RNP-RA/17-0021, Transmittal of Core Operating Limits Report

Transmittal of Core Operating Limits Report

ML17075A088
Person / Time
Site:	Robinson
Issue date:	03/13/2017
From:	Sherman C Duke Energy Progress
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RNP-RA/17-0021 FMP-001, Rev. 32
Download: ML17075A088 (27)

Text

l(_~ DUKE

~ ENERGYe Serial: RNP-RA/17-0021 MAR 13 2017 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 H. 8. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/RENEWED LICENSE NO. DPR-23 TRANSMITTAL OF CORE OPERATING LIMITS REPORT Ladies and Gentlemen:

Charles E. Sherman H. B. Robinson Steam Electric Plant Unit 2 Director - Nuc Org Effectiveness Duke Energy 3581 West Entrance Road Hartsville, SC 29550 0: 843 8571609 F: 843 8571319 Clruck.Slrennan@duke-energy.com TS 5.6.5.d In accordance with Technical Specifications 5.6.5.d, Duke Energy Progress, LLC is transmitting Revision O to the H. B. Robinson Steam Electric Plant, Unit No. 2, Core Operating Limits Report (COLA) for Cycle 31. A summary of the changes is provided on Page 2 of the attached revision to FMP-001, "Core Operating Limits Report (COLA)." The COLA is Attachment 10.1 to FMP-001.

There are no commitments associated with this letter.

If you have any questions concerning this matter, please contact Tony Pilo, Manager-Nuclear Regulatory Affairs at (843) 857-1409.

Sincerely, Cif.~n Director - Nuc Org Effectiveness CES/cac Attachment c:

NRC Regional Administrator, NRC, Region II NRC Resident Inspector, HBRSEP Mr. Dennis Galvin, NRC Project Manager, NRR

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/17-0021 26 pages (including cover page)

H. B. ROBINSON STEAM ELECTRIC PLANT (HBRSEP), UNIT NO. 2 CYCLE 31 CORE OPERATING LIMITS REPORT, REVISION 0 Note: This report is Attachment 10.1 to HBRSEP, Unit No. 2, Fuel Management Procedure (FMP) - 001

FMP-001 Rev. 32 Page 1 of 25 I

Information Use H. B. ROBINSON NUCLEAR PLANT, UNIT NO. 2 PLANT OPERATING MANUAL VOLUME 6 PART 5 FUEL MANAGEMENT PROCEDURE FMP-001 CORE OPERATING LIMITS REPORT (COLR)

REVISION 32

FMP-001 Rev. 32 Page 2 of 25

SUMMARY

OF CHANGES PRR 2065288, RNEI-0400-0006 FMP-001 Revision 32 Section/Step REVISION COMMENTS Where Applicable Updated from Cycle 30 to Cycle 31 2.5, 10.1.1 Replaced Cycle 30 reload EC 294784 with Cycle 31 RNEI-0400-0006 2.8 Replaced REG-NGGC-0010 with AD-LS-ALL-0007 2.11 Deleted Calculation reference 2.12 Replaced NFP-NGGC-0018 with AD-NF-NGO-0214 8.5 Update revision instructions 10.1.1 Updated applicable limit on burnup form 609 EFPD (21,190 MWD/MTU) to 547 EFPD (19,027 MWD/MTU) 10.1.2.1.2 Update 300 ppm Surveillance limit in 2.1.2 from -39.66 to -39.58 10.1.2.1.3 Update 60 ppm Surveillance limit in 2.1.3 from -43.85 to -43.85 10.1.2.4.1 Delete batch ROB2-25 and ROB2-26 and added ROB2-31 10.1.2.5.2 Delete batch ROB2-25 and ROB2-26 and added ROB2-31 10.1.3 Added reference 28 and updated reference 23 10.1 Figure 1.0 Update the breakpoint burnup in the note of Figure 1.0 from 305 EFPDs 10,600 MWD/MTU) to 273 EFPDs (9,500 MWD/MTU) 10.1 Figure 3.1 Update the V(z) curve and applicability upper burnup from 21,190 MWD/MTU to 19,027 10.2 Replaced NFP-NGGC-0018 with AD-NF-NGO-0214

FMP-001 Rev. 32 Page 3 of 25 TABLE OF CONTENTS SECTION................................................................................................................. PAGE 1.0 PURPOSE............................................................................................................. 4

2.0 REFERENCES

...................................................................................................... 4 3.0 RESPONSIBLITIES.............................................................................................. 5 4.0 PREREQUITES.................................................................................................... 5 5.0 PRECAUTIONS and LIMITATIONS..................................................................... 5 6.0 SPECIAL TOOLS and EQUIPMENT.................................................................... 6 7.0 ACCEPTANCE CRITERIA................................................................................... 6 8.0 PROCEDURE....................................................................................................... 7 9.0 RECORDS.......................................................................................................... 11 10.0 ATTACHMENTS................................................................................................. 11 10.1 HBRSEP UNIT NO. 2, CYCLE 31 CORE OPERATING LIMITS REPORT.... 12 10.2 PROCEDURES POTENTIALLY AFFECTED BY COLR REVISIONS........... 25

FMP-001 Rev. 32 Page 4 of 25 1.0 PURPOSE 1.1 To present the cycle-specific Core Operating Limits Report (COLR) for HBRSEP Unit No. 2 1.2 To provide a means of incorporating the COLR into the Plant Operating Manual (POM). The COLR is placed in the POM to ensure that it resides in a controlled location, and that references are provided that ensure that the requirements specified in NRC Generic Letter 88-16 and Improved Technical Specification 5.6.5 are met.

2.0 REFERENCES

2.1 Improved Technical Specifications 1.1, 3.1.1, 3.1.3, 3.1.5, 3.1.6, 3.2.1, 3.2.2, 3.2.3, 3.4.5, 3.4.6, 3.9.1, and 5.6.5 2.2 PLP-100, Technical Requirements Manual (TRM) 2.3 NRC Generic Letter 88-16, Removal of Cycle-Specific Parameter Limits from Technical Specifications, October 4, 1988.

2.4 License Amendment No. 141 - Regarding Removal of Cycle-Specific Parameter Limits to Core Operating Limits Report 2.5 RNEI-0400-0006 Robinson Cycle 31 COLR Markups 2.6 AD-DC-ALL-0201, Development and Maintenance of Controlled Procedure Manual Procedures 2.7 PLP-001, Plant Nuclear Safety Committee (PNSC) 2.8 AD-LS-ALL-0007, Applicability Determination Process 2.9 Self Assessment # 108207, Technical Specifications 5.0, Administrative Controls 2.10 UFSAR Section 17.3, RNP Quality Assurance Program Description 2.11 AD-NF-NGO-0214, Core Operating Limits Report Generation

FMP-001 Rev. 32 Page 5 of 25 3.0 RESPONSIBILITIES 3.1 RES Reactor Systems and/or Nuclear Fuel Engineering (NFE) is responsible for revising this procedure as changes to the COLR are required. At a minimum, revisions are required once per cycle, at Beginning of Cycle, to make the COLR cycle-specific.

3.2 The Plant Nuclear Safety Committee (PNSC) is responsible for reviewing revisions to the COLR and providing concurrence prior to implementation of COLR revisions (UFSAR Section 17.3, RNP Quality Assurance Program Description, Appendix A Item A.1.6.6.j).

3.3 RES Reactor Systems and Operations are responsible for monitoring plant conditions to ensure the Core Operating Limits specified in this procedure are met.

3.4 Licensing/Regulatory Programs is responsible for providing prompt notification of COLR revisions to the NRC in accordance with ITS 5.6.5.d within 30 days upon procedure approval.

4.0 PREREQUISITES 4.1 None 5.0 PRECAUTIONS and LIMITATIONS 5.1 Requirements for Revision of the COLR 5.1.1 The COLR is cycle-specific, this procedure will be revised at least once per cycle, that is, at the beginning of the cycle.

5.1.2 The methods and requirements established by this procedure for revision of the COLR supplement those of AD-DC-ALL-0201, Development and Maintenance of Controlled Procedure Manual Procedures.

5.1.3 Changes to the COLR will require a 10CFR 50.59 Evaluation as well as PNSC concurrence and notification of the NRC per TS 5.6.5.d as part of the revision process.

5.2 Core Operating Limits Report (COLR) 5.2.1 The current cycle-specific Core Operating Limits Report is provided in 0.1.

5.2.2 The titles for the Methodology references in Attachment 10.1 Section 3 have been altered to match what is currently listed in the RNP Technical Specifications. These report titles may differ slightly from current report titles.

FMP-001 Rev. 32 Page 6 of 25 6.0 SPECIAL TOOLS and EQUIPMENT 6.1 None.

7.0 ACCEPTANCE CRITERIA 7.1 None.

FMP-001 Rev. 32 Page 7 of 25 8.0 PROCEDURE 8.1 Definitions 8.1.1 FQ V(Z) - the Heat Flux Hot Channel Factor is the maximum local heat flux on the surface of a fuel rod divided by the average fuel rod heat flux and including the V (z) penalty and measurement uncertainties.

8.1.2 CFQ = FQ RTP - the cycle-specific FQ limit at Rated Thermal Power (RTP).

8.1.3 K(Z) - the normalized axial dependence factor for FQ versus core elevation.

8.1.4 F'H N - the Nuclear Enthalpy Rise Hot Channel Factor is the integral of linear power along the rod with the highest integrated power divided by the average rod power.

8.1.5 F'H RTP - the cycle-specific F'H limit at Rated Thermal Power (RTP).

8.1.6 PF'H - the Power Factor Multiplier for F'H.

8.1.7 AFD - the Axial Flux Difference is the difference in normalized flux signals between the top and bottom halves of a two-section excore neutron detector.

8.1.8 V(Z) - the ratio of the maximum FQ(Z) produced during and following transient maneuvers to the equilibrium FQ(Z) value at target axial offset conditions.

8.1.9 P - the fraction of rated power (2339 MWt) at which the core is operating.

8.1.10 RTP - Rated Thermal Power is a total reactor core heat transfer rate to the reactor coolant of 2339 MWt.

8.2 Abbreviations 8.2.1 POM - Plant Operating Manual 8.2.2 PNSC - Plant Nuclear Safety Committee 8.2.3 COLR - Core Operating Limits Report 8.2.4 MTC - Moderator Temperature Coefficient

FMP-001 Rev. 32 Page 8 of 25 8.2.5 ITS - Improved Technical Specifications 8.2.6 RIL - Rod Insertion Limits 8.2.7 EFPD - Effective Full Power Day 8.2.8 HBRSEP - H.B. Robinson Steam Electric Plant 8.2.9 NRC - Nuclear Regulatory Commission 8.2.10 RES - Robinson Engineering Section 8.2.11 ARO - All Rods Out 8.2.12 SDM - Shutdown Margin 8.3 Background Information 8.3.1 HBRSEP Unit No. 2, like all other commercial nuclear power plants, is required to operate within the specific core operating limits and restrictions as specified in the Technical Specifications. Examples of these limits/restrictions include power dependent rod insertion limits, and limits of FQ(Z) and F'H, among others. Technical Specification changes and NRC approval were required as specific numerical values for these limits/restrictions were revised. If these changes were frequent, e.g. on a cycle-specific basis, or if they were needed on accelerated schedules, considerable administrative burdens were placed on both the NRC and on utility personnel.

8.3.2 To reduce this burden, the COLR concept was developed in which specific numerical values for certain core operating limits and/or restrictions would be removed from the Technical Specifications and relocated to a COLR document. Using NRC approved methodologies, numerical values for these operating limits and/or restrictions can be updated on an as-needed basis (e.g. each cycle) by simply revising the COLR with appropriate review and notification to the NRC. Hence, revisions to the Technical Specifications are not required.

8.3.3 The NRC endorsed the COLR concept by encouraging licensees to develop such a document in Generic Letter 88-16 which provided guidance for relocation of specific numerical values for various core operating limits and/or restrictions to a COLR and indicated that these values could be changed without prior NRC approval so long as an NRC-approved methodology is followed. Future changes and updates would be allowable provided an Evaluation is performed in accordance with the provisions of 10CFR 50.59, the COLR is suitably revised, and the NRC is promptly informed of the revision.

FMP-001 Rev. 32 Page 9 of 25 8.3.4 The use of a COLR at H. B. Robinson was accepted by the NRC per License Amendment 141. The amendment established requirements for a cycle-specific COLR and for notification of the NRC (ITS 5.6.5.d) when any revisions or supplements (beginning of cycle or midcycle) are made.

Since the COLR is cycle-specific, the COLR will be revised at least once per cycle, that is, at the beginning of the cycle.

8.4 Contents of the H.B. Robinson Unit 2 COLR 8.4.1 Technical Specification ITS 5.6.5.a requires the following cycle-specific core operating limits be established and documented in the Core Operating Limits Reports

1.

Moderator Temperature Coefficient (MTC) Limits

2.

Shutdown Bank Insertion Limits

3.

Control Bank Insertion Limits

4.

Heat Flux Hot Channel Factor (FQ(Z)) Limit, CFQ

5.

K(Z) Curve

6.

Nuclear Enthalpy Rise Hot Channel Factor (F'H N) Limit, F'H RTP

7.

F'H Power Factor Multiplier (PF'H)

8.

Axial Flux Difference (AFD) Limits

9.

V(Z) Curve(s)

10.

Shutdown Margin

11.

Refueling Boron Concentration 8.4.2 The COLR will also contain a listing of the specific methodologies used to support the core operating limits per TS 5.6.5.b.

8.4.3 The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met (TS 5.6.5.c).

FMP-001 Rev. 32 Page 10 of 25 8.5 Revisions to The COLR 8.5.1 Nuclear Fuels Engineering (NFE) shall review and recommend for implementation any changes to the COLR. The changes recommended by NFE are normally transmitted to the plant via Engineering Instruction (EI).

8.5.2 Once NFE recommends a revision to the COLR, a Reactor Engineer shall request a revision to FMP-001 in accordance with the requirements of AD-DC-ALL-0201, Development and Maintenance of Controlled Procedure Manual Procedures.

8.5.3 Other plant procedures shall be reviewed to determine if they require revision in order to implement the revised COLR. At a minimum, the procedures listed in Attachment 10.2 shall be reviewed.

8.5.4 Any required procedure revisions or new procedures necessary to incorporate the change to the COLR shall be completed by the effective date of the COLR change.

8.5.5 The proposed revision of the COLR shall be submitted to the PNSC for review.

8.5.6 The PNSC shall review the proposed revision to the COLR and concur with the changes prior to their implementation in accordance with UFSAR Section 17.3 Appendix A Item A.1.6.6.j.

8.5.7 Upon approval of the COLR revision, Licensing/Regulatory Programs shall notify the NRC per ITS 5.6.5.d within 30 days.

FMP-001 Rev. 32 Page 11 of 25 9.0 RECORDS 9.1 This procedure does not generate any records.

10.0 ATTACHMENTS 10.1 HBRSEP Unit No. 2 Cycle 31 Core Operating Limits Report, Revision 0 10.2 Procedures Potentially Affected By COLR Revisions

ATTACHMENT 10.1 Page 1 of 13 FMP-001 Rev. 32 Page 12 of 25 HBRSEP UNIT NO. 2, CYCLE 31 CORE OPERATING LIMITS REPORT REVISION 0 1.0 OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for HBRSEP Unit No. 2, Cycle 31 has been prepared in accordance with the requirements of ITS 5.6.5 and is applicable to 547 EFPD (19,027 MWD/MTU).

The Improved Technical Specifications affected by this report and the methodologies used for the various parameters are listed below.

Parameter ITS Reference Applicable Methodology (Section 3.0 Number)

MTC 3.1.3 18, 19, 22, 23, 25 Shutdown Bank RILs 3.1.5 8, 18, 19, 22, 23, 25 Control Bank RILs 3.1.6 8, 18, 19, 22, 23, 25 FQ V(Z) 3.2.1, 3.2.3 5, 8, 11, 17, 18, 19, 21, 22, 23, 24, 25, 26, 27 F'H 3.2.2, 3.2.3 3, 5, 11, 17, 18, 19, 20, 21, 22, 23, 24, 25, 26, 27 AFD 3.2.1, 3.2.3 16, 18, 19, 21, 22, 23, 24, 25, 27 Shutdown Margin Requirements 3.1.1, 3.4.5, 3.4.6 8, 18, 19, 22, 23, 25 Refueling Boron Requirements 3.9.1 8, 18, 19, 22, 23 COLR 5.6.5 None

ATTACHMENT 10.1 Page 2 of 13 FMP-001 Rev. 32 Page 13 of 25 HBRSEP UNIT NO. 2, CYCLE 31 CORE OPERATING LIMITS REPORT REVISION 0 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using the NRC-approved methodologies specified in ITS 5.6.5 and the COLR Section 3.0.

2.1 Moderator Temperature Coefficient (ITS 3.1.3) 2.1.1 The Moderator Temperature Coefficient (MTC) limits are:

a) The Positive MTC (ARO) shall be less than or equal to +5.0 pcm/qF for power levels less than 50% RTP, and b) The Positive MTC (ARO) shall be less than or equal to 0.0 pcm/qF at 50%

RTP and above.

c) The Negative MTC (ARO/RTP) shall be less negative than -45.0 pcm/qF.

2.1.2 The 300 ppm Surveillance limit is:

At an equilibrium RTP-ARO boron concentration of 300 ppm the MTC shall be less negative than or equal to -39.58 pcm/qF.

2.1.3 The 60 ppm Surveillance limit is:

At an equilibrium RTP-ARO boron concentration of 60 ppm the MTC shall be less negative than or equal to -43.85 pcm/qF.

2.2 Shutdown Banks Insertion Limits (ITS 3.1.5) 2.2.1 The shutdown banks shall be withdrawn to at least 225 steps.

2.3 Control Bank Insertion Limits (ITS 3.1.6) 2.3.1 The control banks shall be limited in physical insertion as shown in Figure 1.0

ATTACHMENT 10.1 Page 3 of 13 FMP-001 Rev. 32 Page 14 of 25 HBRSEP UNIT NO. 2, CYCLE 31 CORE OPERATING LIMITS REPORT REVISION 0 2.4 Heat Flux Hot Channel Factor - FQ V (Z) (ITS 3.2.1, 3.2.3)

FQ V(Z) d (CFQ/P) x K(Z) for P ! 0.5 FQ V(Z)  (CFQ/0.5) x K(Z) for P d 0.5 Where: P = (Thermal Power / Rated Thermal Power) 2.4.1 CFQ = 2.46 for ROB2-28, ROB2-29, ROB2-30, and ROB2-31 reload batches 2.4.2 K(Z) is specified in Figure 2.0 2.5 Nuclear Enthalpy Rise Hot Channel Factor - F'H (ITS 3.2.2, 3.2.3)

F'H  F'H RTP (1 + PF'H (1-P))

Where: P = (Thermal Power / Rated Thermal Power) 2.5.1 F'H is the measured F'H N multiplied by the measurement uncertainty (1.04) 2.5.2 F'H RTP = 1.80 for ROB2-28, ROB2-29, ROB2-30 and ROB2-31 reload batches 2.5.3 PF'H = 0.2 2.6 Axial Flux Difference (ITS 3.2.1, 3.2.3) 2.6.1 The axial flux difference target bands are r3% and r5% about the target AFD.

2.6.2 V(Z) values for the r3% and r5% target bands are specified in Figures 3.1 and 3.2 2.6.3 The AFD Acceptable Operation Limits are specified in Figure 4.0

ATTACHMENT 10.1 Page 4 of 13 FMP-001 Rev. 32 Page 15 of 25 HBRSEP UNIT NO. 2, CYCLE 31 CORE OPERATING LIMITS REPORT REVISION 0 2.7 Shutdown Margin Requirements (SDM) (ITS 3.1.1, 3.1.4, 3.1.5, 3.1.6, 3.1.8, 3.4.5, 3.4.6, 3.9.1) 2.7.1 The Mode 1 and Mode 2 required SDM versus RCS boron concentration is presented in Figure 5.0.

2.7.2 The Mode 3 SDM requirements are as follows:

a) With at least 2 reactor coolant pumps in operation, the SDM shall be greater than or equal to that specified in Figure 5.0.

b) With less than 2 reactor coolant pumps in operation and the rod control system capable of rod withdrawal, the SDM shall be greater than or equal to 6% 'k/k. This shutdown margin requirement shall be met with a minimum boron concentration of 1950 ppm.

c) With less than 2 reactor coolant pumps in operation and with the rod control system not capable of rod withdrawal, the SDM shall be greater than or equal to that specified in Figure 5.0.

2.7.3 The Mode 4 SDM requirements are as follows:

a) With at least 2 reactor coolant pumps in operation, the SDM shall be greater than or equal to 2.6% 'k/k.

b) With less than 2 reactor coolant pumps in operation and the rod control system capable of rod withdrawal, the SDM shall be greater than or equal to 6% 'k/k. This shutdown margin requirement shall be met with a minimum boron concentration of 1950 ppm.

c) With less than 2 reactor coolant pumps in operation and with the rod control system not capable of rod withdrawal, the SDM shall be greater than or equal to 2.6% 'k/k.

2.7.4 The minimum required SDM for Mode 5 is 2.6% 'k/k.

2.7.5 The minimum required SDM for Mode 6 is 6% 'k/k.

2.8 Refueling Boron Concentration (ITS 3.9.1) 2.8.1 In Mode 6 the minimum boron concentration shall be 1950 ppm.

ATTACHMENT 10.1 Page 5 of 13 FMP-001 Rev. 32 Page 16 of 25 HBRSEP UNIT NO. 2, CYCLE 31 CORE OPERATING LIMITS REPORT REVISION 0 3.0 METHODOLOGY REFERENCES

1) Deleted

2) Not Used for Cycle 31

3) XN-NF-82-21(A), Revision 1, Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations, Exxon Nuclear Company, September 1983

4) Deleted

5) XN-75-32(A) Supplements 1, 2, 3, and 4, Computational Procedure for Evaluating Rod Bow, Exxon Nuclear Company, October 1983

6) Deleted

7) Deleted

8) XN-NF-78-44(A), Generic Control Rod Ejection Analysis, Exxon Nuclear Company, October 1983

9) Not Used For Cycle 31

10) Deleted

11) XN-NF-82-06(A), Revision 1 and Supplements 2, 4, and 5, Qualification of Exxon Nuclear Fuel for Extended Burnup, Exxon Nuclear Company, October 1986

12) Deleted

ATTACHMENT 10.1 Page 6 of 13 FMP-001 Rev. 32 Page 17 of 25 HBRSEP UNIT NO. 2, CYCLE 31 CORE OPERATING LIMITS REPORT REVISION 0

13) Deleted

14) Deleted

15) Deleted

16) ANF-88-054(P), PDC-3: Advanced Nuclear Fuels Corporation Power Distribution Control for Pressurized Water Reactors and Application of PDC-3 to H.B. Robinson Unit 2, Advanced Nuclear Fuels Corporation, October 1990

17) ANF-88-133(P) (A), and Supplement 1, Qualification of Advanced Nuclear Fuels PWR Design Methodology for Rod Burnups of 62 GWd/MTU, Advanced Nuclear Fuels Corporation, December 1991

18) ANF-89-151(A), Revision 0, ANF-RELAP Methodology for Pressurized Water Reactors: Analysis of Non-LOCA Chapter 15 Events, Advanced Nuclear Fuels Corporation, May 1992

19) EMF-92-081(A), Revision 1, Statistical Setpoint/Transient Methodology for Westinghouse Type Reactors, Siemens Power Corporation, July 2000

20) EMF-92-153(P) (A), Revision 1, HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel, Siemens Power Corporation, January 2005

21) XN-NF-85-92(P) (A), Exxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination and Thermal Conductivity Results, Exxon Nuclear Company, November 1986

22) EMF-96-029(P) (A), Volumes 1 and 2, Reactor Analysis System for PWRs Volume 1 - Methodology Description, Volume 2 - Benchmarking Results, Siemens Power Corporation, January 1997

23) EMF-92-116, Revision 0 and Supplement 1(P)(A)-000, Generic Mechanical Design Criteria for PWR Fuel Designs, Siemens Power Corporation, February 1999 and February 2015

24) EMF-2103(P) (A), Revision 0, Realistic Large Break LOCA Methodology for Pressurized Water Reactors, Framatome ANP, April 2003

ATTACHMENT 10.1 Page 7 of 13 FMP-001 Rev. 32 Page 18 of 25 HBRSEP UNIT NO. 2, CYCLE 31 CORE OPERATING LIMITS REPORT REVISION 0

25) EMF-2310(P) (A) Revision 1, SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors, May 2004

26) BAW-10240(P) (A), Revision 0, Incorporation of M5 Properties in Framatome ANP Approved Methods, Framatome ANP, May 2004

27) EMF-2328(P) (A), Revision 0, PWR Small Break LOCA Evaluation Model, S-RELAP5 Based, Framatome ANP Richland, Inc., March 2001 and Errata, January 2008

28) DPC-NE-2005-PA, "Thermal Hydraulic Statistical Core Design Methodology",

Rev. 5 (not used for Cycle 31)

ATTACHMENT 10.1 Page 8 of 13 FMP-001 Rev. 32 Page 19 of 25 HBRSEP UNIT NO. 2, CYCLE 31 CORE OPERATING LIMITS REPORT REVISION 0 NOTE:

The breakpoint between BOL and EOL RIL occurs at 50% of the cycle as defined by burnup. For Cycle 31, this burnup occurs at 273 EFPDs (9,500 MWD/MTU).

Control rod banks shall always be withdrawn and inserted in the prescribed sequence. For withdrawal, the sequence is Control A, Control B, Control C, and Control D. The insertion sequence is the reverse of the withdrawal sequence.

Overlap of consecutive control banks shall not exceed the prescribed setpoint for automatic overlap. The setpoint is 97 steps.

Control bank A must be withdrawn from the core prior to power operation.

At BOL and 0% core power, Control bank B will be at or above step 224.

ATTACHMENT 10.1 Page 9 of 13 FMP-001 Rev. 32 Page 20 of 25 HBRSEP UNIT NO. 2, CYCLE 31 CORE OPERATING LIMITS REPORT REVISION 0 Figure 2.0, Normalized Axial Dependence Factor K(z) for Fq Versus Elevation NOTE: For all power levels the K(z) at all axial levels is 1.0.

ATTACHMENT 10.1 Page 10 of 13 FMP-001 Rev. 32 Page 21 of 25 HBRSEP UNIT NO. 2, CYCLE 31 CORE OPERATING LIMITS REPORT REVISION 0 Figure 3.1 V(z) as a Function of Core Height NOTE:

V(z) data applicable for 0 < burnup < 19,027 MWD/MTU.

For power levels below 50% RTP, the V(z) data at all axial levels is 1.0. It is conservative to apply the above figure to power levels below 50% RTP.

ATTACHMENT 10.1 Page 11 of 13 FMP-001 Rev. 32 Page 22 of 25 HBRSEP UNIT NO. 2, CYCLE 31 CORE OPERATING LIMITS REPORT REVISION 0 Figure 3.2 V(z) as a Function of Core Height Figure 3.2 is not required for Cycle 31

ATTACHMENT 10.1 Page 12 of 13 FMP-001 Rev. 32 Page 23 of 25 HBRSEP UNIT NO. 2, CYCLE 31 CORE OPERATING LIMITS REPORT REVISION 0 NOTE:

For power levels above 90%, power operation is allowed within the target bands (+3% and +5%).

ATTACHMENT 10.1 Page 13 of 13 FMP-001 Rev. 32 Page 24 of 25 HBRSEP UNIT NO. 2, CYCLE 31 CORE OPERATING LIMITS REPORT REVISION 0 Figure 5.0, Shutdown Margin Versus Boron Concentration

ATTACHMENT 10.2 Page 1 of 1 FMP-001 Rev. 32 Page 25 of 25 PROCEDURES POTENTIALLY AFFECTED BY COLR REVISIONS Revisions to the COLR may require that revisions be made to other plant procedures. At a minimum the following procedures should be reviewed to determine if they must be revised:

APP-005 GP-002 CP-010 GP-003 EST-002 GP-006-1 EST-003 AOP-038 EST-028 GP-009-1 EST-048 GP-009-2 EST-049 GP-009-3 EST-050 GP-009-4 EST-105 GP-009-5 EST-146 GP-010 FMP-009 LP-551 FMP-012 LP-552 FMP-014 OP-003 FMP-019 OP-910 FHP-003 OMP-003 Station Curve Book PLP-100 ERFIS CAOC Software AD-NF-NGO-0214 The procedures listed above are those that are typically affected by COLR revisions; however, other procedures may also be affected.