NL-03-080, Core Operating Limits Report for Cycle 13

Core Operating Limits Report for Cycle 13

ML031330184
Person / Time
Site:	Indian Point
Issue date:	05/08/2003
From:	Dacimo F Entergy Nuclear Northeast
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-03-080
Download: ML031330184 (13)

Text

Entergy Nuclear Northeast Indian Point Energy Center A=k 295 Broadway, Suite 1 E Ennt tffoyJ gyBuchanan, P0O. Box 249 Tel 914 734 NY 10511-0249 5340 Fax 914 734 5718 Fred Dacimo Vice President, Operations NL-03-080 May 8, 2003 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-Pl-17 Washington, D.C. 20555-0001

Subject:

Indian Point 3 Nuclear Power Plant Docket No. 50-286 Core O )erating Limits Report for Cycle 13

Dear Sir:

This letter transmits the Core Operating Limits Report (COLR) as required bf Technicai Specification 5.6.5. Enclosed is Indian Point 3 Plant Operating ProcedLre POP-2.3, Revision 13 that ccntains the core operating limits for Cycle 13. Initial criticality for Cycle 13 occurred when mode 2 was entered on April 22, 2001. Indian Point 3 is making no new commitments in this letter.

V y yours, Fred R. Dacimo Vice President, Operations Indian Point Energy Center cc: See next page

Docket No. 50-286 NL-03-080 Page 2 of 2 cc: Mr. Hubert J. Miller Regional Administrator Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406-1415 Resident Inspector's Office Indian Point Unit 3 U.S. Nuclear Regulatory Commission P.O. Box 337 Buchanan, NY 10511 Mr. Robert Milano, Project Manager Project Directorate I Division of Licensing Project Management U.S. Nuclear Regulatory Commission Mail Stop 08C2 Washington, D.C. 20555

Procedure Use Is:

Control CopWfRl*INfOPY lntey Z Continuous Nuclear Northeast D Reference Effective Date: /y LI Information Page 1 of 11 This procedure is TSR CORE 0 13 Writer Reviewer Date Approve Procedure Owner PARTIAL REVISION

REVISION

SUMMARY

(Page 1 of 1) 1.0 REASON FOR REVISION 1.1 Revised to incorporate Cycle 13 core information per DC 03-3-017 RCS.

2.0

SUMMARY

OF CHANGES 2.1 Changed the title of this procedure to reflect Cycle 13 core.

2.2 Deleted the Hot Channel Factor at Rated Thermal Power, FH N for OFA and V5 fuel since these types of fuel are NOT part of the cycle 13 reactor core.

2.3 Changed the Reactor Coolant System and Refueling Cavity Boron Concentration: (SDM of 5% AK/ K value) from1832 ppm to 1865 ppm) for the cycle 13 reactor core.

2.4 Updated Reference 6.2.2 to Indian Point Unit 3 Cycle 13 Reload Safety Evaluation, April 2003 2.5 Deleted Attachment 4, Reactivity Control Parameters, as this data is NOT part of the COLR and required for reactor startup. Reactor Engineering will issue this cycle specific data as Graph RV-14, Reactivity Control Parameters, in the future.

No: POP-2.3 Rev: 13 CORE OPERATING LIMITS FOR CYCLE 13 Page 3 of 11 TABLE OF CONTENTS Section Title Paqe 1.0 PURPOSE ............................ 4 2.0 PRECAUTIONS AND LIMITATIONS ............................ 4 3.0 PREREQUISITES ............................ 4 4.0 PROCEDURE ............................ 5 5.0 DEFINITIONS ........................... 8

6.0 REFERENCES

........................... 8 7.0 RECORDS AND DOCUMENTATION ........................... 8 Attachments

'~ Attachment 1, CONTROL ROD INSERTION LIMITS vs RATED THERMAL POWER ...... 9 Attachment 2, K(z) NORMALIZED FQ(z) AS A FUNCTION OF CORE HEIGHT ............ 10 Attachment 3, AXIAL FLUX DIFFERENCE ENVELOPE LIMITS .................................... 11

1.0 PURPOSE 1.1 This procedure establishes the cycle specific safety limits for the reactor fuel.

1.2 This procedure applies to cycle 13 fuel.

2.0 PRECAUTIONS AND LIMITATIONS 2.1 The data presented in this report applies to Cycle 13 Onlv and SHALL NOT be used for other operating cycles.

2.2 This data is applicable from completion of cycle 13 core reload until initiation of the cycle 14 core reload.

NOTE The Core Operating Limits Report (COLR), including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.

2.3 IF a part of this procedure is changed which affects information contained in the COLR {Definition 5.1}, THEN SUBMIT a copy of this approved procedure to the Site Licensing Manager for transmittal to the NRC per ITS: 5.6.5

{Reference 6.1.1}

2.4 COLR data is provided by Reactor Engineering per procedure RA-25, Control of Core Operating Limits Report.

3.0 PREREQUISITES None

4.0 PROCEDURE 4.1 The following are Core Operating Limits for the cycle 13 reactor fuel:

Table 4.1 CORE OPERATING LIMITS FOR CYCLE 13 REACTOR FUEL PARAMETER VALUE CORRESPONDING APPLICABILITY T.S.

Hot Channel Factor at 2.42 3.2.1 Mode 1 Rated Thermal Power, (B.3.2.1 for Fo (Z) mathematical (Measured via flux formula, error mapping) tolerances, and measurement by flux mapping)

Height Dependent FQ (Z) Refer to Aftachment 2 3.2.1 Mode 1 Multiplier K (Z), referred to as "fraction" Hot Channel Factor at 3.2.2 Mode 1 Rated Thermal Power, FAH N for Vantage + 1.635 Power Factor Multiplier for 3.2.2 Mode l FAH = PFAH PFH for 0.50 P 1.0 0.3 PFAH for P < 0.5 0.4 Equation for FAHN FAHN < FAHRTP (1 + PFAH (1-P)) 3.2.2, B.3.2.2, Mode 1 (Measured via flux B.2.1.1 for variable (Maping) via fluxdefinitions and error mapping) l tolerances Axial Flux Difference Band +/-5% 3.2.3 Mode 1 with Width Refer to Affachment 3 3.2.3 Thermal Power

> 15%

Table 4.1 CORE OPERATING LIMITS FOR CYCLE 13 REACTOR FUEL PARAMETER VALUE CORRESPONDING APPLICABILITY T.S.

Axial Flux Difference -11%, +11% 3.2.3 Mode 1 with Envelope Limits at 90% Refer to Attachment 3 Thermal Power power > 15%

Axial Flux Difference +/-1% 3.2.3 Mode 1 with Envelope Increase for each Refer to Aftachment 3 Thermal Power 2% of rated thermal power > 15%

< 90% RTP but Ž 50% RTP Shutdown Bank Insertion Ž 225 Steps withdrawn 3.1.5 Mode 1 Limits (Indicated) Mode 2 with any Control bank not fully inserted.

N/A during SR 3.1.4.2

'Control Bank Insertion Refer to Attachment 1 3.1.6 Mode 1 Limits Mode 2 with Keff 1.0 N/A during SR 3.1.4.2 Control Bank Overlap Withdraw: A, B, C, D 3.1.6, B.3.1.6 Mode l Pattern Insert: D, C B, A Mode 2 with Keff

Ž1.0 Control Bank-Overlap--- 104 Steps 3.1.6, B.3.1.6 Mode 1 Mode 2 with Keff 1.0 Control Bank Fully 230 Steps 3.1.6, B.3.1.6 Mode 1 Withdrawn Position Mode 2 with Keff 1.0 Shutdown Margin 2 1.3% AK/ K 3.1.1, 3.1.8 Mode 2 during physics tests Mode 2 with Keff

< 1.0

'1 _________________________________ Modes 3,4, 5

Table 4.1 CORE OPERATING LIMITS FOR CYCLE 13 REACTOR FUEL PARAMETER VALUE CORRESPONDING APPLICABILITY T.S.

Reactor Coolant System More restrictive of: 3.9.1 Mode 6 and Refueling Cavity Boron 2 1900 ppm Concentration OR concentration that provides aSDMŽ5%AK/K (SDM of 5% AK/K=

1865 ppm)

I + 4-Moderator Temperature @ 300 ppm - 38.0 pcm/°F 3.1.3 Modes 1, 2, 3 for Coefficient Limits Lower: lower limit

@ 60 ppm - 44.5 pcm/OF

@ LCO 2 - 47.0 pcm/°F Upper: < 0.0 pcm/ F Mode 1 and Mode 2 with Keff 2 1.0 for upper limit

5.0 DEFINITIONS 5.1 Core Operating Limits Report (COLR) - the parts of this procedure which satisfy the requirements of T.S. 1.1, 5.6.5.

6.0 REFERENCES

6.1 Commitment Documents 6.1.1 Technical Specification 5.6.5.

6.2 Development Documents 6.2.1 NRC Generic Letter 88-16 6.2.2 Indian Point Unit 3 Cycle 13 Reload Safety Evaluation, April 2003 6.2.3 Technical Specification 3.1.1, 3.1.3, 3.1.5, 3.1.6, 3.1.8, 3.2.1, 3.2.2, 3.2.3, 3.9.1, B.2.1.1.

6.2.4 Technical Specification 1.1, 5.6.5.

6.2.5 NRC Safety Evaluation Report for T.S. Amendment 103.

6.3 Interface Documents RA-25, Control of Core Operating Limits Report 7.0 RECORDS AND DOCUMENTATION None

No: POP-2.3 Rev: 13 CORE OPERATING LIMITS FOR CYCLE 13 Page 9 of 11 ATTACHMENT 1 CONTROL ROD INSERTION LIMITS vs RATED THERMAL POWER (Page 1 of 1) 230 220 1K 1fz1_1 1 -1 _f_

+

11 34.3,230 IEI

[_ I1 -1/rF 76.3, 230 _

210 200 190

+/-1 111 1/

180 Bank B _ - - 100, 76 170 c 160 w

• s 150 . I7'i=A H _ tl H-=-

II

-_I I -I

§ 140 Q. 130 a, 0,126 BanC tU 120 'I I1I I __ 11 o 110

o. 100 X 90 m 80 MO 70 __ _ + /_ 1___ Bank D 60 50 40 30 20 10 0,L0 4 I .

0 0 10 20 30 40 50 60 70 80 90 100 Power (% of Rated Thermal Power)

CORE OPERATING LIMITS FOR CYCLE 13 N Rev: 13 Page 10 of 11 ATTACHMENT 2 K(z) NORMALIZED FQ(z) AS A FUNCTION OF CORE HEIGHT (Page 1 of 1) 1.02 1

0.98 L.

0 0

0

• 0.96 Cu am L-10 m

a N

E 0.94 0

zm 0.92 0.9 0.88 0 1 2 3 4 5 6 7 8 9 10 11 12 Core Height (Feet)

ATTACHMENT 3 AXIAL FLUX DIFFERENCE ENVELOPE LIMITS (Page 1 of 1) 100 98 96 94 92 90 88 86 84 82 g 80 (D 78 o 76

. 74 w

0 U- ct 72 70

- 68 66 z

64 62 L- 60 0

w LL 58 0 56 C-54 52 50 30 -20 -10 0 10 20 30 40 Axial Flux Difference