NMP1L3143, Submittal of Core Operating Limits Report Cycle 23, Revision 3

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Submittal of Core Operating Limits Report Cycle 23, Revision 3
ML17109A366
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 04/13/2017
From: Moore D
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NMP1L3143
Download: ML17109A366 (14)
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~/ Exelon Generation Technical Specification 6.6.5 NMP1L3143 April 13,.2017 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:

Nine Mile Point, Unit 1, Core Operating Limits Report Enclosed is a copy of the Core Operating Limits Report, Cycle 23, Revision 3 for Nine Mile Point Unit 1 (NMP1 ). 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 me at (315) 349-5219.

Dennis M. Moore Regulatory Assurance Manager, Nine Mile Point Nuc;:lear Station Exelon Generation Company, LLC DMM/RSP

Enclosure:

Core Operating Limits Report for Nine Mile Point Unit 1 Cycle 23, Revision 3

  • cc: NRC Regional Administrator, Region I NRC Project Manager NRC Senior Resident Inspector

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 3 Core Operating Limits Report for Nine Mile Point 1 Cycle 23 CORE OPERATING LIMITS REPORT FOR NINE MILE POINT NUCLEAR STATION UNIT 1 RELOAD 24 CYCLE 23

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Prepared By: Date: _3/30/17 C.Burns Cycle Manager

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ReviewedBy: -~~'"'----........,~~-~-------~ Date: ?,/30/,7 A. Hopkins Independent Reviewer Reviewed By: C::::S--:--~~ Date: 3/5cJ ft}

J. Darweesh Reactor Engineering Reviewer Reviewed By: ---.ih~11<1'-11i""J+-~-61-...b"'"""'lef2~'l?"'"'e...,,(t_ _ _ __ Date: 03/30/2017 D. S. Knep)ber Engineering Safety Analysis Reviewer Approved By: --~----~-'---------- A. Johnson 30MAR17 Date: _ _ _ __

Senior Manager - Cycle Management Station Qualified Review By:

Date: March 31, 2017 E. l<elsey A. Ross Page 1 ofl3

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 3 Core Operating Limits Report for Nine Mile Point 1 Cycle 23 Table of Contents Section Title 1.0 Terms 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 I Flow Line 11 7.0 Modes of Operation 12 8.0 Methodology 13 9.0 References 13 Page 2of13

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 3 Core Operating Limits Report for Nine Mile Point 1 Cycle 23 Record of COLR Nine Mile Point 1 Cycle 23 Revisions Revision Description Rev. Number - 3 New Issuance for Cycle 23 Page 3of13

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 3 Core Operating Limits Report for Nine Mile Point 1 Cycle 23

  • 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 Kp 9 Table 4-4 Flow Dependent Operating Limit MCPR Multiplier, KF 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 4of13

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 3 Core Operating Limits Report for Nine Mile Point 1 Cycle 23 1.0 Terms and Definitions APRM Average Power Range Monitor ARTS APRM, Rod Block, 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 - one 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 - TDFWP in service AND two MDFWPs in service.

Off-rated power dependent OLMCPR multiplier Off-rated flow dependent OLMCPR multiplier LHGR Linear Heat Generation Rate LHGRFACF Off-rated LHGR flow dependent thermal limit multipliers LHGRFACp Off-rated LHGR power dependent thermal limit multipliers MAPFACF Off-rated flow dependent MAPLHGR multiplier MAPFACp Off-rated power dependent MAPLHGR multiplier MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR. Minimum Critical Power Ratio MCPRF Off-rated flowdependent OLMCPR MCPRp Off-rated power dependent OLMCPR MDFWP Motor Driven Feedwater Pump OLMCPR Operating Limit Minimum Critical Power Ratio PROOS Pressure Regulator Out of Service RTP Rated Thermal Power TDFWP Turbine Driven Feedwater Pump Page 5of13

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 3 Core Operating Limits Report for Nine Mile Point 1 Cycle 23 2.0 General Information This report provides the following cycle-specific parameter limits for Nine Mile Point Nuclear Station Unit 1 Cycle 23:

  • 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 thermal limit adjustments and multipliers (MCPRp, MCPRF, Kp, KF)
  • Linear Heat Generation Rate (LHGR)
  • LHGR thermal limit multipliers (LHGRFACp)

Power and flow dependent limits are listed for various power and flow levels. Linear interpolation is to be used to find intermediate values. Nine Mile Point Unit 1 is a non-ARTS plant that utilizes ELLLA operating domain.

The data presented in this report is valid for all licensed operating domains on the operating map, including: *

  • Extended Load Line Limit down to the minimum licensed core flow (i.e., 85.0% of rated) during full power operation,
  • Rated core flow of 67.5 Mlb/hr,
  • End-of-cycle coastdown to a minimum power level of 40% of rated thermal power,
  • Feedwater temperature of no more than -10°F off nominal is licensed for this cycle.

Further information on the cycle-specific analyses for Nine Mile Point Unit 1 Cycle 23 and the .

associated operating domains discussed above is available in Reference 2.

Page 6of13

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 3 Core Operating Limits Report for Nine Mile Point 1 Cycle 23 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 shown 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 power and flow dependent multipliers for MAPLHGR have been removed and replaced with LHGRFACp and LHGRFACF; therefore, MAPFACp and MAPFACF are equal to 1.0 for all power and flow conditions (Reference 1O - 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 Limit1 (GWD/ST) (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

Page 7of13

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 3 Core Operating Limits Report for Nine Mile Point 1 Cycle 23 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 Cycle 23 operating domains. Nine Mile Point Unit 1 Cycle 23 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 Kp 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 MCPRp in Table 4-3.

The power dependent MCPR limits are presented in Table 4-3 and are valid for all GNF2 bundles. Below 45% rated thermal power, the MCPRp limits in Table 4-3 are applied directly; at or above 45% power, the KP multiplier is applied to the OLMCPR from Table 4-1. The appropriate MCPRp or Kp 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 KF 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 Recirculation Loop Operation)

(Reference 2 - Section 11)

Cycle Exposure Feedwater Pump SCRAM Time 2

Option 3 < EOR - 2037 ~ EOR - 2037 Combination MWd/ST MWd/ST B 1.48 1.53 FWP Combination 1 A 1.58 1.63 B 1.52 1.57 FWP Combination 2 A 1.62 1.67 2

OLMCPR values are independent of pressure regulator in-service or out-of service conditions.

3 For tau (i) = 0, use SCRAM Time Option B limits. For ('t) = 1, use SCRAM Time Option A limits. When tau does not equal 0 or 1, use linear interpolation. Tau is defined as:

. _(Tave-TB) h (Ref.7-Item2)

-r - (TA-TB) w ere iA = 0.868 seconds, control rod average scram insertion time limit to notch 39 (Ref. 1 Appendix A-T.S. 3.1.1.c.l) iB = 0.672 + 1.65 . .J Li1.;::;1Ni

'<.'Ni .

  • 0.016 (Ref. 3 -Table 6-11, n ) Ref. 6-ltem 1.2.K,

-r = Li=1 NiTi Ref. 7 - Item 2) ave ( Lf=1Ni where n =number of surveillance tests performed in cycle; N; = number of active control rods measured in the i1h surveillance test; T; =average scram time to notch 39 of all rods measures in the /h surveillance test; and Nt =total number of active rods measured.

Page 8of13

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 3 Core Operating Limits Report for Nine Mile Point 1 Cycle 23 Table 4-2 MCPR Adder for Three Recirculation Loop Operation (GNF2)

(Reference 2- Footnote 7)

Three Recirculation Loop Operation 0.03 Adder Table4-3 Power Dependent MCPR Limits and Multipliers, MCPRp and Kp (GNF2)

(Reference 2 - Appendix D)

Core Core Thermal Power (% of Rated)

EOOS Flow 0 25 <45 ~45 65  :::; 85 > 85 100 Combination (%of Operating Limit Operating Limit MCPR Multiplier, Kp rated) MCPR, MCPRp FWP*  ::;60 3.24 3.24 2.30 1.349 1.216 1.133 1.133 1.000 Combination 1 > 60 3.34 3.34 2.77 FWP  ::;60 3.24 3.24 2.30 1.349 1.216 1.133 1.133 1.000 Combination 2 > 60 3.34 3.34 2.77

60 3.24 3.24 2.30 PROOS4 1.553 1.336 1.198 1.133 1.000

> 60 3.34 3.34 2.77 Table4-4 Flow Dependent Operating Limit MCPR Multiplier, KF (GNF2)

(Reference 2 - Appendix D)

Flow MCPR

(%rated) Multiplier, KF 5 0.0 1.500 S45.0 1.500

>45.0 1.132 75.0 1.000 102.5 1.000 4

Limits apply to PROOS coincident with FWP Combination 1 or 2.

5 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.

Page 9of13

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 3 Core Operating Limits Report for Nine Mile Point 1 Cycle 23 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 nor 11 kW/ft 6

  • 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. Below 45%

RTP, no additional limits are required. These power dependent LHGR multipliers (LHGRFACp) are provided in Table 5-3 for Option Band 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 curves 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)

FuelT e LHGR GNF2* See Table B-3 of Reference 4 Table 5-2 Linear Heat Generation Rate Limits - Gadolinia Rods (Reference 4)

FuelT e LHGR GNF2 See Table B-4 of Reference 4 Table 5-3 Power Dependent LHGR Multiplier LHGRFACp for PROOS

. (GNF2) .

(Reference 2 - Appendix D)

Scram Time Option Core Thermal Power (% of rated) 0 <45 ~45 65 85 100 Option A (i.e. r > 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 6

The GNF2 LHGR limit has been set down to a maximum value of 11 kW/ft for Emergency Procedure Guidelines (EPG) requirements.

Page 10 of13

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 3 Core Operating Limits Report for Nine Mile Point 1 Cycle 23 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 power/flow relationship is shown in Figure 6-1.

Figure 6-1 Limiting Power/Flow Line (References 5 and 8) 120 100 85.0, 100.0) ( 00.0, 100.0)

,....._ lo"

~

"O

.....0:Cl.l

~

.... 80 ~

0

~

~

e~

Jo.

Cl.l

~ 60 0

~ Power= 0.55* W+53 e

Jo.

Cl.l

-=E-- 40 Cl.l Jo.

0 u

20 0

0 20 40 60 80 100 120 Core Flow(% of Rated) - W Page 11of13

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 3 Core Operating Limits Report for Nine Mile Point 1 Cycle 23 7 .0 Modes of Operation The allowable modes of operation are found in Table 7-1. Operation with PROOS is supported in all modes of operation, provided the restrictions identified in the applicable station procedures are met. Operation up to 67.5 Mlb/hr core flow is licensed for this cycle (Reference 2). The minimum coastdown thermal power level is 40% per GESTAR II (Methodology Document 1).

  • All EOOS options allow for three recirculation loop operation.
  • 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 Region Four/Five-loop Operation, FWP Combination 1 Yes Four/Five-loop Operation, FWP Combination 2 Yes PROOS, Four/Five-loop Operation, FWP Combination 1 or 2 Yes Three-loop Operation, FWP Combination 1 Yes' Three-loop Operation, FWP Combination 2 Yes' PROOS, Three-loop Operation, FWP Combination 1 Yes 7 PROOS, Three-loop Operation, FWP Combination 2 Yes 7 7

Per Ref. I Appendix A - TS 3. I. 7 .e, during three-loop operation power is restricted to 90% of rated.

' Page 12 of 13

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 3 Core Operating Limits Report for Nine Mile Point 1 Cycle 23 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, specifically those described in the following document:

1. "General Electric Standard Application for Reactor Fuel," Global Nuclear Fuel Document No. NEDE-24011-P-A-24, March 2017 and U.S. Supplement NEDE-24011-P-A-24-US, March 2017.

9.0 References

1. "Nine Mile Point Nuclear Station, Unit 1 Renewed Facility Operating License", Docket No. 50-220, License No. DPR-63.
2. "Supplemental Reload Licensing Report for Nine Mile Point 1 Reload 24 Cycle 25", Global Nuclear Fuel Document No. 002N6949, Revision 0, March 2017.
3. "Engineering Report for Nine Mile 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 II)," Global Nuclear Fuel Document No. NEDC-33270P, Revision 7, October 2016.
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.
6. "Final Resolved OPL-3 Parameters for Nine Mile Point Unit 1 Cycle 23 (25)", Exelon Document No. ES1600018 Rev. 0, September 2016.
7. "Qualification of the One-Dimensional Core Transient Model for Boiling Water Reactors," General*

Electric Document ID NED0-24154 and NEDE-24154P, Volumes I, II, and Ill, August 1986.

8. "Nine Mile Point 1 Cycle 24 Limiting Load Line Analysis," Global Nuclear Fuel Letter, Document No. 002N5662-RO, March 18, 2015.
9. "Feedwater System Booster Pump to Reactor, N1-0P-16 Rev. 06401, Nine Mile Point Nuclear Station Unit 1 Operating Procedure
10. "Nine Mile Point Nuclear Station Unit 1 TRACG-LOCA Loss-of-Coolant Accident Analysis for GNF2", GEH Nuclear Energy Doc No. 002N3714 Rev. 0, March 2017.

8 The information referenced from this report (see COLR Section 4.2) is cycle independent.

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