LR-N19-0101, Submittal of Core Operating Limits Report, Reload 22, Cycle 23, Revision 17

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Submittal of Core Operating Limits Report, Reload 22, Cycle 23, Revision 17
ML19316C923
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 11/12/2019
From: Fleming J
Public Service Enterprise Group
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Document Control Desk, Office of Nuclear Reactor Regulation
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LR-N19-0101
Download: ML19316C923 (34)
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Attachment 1 Contains Proprietary Information to be Withheld from Public Disclosure Pursuant to 10 CFR 2.390 PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 0PSEG Nuclear LLC LR-N19-0101 TS 6.9.1.9 November 12, 2019 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

Subject:

Core Operating Limits Report, Reload 22, Cycle 23, Revision 17 PSEG Nuclear, LLC submits the Core Operating Limits Report (COLR) for Hope Creek Generating Station (HCGS) Reload 22, Cycle 23, Revision 17 as required by Hope Creek Technical Specification 6.9.1.9. is marked proprietary in its entirety because it contains information proprietary to Global Nuclear Fuel - Americas, LLC (GNF-A). GNF-A requests that Attachment 1 be withheld from public disclosure per 10 CFR 2.390(a)(4) and 10 CFR 9.17(a)(4). Attachment 2 is a non proprietary version of the COLR. Attachment 3 is the GNF-A affidavit requesting withholding of proprietary information from public disclosure.

There are no commitments contained in this letter.

Should you have any questions, please contact Mr. Harry Balian at (856) 339 - 2173.

Sincerely, (1. ;--I. ' -

ming Director - Site Regulatory Affairs - Core Operating Limits Report, Reload 22, Cycle 23, Revision 17 - Proprietary - Core Operating Limits Report, Reload 22, Cycle 23, Revision 17 - Non-Proprietary - Affidavit for Core Operating Limits Report for Hope Creek Generating Station Unit 1

TS 6.9.1.9 Page 2 LR-N19-0101 cc: Regional Administrator - NRC Region 1 US NRC NRR Project Manager - Hope Creek US NRC Senior Resident Inspector - Hope Creek NJ Department of Environmental Protection, Bureau of Nuclear Engineering Commitment Coordinator- Hope Creek Generating Station Corporate Commitment Coordinator - PSEG Nuclear, LLC

LR-N19-0101 Attachment 2 Core Operating Limits Report, Reload 22, Cycle 23, Revision 17 (Non-Proprietary Version)

COLR HOPE CREEK 1 Rev 17 (Cycle 23)

CORE OPERATING LIMITS REPORT FOR Hope Creek Generating Station Unit 1 RELOAD 22, CYCLE 23 Reviewed By: ~ ~~ Date: 11 /06'/I'}

Eric S. Scott Page 1 of 27

COLR HOPE CREEK 1 Rev 17 (Cycle 23)

Table of Contents 1.0 Terms and Definitions 4 2.0 References 5 3.0 General Information 6 4.0 Precautions and Limitations 7 5.0 Technical Specifications that Reference the COLR 8 5.1 Average Planar Linear Heat Generation Rate 9 5.2 Minimum Critical Power Ratio 10 5.3 Linear Heat Generation Rate 13 5.4 OPRM Setpoints 15 5.5 Rod Block Monitor 15 Appendix A Method of Core Average Scram Speed Calculation 16 Appendix B Exposure-Dependent Linear Heat Generation Rate Limits 18 Appendix C Backup Stability Protection 24 Appendix D MCPR99.9% Value 26 Page 2 of 27

COLR HOPE CREEK 1 Rev 17 (Cycle 23)

List of Tables TABLE 5.1-1 APLHGR Data for GE14 9 TABLE 5.1-2 APLHGR Data for GNF2 9 TABLE 5.2-1 MCPR Operating Limits Cycle Exposure s 8,556 MWd/MTU (S 7,762 MWd/STU) 11 TABLE 5.2-2 MCPR Operating Limits Cycle Exposure > 8,556 MWd/MTU

(> 7,762 MWd/STU) 11 TABLE 5.2-3 Power Dependent MCPR Multiplier (Kp) Data 12 TABLE 5.2-4 Flow Dependent MCPR Limit (MCPRt) 12 TABLE 5.3-1 Power Dependent Linear Heat Generation Rate Multiplier (LHGRFACp) 14 TABLE 5.3-2 Flow Dependent Linear Heat Generation Rate Multiplier (LHGRFACt) 14 TABLE 5.5.2-1 Control Rod Block Instrumentation Setpoints, Trip Function 1, Rod Block Monitor 15 TABLE B-1 GE 14 LHGR Limits - UO 2 Fuel Rods 20 TABLE 8-2 GE14 LHGR Limits - Gadolinia Bearing Rods 20 TABLE B-3 GE14 LHGR Limits - UO2 Fuel Rods 21 TABLE B-4 GE14 LHGR Limits - Gadolinia Bearing Rods 21 TABLE 8-5 GNF2 LHGR Limits - UO2 Fuel Rods 22 TABLE B-6 GNF2 LHGR Limits - Gadolinia Bearing Rods 22 TABLE 8-7 GNF2 LHGR Limits - UO2 Fuel Rods 23 TABLE B-8 GNF2 LHGR Limits - Gadolinia Bearing Rods 23 TABLE C-1 BSP Region Intercepts (Operation Prior to FFWTR) 25 TABLE C-2 ABSP Region Setpoints 25 TABLE 0-1 MCPR99.9% Value 27 Page 3 of 27

COLR HOPE CREEK 1 Rev 17 (Cycle 23) 1.0 Terms and Definitions ABSP Automated Backup Stability Protection APLHGR Average Planar Linear Heat Generation Rate ARTS APRM and RBM Technical Specification Analysis BSP Backup Stability Protection COLR Core Operating Limits Report DSS-CD Detect and Suppress Solution - Confirmation Density ECCS Emergency Core Cooling Systems EOC End-of-Cycle EOC-RPT End-of-Cycle Recirculation Pump Trip FFWTR Final Feedwater Temperature Reduction FWHOOS Feedwater Heaters Out of Service GNF Global Nuclear Fuel LCO Limiting Condition for Operation LHGR Linear Heat Generation Rate LHGRFACt ARTS LHGR thermal limit flow dependent adjustments and multipliers LHGRFACp ARTS LHGR thermal limit power dependent adjustments and multipliers MCPR Minimum Critical Power Ratio MCPR99.9% Cycle-specific MCPR that ensures at least 99.9% of fuel rods are not susceptible to boiling transition MCPRf ARTS MCPR thermal limit flow dependent adjustments and multipliers MCPRp ARTS MCPR thermal limit power dependent adjustments and multipliers OPRM Oscillation Power Range Monitor RBM Rod Block Monitor RDF Recirculation Drive Flow RTP Rated Thermal Power SAD Amplitude Discriminator Setpoint SLO Single Recirculation Loop Operation TLO Two Recirculation Loop Operation Page 4 of 27

COLR HOPE CREEK 1 Rev 17 (Cycle 23) 2.0 References Methodology References

1. "General Electric Standard Application for Reactor Fuel," NEDE-24011-P-A-28, and the U.S. Supplement NEDE-24011-P-A-28-US, September 2019.

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 22 Cycle 23,"

Global Nuclear Fuel Document No. 004N8343, Revision 0, September 2019.

7. "Fuel Bundle Information Report for Hope Creek Reload 22 Cycle 23," Global Nuclear Fuel Document No. 004N8344, Revision 0, June 2019.
8. "Option B Licensing Basis & Cycle-Independent Transient Evaluation for Implementation of the 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, Revision 0, February 18, 2015.
10. "GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II),"

NEDC-33270P, Revision 9, December 2017.

11. "Hope Creek SRLR Bases Confirmation for Control Rods Inserted at the End of Cycle," Global Nuclear Fuel Letter 005N3138, Revision 0, May 31, 2019.

12."GESTAR II Section 3.4 Compliance Assessment for Hope Creek Cycle 23," Global Nuclear Fuel Document No. 005N5150, Revision 1, October 2019.

Page 5 of 27

COLR HOPE CREEK 1 Rev 17 {Cycle 23) 3.0 General Information This revision oflthe Core Operating Limits Report provides the core operating limits for Hope Creek Generating Station Unit 1 Cycle 23 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). The MCPR 9g_ 9 % values determined for the generation of the MCPR power distribution limits are provided in Appendix D.

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, 1:, 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 27

COLR HOPE CREEK 1 Rev 17 (Cycle 23) 4.0 Precautions and Limitations This document is specific to Hope Creek Generating Station Unit 1 Cycle 23 and shall not be applicable to any other core or cycle design. Revision 17 of the COLR is applicable for Cycle 23 operating from the date of issuance through the end of cycle including consideration of reduced feedwater temperatures for FWHOOS, 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 "all-rods-out" excludes control rods that have been inserted to suppress fuel leakers, address cell friction performance, or other circumstances that would require control rod insertion such as, but not limited to, meeting Technical Specification Operability requirements.

Inserted rods may be removed at any point of the cycle, including after the end of full power capability (References 9 *and 11 ). 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 433.5°F (433.5°F - 60°F

= 373.5°F). Therefore, Cycle 23 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 operation 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 is not supported by this revision of the COLR.

Page 7 of 27

COLR HOPE CREEK 1 Rev 17 (Cycle 23) 5.0 Technical Specifications that Reference the COLR The following Hope Creek Technical Specifications reference this COLR:

Technical Specification Title 2.1 Safety Limits 2.2 Reactor Protection System Instrumentation Setpoints 3/4.1.4.3 Rod Block Monitor 3/4.2.1 Average Planar Linear Heat Generation Rate 3/4.2.3 Minimum Critical Power Ratio 3/4.2.4 Linear Heat Generation Rate 3/4.3.1 Reactor Protection System Instrumentation 3/4.3.6 Control Rod Block Instrumentation 3/4.4.1 Recirculation System Recirculation Loops 6.9.1.9 Administrative Controls, Core Operating Limits Report Page 8 of 27

COLR HOPE CREEK 1 Rev 17 (Cycle 23) 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 APLHGR Limit Average Planar Exposure (kW/ft)

MWd/MTU MWd/STU TLO SLO 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 5.1-2 APLHGR Data for GNF2 APLHGR Limit Average Planar Exposure (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 of 27

COLR HOPE CREEK 1 Rev 17 (Cycle 23) 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 MCPR99.9% 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 of27

COLR HOPE CREEK 1 Rev 17 (Cycle 23)

TABLE 5.2-1 MCPR Operating Limits Cycle Exposure S 8,556 MWd/MTU (S 7,762 MWd/STU)

Main Turbine Bypass Operable Scram Operating Condition Speed GE14 GNF2 Option A 1.49 1.51 TLO-EOC-RPT Operable B 1.39 1.41 A 1.51 1.53 TLO-EOC-RPT Inoperable B 1.40 1.43 A 1.52 1.54 SLO-EOC-RPT Operable B 1.42 1.44 A 1.54 1.56 SLO-EOC-RPT Inoperable B 1.43 1.46 Scram Speed Option A T=1, Scram Speed Option B T=O TLO = Two Recirculation Loop Operation SLO = Single Recirculation Loop Operation TABLE 5.2-2 MCPR Operating Limits Cycle Exposure > 8,556 MWd/MTU (> 7,762 MWd/STU)

Main Turbine Bypass Operable Scram Operating Condition Speed GE14 GNF2 Option A 1.60 1.56 TLO-EOC-RPT Operable B 1.43 1.46 A 1.63 1.58 TLO-EOC-RPT Inoperable B 1.46 1.48 A 1.63 1.59 SLO-EOC-RPT Operable B 1.46 1.49 A 1.66 1.61 SLO-EOC-RPT Inoperable B 1.49 1.51 Scram Speed Option A T= 1, Scram Speed Option B T=O TLO = Two Recirculation Loop Operation SLO = Single Recirculation Loop Operation Page 11 of 27

COLR HOPE CREEK 1 Rev 17 (Cycle 23)

TABLE 5.2-3 Power Dependent MCPR Multiplier (Kp) Data Core Thermal Power (% of Rated)

Operating Condition 24 45 60 ~100 MCPR Multiplier Kp TLO 1.561 1.280 1.150 1.000 SLO 1.561 1.280 1.150 1.000 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 92.9 105 MCPR Limit TLO 1.58 SLO 1.61 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 27

COLR HOPE CREEK 1 Rev 17 (Cycle 23) 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 U0 2 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.

I

5. For the flow dependent LHGR adjustment for SLO, determine a LHGRFACt value by linearly interpolating a LHGRFACt value as a function of rated core flow from Page 13 of 27

COLR HOPE CREEK 1 Rev 17 (Cycle 23) 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 82.2 105 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 27

COLR HOPE CREEK 1 Rev 17 (Cycle 23) 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 23 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 23 and confirms SAD = 1.10 for Hope Creek Cycle 23 operation.

The SAD = 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 1.75, or THERMAL POWER greater than or equal to 90% of RATED THERMAL POWER with MCPR less than 1.44.

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 Trip Function Trip Setpoinf Allowable Valuex a.i) Low Trip Setpoint (LTSP) 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 27

COLR HOPE CREEK 1 Rev 17 (Cycle 23)

Appendix A: Method of Core Average Scram Speed Calculation Page 16 of 27

COLR HOPE CREEK 1 Rev 17 (Cycle 23)

Method of Core Average Scram Speed, -r, Calculation T is defined as 1/2 where: rB = 0.672+1.65 nNl (0.016)

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, M = 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 N1 = total number of active rods measured in Specification 4.1.3.3.a or 4.1.3.3.d.

If rave~ r n, set -c = 0 to apply Option B OLMCPR.

T shall be 1.0 (-c = 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 27

COLR HOPE CREEK 1 Rev 17 (Cycle 23)

Ap pen dix B: Ex pos ure -De pen den t Lin ear He at Ge ner atio n Rate Lim its Page 18 of 27

COLR HOPE CREEK 1 Rev 17 (Cycle 23)

Exposure-Dependent Linear Heat Generation Rate Limits The LHGR limits for all fuel and rod types are considered proprietary information of the vendor. Tables B-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 UO 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 27

COLR HOPE CREEK 1 Rev 17 (Cycle 23)

Tables B-1 and B-2 contain limits applicable to the GE14 bundle types that follow.

  • GE 14-P 1OCNAB401-9G6. 0/6G4. 0-1 00T-150-T6-4238 TABLE B-1: GE14 LHGR Limits - U02 Fuel Rods Peak Pellet Exposure UO 2 LHGR Limit MWd/MTU MWd/STU kW/ft

((

))

TABLE 8-2: GE14 LHGR Limits - Gadolinia Bearing Rods Most Limiting Peak Pellet Exposure Gadolinia LHGR Limit MWd/MTU MWd/STU kW/ft

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Page 20 of 27

COLR HOPE CREEK 1 Rev 17 (Cycle 23)

Tables 8-3 and B-4 contain limits applicable to the GE14 bundle types that follow.

  • GE14-P1 0CNAB401-17GZ-1 00T-150-T6-4237 TABLE 8-3: GE14 LHGR Limits - U02 Fuel Rods Peak Pellet Exposure UO 2 LHGR Limit MWd/MTU MWd/STU kW/ft

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TABLE 8-4: GE14 LHGR Limits - Gadolinia Bearing Rods Most Limiting Peak Pellet Exposure Gadolinia LHGR Limit MWd/MTU MWd/STU kW/ft

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Page 21 of 27

COLR HOPE CREEK 1 Rev 17 (Cycle 23)

Tables B-5 and B-6 contain limits applicable to the GNF2 bundle types that follow.

  • GNF2-P1 0CG28385-14GZ-1 00T2-150-T6-4653 TABLE B-5: GNF2 LHGR Limits - U02 Fuel Rods Peak Pellet Exposure UO 2 LHGR Limit MWd/MTU MWd/STU kW/ft

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))

TABLE B-6: GNF2 LHGR Limits - Gadolinia Bearing Rods Most Limiting Peak Pellet Exposure Gadolinia LHGR Limit MWd/MTU MWd/STU kW/ft

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Page 22 of 27

COLR HOPE CREEK 1 Rev 17 (Cycle 23)

Tables 8-7 and 8-8 contain limits applicable to the GNF2 bundle types that follow.

  • GNF2-P10CG28377-15GZ-100T2-150-T6-4440
  • GNF2-P10CG28375-6G5.0/7G4.0-100T2-150-T6-4441
  • GNF2-P10CG28383-14GZ-100T2-150-T6-4532
  • GNF2-P10CG28399-15GZ-100T2-150-T6-4654
  • GNF2-P1 0CG2B408-2G5.0/1 0G4.0-1 00T2-150-T6-4655 TABLE 8-7: GNF2 LHGR Limits - U0 2 Fuel Rods Peak Pellet Exposure UO 2 LHGR Limit MWd/MTU MWd/STU kW/ft

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TABLE 8-8: GNF2 LHGR Limits - Gadolinia Bearing Rods Most Limiting Peak Pellet Exposure Gadolinia LHGR Limit MWd/MTU MWd/STU kW/ft

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Page 23 of 27

COLR HOPE CREEK 1 Rev 17 (Cycle 23)

Appendix C: Backup Stability Protection Page 24 of 27

COLR HOPE CREEK 1 Rev 17 (Cycle 23)

Backup Stability Protection Region Intercepts Table C-1 values reflect the cycle-specific BSP region intercepts determined for Cycle 23 considering nominal feedwater temperature operation and FWHOOS (Reference 6).

FFWTR is not supported by this revision of the COLR.

TABLE C-1: BSP Region Intercepts (Operation Prior to FFWTR)

Region Boundary Intercept  % Power %Flow Region 1 High Flow Control Line 62.5 46.4 Region 1 Natural Circulation Line 43.5 35.2 Region 2 High Flow Control Line 67.9 53.2 Region 2 Natural Circulation Line 31.7 36.3 Region 1 = BSP Scram Region Region 2 = BSP Controlled Entry Region Automated Backup Stability Protection (ABSP) Region Setpoints Table C-2 values reflect the cycle-specific modified Simulated Thermal Power -

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 and FWHOOS conditions.

TABLE C-2: ABSP Region Setpoints Parameter Setpoint Slope for Trip (mTR1P) 0. 79 (% RTP / % RDF)

Constant Power Line for Trip (PssP-TRIP) 43.5 (% RTP)

Constant Flow Line for Trip (WssP-TRIP) 37.8 (% RDF)

Flow Breakpoint (WssP-BREAK) 16.0 (% RDF)

Page 25 of 27

COLR HOPE CREEK 1 Rev 17 (Cycle 23)

Appendix D: MCPR99.9% Value Page 26 of 27

COLR HOPE CREEK 1 Rev 17 (Cycle 23)

MCPR99.93/4 Value Table D-1 contains the MCPR 9g_ 9%values developed for the determination of the Hope Creek Cycle 23 LCO 3.2.3 MCPR Operating Limits (Reference 6), generated in accordance with Section 5.2. The MCPR 99 _9%value is dependent on the number of reactor coolant recirculation loops in operation.

TABLE D-1: MCPR99.93/4 Value Operating Condition MCPR99.93/4 Value TLO 1.10 SLO 1.13 The MCPR99.9% value is the same for both GE14 and GNF2.

TLO = Two Recirculation Loop Operation SLO = Single Recirculation Loop Operation Page 27 of27

LR-N19-0101 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. ((This_ sentence_ is_ an _example. {3})) 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(6)(4), and the Trade Secrets Act, 18 USC Sec. 1905, and NRC regulations 10 CPR 9.l 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 of 3

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 GNF-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 GNP-A or its licensor.

(9) P11blic 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 profit-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.

GNF-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 of this 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 under 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

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