LR-N02-0222, Core Operating Limits Report - Cycle 13
| ML021720488 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/12/2002 |
| From: | Salamon G Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LR-N02-0222 | |
| Download: ML021720488 (13) | |
Text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 JUN 1 2 2002 0 PSEG Auclear LLC LR-N02-0222 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
CORE OPERATING LIMITS REPORT - CYCLE 13 SALEM GENERATING STATION UNIT NO. 2 FACILITY OPERATING LICENSE DPR-75 DOCKET NO. 50-311 In accordance with section 6.9.1.9 of the Salem Unit 2 Technical Specifications, PSEG Nuclear LLC submits Revision 0 of the Core Operating Limits Report (COLR) for Salem Unit 2 Cycle 13 (NFS-0209, Rev. 0) in Attachment 1 to this letter.
Should you have any questions, please contact Mr. Paul Duke at (856) 339-1466.
Sincer Manager - Nuclear Safety & Licensing Attachment 0
/
95-2168 REV. 7/99
Document Control Desk JUN 12 2002 LR-N02-0222 C
Mr. H. J. Miller, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. R. Fretz, Licensing Project Manager - Salem U. S. Nuclear Regulatory Commission Mail Stop 8B2 Washington, DC 20555 USNRC Senior Resident Inspector - Salem (X24)
Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering PO Box 415 Trenton, NJ 08625
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020606 PSEG Nuclear LLC NFS-0209 Revision 0 January 2002 Core Operating Limits Report for Salem Unit 2, Cycle 13 Ar X,
m PREPARED:
REVIEWED:
CONCURRANCE:
APPROVED:
Michael R. Merholz U
Senior Engineer Bradley A. Beck Engineer Thomas K. Ross Supervisor, SR&SA Michael M. Mannion Manager, Nuclear Fuel Section DATE:
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DATE:
/20o3.
DATE:
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DATE:
I "to a-Page 1 of 1
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020606 NFS-0209 PSEC Nuclear LLC Pige 2 of I I Revision 0 SALEM UNIT 2 CYCLE 13 COLR January 2002 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 3/4.1.1.3) 5 2.2 Control Rod Insertion Limits (Specification 3/4.1.3.5) 6 2.3 Axial Flux Difference (Specification 3/4.2. 1) 6 2.4 Heat Flux Hot Channel Factor - Fq(z) (Specification 3/4.2.2) 6 2.5 Nuclear Enthaply Rise Hot Channel Factor FNa (Specification 3/4.2.3) 8 3.0 References 8
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020606 PSEG Nuclear LLC SALEM UNIT 2 CYCLE 13 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 F1(z) as a Function of Core Height Page Number 9
10 Ii NFS-0209 Revision 0 January 2002 Pace 3 otf I
Figure Number 1
2 3
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020606 NFS-02009 PSEG Nuclear LLC Page 4 or I Revision 0 SALEM UNIT 2 CYCLE 13 COLR January 2002 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Salem Unit 2 Cycle 13 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:
3/4.1.1.3 Moderator Temperature Coefficient 3/4.1.3.5 Control Rod Insertion Limits 3/4.2.1 Axial Flux Difference, 3/4,2.2 Heat Flux Hot Channel Factor - FQ(Z) 3/4.2.3 Nuclear Enthalpy Rise Hot Channel Factor - FNAH
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020606 NFS-0209 PSEG Nuclear LLC Palle 5 of I I Revision 0 SALEM UNIT 2 CYCLE 13 COLR January 2002 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 3/4.1.1.3) 2.1.1 The Moderator Temperature Coefficient (MTC) limits are:
The BOL/AROIHZP-MTC shall be less positive than 0 Ak/k/0F.
The EOL/AROIRTP-MTC shall be less negative than -4.4x10g4 Ak/k/°F.
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
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020606 NFS-0209 PSEG Nuclear LLC Page 6 of 11 Revision 0 SALEM UNIT 2 CYCLE 13 COLR January 2002 2.2 Control Rod Insertion Limits (Specification 3/4.1.3.5) 2.2.1 The control rod banks shall be limited in physical insertion as shown in Figure 1.
2.3 Axial Flux Difference (Specification 3/4.2.1)
(Constant Axial Offset Control (CAOC) Methodology]
2.3.1 The Axial Flux Difference (AFD) target band is +6%, -9%.
2.3.2 The AFD Acceptable Operation Limits are provided in Figure 2.
2.4 Heat Flux Hot Channel Factor - FQ(Z) (Specification 314.2.2)
[F,.y Methodology]
FQ(Z) s t2!C-
- K(Z)forP>0.5 FQ'P FjZZ) *5
- K(Z)forP*<0.5 THERMAL POWER w
RATED THERMAL POWER 2.4.1 FQ2P = 2.40 2.4.2 K(Z) is provided in Figure 3.
2.4.3 FL = FrP
[1.0 + PF(1.O - P)j where: FRf
= 1.78 for unrodded core planes I through 31 1.82 for unrodded core planes 32 through 61 2.13 for the core planes containing Bank D control rods PF. = 0.3
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020606 NFS-0209 PSEG Nuclear LLC Paze 7 of I I Revision 0 SALEM UNIT 2 CYCLE 13 COLR January 2002 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, U,-. to be applied to the Heat Flux Hot Channel Factor FQ(z) shall be calculated by the following formula:
(UQ) 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 = Up*
"U where:
Uqu = Base FQ measurement uncertainty.
= 1.05 U, = Engineering uncertainty factor.
= 1.03
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020606 NFS-0209 PSEG Nuclear LLC Page 8 of 11 Revision 0 SALEM UNIT 2 CYCLE 13 COLR January 2002 2.5 Nuclear Enthalpy Rise Hot Channel Factor - F"NM (Specification 314.2.3)
I*NH
= FmfrP[l.0 +PFAH (1.0-P)]
THERMAL POWER RATED THERMAL POWER 2.5.1 FA1HRP(RFA withIFM) = 1.65 and FsHrP(VSH without IFM) 1.57 2.5.2 PFAM
= 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, UPAH, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor, 17,1 shall be calculated by the following formula:
UFM = 1.0 L
UA+
100.0 where:
UAH = Uncertainty for enthalpy rise 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, UF&, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FAHN shall be calculated by the following formula:
U'F& = U FHA, where:
UFpam =Base Fm measurement uncertainty.
= 1.04
3.0 REFERENCES
- 1. WCAP-12472-P-A, BEACON Core Monitoring and Operations Support System, August 1994.
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020606 PSEG Nuclear LLC SALEM UNIT 2 CYCLE 13 COLR FIGURE 1 240 220 200 180 160 140 120 100 80 0
10 20 30 40 50 60 70 PERCENT OF RATED THERMAL POWER (%)
80 90 100 NFS-0209 Revision 0 January 2002 Pagce 9 of' [L ROD BANK INSERTION LIMITS vs. THERMAL POWER mu U
f i l
I1 1.
I BIANKBl 0186T II-.1100 17Co BANK~~AN BDi__
A I
I-.
J
-L k
"0
- 0 t
U) 0 3
0 Z
0~
o.9
-J 0
.Iz 0 o 60 40 20 10
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020606 NFS-0209 PSEG Nuclear LLC Page 10or II Revision 0 SALEM UNIT 2 CYCLE 13 COLR January 2002 FIGURE 2 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER 100 1,.
1,
,1 1r-I I..
I I
(-11,90)1 (11,90) so UNACCEPTABLE UNACCEPTABLE OPERATION OPERATION ACCEPTABLE OPERATION 60 40 60 0
-50
-40
-30
-20
-10 0
10 20 30 40 50 Flux Difference (% Defta I)
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020606 PSEG Nuclear LLC SALEM UNIT 2 CYCLE 13 COLR FIGURE 3 Page I I of I I K(Z) - NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT 12 t.0 0.8 N
0 0.6 (9
0 z
S0.6 0i.
N z
0.4 0.2 2
4 6
CORE HEIGHT (FEET) 8 10 12 N FS- 0209 Revision 0 January 2002 (Z)tA H eight (F*E) 2.40 1.0 0.0 2.40 1.0 6.0 2.22 0.925 12.0 0.0 L 0 12