ML20197B874

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Proposed Tech Specs Pages Revising Proposed Amends in 971101 Request by Expanding Note in LCO 3.3.1.1,Table 3.3.1.1-1,to Allow 12 Hours to Adjust Allowable Value,Specified in COLR, After Sufficient Reduction in Feedwater Temperature
ML20197B874
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 12/18/1997
From:
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20197B855 List:
References
NUDOCS 9712240061
Download: ML20197B874 (16)
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Text

-_..__ _ . _ . __ _ __ . _ . . _ _ _ , _ _ _ . . . _ . . _ _ . . _ . . _ _ - . _ . _ . . _ _ . _ .

1

.4 i

ENCLOSURE 2 i

llRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS,1 AND 2

[

E DOCKET No 4 325 AND 50-324/ LICENSE NOS. DPR 71 AND DPR-62 )

SUPT . LENT TO REQUEST FOR LICENSE AMENDMENTS l FNilANCt . OPTION 1 A STA131LITY TECilNICAL SPECIFICATIONS i j

l i

i l

I p  ;

I MARKED UP IMPROVi?D TECilNICAI, SPECIFICATION PAGES UNIT 1  !

i i t

r 9

s k

't O 4 1

--;_.__.-._.-_. . . _ , . , - .. _ - . . . _ . . . ;_ . ._ a , , ._._ __.-.-___uw.~

RPS Instrumentation 3.3.1.1

[ f able 3.3.1.1 1 (page 1 of 3) teactor Protection systen Instrwentation APPLICABLE COND1110N1 M00ts On t[QulttD REftathCfD OTNtt CHAkkit$ FRCM

$PECIFl[0 P(a TRIP REQUltID $URVt lLLANCE ALLOWABLE FUNCil0N CON 0lflohl $fSTEM ACil0N 0.1 REQUlt(MENTS VALLE

1. Intermediate tanee Munitors
a. Neutron Flum -Nish 2 3 C tt 3.3.1.1.2 s 120/125

$t 3.3.1.1.4 divletore of st 3.3.1.1.5 full scale 14 3.3.1.1.6 SR 3.3.1.1.7 st 3.3.1.1.13 54 3.3.1.1.15 5(*) 3 N st 3.3.1.1.2 s 120/125 tt 3.3.1.1.4 divletons of SR 3.3.1.1.5 full scale

$4 3.3.1.1.13 52 3.3.1.1.15

b. Inop 2 3 G SR 3.3.1.1.4 NA st 3.3.1.1.5 st 3.3.1.1.15

$(a) 3 N $2 3.3.1.1.4 NA

$R 3.3.1.1.5 SR 3.3.2.2.15

2. Averste Power Range Monitore
s. Neutron Flus -Migh, 2 2 G SR 3.3.1.1.1 5 151 RTP Startm SR 3.3.1.1.4 st 3.1.1.1.5 st 3.3.1.1.7 st 3.3.1.1.8

$t 3.3.1.1.11

$R 3.3.1.1.15 SR 3.3.1.1.17

b. Flow elesed sinuteted 1 2 F SR 3.3.1.1.1 (b)

Thermal Power -Nigh SR 3.3.1.1.3 st 3.3.1.1.5 st 3.3.1.1.8 SR 3.3.1.1.11

$2 3.3.1.1.14 st 3.3.1.1.15 st 3.3.1.1.18 (continued)

(a) Vith any control rod withdra.m f ran a core cell containing one or more tuet asseelies.

(b) Allowable Values specified in the Cott.

AIkaakte Ulve r4Wicadion reguinsd b Ce y CCLR due lo redoc-tivrts Meedwader-tempecakore nm3 he clala.yect for uph IA k urs.

Brunswick Unit 1 3.3 8 Amendment No.

i RPS Instrumentation B 3.3.1.1 1

BASES (a. .+ i APPLICABLE 2.b. Averaae Power Ranae Monitor Flow Biased Simulated SAFETY ANALYSES, Thermal Power-Hioh (continued)

LCO, and ,

APPLICABILITY gross violation of the licensed operating domain. Operation outside the licensed operating domain may result in anticipated operational occurrences and postulated accidents being initiated from conditions beyond those assumed in the safety analysis. Operation within the licensed operating gde domain also ensures compliance with General Design j Criterion 12.

General Design Criterion 12 requires protection of fuel S thermal safety limits from conditions caused by c>

neutronic/ thermal hydraulic instability. Neutronic/ thermal v hydraulic instabilities result in power oscillations which ed could result in exceeding the MCPR SL. f

't The area of the core power and flow operating domain susceptible to neutronic/ thermal hydraulic instability is affected by the fraction of Core Boiling Boundary (LCO 3.2.3, FCBB). " Setup" and normal ("non-Setup") Average '

Power Range Monitor Flow Biased Simulated Thermal Power-High Function Allowable Values are specified in _the 1 Core Operating Limits Rcport (COLR)CWhen the normal value -

1 is selected protection against neutronic/ thermal hydraulic instability is provided by preventing operation in the susceptible area of the operating domain during operation outside the Restricted Region of the operating domain specified in the COLR with the FCBB limit not required to be met. When the ' Setup" value is selected meeting the FCBB limit provides protection against neutronic/ thermal hydraulic instability.

&W rip re[ere nce " Setup" and "non-Setup" values are selected by operator det.getI446eQ) manipulation of the recessed Setup button on each flow i

I jag g g P control trip reference card. Selection of the " Setup" value is intended only for planned operation in the Restricted l

Q W 5 d p# e/x.5, j v

Region as specified in the COLR. Operation in the Restricted Region with the Average Power Range Monitor Flow l Biased Simulated Thermal Power-High Function in " Setup" requires the FCBB limit to be met and is not generally consistent with normal power operation.

The Average Power Range Monitor Flow Blased Simulated Thermal Fower-High Function uses a trip level generated by the flow control trip reference card based on recirculation loop drive flow. The propei representation of drive flow as i

I (continued)

(

Brunswick Unit 1 B 3.3-9 Revision No.

4 Itisert A The area of the core power and flow operating domain susceptible to neutronic/ thermal hydraulic instability can be affected by reactor parameters such as reactor inlet feedwater temperature. Two complete and independent sets of Average Power Range hionitor Flow Biased Simulated Thermal Power -liigh Function Allowable Values are specilled in the CORE OPERATING LIMITS REPORT (COLR). Set 1 (Normal Trip Reference Set) provides protection against neutronic/ thermal hydraulic instability during expected reactor operations Set 2 (Alternate Trip Reference Set) provides protection against neutronic/ thermal hydraulic instability during rcactor operating conditions requ'. ring added stability protection .'.nd is conservative with respect to Set 1. Feedwater temperature values requiring transition between flow control trip reference card sets are specified in the COLR. In the event o ra feedwater temperature reduction, Allowable Value modificatien (from the Normal Trip Reference Set to the Alternate Trip Reference Set)is required to preserve the margin associated with the potential for the onset of neutronic/ thermal hydraulic instability which existed prior to the feedwater temperature reduction. The Allowable Value modification required by the COLR may be delayed up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to allow time to adjust and check the adjustment of each flow control trip reference card. At the end of the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> period, the Allowable Value modifications must be complete for all of the required channels or the applicable Condition (s) must be entered and the Required Actions taken The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> time period is acceptable based on the low probability of a neutronic/ hydraulic instability event and the continued protection provided by the flow control trip reference card. In addition, when the feedwater temperature reduction results in operation in either the Restricted Region or Monitored Region, the requirements for the Period Ilased Detection System (LCO 3.3.1.1, Period llased Detection System (PBDS))

provide added protection against neutronic/ thermal hydraulic instability during the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> time period.

. l ENCLOSURE 3 11RUNSWICK STEAh! ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 AND 50 324/ LICENSE NOS. DPR-71 AND DPR-62 SUPPLEh1ENT TO REQUEST FOR LICENSE Ah1ENDMENTS ENilANCED OPTION 1 A STABILITY TECilNICAL SPECIFICATIONS 4

MARKED-UP IMPROVED TECliNICAI, SPECIFICATION PAGES - UNIT 2

. -~.,.-..--..---.,..,n.- - - . . , ,. . , - - , , - . , , - , . . _ , . , . , , - -

RPS Instrumentation I

3.3.1.1 f abli 3.3.1.1 1 (page 1 of 3) 4e tesctor Protection System Instrisnentation APPLICA8LE CONDIT10h5 KEtt A tt0UIRED t!FittWCfD afkta CHAubtL S faces SPEClfl[D Pit TRIP tt0Ultt0 suavglLLANCE ALLCWASLE FUECil0N CONDlilous $YSTEM ACil0N D.1 at0UlttMEWil VALUE

1. Interinedlete Range monitors
a. keutrcn Flux -Nigh 2 3 G sa 3.3.1.1.2 s 120/125 sa 3.3.1.1.4 divisions of sa 3.3.1.1.5 futt scale sa 3.3.1.1.6 sa 3.3.1.1.7 sa 3.3.1.1.13 sa 3.3.1.1.15 5(*) 3 N sa 3.3.1.1.2 s 120/125 st 3.3.1.1.4 divisions of sa 3.3.1.1.5 futt scale sa 3.3.1.1.13 sa 3.3.1.1.15
b. Irg 2 3 G sa 3.3.1.1.4 WA sa 3.3.1.1.5 sa 3.3.1.1.15 5(e) 3 , g, 3,3,g,9,4 gg sa 3.3.1.1.5 sa 3.3.2.2.15 i 2. Average Power Range konttore
e. Woutron Flux -Nish, 2 2 G sa 3.3.1.1.1 s 15% RTP starttp sa 3.3.1.1.4 sa 3.3.1.1.5 sa 3.3.1.1.7 sa 3.3.1.1.8 sa 3.3.1.1.11 sa 3.3.1.1.15 sa 3.3,1,1,17
b. Flow Bissed sleuteted 1 2 7 st 3.3.1.1.1 (b)

Thorinal Power -Nigh sa 3.3.1.1.3 Sa 3.3.1.1.5 sa 3.3.1.1.8 sa 3.3.1.1.11 sa 3.3.1.1.14 sa 3.3.1.1.15 sa 3.3.1.1.18 (contirued)

(a) Vith any control rod withdrawn f *.m a core cent containing one or more fuel assembtles.

(b) Allowable values specified in the Cott. 3 lonwLle W/Oc mulifict-hb. re oirec( h4 tLe couR cloe 4 l

rcotoct iou icAce/ Met-feyd Morm Atm3 6e.Cie/qcd Qc up 4o M. bons j Brunswick Unit 2 3.3-8 Amendment No.

RPS Instrumentation

- B 3.3.1.1  ;

,[ BASES  ;

"(b ,

APPLICABLE 2.b. Averaae Power Ranae Monitor Flow Biased Simulated SAFETY ANALYSES, Thermal Power-Hiah (continued)

LCO, and 4 APPLICABILITY gross violation of the licensed operating domain. Operation outside the licensed operating domain may result in anticipated operational occurrences and sostulated accidents ,

being initiated from conditions beyond taose assumed in the . .

safety analysis. Operation within the licensed operating domain also ensuras compliance with Genercl Design o Criterion 12. u General Design Criterion 12 requires protection of fuel h thermal safety limits from conditions caused by  %-

neutronic/ therm 1 hydraulic instability. Neutronic/ thermal &

hydraulic instabili1 ms result in power oscillations which a, >

hsed A ~

could result in exceeding the MCPR SL.

The area of the core power and flow operating domain susceptible to neutronic/ thermal hydraulic instability is y

affected by the Frac'.lon of Core Boiling Boundary N

(LC03.2.3,FCBB). ' Setup" and normal ("non Setup") Average' Power Range Monitor Flow Biased Simulated Thermal Power-High Function Allowable Values are specified in the Core Operating Limits Report (COLR)C When the normal value

i. is selected protection against neutronic/ thermal hydraulic
instability is provided by preventing operation in the susceptible area of the operating domain during operation outside the Restricted Region of the operating domain specified in the COLR with the FCBB limit not required to be '

met. When the " Setup" value is selected meeting the FCBB i limit provides protection against neutronic/ thermal hydraulic instability.

hael hip re leyence " Setup" and "non-Setup" values are selected by operator ggg manipulation of the recessed Setup button on each flow

, control trip reference card. Selection of the " Setup" value melude.s %rbp

  • a ul is intended only for planned operation in the Restricted

" nn y-sebp " A /ocs. Region as specified in the COLR. Operatien in the Restricted Region with the Average Power Range Monitor Flow Biased Simulated Thermal Power-High Function in " Setup" requires the FCBB limit to be met and is not generally consis+.ent with normal power operation.

The Average Power Range Monitor Flow Biased Simulated Thermal Power-High Function uses a trip level generated by the flow control trip reference card based on recirculation '

loop drive flow. The proper representation of drive flow as (continuedl Brunswick Unit 2' B 3.3-9 Revision No.

1 l

l ,

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

l l

i insert A The area of the core power and flow operating domain susceptible to neutronic/ thermal hydraulic instability can be affected by reactor parameters such as reactor inlet feedwater temperature. Two complete and independent sets of Average Power Range Monitor Flow liiased Simulated Thermal Power - liigh Function Allowable Values are specified in the CORE OPERATING LIMITS REPORT (COLR). Set 1 (Normal Trip Reference Set) provides protection against neutronic/ thermal hydraulic instability during expected reactor operations. Set 2 (Alternate Trip Reference Set) provides protection against neutronic/ thermal hydraulic instability during reactor operating conditions requiring added stability protection and is conservative with respect to Set 1. Feedwater temperature values requiring transition between flow control trip reference card sets are specified in the COLR In the event of a feedwater temperature reduction, Allowable Value modification (from the Normal Trip Reference Set to the Alternate Trip Reference Set)is required to preserve the margin associated with the potential for the onset of neutronic/ thermal hydraulic instability which existed prior to the feedwater temperature reduction. The Allowable Value modification required by the COLR may be delayed up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to allow time to adjust and check the adjustment of each flow control trip reference card. At the end of the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> p:ried, the AllowaF 'ue modifications must be complete for all of the required channelt or the applicable Conwtion(s) must be entered and the Required Actions taken. The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> time period is acceptable based on the low probability of a neutronic/ hydraulic instability event and the continued protection povided by the flow control trip reference card. In addition, when the feedwater temperature reduction results in operation in either the Restricted Region or Monitored Region, the requirements for the Period Based Detection System (LCO 3.3.1.1, Period 11ased Detection System (PBDS))

provide added protection against neutronic/theimal hydraulic instability during the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> time period.

. I t

liNCLOSURE 4 1

PRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 ,

DF. .ET NOS. 50-325 AND 50 324/ LICENSE NOS. DPR-71 AND DPR-62 SUPPLEMENT TO REQUEST FOR LICENSE Ah1ENDMENTS ENilANCED OPTION 1 A STAlllLITY TECllNICAL SPECIFICATIONS TYPED IMPROVED TliCilNICAL SPl?CIFICATION PAGES - UNIT I I

1 ,

l l:

r

i RPS Instrumentation i 3.3.1.1 l febte 3.3.1.1 1 (pers 1 of 3) ,

Reector Protectl6.e System Instr seenteilen l l

i APPLICABLE CONDITlout i MODES 04 M euleED atFEnfuCED l OTNER CNANNELS ' Ret 1 i

SPECIFit0 PER TalP P':UIRED suaVEILLA tt ALLOWABLE FUNCfl0N CONDill0NS SYSTEM ACfl0N D.1 ateUInf8ENTS VALUE

1. Interem.;ete tenee Monitors
a. Newtron f tua -Mish 2 3 0 sa 3.3.1.1.2 s 120/125 sa 3.3.1.1.4 divisions of SR 3.3.1.1.5 futt scale se 3.3.1.1.6 sa 3.3.1.1.7 sa 3.3.1.1.13 sa 3.3.1.1.15 5(e) 3 p sa 3.3.1.1.2 s 120/125 sa 3.3.1.1.4 divisions of sa 3.3.1.1.5 fuit ecele sa 3.3.1.1.13 sa 3.3.1.1.15
b. hop 2 3 C sa 3.3.1.1.4 NA sa 3.3.1.1.5 sa 3.3.1.1.15

$(e) 3 N sa 3.3.1.1.4 NA sa 3.3.1.1.5 54 3.3.2.2.15

2. Averesa Powgr eense Monitore
e. Woutron Flus -Mish, t 2 0 sa 3.3.1.1.1 s 15% afP s t ort, sa 3.3.1.1.4 sa 3.3.1.1.5 sa 3.3.1.1.7 sa 3.3.1.1.8 sa 3.3.1.1.11 sa 3.3.1.1.15 SR 3.3.1.1.17
b. Flow slaaed slauteted 1 2 F sa 3.3.1.1.1 (b)

Theriest Power -411th sa 3.3.1.1.3 sa 3.3.1.1.5 sa 3.3.1.1.8 sa 3.3.1.1.11 sa 3.3.1.1.14 sa 3.3.1.1.15 sa 3.3.1.1.18 (continued)

(a) With any control rod withdre m free a core er:t contelnins one or more fuel eseeabtles.

(b) Attowable Vetues speelflod in the Cola. Attoweble Vetue sedification reculred by the COLA due to redtettons in feeduster temperature may be deleyed for w to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Brunswick Unit 1 3.3-8 Amendment No.

RPS Instrumentaticn B 3.3.1.1 BASES  ;

- APPLICABLE l b. Averaae Power Ranae Monitor Flow Biased Simulated SAFETY ANALYSES, "hermal Power-Hiah (continued) ,

LCO, and APPLICABILITY gross violation of the licensed operating domain. Operation '

outside the licensed operating domain may result in anticipated operational occurrences and postulated accidents  :

being initiated from conditions beyond those assumed in the safety analysis. Operation within the licensed operating domain also ensures compliance with General Design Criterion 12.

General Design Criterion 12 requires protection of fue) '

thermal safety limits from conditions caused by .

neutronic/ thermal hydraulic instability. Neutronic/ thermal hydraulic instabilities resuit in power oscillations which_ -

could result in exceeding the MCPR SL.

The area of the core power and flow operating domain suscentible to neutronic/ thermal hydraulic instability can ,

be affected by reactor parameters such as reactor inlet feedwater temperature. Two complete and independent sets of Average Power Range Monitor flow Biased Simulated Thermal l Power-High Function Allowable Values are specified in the COREOPERATINGLIMITSREPORT(COLR). Set 1 (Normal Trip

- Reference Set) provides protection against neutronic/ thermal i hydraulic instability during expected operations. Set 2 ,

(Alternate Trip Reference Set) provides protection against neutronic/ thermal hydraulic instability during reactor .

operating conditions requiring added stability protection '

and is conservative with respect to Set 1. Feedwater temperature values requiring transition between the flow control trip reference card sets are specified in the COLR.

l In the ever.t of a feedwater temperature reduction, Allowable  :

Value modification (from the Normal Trip Reference Set to the Alternate Trip Reference Set) is required to preserve

! the margin associated with the potential for the onset of neutronic/ thermal hydraulic instability, which existed prior L to the feedwater temperature reduction. The Allowable Value I modification required by the COLR may be delayed up to

l. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to allow time to adjust and check the adjustment of

! each flow control trip reference card. At the end of the

12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> period, the Allowable Value modifications must be -

I complete for all of the required channels _or the applicable  ;

Condition (s) must be entered and Required Actions taken.

The-12 hour time period is acceptable based on the low probability of a neutronic/ thermal hydraulic instability (continued)

E Brunswick Unit 1- B 3.3-9 Revision No.

i

---y -, ,.-w ,,c,- ,,-w -w-,-mm y gw , , , ,7y,n-wr-ei=-wwe-- w --- u - - n-- es me s evi - - w .r-.* -- - - - - - - -- -- -r-= f

RPS Instrumenthtion B 3.3.1.1 4

BASES APPLICABLE 2.h. ... Average Power Ranae Monitgr_flpw Biased Simulated SAFETY ANALYSES, Thermal Power-Hioh (continued)

LCO, and APh.ICABILITY event and the continued protection provided by the flow control trip reference card. In addition, when the feedwater temperature reduction results in operation in either the destricted Region or tionitored Region, the requirements for the Period Based Detection System (LCO 3.3.1.3, Period Based Detection System (PBDS)), provide added protection against neutronic/ thermal hydraulic instability during the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> time period.

The area of the core power and flow operating domain susceptible to neutronic/ thermal hydraulic instability is affected by the Fraction of Core Boiling Boundary (LCO 3.2.3, FCBB). " Setup" and normal ("non-Setup") Average Power Range Monitor Flow Biased Simulated Thermal Power-High Function Allowable Values are specified in the COLR for each trip reference set. When the normal value is selected protection against neutronic/ thermal hydraulic instability is provided by preventing operaticn in the susceptible area of the operating domain during operation outside the Restricted Region of the operi. ting doniain specified in the COLR with the FCBB limit not required to be met. When the " Setup" value is selected meeting the FCBB limit provides protection against neutronic/ thermal hydraulic instability.

Each trip reference set (Set I and Set 2) includes " Setup" and "non Setup" values. " Setup" and "non Setup" values are selected by o>erator manipulation of the recessed Setup button on eac1 flow control trip reference card. Selection of the " Setup" value is intended only for 31anned operation in the Rastricted Region as specified in tie COLR.

Operation in the Restricted Region with the Average Power Range Monitor Flow Biased Simulated Thermal Power-High Function in " Setup" requires the FCBB limit to be met and is iiot generally consistent with normal power operation.

The Average Power Range Monitor Flow Biased Simulated Thermal Power-High Function uses a trip level generated by the flow control trip reference card based on recirculation loop drive flow. T!ie proper representation of drive flow as (continued)

Brunswick Unit 1 B 3.3-10 Revision No.

I liNCLOSURE5 .

HRUNSWICK STEAh! ELECTRIC PLANT, UNIT NOS.1 AND 2 '

DOCKET NOS. 50 325 AND 50-324/ LICENSE NOS. DPR 71 AND DPR 62 SUPPLEh1ENT TO REQUliST FOR LICENCE Ah1ENDhiENTS ENilANCED OPTION 1 A STABILITY TECllNICAl, SPECIFICATIONS r

a l

F TYPliD lhiPROVED TECIINICAL SPECIFICATION PAGES -(JN_[T_2 4

_ - y o , . ., y _, ,- m_,.. ,

._ . . ~ _ ._. . - - - -- .-- _~

RPS Instrumentatien 3.3.1.1 Table 3.3.1.1 1 (pose 1 of 3)  !

Reactor Protection $yeten Instruonntatten l l

APP'.lCAttt Coel130Ns M@Es Os ' ateUlsE0 M ff aENCAD JTNEa CNANNEls fa0N sPECIFit0 Pts talP MOUlstD sueWtlLLANCE ALLOWAsLE FUNCil0N CONDill0Ns sYstEN ACil0N D.1 steuleEMENis VALUE i

1. Intermedicto Renee Monttore
e. Neutron Itun .--Nigh 2 3 G sa 3.3.1.1.2 s 120/125 i sa 3.3.1.1.4 divletone of sa 3.3.1.1.5 futt scale M 3.3.1.1.6 sa 3.3.1.1.7 '

sa 3.3.1.1.13 sa 3.3.1.1.15 5I*3 3 N sa 3.3.1.1.2 s 120/125 sa 3.3.1.1.4 divisions of sa 3.3.1.1.5 full acete sa 3.3.1.1.13 M 3.3.1.1.15

b. Inop 2 3 0 sa 3.3.1.1.4 NA sa 3.3.1.1.5 sa 3.3.1.1.15 5(8I 3 N sa J.3.1.1.4 NA sa 3.3.1.1.5 sa 3.3.2.2.15
2. Average Power Range Monttoro
e. Neutron flus -Nlph, 2 2 C sa 3.3.1.1.1 s 15X RTP startup sa 3.3.1.1.4 sa 3.3.1.1.5 sa 3.3.1.1.7 sa 3.3.1.1.8 sa 3.3.1.1.11 sa 3.3.1.1.15 sa 3.3.1.1.17
b. Flow slesed slaulated 1 2 F sa 3.3.1.1.1 (b)

Thermet Power -Migh sa 3.3.1.1.3 sa 3.3.1.1.5 sa 3.3.1.1.8 sa 3.3.1.1.11 la 3.3.1.1.14 sa 3.3.1.1.15 Sa 3.3.1.1.18 (continued)

(a) With any control rod withdr.am from a core cett contelning one or more fuel sess e lles.

(b) Allowebte Vetuvo spectfled in the Cola. Attowebte Vetue modificetton regJired by the COLA dae to reductf une ir feedwater temperature may be deleyed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Brunswick Unit 2 3.3-8 Amendment No. ,

- , --n --, , > - - , - ,, , , , . - - - . . - - ~ . . , --,n> , ,-, -,

l l

RPS Instrumentatisn ,

8 3.3.1.1 1

. I l

BASES APPLICABl,E N.b. Averaae Power Ranae Monitor Flow Wiased Simulated i SAFETY ANALYSES, "hermal Power-Hioh (continued)

LCO, and APPLICABILITY gross violation of the licensed operating domain. Operation outside the licensed operating do, main may result in anticipated operational occurrences and >ostulated accidents being initiated from conditions beyond tiose assumed in the safety analysis. Operation within the licensed operating

- domain elso ensures compliance with General Design Criterion 12.

General Design Criterion 12 requires protection of fuel thermal safety limits from conditions caused by neutronic/ thermal hydraulic instability. Neutronic/ thermal hydraulic instabilities result in power oscillations which ,

could result in exceeding the MCPR SL.

The area of the core power and flow operating domain susceptible to neutronic/ thermal hydraulic instability can 4 be affected by reactor parameters such as reactor inlet feedwater temperature. Two complete and independent sets of -

Average Power Range Monitor Flow Biased Simulated Thermal Power-High Function Allowable Values are specified in the CGRE OPERATING LIMITS REPORT (COLR). Set 1 (Normal Trip Reference Set) )rovides protection against heutronic/ thermal hydraulic instasility during expected operations. Set 2 (Alternate Trip Referarce Set) provides protection against neutronic/ thermal hydraulic instability during reactor operating conditions requiring added stability protection and is conservative with respect to Set 1. Feedwater t temperature values requiring transition between the flow control trip reference card sets are specified in the COLR.

In the event of a feedwater temperature reduction, Allowable Value modification (from the Normal Trip Reference Set to the Alternate Trip Reference Set) is required to preserve the margin associated with the potential for the onset of neutronic/ thermal hydraulic instability, which existed prior to the feedwater temperature reduction. The Allowable Value modification required by the COLR may be delayed up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to allow time to adjust and check the adjustment of each flow control trip reference card. At the end of the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> period, the Allowaole Value modifications must be complete for all of the required channels or the applicable Condition (s) must be entered and Required Actions taken.

The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> time period is acceptable based on the icw l

probability of a neutronic/ thermal hydraulic instability I (continupJ1 Brunswick Unit.2 B 3.3 Revision No.  ;

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RPS Instrumentation B 3.3.1.1 BASES APPLICABLE 2.b. Averace Power Rance Monitor Flow Biased Simulated SAFETY ANALYSES, Thermal Power-Hiah (continued)

LCO, and APPLICABILtTY event and the continued protection provided by the flow control trip reference card. In addition. when the l feedwater temperature reduction results in operation in '

either the Restricted Region or Monitored Region, the requirements for the Period Based Detection System (LCO3.3.1.3,PeriodBasedDetectionSystem(PBDS)), provide added protection against neutronic/ thermal hydraulic instability during the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> time pericd.

The area of the core power and flow operating domain susceptible to neutronic/ thermal hydraulic instability is affected by the Fraction of Core Boiling Boundary (LCO 3.2.3, FCBB). " Setup" and normal ("non-Setup") Average Power Range Monitor Flow Biased Simulated Thermal Power-High Function Allowable Values are specified in the COLR for each trip reference set. When the normal value is selected protection against neutronic/ thermal hydraulic instability is provided by preventing operation in the suscernble area of the operating domain during operation outside the Restricted Region of the operating domain specified in the COLR with the FCBB limit not required to be met. When the " Setup" value is selected meeting the FCBB limit provides protection against neutronic/ thermal hydraulic instability.

Each trip reference set (Set I and Set 2) includes " Setup" and "non-Setup" values. " Setup" and "non-Setup" values are selected by 03erator manipulation of the recessed Setup button on ea.n flow control trip reference card. Selection of the " Setup" value is intended only for planned operation in the Restricted Rsgion as specified in the CCtR.

Operation in the Restricted Region with the Average Power Range Monitor flow Biased Simulated Thermal Power-High Function in " Setup" requires the FCBB limit to be met and is not generally consistent with normal power operation.

The Average Power Range Monitor Flow Biased Simulated Thermal Power-High Function uses a trip level generated by the flow control trip reference card based on recirculation loop drive flow. The proper representation of drive flow as (continued) i 1

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! Brunswick Unit 2 B 3.3-10 Revision No.

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