ML15240A101
| ML15240A101 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 08/24/2015 |
| From: | Ballinger P, Covington L, Custer J, Dia K, VanderPlas R Nebraska Public Power District (NPPD) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML15240A097 | List: |
| References | |
| NLS2015082 | |
| Download: ML15240A101 (26) | |
Text
NLS2015082 Enclosure 5 Page 1 of 26 COOPER NUCLEAR STATION CORE OPERATING LIMITS REPORT CYCLE 29, REVISION 0 PROPOSED MARKUP OF COLR TO REFLECT REFERENCE TO TECHNICAL SPECIFICATIONS NON-PROPRIETARY (REPLACEMENT FOR NLS2015016, ATTACHMENT
- 2)
CNS Cycle 29 COLR Revision 0 COOPER NUCLEAR STATION CORE OPERATING LIMITS REPORT Cycle 29 Revision 0 Print Sign Date Lorne Covington Preparer and Ryan VanderPlas Reviewer Paul Ballinger Reactor and Fuels Engineering Jeremy Custer Supervisor Approved by Khalil Dia 1 of 25 CNS Cycle 29 COLR Revision 0 REVISION HISTORY Revision 0 Date 9/10/14 Description Original issue 2 of 25 CNS Cycle 29 COLR Revision 0 TABLE OF CONTENTS 1. INTRODUCTION
..........................................................................
4 2. AVERAGE PLANAR LINEAR HEAT GENERATION RATE ...........................
6 2.1 Technical Specification Reference
..................................................
6 2.2 Two Recirculation Loop Operation
..................................................
6 2.3 Single Recirculation Loop Operation................................................
7 Table 2-1 : MAPLHGRsTD Values............................................................
8 Table 2-2: Power Dependent LHGRFACp Multiplier
......................................
9 Table 2-3: Flow Dependent LHGRFACf Multiplier
.......................................
10 3. MINIMUM CRITICAL POWER RATIO .................................................
11 3.1 Technical Specification Reference........
.........................................
11 3.2 Two Recirculation Loop Operation.................................................
11 3.3 Application of Scram Time Surveillance Data to OLMCPR(100)................
12 3.4 Single Recirculation Loop Operation
.................................................
13 3.5 Use of Full Arc Turbine Control Valve................................................
14 Table 3-1: OLMCPR Values for OLMCPR(1 00) Calculation
............................
15 Table 3-2: Power Dependent Kp and MCPRp............................................
16 Table 3-3: Flow Dependent MCPRf .......................................................
17 4. TURBINE BYPASS SYSTEM RESPONSE TIME ...................................
18 4.1 Technical Specification Reference.................................................
18 4.2 System Response Time ............................................................
18 5. ROD BLOCK MONITOR TRIP SETPOINTS...........................................
18 5.1 Technical Specification Reference.................................................
18 5.2 Trip Setpoints........................................................................
18 Table 5-1: Rod Block Monitor Channel Settings .........................................
19 6. MAXIMUM LINEAR HEAT GENERATION RATE .....................................
20 6.1 Technical Requircments Manua!S~pec~ification Reference........................
20 6.2 Two Recirculation Loop Operation.................................................
20 6.3 Single Recirculation Loop Operation
..............................................
21 Table 6-1 : Bounding LHGRsTD Values By Fuel Bundle Type ...........................
22 7. STABILITY POWER/FLOW MAP .......................................................
23 7.1 Technical Specification Reference.................................................
23 7.2 Stability Exclusion Region..........................................................
23 Figure 7-1: Stability Exclusion Region Map ..............................................
25 8. REFERENCES............................................................................
26 3 of 25 CNS Cycle 29 COLR Revision 0 1. INTRODUCTION The Core Operating Limits Report (COLR) provides the limits for operation of the Cooper Nuclear Station for Cycle 29 at a rated power of 2419 MwTH. Cooper Nuclear Station Technical Specification 5.6.5(a) requires the COLR to contain the following limits:* The Average Planar Linear Heat Generation Rate for Specification 3.2.1, and 3.7.7 o The Minimum Critical Power Ratio for Specifications 3.2.2 and 3.7.7,* The Linear Heat Generation Rates for Specifications 3.2.3 and 3.7.7* The three Rod Block Monitor Upscale Allowable Values for Specification 3.3.2.1,* The power/flow map defining the Stability Exclusion Region for Specification 3.4.1.In addition, the following information is required to be in the COLR:* Turbine Bypass System response time for Surveillance Requirement 3.7.7.3, The analytical methods used to determine the core operating limits are those previously reviewed and approved by the NRC as required by Technical Specification 56.5(b). These methods are:* NEDE-2401 1-P-A-i19-US, "General Electric Standard Application for Reactor Fuel", May 2012 (Reference 1),*NEDE-23785-1-P-A, 'The GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of-Coolant Accident", Volume Ill, Revision 1, October 1984 (Reference 2),*NEDO-31 960-A and NEDO-31 960-A Supplement 1, "BWR Owner's Group Long-Term Stability Solutions Licensing Methodology", November 1995 (Reference 3).4 of 25 CNS Cycle 29 COLR Revision 0 2. AVERAGE PLANAR LINEAR HEAT GENERATION RATE 2.1 Technical Specification Reference Technical Specifications 3.2.1 and 3.7.7.2.2 Two Recirculation Loop Operation During steady-state power operation, the maximum Average Planar Linear Heat Generation Rate (MAPLHGR), as a function of fuel bundle type, axial location, and average planar exposure, shall not exceed the applicable limiting value.The maximum allowable Average Planar Linear Heat Generation Rate with two recirculation loops in operation is defined as follows: MAPLHGR Limit = minimum [MAPLHGR(P), MAPLHGR(F)]
where, MAPLHGR(P)
= MAPLHGRsTD
- ' LHGRFACp, MAPLHGR(F)
= MAPLHGRsTD
- LHGRFACf, MAPLHGRsTD
= Fuel bundle type and exposure dependent MAPLHGR values for rated core power and flow conditions represented by the values shown in Table 2-1, LHGRFACp = Core power dependent multiplier shown in Table 2-2, LHGRFACf = Core flow rate dependent multiplier shown in Table 2-3.The MAPLHGRsTD values presented in Table 2-1 are the most limiting values for each fuel bundle type from the exposure dependent values defined in Section 16 of Reference
- 6. The core monitoring computer will be used to verify the MAPLHGR limits for each fuel bundle type are not violated.The LHGRFACp and LHGRFACf multipliers presented in Table 2-2 and Table 2-3, respectively, are defined in References 5, 6, and 14.LHGRFACp and LHGRFACf multipliers are applied to MAPLHGR.No thermal limits monitoring is required below 25% of rated power. Therefore, the MAPLHGR limit defined above is only applicable for core conditions at or above 25% of rated power.5 of 25 CNS Cycle 29 COLR Revision 0 2.3 Single Recirculation Loop Operation The maximum allowable Average Planar Linear Heat Generation Rate with one recirculation loop in operation (SLO) is defined as follows: MAPLHGR Limit = minimum [MAPLHGR(P), MAPLHGR(F), MAPLHGR(SLO)]
= MAPLHGRsTD
= Single loop operation MAPLHGR multiplier, and MAPLHGR(P) and MAPLHGR(F) are as defined in Section 2.2 above.As shown above, it is not necessary to apply both the off-rated (LHGRFACp and LHGRFACf) and SLO multiplier corrections at the same time.The single loop operation MAPLHGR multiplier for each fuel bundle type are defined in Section 16 of Reference 6 as shown in the table below.SLO MAPLHGR Fuel Bundle Type Multiplier I All bundles 0.87 6 of 25 CNS Cycle 29 COLR Revision 0 Table 2-1" MAPLHGRsTD Values Average MAPLHGRsTD Values for all GE14C Planarbude Exposurebude (GWd/MT) (kW/ft)0.00 12.82 21.10 12.82 63.50 8.00 70.00 5.00 GNF Bundle # GNF Fuel Bundle Identification EDB-2801 GE1 4-P10ODNAB393-1 7GZ-100OT-1 50-T6-2801 (GE1 40)EDB-3033 GEl14-P10ODNAB383-2G6.0/1 2G5.0-100aT-1 50-T6-3033 (GE140)EDB-31 87 GEl14-P10ODNAB381
-1 5GZ-100OT-1 50-T6-31 87 (GE14C)Average MAPLHGRsTD Values for all GNF2 Planar bundles Exposure (GWd/MT) (kW/ft)0.00 12.45 29.40 12.45 67.00 7.50 70.00 6.69 GNF Bundle # GNF Fuel Bundle Identification EDB-41 15 GNF2-P1 0DG2B390-1 4GZ-1 00T2-1 50-T6-41 15 (GNF2)EDB-41 16 GNF2-P1 0DG2B389-1 2GZ-1 00T2-1 50-T6-41 16 (GNF2)EDB-4276 GNF2-P1 0DG2B391 -1 4GZ-1 00T2-1 50-T6-4276 (GNF2)EDB-4277 GNF2-P1 0DG2B390-2G7.0I1 0G6.0-1 00T2-1 50-T6-4277 (GNF2)7 of 25 CNS Cycle 29 COLR Revision 0 Table 2-2: Power Dependent LHGRFACp Multiplier*
Equipment In Service and Turbine Bypass Valve Out-of-Service (1 Valve 005)Limits for Power < 30.0%Power %) Limit for Flow >50.0% Limit for Flow -<50.0%25.0 .4050.505 30.0 .4220.530 Limits for Power >30.0%Power (%) Limit 30.0 0.634 100.0 1.000 Values are based on Turbine Bypass Value Out-of-Service and are conservative to the Equipment in Service values.8 of 25 CNS Cycle 29 COLR Revision 0 Table 2-3: Flow Dependent LHGRFACf Multiplier Equipment in Service and Turbine Bypass Valve Out-of-Service (1 Valve OOS)Limits for a Maximum Runout Flow of 107.0%Flow(%) Limit 32.5 0.677 90.0 1.000 107.0 1.000 Limits for a Maximum Runout Flow of 102.5%Flow(%) Limit 32.5 0.706 80.0 1.000 102.5 1.000 Limits for a Maximum Runout Flow of 112.0%Flow(%) Limit 32.5 0.642 90.0 1.000 112.0 1.000 Limits for a Maximum Runout Flow of 117.0%Flow(%) Limit 32.5 0.606 90.0 1.000 117.0 1.000 9 of 25 CNS Cycle 29 COLR Revision 0 3. MINIMUM CRITICAL POWER RATIO 3ol Technical Specification Reference Technical Specifications 3.2.2 and 3.7.7.3.2 Two Recirculation Loop Operation During steady-state power operation, the minimum Critical Power Ratio (MCPR)shall be greater than or equal to the Operating Limit MCPR (OLMCPR) defined as a function of cycle exposure and plant conditions.
The Operating Limit MCPR with two recirculation loops in operation is defined as follows: OLMCPR = maximum [MCPRp, MCPRf]where, MCPRp = Core power dependent MCPR shown in Table 3-2, MCPRf = Core flow rate dependent MCPR shown in Table 3-3.The MCPRp and MCPRf values presented in Table 3-2 and Table 3-3, respectively, are defined in References 5, 6, and 14.As shown in Reference 4, the MCPRp value is calculated as follows: For P > P(Bypass), MCPRp = OLMCPR(100)
- K For P < P(Bypass), MCPRp = MCPRp as a function of core flow where, P(Bypass)
= P(Bypass) is the core power level below which the Turbine Stop Valve closure and Turbine Control Valve fast closure scrams are assumed to be bypassed.P(Bypass) is currently set at 30% of rated power.OLMCPR(100)
= OLMCPR for rated core power and flow conditions.
OLMCPR(1 00) is defined as a function of scram time surveillance data as defined in Section 3.3.Kp= Core power dependent OLMCPR multiplier.
No thermal limits monitoring is required below 25% of rated power. Therefore, the OLMCPR limit defined above is only applicable for core conditions at or above 25% of rated power.10 of 25 CNS Cycle 29 COLR Revision 0 3.3 Application of Scram Time Surveillance Data to OLMCPR(1 00)The OLMCPR(100) value applicable to the MCPRp calculation presented in Section 3.2 is determined based on scram time surveillance data recorded for the current operating cycle and the following methodology defined in Reference 7, Reference 11, and Reference 12.3.3.1 Mean Scram Time (tav)The mean scram time for control rod insertion to notch 36 is calculated as follows: n i=l where, i = Scram time test sequential identification number, n = Number of scram time tests performed to date in the cycle (including beginning of cycle), Ni= Number of control rods measured in test i, S= Average insertion time to notch 36 measured in test i.3.3.2 20% Insertion Conformance Limit Scram Time (tB)The 20% insertion conformance limit scram time is calculated as follows: where, dU= Mean of the distribution for average scram time insertion to position 36 used in the ODYN Option B analysis,= Standard deviation of the distribution for average scram time insertion to position 36 used in the ODYN Option B analysis, N] = Total number of control rods measured during the first surveillance test performed at beginning of cycle.11 of 25 CNS Cycle 29 COLR Revision 0 The values for p., a and N 1 are given below.p. = 0.830 a = 0.019 N 1 = 137 Using the values given above, Reference 7 defines the 20% insertion conformance limit scram time as, r 1 1=O0.830+O0.367 r~1'3.3.3 Scram Time Quality Factor (1;)The scram time quality factor is calculated as follows: lft1ave <-tIB, 1t---0.If >t1B, T"--Zave -- rB T'A --B where, TrA = Technical Specification limit for 20% insertion (notch 36)= 1.08 seconds (Technical Specification Table 3.1.4-1).3.3.4 Calculation of OLMCPR(100)
The OLMCPR for rated power and core flow conditions is calculated as follows based on the calculated values for tave, tg, and -r: OLMCPR(1 00) = maximum {OLMCPRB + -;*(LMPA OLMCPRB)Using the following value obtained from Section 15 of Reference 6, OLMCPRs = Is the maximum of either the Stability OLMCPR at Rated Power / Rated Flow = 1.41, or the SLO pump Pump Seizure event at rated conditions
= 1.43 -0.02 = 1.41.and the following values obtained from Section 11 of Reference 6, OLMCPRA = Option A OLMCPR value given in Table 3-1, OLMCPRB = Option B OLMCPR value given in Table 3-1.12 of 25 CNS Cycle 29 COLR Revision 0 3.4 Single Recirculation Loop Operation The Operating Limit MCPR with a single recirculation loop in operation is defined as follows: OLMCPR = maximum [MCPR(SL-P), MCPR(SL-F)]
where, For P > P(Bypass), For P < P(Bypass), For all core flows, MCPR(SL-P)
= [OLMCPR(100)+AOLMCPR(SLO)]
- p MCPR(SL-P)
= MCPRp + AOLMCPR(SLO), MCPR(SL-F)
= MCPRf + AOLMCPR(SLO), AOLMCPR(SLO)
= 0.02 from Section 11 of Reference 6, and OLMCPR(100), MCPRp, and MCPRf are as defined in Section 3.2.The increase in the OLMCPR for single loop operation corresponds to an increase in the safety limit MCPR (SLMCPR) for single loop operation as described in Reference 6.3.5 Use of Full Arc Turbine Control Valve The Operating Limit MCPR when using full arc turbine control valve mode (CNS operating procedures refer to this as single valve mode) is defined as follows: OLMCPR (single valve mode) = OLMCPR + AOLMCPR (single valve mode)where, OLMCPR -OLMCPR as calculated in Section 3.2 for two recirculation loop operation or in Section 3.4 for single loop operation.
AOLMCPR (single valve mode) = 0.01 from Appendix G of Reference 6.13 of 25 CNS Cycle 29 COLR Revision 0 Table 3-1: OLMCPR Values for OLMCPR(1 00) Calculation EqimetStts Applicable Cycle OLMCPRA OLMCPRB Eqipet~ats Exposure Range GNF2 GE14C GNF2 GE14C BOO to InSevie EO-254Gd/T 1.47 1.48 1.37 1.37 Eqipen OR2.0 Gd/T 1.54 1.60 1.44 1.43________________to EOC_ __ _ _ _Turbine Bypass Valve Out of Service BOO to EOC 1.56 1.61 1.46 1.44 (TB VOOS) _______________
NOTES: 1. The range of OLMCPR values are defined as follows: OLMCPRA = Option A OLMCPR from Reference 6 based on Option A analysis using full core scram times defined in Technical Specification Table 3.1.4-1.OLMCPRB = Option B OLMCPR from Reference 6 based on Option B analysis described in Reference 1.2. The OLMCPR values presented above apply to rated power operation based on a two loop operation Safety Limit MCPR (SLMCPR) of 1.11.3. The OLMCPR values presented above bound Increased Core Flow (ICF) operation to 105% of rated flow throughout the cycle.4. Exposure ranges are defined as follows: BOO = Beginning of cycle, EOC =End of cycle, EOR = End of rated power operation at rated core flow and all rods withdrawn.
EOR is projected to be 15.113 GWd/MT in Reference 6 Section 3. The EOR exposure will vary based on actual cycle operations.
- 5. OLMCPRB for GNF2 for equipment in service from BOO to EOR-2.504 GWd/MT is set by the Inadvertent HPCI /L8 transient..
14 of 25 CNS Cycle 29 COLR Revision 0 Table 3-2: Power Dependent Kp and MCPRp*Equipment in Service and Turbine Bypass Valve Out-of-Service (1 Valve 005)Limits for Power <30.0% ____________
____________
Limit for Flow >50.0% Limits for Flow <50.0%Power (%) MCPRp MCPRp 25.0 3.40 2.66 30.0 3.12 2.37 Limits for Power >30.0%Power (%) Limit Kp 30.0 1.481 45.0 1.280 60.0 1.151 85.0 1.082 100.0 1.000 Values are based on Turbine Bypass Value Out-of-Service and are conservative to the Equipment in Service values.15 of 25 CNS Cycle 29 COLR Revision 0 Table 3-3: Flow Dependent MCPRf Equipment in Service and Turbine Bypass Valve Out-of-Service (1 Valve 00S)Limits for a Maximum Runout Flow of 107.0%Limit Flow(%) MCPRf 30.0 1.580 85.7 1.240 107.0 1.240 Limits for a Maximum Runout Flow of 102.5%Flow(%) _________Limit 30.0 1.539 80.0 1.245 102.5 1.245 Limits for a Maximum Runout Flow of 112.0%Flow(%) Limit 30.0 1.625 90.0 1.250 112.0 1.245 Limits for a Maximum Runout Flow of 117.0%Flow(%) Limit 30.0 1.680 90.0 1.287 117.0 1.245 16 of 25 CNS Cycle 29 COLR Revision 0 4. TURBINE BYPASS SYSTEM RESPONSE TIME 4.1 Technical Specification Reference Technical Specification 3.7.7.3.4.2 System Response Time The system response time for the Turbine Bypass System to be at 80% of rated bypass flow is 0.3 seconds. This was obtained from Reference 8.5. ROD BLOCK MONITOR TRIP SETPOINTS 5.1 Technical Specification Reference Technical Specification 3.3.2.1.5.2 Trip Setpoints The allowable values for the power dependent Rod Block Monitor (RBM) upscale trip setpoints are defined in Table 5-1, along with the applicable reactor power ranges associated with each trip setpoint.
The Analytical Limit (AL) and Technical Specification Allowable Value (AV) presented in Table 5-1 were determined in Reference 9 and Reference 4.17 of 25 CNS Cycle 29 COLR Revision 0 Table 5-1: Rod Block Monitor Channel Settings Analytical Allowable Trip Function Limit Value Low Power Setpoint (LPSP) 30.0% 27.5%Intermediate Power Setpoint (IPSP) 65.0% 62.5%High Power Setpoint (HPSP) 85.0% 82.5%Downscale Trip Setpoint (DTSP) 89.0% 92.0%Scaled Cycle Tri Fncton Applicable Core Generic Specific Analytical Allowable TiFucin Power Range MCPR MCPR Limit 3 Value 3______ _____ Lim it 2 Lim it 2_ _ _ _Low Trip Setpoint LPSP-<P < IPSP 1.35 1.32 <123.0 /125 < 120.0 /125 (LTSP)Intermediate Trip IPSP_ P p< HPSP 1.35 1.32 -118.0 /125 <115.01125 Setpoint (ITSP)High Trip Setpoint HPSP- P 1.35 1.32 <113.2 /125 < 110.51125 (HTSP)NOTES: 1. Setpoints are given in units of percent of rated power.2. The RBM trip level settings associated with the MCPR limit, shown in the cycle specific MCPR limit in the above table, were verified in Section 10 of Reference 6 to bound the cycle specific Rod Withdrawal Error (RWE) analysis for an RBM setpoint of 111% of reference level. The scaled generic MCPR limit is based on an adjusted MCPR limit from the generic analysis documented in Reference 4 performed for an Analyzed Trip Level Setting (without RBM filter) of 114.0% of the reference level or an Analyzed Trip Level Setting (with RBM filter) of 113.2% of the reference level.The generic MCPR limit of 1.30 was calculated in Reference 4 for an SLMCPR of 1.07. The scaled generic MCPR limit documented above was calculated by multiplying the generic limit of 1.30 by the ratio of the SLMCPR values (1.11/1.07).
- 3. RBM trip setpoints are given in units of divisions of full scale.18 of 25 CNS Cycle 29 COLR Revision 0 6. MAXIMUM LINEAR HEAT GENERATION RATE 6.1 Technical Rcgu'.",,mcn:ts
........Specification Reference Technical Specifications 3.2.3 and 3.7.7.Technical Requirements ,Manual Spoci'ication T3.2.1.6.2 Two Recirculation Loop Operation During steady-state power operation, the maximum Linear Heat Generation Rate (LHGR) in any fuel rod in any fuel bundle at any axial location shall not exceed the applicable limiting value.The maximum allowable Linear Heat Generation Rate with two recirculation loops in operation is defined as follows: LHGR Limit = minimum [LHGR(P), LHGR(F)]where, LHGR(P) = LHGRsTD
- LHGRFACf, LHGRsTD = Fuel bundle type, fuel rod type, and peak pellet exposure dependent maximum LHGR values for rated core power and flow conditions represented by the values shown in Table 6-1, LHGRFACp = Core power dependent multiplier shown in Table 2-2, LHGRFACf = Core flow rate dependent multiplier shown in Table 2-3.The LHGRsTD values presented in Table 6-1 represent the maximum allowable peak pellet power (LHGR) as a function of pellet exposure for each pin type in each fuel bundle design. The maximum allowable LHGR limit values have the following pin type dependencies; UO 2 only pins which can either be full and partial length fuel rods, Gadolinia rods based on the local and maximum gadolinia concentration in the rod. The values in Table 6-1 were obtained from Reference
- 13. The core monitoring computer will be used to verify the pellet specific LHGR limits for each fuel bundle type are not violated.No thermal limits monitoring is required below 25% of rated power. Therefore, the LHGR limit defined above is only applicable for core conditions at or above 25% of rated power.19 of 25 CNS Cycle 29 COLR Revision 0 6.3 Single Recirculation Loop Operation The maximum allowable Linear Heat Generation Rate with one recirculation loop in operation (SLO) is defined as follows: LHGR Limit = minimum [LHGR(P), LHGR(F), LHGR(SLO)]
= LHGRsTD
= Single loop operation PLHGR multiplier, and LHGR(P) and LHGR(F) are as defined in Section 6.2 above.As shown above, it is not necessary to apply both the off-rated (LHGRFACp and LHGRFACf) and SLO multiplier corrections at the same time.The single loop operation peak LHGR (PLHGR) multipliers for each fuel bundle type are defined in Section 16 of Reference 6 as shown in the table below.I SLO PLHGR Fuel Bundle Type Multiplier All bundles 0.87 20 of 25 CNS Cycle 29 COLR Revision 0 Table 6-1: Bounding LHGRsTD Values By Fuel Bundle Type EDB-2801, EDB-3033, and EDB-3187 LHGRsTD LHGRsTD Peak Pellet (kW/ft) (kW/ft)Expoure UO 2 Only bounding Exposuregad for all (GWd/MT) gad conc to_______ _______ 6% max GNF Proprietary data deleted Bundle Types GFBundle # GNF Fuel Bundle Identification EDB-i~2801 GEl14-PI10DNAB393-1 7GZ-100OT-1 50-T6-2801 (GE14C)EDB-O303 GE1 4-P10ODNAB383-2G6.0/1 2G5.0-100OT-1 50-T6-3033 (GE14C)ED-387GEl14-P10ODNAB381
-1 5GZ-100OT-1 50-T6-31 87 (GE14C)EDB-4115, EDB-4116, EDB-4276, and________EDB-4277_____
LHGRsTD LHGRsTD Peak Pellet (kW/ft) (kW/ft)Expoure U0 2 Only bounding Exposuregad for all (GWdIMT) gad conc to_______ _______7%
max GNF Proprietary data deleted Bundle Types GN unl GNF Fuel Bundle Identification EDB-4115 -GNF2-P1 0DG2B390-1 4GZ-1 00T2-l150-T6-41 15 (GNF2)EDB-4416 G NF2-P1 0DG2B389-1 2GZ-l100T2-l150-T6-41 16 (GNF2)EDB-4276 GNF2-P1 0DG2B391 -1 4GZ-1 OOT2-1 50-T6-4276 (GNF2)EDB-427 GNF2-P1 0DG2B390-2G7.0/1 0G6.O-1 00T2-1 50-T6-4277 (GNF2)21 of 25 CNS Cycle 29 COLR Revision 0 7. STABILITY POWER/FLOW MAP 7.1 Technical Specification Reference Technical Specification 3.4.1.7.2 Stability Exclusion Region The stability region is represented by the Exclusion Region boundaries defined in Section 15 of Reference
- 6. A detailed view of the Exclusion Region of the power/flow map is presented in Figure 7-1.Intentional operation within the Exclusion Region is prohibited.
The Exclusion Region is defined in the table below.Exclusion Region Power (% of CLTPFlw(ofRtd
____________Rated)
Flow__(%_of__Rated)
Highest Flow Control 774.Line Endpoint Natural Circulation 413.LineEndpoint
_____________________
The region boundaries are defined using the modified shape function given in Reference
- 10. The calculation of the region boundaries as a function of core thermal power and core flow rate is summarized below.where, P = a core thermal power value on the region boundary (% of rated), W = the core flow rate corresponding to power, P, on the region boundary (%of rated), PA = core thermal power at the highest flow control line endpoint (% of rated on the highest flow control line), PB -core thermal power at the natural circulation line endpoint (% of rated on the natural circulation line), 22 of 25 CNS Cycle 29 COLR Revision 0 WA = core flow rate at the highest flow control line endpoint (% of rated on the highest flow control line), WB = core flow rate at the natural circulation line endpoint (% of rated on the natural circulation line).23 of 25 CNS Cycle 29 COLR Revision 0 Figure 7-1" Stability Exclusion Region Map 110 .-- -N'atu'ral w irc tion 'Line l. .. .. .......; ....-a- xtedddOperating Domnain 100 .. .. .. .. Exclusion Region ...Boundary_, .,,
0 1 20 3 0 5 0 7 0 9 0 1 2 CoeFiw%924 of.25 CNS Cycle 29 COLR Revision 0 8. REFERENCES The following references are identified in this report: I. NEDE-2401 1-P-A-I19, "General Electric Standard Application for Reactor Fuel", September 2012.2. NEDE-23785-1-P-A, "The GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of-Coolant Accident", Volume Ill, Revision 1, October 1984.3. NEDO-31 960-A and NEDO-31 960-A Supplement 1, "BWR Owner's Group Long-Term Stability Solutions Licensing Methodology", November 1995.4. NEDC-31892P, "Extended Load Line Limit and ARTS Improvement Program Analyses for Cooper Nuclear Station Cycle 14", Revision 1, May 1991.5. NEDC-33270P, "GNF2 Advantage Generic Compliance with NEDE-2401 1-P-A (GESTAR II)", Revision 4, October 2011.6. 001 N0731-R1, 'Supplemental Reload Licensing Report for Cooper Nuclear Station Reload 28 Cycle 29", Revision 0, July 2014.7. CNS Procedure 10.9, "Control Rod Scram Time Evaluation", current revision.8. GE Design Specification 22A2859, "Turbine-Generator and Steam Bypass System", Paragraph 4.3.8, Revision 3.9. NEDC 98-024, "APRM -RBM Setpoint Calculation", current revision.10. NEDE-3321 3P-A, "ODYSY Application for Stability Licensing Calculations Including Option I-D and II Long Term Solutions", April 2009.11. GE Letter DTI:NPPD 81-029, "ODYN Option B Scram Time Surveillance Procedures," March 29, 1981.12. GE Letter DGC:89-190, "Cooper Reload 13 Technical Specification Changes," November 30, 1989.13. 001N0757-R1, "Fuel Bundle Information Report for Cooper Nuclear Station Reload 28 Cycle 29", Revision 0, July 2014.14. NEDC-33763P, "GNF2 Fuel Design Cycle-Independent Analyses for Cooper Nuclear Station", Revision 1, July 2012.25 of 25