nine mile point cycle 11 core operating limits report ... · core opera ting limits report document...

Constellation Energy,* Nine Mile Point Nuclear Station

P.O. Box 63Lycoming, NY 13093

May 1, 2006

U. S. Nuclear Regulatory CommissionWashington, DC 20555-0001

ATTENTION:

SUBJECT:

Document Control Desk

Nine Mile Point Nuclear StationUnit 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 MilePoint 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. SchimmelManager Engineering Services

MAS/RF/sac

Attachment: (1) Nine Mile Point Unit 2 Core Operating Limits Report

cc: S. J. Collins, NRCT. G. Colburn, NRCResident Inspector, NRC

j4ocL4

Document Control DeskMay 1, 2006

bcc: L. S. LarragoiteC. W. Fleming, EsquireT. J. O'ConnorJ. A. HuttonM. H. Miller/T. F. SyrellJ. L. LyonM. 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 2Core Operating Limits Report

Nine Mile Point Nuclear Station, LLCMay 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:

IndependentlyReviewed by:

Approved by:

Approved by:

. L. Winklebleck

.. tA InR. C

M. A. Armenta

3 /a S Ad;

Fuel Engineer

3 /-1 f /ZFuel Engineer

Principal Engineer, Nuclear FuelsServices

J. N. Darweesh

P. I. Wengloski

Supervisor, Reactor Engineering

Approved by: /7o6Director, Nuclear Fuels Services

This Controlled Document provides cycle specific core operating limits for use in conjunction with the Nine Mile PointUnit 2 Technical Specifications. Document pages may only be changed through a reissue of the entire document.

Revision 0Cycle 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) ............. .......... 113.1 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 0Cycle 11

NINE MILE POINT UNIT 2CORE OPERA TING LIMITS REPORT

1.0 AVERAGEPLANAR LINEAR HEAT GENERATION RATE (APLHGRJ


The APLHGR(s) for each type of fuel as a fimction of AVERAGE PLANAREXPOSURE 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 recirculationloop operntion limit when in single recirculation loop operation.

Page I O 19

NINE MILE POINT UNIT 2 COLR2-11, Revision 0Cycle 11Table 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 bedetermined by linearly interpolating between the previous and next point in eachcolumn. MAPLHGRs are interpolated between exposure points for which explicitvalues are given.

Page 2 of 19

Revision 0cycle 11

NINE MILE POINT UNIT 2CORE OPERATING LIMITS REPORT

2.0 MINIMUM CRITICAL POWER RATIO (ODYN OPTION B)


The Minimum Critical Power Ratio (MCPR) shall be equal to or greater than theappropriate 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 perSpecification 3.1.4.

,=672 + 1.65 * £ N, I Nj * .016

2 n

i.1 i-i

n = number of surveillance tests performed in cycleNi= number of active control rods measured in the iP surveillance testr, =:average scram time to notch 39 of all rods measured in the i? surveillance testN, = 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 a1.07 Safety Limit MCPR (SLMCPR) for two recirculation loop operation and a 1.09 SafetyLimit 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-RPTOut 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.TheOLMCPR values for all other analyzed EOOS transient events are bounded by theNormal Operation limits.4. For operation between 30% and 90% RTP with a backup pressure regulator out ofservice, 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 asdefined in the Cycle Management Report

Page 3 of 19

Figure 2a-14Nine 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-14Nine 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 INine 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 1U 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 . 00 0.2 0.4 0.6 0.81

Tau

Page 6 of 19

Figure 2b-11Nine 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 I18 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 0Cycle lI.

Kf vs Core Flow

1.4

1.3

1.2

66.�e

1.1

0

0.920 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 0Cycle 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 fromFigures 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 thisFigureOperating Limi MCPR (P) = OLMCPR(P) = f1.58+00080(70%-P}l

There are no additional MCPRlimirs required for operation <30% and >90% RTP with abackup 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 REGIONEnter 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 0Cycle 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 fromFigures 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 abackup pressure regulator out of service.

2.1

2

ACCEPTABLE REGIONOperating MCPR shall be > MCPR limit line

1.7

RESTRICTED REGIONEn'ter Tech. Spec.s .2.2

1.6 | - _ |_ __ - 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 0Cycle 11


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 inany fuel assembly at any axial location shall not exceed the limiting values shownin RSLD-10, Revision 0, "Nine Mile Point Unit 2 Reload 10, Reload SpecificLattice 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 twocurves. Compliance with these limits will be monitored by the plant's processcomputer.

NOTE: For operation >30% and <90% RTP with a backup pressure regulator out ofservice, additional LHGR limit requirements have been established as shown inFigure 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 ofservice.

Page II of 19

Figure 3-11

LHGR Limit for Operation Between 30% and 90% RTPWithout a Backup Pressure Regulator

for GE11

U.9 , V -

F'ES7I 4i rRICTEI_.. U. I

) REGIONA A

0

-JU.

0.

UY 1-t nte r 1-ech M.",:;v0-

0.8 _ _ _ _ _ _ _ _ _

75 __ _ 1 t _ 1_ j _ _ _ _ / i I _

I -- I .____'.7 _ _

ACCEPT1BIE R EG1bNOpeatng MFLPD shall be * MFLPD * 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% RTPWithout a Backup Pressure Regulator

for GE14C

RES RICTED :REGI N0T _Tech. e. 3,231

..85 - _

0 .8_ _ _ _ _ _ _ _ I _ _IA_ _ _ _ _ _

7aa. 7

n A_r 4 5 -

7U.

:^ 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 0Cycle 11


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 0Cycle I1


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 looprecirculation flow which produces a rated core Slow of 108.5MLB/HR. AW is defined as the difference in indicated drive flow(in percent of drive flow which produces rated core flow) betweentwo loop and single loop operation at the same core flow. AW - 0for two loop operation. AW = 5% for single loop operation.

Page 15 of 19

Revision 0Cycle 11


6.0 REFERENCES FOR TECHNICAL SPECIFICATION

Technical Specification 5.6.5.b. 1:General Electric Standard Application for Reactor Fuel, NEDE 24011 -P-A-15and NEDE 2401 1-P-A-15-US (September 2005).

Page 16 of 19

Revision 0Cycle 11

NINE MILE POINT UNIT 2CORE 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 andNEDE 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 andNEDE 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 andNEDE 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 andNEDE 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 andNEDE 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 andNEDE 24011 -P-A-I5-US (September 2005).

Page 17 of 19

Revision 0Cycle II

NINE MILE POINT UNIT 2CORE OPERTINGLIMITSREPORT

8.0 SOURCE DOCUMENTS

The Core Operating Limits contained in this report were obtained from the followingdocuments:

CORE OPERATING LIMIT REFERENCE

Section 1.0 - APLHGR LIMITS

Section 2.0 - MCPR LIMITS

Section 3.0 - LHGR LIMITS

"Engineering Report for Nine Mile PointNuclear Station Unit 2, Reload 10, Cycle11", 0000-0050-1550-ER, Rev 0, March2006

'Engineering Report for Nine Mile PointNuclear Station Unit 2, Reload 10, Cycle11" 0000-0050-1550-ER, Rev 0, March2006

"'Engineering Report for Nine Mile PointNuclear Station Unit 2, Reload 10, CycleI I", 00000050-1550-ER, Rev 0, March2006

Page 18 of l9

Revision 0Cycle I1I


8.0 SOURCE DOCUIMENTS (Cont)

CORE OPERATING LIMIT REFERENCE

Section 4.0 - APRM SETPOINTS

Limits for Technical SpecificationTable 3.3. 1.1-1 (OPRM Upscale3

Section 5.0 - RBM SETPOINTS

"Engineering Report for Nine Mile PointNuclear Station Unit 2, Reload 10, Cycle11"' 0000-0050-1550-ER, Rev 0, March2006

GE Engineering Report for Nine Mile PointNuclear Station Unit 2 Reload 2 Cycle 3,NFD92-016 January 1992

Page 19 of 19

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