L-MT-09-056, NAD-MN-020, Revision 0, Monticello Nuclear Generating Plant, MNGP Core Operating Limits Report for Cycle 25.
ML091400198 | |
Person / Time | |
---|---|
Site: | Monticello ![]() |
Issue date: | 05/15/2009 |
From: | O'Connor T Northern States Power Co |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
L-MT-09-056 NAD-MN-020, Rev 0 | |
Download: ML091400198 (44) | |
Text
May 15,2009 L-MT-09-056 Technical Specification 5.6.3 U.S; Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Monticello Nuclear Generating Plant Docket 50-263 Renewed Facility Operating License No. DPR-22 MNGP Core Operating Limits Report for Cvcle 25
References:
- 1) Amendment No. 159, "Issuance of Amendment Re: Request to Install Power Range Neutron Monitoring System," dated February 3, 2009. (ADAMS Accession No. ML083440681)
Pursuant to Monticello Nuclear Generating Plant (MNGP) Technical Specification (TS) 5.6.3, "Core Operating Limits Report (COLR)," the Northern States Power Company - a Minnesota corporation (NSPM), is providing the MNGP COLR for Cycle 25. In addition to providing the associated changes reflective of the fuel installed this refueling outage (RFO) and associated core design, this COLR also reflects changes related to installation of a Power Range Neutron Monitoring System (PRNMS)
(Reference 1).
Information related to the prior Option I-D stability solution has been completely replaced with that required for implementation of the Option Ill long-term stability solution which utilizes the Oscillating Power Range Monitoring (OPRM) approach implemented on the General Electric-Hitachi NUMAC PRNMS computer platform. This includes information associated with the cycle-specific OPRM Period Based Detection Algorithm (PBDA) setpoints and the Option Ill Backup Stability Protection (BSP) Region definition.
The COLR provides the cycle-specific values of limits established applying U.S. Nuclear Regulatory Commission (NRC) approved methodologies such that the applicable limits of the plant safety analysis are met. TS 5.6.3 requires the COLR, including any mid-cycle revisions or supplements, be provided to the NRC upon issuance.
Summaw of Commitments No new commitments or changes to any existing commitments are proposed by this letter.
2807 West County Road 75 e Monticello, Minnesota 55362-9637 Telephone: 763.295.51 51 Fax: 763.295.1454
Document Control Desk L-MT-09-056 Page 2 of 2 f perjury that the foregoing is true and correct. Executed on onticello Nuclear Generating Plant
~ o r t h q nStates Power Company - Minnesota Enclosure cc: Administrator, Region Ill, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC Minnesota Department of Commerce
ENCLOSURE l MONTICELLO NUCLEAR GENERATING PLANT CYCLE 25 CORE OPERATING LIMITS REPOM MAD-MN-020, Revision 0
MontPeello Nuelear Generating Plant Cycle 25 Core OpbratPng Limits Report Date: 2 7 ~ 2 0 0 9 ,
Verified E& Dabs: 3- w:.f39 Revtewed By: 0ate: 3-24-04 '
Sup&vkm, IR@actw I
Engineering Monffcello
~ u p e d rNuclear
, hdysls and Desfgn
1.0 Core Operating Limits Report (COLR)
This Core Operating Limits Report for Monticello Nuclear Generating Plant Cycle 25 is prepared in accordance with the requirements of Technical Specification 5.6.3. The core operating limits are developed using NRC approved methodology (References 1, 3, 4, and lo), and are established such that all applicable thermal limits of the plant safety analysis are met.
The SLMCPR of 1. I 0 was used for two-loop operation for all fuel types in Cycle 25. The SLMCPR for single loop operation is 1.12. These values are consistent with the values specified in Reference 2.
Due to the implementation of the Option Ill Stability Long Term Solution Oscillating Power Range Monitoring (OPRM) System for Cycle 25, this report no longer includes the Option I D stability exclusion region definition, buffer region definition, and power distribution limits previously required by Amendment 97 of Monticello's operating license approved by the NRC in Reference 10. This information has been replaced with the Option Ill Backup Stability Protection (BSP) Region definitions for use in providing backup thermal hydraulic stability protection when the Option Ill OPRM system is declared INOPERABLE.
In addition to the BSP region definitions, the approved operating license amendment for the implementation of the OPRM System (Reference 27) requires that the OPRM Period Based Detection Algorithm (PBDA) setpoints for each cycle be presented in the COLR, along with the Single Loop Operation (SLO) delta W Allowed Value adjustment to the APRM Simulated Thermal Power - High flow biased scram setpoint. These parameters are presented in the COLR for the first time in Cycle 25.
2.0 References I.O General Electric Standard Application for Reactor Fuel (GESTAR-Ilk NEDE-24011-P-A-16, October 2007.
2.0 Supplemental Reload Licensinu Report for Monticello Reload 24, Cvcle 25, 0000-0083-9607-SRLR, Revision 1, March 2009.
3.0 General Electric Licensing Topical Report ODYSY Application for Stabilitv Licensinu Calculations, NEDC-32992-P-A, DRF A13-00426-00, July 2001.
4.0 Reactor Stabilitv Detect and Suppress Solutions Licensinu Basis Methodolouv for Reload Ap~lications,Licensing Topical Report, NEDO-32465-A, August 1996.
5.0 Fuel Bundle Information Report for Monticello, Reload 24, Cvcle 25, 0000-0083-9607-FBIR, Revision 0, January 2009.
6.0 Letter from M. F. Hammer (NSP) to USNRC dated December 4 1997, Revision 1 to License Amendment Request dated Julv 26, 1996 Sup~ortinathe Monticello Nuclear Generating Plant Rerate Prouram, including attached exhibits.
7.0 Document GE14 Fuel Design Cvcle-Independent Analvsis for Monticello Nuclear Generatina Plant, GE-NE-0000-0013-9576P, GE Nuclear Energy (Proprietary),
March 2003.
8.0 Letter from Les Conner (GNF) to R. J. Rohrer (NMC), dated March 24,2003, Monticello Option B Licensinq Basis, IC.MN.2003.010, Global Nuclear Fuel.
NAD-MN-020, Monticello Cycle 25 COLR, Revision 0 Page 2 of 41
9.0 GE14 Fuel Desiun, Cvcle Independent Transient Analvsis for Monticello Nuclear Generatinq Plant, GE-NE-0000-0014-7048-01P, Rev. 0, March 2003 (GNF Proprietary).
10.0 BWR Owners Group Lonu Term Stabilitv Solution Licensinu Methodolouy, NEDO-31960-A, Licensing Topical Report, November 1995 (including Supplement 1).
11.0 Reactor Lona-Term Stabilitv Solution Option Ill: Licensinu Basis Hot Channel Oscillation Maanitude for Monticello Nuclear Generatinu Plant, GHNE-0000-0073-4167-R2, December 2007.
12.0 Plant-Specific Reuional Mode DlVOM Procedure Guideline, GE-NE-0000-0028-9714-R1, June 2005.
13.0 Backup Stabilitv Protection (BSP) for Inoperable Option Ill Solution, OG-02-0119-260, July 2002.
14.0 Letter from M. F. Hammer (NSP) to USNRC dated July 30,1998, "Supplementary lnformation Regarding the Monticello Power Rerate (TAC No. 96238)", including attachments.
15.0 Letter from Tae Kim (USNRC) to Roger 0 Anderson (NSP), "Monticello Nuclear Generating Plant - Issuance of Amendment Re. Power Uprate Program (TAC No.
M96238)," including enclosures, September 16, 1998.
16.0 Fuel Bundle Information Report for Monticello Nuclear Generatinu Plant, Reload 22, Cvcle 23, 0000-0029-6441-FBIR, Revision 0, (Proprietary), January 2005.
17.0 Fuel Bundle lnformation Report for Monticello Reload 23 Cvcle 24, 0000-0052-4339-FBIR, Revision 0, January 2007.
18.0 Supplemental Reload Licensinu Report for Monticello Reload 23, Cvcle 24, 0000-0052-4339-SRLR, Revision 2, September 2007.
19.0 Supplemental Reload Licensina Report for Monticello Nuclear Generatinu Plant, Reload 22, Cvcle 23, 0000-0029-6441-SRLR, Revision 0, January 2005.
20.0 Supplemental Reload Licensina Report (SRLR) for Monticello Reload 21, Cvcle 22, 0000-0007-8709SRLR-0, Revision 0, March 2003.
21.0 Monticello Nuclear Generatinu Plant, Cvcle 24 Core Operatinu Limits Report NAD-MN-015, Revision I,December 2008.
22.0 Monticello Nuclear Generatinq Plant, Cvcle 23 Core Operatinu Limits Report, NAD-MN-010, Revision 2, September 2006.
23.0 Monticello Operations Manual, Section B.05.01.02-06, Revision 4, Figure 9 "RBM ROD BLOCK Trip Levels", page 11 of 13.
24.0 GE BWR Licensing Report, Averaue Power Ranqe Monitor, Rod Block Monitor, and Technical Specification Improvement (ARTS) Proqrarn for Monticello Nuclear Generation Plant, NEDC-30492-P, Section 4, April 1984.
25.0 GE Services lnformation Letter, Backup Pressure Reuulator, GE SIL No. 614 Revision I,March 15, 1999.
NAD-MN-020, Monticello Cycle 25 COLR, Revision 0 Page 3 of 41
26.0 Nuclear Manaaement Com~anvMonticello Nuclear Generatins Plant Pressure Reaulator Downscale Failure Analvsis, GE-NE-0000-0051-2643-R0,September 2007.
27.0 Letter from Peter S. Tam (USNRC) to Timothy J. O'Connor (Northern States Power Company), "Monticello Nuclear Generating Plant (MNGP) - Issuance Of Amendment Regarding The Power Range Neutron Monitoring System (TAC No.
MD8064),lr dated January 30,2009, NAD Letter Number IC-MN-2009-024.
28.0 GEH-NE-0000-0076-2388-Rl , "Nuclear Management Company, LLC, Monticello Nuclear Generating Plant, PRNM Licensing Setpoints - CLTP Operation",
December 2007.
3.0 Rod Block Monitor Operability Requirements The ARTS Rod Withdrawal Error (RWE) analysis (Reference 2) validated that the following MCPR values provide the required margin for full withdrawal of any control rod during Monticello Cycle 25:
For Power < 90%: MCPR 2 1.75 For Power 2 90%: MCPR 2 1.44 When the core power is less than 90% of rated and the MCPR is less than 1.75, then a limiting control rod pattern exists and the Rod Block Monitor is required to be operable. If the core power is greater than or equal to 90% and the MCPR is less than 1.44, then a limiting control rod pattern exists and the Rod Block Monitor is required to be operable.
Reference:
Technical Specification Table 3.3.2.1 -1 Function I.
4.0 Rod Block Monitor Upscale Trip Setpoint 4.1 Technical Specification Trip Setpoints and Allowable Values Function Trip Setpoint Allowable Values Low Power Range - Upscale (a) s 1201125 of full scale s 120.41125 of full scale Intermediate Power Range - Upscale (b) s 1151125 of full scale s 115.41125 of full scale High Power Range - Upscale (c), (d) s 1101125 of full scale s 110.41125 of full scale A~plicableThermal Power (a) Thermal Power 2 30% and c 65% RTP and MCPR is below the limit specified in Section 3.
(b) Thermal Power 2 65% and c 85% RTP and MCPR is below the limit specified in Section 3.
(c) Thermal Power 2 85% and c 90% RTP and MCPR is below the limit specified in Section 3.
(d) Thermal Power 2 90% RTP and MCPR is below the limit specified in Section 3.
Reference:
Technical Specification Table 3.3.2.1-1 Functions I.a, I.b, and I.c.
The Reference for the "Trip Setpoints" is Reference 23.
The Reference for the "Ailowable Values" is Reference 24.
NAD-MN-020, Monticello Cycle 25 COLR, Revision 0 Page 4 of 41
5.0 Minimum Critical Power Ratio (MCPR) 5.1 Option A The Operating Limit Minimum Critical Power Ratio (OLMCPR) for Option A does not account for scram speeds that are faster than those required by Technical Specifications.
5.1.IOption A OLMCPR for Two Recirculation Loop Operation The Option A OLMCPR shall be determined for two recirculation loop operation as follows:
If core thermal power (P) is r 45% of rated core thermal power, then the Option A OLMCPR for all fuel types is the areater of { I .70
- K(P) from Figure 3) or {MCPR(F) from Figure 41, where 1.70 is the Option A OLMCPR at rated (100%) core thermal power reported in Table 25.
i.e. if P 2 45% rated core thermal power, then Option A OLMCPR limit
= Maximum of 1.70 * {K(P) from Figure 3) or {MCPR(F) from Figure 4).
If core thermal power (P) is < 45% of rated core thermal power, the Option A OLMCPR for all fuel types is obtained from Figure 3.
Reference:
Technical Specification Section 3.2.2.
5.1.2 Option A OLMCPR for Single Recirculation Loop Operation The Option A OLMCPR as defined above for two recirculation loop operation in Section 5.1 .Iis increased by the following adder for single recirculation loop operation:
0.02 AMCPR adder to account for core flow measurement and TIP reading uncertainties.
Reference:
Technical Specification Section 3.2.2.
NAD-MN-020, Monticello Cycle 25 COLR, Revision 0 Page 5 of 41
5.2 Option B Option B does take into account the measured scram speeds that are faster than the Technical Specification requirements, thus reducing the potential consequences of a limiting transient. Calculation of the Option B OLMCPR value as a function of measured scram speeds is described in Section 10.
5.2.1 Option B OLMCPR for Two Recirculation Loop Operation The Option B OLMCPR shall be determined for two recirculation loop operation as follows:
The rated (100%) core thermal power Option B OLMCPR (OLMCPR~;~;, ) is 1.59, and is reported in Table 25. This OLMCPR~;~?,, of 1.59 is modified as described in Section 10 to be a function of the measured scram speeds to yield OLMCPR~;~,, .
Then, if core thermal power (P) is 2 45% of rated core thermal power, the Option B OLMCPR for all fuel types is the greater of:
OLMCPR~;~,, * {K(P) from Figure 3) or {MCPR(F) from Figure 4).
i.e. if P 2 45% rated core thermal power, then Option B OLMCPR limit
= Maximum of {OLMCPR~;~,,
- K(P) from Figure 3) or {MCPR(F) from Figure 4).
If core thermal power (P) is < 45% of rated core thermal power, the Option B OLMCPR for all fuel types is obtained from Figure 3.
Reference:
Technical Specification 3.2.2.
5.2.2 Option B OLMCPR for Single Recirculation Loop Operation The Option B OLMCPR as defined above for two recirculation loop operation in Section 5.2.1 is increased by the following adder for single recirculation loop operation:
0.02 AMCPR adder to account for core flow measurement and TIP reading uncertainties.
Reference:
Technical Specification 3.2.2.
5.3 Pressure Regulator Out of Service (PROOS) Operation Reference 25 GE SIL 614, Revision 1 describes the impact of operation without a backup pressure regulator (also called PROOS). This section provides power dependent MCPR limits when a backup pressure regulator is not operational.
The existing power dependent MAPLHGR and LHGR limits described in Sections 8.1 and 8.2 have been found to be valid (bounding) for operation without a backup pressure regulator (References 26 and 2).
A Pressure Regulator Fails Down-Scale (PRFDS) event without backup pressure regulator was evaluated for Monticello (Reference 26). This event resulted in a more NAD-MN-020, Monticello Cycle 25 COLR, Revision 0 Page 6 of 41
restrictive Power Dependent MCPR limit than required for normal reduced power operation with both pressure regulators operational. Figure 8 provides the required more restrictive power dependent MCPR ARTS limits for powers below 85% and greater than or equal to 45%. For powers greater than or equal to 85% or below 45%, the power dependent MCPR and K(P) ARTS limits provided in Figure 3 are still valid. The existing Pressure Regulator Out of Service limits were confirmed to remain applicable for Cycle 25 (Reference 2).
Figure 8 combines the unchanged limits from Figure 3 along with the more restrictive limits determined in Reference 26 for PROOS operation. Figure 8 should only be used for operation without a backup pressure regulator. Figure 8 is valid for both Option A and Option B OLMCPR limits.
An interim MFLCPR Limit is provided in Figure 9. This limit should only be used if the Gardel thermal limit input has not been modified as described in Sections 5.3.1 or 5.3.2 to account for pressure regulator out of service operation. i.e. Only Figure 8 or Figure 9 should be used to provide the appropriate PROOS limit. These figures should not be utilized in combination.
5.3.1 OLMCPR for Two Recirculation Loop Operation, WITHOUT A BACKUP PRESSURE REGULATOR.
The Option A or B OLMCPR shall be determined for two recirculation loop operation as follows:
The Option A OLMCPR is calculated as shown below for the Option B example with the following exception:
The OLMCPR:;~~ is replaced with the Option A OLMCPR of 1.70.
The Option B OLMCPR is calculated as follows:
The rated (100%) core thermal power Option B OLMCPR ( o L M c P R ~ : ~ )~is~ 1.59, ~
and is reported in Table 25. This OLMCPR~~~~,of 1.59 is modified as described in Section 10 to be a function of the measured scram speeds to yield OLMCP~R ;,;:
Then, if core thermal power (P) is 2 85% of rated core thermal power, the Option B OLMCPR for all fuel types is the greater of:
OLMCP~
R
- ,;; * {K(P) from Figure 8) or {MCPR(F) from Figure 41, i.e. if P 2 85% rated core thermal power, then Option B OLMCPR limit
= Maximum of {OLMCPR~ ;:,
- K(P) from Figure 8) or {MCPR(F) from Figure 4).
If core thermal power (P) is < 85% of rated core thermal power, the OLMCPR for all fuel types is obtained from Figure 8.
NAD-MN-020, Monticello Cycle 25 COLR, Revision 0 Page 7 of 41
5.3.2 OLMCPR for Single Recirculation Loop Operation, WITHOUT A BACKUP PRESSURE REGULATOR The Option A or B OLMCPR as defined previously for two recirculation loop operation in Section 5.3.1 is increased by the following adder for single recirculation loop operation:
0.02 AMCPR adder to account for core flow measurement and TIP reading uncertainties.
6.0 Bower-Flow Map The Power-Flow Operating Map based on analysis to support Cycle 25 is shown in Figures 5, and 6. The Power-Flow Operating Map is consistent with a rated power of 1775 MWth as described in References 6, 14, and 15.
7.0 Approved Analytical Methods NEDE-24011-P-A Rev. 16 "General Electric Standard Application for Reactor Fuel (GESTAR)"
NEDE-24011-P-A-US Rev. 16 "General Electric Standard Application for Reactor Fuel (GESTAR) - Supplement for the United States."
NEDO-31960-A "BWR Owners G~OUD Lona-Term Stabilitv Solution Licensina Methodoloay," Licensing Topical Report, June 1991.
NEDO-31960-A Sup. 1 "BWR Owners Group Lonn-Term Stabilitv Solution Licensina Methodoloav, (Supplement I)," Licensing Topical Report, Supplement I,March 1992.
NEDC-32992P-A General Electric Licensing Topical Report, "ODYSY Application for Stabilitv Licensina Calculations," July 2001.
NEDO-32465-A General Electric Licensing Topical Report, "Reactor Stabilitv Detect and Suppress Solutions Licensina Basis Methodoloav and Reload Applications," August 1996.
NSPNAD-8608-A Rev. 4 "Reload Safetv Evaluation Methods for Application to the Monticello Generatina Plant." October 1995.
NSPNAD-8609-A Rev. 3 "Qualification of Reactor Phvsics Methods for Application to Monticello," October 1995.
NAD-MN-020, Monticello Cycle 25 COLR, Revision 0 Page 8 of 41
8.0 Fuel Rod Heat Generation Rate 8.1 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) as a Function of Exposure The MAPLHGR limits in Tables 1 through 10 are conservative values bounding all fuel lattice types (all natural uranium lattices are excluded) in a given fuel bundle design, and are intended only for use in hand calculations as described in Technical Specification 3.2.1. No channel bow effects are included in the bounding MAPLHGR values in Tables 1 through 10 as there are no reused channels. MAPLHGR limits for each individual fuel lattice for a given bundle design as a function of axial location and average planar exposure are determined based on the approved methodology referenced in Monticello Technical Specification 5.6.3.b and are loaded into the process computer for use in core monitoring calculations.
When and if hand calculations are required:
8.1 .I Two-Recirculation Loop Operation (MAPLHGR)
At rated core thermal power and core flow conditions, the MAPLHGR limit for each fuel bundle design as a function of average planar exposure shall not exceed the bounding limits provided in Tables 1 through 10.
The MAPLHGR limit is adjusted for off-rated core thermal power and core flow conditions by determining the following:
MAPLHGR(P) = MAPFAC(P)
- MAPLHGR limit from Tables 1 through 10.
MAPLHGR(F) = MAPFAC(F)
- MAPLHGR limit from Tables 1 through 10.
where MAPFAC(P) and MAPFAC(F) are determined from Figures 1 and 2, respectively, and where P is the core thermal power in percent of rated, and F is the core flow in percent of rated.
The Technical Specification (TS) MAPLHGR limit is determined as follows:
MAPLHGR (TS) Limit = Minimum{MAPLHGR(P), MAPLHGR(F))
Note that all natural uranium lattices are excluded in Tables 1 through 10.
Straight line interpolation between nearest data points is permitted only within each individual Tables Ithrough 10.
8.1.2 Single Recirculation Loop Operation (MAPLHGR)
When in single recirculation loop operation, perform the following:
8.1.2.1 Perform the action specified in Section 8.1 .Iabove.
8.1.2.2 Separately, apply the single loop operation multiplier to the limiting values of MAPLHGR from Tables Ithrough 10 as follows:
for GE14C: multiplier is 0.90.
8.1.2.3 Select the more limiting (i.e. smaller) value from Sections 8.1.2.1 or 8.1.2.2.
Reference:
Technical Specification 3.2.1, NAD-MN-020, Monticello Cycle 25 COLR, Revision 0 Page 9 of 41
8.2 Linear Heat Generation Rate (LHGR)
The uranium dioxide (U02)and gadolinia LHGR limits as a function of fuel rod peak pellet exposure for each bundle type in Cycle 25 is provided in Tables 11 through 20. The gadolinia LHGR limits in Tables 11 through 20 are bounding gadolinia LHGR limits for all the gadolinia concentrations occurring in each of the bundle types used in Cycle 25. The LHGR limits are fuel rod nodal limits, and are to be applied at every node of the fuel rod including the natural uranium lattices.
The individual LHGR limits for the uranium dioxide and gadolinia fuel rods in each fuel bundle type used in Cycle 25, as a function of axial location and pellet exposure are determined based on the approved methodology referenced in Monticello Technical Specification 5.6.3.b and are loaded into the process computer for use in core monitoring calculations.
The LHGR limits are presented in this report for use when and if hand calculations are performed to demonstrate compliance with Technical Specification 3.2.3.
When and if hand calculations are performed:
8.2.1 Two-Recirculation Loop Operation (LHGR)
At rated core thermal power and core flow conditions, the LHGR limit for each fuel bundle design as a function of peak pellet exposure and fuel pin type shall not exceed the bounding limits provided in Tables I 1 through 20.
The LHGR limit is adjusted for off-rated core thermal power and core flow conditions by determining the following:
LHGR(P) = MAPFAC(P)
- LHGR limit from Tables 11 through 20.
LHGR(F) = MAPFAC(F)
- LHGR limit from Tables 11 through 20.
where the multipliers MAPFAC(P) and MAPFAC(F) are determined from Figures Iand 2, respectively, and where P is the core thermal power in percent of rated, and F is the core flow in percent of rated.
The Technical Specification (TS) LHGR limit is determined as follows:
LHGR TS Limit = Minimum{LHGR(P), LHGR(F))
Note that the LHGR limits are fuel rod nodal limits, and are to be applied at every node of the fuel rod, including the natural uranium lattices. Straight line interpolation between nearest data points is permitted only within each individual Tables 1Ithrough 20.
8.2.2 Single Recirculation Loop Operation (LHGR)
When in single recirculation loop operation, perform the following:
8.2.2.1 Perform the same action specified in Section 8.2.1 above. There are no separate single loop operation specific multipliers applicable to LHGR, i.e. the multipliers from Section 8.2.1 also apply to single recirculation loop operation.
Reference:
Technical Specification Section 3.2.3.
NAD-MN-020, Monticello Cycle 25 COLR, Revision 0 Page 10 of 41
Table 1:
MAPLHGR Limits")
GE14C EDB-2598"': GEl4-PlODNAB393-17GZ100T-145-T6-2598 (formerly EDB-2587)
Average Planar Exposure MAPLHGR Limit GWDIMTU(GWD1STU) (kwlft)"'
Note:
(1) Values in Table 1 are for two recirculation loop operation; see Section 8.1.1.
For single recirculation loop operation, see Section 8.1.2.
(2) Engineering Data Bank (EDB) number, Reference 2.
(3) MAPLHGR limits from Reference 2.
NAD-MN-020, Monticello Cycle 25 COLR, Revision 0 Page 11 of 41
Table 2:
MAPLHGR ~irnits)
(formerly EDB-2588)
Average Planar Exposure MAPLHGR Limit GWDIMTU (GWDISTU) (kwlft) (3' Note:
(1) Values in Table 2 are for two recirculation loop operation; see Section 8.1.1.
For single recirculation Ioop operation, see Section 8.1.2.
(2) Engineering Data Bank (EDB) number, Reference 2.
(3) MAPLHGR limits from Reference 2.
NAD-MN-020, Monticello Cycle 25 COLR, Revision 0 Page 12 of 41
Table 3:
MAPLHGR Limits)
GE14C EDB-2824"': GE14-PlODNAB392-16GZ100T-145-T6-2824 Average Planar Exposure MAPLHGR Limit GWDIMTU (GWDISTU) (kwlft) '3' 0.00 ( 0.00) 8.33 0.22 ( 0.20) 8.37 1.10 ( 1.00) 8.44 2.20 ( 2.00) 8.54 3.31 (3.00) 8.63 4.41 ( 4.00) 8.73 5.51 ( 5.00) 8.84 6.61 ( 6.00) 8.93 7.72 ( 7.00) 9.02 8.82 ( 8.00) 9.11 9.92 ( 9.00) 9.21 11.02 (10.00) 9.32 12.13 (1 1.00) 9.44 13.23 (12.00) 9.56 14.33 (13.00) 9.50 15.43 (14.00) 9.50 16.53 (15.00) 9.52 18.74 (17.00) 9.54 22.05 (20.00) 9.56 27.56 (25.00) 9.60 33.07 (30.00) 9.41 38.58 (35.00) 8.91 41.33 (37.49) 8.67 44.09 (40.00) 8.43 49.60 (45.00) 7.90 55.12 (50.00) 7.39 60.63 (55.00) 5.79 63.16 (57.30) 4.68 63.50 (57.61) 4.84 63.59 (57.68) 4.91 63.72 (57.81) 4.90 63.76 (57.85) 4.73 Note:
(1) Values in Table 3 are for two recirculation loop operation; see Section 8.1.1.
For single recirculation loop operation, see Section 8.1.2.
(2) Engineering Data Bank (EDB) number, Reference 2.
(3) MAPLHGR Data Reference 2.
NAD-MN-020, Monticello Cycle 25 COLR, Revision 0 Page 13 of 41
Table 4 MAPLHGR Limits")
GE14C EDB-2480"': GE14-P10DNAB391-14G'&100T-145-T6-2480 (formerly EDB-2427) 60.63 (55.00) 63.50 (57.61) 63.72 (57.81) 63.79 (57.87) 64.37 (58.40) 4.90 64.39 (58.42)
Note:
(1) Values in Table 4 are for two recirculation loop operation; see Section 8.1 .l.
For single recirculation loop operation, see Section 8.1.2.
(2) Engineering Data Bank (EDB) number, Reference 2.
(3) MAPLHGR Data Reference 2.
NAD-MN-020, Monticello Cycle 25 COLR, Revision 0 Page 14 of 41
Table 5:
MLAPLHGR Limits")
GE14C EDB-2932"): GE14-P10DNAB392-17GZ-100T-145-T6-2932 Average Planar Exposure MAPLHGR Limit GWD/MTU (GWDISTU) (kWlft) ")
64.44 (58.46) 4.90 64.48 (58.50) 4.89 Note:
(1) Values in Table 5 are for two recirculation loop operation; see Section 8.1.1.
For single recirculation loop operation, see Section 8.1.2.
(2) Engineering Data Bank (EDB) number, Reference 2.
(3) MAPLHGR Data Reference 2.
NAD-MN-020, Monticello Cycle 25 COLR, Revision 0 Page 15 of 41
Table 6:
MAPLHGR ~imits"'
Average Planar Exposure MAPLHGR Limit GWDJMTU (GWDISTU) (kwlft) "'
Note:
(1) Values in Table 6 are for two recirculation loop operation; see Section 8.1 .l.
For single recirculation loop operation, see Section 8.1.2.
(2) Engineering Data Bank (EDB) number, Reference 2.
(3) MAPLHGR Data Reference 2.
NAD-MN-020, Monticello Cycle 25 COLR, Revision 0 Page 16 of 41
Table 7:
MAPLHGR Limits")
GE14C EDB-3100"): GE14-P10DNAB424-14GZ100T-145-T6-3100 Average Planar Exposure MAPLHGR Limit GWDIMTU (GWDISTU) (kwlft) ")
Note:
(1) Values in Table 7 are for two recirculation loop operation; see Section 8.1.1.
For single recirculation loop operation, see Section 8.1.2.
(2) Engineering Data Bank (EDB) number, Reference 2.
(3) MAPLHGR Data Reference 2.
NAD-MN-020, Monticello Cycle 25 COLR, Revision 0 Page 17 of 41
Table 8:
RlAPLNGR Limits)
GE14C EDB-3101'~':GE14-P10DNAB375-16GZ-100T-145-T6-3101 Average Planar Exposure MAPLHGR Limit GWDlMTU (GVVDISTU) (kW/ft) 0, 0.00 ( 0.00) 8.18 0.22 ( 0.20) 8.24 1.10 ( 1.00) 8.32 2.20 ( 2.00) 8.39 3.3 1 ( 3.00) 8.45 4.41 ( 4.00) 8.52 5.51 ( 5.00) 8.58 6.61 ( 6.00) 8.65 7.72 ( 7.00) 8.72 8.82 ( 8.00) 8.80 9.92 ( 9.00) 8.89 11.02 (10.00) 9.00 12.13 (11.00) 9.11 13.23 (12.00) 9.23 14.33 (13.00) 9.21 15.43 (14.00) 9.22 16.53 (15.00) 9.26 17.64 (16.00) 9.29 18.74 (17.00) 9.3 1 19.84 (18.00) 9.32 20.94 (19.00) 9.33 22.05 (20.00) 9.35 23.15 (21.00) 9.36 24.25 (22.00) 9.37 25.35 (23.00) 9.38 26.46 (24.00) 9.39 27.56 (25.00) 9.41 33.07 (30.00) 9.15 -
38.58 (35.00) 8.66 41.33 (37.49) 8.44 44.09 (40.00) 8.21 49.60 (45.00) 7.77 55.12 (50.00) 7.32 60.63 (55.00) 5.19 61.88 (56.14) 4.64 61.93 (56.19) 4.87 62.00 (56.24) 4.87 62.53 (56.72) 4.69 Note:
(1) Values in Table 8 are for two recirculation loop operation; see Section 8.1.1.
For single recirculation loop operation, see Section 8.1.2.
(2) Engineering Data Bank (EDB) number, Reference 2.
(3) MAPLHGR Data Reference 2.
NAD-MN-020, Monticello Cycle 25 COLR, Revision 0 Page 18 of 41
Table 9:
MAPLHGR ~ i m i t s " '
,4CEDB-3102'~':GEl4-PlODNAB392-16GZ100T-145-T6-3102 Average Planar Exposure MAPLHGR Limit GWDIMTU (GWDISTU) (kW/ft) (3) 0.00 ( 0.00) 8.33 0.22 ( 0.20) 8.37 1.10 ( 1.00) 8.44 2.20 ( 2.00) 8.53 3.31 ( 3.00) 8.63 4.41 ( 4.00) 8.73 5.5 1 ( 5.00) 8.83 6.61 ( 6.00) 8.92 7.72 ( 7.00) 9.00 8.82 ( 8.00) 9.09 9.92 ( 9.00) 9.19 11.02 (10.00) 9.30 12.13 (11.00) 9.42 13.23 (12.00) 9.51 14.33 (13.00) 9.44 15.43 (14.00) 9.44 16.53 (15.00) 9.47 17.64 (16.00) 9.50 18.74 (17.00) 9.52 19.84 (18.00) 9.53 20.94 (19.00) 9.54 23.15 (21.00) 9.56 24.25 (22.00) 9.57 25.35 (23.00) 9.57 26.46 (24.00) 9.59 27.56 (25.00) 9.60 33.07 (30.00) 9.39 38.58 (35.00) 8.89 41.33 (37.49) 8.65 44.09 (40.00) 8.41 49.60 (45.00) 7.95 55.12 (50.00) 7.46 60.63 (55.00) 5.71 1
Note:
63.00 (57.16) 63.41 57.53 63.50 57.61 63.52 57.62 63.66 57.75 4.67 (1) Values in Table 9 are for two recirculation loop operation; see Sectic For single recirculation loop operation, see Section 8.1.2.
(2) Engineering Data Bank (EDB) number, Reference 2.
(3) MAPLHGR Data Reference 2.
NAD-MN-020, Monticello Cycle 25 COLR, Revision 0 Page 19 of 41
Table 10:
MAPLHGR Limits"'
Average PIanar Exposure MAPLHGR Limit GWDIMTU (GWDISTU) (kW/ft) (3) 0.00 ( 0.00) 8.72 0.22 ( 0.20) 8.75 1.10 ( 1.00) 8.79 2.20 ( 2.00) 8.85 3.31 (3.00) 8.92 4.41 (4.00) 8.98 5.51 (5.00) 9.05 6.61 ( 6.00) 9.11 7.72 ( 7.00) 9.17 8.82 ( 8.00) 9.24 9.92 ( 9.00) 9.30 11.02 (10.00) 9.37 12.13 (11.00) 9.46 13.23 (12.00) 9.49 14.33 (13.00) 9.43 15.43 (14.00) 9.45 16.53 (15.00) 9.48 17.64 (16.00) 9.5 1 18.74 (17.00) 9.52 19.84 (18.00) 9.53 20.94 (19.00) 9.54 22.05 (20.00) 9.55 23.15 (21.00) 9.56 24.25 (22.00) 9.57 25.35 (23.00) 9.58 26.46 (24.00) 9.59 27.56 (25.00) 9.60 33.07 (30.00) 9.40 38.58 (35.00) 8.89 41.33 (37.49) 8.65 44.09 (40.00) 8.42 49.60 (45.00) 7.96 55.12 (50.00) 7.46 60.63 (55.00) 5.71 62.99 (57.14) 4.67 63.50 (57.61) 4.79 63.60 (57.70) 4.75 63.61 (57.71) 4.74 63.64 (57.73) 4.73 Note:
(1) Values in Table 10 are for two recirculation loop operation; see Section 8.1.1.
For single recirculation loop operation, see Section 8.1.2.
(2) Engineering Data Bank (EDB) number, Reference 2.
(3) MAPLHGR Data Reference 2.
NAD-MN-020, Monticello Cycle 25 COLR, Revision 0 Page 20 of 41
Table 11 U02IGd Thermal Mechanical LNGR Limits (Reference 5)
Bundle Type: GE14-P10DNAB393-17GZ-1OOT-145-T6-2598 (GEl4C)
Engineering Data Bank (EDB) Bundle Number ': 2598 (formerly EDB-2587)
Peak Pellet Exposure U02LHGR Limit Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit GWdIMT (GWDIST) (kWlft) G W m T (GWDIST) (kwlft) 0.00 (0.00) 13.40 0.00 (0.00) 12.26 70.00 (63.50) 67.07 (60.84) 4.57 Notes:
- 1. Reference 5.
- 2. Applicable multipliers per Section 8.2 will be applied to the data in this table for two recirculation loop and single recirculation loop operations.
Table 12 U02lGd Thermal Mechanical LNGR Limits (Reference 5)
Bundle Type: GE14-P10DNAB393-17GZ-100T-145-T6-2599 (GE14C)
Engineering Data Banlc (EDB) Bundle Number ': 2599 (formerly EDB-2588)
Peak Pellet Exposure U02 LHGR Limit Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit G W m T (GWDIST) (kwlft) G W M T (G'WDIST) (kWlft) 0.00 (0.00) 13.40 0.00 (0.00) 12.26 16.00 (14.51) 13.40 13.53 (12.28) 12.26 63.50 (57.61) 8.00 60.63 (55.00) 7.32 70.00 (63.50) 5.00 67.07 (60.84) 4.57 Notes:
- 1. Reference 5.
- 2. Applicable multipliers per Section 8.2 will be applied to the data in this table for two recirculation loop and single recirculation loop operations.
NAD-MN-020, Monticello Cycle 25 COLR, Revision 0 Page 21 of 41
Table 13 U02lGd Thermal Mechanical LHGR Limits (Reference 5)
Bundle Type: GE14-P10DNAB392-16GZ-1OOT-145-T6-2824 (GE14C)
Engineering Data Bank (EDB) Bundle Number ': 2824 (no former EDB designation)
Notes:
- 1. Reference 5.
- 2. Applicable multipliers per Section 8.2 will be applied to the data in this table for two recirculation loop and single recirculation loop operations.
Table 14 U02lGd Thermal Mechanical LHGR Limits (Reference 5)
Bundle Type: GE14-P1ODNAB391-14GZ-100T-145-T6-2480 (GE14C)
Engineering Data Bank (EDB) Bundle Number ': 2480 (formerly EDB-2427)
Peak Pellet Exposure U02 LHGR Limit Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit GWd/MT (GWDIST) (kW1ft) GWd/MT (GWDIST) (kwlft) 0.00 (0.00) 13.40 0.00 (0.00) 12.52 16.00 (14.51) 13.40 13.66 (12.39) 12.52 63.50 (57.61) 8.00 61.12 (55.44) 7.47 70.00 (63.50) 5.00 67.61 (61.33) 4.67 Notes:
- 1. Reference 5.
- 2. Applicable multipliers per Section 8.2 will be applied to the data in this table for two recirculation loop and single recirculation loop operations.
NAD-MN-020, Monticello Cycle 25 COLR, Revision 0 Page 22 of 41
Table 15 U(P2lGd Thermal Mechanical LHGR Limits (Reference 5)
Bundle Type: GE14-P1ODNAB392-16GZ-lOOT-145-T6-293 1 (GE14C)
~ n ~ i n e e rData i n ~ Bank (EDB) Bundle Number l: 293 1 (no former EDB designation)
LHGR Limit Notes:
- 1. Reference 5.
- 2. Applicable multipliers per Section 8.2 will be applied to the data in this table for two recirculation loop and single recirculation loop operations.
Table 16 UQ2lGd Thermal Mechanical LHGR Limits (Reference 5)
Bundle Type: GE14-P10DNAB392-17GZ-100T-145-T6-2932 (GE14C)
Engineering Data Bank (EDB) Bundle Nurnber ': 2932 (no former EDB designation)
LHGR Limit Notes:
- 1. Reference 5.
- 2. Applicable multipliers per Section 8.2 will be applied to the data in this table for two recirculation loop and single recirculation loop operations.
NAD-MN-020,Monticello Cycle 25 COLR, Revision 0 Page 23 of 41
Table 17 U02lGd Thermal Mechanical LNGR Limits (Reference 5)
Bundle Type: GE 14-P1ODNAB424-14GZ-100T-145-T6-3100 (GE 14C)
Engineering Data Bank (EDB) Bundle Number ': 3 100 (no former EDB designation)
Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit GWEVMT (GWDJST) (kwlft)
Notes:
- 1. Reference 5.
- 2. Applicable multipliers per Section 8.2 will be applied to the data in this table for two recirculation loop and single recirculation loop operations.
Table 18 U02/Gd Thermal Mechanical LNGR Limits (Reference 5)
Bundle Type: GE14-P10DNAB375-16GZ-100T-145-T6-3 101 (GE14C)
Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit GWEVMT (GWDIST) (kwlft) 63.50 (57.61) 8.00 60.17 (54.59) 7.16 70.00 (63.50) 5.00 66.57 (60.39) 4.48 Notes:
- 1. Reference 5.
- 2. Applicable multipliers per Section 8.2 will be applied to the data in this table for two recirculation loop and single recirculation loop operations.
NAD-MN-020, Monticello Cycle 25 COLR, Revision 0 Page 24 of 41
Table 19 U0216d Thermal Mechanical LMGR Limits (Reference 5)
Bundle Type: GE14-P10DNAB392-16GZ-1OOT-145-T6-3 102 (GE14C)
Engineering Data Bank (EDB) Bundle Number l: 3 102 (no former EDB designation)
Notes:
- 1. Reference 5.
- 2. Applicable multipliers per Section 8.2 will be applied to the data in this table for two recirculation loop and single recirculation loop operations.
Table 20 U021Gd Thermal Mechanical LNGR Limits (Reference 5)
Bundle Type: GE14-P10DNAB391-12GZ-100T-145-T6-3 103 (GE14C)
Engineering Data Bank (EDB) Bundle Number l: 3 103 (no former EDB designation)
Peak Pellet Exposure U02 LHGR Limit Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit GWd/MT (GWDIST) (kwlft) 0.00 (0.00) 13.40 0.00 (0.00) 12.00 16.00 (14.51) 13.40 13.42 (12.17) 12.00 63.50 (57.61) 8.00 60.17 (54.59) 7.16 70.00 (63.50) 5.00 66.57 (60.39) 4.48 Notes:
- 1. Reference 5.
- 2. Applicable multipliers per Section 8.2 will be applied to the data in this table for two recirculation loop and single recirculation loop operations.
NAD-MN-020, Monticello Cycle 25 COLR, Revision 0 Page 25 of 41
9.0 Core Stability Requirements Stabilitv Option Ill Solution For Cycle 25, Monticello has implemented the BWR Owners Group Long Term Stability Solution Option Ill using the Oscillation Power Range Monitor (OPRM) as described in References 4 and 10. The plant specific Hot Channel Oscillation Magnitude (HCOM)
(Reference 11) and other cycle specific stability parameters are used in the Cycle 25 Option Ill Stability Evaluation, which is documented in Reference 2. A Backup Stability Protection (BSP) evaluation is also documented in Reference 2 and is used in the event that the Option Ill OPRM system is declared INOPERABLE, The following Option Ill OPRM stability setpoint determination and the implementation of the associated BSP Regions shown in Figures 5 and 6 provide the stability licensing bases for Monticello Cycle 25.
Option Ill OPRM S e t ~ o i n t s A reload Option Ill evaluation has been performed in accordance with the licensing methodology described in Reference 4. The stability based Operating Limit Minimum Critical Power Ratio (OLMCPR) is determined for two conditions as a function of OPRM amplitude setpoint. The two conditions evaluated are: ( I ) a postulated oscillation at 45%
rated core flow quasi steady-state operation (SS), and (2) a postulated oscillation following a two recirculation pump trip (2PT) from the limiting rated power operating state point.
The OPRM-setpoint-dependentOLMCPR(SS) and OLMCPR(2PT) values are calculated for Cycle 25 in accordance with the BWROG regional mode DlVOM guidelines described in Reference 12. The Cycle 25 Option Ill evaluation provides adequate protection against violation of the Safety Limit MCPR (SLMCPR) for the two postulated reactor instability events as long as the plant OLMCPR is equal to or greater than OLMCPR(SS) and OLMCPR(2PT) for the selected OPRM setpoint in Table 22.
The relationship between the OPRM Successive Confirmation Count Setpoint and the OPRM Amplitude Setpoint is provided in Reference 4 and Table 21. For intermediate OPRM Amplitude Setpoints, the corresponding OPRM Successive Confirmation Count Setpoints have been obtained by using linear interpolation.
The OPRM setpoints for Two Loop Operation (TLO) are conservative relative to Single Loop Operation (SLO) and are, therefore bounding.
NAD-MN-020, Monticello Cycle 25 COLR, Revision 0 Page 26 of 41
Table 21 Relationship Between OPRM Successive Confirmation Count Setpoint and OPRM Amplitude Setpoint Table 22 OPRM Setpoint Versus OLMCPR 1.394 1.285 1.421 I.311 1.450 1.337 OLMCPR Acceptance Criteria The OPRM Period Based Detection Algorithm (PBDA) instrumentation setpoints for use in Technical Specification LC0 3.3.1 .ITable 3.3.1 .I-1 Function 2f shall not exceed the following:
Confirmation Count Setpoint: 16 Amplitude Setpoint: 1.15 NAD-MN-020, Monticello Cycle 25 COLR, Revision 0 Page 27 of 41
Backup Stabilitv Protection Reqions The Backup Stability Protection (BSP) regions are shown in Figure 5, and are given in greater detail in Figure 6. The BSP regions are an integral part of the Tech Spec required alternative method to detect and suppress thermal hydraulic instability oscillations in that they identify areas of the powerlflow map where there is an increased probability that the reactor core could experience a thermal hydraulic instability.
Regions are identified that are either excluded from planned entry and continued operation (Scram Region), or where planned entry is not permitted unless specific operating restrictions are met and specific actions are required to be taken to immediately leave the region following inadvertent or forced entry (Controlled Entry Region). The boundaries of these regions are established on a cycle specific basis based upon core decay ratio calculations performed using NRC approved methodology (Reference 3).
The BSP regions are only applicable when the Upscale Trip function of the OPRM is INOPERABLE. The BSP region boundaries were calculated for Monticello Cycle 25 for nominal feedwater temperature conditions. The endpoints of the regions are defined in Table 23. The region boundaries shown in Figures 5 and 6 are defined using the Generic Shape Function (GSF), which is described in Reference 13.
Table 23 Cycle 25 BSP Region lntercepts for Normal Feedwater Temperature Region Boundary Power Core Flow Core DR Highest Intercepts (%) (%) Channel DR A1 63.8 40.0 ~0.798 ~0.255 B1 48.1 33.8 ~0.799 ~0.279 A2 72.8 50.0 ~0.798 ~0.241 B2 32.3 31.2 ~0.799 ~0.081 Actions For Entrv lnto Scram Reaion Immediate manual scram upon determination that the region has been entered. If entry is unavoidable, early scram initiation is appropriate.
Actions For Entrv lnto Controlled Entrv Reaion If entry is inadvertent or forced, immediately exit from region. The region can be exited by control rod insertion or core flow increase. Increasing the core flow by restarting an idle recirculation pump is not an acceptable method of exiting the region.
Deliberate entry into the Controlled Entry Region requires compliance with at least one of the stability controls outlined below:
- 1. Maintain core average boiling boundary (BB) 2 4.0 feet.
- 2. Maintain core decay ratio (DR) < 0.6 as calculated by an on-line stability monitor.
- 3. Continuous dedicated monitoring of real time control room neutron monitoring instrumentation with manual scram required upon indication of a reactor instability induced power oscillation.
NAD-MN-020, Monticello Cycle 25 COLR, Revision 0 Page 28 of 41
Caution is required whenever operating near the Controlled Entry Region boundary (i.e., within approximately 10% of core power or core flow), and it is recommended that the amount of time spent operating near this region be minimized.
Reference:
Technical Specification 3.3.1 .I 10.0 Scram Time Dependence The Technical Specification Option A (no scram times dependence) OLMCPR can be found in Section 5 of this report. If the Option B scram time dependence option is preferred, then the procedure listed in sections 10.1 may be used.
iO.1 Technical Specification Scram Time Dependence Technical Specification 3.1.4 and Table 3.1.4-1 provide the scram insertion time versus position requirements for continued operations. Technical Specification Surveillance Requirements SR 3.1.4.1 - SR 3.1.4.4 provides the surveillance requirements for the CRDs. Data from testing of the CRDs, or from an unplanned scram, is summarized in Surveillance Test 0081.
Using this cycle specific information, values of Tave can be calculated in accordance with the equation below for the notch 36 position.
The Equation (1) used to calculate the average of all the scram data generated to date in the cycle is:
where: n = the number of surveillance tests performed to date in the cycle; 2N,=
i=l total number of active control rods measured to date in the cycle; and n sum of the scram times to the 36th notch position of all active rods NiTi = measured to date in the cycle to comply with the Technical Specification i=l surveillance requirements SR 3.1.4.1, SR 3.1.4.2, SR 3.1.4.3, SR 3.1.4.4.
NAD-MN-020, Monticello Cycle 25 COLR, Revision 0 Page 29 of 41
The average scram time, T,, is tested against the analysis mean using the following equation:
%ve ZB where:
The parameters p and o are the mean and standard deviation of the distribution of the average scram insertion time to notch 36 position in the ODYN Option B analysis (Table 24), and Nl =: number of active control rods tested at BOC.
Table 24 GEMINI Methods, CRD Notch Position for ZB Determination If the cycle average scram time satisfies the Equation 2 criteria, continued plant operation under the ODYN Option B operating limit minimum critical power ratio (OLMCPR) for pressurization events is permitted. If not, the OLMCPR for pressurization events must be re-established, based on linear interpolation between the Option B and Option A OLMCPRs.
Note that Option B has an OLMCPR applicable to two recirculation loop operation, and an OLMCPR applicable to single recirculation loop operation. The Option B OLMCPR value for single recirculation loop operation is 0.02 greater than the Option B OLMCPR value for two recirculation loop operation.
The equation to establish the new operating limit for pressurization events is given below:
CKMCPR NEW = h%X OLMCPR +
'A -'B
-IJ3 AOLMCPR, OLMCPRmp 1 (4) where:
Tave and 'TB are defined in Equations 1 and 3, respectively; and
'TA = The Technical Specification limit on scram time to notch position 36 .
(Technical Specification Table 3.1.4-1 at notch position 36)
AOLMCPR = the difference between the Option A OLMCPR and the Option B OLMCPR reported in Table 25.
NAD-MN-020, Monticello Cycle 25 COLR, Revision 0 Page 30 of 41
Table 25 Cycle OLMCPR Values
- 1. The Turbine Trip with Bypass transient will be used as the Minimum OLMCPR transient for Option B Analysis.
- 2. All the OLMCPR values reported in Table 25 are for two recirculation loop operation.
- 3. For Options A and B, the OLMCPR value for single recirculation loop operation is 0.02 greater than the OLMCPR value for two recirculationloop operation.
Sample Calculation:
Assume two recirculation loop operation.
If T,, is 0.820 seconds (scram time test) and TB (as calculated with equation 3) is 0.850 seconds then the criteria from Equation 2 is met and the Option B OLMCPR of I.59 can be used.
If T,, is 0.940 seconds and TB is 0.850 seconds, then Equation 2 is not met and a new Option B OLMCPR must be calculated using Equation 4 above.
The example calculation is as follows:
OLMCPR!,"~~,, = 1.53 (from Table 25 above.)
z,, = 0.940 z, = 0.850 z, = 1.080 (Technical Specification Table 3.1.4-1 at notch position 36)
AOLMCPR = 1.70 - 1.53 = 0.17 (from Table 25 above; assume two recirculation loop operation)
OLMcpR, = 4 . 5 3 + (0.940- 0 . 8 ~ ~
- 0.17,
) 1.59) = 1.60 ; two recirculation loop operation.
1.080- 0.850 Note: If single recirculation loop operation Option B OLMCPR value is desired, add 0.02, i.e. 1.60 + 0.02 = 1.62.
11.0 Turbine Bypass System Response Time The TURBINE BYPASS SYSTEM RESPONSE TIME shall be that time interval from when the main turbine trip solenoid is activated until 80% of the turbine bypass capacity is established.
The TURBINE BYPASS SYSTEM RESPONSE TIME shall be 5 I.Iseconds.
Reference:
Technical Specification 1.I, Surveillance Requirement 3.7.7.3.
d2.0 Shutdown Margin (SDM) Confirmation Technical Specification 3.1.1 requires that the SDM be confirmed for Monticello Cycle 25.
Analytical SDM has been confirmed in the Supplemental Reload Licensing Report (Reference 2, Section 4).
For any mid-cycle core loading changes, the analytical SDM will be re-confirmed, formally documented, and reviewed prior to start-up.
93.0 APRM Simulated Thermal Power - High Delta W Allowable Value The APRM Simulated Thermal Power - High Flow Biased Scram Setpoint Allowable Value shall be:
where:
SsTp= Scram setting in percent of rated thermal power (1775 MWt)
W= Loop recirculation flow rate in percent of rated AW = Difference between two-loop and single-loop effective recirculation flow at the same core flow (AW = 5.4% for single loop operation, AW = 0.0 for two-loop operation)
Reference:
Technical Specification 5.6.3, Technical Specification Amendment 146 Table 3.3.1 .I-1 Function 2.b Footnote (b)
NAD-MN-020, Monticello Cycle 25 COLR, Revision 0 Page 32 of 41
Figure 'I Monticello Cycle 25 Power Dependent MAPLHGR and LHGR Multipliers MARHGRI, = MAFfACp
- MAfXHGRstd For 25% > P: No Therml L i d s Required
-< 50% flow For 25% 5 P < 45%, >50% Flow MAPFACp=O.527+0.00155(P-45%)
For 25% I P < 45%, I 50% Row MAPFACp=O.677+0.00775(P-45%)
For45% 5 P C 100%
MAPFACp=I.O+O.O05224(P-100%)
0.20 1 I
, , 1 , ! , , , , 1 , 1 I
, , 1 , 1 I
, , I 1
I , , , I I
I , , , l , , , ' l, I
, I , I , , I , I , , , I I , , , l , ' , , , I I , , , I I I I 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 POWER (% Rated)
NAD-MN-020, Monticello Cycle 25 COLR, Revision 0 Page 33 of 41
Figure 2 Monticello Cycle 25 Flow Dependent MAPLHGR and LHGR Multipliers MAPFACr = MINIMUM [MFRPDr ,MAPMULTr]
MAPMULTF = 1.0 FOR FLOW> 80%
MAPMULTF = 0.94 FOR FLOW.: 80%
MFRPDr = MINIMUM [I .0 , nF + b]
F = CORE FLOW(% OF RATEDIM 00 0.3 30 40 50 60 70 80 90 100 110 Core Flow (% Rated)
NAD-MN-020, MonticelloCycle 25 COLR, Revision 0 Page 34 of 41
Figure 3 Monticello Cycle 25 Power Dependent K(P) 1 MCPR(P) Limits 20 30 40 50 60 70 80 90 100 110 Power (% rated)
NAD-MN-020, Monticello Cycle 25 COLR, Revision 0 Page 35 of 41
Figure 4 Monticello Cycle 25 Flow Dependent CPR Limits MCPR(F) = MAX(1.23, A(F)
- W(C) 1 100 + B(F))
Max Flow = 107.0 A(F) = -0.602 B(F) = 1.745 1 I ,
20 30 40 50 60 70 80 90 100 110 120 Core Flow (% Rated)
NAD-MN-020, Monticello Cycle 25 COLR, Revision 0 Page 36 of 41
Figure 7 Stability Criterion Map 0.0 0.2 0.4 0.6 0.8 1 .O CHANNEL DECAY RATIO NAD-MN-020, Monticello Cycle 25 COLR, Revision 0 Page 39 of 41
Figure 8 Monticello Cycle 25 Power Dependent K(P) and MCPR(P) Limits for Pressure Regulator Out of Service (PROOS)
I I I I I I I I
I ] Operating Limit MCPR Determination I :
I :
For PC25%: No Thermal Limits Monitoring Required OLMCPR(P). No chanae from Fiqure 3 For 25% I P < 45%, > 50% Flow -
OLMCPR(P) = 2.60 + 0.027(45%-P)
For 25% .:P c 45%. r 50% Flow OLMCPR(P) = 2.12 + 0.0295(45%P)
OLMCPR(P1for PROOS OLMCPRIP) = KlPl
- Operatino Limit MCPR (1001. No chanae 20 30 40 50 60 70 80 90 100 110 Power (% Rated)
NAD-MN-020, Monticello Cycle 25 COLR, Revision 0 Page 40 of 41
Figure 9 Pressure Regulator Out Of Service Interim MFLCPR LIMIT 50 60 70 Power (% Rated)
The plot is valid for Option A & B scram times.
The limit is not dependent on core flow.
NAD-MN-020, Monticello Cycle 25 COLR, Revision 0 Page 41 of 41