GO2-23-072, Cycle 27 Core Operating Limits Report
| ML23157A226 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 06/05/2023 |
| From: | Ronnie Garcia Energy Northwest |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| GO2-23-072 | |
| Download: ML23157A226 (1) | |
Text
Richard M. Garcia ENERGY Columbia Generating Station P.O. Box 968, PE20 NORTHWEST Richland, WA 99352-0968 Ph. 509-377-8463 rmgarcia@energy-northwest.com
June 5, 2023 GO2-23-072
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001
Subject:
COLUMBIA GENERATING STATION, DOCKET NO. 50-397 CYCLE 27 CORE OPERATING LIMITS REPORT
Dear Sir or Madam:
In accordance with Columbia Generating Station Technical Specification (TS) 5.6.3.d, Energy Northwest herewith submits the Cycle 27 Core Operating Limits Report (COLR).
The operating limits in the COLR revision were developed in accordance with the requirements of TS 5.6.3.a, b, and c. The changes to the COLR have been reviewed by the Columbia Generating Station Plant Operations Committee.
No new regulatory commitments are made in this letter. If you have any questions or require additional information, please contact Mr. R. M. Garcia, Acting Manager, Regulatory Affairs, at (509) 377-8463.
Executed on this ______ day of __________, 2023.
Respectfully,
OocuSigned by:
~ Richard Garcia
0 1CBC2 7E DO B4457...
R. M. Garcia Acting Manager, Regulatory Affairs
Enclosure - as stated
cc: NRC Region IV Regional Admin NRC Region IV PM NRC Senior Resident Inspector C.D. Sonoda - BPA (w/o enc)
GO2-23-072 Enclosure
Core Operating Limits Report Columbia Generating Station Cycle 27
March 2023
CORE O PERATING L IMITS R EPORT COLUMBIA GENERATING STATION CYCLE 27
Revision 27 March 2023
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Columbia Generating Station Page 1 COLR-01, Revision 27
DESCRIPTION OF CHANGES
Justification The operating limits are established per Technical Specification (TS) 5.6.3a using NRC approved methodology listed in TS 5.6.3b. As required by TS 5.6.3c, the core operating limits are determined such that all applicable limits of the safety analysis are met.
Implement TP20-1-205, Revision 0, Reload Analysis and Core Management Committee (RACMC) Best Practice Guidelines, Core Operating Limits Report (COLR), BWR Owners Group, September 2020 (AR 00424334).
Page(s) Description (including summary, reason, initiating document, if applicable)
All Update document revision number and date. Revision bars not used due to large number of changes.
4,6-13 Add List of Tables and renumber tables to support inclusion. Update Table references. (AR 00424334) 5 Remove Reference Loading Pattern and add Nuclear Design Report per LDCN-21-021 change to FSAR 4.3.2.
6 GE Hitachi adopted a conservative rounding procedure. Change MAPLHGR exposure at (18.91 GWd/MTU, 17.15 GWd/STU) and references per SRLR (no change to ECCS-LOCA analysis).
7,9 Cycle 27 MCPR99.9% for SLO, cycle exposure range and MCPR operating limits per SRLR 7,12,16 Define per TS Bases for SR 3.2.2.2 and simplify scram time description. No change in requirements. Add direct source reference.
Add direct reference to LHGR limits and reference FBIR as basis. No change to limits. (AR 00424334) 7 - 11 Simplify footnotes by moving text that affects limits into COLR body, creating sub-sections for MCPRp, MCPRf, SLO and scram time per SR 3.2.2.2. Remove Non-pressurization Limit column from Table 3.1. Update footnote to specify the bounding MCPR limit from pressurization and non-pressurization events as the Option A and Option B limit, as applicable.
Relocate interpolation, between Option A and B, from the COLR to ENG-NFM-03 because a COLR revision to update Option B is simpler and TSP-CRD-C101 has not implemented interpolation. Move exposure range into the table. Consolidate MCPRp in fewer tables. Specify SLO limits, rather than making user calculate. (AR 00424334) 5,16 Update GESTAR II per SRLR and SRLR, FBIR and NDR for Cycle 27.
12,13 Consolidate LHGRFACp in fewer tables. Update table format. No change to limits. (AR 00424334)
Columbia Generating Station Page 2 COLR-01, Revision 27
Table of Contents
1.0 Introduction and Summary............................................................................................... 5
2.0 Average Planar Linear Heat Generation Rate (APLHGR) Limits for Technical Specification 3.2.1........................................................................................... 6
3.0 Minimum Critical Power Ratio (MCPR) Operating Limits for T echnical Specification 3.2.2........................................................................................................... 7
4.0 Linear Heat Generation Rate (LHGR) Limits for Technical Specification 3.2.3.............................................................................................................................. 12
5.0 Oscillation Power Range Monitor (OPRM) Instrumentation for Technical Specification 3.3.1.1...................................................................................................... 14
6.0 Rod Block Monitor Instrumentation for Technical Specification 3.3.2.1.......................... 15
7.0 References.................................................................................................................... 16
Columbia Generating Station Page 3 COLR-01, Revision 27
List of Tables
Table 1.1 Columbia Generating Station Reference Analytic al Methods....................................... 5 Table 2.1 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)
Versus Average Planar Exposure GNF2 Reload Fuel.................................................... 6 Table 3.1 Operating Limit MCPR (O LMCPR) All Fuel Types....................................................... 9 Table 3.2 Power Dependent MCPR Limits (MCPR p) and Multipliers (Kp)
Application Groups 1 - 4 All Fuel Types........................................................................ 10 Table 3.3 Power Dependent MCPR Limits (MCPR p) and Multipliers (Kp)
Application Group 5 All Fuel Types................................................................................ 11 Table 3.4 Flow Dependent MCPRf Limits All Application Groups All Fuel Types....................... 11 Table 4.1 Power Dependent LHGR Factor (LHGRFACp) Application Groups 1 - 4 All Fuel Types................................................................................................................ 12 Table 4.2 Power Dependent LHGR Factor (LHGRFACp) Application Group 5 All Fuel Types.................................................................................................................... 13 Table 4.3 Flow Dependent LHGR Factor (LHGRFACf) All Application Groups All Fuel Types.................................................................................................................... 13
Columbia Generating Station Page 4 COLR-01, Revision 27
1.0 Introduction and Summary
This report provides the core operating limits for Average Planar Linear Heat Generation Rate (APLHGR), Minimum Critical Power Ratio (MCPR), Linear Heat Generation Rate (LHGR), Oscillation Power Range Monitor (OPRM)
Instrumentation and Rod Block Monitor Instrumentation for Columbia Generating Station as required by Technical Specification 5.6.3. As required by Technical Specification 5.6.3, these limits were determined using NRC-approved methodology and are established so that all applicable limits of the plant safety analysis are met. The specific topical report revisions and supplements which describe the methodology utilized in this cycle specific analysis are shown in Table 1.1.
The reload licensing analyses for this cycle provide operating limits for Average Power Range Monitor / Rod Block Monitor and Technical Specifications Improvement Program (ARTS) and Maximum Extended Load Line Limit Analysis (MELLLA) operation which extends the power and flow operating regime for Columbia Generating Station up to the MELLLA boundary for Two Loop Operation (TLO).
The core operating limits are applicable up to 100% of rated thermal power along and below the MELLLA boundary. The minimum flow for operatio n at rated power is 82.7%.
The maximum flow is 106%.
Single Loop Operation (SLO) is restricted to the Extended Load Line Limit Analysis (ELLLA) boundary. The core operating limits for both TLO and SLO are applicable for normal feedwater temperature, feedwater heaters out of service, final feedwater temperature reduction and coastdown. The Pressure Regulator Out of Service (PROOS)
MCPR and LHGR limits are applicable if two (2) of the three (3) Digital Electro-hydraulic (DEH) pressure controllers are not functional.
The FSAR and Technical Specification Bases reference the COLR for the most recent approved version of the General Electric Standard Application for Reactor Fuel (GESTAR II), which is listed in Table 1.1. The FSAR references the COLR for the most recent versions of the Supplemental Reload Licensing Report, the Fuel Bundle Information Report, the Nuclear Design Report and the GNF2 Fuel Design Cycle-Independent Analyses, which are References 7.2, 7.3, 7.5 and 7.6. The FSAR and Technical Specification Bases reference the COLR for the most recent version of the GNF2 Generic Compliance with GESTAR II, which is Reference 7.7.
Table 1.1 Columbia Generating Station Reference Analytical Methods
NEDE-24011-P-A and NEDE-24011-P-A-US, General Electric Standard Application for Reactor Fuel (GESTAR II) and Supplement for the United States, Revision 31, November 2020.
Columbia Generating Station Page 5 COLR-01, Revision 27
2.0 Average Planar Linear Heat Generation Rate (APLHGR) Limits for Technical Specification 3.2.1
The APLHGR limits for use in Technical Specification 3.2.1, as a function of Average Planar Exposure, shall not exceed the limits shown in Table 2.1. APLHGR limits for single loop operation for GNF2 fuel are obtained by applying a 1.00 multiplier to the two-loop operation APLHGR limits. See Technical Specification 3.2.1 and the applicable Bases for further application details. (Reference 7.2 Table 8)
Table 2.1 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)
Versus Average Planar Exposure GNF2 Reload Fuel Average Planar Exposure MAPLHGR Limit GWd/MTU GWd/ST kW/ft 0.00 0.00 13.78 18.91 17.15 13.78 67.00 60.78 6.87 70.00 63.50 5.50 (Reference 7.2 Table 7)
Columbia Generating Station Page 6 COLR-01, Revision 27
3.0 Minimum Critical Power Ratio (MCPR) Operating Limits for Technical Specification 3.2.2
The MCPR operating limits for use in Technical Specification 3.2.2 are determined by the larger of the flow dependent (MCPR f) and power dependent (MCPRp) limits. See Technical Specification 3.2.2 and the applicable Bases for further application details.
The MCPR99.9% values used to calculate the MCPR operating limits are 1.08 for two loop operation (TLO) and 1.10 for single loop operation (SLO). (Reference 7.2, Section 11)
3.1 Power Dependent MCPR Operating Limits (MCPRp)
Power dependent MCPR limits are applicable to TLO and require the SLO adder when operating in SLO.
Pbypass is 29.5% of rated power.
The power dependent MCPR limits are provided in Table 3.2 for Application Groups 1 - 4 and in Table 3.3 for Application Group 5. The power dependent MCPR limits are provided as Kp multipliers above Pbypass and as absolute MCPRp limits below Pbypass. MCPRp limits above Pbypass are determined by Equation 3-1.
(3-1)
The Operating Limit MCPR (OLMCPR) is provided in Table 3.1 for use in Equation 3-1. Section 3.4 defines application of scram time Option A and Option B OLMCPR. (Reference 7.2 Section 11 & Appendix D)
3.2 Flow Dependent MCPR Operating Limits (MCPRf)
Flow dependent MCPR limits (MCPRf) are applicable to TLO and require the SLO adder when operating in SLO. The flow dependent limits in Table 3.4 are provided as absolute MCPRf limits. (Reference 7.2 Section 11 & Appendix D)
3.3 Single Loop Operation MCPR Operating Limits
For Single Loop Operation (SLO), the MCPR Operating Limit increases by the SLO adder, 0.03. SLO limits specified in Table 3.1, Table 3.2 and Table 3.4 include the SLO adder. (Reference 7.2 Section 11)
3.4 Scram Time ( for Technical Specification SR 3.2.2.2
for use in Technical Specification Bases for SR 3.2.2.2 is defined by Equation 3-2.
(3-2)
where:
Columbia Generating Station Page 7 COLR-01, Revision 27
(3-3)
(3-4)
0.866 seconds (the Technical Specification Table 3.1.4-1 limit on core average scram time to Notch 39);
of surveillance tests rforto date in cycle; total number of active rods measured to date in the cycle; and sum of the scram time to Notch 39 of all active rods measured to date in the cycle to comply with the Technical Specification surveillance requirements; 0.589 seconds (mean scram time to Notch 39 used in the Option B analysis, Reference 7.8, Section 5.0);
0.0101 seconds (standard deviation of, Reference 7.8, Section 5.0); and total number of active rods measured at beginning of cycle to comply with the Technical Specification surveillance requirements.
The NRC has concluded that a statistical approach (Option B) may be used for pressurization events analyzed with TRACG (Reference 7.4, Section 7.5.2.6). In order to take credit for conservatism in the scram speed performance, it must be demonstrated that there is insufficient reason to reject the plant-specific scram speed as being within the distribution assumed in the statistical analysis.
The procedure described below determines the MCPR limit based on the scram times of SR 3.2.2.2. If the scram speed distribution is not within the assumed distribution, the MCPR limit for pressuri zation events must be re-established based on an interpolation between the applicable limits for Option A (scram times of LCO 3.1.4, "Control Rod Scram Times") and Option B (realistic scram times) analyses.
The average scram time,, is tested against the analysis mean using Equation 3-5.
(3-5)
If the cycle average scram time satisfies the Equation 3-5 criterion, continued plant operation under the Option B OLMCPR is permitted. If not, select the Option A OLMCPR in Table 3.1 or interpolate. (Reference 7.9)
Columbia Generating Station Page 8 COLR-01, Revision 27
Table 3.1 Operating Limit MCPR (OLMCPR)
All Fuel Types
Application Scram Cycle Exposure Range3 Group1 Time Option2 2341 MWd/ST EOR-4158 MWd/ST > EOR-4158 MWd/ST 1 Two Loop Operation (TLO) and Equipment In-Service (EIS)
A 1.34 1.31 1.33 B 1.27 1.29 Single Loop Operation (SLO) and EIS A 1.49 B
2 TLO and EOC-RPT Out of Service (RPTOOS)
A 1.36 1.36 1.38 B 1.34 1.29 1.31 SLO and RPTOOS A 1.49 B
3 TLO and Turbine Bypass Valves Out of Service (TBVOOS)
A 1.36 1.36 1.36 B 1.34 1.31 1.31 SLO and TBVOOS A 1.49 B
4 TLO and TBVOOS and RPTOOS A 1.40 1.40 1.40 B 1.34 1.33 1.33 SLO and TBVOOS and RPTOOS A 1.49 B
5 TLO and Pressure Regulator Out of Service (PROOS)
A 1.34 1.32 1.37 B 1.27 1.29 SLO and PROOS A 1.49 B
(Reference 7.2 Section 11)
1 All Application Groups include one TBVOOS. (Reference 7.8, Sections 3.0 & 4.4.1)
2 The OLMCPR for Non-Pressurization Events is specified when greater than the Option A and/or the Option B OLMCPR for Pressurization Events.
3 End of Rated (EOR) is defined as the cycle exposure corresponding to all rods out, 100% power, 100% flow and normal feedwater temperature. (Reference 7.2 Sections 7 & 10)
Columbia Generating Station Page 9 COLR-01, Revision 27
Table 3.2 Power Dependent MCPR Limits (MCPRp) and Multipliers (K p)
Application Groups 1 - 4 All Fuel Types
Application Core Power (%)5 Group4 Flow
(%) 25 29.5 >29.5 45 60 85 100 Operating Limit MCPRp Operating Limit MCPR Multiplier (K p) 1 Two Loop Operation (TLO) and Equipment In-Service (EIS) 50.0 2.15 2.10 1.130 1.089 1.085 1.040 1.000
<50.0 1.98 1.97 SLO and EIS 50.0 2.18 2.13 1.130 1.089 1.085 1.040 1.000
<50.0 2.01 2.00 2 TLO and EOC-RPT Out of Service (RPTOOS) 50.0 2.15 2.10 1.134 1.090 1.085 1.043 1.000
<50.0 1.98 1.97 SLO and RPTOOS 50.0 2.18 2.13 1.134 1.090 1.085 1.043 1.000
<50.0 2.01 2.00 3 TLO and Turbine Bypass Valves Out of Service (TBVOOS) 50.0 2.69 2.52 1.136 1.095 1.092 1.056 1.000
<50.0 2.61 2.49 SLO and TBVOOS 50.0 2.72 2.55 1.136 1.095 1.092 1.056 1.000
<50.0 2.64 2.52 4 TLO and TBVOOS and RPTOOS 50.0 2.69 2.52 1.145 1.097 1.092 1.060 1.000
<50.0 2.61 2.49 SLO and TBVOOS and RP+TOOS 50.0 2.72 2.55 1.145 1.097 1.092 1.060 1.000
<50.0 2.64 2.52
4 All Application Groups include one TBVOOS. (Reference 7.8, Sections 3.0 & 4.4.1)
5 Power dependent MCPR limits are provided for core thermal powers greater than or equal to 25% of rated power at all core flows. The power dependent MCPR limits for c ore thermal powers below Pbypass are subdivided by core flow. A step change in the power dependent MCPR limits occurs at Pbypass because direct scrams on turbine throttle valve closure and turbine governor valve fast closure are automatically bypassed below Pbypass and not applicable per Technical Specification 3.3.1.1.
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Table 3.3 Power Dependent MCPR Limits (MCPRp) and Multipliers (K p)
Application Group 5 All Fuel Types
Core Power (%)7 Application Flow Group6 (%) 25 29.5 >29.5 45 60 65 >65 85 100 Operating Operating Limit MCPR Multiplier (K p)
Limit MCPRp 5 TLO and Pressure Regulator Out of Service (PROOS) 8 50.0 2.15 2.10 1.407 1.309 1.266 1.239 1.182 1.101 1.000
<50.0 2.09 2.05 SLO and PROOS 50.0 2.18 2.13 1.407 1.309 1.266 1.239 1.182 1.101 1.000
<50.0 2.12 2.08
Table 3.4 Flow Dependent MCPRf Limits All Application Groups All Fuel Types Operating Limit MCPRf Flow (%) Two Loop Operation Single Loop Operation (TLO) (SLO) 30.0 1.53 1.56 70.0 1.29 1.32 80.0 1.20 1.23 108.5 1.20 1.23
6 All Application Groups include one TBVOOS. (Reference 7.8, Sections 3.0 & 4.4.1)
7 Power dependent MCPR limits are provided for core thermal powers greater than or equal to 25% of rated power at all core flows. The power dependent MCPR limits for core thermal powers below Pbypass are subdivided by core flow. A step change in the power dependent MCPR limits occurs at Pbypass because direct scrams on turbine throttle valve closure and turbine governor valve fast closure are automatically bypassed below Pbypass and not applicable per Technical Specification 3.3.1.1.
8 At power levels greater than 65%, the pressure regulator failure downscale event is terminated by the APRM Neutron Flux - High scram. At power levels less or equal 65%, the pressure regulator failure downscale event is terminated by the Reactor Vessel Steam Dome Pressure - High scram.
(Reference 7.8, Section 4.4.1)
Columbia Generating Station Page 11 COLR-01, Revision 27
4.0 Linear Heat Generation Rate (LHGR) Limits for Technical Specification 3.2.3
The LHGR limits for use in Technical Specification 3.2.3 are provided as a function of pellet exposure, power and flow. The LHGR limits shall not exceed the product of the exposure dependent LHGR limit and the minimum of the power dependent LHGR Factor (LHGRFACp) or the flow dependent LHGR Factor (LHGRFACf).
See Technical Specification 3.2.3 and the applicable Bases for further application details.
4.1 The exposure dependent LHGR limits are provided in Tables B-1 and B-2 of Reference 7.7. (Reference 7.3, Section 1)
4.2 The power dependent LHGR Factor (LHGRFACp) is provided in Table 4.1 for Application Groups 1 - 4 and in Table 4.2 for Application Group 5.
(Reference 7.2, Appendix D)
4.3 The flow dependent LHGR Factor (LHGRFACf) is provided in Table 4.3.
(Reference 7.2, Appendix D)
Table 4.1 Power Dependent LHGR Factor (LHGRFACp)
Application Groups 1 - 4 All Fuel Types
Application Core Flow Power (%)10 Group9 (%) 25 29.5 >29.5 45 60 85 100 LHGRFACp Multiplier 1 Equipment In-Service (EIS) 50.0 0.527 0.527 0.634 0.713 0.791 0.922 1.000
<50.0 0.527 0.527 2 EOC-RPT Out of Service (RPTOOS) 50.0 0.527 0.527 0.634 0.713 0.791 0.922 1.000
<50.0 0.527 0.527 3 Turbine Bypass Valves Out of Service (TBVOOS) 50.0 0.380 0.414 0.634 0.713 0.735 0.9 02 1.0 00
<50.0 0.420 0.420 4 TBVOOS and RPTOOS 50.0 0.380 0.414 0.634 0.713 0.735 0.902 1.000
<50.0 0.420 0.420
9 All Application Groups include one TBVOOS. (Reference 7.8, Sections 3.0 & 4.4.1)
10 Power dependent LHRGFACp is provided for core thermal powers greater than or equal to 25% of rated power at all core flows. The power dependent LHRGFACp for core thermal powers below Pbypass is subdivided by core flow. A step change in the power dependent LHRGFACp occurs at Pbypass because direct scrams on turbine throttle valve closure and turbine governor valve fast closure are automatically bypassed below Pbypass and not applicable per Technical Specification 3.3.1.1.
Columbia Generating Station Page 12 COLR-01, Revision 27
Table 4.2 Power Dependent LHGR Factor (LHGRFACp)
Application Group 5 All Fuel Types
Application Core Flow Power (%)12 Group11 (%) 25 29.5 >29.5 45 60 65 85 100 LHGRFACp Multiplier 5 Pressure Regulator Out of Service (PROOS) 13 50.0 0.527 0.527 0.634 0.672 0.728 0.728 0.909 1.000
<50.0 0.527 0.527
Table 4.3 Flow Dependent LHGR Factor (LHGRFACf)
All Application Groups All Fuel Types Flow (%) LHGRFACf Multiplier 30.0 0.592 50.0 0.761 80.0 0.966 85.0 1.000 108.5 1.000
11 All Application Groups include one TBVOOS. (Reference 7.8, Sections 3.0 & 4.4.1)
12 Power dependent LHRGFACp is provided for core thermal powers greater than or equal to 25% of rated power at all core flows. The power dependent LHRGFACp for core thermal powers below Pbypass is subdivided by core flow. A step change in the power dependent LHRGFACp occurs at Pbypass because direct scrams on turbine throttle valve closure and turbine governor valve fast closure are automatically bypassed below Pbypass and not applicable per Technical Specification 3.3.1.1.
13 At power levels greater than 65%, the pressure regulator failure downscale event is terminated by the APRM Neutron Flux - High scram. At power levels less or equal 65%, the pressure regulator failure downscale event is terminated by the Reactor Vessel Steam Dome Pressure - High scram.
(Reference 7.8, Section 4.4.1)
Columbia Generating Station Page 13 COLR-01, Revision 27
5.0 Oscillation Power Range Monitor (OPRM) Instrumentation for Technical Specification 3.3.1.1
5.1 Period Based Detection Algorithm (PBDA) trip setpoints for Technical Specification Table 3.3.1.1-1, Footnote (g) and THERMAL POWER value for use in Table 3.3.1.1-1, Footnote (f). See Technical Specification 3.3.1.1 and the applicable Bases for further application details.
APPLICABLE FUNCTION MODES OR OTHER TRIP SETPOINT SPECIFIED CONDITIONS
2 Average Power Range Monitors
- f. OPRM Upscale (f)
Amplitude Trip (Sp) 1.15 Peak/Average Confirmation Count (Np) 16
(f) THERMAL POWER 19.6% RTP.
(Reference 7.2, Section 15.1)
(Reference 7.1, Table 3-2, Item 8.9)
5.2 THERMAL POWER value for Technical Specification 3.3.1.1, Required Action J.1:
THERMAL POWER < 19.6% RTP (Reference 7.1, Table 3-2, Item 8.9)
5.3 OPRM Not Bypassed setpoints for SR 3.3.1.1.17
APRM Simulated Thermal Power (Pb) 24.6 %
Recirculation Drive Flow (Wb) < 60 %
(Reference 7.2, Section 15.2)
(Reference 7.1, Table 3-2, Item 8.9)
Columbia Generating Station Page 14 COLR-01, Revision 27
6.0 Rod Block Monitor Instrumentation for Technical Specification 3.3.2.1
6.1 Rod Block Monitor Instrumentation for Technical Specification Table 3.3.2.1-1, Footnote (f) and Licensee Controlled Specifications Table 1.3.2.1-2 and Appendix A. See Technical Specification 3.3.2.1 and the applicable Bases for further application details.
LIMITING ALLOWABLE FUNCTION TRIP VALUE SETPOINT
1 Rod Block Monitor
- a. Low Power Range - Upscale 118.2 118.6
- b. Intermediate Power Range - 113.2 113.6 Upscale
- c. High Power Range - 108.2 108.6 Upscale (Reference 7.1, Table 3-2, Item 10.7)
6.2 Rod Block Monitor (RBM) Instrumentation MCPR limits for Technical Specification Table 3.3.2.1-1, Footnotes (a), (b) and (c). See Technical Specification 3.3.2.1 and the applicable Bases for further application details.
< 90 % RTP 1.72 90 % RTP 1.41 (Reference 7.2, Section 10)
Columbia Generating Station Page 15 COLR-01, Revision 27
7.0 References
7.1 Design Specification for Division 60, Reactor Core and System Analysis Parameters for Columbia Generating Station.
7.2 006N9157, Revision 0, Supplemental Reload Licensing Report for Columbia Reload 26 Cycle 27, February 2023.
7.3 006N9158, Revision 0, Fuel Bundle Information Report for Columbia Reload 26 Cycle 27, November 2022.
7.4 NEDE-32906P-A, Revision 3, TRACG Application for Anticipated Operational Occurrences (AOO) Transient Analyses, GE Nuclear Energy, September 2006.
7.5 006N9160, Revision 0, Nuclear Design Report for Columbia Cycle 27, October 2022.
7.6 002N3439, Revision 4, GNF2 Fuel Design Cycle-Independent Analyses for Energy Northwest Columbia Generating Station, February 2019.
7.7 NEDC-33270P, Revision 11, GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II), August 2020.
7.8 005N2925, Revision 1, Columbia Generating Station Option B Scram Speed Implementation, March 2020.
7.9 Letter, R. L. Tedesco (NRC) to G. G. Sherwood (GE), Acceptance for Referencing General Electric Licensing Topical Report NEDO-24154, February 4, 1981, Item 2 of the Supplemental Safety Evaluation, page cxvi.
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