ML20209B986

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Rev 13A to Pilgrim Nuclear Power Station COLR for Cycle 13
ML20209B986
Person / Time
Site: Pilgrim
Issue date: 06/23/1999
From:
BOSTON EDISON CO.
To:
Shared Package
ML20209B985 List:
References
NUDOCS 9907080386
Download: ML20209B986 (29)
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Text

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PILGIUM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT ...

RTYPE: G4.02 (CYCLE 13) -

APPROVED I- Ob d O i:rationWrt D partment 9 Manager Date APPROVED: N M 4[ 77 N(icle)r Engin'eeYing ices Group Manager / Date APPROVED: . m dc2!ff e

Operations R' vipommittee Dste ORC Meeting #: 3-Ed r- )

APPROVED: / b7[2J[@

Plant Group Man 3ger I Dhte l

APPROVED: /

SdtiopUlredt(r h

3j'Date f

l EDR D 293 P PDR ,_

COLR REVISION 13A PAGE 1 OF 29

PILGR!M NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT .

RTYPE: G4.02 TABLE OF CONTENTS Pane TITL E/S IG N ATU RE PAG E .. . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . ... . . . .. . . . . . . . . . . . . . . . .. . ... . . . . . . . 1 TA B L E O F CON TENTS . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..................,2 .....

REC O RD O F REVIS ION S . . . . . .. . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 LI ST O F TA B LE S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 LI S T O F FI G U RES . . . . ., . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . a. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5

1.0 INTRODUCTION

... ....... ........ .... . ......................................6 2.0 INSTRUMENTATION TRIP SETTINGS ....... ..... ... . . .. .... .............. . 7 2.1 APRM Flux Scram Trip Setting (Run Mode) .......... .... . ..... ... .... 7 2.2 APRM Rod Block Trip Setting (Run Mode) .. ........... ......... ... ..... 8 2.3 Rod Block Monitor Trip Setting ... .... .. ......... ............. ... . ..... .. . 9.

3.0 ' CORE OPERATING LIMITS ..... . ..... ....... ..... ........... .... .. ......... .. ... 12

. ' 3.1 Average Planar Linear Heat Generation Rate ( AP L H G R) . . .. . . . . . . . . . . . . .. . . .. . . . . . . . . . . . . .. . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 3.2 Linear Heat Generation Rate (LHGR)..................... '.................... 12 3.3 Minimum Critical Power Ratio (MCPR) .... ......... . . . ........ . ... 21 .

3.4 Power / Flow Relationship ... ... ...... .. ...... ... ... . . . . ................. ...... .. 26 4.0 REACTOR VESSEL CORE DESIGN . ......................................26 5.0 REFE RE N C E S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .t. .. . . . . . 2 7 COLR REVISION 13A - PAGE 2 OF 29

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT .

RTYPE: G4.02 RECORD OF REVISIONS Revision , Effective Date. Description 8A 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 isstiance oflicense Cycle 9 operation amendment by NRC for ARTS and SAFER /GESTR 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 Applicabl: for use during approval Cycle 11 Operation 1IC Effective upon final Appligable for use during approval Cycle 11 Operation 11D Effective upon final Applicable for use during approval . Cycle 11 Operation 12A Effective d.ite based on Applicable for use during issuance oflicense Cycle 12 Operation amendment by NRC for SLMCPR of 1.08 ,

12B Effective upon final Renumbered Table 3.3-2 approval to 3.3-1, Sh. 2 of 2 and Table 3.3-1 to 3.3-1, Sh.Iof2 12C Effective upon final Changed Tech Spec section approval numbers referenced due to Tech Amedinent #177.

Pages affected: 6,24 12D Effective upon final incorporated stability log-approval term solution option I-A.

13A Effective upon final Applicable for use during approval Cycle 13 Operation COLR REVISION 13A PAGE 3 OF 29

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT .

RTYPE: G4.02 LIST OF TAdLES Number Title Pace 3.2-1 LHGR Operating Limits 13 3.3-1 MCPR Operating Limits 23 4

4 0 0

+

N COLR REVISION 13A PAGE 4 OF 29

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT .

RTYPE: G4.02 LIST OF FIGURES Number , Title . , , . Pane 2.1-1 Nominal & Allowable APRM Flux Scram Trip 10 Settings (Normal Feedwater Temperature) 2.2-1 Nominal & Allowable APRM Rod Block Trip 11 Settings (Normal Feedwater Temperature) 3.1-1 MAPLHGR for Fuel Type 14 P9 DUB 407-14GZ-100T-141-T 3.1 -2 MAPLHGR for Fuel Type BP8HXP355 15

' ' 3.1.-3 MAPLHOR for Fuel Type BP9 HUB 378.. 16 3.1-4 MAPLHGR for Fuel Type 17 P9 DUB 408-6G5.0/7G4.0 3.1-5 MAPLHGR for Fuel Type 18 P9 DUB 408-16GZ1 3.1-6 Flow-Dependent MAPLHGR Factor (MAPFACp) 19 3.1 -7. - Power-Dependent MAPHLOR Factor (MAPFACp) 20 3.3-1 Flow-Dependent MCPR Limits (MCPRp) 24 l 3.3-2 Power-Dependent MCPR Limits (MCPRp) 25 l 3.4-1 Power / Flow Operating Map 28 4.0-1 Reactor Vessel Core Loading Pattern 29 l

l COLR REVISION 13A PAGE 5 OF 29 -

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 13. In this report, Cycle'13 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:

Reference

)

Technical Specification

~

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 "Averai e Planar Linear Heat Generation Rate 3.11. A - ~

Linear leat Generation Rate (LHOR) 3.11.3 Minirr im Critical Power Ratio (MCPR) 3.11.C Power / Flow Relationship 3.11.D Reactor Vessel Core Design 4.2 If any of the core operating limits in this report are exceeded, actions will be taken l as defined in the referenced Technical Specification. .

1 The core operating limits in this report have been established for the present cycle using tile NRC-approved methodology provided in the documents listed both in Section 5.0, References, and in Technical Specification 5.6.5. These limits are established such that the applicablelimits of the plant safety analysis are met.

1 COLR

. REVISION 13A PAGE 6 OF 29

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

2.1 ' APRM Flux Scram Trio Sett'ine (Run Mode)

Reference Technical Soecifications: Table 3.1.1, 3.1.B.1 l

a. Normal Feedwater Heating or Low Thermal Reactor Power : i TFW 2 TFW(rated)-50 F ,

and rated equivalent at off-rated reactor conditions i OR l P s; 30%

f When the mode switch is in the run position, the average power range monitor (APRM) flux scram trip setting (S3) as a function of aligned drive flow shall be as given by Figure'2.1-1.

With a clamp at 120% of rated core thermal power and Ss = APRM flux scram trip setting in percent of rated thermal power (1998 MWt)-

TFW = Feedwater temperature in F TFW(rated) = Feedwater temperature at design rated reactor power conditions in 'F P= Core Thermal Power in % of rated The aligned drive flow is calcillated from the input drive ~ flow using the relationship given below:

' Wo = Wn100*(AD40) Wo40*(AD100) + DW D *h DWo- AD100 + AD40 Where:

Wo100 = 100.43 '

Wo40 = 32.135 DWo = Wol00 - Wo40

~AD40 = - Low flow drive flow alignment setting l AD100 = High flow drive flow alignment setting Woi = FCTR card input drive flow in percent of rated Wo = Aligned drive flow in percent of rated The APRM flux scram trip setting is valid only for operation using two j recirculation loops. Operation with one recirculation loop out of service is 1 restricted by License Condition 3.E. i l

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

l COLR 1

' REVISION 13A PAGE 7 OF 29 l u

PILGRIM NUCLEAR POWER STATION )

PNPS CORE OPERATING LIMITS REPORT .

RTYPE: G4.02 2.1 .APRM Flux Scram Trio Settinn (Run Mode)(Continued)

b. Reduced Fe.edwater Heating :

)

TFW < TFW(rated)- 50*F rated equivalent at off-rated reactor conditons ,

AND P > 30% ~ s i

Cycle 13 operations are not analyzed for reduced feedwater temperature.

l 2.2 APRM Rod Block Trio Settinn (Run Mode) j Reference Technical Specifications: Table 3.2.C-2,3.1.B.1

. , ' a. Normal Feedwater Heating or Low Thermal Reactor Power ;

TFW 2 TFW(rated)- 50 F rated equivalent at off-rated reactor conditons l OR I P s; 30%

When the mode switch is in the run position, the average power range monitor (APRM) rod block trip s-tting (SRB) as a function of aligned drive flow shall be as given by Figure 2.2-1.

With a clamp at. I 15% of rated core thermal power and Ss = APRM flux scram trip setting in percent of rated thermal power (1998 MW t)-

TFW = Feedwater temperature in F TFW(rated) = Feedwater temperature at design rated reactor powerconditionsin F

~

P= Core Thermal Power in % o"f rated The aligned drive flow is' calculated from the input drive flow using the relationship given below:

Wo = _Wp100*(AD40)- Wn40*(AD100) + DWo*Wp_t DWo- AD100 + AD40 Where:

Wo100 = - 100.43 - ,

- Wo40 = 32.135 1 DWo= Wol00 - Wo40 AD40 = - Low flow drive flow alignment setting

. AD100 = - High flow drive flow alignment setting Woi= FCTR card input drive flow in percent of rated Wo= - Aligned drive flow in percent of rated COLR REVISION 13A PAGE 8 OF 29 4 m

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

2.2 APRM Rod Block Trio Settine (Run Mode)

b. Reduced Feedwater Heating :

TFW < TFW(rated)- 50 F and rated equivalent of off-rated AND P > 30%

Cycle 13 operations are not analyzed for reduced feedwater temperature.

1 l

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:

Reactor Power, P Trip Setpoint -

(% of Rated) (% of Reference Level)

P s 25.9 Not applicable (All RBM Trips 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 seipoint shall be 2 94.0%

of the reference level. The RBM downscale trip is bypassed for reactor power s 25.9% of rated.

COLR REVISION 13A PAGE 9 OF 29 l

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l PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT ...

RTYPE: G4.02 3.0 CORE OPERATING LIMITS 3.1 Averane Planar Linear Heat Generation Rate (APLHGR) ,

Reference Technical Soccification: 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 i smaller of the flow- and power-dependent APLHOR limits, MAPLHGRf I and MAPLHORp The flow-dependent APLHGR limit, MAPLHGRf,is l the product of the MAPLHOR flow factor, MAPFACf, shown in Figure 3.1-6 and the MAPLHGR for rated power and flow conditions. The power-dependent APLHGR limit, MAPLHGRp is the product of the MAPLHGR power factor, MAPFACp, hown in Figure 3.1-7 and the MAPLHGR for rated power and flow conditions. The MAPLHOR for rated power and flow conditions for each fuel type as a function of axial -

' lo' cation a' nd average planar exposure are bassd on the 'a aproved' methodology referenced in Section 5.0 and programmec m 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. l 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) 4 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.

1 l

COLR REVISION 13A - PAGE 12 OF 29 l

.J

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT .

RTYPE: G4.02 Table 3.2-1 l LHOR Operatina Limits LHGR Operating Fuel Type Limit (KW/ft)

GE10-P8HXB355 14.4 GE-11P9 HUB 378 14.4 gel 1-P9 DUB 408-6G5.0/7G4.0 14.4 gel 1-P9 DUB 408-16GZ1 14.4 GE11-P9 DUB 407-14GZ 14.4. ,

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l COLR REVISION 13A PAGE 13 OF 29

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PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 3.3 Minimum Critical Power Ratio (MCPR) l Reference Technical Soecification: 3.11.C j 1

During power o wration, the MCPR shall be greater than or equal to the operating limit MCPR. Tie operating limit MCPR is the greater of the flow- and power-dependent MCPR operating limits, MCPRf and MCPRp. The flow-dependent MCPR operating limit, MCPRf, is provided in Figure 3.3-1. For core thennal powers less than or equal to Pbypass, the power-dependent MCPR operating limit,

-MCPRp, is provided in Figure 3.3-2. Above Pbypass, MCPR > is the product of the rated power and flow MCPR operating limit presented in "able 3.3-1, and the Kp factor presented in Figure 3.3-2. Figure 3.3-2 also specifies the maximum value for Pbypass. The rated power and flow MCPR operating limits presented in Tables 3.3-1 are functions of T .

. The value of x 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:

r... - r, 1.2 5 2 - r, Where:

=

t,,, Average scram time to drop out of Notch 34 N

[Nov e.i N

N, 4.i e

- Adjusted analysis mean to scram time Nn

=

p + 1.65cr ,

N,

\[t.1 j

REVISION 13A COLR j PAGE 21 OF 29

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

Number of surveillance tests performed to date in the present cycle

=

N1 Total number of active control rods

=

Ni Number of active control rods measured in the ith surveillance test ti =

Average scram time to drop out of Notch 34 position of all rods measured in the ith surveillance test

=

Mean of the distribution for average scram insertion time to drop out of Notch 34

=

0.937 see o =

Standard deviation of the distribution for average scram insertion time to dropout of Notch 34

=

0.021 sec l

4 4

COLR REVISION 13 A PAGE 22 OF 29

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.3-1 MCPR Operatina Limits The MCPR operating limits'(OLMCPR) as a function of T for operation from the .

Beginning of Cycle (BOC) to the End of Cycle (EOC) with core flow s107.5% of rated are:

I OLMCPR (t)

I s 0.0 1.35 0.0 < t s 0.I 1.36 0.1 < t s 0.3 1.37 0.3 < t s 0.5 1.38 0.5 < t s 0.6 1.39

. 0.6 < T.s 0.8 1.40 0.8 < t s 1.0 1.41 m

COLR REVISION 13A PAGE 23 OF 29

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PILORic NUCLEAR POWER STATION PNPS COR8 OPERATING LIMITS REPORT RTYPE: G4.02 3.4 Power / Flow Relationship Durina Power Operation 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. The Power / Flow Map, Figure 3.4-1 is applicable to operation with Normal fee.dwater heating.

Cycle 13 operations are not analyzed for reduced feedwater temperature.

Intentional operation within the Restricted Region is prohibited. The Restricted Region boundary as a function of aligned drive flow is as given in Figure 2.2 -1.

Note: The boundary of the Restricted Region is established by analysis in terms of thermal power and core flow as showu in Figure 3.4 - 1. The Restricted Region boundary is defined by the APRM Rod ' lock setpoints, which are a function of reactor recirculation flow as shown by Figure 2.2-1 4.0 REACTOR VESSEL CORE DESIGN Reference Technical Specification: 4.2 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 Type Cycle Number Loaded Irradiated GE-10-P8HXB355 10 76 gel 1-P9 HUB 378 11 136 Gell-P9 DUB 408-6G5.0/7G4.0 12 -

64 Gell-P9 DUB 408-16GZ1 12 144 New gel 1-P9 DUB 407-14GZ-100T-141-T 13 120 G E 1 1 -P9 DU B408-6G5.0/7G4.0-100T- 141 -T 13 40 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.

COLR REVISION 13A PAGE 26 OF 29

1 l

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

5.0 REFERENCES

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 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.

5.4 GENE-A13-00367-54, " Pilgrim Nuclear Power Station Reactor Stability Long-Term Solution Enhanced Option I-A Flow Mapping Application

. Output Cycle 11 Normal Feedwater Temperature Operating Range", l January 1997.

5.5 NEDO-32339-A, Revision 1, " Reactor Stability Long- Term Solution:

Enhanced Option I-A,", GENE, April 1998.

5.6 NEDO-32339 A, Supplement 3, Revision 1, " Reactor Stability Long-Term Solution: Enhannd Option I-A Flow Mapping Methodology,",

GENE, April 1998.

5.7 J11-03474-10SRLR, Rev 0, April 1999," Supplemental Reload Licensing Report, Reload 12, Cycle 13..

I COLR REVISION 13A PAGE 27 OF 29 l

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. . PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING I.INilTS REPORT -RTYPE G. o:

MMMMMMM
MMMMMMMMM
HMMMMMMMMMM '
H M M M M M M M M M M M M
H M M M M M M M M M M M M
MMMMMMMMMMMMM
M E M M M M M M M M M M M
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'  :::H M M M M M M M M M M M M

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MMMMMMMMMMM
MMMMMMMMM
MEMMMMM ill IIIIlIIIIII 1 3 $ 7 9 il 18 15 17 19 ?! 28 25 27 29 il 88 35 37 39 tr 48 45 97 49 $1 Fuel Type A= Gell-P9 DUB 407-14GL100T-141-T (Cycle 13) F=G E l l-P9 H LTB 378- 15G L 10(TT-141 -T (Cycle 11)

B =G E l l -P9 D U B408-605.OnG4.0- 10(TT- 141 -T (Cycle 13) G=GE10-PSHXB355-ilGL100M-145-T (Cycle 10)

C4Elo-P8HXB355-11GL100M-145-T (Cycle 10) H=G E l l-P9D UB 408-16GZ l-10CTT-T41 -T (Cycle 12)

} D=GE10-P810(B355-1IGL100M-145-T (Cycle 10) !=G E l 1 -P9 DUB 4084G 5.0RG4.0- 100T- 141 -T (Cycle 12)

E= Gell-P9 HUB 378-15GL100T-141-T (Cycle 11)

FIGUR E 4.01 Reactor Vessel Core Loading Pattern COLR r

REVISION 13A PAGE 29 OF 29

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