NL-09-047, Revised Core Operating Limits Report, Cycle 16

Revised Core Operating Limits Report, Cycle 16

ML091410286
Person / Time
Site:	Indian Point
Issue date:	05/14/2009
From:	Robert Walpole Entergy Nuclear Northeast
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-09-047
Download: ML091410286 (15)

Text

Entergy Nuclear Northeast Indian Point Energy Center

%g%0-wEnbeW 0 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Tel 9147346710 Robert Walpole Manager, Licensing NL-09-047 May 14, 2009 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

SUBJECT:

Revised Core Operating Limits Report for Indian Point Unit 3 Indian Point Nuclear Generating Unit 3 Docket No. 50-286 License No. DPR-64

Dear Sir or Madam:

to this letter provides Entergy Nuclear Operations, Inc.'s (ENO's) Core Operating Report (COLR) for Indian Point 3 Cycle 16. This report is submitted in accordance with Technical Specification 5.6.5.d.

There are no new commitments identified in this submittal. If you have any questions or require additional information, please contact Mr. Robert Walpole, Manager, Licensing at (914) 734-6710.

Sincerely, RW/dmt

Enclosure:

1. Indian Point 3 Core Operating Limits Report - Cycle 16 cc: next page

~J(42~

NL-09-047 Page 2 of 2 cc: Mr. John P. Boska, NRC NRR Senior Project Manager Mr. Samuel J. Collins, Regional Administrator, NRC Region I IPEC NRC Senior Resident Inspectors Office Mr. Francis J. Murray, President and CEO, NYSERDA Mr. Paul Eddy, New York State Dept. of Public Service

ENCLOSURE 1 TO NL-09-047 Indian Point 3 Core Operatinq Limits Report - Cycle 16 ENTERGY NUCLEAR OPERATIONS, INC INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NO. 50-286

NEntergy Procedure Use Is: Control Copy:

Nuclear Northeast  !] Continuous Effective Date: /,

• O3 Reference O Information Page 1 of 12 3-GRAPII-RPC-16, Revision: 1 C()RE *PERATING LIMITSR PORT Approved By:

C Prpedure Sponsor, I )M/Desugnee Dat0 REVISION era tiO'ýý Team 3B Procedure Owner GENERAL GENERAL REVISION

CORE OPERATING LIMITS REPORT Nn ~-(~RAPH-RPfl-1R P~'~r I I CORE OPERATING LIMITS REPORT .......... ...

Page 2 of 12 REVISION

SUMMARY

(Page 1 of 1) 1.0 REASON FOR REVISION 1.1 Incorporate Cycle 16 Specific Data 2.0

SUMMARY

OF CHANGES 2.1 Changed the title of the Graph to read just "CORE OPERATING LIMITS REPORT". Including "Cycle #" in the GRAPH title requires all procedures that mention or refer to it to be updated every RFO to the new title.

(Feedback IP3-9120) [Editorial 4.6.4]

2.2 Updated data throughout the graph to reflect cycle 16 per Indian Point Unit 3 Cycle 16 Core Operating Limits Report (COLR), Revision 0, as supplied by Westinghouse.

No: 3-GRAPH-RPC-16 Rev: 1 REPORT CORE OPERATING LIMITS Page 3 of 12 TABLE OF CONTENTS SECTION PAGE TS 2.1.1 Reactor Core SLs ....................................... I .......... 4 TS 3.1.1 Shutdow n Margin (SDM ) ...................................................................................... 4 TS 3.1.3 Moderator Temperature Coefficient (MTC) .......................... I ..4 TS 3.1.5 Shutdown Bank Insertion Lim its .......................................................................... 5 TS 3.1.6 Control Bank Insertion Lim its ............................................................................... 5 TS 3.2.1 Heat Flux Hot Channel Factor (FQ(Z)) . ............................................................. 5 TS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor FAH ................................................... 5 TS 3.2.3 Axial Flux Difference (AFD) (Constant Axial Offset Control (CAOC) Methodology) .6 TS 3.3.1 R PS Instrum entation .......................................................................................... 6 TS 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB)

Lim its ...............................................................................................................  ;....................... 6 TS 3.9.1 Refueling Boron Concentration .......................................................................... 6 ATTACHMENTS Attachment 1 OVERTEM PERATURE AT .......................................................................... 7 Attachment 2 OVERPOWER AT ........................................

8 FIGURES Figure 1 Reactor Core Safety Limit - Four Loops in Operation . .................... 9 Figure 2 Rod Bank Insertion Lim its .................................................................................. 10 Figure 3 Hot Channel Factor Normalized Operating Envelope ........................................ 11 Figure 4 Axial Flux Difference Envelope Limits ................................................................ 12

No: 3-GRAPH-RPC-16 Rev: 1 CORE OPERATING LIMITS REPORT Page 4 of 12 NOTE

• The Technical Specification references shown next to each Factor OR Limit in this COLR are there to identify the corresponding sections in the Technical Specifications that refer to the COLR.

• The COLR, including any midcycle revisions or supplements, shall be provided for each reload cycle to the NRC. {T.S. 5.6.5d.}

" The data presented in this report applies to Cycle 16 ONLY and may NOT be used for other cycles of operation, Also, it applies only to operation at a maximum power level of 3188.4 MWt. Any technical change to this document requires a Safety Evaluation to be performed in accordance with 10CFR50.59.

TS 2.1.1 Reactor Core SLs In MODE 1 and 2, the combination of thermal power level, pressurizer pressure, and highest loop average coolant temperature SHALL not exceed the limits shown in Figure 1. The safety limit is exceeded if the point defined by the combination of Reactor Coolant System average temperature and power level is at any time above the appropriate pressure line.

TS 3.1.1 Shutdown Margin (SDM)

The shutdown margin SHALL be greater than or equal to 1.3% Ak/k.

TS 3.1.3 Moderator Temperature Coefficient (MTC)

The MTC upper limit SHALL be < 0.0 Ak/k/°F at hot zero power.

The MTC lower limit SHALL be less negative than or equal to:

-38.0 pcm/2 F @ 300 ppm

-44.5 pcm/ 2 F @ 60 ppm

-47.0 pcm/-F @ 0 ppm

No: 3-GRAPH-RPC-16 Rev: 1 CORE OPERATING LIMITS REPORT Page 5 of 12 TS 3.1.5 Shutdown Bank Insertion Limits The Shutdown Banks SHALL be fully withdrawn when the reactor is in MODE 1 and MODE 2. Shutdown Banks with a group step counter demand position > 225 steps are considered fully withdrawn because the bank demand position is above the top of the active fuel.

TS 3.1.6 Control Bank Insertion Limits The Control Bank Insertion Limits for MODE 1 and MODE 2 with kett > 1.0 are as indicated in Figure 2. Control Bank Insertion Limits apply to the step counter demand position.

Each control bank shall be considered fully withdrawn at > 230 steps.

TS 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))

NOTE

" P is the fraction of Rated Thermal Power (RTP) at which the core is operating.

" K(Z) is the fraction given in Figure 3 and Z is the core height location of FQ.

IF P > .5, Fa(Z) < (2.50/P) x K(Z)

IF P _ .5, Fo(Z) < (5.00) x K(Z)

TS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor FAH NOTE P is the fraction of Rated Thermal Power (RTP) at which the core is operating.

FNH 5 1.70 { 1 +0.3(1 - P)}

No: 3-GRAPH-RPC-16 Rev: 1 CORE OPERATING LIMITS REPORT Page 6 of 12 TS 3.2.3 Axial Flux Difference (AFD) (Constant Axial Offset Control (CAOC)

Methodologv)

The Indicated limit is the Target Band; i.e., the Target +/- 5%

The AFD shall be maintained within the ACCEPTABLE OPERATION portion of Figure 4, as required by TS 3.2.3.

TS 3.3.1 RPS Instrumentation

1. Overtemperature AT Allowable Value as referenced in Technical Specifications Table 3.3.1-1, Function 5, Note 1 Refer to Attachment 1

2. Overpower AT Allowable Value as referenced in Technical Specifications Table 3.3.1-1, Function 6, Note 2 Refer to Attachment 2 TS 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits The following DNB related parameters are applicable in MODE 1:

a. Reactor Coolant System loop Tavg -<576.7°F for full-power Tavg = 572.0°F

b. Pressurizer Pressure _>2204 psig

c. Reactor Coolant System Total Flow Rate > 364,700 gpm TS 3.9.1 Refuelina Boron Concentration When required by Technical Specification 3.9.1, the minimum boron concentration in the RCS, Refuel Canal, and Reactor Cavity SHALL be the more restrictive of either > 2050 ppm or that which is sufficient to provide a shutdown margin _>5% Ak/k.

No: 3-GRAPH-RPC-16 Rev: 1 REPORT CORE OPERATING LIMITS Page 7 of 12 OVERTEMPERATURE AT The Overtemperature AT Function Allowable Value SHALL not exceed the following:

Note: For limitationson the maximum trip Setpoint, see Technical Specification 3.3.1.

AT < AT, [K1 - K2 [(1 + T1s)/(1 + T2s)] (T - T') + K3 (P - P') - f1(AI)]

Where: AT is measured RCS AT, OF (measured by hot leg and cold leg RTDs).

ATo is the loop specific indicated AT at RTP, OF.

s is the Laplace transform operator, sec- 1.

T is the measured RCS average temperature, OF.

T' is the loop specific indicated T at RTP, cF < 572.0°F.

P is the measured pressurizer pressure, psig.

P' is the nominal RCS operating pressure, Ž>2235 psig.

K1 *1.26 K2 > 0.022/°F K3 > 0.00070/psi T1 Ž 25.0 sec T 2 *- 3.0 sec f1(AI) = 4.00[-15.75- (qt- qb)] when qt - qb * - 15.75% RTP 0% of RTP when -15.75% RTP < qt - qb < 6.9% RTP

+3.33[(qt - qb) - 6.9]} when qt - qb > 6.9% RTP Where qt and qb are percent RTP in the upper and lower halves of the core, respectively, and qt + qb is the total THERMAL POWER in percent RTP.

No: 3-GRAPH-RPC-16 Rev: 1 CORE OPERATING LIMITS REPORT Page 8 of 12 OVERPOWER AT The Overpower AT Function Allowable Value SHALL not exceed the following:

Note: Forlimitationson the maximum trip Setpoint, see TechnicalSpecification 3.3.1.

AT _<ATo [K4 - K5 [(m13s)/(1 + - 3 s)](T) - K6 (T - T') - f2 (AI)]

Where: AT is measured RCS AT, OF (measured by hot leg and cold leg RTDs).

ATo is the loop specific indicated AT at RTP, OF.

s is the Laplace transform operator, sec1 .

T is the measured RCS average temperature, OF.

T is the loop specific indicated T at RTP, F _<572.0°F.

K4 < 1.10 K5 - 0.0175/CF for increasing T K6 > 0.0015/1F when T > T 0/0 F for decreasing T 01/F when T s T" T3 > 10 sec f2(AI) = 0

No: 3-GRAPH-RPC-16 Rev: 1 REPORT CORE OPERATING LIMITS Page 9 of 12 Figure 1 Reactor Core Safety Limit-' Four Loops in Operation 6W a) 4)

Q50 Reactor Power (Percent of 3216 MWt)

[Conservative relative to 3188.4 MWt; use as-is for operation at 3188.4 MWt]

No: 3-GRAPH-RPC-16 Rev: 1 CORE OPERATING LIMITS REPORT Page 10 of 12 Figure 2 Rod Bank Insertion Limits (Four Loop Operation) 104 Step Overlap 230 220 --- 7-K - . - -

,34.3,2300 210 200 190 180 L5AiNK B- Iz~ - 100,176 170 160 150

-C 140 -Aý T-~~

130 120 --------- --

+

__i- c~~~1-

.-.- ~-- --- +-_.

C 0) 110 i *. ..... - I.... /

0 100 90 ------------------.- --

C 80 0

Cc 70 ...

• ........I--

- I

--, - - - -.. I i' 60 - - - --..... -"---.-----t--................-

50 7 -

40 -L6 ..-

30 20 10 0

0 10 20 30 ,40 50 60 70 80 90 100 Power (Percent of 3188.4 MWt)

No: 3-GRAPH-RPC-16 Rev: 1 REPORT CORE OPERATING LIMITS Page 11 of 12 Figure 3 Hot Channel Factor Normalized Operating Envelope (For S. G. Tube Plugging up to 10%)

1.2 -

0°.0, 1.001 6.0, 1.0

- ~ -~-.---- 4 12.0, 0.9251 0.8 0

a.

0r UI-N0.6 4.

E Z0 0.4 _________ __________ .4 0.2 0

0 2 4 6 8 10 12 Core Elevation (feet)

No: 3-GRAPH-RPC-16 Rev: 1 CORE OPERATING LIMITS REPORT Page 12 of 12 Figure 4 Axial Flux Difference Envelope Limits 00 3-co

.0-0 a)

-40 -30 -20 -10 0 10 20 30 40' Axial Flux Difference