L-MT-03-033, Submittal of Core Operating Limits Report for Cycle 22

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Submittal of Core Operating Limits Report for Cycle 22
ML031490023
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 05/14/2003
From: Denise Wilson
Nuclear Management Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-MT-03-033
Download: ML031490023 (18)
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Text

Monticello Nuclear Generating Plant Committed to Nurdear Excelenc Operated by Nuclear Management Company, LLC May 14, 2003 L-MT-03-033 Technical Specification 6.7.A.7 US Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 Submittal of the Core Operating Limits Report for Cycle 22 The Monticello Core Operating Limits Report (COLR) for Cycle 22, Revision 0, is enclosed. This report provides the values of the limits for Cycle 22 as required by Technical Specification Section 6.7.A.7. These values have been established using NRC approved methodology such that all applicable limits of the plant safety analysis are met.

The COLR reflects a Safety Limit Minimum Critical Power Ratio (SLMCPR) of 1.10 for two-loop operation, and 1.12 for single-loop operation for all fuel in Cycle 22. This is the same as the SLMCPR for Cycle 21. The appropriate Operating Limit Minimum Critical Power Ratio in the core monitoring system will be updated, prior to startup for Cycle 22.

Please contact Ron Baumer at 763-295-1357 if you have any questions related to this submittal.

David L. Wilson Site Vice President Monticello Nuclear Generating Plant cc: Regional Administrator - III, NRC NRR Project Manager, NRC Sr Resident Inspector, NRC Minnesota Dept. of Commerce : Core Operating Limits Report for Cycle 22 (Rev 0) 2807 West County Road 75

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

ATTACHMENT 1 NUCLEAR MANAGEMENT COMPANY, LLC MONTICELLO NUCLEAR GENERATING PLANT DOCKET 50-263 MAY 14, 2003 Core Operating Limits Report for Cycle 22 16 Pages Follow

I Committed to Nuclear Excellence' Monticello Nuclear Generating Plant Cycle 22 Core Operating Limits Report NAD-MN-005 Revision 0 Prepared By: 6L7 J7'W Peter D. PankratzI Date: 5/5/os Senior Engineer Analyst, Nuclear Analysis and Design Verified By: ,

William J. Lax A Date: s5/5/o3 Principal Engineer, Nuclear Analysis and Design Reviewed By: -I7a_ Date:

Arne L Myrabo Superintendent, Nutlear Engineering - Monticello Approved By: 1 Date: '5- -r- 0,3 Ri ha, J Rohrer Pr ct Manager, Nuclear Analysis and Design NAD-MN-005, Monticello Cycle 22 COLR, Rev. 0 Page I of 16

1.0 Core Operating Limits Report This Core Operating Limits Report for Monticello Cycle 22 has been prepared in accordance with the requirements of Technical Specification 6.7.A.7. The core operating limits have been 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 SLCPR of 1.10 was used for two-loop operation for all fuel types in Cycle 22. The SLCPR 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-IIL). NEDE-2401 1-P-A-14, June2000 2.0 Supplemental Reload Licensing Report for Monticello Nuclear Generating Plant, Reload 21, Cycle 22 0000-0007-8709SRLR, Revision 0 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 Lattice Dependent MAPLHGR Report for Monticello Nuclear Generating Plant, Reload 21. Cycle 22, 0000-0007-8709MAPL, Revision 0 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 Cvcle-Independent Analvsis for Monticello Nuclear Generating Plant. GE-NE-0000-0013-9576P, GE Nuclear Energy (Proprietary),

March 2003.

7.0 Letter from Less Conner (GNF) to R. J. Rohrer (NMC) dated March 24, 2003, Monticello Option B Licensing Basis, IC.MN.2003.010, Global Nuclear Fuel (Proprietary) 8.0 GE14 Fuel Design, Cycle Independent Transient Analysis for Monticello Nuclear Generating Report. GEC-GE-NE-0000-0014-7048-01 P, Rev. 0, March 2003 (GNF Proprietary) 9.0 BWR Owners Group Long Term Stability Solution Licensing Methodology, NEDO-31960-A, Supplement 1, 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-005, Monticello Cycle 22 COLR, Rev. 0 Page 2 of 16

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 validated that the following MCPR values provide the required margin for full withdrawal of any control rod during Monticello Nuclear Generating Plant Cycle 22:

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.

(Source: Reference 2)

Reference Technical Specification Section 3.2.C.2.a 4.0 Rod Block Monitor Upscale Trip Setpoint 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 Technical Specification Sections: Table 3.2.3 Item 4.a, Table 3.2.3 Note 8.

5.0 Minimum Critical Power Ratio 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.

The Minimum Critical Power Ratio (MCPR) limit shall be determined for two Recirculation Loop Operation as follows:

If the thermal power is greater than 45%, then the MCPR limit for all fuel types is the greater of 1.67

  • Kp (Kp from Figure 3) or MCPRF from Figure 4 If thermal power is < 45% the MCPR limit for all fuel types is obtained in Figure 3.

For single loop operation the MCPR limit as defined previously by two-recirculation loop operation is increased by the following adder:

NAD-MN-005, Monticello Cyde 22 COLR, Rev. 0 Page3 of16

0.02 AMCPR adder to account for core flow measuring and TIP reading uncertainties.

Reference Technical Specification Section 3.11.C.

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 an Option B OLCPR value can be seen is section 10.

6.0 Power-Flow Map The Power-Flow Operating Map based on analysis to support Cycle 22 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.

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", Licensing Topical Report, Supplement 1, March 1992 NEDC-32992P-A "General Electric Licensing Topical Report, ODYSY Application for Stability Licensing Calculations, July 2001 8.0 Maximum Average linear Heat Generation Rate as a Function of Exposure When hand calculations are required, the Maximum Average Linear Heat Generation rate (MAPLHGR) for each fuel bundle design as a function of average planar exposure shall not exceed the limiting lattice (excluding natural uranium) provided in Table 1 (based on straight line interpolation between data points) multiplied by the smaller of the two MAPFAC factors determined from Figures 1 and 2.

The MAPLHGR limits in Table 1 are conservative values bounding all fuel lattice types (excluding natural Uranium) in a given fuel bundle design and are intended only for use in hand calculations as described in Technical specification 3.11.A. No channel bow effects are included in the bounding MAPLHGR values below because there are no reused channels. MAPLHGR limits for each individual fuel lattice design in a bundle design as a function of axial location and average planar exposure are determined based on the approved methodology referenced in Monticello Technical Specification 6.7.A.7.b and loaded into the process computer for use in core monitoring calculations.

Reference Technical Specification Section 3.11.A.

NAD-MN-005, Monticello Cycle 22 COLR. Rev. 0 Page4 ofl6

Table 1 MAPLHGR Limit' for each fuel type (kW/ft)

[ Exposure GE11- GE11- GE11- GE11- GE14- GE14- GE14' GE14-

[MWD/STUJ P9DUB P9DUB P9DUB P9DUB PlODNAB PlODNAB PIODNAB PIODNAB 366-16GZ 366-17GZ 380-16GZ[ 380-17GZ 391-14GZ 391-14GZ 393-17GZ 393417GZ 12271] 2 [2272] 2 2368] 2 [2367] 2 [2427] 2 [2428] 2 [2587] 2 [2588] 2 200 8.73 8.28 8.35 8.21 8.36 8.30 8.19 8.22 1000 8.93 8.47 8.49 8.37 8.49 8.45 8.31 8.31 5000 10.01 9.41 9.25 9.13 8.99 8.95 8.80 8.80 10000 10.75 10.61 10.26 10.33 9.59 9.51 9.42 9.42 15000 11.20 11.00 10.84 10.83 10.01 9.84 9.96 9.96 20000 11.29 10.88 10.90 10.96 10.20 9.83 10.01 9.99 25000 10.90 10.75 10.39 10.39 10.22 9.82 9.99 9.97 30000 10.20 10.00 9.82 9.83 10.06 9.79 9.89 9.89 35000 9.54 9.28 9.24 9.25 9.49 9.20 9.29 9.29 40000 8.88 8.54 8.57 8.57 8.93 8.64 8.72 8.72 45000 8.22 7.85 7.88 7.87 8.39 8.12 8.19 8.19 50000 7.56 7.19 7.22 7.21 7.89 7.63 7.69 7.69 55000 6.90 6.55 6.58 6.57 6.26 6.25 6.26 6.26 55920 - - 6.46 - - - - -

55982 - - - 6.44 - -

57610 - - - 4.95 4.95 57684 - - - - -

57694 6.53 - - - -

57700 - - - 4.90 4.90 58047 - - - - -

58225 - 6.13 - -

58320 - - - - 4.59 58390 - 4.55 -

Notes: 1 Table I is for two recirculation loop operation. For single loop operation, multiply the GE11 and GE12 values by 0.80 and the GE14 values by 0.90.

2 Engineering Databank (EDB) Number NAD-MN-005, Monbcello Cycle 22 COLR, Rev. 0 Page 5 of 16

Linear Heat Generation Rate TABLE 2 LHGR Limit' for Each Fuel Type (kW/ft)

GE11- GEII- GEII- GE11- GE14- GE14- GE14- GE14-P9DUB P9DUB P9DUB P9DUB PlODNAB PIODNAB PIODNAB PIODNAB 366-16GZ 366-17GZ 380-16GZ 380-17GZ 391-14GZ 391-14GZ 393-17GZ 393-17GZ 12 2 ]2 2]2]2 [57

[2271] [2272] 2 [2368] [23671 [2427] 2 [2428] 2 [2587] 2 [2588] 2 14.4 14.4 14.4 14.4 13.4 13.4 13.4 13.4 Notes

' Reference Technical Specification Section: 3.11.B.

2 Engineering Databank (EDB) Number.

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 will 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 will be maintained within the stable portion of Figure 7.

Reference Technical Specification Section 3.5.F.

NAD-MN-005, Montcello Cycle 22 COLR, Rev. 0 Page 6 of 16

10.0 Scram Time Dependence The 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 this section can be used.

Technical Specification 3.3.C provides the scram insertion time versus position requirements for continued operations. Technical Specification 4.3.C provides the surveillance requirements for the CRDs. Data from testing of the CRDs, or from an unplanned scram, issummarized 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:

n INivi ave n (1)

YNi )

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

ZJN, total number of active rods measured to date in the cycle; and i=l n sum of the scram time to the 20 percent insertion position of all active rods E N1 r,= measured to date in the cycle to comply with the technical Specification i=1 surveillance requirements NAD-MN-005. Monticello Cycle 22 COLR. Rev. 0 Page 7 of 16

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

fave - VB (2) where:

rB = u + 1.65 (3)

The parameters ptand a are the mean and standard deviation of the distribution of the average scram insertion time to the 20 percent position in the ODYN option B analysis (Table 3).

N, = number of active rods tested at BOC Table 3 GEMINI Methods, CRD Control Fraction vs. Time 0% 5% - 20% 50% 90% 100%

li (sec) 0.200 0.324 0.694 1.459 2.535 2.804 a (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.

The equation to establish the new operating limit for pressurization events is given below:

OLMCPR,,, = OLMCPRptio,B + TA B AOLMCPR (4) where:

'rave and B are defined in Equations 1 and 3, respectively; TA = the Technical Specification limit on core average scram time to the 20 percent insertion limit. (Technical Specification 3.3.C @ 20% insertion)

AOLMCPR= the difference between the OLMCPR calculated using Option A and that using Option B for Pressurization events.

NAD-MN-005, Monticello Cycle 22 COLR, Rev. 0 Page 8 of 16

Table 4 Cycle MCPR Values Transient Option A Option B FW Controller Failure 1.67 1.50 Turbine Trip wlBypass' 1.55

1. The Turbine Trip w/Bypass transient will be used as the Minimum OLMCPR transient for Option B Analysis.

Sample Calculation:

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 1.55 can be used.

Please note fhat fhe value of 1.55 will be used as the minimum Option B OLMCPR. The 1.55 OLMCPR is conservative with respect to the Option B pressurization transient OLMCPR (1.50) presented in Table 4.

If 'rave is 0.800 seconds and TB is 0.70 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:

OLMCPRNew = OLMCPRoptionB + ave B AOLMCPR TA TB OLMCPRpio,,B = 1.50 (from table 4 above)

Tave = 0.800 TB = 0.700 TA = 0.900 (Technical specification 3.3.C)

AOLMCPR= 1.67-1.50 = 0.17 (from table 4 above)

OLMCPR = 1.50 +(0.800-0.700) *0. 17 = 1.59

.0.900-0.700)

NAD-MN-005, Monticello Cycle 22 COLR, Rev. 0 Page 9 of 16

Figure 1 Monticello Cycle 22 Power Dependent MAPLHGR Limits 1.10 1.00 0.90 0.80 IL LL 0.70 I-0 IL MAPLHGRp = MAPFACp MAPLHGRstd 0.60

/ ~ ~~~

<50% flow

<50% flow For 25% > P: No Thermal Limits Required 0

0~ For 25%

  • P < 45%, >50% Flow C) 0.50 MAPFACp=0.527+0.001 55(P-45%)

=0

- >.50% Flow For 25% f P < 45%,

  • 50% Flow

> '50% Flow ~MAPFACp=0.677+0.00775(P-45%)

0~

0.40 For45% S P < 100%

MAPFACp=1 .0+0.005224(P-100%)

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

NAD-MN-005, Monticello Cycle 22 COLR, Rev. 0 Page lO of 16

Figure 2 Monticello Cycle 22 Flow Dependent MAPLHGR Limits 1.1 1

MAPMULT(F) = 0.94 0.9 i; 0.8 I5 IL

  • 0.7 0

I-C.)

IL 0

-z IL MAPFACF = MINIMUM MFRPD,, MAPMULTF]

'L0.5 MAPMULTF = 1.0 FOR FLOW> 80%

MAPMULTF = 094 FOR FLOW- 80%

MFRPD = MINIMUM [1.0, nF + b]

F = CORE FLOW(% OF RATED 00 0.4 n = 0.6758 b =0.4574 0.3 30 40 50 60 70 80 90 100 110 Core Flow (% Rated)

NAD-MN-005, Monticello Cycle 22 COLR, Rev. 0 Page IIof 16

Figure 3 Monticello Cycle 22 Power Dependent CPR Limits 4.0  : I I I I I I Operating Limit MCPR (P) = Kp

  • Operating Limit MCPR (100)

U)

For P< 25%: No Thermal Limits Monitoring Required 51 For 25% < P < 45%, > 50% Flow v OLMCPR(P) = 2.60+0.027(45%-P)

IL For 25% < P < 45%, < 50% Flow 0Fo > 50% For OLMCPR(P) = 2.12+0.0295(45 0/-P) t 3.0 - -- d-- ' For 45% < P < 60% Kp=1.15 +0.00867(60%-P) a.

For 60% < P < 100% Kp=1.00 + 0.00375(100%-P)

-j 0

IRT A 2.5 L.

40 F,low: 50%,\

a. -I Y.,

Ia 9

I 9II 1.5 I - I 1.0 20 30 40 50 60 70 80 90 100 110 Power (% rated)

NAD-MN-005, Monticello Cycle 22 COLR, Rev. 0 Page 12 of 16

Figure 4 Monticello Cycle 22 Flow Dependent CPR Limits 1.8 For W(C) (%Rated Core Flow) > 30%_

MCPR(F) = MAX(1.23, A(F)

  • W(C) 1100 + B(F))

1.7 Max Flow 107.0 A(F) = -0.602 B(F) = 1.745 1.6 cL 0)

E 1.5 0.

n 1.4 c

0 CL a.

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

NAD-MN-005, Monticello Cyde 22 COLR, Rev. 0 Page 13 of 16

f Figure Monticello Nuclear Generating Plant Power-Flow Operating Map area.

Rated /

Power 1750

  • t-I.

Total Core Flow (MLb/Hr)

Page 4 of 16 NAD-MN-005, Monticello Cycle 22 COLR Rev. 0

Figure 6 Monticello Nuclear Generating Plant Power-Flow Operating Map 90 Operation not allowed in the 80 4.4.44.Id.,I.44.IA4 .Ij......... L..... I slanted shading area.

LO IN 75*...rr... 44 ....... ......

0 60 ......I. ... e i t exi:.........*.......

........... . .. R EG ON~

80-`'RV 1euieinth , g-e!dl-iuth 55 4.g.i, .4.4...~. 444 .44. 4 '2.4m'44.,,4 ~.LnI4Y$444cnbo.creqaird 75 d uble.............. Z.......~tie Hil EA t al ?Jat al.C.r.u.a..on 0 ........ d3.%p.pe d in r4 30~~ ~~ ~ ~~~~~~~u~~~~~~~d d;~~~~~~~~~~~~:::............. .a .......

15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 To tal Core Flow (MLb/Hr)

NA Page 15 of 16

Figure 7 Stability Criterion Map 0.7 0

4 0.6 0

U 0.5 -

It 0.4 L z-0.3 0.2-0.1 0.0 . 0 0 0 1.0 0.0 -0.2 0.4 0.6 0.8 1.0 CHANNEL DECAY RATIO NAD-MN-005, Monticello Cycle 22 COLR Rev. 0 Page 16 of 16

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