RA-24-0286, Transmittal of Core Operating Limits Report
| ML24332A022 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 11/27/2024 |
| From: | Mason P Duke Energy Progress |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| RA-24-0286, TS 5.6.5.d | |
| Download: ML24332A022 (1) | |
Text
ei_~ DUKE
~ ENERGY Date: November 27, 2024 Serial: RA-24-0286 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:
Phillip Mason H. B. Robinson Steam Electric Plant Unit 2 Manager - Nuclear Support Services Duke Energy 3581 West Entrance Road Hartsville, SC 29550 843 951 5797 Phillip. Mason@duke-energy.com TS 5.6.5.d In accordance with Technical Specifications 5.6.5.d, Duke Energy Progress, LLC is transmitting Revision Oto the H. B. Robinson Steam Electric Plant, Unit No. 2, Core Operating Limits Report (COLR) for Cycle 35. A summary of the changes is provided on Page 2 of the attached revision to FMP-001, "Core Operating Limits Report (COLR)." The COLR is Attachment 1 to FMP-001.
There are no regulatory commitments associated with this letter.
If you have any questions concerning this matter, please contact Phillip Mason, Manager -
Nuclear Support Services at (843) 951-5797.
~J}J~
Phillip Mason Manager - Nuclear Support Services Attachment c:
NRC Regional Administrator, NRC, Region II NRC Senior Resident Inspector, HBRSEP Mr. Lucas Haeg, NRC Project Manager, NRR
United States Nuclear Regulatory Commission Attachment to Serial: RA-24-0286 35 pages (including cover page)
H. B. ROBINSON STEAM ELECTRIC PLANT (HBRSEP), UNIT NO. 2 CYCLE 35 CORE OPERATING LIMITS REPORT, REVISION 0 Note: This report is Attachment 1 to HBRSEP, Unit No. 2, Fuel Management Procedure (FMP) - 001
(_~ DUKE ENERGY ROBINSON UNIT 2 TECHNICAL PROCEDURE (OPERATING)
FMP-001 CORE OPERATING LIMITS REPORT (COLR)
REVISION 40 Multiple Use
CORE OPERATING LIMITS REPORT (COLR)
FMP-001 Rev. 40 Page 2 of 34 REVISION
SUMMARY
PRR 2534141 DESCRIPTION Upgraded entire procedure to AD-DC-ALL-0202, Writers Manual for Procedures and Work Instructions, and Procedure Automation System (PAS) format. Formatted to allow content to be text searchable. (Editorial)
Deleted the following definitions, as they are duplicated in Attachment 1 Section 2.6.
(Non-Technical)
Section 4.2 OLD Step 3, K(Z): The normalized axial dependence factor for FQ versus core elevation.
Section 4.2 OLD Step 9, P: The fraction of rated power (2339 MWt) at which the core is operating.
Section 6.1 Step 1; Clarified by deleting the word "evaluation". It is not intended to indicate that a 50.59 Evaluation will always be needed. Sometimes only a Screen is needed and performing the 50.59 will determine weather an evaluation is required. (Non-Technical)
Revised the following for RNEl-0400-0030 RO, H.B. Robinson Steam Electric Plant (HBRSEP) Unit No. 2 Cycle 35 Core Operating Limits Report (COLR)
Throughout; Replaced Cycle 34 with Cycle 35. (Editorial)
Deleted the following definitions: (Non-Technical)
Section 4.2 OLD Step 1, FQV(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.
Section 4.2 OLD Step 2, CFQ = FQRTP: The cycle specific FQ limit at Rated Thermal Power (RTP).
Section 4.2 OLD Step 4, F(HN: 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.
Section 4.2 OLD Step 5, F(H RTP: The cycle specific F(H limit at Rated Thermal Power (RTP).
Section 4.2 OLD Step 6, PF(H: The Power Factor Multiplier for F(H.
Section 4.2 OLD Step 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.
Section 8.7 Miscellaneous Document 6; Replaced reference "RNEl-0400-0027" with "RN El-0400-0030" (Editorial)
- Replaced Cycle 34 Core Operating Limits Report with Cycle 35 Core Operating Limits Report.
CORE OPERATING LIMITS REPORT (COLR)
FMP-001 Rev. 40 Page 3 of 34 TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE..................................................................................................................... 4 2.0 SCOPE.......................................................................................................................... 4 3.0 PRECAUTIONS AND LIMITATIONS............................................................................. 4 4.0 GENERAL INFORMATION........................................................................................... 5 5.0 PREREQUISITES......................................................................................................... 6 6.0 INSTRUCTIONS............................................................................................................ 7 6.1 (Information Use) - Requirements for Revision of COLR.................................-.............. 7 6.2 (Reference Use) - Core Operating Limits Report (COLR)............................................. 7 6.3 (Information Use) - Contents of H.B. Robinson Unit 2 COLR....................................... 8 6.4 (Information Use) - Revisions to COLR......................................................................... 9 7.0 RECORDS................................................................................................................... 10
8.0 REFERENCES
............................................................................................................ 10 ATTACHMENTS 1
(Information Use) - HBRSEP Unit No. 2, Cycle 35 Core Operating Limits Report.......................................................................................................................... 14 2
(Information Use) - Procedures Potentially Affected by COLR Revisions.................... 34
CORE OPERATING LIMITS REPORT (COLR) 1.0 PURPOSE
- 1.
To present the cycle-specific Core Operating Limits Report (COLR) for HBRSEP Unit No. 2
- 2.
The COLR is cycle-specific, this procedure will be revised at least once per cycle, at the beginning of the cycle.
2.0 SCOPE 2.1 General
- 1.
To provide a means of incorporating the COLR into the Controlled Procedure Manual procedures. The COLR is placed in the Controlled Procedure Manual procedures 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.
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.
2.2 Organization Responsibilities
- 1.
Reactor Engineering 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.
- 2.
Reactor Engineering and Operations are responsible for monitoring plant conditions to ensure the Core Operating Limits specified in this procedure are met.
- 3.
Regulatory Affairs is responsible for providing prompt notification of COLR revisions to the NRC in accordance with TS 5.6.5.d within 30 days upon procedure approval.
3.0 PRECAUTIONS AND LIMITATIONS None FMP-001 Rev. 40 Page 4 of 34
CORE OPERATING LIMITS REPORT (COLR) 4.0 GENERAL INFORMATION 4.1 Background Information
- 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 Fa(X, Y, Z) and F llH(X, Y), among others.
Tech Spec changes and N RC 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.
- 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 Tech Specs 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.
- 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 NRG-approved methodology is followed. Future changes and updates would be allowable provided the changes are evaluated in accordance with the provisions of 1 0CFR 50.59, the COLR is suitably revised, and the NRC is promptly informed of the revision.
- 4.
The use of a COLR at H.B. Robinson was accepted by the NRC per License Amendment 141 and the information contained in the COLR was expanded per License Amendments 250 and 263. The amendment established requirements for a cycle-specific COLR and for notification of the NRC (TS 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.
FMP-001 Rev. 40 Page 5 of 34
CORE OPERATING LIMITS REPORT (COLR) 4.2 Definitions
- 1.
Axial Flux Difference (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.
- 2.
Rated Thermal Power (RTP): Rated Thermal Power is a total reactor core heat transfer rate to the reactor coolant of 2339 MWt.
- 3.
T avg: RCS Average Temperature 5.0 PREREQUISITES None FMP-001 Rev. 40 Page 6 of 34
6.0 6.1 6.2 CORE OPERATING LIMITS REPORT (COLR)
INSTRUCTIONS (Information Use) - Requirements for Revision of COLR
- 1.
IF Technical changes to the COLR are made, THEN perform an 1 0CFR 50.59 per AD-LS-ALL-0008, 10 CFR 50.59 Review Process.
- 2.
Ensure notification to the NRC per TS 5.6.5.d is part of the revision process.
(Reference Use) - Core Operating Limits Report (COLR)
NOTE The titles for the Methodology references in Attachment 1, (Information Use) - HBRSEP Unit No. 2, Cycle 35 Core Operating Limits Report, Section 3 have been altered to align with what is currently listed in RNP TS. These report titles FMP-001 Rev.40 Page 7 of 34 may differ slightly from current report titles..........................................................................
- 1.
Update the current cycle-specific Core Operating Limits Report provided in Attachment 1, (Information Use) - HBRSEP Unit No. 2, Cycle 35 Core Operating Limits Report.......................................................
6.3 CORE OPERATING LIMITS REPORT (COLR)
(Information Use) - Contents of H.B. Robinson Unit 2 COLR
- 1.
Ensure TS 5.6.5.a requirements for the following cycle-specific core operating limits are established and documented in the Core Operating Limits Reports:
- a.
Shutdown Margin (SOM) Requirements
- b.
Moderator Temperature Coefficient (MTC) Limits
- c.
Shutdown Bank Insertion Limits
- d.
Control Bank Insertion Limits
- e.
Heat Flux Hot Channel Factor Fa (X,Y,Z) Limits
- f.
Nuclear Enthalpy Rise Hot Channel Factor Ft.H (X,Y) Limits
- g.
Axial Flux Difference (AFD) Limits
- h.
Refueling Boron Concentration Limit
- i.
Reactor Core Safety Limits
- j.
Overtemperature ti T and Overpower ti T setpoint parameter values
- k.
Reactor Coolant System pressure, temperature and flow Departure from Nucleate Boiling (DNB) Limits I.
ECCS Accumulator Boron Concentration Limits
- m.
ECCS Refueling Water Storage Tank Boron Concentration Limits.
- 2.
Ensure the COLR contains a listing of the specific methodologies used to support the core operating limits per TS 5.6.5.b.
- 3.
Ensure the core operating limits are 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 SOM, transient analysis limits, and accident analysis limits) of the safety analysis are met (TS 5.6.5.c).
FMP-001 Rev. 40 Page 8 of 34
CORE OPERATING LIMITS REPORT (COLR)
FMP-001 Rev.40 Page 9 of 34 6.4 (Information Use) - Revisions to COLR NOTE Changes recommended by NFE are normally transmitted to the plant via Engineering Instruction (El).
- 1.
[Nuclear Fuels Engineering (NFE)] Review and recommend for implementation any changes to the COLR.
- 2.
[Reactor Engineer] WHEN NFE recommends a revision to the
- COLR, THEN request a revision to FMP-001 in accordance with the requirements of AD-DC-ALL-0201, Development and Maintenance of Controlled Procedure Manual Procedures.
- 3.
At a minimum, review plant procedures listed in, (Information Use) - Procedures Potentially Affected by COLR Revisions, to determine if they require revision in order to implement the revised COLR.
- 4.
IF any required procedure revisions or new procedures are necessary to incorporate the change to the COLR, THEN ensure those procedures are completed by the effective date of the COLR change.
- 5.
IRegulatory Affairs] WHEN the COLR revision is approved AND effective, THEN ensure the NRC is notified per TS 5.6.5.d within 30 days.
CORE OPERATING LIMITS REPORT (COLR) 7.0 RECORDS
- 1.
There are no records generated by this procedure.
8.0 REFERENCES
8.1 Commitment None 8.2 Technical Specifications
- 1.
Section 1.1, Definitions
- 2.
Section 2.1, Safety Limits (SLs)
- 3.
Section 3.1.1, Shutdown Margin (SOM)
- 4.
Section 3.1.3, Moderator Temperature Coefficient (MTC)
- 5.
Section 3.1.5, Shutdown Bank Insertion Limits
- 6.
Section 3.1.6, Control Bank Insertion Limits
- 7.
Section 3.2.1, Heat Flux Channel Factor (FQ(Z))
- 8.
Section 3.2.2, Nuclear Enthalpy Rise Hot Channel Factor (FN~H)
- 9.
Section 3.2.3, Axial Flux Difference (AFD) (PDC-3 Axial Offset Control Methodology)
- 10.
Section 3.3.1, Reactor Protection System (RPS) Instrumentation
- 11.
Section 3.4.1, RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits
- 12.
Section 3.4.5, RCS Loops - MODE 3
- 13.
Section 3.4.6, RCS Loops - MODE 4
- 14.
Section 3.9.1, Boron Concentration FMP-001 Rev.40 Page 10 of 34
CORE OPERATING LIMITS REPORT (COLR) 8.2 Technical Specifications (continued) 8.3 8.4
- 15.
Section 5.6.5, Core Operating Limits Report (COLR)
- a.
Sub Section 5.6.5.a
- b.
Sub Section 5.6.5.b
- c.
Sub Section 5.6.5.c
- d.
Sub Section 5.6.5.d Updated Final Safety Analysis Report None Drawings None 8.5 Procedures
- 1.
AD-DC-ALL-0201, Development and Maintenance of Controlled Procedure Manual Procedures
- 2.
AD-LS-ALL-0008, 10 CFR 50.59 Review Process
- 3.
AD-NF-NGO-0214, Core Operating Limits Report Generation
- 4.
AD-WC-RNP-0420, Shutdown Safety Function Guidelines
- 5.
AOP-019, Malfunction of RCS Pressure Control
- 6.
- 7.
APP-005, NIS and Reactor Control
- 8.
CP-010, Primary System Chemistry
- 9.
EST-003, lncore / Excore Detector Multipoint
- 10.
EST-028, Main Steam Safety Valve Testing
- 11.
EST-047, Reactor Coolant Flow Test
- 12.
EST-048, Control Rod Drop Test
- 13.
EST-049, Control Rod Drive Mechanism Operation Testing
- 14.
EST-050, Refueling Startup Procedure FMP-001 Rev. 40 Page 11 of 34
CORE OPERATING LIMITS REPORT (COLR) 8.5 Procedures (continued)
- 15.
EST-105, Post-Refueling Power Escalation Procedure
- 16.
EST-146, EOL MTC Measurement
- 17.
FHP-003, Fuel Assembly Movement in the Spent Fuel Pit
- 18.
FMP-009, Power Distribution Control
- 19.
FMP-019, Fuel and Insert Shuffle
- 20.
GP-002, Cold Shutdown to Hot Subcritical at No Load T AVG
- 21.
GP-003, Normal Plant Startup From Hot Standby to Critical
- 22.
GP-006-1, Normal Plant Shutdown from Power Operation to Hot Standby
- 23.
GP-009-1, Filling the Refueling Cavity with Fuel in the Reactor Vessel
- 24.
GP-009-2, Filling the Refueling Cavity or Reactor Vessel with Reactor Defueled
- 25.
GP-009-3, Draining the Refueling Cavity with Fuel in the Reactor Vessel
- 26.
GP-009-4, Draining the Refueling Cavity with the Reactor Defueled
- 27.
GP-009-5, Adjusting Reactor Vessel Level After Refueling Cavity Drain with Fuel in the Reactor
- 28.
GP-010, Refueling
- 29.
LP-551, Rod Position Indication System
- 30.
LP-552, Rod Position Indication System On Line Adjustment
- 31.
OP-003, Rod Control and Position Indication
- 32.
OP-910, Spent Fuel Pit Cooling and Purification System
- 33.
OST-020, Shiftly Surveillances
- 34.
TE-NF-PWR-0802, Core Power Distribution Review and Surveillance
- 35.
TE-NF-PWR-0804, Shutdown Margin Surveillance FMP-001 Rev.40 Page 12 of 34
CORE OPERATING LIMITS REPORT (COLR)
FMP-001 Rev. 40 Page 13 of 34 8.5 Procedures (continued)
- 36.
TE-NF-PWR-0809, Target Axial Flux Difference (AFD) Calculation 8.6 Vendor/Technical Manuals None
- 8. 7 Miscellaneous Documents
- 1.
DUKE-QAPD-001, Duke Energy Corporation Topical Report Quality Assurance Program Description Operating Fleet
- 2.
Operating License Amendment No. 250, Regarding Removal of Cycle Specific Parameter Limits to Core Operating Limits Report
- 3.
Operating License Amendment No 263 - Shearon Harris Nuclear Power Plant, Unit 1 and H.B. Robinson Steam Electric Plant, Unit No. 2 - Issuance of Amendments Revising Technical Specifications to Support Self-Performance of Core Reload Design and Safety Analysis
- 4.
NRC Generic Letter 88-16, Removal of Cycle Specific Parameter Limits from Technical Specifications, October 4, 1988
- 5.
PLP-100, Technical Requirements Manual (TRM)
- 6.
RNEl-0400-0030, H. B. Robinson Steam Electric Plant (HBRSEP)
Unit No. 2 Cycle 35 Core Operating Limits Report (COLR)
- 7.
ROD Manual Unit 2, Reactor Operating Data (ROD) Manual Unit 2
- 8.
Self Assessment 108207, Technical Specifications 5.0 Administrative Controls
CORE OPERATING LIMITS REPORT (COLR)
FMP-001 Rev. 40 Page 14 of 34 ATTACHMENT 1 Page 1 of 20
<< (Information Use) - HBRSEP Unit No. 2, Cycle 35 Core Operating Limits Report>>
HBRSEP UNIT NO. 2, CYCLE 35 CORE OPERATING LIMITS REPORT REVISION 0 1.0 CORE OPERA TING qMITS REPORT This Core Operating Limits Report (COLR) for HBRSEP Unit No. 2 Cycle 35 has been prepared in accordance with the requirements of Technical Specification 5.6.5 and is applicable to 671 EFPD.
The Technical Specifications affected by this report are listed below along with the NRC approved analytical methods used to develop and/or determine COLR parameters identified in Technical Specifications.
TS Technical Specification COLR Parameter COLR NRC Approved Section Section Methodology (Section 1.1 Number) 2.1.1 Reactor Core Safety Limits RCS Temperature and 2.1 5,20, 26,28,29, 31, 32, Pressure Safety Limits 33, 35 3.1.1 Shutdown Margin (SOM)
SOM 2.2 26,29,30, 32, 33 3.1.3 Moderator Temperature Coefficient MTC 2.3 26,29, 30,32, 33 3.1.5 Shutdown Bank Insertion Limits Shutdown Margin, 2.4 26, 28, 29, 30, 31, 32, 33, Rod Insertion Limits 35 3.1.6 Control Bank Insertion Limits Shutdown Margin, 2.5 26,28, 29, 30, 31, 32, 33, Rod Insertion Limits 35 3.2.1 Heat Flux Hot Channel Factor Fa, AFD, OP~T, Penalty 2.6 5,24, 26,27,29, 31, 32, Fo(X,Y,Z)
Factors 33, 34 3.2.2 Nuclear Enthalpy Rise Hot Channel FLlH, Penalty Factors 2.7 5, 20, 24,26,27,28,29, Factor F 6H(X, Y) 31, 32, 33,34,35 3.2.3 Axial Flux Difference AFD 2.8 5,24, 26, 27,29, 31, 32, 33, 34 3.9.1 Boron Concentration Min Boron Cone. During 2.9 26,29, 30, 33 Refueling Operations 3.3.1 Reactor Protection System OT~T,OP~T 2.10 5,20, 26,28,29, 31, 32, Instrumentation 33, 35 3.4.1 Reactor Coolant System Pressure, RCS Pressure, 2.11 20, 26,28, 32, 33, 35 rremperature, and Flow DNB Limits Temperature, and Flow 3.5.1 Accumulators Max. and Min. Boron 2.12 29, 30 Cone.
3.5.4 Refueling Water Storage Tank Max. and Min. Boron 2.13 29, 30 Cone.
5.6.5 Core Operating Limits Report Analytical Methods 1.1 None (COLR)
CORE OPERATING LIMITS REPORT (COLR)
FMP-001 Rev.40 Page 15 of 34 ATTACHMENT 1 Page 2 of 20
<< (Information Use) - HBRSEP Unit No. 2, Cycle 35 Core Operating Limits Report>>
HBRSEP UNIT NO. 2, CYCLE 35 CORE OPERATING LIMITS REPORT REVISION 0 1.1 Analytical Methods Analytical methods used to determine core operating limits for parameters identified in Technical Specifications and previously reviewed and approved by the NRC as specified in Technical Specification 5.6.5 are as follows.
1-4.
Deleted.
- 5.
XN-75-32(P)(A), Supplements 1 through 4, Computational Procedure for Evaluating Fuel Rod Bowing, Exxon Nuclear Company, issued October 1983.
6-19.
Deleted.
- 20.
EMF-92-153(P)(A), Revision 1, HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel, Siemens Power Corporation, issued January 2005.
21-23. Deleted.
- 24.
EMF-2103(P)(A), Revision 3, Realistic Large Break LOCA Methodology for Pressurized Water Reactors, Framatome, issued June 2016.
- 25.
Deleted.
- 26.
BAW-10240(P)-A, Revision 0, Incorporation of M5' Properties in Framatome ANP Approved Methods, Framatome ANP, Inc., issued May 2004.
- 27.
EMF-2328(P)(A), Revision O and Supplement 1, Revision 0, PWR Small Break LOCA Evaluation Model, S-RELAP5 Based, Framatome, Inc., issued May 2001 and Errata issued January 2008, Supplement 1 issued March 2012 and approved December 2016.
- 28.
DPC-NE-2005-PA, Revision 6, "Thermal-Hydraulic Statistical Core Design Methodology," NRC Safety Evaluation: ML20212L594.
- 29.
DPC-NE-1008-P-A, Revision 0, "Nuclear Design Methodology Using CASMO-5/SIMULATE-3 for Westinghouse Reactors," NRC Safety Evaluation: ML17102A923.
- 30.
DPC-NF-2010-A, Revision 3, "Nuclear Physics Methodology for Reload Design," NRC Safety Evaluation: ML17102A923.
- 31.
DPC-NE-2011-P-A, Revision 2, "Nuclear Design Methodology Report for Core Operating Limits of Westinghouse Reactors," NRC Safety Evaluation: ML17102A923.
- 32.
DPC-NE-3008-PA, Revision 0, "Thermal-Hydraulic Models for Transient Analysis," NRC Safety Evaluation: ML18060A401.
CORE OPERATING LIMITS REPORT (COLR)
FMP-001 Rev.40 Page 16 of 34 ATTACHMENT 1 Page 3 of 20
<< (Information Use) - HBRSEP Unit No. 2, Cycle 35 Core Operating Limits Report>>
HBRSEP UNIT NO. 2, CYCLE 35 CORE OPERATING LIMITS REPORT REVISION 0
- 33.
DPC-NE-3009-PA, Revision 0, "FSAR / UFSAR Chapter 15 Transient Analysis Methodology," NRC Safety Evaluation: ML18060A401.
- 34.
BAW-10231 P-A, Revision 1, "COPERNIC Fuel Rod Design Computer Code," Framatome ANP, Inc, January 2004.
- 35.
DPC-NE-2004-PA, Revision 2a, "Duke Power Company McGuire and Catawba Nuclear Stations Core Thermal-Hydraulic Methodology using VIPRE-01," NRC Safety Evaluation: ML17102A923.
(Methodology approved for use at H. B. Robinson Steam Electric Plant (HBRSER) Unit No. 2 per License Amendment No. 253 only as described in Section 3.2.2 of ML17102A923)
CORE OPERATING LIMITS REPORT (COLR)
FMP-001 Rev.40 Page 17 of 34 ATTACHMENT 1 Page 4 of 20
<< (Information Use) - HBRSEP Unit No. 2, Cycle 35 Core Operating Limits Report>>
HBRSEP UNIT NO. 2, CYCLE 35 CORE OPERATING LIMITS REPORT REVISION 0 2.0 OPERATING LIMITS Cycle-specific parameter limits for specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using NRC approved methodologies specified in Section 1.1.
2.1 Reactor Core Safety Limits (Sls) (ITS 2.1.1)
Reactor Core Safety Limits are shown in Figure 1.
2.2 Shutdown Margin Requirements (SOM) (ITS 3.1.1, 3.1.4, 3.1.5, 3.1.6, 3.1.8, 3.4.5, 3.4.6)
- 1.
The Mode 1 and Mode 2 required SOM versus RCS boron concentration is presented in Figure 2.
- 2.
The Mode 3 SOM requirements are as follows:
- a.
With at least 2 reactor coolant pumps in operation, the SOM shall be greater than or equal to that specified in Figure 2.
- b.
With less than 2 reactor coolant pumps in operation and the rod control system capable of rod withdrawal, the SOM shall be greater than or equal to 4% ~k/k.
- c.
With less than 2 reactor coolant pumps in operation and with the rod control system not capable of rod withdrawal, the SOM shall be greater than or equal to that specified in Figure 2.
- 3.
The Mode 4 SOM requirements are as follows:
- a.
With at least 2 reactor coolant pumps in operation, the SOM 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 SOM shall be greater than or equal to 4% ~k/k.
- c.
With less than 2 reactor coolant pumps in operation and with the rod control system not capable of rod withdrawal, the SOM shall be greater than or equal to 2.6% ~k/k.
- 4.
The minimum required SOM for Mode 5 is 2.6% ~k/k.
6130 580
~
SM 0
520
$<<)
0%
1l)l)i.
20'Ji.
CORE OPERATING LIMITS REPORT (COLR)
FMP-001 Rev.40 Page 18 of 34 ATTACHMENT 1 Page 5 of 20
<< (Information Use) - HBRSEP Unit No. 2, Cycle 35 Core Operating Limits Report >>
HBRSEP UNIT NO. 2, CYCLE 35 CORE OPERATING LIMITS REPORT REVISION 0 Figure 1 Reactor Core Safety Limits Three Loops in Operation DO NOT OPEAA11E IN THtS AREA ACCEPTABLE OPcRATIO Flux Tnp 1i15%ofRTP 2400psaai 2250pslai 2075ps1a 180Opsia 0%
50%
~ 70%
~0%
eoo.
100%
1'H)%
120
'Percent of 'Rated Thermal Pov Points on Core Safety Limits Plot Pressurizer Power Tcold (°F)
Pressure l11
(% Rated)
(psia) 0.0%
619.9 1800 99.5%
564.1 117.5%
527.5 0.0%
639.7 2075 101.6%
587.0 117.5%
549.4 0.0%
651.3 2250 102.1%
601.4 117.5%
560.6 0.0%
660.6 2400 102.6%
613.4 117.5%
568.8
[1] Pressure is presented with respect to pressurizer pressure. Although limits are originally calculated with respect to core exit pressure, they are converted to pressurizer pressure by subtracting 25 psia to account for the pressure drop.
NOf!: bMEDONA MINIMUM RCS FLOW Of 9S.'9x lOl lom/hr
CORE OPERATING LIMITS REPORT (COLR)
FMP-001 Rev. 40 Page 19 of 34 ATTACHMENT 1 Page 6 of 20
<< (Information Use) - HBRSEP Unit No. 2, Cycle 35 Core Operating Limits Report>>
HBRSEP UNIT NO. 2, CYCLE 35 CORE OPERATING LIMITS REPORT REVISION 0 Figure 2 Shutdown Margin Versus Boron Concentration for Modes 1-3 l2000, 1.1sll 12000~ 1.00 1
-Mode3 o.o 0
4 600 800 1
- 0 120 1400 1600 1800 2 0 HFP ARO BORON CO NTRA.1TION (ppm)
CORE OPERATING LIMITS REPORT (COLR)
FMP-001 Rev.40 Page 20 of 34 ATTACHMENT 1 Page 7 of 20
<< (Information Use) - HBRSEP Unit No. 2, Cycle 35 Core Operating Limits Report>>
HBRSEP UNIT NO. 2, CYCLE 35 CORE OPERATING LIMITS REPORT REVISION 0 2.3 Moderator Temperature Coefficient (ITS 3.1.3)
- 1.
The Moderator Temperature Coefficient (MTC) limits are:
The Positive MTC (ARO/HZP) shall be less than or equal to +5.0 pcm/°F with a linear ramp to 0.0 pcm/°F at 70% RTP. The Positive MTC shall be less than or equal to 0.0 pcm/°F between 70% RTP and 100% RTP.
The Negative MTC (ARO/RTP) shall be less negative than -42 pcm/°F.
- 2.
The 300 ppm MTC Surveillance limit is:
The 300 ppm/ARO/RTP MTC should be less negative than or equal to -36.25 pcm/°F.
- 3. The 60 ppm MTC Surveillance limit is:
The 60 ppm/ARO/RTP MTC should be less negative than or equal to -40.56 pcm/°F.
where:
- a.
ARO stands for all rods out
- b.
HZP stands for Hot Zero THERMAL POWER
- c.
RTP stands for RATED THERMAL POWER
- d.
ppm stands for parts per million (Boron) 2.4 Shutdown Bank Insertion Limits (ITS 3.1.5)
Fully withdrawn for all shutdown banks shall be greater than or equal to 225 steps.
2.5 Control Bank Insertion Limits (ITS 3.1.6)
Control banks shall be limited in physical insertion as specified in Figure 3. Fully withdrawn for all control banks shall be greater than or equal to 225 steps.
CORE OPERATING LIMITS REPORT (COLR)
FMP-001 Rev. 40 Page 21 of 34 ATTACHMENT 1 Page 8 of 20
<< (Information Use) - HBRSEP Unit No. 2, Cycle 35 Core Operating Limits Report>>
HBRSEP UNIT NO. 2, CYCLE 35 CORE OPERATING LIMITS REPORT REVISION 0 Figure 3 Rod Group Insertion Limits Versus Thermal Power (Three Loop Operation)
.225 1( 4.97%, 225) 220 200 180 l 1so
-El
~ 140
.. ~
~
(0%, 215)
Control Bank B V
(67.03%, 225)
/
V
_../ V'"
~
V
/ V Control Bank C 1120
/
..... V
~
-~ 100
- '=
~
~ 80 6
'f 41 60 J
"8 40
~
20 0
Notes:
./ V V
- (0%, B7 0
10 20
~v J ~
-~
Control Bank D
-~
I/
I;~
I 30 40 50 60 70 P*ercent of Rated Therma Power
- 1.
Fully withdrawn position shall be greater than or equal to 225 steps.
- 2.
Control Bank A must be withdrawn from the core prior to power operation.
80
] 0%, 165)
.JI V 90 1@0
- 3.
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.
- 4.
Overlap of consecutive control banks shall not exceed the prescribed setpoint for automatic overlap. The setpoint is 100 steps.
CORE OPERATING LIMITS REPORT (COLR)
FMP-001 Rev. 40 Page 22 of 34 ATTACHMENT 1 Page 9 of 20
<< (Information Use) - HBRSEP Unit No. 2, Cycle 35 Core Operating Limits Report>>
HBRSEP UNIT NO. 2, CYCLE 35 CORE OPERATING LIMITS REPORT REVISION 0 2.6 Heat Flux Hot Channel Factor F:J (X, Y, Z) (ITS 3.2.1)
- 1.
The F~ (X, Y, Z) Steady-State Limit as referenced in ITS 3.2.1 is:
FRTP F~ (X, Y, Z)~ _Q_ K(Z)
- K(BU) for P > 0.5 p
pRTP F~(X, Y,Z)~-Q-K(Z)
- K(BU) for P ~ 0.5
0.5 where
- a.
p
=
THERMAL POWER RATED THERMAL POWER
- b.
FRTP
= 2.60 for both Westinghouse NSSS 15x15 Long Cycle (W15-LC) and Advanced Q
High Thermal Performance (AHTP) fuel types.
C.
K(Z)
= the normalized FQ (X, Y, Z) as a function of core height, as specified in Figure 4, is applicable for both W15-LC and AHTP fuel types.
- d.
K(BU)
= is the normalized FQ (X, Y, Z) as a function of burnup. K(BU) is set to 1.0 at all burn ups and is applicable for both W15-LC and AHTP fuel types.
Note: F/! (X, Y, Z) shall be increased by 3% to account for manufacturing tolerances and 5% to account for measurement uncertainty when comparing against the LCO limits. The manufacturing tolerance and measurement uncertainty are implicitly included in the FQ surveillance limits as defined in COLR Sections 2.6.2 and 2.6.3.
- 2.
The Ft(X, Y, Z)0 P Transient Operational Limit as referenced in ITS 3.2.1 is:
F~ (X, Y, Z)~Ft(X, Y, Z)OP FL (X y Z)OP = F8(X,Y,Z)
- MQ(X,Y,Z)
Q I
UMT*MT where:
- a.
F~ (X, Y, Z) 0P = Cycle dependent maximum allowable design peaking factor that ensures
- b.
F~(X, Y,Z)
FQ (X, Y, Z) LOCA limit is not exceeded for operation within LCO limits.
Ft (X, Y, z)oP includes allowances for calculation and measurement uncertainties.
= Design power distribution for FQ* F8(X, Y,Z) is provided in Appendix A Table A-1 for normal operating conditions and in Appendix A Table A-4 for power escalation testing during initial startup operation.
- c.
MQ(X, Y,Z) = Margin remaining in core location X,Y,Z to the LOCA limit in the transient power distribution. MQ (X, Y, Z) is provided in Appendix A Table A-1 for normal operating conditions and in Appendix A Table A-4 for power escalation testing during initial startup operation.
CORE OPERATING LIMITS REPORT (COLR)
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<< (Information Use) - HBRSEP Unit No. 2, Cycle 35 Core Operating Limits Report>>
- d.
- e.
UMT MT HBRSEP UNIT NO. 2, CYCLE 35 CORE OPERATING LIMITS REPORT REVISION 0
= 1.05 (Total Peak Measurement Uncertainty).
= 1.03 (Engineering Hot Channel Factor).
- 3.
The Ft(X, Y, Z)RPs Transient Reactor Protection System Limit as referenced in ITS 3.2.1 is:
F~ (X, Y, Z)~Ft(X, Y, Z)RPS FL (X y Z)RPS = F8(X,Y,Z)
- Mc(X,Y,Z)
Q UMT*MT where:
- a.
- b.
Ft (X, Y, zyrs = Cycle dependent maximum allowable design peaking factor that ensures FQ (X, Y, Z) Centerline Fuel Melt (CFM) limit is not exceeded for operation within LCO limits. F~ (X, Y, z)RPs includes allowances for calculation and measurement uncertainties.
Fg (X, Y, Z) = Defined above in 2.b
- c.
Mc(X, Y, Z)
= Margin remaining to the CFM limit in core location X,Y,Z from the transient power distribution. Mc(X, Y, Z) is provided in Appendix A Table A-2 for normal operating conditions and in Appendix A Table A-5 for power escalation testing during initial startup operation.
- d.
UMT
= Defined above in 2.d
- e.
= Defined above in 2.e
- 4.
THERMAL POWER and AFD limit reductions required when Ft(x, Y,Z) 0r limit is exceeded are identified in Table 1.
- 5.
KSLOPE = 2.10 %~I / %Fa.
where:
KS LOPE
= reduction to the OPL1 T f2(L1I) breakpoints (ITS 3.3.1) require to compensate for each 1% measured F~(X, Y,Z) exceeds Ft(x, Y,Z)RP5 Iimit.
- 6.
F~ (X, Y, Z) Penalty Factors for Technical Specification Surveillances 3.2.1.2 and 3.2.1.3 are provided in Table 2.
CORE OPERATING LIMITS REPORT (COLR)
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<< (Information Use) - HBRSEP Unit No. 2, Cycle 35 Core Operating Limits Report >>
HBRSEP UNIT NO. 2, CYCLE 35 CORE OPERATING LIMITS REPORT REVISION 0 Figure 4 K(Z) Local Axial Penalty Function for Fa (X, Y, Z)
For Both W15-LC and AHTP Fuel Types (ITS 3.2.1) 1.200 ~------------------- ---- --------,
(0.0, 1.00)
(4.0, 1.00) 1.000 ---------- --
(12.0 0.96154)
(4.0 0.96154) 0.800 0.400 ClOff. Bright
{ft '..
K(Z) 0 1.O 1.'
LOOO 0.200 0.9615 20 0.000 -
- ---+----- ---+------ --------
0.0 2.0 4.0 60 8.0 10.0 12.0 Core Height (ft)
CORE OPERATING LIMITS REPORT (COLR)
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<< (Information Use) - HBRSEP Unit No. 2, Cycle 35 Core Operating Limits Report>>
HBRSEP UNIT NO. 2, CYCLE 35 CORE OPERATING LIMITS REPORT REVISION 0 Table 1 Thermal Power and AFD Limit Reductions Required When F~(X, Y, Z)0 P is Exceeded (ITS 3.2.1)
Negative Margin (%)
Power(%)
AFD Limit Change(%)
Negative Limit Positive Limit
< 2.0
~ 100*
~3
~5
~ 2.0 and < 4.0
~ 97
~4
~5
~ 4.0 and < 6.0
~ 94
~4
~7
~ 6.0
~ 50 N/A N/A
- Note - Confirm positive margin exists at the reduced AFD limits by recalculating margin using updated Monitor Factors. If the out-of-limit condition is not resolved, reduce THERMAL POWER by greater than 3% for each 1 % of negative margin.
CORE OPERATING LIMITS REPORT (COLR)
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<< (Information Use) - HBRSEP Unit No. 2, Cycle 35 Core Operating Limits Report>>
HBRSEP UNIT NO. 2, CYCLE 35 CORE OPERATING LIMITS REPORT REVISION 0 Table 2 - Fo(X, Y, Z} and FAH(X,Y) Penalty Factors For Technical Specification Surveillances 3.2.1 and 3.2.2 Burnup Fa(X,Y,Z)
F&H(X,Y)
(EFPD)
Penalty Factor(%)
Penalty Factor(%)
4 2.00 2.00 12 2.00 2.00 25 2.00 2.00 50 2.00 2.00 75 2.00 2.00 100 2.00 2.00 125 2.00 2.00 150 2.00 2.00 175 2.00 2.00 200 2.00 2.00 225 2.00 2.00 250 2.00 2.00 275 2.00 2.00 300 2.00 2.00 325 2.00 2.00 350 2.00 2.00 375 2.00 2.00 400 2.00 2.43 425 2.00 2.06 450 2.00 2.00 475 2.00 2.00 500 2.00 2.00 525 2.00 2.00 550 2.00 2.00 575 2.00 2.00 600 2.00 2.00 625 2.00 2.00 649 2.00 2.00 661 2.00 2.00 671 2.00 2.00 Note: Linear interpolation is adequate for intermediate cycle burnups. All cycle burnups outside the range of the table shall use a 2% penalty factor for both Fa(X,Y,Z) and Fr:.H(X,Y) for compliance with Tech Spec Surveillances 3.2.1.2, 3.2.1.3, and 3.2.2.2.
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<< (Information Use) - HBRSEP Unit No. 2, Cycle 35 Core Operating Limits Report>>
HBRSEP UNIT NO. 2, CYCLE 35 CORE OPERATING LIMITS REPORT REVISION 0
- 2. 7 Nuclear Enthalpy Rise Hot Channel Factor F1:H (X, Y) (ITS 3.2.2)
- 1.
The FiH(X, Y) Steady-State Limit as referenced in ITS 3.2.2 is:
FiH(X, Y) = MARP (X, Y) * [1.0 + -
1
- * (1.0 - P)]
RRH where:
- a.
- b.
C.
- d.
MARP (X, Y)
RRH p
is the steady-state, maximum allowed radial peak and includes allowances for calculation/measurement uncertainty
= Cycle-specific operating limit Maximum Allowable Radial Peaks.
MARP (X, Y) radial peaking limits are provided in Table 3.
= 5.0 (0.0 < P < 1.0) RRH is the Thermal Power reduction required to compensate for each 1 % measured radial peak, FrH(X, Y), exceeds the limit.
=
THERMAL POWER RATED THERMAL POWER
- 2.
The [FiH(X, Y)]suRv Transient Operational Limit as referenced in ITS 3.2.2 is:
[FL (X Y)]suRv = FfH(X,Y)
- M,1H(X,Y) t:.H I
UMR where:
- a.
[FiH(X, Y)]suRv = Cycle dependent maximum allowable design peaking factor that ensures
- b.
C.
M,1H(X, Y)
- d.
- 3. TRH = 0.02 where:
UMR F11H(X, Y) limit is not exceeded for operation within LCO limits.
[FfH(X, Y)JsuRv includes allowances for calculation and measurement uncertainties.
= Design power distribution for F,1H* FfH(X, Y) is provided in Appendix A Table A-3 for normal operating conditions and in Appendix A Table A-6 for power escalation testing during initial startup operation.
= Margin remaining in core location X,Y, relative to the Operational DNB limits in the transient power distribution. M11H(X, Y) is provided in Appendix A Table A-3 for normal operating conditions and in Appendix A Table A-6 for power escalation testing during initial startup operation.
= 1.0 (Uncertainty value for measured radial peaks). UMR is 1.0 since a factor of 1.04 is implicitly included in the variable M11H(X, Y)
TRH TRH is the OT~T K1 setpoint (ITS 3.3.1) reduction required to compensate for each 1 % measured radial peak, FrH(X, Y) exceeds its limit.
- 4. FrH(X, Y) Penalty Factors for Technical Specification Surveillances 3.2.2.2 are provided in Table 2.
CORE OPERATING LIMITS REPORT (COLR)
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<< (Information Use) - HBRSEP Unit No. 2, Cycle 35 Core Operating Limits Report >>
HBRSEP UNIT NO. 2, CYCLE 35 CORE OPERATING LIMITS REPORT REVISION 0 Table 3 Maximum Allowable Radial Peaks (MARPs)
W15-LC and AHTP Fuel, 100% RTP, Steady State Limits Core Height Axial Peak (ft) 1.05 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.1 3.5 0.12 1.812 1.845 1.915 1.990 2.071 2.156 2.101 2.010 1.927 1.850 1.782 1.069 1.20 1.812 1.845 1.916 1.971 2.051 2.135 2.073 1.982 1.899 1.822 1.738 1.043 2.40 1.812 1.845 1.897 1.941 2.008 2.063 2.020 1.959 1.876 1.799 1.689 1.013 3.60 1.812 1.845 1.915 1.990 2.049 2.046 2.000 1.935 1.872 1.803 1.671 1.003 4.80 1.812 1.845 1.914 1.988 2.061 1.999 1.937 1.876 1.816 1.759 1.685 1.011 6.00 1.812 1.845 1.914 1.987 1.992 1.934 1.875 1.816 1.758 1.704 1.625 0.975 7.20 1.812 1.844 1.913 1.968 1.918 1.859 1.803 1.750 1.696 1.647 1.569 0.942 8.40 1.81 1 1.846 1.843 1.816 1.783 1.763 1.728 1.676 1.628 1.582 1.505 0.903 9.60 1.784 1.815 1.805 1.755 1.695 1.667 1.635 1.605 1.562 1.518 1.439 0.863 10.80 1.792 1.814 1.779 1.723 1.668 1.617 1.570 1.526 1.485 1.445 1.371 0.822 12.00 1.752 1.724 1.671 1.623 1.578 1.534 1.492 1.452 1.413 1.376 1.306 0.784
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<< (Information Use) - HBRSEP Unit No. 2, Cycle 35 Core Operating Limits Report>>
HBRSEP UNIT NO. 2, CYCLE 35 CORE OPERATING LIMITS REPORT REVISION 0 2.8 Axial Flux Difference (ITS 3.2.1, 3.2.3)
The AXIAL FLUX DIFFERENCE (AFD) limits are specified in Figure 5.
2.9 Boron Concentration During Refueling Operations (ITS 3.9.1)
In Mode 6 the minimum boron concentration shall be 2150 ppm.
2.10 Reactor Protection System Instrumentation Setpoints (ITS 3.3.1)
The Reactor Protection System Instrumentation Setpoints are shown in Tables 4 and 5.
2.11 Reactor Coolant System DNB Parameters (ITS 3.4.1)
RCS pressure, temperature, and flow limits for DNB are shown in Table 6.
2.12 Accumulators - Max and Min Boron Concentration (ITS 3.5.1)
The Accumulators boron concentration limits in Modes 1 and 2, and the accumulators boron concentration limits in Mode 3 with pressurizer pressure> 1000 psig is:
Accumulators minimum boron concentration = 2150 ppm
- Accumulators maximum boron concentration = 2375 ppm *
- The safety analyses include 1 % boron measurement uncertainty relative to these values 2.13 Refueling Water Storage Tank - Max and Min Boron Concentration (ITS 3.5.4)
The Refueling Water Storage Tank (RWST) boron concentration limits in Modes 1, 2, 3, and 4 is:
RWST minimum boron concentration= 2150 ppm*
RWST maximum boron concentration= 2375 ppm*
- The safety analyses include 1 % boron measurement uncertainty relative to these values
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<< (Information Use) - HBRSEP Unit No. 2, Cycle 35 Core Operating Limits Report>>
-50 HBRSEP UNIT NO. 2, CYCLE 35 CORE OPERATING LIMITS REPORT REVISION 0 Figure 5 Axial Flux Difference Limits as a Function of Rated Thermal Power 00 Unacceptable Operation naoceptable Operation
(-30 50)
-40
-30 711)
Acceptable *. JPeration 00
-10 so 40 JO 20 0
10 Axial Flux Difference f.,~ Delta I)
{+24,.SO) 20 JO 40 50
CORE OPERATING LIMITS REPORT (COLR)
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<< (Information Use) - HBRSEP Unit No. 2, Cycle 35 Core Operating Limits Report>>
HBRSEP UNIT NO. 2, CYCLE 35 CORE OPERATING LIMITS REPORT REVISION 0 Table 4 - Overtemperature AT Setpoint Parameter Values (ITS 3.3.1)
Parameter Nominal Value Reference T avg at RTP rr ~ 575.9 °F Nominal RCS Operating Pressurizer Pressure P' ~ 2235 psig Overtemperature ~ T reactor trip setpoint coefficient K1 ~ 1.1265 Overtemperature ~ T reactor trip heatup setpoint penalty coefficient K2 = 0.02 / °F Overtemperature ~ T reactor trip depressurization setpoint penalty K3 = 0.00089 / psig coefficient Time constants utilized in the lead-lag compensator for Tavg rr1 ~ 20.08 sec rr2 ~ 3.08 sec f1 (~I) "positive" breakpoint 11 %~I W1 (~I) "negative" breakpoint 16 %~1 W1 (~I) "positive" slope 12.4 %~To I %~1 W1 (~I) "negative" slope 12.4 %~To I %~I Table 5 - Overpower l1T Setpoint Parameter Values (ITS 3.3.1)
Parameter Nominal Value Reference T avg at RTP rr ~ 575.9 °F Overtemperature ~ T reactor trip setpoint coefficient K4 ~ 1.08 Overpower ~ T reactor trip penalty coefficient KS~ 0.02 / °F for increasing Tavg KS = 0.0 / °F for decreasing Tavg Overtemperature ~ T reactor trip heatup setpoint penalty coefficient K6 ~ 0.00277 / °F for T > T' K6 = 0.0 / °F for T ~ T' n-ime constant utilized in the rate-lag compensator for Tavg rr3 ~ 9 sec fz(~I) "positive" breakpoint 11 %~I fz(~I) "negative" breakpoint 16 %~I fz(~I) "positive" slope 12.4 %~To I %~I fz(~I) "negative" slope 12.4 %~To I %~I
CORE OPERATING LIMITS REPORT (COLR)
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<< (Information Use) - HBRSEP Unit No. 2, Cycle 35 Core Operating Limits Report>>
HBRSEP UNIT NO. 2, CYCLE 35 CORE OPERATING LIMITS REPORT REVISION 0 Table 6 Reactor Coolant System DN B Parameters (ITS 3.4.1)
Parameter Indication No. Operable Channels Limits Indicated Pressurizer RTGB (meter) 3 2 2208.00 psig Pressure (SR 3.4.1.1)
RTGB (meter) 2 2 2213.17 psig ERFIS (computer) 3 2 2202.41 psig ERFIS (computer) 2 2 2206.33 psig Indicated RCS Average RTGB (meter) 3 s 578.0 °F Temperature (SR 3.4.1.2)
RTGB (meter) 2 s 577.6 °F ERFIS (computer) 3 s 578.6 °F ERFIS (computer) 2 s 578.3 °F RCS Total Flow Rate (SR 3.4.1.3) 2 98.9 x 106 lbm/hr plus instrument uncertainty (instrument uncertainty determined by EST-047)
(SR 3.4.1.4) 2 102.4 X 106 lbm/hr
(= 98.9 x 106 lbm/hr plus calorimetric instrument uncertainty)
CORE OPERATING LIMITS REPORT (COLR)
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<< (Information Use) - HBRSEP Unit No. 2, Cycle 35 Core Operating Limits Report>>
HBRSEP UNIT NO. 2, CYCLE 35 CORE OPERATING LIMITS REPORT REVISION 0 Appendix A Power Distribution Monitoring Factors Appendix A contains power distribution monitoring factors used in Technical Specification Surveillance. This data was generated in the RNP Cycle 35 Maneuvering Analysis calculation file, RNP-F/NFSA-0381. Due to the size of the monitoring factor data, Appendix A is controlled electronically within Duke Energy and therefore is not included in the Duke Energy internal copies of the COLR. Nuclear Fuels Engineering will control this information via computer file(s) and should be contacted if there is a need to access this information.
Appendix A is available to be transmitted to the NRC upon request.
Filename Checksum / File Size r2c35_AppendixA_rO.pdf 1198240040/1336247
CORE OPERATING LIMITS REPORT (COLR)
FMP-001 Rev.40 Page 34 of 34 ATTACHMENT 2 Page 1 of 1
<< (Information Use) - Procedures Potentially Affected by COLR Revisions >>
NOTE Revisions to the COLR may require that revisions be made to other plant procedures.
The procedures listed in this attachment are those that are typically affected by COLR revisions; however, other procedures may also be affected.
- 1.
At a minimum, review the following documents and software to determine if revisions are required.
AD-NF-NGO-0214 FMP-014 ROD Manual Unit 2, Reactor Operating Data (ROD) Manual Unit 2 AD-WC-RNP-0420 FMP-019 TE-NF-PWR-0802 AOP-019 GP-002 TE-NF-PWR-0804 AOP-038 GP-003 TE-NF-PWR-0809 APP-005 GP-006-1 CP-010 GP-009-1 ERFIS AFD Software GP-009-2 EST-003 GP-009-3 EST-028 GP-009-4 EST-047 GP-009-5 EST-048 GP-010 EST-049 LP-551 EST-050 LP-552 EST-105 OP-003 EST-146 OP-910 FHP-003 OST-020 FMP-009 PLP-100