L-MT-07-033, Submittal of the Core Operating Limits Report for Cycle 24

Submittal of the Core Operating Limits Report for Cycle 24

ML071240104
Person / Time
Site:	Monticello
Issue date:	05/03/2007
From:	Conway J Nuclear Management Co
To:	Document Control Desk, NRC/NRR/ADRO
References
L-MT-07-033 NAD-MN-015, Rev 0
Download: ML071240104 (33)

Text

Monticello Nuclear Generatina Plant Committed to Operated by Nuclear Management Company, LLC May 3,2007 L-MT-07-033 Technical Specification 5.6.3 10 CFR 50.46(a)(3)

U.S. Nuclear Regulatory Commission ATTN: Document Control desk Washington, DC 20555 Monticello Nuclear Generating Plant Docket 50-263 License No. DPR-22 Submittal of the Core Operating Limits Report for Cycle 24

Reference:

1) Letter from NMC to U.S. NRC, "2004 Report of Changes and Errors in ECCS Evaluation Models," dated December 22, 2004.

Pursuant to Monticello Nuclear Generating Plant (MNGP) Technical Specification 5.6.3, "Core Operating Limits Report (COLR)," the Nuclear Management Company, LLC (NMC), is providing the COLR for Cycle 24. The COLR provides the cycle-specific values of the limits established using NRC approved methodologies such that the applicable limits of the plant safety analysis are met.

Also, annually NMC submits a report of changes and errors in the MNGP Emergency Core Cooling System evaluation models. In the December 22, 2004, report (Reference I), NMC discussed several errors that increased the General Electric (GE) 11 fuel Peak Cladding Temperature and provided reasons why a reanalysis was not required. One reason stated was that the remaining G E l l fuel was scheduled to be discharged at the end of the next cycle, in early 2007. This letter confirms that all GEI 1 fuel has been removed from the MNGP core.

This letter makes no new commitments or changes to any existing commitments.

J MT:~Conway Site Vice President, Mo Nuclear Generating Plant Nuclear Management Company, LLC Enclosure (1) cc: Administrator, Region Ill, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC Minnesota Department of Commerce 2807 West County Road 75 Monticello, Minnesota 55362-9637 Telephone: 763.295.5151 Fax: 763.295.1454

ENCLOSURE 1 MONTICELLO NUCLEAR GENERATING PLANT CYCLE 24 CORE OPERATING LIMITS REPORT NAD-MN-015, Revision 0 31 pages follow

NAD-MN-15, Monticello Cycle 24 COLR, Rev. 0

""9 Committed to Nuclear Excellence Monticello Nuclear Generating Plant Cycle 24 Core Operating Limits Report NAD-MN-015 Revision 0 Prepared By: - /?.A Peter Pankratz Date: 3 07 Senior Engineer Analyst, ~ u c l e a ? ~ n a l ~ and s i s Design Verified By: 2 Date: 3-/C-~u"7 uclear Analysis and Design Reviewed By: Date: 3//P/7

- Monticello Date: 3 - 2 /-cl 7 Ronald Harris Project Manager, Nuclear Analysis and Design NAD-MN-015, Monticello Cycle 24 COLR, Rev. 0 Page 1 of 31

1.0 Core Operating Limits Report (COLR)

This Core Operating Limits Report for Monticello Nuclear Generating Plant Cycle 24 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 and 3),

and are established such that all applicable thermal limits of the plant safety analysis are met.

The SLMCPR of 1.10 was used for two-loop operation for all fuel types in Cycle 24. The SLMCPR for single loop operation is 1.12. These values are consistent with the values specified in Reference 2.

This report includes stability exclusion region definition, buffer region definition, and power distribution limits as required by Amendment 97 of Monticellos operating license approved by the NRC in Reference 10.

2.0 References 1.0 General Electric Standard Application for Reactor Fuel (GESTAR-II), NEDE-24011-P-A-15, September 2005.

2.0 Supplemental Reload Licensing Report for Monticello Reload 23, Cycle 24, 0000-0052-4339-SRLR, Revision 1, March 2007.

3.0 General Electric Licensing Topical Report ODYSY Application for Stability Licensing Calculations, NEDC-32992-P-A, DRF AI3-00426-00, July 2001.

4.0 Fuel Bundle Information Report for Monticello Nuclear Generating Plant, Reload 22, Cycle 23, 0000-0029-6441-FBIR, Revision 0, (Proprietary), January 2005.

5.0 Letter from M. F. Hammer (NSP) to USNRC dated December 4 1997, Revision 1 to License Amendment Request dated July 26, 1996 Supporting the Monticello Nuclear Generating Plant Rerate Program, including attached exhibits.

6.0 Document GE14 Fuel Design Cycle-Independent Analysis for Monticello Nuclear Generating Plant, GE-NE-0000-0013-9576P, GE Nuclear Energy (Proprietary),

March 2003.

7.0 Letter from Les Conner (GNF) to R. J. Rohrer (NMC), dated March 24, 2003, Monticello Option B Licensing Basis, IC.MN.2003.010, Global Nuclear Fuel.

8.0 GE14 Fuel Design, Cycle Independent Transient Analysis for Monticello Nuclear Generating Plant, GE-NE-0000-0014-7048-01P, Rev. 0, March 2003 (GNF Proprietary).

9.0 BWR Owners Group Long Term Stability Solution Licensing Methodology, (Supplement 1), NEDO-31960-A, Licensing Topical Report, Supplement 1, March 1992.

10.0 Letter from Tae Kim (USNRC) to Roger O Anderson (NSP), Monticello Nuclear Generating Plant - Issuance of Amendment Re. Implementation of Boiling Water Reactor Owners Group Option 1-D Core Stability Solution (TAC No. M92947),

including enclosures, September 17, 1996.

NAD-MN-015, Monticello Cycle 24 COLR, Rev. 0 Page 2 of 31

11.0 Letter from M. F. Hammer (NSP) to USNRC dated July 30, 1998, Supplementary Information Regarding the Monticello Power Rerate (TAC No. 96238), including attachments.

12.0 Letter from Tae Kim (USNRC) to Roger O Anderson (NSP), Monticello Nuclear Generating Plant - Issuance of Amendment Re. Power Uprate Program (TAC No.

M96238), including enclosures, September 16, 1998.

13.0 Fuel Bundle Information Report for Monticello Reload 23 Cycle 24, 0000-0052-4339-FBIR, Revision 0, January 2007.

14.0 Supplemental Reload Licensing Report for Monticello Nuclear Generating Plant, Reload 22, Cycle 23, 0000-0029-6441-SRLR, Revision 0, January 2005.

15.0 Supplemental Reload Licensing Report (SRLR) for Monticello Reload 21, Cycle 22, 0000-0007-8709SRLR-0, Revision 0, March 2003.

16.0 Monticello Nuclear Generating Plant, Cycle 21 Core Operating Limits Report NAD-MN-003, Revision 0, November 2001.

17.0 Monticello Nuclear Generating Plant, Cycle 23 Core Operating Limits Report, NAD-MN-010, Revision 2, September 2006.

18.0 Monticello Operations Manual, Section B.05.01.02-06, Revision 4, Figure 9 RBM ROD BLOCK Trip Levels, page 11 of 13.

19.0 GE BWR Licensing Report: Average Power Range Monitor, Rod Block Monitor, and Technical Specification Improvement (ARTS) Program for Monticello Nuclear Generation Plant, NEDC-30492-P, Section 4. April 1984 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 24:

For Power < 90%: MCPR 1.70 For Power 90%: MCPR 1.40 When the core power is less than 90% of rated and the MCPR is less than 1.70, 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 1.40, 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 1.

NAD-MN-015, Monticello Cycle 24 COLR, Rev. 0 Page 3 of 31

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) 120/125 of full scale 120.4/125 of full scale Intermediate Power Range - Upscale (b) 115/125 of full scale 115.4/125 of full scale High Power Range - Upscale (c), (d) 110/125 of full scale 110.4/125 of full scale Applicable Thermal Power (a) Thermal Power 30% and < 65% RTP and MCPR is below the limit specified in Section 3.

(b) Thermal Power 65% and < 85% RTP and MCPR is below the limit specified in Section 3.

(c) Thermal Power 85% and < 90% RTP and MCPR is below the limit specified in Section 3.

(d) Thermal Power 90% RTP and MCPR is below the limit specified in Section 3.

Reference:

Technical Specification Table 3.3.2.1-1 Functions 1.a, 1.b, and 1.c.

The Reference for the Trip Setpoints is Reference 18.

The Reference for the Allowable Values is Reference 19.

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.

5.1.1 Option 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 45% of rated core thermal power, then the Option A OLMCPR for all fuel types is the greater of {1.70

• K(P) from Figure 3} or {MCPR(F) from Figure 4}, where 1.70 is the Option A OLMCPR at rated (100%) core thermal power reported in Table 16.

i.e. if P 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 5.1.1 is increased by the following adder for single recirculation loop operation:

0.02 MCPR adder to account for core flow measurement and TIP reading uncertainties.

Reference:

Technical Specification Section 3.2.2.

NAD-MN-015, Monticello Cycle 24 COLR, Rev. 0 Page 4 of 31

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:

100%

The rated (100%) core thermal power Option B OLMCPR ( OLMCPR OptionB ) is 1.57, 100%

and is reported in Table 16. This OLMCPR OptionB of 1.57 is modified as described in New Section 10 to be a function of the measured scram speeds to yield OLMCPR OptionB .

Then, if core thermal power (P) is 45% of rated core thermal power, the Option B OLMCPR for all fuel types is the greater of:

New OLMCPR OptionB * {K(P) from Figure 3} or {MCPR(F) from Figure 4},

i.e. if P 45% rated core thermal power, then Option B OLMCPR limit New

= Maximum of { OLMCPR OptionB

• 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 MCPR adder to account for core flow measurement and TIP reading uncertainties.

Reference:

Technical Specification 3.2.2.

NAD-MN-015, Monticello Cycle 24 COLR, Rev. 0 Page 5 of 31

6.0 Power-Flow Map The Power-Flow Operating Map based on analysis to support Cycle 24 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 5, 11, and 12.

Reference:

Technical Specification 3.4.1.

7.0 Approved Analytical Methods NEDE-24011-P-A Rev. 15 General Electric Standard Application for Reactor Fuel (GESTAR)

NEDE-24011-P-A-US Rev. 15 General Electric Standard Application for Reactor Fuel (GESTAR) - Supplement for the United States.

NEDO-31960-A BWR Owners Group Long-Term Stability Solution Licensing Methodology, Licensing Topical Report, June 1991.

NEDO-31960-A Sup. 1 BWR Owners Group Long-Term Stability Solution Licensing Methodology, (Supplement 1), Licensing Topical Report, Supplement 1, March 1992.

NEDC-32992P-A General Electric Licensing Topical Report, ODYSY Application for Stability Licensing Calculations, July 2001.

NSPNAD-8608-A Rev. 4 Reload Safety Evaluation Methods for Application to the Monticello Generating Plant. October 1995.

NSPNAD-8609-A Rev. 3 Qualification of Reactor Physics Methods for Application to Monticello, October 1995.

NAD-MN-015, Monticello Cycle 24 COLR, Rev. 0 Page 6 of 31

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 7 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 7 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:

8.1.1 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 7.

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 7.

MAPLHGR(F) = MAPFAC(F)

• MAPLHGR limit from Tables 1 through 7.

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 7.

Straight line interpolation between nearest data points is permitted only within each individual Tables 1 through 7.

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 8.1.1 above.

8.1.2.2 Separately, apply the single loop operation multiplier to the limiting values of MAPLHGR from Tables 1 through 7 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-015, Monticello Cycle 24 COLR, Rev. 0 Page 7 of 31

8.2 Linear Heat Generation Rate (LHGR)

The uranium dioxide (UO2) and gadolinia LHGR limits as a function of fuel rod peak pellet exposure for each bundle type in Cycle 24 is provided in Tables 8 through 14. The gadolinia LHGR limits in Tables 8 through 14 are bounding gadolinia LHGR limits for all the gadolinia concentrations occurring in each of the bundle types used in Cycle 24. 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 24, 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 8 through 14.

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 8 through 14.

LHGR(F) = MAPFAC(F)

• LHGR limit from Tables 8 through 14.

where the multipliers 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) 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 8 through 14.

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-015, Monticello Cycle 24 COLR, Rev. 0 Page 8 of 31

Table 1:

MAPLHGR Limits(1)

GE14C EDB-2598(2): GE14-P10DNAB393-17GZ-100T-145-T6-2598 (formerly EDB-2587)

Average Planar Exposure MAPLHGR Limit GWD/MTU(GWD/STU) (kW/ft)(3) 0.00 ( 0.00) 8.14 0.22 ( 0.20) 8.20 1.10 ( 1.00) 8.34 2.20 ( 2.00) 8.47 3.31 ( 3.00) 8.59 4.41 ( 4.00) 8.71 5.51 ( 5.00) 8.84 6.61 ( 6.00) 8.97 7.72 ( 7.00) 9.11 8.82 ( 8.00) 9.23 9.92 ( 9.00) 9.35 11.02 (10.00) 9.47 12.13 (11.00) 9.59 13.23 (12.00) 9.70 14.33 (13.00) 9.80 15.43 (14.00) 9.90 16.53 (15.00) 9.98 18.74 (17.00) 9.98 22.05 (20.00) 9.97 27.56 (25.00) 9.95 33.07 (30.00) 9.83 38.58 (35.00) 9.23 41.33 (37.49) 8.95 44.09 (40.00) 8.66 49.60 (45.00) 8.13 55.12 (50.00) 7.61 60.63 (55.00) 6.26 63.50 (57.61) 4.94 63.59 (57.68) 4.90 63.72 (57.81) 4.89 64.44 (58.46) 4.90 64.47 (58.49) 4.89 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 14.

(3) MAPLHGR limits from Reference 14.

NAD-MN-015, Monticello Cycle 24 COLR, Rev. 0 Page 9 of 31

Table 2:

MAPLHGR Limits(1)

GE14C EDB-2599(2): GE14-P10DNAB393-17GZ-100T-145-T6-2599 (formerly EDB-2588)

Average Planar Exposure MAPLHGR Limit GWD/MTU (GWD/STU) (kW/ft) (3) 0.00 ( 0.00) 8.21 0.22 ( 0.20) 8.26 1.10 ( 1.00) 8.35 2.20 ( 2.00) 8.47 3.31 ( 3.00) 8.59 4.41 ( 4.00) 8.71 5.51 ( 5.00) 8.84 6.61 ( 6.00) 8.97 7.72 ( 7.00) 9.11 8.82 ( 8.00) 9.23 9.92 ( 9.00) 9.35 11.02 (10.00) 9.47 12.13 (11.00) 9.59 13.23 (12.00) 9.70 14.33 (13.00) 9.80 15.43 (14.00) 9.90 16.53 (15.00) 9.98 18.74 (17.00) 9.97 22.05 (20.00) 9.96 27.56 (25.00) 9.94 33.07 (30.00) 9.84 38.58 (35.00) 9.24 41.33 (37.49) 8.95 44.09 (40.00) 8.67 49.60 (45.00) 8.13 55.12 (50.00) 7.62 60.63 (55.00) 6.26 63.50 (57.61) 4.94 63.59 (57.68) 4.90 63.72 (57.81) 4.89 64.46 (58.48) 4.90 64.49 (58.50) 4.89 Note:

(1) Values in Table 2 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 14.

(3) MAPLHGR limits from Reference 14.

NAD-MN-015, Monticello Cycle 24 COLR, Rev. 0 Page 10 of 31

Table 3:

MAPLHGR Limits(1)

GE14C EDB-2824(2): GE14-P10DNAB392-16GZ-100T-145-T6-2824 Average Planar Exposure MAPLHGR Limit GWD/MTU (GWD/STU) (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) 8.54 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 (11.00) 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 14.

(3) MAPLHGR Data Reference 14.

NAD-MN-015, Monticello Cycle 24 COLR, Rev. 0 Page 11 of 31

Table 4 MAPLHGR Limits(1)

GE14C EDB-2480(2): GE14-P10DNAB391-14GZ-100T-145-T6-2480 (formerly EDB-2427)

Average Planar Exposure MAPLHGR Limit GWD/MTU (GWD/STU) (kW/ft) (3) 0.00 ( 0.00) 8.37 0.22 ( 0.20) 8.43 1.10 ( 1.00) 8.54 2.20 ( 2.00) 8.65 3.31 ( 3.00) 8.77 4.41 ( 4.00) 8.90 5.51 ( 5.00) 9.03 6.61 ( 6.00) 9.16 7.72 ( 7.00) 9.27 8.82 ( 8.00) 9.39 9.92 ( 9.00) 9.51 11.02 (10.00) 9.63 12.13 (11.00) 9.75 13.23 (12.00) 9.84 14.33 (13.00) 9.92 15.43 (14.00) 9.98 16.53 (15.00) 10.03 18.74 (17.00) 10.10 22.05 (20.00) 10.20 27.56 (25.00) 10.19 33.07 (30.00) 10.04 38.58 (35.00) 9.44 41.33 (37.49) 9.15 44.09 (40.00) 8.87 49.60 (45.00) 8.33 55.12 (50.00) 7.81 60.63 (55.00) 6.26 63.50 (57.61) 4.95 63.72 (57.81) 4.85 63.79 (57.87) 4.85 64.37 (58.40) 4.90 64.39 (58.42) 4.89 Note:

(1) Values in Table 4 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 14.

(3) MAPLHGR Data Reference 14.

NAD-MN-015, Monticello Cycle 24 COLR, Rev. 0 Page 12 of 31

Table 5:

MAPLHGR Limits(1)

GE14C EDB-2481(2): GE14-P10DNAB391-14GZ-100T-145-T6-2481 (formerly EDB-2428)

Average Planar Exposure MAPLHGR Limit GWD/MTU (GWD/STU) (kW/ft) (3) 0.00 ( 0.00) 8.32 0.22 ( 0.20) 8.37 1.10 ( 1.00) 8.48 2.20 ( 2.00) 8.63 3.31 ( 3.00) 8.75 4.41 ( 4.00) 8.87 5.51 ( 5.00) 8.99 6.61 ( 6.00) 9.11 7.72 ( 7.00) 9.22 8.82 ( 8.00) 9.33 9.92 ( 9.00) 9.44 11.02 (10.00) 9.56 12.13 (11.00) 9.68 13.23 (12.00) 9.79 14.33 (13.00) 9.88 15.43 (14.00) 9.95 16.53 (15.00) 9.84 18.74 (17.00) 9.80 22.05 (20.00) 9.79 27.56 (25.00) 9.79 33.07 (30.00) 9.74 38.58 (35.00) 9.14 41.33 (37.49) 8.87 44.09 (40.00) 8.59 49.60 (45.00) 8.06 55.12 (50.00) 7.56 60.63 (55.00) 6.25 63.50 (57.61) 4.94 63.68 (57.77) 4.86 63.79 (57.87) 4.85 64.30 (58.33) 4.90 64.32 (58.35) 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 14.

(3) MAPLHGR Data Reference 14.

NAD-MN-015, Monticello Cycle 24 COLR, Rev. 0 Page 13 of 31

Table 6:

MAPLHGR Limits(1)

GE14C EDB-2932(2): GE14-P10DNAB392-17GZ-100T-145-T6-2932 Average Planar Exposure MAPLHGR Limit GWD/MTU (GWD/STU) (kW/ft) (3) 0.00 ( 0.00) 8.20 0.22 ( 0.20) 8.24 1.10 ( 1.00) 8.34 2.20 ( 2.00) 8.45 3.31 ( 3.00) 8.58 4.41 ( 4.00) 8.70 5.51 ( 5.00) 8.83 6.61 ( 6.00) 8.96 7.72 ( 7.00) 9.10 8.82 ( 8.00) 9.21 9.92 ( 9.00) 9.33 11.02 (10.00) 9.46 12.13 (11.00) 9.58 13.23 (12.00) 9.69 14.33 (13.00) 9.80 15.43 (14.00) 9.89 16.53 (15.00) 9.97 18.74 (17.00) 9.96 22.05 (20.00) 9.95 27.56 (25.00) 9.93 33.07 (30.00) 9.82 38.58 (35.00) 9.22 41.33 (37.49) 8.94 44.09 (40.00) 8.65 49.60 (45.00) 8.12 55.12 (50.00) 7.59 60.63 (55.00) 6.25 63.50 (57.61) 4.93 63.57 (57.67) 4.90 63.70 (57.79) 4.89 64.44 (58.46) 4.90 64.48 (58.50) 4.89 Note:

(1) Values in Table 6 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-015, Monticello Cycle 24 COLR, Rev. 0 Page 14 of 31

Table 7:

MAPLHGR Limits(1)

GE14C EDB-2931(2): GE14-P10DNAB392-16GZ-100T-145-T6-2931 Average Planar Exposure MAPLHGR Limit GWD/MTU (GWD/STU) (kW/ft) (3) 0.00 ( 0.00) 8.32 0.22 ( 0.20) 8.36 1.10 ( 1.00) 8.43 2.20 ( 2.00) 8.52 3.31 ( 3.00) 8.62 4.41 ( 4.00) 8.72 5.51 ( 5.00) 8.82 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) 9.31 12.13 (11.00) 9.43 13.23 (12.00) 9.55 14.33 (13.00) 9.50 15.43 (14.00) 9.49 16.53 (15.00) 9.51 18.74 (17.00) 9.53 22.05 (20.00) 9.55 27.56 (25.00) 9.60 33.07 (30.00) 9.41 38.58 (35.00) 8.90 41.33 (37.49) 8.67 44.09 (40.00) 8.43 49.60 (45.00) 7.90 55.12 (50.00) 7.38 60.63 (55.00) 5.78 63.13 (57.27) 4.68 63.50 (57.61) 4.83 63.54 (57.65) 4.91 63.68 (57.77) 4.91 63.73 (57.82) 4.73 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-015, Monticello Cycle 24 COLR, Rev. 0 Page 15 of 31

NAD-MN-015 Monticello Cycle 24 COLR, Rev. 0 Table 8 2 UO2/Gd Thermal Mechanical LHGR Limits (Reference 17)

Bundle Type: GE14-P10DNAB393-17GZ-100T-145-T6-2598 (GE14C)

Engineering Data Bank (EDB) Bundle Number 1: 2598 (formerly EDB-2587)

Peak Pellet Exposure UO2 LHGR Limit Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit GWd/MT (GWD/ST) (kW/ft) GWd/MT (GWD/ST) (kW/ft) 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 17.

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 9 2 UO2/Gd Thermal Mechanical LHGR Limits (Reference 17)

Bundle Type: GE14-P10DNAB393-17GZ-100T-145-T6-2599 (GE14C)

Engineering Data Bank (EDB) Bundle Number 1: 2599 (formerly EDB-2588)

Peak Pellet Exposure UO2 LHGR Limit Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit GWd/MT (GWD/ST) (kW/ft) GWd/MT (GWD/ST) (kW/ft) 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 17.

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-015, Monticello Cycle 24 COLR, Rev. 0 Page 16 of 31

NAD-MN-015 Monticello Cycle 24 COLR, Rev. 0 Table 10 2 UO2/Gd Thermal Mechanical LHGR Limits (Reference 17)

Bundle Type: GE14-P10DNAB392-16GZ-100T-145-T6-2824 (GE14C)

Engineering Data Bank (EDB) Bundle Number 1: 2824 (no former EDB designation)

Peak Pellet Exposure UO2 LHGR Limit Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit GWd/MT (GWD/ST) (kW/ft) GWd/MT (GWD/ST) (kW/ft) 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 17.

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 11 2 UO2/Gd Thermal Mechanical LHGR Limits (Reference 17)

Bundle Type: GE14-P10DNAB391-14GZ-100T-145-T6-2480 (GE14C)

Engineering Data Bank (EDB) Bundle Number 1: 2480 (formerly EDB-2427)

Peak Pellet Exposure UO2 LHGR Limit Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit GWd/MT (GWD/ST) (kW/ft) GWd/MT (GWD/ST) (kW/ft) 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 17.

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-015, Monticello Cycle 24 COLR, Rev. 0 Page 17 of 31

NAD-MN-015 Monticello Cycle 24 COLR, Rev. 0 Table 12 2 UO2/Gd Thermal Mechanical LHGR Limits (Reference 17)

Bundle Type: GE14-P10DNAB391-14GZ-100T-145-T6-2481 (GE14C)

Engineering Data Bank (EDB) Bundle Number 1: 2481 (formerly EDB-2428)

Peak Pellet Exposure UO2 LHGR Limit Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit GWd/MT (GWD/ST) (kW/ft) GWd/MT (GWD/ST) (kW/ft) 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 17.

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 13 2 UO2/Gd Thermal Mechanical LHGR Limits (Reference 13)

Bundle Type: GE14-P10DNAB392-16GZ-100T-145-T6-2931 (GE14C)

Engineering Data Bank (EDB) Bundle Number 1: 2931 (no former EDB designation)

Peak Pellet Exposure UO2 LHGR Limit Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit GWd/MT (GWD/ST) (kW/ft) GWd/MT (GWD/ST) (kW/ft) 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 13.

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-015, Monticello Cycle 24 COLR, Rev. 0 Page 18 of 31

TD-NMC-NAD-MN-015 Monticello Cycle 24 COLR, Rev. 0 Table 14 2 UO2/Gd Thermal Mechanical LHGR Limits (Reference 13)

Bundle Type: GE14-P10DNAB392-17GZ-100T-145-T6-2932 (GE14C)

Engineering Data Bank (EDB) Bundle Number 1: 2932 (no former EDB designation)

Peak Pellet Exposure UO2 LHGR Limit Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit GWd/MT (GWD/ST) (kW/ft) GWd/MT (GWD/ST) (kW/ft) 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 13.0

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-015, Monticello Cycle 24 COLR, Rev. 0 Page 19 of 31

9.0 Core Stability Requirements Stability Exclusion Region The stability exclusion region is shown in Figure 5, and is given in greater detail in Figure 6.

Stability Buffer Region The stability buffer region is shown in Figure 5, and is given in greater detail in Figure 6.

Power Distribution Controls Prior to intentionally entering the stability buffer region, the hot channel and core wide decay ratios shall be shown to be within the stable portion of Figure 7. While operating in the stability buffer region, the hot channel and core wide decay ratios shall be maintained within the stable portion of Figure 7.

Normal Region The normal region is shown in Figures 5 and 6.

Reference:

Technical Specification 3.4.1.

NAD-MN-015, Monticello Cycle 24 COLR, Rev. 0 Page 20 of 31

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.

10.1 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 ave 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:

n N i i i =1 ave = n (1)

Ni i =1 where: n = the number of surveillance tests performed to date in the cycle; n

N i =1 i = 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 N

i =1 i i = measured to date in the cycle to comply with the Technical Specification surveillance requirements SR 3.1.4.1, SR 3.1.4.2, SR 3.1.4.3, SR 3.1.4.4.

The average scram time, ave is tested against the analysis mean using the following equation:

ave B (2) where:

N B = + 1.65 n 1 (3)

N i i =1 NAD-MN-015, Monticello Cycle 24 COLR, Rev. 0 Page 21 of 31

The parameters and 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 15), and N1 = number of active control rods tested at BOC.

Table 15 GEMINI Methods, CRD Notch Position for B Determination Notch Position 36 0.830 0.019 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:

ave B OLMCPR NEW = MAX OLMCPR 100% OptionB + OLMCPR, OLMCPR TTWBP (4)

A B where:

ave and B are defined in Equations 1 and 3, respectively; and A = The Technical Specification limit on scram time to notch position 36 .

(Technical Specification Table 3.1.4-1 at notch position 36)

OLMCPR = the difference between the Option A OLMCPR and the Option B OLMCPR reported in Table 16.

Table 16 Cycle OLMCPR Values Transient Option A Option B Inadvertent HPCI / L8 Turbine Trip 1.70 1.53 Turbine Trip with Bypass1 1.57

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 16 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 recirculation loop operation.

NAD-MN-015, Monticello Cycle 24 COLR, Rev. 0 Page 22 of 31

Sample Calculation:

Assume two recirculation loop operation.

If ave is 0.820 seconds (scram time test) and B (as calculated with equation 3) is 0.850 seconds then the criteria from Equation 2 is met and the Option B OLMCPR of 1.57 can be used.

If ave is 0.940 seconds and B 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:

ave B OLMCPR NEW = MAX OLMCPR 100% OptionB + OLMCPR, OLMCPR TTWBP A B OLMCPR 100% OptionB = 1.53 (from Table 16 above.)

ave = 0.940 B = 0.850 A = 1.080 (Technical Specification Table 3.1.4-1 at notch position 36)

OLMCPR = 1.70 - 1.53 = 0.17 (from Table 16 above; assume two recirculation loop operation) 0.940 0.850 OLMCPR NEW = MAX 1.53 +

• 0.17 , 1.57 = 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.

NAD-MN-015, Monticello Cycle 24 COLR, Rev. 0 Page 23 of 31

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 < 1.1 seconds.

Reference:

Technical Specification 1.1, Surveillance Requirement 3.7.7.3.

12.0 Shutdown Margin (SDM) Confirmation Technical Specification 5.6.3.c requires that the SDM be confirmed for Monticello Cycle 24. Analytical SDM has been confirmed in Reference 2, Section 4.

NAD-MN-015, Monticello Cycle 24 COLR, Rev. 0 Page 24 of 31

Figure 1 Monticello Cycle 24 Power Dependent MAPLHGR and LHGR Multipliers W R H G R p = WPFACp

• WPLHGRstd For 25% > I? No Thermal Limits Required For 25% P < 45%, >50% Flow M4FFACp=0.527+0.00155(P-45%)

For 25% < P < 45%, 50% Flow M4FFACp=0.677+0.00775(P-45%)

For 45% 2 P < 100%

WPFACp=I .O+O.O05224(P-100%)

25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 POWER (% Rated)

NAD-MN-015, Monticello Cycle 24 COLR, Rev. 0 Page 25 of 31

Figure 2 Monticello Cycle 24 Flow Dependent MAPLHGR and LHGR Multipliers Core Flow (% Rated)

NAD-MN-015, Monticello Cycle 24 COLR, Rev. 0 Page 26 of 31

Figure 3 Monticello Cycle 24 Power Dependent K(P) 1 MCPR(P) Limits 20 30 40 50 60 70 80 90 100 110 Power (% rated)

NAD-MN-015, Monticello (Cycle24 COLR, Rev. 0 Page 27 of 31

Figure 4 Monticello Cycle 24 Flow Dependent CPR Limits NAD-MN-015, Monticello Cycle 24 COLR, Rev. 0 Page 28 of 31

Figure 5 Monticello Nuclear Generating Plant Power-Flow Operating Map Rated Power NAD-MN-015, Monticello Cycle 24 COLR, Rev. 0 PAGE 29 OF 31

Figure 6 Monticello Nuclear ~eneratingPlant Power-Flow Operating Map OPEbration not a l l owed i n the s l atnted s h a d i n g a r e a .

Total Core F l o w (MLb/Hr)

Page 30 of 31 NAD-MN-015, Mont~celloCycle 24 COLR, Rev 0

Figure 7 Stability Criterion Map 0.0 0.2 0.4 0.6 0.8 1 .0 CHANNEL DECAY RATIO NAD-MN-015, Monticello Cycle 24 COLR Rev. 0 Page 31 of 31