NMP1L3395, Core Operating Limits Report

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Core Operating Limits Report
ML21126A214
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 04/28/2021
From: Shultz B
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NMP1L3395
Download: ML21126A214 (17)
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Text

  1. *'W jJL&E> Exelon Generation Technical Specification 6.6.5 NMP1L3395 April 28, 2021 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-001 Nine Mile Point Nuclear Station, Unit 1 Renewed Facility Operating License No. DPR-63 NRC Docket No. 50-220

Subject:

Core Operating Limits Report Enclosed is a copy of the Core Operating Limits Report, Revision 5, for Nine Mile Point Unit 1 Cycle 25. This report is being submitted pursuant to NMP1 Technical Specification 6.6.5.d.

Should you have any questions regarding the information in this submittal, please contact Mr.

Philip Nichols at (315) 349-7444.

Sincerely, 1 Digitally signed by Shultz, Shultz Brandon I KABrandonK

+~~ ...

j - Date: 2021.04.28 09:37:28 -Q4'00' Brandon K. Shultz Mgr. Site Regulatory Assurance, Nine Mile Point Nuclear Station Exelon Generation Company, LLC

Enclosure:

Core Operating Limits Report, Revision 5 for Nine Mile Point Unit 1, Cycle 25 cc: NRC Regional Administrator, Region I NRC Project Manager NRC Senior Resident Inspector

Core Operating Limits Report April 28, 2021 Page 2 bee: (Without Enclosure)

P. M. Orphanos A. G. Schuerman C. D. Giambrone S. B. Rafferty-Czincila D P. Ferraro R. L. Carmean B. K. Shultz P. M. Nichols

Enclosure Core Operating Limits Report, Revision 5

. for Nine Mile Point Unit 1, Cycle 25

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mlle Point 1, Rev. 5 Core Operating Lbnlil Report for Nine Mlle Point 1 Cycle 25 CORE OPERATING LIMITS REPORT FOR NINE MILE POINT NUCLEAR STATION UNIT 1 RELOAD 26 CYCLE 25

~ Digitally signed by Schaefer, Jason P Schaefer Jason 1

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P~R~cn=Schaefer,Jason p

  • Date: 2021.03.26 08:31 :29 -04'00' 1

Prepared By: _ _ _ _ _ _ _ _ _ _ _ _ _ _ Date: _ _ _ __

Jason P. Schaefer

__ l~~d~;: 2021.03.26 Reviewed By:

- -d .- -

Kelly R. McClure 09:13:07oaQ4'00' ___  ;;._;;;__;;;_

Independent Reviewer I Dlgltally signed by Ross, Andrew M Reviewed By: Ross, Andrew M /-'Date: 2021.03.26 ~~ 4 --04'00' Andrew M. Ross Reactor Engineering Reviewer:.

  • Knepper/ Da VI d s

. * }. Digitally signed by Knepper, David S:

_\DN: cn=KnE:f>per, David s.

Reviewed By: -----------.:-l,:_---~-F""'asM,t0~:-6J2021.li'-~ og:0s*S4 .05'00' David S. Knepper l/

Engineering Safety Analysis Reviewer Megan Doerzbacher Doerzbacher, Megan Approved By: for Ashley Kovacs 2021.03.28 b7a?tP.:07 -Q4'00' Ashley Kovacs

_Senior Manager - NF Cyde Management J /21,/J ~ , A( Digitally signed by Kelsey, Eric A Station Qualified ~~

Review By: __,___* ,* _;; /--Date: 202ck~J.29 09:23:06-()4'00' l:=rlc A Kelsey SOR Reviewer Page 1 of14

Exelon Nuclear - Nuclear Fuels Doc ID: COLRNine Mile Point 1, Rev. 5 Core Operating Limits Report for Nine Mlle Point 1 Cycle 25 Table of Contents Section Trtle 1.0 Tenns and Definitions 5 2.0 General Information 6 3.0 MAPLHGR Limits 7 4.0 MCPR Limits 8 5.0 LHGR Limits 10 6.0 Limiting Power/ Flow Line 11 7.0 Modes of Operation 12 8.0 Methodology 13 9.0 References 14 Page 2 of14

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. S Core Operating Limits Report for Nine Mlle Point 1 Cycle 2S Record of COLR Nine Mlle Point 1 Cycle 25 Revisions Revision Description Rev. Number-5 New Issuance for Cycle 25 Page3 of14

Exelon Nuclear - Nuclear Fuels Doc ID: COLRNlne Mlle Point 1, Rev. 5 Core Operating LimttB Report for Nine Mile Point 1 Cycle 25 List of Tables Page Table 3-1 MAPLHGR Versus Average Planar Exposure - GNF2 7 Table 3-2 MAPLHGR Multiplier for Four and Three Recirculation Loop Operation 7 Table 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR) 8 Table 4-2 MCPR Adder for Three Recirculation Loop Operation 9 Table 4-3 Power Dependent MCPR Limits and Multipliers, MCPRp and l(p 9 Table 4-4 Flow Dependent Operating Limit MCPR Multiplier, l<F 9 Table 5-1 Linear Heat Generation Rate Limits- U0:2 Rods 10 Table 5-2 Linear Heat Generation Rate Limits - Gadolinia Rods 10 Table 5-3 Power Dependent LHGR Multiplier LHGRFACp for PROOS 10 Table 7-1 Modes of Operation 12 List of Figures Figure 6-1 Limiting Power/Flow Line 11 Page 4 of14 .

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 5 Core Operating Umlts Report for Nine Mile Point 1 Cycle 25 1.0 Terms and Definitions APRM Average Power Range Monitor ARTS APRM, Rod Block Monitor, and Technical Specification Improvement Program ELLLA Extended Load Line Limit Analysis EOOS Equipment Out of Service EOR End of Rated. The cycle exposure at which reactor power is equal to rated thermal power with recirculation system flow equal to 100%, all control rods fully withdrawn, all feedwater heating in service and equilibrium Xenon.

FWP Combination 1 Feedwater Pump Combination 1 as defined in Reference 9 Attachment 13 Section 4.0 - TDFWP in service AND one MDFWP in service. This bounds TDFWP in service OR one MDFWP in service OR two MDFWPs in service.

FWP Combination 2 Feedwater Pump Combination 2 as defined in Reference 9 Attachment 13 Section 4.0 - IDFWP In service AND two MDFWPs In service.

Ki= Off-rated flow dependent OLMCPR multiplier l

endent MAPLHGR multiplier MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MCPRp Off-rated power dependent OLMCPR MDFWP Motor Driven Feedwater Pump OLMCPR Operating Limit Minimum Critical Power Ratio PROOS Pressure Regulator Out of Service HTP Rated Thermal Power SLMCPR Safety Limit Minimum Critical Power Ratio TDFWP Turbine Driven Feedwater Pump Pages of14 Exelon Nuclear - Nuclear Fuell Doc ID: COLRNine Mile Point 1, Rev. 5 Core Operating Llmitl Report for Nine Mlle Point 1 Cycle 25 2.0 General Information This report provides the following cyde-specific parameter limits for Nine Mile Point Nuclear Station Unit 1 Cycle 25:

  • Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)
  • MAPLHGR four and three recirculation loop operation multipliers
  • Operating Limit Minimum Critical Power Ratio (OLMCPR)
  • Three recirculation loop operation MCPR adjustment
  • MCPR thennal limit adjustments and multipliers (MCPRp, l(p, l<F)
  • Linear Heat Generation Rate (LHGR)
  • LHGR thennal limit multipliers (LHGRFACp)
  • Limiting Power I Flow Line This report is prepared in accordance with Technical Specification 6.6.5 of Reference 1 Appendix A Power and flow dependent limits are listed for various power and flow levels. Linear interpolation is to be used to find lntennediate values. Nine Mile Point Unit 1 is a non-ARTS plant that utilizes ELLLA operating domain. ,

The data presented In this report is valjd for all licensed operating domains on the operating map, lnduding:

  • Extended Load Line Limit down to the minimum licensed core flow (I.e., 85% of rated) during full power operation,
  • Rated core flow of 67 .5 Mlbnir,
  • Each mode supports operation with up to 10°F reduction in feedwater temperature.

Further infonnation on the cyde-specific analyses for Nine Mile Point Unit 1 Cycle 25 and the associated operating domains discussed above is available in Reference 2. Note that GNF and Nine Mile Point Unit 1 have different cycle numbering schemes. Cycle 25 is referred to as Cycle 27 in all GNF dOCU!llE!ntation.

  • Page6 of14

Exelon Nuclear - Nuclear Fueh Doc ID: COLR N'me MIie Point 1, Rev. 5 Core Operating Limltll Report for Nine Mlle Point 1 Cycle 25 3.0 MAPLHGR Limits 3.1 Technical Specification 3.1.7.a, 3.1.7.e, 6.6.5.a.1 3.2 Description The MAPLHGR limits for each bundle type as a function of average planar exposure is given in Table 3-1. For reduced loop operation, a fuel type dependent multiplier is used, which is shqwn in Table 3-2. For operation with either four or three recirculation loops in service, multiply the values shown in Table 3-1 by the GNF2 value In Table 3-2. The MAPLHGR limits In Table 3-1 provide adequate protection for off-rated conditions, therefore, MAPFACp and MAPFACF are equal to 1.0 for all power and flow conditions (Reference 6 - Section 2). LHGRFACp and LHGRFACF are addressed in Section 5.0. Table 3-1 MAPLHGR Versus Average Planar Exposure - GNF21: (Reference 2 - Section 16.3) Average Planar Exposure MAPLHGR Llmlt1 (GWD/STI (kW/ft) 0.00 9.85 13.61 9.85 16.33 9.50 25.40 9.50 29.94 9.00 41.10 9.00 57.15 6.96. Table 3-2 MAPLHGR Multiplier for Four and Three Recirculation Loop Operation (Reference 2 - Section 16.3) Four and Three Loop Operation Fuel Type Multiplier GNF2 1.00 1 These MAPLHGRs are fuel lattice independent Page7 of14 Exelon Nnclear - Nuclear Fuell Doc ID: COLR Nine Mlle Point 1, Rev. S Core Operating Umtts Report for Nine Mlle Point 1 Cycle 25 4.0 MCPR Limits 4.1 Technical Specification 3.1.7.c, 3.1.7.e, 6.6.5.a.2, 6.6.5.a.3 4.2 Description The OLMCPR Is determined for a given power and flow condition by evaluating the power dependent MCPR and the flow dependent MCPR and selecting the greater of the two. Tables 4-1 and 4-2 originate in Reference 2 and are valid for all operating domains. The current cycle has a mid-cycle MCPR breakpoint, as defined in Table 4-1. Note that PROOS has no effect on the base OLMCPRs in Table 4-1; however, there are PROOS l<p multipliers in Table 4-3. , For three loop recirculation, the adder presented in Table 4-2 must be applied to all limits in Table 4-1 and MCPRi, in Table 4-3. The power dependent MCPR limits are presented in Table 4-3 and are valid for all GNF2 bundles. Equal to' or below 45% rated thermal power, the MCPRp limits in Table 4-3 are applied directly; above 45% power, the l(p multiplier is applied to the OLMCPR from Table 4-1. The appropriate MCPRp or l(p value may be determined by linear Interpolation for statepoints not explicitly listed. The flow adjusted OLMCPR is determined by multiplying the applicable rated condition OLMCPR provided by Table 4-1 (and as affected by Table 4-2) by the applicable 1<F multiplier given in Table 4-4. The appropriate KF value may be determined by linear interpolation. Table 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR) (GNF2, Four/Five Recirculatlon Loop Operatioh) (Reference 2 - Section 11 l Cvcle Exposure Feedwater Pump SCRAM Time Comblnation2.3 Optlon4 < EOR - 2211 ~ EOR - 2211 MWd/ST MWd/ST B 1.48 1.55 FWP Combination 1 'A 1.58 1.65 B 1.51 1.58 FWP Combination 2 A 1.61 1.68 2 O:J.,MCPR values are independent.of pressure regulator in-service or out-of service conditions. 3 The OLMCPR values are based on safety limit minimum critical power ratio (SLMCPR) values of 1.09 for four/five loop operation and 1.11 for reduced loop operation (Reference*2). 4 For tau ('t) ~ 0, use SCRAM Time Option B limits. For (t) ~ l, use SCRAM Time Option A limits. When tau is between O and 1, use linear interpolation in accordance with site procedure to calculate OLMCPR (Reference 3). Page 8 of14 Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 5 Core Operating Limits Report for Nine Mlle Point 1 Cycle 25 Table 4-2 MCPR Adder for Three Recirculation Loop Operation (GNF2) (Reference 2 - Footnote 8) Three Recirculation Loop Operation 0.02 Adder Table 4-3 Power Dependent MCPR Limits and Multlpllers, MCPRp and f{p (GNF2) (Reference 2 - Appendix D) Core Core Thermal Power (% of Rated) EOOS Flow 0 25 S45 >45 65 s 85 > 85 100 Combination (% of Operating Limit Operating Limit MCPR Multlpller, Kp rated) MCPR. MCPR,, FWP, < 60 3.24 3.24 2.31 1.349 1.216 1.133 1.133 1.000 Combination 1 .:?: 60 3.30 3.30 2.78 FWP < 60 3.24 3.24 2.31 1.349 1.216 1.133 1.133 1.000 Combination 2 ~60 3.30 3.30 2.78 < 60 3.24 3.24 2.31 PROOS5 1.553 1.336 1.198 1.133 1.000 o::60 3.30 3.30 2.78 Table 4-4 Flow Dependent Operating Limit MCPR Multlpller, Ki= (GNF2) (Reference 2 -Appendix D) Flow MCPR (% rated) Multiplier~ Ki:6 0.0 1.500 S45.0 1.500 >45.0 1.132 75.0 1.000 102.5 1.000 5 Limits apply to PROOS coincident with FWP Combination 1 or 2. 6 Values are applicable up to a Maximum Runout Flow of 102.5% of rated. Values apply to operation in either FWP Combination 1 or.2 with or without Pressure Regulator in-service. Page9 of14 Eielon Nuclear - Nuclear Fueh Doc ID: COLR Nine Mlle Point 1, Rev. 5 Core Operating Limits Report for Nine Mile Point 1 Cycle 25 5.0 LHGR Limits 5.1 Technical Specification 3.1.7.b, 6.6.5.a.4 5.2 Description The Linear Heat Generation Rate for all fuel bundles shall not exceed the LHGR limits presented In Tables 5-1 and 5-2. Linear interpolation should be used for points not listed in Appendix B of Reference 4. Power adjusted LHGR limits are required for operation with PROOS at greater than or equal to 45% RTP. ~low 45% RTP, no additional limits are required. These power dependent LHGR multipliers (LHGRFACp) are provided in Table 5-3 for Option B and Option A scram times and are applicable to GNF2 (Reference 2). The power adjusted LHGR is determined by multiplying the applicable LHGR limit by the LHGR multiplier, LHGRFACp. The LHGRFACp cutves are independent of recirculation loop operability. The appropriate LHGRFACp values may be determined by linear interpolation. Flow dependent LHGR multipliers (LHGRFACF) are not required (Reference 2). Table 5-1 Linear Heat Generation Rate Limits - U02 Rods (Reference 4 and 7) FuelT e LHGR GNF2 See Table 8-3 of Reference.4 Table 5-2 Linear Heat Generation Rate Limits ..:. Gadolinla Rods (Reference 4 and 7) FuelT e LHGR GNF2 See Table *s-4 of Reference 4 Table 5-3 Power Dependent LHGR Multiplier LHGRFACP for PROOS (GNF2) (Reference 2 - Appendix D), Core Thennal Power (% of rated) Scram Time Option 0 <45 ~45 65 85 100 Option A 0.e. T > O) 1.000 1.000 0.518 0.518 0.636 1.000 Option B 1.000 1.000 0.737 0.867' 0.987 1.000 Page 10 of14 Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mlle Point 1, Rev. 5 Core Operating Limftl Report for Nine Mlle Point 1 Cycle 25 6.0 Limiting Power/Flow Line 6.1 Technical Specification 3.1.7.d, 3.1.7.e, 6.6.5.a.5 6.2 Description The Nine Mile Point Unit 1 limiting power/flow relationship is shown In Figure 6-1. Figure 6-1 Limiting Power/Flow Line (References 5 and 8) 120 (85, 100) (100, 100) 100 ,,,, ~ j ~ ~ 0 80 ~ ~ '.f!. t Ir; 0 60 ~ Power= 0.55* W+53 !Q,I ~ 40 f0 u 20 0 0 20 40 60 80 100 120 Core F1ow .. W (% of Rated) Page 11 of14 Exelon Nuclear - Nuclear Fuel& Doc ID: COLR Nine Mlle Point 1, Rev. 5 Core Opecating Lhntts Report for Nine Mlle Point 1 Cycle 25 7.0 Modes of Operation The allowable modes of operation are found in Table 7-1. Operation up to 67.5 Mlb/hr core flow is llcensed for this cycle (Reference 2). The minimum coastdown thermal power level is 40% per T .S. 3.1. 7 .h (Reference 1).

  • All EOOS options allow for operation in either Option A or Option B.
  • Each mode supports operation with up to 10°F reduction in feedwater temperature.
  • Each mode may be coincident with coastdown operation.

Table 7-1 Modes of Operation (Reference 2) Allowed Operating Options Realon Four/Five-loop Operation, FWP Combination 1 Yes Four/Five-loop Operation, FWP Combination 2 Yes PROOS, Four/Five-loop Operation, FWP Combination 1 Yes PROOS, Four/Five-loop Operation, FWP Combination 2 Yes Three-loop Operation, FWP Combination 1 Yes7 Three-loop Operation, FWP Combination 2 Yes 7 PROOS, Three-loop Operation, FWP Combination 1 Yes 7 PROOS, Three-loop Operation, FWP Combination 2 Yes 7 7 Per Ref. 1 Appendix A-TS 3.1.7.e, during three-loop operation power is restricted to 90%, of rated. Page 12 of14 Exelon Nuclear - Nuclear Fuels Doc ID: COLRNine Mlle Point 1, Rev. 5 Core Operating Limits Report for Nine Mile Point 1 Cycle 25 8.0 Methodology 8.1 Technical Specification 6.6.5.b.1 8.2 Description The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, speclflcally those described in the following document:

1. "General Electric Standard Application for Reactor Fuel," Global Nuclear Fuel Document No. NEDE-24011-P-A-30, April 2020 and U.S. Supplement NEDE-24011-P-A-30-US, April 2020.

Page 13 of14 Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mlle Point 1, Rev. 5 Core Operating L1mit11 Report for Nine Mlle Point 1 Cycle 25 9.0 References

1. "Nine Mile Point Nuclear Station, Unit 1 Renewed Facility Operating License", Docket No. 50-220, License No. DPR-63 (through Amendment 244).
2. "Supplemental Reload Licensing Report for Nine Mile Point Unit 1 Reload 26 Cyde 2r, Global Nudear Fuel Document No. 006N3808, Revision 1, March 2021.
3. "Engineering Report for Nine Mlle Point Nuclear Station Unit 1 Reload 19", Global Nuclear Fuels Document No. 0000-0053-5247-ER Rev. 0, February 2007. 8
4. "GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR 11)," Global Nuclear Fuel Document No. NEDC-33270P, Revision 11, August 2020.
5. "Limiting Relationship Between Core Power and Core Flow Rate (TAC 63532),
  • NRC Letter, Nine Mile Point 1 Technical Specification Amendment 92 to Facility Operating License No. DPR-63, March 24, 1987 (NRC Accession Number ML010990453)
6. "Nine Mile Point Nuclear Station Unit 1 TRACG-LOCA Loss-of-Coolant Accident Analysis for GNF2 Fuel", GEH Nuclear Energy Document No. 002N3714 Rev. 0, March 2017.
7. "Fuel Bundle Information Report for Nine Mile Point Unit 1 Reload 26 Cycle 27", Global Nuclear Fuel Document No. 005N1939, Revision 0, February 2021.
8. "Nine Mile Point 1 Cyde 24 Limiting Load Line Analysis," Global Nuclear Fuel Letter, Document No. 002N5662-R0, March 18, 2019. 9
9. "Feedwater System Booster Pump to Reactor", N1-0P-16 Rev. 06800, Nine Mile Point Nuclear Station Unit 1 Operating Procedure.

8 The information referenced from this report (see COLR Section 4.2 footnote 4) is cycle independent 9 Cycle 24 Referenced in this document refers to GNF C24 which is equivalent to the site C22. Page 14 of14

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