ULNRC-05706, Cycle 18 Core Operating Limits Report
| ML101760118 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 06/24/2010 |
| From: | Maglio S AmerenUE, Union Electric Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| ULNRC-05706 | |
| Download: ML101760118 (26) | |
Text
~~
wAmeren UE AmerenUE Callaway Plant June 24, 2010 ULNRC- 05706 u.s. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Ladies and Gentlemen:
DOCKET NUMBER 50-483 CALLA WA Y PLANT UNIT 1 UNION ELECTRIC CO.
FACILITY OPERATING LICENSE NPF-30 CORE OPERATING LIMITS REPORT PO Box 620 Fulton, MO 65251 Attached is the Callaway Plant Cycle 18 Core Operating Limits Report (COLR).
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.
This letter does not contain new commitments.
If you have any questions concerning this report, please contact us.
Sincerely, L) C'\\:\\ t-\\- A. """
/
Scott A. Maglio, Regulatory Affairs Manager ACS/nls
Attachment:
Callaway Cycle 18 Core Operating Limits Report, Rev. 1 a subsidiary of Ameren Corporation
ULNRC-05706 June 24, 2010 Page 2 cc:
Mr. Elmo E. Collins, Jr.
Regional Administrator U.S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 Senior Resident Inspector Callaway Resident Office U. S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Mr. Mohan C. Thadani (2 copies)
Senior Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 0-8G 14 Washington, DC 20555-2738
ULNRC-05706 June 24, 2010 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 L. S. Sandbothe C. O. Reasoner III S. A. Maglio S. L. Gallagher T. L. Woodward (NSRB)
T. B. Elwood Ms. Diane M. Hooper (WCNOC)
Mr. Dennis Buschbaum (Luminant Power)
Mr. Ron Barnes (APS)
Mr. Tom Baldwin (PG&E)
Mr. Wayne Harrison (STPNOC)
Mr. John O'Neill (Pillsbury Winthrop Shaw Pittman LLP)
Missouri Public Service Commission to ULNRC-05706 Page 1 of 23 Callaway Cycle 18 COLR Callaway Cycle 18 REDESIGN Core Operating Limits Report Revision 1 May 2010 Edited by:
G. E. Hauck P. Schueren Approved:
G. K. Roberts, Manager Nuclear Design C Nuclear Fuel Core Engineering NF-SCP-I0-6, Rev. 1 Electronically Approved Records Are Authenticated in the Electronic Document Management System Westinghouse Electric Company LLC P.O. Box 355 Pittsburgh, PA 15230-0355
©20 1 0 Westinghouse Electric Company LLC All Rights Reserved Reviewed by: ~~~~.l3!..~~ __ /
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Approved by: -r--""'-iL-Jo-"""'--,.>:;I.....--- /
Curve Book Figure 13-1, Rev. 51 to ULNRC-05706 Page 2 of 23 Callaway Cycle 18 COLR NF-SCP-I0-6, Rev. 1 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Callaway Plant Cycle 18 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 (FQ(z>>
3.2.2 Nuclear Enthalpy Rise Hot Channel Factor FI!.HN 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 Curve Book Figure 13-1, Rev. 51 to ULNRC-05706 Page 3 of 23 Callaway Cycle 18 COLR NF-SCP-I0*6, 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% 8k:/k.
2.1.2 The Shutdown Margin prior to blocking Safety Injection below P*ll in MODES 3 and 4 shall be greater than 0%.1k/k as calculated at 200°F.
2.1.3 The Shutdown Margin in MODE 5 shall be greater than or equal to 1.0% &:/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/°F (all rods withdrawn, Rated Thennal Power condition).
2.2.3 The MTC 60 ppm surveillance limit is -45.5 pcm/°F (all rods withdrawn, Rated Thennal Power condition).
2 Curve Book Figure 13-1, Rev. 51 to ULNRC-05706 Page 4 of 23 Callaway Cycle 18 COLR IkI 0.......
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ACCEPTABLE OPERATION 20 30 40 50 60 70 PERCBNT OF RATED THBRMAL POWER Figure 1 Callaway Cycle 18 Moderator Temperature Coefficient Versus Power Level 3
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80 90 100 to ULNRC-05706 Page 5 of 23 Callaway Cycle 18 COLR 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. 51 to ULNRC-05706 Page 6 of 23 Callaway Cycle 18 COLR
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I (30.2, 0).J :.J' 20 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER Figure 2 Callaway Cycle 18 Rod Bank Insertion Limits Versus Rated Thermal Power - Four Loop Operation 5
Curve Book Figure 13-1, Rev. 51 to ULNRC-05706 Page 7 of 23 Callaway Cycle 18 COLR 2.5 Heat Flux Hot Channel Factor - FQ(Z)
(Specification 3.2.1)
FQRTP
---
- K(Z) for P > 0.5 p
FQ(Z) ~ ---
- K(Z) for P :s 0.5 0.5 THERMAL POWER where:
P =
RATEDTHERMALPO~R 2.5.1 FQRTP = 2.50.
2.5.2 K(Z) is provided in Figure 3.
NF-SCP-10-6, Rev. 1 2.5.3 The W(z) ftmctions 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 detennined for several bum ups up to 20000 MWD/MTU in Cycle 18. This pennits detennination ofW(z) at any cycle bumup up to 20000 MWD/MTU through the use of three point interpolation. For cycle bum ups greater than 20000 MWD/MTU, use of 20000 MWD/MTU W(z) values without extrapolation is conservative. The W(z) values were detennined assuming Cycle 18 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 ofO.!7 feet.
The W(z) values are generated asswning that they will be used for a full power surveillance. When a part power surveillance is perfonned, the W(z) values should be adjusted by the factor lIP, when P is > 0.5. When P is ~ 0.5, the W(z) values should be adjusted by the factor 11(0.5), or 2.0.
This is consistent with the adjustment in the FQ(z) limit at part power conditions.
Table A.2 shows the burnup dependent FQ penalty factors for Cycle 18. These values shall be used to increase FQ 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.
6 Curve Book Figure 13-1, Rev. 51 to ULNRC-05706 Page 8 of 23 Callaway Cycle 18 COLR NF-SCP-1O-6, Rev. 1 2.5.4 The uncertainty, UFQ, to be applied to measured FQ(Z) shall be calculated by the following where:
Uqu = Base FQ measurement Wlcertainty = 1.05 when PDMS is inoperable (Uqu is defined by PDMS when OPERABLE)
Ue = Engineering uncertainty factor = 1.03 7
Curve Book Figure 13-1, Rev. 51 to ULNRC-05706 Page 9 of 23 Callaway Cycle 18 COLR Height (feet) 0.00 (bottom) 0.17 0.33 0.50 0.67 0.83 1.00 1.17 1.33 1.50 1.67 1.83 2.00 2.17 2.33 2.50 2.67 2.83 3.00 3.17 3.33 3.50 3.67 3.83 4.00 4.17 4.33 4.50 4.67 4.83 5.00 5.17 5.33 5.50 5.67 5.83 6.00 6.17 6.33 6.50 6.67 6.83 Table A.1 W(z) versus Core Height (Top and Bottom 8% Excluded) 150 4000 10000 MWDIMTU MWDIMTU MWD/MTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.3487 1.4432 1.3687 1.3398 1.4295 1.3593 1.3288 1.4126 1.3471 1.3159 1.3933 1.3331 1.3019 1.3726 1.3178 1.2870 1.3508 1.3017 1.2715 1.3279 1.2847 1.2556 1.3048 1.2672 1.2396 1.2820 1.2496 1.2228 1.2600 1.2313 1.2070 1.2388 1.2139 1.1953 1.2180 1.1991 1.1880 1.1958 1.1851 1.1836 1.1780 1.1752 1.1796 1.1711 1.1731 1.1766 1.1691 1.1722 1.1737 1.1682 1.1703 1.1698 1.1666 1.1682 1.1677 1.1646 1.1658 1.1671 1.1621 1.1630 1.1660 1.1592 1.1596 1.1643 1.1556 1.1558 1.1620 1.1516 1.1514 1.1590 1.1470 1.1466 1.1556 1.1419 1.1411 1.1514 1.1363 1.1352 1.1465 1.1304 1.1291 1.1453 1.1230 1.1208 1.1464 1.1165 1.1148 1.1545 1.1165 1.1200 1.1645 1.1187 1.1282 1.1740 1.1255 1.1399 1.1824 1.1352 1.1503 1.1903 1.1463 1.1600 1.1978 1.1575 1.1697 1.2047 1.1675 1.1787 8
Curve Book Figure 13-1, Rev. 51 NF-SCP-10-6, Rev. 1 20000 MWDIMTU 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.2982 1.2921 1.2838 1.2744 1.2645 1.2541 1.2433 1.2323 1.2213 1.2099 1.1987 1.1876 1.1738 1.1660 1.1711 1.1770 1.1820 1.1869 1.1910 1.1946 1.1988 1.2024 1.2046 1.2057 1.2062 1.2064 1.2063 1.2062 1.2069 1.2144 1.2252 1.2360 1.2449 1.2530 1.2603 1.2657 to ULNRC-05706 Page 10 of 23 Callaway Cycle 18 COLR Height (feet) 7.00 7.17 7.33 7.50 7.67 7.83 8.00 8.17 8.33 8.50 8.67 8.83 9.00 9.17 9.33 9.50 9.67 9.83 10.00 10.17 10.33 10.50 10.67 10.83 11.00 11.17 11.33 11.50 11.67 11.83 12.00 (top)
Table A.1 W(z) versus Core Height (Top and Bottom 8% Excluded) 150 4000 10000 MWD/MTU MWDIMTU MWDIMTU 1.2106 1.1765 1.1868 1.2150 1.1844 1.1936 1.2181 1.1909 1.1991 1.2197 1.1961 1.2033 1.2197 1.1998 1.2060 1.2183 1.2013 1.2072 1.2142 1.2034 1.2064 1.2093 1.2064 1.2044 1.2084 1.2076 1.2040 1.2076 1.2077 1.2034 1.2058 1.2075 1.2012 1.2081 1.2080 1.2005 1.2178 1.2098 1.2028 1.2341 1.2160 1.2135 1.2513 1.2256 1.2263 1.2654 1.2388 1.2382 1.2765 1.2547 1.2493 1.2884 1.2707 1.2626 1.2956 1.2885 1.2740 1.2986 1.3110 1.2847 1.3099 1.3399 1.3044 1.3261 1.3715 1.3266 1.3429 1.4035 1.3447 1.3608 1.4370 1.3611 1.3667 1.4588 1.3713 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 9
Curve Book Figure 13-1, Rev. 51 NF*SCP*10-6, Rev. 1 20000 MWDIMTU 1.2692 1.2708 1.2705 1.2682 1.2638 1.2576 1.2488 1.2386 1.2296 1.2223 1.2179 1.2186 1.2239 1.2308 1.2354 1.2391 1.2429 1.2450 1.2457 1.2479 1.2569 1.2679 1.2769 1.2850 1.2907 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 to ULNRC-05706 Page 11 of 23 Callaway Cycle 18 COLR NF-SCP-I0-6, Rev. 1 Table A.la W(z) versus Core Height for Partial Power Operation (45% Power, 150 MWDIMTU)
(Top and Bottom 8% Excluded)
- The W(z)'s are not increased by the nominal power ratio. In order to be applicable, the W(z) 's must be divided by the relative power at the time of the surveillance Height (feet)
W(z) *
- 0.00 (bottom) 1.0000 0.17 1.0000 0.33 1.0000 0.50 1.0000 0.67 1.0000 0.83 1.0000 1.00 1.5041 1.17 1.4856 1.33 1.4651 1.50 1.4425 1.67 1.4189 1.83 1.3942 2.00 1.3688 2.17 1.3429 2.33 1.3171 2.50 1.2907 2.67 1.2661 2.83 1.2463 3.00 1.2312 3.17 1.2191 3.33 1.2076 3.50 1.1972 3.67 1.1870 3.83 1.1761 4.00 1.1670 4.17 1.1595 4.33 1.1513 4.50 1.1427 4.67 1.1336 4.83 1.1239 5.00 1.1141 5.17 1.1038 5.33 1.0930 5.50 1.0861 5.67 1.0818 5.83 1.0845 10 Curve Book Figure 13-1, Rev. 51 to ULNRC-05706 Page 12 of 23 Callaway Cycle 18 COLR NF-SCP-I0-6, Rev. 1 TableA.la W(z) versus Core Height for Partial Power Operation (45% Power, 150 MWDIMTU)
(Top and Bottom 8% Excluded)
- The W(z) 's are not increased by the nominal power ratio. In order to be applicable, the W(z) 's must be divided by the relative power at the time of the surveillance Height (feet)
W(z) *
- 6.00 1.0893 6.17 1.0932 6.33 1.0955 6.50 1.0968 6.67 1.0982 6.83 1.0993 7.00 1.0998 7.17 1.0991 7.33 1.0973 7.50 1.0940 7.67 1.0897 7.83 1.0844 8.00 1.0772 8.17 1.0695 8.33 1.0654 8.50 1.0614 8.67 1.0566 8.83 1.0558 9.00 1.0616 9.17 1.0732 9.33 1.0859 9.50 1.0961 9.67 1.1038 9.83 1.1122 10.00 1.1158 10.17 1.1159 10.33 1.1238 10.50 1.1365 10.67 1.1505 10.83 1.1662 11.00 1.1691 11.17 1.0000 11.33 1.0000 11.50 1.0000 11.67 1.0000 11.83 1.0000 12.00 (top) 1.0000 11 Curve Book Figure 13-1, Rev. 51 to ULNRC-05706 Page 13 of 23 Callaway Cycle 18 COLR NF-SCP-I0-6, Rev. 1 TableA.2 FQ Penalty Factors as a Function of Cycle Burnup Cycle 18 Burnup 665 837 1008 1180 1351 1523 1695 1866 2038 FQW(z) Penalty Factor (%)
2.00 2.60 3.98 4.24 3.92 3.48 2.96 2.41 2.00 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 burn up 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.
12 Curve Book Figure 13-1, Rev. 51 to ULNRC-05706 Page 14 of 23 Callaway Cycle 18 COLR 1.20 1.10
~ (0, 1.00) 1.00 0.90 0.80 N -
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Q 0.70 ra1 N
1-1 I 0.60 2i 0.50 N -
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0.40 0.30 0.20 0.10 0.00 o
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(6, 1.00)
FQ Elevation (ft. )
K(z) 2.50 0.0 1.00 2.50 6.0 1.00 2.31 12.0 0.925 3
4 5
6 7
8 CORE HEIGHT (FEET)
Figure 3 Callaway Cycle 18 K(z) - Normalized FQ(z) as a Function of Core Height 13 Curve Book Figure 13-1, Rev. 51 NF-SCP-IO-6, Rev. 1 (12,.925) I-9 10 11 12 to ULNRC-05706 Page 15 of 23 Callaway Cycle 18 COLR 2.6 Nuclear Enthalpy Rise Hot Channel Factor - F MJ. N (Specification 3.2.2)
Fl\\HN
- Utili ~ FAf{RTP [1 + PFMi(1-P)]
THERMAL POWER where:
P RATED THERMAL POWER 2.6.2 PF Af{ = 0.3 NF-SCP-IO-6, Rev. 1 2.6.3 The uncertainty, UAf{, to be applied to measured FAf{ shall be 1.04 when PDMS is inoperable (Utili is defined by PDMS when OPERABLE).
2.7 Axial Flux Difference (Specification 3.2.3)
The Axial Flux Difference (AFD) Limits are provided in Figure 4.
14 Curve Book Figure 13-1, Rev. 51 to ULNRC-05706 Page 16 of 23 Callaway Cycle 18 COLR NF-SCP-I0-6, Rev. 1
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Figure 4 Callaway Cycle 18 Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC 15 Curve Book Figure 13-1, Rev. 51 40 f-f--I-f-f--f--
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f-f-I-50 to ULNRC-05706 Page 17 of 23 Callaway Cycle 18 COLR 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 presswizer pressure shall not exceed the limits in Figure 5.
16 Curve Book Figure 13-1. Rev. 51 to ULNRC-05706 Page 18 of 23 Callaway Cycle 18 COLR NF-SCP-I0-6, Rev. 1
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FRACTION OF RATED TH ERMAL POWER Figure 5 Callaway Cycle 18 Reactor Core Safety Limits 17 Curve Book Figure 13-1, Rev. 51 1.2 1.1 to ULNRC-05706 Page 19 of 23 Callaway Cycle 18 COLR NF-SCP-I0-6, Rev. 1 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 T avg coefficient Overtemperature AT reactor trip setpoint pressure coefficient Nominal Tavg atRTP 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 ReS average temperature lag time constant Value Kl = 1.2260 K3 = O.OOI1/psig T'~585.3 OF P' = 2235 psig
'tl ?: 0 sec
't2 ~ 0 sec
't3 ~ 4 sec 4~27 sec ts:5 4 sec
't6 ~ 2 sec when (qt - qb) < -18% RTP o
when -18% RTP.:s (qt - qb):S 10% RTP when (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.
18 Curve Book Figure 13-1, Rev. 51 to ULNRC-05706 Page 20 of 23 Callaway Cycle 18 COLR 2.10 Reactor Trip System Ovelpower /j, T Setpoint Parameter Values (Specification 3.3.1)
NF-SCP-I0-6, Rev. 1 Parameter
..:.V.::;:;a=lu=e ______ _
Overpower AT reactor trip setpoint
~
= 1.1073 Overpower AT reactor trip setpoint T avg rate/lag coefficient Ks = O.02/°F for increasing T avg
= O/oF for decreasing T avg Overpower AT reactor trip setpoint Tavg heatup coefficient
~
= 0.001 51°F for T > Til
= O/oF for T ~ Til Nominal Tavg at RTP Til :s 585.3°F Measured RCS AT lead/lag time constants
'tl ~ 0 sec
't2.::s 0 sec Measured RCS AT lag time constant
't3 ~ 4 sec Measured RCS average temperature lag time constant
't6 ~ 2 sec Measured RCS average temperature rate/lag time constant
't7 ~ 10 sec 2.11 RCS Pressure and Temperature Departure from Nucleate Boiling CDNBl Limits (Specification 3.4.1)
Parameter Indicated Value Pressurizer pressure
~2223 psig RCS average temperature
.::s 590.1 OF 19 Curve Book Figure 13-1, Rev. 51 to ULNRC-05706 Page 21 of 23 Callaway Cycle 18 COLR APPENDIX A Approved Analytical Methods for Detennining Core Operating Limits NF-SCP-I0-6, Rev. 1 The analytical methods used to detennine 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. III 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-10266, BASH Power Shape Sensitivity Studies."
WCAP-I0266-P-A, Addendum 2, Revision 2, "The 1981 Version of the Westinghouse Eecs 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-I0266, Revision 2, "BASH Methodology Improvements and Reliability Enhancements."
20 Curve Book Figure 13-1, Rev. 51 to ULNRC-05706 Page 22 of 23 Callaway Cycle 18 COLR NF-SCP-IO-6, Rev. 1
- 4.
WCAP-12610-P-A, "V ANTAGE+ Fuel Assembly Reference Core Report," April 1995.
NRC Safety Evaluation Reports dated July I, 1991, "Acceptance for Referencing of Topical Report WCAP-12610, 'VANTAGE+ Fuel Assembly Reference Core Report' (T AC NO. 77258)."
NRC Safety Evaluation Report dated September 15, 1994, "Acceptance for Referencing of Topical Report WCAP-I2610, Appendix B, Addendum 1, 'Extended Burnup Fuel Design Methodology and ZIRLO Fuel Performance Models' (TAC NO. M86416)."
- 5.
WCAP-11397-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-Ol Modeling and Qualification for Pressurized Water Reactor Non-LOCA ThennaVHydraulic 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. III
- 8.
WCAP-15063-P-A, Revision I, 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 Perfonnance 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 aT and Thermal Overtemperature IJ. T 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."
21 Curve Book Figure 13-1, Rev. 51 to ULNRC-05706 Page 23 of 23 Callaway Cycle 18 COLR
- 11.
WCAP-11596-P-A, "Qualification of the Phoenix-P/ANC Nuclear Design System for Pressurized Water Reactor Cores," June 1988.
NRC Safety Evaluation Report dated May 17, 1988, "Acceptance for Referencing of Westinghouse Topical Report WCAP-11596 - Qualification of the Phoenix-P/ANC Nuclear Design System for Pressurized Water Reactor Cores."
- 12.
WCAP-I3524-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)"
22 Curve Book Figure 13-1, Rev. 51