LR-N19-0015, Core Operating Limits Report, Reload 21, Cycle 22, Revision 15

Core Operating Limits Report, Reload 21, Cycle 22, Revision 15

ML19065A086
Person / Time
Site:	Hope Creek
Issue date:	03/06/2019
From:	Fleming J Public Service Enterprise Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML19065A085	List: LR-N19-0015, Core Operating Limits Report, Reload 21, Cycle 22, Revision 15
References
LR-N19-0015, TS 6.9.1.9
Download: ML19065A086 (33)

Text

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 PROPRIETARY INFORMATION-WITHHOLD UNDER 10 CFR 2.390 r*1AR 0 6 2019 LR-N19-0015 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Hope Creek Generating Station Renewed Facility Operating License No. NPF-57 NRC Docket No. 50-354 0PSEG Nuclear LLC TS 6.9.1.9

Subject:

Core Operating Limits Report, Reload 21, Cycle 22, Revision 15 In accordance with the Hope Creek Technical Specifications, Section 6.9.1.9., PSEG Nuclear LLC submits the Core Operating Limits Report (COLR) for Hope Creek Generating Station (HCGS) Reload 21, Cycle 22, Revision 15. In accordance with Hope Creek procedures, revision to the Cycle 22 COLR was completed to update the OLMCPR breakpoint exposure to reflect the current Rated (EOR) exposure projection for Hope Creek Cycle 22 Attachment 1 contains information proprietary to Global Nuclear Fuel -Americas, LLC (GNF-A), specifically, Appendix B of the Core Operating Limit Report for HCGS Unit 1. GNF-A requests this appendix titled, "Exposure-Dependent Linear Heat Generation Limits," be withheld from public disclosure in accordance with 10 CFR 2.390(a)(4) and 10 CFR 9.17(a)(4).

Attachment 1, which contains the complete Core Operating Limits Report, is marked proprietary in its entirety, and a non-proprietary version of the report is provided in Attachment

2. An affidavit supporting the GNF-A request is provided in Attachment

3. There are no commitments contained in this letter. Should you have any questions, please contact Ms. Kirsten Stokes at (856) 339-2834.

ftf\.l .--1 wtt.IK J' \ '1-* l-t((}.A, Jean Fleming Director-Site Regulatory Affairs Attachment 1 -Core Operating Limits Report, Reload 21, Cycle 22, Revision 15-Proprietary Attachment 2-Core Operating Limits Report, Reload 21, Cycle 22, Revision 15-Non-Proprietary -Affidavit for Core Operating Limits Report for Hope Creek Generating Station Unit 1 Attachment 1 transmitted herewith contains Proprietary Information.

When separated from Attachment 1, this transmittal document is decontrolled.

t*1AR 0 6 2019 PROPRIETARY INFORMATION-WITHHOLD UNDER 10 CFR 2.390 Document Control Desk LR-N19-0015 Page2 cc: Mr. David Lew, Regional Administrator-NRC Region 1 Mr. Jim Kim, Project Manager -USNRC Mr. Justin Hawkins, USNRC Senior Resident Inspector-Hope Creek Mr. Patrick Mulligan, Manager IV, NJBNE Mr. Lee Marabella, Corporate Commitment Tracking Coordinator Ms. Kirsten Stokes, Hope Creek Commitment Tracking Coordinator Document Control Desk LR-N19-0015 Attachment 2 Core Operating Limits Report, Reload 21, Cycle 22, Revision 15 (Non-Proprietary Version)

COLR HOPE CREEK 1 Rev 15 (Cycle 22) CORE OPERATING LIMITS REPORT FOR Hope Creek Generating Station Unit 1 RELOAD 21, CYCLE 22 Prepared By: Date: O:J/:lo /}cy Eric S. Scott Reviewed By: . Kenneth W. Buckwheat ApprovedBy:

Francis J. fin Date: ;)..

Page 1 of 26 1.0 2.0 3.0 4.0 5.0 5.1 5.2 5.3 5.4 5.5 Appendix A Appendix B Appendix C COLR HOPE CREEK 1 Rev 15 (Cycle 22) Table of Contents Terms and Definitions References General Information Precautions and Limitations Technical Specifications that Reference the COLR Average Planar Linear Heat Generation Rate Minimum Critical Power Ratio Linear Heat Generation Rate OPRM Setpoints Rod Block Monitor Method of Core Average Scram Speed Calculation Exposure-Dependent Linear Heat Generation Rate Limits Backup Stability Protection Page 2 of26 4 5 6 7 8 9 10 13 15 15 16 18 24 TABLE 5.1-1 TABLE 5.1-2 TABLE 5.2-1 TABLE 5.2-2 TABLE 5.2-3 TABLE 5.2-4 TABLE 5.3-1 TABLE 5.3-2 TABLE 5.5.2-1 TABLE B-1 TABLE B-2 TABLE B-3 TABLE B-4 TABLE B-5 TABLE B-6 TABLE B-7 TABLE B-8 TABLE C-1 TABLE C-2 TABLE C-3 COLR HOPE CREEK 1 Rev 15 (Cycle 22) List of Tables APLHGR Data for GE14 APLHGR Data for GNF2 MCPR Operating Limits Cycle Exposure :s; 7,870 MWd/MTU (:s; 7, 140 MWd/STU) MCPR Operating Limits Cycle Exposure>

7,870 MWd/MTU (> 7,140 MWd/S"fU)

Power Dependent MCPR Multiplier (Kp) Data Flow Dependent MCPR Limit (MCPRt) Power Dependent Linear Heat Generation Rate Multiplier (LHGRFACp)

Flow Dependent Linear Heat Generation Rate Multiplier (LHGRFACt)

Control Rod Block Instrumentation Setpoints, Trip Function 1, Rod Block Monitor GE14 LHGR Limits-U0 2 Fuel Rods GE14 LHGR Limits-Gadolinia Bearing Rods GE14 LHGR Limits-U0 2 Fuel Rods GE14 LHGR Limits-Gadolinia Bearing Rods GNF2 LHGR Limits -U02 Fuel Rods GNF2 LHGR Limits-Gadolinia Bearing Rods GNF2 LHGR Limits -U02 Fuel Rods GNF2 LHGR Limits "'"" Gadolinia Bearing Rods BSP Region Intercepts (Operation Prior to FFWTR) BSP Region Intercepts (Required for FFWTR) ABSP Region Setpoints Page 3 of26 9 9 11 11 12 12 14 14 15 20 20 21 21 22 22 23 23 25 25 26 COLR HOPE CREEK 1 Rev 15 (Cycle 22) 1.0 Terms and Definitions ABSP Automated Backup Stability Protection APLHGR ARTS BSP COLR DSS-CD ECCS EOC EOC-RPT FFWTR FWHOOS GNF LCO LHGR LHGRFACt LHGRFACp MCPR MCPRp MCPRf OPRM RBM RDF RTP SAo SLO TLO Average Planar Linear Heat Generation Rate APRM and RBM Technical Specification Analysis Backup Stability Protection Core Operating Limits Report Detect and Suppress Solution -Confirmation Density Emergency Core Cooling Systems End-of-Cycle End-of-Cycle Recirculation Pump Trip Final Feedwater Temperature Reduction Feedwater Heaters Out of Service Global Nuclear Fuel Limiting Condition for Operation Linear Heat Generation Rate ARTS LHGR thermal limit flow dependent adjustments and multipliers ARTS LHGR thermal limit power dependent adjustments and multipliers Minimum Critical Power Ratio ARTS MCPR thermal limit power dependent adjustments and multipliers ARTS MCPR thermal limit flow dependent adjustments and multipliers Oscillation Power Range Monitor Rod Block Monitor Recirculation Drive Flow Rated Thermal Power Amplitude Discriminator Setpoint Single Recirculation Loop Operation Two Recirculation Loop Operation Page 4 of26 COLR HOPE CREEK 1 Rev 15 (Cycle 22) 2.0 References Methodology References

1. "General Electric Standard Application for Reactor Fuel," NEDE-24011-P-A-26, and the Supplement NEDE-24011-P-A-26-US, January 2018. User References

2. "GE Hitachi Boiling Water Reactor Detect and Suppress Solution -Confirmation Density," NEDC-33075P-A, Revision 8, November 2013. 3. Renewed Facility Operating License No. NPF-57, PSEG Nuclear LLC; Hope Creek Generating Station, Docket No. 50-354. 4. "Applicability of GE Methods to Expanded Operating Domains," NEDC-33173P-A, Revision 4, November 2012. 5. "GE14 Compliance with Amendment 22 of NEDE-24011-P-A (GESTAR II)," NEDC-32868P, Revision 6, March 2016. 6. "Supplemental Reload Licensing Report for Hope Creek Reload 21 Cycle 22," Global Nuclear Fuel Document No. 004N2028, Revision 0, February 2018. 7. "Fuel Bundle Information Report for Hope Creek Reload 21 Cycle 22," Global Nuclear Fuel Document No. 004N2029, Revision 0, February 2018. 8. "Option B Licensing Basis & Cycle-Independent Transient Evaluation for Implementation ofthe Technical Specification Improvement Program (TSIP) Scram Speed," Global Nuclear Fuel Document No. 0000-0119-7785, Revision 0, October 2010. 9. "SRLR Bases Confirmation with Control Rods Inserted at End of Cycle for Hope Creek (KT1)," Global Nuclear Fuel Document No. 002N4856 Rev. 0, February 18, 2015. 10. "GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II)," NEDC-33270P, Revision 9, December 2017. 11. "PSEG Nuclear, LLC Cycle Management Report Hope Creek Cycle 22," PSEG Doc. No. HCC22CMR, Revision 1, December 5, 2018. Page 5 of 26 COLR HOPE CREEK 1 Rev 15 (Cycle 22) 3.0 General Information This revision of the Core Operating Limits Report provides the core operating limits for Hope Creek Generating Station Unit 1 Cycle 22 operation.

This report provides information relative to OPRM setpoints, backup stability protection regions, RBM setpoints, single recirculation loop operation, and core average scram speed. The power distribution limits presented here correspond to the core thermal limits for Average Planar Linear Heat Generation Rate (APLHGR), Minimum Critical Power Ratio (MCPR), and Linear Heat Generation Rate (LHGR). Finally, this report provides references to the most recent revision of the implemented approved methodology.

These operating limit values have been determined using NRC approved methods contained in GESTAR-11 (Reference 1). These operating limit values also include limitations where required by the NRC Safety Evaluation Report for Hope Creek License Amendment Number 174, Extended Power Uprate (Reference

3) for the use of GE Licensing Topical Report NEDC-33173P, Applicability of GE Methods to Expanded Operating Domains (Reference 4). The following sections contain operating limit values for both the GE14 fuel design and the GNF2 fuel design. The operating limit values apply to both GE14 and GNF2, unless specific values are provided for a fuel design. The method of calculating core average scram speed, 't, is provided in Option B Licensing Basis & Cycle-Independent Transient Evaluation for Implementation of the Technical Specification Improvement Program (TSIP) Scram Speed (Reference 8). These operating limits 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. Various sections of the Hope Creek Technical Specifications reference this COLR. Those sections are listed in Section 5 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. Page 6 of 26 COLR HOPE CREEK 1 Rev 15 (Cycle 22) 4.0 Precautions and Limitations This document is specific to Hope Creek Generating Station Unit 1 Cycle 22 and shall not be applicable to any other core or cycle design. Revision 15 of the COLR is applicable for Cycle 22 operating from the date of issuance through the end of cycle including consideration of reduced feedwater temperatures for FWHOOS or FFWTR, and a power coastdown to a core thermal power that shall not go below 40% rated core thermal power. End of 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 allowable feedwater temperatures, in the all-rods-out configuration.

The term out" excludes control rods that have been inserted to suppress fuelleakers, address cell friction performance, or other circumstances that would require control rod insertion to meet Technical SpeCification Operability requirements (Reference 9). Operation beyond the end of full power capability is defined as power coastdown operation which includes an operating assumption that vessel dome pressure will decrease during the power coastdown period as steam flow decreases (maintaining constant vessel dome pressure during the power coastdown period was not generically considered by GESTAR-11 for determining the operating limit LCO values described above). FWHOOS was evaluated for a final feedwater temperature reduction of up to 60°F from the design rated thermal power final feedwater temperature of 433.5aF (433.5°F -60°F = 373.5°F).

Therefore, Cycle 22 FWHOOS operation is limited to feedwater system configurations that result in a final feedwater temperature greater than or equal to 373.5°F at rated thermal power. FWHOOS operation and the associated limitations may be implemented any time during the operating cycle prior to cycle extension utilizing FFWTR. FFWTR was evaluated for a final feedwater temperature reduction of up to 86°F from the design rated thermal power final feedwater temperature of 433.5°F (433.5°F -86°F = 347.5°F).

Therefore, Cycle 22 FFWTR operation is limited to feedwater system configurations that result in a final feedwater temperature greater than or equal to 347.5°F at rated thermal power which is compliant with Renewed Facility Operating License No. NPF-57 License Condition 2.C.(11):

The facility shall not be operated with a rated thermal power feedwater temperature less than 331.5°F for the purpose of extending the normal fuel cycle. FFWTR operation and the associated limitations shall only be implemented for the purposes of cycle extension after rated thermal power cannot be maintained at 100% rated total core flow in the all-rods-out configuration.

Page 7 of 26 COLR HOPE CREEK 1 Rev 15 (Cycle 22) 5.0 Technical Specifications that Reference the COLR The following Hope Creek Technical Specifications reference this COLR: Technical Specification Title 2.1 2.2 3/4.1.4.3 3/4.2.1 3/4.2.3 3/4.2.4 3/4.3.1 3/4.3.6 3/4.4.1 6.9.1.9 Safety Limits Reactor Protection System Instrumentation Setpoints Rod Block Monitor Average Planar Linear Heat Generation Rate Minimum Critical Power Ratio Linear Heat Generation Rate Reactor Protection System Instrumentation Control Rod Block Instrumentation Recirculation System Recirculation Loops Administrative Controls, Core Operating Limits Report Page 8 of 26 COLR HOPE CREEK 1 Rev 15 (Cycle 22) 5.1 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 5.1-1 (GE14) and Table 5.1-2 (GNF2) for two recirculation loop operation (TLO). When the Technical Specification 3.4.1.1 Action Statement a.1.d is entered from that section's Limiting Condition for Operation, reduce the APLHGR limits to the values specified in Table 5.1-1 and Table 5.1-2 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 5.1-1 and Table 5.1-2. TABLE 5.1-1 APLHGR Data for GE14 Average Planar Exposure APLHGR Limit (kW/ft) MWd/MTU MWd/STU TLO SLO 0.00 0.00 12.82 10.26 16000 14510 12.82 10.26 21090 19130 12.82 10.26 63500 57610 8.00 6.40 70000 63500 5.00 4.00 TABLE 5.1-2 APLHGR Data for GNF2 Average Planar Exposure APLHGR Limit (kW/ft) MWd/MTU MWd/STU TLO SLO 0.00 0.00 13.78 11.02 18910 17150 13.78 11.02 67000 60780 6.87 5.50 70000 63500 5.50 4.40 Page 9 of26 COLR HOPE CREEK 1 Rev 15 (Cycle 22) 5.2 Minimum Critical Power Ratio LIMITING CONDITION FOR OPERATION The MINIMUM CRITICAL POWER RATIO (MCPR) shall be equal to or greater than the MCPR limit computed from the following steps: 1. Determine 1: as defined in Appendix A. NOTE The SLO operating condition MCPR values in Tables 5.2-1, 5.2-2, and 5.2-4 implement the increase in the MCPR Safety Limit to meet the requirements of Technical Specification 3.4.1.1 Action Statement a.1.c. 2. Linearly interpolate a MCPR value as a function of 1: from the MCPR value at 1:=0 and MCPR value at 1:=1 as specified in Table 5.2-1 and Table 5.2-2 for the appropriate condition.

Repeat for each fuel type. 3. For the power dependent MCPR adjustment, when thermal power is;:: 24% rated core thermal power, determine a Kp value by linearly interpolating a Kp value as a function of core rated thermal power from Table 5.2-3. Multiply the MCPR value obtained from Step 2 by the Kp value to determine the power dependent MCPR limit for each fuel type. When core thermal power is< 24% rated thermal power, no thermal limits are required.

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 5.2-4. 5. Choose the most limiting (highest value) of the power and flow dependent MCPR limits determined in Steps 3 and 4 as the value for the MCPR limit for the Limiting Condition for Operation for each fuel type. Note that the MCPR limit is a function of core average scram speed (1:), 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. 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 10 of 26 COLR HOPE CREEK 1 Rev 15 (Cycle 22) TABLE 5.2-1 MCPR Operating Limits Cycle Exposure S 7,870 MWd/MTU (S 7,140 MWd/STU) Main Turbine Bypass Operable Scram Operating Condition Speed GE14 Option TLO-EOC-RPT Operable A 1.48 8 1.38 TL()-EOC-RPT Inoperable A 1.50 8 1.39 SLO-EOC-RPT Operable A 1.51 8 1.41 SLO-EOC-RPT Inoperable A 1.53 8 1.42 Scram Speed Option A T=1 I Scram Speed Option B T=O TLO = Two Recirculation Loop Operation SLO = Single Recirculation Loop Operation GNF2 1.50 1.40 1.51 1.41 1.53 1.43 1.54 1.44 TABLE 5.2-2 MCPR Operating Limits Cycle Exposure>

7,870 MWd/MTU (> 7,140 MWd/STU) Main Turbine Bypass Operable Scram Operating Condition S()eed GE14 Option TLO-EOC-RPT Operable A 1.59 8 1.42 A 1.61 TLO-EOC-RPT Inoperable 8 1.44 SLO-EOC-RPT Operable A 1.62 8 1.45 SLO-EOC-RPT Inoperable A 1.64 8 1.47 Scram Speed Option A T=1 I Scram Speed Option B T=O TLO = Two Recirculation Loop Operation SLO = Single Recirculation Loop Operation Page 11 of26 GNF2 1.55 1.45 1.57 1.47 1.58 1.48 1.60 1.50 COLR HOPE CREEK 1 Rev 15 (Cycle 22) TABLE 5.2-3 Power Dependent MCPR Multiplier (Kp) Data Core Thermal Power (% of Rated) Operating Condition 24 45 60 MCPR Multiplier Kp TLO 1.561 1.280 1.150 SLO 1.561 1.280 1.150 Kp is linearly interpolated between core thermal power entries. The Kp multiplier is the same for both GE14 and GNF2. TLO =Two Recirculation Loop Operation SLO = Single Recirculation Loop Operation TABLE 5.2-4 Flow Dependent MCPR Limit (MCPRt) Core Flow (% of Rated) Operating Condition 30 60 91.1 MCPR limit TLO 1.56 SLO 1.59 MCPRt is linearly interpolated between core flow entries. The MCPRt value is the same for both GE14 and GNF2. TLO = Two Recirculation Loop Operation SLO = Single Recirculation Loop Operation Page 12 of 26 ;:::100 1.000 1.000 105 COLR HOPE CREEK 1 Rev 15 (Cycle 22) 5.3 Linear Heat Generation Rate LIMITING CONDITION FOR OPERATION The LINEAR HEAT GENERATION RATE (LHGR) shall not exceed the limit computed from the following steps: NOTE The steps performed in 1 through 6 below should be repeated for both U02 and gadolinia bearing fuel rods in each bundle type. 1. Determine the exposure dependent LHGR limit using linear interpolation between the table values in Appendix B. NOTE For two recirculation loop operation (TLO) utilize steps 1, 2, 3, and 6 to determine the LCO LHGR limits. When the Technical Specification 3.4.1.1 ACTION statement a.1.e 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 from the TLO entries in Table 5.3-1. Multiply the LHGR values obtained from Step 1 by the LHGRFACp value to determine the power dependent LHGR limit. 3. For the flow dependent LHGR adjustment for TLO, determine a LHGRFACt value by linearly interpolating a LHGRFACt value as a function of rated core flow from the TLO entries in Table 5.3-2. Multiply the LHGR values obtained from Step 1 by the LHGRFACt value to determine the flow dependent LHGR limit. 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 from the SLO entries in Table 5.3-1. Multiply the LHGR values obtained from Step 1 by the LHGRFACp value to determine the power dependent LHGR limit. 5. For the flow dependent LHGR adjustment for SLO, determine a LHGRFACt value by linearly interpolating a LHGRF ACt value as a function of rated core flow from Page 13 of 26 COLR HOPE CREEK 1 Rev 15 (Cycle 22) the SLO entries in Table 5.3-2. Multiply the LHGR values obtained from Step 1 by the LHGRFACt value to determine the flow dependent LHGR limit. 6. Choose the most limiting (lowest value) of the power and flow dependent LHGR limits determined in Steps 2 and 3 (TLO) or 4 and 5 (SLO) as the value for the LHGR limit for the Limiting Condition for Operation.

TABLE 5.3-1 Power Dependent Linear Heat Generation Rate Multiplier (LHGRFACp)

Core Thermal Power (% of Rated) Operating Condition 24 59.89 ;;::: 100 LHGRFACp Multiplier TLO 0.603 SLO 0.603 LHGRFACp is linearly interpolated between core thermal power entries. The LHGRFACp multiplier is the same for both GE14 and GNF2. TLO = Two Recirculation Loop Operation SLO = Single Recirculation Loop Operation TABLE 5.3-2 Flow Dependent Linear Heat Generation Rate Multiplier (LHGRFACt)

Core Flow (% of Rated) Operating Condition 30 50 52.7 60 LHGRFACt Multiplier TLO 0.500 0.782 SLO 0.500 0.782 LHGRFACt is linearly interpolated between core flow entries. The LHGRFACt multiplier is the same for both GE14 and GNF2. TLO = Two Recirculation Loop Operation SLO = Single Recirculation Loop Operation Page 14 of 26 82.2 105 COLR HOPE CREEK 1 Rev 15 (Cycle 22) 5.4 OPRM Setpoints

5.4.1 Technical

Specifications Table 2.2.1-1, Function 2.f, OPRM Upscale A DSS-CD evaluation was completed for Hope Creek Cycle 22 in accordance with the licensing methodology described in Reference

2. The DSS-CD evaluation confirms that the DSS-CD solution is applicable to Hope Creek Cycle 22 and confirms SAo = 1.10 for Hope Creek Cycle 22 operation.

The SAo = 1.10 is applicable under all operating conditions within the OPRM Armed Region. 5.5 Rod Block Monitor 5.5.1 Reactivity Control Systems, Rod Block Monitor Limiting Condition For Operation Technical Specifications 3.1.4.3 Both rod block monitor (RBM) channels shall be OPERABLE.

APPLICABILITY:

OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to 30% of RATED THERMAL POWER and less than 90% of RATED THERMAL POWER with MCPR less than 1. 73, or THERMAL POWER greater than or equal to 90% of RATED THERMAL POWER with MCPR less than 1.43. 5.5.2 Technical Specifications Table 3.3.6-2, Control Rod Block Instrumentation Setpoints, Trip Function 1, Rod Block Monitor TABLE 5.5.2-1 Control Rod Block Instrumentation Setpoints, Trip Function 1, Rod Block Monitor Function Trip Setpoint Allowable Value a.i) Low Trip Setpoint (L TSP) 123.0 123.4 a.ii) Intermediate Trip Setpoint (ITSP) 118.2 118.6 a.iii) High Trip Setpoint (HTSP) 113.2 113.6 c. Downscale 5 N/A * % RBM Reference Level Page 15 of 26 COLR HOPE CREEK 1 Rev 15 (Cycle 22) Appendix A: Method of Core Average Scram Speed Calculation Page 16 of 26 COLR HOPE CREEK 1 Rev 15 (Cycle 22) Method of Core Average Scram Speed, T, Calculation

't is defined as where: 1/2 'f 8 =0.672+1.65 nNI (0.016) _LN; i=l n ,LN;r; r = ...:.:;i="'--1

__ ave n _LN; i=l rA= 0.86 seconds, control rod scram insertion time limit to notch 39 per Specification 3.1.3.3, n = number of surveillance tests performed to date in cycle, Ni = number of active control rods measured in the ith surveillance test, ri = average scram time to notch 39 of all rods measured in the ith surveillance test, and N 1 = total number of active rods measured in Specification 4.1.3.3.a or 4.1.3.3.d.

If rave set 't = 0 to apply Option B OLMCPR. 't shall be 1.0 (-r = 1.0) prior to performance of the initial scram time measurements for the cycle in accordance with Specification 4.1.3.3. Page 17 of 26 COLR HOPE CREEK 1 Rev 15 (Cycle 22) Appendix B: Exposure-Dependent Linear Heat Generation Rate Limits Page 18 of26 COLR HOPE CREEK 1 Rev 15 (Cycle 22) Exposure-Dependent Linear Heat Generation Rate Limits The LHGR limits for all fuel and rod types are considered proprietary information of the vendor. Tables 8-1 through 8-8 contain exposure-dependent LHGR limits. The tables are presented in pairs since the LHGR limits are presented at separate peak pellet exposures for U0 2 and gadolinia bearing fuel rods. Several of the bundle types have the same exposure-dependent LHGR limits, and the applicable bundle types are noted before each set of tables. The gadolinia fuel rod limits provided for each bundle type reflect the bounding gadolinia LHGR limit for all gadolinium concentrations occurring in that bundle type. Page 19 of 26 COLR HOPE CREEK 1 Rev 15 (Cycle 22) Tables B-1 and B-2 contain limits applicable to the GE14 bundle types that follow.

• G E 14-P 1 OC NAB40 1-9G6. 0/6G4. 0-1 OOT -150-T6-4343

• GE14-P10CNAB401-9G6.0/6G4.0-100T-150-T6-4238

• GE 14-P 1 OCNAB401-14G6.

0-1 OOT -150-T6-4059 TABLE B-1: GE14 LHGR Limits-U0 2 Fuel Rods Peak Pellet Exposure U02 LHGR Limit MWd/MTU MWd/STU kW/ft [[ ]] TABLE B-2: GE14 LHGR Limits-Gadolinia Bearing Rods Most Limiting Peak Pellet Exposure Gadolinia LHGR Limit MWd/MTU MWd/STU kW/ft [[ ]] Page 20 of 26 COLR HOPE CREEK 1 Rev 15 (Cycle 22) Tables B-3 and B-4 contain limits applicable to the GE14 bundle types that follow.

• GE14-P10CNAB401-17G4.0-100T-150-T6-4342

• GE14-P10CNAB401-17GZ-100T-150-T6-4237 TABLE B-3: GE14 LHGR Limits-U02 Fuel Rods Peak Pellet Exposure U02 LHGR Limit MWd/MTU MWd/STU kW/ft ***-*** [[ ]] TABLE B-4: GE14 LHGR Limits-Gadolinia Bearing Rods Most Limiting Peak Pellet Exposure Gadolinia LHGR Limit MWd/MTU MWd/STU kW/ft [[ ]] Page 21 of 26 COLR HOPE CREEK 1 Rev 15 (Cycle 22) Tables B-5 and B-6 contain limits applicable to the GNF2 bundle types that follow.

• GNF2-P10CG28392-13G4.0-100T2-150-T6-4533

• GNF2-P10CG28392-14G4.0-100T2-150-T6-4534 TABLE B-5: GNF2 LHGR Limits-U0 2 Fuel Rods Peak Pellet Exposure U02 LHGR Limit MWd/MTU MWd/STU kW/ft [[ ]] TABLE B-6: GNF2 LHGR Limits-Gadolinia Bearing Rods Most Limiting Peak Pellet Exposure Gadolinia LHGR Limit MWd/MTU MWd/STU kW/ft [[ ]] Page 22 of26 COLR HOPE CREEK 1 Rev 15 (Cycle 22) Tables B-7 and B-8 contain limits applicable to the GNF2 bundle types that follow.

• GNF2-P10CG28382-15GZ-100T2-150-T6-4438

• GNF2-P1 OCG28382-6G5.0/7G4.0-1 OOT2-150-T6-4439

• GNF2-P10CG28377-15GZ-100T2-150-T6-4440

• GNF2-P10CG28375-6G5.0/7G4.0-100T2-150-T6-4441

• GNF2-P1 OCG28392-1 OG5.0/5G4.0-1 OOT2-150-T6-4442

• GNF2-P10CG28372-12GZ-100T2-150-T6-4531

• GN F2-P 1 OCG28383-14GZ-1 OOT2-150-T6-4532 TABLE B-7: GNF2 LHGR Limits -U0 2 Fuel Rods Peak Pellet Exposure U02 LHGR Limit MWd/MTU MWd/STU kW/ft [[ ]] TABLE B-8: GNF2 LHGR Limits-Gadolinia Bearing Rods Most Limiting Peak Pellet Exposure Gadolinia LHGR Limit MWd/MTU MWd/STU kW/ft [[ ]] Page 23 of26 COLR HOPE CREEK 1 Rev 15 (Cycle 22) Appendix C: Backup Stability Protection Page 24 of26 COLR HOPE CREEK 1 Rev 15 (Cycle 22) Backup Stability Protection Region Intercepts Table C-1 values reflect the cycle-specific BSP region intercepts determined for Cycle 22 considering nominal feedwater temperature operation and FWHOOS (Reference 6). Table C-2 provides SSP region intercepts for Cycle 22 for the implementation of FFWTR operation (Reference 6). TABLE C-1: BSP Region Intercepts (Operation Prior to FFWTR) Region Boundary Intercept

%Power .. %Flow Region 1 High Flow Control Line 61.5 45.2 Region 1 Natural Circulation Line 44.0 35.0 Region 2 High Flow Control Line 67.6 52.8 Region 2 Natural Circulation Line 31.7 36.3 TABLE C-2: BSP Region Intercepts (Required for FFWTR) Region Boundary Intercept

%Power %Flow Region 1 High Flow Control Line 65.1 49.8 Region 1 Natural Circulation Line 42.2 35.4 Region 2 High Flow Control Line 71.4 57.7 Region 2 Natural Circulation Line 31.7 36.3 Region 1 = BSP Scram Region Region 2 = BSP Controlled Entry Region Page 25 of 26 COLR HOPE CREEK 1 Rev 15 (Cycle 22) Automated Backup Stability Protection (ABSP) Region Setpoints Table C-3 values reflect the cycle-specific modified Simulated Thermal Upscale scram setpoints for implementation of the ABSP region (Reference 6). The ABSP region is conservatively constructed to encompass BSP Region 1 and generates an immediate automatic reactor scram upon entry. The ABSP region provided is applicable for Nominal, FWHOOS, and FFWTR conditions.

TABLE C-3: ABSP Region Setpoints Parameter Setpoint Slope for -Trip (mTRIP) 0.79 (% RTP/% RDF) Constant Power Line for Trip (PssP-TRIP) 44.0 (% RTP) Constant Flow Line for Trip (WssP-TRIP) 37.8 (% RDF) Flow Breakpoint (WasP-BREAK) 15.3 (% RDF) Page 26 of 26 Document Control Desk LR-N19-0015 Attachment 3 Affidavit for Core Operating Limits Report for Hope Creek Generating Station Unit 1 Global Nuclear Fuel-Americas AFFIDAVIT I, Lukas Trosman, state as follows: (1) I am Engineering Manager, Reactor Physics Technology, Global Nuclear Fuel-Americas, LLC ("GNF-A"), and have been delegated the function of reviewing the information described in paragraph (2) which is sought to be withheld, and have been authorized to apply for its withholding.

(2) The information sought to be withheld is contained in Appendix B of the Core Operating Limits Report for Hope Creek Generating Station Unit 1, titled "Exposure-Dependent Linear Heat Generation Rate Limits." GNF-A proprietary information in Appendix B of the Core Operating Limits Report for Hope Creek Generating Station Unit 1 is identified by a dotted underline inside double square brackets. .

..

In all cases, the superscript notation {3/ refers to Paragraph (3) of this affidavit, which provides the basis for the proprietary determination.

(3) In making this application for withholding of proprietary information of which it is the owner or licensee, GNF-A relies upon the exemption from disclosure set forth in the Freedom of Information Act ("FOIA"), 5 USC Sec. 552(b)(4), and the Trade Secrets Act, 18 USC Sec. 1905, and NRC regulations 10 CFR 9.1 7(a)(4), and 2.390(a)(4) for "trade secrets" (Exemption 4). The material for which exemption from disclosure is here sought also qualify under the narrower definition of"trade secret", within the meanings assigned to those terms for purposes of FOIA Exemption 4 in, respectively, Critical Mass Energy Project v. Nuclear Regulatory Commission, 975F2d871 (DC Cir. 1992), and Public Citizen Health Research Group v. FDA, 704F2dl280 (DC Cir. 1983). ( 4) Some examples of categories of information which fit into the definition of proprietary information are: a. Information that discloses a process, method, or apparatus, including supporting data and analyses, where prevention of its use by GNF-A's competitors without license from GNF-A constitutes a competitive economic advantage over other companies;

b. Information which, if used by a competitor, would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product; c. Information which reveals aspects of past, present, or future GNF-A customer-funded development plans and programs, resulting in potential products to GNF-A; d. Information which discloses patentable subject matter for which it may be desirable to obtain patent protection.

Appendix B, Core Operating Limits Report, Hope Creek Generating Station Unit 1 Page 1 of3 The information sought to be withheld is considered to be proprietary for the reasons set forth in paragraphs (4)a. and (4)b. above. (5) To address 10 CFR 2.390 (b) (4), the information sought to be withheld is being submitted to NRC in confidence.

The information is of a sort customarily held in confidence by A, and is in fact so held. The information sought to be withheld has, to the best of my knowledge and belief, consistently been held in confidence by GNF-A, no public disclosure has been made, and it is not available in public sources. All disclosures to third parties including any required transmittals to NRC, have been made, or must be made, pursuant to regulatory provisions or proprietary agreements which provide for maintenance of the information in confidence.

Its initial designation as proprietary information, and the subsequent steps taken to prevent its unauthorized disclosUre, are as set forth in paragraphs (6) and (7) following.

(6) Initial approval of proprietary treatment of a document is made by the manager of the originating component, the person most likely to be acquainted with the value and sensitivity of the information in relation to industry knowledge, or subject to the terms under which it was licensed to GNF-A. (7) The procedure for approval of external release of such a document typically requires review by the staff manager, project manager, principal scientist or other equivalent authority, by the manager of the cognizant marketing function (or his delegate), and by the Legal Operation, for technical content, competitive effect, and determination of the accuracy of the proprietary designation.

Disclosures outside GNF-A are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensees, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or proprietary agreements.

(8) The information identified in paragraph (2) is classified as proprietary because it contains details of GNF-A's fuel design and licensing methodology.

The development of the methods used in these analyses, along with the testing, development and approval of the supporting methodology was achieved at a significant cost to GNF-A or its licensor.

(9) Pi1blic disclosure of the information sought to be withheld is likely to cause substantial harm to GNF-A's competitive position and foreclose or reduce the availability of making opportunities.

The information is part of GNF-A's comprehensive BWR safety and technology base, and its commercial value extends beyond the original development cost. The value of the technology base goes beyond the extensive physical database and analytical methodology and includes development of the expertise to determine and apply the appropriate evaluation process. In addition, the technology base includes the value derived from providing analyses done with NRC-approved methods. The research, development, engineering, analytical, and NRC review costs comprise a substantial investment of time and money by GNF-A. Appendix B, Core Operating Limits Report, Hope Creek Generating Station Unit 1 Page 2 of 3 The precise value of the expertise to devise an evaluation process and apply the correct analytical methodology is difficult to quantify, but it clearly is substantial.

GNP-A's competitive advantage will be lost if its competitors are able to use the results of the GNF-A experience to normalize or verify their own process or if they are able to claim an equivalent understanding by demonstrating that they can arrive at the same or similar conclusions.

The value ofthis information to GNF-A would be lost if the information were disclosed to the public. Making such information available to competitors without their having been required to undertake a similar expenditure of resources would unfairly provide competitors with a windfall, and deprive GNF-A of the opportunity to exercise its competitive advantage to seek an adequate return on its large investment in developing and obtaining these very valuable analytical tools. I declare tmder penalty of perjury that the foregoing is true and correct. Executed on this 28th day of October 2016. Engineering Manager, Reactor Physics Technology Global Nuclear Fuel-Americas, LLC 3901 Castle Hayne Road Wilmington, NC 28401 Lukas.Trosman@ge.com Appendix B, Core Operating Limits Report, Hope Creek Generating Station Unit 1 Page 3 of 3