Text

Final Rept, Sys Description:Reactor Bldg Emergency Spray Sys, Ref Burns & Roe Drawing 2034,Revision 16
	ML19224B280
Person / Time
Site:	Crane
Issue date:	01/31/1976
From:	; Metropolitan Edison Co
To:	Mullinix W; NRC/IE
References
	TM-0294, TM-294, ZAR-760131-1, NUDOCS 7906140361
	Download: ML19224B280 (34)
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REACTOR BUILDING ErdRGENCY SPRAY SYSTEM (B&R Dwg. No. 2034, Rev.

16)

JERSEY CENTRAL POWER & LIGHT COMPANY TBREE MILE ISLAND NUCLEAR STATICN i

UNIT NO. 2 Issue Date

,. January, 1976 Prepared bf:

J. Hooper Burns and Roe, Inc.

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700 Kinder 2.amack Road

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Oradell, N.J.

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TABLE OF CONTENTS FOR REACTOR BUILDING EMERGENCY SPRAY SYSTEM Page

1.0 INTRODUCTION

1 1.1 System Functions 1

1.2 Summary Description of System:

2 1.3 System Design Requirements 4

2.0 DETAILED DESCRIPTION OF SYSTEM 6

2'l Components 6

2.2 Instruments, Controls, Alarms and 11 Protective Devices 3.0 PRINCIPAL MODES OF OPERATICN 13 3.1 ltartup 13 3.2 Normal Operation 14 3.3 Shutdown 16 3.4 Special or Infrequent Operation 17 3.5 Emergency Operation 18 4.0 HAZARDS AND PRECAUTIONS 19

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t APPENDIX Title Table No.

Reactor Building Emergency Spray Pump

,1 Sodium Thiosulfate Storage Tank 2

Instrumentation and Controls 3

Panel-Mounted Annunciators and Protective 4

Devices Set Points Computer List 5

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.t REACTOR BUILDING EMERGENCY SPRAY SYSTEM l.O INTRODUCTION l.1 System Functions The reactor building emergency spray system serves an engineered safety features function, along with the building emergency cooling system, to cool the reactor building atmosphere following a reactor coolant system piping rupture, thereby effecting a pressure reduction within the building, and consequently, minimizing the potential leakage of radioactivity from the building to the site and surrounding areas.

'r T fe' spray ~ system also f'unctio'nT W ieEtI5e'.~radiciodine from the reactor building atmosphere by chemical reaction and to wash suspended particulate radioactivity out of the reactor building

, atmosphere.

The cooling action is accomplished by spraying water into the reactor building atmosphere, in order to remove heat from the steam released by the piping rupture.

The fluid for the spray system is supplied from the horated water, sodium hydroxide and sodima thiosulfate storage tanks and is discharged into the reactor building by a pump in each of the two system circuits.

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thiosurfate reacts with radiciodine and renroves u f rom-th e-bui-1<Mng---

Tn e hr-that the oudima Liu.usulface remai1Ts stable la L1 atmosphere!

borated water, sodium hydroxide is added to raise the pH of the borated water and maintain it in the alkaline range.

The chemical solutions are gravity fed from their respective storage tank's to the line leading to each system pump.

The chemical storage tanks and their outlet lines are sized to drain at a

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rate proportional to the drainage rate of the borated water

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storage tank.

When the borated water storage tank supply has been exhausted, the reactor _ building emergency spray system functions in a g

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-r recirculation mode by taking suction from the reactor building sump and returning the water to the reactor building by way of the spray system., The post-accident building spray is used in the recirculation mode to continue removal of heat and imine from the reactor building atmosphere.

The reactor building emergency spray system has an interface with the dacay heat removal system in that the spray system pumps take suction from the supply headers f.or the decay heat removal pumps, and during system testing, discharge into the decay heat removal system return line to the barated water storage tank.

The system has no normal operating interface with any other plant system with the exception that each pump motor is cooled by water from the nuclear services closed cooling water system.

1.2 Summarv Description of System (Refer to B&R Dwg. No. 2034, Rev. 16 )

The reactor building emergency spray system discharges borated water into the reactor building atmosphere after a loss of coolant accident (LOCA) to coo 1 the steam released due to the casualty and thereby prevent overpressurization by effecting building cooldown.

System operation is automatically initiated upon receipt of signals from the safety features actuation system (SFAS).

Alkaline sodium thiosulfate and sodium hydroxide are introduced with the spray for radiciodine removal and pH control.

The system also functions to provide long term, post-accident building cooling by recirculating the water from the reactor

-2 building sump through the spray system.

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-t cq pump for heat removal (100% capacity for iodine removal by sodium thiosulfate injection) which takes suction independent 1y' from a decay heat removal system supply header.

Each of the two Reactor BuiIding-Spray Pump Suction headers is connected to the borated waE Sodium thicaul ~ ate--and sedium hydroxide storage tanks and to the reactor building sump and can therefore provide the building spray pumps with suction initially from the borated water storage tank and also from the reactor. building sump, while at the same time, the decay heat removal system is performing its emergency

function, Each of the suction lines to the building spray pumps contains a remotely actuated, electric motor og rated stop valve and a check valve in series.

The electric motor

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operated stop va1ves are normally maintained in the open position and are closed only during normal operation of the decay heat removal system or when isolation of a circuit is requi ed as during maintenance work.

The pumps are cross-connected at the suction but are normally isolated from each other by two stop valves in the interconnecting line.

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separate--i-ine finted-with a normatiy utosed n emetel.y actuated 7 electric.. motor-operated-stop aalve connects + vach-puntp o uution r.pm 'he--sCCFlum thiosulfate s tbrage-tank-outi-et. -The s e--

va-Lues-- m e automaticaAly vpened upon receipc vf a signa 4.--from tjLc SFASL.

The discharge of each pump is routed through an individual reactor building penetration and connects to separate spray headers in the upper portion o'f the reactor building.

Each discharge line is provided with a normally closed, remotely actuated, electric motor operated throttle valve at the pump discharge which opens automatically upon a signal from the SFAS, 5

and a check valve inside the reactor building.

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A test connection is provided frca each of the pump discharge line s, upstream J

of the electric motor operated throttle valve, which returns the pump discharge to the borated water storage tank via the decay heat removal system return line to that tank.

During in-service testing, the pumps take suction from the borated water storage tank and recirculate back to the tank.

Another test connection is provided downstream of each discharge throttle valve to introduce low pressure air or smoke to the spray headers to check for nozzle flow.

The system is automatically activated upon receipt of signals from the cafety features actuation system.

The electric motor operated valves, necessary for system operation, opened at a building pressure of 4 psig, and the pumps are started at a building pressure of 30 psig.

Remote manual activation by operator action is also provided.

1.3 System Desicn Recuirements The reactor building emergency spray system is desig ned to provide sufficient heat removal capability to limit the pressure rise in the reactor building, following a design basis accident, to a point below the 60 psig design pressure of the building, without credit for heat dissipation to the building structure.

This capability is predicated upon each of the two 50% capacity circuits delivering 1500 gpm of spray to the reactor building after the accident.

However, to provide redundancy,. this heat i

removal requirement is also fulfilled by each of the following:

all five of the reactor building emergency cooling system fan-cooler units in operation; or, three fan-cooler units and one F96 193

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Therefore, with either the reactor building emergency spray system, the reactor building emergency cooling systcm or a combination of the two systems being cepable of providing adequate cooling of the reactor building atmosphere, the building integrity will be maintained following an accident and the building pressure will be decreased at a rate which satisfies the site criteria.

The water is introduced into the reactor building atmosphere through two spray headers each containing 96 spray nozzles.

Each spray nozzle delivers approximately 15.5 gpm upon system actuation immediately folicwing the accident.

This flow rate increases sligntly with time as the building pressure decreases as a resv.it of cooldown.

The water la supplied from the borated water sodium hydroxide Nsu4-fate-storage tanks until the tanks are empty.

Thereafter water collected in the building sump is recirculated through the spray no==les.

The sump water, in all cases, meets the NPSH requirements of the spray pumps with the

__ building spray system in the recirculation mode.

Major system components consist of two pumps, the codim r h i osu l f a t a =+-mage >,nk, two spray headers _with fixed spray no==les, interconnecting piping and electric motor operatad valves capable of automatic opening.

The borated water storage ta.nk and the sodium hydroxide storage tank, although not expressly designated as part of the reactor building emergency spray system, serve an integral function with ~ respect to system operation (see Decay Heat Removal System Description, Index.Jo.

20 for further information).

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suction line from the borated water storage tank which provides, in paEj the initial supply of spray water for approximately the first 40 minutes is sized to deliver the expected flows of two decay 9

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heat removal pumps (3000 gpm each), two high pressure makeup,

pumps (500 gpm each), and two building spray pumps (1500 gpm each) plus some margin of runout for each pump.

The tank will deliver approximately 403,000 gals. of water at a minimum concentration of 2270 ppm boron.

The design pressure and temperature of the spray system are 350 psig und 300F, respectively.

Major system piping is classified as Nuclear, Symbol N, designed, fabricated, inspected and erected in accordance with ANSI B31.7, Nuclear Piping.

The seismic requirements of Ciass I apply to the entire system including all components.

Monitoring of system performance and control of system operation is provided in the control room 2.0 DETAILED DESCRIPTION OF SYSTEM 2.1 Components The components in each circuit are identical and each circuit provides a 50% capacity for building cooling and a 100% capacit for iodine removal.

Used in conjunction with the reactor building emergency cooling system, it provides sufficient heat removal to

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prevent over-pressurization of the reactor building in the event of a loss of coolant accident.

Since the system is an engineered safety features system, neither circuit can be out of service except for brief periods during which maintenance is being per-formed on system components.

2.1.1 Reactor Building Spray Pumps, BS-P-1A/BS -P-1B The reactor building spray pumps (see Table 1) are single-stage, horizontal-shaft, single suction, centrifugal pumps rated at 1500 gpm each with a total discharge head of 450 ft.

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%culfate storage tanks entil the supply in the tanks is nearly exhausted and then recirculate the accumulated water from the reactor building sump back to the reactor building through the spray nozzles.--

Cooling water for the pumps' motors is supplied by the nuclear services closed cooling water system.

The pumps are autonatically started by a signal from the safety features actuation system, or can be remotely activated from the control room on the Auxiliary Systems Control Panel Number 3 by operator action.

Testing of the pumps' auto-start feature is possible from the Safety Features Actuation Monitoring and Test Panel No. 13.

Electric Power supply to the pump's motor is provided from the 4160V engineered safety features 9 busses 2-lE for BS-P-1A and 2-2E for BS-P-1B.

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n 2.1.2 Sodium Thiosulfa :e Storace Tank BS-T-1 i

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solution for approximately 40 min. after the'LOCA./ The sod ium I

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Heater con al is automa ic.

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2.1.3 Reac or Building Sorav Nozzles The Rdadt6r' Building ~6 pray no=Zles ari manufactured by Spray

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Co. (model #1713) and are designed to deliver approximately 15.5 gpm at a building pressure of 60 psig with a 4d pai pressure drop through the nozzle.

The noz=les e ce capabl6 of passing particales up to 0.25" in diameter without plugging.

Filtering screens in each reactor building sump outlen line are also sized to pass particles up to this dimension.

Ninety-six spray no==les are fixed in each of the two headers.

The spray headers follow the contour of the reactor building dome at an elevation of between 449'-09" ar d 468'-05" within the building.

2.1.4 Borated Water Storace Tank DH-T-1 Although not expressly designated as a component of the reactor building emergency spray system, the borated water storage tank serves an integral function with respect to initial system operation fo'. lowing the loss-of-coolant accident.

The tank

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' Table 3) is a vertical cylinder, 37'-06" outside diameter, with a vertical straight section of 50 ft. and a self supporting domed roof.

The overall height of the tank *is 60'/04-3/4" and_,_ _

t5 the dry volume i-f 472,964 gals.

The tank is physically located outside of the auxiliary building.

Thermal insulation and redundant electrical heat tracing is provided to automatically maintain the liquid at a minimum temperature of 40F.

The tank will deliver approximately 403,000 ga.1r. (Normal level to Lo/Lo I,evel) of water at a minimum concentration of 2270 ppm boron and provides a source of borated water for the building spray pumps, as well as the decay heat removal pumps (for low pressure injection) and the high pressune makeup pumps, for-approximately 40 minutes after a LOCA.

2..l.5.: Sodium Hydroxide Storage Tank DH-T-2 The sodium hydroxide storage tank is also not expressly designated as a component of this system but serves an integral function following a LOCA.

The tank (see Decay Heat Removal System description, Index No. 20 Table 4) is a vertical cylinder, 84" in outside diameter with an overall height of 52 ft.

and a dry volume of approximately 14,285 gal. of water at a concentration of 20,000 ppm MaOH.

The delivered volume following the LOCA is approximately 11,600 gals.

The sodium hydroxide establishes an alkaline pH in the borated water which is injected into the reactor building after the accident te r.nintaen the Whit 4 y M4e-sodium--thiosuJ, Sate-wh-i-ch is added-for iodine--

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The tank is physically located outside of the auxiliary

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building and thermal insulation is provided.

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maintain the' liquid temperature at approximately 40F.

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2.1.6 Maior System Valves Reactor Buildino Sor v Pumo Discharge Valves-BS-V1A, BS-VlB Cne 350 psig, 300F, 8 inch, SS, electric motor operated globe valve is provided in the discharge line from each reactor building spray pump.

The valves are opened autcmatically within 10 secs.

by a signal frcm the safety features actuation system.

Remote manual operation of each valve is provided from the coolant Systems Monitoring Panel No. 8 in the control room.

Cycling of the valves for periodic test purposes is controlled from the Safety Features Actuation Monitoring and Test Panel No. 13.

During system operation, as the reactor building pilessure decreases, the valves are remote manually throttled to prevent pump runout.

Power supply to the electric motor valve operators is provided from the 480V motor control centers 2-llEA for BS-V1A and 2-21EA for BS-VlB.

Reactor Buildino Spray Pump Suction Valve from Eecav Heat Removal Suction Headers - BS-V3A, BS-V3B One 200 psig, 300F, 10 inch, SS, electric motor operated gate valve is provided in the suction line from the decay heat removal system suction headers to each building spray pump.

These valves are normally maintained in the open position except during operation of the decay heat removal system when the removal system is serving its normal functions.

In these cases, ES-V3A

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and BS-V3B must be closed by opera tor action to isolate the

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The v:lves are remotely controlled from the control room

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valve operators is supplied from the 480V motor control centers 2-llEA for BS-V3A and 2-21EA for BS-V3B.

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One 350 psig, 300F, 4 inch, SS, electric motor operated gate is provided in/

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the sodium thiosulfate s1.orage tank.

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System ls Monitoring

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ators is provide from the 480V motor control centers 2'-11EA r

BS-V4A\\gd 2-21EA for BS-V4B.

v 2.2 Instruments, Controls, Alarms and Protective Devices Instrumentation is provided in the ; control room en' the Auxiliary Systems Control Panel Number 3 for the reactor building emergency spray system to monitor system performance during testing, standby and during actual operation.

(See Table 3).

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A listing of panel mounted annunciator, relief valve and vacuum

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breaker setpoints is given in Table 4.

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annunciated in the control rocm on the coolant systems Monitoring Panel No. 8.

The reactor building spray flow in each circuit is monitored and indicated in the control room.

High and low flow alarm contacts are provided for annunciation.

The low flow alarm is inte2-locked with the reactor builcing high-high pressure monitors to annunciate only during an emergency condition, i.e.,

when the' building high-high pressure monitor has been tripped.

This~ arrangement permits the Low-Flow Alarm to function as a monitor to verify that the Building Spray pumps--have started.

Local instrumentation is also provided to indicate the suction and discharge pressure of each pump with low suction pressure alarmed'in the control room.

The temperatsre and level in the sodium thiosulfate storage tank is monitored and indicated in the control room with high and low condition for each parameter, annunciated.

A gauge glass is fitte.d to the tank for local level indicatien.

The temperature of the solution in the tank is automatically maintained by redundant electrical heat tracing.

A tabulation of the instru- ' -

mentation to the borated water and sodium hydroxide storage tanks can be found in the Decay Heat Removal System Description, Index No. 20.

A relief valve set at 350 psig is provided at the suction of each building scray pump to preclude overpressurization from inadvertent reactor coolant system leakage through closed valves when the spray system is idle during -normal reactor power operations.

A vacuum breaker and pressure relief valve are fitted on the sodium thiosulfate storage tank to prevent damage to the tank.

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For details concerning actuation of the reactor building emergency spray system, refer to the Safety Features Actuation System description, Index No. 50.

3.0 PRINCIPAL MODES OF OPERATION 3.1 Startup Startup of the reactor building emergency spray system consists of testing the operation and performance of the system and preparing it for normal stand-by service.

The borated water storage tank is filled with demineralized water and boric acid to establish a 2270 ppm minimum baron concentration if this has not already been accomplished.

With the circuit electric motor operated discharge valve closed and suction lined up from the borated water storage tank, each pump is started individually and flow is recirculated to the storage tank. Flow rates and pump suction and discharge pressures are noted and recorded for future reference in determining system performance.

System piping up to the circuits ' discharge valve BS-VlA/BS-VlB are maintained filled with borated water.

The automatic actuation feature of all related equipment, including all electric motor operated valves must also be tested to ensure proper operation.

An air or smoke supply is introduced into the nozzle air test connection for each circuit to check for' free flow through the noz=les.

Visual observation of the ribbon indicators attached to each nozzle or of the smoke is required to verify proper nozzle -

operation.

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tank is fi'11e with demineralized Th sodi/

A wat r and sodium tra.osulfate to roduce a 30, m co centration in t e ta T e ta ou let -lin and each b g to th il ing '

spra pump s ion line, up a the. tor oper$t'ed valve is fill h,.f 3':',;,s.gfgQ.

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A n'itrogen-overpressuru ut-~3p roxima te ly 4 psig-1s intr'oducedtto the tank to maintain an inert a t?:Tospherc.

Me-system is then_. lined-up-and-maintained -in-a- atandby uundItte r ready __br emergency opef~ation.r-. It must be ensured that the sodium hydroxide storage tank is also filled and at the prescribed concentration of 20,000 ppm NaCH.

F A low point drain line is provided in each circuit inside the reactor building and fitted with manual stop valves BS-V106A/

BS-V106B.

The purpose of the drain lines is to prevent water from reaching the spray headers by leakage through the building spray pumps' discharge valve during system testing.

These drain lines are sized to pass approximately 16 gpm (flow through'one spray' nozzle) and must be opened prior to reactor startup and remain open during reactor operation.

3.2 Normal Operation The reactor building emergency spray system serves no function during normal plant power operation.

The system provides an engineered safety features function and is a :tuated by signals from the safety features actuation system following a reactor coolant system piping casualty which increases the reactor building pressure above pre-set points.

The system can also be manually placed in service by operator action, if required.

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Upon receipt of an actuation signal, the circuits ' discharge valve BS-VlA/BS-VlB, the W4" thhlfa w adsply v a l.v e s,

.as. V4AZBS-V4n_. and the valves in the lines from the borated wat : r

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storage tank (DH-VSA/DH-VSB) and sodium hydroxid.e storage tank. (DH-V8A/

DH-V8B) are automatically opened followed by automatic starting 3d[.'

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The pumps take suction independently through 'O in. Lines, fitted with electric motor operated valves BS-V3A/BS-V3B (normally open),

from each decay heat removal pump' suction header.

The suction headers are supplied with water from the borated water and sodium hydroxide storage tanks through independent lines fitted with safety features actuated, electric motor operated valves DH-VSA/DH-V5B and DH-V8A/DH-V8B.

The suction lines to the pumps can be cross-connect ed but are normally maintained isolated by manual stop valves, BS-V101A and.BS-V101B.

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each-branch-Line.--i.s-provided with-a-safety-featuresactuated ele ctr.ic-mo tor---

operated.-valvo.,mBS-v4A/_BS. VP The pumps discharge to m.Jependent 8 in. lines fitted with electric motor operated throttle valve BS-VlA/BS-VlB.

These valves are opened fully upon a SFAS Signal but are. remote.

manually throttled in order to prevent pump runout as the reactor building pressure decreases due to cooling of the atmosphere after the accident.

Downstream of the throttle valve, each pu:.

discharge line enters the reactor building through a separate penetration, R '586 for circuit A,

-nd R-583 for circuit B.

Downstream of the building penetration, the piping size is reduced to 6 in. and each line is provided with a check valve for building isolation.

Each circuit is then routed to one of the two spray headers in the upper part of the reactor building.

Physical space limitations within the building required that the 6 in. supply line to each spray header be reduced into 4-4 in. risers, ascending along the reactor building wall and

- reconnecting at the header.

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Before the, supply of water in the borated water storage tan}c' p-..

is exhausted, (approximately 40 min.), the control room operator is alerted by annunciation of the low-low. storage tank.'.evel alarm.

At this time, the suction supply to the pumps murt be transferred from the storage tank to the reactor buiJ.. ling sump.

The operation is performed by action of the control room ope'rator.

The electric motor operated valves, DH-V6A/DH-V6B, in each of the reactor building sump lines to the decay heat removal p.,.mp suction headers are opend, and the supply val.ves DH-VSA/11-v5B from the borated water storage tank, ES "4 /nc-v4B from-t-hu-s Odi-um-thiosul A P e storag_n P-m.-and DH-V8A/DH-V8B from the sodium hydroxide storage tank,to the headers are closed.

Hand switches on the Safety Features Actuation Monitoring and Test Panel No. 3 provide for negating the safety features actuation signal (once the signal has been tripped) se that these valves may be closed.

Cnce the safety features actuation signal has been negated, these valves are closed by depressing their respective actuation switches from the control room.

The reactor building emergency spray system, in this mode, recirculates the water from the reactor building sump through the spray system, and discharges the water into the reactor building atmosphere to continue iodine removal as well as building cooldown and depressurization.

3.3 Shutdown When the. building spray system is shutdown, as is the case during normal reactor power'or shutdown conditions, it is maintained in a standby status with all valving except the safety features

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actuated, electric motor operated valves positioned for system j

operation, and the pumps available for automatic start.

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+r maintenance to equipment in one circuit of the sys tem is required, it must be ensured that the other circuit is fully operable and available in the event of an emergency._._

To shutdown a circuit for maintenance, it is only necessary to de-energize the pump and the safety features actuated valves, close and de-energize the electric motor operated pump suction valve (either BS-v3A or BS-V3B), and close the associated manual valves to isolate the circuit and/or component requiring maintenance.

Following a system test, the building spray pump (s) must be manually stopped and the valves, opened for the test, must be closed and. the system control switch positioned for automatic operation.

3.4 Soecial or Infrecuent operation Provisions have been incorporated into the system to allow testing of each circuit pump and for testing spray nozzle ficw during reactor operation.

Pump performance can be determined by operating the pump taking suction from the borated water storage tank through electric motor operated valve DH-VSA of DH-V5B and discharging through manual test valve BS-VlO3A or BS-V103B and BS-V104 back to the storage tank via the decay heat removal system test line.

The suction and discharge pressures of the pump and the circuit flow is noted and recorded for comparison with initial and prior test results to determine system performance.

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The nozzle flow tes't is perforr.ted by introducing air or smoke through the nozzle test connection, for each circuit, fitted

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.E. mercency Operation Reactor building emergency spray is initiated upon an abnormally high reactor building pressure sensed by redundant pressure monitors within the building.

System activation is a function of the safety features actuation system (see System Description, Index Number 50).

Operation of tne system in the emergency mode is identical to that which has been described under " Normal Operation",

Section 3.2 of this system description.

Additional sodium hydroxide h ed+u eth m u du w may be added to the recirculating water during post-accident operation, if deemed necessary. The solution is added to the respective storage tank from the causti,e mixing tank, via the addition pump, in the chemical addition system and then y

1 introduced into the recirculating water by opening the appropriate storage tank outlet valve (s), once a water level in the storage tank has been established.

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The principal hazard associated with this system is inadver-tent actuation when no emergency condition exists.

Such an occurrence with the reactor in operation or in a shutdown condition could cause damage to equipment and electrical

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Since manual activation w

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Also, prior to routine periodic test of the system pumps, a visual observation of the electric motor operated throttle valves BS-VlA and BS-VlB should be made to ensure that the valves are fully closed.

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ML19224B280

Contents

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1.0 INTRODUCTION

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1.0 INTRODUCTION

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