~l-,iT 1-*~AC:,&;-i<. X-HIA.W 1-40 ( L0(.,... 3, PUT DWG ON CORRECT BORDER SO DRAWING CONTINUATION REFERENCES ON XH-550-6-1 AGREE XH-550-6-t (LDC D-2 J!I,i ("2.

• NC.r.:>e.)

(2-WG-39) -; ~ 2-X32D ""'"

• I 4

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• W(;-~.$)

I Y,,,, * 'Z

V i=. t..:i !--;2.0M 6,.::..70i=C-AY T i;;:.

PER ORR Pl-08-035 OWN: OMN 5-20-08 CHK'D: BS 6-2-08 MOD"1 EC-10792 0\\4 3/4 X32D §1 12*,1* ) lwt;-9 -* IL wc,-7*;., I',...:~ 1 (11_-W(dib -

t{*S

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• 1,.

t---<1-1-1G-3a> ( "a 27 ,--1)';:J--c~-.-' s,1.10 M"'l-'r_'_,. _ _,,,-.,t 1.0*38,**...-_,,, ~ s.s r1 "',~,~,"11-, ~-W(r35. J I l '2.X.\\ /. '- W - 1 fi ~ PNL 53800 l' _/ 1 X420 1 121 CTL TC H2 RCMBR ~Nf~ PNi]; ~0"'-106.N~A.T E '..)\\<!A.1N T.b..NK. SE..~ 0-12 T 1-1IS DW6, FILMED: 6-08 77 AS BUil T-6 PCV-1040 t-RA32RDB $-',., - WtJ -b-CR (c?'v*M>-35) l-W 0-1 S 'Z. R_-:a.!> (**WG-"'.,5) 2-W -152R-3S (2-WG-36) c.s.. s.sl - cf PCV-1027 --1 !Q] XH-550-6-1 CLOC u-~J 1-RA32RDB4 ) \\...*50* '[

• - t" (1*w6 3s)_;

3l?.7Z.. ('l-WG- ;l,BSS) - * (/ - Yt6-:l,fl}--** c.s_, 1" II. N2 PURGE VENT FROM HIGH LEVEL TANKS SEE DWG. M 110E067 SH.4 x:: 1-HA..w :sso-1 ~ ~.-- \\-WO-,'S,Q.*'3, (*-WC,-'37) ~ ' -, "121

• 121 S.S."

"'122 FrtOM ~ IGI-! LE:v'=L RECOMB. 'A" REC MB 'A" REC MB 'B" U'.:>cr> c-.. A':> DELAY OUTLET RELIEF RELIEF iA"IK. ~LIEf= rD:.; (X-HIAW-550-6) XH-550-6-1 XH-550-6-2 .,-~. 1-I 1Aw 550 - 1) T 0 /- Xf?. b NITROGEN PURGE [WG~~

RECDMB. "A' (CONN. BB) [ '

~LOC F"-:2) x-HlAW-550-6 m

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NITROGEN PURGE X-HIAW-550-6 12! LOW,_E;:Vt;.1-.. CiA'? D!:CAY "":'"- COr,.iO'E:"'4SAT E iJ~A1N 'TA.NI'-. GAS :)1:=,C.a:..Y -AN!<~ C U6;C.t_~ UC 1Q3Q \\,~/_! 53058 l:!_C \\O -..,

• ~

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,,

:;:::;;:-----:::::::+/-::..:-: -------:::::~--~-:*-

/ "'122 ' lwe,-*ai-51 11 121 ,., *124 --..... ITEM: ITEM: ITEM: QOATGD 9 'd ATGD 8 ~OATGO 7 (l))/3) 053-1"!2 <Hil3J 053-191 {]IJ/3) '-.... 053-194 (.3/4*w6-40AJ.::-1---.... _. 1 II Pfv-1039C 3/4-DA32R _\\.I) ! l~X32 ~ WG-21-9 ,.,,.-I _wG-J:-j"~~'. _\\.V_,/ 1=-x32tJ .~ --j WG-3-15 I ~. ~- ::* ,,l(,-10-~~*-j REV NOTE 8. GRID REF'S AT A-10 & 0-12 & MlSC DRAWING CONTINUATIONS. ADDED MISC EOUIP ID'S, SAFETY CLASS FLAGS TO 5C.ALE N ONE WL PIPING, LEGEND & NOTES DELETED MISC QA TYPE FLAGS. 04NS15 PER ORR Pl-10-150 OWN: JEK 9-27-10 CHK'D: DB 9-30-10 MO "= EC-15193 APP' : CMR 10-4-10 78 AS BUil T-ADDEO DWG CONTINUATION XH-1-125 LOC 0-10 AT COORDINATE B-6. PER ORR Pl-13-119 OWN, OB 8-21-13 CHK'O: CMR B-26-13 MOD": EC-22545 APP'D1 CMR 8-26-13 79 AS BUil T-ADDEO VALVE NOS. WG-8-1 THRU 10 &. WG-27-8 &. 9, PER ORR Pl-13-250 OWN: JEK 12-18-13 CHK'O: RLM 12-20-13 MOD111 EC-23132 APP', CMR 12-23-13 80 AS BUil T-UPDATE THE REFERENCE DESTINATION DRAWINGS AND DESTINATION NOMENCLATURE DRAIN HOR FROM "#1'21 R.E:cOMBlN~R ~A-- PER ORR Pl-19-086 OWN: PB 05-09-19 CHK'D: MEG 06-10-19 MOD"1 600CE I23t8l APP' : DB 06-llil-19 f--, (-2.w&- ros) 2"" 12". ~.'-.....IW6-*a~4] (-Z *w0:..-4-Z:A.) z"J ~ FR. GAS ,>---------~ DECAY TKS, C2 NSR 1B I III (X-HlAW-550-ll LEGEND CLASS BREAK QA TYPE C2 - SAFETY-RELATED; !SI CLASS 2 NSR - NON-SAFETY-RELATED IA,18,IC,IIA,IIB & III DENOTES PIPING QA TYPES.

9.

NOTES: FOR VALVE POSITIONS SEE OPS MANUAL C PROCEDURE CHECKLIST.

10. FOR SYMBOLS SEE XH-1-105, NF-39214.

REFERENCE DRAWINGS: PHYSICAL NF-39309 RCV-014 TRIPPED BY HIGH RADIATION LEVEL AT 2-RE-30, OR 2-RE-37,LOCATED IN HEADER TO THE PLANT VENT.

2. VALVE SUPPLIED WITH WASTE GAS COMPRESSOR.

3. Q WASTE GAS COMPRESSOR PIECE NUMBERS INDICATED ON NASH ENG. CO. DWG. Na. 15-0122.

4. ALL PIPING AND EQUIPMENT SHOWN IS WITHIN CATEGORY I VENTILATION ZONE.

5. c -L--,

NUMBERS IN PARENTHESIS DENOTE P.S. & E. LINE NUMBERS.

6.

PI-11728, PI-11729 AND ASSOCIATED VALVES BY OTHERS.

7. (1/1) DENOTES EQUIPMENT QA TYPE/DESIGN CLASS.

8. ALL PIPING QA CLASS III.

Thill m.., f document lo a 1001 to ""5&1:employeeo In !he perlarmance o1111elr Jd:13. Yoor P"""'nsl salety I* plG'llded !er t,y LJSllg smaty prar!lll9B, proo,,,tlu... BM "'1Llpm9nl!IB <IOSl!IIME cu~ 1 c.L~ "1../-,--,;.;;;;:;_.;..=.......... -.,i,.*..J j --""'=~--~-~----------- 1-WC-!5.~R / L (1 WG *a'l ) -,--x32~, '-----o_u_,._,._,o_E._Gr_,.._,,_o_E._c._>s_Y_T_t>.N __ 1<_c_u_e,_,_c~LE. _________ ,_1-_w_o_-,_1_1 -------------------------~ DWN DAlE aic:t1iRMfTNO, I 8630 I 100 ~;;~ 3400 ~'"""~"'-~,------t===:.,.;,=;;::==:::r=::;::::::Jt::::;::::1::::,:::r:::;:::J::::;;:::'::t;~tt::':-~ 7 8 THIS DIAGRAM REPLACES WESTINGHOUSE DWG, No. 110E067 SH. 2 REV 11 9 10 PROJECT NO APP' il,CERT Fl.ME FLOW DIAGRAM WASTE DISPOSAL SYSTEM UNJT I & 2 NORTHERN STATES POWER COMPANY 11-*- SCALE NONE REV 80 PRAIRIE ISLAND NUCLEAR GENERATING PLANT XH-1-124 RED WING, MINNESOTA XH-1-124, G" j NSP GENERATION CNJ j 12 A B C D E F H FIGURE 9.1-6 REV. 37 CAD FILE: U09105.DGN N It) 0 0 0 0 0 0 ~ 0 co

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• 122

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MlW!III'~ CTC$10CIMl'*M2U AUlCMATIC" CAS NW..Y'ZEJI IJE.H vu-EG.'t t,U/JJ X-H[A'1H-1tGG 10 REFERENCE DRAWINGS, PHT1CAL. ~-~'1-:J J. !Wl.VGD l-1.1"U ~Im 8l' Gt5 ~tlVI I & C OWff\\. Kt.olC-lNil. Z. N.J,DZII rQIII.mD r"'5 HO (DfffllL'Kl'fr l,,lrNll,.I[,u,a: lll'n.U:[l f"Nli !OHL~.

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A B C D E F G H [- 1 I NG-7-4 I 2 NG-7-36~ "T" NG-22-2 VAPORIZER JACKET NG-7-7 k,_ (( NG-54-1 TANK --RUPTURE

='.;=

DISK s*ii,--f-J::::;~=-,-----.._:-----, ' I " NG-7-11 I

• 121 PI 11932

--o LN2 CONVERTER CXH-749-20) I NG-7-181---, THERMOCOUPLE TUBE & VALVE NG-7-1 T1 NG-7-9 'l><1 Ll Ul LEVEL NG-7-8 I 1>/ I~ NG-7-li!I I r---,_ I V _L,-------,,~--~ ING-7-16;\\ ~ I I _r NG-7-15 ~ I ------+---~--, f NG-7-3 I PRESSURE BU[LO "T" REGULATORY f-------j>l(]-----,.C-~_.i._~-,,_s-{TR:--A_IN]-E-R-3------l;&'J---jjj-:::WWlJL ING-7-37~ 7 .. rrrmnr-1 NG-7-2 _J h IN,'.j-7-41I PRESSURE BUILD CDIL Fl LL 3 ING-7-3':I ~ 4 SEE NF-39246-2 I CC-71-1 ~ CC-3':1-2 n --7 I CC-40-1 1--------/' ' Vi CC-71-2 CC FOR *123 N2 COMPRESSOR n CC-39-1 1'---l'-c"c:--,:c*:--,:;-i I cc-41-2 r 7 CC-4\\-1 '1,,--, ~ "123 N2 COMPRESSOR j{ NG-7-6 I I NG-35-1 ~ iHJ-041 ~--~ ~ NG-35-2 I ~NG-7-131 ~ NG-4B-3 ~ -l 'i NG-44-2 r---

• \\.

I NG-22-11 I NG-48-4 I ./ I" X 3/4" SET Cl 91!li!l0 I 251-31-t 1-I NG-2B-4J7 620 PS[G RUPTURE DISC TO ATMOS I NG-23-1 / 'es' 17879 41 y 60 ps1 SET ~ LOCATED INSIDE CONTROL PANEL HYDROGEN HOUSE l-S[-19 1-2S1-19 TD UNIT 2 ACCUMULATOR 5 NITAOGEN

BLOG,

• ci Xe a

J m TURBINE BLDG. NG-56-3 I I' 6 1 r OUTSIDE ANNULUS 7 INSIDE ANNULUS 8 2-8820 1-IA38RES " 1554 I SI-3-4-l l- \\t-s1-19E ~ \\ 169-0B1 F l-S[-902R-19\\_ t-Sl-190 ~ lll';f~~is,~: L '{I':* UNIT., REACTOR CONTAINMENT j 1-Sl-l9C __ --? VESSEL ~ FOR ELECT. PENETRATION

3 1-251-19-----

/ Pt,~ ~G-2-< 3/4" *3/4" 117-42 r---- RELIEF VALVE-~1/2"VENT-NG-]6-6 r----...__. I 31 PRESSURE TEST FOR CONT. lr-i---- SEE NL-39776-72-1 NG-16-5 I 2S1-3-4-1 53055 rcc-c'C7+cc;\\ 1 NG 16 3 REACTOR SET D I NG-3-3 r ~ NG-Js-4 ~,._.._~.3.1--n;;"_';;'_';i ~ COOLANT "PSIG..______, ~ 91 l! 7 -,~ '\\, ;; Lll~JP VCCUMULO~,~;p 269-081 F e:;--56-10 ¥ I' I 2NG-56-3 ""'1 NG-56-2 ,NJTROGEN TURBINE BLDG. BLOG. I' r----.::.-,

• ,..c-3/-4-NG-}:.

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RA52Rei, 7q5,.J-,~~s'-,v I NG-28-1,.. i/-tXJ_) /as'."05'\\

~J;~NG--4 £1 ~ (,-'I W, : L SV-37057 3/4" --t.*r---t.-CJ---\\.':;i;.J

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f".'.j --,

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• 11 PRESSURIZER
• U REACTOR COOLANT 5 PSIG

~,,;::::=:'.!_~IRELIEF TANK (11/21 DRAIN TANK fil/2) I 251-33-1 I' I' I NG-27-l 1~~~~ \\ NG-15-13 I _.-8 NG-2-19 A REMOVABLE I NG-2-9 I I NG-2-8 I VENT\\ 1/2' ~ ~~5-TD *12 STEAM GEN. I

• 11~* 91

~ A-CCC-CC"C 7 ~ ~ ,~-+- M.S. RELIEF 1-lR. / SEE NF-39218 - *1, l.....,1" 1i'EMOVABLE 1-NG--47 97-1-NG-lr.h v-~ rcc--cc-'7---.__ NG-4lll-2 _,-,::;,;~DOLS L---i,<:1----Lj/;><f---~1'-<J-' --, NG-41H

--,----/,,

7 o---, '\\ f--H-.!_~ TD "11 STEAM GEN. I' I' 9 10 11 12 REVISIONS lZZJ AS BUil T-INSIDE OUTSl E, SEE ANNULUS l XH-1001-6 A-s, _____ UNJT "2 REACTOR CONTAINMENT h .£. _ -i VESSEL ANNULUS 3/4-2NG I 2NG-16-6 I 2NG-16-5 2NG-l6-4 ADD SAFETY CLASS FLAGS TO RC LINES TD PRT & SAFETY CLASS LEGEND, ADD VLV NOS. ZNG-28-2 & NG-28-2, 0-4NS15 / PER ORR PI-09-234 31 FOFI ELECT. PENETRATION 2NG-16-3 OWN: JEK 2-15-10 PRESSURE TEST FOR CONT. -- r--,,, 2NG-l6-2 @ SEE NL-39776-72-1 MOD*: EC-1-4551 REACTOR 1.;:11; APP'D: CMR 2-17-10 COOLANT [::.: I7RI "21 ACCUMULATORS "22 / Y::tt,; 1-,..------j,--------~,-~,~NG~-~l-,-

• " TD CONTAINMENT ~

AS BUil T-LOOP@J ........._ LOOP I 2NG-t6-I I 2NG--4--4 I A 1----1 AIR LOCKS SEE WG ADD SAFETY CLASS FLAGS A 18835 8 CV NL-39776-72--4 10 SI LINES, DWG C NTS & CI-IK'D: DB 2-16-10 ~ f<l I 2NG-2B-2 I 3900 COORDINATES & 51 LN NOS. r, cia--1-l.r,c;cc;;;;,;;' /

w (TYP l SET a -4Z RELIEF VALVE PER ORR PI-Ull-016 sv I'----,;

111 1B ~: jr.h/4' BAK FLGS 3/4 RA52508 11* "'*" 0-4NS15 t-_ - \\_SV-37058 2 'if-!,'<)-{ 3/4' PSIG RTAMETER - 2NCH7-\\ I OWN: JEK 3-11-Hll ¥*i~it~~~7 -~B~JG -1 j £ ~~ -'+',F__. :o-2a-i ~ 1 ~ 2NG-3-J I ~~~~~=E~~t-4784; 7-10 l-- i.,. -----1 J--\\ J- -1/2* J-1-1 -I l1749 1/4'VENT APP': CMR 4-8-10 3/4-2NG-I~~~. -7r-~*-, 1 10 PATH I -? -? I 2NG-11-6 11 2NG-U-] I ~ ]" 1791 BOT~~~~ TRANSFER I rf<0l-- -C;-1..:j--f;:.J<J--C'"}-VH £.........l.... ,-3/4-2NG-1 \\ ~ AS BUILT-UNJT I I ~ )I '- \\..:'SEE D~g ~~~l0llll-J 1,1 7 'f,a_<C7 1/2-ZNG-I CORRECTED LABELING FOR r;:;7, _JI 4 I SJ .It I'_ 3/4'.... 171' PI-1199-4.MOVEDID.FROM [;! i { [E - _)~I 'V \\-X32 * / - ' ~~ 2NG-2--4 ~:~~~ ~~: ~~~:;;:~. 10 y 'i' 18 m - 3/4:r..._i:- 1* < 2NG-2-J 11 2NG-19-1 1 \\ 1 rs=,~-~3,=0=s~s, ~G l I\\ l-2NG-1 PER ORR PI-10-066 I I TO VENT HOR l \\ I 2NG--4-J I _J I SEE XH-1-123 ZNG-z-z0 REMOVEASLE SPOOL PC OWN: KJF 7-2"1-UlJ r-2NG UZI 1 ~ CHK'D1 JLK 8-2-10 I I -[~~~~======~ 2NG-L5-13 I" SIi 1----1 MOD*: EC-1578B 0 0 I 2NG--42-I I -~1/2*......_ 1*/ll Ta 122 STM.llE~MS..RELIEF APP': CMR B-5-10 "21 PRESSURIZER RELIEF TANK !Il/2)

• 21 REACTOR COOLANT DRAIN TANK (11/2)

I' ~=~-'-/---~ [: rOR.SEE DWO.N'"-J'l21'1 !'Ill 2NG-40-2 ['.__ 1/2-2NG-3 l-2NG-3 ~ AS BUILT-11--- TO 0 2\\STM,OE~MS.RELIEF SET D c,;;_J ""1-2NG-3-f>IIIR.SEE ll\\lll.t-F-~'121'1 REV'O 3/4"LN SIZE FOR UNIT 5 PSIG I~ ,i-~NG-~ l OESURGERS TO %* & VLVS Pl Pl 2NG-27-I 11925 I~ NG & 2NG-39-1 THAU 6 TO 2NG-2-9 I\\.._ REMOVEABLE SPOOL PC BE CLOSED. ADDED SAFETY 2NG-2-B 1, 2NG-!5-14 r:i I ZNG-Z-!9 CLASS FLAGS TD DESURGER rt/4~-t3/4~b,,=:::;--,-.. AREA FOR VC SYS & GRID __u_j I j I 1/2' REFERENCES TO XH-1-3"1 &. ~ '\\-ZNG; 2:11 I 2NG--4°-J Xl-l-11!101-5. DELETED '-J:><1-"----1>"1---i><;J-'t*~*L.!t_' "LI---'I;'-.1---'-:-,Ml---c,---c:l QA TYPE FLAGS AT VC SYS CONTINUATIONS, l!l-4NSl5 I NG-56-1 I I NG-2-10 I NG-21-2 \\ ~ NG-2-20

!el iic~;,,~oR.

2NG-56-2 NG-2-18 ~ I 0/ __ ~ _..:;. l'Jll 3/4'Ill 2NG-27-2 I 2NG-2-18 I PER RR PI-1111-125 OWN: JEK B-26-ll!l I I 2NG-2-10 I I 2NG-4-8 2NG-41-\\ I "\\'===:;-----------------,----,-,---'~-~,o~-~*_.1~ _ __,,c><'"\\------'~'---)--~l-~2~N~G-~l-~L _______ ---:::-:::-:::-:---:;:r----------'----------tl------)----------l \\"T---- 1/2-NG--4 __,,,._ 2NG-56-I ---1NG-l5-t2I '-ING-15-lll ~N:3-15-1~ ---1 NG-15-9I 2NG-7-l I NG-25-1 I -.\\_1/2"LINE TO CONTAINMENT LEAKAGE TEST PANEL 2NG-lt-2 I '¥ CHK'D1 OB 9-14-10 MOD*: EC-1-4788 APP' : CMR 9-15-10 ~ AS BUILT-CORRECTEO VALVE DESIG-NATION FROM 2NG-16-16 TO A f-- B C '---C(<Sj---V--3-31-90---j~ NG-28-3 I LL 1/2" :1~: / L==1=-----'-----___, NG-26-5 I l'--'-oo----1 ;, l2S1-t9-3J7 I' \\ NG-1-2 ~ l"f- \\ -H 2NG-l6-6 AT GRID A-10. 1--- I NG-7-40~_ LN2 CONVERTER FILL ~- i NG-28-7

• t21 LN2 PUMP 045-311

---' NG-20-10I 2-PCV-9-44 IRA-38RD SET AT 800 PSICi 1-Sl-902R 1-2S1-19 NG-21-1 I Ml21 NCTR GEN SUPPLY BANK UN[TS SET AT 150 NG-13-1 h,_ PSIG 2:-._ 2" X I' f$5'@ ~JG-13 3/4-NG--4---, 1/2-NG--4 ------; TO *21 VOLUME CONTROL TANK SEE XH-1001-5 S.S. c.s., Pl ll-410 cc,~,~,--,~,~-~"7 T021&22 CST BLANKET AUX. BLDG. PER EC-16718 OWN: KJF 10-19-10 CHK'D: WEH 10-19-L0 AS BUILT-ADDED VALVE ID, WG-3-32. CORRECTED PlPING DA TYPE AND ADDED DRAWING REFERENCE CONTINUATION. OJ ROOM ~',----~ 2NG-20-12 I PER ORR PI-09-163 183-45 I OWN: KJF U,--4-ll!l CHK'O: JBS 10-12-10 D I J NG-16-11 I TD ATMOS" L FROM N2 COMPRESSOR ill§§~r3/4"X32D ,-U NG-ll-5 I ~N-,-,-, -,, \\ 't' ~r 3/4"1/4 I" TO UNJT *2 BORIC ACID EVAPORATOR PKG. SEE XH-1001-128 1 TO UNJT '"I BORIC ACID EVAPORATOR PKG. SEE Xl-l-1--405 1 PRESS RED VALVE STD 0, 65 PSIG l-RA32RDB ~-~"=o,wMETER 2NG-20-14 I 2NG-20-13 MOD": EC-1-4-472 APP' : CMR 10-19-10 NG-7-23 t1NG-54-2 TANK RUPTURE DISK ¢C-4 I 3/4* I' I' I NG-3-1 t-- I' < 3/4-NG-12--t '\\_ BREAK 1-NG--4 IO 0 ~ AS BUILT-3/4-NG-"! ~ 122 I NG-46-1 I JACKET ',' j, I' I NG-2-2 1---, FLANGES '-SECURITY SHUT-OFF VALVE NG-56-4 1-' I 2NG-12-1 3/4-NG-8 PCV

~ ~

I r.(.-12-1 I 1049 usi~ ~ :i :5 ADDED VAL VE ID'S ASSOCIATED WITI-I 121 8c LN2 CONVERTERS. [- ING-7-22I / Vl6,, THERMOCOUPLE TUBE &. VALVE s~ r

• 122 LN2 CONVERTER CXH-749-26) j, AZ

~ ECDNDM[ZER ..:::...J REGULATOR LI 18070 NG-4-4-1 I NG-47-1 I TANK PRESSURE LIOUID LEVEL rN-,-_,---277 rN-,-_,---2675 I N -1><1 NG-7-24 ~ NG-45-1 I ~ '-;'--~ 0 NG-48-1 I ~_,,_

---

v "

11481 '-,r-~ "'t NG-48-2 I i\\[NG-7-29 ~HOSE RV-I SAFETY f NG-7-21 PRESSURE BUILD REGULATORY R-l SET 11! 120 PSIG f---,------{,-:f---,c,..i_--,>1<)~-7'STRAINER A 11111111111 \\ l,-c-l--c}--0-------!HlllH-fll---J NG-7-38~ 7 11111111111 FILL NG-7-20 .J ~ Sl NG-7--42I PRESS~~t BUlLD I' TO ATMOS/ I' NG-6-l K~ SET AT 85 PSJG PRV NG--4-6 I-j I\\KJ-2-12 I-1/2" ---1 NG-20-"I I' fl Sl-19-3 I I' I NG-15-6 ~ 3/4" I NG-1-IJ-7 3/4* I v 3/4" I NG-6-2 j--- SET AT BS PSIG PAV NG-5-1 I NG-56-6 I I' LJ NG-56-5 I Pl m 1,,-'i NG-22-t I l~NG~- -~5 ', i '~ j, - I *--==-=i 3/4' 3 I NG-20-7 f---... NG-20-BI LJ NG-15-5 L__________,i' 3/4 ..:;:, ~ 1/2' 3/4" 1/2' 1/2" 3/4" ~f->"--D---'~h-"--C!----r-~-'---_j_ _ _:,__ __ I NG-28-61--,} 1/2* I 1/2" '] NG-20-5 I A 4 NG-H 3/4"l---t"'l--1 ll~~3 TO LNIT I ACCUMULATOR No-20-si-/ \\ ~ ,;.-,--j ~1/2"--r-CI- ,1,---'-D--,CC-- ,!,1/2" -,1, Sl-31-1 ~ l' X28 l_ SET Cl 900"

~:1-PCV-9-44

-:"~--7 -----~--7

---

~---

3/4'-S1-19 l-Sl-902R IRA-38RG I NG-15--4 d d I NG-15-3 I I NG-15-2 I NG-15-1 I 1-5[-I'! SET AT 800 PSIG '_ i ~ NG-7-31 I NG-43-1 I - ""\\.,, ( SV-33131 \\. NG-41-1 I 0,\\ ~ 1 NG-7-3' I) '-c-/q----1~ H.f-.. --~ .. r-~'~-------,v,---'nn ~ 1><1-1><1-1><1-1><1-1><1-1><1-f-,><] f--!xl f-,><] ( 11 8 7 NG--42-L cc-=~~ r---r '-->

• 122 LN2 PUMP r~

I NG-49_1 I PRESS REG VAL VE - 26-40-1700 PSIG 1 0-45-312 ~ "( SV-33132) Pl \\_,'.'.I2':'N~G~-3~8'.:;--3I ll995} I I2NG-3-4-3I TO PLANT VENT 'w f IZNG-32-3I l2NG-35-7I l2NG-35-BI l2NG-37-3I l2NG-35-t2I T ) ~--;>' FOR CONT. SEE OWG, <e----~ NF-3"1600 I I I r\\/ Pl 11"1'!4 I ~=~=~ l2NG-38-2I I IZNG-35-9I 0I2~N"G'-3'"5--"-4I .I/lzNG-35-51 12NG-37-2II"2N"'G'-'3"5'-1~11 T }2NG 2I ~;::;!;' i='.--1'Q 'f..'.'.::;J1;.°::::'.f""'::5:;:'.::~L:::'.::;1r;:'.:'.,* LYQf'.'.'.---... H~ t' _'r 'JJ[,*I ro 'r. I Pl ll-487 ~ 2NG-3"1--4 1, ~ RN. ~ l2NG-Js-sl IZNG-35-14I I2NG-3"1-3I ~ j N5R C2 ~II~~ I l2NG-3B-il I 2NG-34-II T IZNG-35-2I IZNG-37-1I r-I2~N"G'-3'"5--~,.0 I T l2NG-32-ll .A I I f'./ I IZNG-35-ll I 12NG-3"1-2(t:xi* ~ l2NG-3S-tl ~,,-;;i7 Ill IB '-- _ J IZNG-35-13I HYDRAULIC DESURGERS CXH-101211-S D F --4, G-4, H-41 2 I I IZNG-35-3I 1*.. 3/4* REil 3 I ING-31-3I f--!xl f-,><] Y><l SPARE

• t21 NITROGEN SUPPLY BANK UNJTS Pl 119"12 ING-32-3I ING-34-3I ING-30-3I ING-29-10I T / /

"\\ T ING-29-14I v\\ I I rv I , 'r I NG-29-11 I o;;-- TO,..,--~~:r;. ";NG~-~39~-=6~1@~ ING-2"1-"I DR~ ~ I ~ . ~l1a 1~ :-i ~ 1.. ~ J ING-29-81 ~ TD ] ING-3'1--4I '4 ING~29-6I ~ f-:c.=:::::==-( Pl NG-32-1 4 ~

i(i!..--"~

1148-4 ING-3'!-3I ~ I ~i1 NSRCz.__J --:=:;:::j'l':t:;--( Pl I, 11990 NG-31-1I \\. T ING-29-12I V-,.., I NG~-1I ING-f9*4I TD ING-3"1-2I ~ Pl ~

• '~:;.;;.:::::;---, U-483 ING-39-1I llill I ~ 7

~ 1...!! J HYDRAULIC CESURGERS CXH-1-39 D F --4, G--4, H--41 I 5 T ~ rv 4 ING-29-31 3/4-NG-1-4 PRESS REG VAL VE 2640-1700 PSIG I 6 ING-f-21I LEGEND f'C\\ DENOTES FURNISHED BY WESTINGHOUSE CORP. \\.!!;/ AS DESIGNATED BY FLOW DIAGRAM X-HIAWl-125 ~ DENOTES LIMJTS OF O A TYPE IA & III DENOTES THE PIPING A TYPES 0 DENOTES CONTAINMENT PENETRATION NUMBERS

• DENOTES FURN[SHED WITH & SHOWN ON EQUIP.

CAT. I -F DENOTES CATEGORY I VENTILATION ZONE ALL PIPING OA lII UNLESS OTHERWISE NOTED t 7 / I NG-20-ll I NG-37-1 I I NG-37-3 I * ~ i'---FLOWMETER______.:, ~ Pl 1137-4r---J I' @-- ~ ',---, SV-3305i'l I NG-37-2 I TO 11 CD SPARGER T0un CST BLANKETING I-NG--4----, I-RA32ROB 3/4-X420 " ~p 3/4-NG-5-----:::: I' 1-NG-sr"° PCV PRESSURE RED, VAL VE 107129:0 TO 5 PS@yl 10-47 I N~~,:-.:~1 ll295 I', t* X32 @-X320 I NG-8-1 I , I' ~3/4-X-420 312"13 ~~~ '!=I I~,-,--,-,--,~ 3/4-X3/,D O ~ z

• r I-NG-6 1-i-x32. '-I' rs ~

-I" I" TO HOLD UP TANKS SEE DWG \\_ @

• 1 XH-1--40 l-NG-5_j

/ C' l-X32ll ~----{ u I NG-10-5 fi'\\ I NG-10-7 I ~ I' NG-9-1 I '+' / 3/4" TD WASTE EVAPORATOR PKG SEE XH-1-66-4 I-3/4-NG-5 ~ -z).;~ --~ I' I' WG-3-32 i.,--1-NG-5 Vl---3/4-NG-5 I' ---) TO "121. "122, "124, "125 & "126 LOW LEVEL GAS DECAY TANKS SEE XH-1-12-4 TO *121 AOT EVAPORATOR & WASTE GAS DISPOSAL SYSTEM SEE XH-1-550-1 I 2NG-2s-1 I 1/2-2NG-3/4' 2NG-2-1s jsa-J-10 I N. L w wN 3/4* \\,;,.. 3/4* ~ I' 1-2NG-2 I' PER RR PI-10-197 OWN: KJF 12-16-10 CHK'D: CWL 2--4-11 MOD": EC-16097 APP' : CMR 2-8-11 ~ AS BUILT-ADDEO VALVES & ID'S ASSOCIATED WITH 121 & 122 LN2 CONVERTERS.ALSO lNCORP MINDA CHANGES TO CONFIGURATION. PER ORR PI-12-1"10 OWN: LAB 10-24-12 CHK'D: AP 10-321-12 MOD"1 EC-1B232 APP' : CMR 10-31-12 ~ AS BUILT-ADDED VALVES 2NG-20-13 AND 2NG-20-1-4 AT GRID 0-tl, PER ORR P!-1-4-061 OWN: JEK 4-11-1-4 CHK'D1 ALM 4-16-1-4 MOD*: EC-22167 APP'D: CMR 4-16-1-4 l§§j AS BUILT-ADDED PERMANENT &. TEMP, PIPING FOR BYPASS TO N2 GAS SYS.; THEN REMOVED TEMP. PIPlNG ONCE PROJECT COMPLElEO.lNCORP,FCR

• 22652-001 & -003.

PER ORR PI-18-129 OWN: LAB 12-13-18 CHK'O: MJL 12-16-!B MOD",6M D00022652 APP'D1 DB 12-17-18 l.§_§j AS BUILT-SHOW'D PIPES NOT CONNECT RELOCATED CI-IECK VLV NG-21-2 PER ORR PI-1"1-007 OWN: MEA 2-8-1~ CHK'D: RSA 2-8-19 MOD*1 6DOCEDI22504 APP' : DB 2-11-19 1-NG--4 ___,. 1-2NG-2-..... ~ AS BUILT-1* I 2NG-2-5 I ]' I NG-2-6 I I' I NG-2-7 I I' NG-2-5 I SET D-0!-ZNG-Z l~.SET 11,""\\* 5 PSIG \\ \\ 3/4-5 PSIG \\ / 3/4-NG--4 SET 11 / 3/4-NG--4 I;::-- 2NG2 4 SPSIG':::,,.._ '{ 3/4*1 2NO-]B-t I 9:,"11c"I NG-tB-3 I '{ 3/4*1 NG-18-2 I '{G.'J/'11"'--,-,-_,-.--,~I 2NG-16-7 I /l NG-16-9 I /l NG-16-8 I /l NG-16-7 I 3/4" 3/4" 3/4" 3/4"I-IOSE 1,---------j;,--------j;,-----------j,--CLPG FOR FOR *21 SEAL WTR. & *21 LET ON. HT. EXCH' 5 REF PIPING OWG. NO'S. r PURGING FOR FOR FOR *IL SEAL FIL TEAS DEMINERALIZERS WTR. & "11 LET ON. HT. EXCH' S C2 NSR rntm LEGEND CLASS BREAK QA TYPE Ct - SAFETY-RELATED; IS] CLASS I C2 - SAFETY-RELATED: ISi CLASS 2 NF-39299-1 NF-39299-2 NF-39299-3 CJ - SAFETY-RELATED; ISi CLASS 3 SR - SAFETY-RELATED FLUID BOUNDARY; NON-CODE CLASS NSR - NON-SAFETY-RELATED IA,IB,IC,IlA,IIB &. lil DENOTES PIPING OA TYPES. EXISTING CHECK VALVE NG-7-3-4 WAS NOT SHOWN m DWG. REV'D TD ADD CHECK VAL VE AS SHOWN. PER ORR PI-21-0-49 OWN: LAB 9-28-21 CHK'D1 RSA 9-29-2] MOD*: 601000003250 APP'D: DB 9-29-21 Thill m.., f documem Ill a 1001 to ""5&1:employeeo In !he perlarmance o1111elr Jd:13. Yoor P"""'nsl salety I* plG'llded !er t,y LJSllg smaty prar!lll9B, proo,,,tlu... BM '"1Llpm9nl!IB <IOSl!IIM<I In salfllV training prngr:arn*. manual!! an~ SPAA'I. DWN MCM I DAlE 10-22-85 81c:t!IRCNl"TNO. 8630 I I 10° ~ 1 I 2900 CHECl<ED I I 2 I s I 4 I ICLI PROJECT NO APP' il,CERT SEE REV. 'AR' MISCELLANEOUS GAS SYSTEM UNITS I & 2 FLOW DIAGRAM Fl.ME NORTHERN STATES POWER COMPANY 11-*- PRAIRIE ISLAND NUCLEAR GENERATING PLANT RED WING, MINNESOTA SCALE NONE I REV 87 NF-3924 7 E F l'- s;- N CJ' (Y) J_ z ~ H I I I I NF-39247.DG"I NSP GENERATION CNJ j 8 9 10 12 FIGURE 9.1-9 REV. 37 CAD FILE: U09109,DGN N It) 0 0 0 0 0 0 ~ 0 co

A B C D E 2* F G H 2* 1 A =r!\\_~ mY ~ w 2 16928 CONTROL 59501 HIGH 47015 IWL-16-3B1

• 122 RADWASTE 48 LEVEL 0603 t--2-WL-261 ~A PUMP ~

A -+ WL-J?-S9 BLDG. SUMP PUMP I - ~..._ 1 ~1/Jl I 4" l,t FLOOR PI 11705 1 I FLOOR DRAINS LJ

• 122 RAWASTE BLDG.SUMP I

LA 16853 4* 2 I RAOWASTE BLDG. ECON.AREA SUMP I MEZZ, FLOOR ORAINS7 4* I 3 3 I 4 5 4 I 5 I 6 1 r 7 8 9 8 6 t 7 I 8 I 9 I 10 10 Fl.MED 11 12 REVISIONS ~AS BUILT-ADDED COLOR CODED HEAT TRACINGS. PER ORR PI-W-12111 OWN= JDS 03-30-98 CHK'D: PAS 4-9-98 MOD":,.....,,_,, FILMED: 5/98 ~ ISSUED FOR CONSTR. REV' UNE 2-WS-12 AND ADDED SIGHT GLASS ANO VAL ','ES AS SHOWN. PER ORR PH11111-138 OWN, BMS 8-9-00 CHK'D: CMR 8/30/llllll MO "= 98WLIIJ2 FILMED 9/00 ~ REPLACE 121 ADT ION EXCHANGER DISCHARGE STRAINER WITH EXISTING FIL TEA SYSTEM RELOCATED FROM 123 ADT JON EXCHANGER. [NSTALL NEW FILTER SYSTEM TD 123 ADT JON EXCHANGER AS SHOWN. JSSUED FOR CONSTRUCTION. OWN: LAB 3-26-02 CHK'D: RLC 3-26-02 MOD. No. 0\\WUlll REVIEWED: R.L. COLE 3-26-02 APP'D & CERT: GERRY GORE 3-26-02 PE NO. 24387 ADDED VALVES WL-29-40 &. WL-29-41 AS SHOWN. JSSUED FDR CONSTRUCTION. DWN: LAB 7-3-02 CHK'D: R.L. COLE 718/02 MOD. No. 0\\WL01 REVIEWED: R.L. COLE 7/8/02 APP'O & CERT1 GEORGE T, LENERTZ 7-11-02 PE* 13649 AS BUILT-ADDED Fl-18494 AND FE-27494 AS SHOWN, lSSUED FOR AS BUILT. PER ORR Pl-03-133 OWN: CLN 9/29/03 CHK'D: CMR 10-1-03 MOO": 01WL01 FILMED 10-03 lZ§J AS BUil T-4" CC SUPPLY/ RETURN PIPING ABANDONED AND CAPPED AS SHOWN. PER ORR Pl-10-055 OWN: KJF 4 11Z1 CHK'D: KRK 6-14-10 MOD": EC-15378 APP'01 CMR 8-4-Hil lZZJ AS BUil T-REPLACED CNTL VLV CV-39004 WITH OIAPH VLV WG-21-22 C LDC B-7. PER ORR Pl-12-032 OWN: DB CHK'D: AP 2-28-12 2-29-12 MOD": EC-19083 APP'D1 CMR 2-29-12 ~ AS BUil T-ADDEO !Jii* SAMPLE LINE VAL'.'ES WL-85-6, 7 & REF TO 121 &. 122 ADT MONITOR TNK RECIRC SMPL PER ORR PI-13-238 OWN: DB CHK'D: WB 10-17-13 12-18-13 MOD": EC-22642 APP' : CMR 12-18-13 lZ,:U AS BUil T-REVISEO TO INCLUDE ROOT ISOLATION VALVES WL-165-33. WL-165-34. WL-165-42, WL-165-43. WL-165-44 & WL-165-45. PER ORR Pl-18-074 OWN: LAB 8-7-18 CHK'D: BNS 8-8-18 MOO*: 601000000600 APP' : DB 8-8-18 ~ AS BUILT-ADOED ISOLATION VALVES WL-165-29 & WL-165-30 AS SHOWN TO Pl-11698 &. P[-11699; !601000001053). PER ORR PI-19-213 OWN: LAB 8-8-19 CHK'D: TEO 8-8-19 MOO*: 6DOCEDl28105 APP' : DB 8-8-19 ~ AS BUil T-ADDEO EQUIPMENT ID NO'S ANO VENT &. DRAIN VALVES WL-96-1, WL-97-1 & 2 AND WL-101-1 THRU -4 TO FIL TEF HOUSINGS AS SHOWN. PER ORR PI-21-006 OWN: LAB 3-10-21 CHK'D, JK 3-11-21 MOD,.: 601000002025 APP' : DB 3-11-21 Thli m.., f documem Ii a 1001 to ""5&1:employeeo In !he perlarmance o1111elr Jd:13. Yoor P"""'nsl salety I* plG'llded !er RAD WASTE BUILDING LIQUID WASTE DISPOSAL AND WASTE SOLJDIFICATION SYSTEMS UNIT I & 2 NORTHERN STATES POWER COMPANY 11-*- SCALE NONE I REV 81 A f-- B C D E F (D (Y] N CJ' (Y] J_ z ~ H PRAIRIE ISLAND NUCLEAR GENERATING PLANT NF-39236 AEDWll,IG, Mll,ll,IESOTA I NF-39236,DGI\\J j NSP GENERATION CNJ j 12 FIGURE 9.1-10 REV. 37 CAD FILE: U09110.DGN N It) 0 0 0 0 0 0 ~ 0 co}}