NMP1L3525, Core Operating Limits Report

From kanterella
Revision as of 09:55, 8 May 2023 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Core Operating Limits Report
ML23111A070
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 04/19/2023
From: Shultz B
Constellation Energy Generation
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NMP1L3525
Download: ML23111A070 (1)
v • d • e


Text

Technical Specification 6.6.5 NMP1L3525 April 19, 2023 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 6, for Nine Mile Point Unit 1 Cycle 26. 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.

Eric Kelsey at (315) 349-7037.

Sincerely, CDigitally signed by Shultz, Shultz, Brandon K!\Brandon K. .

1,/ .. Date: 2023.04.19 00:20:28 -04'00' Brandon K. Shultz Mgr. Site Regulatory Assurance, Nine Mile Point Nuclear Station Exelon Generation Company, LLC

Enclosure:

Core Operating Limits Report, Revision 6 for Nine Mile Point Unit 1, Cycle 26 cc: NRC Regional Administrator, Region I NRC Project Manager NRC Senior Resident Inspector

Enclosure Core Operating Limits Report, Revision 6 for Nine Mile Point Unit 1, Cycle 26

Constellation Energy Generation - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 6 Core Operating Limits Report for Nine Mile Point 1 Cycle 26 CORE OPERATING LIMITS REPORT FOR NINE MILE POINT NUCLEAR STATION UNIT 1 RELOAD 27 CYCLE 26 Mcclure, Kelly Prepared By: 2023.03.17 15:42:10 -04'00' K. McClure NF Cycle Manager

~ rngitally signed by Eastmond, Eastmon d, Anrjt~in ti. Date: 2023.03.17 15:26:37 -05'00' Reviewed By:

A Eastmond lndependept Reviewer

/4~~ 1~ . ),pig.itally signed by Kelsey, Eric A

/>-Bate: 2023.03.20 21 :18:08 -04'00' Reviewed By: ll' E. Kelsey Reactor Engineering Reviewer Ahmed Rah ai~igit~lly 1 ,

signed by ~h':1ed, R~ha,t

-E>ate. 2023.03.1716.36.13-0400 Reviewed By: t/

R. Ahmed Engineering Safety Analysis Reviewer Digitally signed by Mccoskey, Kristin Date: 2023.03.21 16:20:26 -05'00' Approved By:

K. Mccoskey Senior Manager - NF Cycle Management Station Qualified

.L,~t.....:0at~:

~

}\Digit.ally signed by Kelsey, Eric A 2023.03.21 21 :46:12 -04'00' Review By:

E. Kelsey SQR Reviewer Page 1 of 14

Constellation Energy Generation - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 6 Core Operating Limits Report for Nine Mile Point 1 Cycle 26 Table of Contents Section Title Page 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 14 Page 2 of 14

Constellation Energy Generation - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 6 Core Operating Limits Report for Nine Mile Point 1 Cycle 26 Record of COLR Nine Mile Point 1 Cycle 26 Revisions Revision Description Rev. Number - 6 Initial Issuance for Cycle 26 Page 3 of 14

Constellation Energy Generation - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 6 Core Operating Limits Report for Nine Mile Point 1 Cycle 26 List of Tables Page Table 3-1 MAPLHGR Versus Average Planar Exposure - GNF2 7 Table 3-2 MAPLHGR Multiplier for 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 4-5 Safety Limit Minimum Critical Power Ratio (SLMCPR) 9 Table 5-1 Linear Heat Generation Rate Limits - U02 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 of 14

Constellation Energy Generation - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 6 Core Operating Limits Report for Nine Mile Point 1 Cycle 26 1.0 Terms and Definitions App. Condition 1 Application (App) Condition 1 is defined as operation with one TDFWP in seNice OR one MDFWP in seNice.

App. Condition 2 Application (App) Condition 2 is defined as operation with one TDFWP in seNice AND one MDFWP in seNice. This bounds TDFWP in seNice OR one MDFWP in seNice OR two MDFWPs in seNice.

App. Condition 3 Application (App) Condition 3 is defined as operation with one TDFWP in seNice AND two MDFWPs in seNice.

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 SeNice 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 seNice and equilibrium Xenon.

Off-rated flow dependent OLMCPR multiplier Off-rated power dependent OLMCPR multiplier LHGR Linear Heat Generation Rate LHGRFACF Off-rated LHGR flow dependent thermal limit multiplier LHGRFACp Off-rated LHGR power dependent thermal limit multiplier 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 MCPRp Off-rated power dependent OLMCPR MDFWP Motor Driven Feedwater Pump OLMCPR Operating Limit Minimum Critical Power Ratio PROOS Pressure Regulator Out of SeNice RTP Rated Thermal Power SLMCPR Safety Limit Minimum Critical Power Ratio TDFWP Turbine Driven Feedwater Pump Page 5 of 14

Constellation Energy Generation - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 6 Core Operating Limits Report for Nine Mile Point 1 Cycle 26 2.0 General Information This report provides the following cycle-specific parameter limits for Nine Mile Point Nuclear Station Unit 1 Cycle 26:

  • Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)
  • MAPLHGR three recirculation loop operation multiplier
  • Operating Limit Minimum Critical Power Ratio (OLMCPR)
  • Three recirculation loop operation MCPR adjustment
  • MCPR thermal limit adjustments and multipliers (MCPRP, 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 unless otherwise specified. 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% of rated) during full power operation,
  • Rated core flow of 67.5 Mlb/hr,
  • Each mode supports operation with up to 10°F reduction in feedwater temperature.

Further information on the cycle-specific analyses for Nine Mile Point Unit 1 Cycle 26 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 26 is referred to as Cycle 28 in all GNF documentation.

Page 6 of 14

Constellation Energy Generation - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 6 Core Operating Limits Report for Nine Mile Point 1 Cycle 26 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 three recirculation loops, in service, multiply the values shown in Table 3-1 by the GNF2 value in Table 3-2. No additional multiplier is required for operation with four recirculation loops in service.

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 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 Three Recirculation Loop Operation (Reference 2 - Section 16.3)

Fuel Type Three Loop Operation Multiplier GNF2 1.00 1

MAPLHGR limits are fuel lattice independent.

Page 7 of 14

Constellation Energy Generation - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 6 Core Operating Limits Report for Nine Mile Point 1 Cycle 26 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 two mid-cycle MCPR breakpoints, 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 Table4-3.

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. Equal to or below 45% rated thermal power, the MCPRP limits in Table 4-3 are applied directly, with the adder from Table 4-2 as required; above 45% power, the KP multiplier is applied to the OLMCPR from Table 4-1 (and as affected by Table 4-2). 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)

(Four/Five Recirculation Loop Operation)

(Reference 2 - Section 11)

Cycle Exposure Feedwater Pump SCRAM Time  ?! 5500 MWd/ST

?! EOR - 2213 Combination 2 ,3 Option4 < 5500 MWd/ST and< EOR-MWd/ST 2213 MWd/ST B 1.45 1.46 1.54 App. Condition 1 A 1.55 1.56 1.64 B 1.47 1.48 1.56 App. Condition 2 A 1.57 1.58 1.66 B 1.50 1.51 1.59 App. Condition 3 A 1.60 1.61 1.69 2

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

3 The OLMCPR values are based on the safety limit minimum critical power ratio (SLMCPR) values in Table 4-5.

4 For tau (r) :S 0, use SCRAM Time Option B limits. For (r) ~ 1, 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 of 14

Constellation Energy Generation - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 6 Core Operating Limits Report for Nine Mile Point 1 Cycle 26 Table 4-2 MCPR Adder for Three Recirculation Loop Operation (Reference 2- Footnote 10)

Three Recirculation 0.03 Loop Operation Adder Table 4-3 Power Dependent MCPR Limits and Multipliers, MCPRP and KP (Reference 2 - Appendix D)

Core Core Thermal Power (% of Rated)

EOOS Flow 0 25  ::;45 > 45 65  ::; 85 > 85 100 Combination (% of Operating Limit rated) Operating Limit MCPR Multiplier, Kp MCPR, MCPRP

< 60 3.25 3.25 2.32 App. Condition 1 1.349 1.216 1.133 1.133 1.000

~ 60 3.27 3.27 2.75

< 60 3.25 3.25 2.32 App. Condition 2 1.349 1.216 1.133 1.133 1.000

~ 60 3.27 3.27 2.75

< 60 3.25 3.25 2.32 App. Condition 3 1.349 1.216 1.133 1.133 1.000

~ 60 3.27 3.27 2.75

< 60 3.25 3.25 2.32 PROOS 5 1.553 1.336 1.198 1.133 1.000

~ 60 3.27 3.27 2.75 Table 4-4 Flow Dependent Operating Limit MCPR Multiplier, KF (Reference 2 - Appendix D)

Flow MCPR

(% rated) Multiplier, KF 6 0.0 1.500

45_0 1.500

> 45.0 1.132 75.0 1.000 102.5 1.000 Table 4-5 Safety Limit Minimum Critical Power Ratio (SLMCPR)

(Reference 2 - Section 11)

Exposure Range Four or Five Loop Value Three Loop Value

< 5500 MWd/ST 1.09 1.12

~ 5500 MWd/ST 1.10 1.12 5

Limits apply to PROOS coincident with any Application Condition.

6 Values are applicable up to a Maximum Runout Flow of 102.5% of rated. Values apply to operation in all Application Conditions with or without Pressure Regulator in-service.

Page 9 of 14

Constellation Energy Generation - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 6 Core Operating Limits Report for Nine Mile Point 1 Cycle 26 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 as* directed 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 addition.al limits are required. These power dependent LHGR multipliers (LHGRFACp) are provided in Table 5-3 for Option B and Option A scram times (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 - UO2 Rods (Reference 4 and 7)

FuelT e LHGR GNF2 See Table 8-3 of Reference 4 Table 5-2 Linear Heat Generation Rate Limits - Gadolinia Rods (Reference 4 and 7)

FuelT e LHGR GNF2 See Table 8-4 of Reference 4 Table 5-3 Power Dependent LHGR Multiplier LHGRFACP for PROOS (Reference 2 - Appendix D)

Core Thermal Power (% of rated)

Scram Time Option 0 < 45 :2:45 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 Page 10 of 14

Constellation Energy Generation - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 6 Core Operating Limits Report for Nine Mile Point 1 Cycle 26 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 ......

"O Cl)

~

~

~

i:i:::

0 80

~

~

~

J...,

Cl) 0 60 i:l.. Power= 0.55* W+53

~

E J...,

Cl)

..c: 40 E-<

Cl)

J...,

0 u

20 0

0 20 40 60 80 100 120 Core Flow= W (% of Rated)

Page 11 of 14

Constellation Energy Generation - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 6 Core Operating Limits Report for Nine Mile Point 1 Cycle 26 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 licensed for this cycle (Reference 2). The minimum coastdown thermal power level is40% perT.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 7M1 Modes of Operation (Reference 2)

Allowed Operating Options Region

. Condition 1 Yes ondition 2 Yes Yes*

Yes Yes Yes Yes 7 Yes 7 Yes 7 Yes 7 PROOS, Three-I Yes 7 PROOS, Three-I Yes 7 7

Per Ref. I Appendix A TS 3.1.7.e, during three-loop operation power is restricted to 90% ofrated.

Page 12 of 14

Constellation Energy Generation - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 6 Core Operating Limits Report for Nine Mile Point 1 Cycle 26 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-31, November 2020 and U.S. Supplement NEDE-24011-P-A US, November 2020.

Page 13 of 14

Constellation Energy Generation - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 6 Core Operating Limits Report for Nine Mile Point 1 Cycle 26 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 247).
2. "Supplemental Reload Licensing Report for Nine Mile Point Unit 1 Reload 27 Cycle 28", Global Nuclear Fuel Document No. 006N9233, Rev. 0, January 2023.
3. "Engineering Report for Nine Mile Point Nuclear Station Unit 1 Reload 19", Global Nuclear Fuel Document No. 0000-0053-5247-ER, Rev. 1, March 2007. 8
4. "GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II)," Global Nuclear Fuel Document No. NEDC-33270P, Rev. 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 27 Cycle 28", Global Nuclear Fuel Document No. 006N9234, Rev. 0, January 2023.
8. "Nine Mile Point 1 Cycle 24 Limiting Load Line Analysis," Global Nuclear Fuel Lette~, Document No. 002N5662-R0, March 18, 2015.

8 The information referenced from this report (see COLR Section 4.2 footnote 4) is cycle independent.

Page 14 of 14

Retrieved from "https://kanterella.com/w/index.php?title=NMP1L3525,_Core_Operating_Limits_Report&oldid=3536735"