LR-N05-0096, Core Operating Limits Report - Cycle 13

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Core Operating Limits Report - Cycle 13
ML050550070
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 02/11/2005
From: Perino C
Public Service Enterprise Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N05-0096
Download: ML050550070 (31)
v • d • e


Text

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 IN FEB 1 1 2005 o PSEG NuitclearLLC LR-N05-0096 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 CORE OPERATING LIMITS REPORT - CYCLE 13 HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 In accordance with section 6.9.1.9 of the Hope Creek Technical Specifications, PSEG Nuclear LLC submits Revision 0 of the Core Operating Limits Report (COLR) for Hope Creek Cycle 13 (NFS-0243, Rev. 0) in Attachment 1 to this letter.

Should you have any questions, please contact Mr. Paul Duke at (856) 339-1466.

Christina L. Perino Director - Regulatory Assurance Attachment pCoD I 95-2168 REV. 7/99

Document Control Desk FEB 1 1 2005 LR-N05-0096 C Mr. S. Collins, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. Daniel Collins, Licensing Project Manager - Hope Creek U. S. Nuclear Regulatory Commission Mail Stop 08B2 Washington, DC 20555 USNRC Senior Resident Inspector - Hope Creek (X24)

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

Document Control Desk LR-N03-0250 Attachment I NFS-0243, Rev. 0

NFS-0243 Revision 0 Hope Creek Generating Station Core Operating Limits Report Cycle 13/ Reload 12 Effective Date: I g1 c5C Prepared By: Date: o0foJ 2o0o Shie-Jeng Pgg, clear Senior Engine,er Reviewed By: Date: 11J31/S Steven G. Bier, Nuclear Fuels Staff Engineer Concurrence I ly:. &Tvt4lfC VT- Date: / /L/ S Donald V. Notigan, Sul Hope Creek Reactor & Analysis Approved By:. Date: I I1s5t5 Michael M. Mannion, Manager Nuclear Fuels/Reactor Engineering Page 1 of 28

NFS-0243 Revision 0 Table of Contents Section Description Page

1.0 INTRODUCTION

5 2.0 TECHNICAL SPECIFICATIONS THAT REFERENCE THE COLR 6 2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE 7 2.2 MINIMUM CRITICAL POWER RATIO 12 2.3 LINEAR HEAT GENERATION RATE 20 2.4 OPRM TRIP SETPOINT 25

3.0 REFERENCES

26 Appendix A: Method of Core Average Scram Speed Calculation 27 Page 2 of 28 p

NFS-0243 Revision 0 List of Tables Table Description Page Table 2.1- 1: APLHGR Data for GE14 Fuel (Two Recirculation Loop Operation) 8 Table 2.1- 2: APLHGR Data for GE14 Fuel (Single Recirculation Loop Operation) 8 Table 2.1- 3: APLHGR Data for SVEA-96+ Fuel (Two Recirculation Loop Operation) 9 Table 2.1- 4: APLHGR Data for SVEA-96+ Fuel (Single Recirculation Loop Operation)9 Table 2.2- 1: Cycle 13 MCPR Operating limits: Cycle Exposure < 8693 MYd/MMTU 13 Table 2.2- 2: Cycle 13 MCPR Operating limits: Cycle Exposure > 8693 MBd/MTU_ 14 Table 2.2- 3: Kf Multiplier Data 19 Table 2.3- 1: LHGR Limit for GE14 (Two Recirculation Loop Operation) 21 Table 2.3- 2: LHGR Limit for GE14 (Single Recirculation Loop Operation) 21 Table 2.3- 3: LHGR Limit for SVEA-96+ (Two Recirculation Loop Operation) 22 Table 2.3- 4: LHGR Limit for SVEA-96+ (Single Recirculation Loop Operation) 22 Page 3 of 28

NFS-0243 Revision 0 List of Figures Figures Description Page Figure 2.1 - 1: APLHGR Limit for Fuel Bundle GEI4 10 Figure 2.1- 2: APLHGR Limit for Fuel Bundle SVEA-96+ 11 Figure 2.2-1: Rated Power MCPR Limit: GE14, Cycle Exposure S 8693 MWD/MTU 15 Figure 2.2-2: Rated Power MCPR Limit: SVEA-96+, Cycle Exposure

  • 8693 MWD/MTU _ 16 Figure 2.2-3: Rated Power MCPR Limit: GE14, Cycle Exposure > 8693 MWD/MTU 17 Figure 2.2-4: Rated Power MCPR Limit: SVEA-96+, Cycle Exposure > 8693 MWD/MTU 18 Figure 2.2-5 Kf Multiplier Curve 19 Figure 2.3- 1: LHGR'Limit for GE14 23 Figure 2.3- 2: LHGR Limit for SVEA-96+ 24 Page 4 of 28

NFS-0243 Revision 0

1.0 INTRODUCTION

The purpose of this report is to provide the Core Operating Limits for Hope Creek Generation Station Unit 1 Cycle 13/ Reload 12 operation. In addition, this report will provide information on Oscillation Power Range Monitor (OPRM) setpoint, single recirculation loop operation, average scram speed and determination of the Core Maximum Fraction of Limiting Power Density. Finally, this report also provides a reference to the most recent revision of the implemented approved methodology. The limits presented here correspond to the core thermal limits for Average Planar Linear Heat Generation Rate (APLHGR), Minimum Critical Power Ratio (MCPR), MCPR Flow Adjustment Factor (Kf) and Linear Heat Generation Rate (LHGR).

These operating limit values have been determined using NRC approved methods contained in GESTAR-II [1], NEDE-2401 1-P-A (Revision 14) and are established such that all applicable fuel thermal-mechanical, core thermal-hydraulic, ECCS, and nuclear limits such as shutdown margin, and transient and accident analysis limits are met.

Hope Creek Technical Specifications Section 3.2 references this report as the source for certain LIMITING CONDITIONS FOR OPERATION. These are included in Section 2 of this document. Hope Creek Technical Specification 6.9.1.9 also requires that this report, including any mid cycle revisions, shall be provided, upon issuance, to the NRC.

This document is specific to Hope Creek Generating Station Unit I Cycle 13 / Reload 12 and shall not be applicable to any other core or cycle design. The thermal limits contained in this report are applicable whether the Crossflowlm correction factor is applied or not applied.

This report is applicable for Cycle 13 operation from the date of issuance through the end of effective full power capability or a cycle exposure of 11938 MJPld~1MYU (10830 Mkld/STU),

whichever occurs first [2]. End of effective full power capability is reached when 100%

rated power can no longer be maintained by increasing core flow (up to 105% of rated core flow), at rated feedwater temperatures, in the all-rods-out configuration.

Page 5 of 28

NFS-0243 Revision 0 2.0 TECHNICAL SPECIFICATIONS THAT REFERENCE THE COLR The TECHNICAL SPECIFICATIONS THAT REFERENCE THE COLR presented in this section are referenced by the Hope Creek Technical Specifications.

Tech. Spec. Title 2.1 Safety Limit Bases 3/4.2.1 Average Planar Linear Generation Rate 3/4.2.3 Minimum Critical Power Ratio 3/4.2.4 Linear Heat Generation Rate 3/4.3.11 Oscillation Power Range Monitor 3/4.4.1 Recirculation System Recirculation Loops 3/4.2.1 Bases Average Planar Linear Heat Generation Rate 6.9.1.9 Administrative Controls, Core Operating Limits Report Page6of 28

NFS-0243 Revision 0 2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMITING CONDITION FOR OPERATION:

All AVERAGE PLANAR LINEAR HEAT GENERATION RATES (APLHGRs) shall be less than or equal to the limits specified in Table 2.1-1 and Table 2.1-3.

When the Technical Specification Section 3/4.4.1 ACTION statement a.l.d is entered from that section's LCO, reduce the APLHGR limits to the values specified in Tables 2.1-2 and 2.1-4.

When hand calculations are required, all APLHGRs for each type of fuel as a function of AVERAGE EXPOSURE shall not exceed the limits specified in Figures 2.1-1 and 2.1-2.

Page 7 of 28

NFS-0243 Revision 0 Table 2.1- 1: APLHGR Data for GE14 Fuel (Two Recirculation Loop Operation)

Bundle Types: GE14-PI OCNAB402-4G6.0/16G4.0-1 0OT-150-T6-2757 GE14-PI OCNAB402-5G6.0/14G4.0-1 0OT-150-T6-2758 Average Planar Exposure APLHGR Limit I MWD/STU MWD/MTU Kivlft I 0.00 0.00 12.82 19130 21090 12.82 57610 - 63500 8.00 63500 1 70000 5.00 Table 2.1- 2: APLHGR Data for GE14 Fuel (Single Recirculation Loop Operation)

Bundle Types: GE14-PI OCNAB402-4G6.0/16G4.0-1 OOT-150-T6-2757 GE14-PI OCNAB402-5G6.0/14G4.0-1 0OT-150-T6-2758 Average Planar Exposure APLHGR Limit MWD/STU MWD/MTU Kw/ft 0.00 0.00 10.25 19130 21090 10.25 57610 l 63500 6.40 63500 l 70000 4.00 Page 8 of 28

NFS-0243 Revision 0 Table 2.1- 3: APLHGR Data for SVEA-96+ Fuel (Two Recirculation Loop Operation)

Bundle Types: SVEA96-PIOCASB326-1 1GZ-568U-4WR-150-T6-2654 SVEA96-P 1OCASB326-1 1G4.5-568U-4WR-150-T6-2655 SVEA96-P1 OCASB360-12GZ-568U4WR-150-T6-2656 SVEA96-P 1OCASB360-12G5.0-568U-4 WR-150-T6-2657 SVEA96-P 1OCASB361-14GZ-568U4WR-150-T6-2658 SVEA96-P1 OCASB360-12G5.5/2G2.5-568U4WR-150-T6-2659 Average Planar Exposure APLHGR Limit MlWD/STU MWD/MTU KDTwft 0.00 0.00 12.85 3340 3680 12.85 14510 16000 10.97 58970 65000 7.24 Table 2.1- 4: APLHGR Data for SV"EA-96+ Fuel (Single Recirculation Loop Operation)

Bundle Types: SVEA96-P1 OCASB326-1 IGZ-568U-4WR-1 50-T6-2654 SVEA96-P1 OCASB326-1 IG4.5-568U-4WR-150-T6-2655 SVEA96-P1 OCASB360-12GZ-568U-4WR-150-T6-2656 SVEA96-P1 OCASB360-12G5.0-568U-4WR-150-T6-2657 SVEA96-PI OCASB361-14GZ-568U-4WR-150-T6-2658 SVEA96-P1OCASB360-12G5.5/2G2.5-568U-4WR-150-T6-2659 Average Planar Exposure APLHGR Limit MWD/STU MWD/MTU Kv/ft 0.00 0.00 10.28 3340 3680 10.28 14510 16000 8.77 58970 65000 5.79 Page 9 of 28

NFS-0243 Revision 0 0 30000 4000 A1WmxirE'eut (MUM)

Figure 2.1-1: APLHGR Limit for GE14 Fuel Page 10 of 28

NFS-0243 Revision 0 0 30000 40000 Figure 2.1- 2: APLHGR Limit for SVEA-96+ Fuel Page 11 of 28

NFS-0243 Revision 0 2.2 MINIMUM CRITICAL POWER RATIO LIMITING CONDITION FOR OPERATION The MINIMUM CRITICAL POWER RATIO (MCPR) shall be equal to or greater than the MCPR limit as computed from the following steps:

1. Determine T as defined in Appendix A.
2. Linearly interpolate a MCPR value as a function of t from the MCPR value at C=

0 and the MCPR value at T = 1 as specified in Table 2.2-1 and Table 2.2-2. The obtained value shall be checked with the value as shown in Figures 2.2-1 to 2.2-4.

3. When in single loop operation, add 0.02 to the MCPR value obtained from Step 2.
4. For core flow correction, first obtain Kf value by linearly interpolating from Table 2.2-3 and check the result with the curve shown in Figure 2.2-5. Multiply the MCPR value obtained from Step 2 (or Step 3 as required) by the Kf value.

Note that the MCPR limit is a function of core average scram speed ('[), cycle exposure, EOC-RPT operability, reactor coolant recirculation loop operation condition and main turbine bypass operability.

EOC-RPT system operability is defined by Hope Creek Technical Specification 3.3.4.2.

Reactor coolant recirculation loop operation condition is defined by Hope Creek Technical Specification 3.4.1.1.

Main Turbine Bypass operability is defined by Hope Creek Technical Specification 3.7.7.

Page 12 of 28

NFS-0243 Revision 0 Table 2.2- 1: Cycle 13 MCPR Operating limits:

Cycle Exposure

Conditions Limit GE14V) SVEA-96+(2)

Option A (T = 1) Rated Power 1.45 1.47 EOC-RPT Operable Option B ('r =0) Rated Power 1.34 1.36 EOC-RPT Operable Option A (T = 1) Rated Power 1.47 1.48 EOC-RPT Inoperable Option B (T =0) Rated Power 1.36 1.37 EOC-RPT Inoperable

1. GE14 fuel design:

GE14-PIOCNAB4024G6.0116G4.0-lOOT-150-T6-2757 GE14-P IOCNAB402-5G6.0O14G4.0-1 OOT-1 50-T6-2758

2. SVEA-96+ fuel design:

SVEA96-PIOCASB326-1 IGZ-568U-4WR-150-T6-2654 SVEA96-PIOCASB326-1 IG4.5-568U-4WR-150-T6-2655 SVEA96-PIOCASB360-12GZ-568U-4VWR-150-T6-2656 SVEA96-PIOCASB360-12G5.0-568U-4WR-150-T6-2657 SVEA96-PIOCASB361-14GZ-568U-4WR-150-T6-2658 SVEA96-PIOCASB360-12G5.5/2G2.5-568U-4UWR-150-T6-2659 Page 13 of 28

NFS-0243 Revision 0 Table 2.2- 2: Cycle 13 MCPR Operating limits:

Cycle Exposure > 8693 Mfl'd/MTU Main Turbine Bypass Operable Cycle Exposure > 8693 M 'dMTU (7886 MWd/STU)

Conditions Limit GE14(') SVEA-96+( 2 )

Option A (r = 1) Rated Power 1.56 1.60 EOC-RPT Operable Option B (T = 0) Rated Power 1.39 1.43 EOC-RPT Operable Option A (T = 1) Rated Power 1.59 1.60 EOC-RPT Inoperable Option B (T = 0) Rated Power 1.42 1.43 EOC-RPT Inoperable

1. GE14 fuel design:

GE14-PlOCNAB4024G6.0/16G4.0-l OOT-150-T6-2757 GE14-PI OCNAB402-5G6.0/14G4.0-lOOT-150-T6-2758

2. SVEA-96+ fuel design:

SVEA96-PIOCASB326-1 IGZ-568U-4WR-150-T6-2654 SVEA96-PlOCASB326-1 IG4.5-568U-4WR-150-T6-2655 SVEA96-PlOCASB360-12GZ-568U4WR-150-T6-2656 SVEA96-PIOCASB360-12G5.0-568U-4WR-150-T6-2657 SVEA96-PIOCASB361-14GZ-568U-4WR-150-T6-2658 SVEA96-P I OCASB360-12G5.5/2G2.5-568U4WR-150-T6-2659 I

Page 14 of 28

NFS-0243 Revision 0 1.65 I I I Main Turbine Bypass Operable Two Loop Operation 1.60 Fuel Type: GE14 Exposure <= 8693 MWD/MTU

. 1.55 (7886 MWD/ST [ ______

E 0._

.E 1.50 0-

[EOC-RPT Inoperable o 1.45 1.4 1.35 EOC-RPT Operable 1.30 0.00 0.10 0.20 0.30 OA0 0.50 0.60 0.70 0.80 0.90 1.00 Tau (Scram Speed)

Figure 2.2-1: Rated Power MCPR Limit: GE14, Cycle Exposure 5 8693 AIMWDJMTU Page 15 of 28

NFS-0243 Revision 0 1.65 Main Turbine Bypass Operable Two Loop Operation 1.60 Fuel Type: SVEA-96+

Exposure <= 8693 MWD/MTU

. 1.55 (7886 MWD/STU) en

.= 1.50 I- [ EOC-RPT Inoperable o 1A5

1.40

=__ IEOC-RPT Operable]

1.35 1.30 ='___

0.00 0.10 0.20 I-I 0.30 0.40

=

0.50 0.60 0.70 0.80 0.90 1.00 Tau (Scram Speed)

Figure 2.2-2: Rated Power MCPR Limit: SVEA-96+, Cycle Exposure

  • 8693 MWD/MTU Page 16 of 28

NFS-0243 Revision 0 1.65 1.60

.- 1.55 14

.E 1.50 C'.

1.40 1.35 1.30 4-0.00 0.10 0.20 0.30 0.40 0.50 0.60 0.70 0.80 0.90 1.00 Tau (Scram Speed)

Figure 2.2-3: Rated Power MCPR Limit: GE14, Cycle Exposure > 8693 MWVDJMTU Page 17 of 28

NFS-0243 Revision 0 1.65 1.60

.= 1.55 E

.E 1.50 CZ A.

o 1.45 9 1.40 1.35 1.30 '-

0.00 0.10 0.20 0.30 0.40 0.50 0.60 0.70 0.80 0.90 1.00 Tau (Scram Speed)

Note The same rated power MCPR operating limit is applied to both EOC-RPT Operable and EOC-RPT Inoperable for SVEA-96+ under the condition of Cycle Exposure > 8693 MWD/MTU, Main Turbine Bypass Operable and Two Loop Operation.

Figure 2.24: Rated Power MCPR Limit: SVEA-96+, Cycle Exposure > 8693 MWD/MTU Page 18 of 28

NFS-0243 Revision 0 Table 2.2- 3: Kr Multiplier Data Initial Flow Kr

(% Rated Flow) Multiplier 25.00 1.2532 82.404 1.0000 105.00 1.0000 1.30 A  : 0 1.25 1.20 1.15

=1'

-- E noSUr

=1.10 S 1.05 1.00 0.95 - (82.404, 1.0000) 0.90 _ II 0.85 0.80 _

20.00 40.00 60.00 80.00 100.00 120.00 Core Flow (% Rated)

Figure 2.2-5 Kr Multiplier Curve Page 19 of 28

NFS-0243 Revision 0 2.3 LINEAR HEAT GENERATION RATE LIMITING CONDITION FOR OPERATION The LINEAR HEAT GENERATION RATE (LHGR) shall not exceed the limit specified in Table 2.3-1 and Table 2.3-3.

When the Technical Specification Section 3/4.4.1 ACTION statement a.l.e is entered from that section's LCO, reduce the LHGR limits to a value specified in Table 2.3-2 and Table 2.3-4.

When hand calculations are required, all LHGRs for each type of fuel as a function of Peak Pellet Exposure shall not exceed the limits specified in Figure 2.3-1 and Figure 2.3-2.

The CORE MAXIMUM FRACTION OF LIMITING POWER DENSITY as implemented in Technical Specification Section 3/4.2.2 shall use a FRACTION OF LIMITING POWER DENSITY that is based on a specified LHGR equal to the exposure dependent LHGR in Table 2.3-1 through Table 2.34 for both GE14 and SVEA-96+ fuel assemblies.

Page 20 of 28

NFS-0243 Revision 0 Table 2.3- 1: LHGR Limit for GE14 (Two Recirculation Loop Operation)

Peak Pellet Exposure LHGR Limit MWD/MTU (kW / ft)

(MIWD/STU) GE14 0

(0) 13.4 16000 (14510) 13.4 63500 (57610) 8.0 70000 (63500) 5.0 Table 2.3- 2: LHGR Limit for GE14 (Single Recirculation Loop Operation)

Peak Pellet Exposure LHGR Limit MWD/MTU (kF / ft)

(MWD/STU) GE14 0

(0) 10.7 16000 (14510) 10.7 63500 (57610) 6.4 70000 (63500) 4.0 Page 21 of 28

NFS-0243 NFS-0243 Revision 0 Table 2.3- 3: LHGR Limit for SVEA-96+ (Two Recirculation Loop Operation)

Peak Pellet Exposure LHGR Limit MWD/MTU (kW / ft)

(MWD/STU) SVEA-96+

0 (0) 13.4 16000 (14510) 10.9 65000 (58970) 7.2 Table 2.3- 4: LHGR Limit for SVEA-96+ (Single Recirculation Loop Operation)

Peak Pellet Exposure LHGR Limit MWD/MTU (kW / ft)

(MWIUSTU) SVEA-96+

0 (0) 10.7 16000 (14510) 8.7 65000 (58970) 5.7 Page 22 of 28

NFS-0243 Revision 0 0 10000 20000 30000 40000 )000 PcakPdM 5pmm(NSNMl Figure 2.3- 1: LHGR Limit for GE14 Page 23 of 28

NFS-0243 Revision 0 0 30000 40000 hek~et EW= (MMI Figure 2.3- 2: LHGR Limit for SVEA-96+

Page 24 of 28

NFS-0243 Revision 0 2.4 OPRM TRIP SETPOINT LIMITING CONDITION FOR OPERATION Four channels of the OPRM instrumentation shall be OPERABLE. Each OPRM channel period based algorithm amplitude trip setpoint (Sp) shall be less than or equal to the Allowable Value of 1.07.

Page 25 of 28

NFS-0243 Revision 0

3.0 REFERENCES

1. Nuclear Fuel Section Design Input File HCG.5-0002,"General Electric Standard Application for Reactor Fuel," General Electric Company, NEDE-2401 I-P-A-14, and the U.S. Supplement NEDE-2401 1-P-A-14-US.
2. Nuclear Fuel Section Vendor Technical Document, NFVD-GE-2004-009-01, "Supplemental Reload Licensing Report for Hope Creek Unit 1 Reload 12 Cycle 13" GE Nuclear Energy 0000-0031-0596-SRLR, Rev. 1, December 2004.
3. Nuclear Fuel Section Design Input File HCG.5-0020, "Fuel Bundle Information Report for Hope Creek Unit I Reload 12 Cycle 13," 0000-0031-0596-FBIR, December 2004.
4. Nuclear Fuel Section Design Input File HCG.5-0024, "Cycle 13 Attachment to NC.NF-AP.ZZ-6004(Q) OPRM Setpoint," December 2004.

Page 26 of 28

NFS-0243 Revision 0 A

Appendix A: Method of Core Average Scram Speed Calculation Page 27 of 28

NFS-0243 Revision 0 Method of Core Average Scram Speed, A, Calculation r is defined as T=(Tave - TB )

T-rB)

TA - TB where:

TA =0.86 seconds, control rod average scram insertion time limit to notch 39 per Specification 3.1.3.3

_ _1/2 TB = 0.672 +1.65jN E N, j (0.016)

Nr EN, n = number of surveillance tests performed to date in cycle, N, = number of active control rods measured in the i'h surveillance test,

= average scram time to notch 39 of all rods measured in the ith surveillance test, and:

N. = total number of active rods measured in Specification 4.1.3.2.a.

If Tave < TB set T = 0 to apply Option B OLMCPR.

T shall be 1.0 (T = 1.0) prior to performance of the initial scram time measurements for the cycle in accordance with Specification 4.1.3.2.

Page 28 of 28

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