2CAN081005, Cycle 21 COLR, Revision 1

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Cycle 21 COLR, Revision 1
ML102320598
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 08/20/2010
From: Giles M
Entergy Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
2CAN081005 ANO2-NE-09-00002, Rev 1
Download: ML102320598 (16)
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2CAN081005 August 20, 2010 U. S. Nuclear Regulatory Commission Attn.: Document Control Desk Washington, DC 20555-0001

SUBJECT:

ANO-2 Cycle 21 COLR, Revision 1 Arkansas Nuclear One, Unit 2 Docket No. 50-368 License No. NPF-6

REFERENCES:

1.

Amendment 290 to the ANO-2 Operating License (NRC Letter Dated May 25, 2010, Arkansas Nuclear One - Issuance of Amendment No. 290 RE: License Amendment Request to Revise Technical Specification 6.6.5, Core Operating Limits Report (TAC No. ME1329)

2. NRC Letter to Westinghouse Dated July 1, 2010, Final Safety Evaluation for Westinghouse Electric Company Addendum 1 to Topical Report WCAP-16500-P, Supplement 1, Revision 1, Application of CE Setpoint Methodology for CE 16x16 Next Generation Fuel (NGF)

(TAC No. ME3583)

Dear Sir or Madam:

Arkansas Nuclear One - Unit 2 (ANO-2) Technical Specification (TS) 6.6.5 requires the submittal of the Core Operating Limits Report (COLR), including any mid-cycle revisions or supplements, to be provided upon issuance for each reload cycle to the NRC. Attached is Revision 1 of the ANO-2 Cycle 21 COLR. The revision supports changes in methodology references approved by the NRC in ANO-2 TS Amendment 290 (Reference 1). A methodology is also added reflecting the NRC approval of a revision to an existing methodology (Reference 2). This completes the reporting requirement for the referenced specification.

This submittal contains no commitments.

Entergy Operations, Inc.

1448 S.R. 333 Russellville, AR 72802 Tel 479-858-4619 Mark A. Giles Manager, Licensing Arkansas Nuclear One

2CAN081005 Page 2 of 2 If you have any questions or require additional information, please contact me.

Sincerely, Original signed by Mark A. Giles MAG/dbb

Attachment:

ANO-2 Cycle 21 Core Operating Limits Report (COLR), Revision 1 cc:

Mr. Elmo E. Collins Regional Administrator U. S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 NRC Senior Resident Inspector Arkansas Nuclear One P. O. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Kaly Kalyanam MS O-8B1 One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. Bernard R. Bevill Arkansas Department of Health Radiation Control Section 4815 West Markham Street Slot #30 Little Rock, AR 72205

Attachment To 2CAN081005 ANO-2 CYCLE 21 CORE OPERATING LIMITS REPORT (COLR)

REVISION 1

ANO2-NE-09-00002 Revision 1 1

ENTERGY OPERATIONS ARKANSAS NUCLEAR ONE - UNIT 2 CORE OPERATING LIMITS REPORT FOR CYCLE 21 REVISION 1

ANO2-NE-09-00002 Revision 1 2

CORE OPERATING LIMITS REPORT FOR CYCLE 21 Revision 1 INDEX PAGE I.

INTRODUCTION........................................................................................................ 3 II.

SUMMARY

OF CHANGES......................................................................................... 3 III.

AFFECTED TECHNICAL SPECIFICATIONS............................................................ 4 IV.

APPROVED METHODOLOGIES USED TO DETERMINE LIMITS........................... 4 V.

CORE OPERATING LIMITS....................................................................................... 7 VI.

LIST OF FIGURES..................................................................................................... 8

ANO2-NE-09-00002 Revision 1 3

ARKANSAS NUCLEAR ONE - UNIT 2 CORE OPERATING LIMITS REPORT FOR CYCLE 21 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 21. This is Revision 1 of the Cycle 21 COLR.

II.

SUMMARY

OF CHANGES Listed below are the changes to the COLR from Revision 0 of the Cycle 21 COLR.

Methodologies no longer used to develop cycle dependent core limits were deleted in Section IV.

- The methodology utilizing CESEC was deleted.

The topical number to the reference for the CENTS code was updated from the combustion engineering numbering scheme to the Westinghouse numbering scheme. Also, within the reference for the CENTS code an editorial correction was made due to the omission of a closing parenthesis.

The remaining items were renumbered.

The basis for the changes noted above is Amendment 290 to the Technical Specifications. That amendment allows for the consolidation of methods used in the determination of core operating limits. As such, methods no longer in use were deleted and the remaining items were renumbered.

Added a methodology reflecting the NRC approval of a revision to an existing methodology (WCAP-16500-P).

The NRC approved a revision to WCAP-16500-P. This new approved methodology is being incorporated into the COLR at this time by adding the approved methodology to the renumbered methodologies.

ANO2-NE-09-00002 Revision 1 4

III. AFFECTED TECHNICAL SPECIFICATIONS

1) 3.1.1.1 Shutdown Margin - Tavg > 200°F
2) 3.1.1.2 Shutdown Margin - Tavg 200°F
3) 3.1.1.4 Moderator Temperature Coefficient
4) 3.1.3.1 CEA Position
5) 3.1.3.6 Regulating and Group P 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 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-11596-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 Specifications 3.1.1.1, 3.1.1.2 for Shutdown Margins, 3.1.1.4 for MTC, 3.1.3.6 for Regulating and Group P CEA Insertion Limits; and 3.2.4.b for DNBR Margin)

2)

CE Method for Control Element Assembly Ejection Analysis, CENPD-0190-A, January 1976 (Methodology for Specification 3.1.3.6 for Regulating and Group P CEA Insertion Limits, and 3.2.3 for Azimuthal Power Tilt)

3)

Modified Statistical Combination of Uncertainties, CEN-356(V)-P-A, Revision 01-P-A, May 1988 (Methodology for 3.2.4.c and 3.2.4.d for DNBR Margin, and 3.2.7 for ASI)

4)

Calculative Methods for the CE Large Break LOCA Evaluation Model, CENPD-132-P, August 1974 (Methodology for Specifications 3.1.1.4 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for ASI)

5)

Calculational Methods for the CE Large Break LOCA Evaluation Model, CENPD-132-P, Supplement 1, February 1975 (Methodology for Specifications 3.1.1.4 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for ASI)

ANO2-NE-09-00002 Revision 1 5

6)

Calculational Methods for the CE Large Break LOCA Evaluation Model, CENPD-132-P, Supplement 2-P, July 1975 (Methodology for Specifications 3.1.1.4 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for ASI)

7)

Calculative Methods for the CE Large Break LOCA Evaluation Model for the Analysis of CE and W Designed NSSS, CENPD-132, Supplement 3-P-A, June 1985 (Methodology for Specifications 3.1.1.4 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for ASI)

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 Specifications 3.1.1.4 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for ASI)

9)

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

Improvement to 1999 Large Break LOCA EM Steam Cooling Model for Less Than 1 in/sec Core Reflood, CENPD-132, Supplement 4-P-A, Addendum 1-P and Final Safety Evaluation for Westinghouse Electric Company (Westinghouse) Topical Report (TR)

CENPD-132, Supplement 4-P-A, Addendum 1-P, Calculative Methods for the CE Nuclear Power Large Break LOCA Evaluation Model - Improvement to 1999 Large Break LOCA EM Steam Cooling Model for Less Than 1 in/sec Core Reflood, (Methodology for Specification 3.1.1.4 MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for ASI)

10) Calculative Methods for the CE Small Break LOCA Evaluation Model, CENPD-137-P, August 1974 (Methodology for Specifications 3.1.1.4 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for ASI)
11) Calculative Methods for the CE Small Break LOCA Evaluation Model, CENPD-137, Supplement 1-P, January 1977 (Methodology for Specifications 3.1.1.4 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for ASI)
12) Calculative Methods for the CE Small Break LOCA Evaluation Model, CENPD-137, Supplement 2-P-A, April 1998 (Methodology for Specifications 3.1.1.4 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for ASI)
13) Technical Manual for the CENTS Code, WCAP-15996-P-A, Rev. 1, March 2005 (Methodology for Specifications 3.1.1.1 and 3.1.1.2 for Shutdown Margin, 3.1.1.4 for MTC, 3.1.3.1 for CEA Position, 3.1.3.6 for Regulating and Group P Insertion Limits, and 3.2.4.b for DNBR Margin)
14) Implementation of ZIRLO Material Cladding in CE Nuclear Power Fuel Assembly Designs, CENPD-404-P-A, Revision 0, November 2001 (Modifies CENPD-132-P and CENPD-137-P as methodology for Specifications 3.1.1.4 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for ASI)
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 Specifications 3.1.1.1 and 3.1.1.2 for Shutdown Margins, 3.1.1.4 for MTC, 3.1.3.6 for Regulating and Group P CEA Insertion Limits, and 3.2.4.b for DNBR Margin)

ANO2-NE-09-00002 Revision 1 6

16) Implementation of Zirconium Diboride Burnable Absorber Coatings in CE Nuclear Power Fuel Assembly Designs, WCAP-16072-P-A, Revision 0, August 2004 (Methodology for Specifications 3.1.1.4 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Tilt, and 3.2.7 for ASI)
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: O. 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.

21) CE 16 x 16 Next Generation Fuel Core Reference Report, WCAP-16500-P-A, Revision 0, August 2007 and Final Safety Evaluation for Westinghouse Electric Company (Westinghouse) Topical Report (TR) WCAP-16500-P, Revision 0, CE [Combustion Engineering] 16 x 16 Next Generation [(NGF)] Core Reference Report, (Methodology for Specifications 3.1.1.4 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, 3.2.4.b, 3.2.4.c, and 3.2.4.d for DNBR Margin, and 3.2.7 for ASI)
22) Application of CE Setpoint Methodology for CE 16 x 16 Next Generation Fuel (NGF),

Addendum 1 to WCAP-16500-P, Supplement 1, Revision 1, July 1, 2010, (Methodology for Specifications 3.2.4.b, 3.2.4.c, and 3.2.4.d for DNBR Margin)

23) Optimized ZIRLOTM, WCAP-12610-P-A and CENPD-404-P-A Addendum 1-A, July 2006 (Methodology for Specifications 3.1.1.4 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Tilt, and 3.2.7 for ASI)
24) Westinghouse Correlations WSSV and WSSV-T for Predicting Critical Heat Flux in Rod Bundles with Side-Supported Mixing Vanes, WCAP-16523-P-A, Revision 0, August 2007 and Final Safety Evaluation for Westinghouse Electric Company (Westinghouse) Topical Report (TR), WCAP-16523-P, Westinghouse Correlations WSSV and WSSV-T for Predicting Critical Heat Flux in Rod Bundles with Side-Supported Mixing Vanes, (Methodology for Specifications 3.2.4.b, 3.2.4.c, and 3.2.4.d for DNBR Margin)
25) ABB Critical Heat Flux Correlations for PWR Fuel, CENPD-387-P-A Revision 0, May 2000 (Methodology for Specifications 3.2.4.b, 3.2.4.c, and 3.2.4.d for DNBR Margin and 3.2.7 for ASI)

ANO2-NE-09-00002 Revision 1 7

V.

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

1) 3/4.1.1.1 - SHUTDOWN MARGIN-Tavg > 200°F The SHUTDOWN MARGIN shall be greater than or equal to 5.0 % k/k in Modes 1, 2, 3, and 4.
2) 3/4.1.1.2 - SHUTDOWN MARGIN - Tavg 200°F The SHUTDOWN MARGIN shall be greater than or equal to 5.0% k/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 140.0 EFPD. From 380.0 EFPD to End of Cycle (EOC) the positive COLR MTC limit line is linear from an MTC of 0.0 E-4 k/k/°F at 0% power to an MTC of -1.0 E-4 k/k/°F at 100% power, which is bounded by the BOC positive MTC limit. Between 140.0 EFPD and 380.0 EFPD the positive MTC limit may be interpolated linearly with burnup.
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 and Group P shall be limited to the withdrawal and insertion limits shown on Figure 3. Figure 3 assumes that Groups 1 through 5 are maintained 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-Tq The measured AZIMUTHAL POWER TILT shall be maintained 0.03.

ANO2-NE-09-00002 Revision 1 8

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 + 0.18 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)

ANO2-NE-09-00002 Revision 1 9

FIGURE 1 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 10-4 k/k/°F whenever THERMAL POWER is 70% of RATED THERMAL POWER and less positive than 0.0 x 10-4 k/k/°F 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.

Moderator Temperature Coefficient

-3.80 E-04

-4.00E-04

-3.50E-04

-3.00E-04

-2.50E-04

-2.00E-04

-1.50E-04

-1.00E-04

-5.00E-05 0.00E+00 5.00E-05 0

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

MTC (Delta K/K/Degree F)

Acceptable Operating Region Unacceptable Operating Region (0, 0.50)

(20, 0.32)

(60, 0.00)

(100, -0.20)

(50, 0.05)

Unacceptable Operating Region

ANO2-NE-09-00002 Revision 1 10 FIGURE 2 REQUIRED POWER REDUCTION AFTER INWARD CEA DEVIATION*

  • When core power is reduced to 60% of rated power per this limit curve, further reduction is not required 0

5 10 15 20 25 30 0

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

Minimum Required Power Reduction (% of Rated Power)

(28% @ 120 min.)

ANO2-NE-09-00002 Revision 1 11 FIGURE 3 CEA INSERTION LIMITS VERSUS THERMAL POWER Note: Regulating Groups 1 through 5 at or above Programmed Insertion Limit SHUTDOWN MARGIN NOT SATISFIED (62.5, 0)

(82.5, 60)

(100, 112.5)

Short Term Steady State Actions Apply Long Term Steady State Actions Apply Short Term Steady State Actions Apply Long Term Steady State Actions Apply SHUTDOWN MARGIN NOT SATISFIED SHUTDOWN MARGIN NOT SATISFIED Transient Insertion Limit Transient Insertion Limit GROUP 6 PDIL GROUP P PDIL (74, 135)

(65, 112.5)

(44, 60)

(20, 0)

Power (%)

Power (%)

Group P CEA Position, Inches Withdrawn Group 6 CEA Position, Inches Withdrawn 150 135 120 105 90 75 60 45 30 15 0

150 135 120 105 90 75 60 45 30 15 0

0 10 20 30 40 50 60 70 80 90 100 0

10 20 30 40 50 60 70 80 90 100

ANO2-NE-09-00002 Revision 1 12 FIGURE 4 DNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATORS ANO-2 Cycle Independent COLSS OOS Limit Lines Minimum One CEAC Operable 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.

3.4 3.3 3.2 3.1 3.0 2.9 2.8 2.7 2.6 2.5 2.4 2.3 2.2 2.1 2.0 1.9 1.8 1.7 1.6 CPC Indicated ASI

-0.3

-0.2

-0.1 0.0 0.1 0.2 0.3 UNACCEPTABLE OPERATION Any Power Level ACCEPTABLE OPERATION Power at or above 90%

ACCEPTABLE OPERATION Power at or above 80%

(-0.20, 2.00)

(-0.20, 2.37)

(-0.20, 2.65)

(0.18, 2.06)

(0.18, 2.49)

(0.18, 2.91)

(-0.10, 2.06)

(-0.07, 2.49)

ACCEPTABLE OPERATION Any Power Level DNBR (0.03, 2.91)

ANO2-NE-09-00002 Revision 1 13 FIGURE 5 DNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATORS ANO-2 Cycle Independent COLSS OOS Limit Both CEACs Inoperable 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.

-0.3

-0.2

-0.1 0.0 0.1 0.2 0.3 4.2 4.1 4.0 3.9 3.8 3.7 3.6 3.5 3.4 3.3 3.2 3.1 3.0 DNBR CPC Indicated ASI UNACCEPTABLE OPERATION Any Power Level

(-0.20, 3.29)

(0.18, 3.57)

(-0.01, 3.57)

ACCEPTABLE OPERATION Any Power Level

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