NLS2006090, Core Operating Limits Report, Cycle 24, Revision 0
| ML063130050 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 11/05/2006 |
| From: | Fleming P Nebraska Public Power District (NPPD) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NLS2006090 | |
| Download: ML063130050 (35) | |
Text
H Nebraska Public Power District Always there when you need us NLS2006090 November 5, 2006 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001
Subject:
Core Operating Limits Report, Cycle 24, Revision 0 Cooper Nuclear Station, Docket No. 50-298, DPR-46 The purpose of this letter is to provide to the Nuclear Regulatory Commission (NRC) the Core Operating Limits Report (COLR) for Cooper Nuclear Station (CNS) for Cycle 24. CNS Technical Specification 5.6.5.d requires that the COLR, including any midcycle revisions or supplements, be provided to the NRC upon issuance for each reload cycle. The COLR for CNS Cycle 24 contains no proprietary information.
In accordance with 10 CFR 50.4(b)(1), we are also transmitting a copy of this COLR to the Regional Office and to the NRC Senior Resident Inspector.
Should you have any questions regarding this matter, please contact Mr. Paul Fleming at (402) 825-2774.
Sincerely,
/lb Enclosure cc: Regional Administrator w/enclosure NPG Distribution w/o enclosure USNRC - Region IV Cooper Project Manager w/enclosure CNS Records w/enclosure USNRC - NRR Project Directorate IV-I Senior Resident Inspector w/enclosure USNRC - CNS COOPER NUCLEAR STATION P.O. Box 98 / Brownville, NE 68321-0098 Telephone: (402) 825-3811 / Fax: (402) 825-5211 www.nppd.com kc~
NLS2006090 Enclosure ENCLOSURE CORE OPERATING LIMITS REPORT CYCLE 24, REVISION 0 COOPER NUCLEAR STATION DOCKET No. 50-298, DPR-46
L CNS Cycle 24 COLR Revision 0 COOPER NUCLEAR STATION CORE OPERATING LIMITS REPORT Cycle 24 Revision 0 Print Sign Date Preparer Covington Lorne j **t0?*0 Christine Reviewer Parkyn IO125]-ky Fuels and Reactor George Griffith Engineering Manager 1 of 32
CNS Cycle 24 COLR Revision 0 REVISION HISTORY Revision Date Description 0 25Oct06 Original issue 2 of 32
CNS Cycle 24 COLR Revision 0 TABLE OF CONTENTS Section Page
1.0 INTRODUCTION
5 2.0 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 3.0 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 4.0 TURBINE BYPASS SYSTEM RESPONSE TIME ......................... 18 4.1 Technical Specification Reference .................... ........................ 18 4.2 System Response Time ............................................. 18 5.0 ROD BLOCK MONITOR TRIP SETPOINTS .................................. 18 5.1 Technical Specification Reference ............................................. 18 5.2 Trip S etpoints ............................................. 18 6.0 MAXIMUM LINEAR HEAT GENERATION RATE ......................... 20 6.1 Technical Requirements Manual Reference ................................. 20
.6.2 Two Recirculation Loop Operation ............................................. 20 6.3 Single Recirculation Loop Operation ........................ 21 7.0 STABILITY POWER/FLOW MAP ............................................ 29 7.1 Technical Specification Reference ............................................. 29 7.2 Stability Exclusion Region ........................................... 29
8.0 REFERENCES
...................................... 32 3 of 32
CNS Cycle 24 COLR Revision 0 LIST OF TABLES Table Page 2-1 MAPLHGRSTD Values By Fuel Bundle Type ............................. 8 3-1 OLMCPR Values for OLMCPR(100) Calculation ........................ 15 5-1 Rod Block Monitor Channel Settings .......................................... 19 6-1 LHGRSTD Values By Fuel Bundle Type ....................................... 22 LIST OF FIGURES Figure Page 2-1 Power Dependent MAPFAC(P) and LHGRFAC(P) Multiplier ..... 9 2-2 Flow Dependent MAPFAC(F) and LHGRFAC(F) Multiplier ........ 10 3-1 Power Dependent K(P) and MCPR(P) for GE14 Fuel with Safety Lim it = 1.12 .......................................... 16 3-2 Flow Dependent MCPR(F) for GE14 Fuel with Safety Lim it = 1.12 .......................................... 17 7-1 Stability Exclusion Region Map .......................................... 31 4 of 32
CNS Cycle 24 COLR Revision 0 INTRODUCTION The Core Operating Limits Report (COLR) provides the limits for operation of the Cooper Nuclear Station for Cycle 24. 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-24011-P-A-15, "General Electric Standard Application for Reactor Fuel", September 2005 (Reference 1),
- NEDE-23785-1-P-A, "The GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of-Coolant Accident", Volume III, 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).
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- 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
- MAPFAC(P),
MAPLHGR(F) = MAPLHGRSTD
- MAPFAC(F),
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, MAPFAC(P) = Core power dependent multiplier shown in Figure 2-1, MAPFAC(F) = Core flow rate dependent multiplier shown in Figure 2-2.
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 Reference
- 6. The values in Table 2-1 are intended only for use in hand calculations as described in Technical Specification 3.2.1. The actual MAPLHGRSTD values defined in Reference 6 are utilized in the process computer. The process computer will be used to verify the MAPLHGR limits for each fuel bundle type are not violated.
The MAPFAC(P) and MAPFAC(F) multipliers presented in Figure 2-1 and Figure 2-2, respectively, are defined in Reference 5.
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CNS Cycle 24 COLR Revision 0 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.
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)]
where, MAPLHGR(SLO) = MAPLHGRSTD
- MAPFAC(SLO),
MAPFAC(SLO) = 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 (MAPFAC(P) and MAPFAC(F)) and SLO multiplier corrections at the same time.
The single loop operation MAPLHGR multiplier for each fuel bundle type are defined in Reference 6 as shown in the table below.
Fuel Bundle Type MAPLHGR SLOMultiplier All GE14B bundles 0.87 All GE14C bundles 0.87 7 of 32
CNS Cycle 24 COLR Revision 0 Table 2-1 MAPLHGRSTD Values By Fuel Bundle Type Average Planar MAPLHGRsTD Values (in kWIft) by GNF Fuel Bundle Design Number Exposure (GWdIMT) EDB- EDB- EDB- EDB- EDB- EDB- EDB- EDB-3881 2476 2611 2569 2800 2801 2901 2902 0.00 12.82 12.82 12.82 12.82 12.82 12.82 12.82 12.82 21.10 12.82 12.82 12.82 12.82 12.82 12.82 12.82 12.82 63.50 8.00 8.00 8.00 8.00 8.00 8.00 8.00 8.00 70.00 5.00 5.00 5.00 5.00 5.00 5.00 5.00 5.00 GNF Bundle # GNF Fuel Bundle Identification EDB-3881 GE14-P1OHNAB385-14GZ-10OT-148-T6-3881 (GE14B)
EDB-2476 GE 14-P1OHNAB379-17GZ-10OT-150-T6-2476 (GE14C)
EDB-2611 GE 14-P1ODNAB393-17GZ-10OT-150-T6-2611 (GE14C)
EDB-2569 GE14-P1ODNAB398-16GZ-100T-150-T6-2569 (GE14C)
EDB-2800 GE 14-P1ODNAB395-14GZ-10OT-150-T6-2800 (GE14C)
EDB-2801 GE14-P1ODNAB393-17GZ-1OOT-150-T6-2801 (GE14C)
EDB-2901 GE14-P1ODNAB385-13GZ-10OT-150-T6-2901 (GE14C)
EDB-2902 G E14-P1ODNAB386-14GZ-1OOT-150-T6-2902 (GE14C) 8 of 32
CNS Cycle 24 COLR Revision 0 Figure 2-1 Power Dependent MAPFAC(P) and LHGRFAC(P) Multiplier 1.00
- I
- I 0.90 -F-- _
- I
- I 0.80 ~~~~1~~~~
- I
- I
- I 0.70 r
7MAPLHGR(p) = MAPFAC(p)
- MAPLHGRstd MAPLHGRstd = Standard MAPLHGR Umits For P.< 25%: No Thermal Limits Monitor Required:
LL 0.60 No Limits Specified.
For 25% < P < 30%
MAPFAC(p) = 0.53 + 0.005-(P-30%) for flow < 50%
MAPFAC(p) = 0.49 + 0.005*(P-30%) for flow > 50%
______ ______ I For P > 30%
0.50 MAPFAC(p) = 1.0 + 0.005224,(P-100%)
J Flow < 50%
u.4u 7 _
I Flow > 50%
0.30- -
0.20 0 10 20 30 40 50 60 70 80 90 100 Power (% Rated) 9 of 32
CNS Cycle 24 COLR Revision 0 Figure 2-2 Flow Dependent MAPFAC(F) and LHGRFAC(F) Multiplier 1.1 1.0 0.9 0.8 MAPLHGRQ) MAPFAC(t) MAPLHGRstd U- MAPLHGRstd = Standard MAPLHGR Limits 4 0.7 For Two Loop Operation LL MAPFAC(Q) - The Minimum of either 0~
4 1. Oor{Af* (Nc/100) + Bf}
Wc = % Rated Core Flow Af and Bf are fuel dependent constants given 0.6 below for GE Fuels through GE14:
Ma~dmum Core Flow
(%Rated) Af Bf 102.5 0.6784 0.4861 0.5 107.0 0.6758 0.4574 112.0 0.6807 0.4214 117.0 0.6886 0.3828 0.4 Li aIW 0.3 i i . =
30 40 50 60 70 80 90 100 110 Core Flow (% Rated) 10 of 32
- 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 [MCPR(P), MCPR(F)]
where, MCPR(P) = Core power dependent MCPR shown in Fiqiure 3-1, MCPR(F) = Core flow rate dependent MCPR shown in Figure 3-2.
The MCPR(P) and MCPR(F) graphs presented in Figure 3-1 and Figure 3-2, respectively, are defined in Reference 6 Appendix D.
As shown in Figure 3-1, the MCPR(P) value is calculated as follows:
For P >- P(Bypass), MCPR(P) = OLMCPR(100)
- Kp For P < P(Bypass), MCPR(P) = MCPR(P) 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 Value 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.
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CNS Cycle 24 COLR Revision 0 3.3 Application of Scram Time Surveillance Data to OLMCPR(100)
The OLMCPR(100) value applicable to the MCPR(P) 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 (tave.
The mean scram time for control rod insertion to notch 36 is calculated as follows:
i12 rave n EN, 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),
N,= Number of control rods measured in test i,
= Average insertion time to notch 36 measured in test i, 3.3.2 20% Insertion Conformance Limit Scram Time (_rBI The 20% insertion conformance limit scram time is calculated as follows:
- =/.u + 1.65ar f_;N_
N, where, u = Mean of the distribution for average scram time insertion to position 36 used in the ODYN Option B analysis, o = 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.
The values for gi, a and N1 are given below.
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- p. = 0.830 S = 0.019
.N = 137 Using the values given above, Reference 7 defines the 20% insertion conformance limit scram time as, B 0.830 + 0.367 1 3.3.3 Scram Time Quality Factor (r)
The scram time quality factor is calculated as follows:
If Tave -<1;B, 1T 0 .
" ave TB If Tave > TB, TA -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, T B,and 1c:
OLMCPR(100) = OLMCPRB + t * (OLMCPRA - OLMCPRB)
Using 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.
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, 13 of 32
CNS Cycle 24 COLR Revision 0 For P > P(Bypass), MCPR(SL-P) = [OLMCPR(100)+AOLMCPR(SLO)] *KP For P < P(Bypass), MCPR(SL-P) = MCPR(P) + AOLMCPR(SLO),
For all core flows, MCPR(SL-F) = MCPR(F) + AOLMCPR(SLO),
AOLMCPR(SLO) = 0.02 from Reference 6 Section 11, and OLMCPR(100),
MCPR(P), and MCPR(F) 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 Appendix G.
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) = 0.03 from Reference 6 Appendix F.
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CNS Cycle 24 COLR Revision 0 Table 3-1 OLMCPR Values for OLMCPR(100) Calculation Equipment Status Applicable Cycle OLMCPRA OLMCPRB
___________________Exposure Range______ ______
Equipment In-Service BOC to EOR-2.326 GWd/MT 1.56 1.39 EOR-2.326 GWd/MT to EOC 1.63 1.46 Turbine Bypass Valve Out of Service BOC to EOC 1.64 1.47 (TBVOOS)
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 1.12.
- 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 10.571 GWd/MT in Reference 6 Section 3. The EOR exposure will vary based on actual cycle operations.
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f . . I CNS Cycle 24 COLR Revision 0 Figure 3-1 Power Dependent K(P) and MCPR(P) for GE14 Fuel with Safety Limit = 1.12 Cycle 24 K(p)IMCPR(p) vs Power for SLMCPR: 1.12 Operating Limit MCPR(p)= Kp*Operating MCPR(100)
For P <25%: No Thermal Limits Monitoring Required No Limits Specied 3-----, Rw->-5%.-------- For 25% <P<P(Bypass): P(Bypass): 30%
Flow >50%: MCPR(P)= 2174+0.052*(30%.P) t a 2.5 .. . - , .. . . . . . . Flow _50%: MCPR(P) =2.30+0.052 (30%-P)
F---
l _*50% -ow For 30% <P<45%: K(P)= 1.28+0.01340*(45%.P) oj I I For45%_< P<60%: K(P)= 1.15+0.00867*(60%.-P) 2----------
For 60%
- P 100%: K(P)= 1,0+0,00375*(100%-P)
II 1,5 '-
I I I
20 30 40 50 60 70 80 90 100 Power (%of Rated) 16 of 32
S t CNS Cycle 24 COLR Revision 0 Figure 3-2 Flow Dependent MCPR(F) for GE14 Fuel with Safety Limit = 1.12 MCPR(q vs Core Flow for SLMCPR: 1.12 1.8 For Core Flow > 55%
MCPR(f) = MAX(1.34, A()VV(c)1100+B(f))
1.7 ---- ----------------- FoLCQre flo -
MCPR(f) = MAX(1 .58, A(f)'W(c)it00+B(f))
Max Flow = 117.0 A(f =-0.662 B() =1.894 Max Flow = 112.0 A(f) = -0.630 B(f) = 1.829 Max Flow = 107.0 A(f) = -0.613 B(f) = 1.776 1.6 - - -- -Ma -F4ow-=-102 A# = 58 -(f)- 7-32 --------
a.
o 117.0%
112.0%
1.51 MCPR(f) below 1070%
55% flow is clipped based on stability requirements 1.4 -- - - - - - - - - -
1.3 .
20 30 40 50 60 70 80 90 100 110 120 130 Core Flow (%of Rated) 17 of 32
- 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.
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CNS Cycle 24 COLR Revision 0 Table 5-1 Rod Block Monitor Channel Settings Trip Function Analytical Limit' Allowable Value 1 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%
Applicable Core MCPR2 Analytical Allowable Trip Function Power Range Limit Limit 3 Value 3 Low Trip Setpoint LPSP - P < IPSP 1.31 < 120.0/125 < 117.0/125 (LTSP)
Intermediate Trip IPSP < P<5 HPSP 1.31
- 115.2/125 < 112.5/125 Setpoint (ITSP)
High Trip Setpoint HPSP < P 1.31 -5110.2/125 <5107.5/125 (HTSP)
NOTES:
- 1. Setpoints are given in units of percent of rated power.
- 2. The RBM trip level settings associated with the MCPR limit were verified in Reference 6 to bound the cycle specific RodWithdrawal Error (RWE) analysis for an RBM setpoint of 111% of reference level. The 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 111.0% of the reference level or an Analyzed Trip Level Setting (with RBM filter) of 110.2% of the reference level.
The generic MCPR limit of 1.25 was calculated in Reference 4 for an SLMCPR of 1.07. The MCPR limit documented above was calculated by multiplying the generic limit of 1.25 by the ratio of the SLMCPR values (1.12/1.07).
- 3. RBM trip setpoints are given in units of divisions of full scale.
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I II I CNS Cycle 24 COLR Revision 0
- 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
- LHGRFAC(P),
- LHGRFAC(F),
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, LHGRFAC(P) = Core power dependent multiplier shown in Figure 2-1, LHGRFAC(F) = Core flow rate dependent multiplier shown in Figure 2-2.
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; U0 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. Each combination of pin type is determined using the fuel bundle gadolinia distributions from Reference 13. The LHGR limits for cycle 24 implement compliance with the Alternative Source Term Reg. Guide 1.183 fuel rod average power limitations as defined in Reference 10. The process computer will be used to verify the pellet specific LHGR limits for each fuel bundle type are not violated.
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CNS Cycle 24 COLR Revision 0 Reference 6 Appendix D defines the LHGRFAC(P) and LHGRFAC(F) multipliers to be identical to the MAPFAC(P) and MAPFAC(F) multipliers presented in Figure 2-1 and Figure 2-2, respectively.
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.
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)]
- LHGRFAC(SLO),
LHGRFAC(SLO) = 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 (LHGRFAC(P) and LHGRFAC(F)) and SLO multiplier corrections at the same time.
The single loop operation peak LHGR (PLHGR) multipliers for each fuel bundle type are defined in Reference 6 as shown in the table below.
Fuel Bundle Type SLO PLHGR Multiplier All GE14B bundles 0.87 All GE14C bundles 0.87 21 of 32
t J CNS Cycle 24 COLR Revision 0 Table 6-1 LHGRSTD Values By Fuel Bundle Type EDB-3881 Peak LHGRsTD LHGRSTD LHGRsTD LHGRs(T LHGRsmT Pellet (kWlft) (kW/ft) (kWIft) (kW/ft) (kW/ft)
Exposure U0 2 Only U0 2 Only 6%Wgad)3%gad 0% gad (GWd/MT) Full Length Partial Length 6%_gad 3-6% max 0.0000 13.400 13.400 11.346 11.800 13.100 12.8880 -... 11.346 -- -
13.0690 .- 11.800 --
15.6420 .- -.-- 13.100 16.0000 13.400 13.400 ..--.
59.9400 -- 8.030 -- 7.462 7.686 59.9401 -- 7.245 -- 7.120 7.120 61.5600 7.832 -- -- -
61.5601 7.308 .-...
63.6470 -- 7.120 --
64.5790 ...-- -- 7.120 65.8270 7.308 ...-- -
66.3590 -- 7.245 ...--
68.4330 -- - -- 6.648 68.8200 -- 6.944 6.309 6.640 --
70.000 6.800 -- -- - -
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CNS Cycle 24 COLR Revision 0 EDB-2476 Peak LHGRSTD LHGRSTD LHGRsTD LHGRsTD LHGRsTD LHGRsTD LHGRsTD LHGRsTD Pellet (kWlft) (kWlft) (kWlft) (kW/ft) (kWlft) (kWlft) (kWlft) (kWlft)
Exposure U0 2 Only U0 2 Only 5% gad 4% gad 4% gad 3% gad 0% gad 0% gad Exposur Full Partial 5% max 5% max 4% max 3% max 4-5% max (GWd/MT) Length Length gad gad gad gad gad 0.0000 13.400 13.400 12.521 12.700 12.800 12.945 13.000 13.100 12.8880 -- --..........
13.6440 .- 12.700 ........
13.6560 .... 12.521 --........
13.7540 .....-- -- 12.945 ....
13.7900 ...... - -- 12.800 --....
15.5220 ........... 13.000 --
15.6420 ...........-- 13.100 16.0000 13.400 13.400 ....-- -- --
59.9400 -- 8.405 7.600 7.712 7.826 7.898 7.950 8.060 59.9401 -- 7.245 7.120 7.120 7.120 7.120 7.120 7.120 61.5600 8.220 ... -- -- -- --
61.5601 7.308 ...--....
61.9400 .
-- 7.120 --......
62.2070 ...... . 7.120 --......
62.8440 .....-- 7.120 -...
62.8780 ........-- 7.120 - --
63.0000 ........-- 7.120 -
63.6000 ........ ..-- 7.120 65.0000 7.308 .............
65.1360 -- 7.245 --..........
67.6100 - - 4.672 --......
67.6460 ...... 4.739 .......
67.9100 ..-.... 4.850 --
68.0390 .......-- 4.830 --..
68.1980 .... - -- 4.776 .-- -
68.4330 .... - ......... 4.888 68.8200 - 5.545 ........--
70.0000 5.000 -- "..........
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CNS Cycle 24 COLR Revision 0 EDB-2611 LHGRsTD LHGRsTD LHGRsTD LHGRsTD LHGRsM LHGRsTD Peak Pellet (kWlft) (kWlft) (kW/ft) (kWlft) (kW/ft) (kW/ft)
Exposure U0 2 Only U0 2 Only 5% gad 3% gad 0% gad 0% gad (GWdIMT) Full Length Partial 5% max gad 3% max gad 5% max gad Length 0.0000 13.400 13.400 12.521 12.945 13.000 13.100 13.6560 -- -- 12.521 -- -
13.7540 ....- 12.945 - --
15.5220 ..... 13.000 --
15.6420 .......-- 13.100 16.0000 13.400 13.400 -- -- -- --
59.9400 -- 8.405 7.600 7.898 7.950 8.060 59.9401 -- 7.245 7.120 7.120 7.120 7.120 61.4900 -- -- 7.120 -- -- --
61.5600 8.220 ...---..
61.5601 7.308 .....--..
62.8780 -- 7.120 ....
63.0000 ......-- 7.120 --
63.6000 ......
-- 7.120 65.0000 7.308 ....-- --
65.1360 -- 7.245 -....
67.6100 . -- 4.672 ...--.
67.9100 .-
-- 4.850 --
68.0390 ...... 4.830 -- --
68.4330 ....-- --. 4.888 68.8200 -- 5.545 ......--
70.0000 5.000 -- -- -- --
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CNS Cycle 24 COLR Revision 0 EDB-2569 LHGRsTD LHGRSTD LHGRsm LHGRsTD LHGRsTD LHGRsTD Peak Pellet (kWlft) (kWlft) (kW/ft) (kWlft) (kWlft) (kWIft)
Exposure U0 2 Only U0 2 Only 4% gad 3% gad 0% gad 0% gad (GWdlMT) Full Length Partial 4% max gad 3% max gad 4% max gad Length 0.0000 13.400 13.400 12.800 12.945 13.000 13.100 13.7540 -- -- -- 12.945 ..--
13.7900 -- -- 12.800 -- -.
15.5220 .....--. 13.000 --
15.6420 .--
-- -- 13.100 16.0000 13.400 13.400 - - -- --
59.9400 -- 8.405 7.826 7.898 7.950 8.060 59.9401 -- 7.245 7.120 7.120 7.120 7.120 61.5600 8.220 -- -- -- --
61.5601 7.308 ...---..
62.8440 -- - 7.120 --....
6 2 .8 7 8 0 ....- - 7 .1 2 0 --..
63.0000 ......-- 7.120 --
63.6000 .....-- -- 7.120 6 5 .0 0 0 0 7 .3 0 8 .....-- --
65.1360 -- 7.245 ....--.
67.9100 ...- - 4.850 --
68.0390 ....-- 4.830 --..
68.1980 .... 4.776 ....--
68.4330 ...- -- 4.888 68.8200 -- 5.545 ......--
70.0000 5.000 -- -- ......
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I I~ I CNS Cycle 24 COLR Revision 0 EDB-2800 LHGRsTD LHGRsTD LHGRsTD LHGRSTD LHGRsTD LHGRsTm LHGRSTD Peak Pellet (kWlft) (kWlft) (kW/ft) (kW/ft) (kW/ft) (kW/ft) (kWlft)
Exposure U0 2 Only U0 2 Only 6% gad 5% gad 5% gad 4% gad 0% gad (GWdlMT) Full Length Partial 6% max 6% max 5% max 4% max 4-6% max
_Length gaad d gad gad gad 0.0000 13.400 13.400 12.255 12.400 12.521 12.800 13.100 13.5000 -- -- -- 12.400 -- --
13.5320 .... 12.255 --.....
.13.6560 ....--. 12.521 - --
13.7900 .......-- 12.800 --
15.6420 -- 13.100 16.0000 13.400 13.400 ...-- --.
59.9400 -- 8.405 7.387 7.462 7.600 7.826 8.060 59.9401 -- 7.245 7.120 7.120 7.120 7.120 7.120 61.0870 - -- 7.120 --.......
61.1570 --.-- 7.120 ......
61.5600 8.220 ......--..
61.5601 7.308 .......-.
61.9400 --... 7.120 --..
62.8440 .......-- 7.120 --
63.6000 .......-- - 7.120 65.0000 7.308 ..........--
65.1360 -- 7.245 ...--....
66.9300 --.-- 4.627 ......
67.0690 -- - 4.572 --......
67.6100 ....--. 4.672 --
68.1980 .......... 4.776 --
68.4330 ..........-- 4.888 68.8200 - 5.545 ..........
70.0000 5.000 ............
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f CNS Cycle 24 COLR Revision 0 EDB-2801 LHGRsm LHGRsTD LHGRsTD LHGRSTD LHGRSTD LHGRsTD Peak Pellet (kWlft) (kWlft) (kWlft) (kWlft) (kW/ft) (kWIft)
Exposure U0 2 Only U0 2 Only 6% gad 5% gad 4% gad 0% gad (GWdIMT) Full Length Partial 6% max gad 6% max gad 4% max gad 4-6% max Length __ad 0.0000 13.400 13.400 12.255 12.400 12.800 13.100 13.5000 -- - - 12.400 -- --
13.5320 - -- 12.255 - --.
13.7900 ..... -- 12.800 --
15.6420 ..-- -- -- 13.100 16.0000 13.400 13.400 -- -- -- --
59.9400 -- 8.405 7.387 7.462 7.826 8.060 59.9401 -- 7.245 7.120 7.120 7.120 7.120 61.0870 ..-- 7.120 -- -- --
61.1570 -. - 7.120 ....
61.5600 8.220 .....-....
61.5601 7.308 ......-.
62.8440 -- 7.120 --
63.6000 .... - -- 7.120 65.0000 7.308 -.......
65.1360 -- 7.245 ...--...
66.9300 --.-- 4.627 ....
67.0690 -- - 4.572 -...
6 7 .6 1 0 0 ...- -..- -
68.1980 ..... 4.776 68.4330 .....- -- 4.888 68.8200 -- 5.545 ....--
70.0000 5.000 .........
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I f CNS Cycle 24 COLR Revision 0 EDB-2901 LHGRsTD LHGRsTD LHGRsTD LHGRsTD LHGRsTD LHGRsTD LHGRsTD Peak Pellet (kWIft) (kW/ft) (kW/ft) (kWlft) (kWIft) (kW/ft) (kW/ft)
Exposure U0 2 Only U0 2 Only 6% gad 5% gad 4% gad 4% gad 0% gad (GWdlMT) Full Length Partial 6% max 5% max 5% max 4% max 4-6% max Length gad gad gad gad gad 0.0000 13.400 13.400 12.255 12.521 12.700 12.800 13.100 13.5320 -- -- 12.255 - -- -- --
13.6560 ...- 12.521 --..
13.6640 .......-- 12.700 --..
13.7900 ........-- 12.800 --
15.6420 ..-- -- -- 13.100 16.0000 13.400 13.400 -- - - --
59.9400 -- 8.405 7.387 7.600 7.712 7.826 8.060 59.9401 -- 7.245 7.120 7.120 7.120 7.120 7.120 61.0870 -- -- 7.120 -- -- -- --
61.5600 8.220 ...--...
61.5601 7.308 ......--..
61.9400 ..
-- 7.120 ....
62.2070 ....-- 7.120 --
62.8440 ....... 7.120 --
63.6000 ..- -..-- 7.120 65.0000 7.308 .....- --
65.1360 - 7.245 .........
67.0690 . -- 4.572 ...--..
67.6460 .....-- 4.739 ....
67.6100 ..... 4.672 -- --.
68.1980 ......... 4.776 --
68.4330 ..- 4.888 68.8200 -- 5.545 ........
70.0000 5.000 .........
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f ,) I CNS Cycle 24 COLR Revision 0 EDB-2902 Peak Pellet LHGRsTD LHGRsTo LHGRsTD LHGRsTD LHGRsm Eapelle (kW/ft) (kWlft) (kWlft) (kW/ft) (kWlft)
Exposure U0 2 Only U02 Only 5% gad 4% gad 0% gad (GWdlMT) Full Length Partial Length 5% max gad 5% max gad 4-5% max gad 0.0000 13.400 13.400 12.521 12.700 13.100 13.6560 - -- 12.521 -- --
13.6640 - - - 12.700 --
15.6420 -- -- -- 13.100 16.0000 13.400 13.400 -- --
59.9400 -- 8.405 7.600 7.712 8.060 59.9401 -- 7.245 7.120 7.120 7.120 61.5600 8.220 -- -- -- --
61.5601 7.308 -- ".-- .
61.9400 .
-- 7.120 --
62.2070 ....-- 7.120 --
63.6000 ..- -- 7.120 65.0000 7.308 - ---.
65.1360 - 7.245 ..--.
67.6460 .-
-- 4.739 67.6100 - - 4.672 -- --
68.4330 ...- - 4.888 68.8200 - 5.545 ....--
70.0000 5.000 -....
Bundle Types GNF Bundle # GNF Fuel Bundle Identification EDB-3881 GE14-P1OHNAB385-14GZ-10OT-148-T6-3881 (GE14B)
EDB-2476 GE14-Pl 0HNAB379-17GZ- 10OT-150-T6-2476 (GE14C)
EDB-2611 GE14-P1ODNAB393-17GZ-10OT-150-T6-2611 (GE14C)
EDB-2569 GE14-PIODNAB398-16GZ-10OT-150-T6-2569 (GE14C)
EDB-2800 GE 14-P1ODNAB395-14GZ-10OT-150-T6-2800 (GE14C)
EDB-2801 GE14-P1ODNAB393-17GZ-10OT-150-T6-2801 (GE14C)
EDB-2901 GE 14-PiODNAB385-13GZ-10OT-150-T6-2901 (GE 14C)
EDB-2902 GE 14-Pi ODNAB386-14GZ-10OT-150-T6-2902 (GE14C)
- 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 Reference 6. A detailed view of the Exclusion Region of the power/flow map is presented in Figure 7-1.
29 of 32
r t j I CNS Cycle 24 COLR Revision 0 Intentional operation within the Exclusion Region is prohibited. The Exclusion Region is defined in the table below.
Exclusion Region Power (% of Rated) Flow (% of Rated)
A 84.36 57.49 B 35.77 32.50 Point "A" is on the highest flow control line and point "B" is on the natural circulation line (see FiQure 7-1).
The region boundaries are defined using the generic shape function given in Reference 6. The calculation of the region boundaries as a function of core thermal power and core flow rate is summarized below.
P=PBX j[ -w .,-W, J2]
where, P = Core thermal power (% of rated) on the region boundary, W = Core flow rate (% of rated) corresponding to power, P, on the region boundary, PA = Core thermal power (% of rated) at point A, PB = Core thermal power (% of rated) at point B, WA = Core flow rate (% of rated) at point A, WB = Core flow rate (% of rated) at point B.
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V ) a'r CNS Cycle 24 COLR Revision 0 Figure 7-1 Stability Exclusion Region Map 110 100 90 80 0
70 0.
60 I--
50 40 30 20 20 30 40 50 60 70 80 Core Flow (%)
31 of 32
- 8. REFERENCES The following references are identified in this report:
- 1. NEDE-24011-P-A-15, "General Electric Standard Application for Reactor Fuel", September 2005.
- 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-31960-A and NEDO-31960-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. GE-NE-L12-00867-12, "Project Task Report Cooper Nuclear Station MIG Project Task 900: Transient Analysis", Revision 1, May 2000.
- 6. 0000-0056-7313-SRLR, "Supplemental Reload Licensing Report for Cooper Nuclear Station Reload 23 Cycle 24 (1.12 MCPR Safety Limit)", Revision 0, August 2006.
- 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.
- 10. GE Letter, FRL-NPP-HP1-06-020, "LHGR Limit for Cooper to Comply with Reg. Guide 1.183", October 20, 2006.
- 12. GE Letter DGC:89-190, "Cooper Reload 13 Technical Specification Changes," November 30, 1989.
- 13. 0000-0056-7313-FBIR, " Fuel Bundle Information Report for Cooper Nuclear Station Reload 23 Cycle 24", Revision 0, August 2006.
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ATTACHMENT 3 LIST OF REGULATORY COMMITMENTS©D Correspondence Number: NLS2006090 The following table identifies those actions committed to by Nebraska Public Power District (NPPD) in this document. Any other actions discussed in the submittal represent intended or planned actions by NPPD. They are described for information only and are not regulatory commitments. Please notify the Licensing Manager at Cooper Nuclear Station of any questions regarding this document or any associated regulatory commitments.
COMMITMENT COMMITTED DATE COMMITMENT NUMBER OR OUTAGE None 4 +
4 +
4 4 4 +
4 4 4 4 4 4-4 4 I PROCEDURE 0.42 1 REVISION 19 1 PAGE 20 OF 27