ML20236U820

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Rev 12B to Pilgrim Nuclear Power Station COLR (Cycle 12)
ML20236U820
Person / Time
Site: Pilgrim
Issue date: 07/13/1998
From:
BOSTON EDISON CO.
To:
Shared Package
ML20236U817 List:
References
NUDOCS 9807310096
Download: ML20236U820 (26)
v • d • e


Text

_ _ _ - _ _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - _

PILGRIM NUCLEAR POWER STATION I

PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 l

l (CYCLE 12)

W N

APPROVED Op61a'bornr$uyort Department Manager Date 1

{

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T APPROVED:

/ afe N6 Engineer ervices Group Manager D

APPROVED:

/}Ab 7/9/97 Operations Repw Commit (ee Date i

Plant ger (Daty' APPROVED:

//

//

7 /-7 89 Sta;6nW/ " " ~ ~ " ~ '

' Dat'e i

i 9807310096 980724 PDR ADOCK 05000293 P

PDR COLR REVISION 128 PAGE 1 OF 26 I

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REr ORT RTYPE: G4.02 2

TABLE OF CONTENTS Paae TITLE / SIGN ATU RE PAGE.....................................

.........1 TABLE OF CONTENTS............

2 RECO RD OF REVI SION S..............................................

.....3 LIST OF TABLES......

...................................................4 LIST O F F IG U RE S......................................

..................................5 1.0 I NTRO D U CTI O N....................................................................

2.0 IN STRUMENTATION TRIP SETTINGS..................................... 7 2.1 APRM Flux Scram Trip Setting (Run Mode)....................... 7 2.2 APRM Rod Block Trip Setting (Run Mode)..........................

7 2.3 Rod Block Monitor Trip Setting.......................................... 8 3.0 C O RE OP ERATIN G LIMITS.................................................... 9 3.1 Average Planar Linear Heat Generation R ate (AP LH G R)......................................................

3.2 Linear Heat Generation Rate (LHGR).................................. 9 3.3 Minimum Critical Power Ratio (MCPR)................................18 3.4 Power / Flow Relationship................................................ 24 l

4.0 REACTOR VESSEL CORE DESIGN................................. 24 l

5.0 R E F E R E N C E S.......................................................... 24 1

1 I

l COLR PAGE 2 OF 26 REVISION 12B l

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PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 RECORD OF REVISIONS

  • Revision Effective Date Description GA Effective date based on Applicable for use during issuance of license Cycle 8 Operation amendment by NRC 9A Effective date based on Applicable for use during issuance of license Cycle 9 operation amendment by NRC for ARTS and SAFERIGESTR 10A Effective date based on Applicable for use during initial startup of Cycle 10 Cycle 10 Operation 11A Effective date based on Applicable for use during initial startup of Cycle 11 Cycle 11 Operation 11B Effective upon final Applicable for use during approval Cycle 11 Operation 11C Effective upon final Applicable for use during epproval Cycle 11 Operation 11D Effective upon final Applicable for use during approval Cycle 11 Operation 12A Effective date based on Applicable for use during issuance of license Cycle 12 Operation amendment by NRC for SLMCPR of 1.08 12B Effective upon final Renumbered Tables:

approval Table 3.2-1 to Table 3.2.1, Table 3.3-2 to Table 3.3.1, Sh. 2 of 2 and Table 3.3.1 to Table l

3.3.1,Sh.1 of 2 COLR REVISION 12B PAGE 3 OF 26

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 LIST OF TABLES Number Title Paae 3.2.1 LHGR Operating Limits 10 3.3.1, Sh.1 of 2 MOC MCPR Operating Limits 20 3.3.1, Sh. 2 of 2 EOC MCPR Operating Limits 21

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l COLR PAGE 4 OF 26 REVISION 12B I-l t

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

i I

LIST OF FIGURES

  • Number Title Paae 3.1-1 Maximum Average Planar Linear Heat 11 l

Generation Rate (MAPLHGR) for Fuel Type BP8DQB323 3.1 -2 Maximum Average Planar Linear Heat 12 Generation Rate (MAPLHGR) for Fuel Type BP8HXB355 3.1 -3 Maximum Average Planar Linear Heat 13 Generation Rate (MAPLHGR) for Fuel Type BP9 HUB 378 3.1 -4 Maximum Average Planar Linear Heat 14 Generation Rate (MAPLHGR) for Fuel Type P9 DUB 408-6G5.0/7G4.0 l

3.1-5 Maximum Average Planar Linear Heat 15 Generation Rate (MAPLHGR) for Fuel Type P9 DUB 408-16GZ1 3.1-6 Flow-Dependent MAPLHGR Factor (MAPFACr) 16 3.1-7 Power-Dependent MAPHLGR Factor 17 (MAPFACp) 3.3-1 Flow-Dependent MCPR Limits (MCPRr) 22 3.3-2 Power-Dependent MCPR Limits (MCPRp) 23 3.4-1 Power / Flow Operating Map 25 4.0-1 Reactor Vessel Core Loading Pattern 26 i

COLR REVISION 12B PAGE 5 OF 26 l

4 I

E PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS 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 12. In this report, Cycle 12.

will frequently be referred to as the present cycle.

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

1 Reference Technical Specification l

APRM Flux Scram Trip Setting (Run Mode)

Table 3.1.1 APRM Rod Block Trip Setting (Run Mode)

Table 3.2.C-2 Rod Block Monitor Trip Setting.

Table 3.2.C-2 Average Planar Linear Heat Generation Rate 3.11.A Linear Heat Generation Rate (LHGR) 3.11.8 Minimum Critical Power Ratio (MCPR) 3.11.C Power / Flow Relationship 3.11.D Reactor Vessel Core Design 5.2 l

If any of the core operating limits in this report are exceeded, actions will be taken as defined in the referenced Technical Specification.

l The core operating limits in this report have been established for the present cycle using the NRC-approved methodology provided in the j

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 COLR REVISION 12B PAGE 6 OF 26 E-_--_------_.---_____

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 2.0 INSTRUMENTATION TRIP SETTINGS:

'2.1 APRM Flux Scram Trio Settina (Run Mode) l Reference Technical Specifications: Table 3.1.1,3.1.B.1 When the mode switch is in the run position, the average pcuer range monitor (APRM) flux scram trip setting (S.) shall be:

S, s 0.66 W + 69%

j with a clamp at 120% of rated core thermal power and S. =

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

W=

Percent of drive flow required to produce a rated core i

flow of 69 Mlb/hr.

l The APRM flux scran. trip setting is valid only for operation using two j

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

restricted by License Condition 3.E.

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

the APRM flux scram trip setting be allowed to exceed 120% of rated J

thermal power.

l 2.2 APRM Rod Block Trio Settina (Run Mode) l l

Reference Technical Specifications: Table 3.2.C-2, 3.1.B.1 When the mode switch is in the run position, the average power ran's monitor (APRM) rod block trip setting (Sas) shall be:

d Saa s 0.66 W + 62%

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

W= Percent of drive flow required to produce a rated

(

core flow of 69 Mlb/hr.

COLR I

REVISION 12B PAGE 7 OF 26

1 P!LGRIM NUCLEAR POWER STATION PNDS CORE OPERATING LIMITS REPORT RTYPE: G4.02 l

2.2 APRM Rod Block Trio Settina (Run Mode) (Continued)

Tha APRM rod block trip setting is valid only for operation using f

recirculation loops. Operation with one recirculation loop out of service is restricted by License Conditiorn 3.E.

2.3 Rod Block Monitor Trio Settina Reference Technical Specification: Table 3.2.C-2

)

Allowable values for the power-dependent Rod Block Monitor trip setpoints shall be:

i Reactor Power, P Trip Setpoint j

(% of Rated)

(% of Reference Level) l P s 25.9 Not applicable (All RBM Trips i

Bypassed) 25.9 < P s 62.0 120 62.0 < P s 82.0 115 82.0 < P 110 The allowable value for the RBM downscale trip setpoint chall be 2 94.0% of the reference level. The RBM downscale trip is bypassed for reactor power s 25 9% of rated.

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i COLR REVISION 128 FAGE 8 OF 26 Y_--__-___________

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RWPE: G4.02 3.0 CORE OPERATING LIMITS

' 3.1 Averaoe Planar Linear Heat Generation Rate (APLHGR)

Reference Technical Specification: 3.11.A Da,1ng 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 "mits, MAPLHGRr and MAPLHGR,. The flow-dependent APLHGR limit, MAPLHGRr, is the product of the MAPLHGR flow factor, MAPFACr, shown in Figure 3.1-6 and the MAPLHGR for rated power and flow conditions. The power-dependent APLHGR limit, MAPLHGRp, is the prod;ct of the MAPLHGR power factor, MAPFACp, shown in Figure 3.1-7 and the MAPLHGR for rated power _ and flow conditions. The MAPLHGR 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 3.1-5.

J; The core loading pattern for each type of fuel in the reactor vessel

[

is shown for the present cycle in Figure 4.0-1.

1 3.2 Linear Heat Generation Race (LHGR)

Reference Technical Specification: 3.11.8 During reactor power operation, the LHGR of any rod in any fuel assembly at any axial location shall not excced the limits presented in Table 3.2.1.

COLR

' REVISION 128 PAGE 9 OF 26 f

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PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.2.1

~

LHGR Operatina Limits LHGR Operating Fuel Tvoe Limit (KW/ft)

BP8DQ8323 14,4 BP8HXB355 14,4 BP9 HUB 378 14,4 BP9 DUB 408-6G5.0/7G4.0 14.4 BP9 DUB 408-16GZ1 14.4 COLR I

PAGE 10 OF 26 l

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. REVISION 12B PAGE 17 OF 26

i l-PILGRIM NUCLEAR POWER STATION l

PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 l

3.3 Minimum Critical Power Ratio (MCPR)

_ Reference Technical Specification: 3.11.C 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 MCPR operating limits, MCPRr and MCPRe. The flow-dependent MCPR operating limit, MCPRr, is provided in Figure 3.3-1. For core thermal powers less then or equal to Ps,..., the power-dependent MCPR operating limit, MCPRp, is provided in Figure 3.3-2. Above Pey., MCPRp is the product of the rated power and flow MCPR operating limit presented in Table 3.3.1, and the Kp factor presented in Figure 3.3-2. Figure 3.3-2 also specifies the maximum value for Pey....

The rated power and flow MCPR operating limits presented in Tables 3.3.1 are functions of t for the indicated MOC and EOC l

cycle exposures.

The value of x in Table 3.3.1 shall be equal to 1.0, unless it is l

calculated from the results of the surveillance testing of Technical Specification 4.3.C, as follows:

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

, 3.3 Minimum Critical Power Ratio (MCPR) (Continued)

Number of surveillance tests performed to date in the n

=

present cycle Total number of active control rods Ni

=

Number of active control rods measured in the i*

N

=

i surveillance test Average scram time to drop *out of Notch 34 position ti

=

of all rods measured in the i surveillance test Mean of the distribution for average scram

=

insertion time to drop out of Notch 34 0.937 sec

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Standard deviation of the distribution for average o

=

scram insertion time to dropout of Notch 34 0.021 sec

=

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COLR REVISION 12B PAGE 19 OF 26 L_-_-___________-____-____

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.3.1, Sh.1 of 2 l

MOC MCPR Operatina Limits The MCPR opercting limits (OLMCPR) as a function of t for operation from the Beginning of Cycle (BOC) to the End of Cycle (EOC) - 4361 MWD /ST with core flow s107.5% of rated are:

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OLMCPR (t}

I t s 0.0 1.31 0.0 < T s 0.1 1.31 0.1 < t s 0.2 1.31 0.2 < t s 0.3 1.31 0.3 < t s 0.4 1.31 0.4 < t s 0.5 1.32 0.5 < t s 0 6 1.33 0.6 < t s 0.7 1.34 0.7 < t s 0. 8 1.34 0.8 < t s 0.9 1.35 0.9 < t s 1.0 1.36 I

i COLR PAGE 20 OF 26 REVISION 12B-V

PILGRIM NUCLEAR POWER STATION

~

PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 l

Tab!e 3.3.1, Sh. 2 of 2 l

EOC MCPR Operatina Limits The MCPR operating !;mits (OLMCPR) as a function of t for operation from the l-End of Cycle (EOC)-'4361 MWD /ST to the EOC with core flow s107.5% of rated are:

1 OLMCPR M l

t s 0.0 1.36 0.0 < t s 0.1 1.37 0.1 < t s 0.2 1.37 0.2 < t s 0.3 1.38 0.3 < t s 0.4 1.38 0.4 < t s 0.5 1,39 0.5 < t s 0.6 1.40 0.6 < t s 0.7 1.40 0.7 < t s 0.8 1.41 0.8 < t s 0.9 1.41 0.9 < t s 1.0 1.42 I

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-REVISION 12B PAGE 21 OF 26 ig

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 5

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PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 RATED MCPR MULTIPLIER (Kp) w n

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PILGRLM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 3.4 Eo_wer/ Flow Rejati.onship During Power Ope _r_aign 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.

Fuel Tyn3

. Cycle Loaded Number Irradiated BP8DQB323 9

96 BP8HXB355 10 140 BP9 HUB 378 11 136 New P9 DUB 408-6G5.0/7G4.0 12 64 P9 DUB 408-16GZ1 12 144

'I otal 580 The reactor vessel core contains 145 crudform-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 EEEERENCES 5.1 NEDE-24011-P-A-13 and NEDE-24011-P-A-13-US," General Electric Standard Application for Reactor Fuel", August,1996.

5.2 NEDC-31852-P," Pilgrim Nuclear Power Station SAFEPJGESTR-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.

I COLR REVISION 12B PAGE 24 OF 26 1

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

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MBIBIBBBBBBBB

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BBBBBBBBBBBBBBBIEG BEM M M M M ME4 H M M

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M M BE N E454BBBBBER H BBBE

-M BRE4E4BIBIM H BRM BEBBBE M M E4 E4 D E E4 H H E4 E+E M MDEE454HE458BRM HHHHHHH 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 FuelTypes (CycleLo8&4)

E BP8DQB323 (Cycle 9)

E BP9 HUB 378 (Cycle 11)

.@ BP8HXB355 (Cycle 10)

E P9 DUB 408-6G5.ORG4.0 (Cycle 12) l 3

P9 DUB 40816GZ1 (Cycle 12)

FIGURE 4.01 Reactor Vessel Core Loading Pattern COLR REVISION 12B PAGE 26 OF 26

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