LR-N06-0214, Core Operating Limits Report - Cycle 14

Core Operating Limits Report - Cycle 14

ML061290268
Person / Time
Site:	Hope Creek
Issue date:	05/02/2006
From:	Jesse M Public Service Enterprise Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N06-0214
Download: ML061290268 (22)

Text

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 0 PSEG Nuclear LLC LR-N06-0214 MAY 0 2 2006 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 CORE OPERATING LIMITS REPORT - CYCLE 14 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 14 (NFS-0253, Rev. 0) in Attachment 1 of this letter.

Should you have any questions, please contact James Barstow at (856) 339-1384.

Sincerely, Michael Jesse Regulatory Assurce Manager Hope Creek Attachment 400 95-2168 REV. 7/99

LR-N06-0214 2 Document Control Desk C Mr. S. Collins, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. S. Bailey, Project Manager- Hope Creek U. S. Nuclear Regulatory Commission Mail Stop 08BI Washington, DC 20555 USNRC Senior Resident Inspector - Hope Creek (X24)

Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering P. 0. Box 415 Trenton, NJ 08625

Document Control Desk LR-N06-0214 Attachment I NFS-0253, Rev. 0

NFS-0253 Revision 0 Hope Creek Generating Station Unit 1 Core Operating Limits Report Cycle 14 / Reload 13 Effective Date: S /l /I6 Prepared By: 4 L.j, 9 Date: L-ulm Steven G. Bier, Nuclear Fuels Staff Engineer Reviewed By: :-,J- -F Date: _/__/_

Shie-Jeng g, i n Engineer Approved By: . Li. Date: _____6 Donald V. Notig , ger-Fuel Tedhnologytation Page 1 of 19

NFS-0253 Revision 0 Table of Contents Section Description Page

1.0 INTRODUCTION

4 2.0 TECHNICAL SPECIFICATIONS THAT REFERENCE THE COLR _ 5 2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE! 6 2.2 MINIMUM CRITICAL POWER RATIO 8 2.3 LINEAR HEAT GENERATION RATE 12 2.4 OPRM TRIP SETPOINT 16

3.0 REFERENCES

17 Appendix A: Method of Core Average Scram Speed Calculation __ 18 Page 2 of 19

NFS-0253 NPS-053 Revision 0 List of Tables Table Description Page Table 2.1-1: APLHGR Data for GE14 Fuel 7 Table 2.1-2: APLHGR Data for SVEA-96+ Fuel 7 Table 2.2-1: Cycle 14 MCPR Operating Limits: Cycle Exposure S 9755 MWD/MTU (S8850 MWDISTU)_ 10 Table 2.2-2: Cycle 14 MCPR Operating Limits: Cycle Exposure > 9755 MWD/MTU

(> 885OMWD/STU) 10 Table 2.2-3: Power Dependent MCPR Adjustments and Multiplier (Kp) Data _ 11 Table 2.2-4: Flow Dependent MCPR Limit (MCPR_) 11 Table 2.3-1: LHGR Limit for GE14 _ 14 Table 2.3-2: LHGR Limit for SVEA-96+ ___ 14 Table 2.3-3: Power Dependent Linear Heat Generation Rate Multiplier (LHGRFAC.) 15 Table 2.3-4: Flow Dependent Linear Heat Generation Rate Multiplier (LHGRFACf) - 15 Page 3 of 19

NFS-0253

- NFS-0253 Revision 0

1.0 INTRODUCTION

The purpose of this report is to provide the Core Operating Limits for Hope Creek Generation Station Unit i Cycle 14/ Reload 13 operation. This report provides the core thermal limits for Average Planar Linear Heat Generation Rate (APLHGR), Minimum Critical Power Ratio (MCPR), and Linear Heat Generation Rate (LHGR), as well as power and flow dependent adjustments to these limits that support off-rated operation and Single recirculation Loop Operation (SLO). Additionally, this report provides the Allowable Value for the Oscillation Power Range Monitor (OPRM) trip setpoint, and the method of average scram speed determination. Finally, this report provides a reference to the most recent revision of the implemented approved licensing methodology.

These operating limit LCO values have been determined using NRC approved methods contained in GESTAR-Il, NEDE-2401I-P-A (Revision 15) 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 69.1.9 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 1 Cycle 14/ Reload 13 and shall not be applicable to any other core or cycle design. The thermal limits contained in this report are applicable whether the Crossflowsm correction factor is applied or not applied.

This report is applicable for Cycle 14 operation from the date of issuance through the end of effective full power capability or a cycle exposure of 12070 MWMTU (10950 MWdISTU, whichever occurs first. 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 4 of 19

NFS-0253 Revision 0 2.0 TECHNICAL SPECIFICATIONS THAT REFERENCE THE COLR The TECHNICAL SPECIFICATIONS TIAT RIFERENCE THE COLR presented in this section are referenced by the Hope Creek Technical Specifications.

Tech. Spec itle 2.1 Bases 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 3/4.2.4 Bases Linear Heat Generation Rate 3/4.3.11 Bases Oscillation Power Range Monitor (OPRM) 314.4.1 Bases Recirculation System 6.9.1.9 Administrative Controls, Core Operating Limits Report Page 5 of 19

NFS-0253 NFS-0253 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 2.1-2 for Two recirculation Loop Operation (TLO).

When the Technical Specification Section 314.4.1 ACTION statement a.L.d is entered from that section's Limiting Condition for Operation, reduce the APLHGR limits to the values specified in Tables 2.1-1 and 2.1-2 for Single recirculation Loop Operation (SLO).

Linear interpolation shall be used to determine APLHGR limits as a function of exposure for intermediate values in Table 2.1-1 and Table 2.1-2.

Page 6 of 19

NFS-0253 Revision 0 Table 2.1-1: APLHGR Data for GE14 Fuel Average Planar Exposure kWfLHGR Limit hWD/M TU MW STU ' Two Loop OSBnre Loop Operation 0.00 0.00 12.82 10.26 21090 19130 - 12.82 - 10.26 63500 57610 8.00 6.40 70000 63500 5.00 4.00 Table 2.1-2: APLHGR Data for SVEA.96+ Fuel Average Planar Exposure APHGflft mD/MU MWD/STU Two Loop Operation Single Loop Operation 0.00 0.00 12.85 10.28 3680 3340 12.85 10.28 16000 14510 10.97 8.78 65000 58970 7.24 5.79 Page 7 of 19

NFS-0253 Revision 0 22 MINIMUM CRITICAL POWER RATIO LIMITING CONDITION FOR OPERATION The MINIMUM CRITICAL POWER RATIO (MCPR) shall be equal to or greater than the MCPR limit computed from the following steps:

1. Determine r as defined in Appendix A.

NOTE The SLO operating condition MCPR values in Tables 2.2-1, 2.2-2, 2.2-3 and 2.2-4 implement the increase in the MCPR Safety Limit to meet the requirements of Technical Specification Section 3/4.4.1 ACTION statement aL .c.

2. Linearly interpolate a MCPR value as a fimction of r from the MCPR value at t = 0 and the MCPR value at r = 1 as specified in Table 2.2-1 and Table 2.2-2 for the appropriate operating condition.

3. For the power dependent MCPR adjustment, when thermal power is 2 30% rated core thermal power, determine a K.p value by linearly interpolating a Kp value as a function of core rated thermal power from Table 2.2-3. Multiply the MCPR value obtained from Step 2 by the Kp value to determine the power dependent MCPR limit.

When core thermal power is > 25% rated and < 30% rated thermal power, determine the appropriate power dependent MCPR limit by linearly interpolating between the MCPR limits as a function of rated core thermal power for the appropriate core flow condition using the information in Table 2.2-3.

4. For the flow dependent MCPR adjustment, determine the appropriate flow dependent MCPR limit by linearly interpolating between the MCPR limits as a function of rated core flow using the information in Table 2.24.

5. Choose the most limiting (highest value) of the power and flow dependent MCPR limits determined in steps 2 and 3 as the value for the MCPR limit for the Limiting Condition For Operation.

Note that the MCPR limit is a function of core average scram speed (X), cycle exposure, core thermal power, total core flow, EOC-RPT operability, the number of reactor coolant recirculation loops in operation, and main turbine bypass operability.

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

Page 8 of 19

NPS-0253 Revision 0 2.2 MINIMUM CRITICAL POWER RATIO (Continued)

Reactor coolant recirculation loop operation 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 9 of 19

NFS-02.53 Revision 0 Table 2.2-1: Cycle 14 MCPR Operating Limits:

Cycle Exposure 5 9755 MWD/MTU (58850MWD/STU)

Main Turbine Byass Operable Operating Condition Scram Speed GE14 SVEA-96+

Option TLO-EOC-RPI Operable B 1.34 1.47 A 1A34 1.49 TLO-EOC-RPT Inoperable B 1.37 1.49 A 1.47 1.30 SLO-EOC-RPT Operable A 1.36 1.50 A 1.35 1.31 SLO-E0C-RPT Inoperable B 1.39 1.40 Scram Speed Option A = 1, Scram Speed Option B ' =0, TLO = Two recirculation

'r Loop Operation, SLO = Single recirculation Loop Operation Table 2.2-2: Cycle 14 MCPR Operating Limits:

Cycle Exposure > 9755 MWD/MTU ( 8850 MWD/STU)

Main Turbie yps Operable _____

Operating Condition Scram Speed GEI4 SVEA-96+

_Option TLO-EOC-RPT Operable A B ; 1 1.57 1.40 1.59 1.42 AB 1.40 1.42 TLO-EOC-RPT Inoperable A 1.61 1.62 B 1.44 1.45 SLO-EOC-RPT Operable A 1.59 1.61 13 1.42 1.44 SLO-EOC-RPT OperableBA 1.63 1.4 1.64 1.47 Scram Speed Option A T= 1,Scram Speed Option B X=0, TLO = Two recirculation Loop Operation, SLO = Single recirculation Loop Operation Page 10 of 19

NFS-0253 Revision 0 Table 2.2-3: Power Dependent MCPR Adjustments and Multiplier (Kp) Data Core Thermal Power (% of rated)

Operating Core Flow Condition (% of rated) 225 < 30 30 45 60 l 2100 MCPR Limit MCPR Multiplier, Kp TL 60 2.25 2.12 1.481 1.280 1.150 1.000

> 60 2.93 2.70

<560 2.27 2.14 SLO 1.481 1.280 1.150 1.000

> 60 2.95 2.72 TLO = Two recirculation Loop Operation, SLO = Single recirculation Loop Operation Table 2.24: Flow Dependent MCPR Limit (MCPRt)

Core Flow (% of rated)

Operating Condition 30 1 60 1 77 J105 MCPR Limit TLO 1.53 XA 1.25 1 1.25 SID 1.55 I.s~

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NFS-0253 Revision 0 23 LINEAR HEAT GENERATION RATE LMITNG CONDITION FOR OPERATION The LINEAR HEAT GENERATION RATE (LHGR) shall not exceed the limit computed from the following steps:

1. Determine the exposure dependent LHOR limit for the appropriate fuel design using linear interpolation between the values in Table 2.3-1 and Table 23-2.

NOTE For Two recirculation Loop Operation utilize steps 1,2, 3 and 6 to determine the LCO LHGR limits for Two recirculation Loop Operation (TLO).

When the Technical Specification Section 3/4A. 1ACTION statement a. Le is entered from that section's Limiting Condition for Operation (LCO), utilize steps 1,4, 5 and 6 to determine the LCO LHGR limits for Single recirculation Loop Operation (SLO).

2. For the power dependent LHGR adjustment for TLO, determine a LHGRFACp value by linearly interpolating a LHGRFACp value as a function of rated core thermal power for the core flow condition being evaluated from the TMO entries in Table 2.3-

3. Multiply the LHGR values obtained from Step 1by the LHGRFACp value to determine the power dependent LHGR limits for each fuel design.

3. For the flow dependent LHGR adjustment for TLO, determine a LHGRFACf value by linearly interpolating a LHGRFACr value as a function of rated core flow from the TLO entries in Table 2.3-4. Multiply the LHQR values obtained from Step 1 by the LHGRFACQ value to determine the flow dependent LHGR limits for each fuel design.

4. For the power dependent LHGR adjustment for SLO, determine a LHGRFACp value by linearly interpolating a LHGRFACp value as a function of rated core thermal power for the core flow condition being evaluated from the SLO entries in Table 2.3-

3. Multiply the LHGR values obtained from Step 1 by the LHGRFACp value to determine the power dependent LHGR limits for each fuel design.

5. For the flow dependent LHGR adjustment for SLO, determine a LHGRFACr value by linearly interpolating a LHGRFACf value as a function of rated core flow from the SLO entries in Table 2.3-4. Multiply the LHGR values obtained from Step 1 by the LHGRFACf value to determine the flow dependent LHGR limits for each fuel design.

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NFS-0253 Revision 0 2.3 LINEAR HEAT GENERATION RATE (Continued)

6. Choose the most limiting (lowest value) of the power and flow dependent LHGR limits determined in steps 2 and 3 (TL) or 4 and 5 (SLO) as the value for the LHGR limit for the Limiting Condition For Operation. -

Page 13 of 19

NFS-0253 Revision 0 Table 2.31: LHGR Limit for GE14 Peak Pellet Exposure LHGR Limit MWD/M MWD/STU' kWMM 0.0 0.0 13.40 16000 14510 13.40 63500 57610 8.00 70000 63500 5.00 Table 2.3-2: LHGR Limit for SVEA-96+

Peak Pellet Exposure LHGRLimit NMWDJIU - ' MWD/STU MM/f 0.0 __0.0 13.41

_16000 14510 110.97 6500058970 7.24 Page 14 of 19

NFS-0253 Revision 0 Table 2.33: Power Dependent Linear Heat Generation Rate Multiplier (LHGRFACp)

U U Core Thermal Power (% of rated)

Operating Core Flow Condition (% of rated) 225 1 <30 1 230 1 61.7 1 70 1 2100 LHGRFACq Multiplier TLO S 60 0.577 0.590 0.634 1.000

> 60 0.476 10.502

• 60 0.577 0.590 SLO 4. 4. 0.634 0.800 0.800

>60 0.476 0.502 I - A Table 2.34: Flow Dependent Linear Heat Generation Rate Multiplier (LHGRFACO Core Flow (% of rated)

Operating Condition 30 1 50 I 52.7 1 60 1 82.2 1 105

_j0 0.500 0.782 SLO 1 0.500 1 0.782 1 0.800 0.800 Page 15 of 19

NFS-0253 Revision 0 2A OPRM TRIP SETPOINT LIMING CONDITION FOR OPERATION Four channels of the OPRM instumentation shall be OPERABLE. Each OPRM channel period based algorithm amplitude trip setpoint (Sp) shall be less tan or equal to the Allowable Value of 1.08.

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NFS-0253 Revision 0

3.0 REFERENCES

1. Nuclear Fuel Section Design Input File HCG,540002,:General Electric Standard Application forReactor Fuel," General Electric Company, NEDE-2401 1-P-A-15, and the U.S. Supplement NEDE-2401 1-P-A-15-US.

2. Nuclear Fuel Section Design Input File, HCG.5-0041, "Supplemental Reload Licensing Report for Hope Creek Unit I Reload 13 Cycle 14" GE Nuclear Energy 0000-0041-6021-SRLR, Rev. 1,March 2006.

3. Nuclear Fuel Section Design Input File HCG.5-0041, "Fued Bundle Information Report for Hope Creek Unit 1 Reload 13 Cycle 14," 0000-0041-6021-FBIR, Rev. 0 February 2006.

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NFS-0253 Revision 0 Appendix A: Method of Core Average Scram Speed Calculation Page 18 of 19 i

NFS-0253 Revision 0 Method of Core Average Scram Speed, X, Calculation r is defined as

'r ( ovTa)

TFA - T, where:

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

= 0.672 +1.65l IJ (0.016)

ENN n = number of surveillance tests performed to date in cycle, N, = number of active control rods measured in the ih surveillance test, x, = average scram time to notch 39 of all rods measured in the ih surveillance test, and N. = total number of active rods measured in Specification 4.1.3.2.a.

if fre,,, S r, set r = 0 to apply Option B OLMCPR.

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

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