ULNRC-05632, Core Operating Limits Report, Cycle 17, Revision 1

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Core Operating Limits Report, Cycle 17, Revision 1
ML091470688
Person / Time
Site: Callaway Ameren icon.png
Issue date: 05/20/2009
From: Sandbothe S
AmerenUE, Union Electric Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
ULNRC-05632
Download: ML091470688 (24)
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Text

Union Electric PO Box 620 Callaway Plant Fulton, MO 65251 May 20, 2009 ULNRC-05632 u.s. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Ladies and Gentlemen:

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

FACILITY OPERATING LICENSE NPF-30 CORE OPERATING LIMITS REPORT

Reference:

ULNRC-05561, dated November 12, 2008 Attached is the Callaway Plant Cycle 17 Core Operating Limits Report (COLR), Revision 1. Revision 1 provides the COLR for use after implementation of revised setpoints from the Margin Recovery Program. Note that Revision 0 COLR was transmitted to NRC via the referenced letter. Revision 0 COLR was for use prior to implementation of revised setpoints from the Margin Recovery Program. The Revision 1 COLR report is provided to the NRC Staff for information. It has been prepared in accordance with the requirements of Technical Specification 5.6.5.

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

s~~~

Scott Sandbothe Manager, Regulatory Affairs DJW/nls

Attachment:

Callaway Cycle 17 Core Operating Limits Report, Rev. 1 a subsidiary of Ameren Corporation

VLNRC-05632 May 20, 2009 Page 2 cc: Mr. Elmo E. Collins, Jf.

Regional Administrator US. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 Senior Resident Inspector Callaway Resident Office US. 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 0-8G14 Washington, DC 20555-2738 Deputy Director Department of Natural Resources P.O. Box 176 Jefferson City, MO 65102

ULNRC-05632 May 20, 2009 Page 3 Index and send hardcopy to QA File A160.0761 Hardcopy:

Certrec Corporation 4200 South Hulen, Suite 422 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 Other Situations ULNRC Distribution:

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

T. B. Elwood D. J. Walker J. W. Knaup Ms. Diane M. Hooper (WCNOC)

Mr. Dennis Buschbaum (TXU)

Mr. Scott Bauer (palo Verde)

Mr. Stan Ketelsen (pG&E)

Mr. Wayne Harrison (STPNOC)

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

Missouri Public Service Commission

Callaway Cycle 17 COLR Rev. 1 Callaway Cycle 17 Core Operating Limits Report Revision 1 September 2008 Edited by:

G. E. Hauck P. Schueren Approved : _ _ ___**_ _ _ _ __ __

T. Rodack, Director Quality and Licensing Programs

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    • Electronically Approved Records Are Authenticated in the Electronic Document Management System ~"CO It: <')t~6':

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Westinghouse Electric Company LLC ... ' ~

POBox 355

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.( 99V£"t Approved by: r-), 01 Curve Book Figure 13-1, Rev. 50

Callaway Cycle 17 COLR Rev. 1 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Callaway Plant Cycle 17 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 from Nucleate Boiling (DNB) Limits 1

Curve Book Figure 13-1, Rev. 50

Callaway Cycle 17 COLR Rev. 1 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% AkIk.

2.1.2 The Shutdown Margin prior to blocking Safety Injection below P-ll in MODES 3 and 4 shall be greater than 0% AkIk as calculated at 200°F.

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

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/oF (all rods withdrawn, Rated Thermal Power condition).

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

2 Curve Book Figure 13-1, Rev. 50

Callaway Cycle 17 COLR Rev. 1 7

UNACCEPTABLE OPERATION (70%, 5.0) r\

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1\

r\

ACCEPTABLE OPERATION 1\

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1\

1

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o 10 20 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER Figure 1 Callaway Cycle 17 Moderator Tern perature Coefficient Versus Power Level 3

Curve Book Figure 13-1, Rev. 50

Callaway Cycle 17 COLR Rev. 1 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.

4 Curve Book Figure 13-1, Rev. 50

Callaway Cycle 17 COLR Rev. 1 225 /11 (28, 225) V I (78,225)

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25 (30.2,0) o V o 10 20 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER Figure 2 Callaway Cycle 17 Rod Bank Insertion Limits Versus Rated Thermal Power - Four Loop Operation 5

Curve Book Figure 13-1, Rev. 50

Callaway Cycle 17 COLR Rev. 1 2.5 Heat Flux Hot Channel Factor - FQ(Z)

(Specification 3.2.1)

F RTP Q

FQ(Z):S - -

  • K(Z) for P > 0.5 P

F RTP Q

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

RATED THERMAL POWER 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 F QW (z) are shown in Table AI.

The W(z) values have been determined for several burnups up to 20000 MWDIMTU in Cycle 17. 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 MWDIMTU W(z) values without interpolation or extrapolation is conservative. The W(z) values were determined assuming Cycle 17 operates with RAOC strategy.

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 lIP, when Pis> 0.5. When Pis :s 0.5, the W(z) values should be multiplied by the factor 1/(0.5), or 2.0. This is consistent with the adjustment in the F Q(z) limit at part power conditions.

Table A2 shows the burnup dependent F Q penalty factors for Cycle 17. These values shall be used to increase F QW (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 A2.

6 Curve Book Figure 13-1, Rev. 50

Callaway Cycle 17 COLR Rev. 1 2.5.4 The uncertainty, U FQ' to be applied to measured F Q(Z) shall be calculated by the following UFQ =U qu *Ue where:

Uqu = Base FQ measurement uncertainty = 1.05 when PDMS is inoperable (Uqu is defined by PDMS when OPERABLE)

U e = Engineering uncertainty factor = 1. 03 7

Curve Book Figure 13-1, Rev. 50

Callaway Cycle 17 COLR Rev. 1 Table Al W(z) versus Core Height (Top and Bottom 8% Excluded)

Height 150 4000 10000 20000 (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU 0.00 (bottom) 1.0000 1.0000 1.0000 1.0000 0.17 1.0000 1.0000 1.0000 1.0000 0.33 1.0000 1.0000 1.0000 1.0000 0.50 1.0000 1.0000 1.0000 1.0000 0.67 1.0000 1.0000 1.0000 1.0000 0.83 1.0000 1.0000 1.0000 1.0000 1.00 1.4854 1.4726 1.3149 1.3095 1.17 1.4738 1.4591 1.3070 1.3024 1.33 1.4594 1.4423 1.2966 1.2928 1.50 1.4427 1.4232 1.2845 1.2818 1.67 1.4245 1.4024 1.2713 1.2701 1.83 1.4051 1.3804 1.2574 1.2579 2.00 1.3847 1.3583 1.2427 1.2451 2.17 1.3636 1.3363 1.2277 1.2319 2.33 1.3420 1.3141 1.2125 1.2185 2.50 1.3203 1.2918 1.1972 1.2052 2.67 1.2977 1.2690 1.1819 1.1910 2.83 1.2748 1.2463 1.1681 1.1764 3.00 1.2585 1.2276 1.1607 1.1675 3.17 1.2489 1.2151 1.1581 1.1651 3.33 1.2415 1.2080 1.1554 1.1666 3.50 1.2339 1.2002 1.1526 1.1702 3.67 1.2252 1.1928 1.1500 1.1766 3.83 1.2159 1.1897 1.1480 1.1833 4.00 1.2080 1.1868 1.1469 1.1895 4.17 1.2016 1.1826 1.1462 1.1947 4.33 1.1958 1.1780 1.1448 1.1990 4.50 1.1894 1.1729 1.1430 1.2024 4.67 1.1824 1.1671 1.1408 1.2046 4.83 1.1749 1.1608 1.1380 1.2055 5.00 1.1667 1.1539 1.1347 1.2058 5.17 1.1581 1.1465 1.1309 1.2060 5.33 1.1492 1.1387 1.1267 1.2059 5.50 1.1393 1.1298 1.1211 1.2044 5.67 1.1321 1.1211 1.1171 1.2040 5.83 1.1342 1.1156 1.1212 1.2096 6.00 1.1388 1.1157 1.1293 1.2195 6.17 1.1466 1.1210 1.1434 1.2305 6.33 1.1534 1.1287 1.1557 1.2395 6.50 1.1593 1.1377 1.1673 1.2477 6.67 1.1648 1.1470 1.1788 1.2552 6.83 1.1701 1.1552 1.1898 1.2608 8

Curve Book Figure 13-1, Rev. 50

Callaway Cycle 17 COLR Rev. 1 Table Al W(z) versus Core Height (Top and Bottom 8% Excluded)

Height 150 4000 10000 20000 (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU 7.00 1.1746 1.1623 1.1997 1.2646 7.17 1.1778 1.1683 1.2083 1.2666 7.33 1.1797 1.1730 1.2156 1.2667 7.50 1.1804 1.1766 1.2214 1.2647 7.67 1.1797 1.1786 1.2257 1.2608 7.83 1.1777 1.1786 1.2286 1.2551 8.00 1.1734 1.1800 1.2289 1.2466 8.17 1.1684 1.1843 1.2285 1.2369 8.33 1.1667 1.1865 1.2316 1.2294 8.50 1.1654 1.1882 1.2350 1.2244 8.67 1.1632 1.1905 1.2374 1.2234 8.83 1.1637 1.1930 1.2428 1.2285 9.00 1.1732 1.1967 1.2532 1.2375 9.17 1.1901 1.2028 1.2671 1.2462 9.33 1.2025 1.2114 1.2797 1.2518 9.50 1.2124 1.2224 1.2918 1.2563 9.67 1.2223 1.2348 1.3024 1.2610 9.83 1.2303 1.2467 1.3078 1.2649 10.00 1.2381 1.2542 1.3173 1.2752 10.17 1.2494 1.2601 1.3352 1.2933 10.33 1.2679 1.2768 1.3531 1.3093 10.50 1.2881 1.2977 1.3686 1.3224 10.67 1.3062 1.3154 1.3818 1.3342 10.83 1.3247 1.3308 1.3934 1.3454 11.00 1.3357 1.3409 1.3986 1.3489 11.17 1.0000 1.0000 1.0000 1.0000 11.33 1.0000 1.0000 1.0000 1.0000 11.50 1.0000 1.0000 1.0000 1.0000 11.67 1.0000 1.0000 1.0000 1.0000 11.83 1.0000 1.0000 1.0000 1.0000 12.00 (top) 1.0000 1.0000 1.0000 1.0000 9

Curve Book Figure 13-1, Rev. 50

Callaway Cycle 17 COLR Rev. 1 Table A.2 FQ Penalty Factors as a Function of Cycle Bumup Cycle 17 Bumup EQW(z) Penalty Factor (%)

5131 2.27 5303 2.35 5475 2.24 5647 2.12 Note: All cycle bumups 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 bumup 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. 50

Callaway Cycle 17 COLR Rev. 1 1.20 1.10 (0, 1. 00) (6, 1. 00)

1. 00 (12, .925)f-h 0.90

....... 0.80 t'I 01

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Q 0.70 r:<I t'I H

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....... 2.50 6.0 1.00 Ii:: 0.40 2.31 12.0 0.925 0.30 0.20 0.10 0.00 o 1 2 3 4 5 6 7 8 9 10 11 12 CORE HEIGHT (FEET)

Figure 3 Callaway Cycle 17 K(z) - Normalized FQ(z) as a Function of Core Height 11 Curve Book Figure 13-1, Rev. 50

Callaway Cycle 17 COLR Rev. 1 2.6 Nuclear Enthalpy Rise Hot Channel Factor - FLHN (Specification 3.2.2)

F LHN<F

_ LHRTP[I+PFLH (l-P)]

THERMAL POWER where: P RATED THERMAL POWER 2.6.2 PFLH = 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. 50

Callaway Cycle 17 COLR Rev. 1 120 110

(-15, 100%) (+10, 100%)

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Figure 4 Callaway Cycle 17 Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC 13 Curve Book Figure 13-1, Rev. 50

Callaway Cycle 17 COLR Rev. 1 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. 50

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Figure 5 Callaway Cycle 17 Reactor Core Safety Lim its 15 Curve Book Figure 13-1, Rev. 50

Callaway Cycle 17 COLR Rev. 1 2.9 Reactor Trip System Overtemperature AT Setpoint Parameter Values (Specification 3.3.1)

Parameter Value Overtemperature AT reactor trip setpoint KI = 1.2260 Overtemperature AT reactor trip setpoint Tavg coefficient Overtemperature AT reactor trip setpoint pressure coefficient K3 = O.OOll/psig Nominal T avg at R TP T' ::: 585.3 of Nominal RCS operating pressure P' = 2235 psig Measured RCS AT lead/lag time constants "I:::: 0 sec "2::: 0 sec Measured RCS AT lag time constant "3 ::: 4 sec Measured RCS average temperature lead/lag time constants t4:::: 27 sec t5 ::: 4 sec Measured RCS average temperature lag time constant "6::: 2 sec when (qt - qb) < -18% RTP o when -18% RTP::: (qt - qb)::: 10% RTP Where, qt and qb are percent RTP in the upper and lower halves of the core, respectively, and qt + qb is the total THERMAL POWER in percent RTP.

16 Curve Book Figure 13-1, Rev. 50

Callaway Cycle 17 COLR Rev. 1 2.10 Reactor Trip System Overpower AT Setpoint Parameter Values (Specification 3.3.1)

Parameter --'V....::a""lu""e"---_ _ _ _ _ __

Overpower AT reactor trip setpoint K4 = 1.1073 Overpower AT reactor trip setpoint Tavg rate/lag coefficient Ks = O.02/oF for increasing Tavg

= O/oF for decreasing Tavg Overpower AT reactor trip setpoint Tavg heatup coefficient K6 = 0.00l5/oF for T > Til

= O/oF for T ::: Til Nominal T avg at R TP Measured RCS AT lead/lag time constants "1 ~ 0 sec "2::: 0 sec Measured RCS AT lag time constant "3::: 4 sec Measured RCS average temperature lag time constant Measured RCS average temperature rate/lag time constant "7~10sec 2.11 RCS Pressure and Temperature 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. 50

Callaway Cycle 17 COLR Rev. 1 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-I0216-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-I0216-P, Rev. 1, Relaxation of Constant Axial Offset Control - FQ Surveillance Technical Specification" (TAC No. M88206).

3. WCAP-I0266-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-l 0266 'The 1981 Version of the Westinghouse ECCS Evaluation Model Using the BASH Code.'"

WCAP-I0266-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-I0266, BASH Power Shape Sensitivity Studies."

WCAP-I0266-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-l 0266, 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. 50

Callaway Cycle 17 COLR Rev. 1 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 Bumup Fuel Design Methodology and ZIRLO Fuel Performance Models' (TAC NO. M86416)."

5. WCAP-l1397-P-A, "Revised Thermal Design Procedure," April 1989.

NRC Safety Evaluation Report dated January 17, 1989, "Acceptance for Referencing of Licensing Topical Report WCAP-l1397, "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-O 1 Modeling and Qualification for Pressurized Water Reactor N on-LOCA ThermallHydraulic Safety Analysis' (TAC No. M98666)."

7. WCAP-I0851-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-I0851, '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 LlT and Thermal Overtemperature LlT 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 LlT Trip Functions. '"

10. WCAP-I0965-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-11596-P-A, "Qualification of the Phoenix-PIANC Nuclear Design System for 19 Curve Book Figure 13-1, Rev. 50

Callaway Cycle 17 COLR Rev. 1 Pressurized Water Reactor Cores," June 1988.

NRC Safety Evaluation Report dated May 17, 1988, "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 I-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-13524 and WCAP-13524, 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. 50

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