ML20100P960

Rev 7 to Design Spec 22A2870, Leak Detection Sys

ML20100P960
Person / Time
Site:	LaSalle
Issue date:	06/09/1976
From:	Gregory P GENERAL ELECTRIC CO.
To:
Shared Package
ML20100P861	List: ML20100P860 ML20100P867 ML20100P876 ML20100P898 ML20100P906 ML20100P917 ML20100P929 ML20100P960
References
22A2870, NUDOCS 9603110425
Download: ML20100P960 (10)

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GEN ER At. ith ELECT,1lC DOCUMENT NO, 7 REv. T . .

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GSPECIFICATION CORAWING .. j C 1l 6*-l TYPE DESIGN SPECIFICATION

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DCCID!Eh'T TITLE t.EAK DETECTION 9YSTTM g.4,,,

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• REVISIONS C f.]

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NUCLEAR ENERGY DIVist0N 22A2870 I

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1.1 This specification defines an t de. scribes the basic requirements of the lesi <

1 detection of a r.uclear boiling wat. . eactor plant; '

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1.2 This; dist';n specification is based ucon no specific division. of work. as4 ~pg'

.x 4 ment or responsibf Tity between the General ~ Electric Cbmoany and its custoners.or . 3;..

'contr4ctors. The division of work is specified elsewhde. ... p, l O

$ 1.3 The instrumentation to be supplied by Others shalt satisfy the. functionap g,h.,

design requirements contained herwin while complying with all applicable regu ' c

- 1ations. Impf tcie equipment requircinents specified are f ntended only as a guide -  ;

' and should not in any way restrict the design of instrumentacion suppl.ied by IJ .

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2. APPLICABLE DOCUMENTS ,

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.. .. 2.1 General _ g 2.1.1 The latest issue of the follewiag references form a part of this spect- h fiuction to'the erte.n:cipwPin her ir:. G:nerai EW.tric Company doc.a:un . sec .

> shoin.by title. Master Parts List (MPL) nuctier, and/or docun.::c number.

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2.2 General Electric Comoany_ Docunents -

{j 4 2.2.1 Sucoortinn Drawines E

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a. Leak Detection IED MPL# E31-1013 $ -

b. Nuclear Boiler P&I0 MPL# B21/22-1010 Reactor Recirculation System P&ID MPLJ 833/35-1010 f4 c.

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d. Reactor Water Cli.nup System P&I) MPL! G33-1010 .

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e. Residual Heat Removal System Pl!D MPL# 'E12-1010 $

f. Reactor Core Isolation Cooling System P&l0 MPL# E51-1010 .x%

g. High Pmssure Cors Spray System P&ID MPL# E22-1510 ~',

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'p 2.2.2 Supporting Specifications , ,

a. Electrical Equipnent Separation for Caraguard System - MPL1 A61/62-4340 a

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3. DESCRIPTION *, '

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i 3.1 The nuclear boiler leak detection system consists of temerature..prects.v. ~- 2 - .

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radiation level, and flow sensors with associated. instrumentation: and' alamr.: ,  %- .

This system detects, annunciatas, and isolater (in certain casest leakages 4 ': . ' $.iX

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.. the fo1 Towing systems: . .

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l# }?; i 4 a. Coolant System within the primary containment gg ,. )

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c. The Reactor Water Cleanup System (RWCU) .-

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d. Residual Heat Removal System (RHR) v:

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e., Reactor Core IsoTation Cooling System (RCI'C) 1

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i Isolatforr and#r a{ars oftaffectedsystems and"the mthods used are sumanetam@*r ir.' Table 1; 2W{

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- i a 1 l l 3,2 L:aks. are detected by utilf rie.g. the following techniques: .

a. Sensing exc:ss fim in the. process.pipino systems o ;.n i o.. Sensing pressure and te@e.rature changes in the primary

, containcent ,J ~fgg l i c. Monitoring temperatures in areas containing equipment and' , [pj" piping systems, .

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d. Monitoring level in the drain sumos [g

e. Radiation monitoring in the dryweil  ;%

3.2.1 Small leaks (5 gpm and less) are detected by temerature and pressure t?

changes and drain pump activities. $ ,

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3.2.2 In addition tn methods, described in Paragraph 3.2.1, large' leaks are M detected by J.4nges in reactor water level and by the changes in the amount of flow in the process line. ,g i

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4. REQUIRErd.N1S W

.s 4 4 .1 Ger.eral Criteria . .

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4 4.1.1 The temperature detectors shall be located or shielded so that they are Fia sensitive to air te@erature and not to the radiated heat from the equip ent.

Divisionally separated cetectors should be located so that, basically the.sase, d

sy enviornmental conditions are monitored by a d,itt:ctor of eacn division. ]

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The ventilation inlet / outlet te.nperatum-and asbient, temperature of tSul p

' '[j 44.1.2 aquipsent rocas for the systems listed in Paragraph 3.1 shall be used~ to.in

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itiate alarnr and/or isolation' logic. The temperature t.larm setpoint can be E i established by. calculating atheat balance for the norinal room enviornannt,; '~.4(;j

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then.. introducing the heat relea$e caused by an alarm limit-leak. s A control .

g 'valume room is necessary for optimum operation of the temperature detection;rg, ;.a /s M*i r

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/ s, sh4.1.2.1 Equipment room cool ng capacity should be sufficient to cool onlysthe.;  ;

1 nemal heat release fron' the system piping and equipnent. If norm 1 or addi - 1 l

', tional capacity is used. it must be contrailed to orevent tregating the leais y'

/ q. detection capacity at alarm and isolatica limits. -

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/,i (I $ 4.h2.'2 When equipment ream coolers are used, the followingsadditional Tep.,_..

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a. Cooler condensate drain monitor'ng b,. 4ticM terrperr.ture at cooler inlet air. J

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4.1.? '.est'stectien in>trumentation shall ncet th= design criteria listed in I l the BWR Equipment Environmer.t31 inter facer Data - F.?L!.,M-CO. ,

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f 4.1.4 The nuclear boiler leak detection. system shall be fasigned to. detect' leaks of steam insida the primary containnent at 1. gpse.witMWa i h

- An alarin shall be actuated at an unidentifiable 1cakage of no more than -

and at an identifiable leakage of no more than 25 gpm.

f: $ 4.1.5 Conpnnents that are part of isolation system shall meet the design criteria listed in the electric equipment separation for safeguard system design specification.

4.2 Leak Detection Within the Primary Containnent. Leaks within the. primary , (

containment snail De cetected by: -

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a. , Measuring pressure and temperature in the primary containee'nt

b. Measuring the flew f ato the equipment drain and the floor drain sumps ,

c. Measuring the cooling yater temperature to and from the primary ,

, containment atmosphere coolers

d. Meas'uring the reactor wate;- level

e. . Measuring the condensate flow from the primary containcent atmosphere coolers -

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. f. heasuring the fission products in the frimary containme'nt atmosphert e

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• p 4LT.) Pressere reasttre ene. The d w containment will be pressurized ant 'l . g:j' asintained at a. slightly positive pressura during re' actor operation. Tha norra$ @ 7 & ir 4

.epeisting; press ~ure is (.75 + 0.1 psig._ ~ Thi presure may fluctuate as.a result:g"f Qds N

.et barometric, pressur1r chanies and. outleakages; however, a pressure. risa above ' MF l ..i1 y~~

...the presat val ve will indicate leakage in the system. A:

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i 4.2.1.E Ternoaraturs .reasurerents. A cooling system circulates the. primary' .

k containment ate.aspnare tnrougn neat exchangers to maintain its design operating! .

temperature of 135*F. An abnormal a-ir temperettrre rise *.bove 135'F will in-- p ,

dicate a coolant and/or steam leakage. A temperature rise in the primary con-- g tainsent.should be .'.atected by mcnitoring; al the primary containment temperature. y, 1 at various-elevatinns, b) inlet and outlet air to the coolers, and.c) the closed .

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.cooMag;-water; temperatura increase >hatween: inlet and. cut.le.t to. the cocilers".1.

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4;2.i.3t.'The~ condensate colitected ftaur the air cooters should be pipedcto the-

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primary conta.inment floor drain sump. The condensate flowrate shall be neasured a before the collection tank. High flowrate shall be annunciated in the main control room, f'

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$ 4.2.2.1 Eculement and floor drain flow reasurenents. The floor drain sucy instru-

, mentation shoulo De cesigned to nave a sensitivity cf detecting leakage of 1 gpal

- - witnin a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period while the equipment drain sumo should have a sensitivity of detecting steam leakage of 50-percent of anticipated backpound leakage. The sump outflow rate, in gpn, sna11 bein'di~cated in the main contrni room. Leakage just below the licens: limit shall be annuaicated. The alarm sait point shall have an -

adjustable range of 0 to 25 gpm for equipment drain sump and 0 to 5 gpm for floor drain sump. The di: charge lines to the radwaste system from both drain sugs shall ..

be provided with sample points outside of the primary containtrent.

$'4.2.2.2 The coulo r.ent drain sumo -(E01). The equiprernt drain sus collects only identified leakages. Inis suap snall receive condensate drainage from pump seel leak-off, reactor vessel head flange vent drain, valve packing leak-off, and other

. + equipment .Backorcund leakaoe will be determ

. i n d during operational tests. Collec-tion in excess of oackg-ound' leakage would be indicativa of the reactor coolant '.'

leakage. The surp sh6' 1 be equipped with a cooling ceans to prevent. liquid flashing and retfuce vaporization of its contents. The sump should haye a cover which should'

' be either sealed or curbed to prevent inflow drainage. The alarm set poi.it shall

' have an adjustable range of 0 to 25 gpm.

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4.2.2.3 ThI.'flode drain suno (FDS). The. leak detection. signal should bel ~ ,MA

actuate; an alarm before the unicentified laakage maches 5 grm . The alanr. M ?,' M ;

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" potet shalli. haw.an adjustable range. of 0 toc i gpm This sump shall' collett $'2Yg ,-f; \'

l leakage: free contist red drivas, valve; flange Isakages fidgWrains cros#df . ,

in, mtar systaar., tha. geimary containce.tt coating unf t drafnst and> any othag$a. .m,Q(

'M 4 potential-sources not, already identified. Leakage f' rom the closed cooling wetr .

l system woMdWdgititted by chan~9es in-the cirsed-cooling-water-systeissurgedmiR 6f;;i level. Background leakage should be observer, during operatfor.al~ test and'serwi , .p . }

! as the bas:is for set; points. #k

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$ 4.2.3 Reactor Vessel Head Clos'.tre. The reactor vessel head closure fs provf5td..

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4 with dou' le seals with a leak-off connection between seals %g3.that is 4

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equipment'dra.fri sug.. Leakage. through the, first seal shall ne detected by a ,1

- D pressure 1mansdueer and. annunciated;in..thaussia(contral rg ].p

}- 4.2.4 PrimorpRecircu.lation Pumo Seat; ThiiTeakage' frons the primarh rM3aNhhtQh~ y' '

t ulation pump seal snall oe pipeo to tne eauf pment drain su,m and instrumented %. -

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s shown in the reference of Paracracn 2.2.1, item c.

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4.2.5 Saktym elief Valves. Temperature sensors, connected to a multipoint j r%. de'.o sha H-bafhElica'a to- Gtcci.' afety/reer f vai+c laeKage eluring rie . . g. .

'rs

,, "* f actor operation. ' Safety / Relief Valvt ter:perature elesents'. $ hall be mounted.

,- using a thermenell, in the vvve discharge piping several feet from the valve

body. Temperature rise above arrbient shan be annunciated in the main control i

room. Instruments art snwn in the .nference Of Faragraph 2.2.1, Item b.'

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- h 4.2.6 Valve Packir,o teekaoe. The elve inner packing leakage should be piped to "(

f the equipnent crain sucp. As a miriimum requirernant, it is reconrended that each' .: i 4

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,- line br equipped with a cethod forivisual inspection during hydrotests. The

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valve seal leakoff applies to all $ower operated valves (larger.than 2 inch). . .;

located inside the drywell for the following systems: Nuclear boiler, reactor , ,

water cleanup, : ore spray, RCIC, R4R and feedwater. Higth.terperature at thaQ, j leak-off line should be annunciate'd in. the main centrol room. ..

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p 4 4.2.7 Leakage of steam or reactor water inside- the A. primary containment should alsag continuous air samp11.n g system be detected by using radioisotopip . techniques.* /

-' should be provided for gross counting of particulates, lodines .andloble. Gases. g The counts shall be recorded in Jhe main control room and actuate an alarm on-high __

activities.  ;

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k Through correlation of proces'; fluid radioactivity via the grub sanple

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analysis nethod, traceable coicentrations of isotopes can be estabitshed. /

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~ The airborne traceable concentratinns can then be related to a corre-I

, sponding leakage rate of process fluid within the drywell voluge.

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,t ' 4.3 Leak Detection External to Prirdry C.,itain:nent k.

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detec+.edReactorusingcoolant a conbination leakage of theeatsidef11cwing:the f4 primary containment shall be ;,

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a. Reactor building sur:p mo.Mtoring, and C s '

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> b. Equipment areas n1 st ja cipe routing area -

El temperature mon torf rp

c. High flow (RHit,' /.C)/,)  ;

d. High a flow (R)CLQ j' i

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4.3.2 A sump system ly.r.11 be provided in the reactor building to collect p

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drains froc the equip:FMC altas. Theesump::moni.toring ins.tcumentation shall' q- .-

be provitted to neasur leakage. The signal (alarm) setting. should indtcate ,

a leakage of 5 gpm. .

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4.3.2.1 (loor_Crain Sumn. Cach equipent area (RER. HPC5, RCIC, and MSL tunnel),

s. should be equip;ec.pitn a sump monitoring system capable of detects:'i cc 'est !cah. g{, l i

'd . hj' age in that :m. f . leakage of 5 yr. : hall be annunciated in the main contr M 4.3.2.2 Ecuipmerh . Orain Sumo. Equipment drain surp shall be. provided to collect

. ?f crainage from variuus equipcent. Orain connection shall be instrumented to >J identifyleake.ge.gources. {

- 4.3.3 In cdditiori to the differential temperature measurecent in the areas y listed beloit, temperature elecents shall be provided to indicate room achient g

, temperature. These temperature el6ments are to ce.tsure temoerature rise due

,a to reactor cotlant leakage. High terperature shall be annunciated in th. ,

main control r Am. Areas to be monitored are:

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. a. liain steam'line tunnel,

b. Pipe area between tunnel exit and turbine, i l

c. RHR,

d. Reactor water cleanup. .!

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e. RCIC equipcent area & RCIC steam piping routing. j

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7 4.3.3.7 Main steam Ifne. Leaks in- the mein steam line shall be detected usife '.1 any one er a connination of the following methods: ,

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" a. Ew water level ifr the reactor' vessel. !h

b. High fim rate at the flow limiter,..and .

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c. HTgli temperature and high .t=nperature dif'ference irv the ma,in, s, team- (

liro tunnel. -

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(1) Reactor Water Level.. The loss. of water in the reactor ve:sel y

J as the resuit of a major leak in any mhjor system is monitored '

at the reactor water level using the same signals that actuate -.

.' *. ,' alar.m on im reactor water level and close selected primary system isolation- valves. and. initiate:. Core S.tandby Cooling

j '

! System. A sunnary of reactor vessel level instrunentation and"

(

j. set points is referenced in: Paragraph;2.2.1. Iteur b.

$ (2) Ster tainLine tourHich Flow. Each dif femntial orassure main steam flowwhich tr3ns::::c.ers limiteigiva shall con-a coin- H f cidence signal for main steam line isolation at 140 percent of th:.effnted li=. rcted f1w. '

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. 4.(3) . Temperature Sensors. The .anbient temerature around the main -

steam lines and the steam tunnel tepsrature differcnce shall i

be treasured by locating temperature sensors at the inlet and -

outlet of the steam tunnel in accessible locations for testing ,~

and calibration during normal operation. High actient and high differential temperatures shall be annunciated in the main

• control room. The alam set point shall correspond to 5 gpm -

ster.m leakage. The Isolation set point shall correspond to

25 gpm steam leakage. t l

4.3.3.1.1 The area around the piping from the pipe tunnel exit to the turbihe inlet should be monitored for steant teakage.. This area may be divided into

- several ventilating zones and ar.tient temerature at each zone shall be measured.

Tegerature rise corresponding to steam leakage of 5 gpm in any zone shall be

': antienciated in the main contml room and automatic isolation' actuated at a ten-perature rise corresponding 'to 25 gpm steam leakage. A minimum of one. tempera-ture switch snall be proviced per main steam isolation logic. Design and i instrumentation of the leak detection systent i.: tre turbine building by the AE unless otherwise shown on the MPL.

4.3.3.2 Reactor Water Cleanuo (RWCU) S/ stem add Residual Heat Remval (RHR) System.

• g High temperature process fiw of :ne reactor water cleanup system and RHi system extemal to the primary contain-ent shall be detected by temperature sensing

_; elements. Temperature sensors shall be located in the inlet and outlet venti-1ation ducts to m!asure te<rterature difference also, local temeraturt sensors

( - shall be located in all compart.-ents containing equipmnt and piping for these .

systems. Alarm in the main control room should be set to annunciate a temperature ..-

rise corresponding to a leakage of 5 gpm and the system isolated at 25 gpm. .

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GENERAL '

ELECTRIC 22A2870 s u o. 9 K  ;

NUCLEAR ENERGY DIVIslON nev. 7 ,. c

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( '4.%3.2.1in' Addition.R.eacter to temperature cetection Water Cleanus metnod,System.

siall be Flow detected .. Leakagg in the by means cleanup systeza.

of ficw M

comparisort between cleanup system inlet and outlet. If the inlet flow exceedse $

m. ,

v outlet flow by 25 percent an alarn shall be actuated and the cleanup system

'O shall be isolated automatically. A bypass timer shall be provided to over- ',-

ride the isolation signal during surges. Instrumentation is shown in reference M@ l 1

- of" Paragraph 2.2.1 Item a. g$4 4 4i 3.3.2.2. Laekage la the. RHR system (sh"+" cooling.moda. of' operatical in.

additforr to temperature detection nethod, shall be detected by a. set of two.

k

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1 idifferential pressure transducers sensing differentici pressure across a flow ,-

N restrictor or elbow. Flow in excess of specified limits shall be alarred and l the system automatically isolated. y:?

4.3.3.3 RCIC Equinrent- Area. ' Leakage-in'.ttris' system shall be detected by tere kh l (n

perature sensors wnicn snail be located irr the equiptent area and its inlet and

{g  ; ,- outlet ventilation ducts fo'r rneasuring anttent and temperature difference rise 5

in the event' of steam leakage. H1' g h actient or high temperature difference shall actuate an alar..' :ad isolata the sy: tam auterratically. Ala:m shou 1d 9 a:t.:atec &g ,

by a temperature rise corresoonding to steam leakage of S gpm and automatically tec7 ate.tne systo: on 25 spm.

h - -

' $ ' 4'.*3. 3. 4 Le'ak Detection in the RCIC Steam Pine Routino Area. Leaks in the RCIC N.

steam pipe routing area snali ce cetected by reans of tenperature sensors. High

~ anbient teroperature and/or hign differential (AT) tcrperature shall actuate an R .

. alarm and isolate the system automatically. Alarm should be actuated by a tern-perature rise corresponding to steam leakage of 5 gpn and automatically isolate p

g on 25 gpm. TL-

" kl. ,N 4.4 System Test -

Q k 4.4.1 Periodic inspection, calibration, and testing shall be perforced to verify-that each component in the system is capable of performing its intended function,  :,

botta individually and in conjunction with other components. Q

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