ML20086H021

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Rev 11B, Pilgrim Nuclear Power Station PNPS Colr
ML20086H021
Person / Time
Site: Pilgrim
Issue date: 06/06/1995
From:
BOSTON EDISON CO.
To:
Shared Package
ML20086H018 List:
References
NUDOCS 9507170382
Download: ML20086H021 (25)
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Text

.

PILGRIh1 NUCLEAR POWER STATION PNPS CORE OPERATING LIhflTS REPORT RTYPE: G4.02 (CYCLE 11)

APPROVED: 6/SI~ f

' Operations @upport Division hianier ' Ifate APPROVED: ds)K rJr/W k/ L l~ Y$5'

' Nuclear Engineerin'g Services Department Afanager Date i

APPROVED:' A/Ii-, Ortc Ah s, <r 5_c2_ 4/rpjs-Opdrdtions ReviAv Committee ]

Date {

J APPROVED: . [ [# # (d  ![ '

Idan%partment hianager Date  !

APPROVED: -

b W (c 6 96~

Statio7: Di[y6 tor / /Date 4

1 4

COLR

] REVISION 11B PAGE 1 OF 25 9507170382 950713 i PDR ADOCK 05000293 i_ 2.

P ,- ,

__,_,f_.,,,,,_._.,__._..__._.___,-__ . _ - . _ ,, _ _ , - ~ ~ ---

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4,02 TABLE OF CONTENTS P3&e TITLE / SIGNATURE PAGE. . . _ . . 1

~ ~ ,

TABLE OF CONTENTS . . . .2 RECORD OF REVISIONS. . . 3 i

LIST OF TABLES. .

. . .. .. .4 i LIST OF FIGURES .5

[

1.0 INTRODUCTION

. .6 2.0 INSTRUMENTATION TRIP SETTINGS . ~ .7 i 2.1 APRM Flux Scram Trip Setting (Run Mode) .7 2.2 APRM Rod Block Trip Setting (Run Mode). .7 -

2.3 Rod Block Morutor Trip Setting. . S 3.0 CORE OPERATING LIMITS . .9 3.1 Average Planar Linear Heat Generation Rate ( APLHGR) . . .9  ;

3.2 .9 Linear Heat Generation Rate (LHGR) .

3.3 . 17 Minimum Critical Power Ratio (MCPR) .  ;

3.4 Power / Flow Relationship.. . .. ... 23 4.0 REACTOR VESSEL CORE DESIGN.. . . 23 .

5.0 REFERENCES

. . .. . .23 COLR.

REVISION 11B PAGE 2 OF 25

PILGRIM NUCLEAR POWER STATION j PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 J

i RECORD OF REVISIONS <

I Revision Effective Date Descnotion 1

l
8A Effective date based on Applicable for use dunng  ;

j _

issuance oflicense Cycle 8 Operation j i amendment by-NRC l

j- 9A Effective date based on Applicable for use during i issuance oflicense Cycle 9 operation l amendment by NRC for

ARTS and SAFER /GESTR I i j 10A Effective date based on Applicable for use during 1j initial startup of Cycle 10 Cycle 10 Operation 1

, IlA Effective date based on Applicable for use during  ;

j initial startup of CycleTI Cycle 11 Operation j 11B Effective upon final Applicable for use during j approval Cycle 1I Operation g

i i

a i

i l

COLR REVISION 11B PAGE 3 OF 25

PILGRIM NUCLEAR POWER STATION L PNPS CORE OPERATING LIMITS REPORT RTYPE. G4.02 i

i LIST OF TABLES l

l Number Title Pace l 3.2-1 LHGR Operating Limits 10 3.3-1 MOC MCPR Operating Limits 19 l .

33-2 EOC MCPR Operating Limits 20 i

l l

1 COLR REVISION 11B PAGE 4 OF 25

PILGRIM NUCLEAR POWER STATION  ;

PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 ~

LIST OF FIGURES Number Ijile P_ age r 3 1-1 Maximum Average Planar Linear Heat Generation 11 Rate (MAPLHGR) for Fuel Type BP8DRB300 3.1-2 Maximum Average Planard.inear Heat Generation '

12 Rate (MAPLHGR) for Fuel Type BP8DQB323 '

3.1-3 Maximum Average Planar Linear Heat Generation 13 Rate (MAPLHGR) for Fuel Type BP8HXB355  !

i 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 3.1-6 Power-Dependent MAPHLGR FNetor (MAPFACp) 16 i

l 3.3-1 Flow-Dependent MCPR Limits (MCPRr) 21 1 3.3-2 Power-Dependent MCPR Limits (MCPRp) 22 3.4-1 Power / Flow Operating Map 24 4.0-1 Reactor Vessel Core Loading Pattern 25 I

COLR REVISION 1IB PAGE 5 OF 25

r PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIh1ITS REPORT RTYPE; G4,02

1.0 INTRODUCTION

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

f Although this report is not part of the PNPS Technical Specifications. the l' Technical Specifications refer.to this report for the applicable values of the following fuel-related parameters:

Reference Technical Snecification ,

APRhi Flux Scram Trip Setting (Run Mode) Table 31 1  ;

APRM Rod Block Trip Setting (Run Mode) Table 3.2.C-2  !

L Rod Block Monitor Trip Setting Table 3 2C-2 Average Planar Linear Heat Generation Rate

)

3.11.A Linear Heat Generation Rate (LHGR) 3.11.B Minimum Critical Power Ratio (MCPK) 3.11.C Power / Flow Relationship 3.11.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 Tectuucal 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.AA. These limits are established such that the applicable limits of the plant safety analysis are met.

I j

COLR REVISION 1IB PAGE 6 OF 25

i l

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 r

! 2.0 INSTRUMENTATION TRIP SETTINGS.

j 2.1 APRM Flux Scram Trio Settine (Run Mode) l Reference Technical Specificat.ipons: Table 3.1 l. 31.B.1 l

l When the mode switch is in the run position the average power range  !

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

i

) S, s 0.66 W + 69%

l l

with a clamp at 120% of rated core thermal power and '

S. = APRM flux scram trip setting in percent of rated thermal i power (1998 MW i).

W= Percent of drive flow required to produce a rated core flow of 69 Mlb/hr. i The APRM 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.

l In accordance with Technical Specification Table 3.1.1, Note 15. for no combiaation ofloop recirculation flow rate and core thermal power shall l the APRM flux scram trip setting be allowed to exceed 120% ofrated thermal power.

i 2.2 APRM Rod Block Trio Settine (Run Mode)

Reference Technical Soecifications: Table 3 2.C-2,3.1.B.1 I

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

monitor (APRM) rod block trip setting (Sas) shall be:

Saa s 0.66 W + 62%

with a clamp at 115% of rated core thermal power and San = APRM rod block trip setting in percent of rated thermal power (1998 MW i ).

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

COLR REVISION 11B PAGE 7 OF 25

PILGRlhi NUCLEAR POWER STATION l PNPS CORE OPERATING LIhflTS REPORT RTYPE. G4.02 2.2 APRhBod Block Trip.lelting (RunlfodeL.(Continued)

" 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.

d 2.3 Rod Block Monitor Trio Setting

[ Reference Technical pecific on: Table 3.2.C-2 Allowable values for the power-dependent Rod Block Monitor trip j setpoints shall be: .

Reactor Power. P Trip Setpoint

(% of Rated) (% of Reference Level)

/  :

P s 25.9 Not applicable ( All RBM Trips Bypassed) i 25.9 < P s 62.0 120 62.0 < P s 82.0 115 i 82.0 < P 110 The allowable value for the RBM downscale trip setpoint shall be 2 94.0% i of the reference level. The RBM downscale trip is bypassed for reactor power 125.9% of rated.

I f

f l

COLR REVISION 11B PAGE 8 OF 25 l

,. . . - - . . - . . - . . . - , - . . . . . - , , :.n ~ . .. .'

^

h l I lLGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 3.0 CORE OPERATING LIMITS l-3.1 Average Planar Linear Heat Generation Rate (APLHGR)

L Rehrence Technical Specification: 3.11. A ,

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, MAPLHGRr i I' and MAPLHGR,. The flow-dependent APLHGR limit, MAPLHGRr, is l the product of the MAPLHGR flow factor, MAPFACr, shown in Figure

3.1-5 and the MAPLHGR for rated power and flow conditions. The L power-dependent APLHGR limit, MAPLHGRp, is the product of the i

!. .MAPLHGR power factor, MAPFACp, shown in Figure 3.1-6 and the  ;

l MAPLHGR for rated power and flow conditions. The MAPLHGR for l rated power and flow conditions for each fuel type as a function of axial location and averagt planar exposure are based on the approved methodology referenced in Section 5.0Tnd programmed in the plant process computer. The MAPLHGR for rated power and flow conditions '

1 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 Specification; 3.11.B 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.

COLR REVISION 11B PAGE 9 OF 25

L PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT _RTYPE: G4.02 l

i Table 3.2-1 t

j LHGR Ooeratine Limits i.

LHGR Operating Fuel Tyne .. Limit (KW/ft)

- l

. ~ l BP8DRB300 13.4 l

BP8DQB323 14.4 BP8HXB355 14.4 i BP9Hb3378 - 14.4 I

I l

l J

l i

-COLR REVISION 11B PAGE 10 OF 25  ;

. . . . ~ . . , - ,_r .c , . , - . . . . . . . . . . _ ~ . - .--.--,,,,..,-..--.,-y,..-r-. . ,....y,,#..--.........,v.,,,,-r ~ ~; - , w.p p. ,,,.m.

c 2

E:

8 -

3 12.5 12.3 Q2.1 12.0 11.5 11.5 g

11.4 g y

II en S 3oy 'l I .o  %

lE

'd10.5 e

\ h

=

10.3 O b 10 \

d 9.5 N \

Si i $

1 7 (XX) 4 200 to g

7 8.3 o

8 N q

O 5,(XX) 10,(XX) 15,000 20,000 25,(XX) 30,(4X) 35,(XX) 40,000 45,000 Pl.ANAR AVERAGE EXPOSURE (hlWD/ST) 2' m

i FIGURE 3.14 i

4 a, g Maximum Average Planar Linear Heat Generation Rate

y 5; @

(MAPLHGR) for Fuel Type BP8DRB300 t

?

2-g' 13.5 .

~

13.1 E 13

~

12 12.5 '12.5

\.8 m

p ( 12 1 11.6, 7 C 11.5

)

a s e e

O n.

10.5 N l d O

6 [

4 10 l Q2 E p l(XX) h 9.5 ,

g 2

9 7 (X) o W

H 8.7 8,5 0 5,(XX) 10,(XX) 15,(XX) 20,(XX) 25,(XX) 30,(XX) 35,(XX) 40,(XX) 45,(XX)

Planar Average Exposure (MWD /ST)

}

3

, g FIGURE 3.1-2 "

o,8 Maximum Average Planar Linear Heat Generation Rate d5 .S

($1APLHGR) for Fuel Type BP8DQB323 S 5

13

$,- 12.5 8

%q 12 W ( "' I 11.5 x 11 1 ffttA 11A god m z

10.5 ~

N N

a '" \

Q m

f 9.5 O a:

g 9

y 1000

\

a g

s .5 200

\ -

't

,c r g r S

) 9 7.5 \g 7

~ \ @

]

6.5 \ b 6 \

ss b 5.5 y 0 5,000 10,000 15,000 20,000 25,000 30,000 35,0(X) 40,000 45,000 50,(XX)

% g Planar Average Exposure (MWD /ST)

- g

{g FIGURE 3.1-3: Maximum Average Planar Linear IIcat Generation g f, Rate (MAPLHGR) for Fuel Type HP811XB355 p g

y 13 jo 12.5 Z 12 to 11.6 j 3 3..;

11.0, 11.o 10.5

  • o.2 io.o m 10 < 8
o c

m h o.5 _

O g 5 ,y y

M 9 a

I h

a p 1(XX) \\87 k' o 8.5 x z

$ 200 a

' 4 8 j- \, 3o C g

7.5 ' -- 9 M

7.4 7 'O 6.5 h\ 6.7 H

b 6

5.5

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

, $~ Planar Average Exposure (MWD /ST) rn

] kn FIGURE 3.1-4: Maximum Average Planar Linear IIcat Generation "

l gg Rate (MAPLHGR) for Fuel Type BP9 HUB 378 y

. I.

g

r l

l l

x 1.1 n.

8

=

1.0

, j O.9- "

/

/ /

/ AIAPLilGRp = hlAPFACp ' AIAPLilGR3 ID O 5

M o f l hIAPLilGitSTD = Standard MAPLliGR Limits m b 0.8 -

from Figures 3.1-1 through 3.14 O

> /

/- hlAPFAC p for IAI F= W (LO, Ap Uj; 19

. si y

)'

O [ / scoop tube scipoint d 0.7 - f [ calibration postioned F- Fraction of Rated Core Flow such that Flowmax= A :I and By are fuel-type dependent C3 consmivWlom O > - -

~

107.0 % Flowmax Fuct Tvoc GE8x8EB. HP/P8x8R q

[ -N 112.0 7c (% Rated) Ap Bp m

  1. II ~
  • w i 0.6 7 102.5 0.4861 0.6784 @

107.0 0.4574 0.6758 g o

iI2.0 0.4214 0.6807 H 3

I I7.0 0.3828 0.6886 O.5 y 30 50 70 90 110 y CORE FLOW (%. RATED) x u

m..

2,8 FIGURE 3.1-5 i

o"e

" g Flow Dependent MAPLIIGR Factor (MAPFACp)

  • g

1.0 --

N 8-g

^

0.9 -/

g l P > 45%

$ o'8

% /

r 6 0.7 P .p33< P s 45%

n3 s e i MAPLilGRp = MAPFACp

  • MAPLilGRSTI) h '

8 8 -

k MAPLilGRSTI) = Standard M Al1.IIGR I.imits from Figures 3.1-1 thn> ugh 3.1-4 ]

( 0.6 l i

i P = % Rated Core %crrnal Power g

g i ihyp,, = % Rated Core Thermal Power that Corresponds to the Setpoint o

O 8 I

N C Flow s50% Rated L '

i ore j for Bypass of Scram Signals Generated by Closure of Turbine EIl

]m 0.5 l l l p ,' stop Valvts or Fast Closure of Turbine Conin>l Valves -

j i (Maximum lhypass = 45%)

.4 l Core Flow >50% Rated I h 't tt1

% i For P < 25%: No Themial Monitoring is Required (No Limits Specified) y

[ ' _ g s

m i -

For 25% s P s 45% : P < pilypass and Core Flow s 50% Rated: "A Q l I Q

g MAPFACp = 0.55 + 0.005 (P - 45%) t-*

$ 0.3 l a ,

I For 25% s P s 45% : P < llynass and Core Flow > 50% Rated:

E

' q

, M APFACp = 0.50 + 0.006 (P - 45%) -

c.n I ,

d 0.2 -

i For 25% s P s 45% anil P >PHwass:

x

!]

' I O . MAPFAC p= 1.0 + 0.005224 (P - 100%) O A -

N l  ! For P > 45%: M API;ACp u 1.0 + 0 00522 8 (P - 100%)

l i I e I

I I I m 0.0 :x3 5o 0 20 40 M**"ByPus 60 80 p

100 m tn cn  % RATED CORE TilERMAL POWER (P) "

o i 08 vg FIGURE 3.1-6 o

f c)

Power Dependent MAPLHGR Factor (MAPFACp) "

PILGRIM NUCLEAR 'OWER STATION PNPS CORE OPER.' NG LIMITS REPORT RTYPE: G4.02 3.3 Minimum Critical Power Ratio (MCPR)

Reference Technical Snecification- 311C During power operation. the MCPR shall be greater than or equal to the

' operating limit MCPR. The operating limit MCPR is the greater of the flow- and power-dependent hiCPR operating limits, MCPRp and MCPRe.

The flow-dependent hiCPR operating limit, MCPRr, is provided in Figure 3.3-1. For core thermal powers less than or equal to Ps>, , the power-dependent MCPR operating limit, MCPRp, is provided in Figure 3.3-2.

Above Psyp , MCPRp is the product of the rated power and flow MCPR operating limit presented in Tables 3.3-1 and 3.3-2 and the Kp factor presented in Figure 3.3-2. Figure 3.3-2 also specifies the maximum value for Ps3,. . 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, t, for the indicated MOC and EOC cycle exposures.

The value of the average scram insertion time (t) in Table 3.3-1 shall be equal to 1.0, unless it is calculated from the results of the surveillance testing of Technical Specification 4 3.C. as follows: '

i r-n

! 1.275 - n l

r l

Where.

=

Tm Average scram time to the 30% insenion position j [ N, r,

=

[ N'

=

is Adjusted analysis mean scram time I

=

+ 1.65cr ! ,N,

[N.

COLR REVISION 11B PAGE 17 OF 25

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 3.3 Minimum Critical Power Ratio (MCPR) (Continug.d.)

n =

Number of surveillance tests performed to date in the present cycle Ni =

Total number of active control rods Ni =

Number of actNe control rods measured in the i*

surveillance test ti =

Average scram time to the 30% insertion position of all rods measured in the i* surveillance test 4 =

Mean of the distribution for average scram insertion time to the 30% position

=

0.945 sec o =

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

=

0.064 sec COLR REVISION 11B PAGE 18 OF 25

- PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.3-1 l J

MOC MCPR Operatine Limits For operation from the Beginning of Cycle (BOC) to the End of Cycle (EOC) - 5250  !

MWD /ST as a function ofcore flow:

l

~ '

~ ,

. ~

MCPR O_perating Limn '

Average Scram 102% Rated < Core Flow Insertion Time ( t ) Core Flow s102% Rated s107 5% Rated t s 1.0 1.40 1.45 I

w i

.. l l

COLR REVISION 11B- PAGE 19 OF 25

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

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE. G4.02 Table 3.3-2 EOC MCPR Operatine Limits For operation from the EOC - 5250 MWD /ST to the EOC with core flow s107.5% of rated: ,

. s.

Average Scram Insertion Time ( : ) MCPR Operatina Limit T s 1.0 1.45 e

l COLR REVISION 11B PAGE 20 OF 25 E -- _ --

. 'I y I I I S. I l I I P?. \ Few F2 0.40:

MCPRp = hlasimum (1.20, Ap F + lif ) ~

j{

W l.6 ' \

For F < 0 40 gN MCIH g = ( Ap F + H )( I + 0.32 ( 0.40 - F))

F Wh'*

uI \ \ m \ '

F = Fracthm of Rated Core Flow Ay and BF are Flow Dependent Constants

~ ~

Given Delow:

2 N s Flowmn ^E U "

s O

d x x '

x 102.5

-0.571 E

1.655 8

W I'4 5) 107.0 -0.586 ' l.697 M F i12.0 O

-0.602 h Scoop tube setpoint i17.0 1.747 p calibration posthmed / < \

0.632

i 1.809 m

W l~3

=V VW iu x x s s

,.2 \ \ \\  !

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

{

o n a Oo FIGURE 3.3-1 M "E -

Flow Dependent MCPR Limits (MCPRp ) g

t 3'

I I l

@ 34'~ Operstmg Limit h1CPRp

5. m for Core How > 50% Rated U- 0;rrating Limit htCPRp=Kp
  • OLhtCPR(100) -

g i /

O A 32 i OLh1CPR(100) = Operating Limit htCI'R Values for 100% Nated Core Thermal Power

~

y 9

~

/

8 i 4 3.0 ' f from Table 33-1 and Table 3.3-2 P = % Rated Core Dermal Power -

l h

a 2.8 - ,

l

, P yyp,,,= % Rated Core hermal Power that Corresponds to the Scipoint for Hypass of i Scram Signals Generated by Closure of Tsubine Stop Valves or Fast Closure of -

U 8 I

Tinbine Control Valves (hfasimum I[g O 2.6 3 i K p = Rated htCPR hfultiplict as Defined Helow. yp,,, = 45% )

b Operating Limit blCPR p 2.4 -- for Core Flow s 50% Rated i

m M '

,q For P < 25%: No Dermal hfonihuing is Required (No Limits aru Specified) -

Z

/ m O

g 2.2 i

'w l For 25% s P s 45% an<l P < pnymu : ---

to 2.0_  % _KDyn + hsto (45% - Pi W

i i N K p-OLh1CPR(100) i til

1.8 '

Where K Byp- I.95 and K 3;o= 0 0125 for Core Flow s 50% Ra.ed or O K

m Byp = 235 and K3 ;o= 0M3 for Core Flow > 50% Ratej l

For 25% s Ps 45% and P > EDynau : Kp = I.28 + 0.0134 (45% - P)

'. h >Q

" d

' ' -- 1'6 Z N 8 For 45% < P < N4: Kp = 1.15 h 0 00867 (60% - P) D C i w i 1.5 3

g r*

1 I For P 2 NM: Kp = 1.0 + 0 00U5 (Ima - P) 8 w m M l

[  %

1 l IA W y j

i y tn Kp for Payp,,,< P s 45% -

C* N

^

' l K y for P> 60% l 1.3 H tri N / d

! f p 45% < P < 60% l N  %

{  %

i.2 ggO 4

i lK for . g,3

, ~ ~ -

i i N w M y 20 30 40 ** I}typass 50 60 70 80 90 100 t

E

% RATED CORE TilERMAL POWER (P) 1 0

'*" FIGURE 3.3-2 Power Dependent MCPR Limits (MCPRp) 11 s FJ

, PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 3.4 Power / Flow Belationship During Power Operatipn .

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. l 1

4.0 REACTOR VFSSEL 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.

Fuel Tyne Cvele Loaded Number Irradiated l 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 cruciform-shaped control rods. The control materials used are either boron carbide powder (B4C) compacted to approximately 70% of the theoretical density or a combination of boron carbide powder and solid hafnium.

5.0 REFERENCES

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

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

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

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

4 COLR REVISION 11B PAGE 23 OF 25

- , , . , - -- -.m-,

9 2600 i  ; i i i  ; 330 g APRM SCRAM 0.66W + 69%

g' 2400 CLAMP @ 120% 7 120 y-5 22m APRM ROD BLOCK 0.66W + 62%

1 I I N / f '

I'O G 1998 CLAMP @ l15%

e

/ [/

f r 100 iS00 \ y j

7 7 90 g

,f iux, // / ,/ D Y

- 3p 7 x -

80 x a U 34W 7

/ -

Operation Prohibited

-> b O g Outside this Curve 70

/ b g

O m

I 12m - g 26% Pump 60$

$ Speed Line

.c D 1000

] $

50 "

b  % d Natural "

E 300 3

. Circulation -

4g $

1 ine j g g ax) u v g

30$ $

m 400 i <

/ /

20 $

200 <

/ o

/ 10 W s

9 r$

0 5 10 20 25 n

15 30 35 40 45 50 55 60 65 69 75 80 y Core Flow (MLil/IIR)

S

's 4

8 8 FIGURE 3.4-1 a, E "

d Power / Flow Operating Map E 8

l.. . .

psp comeceem 1,me<1m11 me,eer .zx. . c .e2 i  :: M8484BBM24:4 l

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!  :: 3 BEBR M BBBBBiltBEBEBEBIBi

!  :: 3 8 5 B i s t i t :4 B B B a i t 5 8 54 B E B

1!428BEECHHBE33:4XBEBEBE l l Mate 4BEMMi49ENHIGBEM
3 RRG H BBBBBIB!i4ECREBEBE

! :3BRMi4 CiiliBEREBEBREGH l  :: 84BEBIMMBBBBBBBBB8M i

ii;MaiBRMi4Mi1M98

' ' ' ' i i MB8B8MB8ME4 ' i i l l l l

- l l ll l 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 1

Fuel Types ( Cycle Loaded) l

@ BP8DRB300 (Cycle 8) $ BP8HXB355 (Cycle 10)

@ BP8DQB323 (Cycle 9) 5 BP9 HUB 378 (Cycle 11) i FIGURE 4.0-1 Reactor Vessel Core Loading Pattern COLR Revision 11B Page 25 of 25

. - . - _ - - . - - .-. -. _.-_.-._ - _.__ -___ - -___ .. :_

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