ULNRC-05421, Submittal of Core Operating Limits Report

Submittal of Core Operating Limits Report

ML071640363
Person / Time
Site:	Callaway
Issue date:	06/06/2007
From:	Graessle L AmerenUE
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ULNRC-05421
Download: ML071640363 (22)

Text

AmerenUiE PO Box 620 Callaway Plant Fulton, MO 65251 June 6, 2007 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1I- 13 7 Washington, DC 20555-0001 Ladies and Gentlemen: ULNRC-0542 1 CALLA WAY PLANT DOCKET NUMBER 50-483 CORE OPERATING LIMITS REPORT W~Amereft Attached is the Callaway Plant Cycle 16 Core Operating Limits Report IE (COLR), Revision 1. Revision 1 incorporates changes to the COLR associated ULwith implementation of License Amendment 182 and License Amendment 183.

License Amendment 182 revised TSs 3.1.7, 3.2.1, 3.2.4, and 3.3.1 to allow the use of BEACON instead of the flux mapping system to obtain power distribution measurements in the core. COLR, Revision 1, includes a formula for calculating the uncertainty to be applied to measured Fq(Z).

License Amendment 183 relocated certain cycle-specific core operating limits from the TSs to the COLR, including TS Figure 2. 1.1-1, "Reactor Core Safety Limits"; OTDT parameters in Table 3.3. 1 -1 Note 1; OPDT parameters in Table 3.3. 1-1 Note 2; and the values of pressurizer pressure and RCS average temperature from TS 3.4. 1. COLR, Revision 1, incorporates these changes.

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 Acting Manager, Regulatory Affairs DJW/tdp

Attachment:

Callaway Cycle 16 Core Operating Limits Report, Rev. 1 a subsidiary ofAmeren Corporation

ULNRC-05421 June 6, 2007 Page 2 cc: U.S. Nuclear Regulatory Commission (Original and 1 copy)

Attn: Document Control Desk Mail Stop PI-137 Washington, DC 20555-000 1 Mr. Bruce S. Mallett 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. Jack N. Donohew (2 copies)

Licensing Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 7E1 Washington, DC 20555-2738 Missouri Public Service Commission Governor Office Building 200 Madison Street P0 Box 360 Jefferson City, MO 65 102-0360 Deputy Director Department of Natural Resources P.O. Box 176 Jefferson City, MO 65102

ULNRC -05421 June 6, 2007 Page 3 bcc: C. D. Naslund C. R. Younie D. T. Fitzgerald G. A. Hughes D. E. Shafer (470) (2 copies)

S. L. Gallagher (100)

L. M. Belsky (NSRB)

K. A. Mills J. B. Mclnvale K. R. Bryant D. J. Walker A160.0761 Certrec Corporation 4200 South Hulen, Suite 630 Fort Worth, TX 76109 (Certrec receives ALL attachments as long as they are non-safeguards and public disclosed).

Send the following without attachments:

Ms. Diane M. Hooper Mr. Dennis Buschbaum Supervisor, Licensing TXU Power WCNOC Comanche Peak SES P.O. Box 411 P.O. Box 1002 Burlington, KS 66839 Glen Rose, TX 76043 Mr. Scott Bauer Mr. Stan Ketelsen Regulatory Affairs Manager, Regulatory Services Palo Verde NGS Pacific Gas & Electric P.O. Box 52034, Mail Stop 104/5/536 Mail Station 7636 P.O. Box 56 Phoenix, AZ 85072-2034 Avila Beach, CA 93424 Mr. Scott Head Mr. John O'Neill Supervisor, Licensing Pillsbury Winthrop Shaw Pittman LLP South Texas Project NOC 2300 N. Street N.W.

Mail Code N5014 Washington, DC 20037 P.O. Box 289 Wadsworth, TX 77483

Callaway Cycle 16 Core Operating Limits Report Revision 1 May 2007 Edited by:

M. F. Muenks P. Schueren Approved:

R. Sisk, Manager Fuel Engineering Licensing "Electronically Approved Records Are Authenticated in the Electronic Document Management System" Westinghouse Electric Company LLC P.O. Box 355 Pittsburgh, PA 15230-0355

©2007 Westinghouse Electric Company LLC All Rights Reserved NF-SCP-07-27, Rev. 1 Reviewed by:

Approved by:.

Curve Book Figure 13-1, Rev 47

Callaway Cycle 16 COLR Rev. I Rv 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 (RIS) Instrumentation 3.4.1 RCS Pressure and Temperature Departure from Nucleate Boiling (DNB) Limits 2

Curve Book Figure 13-1, Rev 47

Callaway Cycle 16 COLR Rv Rev. I 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 Mart-in (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/.

2.1.2 The Shutdown Margin prior to blocking Safety Injection below P-1Il in MODES 3 and 4 shall be greater than 0% Ak/ as calculated at 200'F.

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 pcmI0 F (all rods withdrawn, Rated Thermal Power condition).

2.2.3 The MTC 60 ppmn surveillance limit is -45.5 pcm/ 0 F (all rods withdrawn, Rated Thermal Power condition).

3 Curve Book Figure 13-1, Rev 47

Callaway Cycle 16 COLR Rev. I Rv 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 47

Callaway Cycle 16 COLR Rev. 1 Rv mO 22 51 1 1 1 1 1 1 I (28, 225) Li (78, 225) L 00,( U 175 -

H (0,161) 1500 1 11 Y1 , 70 01 ANK C 125 - - - - - -

0 H

W-0 100 - - - - - -

BANK D 75--

- 0z ---- 0z 0

50-7 7 (0,46)1 25 ------ ---

01 1 1 1 1 1 0 10 20 z ýý-

0.2,0) -Z 30 40 s0 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 47

Callaway Cycle 16 COLR Rev. I Rv 2.5 Heat Flux Hot Channel Factor - F0(Z)

(Specification 3,2. 1)

FQRTP FQ(Z) < * (Z for P > 0.5 P

F T F Q(Z) <

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

RATED THERMAL POWER 2.5.1 FQRT P=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. 1.

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 bumnup; 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.

Table A.2 shows the burnup dependent F. penalty factors for Cycle 16. These values shall be used to increase FQ\V(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.

2.5.4 The uncertainty, UFQ, to be applied to measured FQ(Z) shall be calculated by the following UFQ = V U, where:

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

Uý= Engineering uncertainty factor = 1.03 7

Curve Book Figure 13-1, Rev 47

Callaway Cycle 16 COLR Rev. I Rv Table A.1I 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 1.250ý4 1.2504 6.83 1.2158 1.1529 1.1923 1.2583 1.2583 8

Curve Book Figure 13-1, Rev 47

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

Height 150 4000 10000 20000 Bounding (feet) MWD/MTU MWDIMTU MWD/MTU MWDIMTU WWz 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 l.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 9

Curve Book Figure 13-1, Rev 47

Ca~llway Cycle 16 COLR Rev. I Rv Table A.2 F QPenalty Factors as a Function of Cycle Burnup Cycle 16 Burnup Fw(z) Penalty Factor M%

1009 2.06 1180 2.33 1352 2.31 1524 2.26 Note: All cycle burnups not in the range of the above table ýshall 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.

10 Curve Book Figure 13-1, Rev 47

Callaway Cycle 16 COLR Rev. I Rv 1.20 II I I I I I I I I I I II II I II 1I1I 1 I I 1 1 1 1 1 I1 1 1 I I I II II 1.10 II I I II I I I I~I I III II I I I I I II I I I II II I I I I I I I I I III I 1.00U 1(0, 1L.00) 1 H 6, 1. 00) 1

~+~+ (12, II III .925)III I 0.90 0.80 0.70 I

0 0.60 0.50 -f PQ 2.50 Elevation (ft.)

0.0 K(z) 1.00 0.40 -I 2.50 6.0 1.00 2.31 12.0 0.925 III III I II 11111

0.30 0.20 0.10 0.00 I 0 1 2 3 4 5 6 7 8 9 10 11 12 CORE HEIGHT (FEET)

Figure 3 Callaway Cycle 16 K(z) - Normalized FQ(z) as a Function of Core Height Curve Book Figure 13-1, Rev 47

Callaway Cycle 16 COLR Rev- I Rv 2.6 Nuclear Enthalp~y Rise Hot Channel Factor - FA.

(Specification 3.2.2)

T A.N :: FAHR" P [1 + PFAH( -P)]

THERMAL POWER where: P=

R-ATED THERMAL POWER 2.6.1 FaRTP = 1.59 2.6.2 PFAH,= 0.3 2.7 Axial Flux Difference (Specification 3.2.3)

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

12 Curve Book Figure 13-1, Rev 47

Callaway Cycle 16 COLR Rev. 1 Rv 12 11 10 0

0 t

-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 13 Curve Book Figure 13-1, Rev 47

Callaway Cycle 16 COLR Rev.

Rv I 2.8 Reactor Core Safety Limits (Safety Limit 2. 1. 1)

In MODES 1 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.

14 Curve Book Figure 13-1, Rev 47

Callaway Cycle 16 COLR Rev. 1 660-Un 64D-620 E60pa POWER 5610 Curve Book Figure 13-1, Rev 47

Callaway Cycle 16 COLR Rv Rev. I 2.9 Reactor Trip System Overtemperature AT Settoint Parameter Values (Specification 3.3. 1)

Value Overtemperature AT reactor trip setpoint K,= 1.1950 Overtemperature AT reactor trip setpoint Tavg coefficient K(2 = 0.0251I/OF Overtemperature AT reactor trip setpoint pressure coefficient K(3= 0.061l16/psig Nominal Tavg at RTP T' < 585.3 OF Nominal RCS operating pressure P' = 2235 psig Measured RCS AT lead/lag time constants c > 8 sec C2< 3 sec Measured RCS AT lag time constant -3=0 sec Measured RCS average temperature lead/lag time constants t 4 >28 sec t 5 <4 sec Measured RCS average temperature lag time constant U6= 0 sec f, (AI) =-0.0325 {21 % + (q, - qb)} when (qt - qb) < -21 % RTP 0 when -21 %RTP < (qt - qb) < 8% RTP 0.02973 {(qt -qb) - 8 when (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.

16 Curve Book Figure 13-1, Rev 47

Callaway Cycle 16 COLR Rev.

Rv I 2.10 Reactor Trip System Overpower AT Setpoint Parameter Values (Specification 3.3. 1)

Parameter Value Overpower AT reactor trip setpoint K(4= 1.1073 Overpower AT reactor trip setpoint Tag rate/lag coefficient K(5 = 0.02/'F for increasing Tavg

=0/ 0 17 for decreasing Tavg Overpower AT reactor trip setpoint Tayvg heatup, coefficient K6 = 0.00 15/'F for T> T" 0

= 0/ 17 for T <T" Nominal Tavg at RTP T" < 585.3 0F Measured RCS AT lead/lag time constants ',> 8 sec T2<3 sec Measured RCS AT lag time constant T3= 0 sec, Measured RCS average temperature lag time constant T6= 0 sec Measured RCS average temperature rate/lag time constant U7 > 10 sec f2(AI) = 0 for all Al.

2.11 RCS Pressure and Temn~erature Departure from Nucleate Boiling (DNB) Limits (Specification 3.4. 1)

Parameter Indicated Value Pressurizer pressure > 2223 psig RCS average temperature < 590.1 OF 17 Curve Book Figure 13-1, Rev 47

Callaway Cycle 16 COLR Rv Rev. I 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:

1. 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 lA, "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- 1 021 6-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-102667'he 1981 Version of the Westinghouse ECCS Evaluation Model Using the BASH Code."'

WCAP-1I0266-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 1 to WCAP-10266, BASH Power Shape Sensitivity Studies."

WCAP-1I0266-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.

18 Curve Book Figure 13-1, Rev 47

Callaway Cycle 16 COLR Rev.

Rv I NRC Safety Evaluation Reports dated July 1, 1991, "Acceptance for Referencing of Topical Report WCAP- 126 10, 'VANTAGE+ Fuel Assembly Reference Core Report' (TAC NO. 77258)."

NRC Safety Evaluation Report dated September 15, 1994, "Acceptance for Referencing of Topical Report WCAP- 126 10, 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- 11397, "Revised Thermal Design Procedure."

6. WCAP-14565-P-A, "VIPRE-Ol 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-OlI Modeling and Qualification for Pressurized Water Reactor Non-LOCA Thermal/Hydraulic Safety Analysis' (TAC No. M98666)."

7. WCAP- 108511-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-1 085 1, 'Improved Fuel Performance Models for Westinghouse Fuel Rod Design and Safety Evaluations."'

8. WCAP- 15063 -P-A, Revision 1, with Errata, "Westinghouse Improved 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 1, '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 Ev aluation 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 WCAIP 10966-NP."

11. WCAP-l 1596-P-A, "Qualification of the Phoenix-P/ANC Nuclear Design System for, 19 Curve Book Figure 13-1, Rev 47

Callaway Cycle 16 COLR Rev.

Rv I Pressurized Water Reactor Cores," June 1988.

NRC Safety Evaluation Report dated May 17, 198 8, "Acceptance for Referencing of the Westinghouse Topical Report WCAP- 11596 - Qualification of the Phoenix-P/ANC Nuclear Design System for Pressurized Water Reactor Cores."

12. WCAP- 13524-P-A, Revision I1-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-1 3524 and WCAP-1 3524, Revision 1, '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)"

20 Curve Book Figure 13-1, Rev 47