ULNRC-05530, Core Operating Limits Report, Revision 2

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Core Operating Limits Report, Revision 2
ML082140283
Person / Time
Site: Callaway Ameren icon.png
Issue date: 07/24/2008
From: Graessle L
AmerenUE, Union Electric Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
ULNRC-05530
Download: ML082140283 (25)
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Text

AmerenUE P0 Box 620 Callaway Plant Fulton, MO 65251 July 24, 2008 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop P1-137 Washington, DC 20555-0001 ULNRC-05530 wd1Ameref/ Ladies and Gentlemen:

DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT 1 UNION ELECTRIC CO.

FACILITY OPERATING LICENSE NPF-30 CORE OPERATING LIMITS REPORT Attached is the Callaway Plant Cycle 16 Core Operating Limits Report (COLR),

Revision 2. Revision 2 incorporates changes to the COLR to address the Westinghouse Technical Bulletin TB-08-4, "FQ Surveillance at Part Powers". The Bulletin provides notification that the current tools and guidance used for conducting technical specification surveillance measurements of transient heat flux peaking factors at reduced power conditions may be non-conservative. The Bulletin states that when performing transient FQ surveillances at reduced power conditions, it is necessary to correct both the cycle specific core operating limits and the burn-up and axial dependent transient penalty factors (W(z)'s) at the time of measurement.

The specific guidance for conducting the transient FQ measurement is provided in the COLR Section 2.5. Past COLR revisions addressed the adjustment of the limits, but did not address the adjustment of the W(z)'s. Consequently the COLR has been revised to correct any deficiency.

Callaway has reviewed the results of FQ surveillances for recent cycles and determined that in all cases the plant operated within the bounds of the analysis. One case in cycle 16 was identified in which the measured FQ, when adjusted as required by the Bulletin, would have slightly exceeded the limit (by 0.08%). Exceeding the limit by this amount would not have resulted in exceeding the core peaking factor limits. Callaway Technical Specifications require reducing both the positive and negative axial flux difference (AFD) limits by > 1% for each 1% that the transient FQ limit is exceeded. This ensures that, even if a transient occurred, the core peaking factor limits are not exceeded. Callaway Plant operates to AFD limits that are more A od a subsidiary of Ameren Corporation

ULNRC-05530 July 24, 2008 Page 2 conservative than those specified in the COLR and used in the safety analysis. The conservatism is greater than the margin by which the transient FQ limit would have been exceeded.

This report is provided to the NRC Staff for information. It has been prepared in accordance with the requirements of Technical Specification 5.6.5.d.

If you have any questions concerning this report, please contact us.

Very truly yours, Luke H. Graessle Manager, Regulatory Affairs DJW/nls

Attachment:

Callaway Cycle 16 Core Operating Limits Report, Revision 2

ULNRC-05530 July 24, 2008 Page 3 cc:

U.S. Nuclear Regulatory Commission (Original and 1 copy)

Attn: Document Control Desk Mail Stop P1-137 Washington, DC 20555-0001 Mr. Elmo E. Collins, Jr.

Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Mr. Mohan C. Thadani (2 copies)

Licensing Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop O-8G14 Washington, DC 20555-2738

ULNRC-05530 July 24, 2008 Page 4 Index and send hardcopy to QA File A160.0761 Hardcopy:

Certrec Corporation 4200 South Hulen, Suite 630 Fort Worth, TX 76109 (Certrec receives ALL attachments as long as they are non-safeguards and may be publicly disclosed.)

Electronic distribution for the following can be made via Responses and Reports ULNRC Distribution:

A. C. Heflin F. M. Diya T. E. Herrmann S. M. Maglio T. B. Elwood L. H. Graessle S. L. Gallagher L. M. Belsky (NSRB)

Mr. Ron Reynolds, Director (SEMA)

Mr. Edward Gray, Senior REP Planner (SEMA)

Mr. John Campbell, REP Planner (SEMA)

Ms. Diane M. Hooper (WCNOC)

Mr. Dennis Buschbaum (TXU)

Mr. Scott Bauer (Palo Verde)

Mr. Stan Ketelsen (PG&E)

Mr. Scott Head (STP)

Mr. John O'Neill (Pillsbury Winthrop Shaw Pittman LLP)

Missouri Public Service Commission Mr. Floyd Gilzow (DNR)

Westinghouse Non-Proprietary Class 3 Callaway Cycle 16 Core Operating Limits Report Revision 2 July 2008 Edited by:

G. E. Hauck P. Schueren Approved:

T. Rodack, Director Quality and Licensing Programs "Electronically Approved Records Are Authenticated in the Electronic Document Management System" Westinghouse Electric Company LLC P.O. Box 355 Pittsburgh, PA 15230-0355 C2008 Westinghouse Electric Company LLC All Rights Reserved NF-SCP-07-27, Rev. 2 Reviewed by:

Approved by:

52Q Lt i7.),3L

-7I 3z>

Curve Book Figure 13-1, Rev 48

Callaway Cycle 16 COLR Rev. 2 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Callaway Plant Cycle 16 has been prepared in accordance with the requirements of Technical Specification 5.6.5.

The Core Operating Limits affecting the following Technical Specifications are included in this report.

3.1.1, 3.1.4, 3.1.5, 3.1.6, 3.1.8 Shutdown Margin 3.1.3 Moderator Temperature Coefficient 3.1.5 Shutdown Bank Insertion Limits 3.1.6 Control Bank Insertion Limits 3.2.1 Heat Flux Hot Channel Factor 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor 3.2.3 Axial Flux Difference 2.1.1 Reactor Core Safety Limits (SLs) 3.3.1 Reactor Trip System (RTS) Instrumentation 3.4.1 RCS Pressure and Temperature Departure friom Nucleate Boiling (DNB) Limits 2

Curve Book Figure 13-1, Rev 48

Callaway Cycle 16 COLR Rev. 2 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the subsections which follow.

These limits have been developed using the NRC-approved methodologies specified in Technical Specification 5.6.5.

2.1 Shutdown Margin '

(Specifications 3.1.1, 3.1.4, 3.1.5, 3.1.6, and 3.1.8) 2.1.1 The Shutdown Margin in MODES 1-4 shall be greater than or equal to 1.3% Ak/k.

2.1.2 The Shutdown Margin prior to blocking Safety Injection below P-Il in MODES 3 and 4 shall be greater than 0% Ak/k as calculated at 2007F.

2.1.3 The Shutdown Margin in MODE 5 shall be greater than or equal to 1.0% Ak/k.

2.2 Moderator Temperature Coefficient (Specification 3.1.3) 2.2.1 The Moderator Temperature Coefficient shall be less positive than the limits shown in Figure 1. These limits shall be referred to as upper limit.

The Moderator Temperature Coefficient shall be less negative than -47.9 pcm/°F.

This limit shall be referred to as the lower limit.

2.2.2 The MTC 300 ppm surveillance limit is -40.4 pcm/0 F (all rods withdrawn, Rated Thermal Power condition).

2.2.3 The MTC 60 ppm surveillance limit is -45.5 pci-/'F (all rods withdrawn, Rated Thermal Power condition).

3 Curve Book Figure 13-1, Rev 48

Callaway Cycle 16 COLR Rev. 2 H

rT4 H

r~x, 0U E-1 0

0 E-7 6

UNACCEPTABLE OPERATION

-T I

I I 1T 1

~~(70%,

5.0o) 3 0

1 1

1 1

0 10 20 30 40 50 60 70 80 90 10 PERCENT OF RATED THERMAL POWER 0

Figure 1 Callaway Cycle 16 Moderator Temperature Coefficient Versus Power Level 4

Curve Book Figure 13-1, Rev 48

Callaway Cycle 16 COLR Rev. 2 2.3 Shutdown Bank Insertion Limits (Specification 3.1.5)

The shutdown banks shall be withdrawn to at least 225 steps.

2.4 Control Bank Insertion Limits (Specification 3.1.6) 2.4.1 Control Bank insertion limits are specified by Figure 2.

2.4.2 Control Bank withdrawal sequence is A-B-C-D.

The insertion sequence is the reverse of the withdrawal sequence.

2.4.3 The difference between each sequential Control Bank position is 115 steps when not fully inserted and not fully withdrawn.

5 Curve Book Figure 13-1, Rev 48

Callaway Cycle 16 COLR Rev. 2 225_

(28, 225) 4 (78, 225)k I

200 ------

BANK B PI H

0 H

0 4

0 1751

((1,0116)

  • 1 I n i

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71117-0 10 20 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER Figure 2 Callaway Cycle 16 Rod Bank Insertion Limits Versus Rated Thermal Power - Four Loop Operation 6

Curve Book Figure 13-1, Rev 48

Callaway Cycle 16 COLR Rev. 2 2.5 Heat Flux Hot Channel Factor - FQ(Z)

(Specification 3.2.1)

FQ~r FQ(Z) <

F

  • K(Z) for P > 0.5 P

F RTP FQ FQ(Z) < -*

K(Z) for P < 0.5 0.5 THERMAL POWER where:

P =

RATED THERMAL POWER 2.5.1 F RQP 2.50.

2.5.2 K(Z) is provided in Figure 3.

2.5.3 The W(z) functions that are to be used in Technical Specification 3.2.1 and Surveillance Requirement 3.2.1.2 for determining FQW(z) are shown in Table A.I.

The W(z) values have been determined for several burnups up to 20000 MWD/MTU in Cycle 16. This permits determination of W(z) at any cycle burnup up to 20000 MWD/MTU through the use of three point interpolation. For cycle burnups greater than 20000 MWD/MTU, use of 20000 MWD/MTU W(z) values without interpolation or extrapolation is conservative.

The W(z) values were determined assuming Cycle 16 operates with RAOC strategy. Also included is a W(z) function that bounds the W(z) values for all Cycle 16 burnups. Use of the bounding W(z) values will be conservative for any Cycle 16 burnup; however, additional margin may be gained by using the burnup dependent W(z) values.

The W(z) values are provided for 73 axial points within the core height boundaries of 0 and 12 feet at intervals of 0.17 feet.

The W(z) values are generated assuming that they will be used for a full power surveillance. When a part power surveillance is performed, the W(z) values should be multiplied by the factor I/P, when P is > 0.5. When P is < 0.5, the W(z) values should be multiplied by the factor 11(0.5), or 2.0.

This is consistent with the adjustment in the F0(z) limit at part power conditions.

Table A.2 shows the burnup dependent FQ penalty factors for Cycle 16. These values shall be used to increase F W(z) when required by Technical Specification Surveillance Requirement 3.2.1.2. A 2% penalty factor should be used at all cycle burnups that are outside the range of Table A.2.

7 Curve Book Figure 13-1, Rev 48

Callaway Cycle 16 COLR Rev. 2 2.5.4 The uncertainty, UFQ, to be applied to measured FQ(Z) shall be calculated by the following UFQ = U

  • Uo where:

U,. = Base FQ measurement uncertainty 1.05 when PDMS is inoperable (Uq, is defined by PDMS when OPERABLE)

U= Engineering uncertainty factor 1.03 8

Curve Book Figure 13-1, Rev 48

Callaway Cycle 16 COLR Rev. 2 Table A.1 W(z) versus Core Height (Top and Bottom 6% Excluded)

Height 150 4000 10000 20000 Bounding (feet)

MWD/MTU MWD/MTU MWD/MTU MWD/MTU W(z) 0.00 (bottom) 1.0000 1.0000 1.0000 1.0000 1.0000 0.17 1.0000 1.0000 1.0000 1.0000 1.0000 0.33 1.0000 1.0000 1.0000 1.0000 1.0000 0.50 1.0000 1.0000 1.0000 1.0000 1.0000 0.67 1.0000 1.0000 1.0000 1.0000 1.0000 0.83 1.3934 1.4732 1.4016 1.3370 1.4732 1.00 1.3853 1.4618 1.3944 1.3324 1.4618 1.17 1.3730 1.4462 1.3835 1.3244 1.4462 1.33 1.3588 1.4281 1.3704 1.3144 1.4281 1.50 1.3438 1.4084 1.3559 1.3039 1.4084 1.67 1.3284 1.3877 1.3405 1.2930 1.3878 1.83 1.3122 1.3662 1.3244 1.2817 1.3662 2.00 1.2951 1.3436 1.3076 1.2699 1.3436 2.17 1.2774 1.3202.

1.2904 1.2578 1.3202 2.33 1.2594 1.2965 1.2733 1.2455 1.2967 2.50 1.2412 1.2730 1.2568 1.2332 1.2732 2.67 1.2240 1.2488 1.2426 1.2203 1.2509 2.83 1.2093 1.2253 1.2316 1.2072 1.2327 3.00 1.1969 1.2105 1.2225 1.1985 1.2225 3.17 1.1886 1.2022 1.2145 1.1949 1.2146 3.33 1.1859 1.1936 1.2071 1.1936 1.2084 3.50 1.1833 1.1867 1.2008 1.1936 1.2030 3.67 1.1797 1.1821 1.1952 1.1944 1.1987 3.83 1.1771 1.1788 1.1896 1.1998 1.2005 4.00 1.1752 1.1752 1.1834 1.2052 1.2052 4.17 1.1732 1.1709 1.1768 1.2091 1.2091 4.33 1.1706 1.1662 1.1705 1.2121 1.2121 4.50 1.1675 1.1610 1.1640 1.2143 1.2143 4.67 1.1639 1.1552 1.1573 1.2152 1.2152 4.83 1.1596 1.1490 1.1508 1.2150 1.2150 5.00 1.1552 1.1421 1.1439

.1.2136 1.2136 5.17 1.1495 1.1349 1.1366 1.2108 1.2108 5.33 1.1425 1.1273 1.1289 1.2065 1.2065 5.50 1.1412 1.1182 1.1198 1.2025 1.2025 5.67 1.1457 1.1101 1.1134 1.2015 1.2015 5.83 1.1505 1.1086 1.1178 1.2059 1.2059 6.00 1.1588 1.1088 1.1267 1.2145 1.2145 6.17 1.1709 1.1129 1.1420 1.2247 1.2247 6.33 1.1837 1.1213 1.1562 1.2340 1.2340 6.50 1.1958 1.1315 1.1693 1.2424 1.2424 6.67 1.2065 1.1420 1.1815 1.2504 1.2504 6.83 1.2158 1.1529 1.1923 1.2583 1.2583 9

Curve Book Figure 13-1, Rev 48

Callaway Cycle 16 COLR Rev. 2 Table A. 1 W(z) versus Core Height (Top and Bottom 6% Excluded)

Height 150 4000 10000 20000 Bounding (feet)

MWD/MTU MWD/MTU MWD/MTU MWD/MTU W(z) 7.00 1.2239 1.1643 1.2019 1.2656 1.2656 7.17 1.2301 1.1759 1.2100 1.2714 1.2714 7.33 1.2339 1.1874 1.2160 1.2754 1.2754 7.50 1.2387 1.1981 1.2220 1.2777 1.2777 7.67 1.2447 1.2079 1.2283 1.2782 1.2782 7.83 1.2489 1.2168 1.2330 1.2770 1.2773 8.00 1.2540 1.2237 1.2378 1.2739 1.2739 8.17 1.2617 1.2304 1.2439 1.2691 1.2691 8.33 1.2703 1.2410 1.2500 1.2630 1.2715 8.50 1.2763 1.2517 1.2550 1.2540 1.2763 8.67 1.2797 1.2606 1.2584 1.2448 1.2797 8.83 1.2854 1.2708 1.2608 1.2438 1.2858 9.00 1.2946 1.2800 1.2603 1.2449 1.2955 9.17 1.3059 1.2883 1.2571 1.2502 1.3065 9.33 1.3159 1.3007 1.2572 1.2580 1.3178 9.50 1.3218 1.3167 1.2605 1.2633 1.3273 9.67 1.3254 1.3335 1.2719 1.2679 1.3350 9.83 1.3343 1.3484 1.2818 1.2831 1.3484 10.00 1.3486 1.3690 1.2906 1.3017 1.3692 10.17 1.3669 1.3982 1.2994 1.3172 1.3982 10.33 1.3877 1.4279 1.3078 1.3318 1.4279 10.50 1.4104 1.4550 1.3195 1.3459 1.4550 10.67 1.4333 1.4782 1.3351 1.3590 1.4782 10.83 1.4540 1.4975 1.3494 1.3700 1.4975 11.00 1.4690 1.5123 1.3597 1.3770 1.5123 11.17 1.4723 1.5199 1.3651 1.3763 1.5199 11.33 1.0000 1.0000 1.0000 1.0000 1.0000 11.50 1.0000 1.0000 1.0000 1.0000 1.0000 11.67 1.0000 1.0000 1.0000 1.0000 1.0000 11.83 1.0000 1.0000 1.0000 1.0000 1.0000 12.00 (top) 1.0000 1.0000 1.0000 1.0000 1.0000 10 Curve Book Figure 13-1, Rev 48

Callaway Cycle 16 COLR Rev. 2 Table A.2

  • FQ Penalty Factors as a Function of Cycle Burnup Cycle 16 Burnup 1009 1180 1352 1524 FoW(z) Penalty Factor (%)

2.06 2.33 2.31 2.26 Note:

All cycle burnups not in the range of the above table shall use a 2.0% penalty factor for compliance with Surveillance Requirement 3.2.1.2.

For values of burnup between two of those listed in the first column, the greater of the two corresponding penalty factors shall be used for compliance with Surveillance Requirement 3.2.1.2.

11 Curve Book Figure 13-1, Rev 48

Callaway Cycle 16 COLR Rev. 2 N

0l r:i N

H U

N 1.20 1.10 1.00 0.90 0.80 0.70 0.60 0.50 0.40 0.30 0.20 0.10 0.00 I

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K(z) 2.50 0.0 1.00 2.50 6.0 1.00 2.32.

12.0 0.925 I

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I, 0123456789101112 CORE HEIGHT (FEET)

Figure 3 Callaway Cycle 16 K(z) - Normalized FQ(z) as a Function of Core Height 12 Curve Book Figure 13-1, Rev 48

Callaway Cycle 16 COLR Rev. 2 2.6 Nuclear Enthalpy Rise Hot Channel Factor - FAH" (Specification 3.2.2)

F,, < F,,RT [I + PFAH(l-P)]

THERMAL POWER where:

P =

RATED THERMAL POWER 2.6.1 2.6.2 FH

= 1.59 PFAH = 0.3 2.7 Axial Flux Difference (Specification 3.2.3)

The Axial Flux Difference (AFD) Limits are provided in Figure 4.

13 Curve Book Figure 13-1, Rev 48

Callaway Cycle 16 COLR Rev. 2 0

0 E-z 120

(-17, 10%

(+13, 100%)

1 0 0

,iI I I Il 1:i UNACCEPTABLE UNACCEPTABLE go0 OPERATION OPERATION 80 ii ACCEPTA BLE 7 0 i

PERATION fil 50I

-- (-30, 50%)

(+26, 510%.)

40 -

f I

II 20 10 0 11

-50

-40

-30

-20

-10 0

10 20 30 40 50 AXIAL FLUX DIFFERENCE

(% DELTA-I)

Figure 4 Callaway Cycle 16 Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC 14 Curve Book Figure 13-1, Rev 48

Callaway Cycle 16 COLR Rev. 2 2.8 Reactor Core Safety Limits (Safety Limit 2.1. 1)

In MODES I and 2, the combination of THERMAL POWER,. Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits in Figure 5.

15 Curve Book Figure 13-1, Rev 48

Callaway Cycle 16 COLR Rev. 2 680 660 640 620 C-)

600 580 560 FRACTION OF RATED THERMAL POWER Figure 5 Callaway Cycle 16 Reactor Core Safety Limits 16 Curve Book Figure 13-1, Rev 48

Callaway Cycle 16 COLR Rev. 2 2.9 Reactor Trip System Overtemperature AT Setpoint Parameter Values (Specification 3.3.1)

Parameter Overtemperature AT reactor trip setpoint Overtemperature AT reactor trip setpoint Tavg coefficient Overtemperature AT reactor trip setpoint pressure coefficient Nominal Tavg at RTP Nominal RCS operating pressure Measured RCS AT lead/lag time constants Measured RCS AT lag time constant Measured RCS average temperature lead/lag time constants Measured RCS average temperature lag time constant fl(AI) = -0.0325 {21% + (q, - qb)}

when 0

when 0.02973 {(q, - qb) - 8%}

when Value K, = 1.1950 K7 = 0.0251/OF K3 = 0.001 16/psig T' < 585.3 OF P'= 2235 psig T > 8 sec

-_ < 3 sec T3 = 0 sec t4 > 28 sec t5 < 4 sec

,r6 = 0 sec (q, - qb) < -21% RTP

-21% RTP < (q, - qb) < 8% RTP (q, - qb) > 8% RTP Where, q, and qb are percent RTP in the upper and lower halves of the core, respectively, and q, + qb is the total THERMAL POWER in percent RTP.

17 Curve Book Figure 13-1, Rev 48

Callaway Cycle 16 COLR Rev. 2 2.10 Reactor Trip System Overpower AT Setpoint Parameter Values (Specification 3.3.1)

Parameter Overpower AT reactor trip setpoint Overpower AT reactor trip setpoint Tavg rate/lag coefficient Overpower AT reactor trip setpoint Tav9 heatup coefficient Nominal T., at RTP Measured RCS AT lead/lag time constants Measured RCS AT lag time constant Measured RCS average temperature lag time constant Measured RCS average temperature rate/lag time constant f-(AI) = 0 for all Al.

Value K 4 = 1.1073 K5 = 0.02/°F for increasing T.vg

= 0/1F for decreasing Tvg K6.= 0.0015/0 F for T > T"

= 0/0F for T < T" T" < 585.3 0 F 11 > 8 sec T2 < 3 sec T- = 0 sec T6 = 0 sec

>7

> 10 sec 2.11 RCS Pressure and Temperature Departure from Nucleate Boiling (DNB) Limits (Specification 3.4. 1 )

Parameter Pressurizer pressure RCS average temperature Indicated Value

> 2223 psig

< 590.1 OF 18 Curve Book Figure 13-1, Rev 48

Callaway Cycle 16 COLR Rev. 2 APPENDIX A Approved Analytical Methods for Determining Core Operating Limits The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

I WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.

NRC letter dated May 28, 1985, "Acceptance for Referencing of Licensing Topical Report WCAP-9272(P)/9273(NP), "Westinghouse Reload Safety Evaluation Methodology"."

2.

WCAP-10216-P-A, Revision I A, "Relaxation of Constant Axial Offset Control - FQ Surveillance Technical Specification," February 1994.

NRC Safety Evaluation Report dated November 26, 1993, "Acceptance for Referencing of Revised Version of Licensing Topical Report WCAP-10216-P, Rev. 1, Relaxation of Constant Axial Offset Control - FQ Surveillance Technical Specification" (TAC No. M88206).

3.

WCAP-10266-P-A, Revision 2, "The 1981 Version of the Westinghouse ECCS Evaluation Model Using the BASH Code," March 1987.

NRC letter dated November 13, 1986, "Acceptance for Referencing of Licensing Topical Report WCAP-10266 'The 1981 Version of the Westinghouse ECCS Evaluation Model Using the BASH Code."'

WCAP-10266-P-A, Addendum 1, Revision 2, "The 1981 Version of the Westinghouse ECCS Evaluation Model Using the BASH Code Addendum 1: Power Shape Sensitivity Studies," December 1987.

NRC letter dated September 15, 1987, "Acceptance for Referencing of Addendum I to WCAP-10266, BASH Power Shape Sensitivity Studies."

WCAP-10266-P-A, Addendum 2, Revision 2, "The 1981 Version of the Westinghouse ECCS Evaluation Model Using the BASH Code Addendum 2: BASH Methodology Improvements and Reliability Enhancements," May 1988.

NRC letter dated January 20, 1988, "Acceptance for Referencing Topical Report Addendum 2 to WCAP-10266, Revision 2, "BASH Methodology Improvements and Reliability Enhancements."

4.

WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Reference Core Report," April 1995.

19 Curve Book Figure 13-1, Rev 48

Callaway Cycle 16 COLR Rev. 2 NRC Safety Evaluation Reports dated July 1, 1991, "Acceptance for Referencing of Topical Report WCAP-12610, 'VANTAGE+ Fuel Assembly Reference Core Report' (TAC NO. 77258)."

NRC Safety Evaluation Report dated September 15, 1994, "Acceptance for Referencing of Topical Report WCAP-12610, Appendix B, Addendum 1, 'Extended Burnup Fuel Design Methodology and ZIRLO Fuel Performance Models' (TAC NO. M86416)."

5.

WCAP-1 1397-P-A, "Revised Thermal Design Procedure," April 1989.

NRC Safety Evaluation Report dated January 17, 1989, "Acceptance for Referencing of Licensing Topical Report WCAP-1 1397, "Revised Thermal Design Procedure."

6.

WCAP-14565-P-A, "VIPRE-01 Modeling and Qualification for Pressurized Water Reactor Non-LOCA Thermal-Hydraulic Safety Analysis," October 1999.

NRC letter dated January 19, 1999, "Acceptance for Referencing of Licensing Topical Report WCAP-14565, 'VIPRE-01 Modeling and Qualification for Pressurized Water Reactor Non-LOCA Thermal/Hydraulic Safety Analysis' (TAC No. M98666)."

7.

WCAP-1 0851-P-A, "Improved Fuel Performance Models for Westinghouse Fuel Rod Design and Safety Evaluations," August 1988.

NRC letter dated May 9, 1988, "Westinghouse Topical Report WCAP-10851, 'Improved Fuel Performance Models for Westinghouse Fuel Rod Design and Safety Evaluations."'

8.

WCAP-I 5063-P-A, Revision 1, with Errata, "Westinghouse mnproved Performance Analysis and Design Model (PAD 4.0)," July 2000.

NRC letter dated April 24, 2000, "Safety Evaluation Related to Topical Report WCAP-15063, Revision I, 'Westinghouse Improved Performance Analysis and Design Model (PAD 4.0)' (TAC NO. MA2086)."

9.

WCAP-8745-P-A, "Design Bases for the Thermal Overpower AT and Thermal Overtemperature AT Trip Functions," September 1986.

NRC Safety Evaluation Report dated April 17, 1986, "Acceptance for Referencing of Licensing Topical Report WCAP-8745(P)/8746(NP), 'Design Bases for the Thermal Overpower and Thermal Overtemperature AT Trip Functions."'

10.

WCAP-10965-P-A, "ANC: A Westinghouse Advanced Nodal Computer Code," September 1986.

NRC letter dated June 23, 1986, "Acceptance for Referencing of Topical Report WCAP 10965-P and WCAP 10966-NP."

11.

WCAP-1 1596-P-A, "Qualification of the Phoenix-P/ANC Nuclear Design System for 20 Curve Book Figure 13-1, Rev 48

Callaway Cycle 16 COLR Rev. 2 Pressurized Water Reactor Cores," June 1988.

NRC Safety Evaluation Report dated May 17, 1988, "Acceptance for Referencing of the Westinghouse Topical Report WCAP-1 1596 - Qualification of the Phoenix-P/ANC Nuclear Design System for Pressurized Water Reactor Cores."

12.

WCAP-1 3524-P-A, Revision 1-A, "APOLLO: A One Dimensional Neutron Diffusion Theory Program," September 1997.

NRC letter dated June 9, 1997, "Acceptance for Referencing of Licensing Topical Reports WCAP-l 3524 and WCAP-13524, Revision ], 'APOLLO - A One-Dimensional Neutron Diffusion Theory Program."'

13.

WCAP-12472-P-A, ""BEACON Core Monitoring and Operations Support System,"

August 1994.

NRC letter dated February 16, 1994, "ACCEPTANCE FOR REFERENCING OF LICENSING TOPICAL REPORT WCAP-12472-P, 'BEACON: CORE MONITORING AND OPERATIONS SUPPORT SYSTEM' (TAC NO. M80078)"

21 Curve Book Figure 13-1, Rev 48

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