LR-N06-0410, Core Operating Limits Report - Cycle 16

Core Operating Limits Report - Cycle 16

ML062910178
Person / Time
Site:	Salem
Issue date:	10/09/2006
From:	Joyce T Public Service Enterprise Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N06-0410
Download: ML062910178 (14)

Text

I . ) PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 0 PSEG ANuclear LLC Technical Specification 6.9.1.9 OCT 09 200 LR-N06-0410 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555-001 Salem Nuclear Generating Station Unit 2 Facility Operating License No. DPR-75 NRC Docket No. 50-311

SUBJECT:

CORE OPERATING LIMITS REPORT - CYCLE 16 In accordance with section 6.9.1.9 of the Salem Unit 2 Technical Specifications, PSEG Nuclear LLC submits the Core Operating Limits Report (COLR) for Salem Unit 2 Cycle 16 in Attachment 1 to this letter.

Should you have any questions regarding this submittal, please contact Mr. E. Villar at (856) 339-5456.

Sincerely, Thomas P. Joyce Site Vice President - Salem Attachments (1)

/4)001 95-2168 REV. 7/99

Page 2 OCT 0 9 2006 Document Control Desk LR-N06-041 0 C Mr. Samuel Collins, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U. S. Nuclear Regulatory Commission Attn: Mr. S. Bailey, Licensing Project Manager- Salem Mail Stop 08B1 Washington, DC 20555-0001 USNRC Senior Resident Inspector - Salem (X24)

Mr. K.Tosch, Manager IV Bureau of Nuclear Engineering P.O. Box 415 Trenton, NJ 08625

NF-PSE-06-48 Revision 0 August 2006 Core Operating Limits Report for Salem Unit 2, Cycle 16 PREPARED: B. W. Ge.=, DATE:

Westinghouse Engineer REVIEWED: I, R. Guthridge DATE:

Westinghouse Engineer APPROVED: T._RQdapk DATE:

Westinghouse Manager "Electronkally Approved Records Are Authenticated In the Electronic Document Management System" Page I of 12

PSEG Nuclear LLC Page 2 of 12 Revision 0 SALEM UNIT 2 CYCLE 16 COLR August 2006 TABLE OF CONTENTS Section Section Title Page Number Number Table of Contents 2 List of Figures 3 1.0 Core Operating Limits Report 4 2.0 Operating Limits 5 2.1 Moderator Temperature Coefficient (Specification 3.1.1.3) 5 2.2 Control Rod Insertion Limits (Specification 3.1.3.5) 6 2.3 Axial Flux Difference (Specification 3.2.1) 6 2.4 Heat Flux Hot Channel Factor - Fo(z) (Specification 3.2.2) 6 2.5 Nuclear Enthaply Rise Hot Channel Factor F%,, 1 (Specification 3.2.3) 8 2.6 Boron Concentration (Specification 3.9.1) 8 3.0 References 9

PSEG Nuclear LLC Page 3 of 12 Revision 0 SALEM UNIT 2 CYCLE 16 COLR August 2006 LIST OF FIGURES Figure Page Number Number 1 Rod Bank Insertion Limits vs. Thermal Power 10 2 Axial Flux Difference Limits as a Function of Rated Thermal Power !1 3 K(z) - Normalized Fo(z) as a Function of Core Height 12

PSEG Nuclear LLC Page 4 of 12 Revision 0 SALEM UNIT 2 CYCLE 16 COLR August 2006 1.0 CORE OPERATING LIMITS REPQRT This Core Operating Limits Report (COLR) for Salem Unit 2 Cycle 16 has been prepared in accordance with the requirements of Technical Specification 6.9.1.9.

The Technical Specifications affected by this report are listed below:

3.1.1.3 Moderator Temperature Coefficient 3.1.3.5 Control Rod Insertion Limits 3.2.1 Axial Flux Difference 3.2.2 Heat Flux Hot Channel Factor - F0 (Z) 3.2.3 Nuclear Enthalpy Rise Hot Channel Factor - FAllN 3.9.1 Boron Concentration

PSEG Nuclear LLC Page 5 of 12 Revision 0 SALEM UJNITT 2 CYCIE 16 COLR August 2006 2.0 .OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using the NRC-approved methodologies specified in Technical Specification 6.9.1.9.

2.1 Moderator Temperature Coefficient (Specification 3.1.1.3) 2.1.1 The Moderator Temperature Coefficient (MTC) limits are:

The BOL/ARO/HZP-MTC shall be less positive than or equal to 0 Ak/k"°F.

The EOL/ARO/RTP-MTC shall be less negative than or equal to -4.4x10"4 Ak/kI°F.

2.1.2 The MTC Surveillance limit is:

The 300 ppm!ARO/RTP-MTC should be less negative than or equal to -3.7xl 0"4 Ak/k/F.

where: BOL stands for Beginning of Cycle Life ARO stands for All Rods Out HZP stands for Hot Zero THERMAL POWER EOL stands for End or Cycle Life RTP stands for Rated THERMAL POWER

PSEG Nuclear LLC Page 6 of 12 Revision 0 SALEM UNIT 2 CYCLE 16 COLR August 2006 2.2 Control Rod Insertion Limits (Specification 3.1.3.5) 2.2.1 The control rod banks shall be limited in physical insertion as shown in Figure 1.

2.3 Axial Flux Difference (Specification 3.2.1)

[Constant Axial Offset Control (CAOC) Methodology]

2.3.1 The Axial Flux Difference (AFD) target band shall be the more restrictive of

(+6%, -9%) or the target band as defined in Reference 2.

2.3.2 The AFD Acceptable Operation Limits are provided in Figure 2.

2.4 Heat Flux Hot Channel Factor - F0 (Z) (Specification 3.2.2)

[F,., Methodology]

F0 (Z) 5 FE . K(Z)for P > 0.5 RP Fp(Z) S 0.5

• K(Z)forP P.S0.5 where: P = THERMA4L POWER RATED THERMAL POWER 2.4.1 FoQp 2.40 2.4.2 K(Z) is provided in Figure 3.

2.4.3 F.,, - FJ.RT"[1.0 + PFý, (1.0- P)]

where: F,'JTP 1.80 for unrodded upper core planes I through 21 1.81 for unrodded lower core planes 22 through 61 2.13 for the core planes containing Bank D control rods PF,,. = 0.3

PSEG Nuclear LLC Page 7 of 12 Revision 0 SALEM UI'fT 2 CYCLE 16 COLR August 2006 2.4.4 If the Power Distribution Monitoring System (PDMS) is used for core power distribution surveillance and is OPERABLE, as defined in Technical Specification 3.3.3.14, the uncertainty, UFQ, to be applied to the Heat Flux Hot Channel Factor FQ(z) shall be calculated by the following formula:

U = (.0+-1.0 U, where:

UQ = Uncertainty for power peaking factor as defined in equation 5-19 of Reference I.

Uý = Engineering uncertainty factor.

= 1.03 Note: UrQ= PDMS Surveillance Report Core Monitor Fxy Uncertainty in %.

2.4.5 If the INCORE movable detectors are used for core power distribution surveillance, the uncertainty, UFr, to be applied to the Heat Flux Hot Channel Factor FQ(z) shall be calculated by the following formula:

UFQ =UV. "Ue where:

Uq, = Base FQ measurement uncertainty.

= 1.05 Uý = Engineering uncertainty factor.

= 1.03

PSEG Nuclear LLC Page 8 of 12 Revision 0 SALEM UNIT 2 CYCIE 16 COLR Augmst 2006 2.5 Nuclear Enthapy"Rise Hot Channel Factor - ENA11 (Specification 3.2.3)

F'a* = FndrP[1.0+PFA 1q(L0-P)]

where: P THERMAL POWER RATED THERMAL POWER 2.5.1 FdrTP 1.65 2.5.2 PFAIt = 0.3 2.5.3 If the Power Distribution Monitoring System (PDMS) is used for core power distribution surveillance and is OPERABLE, as defined in Technical Specification 3.3.3.14, the uncertainty, UFAN, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor, Fa*, shall be calculated by the following formula:

Urzff = 1.0 + U.-.f 100.0 where:

U&H = Uncertainty for enthalpy rise Nuclear Enthalpy Rise Hot Channel Factor as defined in equation 5-19 of Reference 1.

2.5.4 If the INCORE movable detectors are used for core power distribution surveillance, the uncertainty, UrAu, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FnHN shall be calculated by the following formula:

UKJ* = UFI,,,

where:

UF-Am =Base F,,%N measurement uncertainty.

= 1.04 2.6 Boron Concentration (Specification 3.9. 1)

A Mode 6 boron concentration, maintained at or above 2125 ppm, in the Reactor Coolant System, the fuel storage pool, the refueling canal, and the refueling cavity ensures the most restlrictive of the following reactivity conditions is met:

a) A K-effective (Klf) of 0.95 or less at All Rods In (ARl), Cold Zero Power (CZP) conditions with a I% &k/k uncertainty added.

b) A Kýfr of 0.99 or less at All Rods Out (ARO), CZP conditions with a 1%

Ak/k uncertainty added.

c) A boron concentration of greater than or equal to 2000 ppm, which includes a 50 ppm conservative allowance for uncertainties.

PSEG Nuclear LLC Page 9 of 12 Revision 0 SALEM UNIT 2 CYCLE 16 COLR August 2006

3.0 REFERENCES

I. WCAP-12472-P-A, BEACON Core Monitoring and Operations Sport System.

August 1994.

2. Salem Unit 2 Reactor Engineering Procedure, S2.RE-RA.ZZ-001I (Q), Tables.

3. Salem Nuclear Generating Station Unit No. 2, Amendment No. 251, License No.

DPR-75, Docket No. 50-311

PSEG Nuclear LLC Page 10of 12 Revision 0 SALFM UIMT 2 CYCLE 16 COLR Aug=st 2006 FIGURE 1 ROD BANK INSERTION LIMITS VS. THERMAL POWER 240 220 - - - -70.0, 226 200 z- BANK BII III III I I 180 o.16 4100, 170ý 160 1 /

2 BANK C c- 140 100 z0 60 40 20

<1101 0 10 20 30 40 50 60 70 80 90 100 PERCENT OF RATED TH ERMAL POWER (%)

PSEG Nuclear LLC Page I I of 12 Revision 0 SALEM UNIT 2 CYCLE 16 COLR August 2006 FIGURE 2 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER 100 80 60 Mo ir~

It V.

40 20 0.

Flux Dilferee (% Delta I)

b PSEG Nuclear LLC Page 12of 12 Revision 0 SALEM UNIT 2 CYCLE 16 COLR August 2006 FIGURE 3 K(Z) - NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT 1.2 1.0 0.8 _ _ _ _ _ _ _

0 JFQ K(Z) Height (FT)

_ __ I

_ _ _ _ _ _ _ _2.40 _ _ _1.00.

2.40 1.0 6.0 z

0.6 2.2 0.925 12.0 00.4 z

0.2 0.0 L.

0 2 4 6 8 10 12 CORE HEIGHT (FEET)

I