ML19262A517

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Final Sys Description (Index 64),Radwaste Disposal Reactor Coolant Leakage Recovery Sys (Burns & Roe Drawing 2632, Revision 2)
ML19262A517
Person / Time
Site: Crane Constellation icon.png
Issue date: 04/30/1976
From: Iskyan H
BURNS & ROE CO.
To:
References
TASK-TF, TASK-TMR PROC-760430, NUDOCS 7911090551
Download: ML19262A517 (20)


Text

"

/q FINAL SYSTEM DESCRIPTION (Index No. 64)

RADWASTE DISPOSAL REACTOR COOLANT LEAKAGE RECOVERY SYSTEM (B&R Dwg. No. 2632, Rev. 2)

JERSEY CENTRAL PCWER AND LIGHT CCMPANY THREE MILE ISLAND NUCLEAR STATION UNIT No. 2 Issue Date April, 1976, f919'287 Prepared by:

H. Iskyan Burns and Roe, Inc.

700 Kinderkamack Road Oradell, N.J.

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07649

TABLE OF CONTENTS Section Pace

1.0 INTRODUCTION

1 1.1 System Functions l-1.2 Summary Description of System 1

1.3 System Design Requirements 3

2.0 DETAILED DESCRIPTION OF SYSTEM 4

2.1 Components 4

2.2 Instruments, Controls, Alarms, and Protective Devices 6

3.0 PRINCIPAL MCDES OF OPEFATIGT 8

3.1 Startup 8

3.2 Normal Operation 8

3.3 Shutdown 8

3.4 Special or Infrequent Operation 9

3.5 Emergency 10 4.0 HAZARDS AND PRECAUTIONS 10 1919 288'

+w

-o e

APPENDIX TITLE TABLE NO.

Reactor Coolant Drain Tank i

Leak Transfer Pumps 2

Leakage coolers 3

Instrumentation and controls 4

Panel Mounted Annunciations and 5

Computer Inputs 1919 289

1.0 INTRODUCTION

1.1 System Functions The purpose of the Reactor Coolant Leakage Recovery System is to provide quenching capacity for the pressurizer relief valves blowdown, and to receive, measure, cool, and transfer leakage frcm the following sources:

a) Power operated valve stem leakoffs within the Reactor Coo.

ant pressure boundry physically-located inside the Reacto.

Building.

b)

Reactor Coolant Pump Seals c)

Pressurizerrelief valves.

The Reactor Coolant Leakage recovery system interfaces with the following systems (Drawing numbers refer.to Burns and Roe, Inc. flow diagrams) a)

Reactor Coolant Coolant Makeup Purification (Dwg. 2024) b)

Demineralized Service Water, (Dwg. 2007) c)

Radwaste Disposal-Reactor Coolant Liquid (Dwg. 2027) d)

Radwaste Disposal Gas (Dwg. 2028) e)

Nitrogen for Nuclear and Radwaste (Dwg. 2036) f)

Decay Heat closed Cooling Water (Dwg. 2035) g)

Decay Heat Removal (Dwg. 2026) h)

Reactor Coolant Pump Seal Recir. & Cooling Water (Dwg. 2601) 1.2 Sun: mary Description of System (B&R Dwg. No. 2632, Rev. 2 )

The Reactor Coolant Leakage Recovery System consists of the Reactor Coolant Drain Tank, two independent.50% transfer pur piping from the leakage sources to the Tank, from the tank 1919 290 9

to the Drain Header, and associated valves and instrumentatic Leakage is collected from the four Reactor Coolant Pump Leakage chambers.

With normal leakage the pump Seal leak-age is measured and gravity flows to the TTnk.

For high leakage, the f low measuring device is bypassed.

For gross leakage some of the liquid goes to the Reactor Building Sump.

Leakoff from the annular space between the layers of valve packing similarly flows by gravity to the Reactor Coolant Drain Tank.

Per se, valve stem leakoff flow is not measured however, thermocouples are located on the pipe surface so that the presence of a leak may be determined, and its severity evaluated.

The leakage in the Reactor Coolant Drain Tank is circulated by one or two of Leakage Transfer Pump (s).

The circulated water im cooled by one or two of Leakage cooler (s).

The cooled water flow may be divided between the Reactor Coolant Drain: Header and the~ return to' the Reactor Coolant Drain Tank.

Water in.the Reactor C'olant Drain Header flows to c

either the ReactoreCoolant Bleed Holdup Tank or the Misc-

'ellaneous Waste Tank.

A minimum level of cooled water is maintained in the Drain Tank to quanch pressurizer relief valve blowdown.

1919 291 -

k To minimize small pressure transients which might inhibit gravity flow, the Reactor Coolant Drain Tank is vented to the large volumes of the Reactor Coolant Bleed Holdup Tanks.

A nitrogen blanket is normally maintained on both the Drain and Bleed Holdup Tanks.

The vent to the WI3 System, and Ehe nitrogen supply valve are normally closed.

1. 3 ~

System Desian Requirements The design of the Reactor Coolant Leakage Recovery System considers both the flowrate and temperature of reactor coolant leakage.

The system design flowrate (leakage rate) is equal to the maximum permitted leakage rate of identified rer etor coolant leakage (30 gpm).

The coolers heat removal capacity is designed to maintain o

the Drain Tank at 126 F with 3 gpm Reactor Coolant Pump seal leakage, 15 gpm valve stem leakage, and 15 gpm pressurizer relief valve 1e'akage,. If the -three relief valves simultaneously blowdown, Tank temperature will o

instantaneously increase to 191 F and in two hours o

return to its equilbrium temperature, 126 F.

The Tank instrumentation is sufficently sensitive to measure a leakage rate of one gpm in one hour.

Admittance to the Redctor Building is not required because pump and remote valve status is controlled frcm the Control Rocm.

1919 292

_3_

The stainless steel system is Seismic class II and class C cleanliness.

The piping is fabricatad in accordance with ANSI B31.7.0.

2Property "ANSI code" (as page type) with input value "ANSI B31.7.0.</br></br>2" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process..0 DETAILED DESCRIPTION OF SYSTEM 2.1 Components 2.1.1

_ Reactor Coolant Drain Tank, WDL-T-3 The 7,240 gallon Reactor Coolant Drain Tank (Table 1) collects leakage, and quenches a blowdown of the pressurizer relief valve.

To ensure sufficient quenching capability o

the tank temperature is normally maintained below 126 and water level is maintained above 75 3/8" full.

The tank is normally nitrogen blanketed.

The vapor space is connected ot the Reactor Coolant Bleed Holdup. Tanks to absorb pressure changes.

The tank may be vented to the wrG system.

The tank is protected by a 150 psi relief valve.

which relieves to the Reactor Building Sump and a 200 + 25 pr rupture disc.

If it is necessary to completely drain the tank, Ehe contents may be manually drained to *.he Reactor Building Sump.

The Reactor Coolant Drain Tank is located in the Reactor Building at the 289'-0" level.

2.1.2 Le'akace Transfer Pumps, WDL-P-9A and WDL-P-9B The single stage centrifugal pumps (Tdble 2) are rated at 400 gpm with a Total Dynamic Head of 150 feet.

The pumps take their suction from the Reactor CooleAt Drain Tank, and discharge to their individual coolers.

} 93 9~ 29b

282'-6" adjacent to the

' he two pumps are located at T

WDL-P-9A and 9B Reactor Coolant Drain Tank Cubicle, are powered from MCC 2-34 and 2-44 respectively, and are controlled locally or from Panel SA.

2.1.3 Leakace Coolers, WDL-c-1A and WDL-c-1B The leakage is pumped through the tube side of the Coolers The horizontal heat exchanger shell is cooled (Table 3).

by the Decay Heat Closed Water Cooling (DHCCW) system.

The DHCCW cystem has two pumps which maintain circulation For a through the coolers during normal operation.

further explaination of operation on the shell side of this cooler, see the Decay Heat Closed water Cooling System Description, Index No. 29.

2.1.4 Maior Svstem Valves Pumoout Control Valve, WDL-Vill 8 This 4" stainless steel 150 psi valve is located off of the cooler discharge header.

By throttling this the relative recirculation / transfer valve en Panel 8A, ratio for the Bleed Holdup Tanks may be varied.

To ensure sufficient quenching capacity the valve will automatically shut before minimum the level falls be'ow its specified minimum.

Reactor Drain Tank / Reactor Bleed Tank Interconnect (Inside Containment) WDL-V1095.

WDL-VlO95, is normally open to equalize pressure between the Drain Tank in the Reactor Building and the Bleed Hold-The two inch 600 psi up Tank in the Auxiliary Building.

valve will shut with an Es signal.

To protect the Bleed

~

19I9 294.

Holdup Tanks from overpressurization, the valve will close with high pressure in the Drain Tank.

It will automatically reopen with decreasing pressure.. The valve is controlled from Panel 8A with an AUTO-CLOSE switch.

Indication is on Panels 8A, 13, and 15.

Reactor Drain Tank / Reactor Bleed Tank Interconnect Valve (Cutside Containment Isolation), WDL-V1092 WDL-V1092 is similar to WDL-V1092 except that it is controlled by an OPEN-CLOSE pusbutton, and it does not automatically close with high Drain Tank pressure.

Both containment isolation valves close with and ES signal.

Containment Isolation Valves WDL-V127, and WDL-V126 WDL-V127 and WDL-V126 are one inch, 600 psi, normally shut valves to the WDG System.

They have indication and control on Panel 301B.

2.2 Instruments, Controls, Alarms, and Protective Devices 2.2.1 Instruments and Controls evalute " leakage, ~~tQelve- { ~

To nonquant~itatively_

thermocouples are on the pressurizer relief valve piping, and two on the piping form each of the 27 valve stem leakoffs.

Generally the thermocouples for the valve leakoff piping are on the pipe surface 2 and 7 feet from the valve.

The thermocouples supply signals to Multipoint Recorder, YM-TR-7167 on Panel 10.

The recorder enables the operator to observe trends and abnormalities in temperature readings 1919$95.

~

--u.

which might be indicative of leakage.

Leakage from the Reactor Coolant Pump Seal flows into an eccentric 1y mounted catch basin.

A full catch basin dumps its fluid and actuates a proximity switch.

Thus flowrate is directly proportional to the flowswitch actuation rate.

If the maximum flowrate of the catch basin is exceeded, the leakage bypasses the catch basin.

Separate indication is provided for each pump cn Panel BA.

Level instrumentation, provided on Pani 8A, is used to determine leakage into the tank, and to evaluate the requirements for additional tank pumpdown.

The amount of liquid pumped out of Drain Tank to the Reactor Coolant Orain Header is monitored by flowrecorder, WDL-FR-7100, on Panel 8A and controlled by WDL-Vill 8 hand-switch, WDL-FHC-7101, on the same Panel.

For a specific description of these and other instruments and controls, see Table 4.

2.2.2 Alarms and Protective Devices For a list of the alarms see Talbe 5.

As noted previously, WDL-Vill 8, Tank Pumpout valve, is interlocked to shut and prevent the Tank level frcm falling below the minimum level required for quenching the relief valve blowdown.

Bleed Holdup Tank / Drain Tank interconnect valves, WDL-V1095 is shut with high pressure in the Drain Tank. If a Pressurizer Relief valve lifted and failed to reset, the Bleed Holdup 1919 29~6.

.=

Tank is protected from rupture by shutting WDL-V1095.

The Auxiliary Building is thus protected against contamination which might result from a Reactor Bleed Holdup Tank failure.

The Drain Tank itseAf is protected by a 150 psig relief valve and a 200 + 25 psig rupture disc which would fail if a Pressurizer relief valve failed to reseat.

3.0 PRINCIPAL MODES OF OPERATION 3.1 Startuo For intifial startup, the discharge valves of each Transfer Pump, WDL-V1105A and B, and the loop throttled valve, WDL-V1119, are positioned so that each pump discharges 400 gpm when both are operating, and so that one pump will discharge less than 600 gpm when operating singlely Oxygen is purged from the Tank by Nuclear Nitrogen.

t For normal startup, one or two Leakage Transfer Pumps are started with the corresponding DECCW Leakge Closed Cooling Pumps.

The Pumpout Valve, WDL-Vlll8, is positioned Leakage water is recirculated and pumped out of the Drain Tank as required by leakage condit ons.

3.2 Normal Cperation The flow from the Reactor Coolant Pump Seals, and the temperature of the system drain piping is recorded to determine abnormal leakage in system ccmponents.

For design leakage ccnditions both Transfer Pumps, both coolers, and the corresponding Leakage DECCW Pumps are in operation.

The position of the Pumpout Control Valve, WDL-Vlll8, is determined by the Tank Level and the pump-out flow recorders, WDL-FR-7100.

The Transfer Pumps i919297

-mam

0 discharge 800 gpm of 126 F liquid through the coolers.

Twenty four (24) gpm is directed to the Reactor Coolant Drain Header, and the remaining 776 gpm of cooled leakage is returned to the Drain Tank.

For conditions less than maximum design, one pump may be run, or if leakage is small one pump may ocessionally run to pump-down and cool the Drain Tank.

Under these conditions, the Tank Temperature should be maintained below 150 F.

If level measurements are required, WDL-V1118 is shut, and the Drain Tank Leakage recirculated withcot discharge.

The multipoint temperature recorded runs as required.

The normal operating level should be maintained between 74 1/16" and 77 7/8" (303 gallons).

The discharge of the Dfain Tank is normally directed to one of the Bleed Holdup Tanks.

It may also be directed to the Miscellaneous Waste Holdup Tank.

3.3 Shutdown The Leakage Transfer Pumps and the associated Leakase~

DHCCW M ps are stopped manually.

3.4 Special or Infrecuent oceration After a pressuriser relief valve has blowndown.to the tank excessive backpressure may cause RC Pump Seal Water to temporarily overflow to the Reactor Euilding Sump.

The both Transfer Pumps and both Leakage DHCCW Pumps should be started with maiimum recirculation flow.

The Tank Level should be permitted to increase to 9/

maximum operating limit T/7 7/8) bEfore pdinpout 6f

-~

~

~-t he Tank 2.s resumed.

1919 298'.

.~

A malfunctioning pump may be repaired while operation continues with one pump.

3.5 Emeroency The Containment Isolation valve shut with an ES signal The Leakage Transfer Pumps are unpowered and idle during a Loss of Coolant Accident (ES signal) and during a Loss of Power Accident.

4.0 HAZARDS AND PRECAUTICNS To ensure that a quenching capacity is maintained, the maximum temperature and normal level conditions should be meet at all times there is a bubble in the pressurizer (the reactor coolant system is pressurized).

The Leakage is radioactive and should be treated according.ly.

When entering or venting a nitrogen blanketed tank, the area should be ventilated to ensure that the air contains a minimum amount of oxygen.

1 There is no interlock which ensures that the Leakgge DHCCW Pumps are running when the Leakage Transfer Pumps are running.

There will be no heat transfer unless there is ficw on both sides of the same cooler.

i919 299. _ _. _ _ _... _.

TABLE 1 REACTOR COOLANT DRAIN TANK Identification WDL-T-3 11anufacturer Richmond Engineering Co.,

Inc.

Capacity - gallons 7240 Installation Horizontal Outside diameter & Length, Ft.

8, 23 Shell Material SA-264 Shell Thickness, in.

2-1/16 Design Temperature, F

500 Design pressure, psig 550 Corrosion Allowance, in.

O Design Code 1968 ASME Code, Sec. III, Class C Ccde Stamp Required Yes Classification Level Code N-2 Quality Control 2

Seismic I

Cleanliness B

1")19 300

TABLE 2 LEAKAGE TRANSFER PUMPS PUMP DETAILS Identification WDL-P-9A, WDL-P-9B Number Installed 2

Manufacturer Crane-Deming Model No.

VA-40E Type Single Stage vertical In-Line Rated Speed, rpm 1800 Rated Capacity, gpm 400 Rated total dynamic head, ft.

150 NPSH, ft.

6 Design pressure, psig 150 O

Design Temperature, F

250 Lubricant / Coolant oil / air MOTOR DETAILS Manufacturer U.S. Motors Type Squirrel Cage Induction Enclosure Enclosed Rated, Horsepower 40 Speed, rpm 1800 Lubricant / Coolant oil

/ Air Power requirements 460v/3%/ 60 HZ, Full Load Current Power Source 480v MCC 2-34 for WDL-P-9A 480v MCC 2-44 for WDL-P-9B Classification Level Code C

Quality Control Q-4 Seismic II Cleanliness B

TABLE 3 LEAKAGE COOLERS Identification WDL-C-1A WDL-C-13 Number Installed 2

Manufacturer Struthers Wells Cleanliness Factor 0.8 6

Heat Transfer, Btu-hr 5.82 x 10 Tube Side 5

Fluid Flow, Ib/hr-source 2 x 10 Design Pressure, psig 150 Design Temperature, F

250 Material 304SS Pressure Drop, psi 10 Shell Side Fluid Flow, lb/hr-source 2 x 10 Design Pressure, psig 150 C

Design Temperature, F

20U Material CS Pressure drop, psi 10 Leve:

Classification Shell Tube Code ASME VIII ASME VIII Quality control Q-4 o-4 Seismic II II Cleanliness D

B (919 302.

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