ML18100A417

Proposed Tech Specs Supporting Boron Concentration Reduction

ML18100A417
Person / Time
Site:	Salem
Issue date:	06/11/1993
From:	Public Service Enterprise Group
To:
Shared Package
ML18100A416	List: ML18100A415 ML18100A417 ML20045B880
References
NUDOCS 9306210208
Download: ML18100A417 (177)

Text

ATTACHMENT 2 llAllKBD OP TBCJDIICAL SPBCIWICATIOB PAGBS 93062 l 0209 930611

'~

PDR ADOCK 05000272

,/

p PDR

Salem Technical Specification Change Package PSE&G SALEM TECHNICAL SPECIFICATION INSERTS Insert A:

4.1.2.1 a. When the boric acid tank is a required water source, by verifying at least once per 7 days that:

(1) the flow path trom the boric acid tank to the boric acid transfer pump, the boric acid trans!er pump, and the recirculation path from the boric acid transfer pump to the boric acid tank is ~ 63°F, and (2) the flow path between the boric acid transfer pump recirculation line to the charging pump suction line is 2:.

50°F, Insert B:

4.1.2.2 a. By verifying at least once per 7 days that:

(l) the flow path from the boric acid tank. to the boric acid transfer pump and from the recirculation line back to the boric acid tank is 2:. 63°F, and (2) the flow path between the boric acid tank recirculation line to the charginq pump suction line is ~ S0°F, Insert C:

b.

For the refueling water storage tank by:

l.

Verifying i:he boron concentration at least once per 7

days,

2.

Verifying the borated water volume at least once per 7 days, and

3.

Verifying the solution temperature at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, when it is the source of borated water and the outside air telllperature is less than 35&F.

Insert D:

b.

For the refueling water stora9e tank by:

1.

Verifying the boron concentration at least once per 7

days,

2.

Verifying the borated water volume at least once per 7 days, and

3.

verifying the solution te~perature at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the outside air temperature is less than 35°F.

Insert E:

tank in accordance with TS Figure 3.1-2, and additional makeup from either:

(1) the second boric acid tank and/or batching, or (2) a maximum of 41, BOO gallons of 2300 ppm borated water from the refueling water storage tank.

with the refueling water, storage tank as the only borated water source, a maximum of 73,800 gallons of 2300 ppm borated water is required.

Salem Technical specification Chan9e Package Insert F:

The 37, ooo qallon limit in the refueling water storage tank for Modes 5 an.d 6 is based upon 21, 210 gallons that is ~ndetectable due to lower tap location, 8550 gallons for instrument error, 7100 gallons required for shutdown marqin, and an additional 140 gallons due to roundinq up~

Insert G; The-boric acid tanks, pwnps, valves, and p1p*1ng contain a boric acid solution concentration of.between 3.75% and 4.0% by weight.

To ensure that the boric acid remains in solution, the tank fluid temperature and the process pipe wall temperatures are monitored to ensure a teJnperature of 63°F, or above is maintained.*

The tank fluid and pipe wall temperatures are monitored in the main control room.

A 5 ° F marqin is provided to ensure the boron wi 11 - not precipitate out.

Should a~bient temperature decrease below 63°F, the boric acid tank heaters, in conjunction with boric acid pump

~ecirculation, are capable of maintaining the boric acid in the tank and in the pump at or above 63°F.

A small amount of boric acid in the flowpath between the boric acid recirculation line and the suction line to the charging pump will precipitate out, but it will not cause flow blockage even with temperatures below 50°F.

INSERT H:

The maximum expected boration capability (minimum boration volume) requirement is established to conservatively bound expected operating conditions throughout core operating life. The ~nalysis assumes that the most reactive control rod is not inserted into the core.

3/4.l REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONiROL SHUTDOWN MARGIN - Tavg > 200°F LIMITING CONDITION FOR OPERATION 3.1.1.1 The SHUTDOWN MARGIN shall be!. 1.6i ~k/k.

APPLICABILITY:

MODES l, ~*. 3, and 4.

ACTION:

With the SHUT OWN MARGrN < 1.6% ~k/k, ilTITlediately initiate and continue boration at> 10 gpm ef 20;000 ~pm !:Jorie acid selt1tieR or equivalent I

until the required SHUTDOWN MARGIN is restored.

SURVEILLANCE REQUIREMENTS 4.1.1.1.1 The SHUTDOWN MARGIN shall be determined to be!. 1.6% ~k/k:

a.

Within one hour after detection of an inoperable control rod(s) and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter while the rod(s) is inoperable. If the inoperable control rod is inwnovable or untrippable, the above required SHUTDOWN MARGIN shall be increased by an amount at least equal to the withdrawn worth of the i11111ovable or untrippable control rod(s).

b.

When in MODES 1 or 2*, at least once per 12 h~urs by verifying that control bank withdrawal.is within the limits of Specification

.3. 1. 3. 5.

c *.. When in MOOE 2 11 ~. within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to achieving reactor criticality by verifying that the predicted critical control rod position is.within the limits of specification 3.1.3.5.

See Special Test Exception 3.10. 1

. With Keff !. 1.a

1. iWith Keff < 1.0 SALEM - UNIT l 3/ 4 l -1

REACTIVITY CONTROL SYSTEMS SHUTDOWN MARGIN - i

< 200"F avg -

LrMIT!NG CONOii!ON FOR OPERATtON 3.1.1.2 The SHUTDOWN MARGIN shall be! 1.0S 4k/k.

APPLICABILITY:

MOOE 5 *.

ACTION:

I ~~G\\PM oF ~ c:,~\\....\\.l\\\\ON C...of'i~f:\\\\N\\~~ ~ 656CPPm~oi\\ON With the SHUTDOWN MARGJN < 1.0S 4k/k, i1T111ediately initiate and continue boration at ;f10 gpm ef 2e,eoo pp111 bcr1e aeht sel~tieFI or I.

equivalent until the required SHUTOOWPt MARGIN is restored.

SURVEILLANCE REQUIREMENTS 4.1.1.2 The SHUTOOWN MARGIN shall be determined to be! 1.0S ~k/k:

a.

Within one hour after detection of an inoperable control rod(s) and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter while the rod(s)

~s inoperable. If the inoperable control rod is inwnovable or untr; pable, the SHUTCOWN MARGIN shall b1 increased by an amount at least equal to the withdrawn worth of the irnnovable or untri~~a~

control rod(s).

b.

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by.consideration of the following factors:

1.

Reactor coolant system boron concentration,

2.

Control rod ~osition,

3.

Reactor coolant system average temperature,

4.

Fuel burnup based on gross thermal energy generation,

5.

~enon concentration,.and

6.

SJmarium concentration.

SALEM - UNIT 1 3/4 l-3 AmelilD!llt No. 83 I

Salem Technical Speci!ication Change Package REACTIV [TY CONTi\\OL SYSiEMS 3/4. 1.Z 80RAT10N SYSTEMS FlOW PATHS - SHUTOOWN LIMITING CONDITION FO~_;:O;..;..P=ERA.;;.,;..o..Tt;;..;:O:.;,.:.N ______________ _

3.1.2.1

~s a m;ni111U111. one of the follow;ng boron injection fl~ paths shall bl OPERABLE:

a.

A flow path fr0111 the boric acid tanks via a boric acid transfer pwap and cha rg i n9 puinp to the Reac:tor Coo 1 ant Systtm t f on 1 y the boric acid storage tank 1n Spec1f1cat1on 3. l.2.7a is OPERA8l£, or

b.

The flow path f'n>ll'I the l"efuel fng water storage tank *ria a ehargfog Pl.m!P to the Reactor Coolant System if only tl-ie refueling water-storage tank in Spec1ficat1on 3. l.2. 7b ts OPERABLE.

APPlICABILITY:

HODES S and 6.

ACTION:

"Ith none of the above flow paths OPERASlE. suspend all operations 1nvolv1ng CORE ALTERATIONS or positive reactivity changes until at least one injection path ts restored to OPERABLE status.

SURVEILLANCE REQUIREMENTS

~~~r- *#\\~':-ea-st~-= of the 1bove,.equ'ired f1ow paths sha 11 be. A~"'-

s tra ted OPERABl.E: [

I

-_1Ns~~r.A.

ta, At lent rs"ca par 7 d11> ! by we1 ffying that the te*era e:1;1 re e f'

• tAe_l\\r:U Bl"acecf ~"'"~h" e;....~lill! fle\\I it0th-h

'.14&

0 f'.*,qlt~a-

• .flew ~u._ i.,. CAe be11h a&fd ;uk; h 1.1ucl,-

b.

At. least once per 31 days by verifying that each valve (manual, power operated or autom4ttc} 1n the flow path that fs not locked, sealed. or othr:~ise secured 1n pos1t1on, ts fn its correct

• po5i tiara

• SAL£M - UN IT 1

)/ il l ~ 7

Salem Technical Specification.Change Package REACTIVITY CONTROL SYSTEMS FLOW PATHS - OPERATING LlHITlNG CONDITION FOR OPERATION 3.1.2.2 Each of the fo11owing boron inJect1on.flow paths shall be OPERABLE:

a.

The f1ow path from the bor;c acid tanks via a boric &cid transfer PtlllP and a charging pump to the Reactor Coolant System, and

b.

The now path from the refuel fng water storage tank vh a chargfng pump to 'the Reactor Coolant System.

APPLICABILITY:* l<<IDES l, 2, 3 and 4.

ACTION:

a.

Wftb the flow path fnnn the boric acid tAP.ks inoperable, restore the ;noperable now path to OPERABLE status withfn 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or b1 fn at leHt HOT STAKDBY and borated to 1 SHUTOQIN MARGIH equivalent to at least 11 6k/k at 200*F wfthfn the next 6 haurs; restore the flow path to OPERABLE status w1thtn the next 7 days or be in COLD SHUTDOWH within the next 30 hOurs.

b.

With the flow path from the refue11ng wat1r $torage tank

• inoperable*. nesture the flow Pith to OPER.A8t£ status w1th1n one* hour or be fn at least HOT STANDBY w1 th1n the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and ;n COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUlREMEHTS 4.1.2. Z Each..().~.t.ti~ ~~~e. ~u1red f1ow paths shil 1 be duxmst?-ated OPWBl.f: I l.tN"'cr.c ( 01 I

1.

I.to lea.st 111111 per 7 _.ays b~ veri#yiPI§ e"at ttte ~~r.i~re ef.

--t.fte liien eraeell 111~"'1 eA ef U1e fl Gl1

~*~ii #q* the iaeJ"i ctGi-d

.~Rkl h

~ J 4rF.

h.

At least once per 31 days by verifying that each valve (manual.

power operated or automatic) fn the flow path that is not locked, sealed~ or otherwise secured in position, is in Its correct 1><>sition.

SAL£11 - UNIT 1 J/4 1-8

Salem Technical Specification Change Package REACTIVITY CONTROL SYST£i~S SURVEILLANCE REOUIREHE!tTS (Continued)

At least once per 18 months during shutdown by verifying that

• each automac;c valve in the flow path actuates te> 1:s COr"re1:t postt1on on a safety injection test signal.

J,.,_T L.eAST *NCIC f~ le> MaA.1"/115 BY l/G'Jl!IF"t/M:;

""(PA-I "'nlrE FLou>. Pt+-7>1

~fl!'tpi.J1£Hl:} B'{ SPeG1P1c:A-7fOIV

3. I* Z. 2.. °'

'J)£1.1 v<<t!:S AT L6"~S r 33 G Pl'-1 -ro T1-fti K~?O"' C-~1..-441-r SysrcM.,

-~== =*

SALEM - UNlT 1

)/ 4 1 -9

• ~.*~

Salem Technical specification Change Package SOR.AT~~ ~ATER SOURC~S

• S~TjQWN LI~!TI~G CONOtTlOH FOR OPERATtOH J.l.Z.7 As* mini11111, on* of th* fa11°"'tng borated 'Wlt.r sou.-ces shill bt OPERABLE:

a.

A borlc ~Cid Jtoraa* 1y1ce*.,., al la*** 1111e asse<6atad hear

"'"H'-1 l)'Uil* 'llU:~t

~

~~--.........._""" mintmuai conu1ned volume ~11Dns, * ~

~'°

tJWD ~' ?o L----

b.

l.

A in1n1-solution t11na.ratut'I of~

Tht rtfu11 tn9 ~tar stor191 tank vftJu ;ji>.

]

,s,, aoo_

1.

A *int.. contatnld val'-"'t of -l31:&D11.r CJAJ.oni.

z.

A arin'llllUI boron conc1ntrat1on of. 2300 pp11, ana

3.

A 111 ni11111 so I ut1an tlfllPlntuN of JS*F.

APCt\\.!CA8tUTY:

IClDES S £nd 5.

ACTTON:

With no boratld Nmtlr sourc1 OPERABLi, suspend 111 0119rat10ns fnvo1vtn9 CORE ALTOATI°"5 ar DOS1th* reactivity chlngu unt:11 at least ~n.e boratld wau.- sourc1 ts l"tstortd to OPERABLE suaas.

SUAV[lLL.AJICI RIQYtAUCJCTS 4.1.Z.1 The above.-.cau1.-.d bor1t1d ~UI" sourc* shall be demonnrated Oi"'WILE:

°F'o3'L ~

b~.

~J--.-""""""-

a.

4t least once per 7 dlys by:

~ ~

'-~~~~~~~~...a..~~~~~~~--1 L

Yenfyt119 t'-4 bOran conc1nt~acton al '"*-atlr,

2.

Verity1n9 the -.ctr ~.. -,il ~* th* tank, and

l.

V1r~,,~,9 the bar1c acid stara;* tan~ scftwt-~~n t~*r*tUr!

~h*n ~~ ts t~* iource of bor1ted Wit*~

• SALEM

• UNIT 1

)/4 1-14

Salem Technical Specification Change Package REACTIVITY CONTROL SYSTEM SURVEILLANCE REQUIREMENTS (Cont1nued) b

• SA LEH -

UN IT l

)/t', l-15

Salem Technical Specification Change Package REACTIVITY CON'TRO L SYSTEMS BORATED WATER SOl!lCES *OPERATING LIMITING CONOJTIOH FOR OPERATlOH

~ t!oN "/"Artt>rl> Vc>Lt.HPTI" "F c.>A~ 1AJ ACco~"MNccr,.,.,,m

~.1-e.

E*eh el-the fo11mt1ng borated water sourc~s

a. A bortc acid storage s1ste111 *~d at least e~e aste1tag-.~ -eat S~CUtl "1th:

3.

A_ mtn1rnu111 solut1on teqierature of i~:~.:~/,IG.3*FI

b. -.The refueltng water storage t.lntc with:

1. A contained volume of between 364.500 1nd 400.000 gallon~ of wa~er.

2. A bOron concentratton of between 2.300 and 2,500 ppm. and

3. A arlnt1111.1m so1ut1on t~erature of 359F.

APPLICABILITY:

MOIES lt 2. 3 and 4

• ACTION:

a. W1th the boric a~1d storage system inoperable and being used as one of the above required borat1on water systenis. restore the storage syltet'I' to OPERABLE status wth1n 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be tn at least HOT STANl'RY 1111thi11 the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> &nd borated to a SHUflJJWN ~RGfH equivalent to at least 11 de1ta K/k at ZDO"F; restore the ban c ac1 d storaqe systern to OPERAB l.I status within thl' next 7 days or be in COLD SHUTOOWN llithin the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

b. With the refue11ng water storage tank 1ni>perable, restore. the t4nk to OPERABl! status within one hour or be 1n at least. HOT SfANQl1 wiihin the ntxt 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Ind tn COLD SHUTOOWH w1th1n the fo11aw1ng 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVE l LLANCE REOUlREMEKfS 4.1.2.8 Ead'I borated water source shall be demonstratad OPERABLE:

SA l..£M -

UN 1.1' l

)/4 1-16

Salem Technical Specification Change Package

3.

'/er~f7in9 t."te bol".fr..... ~ 'st.... ::'r.e s1s:~ s~l.::~:~

~en:cll"ltUl'I.

\\\\

I' n

"*'=

-~*.. -

SAL~'1

• url!T J/S 1-17

Salem Technical Specification Change Package BORIC ACID TANK CONTENTS BASED ON RWST CONCENTRATION

(/)

z 0

_J

_J

<(

(.9 r-CD z

w

?

_J 0 >

Cl w

a:

0 r-en

~

~

z -

~

7,800 t-I REGION G>F I

I I

I I

I I

I ACC!:EPTABLE 0PERATION

- ~ - - -, -- -.... - - -.., - - - -,- - - -, - - - -.- --

7,600 I

I i

7,400 7,200 7,000 6,800 6,600 6,600 6,700 6,800 6,900 7,000 CONCENTRATION IN BAT ppm BORON SALEM - UNIT 1 Figure 3. 1-2 3/4 1-17(a)

3/4.9 REFUELING OPERATIONS BORON CONCENTRATION LIMITING CONDITION FOR OPERATION 3.9.l With the reactor*vessel head unbolted or removed, the boron con-centration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained unifonn and sufficient to ensure that the more restrictive of the following reactivity conditions is met:

a.

b.

Either a Keff of 0.95 or less, which includes a 1% ~k/k conser-vative allowance for uncertainties, or A boron concentration of > 2000 ppm, which includes a 50 ppm conservative allowance foi=°"uncertainties.

APPLICABILITY:

MOOE 6*

ACTION:

With the requirements of the above specificati n not satisfied, irrmediately suspend all operations involving CORE ALTERATI S or positive reactivity changes and initiate and continue boration at > 10 ~~m ef 20,000 ~~ffi eerie aeia selYtieR or its equivalent until K -

is reduced to < 0.95 or the boron concentration is restored to > 2500 ppm, whichever-is the more restrictive. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.1.1 The more restrictive of the above two reactivity conditions shall be detennined prior to:

a.

Removing or unbolting the reactor vessel head, and

b.

Withdrawal of any full length control rod in excess of 3 feet fran its fully inserted position.

4.9.l.2 The boron concentration of the reactor coolant system and the refueling canal shall be detennined by chemical analysis at least 3 times per 7 days with a maximum time interval between samples of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

W

~

• v:> ~-\\t;..Q__~ wak.-\\t:.Q._ ~V~

~~b~~~ ~~w*~

• The reactor shall be maintained in MODE 6 when the reactor vessel ~

l'lead ; s unbolted or removeeb SALEM-UNIT l 3/4 9-1

3/4.10 SPECIAL TEST EXCEPTIONS SHUTDOWN MARGIN LIMITING CONDmON FOR OPERATION 3.10.1 The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 may be suapended for me.asur1111191lt of control rod worth and shutdown margin provided th* reactivity equivalent to at least the highest estimated control rod worth is available for trip insertion from OP!RABL! control rod(s), and APPLICABILITY:

MOD! 2.

ACTION:

With any full length control rod* not fully inserted and with less than the above reactivity equivalent available for trip insertion, i.JJIDediately initiate and continua boration at ~ lQ gpe of 20,QQO PP* be*ie aeid solution or its equivalent until th SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.

With all full length control rods inserted and the reactor subcritical by lass than the above reactivity equivalent, u..diately initiate and continue. boration at ~

or it*

equi va_lent until th* SHUTDOWH KAR.GIN required by Specif ie&tion 3. 1. 1.1 is restored.

SURVIILLANCI R!QUilU!MINTS 4.10.1.1 Th* position of each full len1th.and part lenath rod either partially or FULLY WITHDRAWN shall be determined at laaat once per 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

4.10.1.2 E&ch full len1th rod not fully inserted shall be demonstrated capable of full insertion when tripped from at least th* 50% withdrawn position within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to reducin1 the SBUTDOWN MAllGIN to less than th* limits of Specification 3.1.1.1 *

'*5" SALIM - UNIT l 3/4..10-1 Amendment No. 91

REACTIVITY CONTROL SYSTEMS BASES 3/4.1.2 BORATJON SYSTEMS Salem Technical Specification Change Package The boron 1nject1on system ensures that ne tive rea,tivity control Is available during each lllOde of rac11tty operation The components requ1red to perform this function include:

1) borated water ources. 2) charg1ng pumps, J) separate flow path~, 4) boric acfd tran5fer pu~s. 5) 1ssee~aied heat \\Pie4~9 S¥Uems, u:id Ci) an emergenc:y power supply from OPERA8 l£ dtesel generators.

---H--=--:-r

~~~----.*H---' W1th the RCS average te111Peratllre* above 200°F. a m1n1-..rn of two boron injection flow paths are required to ensure stngle functtonat capability fn the event an assumed fat lure renders one of the flow paths inoperable. The boratfon capability of either fl~ path ts suffictent to provtde a SHIJTOOWN litARGIN from-expected.0perat1ng cond1t1ons of l.&S delta k/k after ienon dec~y and cooldown to 2009F. The 11u:111llm expected borat1on capabf 11ty requirement occurs at EOL fronr full power equt 1 tbru111 xenon condittons and requ1 res 510' galle"' of 29,999 borated water fro borf c actd s'e~a9a cank' 8&000 gel lens of 2300,.,~

However, to be consistent

~fth the ECCS requirements, the RWST ts requ red to h ve a ~intau"~ contafn!d volume or 350,000 gallons ct.Jrtng operations 1n MOCES

• 2, 3 and 4.

/"'~~ /5.

A--f /Ni<<f' G 1 W'lth the ics tempe~ature below 200~. one injection sy5tem t5 acceptable without single failure consideration on the basfs or the stable reactivity cond1tton of the reactor &nd the 1dd1ttonal restrictions prohibiting CORE ALTERATIONS and positive reactivity change tn the event the single tnject1on system becomes tnoperable.

$i Op

.The boron capab111ty required bel0\\11 2 O°F 1s suff c1ent to provide a SHlJTOOWN MARGIN of ll delta k/k after xen decay and ooldown frOCll ZOO."F to 140°F. This condft1on requires efther gallons of borated water from the boric ae1d storage tanks or gallons of ~3po pp* borate<! water from the refuel~ water storage tank.

~:Al~~~ Gonta1ned water volume and boron ~~~ration o( the RWST also en$ure a pH value of between e.s an~ 11.0 for the solution recirculated w1thin contafninent after a UlCA.

Thts pH band *tn1mf zes the evolution of todfne and m1ntm1zes the effect of Chloride and caust1c stress corrosion on mechanical systems and coinponents.

The contatned water volume limits tnclude allowance for water not ava11able because of d1sch1r1]e line locatton and other physical character!st tcs.

The OPERABILITY of one boron injection system during REFUELING ensures that this system Is available for reactivity control while in "OIE 6.

SA LEH -

UN lT l 8 3/4 1-3

3/4. l REACTIVITY CONTROL SYSTEMS 3/4. 1. l BORATION CONTROL SHUTDOWN MARGIN - Tavg > 200°F LIMITING CONDITION FOR OPERATION

3. 1. 1. l The SHUTDOWN MARGIN shall be greater than or equal to 1.6% delta k/k.

APPLICABILITY:

MODES 1, 2*, 3, and 4.

ACTION:

With the SHUTDOWN MARGIN less than 1.6% delta k/k, immediately initiate and continue boration at gPeateP thaA eP eq~al te 10 gpm of a soluti~n containing greater thafl er equal te 20,000 ppRl!boron or equivalent until the required SHUTDOWN MARGIN is restored.

~:::::: 6

~~0f'Pt"M. l SURVEILLANCE REQUIREMENTS

4. l. l. 1.1 The SHUTDOWN MARGIN shall be determined to be greater than or equal to 1.6% delta k/k:

a.

b.

c.

Within l hour after detection of an inoperable control rod(s) and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter while the rod(s) is inoperable.

If the inoperable control rod is inunovable or untrippable, the above required SHUTDOWN MARGIN shall be increased by an amount at least equal to the withdrawn worth of the immovable or untrippable control rod(s).

When in MODE l or MOOE 2 with K greater than or equal to 1.0, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verif~f ng that control bank withdrawal is within the limits of Specification 3. 1.3.5.

When in MODE 2 with K less than 1.0, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to achieving reactor cri!ftality by verifying that the predicted criti-cal control rod position is within the limits of Specification 3.1.3.5.

• See Special Test Exception 3. 10. 1 SALEM - UNIT 2 3/4 1-1

REACTIVITY CONTROL SYSTEMS SHUTDOWN MARGIN - Tavg ~ 200°F LIMITING CONDITION FOR OPERATION

3. 1. 1.2 The SHUTDOWN MARGIN shall be greater than or equal to 1.0% delta k/k.

APPLICABILITY:

MODE 5.

ACTION:

With the SHUTDOWN MARGIN less than 1.0% delta k/k, immediately initiate and continue boration at greater thaA er e~wal.te lQ gpm of a solution containing greater than er equal t-e 29,999 pplm boron or equivalent until the required SHUTDOWN MARGIN is restored.

~ 6{,b o Pf'W\\f SURVEILLANCE REQUIREMENTS 4.1.1.2 The SHUTDOWN MARGIN shall be determined to be greater than or equal to 1.0% delta k/k:

a.

Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after detecti'on of an inoperable control rod(s) and at least once per 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.s thereafter while the rod(s) is inoperable.

If the inoperable control rod is innovable or untrippable, the SHUTDOWN MARGIN shall be increased by an amount at least equal to the withdrawn worth of the i111110vable or untrippable control rod(s).

b.

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by consideration of the following factors:

1.

Reactor coolant system boron concentration,

2.

Control rod position,

3.

Reactor coolant system average temperature,

4.

Fuel burnup based on gross thermal energy generation,

5.

Xenon concentration, and

6.

Samarium concentration.

SALEM - UNIT 2 3/4 1-3

)

~*.,

Salem Technical Specification Change Package RE~CTIVI'iY C~NT~Ol SYSic~S l/4, l.Z SORATION SYSTE~S FLOW PAT~S - SHUTDOWN

. UHtTtHG COHOITtON FOR OPERATTOH J.1.z.1 As a ~fni.-ia, one ot tne rollO'lting boron inj1etion rtow patns snal1 tie OPE!lA8lE:

a.

A flow pith tro. the barfc l~fd t..nks vt1 1 barfc 1cid tr1nsf1r oump and curgi~9 p~ to U* Ructor Cool1nt Syst* ff th* Darii: !lc'id storag1 tu.It tn Sp1cfttcn'fon 3.1. z.s. ts OPERAS~. 01"

b.

The t1cv ~th tru tbt rtfu*I f n; v&tar statlge tuk vh 1 ch1rging PUlllP to ua. Re*ctor Caal1nt Syst* it tn* r11tuelf11g ~tu* storage tank fn SpecHfca~ton l.1..Z.Sb is OPERAILE.

APPUCA8IUTY:

MODES 5 ind &

• ACTTCJH:

With non. of tJat ibcw* now ~tits OPW81.E, susP.nd 111 op1ru1on1 involvfng CORE ALTERATIONS or pos1tt~* rw*ctivity cn.nges until It 1111~*an1 fnjectfon

~c.h

• h r11tored to O'ERA8Li 1ucu1.

SURVEILUNCE ~EQU IREMEHTS

~-t.Z.l At 1111t one at ttl* above r1qufr1d r1ov o*Uls snall be demonstrated OPERABLE:. I (2111.S~T Aj

, i..

Ai 1~11' IHI." J ~1)1* 1r **r* tf~"f tft*e t11* e***1*u1ttt ot ena 1

• h11t trae1~ **,.i*R *~*tit* *~, *

.,...+~ tr**l*t' &ft*R 1r *~Hal* t..

l*S'F-..~*~ a fl..w,.,h,,.. N'I* *eri* a1i* ~ftkl t1 Y**tl.-

At 11.. i onc1 per Jl d1ys by v1rffyfn9 th1t 11ch ~alve (111nu11, powr GP*l"ltH or 1uta.~tic:) ;n tn1 rlow pnh that ts ndt toet~.

SHIM. or otntndH S1cur1d in posi t1on, is fn its c:arr1c~ posl tlon.:

I SALEH - UNIT Z J/4 1-7 Amendment Ho. 40

.. -~.. :~

• ~*---**---..-

REACTIVITY CONTROL SYSTE>tS FLOW PATHS - OPERATING LIMITING COHDITlON FOR OPE.RATION Salem Technical Specification Change Package 3.1.2.2 At leis~ two of the fol10'toting thr~ boron fnj1ctfon flaw paths $~ll bt OPERABLE:

l.

The flow ~th froa the boric -ac1d tanks vfi

• boric acid transfer pump and a charging pump to the Re*ct.or Cool1nt Systl!ll.

b.

Two flow S)iths from Ul9 rt1fueltng water stora~* tank vta chirgfng Pl.QPS ta the Re.actor Cool1nt Syste11.

APPLlCA81LI1Y:

HODES l. Z, 3 ind 4.

AC!JQ!!:

With only one of th* above required boron fnjectfon flow paths to th* Reec:tor Caolut System OPERABLE, r.stor. at leHt two baron fnjtction flow p~t.hs t:o the hactor eoalant Syst1* to OPERABLE st.tus 'li1th1n 7% hours or b* in u leut HOT STANDIY *nd borated to ~ SHUTO<Mt MAAGlN equhalant to at l*ut 1%

)

. delta lc/k at ZOO*f within the nut. 6 haurs; rHtort &t lust blo flow paths to OPERABLE status w1th1n tht next 7 days or be fn COLD SHUTDOWN within t"8 next 30 haurs.

SURVEILLANCE REQ"!IREMENTS

-......r**......

shall_bt dtnonstrittd OPERABLE:

--tt.

Al ltHt o~a per 31 days by vtrifyfng_ that each valve (a&nual, power operated or *utollat1c) f n the tl<nt path th&t ts not lo~k*d, sealed, or othtr~f se secured fn pasitfon 1 Is tn fts corttct posftfon.

e_

At least one* p*r 18 lllOnths durfng shutdown by verifying th&t eac~

1'-tOll4t1c: v1lv* 1n the flow pith actuates to its correct posftion on a ~*fety tnjectfon t*St s1gna1.

G-

'At lust once per 18 months by verifying that. the t'low path required by Spec1rtcat1on 3.l.2.Z.a d*lfvars at least~o the Reactor Coolant System.

'3 3 tr..P/tlf SALEH - UHlT 2 3/4 1-8

Salem Techn~cal Speci!ication Change Package RU\\CTIVtT'i CONTRO~ SYSTEMS SOR.AT£0 WATER SOURCES

• SHUTOOVN LlMITTHG CONOlTIOH FOR OPERATIOH J. l.2.5 A$ '*ini*ua, one of U11 to)lcnring borated w1t1r sourc11 shill bt OPERABLE:

a.

A boric ~c:1d scarage ay1te.cilft~ ** hue ** auu~~**~ heat "tHetng *YH** with:

-; c?,'900* J

1.

A 1tni-conU1n*d vol'* of-aa9g*l1an1, f '5'""0 ~D G.1'o i--- Z.

81twufH,aee irtd **a.Se& Pl* of boron, and

l.

A *inf-solution taperab.IT'9 at~145 9Fr -I G.3-F]

The T'9fuelfng waur storaoe tank vfth:

r--t g? ooo I

1.

A *in1-i:onuintd vol me ot 12, seef9allons r

2.

A *inf.,. boron conctntratfon ot 2 r JO~. ppm, a.nd

3.

A *ini1111m soluttan t.ltlO*ratur. of JS*F.

)

APPLICAllLITY:

~ES 5 and &.

M;JlON:

With no bor1tld vat.tr Jovtc1 OPE.WU, susp1nd 111 operatfons' invohing CORE ALTERATlOHS or po1tttv1 rtact1~ity chanv1s until at le11t ane borited w*t*r sourct* 1s* restored t.o OPERAIU s~tus.

4.1.2.S

a.

1.

z.

. l.

V1rffyint the '>taron c;onc1ntratton of tr-.iet*I"',

Vtrffyfn9 th* wit*~ ~;**1 01 ~ tank, *nd V.r.~.*~1ncJ Ute boric; 1ctd stcr"1q1. ~nk 1olutfoh ~rature..,hen tt f 1 th* 1ourc1 of bor1tld w1t1r.

~:d~~~~,-~~~b~-~~~~~~~~~4~ho~u:rs~b~y=Y:*:rf~f~y~fn~~th~~~~~*~r*;t~o~r*~w:n*~n~1---=:t~-

~\\.,,1>1 ~

outside *tr tMOerature Is

.c SALEM - UH IT 2 3/4 i-11

)

Salell\\ Technical specitication Chanqe Package REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCES

• OPERATiHG LIMITING CONDITION FOR OPERATION A C!'1N{,lu.va> f/oLV,,.,t: oF. "'30.e-.+ 7at.t>

"'"~,llJ Acc.~;W::C,._,77'1 At;c.i?:c

'5.J-2..

3.1.2.6 As a *fn;mUll, the tallowing bor1t1d w*t*r sour~* s sh*ll bt OPERABLE H required by Speciffc:atto~ l. 2t ____ 3~1* z.. z.:

a.

A borf c ~Cid storage syst.. *ftd *' J11ti oAe *****4*\\** "°'"°""'tei~t

---

~:::!:~!:.W!.:1~th~: -I A '3t.tiW C-.UC8'U 7;9N ~11.J cc

~

Ki

b.

3.

A 1inf1N1 solutfon tMP*raturt at~~!~:. [t., t,*F I Th* r*fuelfng w~t*~ storage tank with:

• • l.

A contained vol\\1111 of betwtn 364,500 and 400,000 gallons of w1t1r 1

z.

A boran conc1ntnt1on of Get'Ween 2.Joo and 2,soo ppm. and

3.

A *inf...- so1ut1on te111Ptr1turt of 35*F.

APPl.ICABILlTY:

NlDES 1. 2, 3 and 4.

ACT I OH:

\\If th Ule boric &cid storage Systta inoperable Ind befng used 1$ Ont of tM ibovt requtrtd borat*d ~tAr sourc:1s. restore the storage syst.111 to OPEBABLE st*tus wf tntn 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be tn 1t 111st HOT STAHOBY wtthtn tbt next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and bor1tld to a SHUTOO\\JN ~RGIH equiwaltnt to at least lS dtlt1 tit at 200°F: restore the borie 1cid storage sy,ta to OPERABLE natus w1thtn Ula nut 7 days* ar bt in

. COLD SHUTDOWN wttbtn tltt nt:ict JO haurs.

b.

Wf ~ th* "fueling water storage tank. fnoperab1*, rut.on tht tank to OPERASLE st&tus \\ifitftfn one hour ort bt fn at hast HOT STAHOBY within tn* next & hours and tn COLD SHUTDOWH wfthtn tft* fo110"'ing 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLAH.fE REQUIREM£HTS 4, l.Z.6 Each borated vatar sourc1 shall be dl'ft!Qnstra~*d OPERABLE;*

if~~b~~ ~~I W~cr*'-'":::::>1Rl.-~1

. '* -Vi.'*1conc1 par di)'Sby:

~wo;M.n_.

I.

Ver Hying t~ t>o-,*-,~ r.oncantrat i no frr dch wo1t1r saurc1.

2.

Verifying t.1\\11' ~*~..,. "'l ot u~.~ ***atv sourc*, ~nd

l.

~*r; fvino tn1 ba~ic acid 1toraq* systt11 1olut1on ~

I :* ;,':;:.::1;.gzi:ggE?pI -~~*:; ]

SALEH - UNIT 2 3/4 l-lZ Ameu1hent lb. SS

Salem Technical Specification Change Package BORIC ACID TANK CONTENTS Bt\\SED ON RWST CONCENTRATION U) z 7,800 0

_J

_J

<(

t-

-1 I REGIONQF t

I I

I I

I I

ACEPTABLE 0PERATION

""'I..

... r-

........ I""'.........,

""' I""'

(.!)

7,600 I-

~

z 7,400 w

~

> 7,200

_J 0 >

0 7,000 w

a:

0 J-U)

~

6,800

~

2 6,600

-~

6,600 6, 700 6,800 6,900 7,000 CONCENTRATION IN BAT* - ppm BORON SALEM - UNIT 2 Figure 3.1-2 3/4 1-12(a)

3/4.9 REFUELING OPERAT!ONS 3/4.9.l 90RON CONCENTRAT!ON LIMITING CONOIT!ON FOR OPERATION 3.9.l With the reactor vessel nead closure bolts less than. fully tensioned or

,_;th the head removed, the bor'On concentration of all filled por'tions of tl'le Reactor Coolant Systam and the refueling canal shall be maintained uniform and sufficient to ensure that th1 more restrictive of the following reactivity conditions is met:

a.

Either a K1ff of 0.95 or less, ~nich includes a 1% il.IV'k conservative allowance for uncertainties, or

b.

A boron concentration of greater than or equal to ZOOO ppm, which includes a SO ppm conservative allowanc1 for uncertainties.

APPLICABILITI:

MOOE 6" ACT!ON:

With the requirements of

• above specification not s~tisfitd, immediataly suspend all operations i olving CORE ALTEAATIONS or positive reactivity r ~ ~';<APM I cnang1s and initiata and continu1 boration at 9"*t1r ~*n ar 1qwal tG lQ gpat~

of a solution con~ining great.r tnan er e~ual ta ZQ,000 ~pm boron or its equi va lint unti 1 K1 ff is r1duc1d to 1 ess than or aqua 1 to 0. 95 or th* bor'On conc1ntration is T""WStol"9d to greatar than or equ~l to ZOOO ppm, ~nichever is th* 11are T""Wstrictive.

The ?rovisions of Sp1cification 3.0.3 are not ~plicacle.

SURVEILLANCE REQUIREMENTS 4.9.l.l The lllOre restrictive of the acove t~o reactivity conditions shall be d1tarmin1d ?rior to:

a.

R111aving or unaolting the reac::or vessel head, and*

b.

Withdra'.al of any full 11ngtn contr'Ot ~d in excass of 3 feet from its fully ins1rtad pdsition.

4. S. l. Z The ~oran conc1ntrat ion of tne reac:or coo 1 ant sy.stam and t!'l1 r"efue i i ng canal snall be d1tarmined by chemical analysis at least once per 7Z hours.

lthe reactor sna11 be maintained in ~OE 6 whenever" fuel is in t!'le r"eactor

'<lit!'l tne,.*actor "essel ritad closure colts less tnan fully t1nsioned or *o1it:i tne nead removed.

SALfM

• UNtT Z 3/4 9-l

J/4.10 SPECIAL TEST EXCEPTIONS SHUTDOWN MARGIN LIMITING CONDITION FOR OPERATION 3.10.l The SBU'l'DowN MARGIN requirement of Specification 3.1.1.1 may be suspended for me&suremant of control rod worth and shutdown mar1in provided the reactivity equivalent to at least the highest estimated control rod worth is available for trip insertion from OPERABLE control rod(s).

APPLICABILITY:

MODE 2.

ACTION:

a.

With any full length control rod not fully inserted and with less than the above reactivity equivalent available for trip insertion, immediately initiate and continue boration at sreater t~ er eq~al ta 10 spm *of a solution containing greater than er eqttal to 20,000

-pfll-boron or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.

~

With all full length control rods inserted and the reactor subcritical by less than the above reactivity equivalent, immediately initiate and continue boration at greater than er eq~~

te lQ gpm of a solution containing greeter than er eqti:al te 20,000

-ppm-boron or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.

SURVEILLANCE REQUIR!H!NTS 4.10.1.l The position of each full length rod either partially or FULLY WITHDRAWN shall be determined at lea5t once per 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

4.10.1.2 Each full len1th rod not fully inserted shall be demonstrated capable of full insertion when tripped from at least the 50% withdrawn position within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to reducin1 the SBUTDOWN MARGIN to less than the limits of Specification 3.1.1.1.

SALEM - UNIT 2 3/4 1.0-1 Amendment No. 66

Salem Technical Specification Change Package '

REACTlVITY CONTROL SYSTEMS BASES 3/4.1.2 BORATlOff SYSTEMS The boron tnje(t ion syste* ensures that ne the reiact fv1ty control ts ava11able during each mode or fac11tty operation The c~onents requfrtd to perfonn this function include:

1) bor*ted water ources. 2) charging pumps. 3) separate f1C1i1 paths. 4) boric acid transfer pu"'1s. 5) assa;faled~eat \\ree*ft9 s~s~e""* a~~ 6) an emergency power supply frOl'll OPERA8l.E diesel ~nerators.

,.....~-~~H~With the RCS average temperatu~e *~ve 20011f. a minimum "of two bor"Ol'I injection r1ow paths are requ1red to ensure sfngle functfonal capabf 11t1 fn the event an assumed failure renders one of the flO'W paths inoperable. The boratto~

capab111ty--of e1ther flow path 1s suff1c1ent to provtde a SHIJT[l)WN MARGI~ frOft expected operating cond1t1ons.of.l.6S de1ta k/k after xenon decay and cooldCliln to 200-r. The-rnax.t~~ e~~ct.ed:.bcu:att~Oll...CaRa~.tHt.Y,.*_Jequt rement occurs at EOL i rom u power*equ111bruia KeOOil eondit1ons and requ~res Sl96 gallons oH9.900

'ffll':bOrated water fr bOrf c ac1 dHl~M-~Wf!&-GP~~Hia+:Htf'lio-1:~~1Q-1~

However. to be consistent with the ECCS requirements, the RWST 1 required to have a mfn1nim contained vo1ume of 350,000 gallons during opera 1 ons 1n MOtES 1., 2, 3 ind 4

).....,.1..v~tt t1~ ~cs tenperature belaw 20091=', one fnjection system ts acceptable wtthout ~tngle failure constder1tion on the basis of t~e stable reactivity cond1tfon of the reactor and the addftfonal restrtct1ons prohibttfng CORE ALTERATIONS and posft1~ reacthfty Change fn the event the single.fnject1on system* becoines 1noptrable.

...... L:;...~-0~

f The boron capabtlfty require low 200'f fs sur fcfent to provide a SHllTOOWN HAAGlN of 11 delta t/k aft xenon decay and ooldo.tn from *200°F to 140-F. This condft1on requ1res either gallons of borated water from the boric ac1d stor1g1 tints or gallons of 2300 PP* borated ~ater

~refueling water storage tanlc.

. z100 The l11111ts on conta1nad *ater volume and boron eoncentratfon of the RWST also ensure a pH value of bet~een 8.5 and 11.0 for the solutton recirculated w1thfn contaln1111nt after 1 lDCA.

Th1s pH band m1n1m1z~s the evolution of 1od1ne an~ m1n1m1zes the effect of chlorfde ind caustic st~ess corrosion on mechanical systems and components. The cont11ned water volume lfmtts include allowance for water not available because of discharge line locat1on and other physical c:haracteri$tlcs.

The OPERAS l LITY of one borot1 1 oJect ton system 0dur1ng REFUE UHG ensures that this system ts available for r"eactlv1ty control wh11e 1n MOCE 6.

SA LEM - UN IT 2 B 3/4 1-3

~

No. 55

ATTACHMENT 3 TECHNICAL BASES AND OPERATIONAL ANALYSIS

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606, REV. 00 TECHNICAL BASES AND OPERATIONAL ANALYSIS FOR SALEM NUCLEAR GENERATING. STATION UNITS 1 AND 2 PREPARED FOR PUBLIC SERVICE ELECTRIC AND GAS COMPANY BY ABB COMBUSTION.ENGINEERING NUCLEAR SERVICES PDR ADOCK 05000272

(

9306210212 9306 i-1 ---~

\\

P PDR

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS Section Table of Contents Title

1.0 INTRODUCTION

CEN-606 REV. 00 6

1.1 PURPOSE AND SCOPE..

6 1.2 REPORT ORGANIZATION 8

1.3 PAST vs. PRESENT METHODOLOGY OF SETTING BAT CO~CENTRATION 9 2.0 TECHNICAL BASES FOR REDUCING BAT CONCENTRATION

• 12 2.1 BORIC ACID SOLUBILITY 12 2.2 METHOD OF ANALYSIS AND ASSUMPTIONS.........

12 2.2.1 RCS Boron Concentration vs. Tem.12erature...

12 2.2.2 ImQact of Cool down Rate........... 19 2.2.3 AQQlicability to Future Reload Cycles 21 2.2.4 Boron Mixing in the RCS and in the Pressurizer....

22 2.3 BORATED WATER SOURCES -

SHUTDOWN (MODES 5 AND 6) 23 I

2.3.1 2.3.2 2.3.3 2.3.4 2.3.5 2.3.6 Boration Reguirements for Modes 5 and 6 Assum12tions Used in the Analysis of Modes 5 and 6 Modes 5 and 6 - Analysis and Outline Modes 5 and 6 -

Cooldown -

Makeu12 from the RWST Boration Requirements -

Modes 5 & 6 Modes 5 and 6 -

Cooldown, Using BATs BAT Storage Requirements ABB Combustion Engineering Nuclear Services Pag~ 2 of 133

.. ' ~... ~*..:.'

23 25 29 31

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 Section Table of Contents (continued)

Title 2.4 BORATED WATER SOURCES -

OPERATING (MODES 1, 2, 3, and 4) 32 2.4.1 Boration Requirements for Modes l, 2, 3, 2.4.2 2.4.3 2.4.4 2.4.5 and 4................

~.

Assumptions Used in the Modes 1, 2, 3, and 4 Analysis.

Modes 1, 2, 3, and 4 Analysis Results-Equilibrium Xenon Scenario *. *. *.

Modes l, 2, 3, and 4 Analysis.Results-Peak Xenon Scenario Simplification Used Following RHRS Initiation..

2.5 BORATION SYSTEMS -

BASES.....

2.6 2.5.1 2.5.2 Derivation of the 73,800 Gallon Volume (RWST)

Derivation of the 4L 800 Gallon RWST Volume Required when the Smallest BAT Volume is ACTION STATEMENTS ON FLOW REQUIREMENTS TABLES -

SECTION 2..

FIGURES -

SECTION 2 ABB Combustion Engineering Nuclear Services Page 3 of 133 32 32 34 38 40 42 43 44 45 48 87

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS Section Table of Contents (continued)

Title CEN-606 REV. 00 3.0 OPERATIONAL ANALYSIS..............

• 95

3.1 INTRODUCTION

TO THE OPERATIONAL ANALYSIS... * *...

95 3.2 RESPONSE TO EMERGENCY SITUATIONS * *...

3.2.1 3.2.2 3 *. 2. 3 Accident Boration Requirements.

Shutdown Margin Recovery Emergency Boration...

3.3 FEED-AND-BLEED OPERATIONS 95 96 97 98 99 3.4 BLENDED MAKEUP OPERATIONS.. ~............ 101 3.5 SHUTDOWN TO REFUELING -

MODE 6............. 103 3.6 SHUTDOWN TO COLD SHUTDOWN -

MODE 5........... 107 3.7 LONG TERM COOLING AND CONTAINMENT SUMP pH....... 109 TABLES -

SECTION 3.

FIGURES -

SECTION 3

... 110

. 123 4. 0 REFERENCES....................... 13 3 ABB Combustion Engineering Nuclear Services Pag~ 4 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES.AND OPERATIONAL ANALYSIS CEN-606 REV. 00 Section Appendix 1 Appendix 2 Appendix 3 Appendix 4 Table.of Contents (continued)

Title Page List of Appendices Derivation of the Reactor Coolant System Feed-and-Bleed Equation.

Methodology for Calculating Dissolved Boric Acid per Gallon of Water.

Methodology for Calculating the Conversion Factor Between Weight Percent Boric Acid Al-1

. A2-1 and ppm Boron................. A3 -1 Bounding Core Reactivity Considerations...

A4-1 ABB Combustion Engineering Nuclear Services Page,5 of 1 33

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS

1.0 INTRODUCTION

1.1 PURPOSE AND SCOPE CEN-606 REV. 00 This report defines the methodology and outlines the technical bases which allow a reduction in the Boric Acid Tank (BAT) concentration to the point where heat tracing of the boric acid makeup system is no longer required to prevent boric acid precipitation.

The basic methodology or procedure used to set the minimum BAT concentration and level for Modes 1, 2, 3, and 4 is derived from the safe shutdown requirements of Reference 4.1, (NUREG 0800 Branch Technical Position RSB 5-1, "Design Requirements for the Residual Heat Removal System", (BTP 5-1)) ~

For purposes of implementing the requirements for heat removal capability for compliance with this position, plants were divided into three classes by the NRC.

Salem Unit 1 is a Class 3 plant and Unit 2 is a Class*2 plant per BTP 5-1.

Classes 2 and 3 are defined as follows in the Branch Technical Position:

Class 2 "Partial implementation of this position for all plants (custom or standard) for which CP or PDA applications are docketed on or after January 1, 1978 and for which an OL issuance is expected on or after January 1, 1979."

Class 3 "The extent to which the implementation guidance in Table 1 will be backfitted for all operating reactors and all other-plants for which the issuance of the OL is expected before January 1, 1979, will be based on the combined' I&E and DOR review of related plant features for operating reactors."

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BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 A table is included in the BTP which describes recommended implementation for Class 2 and 3 plants.

Two independent and redundant boration flow paths with appropriate borated water are provided in Salem Units 1 and 2 to compensate for reactivity changes and all expected transients throughout core life.

The sources of borated water are the BATs and the Refueling Water Storage Tank (RWST).

The design bases used to establish the required volume and boron concentration in the BAT hav~.been examined, and the results are presented in this Section.

In addition, the minimum RWST volume requirements for RCS boration have been calculated.

Sufficient dissolved boric acid must, be maintained in the BATs to provide the shutdown margin specified in the LCOs for Technical Specification (TS) 3.1.1.1 for a cooldown from hot standby (Mode 3) to cold shutdown (Mode 5) conditions.

Further, both the minimum level and boron concentration which must be maintained in the BATs for Modes 5 and 6 are based upon the ability to maintain the shutdown margin specified in the LCOs for TS 3.1.1.2 (Mode 5) following xenon decay*and cooldown from 200°F to 135°F.

This document has been prepared to support a reduction in the concentration and volume of boric acid which must be maintained in the BATs at Salem Units 1 and 2 to maintain adequate shutdown margin.

It also shows that this margin can be provided by one (1) BAT for each unit for most of the operational conditions as shown in Technical Specification Figures 3.1.2.8 (Unit 1) and 3.1.2.6 (Unit 2).

The studies described herein support a reduction in boric acid concentration to levels below that at which precipitation can occur at the temperatures normally expected in the BATs ABB Combustion Engineering Nuclear Services Pag~ 7 of 133

.~,.....

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 and associated piping areas of the plants.

This reduction eliminates the requirement for heaters and heat tr_acing on the BATs and associated piping.

To accomplish this, the analysis performed to support the original requirements for boric acid has been reevaluated, incorporating the revised boration-to-cold-shutdown methodology.

This methodology has been developed to demonstrate the acceptability of reducing the concentration and volume of stored boric acid.

The work described in this report was performed specifically for Salem Units 1 and 2.

To the extent possible, the calculations performed and th~ values obtained will be applicable to future fuel cycles.

(See Section 2.2.3.)

The physics parameters used in this analysis have been selected conservatively to bound core physics parameters for the next reload fuel cycle.

Future cycle core physics parameters.are to be compared to the data in Appendix 4 to ensure that the results of these calculations remain bounding.

The values in Technical Specification Figure 3.1.2.8 (Unit 1) and Figure 3.1.2.6 (Unit 2) may change slightly; however, there should not be a need to heat trace the piping and components of the boric acid system for the remainder of plant life.

1.2 REPORT ORGANIZATION This report has been organized into three sections:

Introduction, Technical Bases, and Operational Analysis.

In Section 2.0, "Technical Bases for Reducing BAT Concentration", the methodology which allows a significant reduction in BAT tank concentration and volume is outlined, and the results of the detailed calculations performed in support of the Technical Requirements for the Technical Specifications are presented.

Separate calculations were ABB Combustion Engineering Nuclear Services Pag~ 8 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 performed for TS 3.1.2.7 (Unit 1) and TS 3.1.2.5 (Unit 2)

(Borated Water Source -

Shutdown); TS 3.1.2.8 (Unit 1) and TS 3.1.2.6 (Unit 2) (Borated water Source - Operating); as well as Bases Specification 3/4.1.2 (Boration System Bases).

In addition, revised action statements have. been prepared for TS 3.1.1.1 (Reactivity control Systems/Shutdown Margin/Tave >200°F), TS 3.1.1. 2 (Reactivity Control Systems/Shutdown Margin/Tavg,5200°F), Specification 3. 9.1 (Refueling Operations/Boron Concentration), Specification 3.10.l (Special Test Exception/Shutdown Margin), and S~rveillance Requirement 4.1.2.2 (Reactivity Control Systems/Flow Paths Operating) (Unit 2 only in current Technical Specifications).

I In Section 3.0, "Operational Analysis", the impact of the reduction in the concentration of boric acid stored in the BATs on normal operations is outlined.

The operations evaluated in Section 3.0 are as follows: feed-and-bleed, blended makeup, shutdown-to-refueling, and shutdown-to-cold-shutdown.

Tables and figures are co~tained at the end of Sections 2.0 and 3.0 for convenient reference.

)

1.3 PAST vs. PRESENT METHODOLOGY OF SETTING BAT CONCENTRATION Prior to the development of the new methodology for setting.

BAT concentration and level described in this report, the level and concentration specified in the plant Techni6al Specifications for Modes 1, 2, 3, and 4 were based upon the ability to perform a cooldown-to-cold-shutdown in the absence of letdown.

(Safe Shutdown requirements of NUREG-0800, BTP 5-1 event).

Using the old methodology, the reactor coolant system (RCS) was borated prior to initiating cooldown to the boron concentration required to provide a ABB Combustion Engineering Nuclear Services Pag~ 9 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 shutdown margin ~1.6% Ak./k at temperatures >200°F (refer to TS 3/4.1.1.1).

Boration without letdown can be accomplished using safety grade equipment. In the limiting situation, it was assumed that letdown was not available,- and boration was accomplished by charging to the RCS (consequently filling the pressurizer).

In this scenario, boron concentration in the RCS typically had to be increased by approximately 900 ppm prior to commencing cooldown, and the limited volume available in the pressurizer necessitated storing highly concentrated boric acid solution in the.BATS.

However, subsequent advances have made it possible to develop new methodologies for setting BAT concentration and levels.

The methodology for setting concentration and level of Modes 1, 2, 3, and 4 described in this report d~ffers from previous methodologies in that boration of the RCS is performed concurrently with plant cooldown, i.e.,

concentrated boric acid is added concurrently with cooldown, thereby providing the RCS inventory makeup to compensate for coolant contraction.

By determining the boron concentration required to maintain proper shutdown margin at each temperature during a plant cooldown, the concentration of boric acid in the BATs can be decoupled from available pressurizer volume.

As the present study shows, the concentration of boric acid which must be maintained in the BATs to allow cooldown-without-letdown to cold shutdown conditions can be reduced to a value between 3.75 and 4.0 weight percent,, where heat tracing of the boric acid system is no longer required, i.e., the ambient temperature in the auxiliary building is sufficient to prevent boric acid precipitation.

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BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 Similarly, this new methodology was utilized in setting the minimum concentration and level of the boration source which is required to be operational in Modes 5 and 6.

since letdown is available in the cooldown scenarios of Modes 5 and 6, feed-and-bleed may be conducted when it is necessary to increase.RCS boron concentration.

In addition, boration can be conducted concurrently with cooldown as part of normal system makeup.

By ensuring that the boron concentration is maintained greater than that required for proper shutdown margin at all temperatures, the boric acid concentration in the BATs can be lowered to a value between 3.75 and 4.0 weight percent for Modes\\5 and 6.

, ABB Combustion Engineering Nuclear Services Pag~ 11 of 1 33

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 2.0 TECHNICAL BASES FOR REDUCING BAT CONCENTRATION 2.1 BORIC ACID SOLUBILITY Figure 2-1 is a plot of solubility of boric acid in water vs. temperature, for.temperatures between 32°F and 160°F.

The data for Figure 2-1 were obtained from Reference 4.2 and are included herein as Table 2-1.

Note that the solubility of boric acid at 32°F is 2.52 weight percent and, by interpolatio.n, at.58°F is 4.00 weight percent.'.At or below a concentration of 4.0 weight percent boric acid, the normal ambient temperature in the auxiliary building will be sufficient to preclude precipitation within the Boric Acid Makeup Subsystem.

In Reference 4.3, the requirement for monitoring and recording the ambient temperature in the vicinity of the BATS was identified to verify that the temperature is maintained above 63°F.

The 63°F temperature is specified to provide a 5°F margin of conservatism above the 58°F solubility limit.

Maintenance of the ambient temperature is further ensured by.Technical Specification Surveillance Requirements.

2.2 METHOD OF ANALYSIS AND ASSUMPTIONS 2.2.1 RCS Boron Concentration vs. Temperature 2.2.1.1 Operating Modes 1, 2, 3, and 4 -

Equilibrium Xenon Scenario As described in Section 1.3, the methodology developed to justify a significant reduction in the concentration of" boric acid which must be maintained in the BATs in Modes 1, 2, 3, and 4 differs from the previous methodology in that ABB Combustion Engineering Nuclear Services Page, 1 2 of 1 33

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 boration of the RCS is performed concurrently with cooldown.

In order to ensure adequate shutdown margin during the cooldown process, concentrated boric acid solution is added as part of normal system makeup.

To employ a methodology allowing boration conqurrent with cooldown, the exact boron concentration in the reactor coolant necessary to maintain the required shutdown margin must be known at any temperature during the cooldown process.

In addition, in order to ensure applicability for the entire fuel cycle, a conservative cooldown scenario has been developed which incorporates the maximum increase in RCS boron concentration which the operator must achieve in order to maintain an adequate shutdown margin at the most limiting time in the fuel cycle.

Such a limiting scenario is as follows:

1.

Conservative core physics parameters are used to

-determine *both the concentration and the volume of boric acid solution which must be provided from the BATs during plant cooldown.

For this analysis, the end-of-life (EOL) initial boron concentration is assumed to be zero ppm.

EOL moderator cooldown effects are used to maximize the reactivity change during the plant cooldown.

EOL values of inverse boron worth (IBW) were used in combination with EOL moderator reactivity insertion rates, normalized to the most Negative Technical Specification Moderator Temperature

\\

Coefficient (MTC) limit, since it is known that this yields results that are more limiting than any actual combination of MTC and IBW values throughout the fuel cycle.

These assumptions assure that the required boron concentration and the minimum BAT volume requirements conservatively bound all plant cooldowns during core life.

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BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS

2.

The most reactive rod is stuck in the full out position.

CEN-606 REV. 00

3.

Prior to time zero, the plant is operating at 100%

power, with core xenon concentration at the 100% power equilibrium level.

4.

There is zero RCS leakage.

5.

At time zero, the plant is shutdown and held at hot zero power conditions for 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br />, at wbich time the xenon transient after shutdown will have decayed back to the 100% power equilibrium level.

(Further xenon decay will add positive reactivity to the core during the plant cooldown).

No credit was taken for the negative reactivity added during the xenon transient following reactor shutdown.

6.

At time ~ 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br />, loss of offsite power is assumed, and all non-safety grade plant equipment and components are assumed to become inoperative.

A cooldown-to-cold-shutdown is initiated.

The scenario outlined above has been used to generate the borated water requirements for Modes 1, 2, 3, and 4.

It produces a situation wherein positive reactivity will be added to the reactor core from two sources at the time cooldown-from-hot-shutdown is initiated.

The two reactivity sources are (1), the temperature effect due to an overall negative isothermal temperature coefficient of reactivity, and (2), the poison (xenon) effect due to the decay C?f xenon-135 below the 100% power ABB Combustion Engineering Nuclear Services Page,14 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 equilibrium level.

This scenario, therefore, represents the greatest operational challenge in meeting the requirement for boration of the RCS and maintaining the shutdown margin required by the Technical Specifications while cooling the plant from hot standby to cold shutdown conditions.

Although this specification is only applicable to Modes,1, 2, J, and 4, sufficient volume is stored in the BATs to provide for boration to Mode 5 (Cold Shutdown).

2.2.1.2 Operating Modes 1, 2, 3, and 4 Peak*Xenon Scenario A second scenario has been considered in this study.

In this case, the bounding assumptions in Section 2.2.1.1 have been modified to cover the condition of peak xeno~ in the core at the time cooldown is initiated.

Additionally, to ensure applicability for the entire fuel cycle, a conservative cooldown scenario has been devised which incorporates the maximum incr~ase in RCS boron concentration which the operators must achieve in order to maintain an adequate shutdown margin at the most limiting time in the fuel cycle.

Such a limiting scenario is as follows:

1.

Conservative core physics parameters are used to determine both the concentration and the volume of boric acid solution which must be provided from the BATs during plant cooldown.

As in th~ equilibrium xenon scenario (Section 2.2.2.1), one case has been examined, with the initial boron concentration equal to zero (O) ppm, with xenon concentration in the core at the post-trip peak at the time cooldown is initiated.

EOL moderator cooldown effects are used to maximize the reactivity change during the plant cooldown.

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BORl'.C ACID COWCBJITRATION REDUCTION Bl'FORT

~ECBBJ:~L BASES 1'lllD OPBRATIO:tmL ANALYSIS CEN-606 REV. 00 EOL values of inverse boron worth (IBW) were used in combination with EOL moderator reactivity insertion rates, normalized to the most Negative Technical Specification Moderator Temperature Coefficient (MTC) limit, since it is known that this yields results that are more limiting than any actual combination of MTC and IBW values throuqhout the fuel cycle.

These assumptions assure that the requirements for minimum BAT volume and boron concentration conservatively bound all plant cooldowns during core life.

2.

The most reactive rod is stuck in the full out position.

3.

Prior to time zero, the plant is operating at 100%

power, with core ~enon concentration at t~e 100% power equilibrium level.

4.

There is zero RCS leakage.

5.

At time zero (t-O), the plant i.s shut down and held in the hot, zero power condition (547°F and 2250 psia) for approximately 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />, at which time the xenon transient after shutdown will have reached its peak.

During this interval, the plant is diluted by 140 pp~

to zero ppm boron.

(Reference 4.4).

This dilution is the :maximum possible at EOL during this time period.

6.

For conservatism, reactor coolant average temperature has been assumed to be 547°F.

At time ~ 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />, with core xenon at the post-shutdown peak, a cooldown-to-cold-shutdown is initiated.

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BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 The peak xenon scenario described herein has been used to define, for plant administrative procedures, the volume of borated water which must be available in the two BATs in the event that the plant operating staff intends to maintain the criticality at hot, zero power conditions for seven hours by deborating to compensate for xenon buildup.

The scenario is postulated to account for the following:

1.

Conditions exist which cause the operating.staff to hold th plant at hot standby conditions, '~nd

2.

During this interval, core xenon concentration peaks.

For the ensuing cooldowri, the two elements which add positive reactivity to the core are considered in this analysis.

The plant must be borated to maintain the required shutdown margin as core xenon decays to the equilibrium level.

When cooldown is initiated, additional boration will take place as makeup from the BAT and RWST is added to compensate for coolant contraction.

2.2.1.3.

Operational Modes 5 and 6 The methodology developed to determine the boration requirements for Modes 5 and 6 differs from the method used in previous refueling cycles.

Consistent with the new methodology, boration of the RCS is performed concurrently with cooldown.

Concentrated boric acid is added during the cooldown evolution as part of normal system makeup.

To employ this methodology, the exact boron concentration required in the RCS, must be known throughout the temperature range during the cooldown process.

ABB Combustion Engineering Nuclear Services Page.1 7 of 1 33

./": *. -~

BORIC ACID CONCENTRATION REDUCTION-EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 The following scenario was developed to identify the most limiting cooldown transient for Modes 5 and 6.

1.

EOL conditions are assumed, with the initial boron concentration in the reactor coolant at the level necessary to provide a shutdown margin of 1.0% Ak/k at 200°F and with a xenon free core.

EOL MTC effects are used to maximize the reactivity change during the plant cooldown.

IBW data at EOL were used in conjunction with EOL MTC reactivity insert*ion rates normalized to the most.Negative Technical Specification MTC limit, since it is known that this yields results more limiting than does any actual combination of MTC and IBW values throughout the fuel cycle.

2.

The most reactive rod is stuck in the full out position.

3.

There is zero RCS leakage.

4.

RCS feed-and-bleed can be used to increase boron concentration.

5.

RCS makeup is supplied either from the RWST alone or from a blended combination of makeup from the BAT and the Demineralized Water Storage Tank (DWST).

6.

The most limiting scenario for boration in Modes 5 and

6. requires that a shutdown margin of 1. 0% Ak/k be maintained during the cooldown from 200°F to 135°F.

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BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 2.2.2 In Mode 6, with the reactor vessel head detensioned or removed, the boron concentration in the RCS, the refueling canal, and the refueling cavity must be maintained at the most restrictive of the following two reactivity conditions:

a.

keff of ~0.95 or less, which includes a 1% Ak/k allowance for uncertainties, or

b.

A boron concentration ~2000 ppm, which includes a 50 ppm allowance for uncertainties.

If the required shutdown margin for Mode 6 is not satisfied, the current TS 3.9.1 requires an immediate suspension of core alteration or of positive reactivity addition and initiation of boration at a rate ~10 gpm of a solution contaj_ning ~20,000 ppm boron, to be maintained until the required concentration has been restored.

The rate at which borated solution is to be added in this case must be increased in ~roportion to the decrease in the concentration of the solution in the BATs.

TS 3.1.2.1 requires that a flow path from either the RWST or at least one BAT be available to meet this requirement.

Impact of Cooldown Rate As discussed in the previous section, a conservative cooldown scenario was selected for use in determining the boron concentration levels required in the RCS. These concentration results were then used to define the minimum Technical Specification BAT tank inventory requirements.

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BORIC ACID COHCJDJTRA~IOH REDUC~lOB EFFORT TECBlilOL BASES lU1D OPERATIONAL UALYSIS CEN-G06 REV. Oo In the equilibriu~ xenon scenario for Modes 1, 2, 3, and 4, positive reactivity was added concurrently from two sources at the time that plant cooldown from hot standby was initiated.

The component resu~ting from an overall negative isothermal temperature coefficient of reactivity is independent of time but is directly dependent on the change in coolant temperature.

In contrast, the component resulting from the decay of xenon-l3S below the equilibrium value at 100% power is independent of temperature but is directly dependent on time.

As a result, for a given temperature decrease, a slow cooldown rate wil~ require the addition of more boron to the reactor coolant than will a fast cooldown rate, since coMpensation must be provided for more positive reactivity due to xenon decay.

A maximum allowable cooldown rate of 100°F/hr is established in Salem Technical Specification 3/4.4.9; however, there is an administrative limit of 50°F/hr. The required boron concentration as a function of temperature during a plant cooldown is shown graphically in Figure 2-2.

The bases for Technical Specifications 3.1.2.7 (Unit 1) and 3.1.2.5 (Unit

2) include the consideration of a cooldown following xenon decay.

As a result, boration requirements are independent of cooldown rate for the analysis of Mode 5.

An effective cooldown rate of 10°F/hr was assumed for the deterlnination of the required volume of boric acid solution and the boron concentration of that solution in the BATS durinq Modes 1, 2, 3, and 4; these calculations esta~lish the Technical specification limits for these parameters.

This slow cooldown rate was selected to ensure that the required volume of boric acid solution was chosen ABB Combustion Engineering Nuclear Services Page 20 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 2.2.3 conservatively.

As shown in Tabl~ 2-2, taking the plant from hot standby to cold shutdown (a change of 347°F) requires 34.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />, including an initial delay at *hot standby of 4.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> and an additional 13.35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br /> for added conservatism.

An effective cooldown rate of 10.0°F/hr is thereby main~ained in cooling the plant from an average coolant temperature of 547°F to an average coolant temperature of 200°F in 34.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.

This scenario will conservatively bound cooldowns that occur earlier and/or at higher cooldown rates.

The above scenario bounds the reactivity effects of the BTP 5-1 cooldown.

It is assumed in the BTP 5-1 scenario that Safety Grade plant equipment will be capable of bringing the RCS to RHRS entry conditions within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> after cooldown is initiated.

Applicability to Future Reload Cycles To ensure that the current analysis will be valid for future cycles, data provided by Salem conservatively bounding both Units 1 and 2 was utilized in the analysis.

It is anticipated that the physics data used in this analysis will bound future fuel cycles of similar reload car.es unless changes are made to the fuels related Technical Specifications~

Appendix 4 contains the bounding physics assumptions used to produce the required boron concentration values.

As long as the input is more conservative than the physics parameters used in this analysis, the values generated in this analysis and presented in this report will bound the boron concentration values for future reload cycles.

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BORIC ACID COBCENTRATIOH REDUCTION EFFORT TECBIUCAL BASES AND OPERATrOHJU. ANALYSIS CJ!:N-606 REV. CO 2.2.4 Boron Mixing in the RCS and in the Pressurizer A constant pres&urizer level was assUJUed throughout the cooldown calculations described in sections 2.J and 2.4, i.e., plant operators charged to the RCS only as necessary J

to makeup for coolant contraction.

In this situation, the driving force for the mixinq ot tluid between the RCS and the pressurizer is s~all.

As a conservatism, complete mixing was assumed between all makeup fluid added to the reactor coolant system through the loop charginq nozzles and the pressurizer.

Further, system pressure must be reduced during the plant cooldown process, as indicated in Section 2.4.

This pressure reduction is necessary to ensure that the Reactor Vessel Pressure-Temperature limits are not violated; it is also requi~ed since the RHRS is a low pressure system and is normally aligned at or below an RCS p~essure not greater than 375 psig; in this analysis, realignment was assumed to occur at a pressure of 350 psia.

Durinq a natural circulation cooldown, this depressurization is typically performed*usinq the auxiliary pressurizer spray system.

For additional conservatism, boron added to the pressurizer via the spray system in Modes 1, 2, J, and 4 was assumed to remain in the pressurizer and thus to be unavailable for mixinq with the fluid in the rem~inder of the Res.

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BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 2.3 BORATED WATER SOURCES -

SHUTDOWN (MODES 5 AND 6) 2.3.1 Boration Regµirements for Modes 5 and 6

.As stated in the plant Technical Specifications, a boration capacity providing a shutdown margin of 1.0% L\\k/k following xenon decay is required at temperatures less than or equal to 200°F.

This boration capability is sufficient to provide the required shutdown margin during a plant cooldown from 200°F to 135°F.

2.3.2 The required RCS boron concentrations were determined on this basis for temperatures of 200°F and 135°F, using conservative core physics data furnished by Salem (Reference 4.5).

Intermediate points were determined by linear interpolation.

The data for a Mode 5 and 6 cooldown are given in Table 2-3 and*are plotted as the required shutdown curve in Figures 2-3 and 2-4.

Note in Table 2-3 that a total increase in boron concentration of 83.3 ppm is required for the plant cooldown from 200°F to 135°F in Modes 5 and 6.

Assumptions Used in the Analysis of Modes 5 and 6 A complete list of assumptions and initial conditions used in calculating the minimum BAT inventory requirements for Modes 5 and 6 is contained in Table 2-4.

In the process of taking the plant from hot standby to cold shutdown, the RHRS will normally be aligned after entering Mode 4, i.e., when the RCS temperature and pressure have been lowered to approximately 350°F and 375 psig.

For conservatism, in this analysis the RHRS operating pressure is assumed to be 350 psia.

As shown in the next section, the total system ABB Combustion Engineering Nuclear Services l,

Page,23 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 2.3.3 volume, i.e., RCS volume, plus pressurizer (PZR) volume, plus RHRS volume, must be known for the analysis of Modes 5 and 6 cooldowns.

The exact volumes of each of these have been determined for use in this analysis to establish the BAT inventory requirements.

The volume of the RHRS has been determined in Reference 4.6.

The system volume used in the calculation is as follows:

(RCS volume) + (PZR volume at 0% power) + (RHRS Volume) or (10,812 ft 3 )

+ (500 ft3 )

+ (1700 ft 3 ) = 13,012 ft 3 Modes 5 and 6 - Analysis and Outline As noted in Section 2.3.1, the required boration capacity is based upon pr0viding shutdown margins of 1.0% Ak/k following xenon decay and a plant cooldown from 200°F to 135°F.

The operating scenario employed in determining the required RCS boron concentration and ensuring that proper shutdown margin will be maintained is as follows:

A.

The systems are initially at a temperature and pressure of 200°F and 350 psia.

At EOL, the initial boron concentration in the RCS, pressurizer, and the RHRS is 893.9 ppm b_oron.

The RHRS is aligned arid in operation.

The core is xenon-free.

B.

With charging limited to makeup for coolant contraction only, the RWST alone does not provide sufficient boron to compensate for the positive reactivity added during ABB Combustion Engineering Nuclear Services Page,24 of 1 33

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 2.3.4 the cooldown by the moderator coefficient.

Using borated water from the RWST (boron concentration = 2300 ppm), a system feed-and-bleed must be conducted to increase boron concentration in the RCS before proceeding with the cooldown below 200°F.

This initial feed-and-bleed (60 minutes at 75 gpm) to approxim~tely 960.0 ppm ensures that the RCS boron concentration is maintained above the level required to provide adequate shutdown margin while the plant is cooled from 200°F to 135°F.

C.

A plant cooldown is then performed from an average coolant temperature of 200°F to an average temperature of 135°.

Makeup water from the RWST (2300 ppm boron) is charged to the RCS as necessary to compensate for coolant contraction during the cooldown.

D.

Alternatively, with the BATs available, makeup may be supplied by blending boric acid solution from the BATs with demineralized water from the PWSTs.

Modes 5 and 6 - Cooldown Makeup from the RWST From Equation 2.0 of Appendix 2 and the conversion factor that is derived in Appendix 3, the initial boric acid mass in the system can be calculated as follows:

ABB Combustion Engineering Nuclear Services Page :25 of 1 33

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 At EOL, Mba =

8 9 3

• 9 ppm 12 I 512

• Q ft J

+

5 Q Q, Q ft J 1748.34 ppm/wt.%

0.01662 ft 3 /lbm 0.01912 ft 3 /lbm 100 -

((893.9 ppm)/(1748.34 ppm/wt.%)]

or Mba = 4, 003. 3 lbm boric acid (EOL)

The initial total system mass of 782,981.8 lbm given in Tables 2-5 and 2-6 was obtained as follows:

Minit =*(Initial Boric Acid) +(Initial RCS Water Mass)

+ (Initial RHRS Water Mass) + (Pressurizer Water Mass)

Minit; = 4003. 3 lbm + (10,812ft 3 +1700ft 3 )

+

(500.0ft 3 )

(0.01662 ft 3/lbm)

• (0.01912 ft 3/lbm)

Thus,

• Minit; = 782,981.8 lbm (EOL)

The boron concentration at the end of the feed-and-bleed evolution is determined by an iterative calculation.

This endpoint concentration then permits charging (from the RWST) only as required to compensate for coolant contraction an~

ensures that the final concentration provides the required shutdown margin at the end of the cooldown, (135°F).

ABB Combustion Engineering Nuclear Services Pag~ 26 of 1 33

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 As indicated above, the initial boron concentration is equal to 893.9 ppm; the mass of boric acid in the system is 4, 003. 3 lbm; and the total system mass (Mrot> is equal to 782,981.8 lbm.

The volume of water and the pressure in the pressurizer are held constant at 500.0 ft3 and 350 psia, respectively, and complete mixing is assumed between the PZR and the RCS, as discussed previously.

The boron concentration in the RWST is 2300 ppm.

Equation 9 *. o of Appendix 1 was used to determine* the time and volume required to complete the initial feed-and-bleed evolution.

Defining the time constant as follows,

't" =

(ms..) RCS+ (mi..) RHRS+ (mw> PZR Cm> in 10' 812 ft 3 + 1, 7 00 ft 3 500. 0 ft 3

+

't" =

0.01662 ft 3 /lbm 0.01912 ft 3/lbm (75 gal/min) x (8.329 lbm/gal) (ll Therefore,

't" = 1, 247. 01 minutes (at 200° F and 350 psia)

The feed-and-bleed equaticin is:

-~

-~

C(t) = Co(e T)

+ cin (1-e T)

ABB Combustion Engineering Nuclear Services Pag~ 27 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 Conducting a feed-and-bleed operation with one charging pump delivering 75 gpm and letdown flow equal to 75 gpm, 60 minutes are required to reach a boron concentration of 960.0 ppm in the RCS.

This equates to a feed-and-bleed volume of 4,500 gallons.

The volume and concentration of makeup required was then calculated for each 10°F. increment of cooldown from 200°F to 135°F, and the results are tabulated in Table 2-5. The BACR Code (Reference 4.7) and the following equations were used to perform this analysis:

Shrinkage Mass =

RWST Water Volume (@ 70° F)

=

Shrinkage Mass

8. 329 0 lbm/ gal (ll Boric Acid Added = (RWST Volume) x 0.11103 lbm/gal <2 J Total Boric Acid = Initial Boric Acid +Boric Acid Added Total System Mass = Initial System Mass + Shrinkage Mass

+ Boric Acid Added Final Concentration =

(I)

(2)

(3)

Reference 4.8 Appendix 2 Appendix 3 (Total Boric Acid) (100) (1748.34) ! 3 l Total System Mass ABB Combustion Engineering Nuclear Services Page :28 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 2.3.5 The data are plotted as the actual shutdown curve in Figure 2-3.

As shown in the figure, a shutdown margin greater than that required by the Technical Specifications was maintained throughout the evaluation.

A minimum RWST concentration of 2300 ~pm boron is therefore specified to ensure that the proper shutdown margin is maintained.

RWST Boration Requirements - Modes 5 and 6 Four factors must be considered in determining the RWST water volume required to cool the plant from 200°F to 135°F while maintaining the reqtiired shutdown margin.

These factors are as follows:

(1)

Initial feed-and-bleed volume (2)

Coolant contraction volume (3)

An adjustment to insure conservatism (4). Roundup to next 100 gallons Therefore, the total required volume is as follows:

VolRwsT = Feed-and-Bleed + Shrinkage + Conservatism or VolRwsT = 4, 500 gal+ 2, 029. 6 gal+ 500 gal ABB Combustion Engineering Nuclear Services Page.29 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS and VolRwsT = 7, 029. 6 gallons Round upwards to nearest 100 gallons:

VolRwsT = 7, 100 gallons Volume allowance for level instrument uncertainties:

Vol inst = 8, 5 5 0 gal 1 ans Volume below lower instrument tap:

Vol 1inst = 21, 210 gallons CEN-606 REV. 00 The sum of these volumes yields a require_d volume of 36, 860 gallons.

Rounded upwards to the nearest 1000 gallons, this becomes:

VolRwsT = 37, ooo gallons

\\,

The Bases number will reflect this new requirement.

ABB Combustion Engineering Nuclear Services Page,30 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 2.3.6 Modes 5 and 6 -

Cooldown, Using BATs BAT Storage Requirements The analysis of a cooldown from 200°F to 135°F using makeup from the BATs is described in this section.

Initial conditions and assumptions used in this analysis are

• identical to those used in the analysis of cooldown using the RWST and are listed in Table 2-4.

The results are shown in Table 2-6.

The results of the calculations for system cooldown in Modes 5 and 6, from 200°F and 350 psia to 135°F and 350 psia and using boric acid from the BATs for makeup, are given in Table 2-6. These data are plotted as the actual shutdown curve in Figur~ 2-4.

As shown in the figure, a shutdown margin greater than that required by the Technical Specifications is maintained throughout the transient.

For Modes 5 and 6, a minimum BAT concentration of 6560 ppm boron (equivalent to 3.75 weight percent boric acid) is therefore prescribed in TS 3.1.2.7 (Unit 1) and TS 3.1.2.5 (Unit 2).

The minimum usable volume to be prescribed in the Technical Specifications is 2,600 gallons.

This volume was determined as follows:

(4)

Makeup volume<4>

Additional volume for conservatism Total

=

=

2,029.6 gallons 500.0 gallons

= 2,529.6 gallons Round up to nearest 100 gallons= 2,600.0 gallons Total of values in BAT*Volume column in Table 2-6 ABB Combus~ion Engineering -Nuclear Services Pag~ 31 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 2.4 BORATED WATER SOURCES - OPERATING (MODES 1, 2, 3 and 4) 2.4.1 Boration Requirements for Modes 1. 2. 3. and 4 A shutdown margin ~ 1.6% Ak/k must be maintained throughout the cooldown.. From this basis, the required RCS boron concentrations were determined using conservative core

, physics data provided by Salem (Reference 4.3) and the 2.4.2 limiting cooldown scenario outlined in Section 2_.2.1.1 above.

These data are given in Table 2-7 and ~~e* plotted as the Required Shutdown curve in Figure 2-5.

The results of the analysis are shown in Table 2-9 and are plotted as the Actual Shutdown curve in Figure 2-5.

Assumptions Used in the Modes 1. 2. 3 and 4 Analysis A complete list of assumptions and initial conditions used in calculating the minimum BAT inventory required for Modes 1, 2, 3 and 4 is contained in Table 2-8.

As stated in Section 2.2.4, all fluid added to the RCS via the loop charging nozzles is assumed to mix completely and instantaneously with the RCS and the PZR.

In line with this assumption, the mass of water in the PZR was added to and treated as part of the total mass of water in the RCS, and this total was then used in calculating system boron concentration.

Boron concentration in terms of weight fraction is defined as follows:

Boron Concen tr a ti on = Mass of Boron in System*

Total System Mass ABB Combustion Engineering Nuclear Services Page,32 of 133

.~

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 where, if complete mixing is assumed between the RCS and the PZR, the total system mass is the sum of the mass of boron in the system, the mass of water in the RCS, and the mass of water in the PZR.

For the EOL case analyzed, the initial total system mass of 527,311.7 'lbm in Tables 2-9 through 2-33 was calculated as follows:

Total Mass = Initial Boron Mass + Initial RCS Water Mass

+ Initial PZR Water Mass or (S)

• (6) 0 +

10,812 ft 3

+

500.0 ft 3

0. 021251 ft 3 I lb~S)

o. 02697 s ft 3 I lb~

6

= 527 1 311

• 7 lbm Specific volume of compressed water at 547°F and 2250 psia Specific volume of saturated water at 2250 psia ABB Combustion Engineering Nuclear Services Pag~ 33 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 2.4.3 Modes 1. 2. 3, and 4 Analysis Results-Eguilibrium Xenon Scenario As previously stated, the boration capacity required to reduce the average coolant temperature to or below 200°F is determined by the requirement for providing a shutdown margin of at least 1.6%.6.k/k, after xenon decay and a plant cooldown to greater than 200°F from normal operating conditions.

Assuming the initial conditions outlined in Table 2-8, a plant cooldown to an RCS average temperature of 200°F is conducted, starting f.rom an initial RCS average temperature of 547°F.

Charging to, the RCS is performed only as necessary to compensate for coolant contraction.

Initially, the charging

'pumps will take suction from the BAT; when the BAT has been*

drained, the charging pump suction is aligned to the RWST for the duration of the cooldown.

The calculated RCS boron concentration versus temperature for plant cooldown and depressurization from 547°F and 2250 psia to 200°F and 350 psia, with a boric acid concentration of 3.75 weight percent in the BAT and a boron concentration in the RWST of 2300 ppm,* is given in Table 2-9.

The required concentration as a function of temperature is given in Table 2-7 and is plotted on Figure 2-5 as the Required Concentration curve.

For the EOL case analyzed, the results of these calculations are plotted as the actual concentration curve in Figure 2-5.

The exact temperature at which the charging pump suction was transferred f:r:om the BAT~ to t:he RWST was determined using ABB Combustion Engineering Nuclear Services Page,34 of 1 33

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 an iterative calculation; in this way, the smallest BAT volume necessary to maintain the required shutdown margin was deterrnined for the given set of tank concentrations.

At all times, the RCS boron concentration is greater than that necessary for the required shutdown margin during the cooldown.

Note in Table 2-7 that the required shutdown margin drops from 1.6% dk./k to 1.0% Llk/k at an average coolant temperature of 200°F.

Following xenon decay, with the coolant at* 200°F, the final concentration required in the RCS is 893.9 ppm boron.

Using the scenario outlined above,

• the final system concentration will always be greater than this amount.

A detailed parametric analysis was performed for the Modes 1, 2, 3, and 4 Technical Specification (Specification 3.1.2.8 (Unit 1) and 3.1.2.6 (Unit 2)).

In this study, BAT concentration was varied from 6560 ppm boron (3.75 weight percent boric acid) to 6990 ppm boron (4.0 weight percent boric acid) and RWST concentration was varied from 2300 ppm boron to 2500 ppm boron.

The results are shown in Tables 2-9 through 2-33 for the EOL case analyzed.

The following equations were used to obtain the values in these tables:

Shrinkage Mass

=

(10 812) (__!_ - --1:..)

vf vi ABB Combustion Engineering Nuclear Services Page,35 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS BAT Vol.

=

RWST Vol =

Shrinkage Mass (8.3290 lbm/gal) <7 >

Shrinkage Mass (8.3290 lbm/gal)

CEN-606 REV. 00 Boric Acid Added = (BAT Vol) x (Mass of Boric Acid/gal) <0 >

or Boric Acid Added = (RWST Vol') x (Mass of Boric Acid/gal)

Total Boric Acid = (Initial Boric Acid) + (Boric Acid Added)

Prior to RHRS alignment, Total System Mass =

(RCS Water Mass) + (PZR Water Mass) 191

+ (Total boric acid)

Final Concentration = (Total Boric Acid) (100) (1748. 34)

(Total System Mass)

(T)

(8)

(9)

Density of Water at 70°F See Appendix 2 3

PZR Water Mass = (500. 0 *ft )

-;- v, at applicable Psat ABB Combustion Engineering Nuclear Services Page,36 o( 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 The value of the total system mass at any temperature and pressure in Tables 2-9 through 2-33 may be obtained as follows:

RCS Water Mass + PZR Water Mass + Total Boric Acid Mass + RHRS water Mass (when on RHRS)

For example, the Total System Mass at 200°F and 350 psia in Table 2-9 is as follows:

10, 812 ft 3

+

500.0 ft 3

+

1,700 ft 3

0. 01662 ft 3 I lb~lO)

o. 01662 ft 3 I lbm

+ 4 I 15 6

• 8 lbm or Mtot = 783,135.4 lbm For the EOL case analyzed, the calculated concentration values given in Tables 2-9 through 2-33 were compared to the values in Table 2-7, which shows the concentrations which must be maintained at.all temperatures during cooldown through the range from 547°F to 200°F.

In each case, the actual system boron concentration was greater than that.

necessary for the required shutdown margin.

(10)

(11) vr of compressed water @ 200°F and 350 psia vr of sa:turated water @

• 350 ps ia ABB Combustion Engineering Nuclear Services Page: 37 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 2.4.4 To set the minimum Technical Specification BAT volume corresponding to the various BAT and RWST concentrations, the makeup volumes from Table 2-9 through 2-33 were combined into Table 2-34.

To establish the required volumes which must be stored in the BATS, the higher boration volumes were adjusted by adding 100 gallons for conservatism and rounding the result upwards to the nearest 50 gallons.

These results are given in Table 2-35 ~nd are illustrated in Figure 2-6, which shows the boration volumes, and in Figure 2-7, which shows the required volume which must be available*

in the BAT.

Modes 1. 2. 3, and 4 Analysis Results -

Peak Xenon Scenario The initial conditions are identical to those for the equilibrium xenon analysis in Section 2.3.3 and are given in Table 2-8.

The plant is held at the hot, zero power temperature of 547°F.

The required boron concentration data as a*function of temperature for the peak.xenon scenario were provided in Reference 4.3.

These data points were adjusted upwards by 140 ppm to describe a conservative late-in-life scenar_io.

The data are shown in Table 2-36 and are plotted as the Required Concentration curve in Figure 2-8.

For the cooldown from 547°F to 200°F in the peak xenon scenario, charging to the RCS is performed only as necessary to compensate for coolant contraction..Initially, the.

charging pumps will take suction from the BAT; an iterative calculation is then perf ~rmed to determine the temperature at which the charging pump suction is t_o be realigned to the RWST, to avoid overborat~ng the RCS during cooldown.

ABB Combustion Engineering Nuclear Services

• Page,38 of 1 33

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 In this way, the smallest BAT volume required to maintain the required shutdown margin throughout the cooldown is established.

The analysis has been performed using near EOL conditions, with an initial RCS boron concentration of zero (0) ppm.

Note in Table 2-36 that the required shutdown margin decreases from 1.6% Ak/k to 1.0% Ak/k at a coolant temperature of 200°F.

Following xenon decay, with the coolant temperature at 200°F, the final boron concentration required in the RCS is 1033.9 ppm.

The results are plotted as the Actual Concentration curve in Figure 2-8.

At all times, the RCS boron concentration is greater than that necessary for the required shutdown margin during the cooldown.

The equations-used in calculating the values in Table 2-37 were identical to those described in Section 2.4.3.

As in Section 2.4.3, the total system mass at any temperature and pressure in Table 2-37 may be obtained as follows:

Mtot = RCS Water Mass + PZR Water Mass *

+ Total Boric Acid Mass

+ RHRS Water Mass (when on RHRS)

For example, the Total System Mass at 200°F and 350 psia, with boron concentration at 1041.4 ppm, in Table 2-37 is as follows:

ABB Combustion Engineering Nuclear Services Page ;39 of 1 33

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 2.4.5 10,812 ft 3

+

500.0 ft 3

+

1700 ft 3

o. 01662 ft 3 I lbm 0.01912 ft 3 /1b~ll)

o. 01662 ft 3 I lb m

+ 4 I 6 6 7

• 9 lbffl or Mtot =- 783,646.4 lbm The activities involved in bringing the plant to the conditions described by the peak xenon scenario are considered to be unrealistic.

Nevertheless the results of the analysis are provided as guidance to the operating staff.

Should a situation arise at or near EOL where it may be deemed desirable to maintain hot, zero power conditions for a sustained period, i.e., several hours, before

shutdown, it would be necessary to have a usable BAT inventory of approximately 10,000 gallons of 3.75 wt% boric acid available in the BATs.

Simplification Used Following RHRS Initiation The results of the analysis of cooldown and depressurization are given in Tables 2-9 through 2-33 and in Table 2-37. In the cooldown procedure for Salem Units 1 and 2, the RHRS must be aligned to the RCS at a.temperature of 350°F and a pressure below 375 psig.

In this analysis, the RHRS is conservatively assumed to be aligned at an RCS temperature and pressure of 350°F and 350 psia.

Following this alignment, the volume and mas:-; of the system that the ABB Combustion Engineering Nuclear Services Page 40 of 1 33

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 operator must consider during the subsequent cooldown will be increased by the volume and mass of fluid present in the RHRS.

In addition, the total mass of boron in the system will also be increased by the amount of boron in the RHRS prior to alignment.

For this analysis, a value of 1700 ft3 was used for the RHRS volume.

In the tables in Section 2.4.3 and 2.4.4, this RHRS volume is added when the system reaches 350°F and 350 psia.

The boron concentration in the RHRS is assumed to be equal to that in the RCS at the time the RHRS is brought into service.

ABB Combustion Engineering Nuclear Services Page 41 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS 2.5 BORATION SYSTEMS -

BASES CEN-606 REV. 00 The BASES section of the Technical Specifications was developed to demonstrate the capability of the boration system to maintain adequate shutdown margin from all

• operating conditions.

The following change to Bases Section 3/4.1.2 of the plant Technical Specifications is proposed:

"With the* RCS temperature above 200°F, a minim.um of two boron injection flow paths are required to ensu~e single functional capability in the event an assumed failure renders one of the flow paths inoperable.

The boration capability of either flow path is sufficient to provide a SHUTDOWN MARGIN from expected operating conditions of 1.6%

llk/k after xenon decay and cooldown to 200°F.

The maximum expected boration capability (minimum boration volume) requirement is established to conservatively bound expected operating conditions throughout core operating life~

The analysis assumes that the most reactive:* control rod is not inserted into the core.

The _maximum expected capability occurs at EOL from full power equilibrium xenon conditions and requires boric acid solution from the BATs in the allowable concentrations and volumes of Technical Specification Figures 3.1.2.8 (Unit 1) and 3.1.2.6 (Unit 2),

plus approximately 41,800 gallons of 2300 ppm borated water from the RWST.

With the refueling water storage tank as the only borated water source, a maximum of 73,800 gallons of 2300 ppm borated water is required. However, to be consistent with the ECCS requirements, the RWST is required to have a minimum contained volume of 350,000 gallons for operation in Modes 1, 2, 3, and 4."

ABB Combustion Engineering Nuclear Services Page. 42 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 2.5.1 Note that the bases were derived for a cooldown-with-letdown scenario in which we calculate RWST volume alone or the RWST volume required with the smallest BAT volume being used prior to using the RWST.

This is a cooldown beyond the.

requirements of BTP 5-1.

Derivation of the 73,800 Gallon Volume CRWST)

The required RWST volume of 73,800 gallons was determined as follows:

A.

Calculations were performed for a plant cooldown from 547°F and 2250 psia to approximately 350°F and 350 psia, compensating for coolant contraction* by charging of 70°F borated water from the RWST, at a concentration of 2300 ppm boron.

The boron concentration in the RCS is initially at o ppm.

B.

The RHRS is aligned to the RCS when the RCS reacnes a temperature and pressure of 350°F and 350 psia.

The RHRS volume has been determined to be 1700 ft3

, and, at the time of shutdown cooling initiation, the concentration in the RHRS is assumed to be equal to the concentration in the RCS.

Typically, the RHRS will be at normal refueling concentration (~ 2300 ppm), but the lower value was chosen for added conservatism.

c.

Cooldown of the system is continued from 350°F and 350 psia to 200°F and 350 psia, using borated water from the RWST (2300 ppm and 70°F) as necessary to makeup for contraction.

D.

Using the methodology described in Appendix 1, a feed-ABB Combustion Engineering Nuclear Services Page,43 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 2.5.2 and-bleed calculation is performed until the boron concentration in the RCS reaches a value not less than 920.8 ppm to ensure that an adequate shutdown margin is maintained during cooldown to 200°F.

E.

The volumes calculated in paragraphs A through D are summed, and the total is then rounded up to the nearest 1000 gallons.

F.

RWST volume adjustments of_ 21, 210 gallons that is Undetectable due to lower instrument tap location and of 8,550 gallons for instrumentation error are added to the total from E. above and rounded up to the nearest 100 gallons, giving a total of 73,800 gallons for cooldown using water from the RWST alone.

This value is contained in Table 2-38 and in the Bases section 3 / 4. 1. 2.

Derivation of the 41,800 Gallon RWST Volume Required when the smallest BAT Volume is Used The RWST volume used after the BAT is used per Technical Specification 3.1.2.8'(Unit 1) and 3.1.2.6 (Unit 2) consists of the following parts:

A.

Calculations were performed for a plant cooldown from 547°F and 2250 psia to approximately 350°F and 350 psia, compensating for coolant contraction by charging 6,911.3 gallons from the BAT and then with 70°F borated water (2300 ppm) from the RWST.

The concentration in the RCS is initially at o ppm.

Using a O ppm start*

will maximize the required RWST volume makeup.

ABB Combustion Engineering Nuclear Services Page_ 44 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 B.

The RHRS is aligned to the RCS when the RCS reaches a temperature and-pressure of 350°F and 350 psia.

As determined in Reference 4.6, the RHRS volume is 1700 ft 3, and, at the time of initiation, the concentration in the RHRS is assumed to be equal to the concentration in the RCS.

Normally, the RHRS will be at refueling concentration (~2300 ppm), but the lower value was chosen for conservatism.

c.

Cooldown of the system is continued from 350°F and 350 psia to 200°F and 350 psia, using borated water from the RWST (2300 ppm and 70°F) as necessary to makeup for contraction.

D.

RWST volume adjustments of 21,200 gallons (undetectable due to lower instrument tap location) and of 8,550 gallons (for instrumentation error) are added to the total from c. above and rounded up to the nearest 100 gallons, giving a minimum of 41,800 from the RWST gallons when the smallest BAT volume is u,sed.

The plant cooldown using water from the BAT and then the RWST as discussed above results in a minimum required RWST water volume of 41,800 gallons.

This value is derived in Table 2-39 and is incorporated into Technical Specification Bases Section 3/4.1.2.

2.6 ACTION STATEMENTS ON FLOW REQUIREMENTS The current Salem Units 1 and 2 Technical Specifications contain action statements which require boration from the BATs.

Since the concentration of boron in the BATs will be reduced, an increase in the minimum flow rate is required.

ABB Combustion Engineering Nuclear Services Page,45 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 The increased flow rate is applicable to Technical Specifications 3.1.1.1, 3.1.1.2, 3.9.1, and 3.10.1, as well as in Surveillance Requirement 4.1.2.2 (Unit 2 only in current Technical Specifications).

The current Action Statement is as follows:

"Immediately initiate and continue boration at ~ 10 gpm of 20,000 ppm boric acid solution or equivalent."

This boration capability uses the current minimum boric acid concentration in the BAT.

The specified flow rate is limited by the current indicating range of the flow measurement instrumentation in the boric acid line to the blending tee, which provides an alternate flow path for emergency boration.

To determine the new requirements, the amount of boron added to the system under the existing requirements must be evaluated.

Using the methods and equations in Appendix 2, the mass of boric acid per gallon of solution is as follows:

where:

and:

Therefore:

CxMw Mba = 100 -

C c = Concentration in weight percent boric acid My= 8.13985 lbm/gallon at 165°F (Reference 4.8)

(

2o,ooo) 8.13985

=

1748.34 lOO _ ( 20 I 000 )

1748.34 ABB Combustion Engineering Nuclear Services Page, 46 of 1 33

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS and Mba = 1. 05143lbm/ gallon CEN-606 REV. 00 At a flow rate of 10 gpm, 10.1543 pounds of boric acid are added to the system per minute.

At the new minimum boric acid concentration of 6,560 ppm of boron (3.75 wt% boric acid), one gallon of solu~ion contains 0.32451 pounds of boric acid.

The new flow r~quirement is determined by dividing the current minimum boric acid injection rate by the new minimum concentration,c as follows:

Flow Ratecgpml = 10.5143 lb/minute

o. 32451 lb/ gal or Flow Rategpm = 32. 4 gpm which is rounded upwards to Flow Rategpm = 33 gpm Therefore, the new Technical Specification action statements should read as follows:

"Initiate and continue boration at greater than or equal to 33 gpm of a solution containing greater than or equal to 6560 ppm boron or its equivalent."

ABB Combustion Engineering Nuclear Services Page 47 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS Table 2-1 Boric Acid Solubility in Water111 Temperature H3BO (oF)

(wt.%)

32.0 2.52

41. 0 2.98 50.0 3.49 59.0 4.08 68.0 4.72 77.0 5.46 86.0 6.23 95.0 7.12 104.0 8.08 113.0 9.12 122.0 10.27 131. 0 11.55 140.0 12.97 149.0 14.42 158.0 15.75 167.0 17.41 176.0 19.10 (I)

Reference 4.2 ABB Combustion Engineering Nuclear Services CEN-606 REV. 00 Page,48 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS Table 2-2 Time Intervals for Determining an Effective RCS Cooldown Rate Initial,¥ct Period c Standby hold 4.00 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> Plant Cooldown from 547°F to 200°F CZ>

17.35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br /> Additional Conservatism 13.35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br /> Total 34.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> 4-hours per requirements of BTP RSB 5-1 CEN-606 REV. 00 (I)

(2)

An average cooldown rate of 20°F/hr is assumed for this analysis.

Integrated Operating Procedure IOP-6, "Hot Standby to Cold Shutdown", specifies a cooldown rate less than 100°F/hr with an administrative limit of soL*!:r.

ABB Combustion Engineering Nuclear Services Page, 49 of 133

BORIC ACID-CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS Table 2-3 CEN-606 REV. 00 Required Boron Concentration for a Plant Cooldown (I)

(2)

Modes 5 and 6 Temperature (OF) 200111 200121 190 180 170 160 150 140 135 Shutdown Margin 1.6 Ak/k Shutdown Margin 1.0 Ak/k Concentration (ppm Boron)

Equilibrium Xenon EOL 920.8 893.9 906.5 920.2 933.9 945.6 958.9 970.8 977.2 ABB Combustion Engineering Nuclear Services Page,50 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS Table 2-4 CEN-606 REV. 00 Initial Conditions and Assumptions Used in the Modes 5 and 6 Calculation

a.

Reactor Coolant System Volume 10,812 ft3

b.

Reactor Coolant System Pressure 350 psia111

c.

Pressurizer Volume(@ 0% Power Level) 500.0 ft3

d.

Pressurizer is at S~turation

e.

Reactor Coolant System Leakage 0

f.

Boration Source Concentration Refueling Water Storage Tank (RWST) 2300 ppm boron Boric Acid Storage Tank (BAT)

3. 75 wt% BoricAcid

g.

Boration Source Temperature 70°F

h.

• Initial RCS Concentration (EOL) 893.9 ppm boron

j.

Complete and Instantaneous *Mixing Between Pressurizer and RCS

k.

Constant PZR Level Maintained, Charging to Compensate for Coolant Contraction I.

RHRS Volume 1700 ft3 m.

Total System Volume (RCS+RHRS+PZR) 13,012.0 ft3 (I)

RHRS entry pressure is* assumed to be 350 psia for conservatism ABB Combustion Engineering Nuclear Services Page 51 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS

• Plant Cooldown from

. 200 °F to 135 °F TABLE 2-5 Salem Nuclear Generating Station Feed & Bleed Usina the RWST 23Xl com Boric Acid AVG. SYS. TEMP.

PZR PFESS SPECIFIC SHRIN<AGE RWST B/A TOTAL B/A VOLUME MASS Ti Tf (cu.ft./lbm)

(cu.ft./lbm)

("F)

("F)

(psi a)

Vi Vf (lbm)

• 200 200 350 0.01662 200 200 100 100 170 160 150 Feed and Bleed from RWST 200 350 0.01662 100 350 0.01662 100 350 0.01655 170 350 0.01649 160 350 0.01643 150 350 0.01638 135 350 0.01632 Shrinkage Volume =

Feed-and-Bleed Volume=

RvVST Total Volume =

0.01662 0.0 60 Minutes at 0.01662 0.0 0.01655 3,184.2 0.01649 2,750.8 0.01643 2,770.9 0.01638 2,324.6 0.01632 2,800.3 0.01626 3,065.7 2029.6 Gallons 4500.0 Gallons 6529.6 Gallons ABB Combustion Enaineerina Nuclear Services VOLUfvE ADDED (gaO (lbrn)

(lbrn) 0.0 0.0 4,003.3 75 GPM

• 0.0 0.0 4,300.7 382.3 42.4 4,343.2

lll.3 36.7 4,379.8 332.7 36.9 4,416.8 279.1 31.0 4,447.8 337.2 37.4 4,485.2 368.1 40.9 4,525.1 75 GPM for.

CEN-606 70 °F TOTAL FINAL CONC.

SYS.MASS Obrn)

(ppm boron) 60 Minutes BACR Version 2 Paue 52 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 TABLE 2-6 Salem Nuclear Generating Station Plant Cooldown - Modes 4 & 5 BAT 3.75 wt. % Boric Acid 70 'f 200'fto135 'f AVERAGE SYSTEM PZR SPECIFIC SHRINKAGE BAT B/A TOTALB/~

TOTAL FINALCONC.

TEMPERATURE PRESS.

VOLUME MASS VOLUME ADDED SYS.MASS Ti Tf Vi Vf

(°F)

(°F)

(psia)

(cu.ft./lbm)

(cu.ft./lbm)

(lbm)

(gaQ (lbm)

(lbm)

(lbm) loom boron) 200 200 350 0.01662 0.01662 0.0 0.0 0.0 4,003.3 782,981.8

<]:!~3.9 200 190 350 0.01662 0.01655 3,184.2 382.3 124.1 4,127.3 786,290.0

.* i9;f7.7 190 180 350 0.01655 0.01649 2,750.8 330.3 107.2 4,2.34.5 789,148.0 938,1 180 170 350 0.01649 0.01643 2,no.9 332.7 108.0 4,342.5 792,026.9

.* 958;6 170 160 350 0.01643 0.01638 2,324.6 279.1 90.6 4,433.0 794,442.0

.* \\.975.6 160 150 350 0.01638 0.01632 2,808.3 337.2 109.4 4,542.4 797,359.7 :

*****.*.1:\\~1-11;~

150 135 350 0.01632 0.01626 3,065.7 368.1 119.4 4,661.9 800,544.9 TOTAL BAT VOLUME=

2,029.6 GALLONS BACR Ve111ion 2 ABB Combustion Engineerina Nuclear SeNices Paae 53 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS Table 2-7 Required Boron Concentration for a Cooldown From 54 7°F to 200°F Equilibrium Xenon Scenario Temperature EOL OF Concentration (ppm boron) 547

-79.0 637

-16.4 527 42.3 617 96.0 607 148.6 497 191.8 487 237.8 477 281.9 467 315.2 457 353.6 447 385.0 437 418.9 427 451.7 417 478.6 407 508.0 397 533.4 387 560.1 377 586.1 367 608.4 357 632.3 347 653.5 337 675.6 327 697.3 317 716.4 307 736.7 297 755.0 287 774.1 277 792.8 267 811.4 257 829.6 247 843.9 237 861.1 227 878.2 217 892.9 207 909.0 200 920.8 200 111 893.9 CEN-606 REV. 00 (I)

After Shutdown Margin Change from l.6%~k/k to 1.0% ~k/k ABB Combustion Engineering Nuclear Services Pag~ 54 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 Table 2-8 Initial Conditions and Assumptions Used in the Modes 1, 2, 3, and 4 Calculation

a.

Reactor Coolant system Volume 10,812 ft3

b.

Reactor Coolant System Pressure 2250 psia

c.

Pressurizer Volume (@ 0% Power Level)

*soo.o ft3

d.

Pressurizer is at Saturation

e.

Reactor Coolant system Leakage 0

f.

RCS Depresurization Performed as Shown in Tables 2-9 through 2-33

g.

Initial RCS and PZR Concentration -

EOL 0 ppm boron

i.

Complete and Instantaneous Mixing Between Pressurizer and RCS

j.

Constant PZR Level Maintained,Charging to Compensate for Coolant Contraction

k.

Boron Concentration in RCS equal to Concentration in RHRS at Time of Residual Heat Removal Initiation

1.

Boration Source Temperature Refueling Water Storage Tank (RWST) 70°F Boric Acid Tank (BAT) 70°F

m.

RHRS Volume 1,700 ft3 n.

Total System Volume (RCS+PZR+RHRS) 13,012 ft3 ABB Combustion Engineering Nuclear Services Page 55 of 133

.~

ORIC ACID CONCENTRATION REDUCTION RT TECHNICAL BASES AND OPERATIONAL ANALYSIS Plant Cooldown from 547 "F to 200 "F AVERAGE SYSTEM PZR TEMPERATURE PRESS.

Ti Tf

("F)

("F)

( sia 547 547 2250 547 535 2250 535 520 2250 520 510

. 2250 510 500 2250 500 490 2250 490 480 2250 480 470 2250 470 460 2250 460 450 2250 450 432 2250 432 420 2250 420 410 2250 410 400 2250 400 380 2250 380 370 2250 370 360 2250 360 350 2250 350 350 350 350 350 350 SPECIFIC VOLUME Vi Vf (cu.ft./lbm cu.ft./lbm 0.02125 0.02125 0.02125 0.02092 0.02092 0.02055 0.02055 0.02031 0.02031 0.02009 0.02009.

0.01989 0.01989 0.01969 0.01969 0.01951 0.01951 0.01933 0.01933 0.01916 0.01916 0.01887 0.01887 0.01869 0.01869 0.01855 0.01855 0.01842 0.01842 0.01816 0.01816 0.01804 0.01804 0.01792 0.01792 0.01781 0.02698 0.01912 0.01781 0.01797 TABLE 2-9 Salem Nuclear Generating Station BM a~ ~%~~k~

RWST 2300 Boric Acid SHRINKAGE BAT RWST B/A MASS VOLUME VOLUME ADDED (lbm ga lbm 0.0 0.0 0.0 7,988.2 959.1 0.0 311.2 9,495.2 1,140.0 0.0 369.9 6,089.2 731.1 0.0 237.2 5,829.6 699.9 0.0 227.1 5,411.5 649.7 0.0 210.8 5,521.5 662.9 0.0 215.1 5,208.2 625.3 0.0 202.9 5,163.1 619.9 0.0 201.2 4,965.4 596.2 0.0 193.5 8,494.7 1,019.9 0.0 331.0 5,548.6 0.0 666.2 74.0 4,523.1 0.0 543.1 60.3 4,115.8 0.0 494.1 54.9 8,408.4 0.0 1,009.5 112.1 3,962.6 0.0 475.8 52.8 4,015.6 0.0 482.1 53.5 3,728.5 0.0 447.7 49.7 7,614.9 0.0 914.3 0.0 (5,575.7) o:o (669.4) 0.0 Add in RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC,)

350 350 350 0.01797 0.01797 0.0 0.0 0.0 0.0 350 300 350 0.01797 0.01743 21,571.2 0.0 2,589.9 287.6 300 260 350 0.01743 0.01707 15,139.0 0.0 1,817.6 201.8 260 230 350 0.01707 0.01683 10,452.5 0.0 1,254.9 139.3 230 200 350 0.01683 0.01662 9,393.6 0.0 1,127.8 125.2 I TOTAL BAT VOLUME= 7,704.0 GALLONS I 70 "F 70 "F CEN-REV. 00 TOTAL TOTAL FINAL B/A SYS. MASS CONC.

lbm 0.0 311.2 681.2 918.4 1,145.5 1,3.56.4 1,571.5 1,774.4 1,975.6 2,169.0 2,500.0 2,574.0 2,634.3 2,689.1 2,801.2 2,854.0 2,907.6 2,957.3 2,957.3 2,957.3 3,402.9 3,690.4 3,892.3 4,031.6 4,156.8 l>m)

(p m boron)

i:~ ~Jii*

551,802. 7 :

::::,'i,:.: **::::1~:jg

~~~::~:: *:*******::* ::i:: :\\!:\\***:111)11~1 E:::: :

1 ll!~~JI 585,152.6 **

':9~M*

593,978.3.

73Sl9 599,600.8..

75ois 604,184.2 *.

7~2~~

608,3.54.9 772'.8 616,875.3 793.9 620,890.7.

624,959.8 628, 738.1.*.

636,353.0.

630,m.3 ***

725,825.1 747,683.9.

763,024.7 773,616.6 783,135.4 i863'.0.

.. *. <a§Ha

. < > ;; *t~jj~

BACR Version 2 Pa e 56of133

ORIC ACID CONCENTRATION REDUCTION RT TECHNICAL BASES AND OPERATIONAL ANALYSIS TABLE 2-10 Salem Nuclear Generating Station Plant Cooldown from 547 °F to 2aa °F BAT 3.8125 wt.% Boric Acid RWST 230a AVERAGE SYSTEM PZR TEMPERATURE PRESS.

SPECIFIC VOLUME SHRINKAGE BAT MASS VOLUME Ti Tf

(°F)

(°F) 547 547 547 535 535 520 52a 510 51a 5ao 50a 490 49a 480 480 470 470 460 460 450 450 436 436 425 425 410 410 4ao 4aa 385 385 370 370 360 360 350 350 350 350 350 Add in RHRS 35a 350 35a 3ao 300 260 260 23a 23a 200

( sia 2250 2250 2250

. 2250 2250 2250 2250 225a 2250 2250 225a Vi cu.ft./lbm 0.02125 0.02125 0.02092 0.02055 0.02031 o.02oa9 o.a1989 0.01969 0.01951 0.01933 a.01916 Vf (cu.ft./lbm 0.02125 0.02092 0.02055 0.02031 0.02009 0.01989 0.01969 0.01951 0.01933 0.01916 o.a1893 (lbm) 0.0 7,988.2 9,495.2 6,089.2 5,829.6 5,411.5 5,521.5 5,208.2 5,163.1 4,965.4 6,618.5 959.1 1,140.0 731.1

'699.9 649.7 662.9 625.3 619.9 596.2 794.6 0.01877 5,112.7 2250 0.01893 0.0 2250 0.01877 0.01055 6,835.2 a.a 2250 a.01855 0.01842 4,115.8 a.o 2250 0.01842 o.a1822 6,446.7 0.0 2250 0.01822 0.01804 5,924.2 a.o 225a o.a10a4 0.01792 4,015.6 0.0 2250 0.01792 0.01781 3,728.5 a.o 35a 0.02698 0.01912 7,614.9 0.0 35a 0.01781 0.01797 (5,575.7) 0.0.

VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

350 i 0.01797 0.01797 a.o a.o 350 35a 350 350 0.01797 0.01743 0.01743 0.01707 0.01707 0.01683 a.01683 0.01662 21,571.2 15,139.0 10,452.5 9,393.6 a.a 0.0 0.0 o.a I TOTAL BAT VOLUME= 7,478.7 GALLONS I ABB Combustion En Nuclear Services Boric Acid RWST B/A VOLUME ADDED lbm 0.0 0.0 316.6 0.0 376.4 0.0 241.4 0.0 231.1 0.0 214.5 0.0 218.8 0.0 206.4 0.0 204.6 0.0 196.8 0.0 262.3 613.8 682 820.7 91.1 494.1 54.9 774.0 85.9 711.3 79.0 482.1 53.5 447.7 49.7 914~3 0.0 (669.4) 0.0 0.0 0.0 2,589.9 287.6 1,817.6 201.8 1,254.9 139.3 1,127.8 125.2 70 °F 70 °F CEN-REV. 00 TOTAL TOTAL FINAL CONC..

B/A SYS. MASS lbm 0.0 316.6 693.0 934.3 1,165.4 1,379.9 1,598.7 1,805.2 2,009.8 2,206.6 2,468.9 2,537.1 2,628.2 2,683.1 2,769.0 2,848.0 2,901.5 2,951.2 2,951.2 2,951.2 3,395.9 3,683.5 3,885.3 4,024.6 4,149.9 lbm 527,311.7 535,616.6 545,488.1 551,818.6 725,818.1

• 747,676.9 763,017.8.

773,609.6

.*.******.. ::1:~

BACR Version 2 Pa e 57of133

ORIC ACID CONCENTRATION REDUCTION RT TECHNICAL BASES'AND OPERATIONAL ANALYSIS TABLE 2-11 Salem Nuclear Generating Station Plant Cooldown from 547 °F to 200 °F BAT 3.875 wt.% Boric Acid RWST 2300 Boric Acid AVERAGE SYSTEM PZR TEMPERATURE PRESS.

SPECIFIC VOLUME SHRINKAGE BAT RWST B/A MASS VOLUME VOLUME ADDED n

n Vi Vf

°F)

(°F (psia cu.ft./lbm cu.ft./lbm lbm

. (ga 547 547 2250 0.02125 0.02125 0.0 0.0 547 535 520 510 535 2250 0.02125 0.02092 0.02055 0.02031 0.02092 7,988.2 959.1 520 2250 0.02055 9,495.2 1,140.0 510

'2250 0.02031 f;),089.2 731.1 500 2250 0.02009 5,829.6 699.9 500 490 490 480 480 465

'465 450 450 440 440 420 420 410 410 400 400 385 385 370 370 360 360 350 350 350 350 350 Add in RHRS 350 350 350 300 300

'260 260 230 230 200 2250 0.02009 0.01989 5,411.5 649.7 2250 0.01989 0.01969 5,521.5 662.9 2250 0.01969 0.01942

' 7,777.8 933.8 2250 0.01942 0.01916 7,558.9 907.5 2250 0.01916 0.01900 4,754.5 570.8 2250 0.01900 0.01869 9,288.8 0.0 2250 0.01869 0.01855 4,523.1 0.0 2250 0.01855 0.01842 4,115.8 0.0 2250 0.01842 0.01822 6,446.7 0.0 2250 0.01822 0.01804 5,924.2 0.0 2250 0.01804 0.01792 4,015.6 0.0 2250 0.01792 0.01781 3,728.5 0.0 350 0.02698 0.01912 7,614.9 0.0 350 0.01781 0.01797 (5,575.7) 0.0 VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

350 0.01797 0.01797 0.0 0.0 350 350 350 350 0.01797 0.01743

' 0.01743 0.01707 0.01707 0.01683 0.01683 0.01662 21,571.2 15,139.0 10,452.5 9,393.6 0.0 0.0 0.0

. 0.0 I TOTAL BAT VOLUME = 7,254.9 GALLONS I ga lbm o~o 0.0 0.0 322.0 0.0 382.8 0.0 245.5 0.0 235.0 0.0 218.2 0.0 222.6 0.0 313.5 0.0 304.7 0.0 191.7 1, 115.2 123.8 543.1 60.3 494.1 54.9 774.0 85.9 711.3 79.0 482.1 53.5 447.7 49.7 914.3 0.0 (669.4) 0.0 0.0 0.0 2,589.9 287.6 1,817.6 201.8 1,254.9 139.3 1,127.8 125.2 70 °F 70 °F CEN-REV. 00 TOTAL TOTAL

-- FINAL CONC.

B/A SYS. M.ASS (lbm 0.0 322.0 704.8 950.3 1,185.3 1,403.4 1,626.0 1,939.5 2,244.2 2,435.9 2,559.7 2,620.0 2,674.9 2,760.8 2,839.8 2,893.3 2,943.0 2,943.0 2,943.0 3,386.5 3,674.1 3,875.9 4,015.2 4,140.4 lbm)

(p m boron 725,808.7 *..*

747,667.5.*.

763,008.4 *.

773,600.2 >'

783,119.0 BACR Version 2 Pa e 58of133

ORIC ACID CONCENTRATION REDUCTION RT TECHNICAL BASES AND OPERATIONAL ANALYSIS Plant Cooldown from 547 "F to 200 "F AVERAGE SYSTEM PZR TEMPERATURE PRESS.

Ti Tf "F

("F)

( sia 547 547 2250 547 535 2250 535 520 2250 520 510

. 2250 510 500 2250 500 490 2250 490 480 2250 480 470 2250 470 460 2250 460 450 2250 450 442 2250 442 430 2250 430 410 2250 410 400 2250 400 385 2250 385 370 2250 370 360 2250 360 350 2250 350 350 350 350 350 350 SPECIFIC VOLUME Vi Vf cu.ft./lbm (cu.ft./lbm 0.02125 0.02125 0.02125 0.02092 0.02092 0.02055 0.02055 0.02031 0.02031 0.02009 0.02009 0.01989 0.01989 0.01969 0.01969 0.01951 0.01951 0.01933 0.01933 0.01916 0.01916

. 0.01903 0.01903 0.01884 0.01884 0.01855 0.01855 0.01842 0.01842 0.01822 0.01822 0.01804 0.01804 0.01792 0.01792 0.01781 0.02698 0.01912 0.01781 0.01797 TABLE 2-12 Salem Nuclear Generating Station BAT 3.9375 wt.% Boric Acid RWST 2300 Boric Acid SHRINKAGE BAT RWST B/A M.ASS VOLUME VOLUME ADDED lbm lbm 0.0 0.0 7,988.2 959.1 0.0 327.4 9,495.2 1,140.0 0.0 389.2 6,089.2 731.1 0.0 249.6 5,829.6 699.9 0.0 238.9 5,411.5 649.7 0.0 221.8 5,521.5 662.9 0.0 226.3 5,318.2 625.3 0.0 213.5 5,163.1 619.9 0.0 211.6 4,965.4 596.2 0.0 203.5 3,797.2 455.9 0.0 155.6 5,640.2 0.0 677.2 75.2 9,128.9 0.0 1,096.0 121.7 4,115.8 0.0 494.1 54.9 6,446.7 0.0 774.0 85.9 5,924.2 0.0 711.3 79.0 4,015.6 0.0 482.1 53.5 3,728.5 0.0 447.7 49.7 7,614.9 0.0 914.3 0.0 (5,575.7) 0.0 (669.4) 0.0 Add in RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

350 350 350 0.01797 0.01797 0.0 0.0 0.0 0.0 350 300 350 0.01797 0.01743 21,571.2 0.0 2,589.9 287.6 300 260 350 0.01743 0.01707 15,139.0 0.0

.1,817.6 201.8 260 230 350 0.01707 0.01683 10,452.5 0.0 1,254.9 139.3 230 200 350 0.01683 0.01662 9,393.6 0.0 1,127.8 125.2 jTOTAL BAT VOLUME= 7, 140.0 GALLONS I 70 "F 70 "F CEN-REV. 00 TOTAL TOTAL FINAL CONC.

B/A SYS. M.ASS lbm) 0.0 327.4 716.6 966.2 1,315.2 1,427.0 1,653.3 1,866.8 2,078.4 2,281.9 2,437.6 2,512.8 2,634.5 2,689.3 2,n5.3

• 2,854.2 2,907.8 2,957.5 2,957.5 2,957.5 3,403.1 3,690.7 3,892.5 4,031.8 4,157.0 lbm m boron) 527,311.7 ff:/ /

> :((ji(j

........ >:r 535,627.4.\\}: :\\. tig 545 511 1 > r. * *;.*.*.*.*.:...*. *.:.. *.*.... *

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BACR Version 2 Pa e 59of133

ORIG ACID CONCENTRATION REDUCTION RT

. TECHNICAL BASES AND OPERATIONAL ANALYSIS TABLE 2-13 Salem Nuclear Generating Station Plant Cooldown from 54 7 "F to 200 "F BAT 4.0 wt. % Boric Acid RWST 2300 Boric Acid AVERAGE SYSTEM PZR TEMPERATURE PRESS.

SPECIFIC VOLUME SHRINKAGE BAT RWST B/A MASS VOLUME VOLUME ADDED Ti Tf Vi Vf

("F)

("F)

( sia cu.ft./lbm (cu.ft./lbm lbm (ga (ga (lbm 547 547 2250 0.02125 0.02125 0.0 0.0 0.0 0.0 547 535 2250 0.02125 0.02092 7,988.2 959.1 0.0. 332.8 535 520 2250 0.02092 0.02055 9,495.2 1, 140.0 0.0 395.6 520 510

. 2250 0.02055 0.02031 6,089.2 731.1 0.0 253.7 510 500 2250 0.02031 0.02009 5,829.6 699.9 0.0 242.9 500 490 2250 0.02009 0.01989 5,411.5 649.7 0.0 225.5 490 480 2250 0.01989 0.01969 5,521.5 662.9 0.0 230.1 480 470 2250 0.01969 0.01951 5,208.2 625.3 0.0 217.0 470 460 2250 0.01951 0.01933 5,163.1 619.9 0.0 215.1 460 450 2250 0.01933 0.01916 4,965.4 596.2 0.0 206.9 450 445 2250 0.01916 0.01908 2,367.3 284.2 0.0 98.6 445 430 2250 0.01908 0.01884 7,070.1 0.0 848.9 94.3 430 410 2250 0.01884 0.01855 9, 128.9 0.0 1,096.0 121.7 410 400 2250 0.01855 0.01842 4,115.8 0.0 494.1 54.9 400 385 2250 0.01842 0.01822 6,446.7 0.0 n4.0 85.9 385 370 2250 '

0.01822 0.01804 5,924.2 0.0 711.3 79.0 370 360 2250 0.01804 0.01792 4,015.6 0.0 482.1 53.5 360 350 2250 0.01792 0.01781 3,728.5 0.0 447.7 49.7 350 350 350 0.02698 0.01912 7,614.9 0.0 914.3 0.0 350 350 350 0.01781 0.01797 (5,575.7) 0.0 (669.4)

Q.O Add in RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

350 350 350 0.01797 0.01797 0.0 0.0 0.0 0.0 350 300 350 0.01797 0.01743.

21,571.2 0.0 2,589.9 287.6 300 260 350 0.01743 0.01707 15,139.0 0.0 1,817.6 201.8 260 230 350 0.01707 0.01683 10,452.5 0.0 1;254.9 139.3 230 200 350 0.01683 0.01662 9,393.6 0.0 1,127.8 125.2 I TOTAL BAT VOLUME = 6,968.3 GALLONS I 70 "F 70 "F CEN-REV. 00 TOTAL TOTAL FINAL CONC.

B/A SYS. MASS lbm) 0.0 332.8 728.5 982.2 1,225.1 1,450.6 1,680.6 1,897.6 2,112.8 2,319.7 2,418.3 2,512.5 2,634.2 2,689.1 2,n5.o 2,854.0 2,907.5 2,957.3 2,957.3 2,957.3 3,402.9

. 3,690.4 3,892.2 4,031.6 4,156.8 lbm (ppm boron 521,311.1 ::::>*

• • • • • :*o:o 535 632 0

>? > **

• 10.aj&

545:523:6 }1:::1:::. p.._.. *. p ?~~~

551,866.5 T /.... att2.

557,939.0 *.** r ::: m~~

E:E~ !!! l~/.*

__.*._.**6

..,56450.*_:.*

.. =*:.* :*:.:n.'!:l.:.':

... :.. :.:_.60

.. :**.:*.*.*,:*-=.* ::

..* :.*~.*_.0*1_.:,*.:_*.:*-**_

.... =*_..

• _=.

sao 131 o ?fftm ***......

~

1:::

~ lir' f i)I~ iii 594 933 6 //.. *.. *.*. 7~;4 604: 184:2.:*:.*:; *.*, s1e.2;a 608 354 8 }/:

.x.;_=.:_:;,,,.:*.=.*~~.*:.:.:0=***=.*_*

I

{\\\\:':'* :*.

l:'.t*&.

614,887.4.*

7a~[a

~ ti 1 !

1

!S \\!~II~

~., 1i~J:i.

1!f i

~::{::\\::::::;:::..... ***. ******.*.-..... *.*.*.*.*.*

630,n7.3 <* /*<<./ 819:7 725,~.1 > ****************** ki~

747,683.8.*:**-* />.>\\ aG.~:9.'

163,024.1

• a~Hdi n3,616.5 :. '... :s11.1 783, 135.3.

s~a;o:

BACR Version 2 Pa e 60of133

BORIC ACID CONCENTRATION REDUCTION ORT TECHNICAL BASES AND OPERATIONAL ANALYSIS TABLE 2-14 Salem Nuclear Generating Station Plant Cooldown from 547 "F to 200 "F BAT

3. 75 wt. % Boric Acid RWST 2350 Boric Acid AVERAGE SYSTEM PZR TEMPERATURE PRESS.

SPECIFIC VOLUME SHRINKAGE.

BAT RWST B/A MASS VOLUME VOLUME ADDED Ti Tf Vi Vf

("F

("F)

(psia cu.ft./lbm (cu.ft./lbm lbm) ga ga (lbm 547 547 2250 0.02125 0.02125 0.0 0.0 0.0 0.0 547 535 2250 0.02125 0.02092 7,988.2 959.1 0.0 311.2 535 520 2250 0.02092 0.02055 9,495.2 1, 140.0 0.0 369.9 520 510 2250 0.02055 0.02031 6,089.2 731.1 0.0 237.2 510 500 2250 0.02031 0.02009 5,829.6 699.9 0.0 227.1 500 490 2250 0.02009 0.01989 5,411.5 649.7 0.0 210.8 490 480 2250 0.01989 0.01969 5,521.5 662.9 0.0 215.1 480 470 2250 0.01969 0.01951 5,218.2 625.3 0.0 202.9 470 460 2250 0.01951 0.01933 5,163.1 619.9 0.0 201.2 460 450.

2250 0.01933 0.01916 4,965.4 596.2 0.0 193.5 450 434 2250 0.01916 0.01890 7,555.0 907.1 0.0 294.4 434 420 2250 0.01890 0.01869 6,488.2 0.0 779.0 88.4 420 410 2250 0.01869 0.01855 4,523.1 0.0 543.1 61.6 410 400 2250 0.01855 0.01842 4,115.8 0.0 494.1 56.1 400 385 2250 0.01842 0.01822 6,446. 7 0.0 774.0 87.8 385 370 2250 0.01822 0.01804 5,924.2 0.0 711.3 80.7 370 360 2250 0.01804 0.01792 4,015.6 0.0 482.1 54.7 360 350 2250 0.01792 0.01781 3,728.5 0.0 447.7 50.8 350 350 350 0.02698 0.01912 7,614.9 0.0 914.3 0.0 350 350 350 0.01781 0.01797 (5,575.7) 0.0 (669.4) 0.0 Add in RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

350 350 350 0.01797 0.01797 0.0 0.0 0.0 0.0 350

. 300 350 0.01797 0.01743 21,571.2 0.0 2,589.9 293.9 300 260 350 0.01743 0.01707 15,139.0 0.0 1,817.6 206.3 260 230 350 0.01707 0.01683 10,452.5 0.0 1,254.9 142.4 230 200 350 0.01683 0.01662 9,~3.6 0.0 1,127.8 128.0 I TOTAL BAT VOLUME= 7,591.2 GALLONS I 70 "F 70 "F CEN-REV. 00 TOTAL TOTAL FINAL CONC.

B/A SYS. MASS lbm 0.0 311.2 681.2 918.4 1,145.5 1,3!56.4 1,571.5 1,n4.4 1,975.6 2,169.0 2,463.4 2,551.8 2,613.4 2,669.5 2,757.3 2,838.0 2,892.7 2,943.5 2,943.5 2,943.5 3,387.1 3,681.0 3,887.2 4,029.6 4,157.6 lbm (p m boron) 725,009.3. >> (. :~i~.~

747,674.4 763,019.7.

773,614.6 783,136.2...

• • 91().7:

.. 928'.;i BACR Ver:sion 2 Pa e 61 of 133

ORIG ACID CONCENTRATION REDUCTION RT TECHNICAL BASES AND OPERATIONAL ANALYSIS TABLE 2-15 Salem Nuclear Generating Station Plant Cooldown from 547 "F to 20a "F BAT

. 3.8125 wt.% Boric Acid RWST 2350 AVERAGE SYSTEM PZR TEMPERATURE PRESS.

SPECIFIC VOLUME SHRINKAGE BAT MASS VOLUME Ti Tf

("F "F) 547 547 547 535 535 520 52a 510 510 saa 500 490 490 48a 480 470 47a 460 460 450 450 438 438 420 420 410 410 400 4aa 385 385 37a 370 360 360 350 350 35a 350 350 Add in RHRS 350 350 350 300 30a 260 260 230 230 200 Vi Vf

( sia) cu.ft./lbm (cu.ft./lbm 2250 0.02125 0.02125 2250 2250

. 225a 2250 2250 225a 2250 225a 2250 2250 0.02125 0.02092 0.02055 0.02031 o.02oa9 0.01989 0.01969 a.a1951 a.a1933 0.01916 o.a2092 0.02055 0.02031 0.020a9 0.01989 0.01969 0.01951 0.01933 o.a1916 0.01896 lbm ga~

a.a 0.0 7,988.2-959.1 9,495.2 1,140.0 6,089.2 731.1 5,829.6

'699.9 5,411.5 649.7 5,521.5 662.9.

5,208.2 625.3 5,163.1 619.9 4,965.4 596.2 5,685.0 682.5 2250 0.01896 0.01869 8,358.3 0.0 2250 0.01869 0.01855 4,523.1 0.0 2250 0.01855 0.01842 4,115.8 0.0 225a a.01842 0.01822 6,446. 7 0.0 2250 0.01822 0.01804 5,924.2 0.0 2250 0.01804 0.01792 4,015.6 0.0 2250 0.01792 0.01781 3,728.5 0.0 350 0.02698 o.a1912 7,614.9 o.a 350 0.01781 0.01797 (5,575.7) 0.0 VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

350 0.01797 0.01797 a.a o.a 350 o.a1797 0.01743 21,571.2 0.0 350 o.a1743 0.01707 15,139.0 0.0 350 0.01707 o.a1683 10,452.5 0.0 350 0.01683 0.01662 9,393.6 0.0

!TOTAL BAT VOLUME= 7,366.6 GALLONS I ABB Combustion En Boric Acid RWST B/A VOLUME ADDED ga (lbm 0.0 0.0 0.0 316.6 0.0 376.4 0.0 241.4 0.0 231.1 0.0 214.5 0.0 218.8 0.0 206.4 0.0 204.6 a.o 196.8 0.0 225.3

- 1,003.5 113.9 543.1 61.6 494.1 56.1 774.0 87.8 711.3 80.7 482.1 54.7 447.7 50.8 914.3 0.0 (669.4) 0.0 a.a 0.0 2,589.9 293.9 1,817.6 206.3 1,254.9 142.4 1,127.8 128.0 70 "F 70 "F

• CEN-REV. 00 TOTAL TOTAL FINAL CONC.

B/A SYS. MASS (lbm 0.0 316.6 693.0 934.3 1,165.4 1,379.9 1,598.7 1,805.2 2,009.8 2,206.6 2,431.9 2,545.8 2,607.4 2,663.5 2,751.3 2,832.1 2,886.8 2,937.6 2,937.6 2,937.6 3,380.2 3,674.1 3,880.4 4,022.8 4,150.8 521,311.1 ::::'. t? }\\ :,: : :::::::::;9.lP 535,616.6 !*)* '}/,;,:,=:!::::19~;~

E:Eiiill 569 245 s *:.:-;.:

}\\/:{~f:(::: ::-491r*o 574:660:2 :.:.-_.::=.:=_

l$4~l~

580,028.0 ;,:,}:;::::::!'.

ii: 1*::~0$.i~

585,190.2 :..,*.:*: *******\\':i§.$Q($

591,100.5 ; <

<' 1'19;3.

599,572. 7

.. 742~4 604,157.4.

754.6 000,329.3

• 1ss.5 614,863.8 **

782.3 620,868.7 1Q7.5 624,939.1.*

807.6 628,718.4 816.9 636,333.4.*.

.*:.. *.. : <~9[:;1 630,757.7 :_

. '814'.2 725,802.4

.*.. 814.2 747,667.5 *::

. : ***** *8~9.~

763,012.8

• aa!:L+

n3,607.8 :... *.: >. : 9da}t 783,129.3

• <. *s~a)i*

BACR Velliion 2 Pa e 62of133

BORIC ACID CONCENTRATION REDUCTION ORT TECHNICAL BASES AND OPERATIONAL ANALYSIS Plant Cooldown from 547 °F to 200 °F AVERAGE SYSTEM PZR TEMPERATURE PRESS.

Ti Tf SPECIFIC VOLUME Vi Vf TABLE 2-16 Salem Nuclear Generating Station BAT 3.875 wt. % Boric Acid RWST 2350 Boric Acid SHRINKAGE BAT RWST B/A MASS VOLUME VOLUME ADDED 70 "F 70 "F TOTAL TOTAL B/A SYS. MASS CEN-REV. 00 FINAL CONC.

(°F)

(°F) cu.ft./lbm) lbm (ga (ga lbm lbm t---_.__.---t_..___.._-+--'(,_Ps_ia_.__~c_u_.ft_./_lb_m_.__+-'-_;.___.__t---__,___.__-+--___,=---<'----+----=='--L...--+_.__--L--+--->---'----'1---->-lb_m_,_)-----1 (p m boron 2250 0.02125 527,311.7 *. ********

o.o:

547 547 0.02125 0.0 0.0 0.0 0.0 0.0 547 535 0.02092 7,988.2 959.1 0.0 322.0 322.0 2250 0.02125 535,622.0 *****.

• 1Ci5A.

545,499.9 ***.***.**. :***

}:.:2_2$;9 535 520 2250 0.02092 0.02055 9,495.2 1,140.0 520 510 2250 0.02055 0.02031 6,089.2 731.1 510 500 2250 0.02031 0.02009 5,829.6 699.9 500 490 2250 0.02009 0.01989 5,411.5 649.7 490 480 2250 0.01989 0.01969 5,521.5 662.9 480 470 2250 0.01969 0.01951 5,208.2 625.3 470 460 2250 0.01951 0.01933 5,163.1 619.9 460 450 2250 0.01933 0.01916 4,965.4 596.2 450 441 2250 0.01916 0.01901 4,275.4 513.3 441 420 2250 0.01901 0.01869 9,767.8 0.0 420 410 2250 0.01869 0.01855 4,523.1 0.0 410 400 2250 0.01855 0.01842 4,115.8 0.0 400 385 2250 0.01842 0.01822 6,446.7 0.0 385 370 2250 0.01822 0.01804 5,924.2 0.0 370 360 2250 0.01804 0.01792 4,015.6 0.0 360 350 2250 0.01192 0.0:1781 3,728.5 0.0 350 350 350 0.02698 0.01912 7,614.9 0.0 350 350 350 0.01781 0.01797 (5,575.7) 0.0 Add in RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.).

350 350 350 300 350 I 0.01191 0.01191 o.o o.o 350 0.01797 0.01743 21,571.2 0.0 300 260 350 0.01743 0.01707 15,139.0 0.0 260 230 350 0.01707 0.01683 10,452.5 0.0 230 200 350 0.01683 0.01662 9,393.6 0.0 I TOTAL BAT VOLUME= 7, 197.4 GALLONS I Nuclear SeNices 0.0 382.8 0.0 245.5 0.0 235.0 0.0 218.2 0.0 222.6 0.0 210.0 0.0 208.1 0.0 200.2 0.0 172.4 1,172.7 133.1 543.1 61.6 494.1 56.1 774.0 87.8 711.3 80.7 482.1 54.7 447.7 50.8 914.3 0.0 (669.4) 0.0 0.0 0.0.

2,589.9 293.9 1,817.6 206.3 1,254.9 142.4 1,127.8 128.0 704.8 950.3 1,185.3 1,403.4 1,626.0 1,835.9 2,044.1 2,244.2 2,416.6 2,549.7 2,611.3 2,667.4 2,755.2 2,835.9 2,890.6 2,941.4 2,941.4 2,941.4 3,384.7 3,678.6 3,884.8 4,027.2 4,155.2 551,834.5 ::

~HG.

557,899.1 ii:} :.\\ (<

~11*,!f 563,520.0 :: :.::>**: *B~i 569,212.9 r. : *

• 499)t 574,691.0... :.:*::. : ft : ss~1g

t !iii ii 599,576.5.* :;:!:

i\\l:!il *?ii§ 604,161.3 :::)} :.* : :~ii~~

608,333.1 /*:~~:)('.~ ~/:::*::: *.*.*.*.*.*.*.*.*.*.*.*.*.*.*.*.*.*.

614,867.6 t<

• ??li9i4i 620,872.6,. r*i

• \\ 3~~i§ E:S:~ s":,"ca~I 630,161.5 *.

a1\\S:a.

. *.. /;{)\\(~)\\\\\\

725,006.9 ** >.:*.. :a.*1s;a 747,67*2.o **** * ***

• :}a~o:2 763 017 3 896/1.

n3,612.2

• .:91.0J 103.133.8 s~.z~a BACR Version 2 Pa e 63of133

BORIC ACID CONCENTRATION REDUCTION RT TECHNICAL BASES AND OPERATIONAL ANALYSIS TABLE 2-17 Salem Nuclear Generating Station

• Plant Cooldown from 547 "F to 200 "F BAT 3.9375 wt.% Boric Acid AVERAGE SYSTEM PZR TEMPERATURE PRESS.

n Tf

("F "F) sia 547 547 2250 547 535 2250 535 520 2250.

520 510 2250 510 500 2250 500 490 2250 490 480 2250 480 470 2250 470 460 2250 460 450 2250 450 445 2250 445 430 2250 430 415 2250 415 400 2250 400 385 2250 385 370 2250 370 360 2250 360 350 2250 350 350 350 350 350 350 SPECIFIC VOLUME Vi Vf cu.ft./lbm cu.ft./lbm 0.02125 0.02125 0.02125 0.02092 0.02092 0.02055 0.02055 0.02031 0.02031 0.02009 0.02009 0.01989 0.01989 0.01969 0.01969 0.01951 0.01951 0.01933 0.01933 0.01916 0.01916.

0.01908 0.01908 0.01884 0.01884 0.01862 0.01862 0.01842 0.01842 0.01822 0.01822 0.01804 0.01804 0.01792 0.01792 0.01781 0.02698 0.01912 0.01781 0.01797 RWST 2350 SHRINKAGE BAT MASS VOLUME lbm 0.0 7,988.2 959.1 9,495.2 1,140.0 6,089.2 731.1 5,829.6 699.9 5,411.5 649.7 5,521.5 662.9 5,318.2 625.3 5,163.1 619.9 4,965.4 596.2 2,367.3 284.2 7,070.1 0.0 6,858.6 0.0 6,386.1 0.0 6,446.7 0.0 5,924.2 0.0 4,015.6 0.0 3,728.5 0.0 7,614.9 0.0 (5,575.7) 0.0 Add in RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

350 350 350 0.01797 0.01797 0.0 0.0 350 300 350 0.01797 0.01743 21,571.2 0.0 300 260 350 0.01743 0.01707 15,1;39.0 0.0 260 230 350 0.01707 0.01683 10,452.5 0.0 230 200 350 0.01683 0.01662 9,393.6 0.0 I TOTAL BAT VOLUME = 6,968.3 GALLONS I Boric Acid RWST B/A VOLUME ADDED lbm 0.0 0.0 327.4 0.0 389.2 0.0 249.6 0.0 238.9 0.0 221.8 0.0-226.3 0.0 213.5 0.0 211.6 0.0 203.5 0.0 97.0 848.9 96.3 823.5 93.4 766.7 87.0 774.0 87.8 711.3 80.7 482.1 54.7 447.7 50.8 914.3 0.0 (669.4) 0.0 0;0 0.0 2,589.9 293.9 1,817.6 206.3 1,254.9 142.4 1,127.8 128.0 70 "F 70 "F CEN-REV. 00 TOTAL TOTAL FINAL CONC.

B/A SYS. MASS lbm 0.0 327.4 716.6 966.2 1,315.2 1,427.0 1,653.3 1,866.8 2,078.4 2,281.9 2,379.0 2,475.3 2,568.7 2,655.7 2,743.6 2,824.3 2,879.0 2,929.8 2,929.8 2,929.8 3,371.3 3,665.2 3,871.4 4,013.8 4,141.8 IJm

(

m boron

.*** <§:1*~01

• • >**a.~1:1 725,793.5 *....

747,658.6 *.*.*

763,003.9 n3,598.8...

783,120.4

• • * **so1:1:

BACR Ver.>ion 2 Pa e 64of133

ORIC ACID CONCENTRATION REDUCTION RT TECHNICAL BASES AND OPERATIONAL ANALYSIS TABLE 2-18 Salem Nuclear Generating Station Plant Cooldown from 547 "F to 200 "F BAT 4.0 wt. % Boric Acid RWST 2350 Boric Acid AVERAGE SYSTEM PZR TEMPERATURE PRESS.

SPECIFIC SHRINKAGE BAT RWST B/A VOLUME MASS VOLUME VOLUME ADDED Ti Tf Vi Vf

("F)

("F

( sia cu.ft./lbm cu.ft./lbm lbm lbm 547 547 2250 0.02125 0.02125 0.0 0.0 547 535 2250 0.02125 0.02092 7,988.2 959.1 0.0.

332.8 535 520 2250 0.02092 0.02055 9,495.2 1, 140.0 o.o 395.6 520 510

. 2250 0.02055 0.02031 6,089.2 731.1 0.0 253.7 510 500 2250 0.02031 0.02009 5,829.6 699.9 0.0 242.9 500 490 2250 0.02009 0.01989 5,411.5 649.7 0.0 225.5 490 480 2250 0.01989 0.01969 5,521.5 662.9 0.0 230.1 480 470 2250.

0.01969 0.01951 5,3)8.2 625.3 0.0 217.0 470 460 2250 0.01951 0.01933 5,163.1 619.9 0.0 215.1 460 448 2250 0.01933 0.01912 5,909.9 709.6.

0.0 246.2 448 435 2250 0.01912 0.01892 6, 141.8 0.0 737:4 83.7 435 420 2250 0.01892 0.01869 6,956.9 0.0 835.3 94.8 420 410 2250 0.01869 0.01855 4,523.1 0.0 543.1 61.6 410 400 2250 0.01855 0.01842 4,115.8 0.0 494.1 56.1 400 385 2250 0.01842 0.01822 6,446.7 0.0 774.0 87.8 385 370 2250 0.01822 0.01804 5,924.2 0.0 711.3 80.7 370 360 2250 0.01804 0.01792 4,015.6 0.0 482.1 54.7 360 350 2250 0.01792 0.01781 3,728.5 0.0 447.7 50.8 350 350 350 0.02698 0.01912 7,614.9 0.0 914.3 0.0 350 350 350 0.01781 0.01797 (5,575.7) 0.0 (669.4) 0.0 Add in RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

350 350 350 0.01797 0.01797 0.0 0.0 0.0.

0.0 350 300 350 0.01797 0.01743 21,571.2 0.0 2,589.9 293.9 300 260 350 0.01743 0.01707 15,139.0 0.0 1,817.6 206.3 260 230 350 0.01707 0.01683 10,452.5 0.0 1,254.9 142.4 230 200 350 0.01683 0.01662 9,393.6 0.0 1,127.8 128.0 I TOTAL BAT VOLUME= 6,797.5 GALLONS I 70 "F 70 "F CEN-REV. 00 TOTAL TOTAL FINAL CONC.

B/A SYS. MASS lbm 0.0 332.8 728.5 982.2 1,225.1 1,450.6 1,680.6 1,897.6 2,112.8 2,359.0 2,442.7 2,537.5 2,599.1 2,655.2 2,743.0 2,823.7 2,878.4 2,929.2 2,929.2 2,929.2 3,370.6 3,664.5 3,870.8 4,013.2 4,141.2 lbm m boron 527,311.1 :t:r:::::rJ:::::-J:::r::::::b10*

535 632 0===,==

=,

db.at&

~ i.Jtt1111

.563,576.0 :::=:., ::::li! ::i::1. :1~1 569,3Zl.s :*=::*

, r 5164 574,752.7 ?: : :==::(::* $.'l?i~

580, 131.0 ~;f:~~j{!;'.( ::.=::::::<-:~::\\:}~636it

~:~ ~,,~;.:;*'II 599,564.3..

§39]9' 604,149.1

>** 7g~;~

600,320.9 z~H*

614,855.4 *****-**** r.;,=_ =vattu

?j...* ;

1;1~1

~ '.;; '.:::111 630,749.3 :. :

81/t9 725,792.8 < \\{ >:~\\~1::~\\

747,657.9.* *.

• _*: ras§;~.

163,003.2

=i)*iQ?.&;s

~~~:~::~ ***:.. **.**

< * :: l~l;i BACR Version 2 Pa e 65of133

ORIC ACID CONCENTRATION REDUCTION*

RT TECHNICAL BASES AND OPERATIONAL ANAL SIS TABLE 2-19 Salem Nuclear Generating Station Plant Cooldown from BAT 3.75.

wt. % Boric Acid 70"F 547 "F to 200 "F RWST 2400.

Boric Acid 70 "F AVERAGE SYSTEM PZR SPECIFIC SHRINKAGE BAT RWST B/A TOTAL TOTAL FINAL TEMPERATURE PRESS.

VOLUME*

MASS VOLUME VOLUME ADDED B/A SYS. MASS CONC.

Ti Tf VI Vf "F

"F la cu.ft./lbm cu.ft./lbm lbm lbm lbm lbm mboron 547 547 2250 0.02125 0.02125 0.0 0.0 0.0 0.0 527,311.7

.=::*:

(Q.O 547 535 2250 0.02125 0.02092 7,988.2 959.1 0.0 311.2 311.2 535,611.2

• lQl.6 535 520 2250 0.02092 0.02055 9,495.2 1,140.0 0.0 369.9 681.2 545,476.3

• 218.3

.**. ~i~<>

520 510 2250 0.02055 0.02031 6,089.2 731.1 0.0 237.2 918.4 551,002.7 510 500 2250 0.02031 0.02009 5,829.6 699.9 0.0 227.1 1,145.5 557,859.4 359;('j 500 490 2250 0.02009 0.01989 5,411.5 649.7 0.0 210.8 1,356.4 563,481.8

. 426:8 490 480 2250 0.01989 0.01969 5,521.5 662.9 0.0 215.1 1,571.5 569,218.4

• \\.m,7:*

480 470 2250 0.01969 0.01951 5,3>8.2 625.3 0.0 202.9 1,774.4 574,629.5 539;9

~ 470 460 2250 0.01951 0.01933 5,163.1 619.9 0.0 201.2 1,975.6 579,993.8

• • =59s;s

... 11;*1 460 450 2250 0.01933 0.01916 4,965.4 596.2 0.0 193.5 2,169.0 585,152.6.;**.

450 436 2250 0.01916 0.01893 6,618.5 794.6 0.0 257.9 2,426.9 592,029.0 716.7 436 420 2250 0.01893 0.01869 7,424.8 0.0 891.4 103.3 2,530.2 599,557.1

~111 420 410 2250

. 0.01869 0.01855 4,523.1 0.0 543.1 63.0 2,593.2 604,143.2 410 400 2250 0.01855 0.01842 4, 115.8 0.0 494.1 57.3 2,650.5 608,316.2

!~1-#

400 385 2250 0.01842 0.01822 6,446.7 0.0 774.0 89.7 2,740.2 614,852.6 11Q;g 385 370 2250 0.01822 0.01804 5,924.2 0.0 711.3 82.5 2,822.7 620,859.3 7ij;f9 370 360 2250 0.01804 0.01792 4,015.6 0.0 482.1 55.9 2,878.5 624,930.8 805.3 360 350 2250 0.01792 0.01781 3,728.5 0.0 447.7 51.9 2,930.4 628,711.3 Q14,~

350 350 350 0.02698 0.01912 7,614.9 0.0 914.3 0.0 2,930.4 636,326.2 0os.~2.

350 350 350 0.01781 0.01797 (5,575.7 0.0 (669.4) 0.0 2,930.4 630,750.5 ai2.a Add in RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC;)

350 350 350 0.01797 0.01797 0.0 0.0 0.0 0.0 3,372.0 725,794.2

.=:~l?*3 350 300 350 0.01797 0.01743 21,571.2 0.0 2,589.9 300.2 3,672.2 747,f>>S.7 858.7.

300 260 350 0.01743 0.01707 15,139.0 0.0 1,817.6 210.7 3,883.0 763,015.4 8~.7 260 230 350 0.01707 0.01683 10,452.5 0.0 1,254.9 145.5 4,028.4 773,613.4 910;4 230 200 350 0.01683 0.01662 9,:E3.6 0.0 1,127.8 130.7 4,159.2 783,137.7 9k8:5 I TOTAL BAT VOLUME= 7,478.7 GALLONS I BACR Versi:m 2 Pa e 66of133

ORIC ACID CONCENTRATION REDUCTION ORT TECHNICAL BASES AND OPERATIONAL ANAL: SIS TABLE 2-20 Salem Nuclear Generating Station Plant Cooldown from 547 "F to 200 "F BAT 3.8125 wt.% Boric Acid RWST 2400 Boric Acid AVERAGE SYSTEM PZR TEMPERATURE PRESS.

SPECIFIC VOLUME SHRINKAGE BAT RWST B/A MASS VOLUME VOLUME ADDED Ti Tf 547 547 547 535 sia 2250 2250 Vi Vf cu.ft./lbm cu.ft./lbm lbm 535 520 2250 0.02125 0.02125 0.02092 0.02055 0.02031 0.02009 0.01989 0.01969 0.01951 0.01933 0.02125 0.02092 o.o2o55 0.02031 0.02009 0.01989 0.01969 0.01951 0.01933 0.01916 0.0 7,988.2 9,495.2 6,089.2 5,829.6 5,411.5 5,521.5 5,318.2 5,163.1 4,965.4 0.0 959.1 1,140.0 731.1 520 510 2250 510 500 2250

• 699.9 649.7 662.9 625.3 619.9 596.2 500 490 2250 490 480 2250 480 470 2250 470 460 2250 460 450 2250 450 440 2250 0.01916 0.01900 4,754.5 570.8 440 420 2250 0.01900 0.01869 9,288.8 0.0 420 410 2250 0.01869 0.01855 4,523.1 0.0 410 400 2250 0.01855 0.01842 4,115.8 0.0 400 385 2250 0.01842 0.01822 6,446.7 0.0 385 370 2250 0.01822 0.01804 5,924.2 0.0 370 360 2250 0.01804 0.01792 4,015.6 0.0 360 350 2250 0.01792 0.01781 3,728.5 0.0 350 350 350 0.02698 0.01912 7,614.9 0.0 350 350 350 0.01781 0.01797 (5,575.7 0.0 Add in RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

350 350 350 0.01797 0.01797 0.0 0.0 350 300 350 0.01797 0.01743 21,571.2 0.0 300 260 350 0.01743 0.01707 15,139.0 0.0 260 230 350 0.01707 0.01683 10,452.5 0.0 230 200 350 0.01683 0.01662 9,393.6 0.0

[TOTAL BAT VOLUME=* 7,254.9 GALLONS I lbm 0.0 0.0 0.0 316.6 0.0 376.4 0.0 241.4 0.0 231.1 0.0 214.5 0.0 218.8 0.0 206.4 0.0 204.6 0.0 196.8 0.0 1,115.2 543.1 494.1 n4.o 711.3 482.1 447.7 914.3 (669.4) 0.0 2,589.9 1,817.6 1,254.9 1,127.8 188.4 129.3 63.0 57.3 89.7 82.5 55.9 51.9 0.0 0.0 0.0 300.2 210.7 145.5 130.7 70"F 70 "F TOTAL TOTAL FINAL B/A SYS. MASS CONC.

lbm 0.0 316.6 693.0 934.3 1,165.4 1,379.9 1,598.7 1,805.2 2,009.8 2,3>6.6 2,395.1 2,524.3 2,587.3 2,644.6 2,734.3 2,816.8 2,872.7 2,924.6 2,924.6 2,924.6 3,365.2 3,665.5 3,876.2 4,021.7 4,152.4 l>m mboron 527,311.7..* *.. ***:* '<.***::;*;;ii!'i!!,q~g g~~~ ','{I 563,505.3 569,245.6 574,660.2 580,028.0 585,190.2 590,133.2 599,551.2 604,137.3 608,310.3 614,846.7 620,8.53.4 624,924.9 628,705.4 636,320.3 630,744.6 725,787.4 747,658.9 763,008.6 n3,606.6 783,131.0

>f~~n 491.0

... 549;~

.. ***. oos:ii

• ~l:i

/~-[~.

760.1

~:§ 793;2 Ji*!

• .*./~~[i 810~6

/~19.~t>

857.:1 888.2 90~.9 927~0 BACR Version 2 Pa e 67of133

ORIC ACID CONCENTRATION REDUCTION ECHNICAL BASES AND OPERATIONAL ANAL TABLE 2-21 Salem Nuclear Generating Station Plant Cooldown from 547 "F to 200 "F BAT 3.875 wt. % Boric Acid RWST 2400 Boric Acid AVERAGE SYSTEM PZR TEMPERATURE PRESS.

SPECIFIC SHRINKAGE BAT RWST B/A VOLUME M~S VOLUME VOLUME ADDED Ti TI "F

547 547 535 520 510 500 490 480

. 470 460 450 443 420 410 400 385 370 360 350 350 "F

Add in AHAS 547 535 520 510 500 490 480" 470 460 450 443 420 410 400 385 370 360 350 350 350 350 350 350 300 300 260 260 230 230 200 Vi Vf c:u.ft./lbm cu.ft./lbm lbm 2250 0.02125 0.02125 0.0 0.0 2250 0.02125 0.02092 7,988.2 959.1 2250 0.02092 0.02055 9,495.2 1,140.0 2250 0.02055 0.02031 6,089.2 731.1 2250 0.02031 0.02009 5,829.6 699.9 2250 0.02009 0.01989 5,411.5 649.7 2250 0.01989 0.01969 5,521.5 662.9 2250 0.01969 0.01951.

5,318.2 625.3 2250 0.01951 0.01933 5,163.1 619.9 2250 0.01933 0.01916 4,965.4 596.2 2250 0.01916 0.01904 3,319.8 398.6 2250 0.01904 0.01869 10,723.5 0.0 2250 0.01869 0.01.855 4,523.1 0.0 2250 0.01855 0.01842 4,115.8 0.0 2250 0.01842 0.01822 6,446.7 0.0 2250 0.01822 0.01804 5,924.2 0.0 2250 0.01804 0.01792 4,015.6 0.0 2250 0.01792 0.01781 3,728.5 0.0 350 0.02698 0.01912 7,614.9 0.0 350 0.01781 0.01797 (5,575.7 0.0 VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

350 0.01797 0.01797 0.0 0.0 350 0.01797 0.01743 21,571.2 0.0 350

.0.01743 0.01707 15,139.0 0.0 350 0.01707 0.01683 10,452.5 0.0 350 0.01683 0.01662 9,393.6 0.0 IT..::OTAL BAT VOLUME= 7,082.7 GALLONS I

~--------------------- - - -

lbm 0.0 0.0 322.0 0.0 382.8 0.0 245.5 0.0 235.0 0.0 218.2 0.0 222.6 0.0 210.0 0.0 208.1 0.0 200.2 0.0 133.8 1,287.5 149.3 543.1

• 63.0 494.1 57.3 n4.o 89.7 711.3 82.5 482.1 55.9 447.7 51.9 914.3 0.0 (669.4) 0.0 0.0 0.0 2,589.9 300.2 1,817.6 210.7 1,254.9 145.5 1,127.8 130.7 70 "F 70 "F TOTAL TOTAL FINAL B/A SYS. M~

CONC.

lbm 0.0 322.0 704.8 950.3 1,185.3 1,403.4 1,626.0 1,835.9 2,044.1 2,244.2 2,378.1 2,527.3 2,590.3 2,647.6 2,737.3 2,819.7 2,875.6 2,927.5 2,927.5 2,927.5 3,368.7 3,668.9 3,879.6 4,025.1 4,155.8 l>m mboron 521,311. 7 ;. : *:*. ::**:: ::.'}):::]g~g*

535,622.0 :* ;.. >

},:i=:l~;J:

~E1 ~,';;\\~I 569,272.9 *:* * *

,4~ifl 574,691.0 *... *:

... <558;5 580,002.3

. ******. t.1U~i1 585,227.8

~79:#

588,681.4

.. *.* zqg.a 599,554.2

. 737;0 604, 140.2 14~;6 608,313.3 760.9 614,849.7.

778.4 620,856.4 794.0 624,927.9

~()4.5 628,708.4 814.1 636,~.3 ;

~~*4 630,747.6 811.5 725,790.9 747,662.3 763,012.1 773,610.1 783,134.4 811.5

• asi9 aa9.o 909.7 927;8 BACR Version 2 Pa e 68of133

ORIC ACID CONCENTRATION REDUCTION TECHNICAL BASES AND OPERATIONAL ANAL TABLE 2-22 Salem Nuclear Generating Station Plant Cooldown from 547 °F to 200 °F BAT RWST 3.9375 2400 AVERAGE SYSTEM PZR TEMPERATURE PRESS.

SPECIFIC VOLUME SHRINKAGE BAT MASS VOLUME Ti Tf VI Vf

°F

°F la cu.ft./lbm cu.ft./lbm lbm 547 547 2250 O.Cl2125 0.02125 0.0 0.0 547 535 2250 0.02125 0.02092 7,988.2 959.1 535 520 2250 0.02092 0.02055 9,495.2 1,140.0 520 510 2250 0.02055 0.02031 6,089.2 731.1 510 500 2250 0.02031 0.02009 5,829.6 699.9 500 490 2250 0.02009 0.01989 5,411.5 649.7 490 480 2250 0.01989 0.01969 5,521.5 662.9 480 470 2250 0.01969 0.01951 5,208.2 625.3 470 460 2250 0.01951 0.01933 5,163.1 619.9 460 447 2250 0.01933 0.01911 6,383.4 766.4 447 435 2250 0.01911 0.01892 5,668.4 0.0 435 420 2250 0.01892 0.01869 6,956.9 0.0 420 410 2250 0.01869 0.01855 4,523.1 0.0 410 400 2250 0.01855 0.01842 4,115.8 0.0 400 385 2250 0.01842 0.01822 6,446.7 0.0 385 370 2250 0.01822 0.01804 5,924.2 0.0 370 360 2250 0.01804 0.01792 4,015.6 0.0 360 350 2250 0.01792 0.01781 3,728.5 0.0 350 350 350 0.02698 0.01912 7,614.9 0.0 350 350 350 0.01781 0.01797 (5,515.7 0.0 Add in RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

350 350 350 0.01797 0.01797 0.0 0.0 350 300 350 0.01797 0.01743 21,571.2 0.0 300 260 350 0.01743 0.01707 15,139.0 0.0 260 230 350 0.01707 0.01683 10,452.5 0.0 230 200 350 0.01683 0.01662 9,393.6 0.0 I TOTAL BAT VOLUME = 6,854.3 GALLONS I wt. % Boric Acid Boric Acid RWST B/A VOLUME ADDED lbm 0.0 0.0 0.0 327.4 0.0 389.2 0.0 249.6 0.0 238.9 0.0 221.8 0.0 226.3 0.0 213.5 0.0 211.6 0.0 261.6 680.6 78.9 835.3 96.8 543.1 63.0 494.1 57.3 774.0 89.7 711.3 82.5 482.1 55.9 447.7 51.9 914.3 0.0 (669.4 0.0 0.0 0.0 2;589.9 300.2 1,817.6 210.7 1,254.9 145.5 1,127.8 130.7 70 °F 70 °F TOTAL TOTAL CEN-REV. 00 FINAL B/A SYS. MASS CONC.

lbm 0.0 327.4 716.6 966.2 1,205.2 1,427.0 1,653.3 1,866.8 2,078.4 2,340.0 2,418.9 2,515.8 2,518.7 2,636.0 2,725.7 2,008.2 2,864.1 2,916.0 2,916.0 2,916.0 3,355.4 3,655.6 3,866.3 4,011.8 4,142.5 l:>m m boron 527 311 1 *.. ;:.::::::.=***=*=::::;**=**;.*;**........ :.-:*o****:o***.*

I

/*:*: ***

. **'.:'.. ~

.*. f :; **li8~*

563 E.~55:21 :.:~4;*.. *:.=.:*1.11_i

.*,.1:.=_.:.. !**.i*:.::.~<.i "r11

• • • =*****~g\\~

~~::::: :

< ~~:~*

580,096.6,

~m;!

586,741.6 :*.

§~;~

592,488.9 :

• . 713:8 599,542.6

.z~:=a 604,128.7 748":3 608,3>1.7 757.6 614,838.1 775.1 620,844.8 790.8 624,916.4 8Q1.3 628,696.8 fl1.0.9 636,311.8

~1.~

630,736.1 808.~

725,777.6 808:3 747,649.0 854.8 762,998.8 aas.9 773,596.8 906.7 783, 121.1 924.8 BACR Version 2 Pa e 69of133

ORIC ACID CONCENTRATION REDUCTION TECHNICAL BASES AND OPERATIONAL ANAL.:

TABLE 2-23 Salem Nuclear Generating Station Plant Coolclown from BAT 4.0 wt. % Boric Acid 70 "F 547 "F to 200 "F RWST 2400 Boric Acid 70 "F AVERAGE SYSTEM PZR SPECIFIC SHRINKAGE BAT RWST B/A TOTAL TOTAL FINAL TEMPERATURE PRESS.

VOLUME M.ASS VOLUME VOLUME ADDED B/A SYS.MASS CONC.

Ti Tf VI Vf "F

"F ia cu.ft./lbm cu.ft./lbm lbm lbm lbm l>m mboron 547 547 2250 0.02125 0.02125 0.0 0.0 0.0 527,311.7

• .**. * (to 547 535 2250 0.02125 0.02092 7,988.2 959.1 0.0 332.8 332.8 535,632.8 19~.6 535 520 2250 0.02092 0.02055 9,495.2 1,140.0 0.0 395.6 728.5 545,523.6 :.:.. ::_

~.5 520 510 2250 0.02055 0.02031 6,089.2 731.1 0.0 253.7 982.2 551,866.5 :

• au.2 510 500 2250 0.02031 0.02009 5,829.6 699.9 0.0 242.9 1,225.1 557,939.0 :*..

383.9 500 490 2250 0.02009 0.01989 5,411.5 649.7 0.0 225.5 1,450.6 563,576.0

... ~~#

490 480 2250 0.01989 0.01969 5,521.5 662.9 0.0 230.1 1,680.6 569,327.5

• . &16;1 480 470 2250 0.01969 0.01951 5,208.2" 625.3 0.. 0 217.0 1,w:J7.6 574,752.7

'1:1 470 460 2250 0.01951 0.01933 5,163.1 619.9 0.0 215.1 2,112.8 580,131.0 :

460 450 2250 0.01933 0.01916 4,965.4 596.2 0.0 206.9 2,319.7 585,:1>3.3

692!9 450 435 2250 0.01916 0.01892 7,086.4 0.0 850.8 98.6 2,418.3 592,488.3

• • 71ii'.6 435 420 2250 0.01892 0.01869 6,956.9 0.0 835.3 96.8 2,515.1 599,542.0 il.:1 420 410 2250 0.01869 0.01855 4,523.1 0.0 543.1 63.0 2,578.1 604,128.0 410 400 2250 0.01855 0.01842 4,115.8 0.0 494.1 57.3 2,635.4 608,:!>1.1 I:~

400 385 2250 0.01842 0.01822 6,446.7 0.0 n4.o 89.7 2,725.1 614,837.5 385 370 2250 0.01822 0.01804 5,924.2 0.0 711.3 82.5 2,007.5 620,844.2

• 1@9;~

370 360 2250 0.01804 0.01792 4,015.6 0.0 482.1 55.9 2,863.4 624,915.7 *.*

80h1 360 350 2250 0.01792 0.01781 3,728.5 0.0 447.7 51.9 2,915.3 628,696.2

. ~19~r 350 350 350 0.02698 0.01912 7,614.9 0.0 914.3 0.0 2,915.31 636,311.1

• • • • • aPt*Q

.::::.*:*:=<:::.:: *:*

350 350 350 0.01781 0.01797 (5,575.7 0.0 (669.4) 0.0 2,915.3 630,735.4

.. QQ~~1 Add in RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

.*.. ~&~.1 3501 350 350 0.01797 0.01797 0.0 0.0 0.0 0.0 3,334.6 725,776.8 350 300 350 0.01797 0.01743 21,571.2 0.0 2,589.9 300.2 3,6.54.8 747,648.3 Q~.7 300 260 350 0.01743 0.01707 15,139.0 0.0 1,817.6 210.7 3,865.6 762,998.0 ass.a 260 230 350 0.01707 0.01683 10,452.5 0.0 1,254.9 145.5 4,011.0.

n3,596.o

906.5 230 200 350 0.01683 0.01662 9,393.6 0.0 1,127.8 130.7 4,141.8 783,120.3 924.7 I TOTAL BAT VOLUME= 6,684.1 GALLONS I BACR Ver.iion 2 Pa e 70of133

ORIC ACID CONCENTRATION REDUCTION ORT TECHNICAL BASES AND OPERATIONAL ANAC SIS TABLE 2-24 Salem Nuclear Generating Station Plant Cooldown from 547 "F to 200 "F BAT 3.75 wt. % Boric Acid RWST 2450 Boric Acid AVERAGE SYSTEM PZR TEMPERATURE PRESS.

SPECIFIC SHRINKAGE BAT RWST B/A VOLUME MASS VOLUME VOLUME ADDED Tl Tf Vi Vf "F

"F la cu.ft./lbm cu.ft./lbm lbm 547 547 547 535 535 520 520 510 510 500 500 490 490 480 480 470 470 460 460 450 450 439 439 420 420 410 410 400 400 385 385 370 370 360 360 350 350 350 350 350 Add in RHRS 350 350 350 300 300 260 260 230 230 200 2250 2250 2250 2250 2250 2250 2250 2250 2250 2250 2250.

2250 2250

'2250 2250 2250 2250 0.02125 0.02125 0.02092.

0.02055 0.02031 0.02009 0.01989 0.01969 0.01951 0.01933 0.01916 0.01898 0.01869 0.01855 0.01842 0.01822 0.01804 0.02125 0.02092 0.02055 0.02031 0.02009 0.01989 0.01969 0.01951 0.01933 0.01916 0.01898 0.01869 0.01855 0.01842 0.01822 0.01804 0.01792 0.0 7,988.2 959.1 9,495.2 1,140.0 6,089.2 731.1 5,829.6 699.9 5,411.5 649.7 5,521.5 662.9 5,al8.2 625.3 5,163.1 619.9 4,965.4 596.2 5,219.3 626.6 8,823.9 0.0 4,523.1 0.0 4, 115.8 0.0 6,446.7 0.0 5,924.2 0.0 4,015.6 0.0 2250 0.01792 0.01781 3,728.5 0.0 350 0.02698 0.01912 7,614.9 0.0 350 0.01781

'0.01797 (5,575.7 0.0 VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

350 0.01797 0.01797 0.0 0.0 350 350 350 350 0.01797 0.01743 0.01743 0.01707 0.01707 0.01683 0.01683 0.01662 21,571.2 15,139.0 10,452.5 9,~3.6 0.0 0.0 0.0 0.0 I TOTAL BAT VOLUME= 7,310.7 GALLONS I lbm 0.0 0.0 0.0 311.2 0.0 369.9 0.0 237.2 0.0 227.1 0.0 210.8 0.0 215.1 0.0 202.9 0.0 201.2 0.0 193.5 0.0 203.4 1,059.4 125.4 543.1 64.3 494.1 58.5 n4.o 91.6 711.3 84.2 482.1 57.1 447.7 53.0 914.3 0.0 (669.4) 0.0 0.0 0.0 2,589.9

• 306.6 1,817.6 215.2 1,254.9 148.6 1,127.8 133.5 70 "F 70 "F TOTAL TOTAL FINAL BIA SYS. MASS CONC.

lbm 0.0 311.2 681.2 918.4 1,145.5 1,356.4 1,571.5 1,n4.4

' 1,975.6 2,169.0 2,372.4 2,497.8 2,562.1 2,620.6 2,712.2 2,796.4 2,853.5 2,906.5 2,906.5 2,906.5 3,344.4 3,651.0 3,866.2 4,014.7 4,148.2 l:>m m boron

~~~:~ ::;;\\:::1\\'.:*?:\\:<<::.=::jci~:i 545,476.3 **.::.*. :

}=.**** :218~3 551,002.7 =::: :.::. ):

,iJ,~9

'.;'""I' 574,629.5 * >

539;9 579,993.8 *.*.

595;5 585, 152.6

~48'.1 590,575.3 *.

~9~'.~

599,524.6.

7~9.4 604, 112.0 741.5 608,286.3 *.

• 153.2 614,824.6.:

.*.. 111;~

620,833.0 7~,~

624,905.7 7QQ;3 628,687.3 aruia 636,312.2

?~~;?,

630,726.5

805.7 725,766.6 747,644.4 762,998.6 n3,599.7 783,126.8

• 00s~9 9&7.:3 926.1 BACR Vemion 2 Pa e 71 of 1.33

ORIC ACID CONCENTRATION REDUCTION ECHNICAL BASES AND OPERATIONAL ANAC TABLE 2-25 Salem Nuclear Generating Station Plant Cooldown from BAT 3.8125 wt. % Boric Acid 547 "F to 200 "F RWST 2450 Boric Acid AVERAGE SYSTEM PZR SPECIFIC SHRINKAGE BAT RWST B/A TEMPERATURE PRESS.

VOLUME MASS VOLUME VOLUME ADDED Ti Tf VI Vf "F

"F sla cu.ft./lbm cu.ft./lbm lbm lbm 547 547

• 2250 0.02125 0.02125 0.0 0.0 547 535 2250 0.02125 0.02092 7,988.2 959.1 316.6 535 520 2250 0.02092 0.02055 9,495.2 1,140.0 0.0 376.4 520 510 2250 0.02055 0.02031 6,089.2 731.1 0.0 241.4 510 500 2250 0.02031 0.02009 5,829.6

.699.9 0.0 231.1 500 490 2250 0.02009 0.01989 5,411.5 649.7 0.0 214.5 490 480 2250 0.01989 0.01969 5,521.5 662.9 0.0 218.8 480 470 2250 0.01969 0.01951 5,3>8.2 625.3 0.0 206.4 470 460 2250 0.01951 0.01933 5,163.1 619.9 0.0 204.6 460 450 2250 0.01933 0.01916 4,965.4 596.2 0.0 196.8 450 442 2250 0.01916 0.01903 3,797.2 455.9 0.0 150.5 442 425 2250

. 0.01903 0.01877 7,933.9

• o.o 952.6 112.8 425 410 2250 0.01877 0.01855 6,835.2 0.0 820.7 97.1 410 400 2250 0.01855 0.01842 4, 115.8 0.0 494.1 58.5 400 385 2250 0.01842 0.01822 6,446.7 0.0 n4.0 91.6 385 370 2250 0.01822 0.01804 5,924.2 0.0 711.3 84.2 370 360 2250 0.01804 0.01792 4,015.6 0.0 482.1 57.1 360 350 2250 0.01792 0.01781 3,728.5 0.0 447.7 53.0 350 350 350 0.02698 0.01912 7,614.9 0.0 914.3 0.0 350 350 350 0.01781 0.01797 (5,575.7) 0.0 (669.4) 0.0 Add in RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

350 350 350 0.01797 0.01797 0.0 0.0 0.0 0.0 350 300 350 0.01797 0.01743 21,571.2 0.0 2,589.9 306.6 300 260 350 0.0,1743 0.01707 15,139.0 0.0 1,817.6 215.2 260 230 350 0.01707 0.01683 10,452.5 0.0 1,254.9 148.6 230 200 350 0.01683 0.01662 9,aJ3.6 0.0 1,127.8 133.5 I TOTAL BAT VOLUME= 7, 140.0 GALLONS I 70 "F 70"F TOTAL TOTAL FINAL B/A SYS.MASS CONC.

lbm l:>m m boron 0.0 527,311.7

\\****Jc.to 316.6 535,616.6

.. -111=

693.0 545,488.1 934.3 551,818.6

• • _296;0 1,165.4 557,879.3.

aas~2 1,379.9 563,505.3

.* \\~gg::1 1,598.7 569,245.6

• 1~~:;,g 1,005.2 574,660.2

549;2 2,009.8 580,028.0 2,3>6.6 585,190.2 2,357.1 589,137.9.

• *:a.sa~~

2,469.9 597,184.6

• .. ~~1:;*1 2,567.0 604,117.0.

ii 2,625.5 608,291.3 2,717.1 614,829.5.

2,001.3 620,838.0.

2,858.4 624,910.7 2,911.4 628,692.2 Jl:Z 2,911.4 636,:J>7.2 2,911.4 630,731.5 867'.6 3,350.1 725,n2.3 Q07.0 3,656.*7 747,650.1

~.1 3,871.8 763,004.3 887.2 4,020.4 na,oo5.4 908.6 4,153.9 783,132.5 927.4 BACR Version 2 Pa e 72of133

RIC ACID CONCENTRATION REDUCTION RT TECHNICAL BASES AND OPERATIONAL ANALYSIS TABLE 2-26 Salem Nuclear Generating Station Plant Coolclown from BAT 3.875 wt. % Boric Acid 547 "F to 200 "F RWST 2450 Boric Acid AVERAGE SYSTEM PZR SPECIFIC SHRINKAGE BAT RWST B/A TEMPERATURE PRESS.

VOLUME MA.SS VOLUME VOLUME ADDED Ti Tf VI Vf "F

"F la cu.ft./lbm cu.ft./lbm lbm lbm 547 547 2250 0.02125 0.02125 0.0 0.0 0.0 547 535 2250 0.02125 0.02092 7,988.2 959.1 0.0 322.0 535 520 2250 0.02092 0.02055 9,495.2 1,140.0 0.0 382.8 520 510 2250 0.02055 0.02031 6,089.2 731.1 0.0 245.5 510 500 2250 0.02031 0.02009 5,829.6 699.9 0.0 235.0 500 490 2250 0.02009 0.01989 5,411.5 649.7 0.0 218.2 490 480 2250 0.01989 0.01969 5,521.5 662.9 0.0 222.6 480 470 2250 0.01969 0.01951 5,Zl8.2 625.3 0.0 210.0 470 460 2250 0.01951 0.01933 5,163.1 619.9 0.0 208.1 460 450 2250 0.01933 0.01916 4,965.4 596.2 0.0 200.2 450 446 2250 0.01916 0.01909 1,892.2 227.2 0.0 76.3

.+46 430 2250 0.01909 0.01884 7,545.2 0.0 905.9 107.2 430 410 2250 0.01884 0.01855 9,128.9 0.0 1,096.0 129.7 410 400 2250 0.01855 0.01842 4, 115.8 0.0 494.1 58.5 400 385 2250 0.01842 0.01822 6,446.7 0.0 774.0 91.6 385 370 2250 0.01822 0.01804 5,924.2 0.0 711.3 842 370 360 2250 0.01804 0.01792 4,015.6 0.0 482.1 57.1 360 350 2250 0.01792 0.01781 3,728.5 0.0 447.7 53.0 350 350 350 0.02698 0.01912 7,614.9 0.0 914.3 0.0 350 350 350 0.01781 0.01797 (5,575.7 0.0 (669.4) 0.0 Add in RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

350 350 350 0.01797 0.01797 0.0 0.0 0.0 0.0 350 300 350 0.01797 0.01743 21,571.2 0.0 2,589.9 306.6 300 260 350 0.01743 0.01707 15,139.0 0.0 1,817.6 215.2 260 230 350 0.01707 0.01683 10,452.5 0.0 1,254.9 148.6 230 200 350 0.01683 0.01662 9,393.6 0.0 1,127.8 133.5

[TOTAL BAT VOLUME= 6,911.3 GALLONS I 70 "F 70"F TOTAL TOTAL B/A SYS.MASS lbm l:>m 0.0 527,311.7 322.0 535,622.0 704.8 545,499.9 950.3 551,834.5 1,185.3 557,899.1 1,403.4 563,528.8 1,626.0 569,272.9 1,835.9 574,691.0 2,044.1 580,062.3 2,244.2 585,227.8 2,320.5 587,196.4 2,427.8 594,848.8 2,557.5 604,107.5 2,616.0 608,281.7 2,707.6 614,820.0 2,791.8 620,828.5 2,848.9 624,901.2 2,901.9 628,682.7 2,901.9 636,297.7 2,901.9 630,722.0 3,339.1 725,761.3 3,645.7 747,639.2 3,860.9 762,993.4 4,009.4 773,594.4 4,143.0 783,121.5 CEN-REV. 00 FINAL CONC.

m boron

) ':o;o JPr~1

.. 225;9

.... 11::1

• • .. a:mA ii:~

. ~~;9

< 616.1

~7:§.. 9

~~*~

.713;6 740.2 7.~1.. !}

~-;~

797!1

.fl;~

QQ4i4 AA4.;4

.. :as2ts a1~1

. 900.1 924;9 BACR Version 2 Pa e 73of133

ORIC ACID CONCENTRATION REDUCTION TECHNICAL BASES AND OPERATIONAL ANAL TABLE 2-2:7 Salem Nuclear Generating Station Plant Cooldown from 547 "F to 200 "F BAT 3.9375 wt.% Boric Acid RWST 2450 Boric Acid AVERAGE SYSTEM PZR TEMPERATURE PRESS.

SPECIFIC SHRINKAGE BAT RWST B/A VOLUME MASS VOLUME VOLUME ADDED Ti Tf "F

"F 547 547 547 535 535 520 520 510 510 500 500 490 490 480 480 470 470 460 460 449 449 435 435 420 420 410 410 400 400 385 385 370 370 360 360 350 350 350 350 350 Add in RHRS 350 350 350 300 300 260 260 230 230 200 la 2250 2250 2250 2250 2250 2250 2250 2250 2250 2250 2250 2250 2250 2250 2250 VI cu.ft.Jlbm o.~125 o.~125 0.02092 o.~55 0.02031 0.02009 0.01989 0.01969 0.01951 0.01933 0.01914 0.01892 0.01869 0.01855 0.01842 Vf cu.ft./lbm o.~125 0.02092 0.~55 0.02031 0.02009 0.01989 0.01969 0.01951 0.01933 0.01914 0.01892 0.01869 0.01855 0.01842 0.01822 lbm 0.0 0.0 7,988.2 959.1 9,495.2

. 1,140.0 6,009.2 731.1 5,829.6 699.9 5,411.5 649.7 5,521.5 662.9 5,208.2 625.3 5,163.1 619.9 5,437.3 652.8 6,614.5 0.0 6,956.9 0.0 4,523.1 0.0 4, 115.8 0.0 6,446.7 0.0 2250 0.01822 0.01804 5,924.2 0.0 2250 0.01804 0.01792 4,015.6 0.0 2250 0.01792 0.01781 3,728.5 0.0 350 0.02698 0.01912 7,614.9 0.0 350 0.01781 0.01797 (5,575.7 0.0

. VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

. 350 0.01797 0.01797 0.0 0.0 350 0.01797 0.01743 21,571.2 0.0 350 0.01743 0.01707 15,139.0 0.0 350 0.01707 0.01683 10,452.5 0.0 350 0.01683 0.01662 9,393.6 0.0

!TOTAL BAT VOLUME= 6,740.7 GALLONS I Nuclear Services lbm 0.0 0.0 0.0 32:7.4 0.0 389.2 0.0 249.6 0.0 238.9 0.0 221.8 0.0 226.3 o.o 213.5 0.0 211.6 0.0 222.9 794.1 94.0 835.3 98.9 543.1 64.3 494.1 58.5 n4.o 91.6 711.3 84.2 482.1 57.1 447.7 53.0 914.3 0.0 (669.4) 0.0 0.0 0.0 2,589.9 306.6 1,817.6 215.2 1,254.9 148.6 1,127.8 133.5 70"F 70 "F TOTAL TOTAL FINAL

• coNc.

BIA SYS. M.ASS lbm 0.0 32:7.4 716.6 966.2 1,205.2 1,427.0.

1,653.3 1,866.8 2,078.4 2,3>1.3 2,395.3 2,494.1 2,558.4

=~:::~ ;::*: '*\\.

,_* :~~;1

~ t i;f,; 1:1 2,616.9 608,282.7

?~~:2.

2,708.6 2,792.7 614,821.0

.* -770;2 620,829.4

. ?~.§ 2,849.8 2,902.8 2,902.8 2,902.8 624,902.1 797;3 628,683.7

S0l*3

.* : ~*::

3,340.2 725,762.4 004.6 3,646.8 3,862.0 141,640.2 i#.*e 762,994.4 884;9 4,010.5 4,144.0 n3,595.5 906.4 783, 122.6 925.2 BACR Version 2 Pa e 74of133

ORIC ACID CONCENTRATION REDUCTION RT TECHNICAL BASES AND OPERATIONAL ANALYSIS Plant Cooldown from 547 "f to 200 "f AVERAGE SYSTEM PZR TEMPERATURE PRESS.

Ti TI "f

"f.

547 547 535 520 510 500 490 480 470 460 450 441 420 410 400 385 370 360 350 350 Add in RHRS 547 535 520 510 500 490 480 470 460 450 441 420 410 400 385 370 360 350 350 350 350 350 350 300 300 260 260 230 230 200 SPECIFIC VOLUME Vi Vf cu.ft./lbm cu.ft./lbm 0.02125 0.02125 0.02125 0.02092 0.02092 0.02055 0.02055 0.02031 0.02031 0.02009 0.02009 0.01989 0.01989 0.01969 0.01969 0.01951 0.01951 0.01933 0.01933 0.01916 0.01916 0.01901 TABLE 2-29 Salem Nuclear Generating Station BAT

3. 75 wt. % Boric Acid RWST 2500 Boric Acid SHRINKAGE BAT RWST B/A MASS VOLUME VOLUME ADDED lbm 0.0 0.0 311.2 0.0 369.9 0.0 237.2 0.0 227.1 0.0 210.8 0.0 215.1 0.0 202.9 0.0 201.2 0.0 193.5 0.0 166.6 1,172.7 141.7 543.1 65.6 494.1 59.7 774.0 93.5 711.3.

85.9 482.1 58.3 447.7 54.1 914.3 0.0 (669.4) 0.0 0.0 0.0 2,589.9 312.9 1,817.6 219.6 1,254.9 151.6 1,127.8 136.3 I TOTAL BAT VOLUME= 7, 197.4 GALLONS I 70 "f 70 "f CEN-REV. 00 TOTAL TOTAL FINAL B/A SYS. MASS CONC.

lbm 0.0 311.2 681.2 918.4 1,145.5 1,356.4 1,571.5 1,774.4 1,975.6 2,169.0 2,335.6 2,477.3 2,542.9 2,602.6 2,696.1 2,782.1 2,840.3 2,894.4 2,894.4 2,894.4 3,330.6 3,643.5 3,863.1 4,014.7 4,151.0 bm m boron

~~ ~ :~ illi:il:!*:1::!1!:1:::!l*::*.::::1:::::::::*1~~~:#

545,476.3 ::::u::*,*:

• x.>21aia 551,ao2.1

• • * *29ro 557,859.4 *.. *..

. ~~Q 563,481.8 *.

1i~~

569,218.4

,~'.?

574,629.5

• • ' g~;~*

579,993.8

. 595~5 585, 152.6 648H 589,594.7

.~~?.;§ 599,504.2 604,092.9 :

608,268.4 614,808.5 620,818.7.

t:i.¥~

~:: :<

.*,. >~I~~

636,290.2 :.:: :.. *:

'7§.. 3 630,714.5 ';/:

. **ii).J.~

725,752.8 747,636.9 762,995.6 773,599.7 783,129.6

. ~~~*~

. ~~~;q aes;2 961.~~

926.7 BACR Version 2 Pa e 76of133

ORIC ACID CONCENTRATION REDUCTION TECHNICAL BASES AND OPERATIONAL ANAL:

TABLE 2-30 Salem Nuclear Generating Station Plant Cooldown from 547 "F to 200 "F BAT 3.8125 wt.% Boric Acid AVERAGE SYSTEM PZR TEMPERATURE PRESS.

TI Tf "F

547 547 535 520 510 500 490 480 470 460 450 445 420 410 400 385 370 360 350 350 "F

Add in RHRS 547 535 520 510 500 490 480 470 460 450 445 420 410 400 385 370 360 350 350 350 350 350 350 300 260 230 300 260 230 200 sia 2250 350 350 0.01707 0.01683 0.01683 0.01662 RWST 2500 SHRINKAGE BAT MASS VOLUME lbm 0.0 10,452.5 9,393.6 0.0 0.0

[TOTAL BAT VOLUME= 6,968.3 GALLONS I Boric Acid RWST B/A.

VOLUME ADDED lbm 0.0 0.0 316.6 0.0 376.4 0.0 241.4 0.0 231.1 0.0 214.5 0.0 218.8 0.0 206.4 0.0 204.6 0.0 196.8 0.0 93.8 1,401.8 169.4 543.1 65.6 494.1 59.7 774.0 93.5 711.3 85.9 482.1 58.3 447.7 54.1 '

914.3 0.0 (669.4) 0.0 0.0 0.0 2,589.9 312.9 1,817.6 219.6 1,254.9 151.6 1,127.8 136.3 70 "F 70 "F TOTAL TOTAL FINAL CONC.

B/A SYS. MftSS lbm 0.0 316.6 693.0 934.3 1,165.4 1,379.9 1,598.7 1,005.2 2,009.8 2,206.6 2,~.4 2,469.8 2,535.4 2,595.1 2,688.7 2,n4.6 2,832.9 2,886.9 2,886.9 2,886.9 3,322.0 3,634.9 3,854.5 4,006.1 4,142.4 bm mboron E:E:!

1

'~

1rll

~~::::~ ) < :< : l;i 569,245.6 491.0 574,660.2

' ~~;~

580,028.o ******

• • • • • $:>s~a 585, 190.2 659.3 587,651.3 599,496.7 604,085.4 608,260.9 614,801.1 620,811.3 ', '

624,885.1 628,667.8 636,282.7 '

630,707.0 725,744.2 747,628.3 762,987.0 n3,591.1 783,121.0

~.4 7fp.3 733~8

' ' 764lli 784.4 79is

.* I~I aso.o.

. aaa.2 sos.4 924~a BACR Velliion 2 Pa e 77of133

RIC ACID CONCENTRATION REDUCTION ECHNICAL BASES AND OPERATIONAL ANAL TABLE 2-31 Salem Nuclear Generating Station Plant Cooldown from BAT 3.875 wt. % Boric Acid 547 "F to 200 "F RWST 2500 Boric Acid AVERAGE SYSTEM PZR SPECIFIC SHRINKAGE BAT RWST B/A TEMPERATURE PRESS.

VOLUME MASS VOLUME VOLUME ADDED Ti Tf VI Vf "F

"F ia cu.ft./lbm cu.ft./lbm lbm lbm 547 547 2250 0.02125 0.02125 0.0 0.0 547 535 2250 0.02125 0.02092 7,988.2 959.1 0.0 322.0 535 520 2250 0.02092 0.02055 9,495.2 1,140.0 0.0 382.8 520 510 2250 0.02055 0.02031 6,089.2 731.1 0.0 245.5 510 500 2250 0.02031 0.02009 5,829.6 699.9 0.0 235.0 500 490 2250 0.02009 0.01989 5,411.5 649.7 0.0 218.2 490 480 2250 0.01989 0.01969 5,521.5 662.9 0.0 222.6 480 470 2250 0.01969 0.01951 5,208.2 625.3 0.0 210.0 470 460 2250 0.01951 0.01933 5,163.1 619.9 0.0 208.1 460 448 2250 0.01933 0.01912 5,909.9 709.6 0.0 238.2 448 435 2250 0.01912 0.01892 6,141.8 0.0 737.4 89.1 435 420 2250 0.01892 0.01869 6,956.9 0.0 835.3 100.9 420 410 2250 0.01869 0.01855 4,523.1 0.0 543.1 65.6 410 400 2250 0.01855 0.01842 4, 115.8 0.0 494.1 59.7 400 385 2250 0.01842 0.01822 6,446.7 0.0 774.0 93.5 385 370 2250 0.01822 0.01804 5,924.2 0.0 711.3 85.9.

370 360 2250 0.01804 0.01792 4,015.6 0.0 482.1 58.3 360 350 2250 0.01792 0.01781 3,728.5 o~o 447.7 54.1 350 350 350 0.02698 0.01912 7,614.9 0.0 914.3 0.0 350 350 350 0.01781 0.01797 (5,575.7 0.0 (669.4) 0.0 Add in RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

350 350 350 0.01797 0.01797 0.0 0.0 0.0 0.0 350 300 350 0.01797 0.01743 21,571.2 0.0 2,589.9 312.9 300 260 350 0.01743 0.01707 15,139.0 0.0 1,817.6 219.6 260 230 350 0.01707 0.01683 10,452.5 0.0 1,254.9 151.6 230 200 350 0.01683 0.01662 9,393.6 0.0-1,127.8 136.3

[TQTAL BAT VOLUME= 6,797.5 GALLONS I 70 "F 70 "F TOTAL TOTAL FINAL B/A SYS.M.ASS CONC.

lbm lbm m boron 0.0 527,311.7

• • • • .*.. *****' * *o.o 322.0 535,622.0 105.1 704.8 545,499.9

.::,,~,9 950.3 551,834.5 301.1 1,185.3 557,899.1

• • • • • • • • *.,.!:i*i!!

1!!ili!

1,403.4 563,528.8 *'.*

1,626.0 569,272.9

.... \\:~B;~

1,835.9 574,691.0 2,044.1 580,062.3

. )'616;1 2,282.3 586,210.5

• . ~00*7 2,371.4 592,441.4.

< ~~;f:J 2,472.3 599,499.2:

. 721;0 2,538.0 604,087.9 1a'4'.5 2,597.7 608,263.4 746.6 2,691.2 614,803.6 7~.3 2,m.1 620,813.8 782~1 2,835.4 624,887.7 10s.a 2,889.5 628,670.3 8~.6 2,889.5 636,285.2

.7Qa.9 2,889.5 630,709.5 801.0 3,324.9 725,747.1 8(1j.O 3,637.8 747,631.2 850.7 3,857.4 762,989.9 883.9 4,009.0 773,594.0 906.1 4,145.3 783,123.9 925.4 BACR Vclliion 2 Pa e 78of133

ORIC ACID CONCENTRATION REDUCTION TECHNICAL BASES AND OPERATIONAL ANA TABLE 2-32 Salem Nuclear Generating Station Plant Cooldown from 547 "F to 200 'f BAT 3.9375 wt. % Boric Acid RWST 2500 Boric Acid AVERAGE SYSTEM PZR TEMPERATURE PRESS.

SPECIFIC VOLUME SHRINKAGE BAT RWST B/A MASS VOLUME VOLUME ADDED Ti Tf

'f "F

547 547 535 520 510 500 490 480 470 460 452 435 420 410 400 385 370 360 350 350 Add in RHRS 547 535 520 510 500 490 480 470 460 452 435 420 410 400 385 370 360 350 350 350 350 350 350 300 300 260 230 260 230 200 Vi Vf ia cu.ft./lbm cu.ft./lbm lbm 2250 0.02125 0.02125 0.0 2250 0.02125 0.02092 7,988.2 959.1 2250 0.02092 0.02055 9,495.2 1, 140.0 2250 0.02055 0.02031 6,089.2 731.1 2250 0.02031 0.02009 5,829.6 699.9 2250 0.02009 0.01989 5,411.5 649.7 2250 0.01989 0.01969 5,521.5 662.9 2250 0.01969 0.01951 5,208.2 625.3 2250 0.01951 0.01933 5,163.1 619.9 2250 0.01933 0.01919 3,965.3 476.1 2250 0.01919 0.01892 8,086.5 0.0 2250 0.01892 0.01869 6,956.9 0.0 2250 0.01869 0.01855 4,523.1 0.0 2250

. 0.01855 0.01842 4,115.8 0.0 2250 0.01842 0.01822 6,446.7 0.0 2250 0.01822 0.01804 5,924.2 0.0 2250 0.01804 0.01792 4,015.6 0.0 2250 0.01792 0.01781

'3,728.5 0.0 350 0.02698 0.01912 7,614.9 0.0 350 0.01781 0.01797 (5,575.

0.0 VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

350 0.01797 0.01797 0.0 0.0 350 0.01797 0.01743 21,571.2 0.0 350 0.01743 0.01707 15,139.0 0.0 350 0.01707 0.01683 10,452.5 0.0 350 0.01683 0.01662 9,393.6 0.0

[TOTAL BAT VOLUME = 6,564.0 GALLONS [

0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 970.9 835.3 543.1 494.1 774.0 711.3 482.1 447.7 914.3 (669.4) 0.0 2,589.9 1,817.6 1,254.9 1,127.8 lbm 0.0 327.4 389.2 249.6 238.9 221.8 226.3 213.5 211.6 162.5 117.3 100.9 65.6 59.7 93.5 85.9 58.3 54.1 0.0 0.0 0.0 312.9 219.6 151.6 136.3 70 "F 70 "F TOTAL TOTAL FINAL CONC.

B/A SYS. MASS lbm 0.0 327.4 716.6 966.2 1,205.2 1,427.0 1,653.3 1,866.8 2,078.4 2,240.9 2,358.2 2,459.2 2,524.8 2,584.5 2,678.0 2,763.9 2,822.2 2,876.3 2,876.3 2,876.3 3,319.7 3,622.6 3,842.2 3,993.9 4,130.1 lbm m boron 527,311.7 w'."

,. )Q;Q 535,627.4

. 1(.)6.9 545,511.7 2.29.1 551,850.5

~~1 557,919.0

&tk/i 563,552.4

. ~gi?

569,:IXl.2

~pt;?

574,721.9

... 567~9

.. II 580,096.6 584,224.4 592,428.2 599,486.0 604,074.7 608,250.2 614,790.4 620,800.6 624,874.5 628,657.1 636,272.1 630,696.4 725,731.9 747,616.1 762,974.7 773,578.8 783,108.7 31?:lg Z§P:/{

742~9 761.6 7fa:4 789.6 799~9

<,z9.Q;3 197.3

• 797;3 647.2 aao.4 902.6 922.1 BACR Version 2 Pa e 79of133

bRIC ACID CONCENTRATION REDUCTION RT TECHNICAL BASES AND OPERATIONAL ANAL SIS TABLE 2-33 Salem Nuclear Generating Station Plant Cooldown from 547 °F to 200 °F BAT 4.0 wt.% Boric Acid RWST 2500 Boric Acid AVERAGE SYSTEM PZR TEMPERATURE PRESS.

SPECIFIC VOLUME SHRINKAGE BAT RWST B/A M~S VOLUME VOLUME ADDED Ti Tf

°F 547 547 535 520 510 500 490 480 470 454 450 435 420 410 400 385 370 360 350 350

°F Add in AHAS 547 535 520 510.

500 490 480 470 454 450 435 420 410 400 385 370 360 350 350 350 350 350 350 300 300 260 260 230 230 200 Vi Vf la cu.ft./lbm cu.ft./lbm lbm 2250 0.02125 0.02125 0.0 2250 0.02125 0.02092 7,988.2 2250 0.02092 0.02055 9,495.2 1, 140.0 2250 0.02055 0.02031 6,089.2 731.1 2250 0.02031 0.02009 5,829.6 699.9 2250 0.02009 0.01989 5,411.5 649.7 2250 0.01989 0.01969 5,521.5 662.9 2250 0.01969 0.01951 5,208.2 625.3 2250 0.01951 0.01922 8,131.8 976.3 2250 0.01922 0.01916 1,996.7 0.0 2250 0.01916 0.01892 7,086.4 0.0 2250 0.01892 0.01869 6,956.9 0.0 2250 0.01869 0.01855 4,SZ3.1 0.0 2250 0.01855 0.01842 4,115.8 0.0 2250 0.01842 0.01822 6,446.7 0.0 2250 0.01822 0.01804 5,924.2 0.0 2250 0.01804 0.01792

. 4,015.6.

0.0 2250 0.01792 0.01781 3,728.5 0.0 350 0.02698 0.01912 7,614.9 0.0 350 0.01781 0.01797 (5,575.7 0.0 VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

350 0.01797 0.01797 0.0 0.0 350 0.01797 0.01743 21,571.2 0.0 350 0.01743 0.01707 15,139.0 0.0 350 0.01707 0.01683 10,452.5 0.0 350 0.01683 0.01662 9,393.6 0.0 I TOTAL BAT VOLUME= 6,444.3 GALLONS I lbm 0.0 0.0 332.8 0.0 395.6 0.0 253.7 0.0 242.9 0.0 225.5 0.0 230.1 0.0 217.0 0.0 338.8 239.7 29.0 850.8 102.8 835.3 100.9 543.1 65.6 494.1 59.7 774.0 93.5 711.3 85.9 482.1 58.3 447.7 54.1 914.3 0.0 (669.4) 0.0 0.0 0.0 2,589.9 312.9 1,817.6 219.6 1,254.9 151.6 1,127.8 136.3 70 °F 70 °F CEN-REV. 00 TOTAL TOTAL FINAL CONC.

BIA SYS. M~S lbm lbm m boron 0.0 332.8 728.5 982.2 1,225.1 1,450.6 1,680.6 1,897.6 2,236.5 2,3>5.4 s2:1.a11.1

• .* *. **. = =*=... *:=:=.::**.:*'.*=:=*o~o EI!: {$' x;lf 557,939.0 >

!\\!!fili!:

~:~i,,\\' \\'.ill 2,368.2 592,438.2 E>9l:J;$

2,469.1 599,496.0

..720. {

2,534.8 604,084.7 733.6 2,594.5 608,a>0.2 745.7 2,688.0 2,n3.9 614,800.4

. 764.4 620,810.6 181.2 2,832.2 624,884.5 7Q2.4

. 2,886.3 628,667.1 802.7 2,886.3 2,886.3 636,282.1 793.1 630,706.3 ado.1 3,321.2 725,743.4 BQC.l.1 3,634.1 747,6Zl.5

• . ai9.8 3,853.7 4,005.4 762,986.2 883.1 773,590.3 9QS.2 4,141.6 783, 120.2 924.6 BACR Version 2 Pa e 80of133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS Table 2-34 Minimum Boration Volume vs.

Stored Boric Acid Concentration for Modes 1, 2, 3, and 4 - Equilibrium Xenon EOL Case Minimum Volume (gallons>

BAT COHC.

BAT COHC.

RWST RWST RWST RWST (ppa (wt%

COHC.

COHC.

COHC.

COHC.

Boron)

Boric Acid) 2300 ppa 2350 ppm 2400 ppm 2450 ppm 6560 3.75 7,704.0 7,591.2 7,478.7 7,310.7 6668 3.8125 7,478.7 7,366.6

• 1,254.9 7,140.0 6775 3.875 7,254.9 7,197.4 7,082.7 6,911.3 6883 3.9375 7, 140.0 6,968.3 6,854.3 6,740.7 6990 4.00 6,968.3 6,797.5 6,684.1 6,564.0 CEN-606 REV. 00 RWST COHC.

2500 ppm 7,197.4 6,968.3 6,797.5 6,564.0 6,444.3 ABB Combustion Engineering Nuclear Services Page 81 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS Table 2-35 CEN-606 REV. 00 Minimum Volume Stored in Boric Acid Tank BAT COHC.

(ppm Boron) 6560 6668 6775 6883 6990 vs.

Stored Boric Acid Concentration for Modes 1, 2, 3, and 4 Minimum stored Volume (Gallons>*

BAT COHC.

RWST RWST RWST (wt.%

COHC.

CONC.

COHC.

Boric Acid) 2300 ppm 2350 ppm 2400 ppm 3.75 7,850 7,700 7,600 3.8125 7,600 7,500 7,400 3.875 7,400 7,300 7,200 3.9375 7,250 7,100 7,000 4.0 7,100 6,900 6,800 RWST RWST COHC.

CONC.

2450 ppm 2500 ppm 7,450 7,300 7,250 7' 100 7,050 6,900 6,850 6,700 6,700 6,550

• Stored BAT Volume equal to Boration Volume from Table 2-34, plus 100 gallons for conservatism, rounded up to the nearest 50 gallons.

ABB Combustion Engineering Nuclear Services Page 82 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS Table 2-36 Required Boron Concentration for a Cooldown From 54 7°f to 200°F Peak Xenon Scenario Temperature EOL + 140 Of Concentration (ppm boron) 547

-107.2 537

-65.8 627

• 8.1 517 42.7 507 93.2 497 136.8 487 183.8 477 230.9 467 267.3 457 310.7 447 347.0 437 386.9 427 426.0 417 469.0 407 495.0 397 526.8 387 560.1 377 592.7 367 621.3 357 651.6 347 678.7 337 708.8 327 734.2 317 758.8 307 784.4 297 807.8 287 831.7 277 855.2 267 878.2 257 900.7 247 918.9 237 940.0 227 960.6 217 978.8 207 996.1 200 1013.0 200111 1033.9 111 After Shutdown Margin Change from 1.6\\ l!ik/k to 1.0\\ l!ik/k CEN-606 REV. 00 ABB Combustion Engineering Nuclear Services Pag~ 83 of 133

ORIC ACID CONCENTRATION REDUCTION RT TECHNICAL BASES AND OPERATIONAL ANAL: SIS Plant Cooldown from 547 "F to 200 "F AVERAGE SYSTEM PZR TEMPERATURE PRESS.

Ti Tf SPECIFIC VOLUME Vi TABLE 2-37 Salem Nuclear Generating Station - Peak Xenon Case BAT

3. 75 wt. % Boric Acid 70 "F RWST 2300 Boric Acid 70 "F SHRINKAGE BAT RWST B/A TOTAL TOTAL MASS VOLUME VOLUME ADDED B/A SYS. MASS Vf FINAL CONC.

cu.ft./lbm cu.ft./lbm lbm lbm lbm l>m m boron 547 547 2250 0.02125 0.02125 0.0 0.0 0.0 547 535 2250 0.02125 0.02092 7,988.2 959.1 0.0 535 520 2250.

0.02092 0.02055 9,495.2 1, 140.0 0.0 520 510 2250 0.02055 0.02031 6,089.2 731.1 0.0 510 500 2250 0.02031 0.02009 5,829.6 699.9 0.0 500 490 2250 0.02009 0.01989 5,411.5 649.7 0.0 490 480 2250 0.01989 0.01969 5,521.5 662.9 0.0 480 470 2250 0.01969 0.01951*

5,318.2 625.3 0.0 470 460 2250 0.01951 0.01933 5,163.1 619.9 0.0 460 450 2250 0.01933 0.01916 4,965.4 596.2 0.0 450 435 2250 0.01916 0.01892 7,086.4 850.8 0.0 435 420 2250 0.01892 0.01869 6,956.9 835.3 0.0 420 410 2250 0.01869 0.01855 4,523.1 543.1 0.0 410 400 2250 0.01855 0.01842 4,115.8 494.1 0.0 400 393 2250 0.01842 0.01832 3,141.3 377.1 0.0 393 380 2250 0.01832 0.01816 5,267.1 0.0 632.4 380 360 2250 0.01816 0.01792 7,978.2 0.0 957.9 360 350 2250 0.01192 0.01101 a;120.5 o.o 447.7 350 350

. 350 0.02698 0.01912 7,614.9 0.0 914.3 350 350 350 0.01781 0.01797 (5,575.7) 0.0 (669.4)

Add in RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

350 350 350 0.01797 0.01797 0.0 0.0 0.0 350 300 350 0.01797 0.01743 21,571.2 0.0 2,589.9 300 260 350 0.01743 0.01707 15,139.0 0.0 1,817.6 260 230 350 0.01707 0.01683 10,452.5 0.0 1,254.9 230 200 350 0.01683 0.01662 9,393.6 0.0 1, 127.8 I TOTAL BAT VOLUME= 9,784.5 GALLONS I 0.0 0.0 311.2 311.2 369.9 681.2 237.2 918.4 227.1 1,145.5 210.8 1,3.56.4 215.1 1,571.5 202.9 1,774.4 201.2 1,975.6 193.5 2,169.0 276.1 2,445.1 271.0 2,716.2 176.2 2,892.4 160.4 3,052.7 122.4 3,175.1 70.2 3,245.3 106.4 3,3.51.7 49.7 3,401.4 0.0 3,401.4 0.0 3,401.4 0.0 3,913.9 287.6 4,311.5 201.8 4,403.3 139.3 4,542.7 125.2 4,667.9 726,336.1 748,194.9 763,535.8 774,127.6 783,646.4 876.8 907.1.

919.1 937.0

• • • • 945.2 9&.9 9.42.1 a42.1 9p1.8 1,008.3 1,025.9 1041.4 BACR Version 2 Pa e 84of133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 Table 2-38 Calculation of the 73,800 Gallon RWST Volume In Bases Section 3/4. 1.2 24,375.0 gallons System Feed-and-Bleed (Part D) 12,067.3 gallons Cooldown to 350°F and 350 psi a (Part A) 6,790.3 gallons Cooldown to 200°F on RHRS (Part C) 43,232.6 gallons Total 44,000.0 gallons Final Volume Rounded up to the nearest 1000 gallons 21,210.0 gallons Volume adjustment due to instrument tap location 8,550.0 gallons Volume adjustment due to instrumentation uncertainties 73,800.0 gallons Total volume required for cooldown using RWST only ABB Combustion Engineering Nuclear Services Page 85 of 1 33

BORZC ACZD CONCENTRATZON REDUCTZON EFFORT TECHNZCAL BASES AND OPERATZONAL ANALYSZS CEN-606 REV. 00 Table 2-39 Calculation of the 41,800 Gallon Volume In Bases Section 3/4.1.2 12,067.3 gallons cooldown to 350°F and 350 psia (Part A) 6,790.3 gallons Cool down to 200°F on RHRS (Parts B and C)

(6,968.3) gallons Smallest BAT Inventory for 2300 ppm Boron RWST (from Table 2-13) 11,889.3 gallons Total 12,000.0 gallons Total, Rounded up to Nearest 1,000 gallons 21,210.0 gallons Volume adjustment due to instrument tap location 8,550.0 gallons Volume adjustment due to instrumentation uncertainties in 41,800.0 qallons Total RWST volume required when minimum BAT volume is used ABB Combustion Engineering Nuclear Services Page, 86 of 1 33

BORIC ACID CONCEKTRATION REDUCTION EFFORT CEN-606 TECHNICAL BABBS AND OPERATIONAL ANALYSIS REV. 00 0

u

<(

FIGURE 2-1 SALEM UNITS 1 & 2 SOLUBILITY OF BORIC ACID IN WATER 20.--~~~~~~~~~~~~~~~~~~~---.

u 15 0:

0 m z

0 r

<(

0:

r z w

u z 0 u

. INSOLUBLE 10 SOLUBLE 5

0 L--~~~~--'-~~~~__._~~~~---""--~~~~

0 50 100 150 ABB Combustion Engineering Nuclear Services Pag~ 87 of 133

BORXC ACZD CONCEN'l'RATXOH REDUCTXON EFFORT TECIDIZCAL BASES ARD OPERATXOHAL AHALYSXS CEN-606 REV. 00 z

0 II 0

([)

E Q.

Q.

z 0

I-

<{

II I-z w u z 0 u z

0 II 0

([)

0 w a:

) a w

II FIGURE 2-2 SALEM UNITS 1 ANO 2 REQUIRED BORON CONCENTRATION FOR PLANT COOLOOWN 1,000 800 600 400 200 o

(200) 600 500 400 300 RCS iEMPERATURE 200 "F

ABB Combustion Engineering Nuclear Services Page, 88 of 133

BORXC ACXD CONCEBTRATXOH REDUCTION EFFORT TBCBBXCAL BABBS ABD OPERATIONAL ANALYSIS CEN-606 REV. 00.

z 0

0:

0 m E

Q.

Q.

z 0

1-

<I:

0:

1-z w

u z 0 u (f) u 0:

. FIGURE 2-3 EOL SALEM -

MODES 5 & 6 COOLDOWN -

200"F TO 135"F INITIAL FEED-&-BLEED FROM RWST @ 2300 ppm BORON 1000 FEED-&-BLEED FROM RWST 4500 GALLONS INCREASE CONCENTRATION 893.9 ppm TO 960 ppm 980

.. c.r:-.~r.... :i:~.~!-:i;:.~.. ?.-: ~. ~.. ?:-: ~).......

/<

/

)<.

/

960

............... ***.*************************************7~.-:.....................

I'

/

///

940

-......................................... /'"....................................

920 900 880 220 I'

I' I'

/

I' I' x I'

I' I'

I'

.............. *.-*************X*************************************************

I' I'

I',,

/

EQUILIBRIUM XENON x

I' I'

I'

• • • • • • • • • • • • • • ***/***************************************************************

/

I' 200 180 160 140 RCS TEMPERATURE -

.F ACTUAL CONC.

0 REQUIRED CONC.

• ---7+'.----

120 ABB Combustion Engineering Nuclear Services.

Page 89 of 1 33

BORIC ACID COHCEHTRATIOH REDUCTION EFFORT TECHNICAL BABBS AND OPERATIONAL ANALYSIS CEN-606 REV. 00 z

0 0:

0 m E

Q.

Q.

z 0

I-

<(

0:

I-z w

u z 0 u rJ).

u 0:

FIGURE 2-4 EOL SALEM -

MODE S COOLDOWN -

200 *F TO 135 *F MAKEUP FROM BAT@ 3.75 wt% BORIC ACID 1, 040 1,020 1000 980 960 940 920 900 880 220

)<

/

• ..*.*.**...... ).I' *.......*........*.......

/.X.

, x/.

• • • • • • ....*.*.*.***...**..*......**.*.....*..,.t'........................................

/

,/

/

/ x,,

........................ ******X*****************************************************

/

/

/

/

.,/'.

,,,"/

(ref. TABLES 2-3 & 2-6) 200 180 160 140 RCS TEMPERATURE -

.F ACTUAL CONC.

0 REQUIRED CONC.

• ---)f---*

120

• ABB Combustion Engineering Nuclear Services Page, 90 of 1 33

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSIS REV. 00 z

0 CI 0

CD E

0..

.Q_

z 0

I-

<(

CI 1-z w u z 0 u en u

CI 1~000

• BOO 600 400 200 0

FIGURE 2 EOL SALEM NUCLEAR GENERATING STATION -

UNITS 1 & 2 MODES 1 THROUGH 4 COOLDOWN -

EQUILIBRIUM XENON

• • • • • • • • • • • • • • • • • • ' **.*********.***********************.,,,f ***********************...**..

/

/ "

/

/

/

/

/-

....................... ***************/*************************************************

I I

I I

I I

I I

I "

I I

I I

I

/

I I

I I,.

I I

I I I I

I I

I I

RWST ~ 2300 ppm BORON BAT@ 3.75 wt% BORIC ACID (ref. TABLES 2-7 & 2-9)

........... ****/****...................................................................

I I

I I I

/

I I I

I I I I

I 600 500 400 300 200 100 RCS TEMPERATURE -

"F ACTUAL CONC.

REQUIRED CONC.

ABB Combustion Engineering Nuclear Services Page 91 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 U1 z 0

_J

_J

<{

~

I-

<{

CD 2

0 CI LL w

2

J

_J 0 >

z 0

I-

<{

CI 0

CD 7.,800 7.,600 7.,400 7.,200 7.,000 6.,800 6... 600 6.,400 FIGURE 2-6 SALEM NUCLEAR GENERATING STATION UNITS 1 & 2 BORATION VOLUME vs CONCENTRATION IN BAT 0

I o

0 0

I o

REGION OF ACCEPTABLE OPERATION ;

0 I

I o

0 I

I o

(

i******~,******1* *******1*****.. **1**********:**********:**********:**********:**********

... ~><..... ~~L........ :......... :..........:..........:.......... :.......... :..........

x :

~ ~

,,,, : ',L

~

.,:_~-.. :*....... '~~-....... :*"""... :........ :**....... :*........ *:*........ *:*.........

. ~'

.. ~..

\\_'II,,

'(

... '...... ;. ::*:":-,... ;...... ~~=--~-........ ~. ~ ~:... ~....... ~......... ~....................

/ ' :

... :... ~..,....... ;..... :---..,. !......... ;

'":--,~....,... ~... ~... -~......... ~......... :.........

.... ~ : ' :

........ ~...... ><........ ~... '>:-.... ;......... ~~:-,,.... ;. :"-.-';:... i.......... :........

~:~

'.. ~

x :

~

-~.

,*

• .:_~........ ~:-,.~.... ~... :-..,~:****"'"

'*, i

)('.

........ ~......... ~......... ~......... :... '!:-.~... :....... **~:.*...... :....,~~~-. :...... :,w(

CONC~NTRA T;I ON I N; RWST: :

...,~

• • • • • • • • +********+*********~;~g.~g:.... :*~* v:***'.... '..'>'.**,<****;>>~... ~:;

2400 ppm

.......... :.......... :......... -~~?Do*.~~-~-.. ~.~\\

........ ~........ >*~.........

.::SD ppm ~

.)k:.

6560 p*pm 4

.c~ :.?~.:.w~.~J... :..

'/

6.,600 6., 700 6,800 6.,900 7,000 CONCENTRATlnN IN BAT ppm BORON ABB Combustion Engineering Nuclear Services Page 92 of 133

BORXC ACXD COBCENTRATXOB REDOCTZOB EFFORT TBCJUD:CAL BABBS Alm OPBRATXOBAL ABALYSXS CEB-606 REV. 00

(/)

z 0

_J

_J

<t:

(.'.)

I-

<t:

CD

~

0 CI LL w

~

J

_J 0 >

0 w CI 0 I-(/)

0 w CI -:J 0 w CI 7,600 7,400 7,200 7,000 6,800 6.. 600 FIGURE 2-7 SALEM NUCLEAR GENERATING STATION UNITS*1 & 2 BAT STORED VOLUME REQUIRED vs. BAT CONCENTRATION

~.......... *......... *,*........ *..........

REGION OF A~CEPTABLE OPERATION

--- pS60 PP.m

...... ( 3.. 7.S..,.Yt9.6).... ;...

~ -........

~........ *:*,._......

6.. 600 6, 700 6,800 6,900

~*

7.. OIJG

. CONCENTRA T 11JN I N BAT ppm BORON ABB Combustion Engineering Nuclear Services Page 93 of 133

BORXC ACXD CONCENTRATION REDUCTXON EFFORT TECBHXCAL BABBS ARD OPERATIONAL ANALYSIS 3.0 OPERATIQNAL ANALYSIS

3.1 INTRODUCTION

TO THE OPERATIONAL ANALYSIS CEN-606 REV. 00 The results of the evaluation performed to demonstrate the general impact on plant operations of a reduction in the boron concentration in the BATs are presented in this section.

The specific areas discussed include (1) operator response to emergency situations, (2) typical plant feed-and-bleed operations, (3) typical plant blended makeup operations, (4) plant shutdown to refueling, and (5) plant shutdown to cold shutdown.

Since it would be impossible to evaluate each of these five areas while considering all possible combinations of plant conditions, conservative initial plant parameters and analysis assumptions were selected for use in the analyses which would lead-to "worst case" results.

As a consequence, the results, i.e., the volumes and final concentrations that were obtained, will in general be bounding for any event or any set of initial plant-conditions.

3.2 RESPONSE TO EMERGENCY SITUATIONS Several operating evolutions which may have to be performed in response to a variety of emergency situations are discussed in this section.

Accident boration requirements, shutdown margin recovery, and emergency boration have been evaluated, and the findings are reported in the following paragraphs.

This discussion includes an explanation of the manner in which the plant operating staff can continue to operate Salem Units 1 & 2 safely with a r~duction in the boron concentration in the solution stored in the BATs.

ABB Combustion Engineering Nuclear Services Page 95 of 133

BORXC ACXD CONCENTRATXON REDUCTXON EFFORT TECHNXCAL BASES AND OPERATXONAL ANALYSXS CEN-606 REV. 00 3.2.1 Accident Boration Requirements During the feasibility study, the plant Accident Analyses in Chapter 15 of the Updated Final Safety Analysis Report (UFSAR) were reviewed.

In the UFSAR, no mention is made of boric acid addition to the RCS from the BATs.

During safety injection, the charging pumps are aligned to the RWST for reactivity control.

Accordingly, the immediate consequences of such events as the steam line break, overcooling, boron dilution, etc., will not be affected by the reduction in the concentration of boron in the BATs.

A generic concern exists regarding a potential return to criticality during the cooldown following a Main steam Line Break (MSLB) or a Steam Generator TUbe Rupture (SGTR) event.

Following is a list of plant instructions and procedures which instruct the operator, either directly or by reference, to maintain shutdown margin by boration either from the RWST or the BAT.

With the reduction in concentration in the BATs, it will be necessary to revise the required BAT volumes.

With a minimum concentration of 3~75 wt% boric acid, the new required volumes will be 3.2 times greater than the present requirements.

Sl.OP-SO.CVC-0006(Q) Boron Concentration Control OP-AB.SG-OOOl(Q)

EOP-SGTR 1 EOP-SGTR 2 EOP-SGTR 3 EOP-SGTR 4 EOP-LOCA 2 EOP-FRSM 2 Steam Generator Tube Leak Steam Generator Tube Rupture Post-SGTR Cooldown SGTR with LOCA, Subcooled Recovery SGTR with LOCA, Saturated Recovery Post-LOCA Cooldown with Depressurization Response to Loss of Core Shutdown ABB Combustion Engineering Nuclear Services Page 96 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS EOP-LOSC 1 EOP-LOSC 2 Loss of Secondary Coolant Multiple Steam Generator Depressurization CEN-606 REV. 00 EOP-TRIP-5 Natural Circulation Cooldown without RVLIS During an MSLB, plant procedures and instructions also direct the operating personnel to borate the RCS to maintain shutdown margin.

With the reduction in BAT concentration, it will also be necessary to revise the requirements for stored volume in the BATs, as in the case of the SGTR discussed above.

3.2.2 Shutdown Margin Recovery In the event that the required shutdown margin is lost, the action statements associated with Technical Specifications 3.1.1, 3.1.2, 3.9.1, and 3.10.1 require that boration be initiated immediately.

In Technical surveillance Requirement 4.1.2.2, verification is required that a flow rate of 10 gpm is provided by the boration system flow path from the BATs to the RCS.

This requirement is discussed in detail in Section 2 of this report.

The reduction in boric acid concentration in the BATs necessitates a revision to the TSR, increasing the flow rate requirement from 10 gpm to 33 gpm

• ABB Combustion Engineering Nuclear Services Pag~ 97 of 133

BORZC.a.c~D co*cl31'EtA~IOW RBDUC'!IOR BJTOR~

'l'BCBXXQL BUBS AND OPBRA1'IODL ADLYSI.&

3.2.3 Bmergency Boration CDl'-50&

azv. oo The main !low path for emergency boration runs from the boric acid transfer pumps directly to the charqinq pump suction, via emergency flow control valv*, 1(2)-CV-175.

These flow control valves and the tlow path are designed for a flow ot 150 gpm, the output of 2 boric acid transfer pumps.

The Salem Boron concentration Control Procedure, Sl.OP-so. cvc-0006 (Q), discusses the use of other ~low paths for emerqency boration.

Boric acid solution can be charged throuqh either the normal boration path (via 1(2)-CV-172 and 1(2)-CV-181). or the alt*rnate emergency boration path (via 1(2)-CV-172 and 1(2)-CV-174).

In the existing con~iquration, l-inch diameter piping has been used in these flow paths.

Should it be necessary to increase the system tlow capacity, the piping in the normal boration flow path to the charging pump suction may be replaced with 2-inch diameter piping.

Since the alternate emergency flow path is the third option, with limited usage, it is judqed that this piping may remain as 1-inch diameter.

Information is also provided regarding the volume(s) of boric acid required for boration when emergency boration is called for in response to a cooldown or in the event one or more Rod Cluster control Assemblies (RCCAs) are not fully inserted.

A listinq is provided of the required volumes of boric acid solution at a concentration of 20,000 ppm; volumes are provided as a function of RCS averaqe temperature ranqe.and as a function of the number of RCCAs not fully inserted.

At the new minimum concentration of solution in the BATs, 3.75 weight percent, it will be ABB Combustion Engineering Nuclear Services Page 98 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 necessary to revise th.e listing to increase the volumes of solution which must be maintained in the BATs by a factor of 3.2, i.e, the stored volume will be 3.2 times greater than the volumes currently listed.

3.3 FEED-AND-BLEED OPERATIONS During a feed-and-bleed operation performed to increase system boron concentration, the charging pumps are used to inject concentrated boric acid into the RCS, with the excess inventory normally being diverted to the liquid waste system via letdown.

The rate of increase in boron concentration at any given point in time is proportional to the difference between the system concentration and the concentration in the charging fluid.

The equation describing feed-and-bleed has been derived from this relationship; the equation and its derivation are presented in Appendix 1. It is axiomatic that, with a reduction in the boron concentration in the BATs to the point at which heat tracing is no longer required, the maximum rate of change of RCS boron concentration that can be achieved during feed-and-bleed will be less than is currently achievable.

The purpose of the evaluation described in this Section was to determine the rate of change in RCS boron concentration which may be achieved with a reduced concentration of boron in the BATs, using feed-and-bleed.

The analysis was performed assuming hot zero power conditions, with other key parameters and conditions as shown in Table 3-1.

Feed-and-bleed operation was analyzed with one and two charging pumps operating, and from initial boron concentrations in the RCS of zero ppm and 1000 ppm.

ABB Combustion Engineering Nuclear Services Page 99 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 The results are presented in Tables 3-2 through 3-5.

Equation 9.0 of Appendix 1 was used to generate the results in these tables.

The value of the system mass used to obtain the time constant in Equation 9.0 was calculated as follows:

(m )

+

w loops or

=

10,812 ft 3

+

500.0 ft 3

527 I 308

• 3 lbm From this system mass (527,308.3 lbm), the value of the feed-and-bleed time constant with one charging pump delivering 75 gpm is 4t75 =

527,308.3 lbm 75 gpm x 8. 329 lbmf gallon< 3 >

or

'f = 844. 13 minutes The value of the Feed-and-Bleed time constant with two charging pumps delivering 75 gpm each (total of 150 gpm} is (I)

(2)

(3)

Specific volume of compressed water @ 547°F and 2250 psia Specific volume of saturated water @ 2250 psia Density of water at 70°F ABB Combustion Engineering Nuclear Services Page 100 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 NOTE:

't" =

527,308.3 lbm 150 gpm x 8. 329 lbm/ gal or

't" 150 = 420. 07 minutes Use of 2 charging pumps is limited to Modes 1, 2, and 3 by TS 3.1.4.

The boron concentration required for the cases shown in Tables 3-2 through 3-5 are plotted in Figures 3-1 through 3-4 for comparison.

Note that even with reduced boric acid concentrations in the BATs, significant rates of increase in boron concentration in the RCS will still be achievable.

3.4 BLENDED MAKEUP OPERATIONS During typical plant blending operations, concentrated boric acid via 1{2)-CV-172 is mixed with demineralized water via 1{2)-CV-179 at the blending tee and then added to the volume control tank {VCT).

Since the ability to blend and add makeup to the RCS and to other systems is important to plant operations, two parametric studies were performed to demonstrate the effect of a reduction in boron concentration in the BAT.

The studies performed were as follows:

1.

Flow through 1{2)-CV-172 was varied between 2.0 gpm and 40.0 gpm while the flow through 1(2)-CV-179 is varied to give a total flow out of the blending tee of 75 gpm, through Flow Control Valve 1{2)-CV-181.

ABB Combustion Engineering Nuclear Services Pag~ 101 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00

2.

Flow through 1(2)-CV-172 is varied between 2.0 gpm and 40.0 gpm while the flow through 1(2)-CV-179 is varied to give a total flow out of the blending tee of 150 gpm, through Flow Control Valve 1(2)-CV-181.

In each of these studies, the temperature in both the BAT and the demineralized water supply was assumed to be 70°F, and boric acid concentrations of 3.75, 3.8125, 3.875, 3.9375, and 4.0 weight percent were considered.

The results are shown in Tables 3-6 and 3-7. The final concentration out of the blending tee in each of these tables was obtained using the following equation:

(FyxCr) (100) (1748.34)

(FY X Cy)

+

(Fout x D,.,)

In this equation, C00t is the boron concentration leaving the blending tee in ppm boron, FY is the f lowrate coming out of 1(2)-CV-172 in gallons per minute, CY is the boron concentration in the BATs lbm per gallon, F00t is the total flow leaving the blending tee in gpm, 011 is the density of water at 70°F in lbm per gallon, and 1748.34 is the conversion factor between concentration expressed in weight percent boric acid and concentration expressed in terms of ppm boron.

(See Appendix 3 for a derivation of this conversion factor).

The data contained in Tables 3-6 and 3-7 are plotted in Figures 3-5 and 3-6.

Note that following the reduction in BAT concentration, a full range of f lowrates and boron concentrations is available for blended makeup operations.

ABB Combustion Engineering Nuclear Services Pag~ 102 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS 3.5 SHUTDOWN TO REFUELING -

MODE 6 CEN-606 REV. 00 Shutdown to refueling conditions is normally the most limiting evolution that an operator must perform involving system boration, i.e., this evolution involves the addition of the maximum amount of boron to the RCS.

A shutdown to refueling normally occurs at the end of each fuel cycle, when the boron concentration for criticality is low, and an increase to the refueling boron concentration must be accomplished.

In the most limiting case, boron concentration must be raised from zero ppm to an assumed refueling concentration of 2300 ppm.

The results of the evaluation of plant shutdown to refueling conditions are discussed in this Section.

The evaluation

• was performed to demonstrate the effect on makeup inventory requirements of a reduction in BAT concentration.

A list of key parameters and conditions assumed in the analysis is contained in_Table 3-8.

The evaluation was performed for EOL conditions in order to maximize the amount of boron that must be added to the RCS.

Durini this transient, it is necessary to increase the boron concentration in the RCS from zero ppm to the assumed refueling concentration of 2300 ppm.

The shutdown for refueling was assumed to take place as follows:

1.

RCCAs are inserted to bring the reactor to hot zero power conditions.

2.

At time= o {following shutdown), feed-and-bleed is commenced, with one charging pump operating and taking suction from the BATs.

(Two cases were run, the first with the boron concentration in the BATs at 3.75 weight ABB Combustion Engineering Nuclear Services Pag~ 103 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 percent, the second with the concentration in the BATs at 4.00 weight percent).

3.

The feed-and-bleed operation is continued for 168 minutes for the first case (BATs at 3.75 weight percent) and for 107 minutes in the second (BATs at 4.0 weight percent).

4.

Plant cooldown and depressurization is commenced, taking the RCS from an average coolant temperature and system pressure of 547°F and 2250 psia, to a pressure of 350 psia and an average coolant temperature 5 350°F.

5.

The RHRS is aligned and placed in operation after the primary coolant is at 350 psia and the temperature has decreased below 350°F; the boron concentration in the RHRS is assumed to be equal to that in the RCS.

6.

Following alignment of the RHRS, plant cooldown is continued from 350°F to 135°F at.350 psia.

7.

Makeup inventory is supplied from the BATs.

The boric acid concentration as a function of temperature and the corresponding inventory required from the BATs as determined by the analysis are shown in Tables 3-9 and 3-10.

The coolant average temperature and boron concentration data from this table are plotted in Figures 3-7 and 3-8.

The boric acid concentration during the initial feed-and-bleed operation was calculated for each case using the methodology discussed in Section 3.3 above.

Concentration during the subsequent plant cooldown was calculated in the same manner as the concentration for the plant cooldown in Section 2.4.

ABB Combustion Engineering Nuclear Services Page 1 04 of 1 3 3

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASBS AND OPERATIONAL ANALYSIS CEN-606 REV. 00 Note that the boron content of the RCS was raised from zero ppm at the start of the evaluation to greater than 2300 ppm by the time the plant had been cooled and depressurized to 135°F and 350 psia.

A total volume of 29,962.6 gallons of 3.75 weight percent boric acid solution was required.

Of this volume,. 9,075.0 gallons were used during the initial 121 minute feed-and-bleed operation, and 20,887.6 gallons were charged into the RCS to compensate for coolant shrinkage during the cooldown.

For the 4.0 weight percent case, a total volume of 28,912.6 gallons was required.

Of this volume, 8,025.0 gallons were used during the 107 minute feed-and-bleed operation, and 20,887.6 gallons were charged.

to compensate for coolant contraction.

Each BAT contains a usable volume of approximately 7,500 gallons, defined as the volume between upper and lower level taps.

There are two BATs in each unit; thus the available volume from both tanks is approximately 15,000 gallons.

As shown in Table 3-10, the. volume of 4.0 weight percent boric acid solution required to conduct the shutdown to refueling operation is approximately 1.9 times the capacity of the BATs.

(With a boron concentration of 3.75 weight percent in the BATs, the volume required is 2.0 times the capacity of

.two BATs).

This result is conservative or bounding and thus represents the maximum volume that could be required, assuming a refueling concentration of 2300 ppm boron and the specified BAT concentration.

The stored volume of boric acid solution required by Technical Specifications 3.1.5 and 3.1.6 should be contained in one BAT for each Unit.

Since there are only two BATs for each Unit, with a combined capacity of approximately 15,000 gallons, additional provisions or operator action may be required in order to establish a Mode 6 condition in the plant.

ABB Combustion Engineering Nuclear Services Pag~ 105 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 These provisions could include some combination of the following:

1.

The initial plant feed-and-bleed and some portion of the plant cooldown may be performed using the RWST, decreasing the total inventory needed from the BATs.

2.

a.

Prior to commencing the evolution, both BATs are filled and are available for use*.

b.

During the initial phase of the cooldown, makeup may be taken from one BAT until depleted.

The.charging pumps may then be realigned to take suction from the second BAT for continued charging, and the first BAT may be replenished while cooldown is continued.

These provisions or operator actions would be necessary only once during each fuel cycle, just prior to the time a shutdown for refueling is to be performed.

These are relatively simple actions which may be planned in advance so as. to have no impact on maintenance activities or on the refueling schedule

• ABB Combustion Engineering Nuclear Services Pag~ 106 of 1 33

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS 3.6 SHUTDOWN TO COLD SHUTDOWN -

MODE 5 CEN-606 REV. 00 As discussed above, shutdown to refueling is the most limiting evolution that an operator must perform involving system boration.

That evolution is normally performed only once during each fuel cycle, just prior to refueling.

Conditions such as unscheduled plant maintenance may occur during a fuel cycle, however, which require that the plant be taken to cold shutdown conditions.

Although not limiting with respect to boration requirements, it is important to have the ability to perform such a shutdown quickly and efficiently.

The results of the evaluation of shutdown to cold shutdown are described in this section.

The analysis was performed to determine the effect on makeup inventory requirements of a reduction in BAT concentration.

A list of key parameters and conditions assumed in the analysis is contained in Table 3-11.

This evaluation was performed for EOL conditions, with an MTC of -44 and an assumed required cold shutdown boron concentration of 920.8 ppm boron.

The actual concentration required through most of cycle life will be lower, and the volume of boric acid actually required from the BATs will be significantly lower than those calculated herein.

The steps followed in reaching cold shutdown are as follows:

1.

RCCAs are inserted to bring the reactor to hot zero power conditions

• ABB Combustion Engineering Nuclear Services Pag~ 107 of 1 33

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00

2.

A plant cooldown and depressurization is initiated to reduce system pressure from 2250 to 350 psia and average coolant temperature from 547°F to a temperature

~350°F. Makeup inventory is supplied from the BATs.

3.

The RHRS is aligned and placed in operation at a pressure of 350 psia and a temperature ~350°F.

4.

After placing the RHRS in operation, plant cooldown is continued from 350°F to 200°F.

Makeup inventory is supplied from the BATs.

The results of the evaluation showing the system boron concentration as a function of temperature and the total BAT inventory requirements are given in Tables 3-12 and 3-13.

In both cases, the concentration in the RHRS was assumed to be equal to the concentration of the RCS at the time of RHRS initiation.

System boron concentration as a function of temperature ~s plotted in Figures 3-9 and 3-10.

The concentration at each time step during the plant cooldown was calculated using the methodology described in Section 2.4 of this report.

During the period in which blended makeup was used, data was calculated using the methodology described in section 3.4.

A total volume of 11,963.6 gallons of 3.75 weight percent boric acid solution (11,366.0 gallons of 4.0 weight percent) was required to complete the shutdown to cold shutdown with the boric acid concentration in the RHRS equal to that in the RCS at the time of system initiation.

These results are conservative, as plant operating procedures require recirculation of the RHRS through the RWST prior to initiation of RHRS, and the concentration within that system ABB Combustion Engineering Nuclear Services Page 108 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 will normally be at or near that of the RWST any time that the RHRS is placed in operation.

3.7 LONG TERM COOLING AND CONTAINMENT SUMP pH The impact of the Boric Acid Reduction Effort on post-LOCA long term cooling and containment sump pH has.been reviewed and evaluated.

The results of each evaluation are discussed qualitatively below.

Typically, the performance of the Emergency Core Cooling System (ECCS) during extended periods of time following a loss-of-coolant accident (LOCA) is analyzed to address residual heat removal via continuous boiling of fluid in the reactor vessel.

As borated water is delivered to the core region via safety injection while virtually pure water escapes as steam, high levels of boric acid may accumulate in the reactor vessel.

As an input to this analysis, boron concentration in the BATs was assumed to be at the maximum concentration of 22,500 ppm (12.87 weight percent). _Any such calculation will conservatively bound the maximum boric acid and tank concentration of 4.0 weight percent.proposed as the result of the analysis described in this report.

Since the solution stored in the BATs is not pumped into the RCS by the Emergency Core Cooling System during the Design Basis Accident, the change in BAT concentration proposed herein will have no effect on the Containment Sump pH

.Analysis.

ABB Combustion Engineering Nuclear Services Pag~ 109 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS Table 3-1 Salem Nuclear Generating Station - Units 1 & 2 Key Plant Parameters and Conditions Assumed in Generating the Feed-and-Bleed Curves RCS Volume 10,812 ft3 RCS Pressure 2250 psia RCS Average 547°F Temperature Pressurizer Volume 500.0 tt3 Pressurizer Temp.

saturation

& Press.

RCS Leakage zero BAT Temperature 70°P Mixing Between RCS Complete and and PZR Instantaneous PZR Level During constant Peed and Bleed Letdown Flowrate:

1 - Charging Pump 75 qpm 2 - Charging Pumps 150 qpm CEN-606 REV. 00 ABB Combustion Engineering Nuclear Services Page 11 O of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSES REV. 00 TABLE 3-2 SALEM NUCLEAR GENERATING STATION -

FEED AND BLEED EVALUATION FEED-&-BLEED @75 GPM; INITIAL CONCENTRATION@ Oppm BORON TIME EXPONBN11AL CONCw/

CONCW/

CONCW/

CONCW/

CONCW/

CONCW/

VALUE RWST @2300 ppm BAT@3.7SWI/%

BAT@ 3.812S Wl/'fo BAT@ 3.87S wt/%

BAT@ 3.9375 WI/%

BAT@ 4.00WI/%

(minuies) 1-e"' c-iitau) ppm ppm Wiii ppm ppm ppm 0.00 0.0000 0.000 0.000 0.000 0.000 0.000 0.000 10.00 0.0118 27.086 77.211 78.497 19.184 81.071 82358 20.00 0.0234 53.853 153512 1S6.CJ70 158.&9 161.187 163.746 30.00 0.0349 80.305 228.915 232.730 236545 240.360 244.176 40.00 0.0463 106.446 303.429 308.486 313544 318.811 323.658 50.00 0.0515 132.278 377.067 383.351 389.635 395.920 402.21)4 60.00 0.0686 151.IKY1 449.837 457.334 464.831 472.lZS 479.SUi 70.00 0.0796 183.034 521.750 530.445 539.141 547.837 556.533 80.00 0.0904 207.965 592.816 602.<66 612576 622.457 632.337 90.00 0.1011 232.@

663.045 674.096 685.146 696.197 707.248 100.00 0.1117 256.949 732.447 744.6.55 756.862 769.069 781Zl7 110.00 0.1222 281.009 801.032 814.383 827.733 841.CM 854.434 120.00 0.1325 304.786 868.11>9 883.289 897.769 912.250 926.730 130.00 0.14Z7 328.283 935.788 951.385 966.981 982.m 998.174 140.00 0.1528 351.503 1001.978 1018.678 1035.378 1052.077 1068.n1 lS0.00 0.1628 374.450 1067.389 1085.179 1102.969 1120.758 ll38548 160.00 0.17Z7 397.126 1132029 1150.896 1169.764 1188.631 1207.498 170.00 0.1824 419535 1195.908 1215.840 1235.m 1255.704 1275.636 180.00 0.1920 441.681 1259.035 1280.019 1301.003 1321.987 1342.971 190.00 0.2016 463566 1321.419 1343.442 1365.466 1387.490 1409.513 200.00 0.2110 485.192 1383.067 1406.119 i429.170 1452.221 1475.272 210.00 0.22(]2 506.565 1443.990 1468.057 1492.123 1516.190 1540.256 220.00 0.2294 527.685 1504.196 1529.265 1554.335 1579.405

.1604.475 230.00 0.23&5 548.SS7 1563.692 1589.753 1615.815 1641.876 1667.938 240.00 0.2475 569.183 1622.487 1649.529 1676.570 1703.612 1730.653 ABB Combustion Engineering Nuclear Services Page 111 of 1 33 WSASEC3FB

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSES REV. 00 TABLE 3-3 SALEM NUCLEAR GENERATING STATION -

FEED AND BLEED EVALUATION FEED-&-BLEED @150 GPM;. INITIAL CONCENTRATION @Oppm BORON TIME BXPONBlfDAL CONC.w/

CONC. W/

CONC.W/

CX>NC. W/

CONC. W/

CX>NC. W/

VAWB RWST @2300 ppm BAT@3.75wtl%

BAT@ 3.8125 Wl/'lf>

BAT @ 3.875 Wl/'lf>

BAT@ 3.9375 wt/%

BAT@4.00Wll'J' (minula) 1-e" (-a.tau) ppm ppm ppm ppm ppm ppm 0.00 0.0000 0.000 0.000 0~000 0.000 0.000 0.000 10.00 0.0234 53.853 153.512 156.070 1S8.Q9 161.187 163.746 20.00 0.0463 106.446 303.429 308.486 313.544 318.Wl 323.658 30.00 0.0686 157.lm 449.837 457.134 464.831 472.liB 479.826 40.00 0.0904 207.965 592.816 602.<66 612S76 622.457 632.337 50.00 0.1117 256.949 732.447 744.6.S5 756.862 769.QS9 781Z77 60.00 0.1325 304.786 868.81)1) 883289 897.769 912.250 926.730 70.00 0.1528 351.503 1001.978 1018.678 1035.378 1052.077 1068:.m 80.00 0.1727 397.126 11320'29 1150.896 1169.764 1188.631 1207.498 90.00 0.1920 441.681 1259.035 1280.019 1301.003 1321.987 1342971 100.00 0.2110 485.192 1383.067 1406.119 1429.170 14S'2.221 1475.272 110.00 0.2294 527.685 1504.196 1529.265 1554.335 1579.405 1604.475 120.00 02475 569.183 16n487 1649.529 1676.570 1703.612 1730.653 130.00 0.2651 609.109 1738.010 1766.976 1795.943 1824.910 1853.877 140.00 0.2823 649.287 1850.827 1881.674 1912.521 1943.368 1974.215 150.00 02991 687.'H/

1961.003 1993.686 2Q26.369 2059.053 20'Jl.736 160.00 0.3155 725.683 2068.599 2103.075 2137.552 2172.Cl28 2206.505 170.00 0.3315 762.545 2173.675 220'J.903 2246.131 2282..3S9 2318.587 180.00 0.3472 798.543 2276292 2314230 2352.168 2390.106 2428.044 190.00 0.3625 833.699 2376.SOS 2416.114 2455.722 2495.330 2534.939 200.00 0.3774 868.032 2474.372 2515.612 2556.851 259&.091 2639.331 210.00 0.3920 901.561 2569.948 2612781 2655.613 2698.446 2741.278 220.00 0.4062 9343>5 2663.286 2707.674 2752.062 2796.450 2840.838 230.00 0.4201 966.282 2754.438 2800346 2846253 2892.160 2938.068 240.00 0.4337 997.510 2843.456

. 2890.847 2938.238 2985.629 3033.020 ABB Combustion EngineerinQ Nuclear Services Page 11 2 of 1 33 WSA.SEC3FB

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSES REV. 00 TABLE 3-4 SALEM NUCLEAR GENERATING STATION -

FEED AND BLEED EVALUATION FEED-&-BLEED @ 75 GPM; INITIAL CONCENTRATION @ 1000 ppm BORON TIME 1-EXP EXPONENTIAL CONC.w/

CONC. W/

CONC. W/

CONC. W/

CONC. W/

CONC. W/

VALUE VALUE RWST@2300 j>pm BAT@ 3.75WI/%

BAT@3.8125W1/%

BAT@ 3.875 WI/%

BAT @ 3.9175 WI/%

BAT@4.00W1/%

(minutes) 1-e" (-tAau) e" (-ti\\au) ppm ppm ppm ppm ppm ppm 0.00 0.0000 1.0000

• 1000.000 1000.000 1000.000 1000.000 1000.000 1000.000 10.00 0.0118 0.9882 1015.310 1065.434 1066.721 1068.008 1069.295 1070.S81 20.00 0.0034 0.97<i6 1030.439

~130.097 1132.656 1135.214 1137.773 1140.332 30.00 0.0349 0.9651 1045.390 1193.999 1197.814 1201.630 1205.445 1209.260 40.00 0.0463 0.9531 1060.165 1257.149 1262..206 1267.263 1272.320 1277377 S0.00 0.0515 0.9425 1074.7<i6 1319.554 1325.839 1332.123 1338.408 1344.692 60.00 0.0686 0.9314 1089.195 1381.22.S 1388.722 1396.220 1403.717 1411.214 70.00 0.0796 0.9204 1103.454 1442.169 1450.865 1459.561 1468.257 1476.953 80.00 0.0904 0.9096 1117.545 1502.396 1512.276 1522.157 1532.037 1541.917 90.00 0.1011 0.89&9 1131.471 1561.914 1572.964 1584.015 1595.066 1606.117 100.00 0.1117 0.8883 1145.232 1620.730 1632.938 1645.145 1657.353 l<i69.560 110.00 0.1222 0.8778 1158.831 1678.854 1692.205 1105555 1718.906 1732.256 120.00 0.1325 0.8615 1172.270 1736.293 1750.774 1765.254 1779.734 1794.214 130.00 0.1427 0.8573 1185.551 1193.056 1808.653 1824.249 1839.846 1855.442 140.00 0.1528 0.8472 1198.676 1849.151 1865.851 1882.550 1899.250 1915.949 150.00 0.1628 0.8372 1211.645 1904585 1922.375 1940.164 1957.954 1975.744 160.00 0.1727 0.8273 1224.463 1959.3<i6 1978.233 1997.100 2015.967 2034.834 170.00 0.1824 0.8176 1237.129 2013.502 2033.434 2053.365 2073.297 2093.229 180.00 0.19'211 O.llOIK>

1249.646 2067.000 2087.984 2108.968 2129.952 2150.936 190.00 0.2016 0.7984 1262.015 2119.869 2141.892 2163.916 2185.939 2207.963 200.00 0.2110 0.78SU 1274.239 2172.114 2195.165 2218.217 2241.268 2264.319 210.00 o.22m 0.7798 1286.319 2223.745 2247.811 2271.878 2295.944 232D.011 220.00 0.2294 0.77~

1298.257 2274.767 2299.837 2324.907 2349.977 2375.047 230.00 0.2385 0.7615 131D.054 2325.189 2351.250 2377.312 2403.373 2429.435 240.00 0.2475 0.7525 1321.712 2375.017 2402.058 2429.099 2456.141 2483.182

~

ABB Combustion Engineering Nuclear Services Pa~e 113 of 133 WSASECJFB

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSES REV. 00 TABLE 3-S SALEM NUCLEAR GENERATING STATION -

FEED AND BLEED EVALUATION FEED-&~BLEED @150GPM; INITIAL CONCENTRATION@ 1000p[)mBORON TIME 1-BXP EXPONENTIAL CONCw/

CONCW/

CONCW/

CONCW/

CONCW/

OONCW/

VALUE VALUE RWST @2300 ppm BAT@3.75WI/%

BAT @ 3.8125 WI/%

BAT@ 3.875 WI/%

BAT @ 3.9375 Wl/'1f>

BAT@ 4.00 WI/%

(minutes) 1-e" (-tAau) e" (-titau) ppm ppm ppm ppm ppm ppm 0.00 0.0000 1.0000 1000.000 1000.000 1000.000 1000.000 1000.000 1000.000 10.00 O.O"l34 0.97(J6 1030.439 1130.097 1132656 1135.214 1137.773 1140.332 20.00 0.0463 0.9537 1060.165 1257.149 1262.206 1267.263 1272320 1277.377 30.00 0.0686 0.9314 1089.195 1381.225 1388.712 1396.220 1403.717 1411.214 40.00 0.0904 0.9096 1117.545 1502.396 1512.276 152.2.157 1532037 1541.917 S0.00 0.1117 0.8883 1145.232 1620.730 1632938 1645.145 1657.353 1669.S(i()

60.00 0.1325 0.8675 1172.270 1736.293 1750.774 1765.254 1779.734 1794.214 70.00 0.1528 0.847Z.

1198.676 1849.151 1865.851 1882.SSO 1899.250 1915.949 80.00 0.1727 0.8273 1224.463 1959.366 1978.233 1997.100 2015.967 2034.834 90.00 0.1920 0.80IK>

1249.646 2067.000 2087.984 2108.968 2129.952 2150.936 100.00 0.2110 0.78SO 1274.239 2172114 2195.165 2218.217 2241.268 2264.319 110.00 0.229-l 0.7706 1298.257 2274.767 2299.837 2324.907 2349.977 2375.047 120.00 0.2475 0.7525 1321.712 2375.017 2402.058 2429.099 2456.141 2483.182 130.00 0.2651 0.7349 1344.618 2472919 2501.885 2530.8S'2 2559.819 2588.786 140.00 0.2823 0.7177 1366.988 2S68.S'28 2599.375 2630.223 2661.070 2691.917 lS0.00 0.2991 0.700) 1388.834 2661.899 2694.583 27Z7.266 2759.950 2792633 160.00 0.3155 0.6845 1410.169 2753.084 2787.561 2822.038 2856.514 289Q.991 170.00 0.3315 0.6685 1431.004 2842134 2878.362 2914.590 2950.818 2987.046 180.00 0.3472 0.6528 1451.351 2929.099 2967.037 3004.975 3042913 308(1852 190.00 0.3625 0.6375 1471.221 3014.027 3053.636 3093.244 3132853 3172461 200.00 0.3774 0.6226 149Q.6Z7 3096.967 3138.207 3179.446

.3220.686 3261.925 210.00 0.3920 0.60S>

1509.578 3177.965 3220.798 3263.630 3306.463 3349.295 220.00 0.4062 0.5938 1528.085 3257.067 3301.455 3345.843 339Q.231 3434.619 230.00 0.4201 0.5799 1546.159 3334.316 338Q.223 3426.130 3472038 3517.945

!40.00 0.4337 0.5663 1563.810 3409.756 3457.147 3504.538 3551.929 3599.320

• - --r~:Ern Combustion Engineering Nuclear Services Page 114 of 133 WSASEC3FB

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN 606 TECHNICAL BASES AND OPERATIONAL ANALYSES REV. 00 TABLE3-6 SALEM NUCLEAR GENERATING STATION - TYPICAL BLENDED MAKEUP OPERATIONS

@ 75 GPM OUT OF BLENDING TEE CONCENTRATION OUT OF TEE (ppm BORON)

FLOW (GPM) THROUGH BAT BAT BAT BAT BAT 1(2)-CV-172 1(2)-CV-179

@3.75wt%

@3.8125wt%

@3.875wt%

@3.9375wt%

@4.0wt%

2.00 73.00 181.46 184.60 187.74 190.89 194.D4 4.00 71.00 362.54

.368.81 375.0S 38137 387/i6 6.00 69.00 54325 552.64 562.D2 571.43 580.84 8.00 67.00 723.58 736.D7 748.56 761.0S 773DJ 10.00 65.00 903.54 919.12 934.70.

95032 965.93 12.00 63.00 1083.13 1101.79 1120.44 1139.14 1157.84 14.00 61.00 1262.35 1284.07 1305.79 132756 134932 16.00 59.00 1441.20 1465.97 1490.74 1515.56 1540.38 18.00 57.00 1619.68 1647.49 167530 1703.16 1731.02 20.00 55.00 1797.80 1828.63 1859.46 189036 1921.24 22.00 53.00 1975.55 2009.40 2043.23 2077.15 2111.05 24.00 51.00 2152.93 2189.78 2226.62 2263.53 2300.44 26.00 49.00 2329.95 2369.79 2409.61 2449.52 2489.41 28.00 47.00 2506.61 2549.42 2592.22 2635.10 2677.97 30.00 45.00 2682.90 2728.68 2774.44 2820.29 2866.12 32.00 43.00 2858.84 2907.57 2956.27 3005.08 3053.85 34.00 41.00 3034.42 3086.08 3137.72 3189.47 3241.18 36.00 39.00 3209.63 3264.23 3318.79 3373.46 3428.10 38.00 37.00 3384.49 3442.01 3499.48 3557.07 3614.61 40.00 35.00 3559.00 3619.41.

3679.78 3740.27 3800.72 ABB C.ombustion Engineering Nuclear Services Page 115 of 133 BLEND

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN 606 TECHNICAL BASES AND OPERATIONAL ANALYSES REV. 00 TABLE3-7 SALEM NUCLEAR GENERATING STATION -1YPICAL BLENDED MAKEUP OPERATIONS

@ 150 G PM OUT OF BLENDING TEE CONCENTRATION OUT OF TEE (ppm BORON)

FLOW (GPM) rnROUGH BAT BAT BAT BAT BAT 1(2)-CV-172 1(2)-CV-179

@3.75wt%

@3.8125wt%

@3.875wt%

@39375wt%

@4.0wt%

2.00 148.00 90.78 92.35

. 93.92 95..50 97.00 4.00 146.00 181.46 184.60 187.74 190.89 194.D4 6.00 144.00 272.05 276.76 281.46 286.18 290.90 8.00 142.00 36254 368.81 375.0S 38137 387h6 10.00 140.00 45294 460.77 468.60 476.45 48430 12.00 138.00 54325 552.64 562.D2 571.43 580.84 14.00 136.00 633.46 644.40 65534 66631 67727 16.00 134.00 72358 736IJ7 74856 761.0S 773.60 18.00 132.00 813.61 827.65 841.68 855.75 869.82 20.00 130.00 90354 919.12 934.70 95032 96593 22.00 128.00 99339 1010.51 1027.62 1044.78 1061.94 24.00 126.00 1083.13 1101.79 1120.44 1139.14 1157.84 26.00 124.00 117279 119298 1213.17 1233.40 1253.63 28.00 122.00 126235 1284.07 1305.79 1327.56 1}49.32 30.00 120.00 1351.82 1375.07 1398.31 1421.61 1444.90 32.00 118.00 1441.20 1465.97

• 1490.74 1515.56 1540.38 34.00 116.00 1530.49 1556.78 1583.07 1609.41 1635.75 36.00 114.00 1619.68 1647.49 1675.30 1703.16 1731.02 38.00 112.00.

1708.79 1738.11 1767.43 1796.81 1826.18 40.00 110.00 1797.80 1828.63 1859.46 1890.36 1921.24 ABB Combustion Enwneerin~ Nuclear Services Page 116 of 133 BLEND

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS Table 3 - 8 Key Plant Parameters and Conditions Assumed in the Shutdown-to-Refueling Evaluation RCS Volume 10,812 ft3 Initial RCS Average 547°F Loop Temperature Pressurizer Volume soo.o ft3 Pressurizer Pressure Saturation.

RCS Leakage zero BAT Temperature 70°F Mixing Between RCS Complete and and Pressurizer Instantaneous Pressurizer Level constant During Feed '

Initial RCS concentration o ppm Boron BAT concentration 3.75 '

4.0 wt.% Boric RWST concentration 2300 ppm Boron RBRS Volume 1700 ft3 Boron concentration in RHRS=

Boron concentration in RCS at Time of RBRS Initiation Refueling concentration 2300 ppm boron (Mode 6)

CEN-606 REV. 00 Bleed Acid ABB Combustion Engineering Nuclear Services Page 11 7 of 1 33

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSES REV. 00 TABLE 3-9 SALEM NUCLEAR GENERATING STATION -

REFUELING COOLDOWN FROM 547°F TO 135"F FEED-AND-BLEED AND MAKEUP FROM BAT wf3.75 wt% BORIC ACID @ 7CJ'F AVG.SYS.TEMP.

PZR SPECIFIC VOLUME.

SHRINKAGE BAT VOL B/A TOTAL TOTALSYST.

FINAL PRESS; MASS

@70"F ADDED BORIC ACID MASS CONC.

Ti (°P)

To(°P)

(plia)

Vi (lt3/lbm )

VI (113/lbm)

(lbm)

(gallons)

(lbm)

(lbm)

(lbm)

(ppalbon) 547 547 2250 0.021251 0.021251 0.0 9,075.0 0.0 2,831.8 530,140.1 933.9 547 540 2250 0.021251 0.021-06 4,7362 568.6 184.5 3,0163 535,060.8 985.6 540 530 2250 0.02106 0.02079 6,5455 785.9 255.0 3,2713 541,8613 1,0555 530 500 2250 0.02079 0.02009 18,120.5 2,175.6 706.0 3,9773 560,687.8 1,2402 500 470 2250 0.02009 0.01951 16,141.2 1,938.0 628.9 4,6062 577,457.8 1,394.6 470 440 2250 0.01951 0.01900 14,883.0 1,786.9 579.9 5,186.0 592,920.7 1,5292 440.

410 2250 0.01900 0.01855 13,811.9 1,6583 538.1 5,7242 607,270.7 1,648.0 410 390 2250 0.01855 0.01828 8,613.6 1,0342 335.6 6,059.8 616,219.9 1,7193 390 360 2250 0.01828 0.01792 11,888.7 1,427.4 463.2 6,523.0 628,571.8 1,8143 1(,()

350 2250 0.01792 0.01781 3,7285 447.7 145.3 6,6682 632,445.6 1,843.4 I \\ll 350.

350 0.01781 0.01797 (5,575.7 (669.4 (2172 6,451.0 626,652.7 1,79?.8

~~u 350 350 0.02698 0.01912 7,618.4 914.7 296.8 6,747.8 634,567.9 1,859.1 350 350 350 0.01797 0.01797 0.0 0.0 0.0 6,747.8 634,567.9 1,859.1 ADD IN RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

350 350 350 0.01797 0.01797 0.0 0.0 0.0 7,764.6 730,186.8 1,859.1 350 300 350 0.01797 0.01743 21,571.2 2,589.9 840.4 8,605.0 752,5985 1,999.0 300 250 350 0.01743 0.01699 18,590.4 2,232.0 724.3

.9,3293 771,913.2 2,113.0 250 240 350 0.01699 0.01691 3,484.0 418.3 135.7 9,465.1 775,532.9 2,133.8 240 220 350 0.01691 0.01676 6,6222 795.1 258.0 9,723.1 782,413.1 2,172.7 220 200 350 0.01676 0.01662 6,2885 755.0 245.0 9,968.1 788,946.6 2,209.0 200 180 350 0.01662 0.01649 5,935.0 712.6 231.2 10,199.3 795,112.8 2,242.7 180 160 350 0.01649 0.01638 5,0955 611.8 198.5 10,397.9 800,406.8 2,2712 160 150 350 0.01638 0.01633 2,5735 309.0 100.3 10,498.1 803,080.6 2,2855 150 140 350 0.01633 0.01628 2,1185 254.4 82.5 10,580.7 805,281.7 2,2972 140 135 350 0.01628 0.01626 1,182.0 141.9 46.1 10,626.7 806,509.7 2,303.6 FEED-AND-BLEED BAT VOL (0 ppm to 1103.7 ppm)

=

9,075.0 GALLONS (121 minutes at 75 gpm)

TITT AL BAT VOLUME

=

29,962.6 GALLONS ABB COMBUSf ION ENGINEERING NUCLEAR SERVICES Pal?.e 118 of 133 SSEC3jlEF L.

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSES REV. 00 TABLE 3-10 SALEM NUCLEAR GENERATING Sf ATION -

REFUELING COOLDOWN FROM 547°F TO 135°F FEED-AND-BLEED AND MAKEUP FROM BAT w/4.0 wt% BORIC ACID @ 7CfF AVG.SYS.TEMP.

PZR SPECIFIC VOLUME SHRINKAGE BAT VOL BIA TOTAL TOTALSYST.

FINAL PRESS.

MASS

@70"F ADDED BORIC ACID MASS CONC.

Ti("F)

To (°F)

(psia)

Vi (ft31lbm )

Vf (ft3/lbm)

(lbm)

(gallons)

(lbm)

(lbm)

(lbm)

(ppm Boron) 547 547 2250 O.l:r21251 O.l:r21251 0.0 8,025.0 0.0 2,523.0 529,8313 832.6 547 540 2250 O.l:r21251 O.l:r2106 4,7362 568.6 254.1 2,777.1 534,821.6 907.8 540 530 2250 O.l:r2106 O.l:r2079 6,5455 785.9 272.7 3,049.8 541,639.8 984.4 530 500 2250 0.(}2079 O.l:r2009 18,120.5 2,175.6 730.5 3,7803 560,490.7 1,1792 500 470 2250 0.(}2009 0.01951 16,141.2 1,938.0 672.6 4,452.9 577,3045 1,348.5 470 440 2250 0.01951 0.01900 14,883.0 1,786.9 620.1 5,073.0 592,807.6 1,4%.2 440 410 2250 0.01900 0.01855 13,811.9 1,6583 515.5 5,6485 607,195.0 1,626.4 410 390 2250.

0.01855 0.01828 8,613.6 1,0342 358.9 6,007.4 616,1675 1,704.6 390 360 2250 0.01828 0.01792 11,888.7 1,427.4 495.4 6,502.7 628,551.6 1,808.8 1(,()

350 2250 0.01792 0.01781 3,7285 447.7 155.4 6,658.1 632,4355 1,840.6

\\*111 350 350 0.01781 0.01797 (5,575.7 (669.4 0.0 6,658.1 626,859.8 1,857.0

_~All SAT 350 0.02698 0.01912 7,618.4 914.7 0.0 6,658.1 634,478.2 1,834.7 350 350 350 0.01797 0.01797 0.0 0.0 0.0 6,658.I 634,478.2 1,834.7 ADD IN RHRS VOLUME (ASSUME BORON CONC. = RCS BORON CONC.)

350 350 350 0.01797 0.01797 0.0 0.0 0.0 7,661.4 730,083.6 1,834.7 350 300 350 0.01797 0.01743 21,571.2 2,589.9 869.6 8,530.9 752,524.4 1,982.0 300 250 350 0.01743 0.01699 18,590.4 2,232.0 749.4 9,280.4 771,8642 2,102.l 250 240 350 0.01699 0.01691 3,484.0 418.3 140.4 9,420.8 775,488.6 2,123.9 240 220 350 0.01691 0.01676 6,6222 795.1 267.0 9,687.8 782,377.8 2,164.9 220 200 350 0.01676 0.01662 6,288.5 755.0 253.5 9,9413 788,919.8 2,203.1 200 180 350 0.01662 0.01649 5,935.0 712.6 239.3 10,180.5 795,094.0 2,238.6 180 160 350 0.01649 0.01638 5,0955 611.8 205.4 10,385.9 800,394.9 2,268.6 160 150 350 0.01638 0.01633 2,5735 309.0 103.7 10,489.7 803,072.1 2,283.7 150 140 350 0;01633 0.01628 2,l18_"'i 254.4 85.4 10,575.1 805,276.1 2,2%.0 140 135 350 0.01628 0.01626 1,182.0 141.9 47.6 10,622.7 806,505.7 2,302.8 FEED-AND-BLEED BAT VOL (0 ppm to 832.6 ppm)

=

8,025.0 GALLONS (107 minutes at 75 gpm)

TOTAL BAT VOLUME

=

28,912.6 GALLONS

[ABBCUMBUSTI6N-ENGINEERING NUCLEAR SERVICES Pae.e 119 of 133 SSEC3REF

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS Table 3-11 CEN-606 REV. 00 Key Plant Parameters and Conditions Assumed in the Shutdown-to-Cold-Shutdown Evaluation RCS Volume 10,812 ft3 Initial RCS Average Temperature 547°F Pressurizer Volume soo.o ft3 Pressurizer condition saturation RCS Leakage Zero BAT Temperature 70°F Demineralized water Temp.

70°F Mixing Between RCS complete and and Pressurizer Instantaneous Pressurizer Level constant During cooldown Initial RCS Boron o ppm Boron Concentration BAT concentration 3.75 & 4.0 wt% Boric Acid RWST Concentration 2300 ppm Boron RBRS Volume 1700 ft3 Boron concentration in RHRS Equal to Concentration in RCS at time of RBRS Initiation (Cases I and II)

ABB Combustion Engineering Nuclear Services Page 1 20 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-606 TECHNICAL BASES AND OPERATIONAL ANALYSES REV. 00 TABLE 3-12 SALEM NUCLEAR01'3NERATING STATION -

PLANTCOOLDOWN FROM 547°FTO 20CJ>F WITH BLENDED MAKEUP BAT@ 3.75 wt% BORIC ACID AVG.SYS.TEMP.

PZR.

SPBCIFIC VOLUME !SHRINKAGE BLEND BAT VOL PRIMARYH20 B/A TOTAL TOTAL FINAL PRESS.

MASS RATIO

@70°F

@70°F ADDED BORIC ACID SYS.MASS CONC.

Ti (°F)

TC("F)

(psia)

Vi {ft3/lbm) vr (ft3/lbml (lbm)

(gallons)

(gallons)

(lbm)

(lbm)

(lbm)

(ppm boron) 541 541 2250 0.021251 0.021251 0.0 0.0 0.0 0.0 0.0 0.0 527,308.3 0.0 541 540 2250 0.021251 0.02106 4,736.2 0.0 568.6 0.0 184.5 184.5 532,229.0 60.6 540 530 2250 0.02106 0.02CJ79 6,545.5 0.0 185.9 0.0 255.0 439.5 539,029.S 142.6 530 500 2250 0.02CJ79 0.02009 18,12°'5 0.0 2,175.6 0.0 706.0 1,145.5 557,856.0 359.0 500 470 2250 0.02009 0.01951 16,141.2 0.0 1,938.0 0.0 628.9 1,774.4 574,626.1 539.9 470 440 2250 0.01951 0.01900 14,883.0 1.0 893.4 893.4 289.9 2,064.3 589,799.0 611.9 440 410 2250 0.01900 0.01855 13,811.9 1.0 829.1 829.1 269.1 2,333.4.

603,879.9 675.6 410 390 2250 0.01855 0.01828 8,613.6 1.0 517.1 517.1 167.8 2,5012 612,661.4 713.8 390 370 2250 0.01828 0.01804 7,873.1 1.0 472.6 472.6 153.4 2,654.6 620,687.8 747.7 370 350 2250 0.01804 0.01781 7,744.2 1.0 464.9 0.0 150.9 2,805.4 628,582.8 780.3 350 350 350 0.01781 0.01797 (5,515.1 1.0 0.0 0.0 0.0 2,805.4 623,007.l 787.3 350 350 350 0.02698 0.01912 7,618.4 1.0 457.3 0.0 0.0 2,805.4 630,625.S 777.8 ADD IN RHRS VOLUME (ASSUME BORON CONC. =RCS BORON CONC.)

350 350 350 0.01797 0.01797 0.0 1.0 0.0 0.0 0.0 3,228.2 725,650.4 777.8 350 320 350 0.01797 0.01763 13,427.8 1.0 806.1 806.1 261.6 3,489.8 739,339.8 825.2 320 290 350 0.01763 0.01734 11,869.3 1.0 712.5 712.5 231.2 3,72LO 751,4402 865.7 290 260 350 0.01734 0.01707 11,413.2 1.5 548.1 822..2 177.9 3,898.8 763,031.3 893.3 260 240 350 0.01707 0.01691 6,935.4 2.0 277.6 555.1 90.1 3,988.9 770,056.7 90-S.6 240 220 350 0.01691 0.01676 6,6222 2.0 265.0 530.0 86.0 4,074.9 776,764.9 917.2 220 200 350 0.01676 0.01662 6,288.5 2.0 251.7

~!)'3.3 81.7 4,156.6 783,135.1 928.0 TOTAL BAT VOLUME

=

11,963.6 GALLONS

• TOTAL PRIMARY WATER VOLUME=

6,641.6 GALLONS ABB COMBUSTION ENGINEERING NUCLEAR SERVICES

• Paie 121 of 133 SF.c3CSD2

BORIC ACID CONCENTRATION REDUCTION EFFORT CEN-TECHNICAL BASES AND OPERATIONAL ANALYSES REV. 00 TABLE 3-13 SALEM NUCLEAR GENERATING STATION -

PLANTCOOLDOWN FROM 547°F TO 20<1'F WITH BLENDED MAKEUP BAT@ 4.00 wt% BORIC ACID AVG.SYS.TEMP.

PZR.

SPBQFIC \\fOLUME !SHRINKAGE BLEND BAT VOL PRIMARYH20 BIA TOTAL TOTAL FINAL PRESS.

MASS RATIO

@70°F

@70°F ADDED BORIC ACID SYS.MASS CONC.

Ti ("F)

Tf("F)

(llSia)

Vi (fl3Jlbm) vr (fa3Jlbm)

(Ihm)

{gallons)

(gallons)

{Ihm)

(Jbm)

(lbm)

(ppm boron) 547 547 2250 0.021251 0.021251 0.0 0.0 0.0 0.0 0.0 0.0 5'Z1,3083 0.0 547 540 2250 0.021251 0.02106.

4,736.2 o.o 568.6 0.0 197.3 197.3 532,241.8 64.8 540 530 2250 0.02106 0.02079 6,54S.5 0.0 785.9 0.0 272.7 470.1 539,060.0 lS2.S 530 500 2250 0.02079 0.02009 18,120.5 0.0 2,175.6 0.0 155.0 1,225.1 557,935.5 383.9 500 470 2250 0.02009 0.019Sl 16,141.2 0.0 1,938.0 0.0 672.5 1,897.6 514,1493 577.2 470 440 2250 0.019Sl 0.014JOO 14,883.0 1.0 893.4 893.4 310.1 2,207.7 589,942.4 654.3 440 410 2250 0.01900 0.01855 13,811.9 1.0 829.1 829.1 W.7 2,495.4 604,042.0 722.3 410 390 2250 0.01855 0.01828 8,613.6 1.0 517.1 517.1 179.4 2,674.9 612,835.0 763.1 390 360 2250 0.01828 0.01792 11,888.7 1.0 713.7 713.7 247.7 2,922.6 624,971.4 817.6

\\tll) 350 2250 0.01792 0.01781 3,728.S 1.0 223.8 0.0 77.7 3,000.2 6'18,777.6 834.2

~:1 350 350 0.01781 0.01797 (5,515.1 1.0 0.0 0.0.

0.0 3,000.2 623,201.9 841.7 350 350 0.02698 0.01912 7,618.4 1.0 457.3 0.0 0.0

' 3,000.2 630,8203 831.5 ADD IN RHRS VOLUME (ASSUME BORON CONC. "" RCS BORON CONC.)

350 350 350 0.01797 0.01797 0.0 2.0 0.0 0.0 0.0 3,452.3 725,874.5 831.5 350 320 350 0.01797 0.01763 13,427.8 2.0 537.4 1,074.8 162.3 3,614.7 739,464.7 854.6 320 290 350 0.01763 0.01734 11,869.3 2.0 415.0 950.0 143.5 3,758.2 751,477.4 874.4 290 260 350 0.01734 0.01707 11,413.2 2.0 456.8 913.5 138.0 3,896.2 763,028.6 892.7 260 240 350 0.01707 0.01691 6,935.4 2.0 277.6 SSS.I 83.8 3,980.0 770,047.8 903.6 240 220 350 0.01691 0.01676 6,6222 2.0 265.0 530.0 80.1 4,060.1 776,750.1 913.9 220 200 350 0.01676 0.01'i62 6,288.5 2.0 251.7 S03.3 76.0 4,136.1 783,114.6 923.4 TOTAL BAT VOLUME

=

11,366.0 GALLONS.

TOT AL PRIMARY WATER VOLUME =

7,480.2 GALLONS ABB COMBUSTION ENGINEERING NUCLEAR SERVICES Page 122 of 133

BORXC ACXD COHCENTRATXON REDUCTZOH EFFORT TECHHXCAL BASES AHD.OPERATXONAL AHALYSXS CEH-606 REV. 00 z

0 0:

0 m E

Q.

Q.

z 0

I-

<(

0:

I-z w u z 0 u (J) u 0:

FIGURE 3-1 SAlEM NUCLEAR GENERATING STATION UNITS 1 & 2 FEED & BLEED @ 75 GPM FROM HOT ZERO POWER

.. */~

/

INITIAL CONCENTAAT I ON = 0 ppm BORON

"._'; /

1,500 (ref. TABLE 3-2)

• ** /':..._,

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • ,'*/*

• Z"'

.*'>;/

1,000

.......... *.*...............................* -:.~~---*********************************

500

... ~

~

o~.r-~~~-"-~~~~-'--~~~~--~~~"""".""""....._~~---'---'

0 50 BAT@ 3.75 wt96 0

100 150 TIME MINUTES BAT @ 3. 875 wt96 200 250 BAT @ 4.0 wt%

ABB Combustion Engineering Nuclear Services Pag~ 1 23 of 1 33

BORXC ACXD COHCE!ITRATXON REDUCTION EFFORT TECJDIXCAL BASES ARD OPERATIONAL ANALYSIS CEH-606 REV. 00 FIGURE 3-2 SALEM NUCLEAR GENERATING STATION UNITS 1 & 2 z

0 CI 0 m 2J500 E

Q_

Q_

z 2,000 0

I-

<(

CI I-z 1,500 w

u z 0 u

(/')

u CI 500 0

0 FEED & BLEED @ 150 GPM FROM HOT ZERO POWER INITIAL CONCENTRATION = 0 ppm BORON (ref. TABLE 3-3)

>(

)C

.............................................................. : ~,.>,...............

.")(

. /

~ "

I..*"'

,;.(

. /

.................. -......................... : : *.'"/~'

'/

.-~~,.

. /

. /

. :~,/

~ /

...............................,:_,:,-(...............................................

50 100 150 200 250 TIME MINUTES BAT @ 3.75 wt%

BAT @ 3.875 wt%

BAT @ 4.0 wt%

0

• --~---*

ABB Combustion Engineering Nuclear Services Pag~ 124 of 1 33

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BABBS AND OPERATIONAL ANALYSIS CEN-606 REV. 00 z

0 a:

0 m E

0.

0.

z 0

I-

<{

a:

I-z w

u z 0 u (fl u

er 1,800 1,600 1,200 FIGURE 3-3 SALEM NUCLEAR GENERATING STATION UNITS 1 & 2 FEED-AND-BLEED @ 75 GPM FRCM HOT ZERO POWER

~

...................................................................... *.-=. ~: :;,,?!'~..

INITIAL CONCENTRATION= 1000 ppm BORON

.**"ji{_/

(ref. TABLE 3-4)

.- : : * /

.*..,,/

• -*******************-***************************************.**;1*..

. /

. /*

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • .:*%~...........................

. /

-=*~

. /

. /

. /

. /

............................. -...... *.'.i*;,' *................. -..... -........ -.... -.

/

-... - -.................... -; r.

. /. /

. *,... /

i 1,000~~~~-'-~~~~..__~~~_.._~~~----'~~~---'

0 50 TIME BAT @ 3:75 wt%

---4---

100 150 200 250 MINUTES BAT@ 3.875 wt%

BAT @ 4.0 wt%

--~--

ABB Combustion Engineering Nuclear Services Pag~ 1 25 of 133

L-BORJ:C ACZD CONCEHTRATJ:ON REDUCT:ION EPPORT TECBNZCAL BABBS AND OPERAT:IONAL ANALYSJ:S CEN-606 REV. 00 z

0 a:

0 m E

Q.

Q.

z 0

1-

<l a:

1-z w

u z 0 u r.h u a:

FIGURE 3-4 SALEM NUCLEAR GENERATING STATION UNITS 1 & 2 4,000 3,500 3,000 2,500 2,000 1,500 1, 000:

0 FEED-&-BLEED @ 150 GPM FROM HOT ZERO POWER INITIAL CONCENTRATION = 1000 ppm BORON (r-ef. TABLE 3-5)

....................................................... -....... *:*.. *.... ~-.:.-.** ~;~*<...

~!),,

j:.1"""

./)<

rl '

1c"1,'

.......................................................,:~('.".

~-,

/_,<

r:'(>"

t-Y

,,.,,~

.................................... -.. :-.,. /.

/~(

,-.,..:/"

v.

//

. /

//

'/'r'

").........................................................

50 100 150 200 250 TIME MINUTES BAT (ll 3.75 wt%

BAT @ 3.875 wt%

BAT @ 4.0 wt%

e

---~---

-*-~~*-*

ABB Combustion Engineering Nuclear Services

.Page 126 of 133

BORIC ACXD CORCEHTRATION REDUCTION EFFORT TECHNICAL BABBS AND OPERATIONAL ANALYSIS CEN-606 REV. 00 z

0 a:

4,000

@ 3, ODO E

Q.

Q.

w

~ 2, ODO LL 0

I-

)

0 z

0 I-

<(

a:

1-z UJ u z 0 u 1,000 FIGURE 3-5 SALEM NUCLEAR GENERATING STATION -

UNITS 1 ANO 2 BLENDED MAKEUP OPERATIONS w/ 75 GPM OUT OF TEE (ref. TABLE 3-6) o~,;....-~~~~--1.~~~~~--'-~~~~~--'-~~~~~-'

0 10 20 30 40 FLOW FROM 1(2J-CV-172 GPM BAT @ 3. 75 wt%

--4--

BAT @ 3.875 wt9'

---7<---*

ABB Combustion Engineering Nuclear Services BAT g 4.0 wt9' Pag,e 127 of 133

BORXC ACXD CONCBBTRATXON REDUCTXON EFFORT TECllNXCAL BABBS AND OPERATXONAL ANALYSXS CEN-606 REV. 00 2,000 z

0 er:

0 rn 1,500 E a.

a.

w w

f-1 J 000 LL 0

f-

)

0 z

0 f-

<{

er:

f-z w

u z 0 u 500 0

FIGURE 3-6 SALEM NUCLEAR GENERATING STATION -

UNITS 1 AND 2 t3LENOEO MAKEUP OPERATIONS w/ 150 GPM OUT OF TEE

,*>f

.v:~,.

"'x 0

.-.{ /

• "" -;~

.')I

................................................................ -;~,,.

• .J,

,*X:

,-~.t

• • • • • • • • • • • • • • • • • • • • • • • • • • .......*.... *****I 10 FLOW FROM BAT @ 3.75 wt%

0 20 (ref. TABLE 3-7) 30 1( 2)- CV-172 GPM BAT @ 3.875 wt%

BAT @ 4.0 wt%

' /

---~---

40 ABB Combustion Engineering Nuclear Services Page 1 28 of 133

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS FIGURE 3-7 CEH-606 REV. 00 SALEM NUCLEAR GENERATING STATION UNITS 1 & 2 z

0 a:

0

!D E

0..

0..

z 0

I-

<t:

a:

I-z w

u z 0 u (f) u a:

2,500 2,000 1,500 1,000 500 0

600 REFUELING COOLDOWN FROM 547'F TO 135'F INITIAL FEED-&-BLEED:

121 MINUTES @ 75 GPM FROM BAT @ 3. 75 wt% BORIC ACID (ref. TABLE 3-9) 500 41]0 300 200 RCS AVERAG:

TEMPERATURE "F

. 1 c:-:

ABB Combustion Engineering Nuclear Services Page 129 of 133

BORIC ACID CONCE!ITRATION REDUCTION EFFORT TECHNICAL BABBS AND OPERATIONAL ANALYSIS FIGURE 3-8 CEN-606 REV. 00 SALEM NUCLEAR GENERATING STATION UNITS 1 & 2 REFUELING COOLDOWN FROM 547 'F TO 135'F 2,500 ~~~~~~~~~~~~~~~~~~~~~~

z 0

0:

0 Q)

E Q.

Q.

z 0

I-

<(

2,000 1,500 er 1,000 1---z w

u z

0 u INITIAL FEED-&-BLEED:

107 MINUTES g 75 GPM FROM BAT g 4.0 wt% BORIC ACID (ref. TABLE 3-10)

([)

500 u

0:

0 600 500 400 300 RCS AVERAGE TEMPERATURE ABB Combustion Engineering Nuclear Services 200 100 Pag~ 130 of 1 33

BORIC ACID CONCEllTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 z

0 0:

0 CD E

0.

0.

z 0

I-

<(

0:

I-z w

u z 0 u Cf) u 0:

1~000 FIGURE 3-9 SALEM NUCLEAR GENERATING STATION UNITS 1 & 2 SHUTDOWN TO COLD SHUTCOWN 547"F TO 200"F 800 600 400 200 0

600 500 BLENDED MAKEUP w/BAT@ 3.75 wt% BORIC ACID

(~ef. TABLE 3-12) 400 300 200 RCS AVERAGE COOLANT TEMPERATURE F

100 ABB Combustion Engineering Nuclear Services Page 131 of 1 33

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BABBS Alfi> OPERATIONAL ANALYSIS CEN-606 REV. 00 z

0 a:

0

(!]

E Q_

Q_

z 0

I-a:

I-z w

u z 0 u

(/)

u a:

FIGURE 3-10 SALEM NUCLEAR GENERATING STATION UNITS 1 & 2 SHUTDOWN TO COLO SHUTDOWN -

547"F TO 200"F 1,000 800 600 400 200 0

600 FEED-&- BLEED BAT @ 4.0 wt'6 BORIC ACID.

(ref. TABLE 3-13) 500 400 300 200 RCS AVERAGE TEMPERATURE "F

100 ABB Combustion Engineering Nuclear Services Page 1 32 of 1 33

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES ~

OPERATIONAL ANALYSIS

4.0 REFERENCES

CEN-606 REV. 00 4.1 U.S. Nuclear Regulatory Commission Standard Review Plan NUREG-0800 Section 5.4.7.

"Residual Heat Removal (RHR) system" and Branch Technical Position (RSB) 5-1 "Design Requirements of the Residual Heat Removal System" 4.2 Technical Data Sheet IC-11, us Borax & Chemical Corpo-ration, 3-83-J.W.

4.3 Phase II Report, "System Modification Study for Salem Nuclear Generating Plants", March 1993 4.4 Letter, Mr. *Glenn Schwartz, PSE&G, to Ms. Donna Hayes, ABB Combustion Engineering Nuclear Services, May 12, 1993 4.5 ABB Nuclear Fuels QA Verified Boron Requirements for Salem, GM-FE-0092, Rev. 01, K. J. Loeffler, ABB Nuclear Fuels, to D. Hayes, ABB Combustion Engineering Nuclear Services, May 5, 1993 4.6 Residual Heat Removal System Volume Calculation, Calculation No. MISC-MECH-CALC-100, Rev. 00, April 30, 1993 4.7 BACR Computer Code, Version 2, Calculation OOOOO-MPS-2CALC-Ol3, Rev. 01 4.8 "Flow of Fluids", Technical Paper No. 410, Crane Co., 1988 ABB Combustion Engineering Nuclear Services Page 133 of 1 33

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS Appendix 1 Derivation of the Reactor coolant System Feed-and~Bleed Equation Purpose of Definitions CEN-606 REV. 00 This appendix presents the detailed derivation of an equation which can be used to compute the reactor coolant system (RCS) boron concentration change during a feed-and-bleed operation.

For this derivation, the following definitions were used:

mfn

= mass f lowrate into the RCS mout

= mass f lowrate out of the RCS n;,

= boron mass f lowrate m.,

= water mass f lowrate n;,

= boron mass m.,

= water mass c,n

= boron concentration going into RCS Cout

= boron concentration going out of RCS c 0

= initial boron concentration C(t)

= boron concentration as a function of time CRcs

=

RCS boron concentration Simplifvinq Assumptions During a feed-and-bleed operation, the RCS can be pictured as a closed container having a certain volume, a certain mass, and an initial boron concentration.

Coolant is added at one end via the charging pumps.

The rate of. addition is dependent on ABB Combustion Engineering Nuciear Services Page Al-1 of Al-6

BORIC ACZD CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 the number of charging pumps that are running with the concentration being determined by the operator.

Coolant is removed at the other end via letdown at a rate that is approximately equal to the charging rate and at a c*oncentration determined by fluid mixing within the RCS.

The mass flowrate into system is given by the following equation:

.ch

= (.rhb + Ih )

m w

For typical boron concentrations within the chemical and volume control system, IDw is very much greater than II\\,* (For example, a J.5 weight percent boric acid solution contains only 0.04 lbm of boric acid per lbm of water).

Therefore the above equation can be simplified to the following:

(1.0)

In a similar manner, the mass flowrate coming out of the system, given by can be simplified by again realizing that 'Illw. is very much greater than ~ or (2. 0)

For a feed-and-bleed operation with a constant pressurizer level and system temperature, the mass flowrate into the RCS will be equal to the mass flowrate out of the RCS, or ABB Combustion Engineering Nuclear Services Page Al-2 of Al-6

BORZC ACZD COHCEHTRATXOH REDUCTZOH EFFORT TECBHXCAL BASES ARD OPBRATZOHAL AHALYSZS Since m.. >> n;,, then CEH-606 REV. 00 where (m.,) RCS is a constant for a constant system temperature.

The rate of change of the RCS concentration is therefore (6. 0) substituting Equation 5.0 into Equation 6.0 yields the following:

and from Equation 4.0 d

<mi..> in ( C1n -

CRcs>

CRcs = _..;;.__-==---==--....=~

dt (m) RCS (7. 0)

ABB Combustion Engineering Nuclear Services Page Al-4 of Al-6

BORXC ACXD CONCBNTRATXON REDUCTXON EFFORT TE~BNXCAL BASES AND OPERATXONAL ANALYSXS Solvinq Equation 7.0 for concentration yields:

=

or

• C(t) f d CRCS

=

C(O)

Cin -

CRCS t

Cm.. > in J dt Cm.. > Res o CEN-606 REV. 00 Inteqratinq from some initial concentration c0 to some final concentration C(t) and multiplyinq throuqh by a minus one gives the followinq:

CCO) ln ( CRCS -

cin>

=

CC t) ln [ C( t) -

Cin] =

Co - Cin ABB Combustion Engineering Nuclear Services t

t Paqe Al-5 of Al-6

BORIC ACID CONCENTRATION REDUCTION EFFORT TECBBICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 Continuing to solve for C(t), this equation becomes:

C( t) -

Cin =

Co -

C1n e - Cm,,> J.n I Cm,) 11.a or C ( t) = C

+ ( C -

C ) e - cm,,> ut/ cm,,> 1tc:1 in o

in (8.0)

If we define the time constant ~ to be as follows:

then Equation 8.0 becomes (9. 0)

ABB Combustion Engineering Nuclear Services Page Al-6 of Al-6

BORIC ACID CONCEBTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS Appendix 2 CEN-606 REV. 00 Methodology for Calculating Dissolved Boric Acid per Gallon of Water Purpose The purpose of this appendix is to show the methodology used to calculate the mass of boric acid dissolved in each gallon of water for solutions of various boric acid concentrations.

A solution temperatures of 70°F was used for both the RWST and the BAT.

Methodology and Results Boric acid concentration expressed in terms of weight percent is defined as follows:

C = mass of boric acid x 100 total solution mass or C=

mass of boric acid x 100 (mass.of boric acid) + (mass of water)

(1. 0)

ABB Combustion Engineering Nuclear Services Page A2-1 of A2-3

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 Defining the mass of boric acid as ~ and the mass of water as 1nw 1 and substituting into equation (1.0) gives the following:

mba c = ----"~- x 100 mba + m..,

or (C) x (m"')

100 -c (2. 0)

From Appendix A of Reference 4.8, the density of water at 70°F is 8.3290 lbm/gallon.

Using this figure and Equation 2.0, the mass of boric acid per gallon of solution is calculated as shown in the following table:

ABB Combustion Engineering Nuclear Services Page A2-2 of A2-3

BORIC ACID CONCEBTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS Appendix 3 CEN-606 REV. 00 Methodology for Calculating.the Conversion Factor Between Weight Percent Boric Acid and ppm Boron Purpose The purpose of this appendix is to show the methodology used to derive the conversion factor between concentration in terms of weight percent boric acid and concentration in terms of parts per million (ppm) of naturally occurring boron.

Results For any species (solute) dissolved in a solvent, a solution having a concentration of exactly 1 ppm can be obtained by dissolving 1 lbm of solute in 999,999 lbm of solvent.

An aqueous solution having a concentration of 1 ppm boric acid, therefore, is obtained by dissolving 1 lbm of boric acid in 999,999 lb* of water, or 1 lbm boric acid 1 lbm boric acid

= 106 lbm solution 1 ppm = 1 lbm boric acid + 999, 999 lbm water ABB Combustion Engineering Nuclear Services Page AJ-1 of AJ-2

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS CEN-606 REV. 00 For any species (solute) dissolved in some solvent, a solution having a concentration of 1 weight percent (w/%)

can be obtained by dissolving 1 lbm of solute in 99 lbm of solvent.

An aqueous solution having a concentration of 1 weight percent boric acid, therefore, can be obtained by dissolving 1 lbm of boric acid in 99 lbm of water, or 1 wt%

1 lbm boric acid

= ~--~~--,"""""""'"-...,.....,,....-~--,,...,.-~~~

100 1 lbm boric acid + 99 lbm water

= 1 lbm boric acid 100 lbm solution Dividing these last two equations yields a ratio of 104, or 1 weight percent boric acid = 10, 000 ppm boric acid (1.0)

To convert from ppm boric acid (weight fraction) to ppm boron (weight fraction), multiply Equation 1.0 by the ratio of the molecular weight of boric acid (naturally occurring H3so3 ) to the atomic weight of naturally occurring boron.

From the Handbook of Chemistry and Physics, CRC Press, 1 weight percent boric acid = (10, 000)

!~: :~ ppm boron where (10.81/61.83) is the ratio of the mass of boron in the boric acid to the total molecular mass of boric acid.

or 1 weight percent boric acid= 1748.34 ppm boron ABB Combustion Engineering Nuclear Services Page AJ-2 of A3-2

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BASES AND OPERATIONAL ANALYSIS Appendix 4 CEN-606 REV. 00 Bounding Core Reactivity Considerations The methodology used to compute core reactivity and the required changes in boron concentration resulting therefrom are described in this appendix.

This methodology was used to conservatively bound the reactivity effects of the cooldown described in Section 2.2.1.1 of this report.

The cooldown scenario is summarized in the following paragraphs, along with a discussion of the methods used to compute the changes in boron concentration made necessary by the cooldown.

Cooldown Scenario and Assumptions The following scenario was evaluated to establish the bounding boron concentrations which have been used in this report.

1.

Shutdown Margin Requirements:

200°F < T8~ < 547°F Tave < 200°F 1600 pcm 1000 pcm

2.

Reactor is initially at Hot Full Power (HFP),

equilibrium xenon and samarium conditions, resulting in a boron concentration of o ppm.

In addition, the control rods are at the Technical Specification Insertion Limits.

This combination of conditions maximizes the change in boron concentration required to ABB Combustion Engineering Nuclear Services Page A4-1 of A4-9

BORIC ACID CONCENTRATION REDUCTION EFFORT TECHNICAL BABBS AND OPERATIONAL ANALYSIS CEN-606 REV. 00 maintain Shutdown Margin (SDM) and to compensate for a reactor trip and subsequent cooldown to cold, xenon free conditions.

3.

The most reactive control rod is assumed to be stuck in the fully withdrawn position and is therefore not available for shutdown reactivity control.

4.

At t=O, the reactor is tripped and held at Hot Zero Power (HZP) conditions (547°F) for 22.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.

5.

At t=22.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, a plant cooldown from 572°F to 135°F is initiated, at an average rate of 10°F/hr.

(At temperatures at and below 200°F, it is assumed all xenon has decayed and that the core is xenon free).

The use of assumptions 4 and 5 ensures that the maximum rate of xenon decay is accounted for in the bounding boron calculations.

The peak xenon concentration is reached approximately seven (7) hours after reactor shutdown.

After the xenon peak is reached the -xenon in the core begins to decay, adding reactivity to the system.

This reduces the negative reactivity wnich had been added by the initial increase in xenon, and the xenon returns to the steady~state operating value approximately 22.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> after shutdown.

6.

At times beyond 22.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, the reactor must be borated to compensate for.the continuing decay of xenon.

Thus, the bounding boron concentration which are calculated must offset the the positive reactivity contribution from both the cooldown and the xenon decay.

ABB Combustion Engineering Nuclear Services Page A4-2 of A4-9

BOR%C.ACJD COBCKll'l'RA'l'tOll RBDUCTIOH BF70RT TBCJllf%CAL BMBS Alm OPBRATIOHAL ANALYSIS CD-606 R!V. 00

7.

The samarium concentration is assumed to remain constant for the entire scenario.

This is a conservative assumption wnich increases the calculated boron requirements, since the negative reactivity worth of the samarium increases with time after *butdown.

a.

The boron concentrations were normalized. to an End-or-Lite CEOL), HFP M'l'C ot -44.0 pcm/*F.

This was done to bound current Technical Specification limits and is considered conservative for current cycle *lengths and teed enrichments.

9.

It has been noted that under certain condition~ and for a limited time, the boration transient from peak xenon conditions is more limiting than the equilibrium xenon ca** de*cribed here.

In the unlikely event that the plant were to be held at hot, zero power conditions for several hours until the xenon transient reached its peak, additional Doric acid would be required.

This is not considered to be a reali*tic situation, but this scenario has been analyzed.

The results of the analysis are presented in section 2.4.4 ot the report

• ABB Combustion Engineering Nuclear Services Paqe A4-3 Of A4-9

BORIC ACID COXCBlrl'RATXOM RBDUCTION BJTORT TBCmll:CAL BABBS AlfD OPBRA'l'IOHAL ANALYSIS CBN-606 RIV. 00 The limitinq boron concentration curves were calculated for Salem Unit 2, Cycle 6.

Unit 2, Cycle 6 is the most limitinq case and bounds the reload desiqn boron requirements; hence, with additional conservatism, the results may be considered bounding for near-term tuture reloads.

The results are also conservative for Salem Unit 1, Cycle 11.

The lim.itin9 borori*-

curves used in this report were determined from the most r.. trictive normalized cycle calculations (Unit 2, Cycle 6),

with additional conservatism.

These curves are shown in Figures A5-l and A5-2.

Deagription ot Methodology The boundinq changes in boron concentration which are required to maint*ain SOM during the conservative post-trip cooldown were calculated using the standard Westinqhouae shutdown margin p~ocedure. A brief description of this procedure follows.

Por a given fuel cycle, a table of required boron concentration versus temperature and average burnup is utilized to maintain SDM during shutdown and eooldown.

The values ot boron concentration in the table are calculated using the following assumptions:

1.

No xenon or samariwn pl:- *. :..:.~,-.t* -tw.-:*coi~;

2.

Most reactive control rod stuck out of core, Je The maximum Technical Specification SOM of 1600 pcm is present, and

4.

A margin of safety is included in the maximum boron concentrations as an allowance for calculational uncertaintyr ABB Combustion Engineering Nuclear Services Page A4-4 ot A4-9

BOBIC AC%D CORCSll'l'llATIOH RBDOCTIOH BPPORT IJIBCIDl:ICAL ua*s AND OPBR1TI0Hll AHALYSIS CDl-606 RBV. 00 Implicitly included in the table are the chanqes in total temperature defect and rod worth associated with chanqes in temperature and burnup.

Corrections are made to the values in thid table to account tor the presence or xenon and samarium and for the change in required SDM which occur* at temperature* at and below 2ooor, and to normalize the data to the most neqative moderator teinperature coefficient (MTC) of -44.0 pcm/°F.

The xenon worth correction is determined from a table of total xenon worth as a function of equilibrium power level and ti~e follo~ing plant trip for EOL conditions and is calculated with no boron.

The samarium worth correction is determined from a table of total samarium worth as a function of power level before trip and time following plant trip, and is also calculated with no btiron.

Because the negative reactivity worth of samariWD increases followin9 a plant trip, the value of samarium worth at the time of trip was used in all calculations as an additional conservati.sm.

A reactivity correction versus temperature is made to normalize tha actual most ne9ative EOL MTC to the proposed most n99ative Technical SpeciC~-c1tic;h ~TC v&lue of

-44.0 'f'CIA/°F.

Thi* waa done conservatively by linearly applyin9 the difference between the predicted actual most-ne9ative MTC and -44.0 pcm/°F times the eooldown te11\\perature.

ABB Combustion Engineering Nuclear Services Page A4-5 of A4-9

BORIC ACID COBCJDl'l'RA~IOH REDUCTION BFFORT

'l'BCIDIICAL PSD HD OPBRA'l'lONll ANALYSIS CEN-606 REV. 00 Integral boron worths are used to translate the previously discussed reactivity corrections into chan9es in boron concentration.

These inte9ral boron worth* are obtained from a table of integral boron worth vs. bOron concentration tor temperatures ranqinq from 68*F to S47°P calculated at l!:O'.L.conditions.

The integral worth is used to determine a correction factor for xenon and samariwa worth at the maximum boron concentration and to determine the final boron concentration after accounting for the xenon and samarium, any chan9e in SOM requirement, and the maximWll Technical Specification £0L MTC normalization.

Th* tinal minimum boron concentration as a f'unction of temperature is determined as follows:

a.

The maxi:mum boron concentration is determined from the table of :maximum ~oron concentration.

b.

The reactivity contributions of boron-free xenon and Balllarium, the SDM requirements, and the most neqative MTC noraalization are determined.

c.

The integral boron worth for the maximum boron is read from the table at the shutdown temperature.

d.

A correction tactor is determined from this worth and ie applied to the xenon and samarium worth to account for the reduction in xenon and samarium worth due to the presence of boron.

ABB Combustion Engineering Nuclear Services Page A4-6 of A4-9

BOaIC ACXD COHCENTRA~IOB RBDUC'l'IOlf B~roaT TBCBNICAL BASBS AND OPERATIONAL AMALY8IS Cl:H-60' REV. 00

e.

The corrected xenon and samarium worth, the SOM requirement correction, and the most negative MTC normali~ation reactivity are subtracted from the inteqral boron worth to obtain the net reactivity required to supply minimum SOM.

f.

With this value, the resulting boron concentration required to provide SOX is raad from the inteqral boron worth table.

Verification ot Future Reloads The methodology discussed above will be applied to tuture reload cores to ensure that the required boron concentrations calculated for the reload are bounded by the limiting curves (Figures A4-1 and A4-2) given in this report

• ABB Combustion Engineering Nuclear Services

RIC ACID REDUCTION CONCENTRATIO ORT TECHNICAL BASES AND OPERATIONAL ANALYSES FIGURE A4-1 Sale.m Unit 2 EOC 6 BORAID Analysis MTG = -44, Cool down @ Max Xe., about t= 7 hrs. After Shutdown 1200 1000 E

BOO

a.

a. -5 0

CD "O

600 400

~

200

J i 0

a:

-200

-400 0

/

I v

I I

I I

20 40 i

I I

/

I I

7 I

I I

l I

I i

I I

i I

i I

I i

i I

I I

I I

I I

I I

i l

I i

i i

I I

I I

I I

60 80 100 120 140 160 Time After Shutdown (hours) 1-ARl-WRSO ABB Combustion Engineering Nuclear Services Page A4-8 of A4-9

BORIC ACID REDUCTION CONCENTRATIO iiECHNICAL BASES AND OPERATIONAL A ORT SES FIGURE A4-2 Salem Unit 2 EOC 6 BORAID Analysis MTC = -44, Cooldown @ Eq. Xe., t=22 hrs. After Shutdown 1200 1000 E

0.

800

0. -E soo 0

al

-0 400 (J,)....

• 5 200 i a:

I 0 l

-200 20 v

I I

40 I

/

I v

/ --

I I

I I

I i I

I I I I

I I

I I

I I

60 80 100 120 140 160 180 lime After Shutdown (hours) 1-ARl-WRSO

-606 REV.00 ABB Combustion Engineering Nuclear Services Page A4-9 of A4-9