2CAN030504, Cycle 18 Core Operating Limits Report

From kanterella
Jump to navigation Jump to search
Cycle 18 Core Operating Limits Report
ML050950438
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 03/29/2005
From: James D
Entergy Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
2CAN030504
Download: ML050950438 (15)
v • d • e


Text

""AEntergy Entergy Operations, Inc.

1448 S.R. 333 Russellville, AR 72802 Tel 479-858-4888 2CAN030504 March 29, 2005 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

SUBJECT:

ANO-2 Cycle 18 COLR Arkansas Nuclear One, Unit 2 Docket No. 50-368 License No. NPF-6

Dear Sir or Madam:

Arkansas Nuclear One, Unit 2 (ANO-2) Technical Specification 6.6.5.d requires the submittal of the Core Operating Limits Report (COLR) for each reload cycle. Attached is Revision 0 of the ANO-2 Cycle 18 COLR. This completes the reporting requirement for the referenced specification.

This submittal contains no new commitments.

If you have any questions or require additional information, please contact David Bice at 479-858-5338.

I declare under penalty of perjury that the foregoing is true and correct. Executed on March 29, 2005.

Sincerely, ale. James A

g Director, Nuclear Safety Assurance D Jldbb

Attachment:

1. ANO-2 Cycle 18 Core Operating Limits Report (COLR) 06

2CAN030504 Page 2 of 2 cc:

Dr. Bruce S. Mallett Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Drew Holland MS 0-7 D1 Washington, DC 20555-0001 Mr. Bernard R. Bevill Director Division of Radiation Control and Emergency Management Arkansas Department of Health 4815 West Markham Street Little Rock, AR 72205

Attachment I To 2CAN030504 ANO-2 Cycle 18 Core Operating Limits Report (COLR)

A2-NE-2004-001 Revision 0 ENTERGY OPERATIONS ARKANSAS NUCLEAR ONE - UNIT 2 CORE OPERATING LIMITS REPORT FOR CYCLE 18 1

A2-NE-2004-001 Revision 0 CORE OPERATING LIMITS REPORT FOR CYCLE 18 INDEX PAGE I.

INTRODUCTION................................................

3 II.

SUMMARY

OF CHANGES.................................................

3 III.

AFFECTED TECHNICAL SPECIFICATIONS.................................................

3 IV.

APPROVED METHODOLOGIES USED TO DETERMINE LIMITS...............

............ 4 V.

CORE OPERATING LIMITS.................................................

5 VI.

LIST OF FIGURES................................................

7 2

A2-NE-2004-001 Revision 0 ARKANSAS NUCLEAR ONE - UNIT 2 CORE OPERATING LIMITS REPORT FOR CYCLE 18 I.

INTRODUCTION This CORE OPERATING LIMITS REPORT (COLR) has been prepared in accordance with the requirements of Arkansas Nuclear One - Unit 2 (ANO-2) Technical Specification 6.6.5 for ANO-2's Cycle 18. This is Revision 0 of the Cycle 18 COLR.

II.

SUMMARY

OF CHANGES Listed below are the changes to the COLR from the latest revision of the Cycle 17 COLR.

Section IV, Approved Methodologies Used to Determine Limits," was added as part of the Technical Specification change request that was approved in the NRC's SER for Amendment 257.

Modified the EFPD breakpoints that specifies where a less positive (burnup dependent)

MTC was credited in the safety analyses.

The changed the first breakpoint from 124.9 EFPD to 125.0 EFPD. The second breakpoint was changed from 394.7 EFPD to 395.8 EFPD.

Modified Figure 3 by rotating the axis of the graph and splitting the graph into two (2) group specific graphs. Also included shading to specific areas to illustrate when Long term Steady State Actions apply and when Short Term Steady State Actions apply and when shutdown margin was not satisfied. There are no limit changes.

Linear Heat Rate has been changed from < 13.5 kWlft up to a burnup of 200 EFPD and

< 12.7 kWlft for burnups exceeding 200 EFPD to < 13.7 kWlft.

Ill. AFFECTED TECHNICAL SPECIFICATIONS

1) 3.1.1.1 Shutdown Margin - Tavg > 200OF
2) 3.1.1.2 Shutdown Margin - Tavg < 200OF
3) 3.1.1.4 Moderator Temperature Coefficient
4) 3.1.3.1 CEA Position
5) 3.1.3.6 Regulating CEA Insertion Limits
6) 3.2.1 Linear Heat Rate
7) 3.2.3 Azimuthal Power Tilt - Tq
8) 3.2.4 DNBR Margin
9) 3.2.7 Axial Shape Index 3

A2-NE-2004-001 Revision 0 IV. APPROVED METHODOLOGIES USED TO DETERMINE LIMITS Provided below are the analytical methods used to determine the core operating limits addressed by the individual Technical Specifications. These methods have been reviewed and approved by the NRC.

1) "Qualification of the PHOENIX-P / ANC Nuclear Design System for Pressurized Water Reactor Cores," (WCAP-1 1596-P-A), June 1988, "ANC: A Westinghouse Advanced Nodal Computer Code" (WCAP-10965-P-A), September 1986, and "ANC: A Westinghouse Advanced Nodal Computer Code: Enhancements to ANC Rod Power Recovery" (WCAP-10965-P-A, Addendum 1), April 1989 (Methodology for Specification 3.1.1.1, 3.1.1.2, 3.1.1.4, 3.1.3.6; and 3.2.4.b)
2)

"CE Method for Control Element Assembly Ejection Analysis," CENPD-0190-A, January 1976 (Methodology for Specification 3.1.3.6 and 3.2.3)

3) "Modified Statistical Combination of Uncertainties, CEN-356(M)-P-A, Revision 01-P-A, May 1988 (Methodology for 3.2.4.c, 3.2.4.d and 3.2.7).
4)

"Calculative Methods for the CE Large Break LOCA Evaluation Model," CENPD-132-P, August 1974 (Methodology for 3.1.1.4, 3.2.1, 3.2.3 and 3.2.7)

5) "Calculational Methods for the CE Large Break LOCA Evaluation Model," CENPD-132-P, Supplement 1, February 1975 (Methodology for 3.1.1.4, 3.2.1; 3.2.3 and 3.2.7)
6)

"Calculational Methods for the CE Large Break LOCA Evaluation Model," CENPD-132-P, Supplement 2-P, July 1975 (Methodology for 3.1.1.4, 3.2.1, 3.2.3 and 3.2.7)

7) "Calculative Methods for the CE Large Break LOCA Evaluation Model for the Analysis of CE and W Designed NSSS,' CEN-132, Supplement 3-P-A, June 1985 (Methodology for 3.1.1.4, 3.2.1; 3.2.3 and 3.2.7)
8)

"Calculative Methods for the CE Nuclear Power Large Break LOCA Evaluation Model,"

CENPD-132-P, Supplement 4-P-A, Revision 1, December 2000 (Methodology for 3.1.1.4, 3.2.1; 3.2.3 and 3.2.7)

9) "Calculative Methods for the CE Small Break LOCA Evaluation Model," CENPD-137-P, August 1974 (Methodology for 3.1.1.4, 3.2.1, 3.2.3, and 3.2.7)
10) "Calculative Methods for the CE Small Break LOCA Evaluation Model," CENPD-137, Supplement 1-P, January 1977 (Methodology for 3.1.1.4, 3.2.1, 3.2.3, and 3.2.7)
11) "Calculative Methods for the CE Small Break LOCA Evaluation Model," CENPD-137, Supplement 2-P-A, April 1998 (Methodology for 3.1.1.4, 3.2.1, 3.2.3, and 3.2.7)
12) "CESEC-Digital Simulation of a Combustion Engineering Nuclear Steam Supply System,"

December 1981 (Methodology for 3.1.1.1, 3.1.1.2, 3.1.1.4, 3.1.3.1, 3.1.3.6, and 3.2.4.b)

13) "Technical Manual for the CENTS Code," CENPD 282-P-A, February 1991 (Methodology for 3.1.1.1, 3.1.1.2, 3.1.1.4, 3.1.3.1, 3.1.3.6, 3.2.4.b) 4

A2-NE-2004-001 Revision 0

14) "Implementation of ZIRLO Material Cladding in CE Nuclear Power Fuel Assembly Designs,"

CENPD-404-P-A, November 2001 (Modifies CENPD-132-P and CENPD-137-P as methodology for 3.1.1.4, 3.2.1, 3.2.3, and 3.2.7)

15) "Qualification of the Two-Dimensional Transport Code PARAGON," WCAP-16045-P-A, August 2004 (May be used as a replacement for the PHOENIX-P lattice code as methodology for 3.1.1.1, 3.1.1.2, 3.1.1.4, 3.1.3.6, and 3.2.4.b)
16) 'Implementation of Zirconium Diboride Burnable Absorber Coatings in CE Nuclear Power Fuel Assembly Designs," WCAP-16072-P-A, August 2004 (Methodology for 3.1.1.4, 3.2.1, 3.2.3, and 3.2.7)
17) Letter: O.D. Parr (NRC) to F.M. Stern (CE) dated June 13, 1975 (NRC Staff Review of Combustion Engineering ECCS Evaluation Model).

NRC approval for items 4, 5 and 9 methodologies.

18) Letter: 0. D. Parr (NRC) to A.E. Scherer (CE), dated December 9, 1975 (NRC Staff Review of the Proposed Combustion Engineering ECCS Evaluation Model changes). NRC approval for item 6 methodology.
19) Letter: K.Kniel (NRC) to A. E. Scherer (CE), dated September 27, 1977 (Evaluation of Topical Reports CENPD-133, Supplement 3-P and CENPD-137, Supplement 1-P). NRC approval for item 10 methodology.
20) Letter: 2CNA038403, dated March 20, 1984, J.R. Miller (NRC) to J.M. Griffin (AP&L),

"CESEC Code Verification." NRC approval for item 12 methodology.

V. CORE OPERATING LIMITS The cycle-specific operating limits for the specifications listed are presented below.

1) 3/4.1.1.1 - SHUTDOWN MARGIN-Tayp > 200OF The SHUTDOWN MARGIN shall be greater than or equal to 5.0 % Ak/k in Modes 1, 2, 3, and 4.
2) 3/4.1.1.2 - SHUTDOWN MARGIN - Tag,
  • 200OF The SHUTDOWN MARGIN shall be greater than or equal to 5.0% Ak/k in Mode 5.
3) 3.1.1.4-MODERATOR TEMPERATURE COEFFICIENT The Moderator Temperature Coefficient (MTC) shall be in accordance with Figure 1. The Beginning of Cycle (BOC) positive COLR MTC limit line of Figure 1 is from BOC to 125.0 EFPD. From 395.8 EFPD to End of Cycle (EOC) the positive COLR MTC limit line is linear from an MTC of 0.0 E-4 Ak/kIOF at 0% power to an MTC of -1.0 E-4 Ak/k/OF at 100% power which is bounded by the BOC positive MTC limit. Between 125.0 EFPD and 395.8 EFPD the positive MTC limit may be interpolated linearly with burnup.

5

A2-NE-2004-001 Revision 0

4) 3.1.3.1 - CEA POSITION With one or more CEAs trippable but misaligned from any other CEAs in its group by more than the Technical Specification 3.1.3.1 allowed value, the minimum required core power reduction for Modes 1 and 2 is specified in Figure 2.
5) 3.1.3.6 - REGULATING CEA INSERTION LIMITS The regulating CEA groups (Groups 6 & P) shall be limited to the withdrawal and insertion limits shown on Figure 3. Figure 3 assumes that Groups 1 through 5 are at or above the Programmed Insertion Limit.
6) 3/4.2.1 - LINEAR HEAT RATE With COLSS out of service, the linear heat rate shall be maintained < 13.7 kW/ft.
7) 3.2.3 - AZIMUTHAL POWER TILT-TL The measured AZIMUTHAL POWER TILT shall be maintained < 0.03.
8) 3/4.2.4 - DNBR MARGIN The DNBR limit shall be maintained by one of the following methods:

a)

With COLSS in service and neither CEAC operable - Maintain COLSS calculated core power less than or equal to COLSS calculated core power operating limit based on DNBR decreased by 10%.

b) With COLSS out of service and at least one CEAC operable - Operate within the Region of Acceptable Operation shown on Figure 4, using any operable CPC channel.

c) With COLSS out of service and neither CEAC operable - Operate within the Region of Acceptable Operation shown on Figure 5, using any operable CPC channel.

9) 3.2.7 - AXIAL SHAPE INDEX The core average AXIAL SHAPE INDEX (ASI) shall be maintained within the following limits:

a) COLSS IN SERVICE

- 0.27 < ASI < + 0.27 b) COLSS OUT OF SERVICE (CPC)

-0.20< ASI < + 0.20 6

A2-NE-2004-001 Revision 0 VI. LIST OF FIGURES Figure 1 Moderator Temperature Coefficient Figure 2 Required Power Reduction After Inward CEA Deviation Figure 3 CEA Insertion Limits Versus Thermal Power Figure 4 DNBR Margin Operating Limit Based on Core Protection Calculators (COLSS Out of Service, CEAC Operable)

Figure 5 DNBR Margin Operating Limit Based on Core Protection Calculators (COLSS Out of Service, Both CEACs Inoperable) 7

A2-NE-2004-001 Revision 0 FIGURE 1 Moderator Temperature Coefficient (O. 0-50) 11-U nacce; table ROlperating ReCIon 0.00E+00 (20.

132)

(50, 0. 5) (60,

.00)

.- n F -l 4

I

-1.OOE-04 IL.

CD 0) c] -1.50E-04 i

-2.OOE-04 0

I--

-2.50E-04

-3.0OE-04

-3.50E-04

-4.OOE-04 Acc ptabl Ope ratinl Regi n U acce able §peratig Regon I

I

-3.80 E-04 0

10 20 30 40 50 60 70 E

Core Power (% of Rated Thermal Power) 80 90 100 Note:

Per Technical Specification 3.1.1.4.a. and b., the Moderator Temperature Coefficient (MTC) maximum upper design limit shall be less positive than +0.5 x 10i4 Akk/k/F whenever THERMAL POWER is 5 70% of RATED THERMAL POWER and less positive than 0.0 x 104 Ak/k/OF whenever THERMAL POWER is > 70% of RATED THERMAL POWER. Therefore, the actual MTC must be less than the COLR upper limit at zero power. At all other powers, the actual MTC may be equal to the COLR upper limit.

8

A2-NE-2004-001 Revision 0 FIGURE 2 REQUIRED POWER REDUCTION AFTER INWARD CEA DEVIATION*

30 25 IC I-a-

W 20 I'-

C 0

V0 V15 0

.1..

10 E

5 0

0 15 30 45 60 75 90 105 120 Time After Deviation (minutes)

  • When core power is reduced to 60% of rated power per this limit curve, further reduction Is not required 9

A2-NE-2004-001 Revision 0 FIGURE 3 CEA INSERTION LIMITS VERSUS THERMAL POWER 150 135 120 105 c

3, 0

b.r 0

90 75 60 45 30 j GROUP"Pw PDIL i

i Z

i i

i i

i/(74,15 Trnsient Insertion Limit i

i _ __

_ _ _11(6 112.5)

Long TernSmady

/

State Actiom A Ip SHUfTDOWN IMARGIN NOT 1/

l SATiSFED

.iI.........

Shorl Tenn Steady State J

.- ActionsApplyt  ~~ I.:

l..

SHUTDOWN i

MARGN NOT ii i

i SiATISFED

,i

.. _. i _ 7t._.ii_......

~~~~~.... __.. _i_ _ -

._....... i_~~i-'~'

ii 7!

i I

i, I

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

3 I?

e 0

0 0-zo 0.6 23 150 135 120 105 90 75 60 45 30 15 0

15 0

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

Note: Regulating Groups 1 through 5 at or above the Programmed Insertion Limit 10

A2-NE-2004-001 Revision 0 FIGURE 4 DNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATORS ANO-2 Cycle Independent COLSS OOS Limit Lines Minimum One CEAC Operable 3.0 2.9t 2.8t 2.7 2.6t 2.5 2.4t D

N B

R 2.3t ACCEPTABLE OPERATION Any Power Level (0.04, 2.83)

(0.20, 2.83)

(-0.20, 2.58)

ACCEPTABLE OPERATION Power at or above 80%

(-0.09, 2.41)

(0.20, 2.41)

(-0.20, 2.31)

ACCEPTABLE OPERATION Power at or above 90%

(-0.10, 1.99)

~(0.20, 1.99)

(-0.20, 1.94)

UNACCEPTABLE OPERATION Any Power Level 2.21 2.1t 2.01 1.gT 1.8t 1.7t 1.6 -

-0.3

-0.2

-0.1 0.0 CPC Indicated ASI 0.1 0.2 0.3 NOTE:

DNBR greater than that indicated at the top of the figure is acceptable, provided the indicated ASI limits remain between the bounds that are shown for lower DNBR.

11

A2-NE-2004-001 Revision 0 FIGURE 6 DNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATORS ANO-2 Cycle Independent COLSS OOS Limit Both CEACs Inoperable D

N B

R 3.01.

-0.30

-0.20

-0.10 0.00 0.10 0.20 0.30 CPC Indicated ASI NOTE:

DNBR greater than that indicated at the top of the figure is acceptable, provided the indicated ASI limits remain between the bounds that are shown for lower DNBR.

12

Retrieved from "https://kanterella.com/w/index.php?title=2CAN030504,_Cycle_18_Core_Operating_Limits_Report&oldid=5385680"