LR-N07-0028, Core Operating Limits Report - Cycle 19
| ML071090181 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 04/11/2007 |
| From: | Joyce T Public Service Enterprise Group |
| To: | Document Control Desk, NRC/NRR/ADRO |
| References | |
| LR-N07-0028 | |
| Download: ML071090181 (15) | |
Text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 0 PSEG Nuclear LLC APR 1t 20, Technical Specification 6.9.1.9 LR-N07-0028 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555-001 Salem Nuclear Generating Station Unit 1 Facility Operating License No. DPR-70 NRC Docket No. 50-272
SUBJECT:
CORE OPERATING LIMITS REPORT - CYCLE 19 In accordance with section 6.9.1.9 of the Salem Unit 1 Technical Specifications, PSEG Nuclear LLC submits the Core Operating Limits Report (COLR) for Salem Unit 1 Cycle 19 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) 4o DI 95-2168 REV. 7/99
APR 11 Document Control Desk Page 2 LR-N07-0028 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. R. Ennis, 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 LR-N07-0028 Core Operating Limit Report For Salem Unit 1, Cycle 19
COLR SALEM 1 Revision 0 NF-PSE-07-10 January 2007 Core Operating Limits Report for Salem Unit 1, Cycle 19 SIt-k Page 1 of 12
PSEG Nuclear LLC Page 2 of 12 Revision 0 SALEM UNIT 1 CYCLE 19 COLR January 2007 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 3.1.1.4) 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 - FQ(z) (Specification 3.2.2) 6 2.5 Nuclear Enthaply Rise Hot Channel Factor FNAH (Specification 3.2.3) 8 2.6 Boron Concentration (Specification 3.9.1) 8 3.0 References 9
Revision 0 January 2007 PSEG Nuclear LLC SALEM UNIT 1 CYCLE 19 COLR LIST OF FIGURES Figure Title Rod Bank Insertion Limits vs. Thermal Power Axial Flux Difference Limits as a Function of Rated Thermal Power K(z) - Normalized FQ(z) as a Function of Core Height Page 3 of 12 Figure Number 1
2 3
Page Number 10 11 12
PSEG Nuclear LLC Page 4 of 12 Revision 0 SALEM UNIT I CYCLE 19 COLR January 2007 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Salem Unit I Cycle 19 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:
3.1.1.4 Moderator Temperature Coefficient 3.1.3.5 Control Rod Insertion Limits 3.2.1 Axial Flux Difference 3.2.2 Heat Flux Hot Charmel Factor - FQ(Z) 3.2.3 Nuclear Enthalpy Rise Hot Channel Factor - FaHN 3.9.1 Boron Concentration
PSEG Nuclear LLC Page 5 of 12 Revision 0 SALEM UNIT 1 CYCLE 19 COLR January 2007 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 3.1.1.4) 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 -4.4x 10-4 Ak/k/0F.
2.1.2 The MTC Surveillance limit is:
The 300 ppm/ARO/RTP-MTC should be less negative than or equal to -3.7x 10-4 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 of Cycle Life RTP stands for Rated THERMAL POWER
PSEG Nuclear LLC Revision 0 SALEM UNIT 1 CYCLE 19 COLR January 2007 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 - FQ(Z) (Specification 3.2.2)
[Fxy Methodology]
FQRTP FQ(Z) *
- K(Z) for P > 0.5 FQRTP F2 (Z) 0.5
- K(Z)forPSO0.5 THERML P0.5 Page 6 of 12 where:
P
- RATTHERMAL P0 WER RATED THERMAL POWER 2.4.1 FQ2RrP =2.40 2.4.2 K(Z) is provided in Figure 3.
2.4.3 FyL FRTP[1.0+PFy(1.0- P)]
where: FxyRP
=
1.89 for unrodded upper core planes 1 through 7 1.77 for unrodded core planes 8 through 23 1.79 for unrodded core planes 24 through 54 1.85 for unrodded lower core planes 55 through 61 2.13 for the core planes containing Bank D control rods PFx, = 0.3
PSEG Nuclear LLC Revision 0 SALEM UNIT 1 CYCLE 19 COLR January 2007 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 100.0) "Ue where:
UQ = Uncertainty for power peaking factor as defined in equation 5-19 of Reference 1.
Ue = Engineering uncertainty factor.
= 1.03 Note: UFQ= 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, UFQ, to be applied to the Heat Flux Hot Channel Factor FQ(z) shall be calculated by the following formula:
UFQ = Uqu
- Ue where:
Uqu = Base FQ measurement uncertainty.
= 1.05 Ue = Engineering uncertainty factor.
=
1.03 Page 7 of 12
PSEG Nuclear LLC Page 8 of 12 Revision 0 SALEM UNIT 1 CYCLE 19 COLR January 2007 2.5 Nuclear Enthalpy Rise Hot Channel Factor - F NAH (Specification 3.2.3)
IF'AH = FAHTP[1.0+PFAH(1.0-P)]
THERMAL POWER RATED THERMAL POWER 2.5.1 FAHRvTp 1.65 2.5.2 PFAH
= 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, UFAH, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor, FAHN, shall be calculated by the following formula:
UFAI = 1.0 + UAH 100.0 where:
UAH = 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, UFAH, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FAHN shall be calculated by the following formula:
UFAIt = UFAHm where:
UFAHm =Base FAH measurement uncertainty.
=1.04 2.6 Boron Concentration (Specification 3.9.1)
A Mode 6 boron concentration, maintained at or above 2170 ppm, in the Reactor Coolant System, the fuel storage pool, the refueling canal, and the refueling cavity ensures the most restrictive of the following reactivity conditions is met:
a) A K-effective (Keff) of 0.95 or less at All Rods In (ARM), Cold Zero Power (CZP) conditions with a 1% Ak/k uncertainty added.
b) A Keff 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 I CYCLE 19 COLR January 2007
3.0 REFERENCES
- 1. WCAP-12472-P-A, BEACON Core Monitoring and Operations Support System, August 1994.
- 2.
Salem Unit I Reactor Engineering Procedure, SI.RE-RA.ZZ-001 I(Q), Tables.
- 3. Salem Nuclear Generating Station Unit No. 1, Amendment No. 272, License No.
DPR-70, Docket No. 50-272.
Revision 0 January 2007 PSEG Nuclear LLC SALEM UNIT I CYCLE 19 COLR FIGURE 1 ROD BANK INSERTION LIMITS VS. THERMAL POWER Page 10 of 12 240 220 200 180 160 C_ 140 C/)
z0 120 0
z< 100 0
zo 80 C-,
- 26 16.7, 226 z 70.0, 226 BAN K B 1 0, 170k 0,186 I V A
ZABANK C Iz
,41
-BANK D
Iz- - -
0, 8
yl Fl-c-FIR I--- I Y
11#1 f+1w
- 1 1
1 1
1 1
1 60 40 20 0
hA 0
10 20 30 40 50 60 70 PERCENT OF RATED THERMAL POWER (%)
80 90 1 00
Revision 0 January 2007 PSEG Nuclear LLC SALEM UNIT 1 CYCLE 19 COLR FIGURE 2 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER Page ll of 12 100 80 F~
76 I-0-
60 40 20 0
-50 Flux Difference (% Delta I)
N
Revision 0 January 2007 PSEG Nuclear LLC SALEM UNIT I CYCLE 19 COLR FIGURE 3 K(Z) - NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT Page 12 of 12 1.2 1.0 0.8 U
z 0.6 N
0.4 z
0.2 0.0 FQ K(Z)
Height (FT) 2.40 1.0 0.0 2.40 1.0 6.0 2.22 0.925 12.0 t
t t
~1~
0 2
4 6
8 CORE HEIGHT (FEET) 10 12