ML20086H019

Rev 11A to Pilgrim Nuclear Power Station PNPS Colr

ML20086H019
Person / Time
Site:	Pilgrim
Issue date:	04/19/1995
From:	BOSTON EDISON CO.
To:
Shared Package
ML20086H018	List: ML20086H013 ML20086H019 ML20086H021
References
NUDOCS 9507170379
Download: ML20086H019 (25)

Text

._

l PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT l (CYCLE 11) i l

APPROVED: 8)'

Operations S%pon Division Manager Date APPROVED: ///3M2M)d Yb d[ i/

Nuclear Engineering Services Depanment Manager Date l l

APPROVED: b #

O R.C MJEs

• T N f 4/ /.1/fr

)

Operatip Review Committee Date l

. i APPROVED:  ! M h"' I ///f/[

Pla t Manager /' Mate APPROVED:

StatVn Di or " ' ' /7/9f Ifate~ !

1 l

REVISION 11 A PAGE 1 OF 25 9507170379 950713 PDR ADOCK 05000293

_ P, PDR ._,..._____,_..____,,_._2

1

}

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT l

IARLE QEf0NTENTS l E_ age TITLE / SIGNATURE PAGE. .. . . .I i TABLE OF CONTENTS. ,. . . .

.2 i

r RECORD OF REVISIONS. . . .

.3 LIST OF TABLES. .. . . . .4 f

1 LIST OF FIGURES . . . .. . . .

.5

1.0 INTRODUCTION

.6 2.0 INSTRUMENTATION TRIP SETTINGS . .

7 1

2.1 APRM Flux Scram Trip Setting (Run Mode) .7 2.2 APRM Rod Block Trip Setting (Run Mode).. .7  ;

.I 2.3 Rod Block Monitor Trip Setting.. .8 l

l 3.0 CORE OPERATING LIMITS .9 3.1 Average Planar Linear Heat Generation Rate ( APLHGR) . ,

.9 3.2 Linear Heat Generation Rate (LHGR) . .9 .

3.3 Minimum Critical Power Ratio (MCPR). . . .17 3.4 Power 510w Relationship. . . . 23 4.0 REACTOR VESSEL CORE DESIGN.. .

. 23

5.0 REFERENCES

. 23 l

l I

REVISION 11 A PAGE 2 OF 25 i

4

• PILGRLN1 NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT REf0RD OF REVISIONS Revision Effective Date Descrintion SA Effective date based on Applicable for use during issuance oflicense Cycle 8 Operation amendment by NRC 9A Effective date based on Applicable for use during issuance oflicense Cycle 9 operation amendment by NRC for ARTS and SAFER /GESTR 10A Effective date based on Applicable for use during initial stanup of Cycle 10 Cycle 10 Operation 11A Effective date based on Applicable for use during initial stanup of Cycle 11 Cycle 11 Operation REVISION 11 A PAGE 3 OF 25

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

t PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT l- LLS_T OF TABLES Number Title ._Pagg i-3.2-1 LHGR Operating Limits - 10 3.3 MOC MCPR Operating Limits 19 '

3.3-2 EOC MCPR Operating Limits 20 r

t t

s

\

l i

5 h

REVISION 11 A PAGE 4 OF 25

%. . - - . . . _ . _ . ..m. . . - , . , .m-,,..,...mme. -. , . ~ , - . . , - - , , , . , , , _ . . -.~,.m. -

,,,m-.,-, -,r,-,- v.~,, ....-,.....-...,,....,....,_.we.,--

l . .

}. PILGRIhi NUCLEAR POWER STATION i PNPS CORE OPERATING LIMITS REPORT LIST OF FIGURES Number Title P_agg 3.1-1 hiaximum Average Planar Linear Heat Generation i1 Rate (MAPLHGR) for Fuel Type BP8DRB300 3.1-2 Maximum Average Planar Linear Heat Generation 12 Rate (MAPLHGR) for Fue! Type BP8DQB323 3.1-3 Maximum Average Planar Linear Heat Generation 13 l Rate (MAPLHGR) for Fuel Type BP8HXB355 3.1-4 Maximum Average Planar Linear Heat Generation 14 Rate (MAPLHGR) for Fuel Type BP9 HUB 378 3.1-5 Flow-Dependent MAPLHGR Factor (MAPFACr) 15 I 3.1-6 Power-Dependent MAPHLGR Factor (MAPFACp) 16 3.3- 1 Flow-Dependent MCPR Limits (MCPRr) 21 3.3-2 Power-Dependent MCPR Limits (MCPRp) 22 l 3.4-1 Power / Flow Operating Map 24 4.0-1 Reactor Vessel Core Loading Pattern 25 REVISION 11 A PAGE 5 OF 25

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

PILGRIh1 NUCLEAR POWER STATION PNPS CORE OPERATING LIhilTS REPORT

1.0 INTRODUCTION

This report provides the cycle-specific limits for operation of the Pilgrim Nuclear l Power Station (PNPS) during Cycle i1. In this repon Cycle 11 will frequently be i referred to as the present cycle.

I i

! Although this report is not part of the PNPS Technical Specifications, the l Technical Specifications refer to this repon for the applicable values of the i

fcilowing fuel-related parameters:

Reference Technical Specification APRhi Flux Scram Trip Setting (Run hiode) Tab!e 3.1.1 APRhi Rod Block Trip Setting (Run hiode) Table 3.2.C-2 Rod Block hionitor Trip Setting Table 3.2.C-2 Average Planar Linear Heat Generation Rate 3.11. A Linear Heat Generation Rate (LHGR) 3. I 1.B hiinimum Critical Power Ratio (h1CPR) 3.11.C Power / Flow Relationship 3. I 1.D Reactor Vessel Core Design 5.2 If any of the core operating limits in this report are exceeded, actions will be taken as defined in the referenced Technical Specification.  ;

The core operating limits in this report have been established for the present cycle using the NRC-approved methodology provided in the documents listed both in Section 5.0, References, and in Technical Specification 6.9.A 4. These limits are  !

established such that the applicable limits of the plant safety analysis are met.

l l

I REVISION 11 A PAGE 6 OF 25

5 l

i PILGRIh1 NUCLEAR POWER STATION i h PNPS CORE OPERATING LlhilTS REPORT

'f

i 2.0 INS _IBUhfEFTATLOE TRIP SETTINGS:  !

2.1 APRN1 Flux Scram Trio Settine (Run hiode)

Reference _T.echnical Specificationr Table 3.1.1,3.1.B.1  ;

i When the mode switch is in the run position, the average power range '

monitor (APRhi) flux scram trip setting (S.) shall be:

i S, s 0.66 W + 69%

with a clamp at 120% of rated core thermal power and i l i l S. = APRh1 flux scram trip setting in percent of rated thermal l power (1998 MW). i

)

i W= Percent of drive flow required to produce a rated core flow  !

of 69 h11b/hr.  !

The APRhi flux scram trip setting is valid only for operation using two recirculation loops. Operation with one recirculation loop out of service is restricted by License Condition 3.E. '

In accordance with Technical Specification Table 3.1.1, Note 15, for no combination ofloop recirculation flow rate and core thermal power shall <

the APRh! flux scram trip setting be allowed to exceed 120% of rated I thermal power. t h

2.2 APRhi Rod Block Trio Settine (Run hiode)

Reference Technical Specifications: Table 3.2.C-2, 3.1.B. !

When the mode switch is in the run position, the average power range monitor (APRhi) rod block trip setting (Sw) shall be:

Sg3 s 0.66 W + 62%

with a clamp at 115% of rated core thermal power and

~

Sna = APRh1 rod block trip setting in percent of rated thermal power (1998 NfW,).

W= Percent of drive flow required to produce a rated core flow of 69 hilb/hr.

REVISION 11 A PAGE 7 OF 25 C

PILGRIM NUCLEAR POWER STATION )

l PNPS CORE OPERATING LIMITS REPORT i

~  ;

2.2 ' 'APRM Rod Block Triplening_1Run Mode.) (Continued)  !

5

The APRM rod block trip setting is valid only for operation using two  !

recirculation loops. Operation with one recirculation loop out of service is

} restricted by License Condition 3.E.

1 2.3 \

Rod Block Monitor Trio Setting l>

l" Reference Technical Specification: Table 3.2.C-2  !

t Allowable values for the power-dependent Rod Block Monitor trip

, setpoints shall be:

i t

3 Reactor Power, P Trip Setpoint i

(% of Rated) (% of Reference Level) '

a

[;

_ P s 25.9 25.9 < P s 62.0 Not applicable (All RBM Trips Bypassed) 120

~

i 62.0 < P s 82.0 115 82.0 < P 110  !

l The allowable value for the RBM downscale trip setpoint shall be 2 94.0%

3 of the reference level. The RBM downscale trip is bypassed for reactor

j. power s 25.9% of rated.

4 1

i 1

i i

l 1

I REVISION 11 A. PAGE 8 OF 25 3

PILGRIh1 NUCLEAR POWER STATION PNPS CORE OPERATING LIhilTS REPORT i 3.0 CORE OPERATINQ_LIh1IT.S.

3.1 Averace Planar Linear Heat Generation Rate (APLHGR)

Reference TechniqaLSp_ecification: 3.11. A 4

During power operation, APLHGR for each fuel type as a function of axial  ;

location and average planar exposure shall not exceed the applicable

{

limiting value. The applicable limiting value for each fuel type is the

^

smaller of the flow- and power-dependent APLHGR limits, hiAPLHGRr j and MAPLHGR,,. The flow-dependent APLHGR limit, hiAPLHGRr, is the product of the hiAPLHGR flow factor, hiAPFACF, shown in Figure 3.1-5 and the MAPLHGR for rated power and flow conditions. The power-dependent APLHGR limit, hiAPLHGRe, is the product of the ,

hiAPLHGR power factor, hiAPFACp, shown in Figure 3.1-6 and the '

hiAPLHGR for rated power and flow conditions. The hiAPLHGR for rated power and flow conditions for each fuel type as a function of axial location and average planar exposure are based on the approved methodology referenced in Section 5.0 and programmed in the plant process computer. The MAPLHGR for rated power and flow conditions for the limiting lattice in each fuel type (excluding natural uranium) are presented in Figures 3.1-1 through 3.1-4.

The core loading pattern for each type of fuel in the reactor vessel is shown for the present cycle in Figure 4 0-1.

3.2 Linear Heat Generation Race (LHGR)

Reference Technical Specifigation: 3.1 IB During reactor power operation, the LHGR of any rod in any fuel assembly at any axial location shall not exceed the limits presented in Table 3.2-1.

%)

i REVISION 11 A PAGE 9 OF 25

)

PILGRIM NUCLEAR POWER STATION i PNPS CORE OPERATING LIMITS REPORT l

Table 3.2-1 i

LHGR Operatine Lirnits '

LHGR Operating i Fuel Tvoe . Limit (KW/ft) i BP8DRB300 13.4 l

BP8DQB323 14.4 BP8HXB355 14.4 i BP9 HUB 378 14.4  !

l ,

I

't 1

I 4

h .,

)

i 1

I l

i  !

l REVISION 11 A PAGE 10 OF 25 l

l , , ,.,, ,.-,--.n. - . , , - , - , - - - - - - - - ~ ~ ~ - - - - - - - ~ ~ ~ ~ ~ ~ ~ ' - * " ~ ~ ~ " ' - ' ~ ' ' " ~ * ~ " ~ ~ ~ ' " ~ ~ ^ ~ ~ ~ ~ ' ~ " ~ ~ ~ '

5 s.

a 3

'12.0 11.5 m 11 -.

10.9 11.0 w O

h 103 O l'

$ N \

s 10(X) 9 h

4 v2 8.5 , '200 W 8

8 0 5,000 10,000 15,000 20,000 25,000 30,000 35,000 40,000 45,000 PLANAR AVERAGE EXPOSURE (MWD /ST) m

_ FIGURE 3.1-1

{

g Maximum Avprage Hanar Linear Heat Generation Rate (MAPLHGR) for Fuel Type BP8DRB300

?

2-j' 13.5 13 12.5

\12.s 323 Z

12 ( 12.1 _

y 11.6 7 O S 11.5 ' $

11 s

- e E

a 10.5 \ :1 Z

A O 10 h

=

y 1(XX) d 9.5 , :n 97 @

H 8.7 8.5 0 5,(XX) 10,000 15,000 20,000 25,(XX) 30,000 35,(XX) 40,000 45,(XX)

Planar Average Exposure (MWD /ST)

S 1 FIGURE 3.1-2 k Maximum Average Planar Linear Heat Generation Rate

!X (MAPLHGR) for Fuel Type BP8DQB323 r

i

g 13 ll 12.5 12.3

{ l 1.8 q

$ F 12.1 .

I 1.5 T 11.3-, 11.4 g y ,4 lob 10.5 3

n m

c 10 -

m O

$ " \

9.5 ---

M 9 8.5 o e

200 F 8 4lI -

D 7.9 -

7.5 "

, \  :

a

n 6.5 -

H 6 -

5.9D 5.5 0 5,000 10,(XX) 15,000 20,000 25,000 30,000 35,(XX) 40,000 45,000 50,0(X) 7

% Planar Average Exposure (MWD /ST) k FIGURE 3.1-3: Maximqm Ayerage Planar Linear IIcat Generation l g Rate (MAPLHGR) for Fuel Type HP811XB355

l g 13 g: 12.5 -

n

= 12 11.0 11 0 10.5 0.2 10.0 N

e g

[ 9.5 3 y.3 ;g a: c 9 >

b u 1000 (87 h 2(X) 8.0 e g ,

v 7.5 P 3

c 6.5 h(6.7 H b

6.4 6

5.5 0 5,(XX) 10,(XX) 15,000 20,(XX) 25,000 30,(XX) 35,(XX) 40,(XX) 45,000 50,000 55,(XX) 60,0(X) t.o, ,

i? Planar Average Exposure (MWD /ST) u 9, FIGURE 3.1-4: Maximum Aypragp Planar Linear IIcat Generation g Rate (MAPLHGR) for Fuel Type BP9 HUB 378

y 1.1 s.

E' a -

C

{ / /

g"g __

f /

7 MAPLilGRp = MAPFACp

• h1APLilGRSTD 5

O

~

kO

[< 0.8 / ,

MAILIICII 'sS D = Standard MAPLilGR Limits from Figures 3.1-1 through 3.1-4 (T!

O

> /

/ MAPFAC p for i MAPFAC p = MINlEM (1.0, Ap+By F) si y

Q scoop tube setpoint F = Fraction of Rated Core Flow g  % calibration postioned A pand B p are fuel-type dependent d f suc that Rowma!.=

constants given below:

3 s N 107.0 g Flowmax FuelTvtx GE8x8EB. BP/P8x8R h A

S [ N

.x N (% Rated) Ap By to x

"112.0 %

}

0.6 f 102.5 0.4861 0.6784 107.0 0.4574 0.6758 g i I 2.0 0.4214 0.6807 H I I7.0 0.3828 0.6886 0.5 l l 30 50 70 90 7 iio

% CORE FLOW (% RATED)

. G

$ FIGURE 3.1-5 Flow Depepdent MAPLHGR Factor (MAPFACp )

1.0 g

0.9 - -

l .

g a l P > 45%

0.8 r 5 f'

" 0.7 Paypass< P s 45% ; e  : MAPLilGRp = MAPFACp

• MAPLilGRSTI)

) # 3 MAPLilGRSTI) = Standard MAPLilGR Limits frmn Figures 3.1-1 0.6 'h'""8h 31-4

]

m< I i

i P = % Nated Core Dermal Power o

d o I

l [ bypass = % Rated Core Dermal Power that Corresponds to the Sctpoint

" '" " 8" *" "" "

]A 0.5 i Core Flow s 50% Rated .L 8 l l l 7 7, stop Valves or Fast Cknure of Turbme Contml Valves -

O y

g (Maximum lhypass = 45%) tT1 4

j Core Flow >50% Raicd  :

N p

A I For P < 25% : No Thermal Monitoring is Required (No Limits Specified) g k [ _

w l Z

!  ; For 25% s P s 45% : P <pnypass and Core Flow s 50% Rated: Q Q l  : MAPFACp = 0.55 + OJX)5 (P - 45%)

2: ' F 0'3 5 E

k ' 8 For 25% s Ps 45% : P <IIivoass and Core Flow > 50% Rated:

O y l

, MAPFACp = d.50 + 0.006 (P - 45%) -

d

$ 0.2 i For 25% s P s 45% and P >EBypass:

x i -

) ,' i @

o MAPFACp = 1.0 + 0.005224 (P - 100%) O N

OJ For P > 45%: MAPFACp = 1.0 + 0.005224 (P - 100%) _

l t

. I I

I I m 0.0 =

5o 0 20 40 " " Bypass 60 80 10()

g  % RATED CORE THERMAL POWER (P)

R, g FIGURE 3.1-6

, Power Dependent MAPLHGR Factor (MAPFACp )

. .. . ~ . - - - - - .. - .. . . -. - - - - -

PILGRIM NUCLEAR POWER STATION

PNPS CORE OPERATING LIMITS REPORT 3.3 J ilical Power Ratio (MCPR)

Minirnum.C Reference Technical Soecification: 3.1 IC i

Durine power operation. the MCPR shall be greater than or equal to the t t operating limit MCPR. The operating limit MCPR is the greater of the

flow- and power-dependent MCPR operating limits, MCPRe and MCPRe. j l

The flow-dependent MCPR operating limit, MCPRr, is provided in Figure -

[ 3.3-1. For core thermal powers less than or equal to Psypo., the power-i dependent MCPR operating limit, MCPRp, is provided in Figure 3.3-2.  !

Above Psy, MCPRp is the product of the rated power and flow MCPR l- operating limit presented in Tables 3.3-1 and 3.3-2 and the Ke factor  ;

i presented in Figure 3.3-2. Figure 3.3-2 also specifies the maximum value

} for Pam . The rated power and flow MCPR operating limits presented in

Tables 3.3-1 and 3.3 2 are functions of the average scram insertion time, .

l for the indicated MOC and EOC cycle exposures.

p c l The value of the average scram insertion time (t) in Table 3.3-1 shall be j equal to 1.0, unless it is calculated from the results of the surveillance testing of Technical Specification 4 3.C, as follows:

l ,

r-

r. - n '

7 =

l 1.275 - n l

l l

1 l Where:

l' I-

=

l Tm Average scram time to the l

30% insertion position l

l ,

E, N D TN l

=

To Adjusted analysis mean  !

l scram t'me i l '

l

=

Ni

+ 1.65o ,,

[ N,

1. st

(

REVISION 11 A PAGE 17 OF 25

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

PILGRIM NUCLEAR POWER STATION

[

,.. PNPS CORE OPERATING LIMITS REPORT

=

3.3 Minimum Critical Power Ratio (MCPR) (Continued) n- =

Number of surveillance tests performed to date in the

] present cycle l-i Ni =

Total number of active control rods t

i

=

Ni Number of active control rods measured in the i*

[

suneillance test l

_ r, =

i 1

Average scram time to the 30% insertion position of all rods l L

measured in the i* suneillance test '

' =

L ~ Mean of the distribution for average i scram insertion time to the 30% position  !

j- =

0.945 sec 4 i

l 1

o =

Standard deviation of the distribution for average scram insertion time to the 30% position i

=

0.064 sec  !

1 t

l i

l l

l i i

REVISION 11 A PAGE 18 OF 25 1

~~"#' ~ " ~ ~ ~

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT Table 3.3 1 MOC MCPR Operatine Limits For operation from the Beginning of Cycle (BOC) to the End of Cycle (EOC) - 5250 MWD /ST with core flows s102% of rated:

Average Scram Insertion Time ( ) MCPR Operatine Limit

~

l 1

i s 1.0 1.40 l

1 1

i i

I 1

REVISION 11 A PAGE 19 OF 25

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

y a.

• i, I L' PILGRIM NUCLEAR POWER STATION j

f L

PNPS CORE OPERATING LIMITS REPORT l..

l t L' t E Table 3 3-2 '

, t i-  !

EOC MCPR Operatine Limits i e

I For operation from the EOC - 5250 MWD /ST to the EOC with core flow 1107.5% of  !

i..

rated. .

l i

Average Scram l 'Insenion Time ( T ) MCPR Operatine Limit I s 1.0 1.45 ,

)

i l

l i

l l

t l

e.

l I

i REVISION 11 A --

PAGE 20 OF 25

_..,,-..,# ..m__,..,_.-_...., .,m._.,_r,__c_m.,_.....,...,_..,._..,,,_n,,_. . m,4 m_ . , , ,_,-__,,,......,.,,....-v.,,, +t , ,. .,,1

g l I I I I I I

h. ( For F> 0.40:

MCPRy = Maximum (1.20, ApF+U) p

$ 1.6

\ A For F < 0.40:

( MCPRy = ( ApF + B p )( I + 0.32 (0.40 - F))

Where: F = Fraction of Rated Core Flow u \ m \ Ay and By are Flow Dependent Constants

{I \ ^

Given Below:

y N A Flowmax A U l l d

g x x x 102.5 -0.571 1.655 8

N I'# '

\/ 107.0 -0.586 1.697 M F 112.0 -0.602 1.747 O g Scoop tube setpoint 1170 -0.632 1.809 m p calibration postioned / m \ W

" 00 N \ o lllll 2 NNNN xN s s iu 1.2 '

o 1.1 2 20 30 40 50 60 70 80 90 100 110 CORE FLOW (% RATED)

O y FIGPRE 3.3-1 Flow Dppepdent MCPR Limits (MCPRp )

_ _ _ _ _ ._ _ . _ _ _ ._ . _ . _ . - _ .. _ .__ .m_ _ .__._m __ _ .

~

I I I Operating Limit MCPHp

$. a, 3 4 - for Core Nw > 50% Rated Operating Limit MCPRp=Kp

• OLMCPR(100) 5- g i /

O 3.2 i OLMCPR(100) = Operating Limit MCPR Values for 100% Rated Core nermalIbwer

/

- I f frorn Table 3.31 4 '

% 3.0

, P = % Rated Core hermal Power -

D , i PBypass= % Rated Core hermal Ibwer that Corresponds to the Setpoint for Bypass of 22.8- ,

i Scram Signals Generated by Closure of Drbine Stoo Valves or Fast Closure of -

] I I

Turbine Control Valves (Maximum g = 45% )

O 2.6 3 Kp = Rated MCPR Multiplier as Defined Below: yp,33 Z hiing Limit MCPRp l T 2 .4 g

for Core Nw s 50% Rated ,q For P < 250 No nermal Monitoring is Required (No Limits are Specified) -

I ' '

' ] '

For 25% s P s 45% and P < pRvnm :

m 2.2 -

O 2.0 i

i 1

N_w I i

g p,Kgyo, Ksio (45% - Pi OLMCPR(100)

- W tr1 1.8

'  ! Where K Byp= 1.95 and K3;o= 0.0125 for Core Flow s 50% Rated or -

o T

K Byp = 2.35 and K ;o= 0.043 for Core Flow > 50% Rated

$\$ <

For 25% s P s 45% and P > PBvosss : Kp = 1.28 + 0.01M (45% - P) 3

$ E >%

d

- 1'6 Z I

For 45% < P < 60% Kp = 1.15 + 0.00867 (60% - P) O l\ w i

l i 5 f"*

~

i For P 2 60% Kp = 1.0 + 0.00375 (100% - P) - 1.5 c-)

[ N I l l I'4 g M Kp for PBypass< P s 45%

\l C; y l K p for P> 60% l l3 8 I

[ N h I

lK for p 45% < P< 60% l _

N g,y y

--- ^

'  ! l w 1.0 y T 20 30 40 ** SyPass 50 60 70 m 80 90 100 ii

% RATED CORE TIIERMAL POWER (P) i U

] $

FIGURE 3.3-2 Power Dependent MCPR Limits (MCPRp )

3

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT 3.4 P_qwer/ Flow Relationship During Power Opgratino Reference Technical Specification; 3.11.D The power / flow relationship shall not exceed the limiting values shown on the Power / Flow Operating Map in Figure 3.4-1.

• 4.0 REACTOR VESSEL CORE DESIGN Reference Technical Specification: 5.2 The reactor vessel core for the present cycle consists of 580 fuel assemblies of the types listed below. The core loading pattern for each type of fuel is shown for the present cycle in Figure 4.0-1. j Fuel Tvoe Cycle Loaded Number i Irradiated BP8DRB300 8 136 BP8DQB323 9 168  ;

BP8HXB355 10 140 i

New

^

BP9 HUB 378 11 136 i

Total 580  :

The reactor vessel core contains 145 cniciform-shaped control rods. The control  ;

materials used are either boron carbide powder (B4C) compacted to approximate!v  ;

i 70% of the theoretical density or a combination of boron carbide powder and solid  ;

! hafnium.

5.0 REFERENCES

I l

4 5.1 NEDE-24011-P-A-10 and NEDE-24011-P-A-10-US, " General Electric i

} Standard Application for Reactor Fuel, " February and March,1991.

1 i

- 5.2 NEDC-31852-P, " Pilgrim Nuclear Power Station SAFER /GESTR-LOCA l j Loss-of-Coolant Accident Analy, sis", September 1990.

I j 5.3 NEDC-31312-P," ARTS Improvement Program Analysis for Pilgrim l Nuclear Power Station", September 4,1987. ,

i  !

i REVISION 11 A PAGE 23 OF 25 f

. .. _ = _ . . - _ ... _ _.__ .. _ . ._.-.. . - . ~ . _ . _ . . _ _ . _ _ _ _ . . .,_ _ . _ ~_ _ :;n _ _

2W  ;  ;

i l  ;  ; 130 x 2n APRM SCRAM 0.66W + 69%

0 CLAMP @ 120% p- 120 ,

h , I I I N / /

$ 1998 -

APRM ROD BLOCK 0.66W + 62%

CLAMP @ l15%

,,e

/ [/

/

U f ,,e 100 1800 2 7 90 g

{'" / / '

/ s ) 80 (>

y &

f

/

/ \

Operation Prohibited

/

m g

3 7

Outside this Curve @

o o / 70 t A \ $ tn 1200 -

o O 26% Pump 60 m m y 1000 Speed Line _ .

] $

6 30y E goo Natural y

g Circulation ~ 40 - d Line g r

u D

6M 30$ $

m 400 s -

/ l 20 $

! 200 / O 1

.c

/ 10 W

. / d 0

' 0 0 5 10 15 20 25 30 35 40 45 50 55 60 65 69 75 80

p Core Flow (MLB/IIR)

?>

9, FIGURE 3.4-1 M Power / Flow Operating Map

_ _ _ _ _ _ _ _ - - _ _ --____ A - - - - - -- - - - ~

PNPS CORE OPERATING LIMITS REPORT

HHHHHHH

HHHHHHHHH

HHHHHHHHHHH lra4HHHHHHHHHHHH

-MHHHHHHHHHHHH

M H H H H H H H H H H H H

H H H H H H H H H H H H H

HHHHHHHHHHHHH rHHHHHHHHHHHHH

MHHHHHHHHHHHH

HHHHHHHHHHH .

l HHHHHHHHH

HHHHHHH l 1 3 5 7 9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45 47 49 51 Fuel Types ( Cycle Loaded)

E BP8DRB300 (Cycle 8)  % BP8HXB355 (Cycle 10)

{ @ BP8DQB323 (Cycle 9) E BP9 HUB 378 (Cycle 11)

FIGURE 4.01 i

Reactor Vessel Core Loading Pattern Revision 11A Page 25 of 25

_ _ _ _ - - _ _ _ - - - - - - - - . - - .