ML061300524

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Nine Mile Point Cycle 11 Core Operating Limits Report, Revision 0
ML061300524
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 05/01/2006
From: Schimmel M A
Constellation Energy Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML061300524 (24)
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Constellation Energy,* Nine Mile Point Nuclear Station P.O. Box 63 Lycoming, NY 13093 May 1, 2006 U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION:

SUBJECT:

Document Control Desk Nine Mile Point Nuclear Station Unit No. 2; Docket No. 50-4 10 Cycle 11 Core Operating Limits Report. Revision 0 Attached is a copy of the Cycle 11 Core Operating Limits Report (COLR), 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 questions regarding the information in this submittal, please contact M. H. Miller, Licensing Director, at (315) 349-1510.Very truly yours, Mark A. Schimmel Manager Engineering Services MAS/RF/sac

Attachment:

(1) Nine Mile Point Unit 2 Core Operating Limits Report cc: S. J. Collins, NRC T. G. Colburn, NRC Resident Inspector, NRC j4ocL4 Document Control Desk May 1, 2006 Page 2 bcc: L. S. Larragoite C. W. Fleming, Esquire T. J. O'Connor J. A. Hutton M. H. Miller/T.

F. Syrell J. L. Lyon M. Armenta NMP2L 2130 COMMITMENTS IDENTIFIED IN THIS CORRESPONDENCE:

  • NONE Responsible Person/Organization:

Due Date: SAR1TSB Revision Required?

If yes, Type: Initiation Date: NCTS No.: Posting Requirements for Responses

-- NOV/Order No ATTACHMENT (1)Nine Mile Point Unit 2 Core Operating Limits Report Nine Mile Point Nuclear Station, LLC May 1, 2006 NINE MILE POINT UNIT 2 CORE OPERA TING LIMITS REPORT Document No.: COLR2-11 Revision 0, Cycle 11 Name Title Date Prepared by:.I/C. W.~ Lepine 3,A2j3 Fuel Engineer Reviewed by: Independently Reviewed by: Approved by: Approved by:.L. Winklebleck

..tA In R. C M. A. Armenta 3 /a S Ad;Fuel Engineer 3 /-1 f /Z Fuel Engineer Principal Engineer, Nuclear Fuels Services J. N. Darweesh P. I. Wengloski Supervisor, Reactor Engineering Approved by:/7o6 Director, Nuclear Fuels Services 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 the entire document.

Revision 0 Cycle II NINE MILE POINT UNIT 2 CORE OPERA TING LIMITSREPORT Table of Contents Page 1.0 AVERAGE PLANAR LINEAR. HEAT GENERATION RATE E(APLHGR ... 1 1.1 Limits for Technical Specification 3.2.1 2.0 MINIMUM CRITICAL POWER RATIO (ODYN OPTION , 2.1 Limits for Technical Specification 3.2.2...................

3.0 LINEAR

HEAT GENERATION RATE (LHGR) .............

..........

11 3.1 Limits for Technical Specifications 3.2.3 _4.0 AVERAGE POWER RANGE MONITOR SETPOINTS...

14 4.1 Limits for Technical Speciication Table 3.3.1.1-1 (OPRM Upscale)-.....

14 5.0 ROD BLOCK MONITOR _5.1 Allowable Value for Technical Specification Table 3.3.2.1-1

.-.. 15

6.0 REFERENCES

FOR TECHNICAL SPECIFICATIONS

....................................

7.0 REFERENCES

FOR TECHNICAL SPECIFICATION BASES.......

..._7 8.0 SOURCEDOCU S ....................

18 Page i Revision 0 Cycle 11 NINE MILE POINT UNIT 2 CORE OPERA TING LIMITS REPORT 1.0 AVERAGEPLANAR LINEAR HEAT GENERATION RATE (APLHGRJ 1.1 Limits for Technical Specification 3.2.1 The APLHGR(s) for each type of fuel as a fimction 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 .78 times the two recirculation loop operntion limit when in single recirculation loop operation.

Page I O 19 NINE MILE POINT UNIT 2 COLR2-11, Revision 0 Cycle 11 Table 1 MAPLHGR VERSUS AVERAGE PLANAR EXPOSURE Average -MAPLHGR Limlts (kwlft)Planar Bundle Bundle Bundle Bundle Bundle Bundle Bundle Bundle Bundle Bundle Exposuret GEllt.6 GEII9A GEI -13. G.EtllC9C tF14-CIOA 0F14CIOB GF14-CIOC GE14-ClIA GE14-CIB GE14421IG GWd/ST _ I_ _0.00 13.42 13.42 13.42 13.42 12,82 12.82 12.82 12.82 12.82 12.82 14.51 ----12.82 12.82 1282 12.82 12.82 12.82 19.13 -- -- --12.82 12.82 12.82 12.82 12.82 12.82 19.72 13.42 13.42 13.42 13.42 ------ -_27.22 12.29 12.29 12.29 12.29 _ ---- ---57.61 -- -- -8.00 8.00 8.00 8.00 8.00 8.00 63.50 8.90 8.90 8.90 S.90 5.00 5.00 5.00 5.00 5.00 5.00 Fuel Tvpe GE I I-P9CUl375-l2GZ-l20T-146-T6 GEII-P9CUB04 12GZ-120T-146-T6-2504 GE1I -P9CUB407-14GZ-120T-146-T6-2505 GE1I I-P9CUB407-14GZ-120T-146-T6-2506 GEI4-PI OCNAB406-15GZ-1 20T-I50-T6-2687 GE14-PI OCNAB404-15GZ-120T-1 50-T6-2688 GEI4-PICNA13403-17Z-120T-150-T6-2689 GE14-PIOCNAB415^1 7GZ-120T-15Q-T6-2874 GE14-PI OCNAB4l4-I6GZ-12OT-I50-T6-2873 GE14-PINA 417-1 SGZ-12OT-150-T6-2872 ID GEt I-C6 GEl 1-C9A GEi 1C913 GEI IC9C GE14-CIOA GE14-CIOB 0}E147CIOC GEI4-CIIA GE14-C1B GEI4-CIIC NOTE: (1) A M-' indicates that there is no entry for this box and the limit tan be determined by linearly interpolating between the previous and next point in each column. MAPLHGRs are interpolated between exposure points for which explicit values are given.Page 2 of 19 Revision 0 cycle 11 NINE MILE POINT UNIT 2 CORE OPERATING LIMITS REPORT 2.0 MINIMUM CRITICAL POWER RATIO (ODYN OPTION B)2.1 Limits for Technical Specification 3.2.2 The Minimum Critical Power Ratio (MCPR) shall be equal to or greater than the appropriate MCPR limit from Figures 2a-14 and 2b-14 fbr GE14 and Figures 2a-11 and 2b- I1I for GEI I times the K(f) shown in Figure 2c with tau (or "'t')defined as follows: T = (T. -T,) / (tA -where: T^, = 0.866 seconds, control rod average scram insertion time limit to notch 39 per Specification 3.1.4.,=672 + 1.65 * £ N, I Nj * .016 2 n i.1 i-i n = number of surveillance tests performed in cycle Ni= number of active control rods measured in the iP surveillance test r, =:average scram time to notch 39 of all rods measured in the i? surveillance test N, = total number of active rods measured in Specification 3.1.4.1.NOTES: i. The MCPR Operating Limits in Figures 2a-t 1, 2a-14, 2b-11 and 2b-14:are based on a 1.07 Safety Limit MCPR (SLMCPR) for two recirculation loop operation and a 1.09 Safety Limit MCPR for single loop operation.

2. r = 1.0 prior to performance of the initial scram time measurements for the cycle.3. The Operating Limit MCR 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 in Figures 2a-14, 21,4, 2a-1 1J and 2b-1 I.The OLMCPR values for all other analyzed EOOS transient events are bounded by the Normal Operation limits.4. For operation between 30% and 90% RTP with a backup pressure regulator out of service, additional MCPR limit requirements have been established in Figures 2d and 2e.5. EOR on Figures 2a-14, 2b-14, 2a-11, and 2b-ll is the End of Rated exposure as defined in the Cycle Management Report Page 3 of 19 Figure 2a-14 Nine Mile Point 2 Cycle 11 GE14 MCPR Operating Limits (Beginning Of Cycle to EOR-1140 MWdIST)1.54 1.52 Turbine B-ypass Inoper able __1.5 a-0: 1.481 o (0,1.48)/EOC-RPT Inoperable a 1.46-0 ,4 0 0.2 0.4 0.6 0.8 1 Tau Page 4 of 19 Figure 2b-14 Nine Mile Point 2 Cycle 11 GE14 MCPR Operating Limits (EOR-1140 MWdJST to End Of Cycle)r 0-0 0:E a.E 0 0.2 0.4 0.6 0.8 1 Tau Page 5 of 19 Figure 2a-1 I Nine Mile Point 2 Cycle II GEII MCPR Operating Limits (Beginning Of Cycle to EOR.1140 MWd/ST)1.46 1.44 -1.42 1.4 (1, 1.40)-Turbine Bypass Inoperable C 1.38 1 U G 0,1.38)EOC-RPT Inoperable 1.36-1.34 -- (1, 1.34)1.32 -1 0.3 .31)1.3 2 0.4 .0 0 0.2 0.4 0.6 0.81 Tau Page 6 of 19 Figure 2b-11 Nine Mile Point 2 Cycle 11 GE 1I MCPR Operating Limits (EOR-1 140 M`WdcST to End Of Cycle)1.48 / I(I, 1A49)1.48 1.46 -Le EOCRPT Inoperable E 1.44 2 a! 42 -14 (1 1.41)E W I 18 Turbine Bypss Inoperable 1.38 (1 4Et,_ 1.38 0 0.2 0.4 0.6 0.8 I Tau Page 7 of 19 NINE MILE POINT UNIT 2 Figure 2te C01R1-I 1, Revision 0 Cycle lI.Kf vs Core Flow 1.4 1.3 1.2 66. 1.1 0 0.9 20 30 40 50 60 70 80 90 100 110 Core Flow, % of rated Page 8 of 19 NINE MILE POINT UNIT 2 COLR2-11, Revision 0 Cycle 11 Figure 2d GE11 MCPR Limits for Operation Without a Backup Pressure Regulator 2.2 21 2 For operation

>70% but c90% RTP maintain MCPR > normal operation MCPR limit from Figures 2a-1 1 or 2b-11 divided by the fraction of rated thermal power.For operation

>30% and c70% RTP the additional requirements are as shown in this Figure Operating Limi MCPR (P) = OLMCPR(P)

= f1.58+00080(70%-P}l There are no additional MCPRlimirs required for operation

<30% and >90% RTP with a backup pressure regulator out of service.1.9 0.1.7 1.6 1.5 ACCEPTABLE

EGI N Operating MCPR shall be > MCPR limit ime RESTR CTED REGION Enter T ch. opec. 3 ____.........~~~~~~~~~

I _..... ....._... ...1.4 30 35 40 45 50 55 60 Core Thermal Power (P) in units of % Rated Thermal Power (%:RTP)65 70 Page 9 of 19 NINE MILE POINT UNIT 2 COLR2-l, Revision 0 Cycle 11 Figure 2e GE14C MCPR Limits for Operation Without a Backup Pressure Regulator a: C.2.3 For operation

>70% but <90% RTP maintain MCPR > normal operation MCPR limit from Figures 2a-14 or 2b114 divided by the fraction of rated thermal power.2i2 For operation

>300% and c70% RTP the additional requirements are as shown in this figure: 2.2 Operating Limit MCPR (P) = OLMCPR(P)

= lt.72+0.00825(70%.-P)l There are no additional MCPR limits required for operation

<30% and >90% RTP with a backup pressure regulator out of service.2.1 2 ACCEPTABLE REGION Operating MCPR shall be > MCPR limit line 1.7 RESTRICTED REGION En'ter Tech. Spec.s .2.2 1.6 l -_ l_ __ -t 1.5 -- --l It Uilll 30 3S5 40 45 50 55 60 Core Thermal Power (P) In units of % Rated Thermal Power (%YRTP)65 70 Page 10 Of 19 Revision 0 Cycle 11 NINE MILE POINT UNIT 2 CORE OPERATING LIMITS REPORT 3.0 LINEAR HEAT GENERATION RATE (LHGR)3.1 Limits forTechnical 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 limiting values shown in RSLD-10, Revision 0, "Nine Mile Point Unit 2 Reload 10, Reload Specific Lattice Data". This document 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.NOTE: For operation

>30% and <90% RTP with a backup pressure regulator out of service, additional LHGR limit requirements have been established as shown in Figure 3-1 1 and 3-14. There are no additional LHGR limits required for operation<30% and >90% RTP for operation with a backup pressure regulator out of service.Page II of 19 Figure 3-11 LHGR Limit for Operation Between 30% and 90% RTP Without a Backup Pressure Regulator for GE11 U.9 , V -F'ES7 I 4i rRICTEI_.. U. I) REGION A A 0-J U.0.UY 1-t nte r 1-ech M.",:;v0-0.8 _ _ _ _ _ _ _ _ _75 __ _ 1 t _ 1_ j _ _ _ _ / i I _I -- I .____'.7 _ _ACCEPT1BIE R EG1bN Opeatng MFLPD shall be

  • mit MFLPD Umit For 300 A P< 70%65 I MFLPD -[0.8-M0.O02Z5W70%-P)J For 70% S P < 90%: MFLPD =FRTP 5 _ _ _ _C 0.I 30 35 40 45 SO 55 60 65 :70 75 80 85 90 Core Thermal Power (P) In units of % Rated Thermal Power (%RTP)Page 12 of 19 Figure 3-14 LHGR Limit for Operation Between 30% and 90% RTP Without a Backup Pressure Regulator for GE14C RES RICTED :REGI N 0T _Tech. e. 3,231..85 -_0 .8_ _ _ _ _ _ _ _ I _ _IA_ _ _ _ _ _7 a a.7 n A_r 4 5 -7 U.:^ t CCEPTB E :REGION[Operating MFLPD shall be MFLPD limit MrLPD Limit For 30%A s P < 700%,5__ -___ MFLPD = 0.85-0.0035(70°-P)]

For 70% P< 90%: MFLPD FRTP-.0.t 30 35 40 45 50 55 60 65 70 75 Core Thermal Power (P) In units of % Rated Thermal Power (%RTP)80 85 90 Page 13 of 19 Revision 0 Cycle 11 NINE MILE POINT UNIT 2 CORE OPERATING LIMITS REPORT 4.0 AVERAGE POWER RANGE MONITOR SETFOINTS 4.1 Limits for Technical Specification Table 3.3 1.1-1 (OPRM Upscale)ALLOWABLE VALUE< 1.13 Page 14 of 19 Revision 0 Cycle I1 NINE MILE POINT UNIT 2 CORE OPERATING LIMITS REPORT 5.0 ROD BLOCK MONITOR LRBM)5.} Allowable Value for Technical Specification Table 3.3.2.1-1 Function Allowable Value RBM Upscale NOTE::50.66 (NV -AW) + 47%with a maximum of 113%W = Loop Recirculation Flow as a percentage of the loop recirculation flow which produces a rated core Slow of 108.5 MLB/HR. AW is defined as the difference in indicated drive flow (in percent of drive flow which produces rated core flow) between two loop and single loop operation at the same core flow. AW -0 for two loop operation.

AW = 5% for single loop operation.

Page 15 of 19 Revision 0 Cycle 11 NINE MILE POINT UNIT 2 CORE OPERATING LIMITS REPORT

6.0 REFERENCES

FOR TECHNICAL SPECIFICATION Technical Specification 5.6.5.b. 1: General Electric Standard Application for Reactor Fuel, NEDE 24011 -P-A-15 and NEDE 2401 1-P-A-15-US (September 2005).Page 16 of 19 Revision 0 Cycle 11 NINE MILE POINT UNIT 2 CORE OPERA TING LIMITS REPORT

7.0 REFERENCES

FOR TECHNICAL SPECIFICATION BASES 2.1.1 BASES REFERENCE 3: General Electric Standard Application for Reactor Fuel, NEDE 2401 1-P-A-15 and NEDE 2401 1-P-A-lS-US (September 2005).2.1.1 BASES REFERENCE 4: Supplemental Reload Licensing Report for Nine Mile Point Nuclear Station Unit 2, Reload 10, Cycle 1 1, 0000-0023-4708-SRLR, Rev. 0, February 2006.3.1.1 BASES REFERENCE 7: General Electric Standard Application for Reactor Fuel, NEDE 24011 -P-A-15 and NEDE 2401 I-P-A-15-US (September 2005).3.1.6 BASES REFERENCE 1: Supplemental Reload Licensing Report for Nine Mile Point Nuclear Station Unit 2, Reload 10, Cycle 11, 0000-0023-4708-SRLR, Rev. 0, February 2006.03.2.1 BASES REFERENCE 1: General Electric Standard Application for Reactor Fuel, NEDE 24011 -P-A-15 and NEDE 2401 1-P-A-I5-US (September 2005).3.2.2 BASES REFERENCE 2: General Electric Standard Application for Reactor Fuel, NEDE 2401 1-P-A-15 and NEDE 2401 I-P-A-IS-US (September 2005).3.2.2 BASES REFERENCE 3: Supplemental Reload Licensing Report for Nine Mile Point Nuclear Station Unit 2, Reload 10, Cycle 11, 0000-0023-4708-SRLR, Rev. 0, February 2006.3.2.3 BASES REFERENCE 1: General Electric Standard Application for Reactor Fuel, NEDE 2401 1-P-A-15 and NEDE 2401 1-P-A-15-US (September 2005).3.2.3 BASES REFERENCE 2: Supplemental Reload Licensing Report for Nine Mile Point Nuclear Station Unit 2, Reload 10, Cycle 11, 0000-00234708SRLR, Rev. 0, February 2006.3.2.4 BASES REFERENCE 3: General Electric Standard Application for ReactorFuel, NEDE 2401 I-P-A-15 and NEDE 24011 -P-A-I5-US (September 2005).Page 17 of 19 Revision 0 Cycle II NINE MILE POINT UNIT 2 CORE OPERTINGLIMITSREPORT

8.0 SOURCE

DOCUMENTS The Core Operating Limits contained in this report were obtained from the following documents:

CORE OPERATING LIMIT REFERENCE Section 1.0 -APLHGR LIMITS Section 2.0 -MCPR LIMITS Section 3.0 -LHGR LIMITS"Engineering Report for Nine Mile Point Nuclear Station Unit 2, Reload 10, Cycle 11", 0000-0050-1550-ER, Rev 0, March 2006'Engineering Report for Nine Mile Point Nuclear Station Unit 2, Reload 10, Cycle 11" 0000-0050-1550-ER, Rev 0, March 2006"'Engineering Report for Nine Mile Point Nuclear Station Unit 2, Reload 10, Cycle I I", 00000050-1550-ER, Rev 0, March 2006 Page 18 of l9 Revision 0 Cycle I1I NINE MILE POINT UNIT 2 CORE OPERATING LIMITS REPORT 8.0 SOURCE DOCUIMENTS (Cont)CORE OPERATING LIMIT REFERENCE Section 4.0 -APRM SETPOINTS Limits for Technical Specification Table 3.3. 1.1-1 (OPRM Upscale3 Section 5.0 -RBM SETPOINTS"Engineering Report for Nine Mile Point Nuclear Station Unit 2, Reload 10, Cycle 11"' 0000-0050-1550-ER, Rev 0, March 2006 GE Engineering Report for Nine Mile Point Nuclear Station Unit 2 Reload 2 Cycle 3, NFD92-016 January 1992 Page 19 of 19

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