L-MT-06-069, Submittal of Revision 2 to the Cycle 23 Core Operating Limits Report

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Submittal of Revision 2 to the Cycle 23 Core Operating Limits Report
ML063490348
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 10/30/2006
From: Conway J
Nuclear Management Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-MT-06-069 NAD-MN-010, Rev 2
Download: ML063490348 (38)
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Monticello Nuclear Generating Plant Committed to NuclearExcelence Operated by Nuclear Management Company, LLC October 30, 2006 L-MT-06-069 Technical Specification 6.7.A.7 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 Revision 2 to the Cycle 23 Core Operatinq Limits Report Pursuant to Monticello Nuclear Generating Plant (MNGP) current Technical Specification (TS) Section 6.7.A.7 and Improved Technical Specifications (ITS) Section 5.6.3, "Core Operating Limits Report (COLR)," the Nuclear Management Company, LLC (NMC), is submitting Revision2- to the Cycle 23 report. The MNGP 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.

Revision 2 to the Cycle 23 COLR was developed to work with both the CTS and ITS versions of the technical specifications. Minor changes in formatting and terminology have been incorporated within to clearly specify existing CTS information and its corresponding ITS presentation and terminology. One new section was added to define the Turbine Bypass System Response Time in accordance with ITS Surveillance Requirement 3-7.7.3. Additionally, because Global Nuclear Fuel-Americas, LLC, (General Electric) no longer considers certain information proprietary, the MNGP COLR has been declassified and is no longer proprietary.

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

John T. Conway Site Vice President, Monticello Nuclear Generating Plant Nuclear Management Company, LLC Enclosure cc: Administrator, Region III, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC Minnesota Department of Commerce 1/

2807 West County Road 75

  • Monticello, Minnesota 55362-9637 Telephone: 763.295.5151
  • Fax: 763.295.1454

~kiQc A-001

ENCLOSURE I MONTICELLO NUCLEAR GENERATING PLANT CYCLE 23 CORE OPERATING LIMITS REPORT NAD-MN-010 REVISION 2

NAD-MN-10, Monticello Cycle 23 COLR, Rev. 2 Committed to Nu Monticello Nuclear Generating Plant Cycle 23 Core Operating Limits Report NAD-MN-010 Revision 2 Prepared By Date:

Peter Pankratz Senior Engineer Analyst, Nuclepr Analysis and C)esign Verified By: DuS

  • Date:

Doug Shiftb Princip Engine alyst, Nu~lear Analysis and Design Reviewed By: Date:

o?/',[O Th'omas M. Parker Superintendent, N ear Engineering - Monticello Approved By: ý ' = Date: / t Richard J Rohrer Project Manager, Nuclear Analysis and Design NAD-MN-010, Monticello Cycle 23 COLR, Rev. 2 Page 1 of 37

Monticello Nuclear Generating Plant, Cycle 23 Core Operating Limits Report (COLR)

Record of Revisions Revision 2:

1. Updated the heading on pages 1 to reflect the new revision number from Revision 1 to Revision 2.
2. Removed the ((CONTAINS GNF PROPRIETARY INFORMATION))" from the pages that contain this header.
3. Updated the "Prepared By" to Peter Pankratz and the "Verified by" to Doug Shilts.
4. Updated the footers to Revision 2 and changed the number of pages in the report from 30 to 37.

The "PROPRIETARY INFORMATION" statement was also removed from the footers.

5. In section 1.0 inserted the acronym [CTS] which stands for Current Technical Specification in paragraph 1. Also inserted the acronym [ITS] which stands for Improved Technical Specification and the ITS section number that applies ([ITS] ITS 5.6.3) after the [CTS] number.
6. In section 1 removed the term "proprietary" from paragraph 3.
7. In section 1 removed the entire fourth paragraph. The fourth paragraph dealt with proprietary information that is no longer proprietary in this report.
8. In section 2 removed the term "(proprietary)" from Reference 7.
9. In section 3 added the acronym [CTS] to the 'Reference" line. Also added a line which includes the

[ITS] location for the Rod Block Monitor Operability Requirements.

10. Added sections 4.1 and 4.2. 4.1 deals with the [CTS] rod block monitor trip setpoints and 4.2 deals with the [ITS] rod block monitor setpoints and the mode definitions for the trip setpoints.
11. In section 4.1 added the acronym [CTS] to the "Reference" line.
12. In section 4.2 added the acronym [ITS] to the "Reference" line. Added a line which includes the

[ITS] location for the Rod Block Monitor Upscale Trip Setpoint. Added the mode definitions to the setpoints.

13. In section 5 .1.1 and 5.1.2 added the acronym [CTS] to the "Reference" line. Added a line which includes the [ITS] reference [ITS] ITS 3.2.2.
14. In section 5 .2.1 and 5.2.2 added the acronym [CTS] to the "Reference" line. Added a line which includes the [ITS] reference [ITS] ITS 3.2.2.
15. Section 6 added an [ITS] reference for the Power/Flow Map.
16. Section 7 added two additional Approved Analytical Methods to this section.
17. Section 8.1 added the acronym [CTS] and [ITS] with the ITS section number 3.2.1 and 5.6.3.b.
18. Section 8.1.2 added the acronym [CTS] to the "Reference" and added a line [ITS] with the ITS section number 3.2.1.
19. Section 8.2, paragraph 2 added the acronym [CTS] to the "Monticello Technical Specification.

Added the [ITS] reference of [ITS] 5.6.3.b. In paragraph 3 added the acronym [CTS] to the Monticello Technical Specification and add the acronym [ITS] and ITS section 3.2.3.

20. Section 8.2.2.1 added the acronym [CTS] to the "Reference" and added a line [ITS] with the ITS section number 3.2.3.
21. Tables 8, 9,10, 11, and 12 were changed to include the previous proprietary information.

Removed comments 1 and 3 from each Table and renamed comments 2 and 4 to 1 and 2 respectively.

NAD-MN-010, Monticello Cycle 23 COLR, Rev. 2 Page 2 of 37

22. Section 9.0 added the acronym [CTS] and [ITS] with the ITS section number 3.4.1. Included a section on the "Normal" region on the power flow map.
23. Created subsection 10.1 and 10.2. 10.1 is the [ITS] section on scram speed testing and hand calculating the [ITS] OPMCPR based on Option B scram speeds. The option B scram speeds for

[ITS] are measured at notch 36. The Option B scram speeds for [CTS] section 10.2 are measured at the 20% insertion location.

24. In section 10.2 renamed Table 15 to Table 17 and Table 16 to Table 18. Reassigned all references to Table 15 to Table 17 and Table 16 to Table 18.
25. Inserted Section 11.
26. Figures 5 and 6 were modified by including the words "Normal Region" to the maps and also added an arrow that points to the Buffer Region.

NAD-MN-010, Monticello Cycle 23 COLR, Rev. 2 Page 3 of 37

1.0 Core Operating Limits Report (COLR)

This Core Operating Limits Report for Monticello Nuclear Generating Plant Cycle 23 is prepared in accordance with the requirements of [CTS] Technical Specification 6.7.A.7,

[ITS] 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 23. 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 Monticello's operating license approved by the NRC in Reference 10.

2.0 References 1.0 General Electric Standard Application for Reactor Fuel (GESTAR-I1). NEDE-2401 1-P-A-14, June 2000.

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

3.0 General Electric Licensing Topical Report ODYSY Application for Stability Licensing Calculations, NEDC-32992-P-A, DRF A13-00426-00, 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 Desigqn 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 Generatinq 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 11, NEDO-31960-A, Licensing Topical Report, Supplement 1, March 1992.

10.0 Letter from Tae Kim (USNRC) to Roger 0 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-010, Monticello Cycle 23 COLR, Rev. 2' Page 4 of 37

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 0 Anderson (NSP), "Monticello Nuclear Generating Plant - Issuance of Amendment Re. Power Uprate Program (TAC No.

M96238)," including enclosures, September 16, 1998.

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 23:

For Power < 90%: MCPR_ 1.70 For Power >_90%: MCPR _ 1.40 WVhen 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:

[CTS] Technical Specification Section 3.2.C.2.a

[ITS] Technical Specification Table 3.3.2.1-1 Function 1.

4.0 Rod Block Monitor Upscale Trip Setpoint 4.1 [CTS] Technical Specification Trip Setpoints Low Trip Setpoint (LTSP) _ 120/125 of full scale Intermediate Trip Setpoint (ITSP) _ 115/125 of full scale High Trip Setpoint (HTSP) _< 110/125 of full scale

Reference:

[CTS] Technical Specification Sections: Table 3.2.3 Item 4.a, Table 3.2.3 Note 8.

4.2 [ITS] 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.

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

NAD-MN-010, Monticello Cycle 23 COLR, Rev. 2 Page 5 of 37

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 _Ž45% of rated core thermal power, then the Option A OLMCPR for all fuel types is the greate 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 Ž_45% rated core thermal power, then Option A OLMCPR limit

= Max (1.70

  • K(P) from Figure 3, 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:

[CTS] Technical Specification Section 3.11I.C.

[ITS) 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 AMCPR adder to account for core flow measurement and TIP reading uncertainties.

Reference:

[CTS] Technical Specification Section 3.11 .C.

(ITS] Technical Specification Section 3.2.2.

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 (OLMCPRo0onB ) is 1.54, and is reported in Tables 16. This OLMCPRo00oB = 1.54 value is modified as described in Section 10 to be a function of the measured scram speeds to yield NAD-MN-010, Monticello Cycle 23 COLR, Rev. 2 Page 6 of 37

New OLMCPRopnonB. 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 NOLMCPR

,

  • 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 Max {OLMCPRoN*'o,.

  • K(P) from Figure 3, 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:

[CTS] Technical Specification Section 3.11 .C.

[ITS] 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:

[CTS] Technical Specification Section 3.11 .C.

[ITS] Technical Specification 3.2.2.

NAD-MN-010, Monticello Cycle 23 COLR, Rev. 2 Page 7 of 37

6.0 Power-Flow Map The Power-Flow Operating Map based on analysis to support Cycle 23 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:

[ITS) Technical Specification 3.4.1.

7.0 Approved Analytical Methods NEDE-24011-P-A Rev. 14 "General Electric Standard Application for Reactor Fuel" NEDO-31960-A "BWR Owners Group Long-Term Stability Solutions Licensing Methodology," Licensing Topical Report, June 1991.

NEDO-31960-A Sup. 1 "BWR Owners Group Long-Term Stability Solutions 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 Nuclear Generating Plant." October 1995.

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

NAD-MN-010, Monticello Cycle 23 COLR, Rev. 2 Page 8 of 37

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 [CTS] Technical Specification 3.11.A, [ITS] 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 [CTS] Technical Specification 6.7.A.7.b,

[ITS] 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 multipliers to the limiting values of MAPLHGR from Tables 1 through 7 as follows:

for GEl 1: multiplier is 0.80, 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:

[CTS] Technical Specification Section 3.1 .A.

[ITS] Technical Specification 3.2.1.

.NAD-MN-010, Monticello Cycle 23 COLR, Rev. 2 Page 9 of 37

8.2 Linear Heat Generation Rate (LHGR)

The uranium dioxide (U0 2) and gadolinia LHGR limits as a function of fuel rod peak pellet exposure for each bundle type in Cycle 23 are given 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 23. 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 23, as a function of axial location and pellet exposure are determined based on the approved methodology referenced in Monticello [CTS]

Technical Specification 6.7.A.7.b, [ITS] 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 [CTS] Technical Specification 3.11.B, [ITS]

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.

NAD-MN-010, Monticello Cycle 23 COLR, Rev. 2 Page 10 of 37

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:

(CTS] Technical Specification Section 3.1 1.B.

[ITS] Technical Specification Section 3.2.3.

NAD-MN-010, Monticello Cycle 23 COLR, Rev. 2 Page 11 of 37

Table 1: MAPLHGR Limits(")

GEl1 EDB-3823(2): GEll-P9DUB380-17GZ-100T-141-T6 (formerly EDB-2367)

Average Planar Exposure MAPLHGR Limit GWD/MTU (GWD/STU) (kW/ft) 0.00 (0.00) 8.23 0.22(0.20) 8.30 1.10(1.00) 8.43 2.20 (2.00) 8.61 3.31 (3.00) 8.80 4.41 (4.00) 9.00 25.51 (5.00) 9.22 6.60 (6.00) 9.44 7.72 (7.00) 9.70 8.82 (8.00) 9.97 9.92 (9.00) 10.21 11.02 (10.00) 10.39 12.13 (11.00) 10,55 13.23 (12.00) 10.68 14.33 (13.00) 10.76 15.43 (14.00) 10.80

!16.53 (15.00) 10.84_

18.74 (17.00) 10,91 22.05 (20.00) 10.97 27.56 (25.00) 10.40 33.07 (30.00) 9.83 38.58 (35.00) "9.24 44.09 (40.00) 8.58 49.60 (45.00) 7.88 55.12 (50.00) 7.21 60.63 (55,.00). 6.56 61.11 (55.44) 6.54 61.23 (55.55) 6.54

. 61.32 (55.63) 6.48 61.67 (55.94) 6.57 Note:

(1) Values in Table I 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.

NAD-MN-010, Monticello Cycle 23 COLR, Rev. 2 Page 12 of 37

Table 2: MAPLHGR Limitstt GEII EDB-3824t 2 ): GEl1-P9DUB380-16GZ-lOOT-141-T6 (formerly EDB-2368)

Average Planar Exposure MAPLHGR Limit GWD/MTU (GWD/STU) (kW/ft) 0.00 (0.00) 8.36 0.22 (0.20) 8.42 1.10(1.00) 8.55 2.20 (2.00) 8.73 3.31 (3.00) 8.91 4.41 (4.00) 9.11 5.5.1 (5.00) 9.32 6.61 (6.00) 9.55 7.72 (7.00) 9.77 8.82 (8.00) 9.94 9.92(9.00) 10.13 11.02 (10.00) 10.33 12.13 (11.00) 10.52 13.23 (12.00) 10.67 14.33 (13.00) 10.77 15.43 (14.00) 10.82 16.53 (15.00) 10.84 18.74 (17.00) 10.86 22.05 (20.00) 10.88 27.56 (25.00) 10.40 33.07 (30.00) 9.82 38.58 (35.00) 9.24 44.09 (40.00) 8.58 49.60 (45.00) 7.88 55.12 (50.00) 7.21 60.63 (55.00) 6.57 61.01 (55.35) 6.55 61.17 (55.49) 6.54 61.39 (55.69) 6.48 61.60 (55.89) 6.57 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 2.

NAD-MN-010, Monticello Cycle 23 COLR, Rev. 2 Page 13 of 37

Table 3: MAPLHGR Limits(O GE14C EDB-2598t 2 ): GE14-PIODNAB393-17GZ-10OT-145-T6-2598 (formerly EDB-2587)

Average Planar Exposure MAPLtiGR Limit GWD/MTU(GWD/STU) (kW/ft) 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 3 are fbr 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.

NAD-MN-010, Monticello Cycle 23 COLR, Rev. 2 Page 14 of 37

Table 4: MAPLHGR Limits("

GE14C EDB-2599(2": GEl 4-PIODNAB393-17GZ-I0OT-145-T6-2599 (formerly EDB-2588)

Average Planar Exposure MAPLHGR Limit GWD/MTU (GWD/STU) (kW/ft) 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) 1 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 2.

NAD-MN-010, Monticello Cycle 23 COLR, Rev. 2 Page 15 of 37

Table 5: MAPLHGR Limits('ý t

GE14C EDB-2824( ): GE14-PlODNAB392-16GZ-10OT-145-T6-2824 (no former EDB designation)

Average Planar Exposure MAPLHGR Limit GWD/MTU (GWD/STU) (kW/ft) 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 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.

NAD-MN-010, Monticello Cycle 23 COLR, Rev. 2 Page 16 of 37

Table 6: MAPLHGR Limits"i 2

GE14C EDB-2480( ): GE14-PIODNAB391-14GZ-1OOT-145-T6-2480 (formerly EDR-2427)

Average Planar Exposure MAPLHGR Limit GWD/MTU (GWD/STU) (kW/ft) 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 5.5] (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 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.

NAD-MN-010, Monticello Cycle 23 COLR, Rev. 2 Page 17 of 37

t1 Table 7: MAPLHGR Limits )

t 2 GE14C EDB-2481 ): GE14-PIODNAB391-14GZ-IOOT-145-T6-2481 (formerly EDB-2428)

Average Planar Exposure MAPLHGR Limit GWD/MTU (GWD/STU) (kW/ft) 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 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.

NAD-MN-010, Monticello Cycle 23 COLR, Rev. 2 Page 18 of 37

NAD-MN-010 Monticello Cycle 23 COLR, Rev. 2 Table 8 2 U02/Gd Thermal Mechanical LHGR Limits (Reference 4)

Bundle Type: GE 1I-P9DUB380-17GZ- I0OT- 141 -T6 (GE 11)

Engineering Data Bank (EDB) Bundle Number 1: 3823 (formerly EDB-2367)

Peak Pellet Exposure U0 2 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) 14.40 0.00 (0.00) 12.74 14.60 (13.24) 14.40 11.68 (10.59) 12.74 70.00 (63.50) 6.80 64.82 (.58.81) 6.02 Notes:

1. Reference 2.
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.

2 Table 9 U02/Gd Thermal Mechanical LHGR Limits (Reference 4)

Bundle Type: GE 11-P9DUB380-16GZ-100T-141-T6 (GE 11)

Engineering Data Bank (EDB) Bundle Number 1: 3824 (formerly EDB-2368)

Peak Pellet Exposure U0 2 LHGR Limit Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit GWd/MT (GWD/ST) (kW/fl) GWd/MT (GWD/ST) (kW/ft) 0.00 (0.00) 14.40 0.00 (0.00) 12.74 14.60 (13.24) 14.40 11.68 (10.59) .12.74 70.00 (63.50) 6.80 64.82 (58.81) 6.02 Notes:

1. Reference 2.
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-010, Monticello Cycle 23 COLR, Rev. 2 Page 19 of 37

NAD-MN-010 Monticello Cycle 23 COLR, Rev. 2 Table 102 U02/Gd Thermal Mechanical LHGR Limits (Reference 4)

Bundle Type: GE 14-P 1ODNAB393-17GZ-1OOT-145-T6-2598 (GE 14C)

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

Peak Pellet Exposure U0 2 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 2.
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 U02/Gd Thermal Mechanical LHGR Limits (Reference 4)

Bundle Type: GE 14-PI ODNAB393-17GZ- IOOT- 145-T6-2599 (GE 14C)

Engineering Data Bank (EDB) Bundle Number': 2599 (fore rly EDB-2588)

Peak Pellet Exposure U02 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 2.
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-010, Monticello Cycle 23 COLR, Rev. 2 Page 20 of 37

NAD-MN-010 Monticello Cycle 23 COLR, Rev. 2 Table 12 2 U02/Gd Thermal Mechanical LHGR Limits (Reference 4)

Bundle Type: GE14-PI ODNAB392-16GZ-IOOT-145-T6-2824 (GE14C)

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

Peak Pellet Exposure U02 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 2.
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 U02/Gd Thermal Mechanical LHGR Limits (Reference 4)

Bundle Type: GE14-PIODNAB391-14GZ-lOOT-145-T6-2480 (GE14C)

Engineering Data Bank (EDB) Bundle Number t: 2480 (forme ly EDB-2427)

Peak Pellet Exposure U02 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 2.
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-010, Monticello Cycle 23 COLR, Rev. 2 Page 21 of 37

NAD-MN-010 Monticello Cycle 23 COLR, Rev. 2 Table 14 2 UO2/Gd Thermal Mechanical LHGR Limits (Reference 4)

Bundle Type: GE I4-PI ODNAB39 1-14GZ-1OOT-145-4'6-2481 (GE 14C)

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

Peak Pellet Exposure U02 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 2.
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-010, Monticello Cycle 23 COLR, Rev. 2 Page 22 of 37

9.0 Core Stability Requirements Stability Exclusion Region The stability exclusion region is shown in Figure 5, and is given in greater detailin 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:

ICTS] Technical Specification Section 3.5.F.

[ITS] Technical Specification 3.4.1.

NAD-MN-010, Monticello Cycle 23 COLR, Rev. 2 Page 23 of 37

10.0 Scram Time Dependence The [ITS] and [CTS] 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 for [ITS] or 10.2 for [CTS] may be used.

10.1 [ITS] Scram Time Dependence

[ITS] Technical Specification 3.1.4 and Table 3.1.4-1 provide the scram insertion time versus position requirements for continued operations. Improved 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 tare 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:

lNiT, i=1 ave n k I ZN, where: n = the number of surveillance tests performed to date in the cycle; n

N = total number of active control rods measured to date in the cycle; and i=1 sum of the scram times to the 36th notch position of all active rods n measured to date in the cycle to comply with the [ITS] Technical N- r, = 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, Tave is tested against the analysis mean using the following equation:

rave :-! B (2) where:

T B=:=i +1.65 (3)

NAD-MN-010, Monticello Cycle 23 COLR, Rev. 2 Page 24 of 37

The parameters p and a 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 rB Determination Notch Position 1 9 1 c 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:

=

New~~~~~~ 0% T~f*]

"ave - T¢B 0

OLMCPR*NpponB = .LMCPR.

. . OpTo + TA -- tB T AOLMCPR (4) where:

'rave and 'TB are defined in Equations 1 and 3, respectively; and TA = The [ITS) Technical Specification limit on scram time to notch position 36.

([ITS] 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 16.

Table 16 Cycle OLMCPR Values Transient Option A Option B Inadvertent HPCI / L8 Turbine Trip 1.70 1.53 Turbine Trip with Bypass' 1.54

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 this 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-010, Monticello Cycle 23 COLR, Rev. 2 Page 25 of 37

Sample Calculation:

Assume two recirculation loop operation.

If Tave is 0.694 seconds (scram time test) and TB (as calculated with equation 3) is 0.700 seconds then the criteria from Equation 2 is met and the Option B OLMCPR of 1.54 can be used.

Note that the value of 1.54 will be used as the rated (100%) core thermal power Option B OLMCPR (i.e. OLMCPROP°ton, = 1.54). The 1.54 Option B OLMCPR is conservative with respect to the pressurization transient Option B OLMCPR of 1.53 reported in Table 16.

If Tave is 0.800 seconds and tB is 0.600 seconds, then the criteria from Equation 2 is not met and a new Option B OLMCPR must be calculated using Equation 4 above.

The example calculation is as follows:

New= OM~p*00% "Tave -- B OLMCPRoNen -= OLMCPROt*ofB + -- AOLMCPR OptionBA T-- B 0

OLMCPR o% = 1.54 (from Table 16 above)

= 0.800

= 0.600 rA =1.080 ((ITS] Technical Specification Table 3.1.4-1 at notch position 36)

AOLMCPR= 1.70 - 1.53 = 0.17 (from Table 16 above; assume two recirculation loop operation) 0LMCPR L OptN 0.800

.54+ (1.080 --0.600,,

Opio 0.600 *0.17 = 1.61; two recirculation loop operation.

Note: If single recirculation loop operation Option B OLMCPR value is desired, add 0.02, i.e. 1.61 + 0.02 = 1.63.

NAD-MN-01 0, Monticello Cycle 23 COLR, Rev. 2 Page 26 of 37

10.2 [CTS] Scram Time Dependence ICTS] Technical Specification 3.3.C provides the scram insertion time versus position requirements for continued operations. [CTS] Technical Specification 43.C 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 at the 20% insertion position.

The Equation (1) used to calculate the average of all the scram data generated to date in the cycle is:

I

=i=!

Ni ri rave Zn (1)

Y~l where: n = the number of surveillance tests performed to date in the cycle; t N= total number of active control rods measured to date in the cycle; and i=1

~'£ j=

N*r = sum of the scram times to the 20 percent insertion position of all active rods

ý measured to date in the cycle to comply with the [CTS] Technical Specification surveillance requirements.

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

rave

  • T B (2) where:

TB-/II+l. 65 n (3)

Nil The parameters A and a are the mean and standard deviation of the distribution of the average scram insertion time to the 20% insertion position in the ODYN Option B analysis (Table 17), and N 1 = number of active control rods tested at BOC.

NAD-MN-010, Monticello Cycle 23 COLR, Rev. 2 Page 27 of 37

Table 17 GEMINI Methods, CRD Control Fraction vs Time 0% 5% 20% 50% 90% 100%

g (sec) 0.200 0.324 0.694 1.459 2.535 2.804 ac (sec) 0.014 0.016 0.031 0.070 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:

OLMCPRlo*B = OLMCPR1ODnB + a -B AOLMCPR (4)

TA TB where:

Tare and T B are defined in Equations 1 and 3, respectively; and TA = The (CTS] Technical Specification limit on core average scram time to the 20%

insertion limit. ( [CTS] Technical Specification 3.3.C at 20% insertion.)

AOLMCPR = the difference between the Option A OLMCPR and the Option B OLMCPR reported in Table 18.

NAD-MN-010, Monticello Cycle 23 COLR, Rev. 2 Page 28 of 37

Table 18 Cycle OLMCPR Values Transient Option B Inadvertent HPCI / L8 Turbine Trip 1.70 1.53 Turbine Trip with Bypass' 1.54

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 this Table 18 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.

Sample Calculation:

Assume two recirculation loop operation.

If T1aveis 0.694 seconds (scram time test) and TB (as calculated with equation 3) is 0.700 seconds then the criteria from Equation 2 is met and the Option B OLMCPR of 1.54 can be used.

Note that the value of 1.54 will be used as the rated (100%) core thermal power Option B OLMCPR (I.e. OLMCPRoption = 1.54). The 1.54 Option B OLMCPR is conservative with respect to the pressurization transient Option B OLMCPR of 1.53 reported in Table 18.

if tave is 0.800 seconds and tB is 0.700 seconds, then the criteria from 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 New OLMCPR optonB + Tave - B AOLMCPR Option Opt TA - TB OLMCPR"0°o" OLOptionB = 1.54 (from Table 18 above)

Vave = 0.800 TB = 0.700

'CA = 0.900 ([CTS] Technical Specification 3.3.C)

AOLMCPR= 1.70 - 1.53 = 0.17 (from Table 18 above; assume two recirculation loop operation)

OLMCPR New = 1.54÷+ 0.800 - 0.700

  • 0.17 = 1.63; two recirculation loop operation.

Optin K0.900 - 0.700)

Note: If single recirculation loop operation Option B OLMCPR value is desired, add 0.02, i.e. 1.63 + 0.02 = 1.65.

NAD-MN-010, Monticello Cycle 23 COLR, Rev. 2 Page 29 of 37

11.0 [ITS] Turbine Bypass System Response Time The TURBINE BYPASS SYSTEM RESPONSE TIME shall be that time intervalifr6m.-.

when the main turbine trip solenoid is activated until 80% of the turbine bypd*ScRsity

,is established. The TURBINE BYPASS SYSTEM RESPONSE TIME shall b6 '"1'i seconds.

Reference:

ITS 1.1, ITS SR 3.7.7.3.

NAD-MN-O10, Monticello Cycle 23 COLR, Rev. 2 Page 30 of 37

11.0 [ITS] 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:

ITS 1.1, ITS SR 3.7.7.3.

NAD-MN-010, Monticelio Cycle 23 COLR, Rev. 2 Page 30 of 37

Figure 1 Monticello Cycle 23 Power Dependent MAPLHGR and LHGR Multipliers 1.10 1.00 0.90 0.80 0.70 LJL 0 <50% flow MAPLHGRp = MAPFACp

  • MAPLHGRstd 0.60 0~ For 25% > P: No Thermal Limits Required 0- For 25% :< P < 45%, >50% Flow 0.50
  • MAPFAC p=0.527+0.00155(P-45%)

> 50% Flow For 25% _ P < 45%, : 50% Flow MAPFACp=0.677+0.00775(P-45%)

0.

0.40 For 45% < P < 100%

MAPFACp=1.0+0.005224(P-1 00%)

0.30 0.20 II

....!....i....!....i....! 1H ....1....1. .; ...1....1...i 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 POWER (% Rated)

NAD-MN-010, Monticello Cycle 23 COLR, Rev. 2 Page 31 of 37

Figure 2 Monticello Cycle 23 Flow Dependent MAPLHGR and LHGR Multipliers

,.1 vi 0.9

  • " 0.8 0
  • 0.7 0
  • J.6

-j U-n.5

'0.4 0.3 30 .40 50 60 70 80 90 100 110 Core Flow (% Rated)

NAD-MU-01O0, Monticeft Ccy-e 23 COLR, Rev -2 Page 32 of 37

Figure 3 Monticello Cycle 23 Power Dependent K(P) / MCPR(P) Limits 4.0 Operating Limit MCPR (P) = Kp

  • Operating Limit MCPR (100)

For P< 25%: No Thermal Limits Monitoring Required For 25% - P < 45%, > 50% Flow C. OLMCPR(P) = 2.60+0,027(45%-P) 0

.0 CL 3.5 I For 25% < P < 45%,

  • 50% Flow I '

a.

-4 .~ OLMCPR(P) = 2.12+0.0295(45%-P)

V For 45% < P < 60% Kp=1.15 + 0.00867(60%-P)

For 60% < P < 90% Kp=1.056 + 0.00313(90%-P) a-J

.L 3.0 For 90% !5 P < 100% Kp=l.00 + 0.0056(100%-P) 0 N 3.0 A,

U L,. Flo 1< 50%

Al 2.0 a.

1.5 A A 1.0 20 30 40 50 60 70 80 90 100 110 Power (% rated)

NAD-MN-010, Monticello Cycle 23 COLR, Rev. 2 " -

Page 33 of 37

Figure 4 Monticello Cycle 23 Flow Dependent CPR Limits 1.8 1.7 1.6 cr U

E 1.5

3 0m

" 1.4 CL 0.

0 1.3 1.2 1.1 20 30 40 50 60 70 80 90 100 110 120 Core Flow (% Rated)

NAD-MN-010, Monticello Cycle 23 COLR, Rev. 2 Page 34 of 37

Figure 2 Monticello Cycle 23 NowDepe-Ient MAPLHGR and LHGR Multipers..

~

Page 32 7

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