GO2-09-091, Submittal of Cycle 20 Core Operating Limits Report (Colr), Revision 0
| ML091750098 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 06/17/2009 |
| From: | Cullen G Energy Northwest |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| GO2-09-091 | |
| Download: ML091750098 (22) | |
Text
Gregory V. Cullen Regulatory Programs SKA N ERGYW STP.O. Richland, Mail 99352-0968 Box 968, WA Drop P2 Ph. 509-377-6105 F. 509-377-4317 gvcullen@energy-northwestcom June 17, 2009 G02-09-091 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
COLUMBIA GENERATING STATION, DOCKET NO 50-397 CYCLE 20 CORE OPERATING LIMITS REPORT (COLR), REVISION 0
Dear Sir or Madam:
In accordance with the Columbia Generating Station Technical Specifications (TS) 5.6.3.d, Energy Northwest herewith submits-the Cycle 20 COLR, Revision 0. The operating limits in the COLR 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. Should you have any questions or desire additional information regarding this matter, please contact me at (509) 377-6105.
Respectfully, GV Cullen Manager, Regulatory Programs
Enclosure:
COLR 09-20 Revision 0 cc: EE Collins - NRC RIV NJ DiFrancesco - NRC NRR NRC Sr. Resident Inspector -. 988C (2)
WA Horin - Winston & Strawn RN Sherman - BPA/1 399
CYCLE 20 CORE OPERATING LIMITS REPORT (COLR), REVISION 0 ENCLOSURE COLR 09-20 Revision 0
COLR 09-20 Revision 0 Columbia Generating Station Cycle 20 Core Operating Limits Report April 2009
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Columbia Generating Station
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- Cycle 20 Core Operating Limits Report Table of Contents 1.0 Introduction and S um m ary .......................... ... ..................................................................... 1 2.0 Average Planar Linear Heat Generation Rate (APLHGR) Limits for Use in Technical Specification 3.2.1 ........................... ........................... 3........................
3 3.0 Minimum Critical Power Ratio (MCPR) Limit for Use in Technical S pecification 3.2 .2 ......... ... . ........... *.......................... ........ .......................................... . . ... :. 5 4.0 Linear Heat Generation Rate (LHGR) Limits for Use in Technical S pecification 3.2.3 ................................. . ....... .. . .......... .... ................................ ................. 14 5.0 Oscillation Power Range Monitor (OPRM) Instrumentation Limits fo r Use in LCO 3 .3 .1.3 ..................................................................................................... 16 6 .0 Refe re n ce s ............................................. ......................................................................... 17 Columbia Generating Station COLR 09-20 Revision 0
1.0 Introduction and Summary This report provides the Average Planar Linear: Heat Generation Rate (APLHGR) limits, the Minimum Critical Power Ratio (MCPR):limits, the Linear Heat Generation Rate (LHGR) limits and the Oscillation Power Range Monitor (OPRM)
Instrumentation limit.s.for Columbia Generating Station Cycle 20 as required by, Technical Specification'5.6.3. As.'required by Tchriicaj Specifidatio'n 5.6.3, these limits were determined' using NRC-approved m~ethodolkVb "n cldare establ ishied sothat'all applicable limits of the plant safety analysis are.met. LOCA analyses were performed with methodologies that'result in Single Loop .Operation (SLO) APLHGR limits as well as Two Loop Operation (TL0)'APLHGR limits. The APLHGR and LHGR limits for ATRIUM-10.fuel given in this report are documented in Reference 6.1. The APLHGR and LHGGR limits for GE,14fuel given in this repbet are documented in References 6.4 and 6.5, respectively. The full power MCPR limits for all Cycle 20 fuel types (GE14 as well as ATRIUM-10 fuel) are documented in Reference 6.4. The power and flow dependent MCPR limits are documented in Reference 6.6. The basis for the OPRM Instrumentation'limits is documenrted in References 6.3 and6.4.
The MCPR limit is the maximum of (a) the applicable exposure dependent, full power MCPR limit, (b) the applicable powevr dependent MCPR limit, and (c) the applicable flow dependent MCPR limit specified in this report. This stipulation assures that the safety limit MCPR will not be violated during steady-state operation and anticipated operational occurrenc's throughout the'Columbia Generating Station 0perating regime. Full power MCPR limits are specified to define operating Iimits at rated power and flow. Power dependent MCPR limits are specified todefine operating limits at other than rated power conditions. A flow dependentMCPR isspecified to define operating limits at other than rated flow conditions. The flow dependent M CPR limit, set by the limiting Recirculation Flow Increase event, provides bounding protection for all events at reduced flow.
The reload licensing analyses for this cycle provide operating limits for Extended Load Line Limit Analysis (ELLLA) operation which extends the power and.flow operating regime forColumbia Generating Station up to the 10 8% rod line which at full power corresponds to 88% of rated flow. The MCPRlimits defined in this report are applicable up to 100% of rated thermal power along and below the 108% rod line. The minimum flow for operation at rated power is 88% of rated flow; the maximum is 106%.
The specific topical report revisions and supplements which describe the methodology utilized in this cycle specific analysis are shown in Table 1.1.
Columbia Generating Station COLR 09-20 Revision 0
Table 1.1 Columbia Generating Station
-"Reference Topical Reports .
- 1. XN-N F-81.-58(P)(A) Revisionh2ad'Sup Fue/Rod ThermaS-MechanicalResponse uplements 1, and 2, R'ODEX2FulRdTem-Mechanical/Response EEva/l'CtiohrMode/l"Exxon' N uclear Company,' March 1984.
- 2. XN-NF-85-67(P)(A) Revision 1, Generic Mechanical Design fdr Exxon'Nuclear Jet Pump BWR Reload Fuel, Exxon Nuclear ComIpany, september 198 6. '
- 3. EMF-85-74(P) Revision 0 Supplementil(P)(A) and Suipl-iemerit2iP)(A), RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model, Siemens'Power Corporation, February1998.
- 4. ANF-89-98(P)(A) Revision 1 and Supplement 1, Gen6ric Mechanical Design Criteria for BWR Fuel Designs, Advanced Nuclear Fuels Corpbration, May 1'995.
5..' EMF-2361(P)(A) Revision 0, EXEM BWR-2000 ECCS Evaluation Model, Framatome ANP, May 2001.
- 6. EMF-2292(P)(A) Revision 0, A TRIUM'-lO:,'Appendix K,Spray Heat Transfer, Coefficients, Siemens Power Corporation, September 2000.'
- 7. NEDO-32465-A, BWR Owners' Group Reactor Stability Detect andSuppress Solutions Licensing Basis Methodology and Reload Applications, August 1996.
- 8. NEDC-33419P, GEXL97 Correlation Applicabl6 to ATRIUM-10 Fuel, Revision 0,'June 2008.
- 9. NEDE-24011-P-A and NEDE-24011-P-A-USI General Electric Standard Application for Reactor Fuel (GES TAR II) and Supplement for the United States, Revision 16, October 2007.
Columbia Generating Station COLR 09-20 Revision 0
2.0 Average Planar Linear Heat Generation Rate (APLHGR) Limits for Use in Technical Specification 3.2.1 The APLHGRs for use in Technical. Specification 3;2.1, asa function of Average Planar Exposure, shall not exceed the limits shown in the following tables. APLHGR limits for single loop operation for GE14 fuel are obtained by applying a 1.00 multiplier to the two loop operation.APLHGR limits. APLHGRlimits f6rýsi-nge loop operation for ATRIUM-10 fuel are obtained by applying a 0.90 multiplier to the two loop operation APLHGR limits.
- a. Table 2.1i-GE14 Reload Fuel
- b. Table 2.2 -ATRIUM-10 Reload Fuel Columbia Generating Station COLR 09-20 Revision 0
Table 2.1 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)
Versus-Average Planar Exposure
.GEI4Reload Fuel Average Plana*r* 'Esure MAPLHGR Limit GWd/MTU GWd/ST kW/ft 0.00 0.00 12.82 16.00 14.51. *-12.82-21.10 19.14 12.82 63.50 57.61 8.00 70.00 63.50 5.00 Table 2.2 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)
Versus Average Planar Exposure ATRIUM-10 Reload Fuel Average Planar TLO Exposure MAPLHGR (MWd/MTU) (kW/ft) 0 12.5 15000 12.5 67000 7.3 Columbia Generating Station COLR 09-20 Revision 0
3.0 Minimum Critical Power Ratio (MCPR) Limit for Use in Technical Specification 3.2.2 The MCPR limit for use in TechnicalSpecification 3.2:2 shall be greater than or equal to the bounding limits determined from Table i3.1: through Table 3.6. Supporting information for the MCPR limits is provided in Table'3.1-1 through Table 3.1-2.
The MCPR safety limit for Cycle 20 is 1.09 for two loop operation (TLO) and1 .10 for single loop operation,(SLO). The power and flow dependent M CPR limits for SLO require a 0.01 adder to the TLO MCPR limits due to'the difference in the MCPR safety lim it.
Columbia Generating Station COLR 09-20 Revision 0
Table 3.1 Columbia Generating Station
'Two Loop Operation' MCPR Operating Limits A p p l. App . ...
"Exposure'Rar6ge . 2.. . "' . . . ... Option A Option B33 Cond.
All Fuel All Fuel 1 Equipment In Service Full Power Limits (BOC to MOC) 1.38 4 1.384 Full Power Limits (MOC to EOC) 1.42 1.39 5
Flow Dependent Lim its Table 3.6 6
Power Dependent Limits Table 3.2 2 EOC RPT Out of Service (RPTOOS)
Full Power Limits (BOC to MOC) 1.47 1.384 Full Power Limits (MOC to EOC) 1.63 1.46 Flow Dependent Lim its 5 Table 3.6 Power Dependent Limits 6 Table 3.3 3 Turbine Bypass Valve Out of Service (TBVOOS)
Full Power Limits (BOC to MOC) 1.39 1.3854 Full Power Limits (MOC to EOC) 1.47 1.44 Flow Dependent Lim its 5 Table 3.6 Power Dependent Limits 6 Table 3.4 4 TBVOOS and RPTOOS Full Power Limits (BOC to MOC) 1.52 1.41 Full Power Limits (MOC to EOC) 1.67 1.50 Flow Dependent Lim its 5 Table 3.6 Power Dependent Limits 6 Table 3.5 Columbia Generating Station COLR 09-20 Revision 0
Notes for Table 3.1 Note 1: For Single Loop Operation (SLO), the SLMCPR increases by 0.01. This 0.01 increase must also be applied to the Two Loop Operation (TLO) MCPR Operating Limit, when the, limit is not set by Stability, to obtain the SLO Operating Limit. Note 4 identifies which limits are set by. Stability.
Note 2: ... The cycle exposure range designation is defined in Table 3.1-1. End of Rated (EOR),is defined as thecycle exposure corresponding to all rods out, 100% power, 100% flow and normal feedwater temperature. The limits are applicable for normal feedwater temperature, feedwater heaters out of service, final feedwater temperature reduction and coastdown.
Table 3.1!-lCycle Exposure Range Designation Name Exposure Range BOC to MOC < EOR-3938 MWd/MTU (3572 MWd/ST)
MOC to EOC > EOR-3938 MWd/MTU (3572 MWd/ST)
Note 3: The NRC has concluded that a statistical approach (Option B) may be used for pressurization events analyzed with ODYN (References 6.7 and 6.8). 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 I:ro:6edure described below determines the full power MCPR limit based on the scramr times of SR 3.2.2.2 or the Stability based MCPR limit, whichever is greater.
If the scram speed distribution is not within the assumed distribution, the MC PR for pressurization 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 surveillance information for the fuel cycle is the number of active control rods measured for each surveillance test (the first test is at the BOC and is denoted N1 ;
the ith test denoted Ni) and the average scram time to Notch 39 for the active rods measured in test i denoted r . , . .
. The.equation used to calculate -theoverall average of all the-scram data generated to date in the cycle is: - -
£N,,ri T'rae n (1)
ZN, Columbia Generating Station COLR 09-20 Revision 0
where:
n" number of surveillance tests performed to date in the cycle; total number of active rods measured to date in i= .v.the cycle' and srinof the scram time to.Notch 39of all active n
ZN"i rods measured to datei n the cycle to comply
'with the Technical Specifica.tion surveillance r6quirements.
The average'scram time', TV,. istested against.'the-analysis mean using the following equation:
T ~(2) where:
TB =p +1.65 (3)
U. =0.672 seconds (mean scram time to Notch 39 usedin the Option B ana.lyvsis) 0.01 6'seconds (standard deviation of u) totalknumber of active rods measured at
' '*BOC- to cormply with the Technical Specification surveillance requirements.
If the cycle average scram time satisfies the Equation 2 criterion, continued plant operation under the ODYN Option B MCPR for pressurization events is permitted.
If not, the MCPR for pressurization events must-be re-established, based on a linear interpolation between the Option B and Option.A.MCPRs.
The equation to establish the new operating limit is given below:
OLMCPRN" = MAX MCPRopi,,B + ... B AMCPR,MCPRS,ýi,,l _ (4)
A B Columbia Generating Station COLIR 09-20 Revision 0
where:
" ae and B. = defined in Equations I and 3, respectively
'CA 0.866 seconds (the Technical Specification limit on core average scram time to Notch 39)
AMCPR = MCPROpIionA -MCPROptio B (the difference between the MCPR calculated using Option A and that using Option B for pressurization events from Table 3.1-2)
M'CPR 0 pfionA = the limiting pressurization event Option A MCPR MCPRoption B = the limiting pressurization event Option B MCPR MCPRStability = 1.38 (the MCPR set by.Stability)
Table 3.1 cannot be usedwith Equation 4 for interpolation between Option A and Option B MCPR limits because in some instances, Stability sets the OLMCPR.
Table 3.1-2 provides the limiting pressurization event MCPR values for use with Equation 4.
Columbia Generating Station COLR 09-20 Revision 0
Table 3.1-2 Two-Loop Operation Full Power MCPR Limits for Pressurization Events Appi. Exposure Range Option A Option B Cond.
All Fuel All Fuel I Equiptneht-[n Service BOC to MOC [.1.33 1.30 MOC to EOC [ 1:42 1.39 2 EOC RPT Out of Service (RPTOOS)
BOC to MOC- E.47 1.36 MOC to EOC [ 1.63 1.46 3 Turbine Bypass Valve Out of Service (TBVOOS)_
BOC to MOC 1.39 1.36 MOC to EOC 1.47 1.44 4 TBVOOS and RPTOOS .
I BOCtoMOC .1".52 1.41 MOC to EOC [ 167 1.50 Note 4: The Full Power MCPR Operating Limit is set by Stability, and therefore the Option A and Option B values in Table 3.1 cannot be directly used to interpolate between Option A and Option B Full Power MCPR Operating Limits. See Note 3 for guidance.
Note 5: Flow dependent MCPR limits are applicable to TLO and require the SLO 0.01 adder'when operating in SLO.
Note 6: 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 less than 30% of rated power are subdivided by core flow. Limits are provided for core flows greater than 50% of rated flow and less than or equal to 50% of rated flow. A step change in the power dependent MCPR limits occurs at 30% of rated power because direct scrams on turbine throttle valve closure and turbine governor valve fast closure are automatically bypassed below 30% of rated power and not applicable per Technical Specification 3.3.1.1.
The power dependent MCPR limits in Tables 3.2 through 3.5 are provided as Kp multipliers above the direct scram bypass power level (Pbypass) and as absolute MCPRp limits below Pbypass. MCPRp limits above Pbypass are determined through the following equation: MCPRp = Kp x OLMCPR(Full Power Limit). Power dependent MCPR limits are applicable to TLO and require the SLO 0.01 adder when operating in SLO.
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Table 3.2 Columbia Generating Station Application Group 1: Equipment In Service TLO Power Dependent MCPRrLimits All Fuel Types,.
Limits for Power < 30.0%
Power (%) Limit for Flow ,> 50.0% Limit for Flow < 50.0%
MCPRp MCPRp 25.0 2.24 2.24
-30.0 ... 2.-15 2.15,ý Limits for Power >30.0%.
." Power-(%) Limit
____ _____ .. Kp 30.0 1.483 45.0 1.280
.60.0 1.150 85.0 . .. 1.072 100o' 1.000 Table 3.3 Columbia Generating Station Application Group 2: EOC RPT Out of Service (RPTOOS)
TLO Power Dependent MCPR Limits All Fuel Types Limits for Power < 30.0%
Power (%) Limit for Flow> 50.0% Limit for Flow < 50.0%
MCPRp MCPRp 25.0 2.24 2.24 30.0 2.15- . 2.15 Limitsfor Power Ž30.0% ....
'Power (%) Limit 30.0 1.483.
45.0 1.280 60.0 1.150 85.0 1.072 100.0 1.000 Columbia Generating Station COLR 09-20 Revision 0
"Taible 3.4 Columbia Generating Station Application Group 3: Turbine Bypass Valve Out of Service (TBVOOS)
TLO Power Dependent MCPR Limits All Fuel Types, Limits for Power < 30.0%
Power (%) Limit for Flow > 50.0% Limit for Flow < 50.0%
MCPRp - MCPRp 25.0. 3.28 3.12 30.0 2.89 2.69 Limits for Power >_30.0%
Power (%) Limit
...... . . . .. _ _Kp .
30.0 1.483) 45.0 1.280 60.0 1.150 85.0 1.072 100.0 1.000 Table 3.5 .
Columbia Generating Station Application Group 4: TBVOOS and RPTOOS TLO Power Dependent MCPR Limits
.,All Fuel Types
'Limits for Power < 30.0%
Power (%) Limit for Flow > 50.0% Limit for Flow < 50.0%
.. MCPRp MCPRp 25.0 3.28 3.12 30.0 2.89 2.69 Limits for Power Ž30.0%
Power (%) Limit Kp 30.0 1.483 45.0 1.280 60.0 1.150 85.0 1.072 100.0 1.000 Columbia Generating Station COLR 09-20 Revision 0
Table 3.6 Columbia Generating Station..
All Application.Groups TLO Flow Dependent MCPR Limits All Fuel Types Flow (Limit
- MCPRf 0.0 1.85 30.0 1.65 90.0 1.25 108.5 1.25 Columbia Generating Station COLR 09-20 Revision 0
4.0 Linear Heat Generation Rate (LHGR) Limits for Use in Technical Specification 3.2.3 The LHGRs for use in Technical S pecification 3.2.3. are 'given as a function of nodal pellet exposure for both the and, ATRIUM-10
,-GE1:4 fuel. The LHGRs shall not exceed the limits shown in the following:
a.- - Fuel-Bundle Information Report (Reference 6.5) for- GE14 Reload Fuel
- b. Table 4.1 for ATRIUM-10 Reload Fuel Columbia Generating Station COLR 09-20 Revision 0
Table 4.1 Linear Heat Generation Rate (LHGR)
.......... Versus Pellet Exposure.....,
, ., ATRIUM-10 Reload Fuel, -
-Pellet Exposure- LHGR (MWd/MTU) - (kW/ft) 0 13.4 18900 13.4 74400 :7.1 Columbia Generating Station COLR 09-20 Revision 0
5.0 Oscillation Power Range Monitor (OPRM) Instrumentation Limits for Use in LCO 3.3.1.3 The OPRM instrumentation limits for use in LCO 3.3.1.3 shall not exceed the following:
Function Trip Setpoint Perio d'SBased Detectinh'.lgorithm (PBDA)
Amplitude Setpoint: Sp 1.11 Peak/Average Confirmation Count Seto5oint: N2 14 Columbia Generating Station COLR 09-20 Revision'O
6.0 References 6.1 ANP-2602 Revision 0, "Columbia Generating Station Cycle 19 Reload Analysis,"
AREVA NP, March 2007.
6.2 EMF-3172(P) Revision 1, "Columbia Generating Station LOCA-ECCS Analysis MAPLHGR Limit for ATRIUM TM-10 Fuel," Framatome ANP, June 2005.
6.3 NE-02-00-03, Revision 0, "Oscillation Power Range Monitor (OPRM) Trip Setpoints," Energy Northwest, June 17, 2000.
6.4 0000-0098-0322-SRLR, "Supplemental Reload Licensing Report for Columbia Reload 19 Cycle 20," Revision 0, March 2009.
6.5 0000-0098-0322-FBIR, "Fuel Bundle Information Report for Columbia Reload 19 Cycle 20," Revision 1, April 2009.
6.6 GEH-0000-0075-4920-R1, "GEl4 Fuel Design Cycle-Independent Analyses for Energy Northwest Columbia Generating Station," Revision 1, March 2009.
6.7 NEDO-24154 and NEDE-24154-P, "Qualification of the One-Dimensional Core Transient Model for Boiling Water Reactors", Volumes 1, 2 and 3, August 1986.
6.8 Letter JSC-005-86 (MFN-003-86), J. S. Charnley (GE) to H. N. Berkow (NRC),
"Revised Supplementary Information Regarding Amendment 11 to GE Licensing Topical Report N EDE-24011-P-A", January 16, 1986.
Columbia Generating Station COLR 09-20 Revision 0