ML12156A367

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Submittal of Core Operating Limits Report
ML12156A367
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 06/01/2012
From: Swift P
Constellation Energy Nuclear Group, EDF Group, Nine Mile Point
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML12156A367 (23)
v • d • e


Text

P.O. Box 63 CENG .

a joint venture of Lycoming, NY 13093 Constellation "-*eDF Energy, p, D NINE MILE POINT NUCLEAR STATION June 1, 2012 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION: Document Control Desk

SUBJECT:

Nine Mile Point Nuclear Station Unit No. 2; Docket No. 50-410 Core Operating Limits Report Enclosed is a copy of the Core Operating Limits Report, COLR2-14, Revision 0 for Nine Mile Point Unit 2 (NMP2). This report is being submitted pursuant to NMP2 Technical Specification 5.6.5.d.

Should you have any questions regarding the information in this submittal, please contact John J. Dosa, Licensing Director, at (315) 349-5219.

Very truly yours, Paul M. Swift Manager, Engineering Services PMS/MHS

Enclosure:

Nine Mile Point Unit 2 Core Operating Limits Report cc: NRC Regional Administrator, Region I NRC Project Manager NRC Senior Resident Inspector AOOI

ENCLOSURE Nine Mile Point Unit 2 Core Operating Limits Report Nine Mile Point Nuclear Station, LLC June 1, 2012

t NINE MILE POINT UNIT 2 CORE OPERATING LIMITS REPORT COLR2-14 Revision 0, Cycle 14 Name Title Date Prepared by: Fuels Engineer

-,-ý'--a e W o ok Ah n Reviewed by: - Fuels Engineer Melisa Krick Approved by: Supervisor, Reactor Engineer John Darweesh 1/

Approved by: Supervisor, Fuels Robert Close Approved by: General Supervisor, Fuels ______U

/' Phil).engloski This controlled document provides cycle specific core operating limits for use in conjunction with the Nine Mile Point Unit 2 Technical Specifications. Document pages may only be changed through a reissue of (he entire document.

COLR2-14 NINE MILE POINT UNIT 2 Revision 0, Cycle 14 CORE OPERATING LIMITS REPORT TABLE OF CONTENTS 1.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) 1 1.1 Limits for Technical Specification 3.2.1 1 2.0 MINIMUM CRITICAL POWER RATIO (ODYN OPTION B) 3 2.1 Limits for Technical Specification 3.2.2 3 3.0 LINEAR HEAT GENERATION RATE (LHGR) 10 3.1 Limits for Technical Specifications 3.2.3 10 4.0 AVERAGE POWER RANGE MONITOR SETPOINTS 15 4.1 Limits for Technical Specification Table 3.3.1.1-1 (OPRM Upscale) 15 5.0 CONTROL ROD BLOCK INSTRUMENTATION 16 5.1 Allowable Value for Technical Specification Table 3.3.2.1-1 16

6.0 REFERENCES

FOR TECHNICAL SPECIFICATIONS 17

7.0 REFERENCES

FOR TECHNICAL SPECIFICATION BASES 18 8.0 SOURCE DOCUMENTS 19 Page i

NINE MILE POINT UNIT 2 Revision 0, Cycle 14

. COLR2-14 CORE OPERATING LIMITS REPORT 1.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) 1.1 Limits for Technical Specification 3.2.1 The APLHGR(s) for each fuel type as a function of Average Planar Exposure shall not exceed the limits shown in Table 1.

The limits of Table I shall be reduced to a value of 0.78 times the two recirculation loop operation limit when in single recirculation loop operation.

Page 1 of 19

C0LR2-14 NINE MILE POINT UNIT 2 Revision 0, Cycle 14 CORE OPERATING LIMITS REPORT Table 1 MAPLHGR versus Average Planar Average Planar Exposure MAPLHGR Limits (GWD/ST) (KW/ft) 0.00 12.82 14.51 12.82 19.13 12.82 57.61 8.00 63.50 5.00 NOTES: 1. APLHGR(s) are interpolated between exposure points for which explicit values are given Page 2 of 19

COLR2-14 NINE MILE POINT UNIT 2 Revision 0, Cycle 14 CORE OPERATING LIMITS REPORT 2.0 MINIMUM CRITICAL POWER RATIO (ODYN OPTION B) 2.1 Limits for Technical Specification 3.2.2 For 2-Pump Operation, the Minimum Critical Power Ratio (MCPR) shall be equal to or greater than the maximum of the appropriate MCPR(P) from Figures 2c, 2d and 2e or the MCPR(F) from Figure 2f.

For Single Loop Operation, the Minimum Critical Power Ratio (MCPR) shall be equal to or greater than the Minimum Critical Power Ratio for 2-Pump Operation plus 0.02.

NOTES: 1. For Figures 2a and 2b tau (T)defined as follows:

1-ýe - - B T

TA I TB where:

r,1 = 0.866 seconds, control rod average scram insertion time limit to notch 39 per Technical Specification 3.1.4.

  • 1 r>, =0.672+ 1.65 N

nN, X (0.016) n EATi r n = number of surveillance tests performed in cycle Nj = number of active control rods measured in the ih surveillance test r, = average scram time to notch 39 of all rods measured in the io'surveillance test N 1 = total number of active rods measured in Specification 3.1.4.1 T = 1.0 prior to performance of the initial scram time measurements for the cycle

2. ARTS provides for power- and flow-dependent thermal limit adjustments and multipliers, which allow for a more reliable administration of the MCPR thermal limit. The MCPR(P) curves are independent of EOC-RPT and scram time option, but are determined for other EOOS. The MCPR(P) limits for PROOS were converted to a K(P) consistent with the ARTS offrated limits. MCPR(F) is independent of Scram Time Option and all EOOS.
3. The Operating Limit MCPR values for Turbine Bypass Out of Service and EOC-RPT Out of Service are higher (more limiting) than for the standard normal operation case, and are therefore specifically identified where appropriate. The OLMCPR values for all other analyzed EOOS transient events are bounded by the Normal Operation limits.
4. EOR is the End of Rated exposure as defined in the Cycle Management Report.
5. The K(P) multiplier at P-bypass (26% power) for PROOS has been adjusted to match the EIS codition in order to add conservatism under the PROOS condition.

Page 3 of 19

B2-14 NINE MILE*T UNIT 2 REVISION 0, CYCLEO CORE OPERATING LIMITS REPORT Figure 2a MCPR Operating Limits (BOC to EOR-1611 MWdIST) 1.54 (1,1.53) 1.52 1.50 (1,1.50)

(L .,'

o 1.48

.,,

0 1.46 a.

.2

"*" 1.44 E

E

".E 1.42 (1,1.42) 1.40 1.38 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 Tau Page 4 of 19

S2-14 NINE MIL*T UNIT 2 REVISION 0, CYCLE CORE OPERATING LIMITS REPORT I

Figure 2b MCPR Operating Limits (EOR-1 611 MWd/ST to EOC) 1.66 (1,1.65) 1.64 1.62 1.60 1.58 0 1.56 (L 1.54 1.52 1.50 (1,1.50)

E

.G 1.48 M (1,1.47) 1.46 1.44 1.42 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 Tau Page 5 of 19

.1R2-14 NINE MIL a IT UNIT 2 REVISION 0, CYCL*

CORE OPERATING LIMITS REPORT I

Figure 2c MCPR(P) for <26%Power, <75%Flow K(P) for >26% Power for Equipment In Service and Recirculation Pump Trip Out of Service 3.500 3.250 3.000 2.750 2.500 2.250 0-2.000 1.750 1.500 1.250

~~. ......

...........

.......

looo.......

(100, 1.000) 1.000 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Power (% Rated)

Page 6 of 19

.1R2-14 NINE MIL4T UNIT 2 REVISION 0, CYCL*

CORE OPERATING LIMITS REPORT Figure 2d MCPR(P) for <26%Power, <75%Flow K(P) for >26% Power for Turbine Bvoass Out of Service 3.500 3.250 3.000 -

2.750 -

2.500

' 2.250 2.000 -

1.750 1.500 1.250 1.000 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Power (% Rated)

Page 7 of 19

S&2-14 NINE MILE'T UNIT 2 REVISION 0, CYCLO CORE OPERATING LIMITS REPORT Figure 2e MCPR(P) for <26%Power, <75%Flow K(P) for >26% Power for Operation without a Backup Pressure Regulator 3.500 3.250 3.000 2.750 2.500 2,250 (L

2.000 1.750 1.500 1.250

,(:90, 1.038) (100, 1.000) 1.000 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Power (% Rated)

Page 8 of 19

.1R2-14 NINE MIL NT UNIT 2 REVISION 0, CYCL*

CORE OPERATING LIMITS REPORT Figure 2f Flow-Dependent MCPR Limits MCPR(F) 1.80 1.70 1.60 1.50 0.,

1.40 1.30 1.20 1.10 20 30 40 50 60 70 80 90 100 110 120 Flow (% Rated)

Page 9 of 19

C0CLR2-14 NINE MILE POINT UNIT 2 Revision 0, Cycle 14 CORE OPERATING LIMITS REPORT 3.0 LINEAR HEAT GENERATION RATE (LHGR) 3.1 Limits for Technical Specification 3.2.3 During power operation, the Linear Heat Generation Rate (LHGR) of any rod in any fuel assembly at any axial location shall not exceed the minimum of: 1) the limiting values shown in FBIR2-14, Rev 00, "Nine Mile Point Unit 2 Fuel Bundle Information Report" times the LHGRFAC(F) from Figure 3d; and 2) the limiting values shown in FBIR2-14, Rev 00, "Nine Mile Point Unit.2 Fuel Bundle Information Report" times the appropriate LHGRFAC(P) from Figures 3a or 3b or 3c. FBIR2-14, Rev 00, "Nine Mile Point Unit 2 Fuel Bundle Information Report" contains the LHGR limits for both U02 rods (which contain no gadolinium) and the most limiting gadolinium-bearing rods. Other gadolinium-bearing rods have LHGR limits which lie between these two curves. Compliance with these limits will be monitored by the plant's process computer.

NOTES: ARTS provides for power- and flow-dependent thermal limit multipliers, which allow for a more reliable administration of the LHGR thermal limits. The LHGRFAC(P) curves are independent of recirculation pump trip operability, but are determined for other EOOS. The LHGRFAC (P) limits for PROOS are also presented in a manner more consistent with the ARTS offrated limits. LHGRFAC(F) is identical for all EOOS.

Page 10 of 19

.1R2-14 NINE MIL IT UNIT 2 REVISION 0, CYCL*

CORE OPERATING LIMITS REPORT Figure 3a LHGRFAC(P) for < 26% Power, < 75% Flow LHGRFAC(P) for 2 26% Power for Equipment In Service and Recirculation Pump Trip Out of Service 1.000 0.900 0.800 0.700 0.600 CL 0.500

-j 0.400 0.300 0.200 0.100 0.000 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Power (% Rated)

Page 11 of 19

Q*R2-14 NINE MIL& T UNIT 2 REVISION 0, CYCL@

CORE OPERATING LIMITS REPORT Figure 3b LHGRFAC(P) for < 26% Power, < 75% Flow LHGRFAC(P) for > 26% Power 1 .000 for Turbine Bypass Out of Service C1.900 C1.800 C1.700 C1.600 1.500 1.400 C,

1.300 C

1.200 C

).100 C).000 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Power (% Rated)

Page 12 of 19

B2-14 NINE MILEJT UNIT 2 REVISION 0, CYCL*

CORE OPERATING LIMITS REPORT Figure 3c LHGRFAC(P) for < 26% Power, < 75% Flow LHGRFAC(P) for e 26% Power for Operation without a Backup Pressure Regulator (100,1.000)

1. 000 0.900 0.800 0.700 0.600 ILL 0.500

-j 0.400 0.300 0U200 0.100 0,000 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Power (% Rated)

Page 13 of 19

.1R2-14 NINE MILlT UNIT 2 REVISION 0, CYCLO CORE OPERATING LIMITS REPORT Figure 3d Flow-Dependent LGHR Multiplier LHGRFAC(F) 1.100 1 (112,1.000) 1.000 0.900 0.800 0.700 LL 0.600

_j.

0.500 0.400 0.300 0.200 11F<85.09 1 0.100 0.000 20 30 40 50 60 70 80 90 100 110 120 Flow (% Rated)

Page 14 of 19

4 COLR2-14 NINE MILE POINT UNIT 2 Revision 0, Cycle 14 CORE OPERATING LIMITS REPORT 4.0 AVERAGE POWER RANGE MONITOR SETPOINTS 4.1 Limits for Technical Specification Table 3.3.1.1-1 (OPRM Upscale)

Allowable value < 1.13 Page 15 of 19

-

COLR2-14 NINE MILE POINT UNIT 2 Revision 0, Cycle 14 CORE OPERATING LIMITS REPORT 5.0 CONTROL ROD BLOCK INSTRUMENTATION 5.1 Footnote Values for Technical Specification Table 3.3.2.1-1 (a) MCPR < 1.70 (b) MCPR < 1.70 (c) MCPR < 1.70 (d) MCPR < 1.40 (e) MCPR < 1.70 (h) Allowable Value:

Low Power Range - Upscale 124.6 Intermediate Power Range - Upscale 119.6 High Power Range - Upscale 114.6 (i) NTSP:

Low Power Range - Upscale 124.2 Intermediate Power Range - Upscale 119.2 High Power Range - Upscale 114.2 Page 16 of 19

, . . .4 COLR2-14 NINE MILE POINT UNIT 2 Revision 0, Cycle 14 CORE OPERATING LIMITS REPORT

6.0 REFERENCES

FOR TECHNICAL SPECIFICATION 6.1 Technical Specification 5.6.5.b.1:

General Electric Standard Application for Reactor Fuel, NEDE 204011 -P-A-I18 and NEDE 204011-P-A-1 8-US, April 201 1.

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.a* t' COLR2-14 NINE MILE POINT UNIT 2. Revision 0, Cycle 14 WCORE OPERATING LIMITS REPORT

7.0 REFERENCES

FOR TECHNICAL SPECIFICATION BASES 2J1.1 Bases Reference 3:

General Electric Standard Application for Reactor Fuel, NEDE 24011 -P-A-18 and NEDE 2401 l-P-A-18-US, April 2011.

2.1.1 Bases Reference 4:

Supplemental Reload Licensing Report for Nine Mile Point 2 Cycle 14, 0000-0129-4873-SRLR, Rev. 1, April 2012.

3.1.1 Bases Reference 7:

General Electric Standard Application for Reactor Fuel, NEDE 24011-P-A-1 8 and NEDE 24011 -P-A- 18-US, April 2011.

3.1.6 Bases Reference 1:

Supplemental Reload Licensing Report for Nine Mile Point 2 Cycle 14, 0000-0129-4873-SRLR, Rev. 1, April 2012.

3.2.1 Bases Reference 1:

General Electric Standard Application for Reactor Fuel, NEDE 24011-P-A-I18 and NEDE 2401 l-P-A-18-US, April 2011.

3.2.2 Bases Reference 2:

General Electric Standard Application for Reactor Fuel, NEDE 24011-P-A-1 8 and NEDE 2401 I-P-A-18-US, April 2011.

3.2.2 Bases Reference 3:

Supplemental Reload Licensing Report for Nine Mile Point 2 Cycle 14, 0000-0129-4873-SRLR, Rev. 1, April 2012.

3.2.3 Bases Reference 1:

General Electric Standard Application for Reactor Fuel, NEDE 2401 I-P-A-18 and NEDE 2401 l-P-A-18-US, April 2011.

3.2.3 Bases Reference 2:

Supplemental Reload Licensing Report for Nine Mile Point 2 Cycle 14, 0000-0129-4873-SRLR, Rev. 1, April 2012.

Page 18 of 19

4 .~ I*

COLR2-14 NINE MILE POINT UNIT 2 Revision 0, Cycle 14 WCORE OPERATING LIMITS REPORT 8.0 SOURCE DOCUMENTS The Core Operating Limits contained in this report were obtained from the following documents:

Section 1.0 - APLHGR Limits Supplemental Reload Licensing Report for Nine Mile Point 2 Cycle 14, 0000-0129-4873-SRLR, Rev.

1, April 2012.

Section 2.0 - MCPR Limits Supplemental Reload Licensing Report for Nine Mile Point 2 Cycle 14, 0000-0129-4873-SRLR, Rev.

1, April 2012.

Nine Mile Point Station Unit 2 - APRM/RBM/Technical Specifications/Maximum Extended Load Line Limit Analysis (ARTSIMELLLA), NEDC-33286P, Rev. 0, March 2007 (NER-2E-037)

Nine Mile Point Nuclear Station Unit 2 ARTS/MELLLA, Task T0900, GE-NE-0000-0055-2373-RO, Rev. 0, February 2007 (NER-2E-037).

Engineering Report for Nine Mile Point Nuclear Station Unit 2, Reload 11, Cycle 12, 0000-0067-1271 -

ER, Rev 0, March 2008.

Section 3.0 - LHGR Limits Supplemental Reload Licensing Report for Nine Mile Point 2 Cycle 14, 0000-0129-4873-SRLR, Rev.

1, April 2012.

Nine Mile Point Station Unit 2 - APRM/RBM/Technical Specifications/Maximum Extended Load Line Limit Analysis (ARTS/MELLLA), NEDC-33286P, Rev. 0, March 2007 (NER-2E-037).

Nine Mile Point Nuclear Station Unit 2 ARTS/MELLLA, Task T0900, GE-NE-0000-0055-2373-RO, Rev. 0, February 2007 (NER-2E-037).

Section 4.0 - APRM Setpoints Supplemental Reload Licensing Report for Nine Mile Point 2 Cycle 14, 0000-0129-4873-SRLR, Rev.

1, April 2012.

Design Specification Data Sheet 22A2843AM (NMPCNO NSSSI61405000), Neutron Monitoring System.

Section 5.0 - Control Rod Block Instrumentation Supplemental Reload Licensing Report for Nine Mile Point 2 Cycle 14, 0000-0129-4873-SRLR, Rev.

1, April 2012.

Nine Mile Point Station Unit 2 - APRM/RBM/Technical Specifications/Maximum Extended Load Line Limit Analysis (ARTS/MELLLA), NEDC-33286P. Rev. 0, March 2007.

Instrument Limits Calculation Constellation Generation Group Nine Mile Point Nuclear Station Unit 2 Rod Block Monitor (NUMAC ARTS-MELLA), 0000-0053-1006 NMP2 A-M-T506-RBM-Calc-2006, Rev. 1, March 2008 (Found within NMP document NSSS168805002).

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