RNP-RA/04-0059, Transmittal of Core Operating Limits Report

Transmittal of Core Operating Limits Report

ML041460271
Person / Time
Site:	Robinson
Issue date:	05/18/2004
From:	Baucom C Progress Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RNP-RA/04-0059
Download: ML041460271 (14)

Text

C0 Progress Energy Serial: RNP-RA/04-0059 MAY 1 8 2004 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/LICENSE NO. DPR-23 TRANSMITTAL OF CORE OPERATING LIMSTS REPORT Ladies and Gentlemen:

In accordance with Technical Specifications 5.6.5.d, Progress Energy Carolinas, Inc., also known as Carolina Power and Light Company, is transmitting the H. B. Robinson Steam Electric Plant, Unit No. 2, Core Operating Limits Report (COLR) for Cycle 23.

If you have any questions concerning this matter, please contact me.

Sincerely,

@4-C. T. Baucom Supervisor - Licensing/Regulatory Programs RAC/rac Attachment c:

L. A. Reyes, NRC, Region II NRC Resident Inspector, HBRSEP C. P. Patel, NRC, NRR Progress Energy Carolinas. Inc.

Robinson Nuclear Plant 35B1 West Entrance Road Hartsville, SC 29550

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/04-0059 13 pages including cover page H. B. ROBINSON STEAM ELECTRIC PLANT (HBRSEP), UNIT NO. 2 CYCLE 23 CORE OPERATING LIMITS REPORT REVISION 0 Note: This report is Attachment 7.1 to HBRSEP, Unit No. 2, Fuel Management Procedure (FMP)-001

ATTACHMENT 7.1 Page I of 12 HBRSEP UNIT NO. 2, CYCLE 23 CORE OPERATING LIMITS REPORT REVISION 0 1.0 OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for HBRSEP Unit No. 2, Cycle 23 has been prepared per EC 51756 in accordance with the requirements of ITS 5.6.5.

The Improved Technical Specifications affected by this report and the methodologies used for the various parameters are listed below.

ITS Applicable Methodology Parameter Reference (Section 3.0 Number)

MTC 3.1.3 1,2,4,15,18,19, 22 Shutdown Bank RILs 3.1.5 1,2, 4, 8,15, 18, 19, 22 Control Bank RlLs 3.1.6 1,2,4,8,15,18,19,22 Fov(Z) 3.2.1, 3.2.3 1,2, 5, 6, 7, 8, 11, 12,13, 14, 15,17,18,19, 21,22 FAH 3.2.2,3.2.3 1,2,3,4,5, 6, 7,9,10,11, 12, 13,14,15,17,18,19,20, 21,22 AFD 3.2.1, 3.2.3 1, 2, 6, 7, 12, 13, 14, 15, 16, 18,19,21,22 Shutdown Margin Requirements 3.1.1, 3.4.5,3.4.6 1,2,4,8,15, 18,19,22 Refueling Boron Requirements 3.9.1 1,2,4, 8,18,19,22 COLR 5.6.5 None FMP-001 Rev. 18 Page 10 of 22

ATTACHMENT 7.1 Page2of 12 HBRSEP UNIT NO. 2, CYCLE 23 CORE OPERATING LIMITS REPORT REVISION 0 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using the NRC-approved methodologies specified In ITS 5.6.5 and the COLR Section 3.0.

2.1 Moderator Temperature Coefficient (ITS 3.1.3) 2.1.1 The Moderator Temperature Coefficient (MTC) limits are:

a) The Positive MTC (ARO) shall be less than or equal to +5.0 pcm/OF for power levels up to 50% RTP, and b) The Positive MTC (ARO) shall be less than or equal to 0.0 pcm/fF at 50%

RTP and above.

c) The Negative MTC (ARO/RTP) shall be less negative than -40.0 pcm/0F.

2.1.2 The 300 ppm Surveillance limit is:

At an equilibrium RTP-ARO boron concentration of 300 ppm the MTC shall be less negative than or equal to -32.5 pcm/0F.

2.1.3 The 60 ppm Surveillance limit is:

At an equilibrium RTP-ARO boron concentration of 60 ppm the MTC shall be less negative than or equal to -36.6 pcm/OF.

2.2 Shutdown Banks Insertion Limits (ITS 3.1.5) 2.2.1 The shutdown banks shall be withdrawn to at least 225 steps.

2.3 Control Bank Insertion Limits (ITS 3.1.6) 2.3.1 The control banks shall be limited in physical Insertion as shown in Figure 1.0 FMP-001 I

Rev. 18 I

Page 11 of 22

ATTACHMENT 7.1 Page 3 of 12 HBRSEP UNIT NO.2, CYCLE 23 CORE OPERATING LIMITS REPORT REVISION 0 2.4 Heat Flux Hot Channel Factor - F0v (Z) (ITS 3.2.1, 3.2.3)

FoV(Z) < (CFQ/P) x K(Z) for P > 0.5 FoV(Z) < (CFQ/0.5) x K(Z) for P < 0.5 Where: P = (Thermal Power / Rated Thermal Power) 2.4.1 CFQ = 2.46 for ROB-14, ROB-15, ROB-16, ROB-18, ROB-19 and ROB-20 reload batches 2.4.2 K(Z) Is specified in Figure 2.0 2.5 Nuclear Enthalpy Rise Hot Channel Factor - FA&K (ITS 3.2.2, 3.2.3)

FA.H < FAHRTP (1 + PFAH (0-P))

Where: P = (Thermal Power / Rated Thermal Power) 2.5.1 FAH is the measured FAHN multiplied by the measurement uncertainty (1.04) 2.5.2 F^.RTP = 1.80 for ROB-14, ROB-15, ROB-16, ROB-18, ROB-19 and ROB-20 reload batches 2.5.3 PFAH = 0.2 2.6 Axial Flux Difference (ITS 3.2.1, 3.2.3) 2.6.1 The axial flux difference target bands are +/-3% and +/-5% about the target AFD.

2.6.2 V(Z) values for the +/-3% and +/-5% target bands are specified in Figures 3.1 and 3.2 2.6.3 The AFD Acceptable Operation Limits are specified in Figure 4.0 I FMP-001 I

Rev. 18 I

Page 12 of 22

ATTACHMENT 7.1 Page 4 of 12 H.

BRSEP UNIT NO.

2, CYCLE 23 CORE OPERATING LIMITS REPORT REVISION 0 2.7 Shutdown Margin Requirements (SDM) (ITS 3.1.1,3.1.4,3.1.5,3.1.6, 3.1.8, 3.4.5, 3.4.6, 3.9.1) 2.7.1 The Mode 1 and Mode 2 required SDM versus RCS boron concentration is presented in Figure 5.0.

2.7.2 The Mode 3 SDM requirements are as follows:

a) With at least 2 reactor coolant pumps in operation, the SDM shall be greater than or equal to that specified in Figure 5.0.

b) With less than 2 reactor coolant pumps in operation and the rod control system capable of rod withdrawal, the SDM shall be greater than or equal to 4% Ak/k.

c) With less than 2 reactor coolant pumps in operation and with the rod control system not capable of rod withdrawal, the SDM shall be greater than or equal to that specified in Figure 5.0.

2.7.3 The Mode 4 SDM requirements are as follows:

a) With at least 2 reactor coolant pumps in operation, the SDM shall be greater than or equal to that specified in Figure 5.0.

b) With less than 2 reactor coolant pumps in operation and the rod control system capable of rod withdrawal, the SDM shall be greater than or equal to 4% Ak/k.

c) With less than 2 reactor coolant pumps in operation and with the rod control system not capable of rod withdrawal, the SDM shall be greater than or equal to that specified in Figure 5.0.

2.7.4 The minimum required SDM for Mode 5 is 1% Ak/k.

2.7.5 The minimum required SDM for Mode 6 is 6% Ak/k.

2.8 Refueling Boron Concentration (ITS 3.9.1) 2.8.1 In Mode 6 the minimum boron concentration shall be 1950 ppm.

IFMP-001 I

Rev. 18 I

Page I3of 22

ATTACHMENT 7.1 Page 5 of 12 HBRSEP UNIT NO. 2, CYCLE 23 CORE OPERATING LIMITS REPORT REVISION 0 3.0 METHODOLOGY REFERENCES

1) Not Used For Cycle 23

2) XN-NF-84-73(A), Revision 5, 'Exxon Nuclear Methodology For PWRs:

Analysis of Chapter 15 Events," Siemens Power Corporation, October 1990.

3) XN-NF-82-21 (A), Revision 1, "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations," Exxon Nuclear Company, September 1983.

4) EMF-84-093(A), Revision 1, uSteamline Break Methodology for PWRs,"

Siemens Power Corporation, February 1999.

5) XN-75-32(A) Supplements 1, 2, 3, and 4, "Computational Procedure for Evaluating Fuel Rod Bow," Exxon Nuclear Company, October 1983.

6) XN-NF-82-49(A), Revision 1 (April 1989) and Supplement 1 (December 1994), "Exxon Nuclear Company Evaluation Model Revised EXEM PWR Small Break Model," Siemens Power Corporation.

7) EMF-2087(A), "SEM/PWR-98: ECCS Evaluation Model for PWR LBLOCA Applications," Siemens Power Corporation, June 1999.

8) XN-NF-78-44(A)," A Generic Analysis of the Control Rod Ejection Transient for Pressurized Water Reactors," Exxon Nuclear Company, October 1983

9) Not Used For Cycle 23

10) Not Used For Cycle 23

11) XN-NF-82-06(A), Revision 1 and Supplements 2, 4, and 5, "Qualification of Exxon Nuclear Fuel for Extended Burnup (PWR)," Exxon Nuclear Company, October 1986.

12) Not Used For Cycle 23 I FMP-001 I

Rev. 18 1

Page 14 of 22

ATTACHMENT 7.1 Page 6 of 12 HBRSEP UNIT NO. 2, CYCLE 23 CORE OPERATING LIMITS REPORT REVISION 0

13) Not Used For Cycle 23

14) Not Used For Cycle 23

15) Not Used For Cycle 23

16) ANF-88-054(A), "PDC-3: Advanced Nuclear Fuels Corporation Power Distribution Control for Pressurized Water Reactors and Application of PDC-3 to H.B. Robinson Unit 2," Advanced Nuclear Fuels Corporation, October 1990.

17) ANF-88-133(A), and Supplement 1, "Qualification of Advanced Nuclear Fuels PWR Design Methodology for Rod Burnups of 62 GWd/MTU," Advanced Nuclear Fuels Corporation, December 1991.

18) ANF-89-151 (A), and correspondence "ANF-RELAP Methodology for Pressurized Water Reactors: Analysis of Non-LOCA Chapter 15 Events,"

Advanced Nuclear Fuels Corporation, May 1992.

19) EMF-92-081 (A), Revision 1, Statistical Setpoint/Transient Methodology for Westinghouse Type Reactors," Siemens Power Corporation, February 2000.

20) EMF-92-153(A), Revision 0 and Supplement 1, "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel," Siemens Power Corporation, March 1994.

21) XN-NF-85-92(A), uExxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination and Thermal Conductivity Results," Exxon Nuclear Company, November 1986.

22) EMF-96-029(A), Volume 1, Volume 2 and Attachment, "Reactor Analysis System for PWRs," Siemens Power Corporation, January 1997.

23) EMF-92-116(A), "Generic Mechanical Design Criteria for PWR Fuel Designs," Siemens Power Corporation, February 1999.

I FMP-001 I

Rev. 18 l

Page I1of 22

ATTACHMENT 7.1 Page 7 of 12 HBRSEP UNIT NO. 2, CYCLE 23 CORE OPERATING LIMITS REPORT REVISION 0 Figure 1.0.ControlGroup Insertion Limits forThree Loop Operation I

I 225 200 175 160 125 100 75 50 25 0

, (4i 7,225)

(67.03,225)

'0 155 2 5)

(0,16 Bnk B

,So n C

(100,165)

(0,97),

(2.,._)

l I

0 10 20 30 40 50 60 CORE POWER (%)

70 so 90 100 NOTE:

The breakpoint between BOL and EOL RIL occurs at 50% of the cycle as defined by bumup. For Cycle 23, this bumup occurs at 257 EFPDs.

Control rod banks shall always be withdrawn and inserted in the prescribed sequence. For withdrawal, the sequence is Shutdown "A", Shutdown "B", Control "A", Control "B", Control "C", and Control "D". The insertion sequence is the reverse of the withdrawal sequence.

Overlap of consecutive control banks shall not exceed the prescribed setpoint for automatic overlap. The setpoint is 97 steps.

Control bank A must be withdrawn from the core prior to power operation.

At BOL and 0% core power, Control bank B will be at or above step 224.

IFMP-001 I

Rev. 18 l

Page 16 of 22

ATTACHMENT 7.1 Page 8 of 12 HBRSEP UNIT NO. 2, CYCLE 22 CORE OPERATING LIMITS REPORT REVISION 0 Figure 2.0, Normalized Axial Dependence Factor K(z) for Fq Versus Elevation 1.20 1.00 N

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Rev. 18 l

Page 17of 22

ATTACHMENT 7.1 Page 9 of 12 HBRSEP UNIT NO. 2, CYCLE 23 CORE OPERATING LIMITS REPORT REVISION 0 Figure 3.1 V(z) as a Function of Core Height 1.01~

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FMP-001 Rev. 18 Page 18of 22

ATTACHMENT 7.1 Page 10 of 12 HBRSEP UNIT NO. 2, CYCLE 23 CORE OPERATING LIMITS REPORT REVISION 0 Figure 3.2 V(z) as a Function of Core Height 1.10 1.C9 103 I

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FMP-001 Rev. 18 Page 19of 22

i ATTACHMENT 7.1 Page 11 of 12 HBRSEP UNIT NO. 2, CYCLE 23 CORE OPERATING LIMITS REPORT REVISION 0 Figure 4.0, Allowable Deviation from Target Flux Difference 100 a-4:

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For power levels above 90%, power operation is allowed within the target bands (+/-3% and +5%).

l FMP-001 I

Rev. 18 l

Page 20 of 22

ATTACHMENT 7.1 Page l2 of 12 I-BRSEP UNIT NO. 2, CYCLE 23 CORE OPERATING LIMITS REPORT REVISION 0 Figure 5.0, Shutdown Margin Versus Boron Concentration 2.0 -

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IFMP-001 IRev.

18 1Page 21 f2