View source for NL-02-143, Cycle 16 Core Operating Limit Report (COLR)

{{Adams
| number = ML023230043
| issue date = 11/15/2002
| title = Cycle 16 Core Operating Limit Report (COLR)
| author name = Dacimo F
| author affiliation = Entergy Nuclear Northeast, Entergy Nuclear Operations, Inc
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000247
| license number = DPR-026
| contact person = 
| case reference number = NL-02-143
| document type = Fuel Cycle Reload Report, Letter type:NL
| page count = 6
}}

=Text=
{{#Wiki_filter:l                                                                       Entergy Nuclear Northeast Entergy Nuclear Operations, Inc Indian Point Energy Center 295 Broadway, Suite 1 PO Box 249 Buchanan, NY 10511-0249 November 15, 2002 Re:     Indian Point Unit No. 2 Docket No. 50-247 NL-02-143 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station O-P1-17 Washington, DC 20555-0001

==Subject:==
Indian Point Unit 2 Cycle 16 Core Operating Limit Report (COLR)

==Dear Sir:==

In accordance with the Indian Point Unit 2 Technical Specification 6.9.1.11, enclosed is the IP2 COLR for Cycle 16.
There are no commitments contained in this letter.
Should you have any questions regarding this matter, please contact Mr. John McCann, Manager, Licensing, Indian Point Energy Center at (914) 734-5074.
Sin   r Fred Dacimo Vice President - Operations Indian Point 2 cc:    Hubert J. Miller Regional Administrator US Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. Patrick D. Milano, Senior Project Manager, Section 1 Project Directorate I Division of Licensing Project Management US Nuclear Regulatory Commission Mail Stop O-8-2C Washington, DC 20555 NRC Senior Resident Inspector US Nuclear Regulatory Commission PO Box 38 Buchanan, NY 10511

INDIAN POINT 2                                                               GRAPH RPC-6 Revision 5 OPERATIONS CYCLE 16 CORE OPERATING LIMITS REPORT Prepared by:                                                 KZAl L 2 4 dt Reviewer:
Reviewer:
Approval:
Date Effective Date BIENNIAL REVIEW Reviewer / Date Reviewer / Date For use as field copy. Valid for 24 hours:
Qualified Operator           Date / Time 24 Hr Extension:
Control Room Supervisor      Date / Time 24 Hr Extension:
Control Room Supervisor      Date / Time REFERENCE USE GRAPH RPC-6 Rev 5.wpd

CYCLE 16 CORE OPERATING LIMITS REPORT                                                         RPC-6 Rev. 5 Core Operating Limits Report COLR 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 data presented in this report applies to Cycle 16 ONLY and may NOT be used for other cycles of operation. Any technical change to this graph requires a Safety Evaluation to be performed.
NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR Note P is the fraction of full power at which the core is operating.
FAHN<1.70    {1+0.3(1-P)}                                                         Tech. Spec. 3.10.2 HEIGHT DEPENDENT HEAT FLUX HOT CHANNEL FACTOR FOR
* 20% TUBE PLUGGING Note K(Z) is the fraction given in Figure 1 AND Z is the core height location of FQ.
IF P > .5, FQ(Z) < (2.50 /P) x K(Z)                                               Tech. Spec. 3.10.2 IF P < .5, FQ(Z) < (5.00) x K(Z)                                                  Tech. Spec. 3.10.2 Page 1 of 4

RPC-6 CYCLE 16 CORE OPERATING LIMITS REPORT                                            Rev. 5 AXIAL FLUX DIFFERENCE ENVELOPE LIMITS The Indicated Axial Flux Difference limit Tech. Spec. 3.10.2.6.1 is the Target Band; i.e., the Target +/- 5%
The Axial Flux Difference Envelope Limits at 90 percent power are -11%, + 11% AND increase by -1% and +1%, for each 2% of rated power below 90% power, as indicated                                    3.10.2.6.1 Tech. Spec.
by graph RV-10, Unit 2 Target Flux Values INSERTION LIMITS The Shutdown Banks shall be fully withdrawn Tech. Spec. 3.10.4 when the reactor is critical OR approaching criticality.
The Control Bank Insertion Limits for                                            3.10.4 Tech. Spec.
Criticality, are as indicated in Figure 2.
Page 2 of 4

CYCLE 16 CORE OPERATING LIM\ITS RE PORT                                                  RPC-0 Rev. 5 Figure I       HOT CHANNEL FACTOR NORMALIZED OPERATING ENVELOPE (For S. G. Tube Plugging up to 20%)
1.2 0.0,1.00                        6.0,1.00 1.0 112.0, 0.925]I a)
S0.8 0
       .r LiL "0   0.6 N
E 0
Z     0.4 1
E N            -4        4-4-4-*-t-t-11t1 0.2 0
0           2                4         6       8      10           12 Core Elevation (feet)
Page 3 of 4

CYCLE 16 CORE OPERATING LIMITS REPORT                                           RP*C-6 Rev. 5 Figure 2    ROD BANK INSERTION LIMITS (Four Loop Operation) 100 Step Overlap 225 1(66,223 BANK B 200   (0,20951)                           m
   =   175 150 Co 0.
I-Co z   125 0
Co 0
100 z
0 0    75 50 25 0
0         10     20    30       40      50      60  70    80 90 100 Power Level (Percent of Rated Power)
Page 4 of 4}}