ML19224B277

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Final Rept, Sys Description:Decay Heat Removal Sys, Ref Burns & Roe Drawing 2026,Revision 18
ML19224B277
Person / Time
Site: Crane Constellation icon.png
Issue date: 02/28/1976
From: Iskyan H
Burns & Roe
To:
Jersey Central Power & Light Co
Shared Package
ML19224B276 List:
References
TM-0291, TM-291, ZAR-760228, NUDOCS 7906140349
Download: ML19224B277 (42)
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==s [ t _f FINAL SYSTEM DESCRIPTION (Index No. 20) ~ DECAY HEAT REMOVAL SYSTEM (B&R Dwg. No.2026, Rev.18) \\ JERSEY CENTRAL POWER & LIGHT COMPANY THREE MILE ISLAND NUCLEAR STATION UNIT NO. 2 Issue Date: February 1976 Prepared by: H. Iskyan 7906140399 3 Burns and Roe, Inc. ( 700 Kinderkamack Road

Oradell, N.J.

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W* ' TABLE OF CONTENTS FOR DECAY IEAT REMOVAL SYSTEM Section Page

1.0 INTRODUCTION

1 1.1 System Function 1 1.2 Summary Description of the System 2 1.3 System Design Requirements 5 2.0 DETAILED DESCRIPTION OF SYSTEM 6 2.1 Components ?. 2 Instruments, Controls, Alarms, and 16 Protective Devices 3.0 PRINCIPAL MODES OF OPERATION 17 3.1 Startup 17 () 3.2 Normal Operation 17 3.3 Shutdown 19 3.4 Special or Infrequent Operation 20 3.5 Emergency Operation 21 4.0 HAZARDS AND PRECAUTIONS 24 a N 9 l ,f' N. 2 i 's C -196 077 W e w -m.- e m.h

Qf3, ; - 7. ~ ** w;.. p APPENDIX A TITLE TABLE NO. Decay Hea t Removal Pumps 1 Decay Heat Removal Coolers 2 Borated Water Storage Tank 3 Sodium Hydroxide Storage Tank 4 Borated Water Storage Tank Recirculation Pumps S Relief Valve and Vacuum Breaker Listing 6 Instrumentaticn and Controls 7 Panel Mounted Annunciators and Computer Inputs 8 e (m. 3 i; 196 078 C wm 6

e. w._,.. _ ~ ' __ di ~ l,- ~ DECAY HEAT REMOVAL SYSTEM ( l.0 INTRODUCTION 1.1 System Functions The functions of the Decay Heat Removal System (DIIRS ) are as follows: (1) Remove cor a decay heat af ter reactor coolant has reached the minimum tempere ture possible with condensate /feedwater cooling (250 F). Heat is removed from both the core and pressurizer. (2) Fill, recircula te, pur ify (via the Spent Fuel System), and drain the fuel transfer canal for refueling. (]) (3) Minimize -the consequences of a loss of Coolant Accident (LOCA) in the following manner : (a) Inject borated water and sodium hydroxide solutions into the core at a low reactor pressure. (b) Provide long term cooling af ter a LOCA by recirculating water from the Reactor Building Sump to the core. (c) Supply the suction of the high pressure ~ ~ injection Makeup Pumps for long term cooling after a LOCA. 5 1 sn (. Y/~ T t 19607dp ~

4.,__,. MM,=..,1 .- ' - ' ~ ~ ~ =-w _. h _~. ~? (d) Supply the Building Spray Pumps with water -s k from either the BWST/ Sodium Hydroxide Tanks, or from the Reactor Building Sump. (4) Circula te the contents of the Borated Water Storage Tank for mixing and sampling. The DHRS has an interface with the following systems and in conjunction with these. systems performs its primary and secondary functions: (Numbers refer to Burns and Roe flow diagrams. ) 1. Condensate Polishing (Dwg. 2006) 2. Demineralized Service Water (Dwg. 2007) 3. Reactor Coolant Make-up Purification (Dwg. 2024) 4. Chemical Addition (Dwg. 2025) (]} 5. . Spent Fuel Cooling (Dwg. 2026) 6. Radwaste Disposal Liquid (Dwg. 2027) 7. Nuclear Sampling (Dwg. 2031) 8. Reactor Building Spray (Dwg. 2034) 9. Core Feeding (Dwg. 2034) 10. Decay Heat Closed Cooling Water (Dwg. 2035) 11. Nitrogen for Nuclear and Radwaste (Dwg. 2036) 12. Radwaste Miscellaneous Liquid (Dwg. 2045) 13. Radwaste Disposal Reactor Coolant Leakage ~ Recovery (Dwg. 2632) l.2 Summary Description of System (Refer to B&R Dwg. No. 2026, Rev. 18) During reactor cooldown, the steam generators are utilized 3 as heat sinks to reduce the reactor coolant from its normal _t operating temperature of 582 F to approximately 250 F. The f, Decay Heat Removal System then further reduces the coolant ( temperature and maintains the coolant at a tempeyature suitable for cold shutdown conditions. The system may be placed in operation at 320 psig and 250 F.

,~w. _ n I7 M; The DHRS takes suction from the "B " loop reactor outlet 7 5 (hotl g) and returns the coolant back to the reactor through the core flooding injection nozzles after it passes through the Decay Heat Removal pumps and coolers. The system is comprised of two parallel circuits from the point where the reactor outlet supply line connects to the DHRS at the pump suction supply headers within the Auxiliary Building. Both circuits share a common suction from the reactor. Each of the two D'.fRS pumps discharge the coolant into the tube side of its associated cooler. The rcactor coolant, after passing through the coolers returns to the reactor vessel through two separate core flooding nozzles. By circulating the reactor coolant in this manner, the coolant temperature is reduced and the decay heat of the reactor core is transferred to the Decay Heat Closed Cooling Water System (DHCCKJ). (~ ) Provision is made to utilize the DHRS to collapse the pressurizer u, bubble concurrently with core cooldown by lining up the DHRS cooler outlet line to the pressurizer spray line. This permits cooled water to be injected into the pressurizer, cooling it and reducing reactor plant pressure. The DHRS may also be utilized to fill, recirculate, purify, and drain the coolant in the fuel transfer canal during refueling operations after the reactor head has been removed. Normally, the Spent Fuel Cooling System is utilized to fill the fuel transfer canal, however, filling can also be accomplished using the DHRS by taking suction from the borated water storage tank.(BWST) with the DHRS pumps. The pumps discharge the borated water through the system piping into the reactor vessel. With the reactor head removed, the borated (' water over flows into 'the fuel transfer canal. Direct discharge .into the fuel transfer canal via the Spent Fuel Cooling' System is also possible. Recirculation of the w te {

fel transfer canal is accomplished by mixing of the coolant ... ~ ~...

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3 -=w; Fw - in t5e reactor. vessel and the fuel transfer canal during normal ~ E[ refueling operations. Purification is accomplished by -s \\ passing a side stream of the coolant from downstream of the DHR coolers through the purification loop in the Spent Fuel Cooling System and returning the purified coolant into the DHR pump suction supply headers to be returned to the reactor vessel with the recirculating coolant. Purification and cooling are normally accomplished by the Spent Fuel Cooling System. s The DERS also affords a means for draining the fuel transfer canal to approximately the level of tae reactor head flange, and returning the water to the BWST. A line at the outlet of each cooler connects to the BWST via a common header for this purpose. This same line may be used as a recir-culation line for testing dhe operation of DERS components. Further draining of the fuel transfer canal is performed using the Spent Fuel Cooling System. r Sodium hydroxide is injected into the reactor (and the Building Spray Pump Suction) to change the coolant pH, thus making the cond.i tions more f avorable for iodine removal. When the DERS is operating in the Engineered Safety Features mode, water from the BWST and Sodium Hydroxide Storage Tank is injected by the pumps into the reactor vessel af ter the reactor pressure has fallen below the maximum discharge pressure of the pumps. When the BWST water level has been reduced to 6 ft., the operator in the Control Room manually shifts the DH Pump Suction from the BWST to the Reactor Building Sump which has been filled by leakage from the pipe 1 rupture. ] C-1-96 082 e W

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= E-The outlet of the two coolers may be cross connected by opening two cross tie valves. Both pump / coolers may flow into one nozzel inlet if the pipe break-is near the other core inlet. One_o.f.._t_wo recirculation pumps continuously circulate _tae content of the Borated Water Storage Tank to ensure a representative sample. 1.3 System Design Requirements The DHRS is designed to reduce the reactor temperature to 140 F wi:hin 20 hours after shutdown. The major contribution to heat generation is the decay of fission products. Core decay heat generation dependent on the time after shutdown, the power level of Ehe reactor before shutdown, and the length of time that the (.) reactor has been operating at power. The requirement to be able to shutdown to 140 F within 20 hours is based on the following assumption: 1. 800 days of 100% power operation before shutdown. 2. Cooldown from normal operating temperature to 750 F in 6 hours by steaming. 3. 3000 gpm flow through both DER Coolers (Shell and tube side). 4. The Decay Heat Closed Water Cooling System temperature of 95"F and a Nuclear Service River Water temperature of 85 F. 3 Each loop of the DHRS is capable of removing the system design heat load and supplying borated water to the core and associated safety systems during a design basis LOCA. 'l96 083 ~. 6

c The BWST may be samnled at any time. Because one of the Ujp' two' BWST Recircul.a tion Pumps is in operation at all times, E,. the sample is considered reprasentative. k_ The portion of the system not subject to normal reactor . operating pressure is designed to operate at a temperature of 280 F and a pressure of 370 psig. All system piping is of stainless steel and is classified as Nuclear Piping (Symbol N), designed, fabricated, inspected and erected in accordance with ANSI B31.7, Nuclear Power Piping. The seismic requirementa of Class I apply to the entire system including all components. 2.0 DETAILED DESCRIPTION OF SYSTEM 2.1 Co mpone nts 2.1.1 Decav Heat Removal Pumps, DH-P-LA and DH-P-1B The Decay Heat Removal pumps (see Table 1)are single-stage, O centrifugal pumps rated at 3000 gpm each with a total discharge head of 350 ft. They are locatea on the 280' level of Auxili,ary'/Pue1 Handling Building, and are designed in ~acc6rdance with the Nuclear Pump and Valve Code Section'C. A pipo and associated flow orfice to the pump ~ suction ?re in the pump discharge to provide minimum f.1.ow when a discharge valve. is closad. For non ES actuated, non-emergency, operation, an interlock prevents the motor running without Decay Heat Closed Cooling Water f' ow through the motor and pump coolers. Control and indication are avai.lable locally. Panel No. 3 has a control switch) ammeter and run,stop, and power 3 available lights. DH-P-1A and DH-P-1B are powered from 2-lE and 2-2E respectively. )96 ()84

_a gg,. 5 [T.~.~ "I71;2 Borated Water Storace Tank Recirculation Pumos DH-P-2A E, and DH-P-2B The Borated Water Storage Tank Recirculation Pumps s (see Table 5) ensure that the BWST contents are mixed and that a sample is considered representative of the entire tank. Both pumps are located outside; adjacent to the BWST. The single stage centrifugal pumps are rated at 100 gallons per minute with a discharge head of 100 feet. One pump is nonnally running and the other in idle stand by, ready to start if the running pump trips. The pumps are controlled locally from Panel No. 8 by a MAN-STOP-AUTO switch. DH-P-2A and DH-P-2B are powered from 2-32A and 2-42A respectively. 2.1.3 Decav Heat _ Removal Coolers, DH-C-lA and DH-C-1B The Decay Heat Removal Coolers (Table 2) transfers heat from the DHS to _the Decay Hea t Closed Cooling Water System. coolers are two pass shell and tube type with the. Decay s-Heat Closed Cooling water on the shell side and the reactor coolant on the tube side. The shell is decigned in accordance with the ASME Code, Section VIII, and the tubes in accordance with Section III-C lethal, due to the nature of the fluid being carried. Tubes are seal welded into the tube sheet. The coolers are located in the Auxiliary Fuel Handling Building at elevation 280', The Decay Closed Water Cooling, shell side,' has radiation monitor and surge tank which could be used to detect a tube leak. 2 J b /* ~ 'm _7_ l96 085 ~ e e

~ ~., ,.<h*=- -a211.4 Borated Water Storace Tank (BWST), DH-T-1 (f" The BoFated Water Storage Tank (see Table 3) is a vertical cylinder tank of 472,964 gallon capacity and is normally ( filled with water at a concentration of 2270 ppm boron used for emergency injection into.the reactor vessel following a reactor coolant piping rupture and to furnish water to the fuel transfer canal during refueling. A vacuum breaker and pressure relief valve is fitted to the tank. (See Table 6 for settings), Strip heaters are powered from two Class IE Buses (2-llEA and 2-21EA). The f insulated Tank will maintain a water temperature of o greater than 45. F. The tank is designed to withstand an internal pressure equal to a column of water 10 f t. above the normal liquid level in the tank, a vertical line load of 30 psf with a concentrated load of 250 psi. The tank is located outside of the Auxiliary Building in the yard area. O 2.1.5 Sodium Hydroxide Storace Tank DH-T-2 The Sodiu.m Hydroxide Storage Tank (see Table 4) is a vertical cylinder tank of 14,285 gallon capacity and is normally filled with a solution of 20 weight percent NaOH used for pH control during emergency injection following a reactor coolant piping rupture. Strip heaters are powered from two Class IE Buses C 2-llEA and 2-21EA). The insulated Tank will maintain a temperature of greater than 45 F. Nitrogen orossure is maintained in the tank to provide an inert a tmosphere. A vacuum breaker and pressure relief valve is fitted to the tank. (See Table 6 for se ttings). g The tank is located outside of the Auxiliary Building in } the yard area. {. - ~l96 086 e

i .= .3-1 . ' ~ E.- 6 Ma-ior System Valves -am Reactor to DHRS Suction Header Valve, DH-V1 One 2500 psi, 650F, 12 inch SS, electric motor operated gate valve is provided in the Reactor Building between the reactor outlet _(loop B) ' and the DH pump suction header. The valve is shut (except during Decay Heat Removal Cooling) to separate the low pressure DHRS and high pressure reactor cr.olan t. DH-V1 may be open when reactor pressure decreases to 320 psig, the operating pressure of the DHRS It will atitomatically close above that pressure. DH-V1 like the other major DH Valves may be controlled locally by push button or from Panel 3 by a C-N-O Close-Neutral-Open) switch. Indication is -available locally and on Panel 3. - At MCC 2-llEB on the DH-Vl/DH-V171 Unit Compartment is a selector switch which determines whether DH-V1 or its bypass DH-V171 is powered from this Unit Compartment. Normally the selector switch is positioned to DH-V1. In this case the above discussed control switch, indicating lights, and logic, control DH-V1. The cable from MCC 2-llEB to DE-V171 would be unpowered. If DH-V1 were to be repaired, che Unit Compartment Selector switch would be positioned to DH-V171. The control switch, indicating light, and logic formerly associated with DH-V1 would then be used for DH-V171. The cable associated with DH-V1 would then be unpowered. i e i- \\-- _9_ 196 087 G8 -+Nh ew =.w

DH-V1 By-Pass Valve, DH-V 171 ^ wp, y -7 One 250_0 psi, 650F, 8 inch, SS, electric motor operated gate g 7 ---i__ gz valve is install'ed in the by-pass line around the DHRS supply ( valve, DH-V1, to provide suction to the Decay Heat Removal System in the event that DH-V1 is in-operative. DH-V171 is opened only when the DH System is needed and DH-V1 is inoperative. By positioning a selector switch on DH-Vl/DH-V171 Unit Compartment, DH-V171 may be to control the system and DH-V1 control deactivated. Reactor to DHRS Suction Header and Containment Isolation valve (Indside), DH-V2 One 2500 psi, 300F, 12 inch, SS, electric motor operated gate valve is provided in the Decay Heat Removal line downstream of DH-V1, to additionally isolate the high pressure Reactor Coolant System and the low pressure Decay Heat Removal System, and as a containment isolation. Control and indication are available locally and on Panel 3. (]) Indication only is available on Panel 13 and 15. The valve will close (if open) with either an ES signal or with reactor pressure above.320 psig. The motor operator is powered from 2-21EA. Reactor to Decav Heat Removal Pumo Suction Valve, DH-V100A and 100B One 520 psi, 300F. 12 inch SS, electric motor operated valve is provided from the reactor cooldown supply header to each Decay Heat Removal pump suction header. In order to open DH -V100A (B) the corresponding supply valve from the BWST/ Reactor Building Sump,.DH-V102 A (:B), mus t be closed. DH-V100A and 100B will automati.cally close if there is an ES signal and DH-V102A (B) is open. Control and indication is available 2 locally and on Panel 8. Indication only is on Panel 8. {- DH-V100A and 100B are powered from 2-llEA and 2-? LEA respectively. 196 088 7__

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Valve (Ou ts ide), DH-V3 i One 370 psi, 300F, 12 inch, SS, electric motor operated gate isolation valve is provided in the Decay Heat Removal Suction header outside the containment. The valve is in series with DH-V1, and DH-V2 and is closed except during the Decay Heat Removal Cooling. The valve will close with an ES signal, but unlike DH-V1 and DH-V2 it has no signal to close with a reactor pressure greater than 320 psig. Control and indication are available locally and on Panel 3. Indication only is available on Panel 13 and 15. The motor is powered from 2-llEA. DHRS Returns to Reactor Vessel Valves, DH-V4A/DH-V4B One 2500 psi,_300F, 10 inch, SS, electric motor operated gate valve is provided outside the containment in each of the rm, discharge headers from the DH Pumps to the core flood tank s~ inlet line. The valves are closed during normal opera + 'n and open during Decay Heat Removal Cooling. The valves will open with an ES signal and provide a flowpa th for borated water from the tanks into the core. Control and indication are available locally and from Panel 15. Indication only is on Panel 13. DH-V4A and DH-V4B are powered from 2-llEA and 2-21EA respectively. BWST/heactor Building Sumo to Decay Heat Removal Pumo Suction Valve, DR-VlO2A and lO2B One 520 psi, 300F, 14 inch, SS, electric motor operated valve is to each DHR Pump Suction header from BWST/ Reactor C 196 089

h-H_. g Building sump supply line. The valves open with an ES (f signal thus lining up the DH Pump Suction to the BWST. DC-V102A and 102B are interlocked with DC-V100A and 100B res-pectively as previously discussed. This interlock prevents the reactor from being lined up to the BWST or Reactor Building Sump. Control and indication are available locally and on Panel 8. Indication only is on Panel 13. DC -V 102A and 102B are powered from 2-llEA and 2-21EA respectively. BWST ( DH-T-1) Sucolv to DHRS Suction Header Valves, DH-V SA/ DH-V 5B One 200 psi, 300F, 14 inch, SS, electric motor operated gate valve is provided from the BWST to a suction supply line for the DH Removal Pump Makeup Pump, and Building Spray I Pump Suction. The valves open with an ES Signal to provide water from the BWST during the initial phase of a LOCA (DHR Pump Suction is later shifted to the Reactor (~ '8 Building Sump). Control and Indication are available locally and from Panel 8. Indication only is on Panel 13. DC-VSA and SB are powered from 2-llEA and 2-21 EA respectively. Reactor Building Sumo to DHRS Suction Header Valves, DH-V 6A/DH-V 6B One 200 psi, 150F, 18 inch, SS, electric motor operated gate valve is provided in the suction line from the Reactor Building Sump to each DHR pump to permit post-LOCA circulation from the Reactor Building Sump through the DHR Cooler to the reactor. Each valve and the suction line from the sump liner attachment to the valve outlet, including the packing gland ia jacketed to provide a barrier against leakage from j, L 196 090 O s e -~

Wfy-c - : - - Ef the. sump to outside of the Reactor Building should a leak 5 R.. occur which could not be isolated by closing the valve. The jacketing consists of a pipe enclosing the suction line from = the sump to the valve with a split "T" enclosing the valve. A connection is fitted for leak testing the jacket and accessibility for valve maintenance has been provided. Control and indication are available locally and from Panel 15. The normally shut valve does not have an ES signal to close and is the single containment isola *. ion valve in the line. DH-V6A and 6B are powered from 2-llEA and 2-21EA respectively. DERS to Hich Pressure Makeup Pumos Valves, DH-V7A/ DH-V7B One 520 psi, 3OOF, 4 inch, SS, electric motor operated gate valve is provided at the outlet line from each DHR cooler to the Makeup Pump suction. When the BWST is nearly empty, the Makcup Pump Suction is shifted from the BWST to the DH Cooler outlet in order to continue high pressure injection into the reactor. In this post LOCA phase, the DHR Pump suction is shifted from the BWST to the Reactor Building Sump. Control and indication are available locally and from Panel 8. DC-V7A and 7B are powered from 2-llEA and 2-21EA respectively. Sodium Hydroxide Storage Tank (DH-T-2) Supoly to DHRS Suction Header Valves, DH-V8A/DH-V8B One 200 psi, 300F, 4 inch, SS, electric motor operated gate valve is provided in the supply line from the Sodium Hydroxide Storage Tank to the suction header of each DHR pump. Upon f receipt of an ES Signal the valves open and provide sodium (' I96 0 ~

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w. -e j ,""CE-. hydroxide to the suction of the DHR pumps to be added to E E, the injected water for pH control of the spilled reactor coolant. Control and indication are available locally and from Panel 8. Indication only is on Panel 13. DH -V8A and 8B are powered from 2-llEA and 2-21EA respectively. DHRS to Scent Fuel Demineralizer Valve, DH-V 106A /DH-V 106B One 520 psi, 300F, 2 inch, SS, diaphragm operated stop valve is provided in the line from the DHR coolers outlet to the Spent Fuel System between the SF Demineralizers and SF Pump. Opening the valve would enable borated water from the reactor outlet piping (hotleg) to pass through the DHR Pump and coolers to the SF System. From the SF System inlet, the water may be purified and/or directed back to the reactor vessel cavity. Control and indication are on Panel 8. The valves fail closed with a loss of Instrument Air. ~~ DHRS Cooler Outlet Flow Control Valve, DH-V128A /DH-V 128B One 520 psi, 300F, 10 inch, SS electric mctor operated globe flow control valve is provided in the outlet line from each DHR. The valve is throttled to avoid runout during a post-LOCA (taking suction from the Reactor Building Sump). It could be used to control cooldown rate, however, this is normally achieved by the Decay Heat Closed Cooling Water throttle valve, DC-V73A and 73B. Jog control and open/ closed lights are available locally and on Panel 8. A throttle position indicator is on Panel 8. DH-V128A and 128B are powered from 2-llEA and 2-21EA respectively. 7

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_L; c, ~ e +e. -[.. - ~" DHRS Samnlina to Station Chemistrv Laboratorv valve, W E +- DH-Vil2A and 'l2B l One 520 psi, 3OOF, 3/8 inch, SS, diaphragm operated stop valve is provided in the DHR cooler inlet line for sampling of the coolant. Remote _. control of_the valve is provided on the Unit 2 Sample Panel (329) which is located in the Unit 1 sample room. Indication is available on Panel 8. The valve fails closed with a loss of Instrument Air. Decav Heat Puno Discharce Cross-Connect Valves DH-Vl93A and 193B Two S20 psi, 3OOF, 8 inch, motor operated gate valves are provided in the 8 inch Decay Heat Removal Pump discharge. The valves cross connect Ehe outlets of two coolers. If one reactor inlet pipe ruptured, the outlet of both DHR c-Pmnp/ Coolers cculC .e directed through the other inlet i'- pipe. Control and indication are available locally and from Panel 8. DH-Vl93A and 193B are powered from 2-32B and 2-42B repsectively. Borated Water Storace Tank Suocly to the Scent Fuel System, DH-V157 One 125 psi, 250 F, 8 inch motor operated gate valve is provided to connect the BWST to the Spent Fuel (SF) Cooling and Borated Water Recirculation Pump Suctions. By opening this valve, the BWST may be lined up to the SF System and the SF pools filled. ~.' L l96 093 ~ W _w. 3 ee e m m .e we, em e

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,g EI Control and In'dication is available on Panel 8.

The valve is powered from MCC 2-32B. 2.1.7 Miscellaneous valves In general, manual valves are provided in the system for circuit and component isolation and for maintenance purposes. Check valves are provided at points where reverse flow is not tolerable. No check valves, however, are fitted in the Reactvc Building sump lines as th allowable friction losses in these lines are limited for proper DHRS pump operation during emergency recirculation. Relief valves are installed as necessary to protect components and piping from over pressurization. Recirculation lines are provided to permit continuous pump operation against closed valves. 2.2 Instrumentation, Controls, A.tarms and Protective Devices As indicated on Tables 7 and 8, the system is largely t controlled from Auxiliary System Control Console Panel 3, and observed from the Coolant Monitoring Panel 8. Additionally, System pump / motor variables are recorded and alarmed on the BOP and B&W computers. System alarms are annunciated on Panel 8. The"BWST Level Hi'/Lo" alarm indicates that the tank is in its normal operation. condition (nearly full). During a LOCA the '3WST Lo/Lo Level" alarm indicates, that the tank is nearly exhausted and DHR PQmp Suction must manually be shif ted by the operator from the BWST to the Reactor Building Sump. Q ~ 094 I

I w ~ --{ - Each DHR Loop has a " Low Pressure Injection Hi/Lo Flow" alarm. The low flow signals are interlocked to annunciate only with an ES signal. Additionally for the Decay Heat Removal mode, there is a single "DH Removal Low Flow" alarm. The "DH Removal Low Flow" setpoint is less than the " Low Pressure Injection Lo Flow" setpoint. The alarm has no interlock. The " Decay Heat Removal Cooler Outlet Temperature Lo" annunciator is interlocked so that .t will not alarm when the pump for that associated cooler is idle. The System components are protected by vacuum breakers for the tanks only and relief valves for all system ccmponents (Table 6). As described in Section 2.1. 5, DH -VlOOA '(B), suction valves from the reactor, and DH-V102A (B) suction valv es from the BWST, are interlocked to prevent lining up the reactor to the BWST or the Reactor Building Sump. The system is protected from being overpressurized to the normal reactor operating pressure. The DHR System Supply Valves from the reactor outlet pipe, DI -V1 and V2, will not open if reactor pressure is greater than 320 psig. The containment isolation valves in the DER Pump suction will automatically close with an ES signal to prevent pumping down the reactor core during a LOCA. The DH System valvds ~will open with an ES signal to provide ~ a flowpath from the BWST/ sodium hydroxide tanks, through the' pump, cooler, and containment isolation 3 valves, into the core. } -16A-Is ]96 009 U/a e

-m=- ~ normal DHR Pump operation, i e., without an ES signal, P.' the motor will not start unless there is Decay Heat Closed Cooling water flow through the motor and its associated pump oil coolers. The DHR Pump will automatically start with an ES signal, regardless of motor cooling flow. There are alarms on Panel 8 to annunciate this no flow condition. The standby idle BWST Recirculation P"mp will automatically start if the running pump trips. -16B-196 096 ~ emumm y

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.-~. - p p a. g - PRINCIPAL MODES OF OPERATION _ .. f_.q.. - srl Startup pg, AhDp. After reactor shutdown when the reactor pressure .-.nd temp,rature ~/ are less than 320 psig and 250 F respectively, the system is placed in operation to further reduce the coolant temperature to approximately 140F and to maintain this temperature during the shutdown. Both Decay Heat Closed Cooling Water Systems are first placed in their cooldown mode (see System Description Index No. 29). This will require operation of both Nuclear Service River Water loops (Index No. 27) and stoppina Leakage Recovery System Cooling (Index No. 64b Cne BWST ReciFculation" Pump i5 unning with its control ~- - ~ ' switch in max and the other pr.mp is in standby with I its switch in AUTO. { 3.2 Normal Ooeration The Decay Heat Removal System has no function during nc. plant power operation. The system is normally operated to effect reactor plant cooldown and to maintain the reactor in cold shutdown. During normal refueling operation, coolant ia taken from Ehe 36 inch reactor outlet line through a 12 inch line fitted with two high pressure electric motor operated valves in series, DH-V1 and DH-V2, and exits the Reactor Building through penetration R-525. Immediately downstream of the building penetration, a low pressure electric motor operated valve, DH-V3, is proviucd to permit building isolation in the event of a LOCA. The line then connects to each ~of two 14 inch Decay Heat Removal pump suction headers through electric motor operated valves, (, , DH-V100A and DH-V1003, at each connection. At this point, two parallel, separate circuits are established. Each Decay Heat Removal pump, DH-P-1A/DH-P-1B, discharges through a 196 097

_ JCC 2~ - m -- - ; - g q. - e- _W' pf 10 inch line into the tube side of its associated cooler, ~ DH-C-1A/DH-C-1B, where the heat of the reactor coolant is transferred to the Decay Heat Closed Cooling Water System in the shell side of the cooler. Control valve DH-V128A/ DH-V128B may be used to throttle the outlet of each cooler (see explanation below). Each 10 inch cooler outlet line DH-V4. /DH-V4B, prior to is fitted with an isolati)n valve, A its re-entry into the Reactor Building through penetrations R "' d R-590 respectively. Within the Reactor Building, each line connects into one of two 14 inch reactor core flooding lines. The heat removal rate is normally controlled by throttling Decay Heat Closed Cooling Water Flow, DC-V73A and 73B. The rate may also be changed by running only one set of DH Removal and Decay Heat Closed Cooling Water Pumps. The above flowpath may also be used when the reactor loops are drained for Steam Generator or Reactor Coolant Pump / repairs. Special care should be used to maintain the core outlet nozzle below water. This prevents an air bubble from forming and a subsequent flow blockage. The Decay Heat Removal System connects to the pressurizer spray line from either circuit piping outside the Reactor Building. A 3" branch taps off each Decay Heat Removal Cooler outlet header, upstream of containment isolation valves DH-V4A and 4B respectively. Each branch contains a 3" stop valve (DH-V186A and 186B), a 3" check valve (DH-V185A and 185P) and then combine in a tee. Downstream of the tee, the flow is through 3" Reactor Building isolation valve ( DH-V187), into the Reactor Building, through a 3 " check valve ( DH-Vl90), i past a 3/4" drain connection to the pressurizer auxiliary 3: ('. +b 196 098

~ ~ - - me. & :.^.',. ": _E d C.5T spray valve, RC-V149. This permits pressurizer spray down 1R and cooldown which will reduce the reactor plant pressure and temperature. Spray flow to the pressurizer is provided by manually opening valve DH-V187 and electric.mptor operated valve RC-Vl49 located inside the Reactor Building. A " line at the outlet of each coolers pass through DH-Vll2A or DH-Vll2B to the hemistry laboratory. The sample line is used during system operation. A BWST Recirculation Pump is continuously in operation so that the BWST may always be sampled ( locally). 3.3 Shutdown During system shutdown all lines and components must remain filled with borated water to avoid water hammer during system startup. There is no automatic indication if the system has drained dcwn _since the last time.'the_ pump,s were used. An ([~ astute operator'should observe system pre [ssure high, sump ~~ level, _..and borated water on the floor. Surveilance testing is'honducted by opening the suction ~ valve, DH-VSA/DH-VSB, from~ the BWST, starting the pump in corresponding circuit,~and opening the appropriate circuit' ~ test valve DH-V108A/DH-V108B, an'd DH-Vll6 which returns the wat'er from the cooler outlet to the BWST. 3.4 Scecial or Infrecuent Ooeration 3.4.1 Filling the Fuel Transfer Canal After the reactor head has been removed, the DHR System, in conjunction with the Spent Fuel Cooling System, may be ] used to fill the transfer canal.__This is accomplishcd ~ .by adding water to_the__ system from the BWS_T while normal decay (_. 196 099 _19_ =-w..-

M.', "*J ' T T&. Ei! t_ heat removal is in progress. Either or both of the DHRS ( pumps'may be used for the filling operation by opening the ~ electric motor operated valves, DH-V SA/DH-V 5 B, and DH-V102A/ DH-V102B in their _ respective 14 inch pump, suction.line.from the BWST. Care must be taken during this operation to maintain the reactor water at a level consistent with normal recirculation. The SF System and associated pools may also be filled by opening DH-V157 and lining up the ~BWST to the SF System Pumps. 3.4.2 Recirculatina and Purifving the Coolant in the Fuel Transfer Canal The recirculation and purification operation is accomplished in conjunction with the purification loop in the Spent Fuel (SF) Cooling system. The Decay Heat Removal pump (s) discharges a portion from its reactor cooling loop to the SF System. ( The DHR Pumps discharge through the DHR cooler (s), a diaphragm operated globe valve (DH-V106A/106B), into a 2" line leading to the purification loop in the Spent Fuel Ccoling system. The coolant, after passing through the spent fuel filters and demineralizer in the purification loop, may be directed through 3" diaphragm operated globe valve, SF -V12 2, 3" check valve SF-V123 and 3 " gate v alve DH-V188 in a 3 " line which connects to the suction of the DHR pump (s) downstream of the Reactor Building isolation valve, DH-V3. The DHR pump (s) then discharges the purified coo] ant through the system piping into the open reactor vessel and fuel transfer canal. This mode of operation is also discussed in the Spent Fuel ? Cooling System Description (Index No. 19). -} (_ - 196 100 m 6.me-

/ 4. __1 ~ ~' ~ 7 ---97 h-3.4.3 Drainina the File'l Transfer Canal ( The fuel transfer canal can be drained to the level of the reactor outlet nozzles using the DdRS. A line connects from each of the cooler outlet lines through manual valves, DH-V108A/DH-V108B, to an 8 inch line leading to the BWST. At the completion of a reactor refueling with the DHRS operating in its normal mode, a portion of the cooler outlet flow is directed back into the BWST, thereby, lowering the level in the Euel Transfer Canal. Care should be taken during this operation to ensure that the reactor water level is maintained above the outlet nozzles to prevent air from entering the system. When the water level has been 1cwered to the approximate level of the reactor outlet nozzle, use of the DHRS for draining the canal must be suspended. The remaining water is removed by use of the Spent Fuel Cooling System (Index No. 19). (' 3.5 Emercencv Ooeration The DHRS is an engineered safety features system which is capable of injecting borated water from the Borated Water Storage Tank (BWST) into the reactor and accomplishing long-term core cooling af ter LOCA through two circuits, each capable of performing its safety features function independently. 4 v e 196 101 a

      • me.

. ll 4 ~~ zz -Y. g h- $Yh Emercencv Ooeration(continued) ~- ~ w.. (~ When an ES signal is received, both DHR loops are automatically lined up for injecting water from the BWST and Sodium Hydroxide e Storage Tank into the core. If the core outlet valves are open (i.e. if the DHR System were in the Decay Heat Removal Mode), the associated valves (DH-V2, 3, 101A, and 101B) would cluse. Similarly the DH valves which would line up Ehe BWST and Sodium Hydroxide Tank to the DHR, Makeup, and Building Spray Pumps (CH-CA, 8B, SA, SB, 102A and 102B) would open. The gate valves in the discharge path to the reactor (DH-V4A and 4B) would open, although the reactor pressure might be substantially above DHR Systgd[pressu~re.,, Check valves DH-102A and 102B wo61d remain seated and the DHR Pumps would start, circulating through the minimum flow line. Simultaneously, the DHR Support Systems (Nuclear Services River Water and Decay Heat ( Closed Cooling Water) would start to provide cooling to the DHR Heat Exchangers. As reactor pressure decreased to the discharge pressure of the DHR Pumps, the check valves DH-V102A and 102B would unseat and borated water would be injected into the core. Before the BWST and Sodium Hydroxide Storage Tanks were exhausted, Makeup Pump suctions would be shif ted from those tanks to the discharge of the DHR Pumps. The suction of the DH Removal Pumps (and the Building Spray Pumps) would be shif ted from the BWST/ Sodium Hydroxide Tank, to the Reactor Building Sump. The supply valves from the Tanks (DH-VSA, SB, 8A and 8B) would remain open, s r96 102 ~ -p ogemee, emman m

een; _ _ : r' .- ~' -a.:- and the suction _ supply valves from the Reactor Building ggc_ in[i - Sump, DC-V6A and 6B, would be manually opened from the Control Room. Check valves in the lines downstream of the Tanks prevent flow from the sump to the tanks. As Reactor Building (pump suction) and reactor pressure (pump discharge) gradually equalize, flow is throttled with DH-V128A and 128B to avoid pump runout and caviatation. If no action is taken a high flow alarm will annucciate. A high flow alarm might also be indicative of a rupture in that reactor supply line. Post LOCA mode suction from sump) could continue indefinitely by taking water from the sump, cooling it, and pumping it to the core via the core flooding nozzles. The Building Spray Makeup Pumps can similarly indefinitely operate in this mode by taking their suction from the Reactor Building sump and DHR Pump discharge respectively. The operation of the Makeup b and Building Spray Pumps are discussed in greater detail in their. respective System Descriptions (Index No. 17 and res'pectively 28A respectively). CD 96 03 O me. --i.- Q

^ '. ~ ~' hh5I 4.0 Hazards and Preda'utions w_. ( The DHR System has no makeup or pressure maintenance during normal power operation when it is isolated and shutdown. There is no automatic alarm is the sys tem drained down through the chemical sample line or to a sump. Secondary indications, such as the lack of head pressure on the pump gages, excessive liquid radwaste, and borated water on the floor, would be the prime symptoms of an inadvertent system drain down. To avoid excessive temperature transcients in the Decay Heat Closed Cooling Water System, cooldown should normally be varied by throttling DC-V73A and 73B. DHR and Decay Heat Closed Cooling Water temperatures should be closely monitored. If DH-V128A or V128B is opened, DH-V73A or V73B should be opened simultaneously to prevent high ( closed cooling water temperatures. I e To avoid DH Pump runout and/or pump cavitation, throttle system flow with valves DH-V128A and 128B. Nuclear Services River Water and Decay Heat Closed Cooling Water should be started and lined up to the DHR Cooler, before the DHR Pump is started. For non-emergency starting there is no interlock or automatic operation to prevent starting the DH Removal and Decay Heat Closed Water Cooling System before initiating flow Nuclear Service River Water flow through the associated cooler. ? Y s 196 104 O e = ____,mL

y ".* ~ mn. gpT" When both DHR Coolers are in operation, both Decay Heat Closed Water Systems are in their Decay Heat Removal Mo_de. \\ Limited cooling is available to the Reactor Coolant Drain Tank. The maximum Dra. T Tank temperature is limited to 150 h because the tank is used to quench the pressurizer relief valves. Normal Tank discharge and demineralized water (for a cold water supply) are available. During normal operation, the DHR Pump is not lined up to either of its three suction sources (Reactor Vessel, BWST/ Sodium Hydroxide Tank, and the Reactor Building Sump). If the pump inadvertently started, without a suction supply, it would run for a short time before destroying itself. Avoid DER System air binding by maintaining the reactor outlet nozzles below the water level when the reactor {, vessel is drained. The DER System contains reactor coolant and is therefore contaminated. Care should be used when handling the radioactive liquid and components. The BWST and Sodium Hydroxide Storage are nitrogen blanketed. Do not enter the tank without breathing apparatus. The DHR Pump suction strainer differential pressure should be periodically monitored during pump operation. This is especially important when the suction is taken from the Reactor Building Sump. h .C (< 196 105 -2 s - ~ e. s e 4*- -m - = = .=

__ k_, , d " ~ ~- 1 ~- r-g During a LOCA, the suction of the DHR Pump Suctions (and ,7 Building Spray) must be manually shifted from the BWST/ Sodium Hydroxide Tank to the Reactor Building Sump. If the manual transfer is not made, the DHR, Makeup, and Building Spray Pumps will quickly destroy themselves. Additionally, the Makeup Pump Suction must be manually shifted to the DHR Pump discharge. (: t ~ 196 106 _2e_ e --=m-m

i WT; "--! ' ~ r~'. - -TABLE 1 p-4 I~ . DECAY HEAT RE240 VAL PUMPS ( Pumo Details Identification DH-P-1A, DH-P-1B Number installed Two Vendor Babcock and Wilcox Co. Manufacturer Babcock and Wilcox Ltd., Cunada Type Single-stage, horizontal shaft, agle suction, centrifugal Rated Capacity, gpm 3 Rated TDH, ft. 3 5u (min.) NPSH, ft. 14 Speed, rpm 1750 Design Pressure and 520 psig @ 200F and Design Temperature 495 psig @ 300F Lubricant / Coolant Oil /DHCCWS (wa ter) Motor Details Manufacturer Westinghouse Electric Corp. k-Type LLD Horizontal Enclosure Drip-proof Rated Horsepower, hp ' 50 J S' peed, rpm 1750 Power 41607 45 amps (full load) 37 60 hz. Source DH-P-1A 2-lE DH-P-1B 2-2E Lubricant / Coolant Sealed Bearing /DHCCWS (wa ter) Classification Level Code ASME Code for Pumps and Valves for Nuclear Service 1968 Quality Control 2 Seismic I Cleanliness B j .~ C u " 196 107

4,_. d.--...fC ;~ %~' I "f Y TABLE 2 h DECAY HEAT REMOVAL COOLERS Identification . DH-C-1A, DH-C-1B Number Required Two Vendor Babcock & Wilcox Co. Whitlock Mfg. Co. Manufacturer Cleanliness factor . 0.85 Heat Transfer, BTU /hr 30 x 10 Tube Side: Fluid Reactor Coolant Fluid Flow, lbs/hr 1.5 x 10 Design Press. 520 psig @ 250F and Design Temp. 495 psig @ 300F Material 304 SS Press' ire Drop, psig 5.5 ( - Shell Side: Fluid Decay heat closed cooling water system Fluid Flow, lbs/hr-Source 1.5 x 10 Design Press. psig 150 Design Temp, F 200 Material CS Pressure Drop, psig 4.5 Level Classification Shell Tube Code ASME VIII ASME III (Lethal) Quality Control 2 2 Seismic I I Cleanliness C B e ~ ~ 196 108 228 -- - T

m._, 6,4,~ *[ "I' e ~ ~ O_ -- ~ { TABLE 3 ( BORATED WATER STORAGE TANK Identification DH-T-1 Manufacturer Pittsburg-Des Moines Steel Works capacity, gallons 472,964 Installation Vertical Outside diameter & length,ft. 35x51 Shell material 304 S.S. Shell thickness, in. @ O' El. 1/2 @ 51' El. 1/4 Design temperature, F 150 Design pressure, psig 3 Corrosion allowance, in. O Design code AWWA-D100 Code stamp required None Required ~ ( Classification Level Code AWWA-D 100-67 Quality control 3 Seismic I Cleanliness B 3 .a r( -~ 196 109 29 - ~*-- e w. p-- m,_ e =.* w -m e$

.-, 1,,- f 1m'.t.M~ ,-z ~ .e TA BLE 4 SODIUM HYDROXIDE STO9 AGE TANK { Identification DH-T-2 Manufacturer Buffalo Tank Div. Capacity, gallons 14,285 Installation Vertical Outside diameter & leng th, f t. 7 x52 Shell 1.aterial A -2 0 3-C Shell thickness, in. 7/16 to 1/4 Design temperature, F 150 Design pressure. 10' Column of H 0 above top of tank 7 Corrosion allowance, in. 1/16" Design code ASME Sec VIII (1971) Code stamp required None required C Cla s s ifica t ion Level Code ASME VIII Quality Control 3 Seismic I Cleanliness C 3 196 110 o - }gf ji -a M *- ..e

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TABLE 5 Y., BORATED WATER STORAGE TANK RECIRCULATION PUMPS { Pumo Details Identification DC-P-2A, DC-P-2B Number Installed 2 Manufacturer Crane Deming Model No. AA Type Process Rated Speed, rpm 3500 Rated Capacity, gpm 100 Rated total dynamic head, ft. 100 NPSH, ft. 10 Design pressure, psig 150 Design Temperature, F 250 Lubricant / Coolant Oil / Air (~ Motor Details Manufacturer Reliance Type Squirrel Cago Induction Enclosure Totally Enclosed Rated, Horsepower 7.5 Speed, rpm 3600 Lubricant / Coolant Oil / Air Power requirements 460V/35/60 Hz Power Source DC-P-2A MCC 2-32A Power Source DC-P-2B MCC 2-42A Classification Code N-3 Quality Control Q-3 Seismic I Cleanliness B 196 111 -3 1_- _-ame- _g ,--m-

p I 3r TABLE 6 q 0. + Decay Heat Removal System l Relief Valve and Vacuum Breaker Listing $1, Valve Identifica tion Service Location of Valve .Setpoint Back Pressure DH-Rl Relief Decay heat removal line from reactor vessel 370 psig Atmos. DH-R2A/B Relief Decay heat removal pumps, DH-0-1A /B, suction 370 psig Atmos. DH-R3A/B Relief Decay 7 lat removal pumps, DH-P-lA/B, discharge 520 psig Atmos. DH-RS Relief Borator water storage tank, DH-T-1 3.0 psig Atmos. DH-R6 Relief Sodium hydroxide storage tank, DH-T-2 3.0 psig A tmos. DH-R7A/B Relief Decay heat removal circuit "A" "B" return 520 Atmos. to reactor vessel DH-R8A/B Relief Borated water storage tank supply to decay 225 Atmos. heat removal pumps, DH-P-1A/B DH-R9A/B Relief Decay heat to make-up pumps 350 psig Atmos. i DH-V119 Vacuum Borated water storage tank, DH-T-1 1 oz/sq. in.2 Atmos. DH-V146 Vacuum Sodium hydroxide storage tank, DH-T-2 1 oz/sq. in.2 Atmos. NC as ; ha ... w. .41 s

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D oF r - f A A r r T A s r e f 1 H. a a l 3 l - m m e1 e o v nf f 1 3 l t D D. m w l l a p a2 o o h 3 h B a i o F o A A v s ol f f e e 1 v - r r r r t t 1 1 l oo i n3 n f l e o n n Ft Ft wt wt m mD l l d a n o w et n i i i i oi oi o g e l l o o i i gr wu wu l u l u p o R r a a o o F a o v u l L 4h o w w oc oc F c Fc l af o o t r t r r r I., g o n n C C l D l e 1 s .f g g e e ,v d l l /i /i wi si i2 i2 l l vd v) e n 4d Fl F F l C 1 C oC eC I. N. e ra i M I l Dr Dr T sM e u 4n tall r 1 n I e sS D 1 a - a n s s t A A A a u u s-e- s s 2 t 4 ,s n eg e e s s o s st st t2 t2 e e sI s e I 1) 1 ) o ti t t t t el el el el ea ea i F i - t t eI e t 1 i rs al al d a d a d a 'd a rr rr mt mt a a rL r3 a a - e - t e cu cu i v i v i v i v ue ue sO su c c u-u- 1 c vw i c i c vo vo vo vo s p s p n n i i s3 s ic mT mT 3 r - rF n no d r d r om om om om a m a m ad ad d d aF - d al a e a u ol ni ni re re r e re ee ee rn rn n n E e I el n D l D F CF I C I C FR FR FR FD MT MT Ta Ta I I MD M Di I lA( A ( r e t r r r t o o o i t l t t m a t n a r a a h h h h e e er er e e r s c m m c o i e c c c c c c r r r e r e r r e n i r r g i t t i i t t t t u u ut ut ur ur t a d a a e g s t net d d i i i i t t t t t t t o t o t r n l l s ip eri n n w w w w at at ai ai at at i T I A A rum I I S S s S r n r n r m r m r a r a m 6, u - r ee s ee ee es es ec ec l s l l l l e - c f sn w w w w w w pm pm pn pn pi pi en e e e e s f ea o o o o me me ma ma md md va v v s v e irr l l l l 1 i el el er er e n e n er e e e a D DFT F F F F F F TE TI TT TT TI TI LT L L t t s s. Y r n a 4 o

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tac 2 1 1 i T 1 2 t 2 3 4 1 2 1 2 l 2 2 1 2 f F t I s 3 s S E E T T I I T T J 3 3 .v i D F F r r F F T T. T T T T L L 1 1 1 e t -.j - n 1 1 1 1 1 1 1 2 2 2 2 2 2 3 3 3 3 3 gf, - e l s e D t D D D D D D t D C D 91 F 1 d e F F e e t a l E e D p a - I D t D IF F i l F IF t F l i F l s w i M. mo l C g g ( } I

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s, Choded Aorwo ed I, k T44 3 e TAst.S 7 (continued) e. -li I. ~ l Identification Description Ib nct ion Incation Input Range Output Range Setpoint I I fAl-4-TS Temperature Slement Measuree Temperature of Borated Water Tank 0-200 F 100 ogne 0 0 C N/A Storage Tank DIF4-TT input DIF4-TT Temperature

  • Transmite Signal from 081-4-T8 to DIF4-T1 Cable Room 100 Otel 8 0 C
  • +10VDC M/A Transmitter and ub4-TS1 l

tmF4-71 Temperature Indicates Temperature of Sorate<1 Water ranel a

  • 910VDC 0-200* r M/A Indicator Storage Tank ( Dti 1)

DsF4-Tr Temperature Trane. 85837 Temperature for Dis-4-TS1 and ub4-752 , Panel 9 +10VDC 100 cha 1 0 C N/A o DIF4-111 Temperature Switch Provideo Tesserature Alarm on Borated Cable Room +10VDC N/A

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Water Storage Tank 110 r gia) 01-4-732 Temperature Switch Provideo Temperature Control for Cable Itoom +10VDC H/A 50 r (Dal Water storage Tank lleatere 55 r (Of f) p>5-P11 Pressure Indicator Indicates Discharge Pressure of ul-7-1A Fack M2 0-600 peig 0-600 pelg ps/A l al-5-r32 Pressure Indicator Indicates Discharge Pressure Dai-t-la Back M 1 0-600 peig 0-600 pelg p/A Dil-6-TE1 Temperature Slement Measures Inlet Temperature of DiFP-1A Paping 0-350 F 0-350 F N/A i l DIF6-TS2 Temperature Slement Measures Inlet Temperatore of Dei-P-la Pipin8 0-350 F 0-350 F N/A Oti-6-TT1 Temperature Transmite Signal from DH-6-TT1 to Cable Room 0-350 F 110VDC H/A Transmitter al-6-TS1 and D15-4-T11 twi-6-TT2 Temperature Transmite Signal trose Ds!6-TT2 to 011-6-152 Cable Ibom 0-350 F '+10VDC M/A Transmitter and Dil-6-T11 soo'r DF6-711 Temperature Switch Provideo Temperature alarm for Dil-P-1A inlet Cable room 410vDC g/A Di>6-TS2 Temperature Switch Provides Temperature 41 arm for DH-P-15 inlet Cable poom .ovDC M/A 300 r. DeF6-TIl Temperature Indicates temperature for DII-P-1A inlet tanel 8 +10V[c 0-350 F p/A Indicator ub6-712 Temperature Indicates Temperature for ul-r-la inlet ranel 8 +10VDC 0-350 r p/A l Indicator DtF7-LT 14 vel Measures tavel in the Sodiwu ttydroulde Tank 0-50 ft. 9-50 a..a oc N/A Transmitter Storage Tank (tAFT-2) DIF7-1.S Level Alarm Alarms fit and 1414 vel in Sodlum Cable Room . 0-50 ma N/A 44.5' IIA ttydronide Sterage Tank 46.5' t ill OsF7-1,1 14 vel Indicator Indicates I 't in Sodium Irydroulde Panel e e10Vit 0-50 ft. p/A -y,. am

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) f ..,,, e N .=. t a w c... ~ DURNS AND R,OE.!NC. e.s. j W O. No Dase took No, Page No. e q o. ,,eue. Ca n.. sw s .e 5 g, - Sy Check ed Appeved The (~% t" ' l m n TABLE 1 Continued) i Identification Description ranction tocation Input Range Output Range Eetroint i DtFS-TE Tem [erature pea-ures Temperature of Soditen Itydruzide Tank 0-200 F 100 alm 0 0 C M/A Element Storage Tank DFS-TT Temperature Transmite signal frcan teF8-TE to ut-0-TSI Cable Room 100 OHN O O C

  • .10Vtc N/A g

Transmitter & 03-0-T1 g DFS-T! Temper a tur e Indicates temperature of Sodium Hydtcalde Panel 8 g 10VDC 0-200*r N/A. Indicator Storaga Tank ( De t-T-2 ) DikS-TS1 Teeperature controle Temperature in sodium atydroxide 4 Cable Room ,tovDO* 4 Switch / Alarm storage Tank and actuates heatore N/A 45'r g Q 55 r loff) D86-4-T32 Temperature Provides Tamperature alarm in Soflue a j Cable Room e10VEC N/A ggg*pgug [ Switch /Alari trydroulde Storage Tank 50 r ( L) Del-9-PI Pressure Indicator Indicates Pressure of todium Hydroxide errG Y3 0-1 peig 0-5 peig m/A storege Tank ( 011-T-2 ) ( Dit-10-PSI Pressure Ewitch Alarme lit pressure in D.H. supply line Panel 8 g.600 pelg 330 pelg I D FPLA-MIS 8tand Switch Controle DFP-1 A Panel 3 M/A N/A N/A DFP18-MIS Hand Switch Controle pl-P-la Panel 3 g/A N/A w/A 8 g DIEVI-MIS Hand s itch Controle DIEV1 Panel 3 N/A N/% N/A w teFv2-MIS lland Switch Controle Oti-V2 Pasiel 3 N/A N/A N/A ps-V3-mis lland Switch Controle ofEV3 fanel 3 N/A N/A N/A Dit-V44-MIS Stand Switch Controle DEF"4A Panet 15 N/A N/A n/A k tsFv43-n1S Iland Switch Controle 1. - 28 Panet 15 M/A N/A N/A Del-2-TE1A Temp. Element Dil-C-1A outlet Temperature piping Input Piping 0-300 r 100 ohe 0 0 C N/A to YH-TR-1922 on Panel 10 DH-2-TE2A Temp. Element ul-C-1B outlet Temp 9rature Input to Piping 0-300*r 100 ota 0 0 C N/A f YN-TR-1922 on Penel 10 f DIFV6A-MIS Iland Switch Controls Dl.vf A Panel 15 N/A N/A N/A pl-V08-MIS Iland Switch Controls DI.v6B Panet 15 N/A N/A N/A DEV7A-Mis Itand switch Controle DI.V7A Panel e p/A N/A N/A (MFV78-MIS Iland Switch Controls Dt.v78 Panel 8 M/A N/A pjA CN 088-6-T564 hap. Element Dis-P-1A Teeperature Input to YM-TR-1922 Piping 0-350"r 100 ohm 0 0 C H/A Panel 10 ~ Dis-6-TE6e Temp. Element ut-P-18 Temperature Input to YM-TR-1922 Piping 0-350*r 100 otus 0 0*C H/A .._.n._,. 4- ... ~.

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p a m I M l n n i t F m m l e l e e u T w w d e o o t l T 4, a T c o o ev t i i l e 1 I d r t l i r i t t e v p n / / a n i a a F r o n o c v 4 p o 1 l o o c l p pp U u u e I o i N I l i e t g A B l A C o l S L T t r t p a NI N e k c l e c O p p l p e k n k u e p v u k o o o E, ho b m s n a n s v m o s n r t o o e a u u a T a e e a e l l O B t P P T T p t T y p T l w r m r m o o n. n R e 1 l e e e u k k u u e, o l o o D V s a g g g P n n P P C F i i v v a a e a a s t t N d o n r r r t T T l t r l l c c A e n ni o o o a a a o a a e e r o e t t t v e o v v t v v j j S u h m s r s o d d o o S o o n n N s m l l m m m m I i R a t t r r r o a a e e r e a e e s e e e p o o R m e R R e e U B ls. M le i t t t r r t r r) a e a a a t d d t t a t t u) us e, l w w w a ry ty a s w a a ss st d e C y y e t s H l d H H e eg e, d a a d d d H ie e e sE s e e e S c c e e e m e e rg rn s k R e e t t t y u i a a a a a i r r y t y y P n Pi c D D a a s a i W e r r r c d d c c r c c a r C A A 8 o o o e o o e e o e e mna wa te h o m e I 2 2 B B B D s s D D B D D I i C ( t( D t/tN N A n D o E 9 T i 3 5 4 0 0 5 6 t M a 6 6 8 5 7 5 4 5 1 5 7 5 4 2 3 c 4 4 4 4 4 5 4 4 5 5 8 5 5 4 4 A K i 0 0 5 r 5 4 5 5 5 4 1 4 4 5 5 f r r 4 J 4 l 4 4 4 7 e r 4 4 i t t 1 l H t I a L t A A A A A A A A A A A A A A A 2 T E T t 1 T t T E T F r r 2 o E n P P o M. . N N e F E e D D D u l u r D D D D D n og A d i D D E e l t e F I t 6 i e e P I D l F F i t D D i 6 b c F N. ta e 0n yh r n M a wOB T e g C I p. g i.

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