ML15240A099
| ML15240A099 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 08/24/2015 |
| From: | Covington L, Custer J, Dia K, Parkyn C Nebraska Public Power District (NPPD) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML15240A097 | List: |
| References | |
| NLS2015082 | |
| Download: ML15240A099 (26) | |
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NLS20 15082 Enclosure 2 Page 1 of 26 COOPER NUCLEAR STATION CORE OPERATING LIMITS REPORT CYCLE 28, REVISION 1 NON-PROPRIETARY Non-Proprietary Information CNS Cycle 28 COLR Revision 1 COOPER NUCLEAR STATION CORE OPERATING LIMITS REPORT Cycle 28 Revision I Print Sign Date Preparer Christine w -s ReiwrLorne , --b Covington
__ _ _Reactor and Fuels Engineering Jeremy Custer / //Supervisor
______SED Manager Khalil Dia -___,_____" Information Notice This is a non-proprietary version of the Cooper Nuclear Station Cycle 28 COLR, which has the proprietary information removed. Portions of the document that have been removed are indicated by white space inside open and closed bracket as shown here [[ ]].1 of 25 Non-Proprietary Information CNS Cycle 28 COLR Revision 1 Revision 0 1 Date 10/09/12 07/29/15 REVISION HISTORY Description Original issue Proprietary information marked, correct MCPRf for 112% runout/112%
flow 2 of 25 Non-Proprietary Information CNS Cycle 28 COLR Revision 1 TABLE OF CONTENTS 1. INTRODUCTION.........................................................................
4 2. AVERAGE PLANAR LINEAR HEAT GENERATION RATE ...........................
5 2.1 Technical Specification Reference
...................................................
5 2.2 Two Recirculation Loop Operation
............................................ 2.3 Single Recirculation Loop Operation
..........................
......................
6 Table 2-1: MAPLHGRSTD Values.............................................
....... ....... 7 Table 2-2: Power Dependent LHGRFACp Multiplier
..............................
........8 Table 2-3: Flow Dependent LHGRFACf Multiplier
........................................
9 3. MINIMUM CRITICAL POWER RATIO ............................................., ...10 3.1 Technical Specification Reference
.........................................
........10 3.2 Two Recirculation Loop Operation
..................................
10 3.3 Application of Scram Time Surveillance Data to OLMCPR(100)
.................
11 3.4 Single Recirculation Loop Operation.................................................
12 3.5 Use of Full Arc Turbine Control Valve................................................
13 Table 3-1: OLMCPR Values for OLMCPR(100)
Calculation..............................
14 Table 3-2: Power Dependent Kp and MCPRp............................................
15 Table 3-3: Flow Dependent MCPRf .......................................................
16 4. TURBINE BYPASS SYSTEM RESPONSE TIME...................................
17 4.1 Technical Specification Reference
................................................
17 4.2 System Response Time................................................
17 5. ROD BLOCK MONITOR TRIP SETPOINTS
...........................................
17 5.1 Technical Specification Reference.................................................
17 5.2 Trip Setpoints
..........................
17 Table 5-1: Rod Block Monitor Channel Settings ..........................................
18 6. MAXIMUM LINEAR HEAT GENERATION RATE ..............................
........19 6.1 Technical Requirements Manual Reference......................................
19 6.2 Two Recirculation Loop Operation
..............................................
- 19. l 6.3 Single Recirculation Loop Operation
..............................................
20 Table 6-1: Bounding LHGRsTD Values By Fuel Bundle Type ............................
21 7. STABILITY POWER/FLOW MAP................,.......................................
22 7.1 Technical Specification Reference
............................................
,.....22 7.2 Stability Exclusion Region ............................................
.............
22 Figure 7-1: Stability Exclusion Region Map...............................................
24 8. REFERENCES
............................................................
..............
25 3 of 25 Non-Proprietary Information CNS Cycle 28 COLR Revision I 1. INTRODUCTION The Core Operating Limits Report (COLR) provides the limits for operation of the Cooper Nuclear Station for Cycle 28 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,* The Minimum Critical Power Ratio for Specifications 3.2.2 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,* Maximum allowable Linear Heat Generation Rate (LHGR) for Technical Requirements Manual Specification T3.2. 1.The analytical methods used to determine the core operating limits are those previously reviewed and approved by the NRC as required by Technical Specification 5.6.5(b).
These methods are:* NEDE-2401 1-P-A-19, "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-31960-A and NEDO-31960-A Supplement 1, "BWR Owner's Group Long-Term Stability Solutions Licensing Methodology", November 1995 (Reference 3).4 of 25 Non-Proprietary Information CNS Cycle 28 COLR Revision 1 2. AVERAGE PLANAR LINEAR HEAT GENERATION RATE 2.1 Technical Specification Reference Technical Specification 3.2.1.2.2 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 MAPLHGRsTO 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 Non-Proprietary Information CNS Cycle 28 COLR Revision 1 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)J where, 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.Fuel Bundle Typej S Multiplier I All bundles 0.87 6 of 25 Non-Proprietary Information CNS Cycle 28 COLR Revision 1 Table 2-1: MAPLHGRsTD Values Average MAPLHGRsTD Values for all GE140 Planarbude Exposurebude (GWdIMT) (kWlft)0.00 12.82 21.10 12.82 63.50 8.00 70.00 5.00 GNF Bundle # GNF Fuel Bundle Identification EDB-2801 GE14-P1 00NAB393-1 7GZ-1 00T-150-16-2801 (GE14C)EDB-3032 GE1 4-P1 0DNAB383-2G6.0/1 0G5.0-100OT-1 50-T6-3032 (GE1 4C)EDB-3033 GE1 4-P1 0DNAB383-2G6.0/1 2G5.0-100OT-1 50-T6-3033 (GE1 4C)EDB-31 87 GEl 4-P10ODNAB381-1 5GZ-1 00-1--150-T16-31 87 (GEl14C)EDB-31 88 GEl14-PI10DNAB377-1 3GZ-100OT-1 50-T6-31 88 (GEl14C)Average MAPLHGRsTD Values for all GNF2 Planarbude Exposurebude (GWdlMT) (kWlft)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-P10DG2B390-14GZ-100T2-150-T6-41 15 (GNF2)EDB-41 16 GNF2-P10DG2B389-12GZ-100T2-150-T6-41 16 (GNF2)7 of 25 Non-Proprietary Information CNS Cycle 28 COLR Revision 1 Table 2-2: Power Dependent M-HGRFACp Multiplier Equipment In Service and Turbine Bypass Valve Out-of-Service (1 Valve 00S)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 O .634 100.0 1.000 8 of 25 Non-Proprietary Information CNS Cycle 28 COLR Revision 1 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 Non-Proprietary Information CNS Cycle 28 COLR Revision 1 3. MINIMUM CRITICAL POWER RATIO 3.1 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(100) 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 Non-Proprietary Information CNS Cycle 28 COLR Revision 1 3.3 Application of Scram Time Surveillance Data to OLMCPR(100)
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 (tve)The mean scram time for control rod insertion to notch 36 is calculated as follows:=14 i=1 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 (tn The 20% insertion conformance limit scram time is calculated as follows: WN where, S= 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 1 -- Total number of control rods measured during the first surveillance test performed at beginning of cycle.11 of 25 Non-Proprietary Information CNS Cycle 28 COLR Revision 1 The values for jt, a and N 1 are given below.= 0.830 a = 0.019 N 1 = 137 Using the values given above, Reference 7 defines the 20% insertion conformance limit scram time as, z~a=O.830+O0.36"7 1 , 3.3.3 Scram Time Quality Factor (r)The scram time quality factor is calculated as follows: lf rave -Z, r =0.If "tave> TB, T" -- ave -- B where, TA = 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, mB, and t:{OMPB+ OLMCPRs OLMCPR(100)
= maximum OLCR * (OLMCPRA _ OLMCPRB)Using the following value obtained from Section 15 of Reference 6, OLMCPRs = Stability OLMCPR at Rated Power / Rated Flow = 1.45, 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 Non-Proprietary Information CNS Cycle 28 COLR Revision 1 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)]
- K 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 Non-Proprietary Information CNS Cycle 28 COLR Revision 1 Table 3-1: OLMCPR Values for OLMCPR(100)
Calculation Applicable Cycle OLMCPRA OLMCPR 8 Equipment Status Exposure Range GNF2 GE140 GNF2 GEI4C BOC to InSevce ER-.87Gd/T 1.46 1.47 1.36 1.36 Eqipen OR3.8 Gd/T 1.53 1.58 1.43 1.41________ ________to EOC__ _ _ _ __ _ __ _ _ _Turbine Bypass Valve Out of Service BOC to EOC 1.54 1.60 1.44 1.43 (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.Option B OLMCPR from Reference 6 based on Option B analysis described in Reference 1.OLMCPRB =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: BOC = 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 15.114 GWd/MT in Reference 6 Section 3. The EOR exposure will vary based on actual cycle operations.
14 of 25 Non-Proprietary Information CNS Cycle 28 COLR Revision 1 Table 3-2: Power Dependent Kp and MCPRp Equipment in Service and Turbine Bypass Valve Out-of-Service (1 Valve OOS)Limits for Power <30.0%Limit for Flow >50.0% Limits for Flow <50.0%Poe ()MCPRp MCPRp 25.0 j3.40 2.66 30.0 J3.12 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 15 of 25 Non-Proprietary Information CNS Cycle 28 COLR Revision 1 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%Flow%) ILimit 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 it1.245 102.5 11.245 Limits for a Maximum Runout Flow of 112.0%Flow(%)_________________Limit 30.0 1.625 90.0 _ __ _ __ _ __ _ __ _ _1.250 112.01.245 Limits for a Maximum Runout Flow of 117.0%Flow__________%_________
Limit 30.0 _______________1.680 90.0 1.286 117.0 1.245 16 of 25 Non-Proprietary Information CNS Cycle 28 COLR Revision 1 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 Non-Proprietary Information CNS Cycle 28 COLR Revision 1 Table 5-1: Rod Block Monitor Channel Settings Analytical Allowable Trip Function Limit Value 1 Low Power Setpoint (LPSP) 30.0% 27.5%Intermediate Power Setpoint (IPSP) 65.0% 62.5%High Power Setpoint (HPSP) F85.0% 82.5%Downscale Trip Setpoint (DTSP) 89.0% 92.0%Scaled Cycle Applicable Core Generic Specific Analytical Allowable Trip Function Power Range MCPR MCPR Limit 3 Value 3 Limit 2 Limit 2 ______Low Trip Setpoint LPSP<P < IPSP 1.30 1.30 -<123.0 /125 _<120.01/125 (LTSP)Intermediate Trip iPSPP<p<HPSP 1.30 1.30 <118.0/125
_<115.01125 Setpoint (ITSP)High Trip Setpoint HPSP < P 1.30 1.30 -<113.2/125
_<110.5/125 (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 1.25 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 1.25 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 Non-Proprietary Information CNS Cycle 28 COLR Revision 1 6. MAXIMUM LINEAR HEAT GENERATION RATE 6.1 Technical Requirements Manual Reference Technical Requirements Manual Specification 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 Non-Proprietary Information CNS Cycle 28 COLR Revision I 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.SLO PLHGR Fuel Bundle Type Multiplier All bundles 0.87 20 of 25 Non-Proprietary Information CNS Cycle 28 COLR Revision 1 Table 6-1: Bounding LHGRsTD Values By Fuel Bundle Type EDB-2801, EDB-3032, EDB-3033, EDB-3187.
and EDB-3i88 LHGRsTo LHGRsTD Peak Pellet (kWlft) (kW/ft)Exposure UO 2 Only bounding gad for all (GWd/MT) gad conc to 6% max 0.00 13.40 -12.26 13.53 -12.26 16.00 13.40 -_____--60.63 -7.32 63.50 .8.00 --67.07 -4.57 70.00 5.00...._____Bundle Types GNF Bundle # GNF Fuel Bundle Identification-EDB-2801 G E 14-P10ODNAB393-1 7GZ-100OT-1 50-T6-2801 (GEl140)EDB-3032 GEl14-Pi10DNAB383-2G6.0/1 0G5.0-100OT-i150-T6-3032 (GE1 40)EDB-3033 GE 14-P10ODNAB383-2G6.0/1 2G5.0-100OT-i150-T6-3033 (GE14C)EDB-3187 GE1 4-P10ODNAB381-15GZ-100OT-1 50-T6-31 87 (GE1 4C)EDP-31 88 GE14-P1 0DNA8377-1 3GZ-10GOT-I150-T6-31 88 (,GE1 40)EDB-4115 and EDB-4116 LHGRsTD LHGRsTD Peak Pellet (kW/ft) (kW/ft)Expoure UO 2 Only bounding Exposuregad for all (GWd/MT) gad conc to________7%
max Bundle Types GNF Budle # GNF Fuel Bundle IdentifiCation EDB-4115 G NF2-P I10DG2B39G-14GZ-100GT2-!
50-T6-41 15 (GNF2)ED-4j116 [GNF2-P1 00G2B389-12GZ-100GT2-1 50-T6-41 16 (GNF2)21 of 25 Non-Proprietary Information CNS Cycle 28 COLR Revision 1 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 Excfusion 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 CLTPFlwofRtd
___________Rated)
Flow__(_____Rated)
Highest Flow Control 714.Line Endpoint _____________________
Natural Circulation 363.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 Non-Proprietary Information CNS Cycle 28 COLR Revision 1 WA = core flOW rate at the highest flow control line endpoint (% of rated on the highest flow control fine), Wa= core flow rate at the natural circulation line endpoint (% of rated on the natural circulation line).23 of 25 Non-Proprietary Information CNS Cycle 28 COLR Revision 1 Figure 7-1: Stability Exclusion Region Map 110 100 90 80 P- 40+20 10 Naturai' Circulaio F.xtended Operating Domnain.XduSfIorI Region Boundary~u~rRegon Bondary A 70 80 90 100 110 120)w(%}1 .9 0 10 20 30 40 50 60 Core Flo 24 of 25 Non-Proprietary Information CNS Cycle 28 COLR Revision I 8. REFERENCES The following references are identified in this report: 1. NEDE-2401 1-P-A-19, "General Electric Standard Application for Reactor Fuel", May 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. 0000-0140-2587-SRLR, "Supplemental Reload Licensing Report for Cooper Nuclear Station Reload 27 Cycle 28", Revision 1, August 2012.7. 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-0 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:89-1 90, "Cooper Reload 13 Technical Specification Changes," November 30, 1989.13. 0000-0140-2587-FBIR, "Fuel Bundle Information Report for Cooper Nuclear Station Reload 27 Cycle 28", Revision 0, July 2012.14. NEDC-33763P, "GNF2 Fuel Design Cycle-Independent Analyses for Cooper Nuclear Station", Revision 1, July 2012.25 of 25