ULNRC-05561, Core Operating Limits Report, Rev. 0
| ML083290258 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 11/12/2008 |
| From: | Graessle L AmerenUE |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| ULNRC-05561 | |
| Download: ML083290258 (26) | |
Text
AmerenUE Callaway Plant PO Box 620 Fulton, MO 65251 November 12, 2008 ULNRC-05561 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop P1-137 Washington, DC 20555-0001 Ladies and Gentlemen:
W Ameren 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 17 Core Operating Limits Report (COLR), Revision 0. 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.
If you have any questions concerning this report, please contact us.
Sincerely, H. Graessle Manager, Regulatory Affairs DJW/nls
Attachment:
Callaway Cycle 17 Core Operating Limits Report, Rev. 0 46e fI a subsidiary of Ameren Corporation
ULNRC-05561 November 12, 2008 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)
Licensing Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop O-8G14 Washington, DC 20555-2738 Deputy Director Department of Natural Resources P.O. Box 176 Jefferson City, MO 65102
ULNRC-05561 November 12, 2008 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
Attachment
- 1 O )
to ULNRC-05561 Callaway Cycle 17 COLR Rev. 0 Callaway Cycle 17 Core Operating Limits Report Revision 0 September 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
©2008 Westinghouse Electric Company LLC All Rights Reserved NF-SCP-08-54 Reviewed Approved 9
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Attachment to ULNRC-05561 Callaway Cycle 17 COLR Rev. 0 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 Curve Book Figure 13-1, Rev. 49
Attachment to ULNRC-05561 Callaway Cycle 17 COLR Rev. 0 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 2.1.2 The Shutdown Margin in MODES 1-4 shall be greater than or equal to 1.3% Ak/k.
The Shutdown Margin prior to blocking Safety Injection below P-1 I in MODES 3 and 4 shall be greater than 0% Ak/k 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 2.2.2 2.2.3 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/0 F.
This limit shall be referred to as the lower limit.
The MTC 300 ppm surveillance limit is -40.4 pcrn/0 F (all rods withdrawn, Rated Thermal Power condition).
The MTC 60 ppm surveillance limit is -45.5 pcm/IF (all rods withdrawn, Rated Thermal Power condition).
2 Curve Book Figure 13-1, Rev. 49
Attachment to ULNRC-05561 Callaway Cycle 17 COLR Rev. 0 HrU cix 0
E-4 6
UNACCEPTABLE OPERATION
- ' ! il(70%,,
5.0
- ~~
AIII I HIMo,
~o lL L
5~~- -
-LLI' 0
10 20 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER Figure 1 Callaway Cycle 17 Moderator Temperature Coefficient Versus Power Level 3
Curve Book Figure 13-1, Rev. 49
Attachment to ULNRC-05561 Callaway Cycle 17 COLR Rev. 0 2.3 Sutdown 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. 49
Attachment to ULNRC-05561 Callaway Cycle 17 COLR Rev. 0 22s[
I I I I (28,225) 1 U (78, 225) I 1 11ý71--7I 1W I
IIIT H
E-4 0
H E-1 H
0 0
04 2 o U t I I I ' -
-I I I -
BANK B 3.75 ---
(100, 161) 150
'fBANK C
100-0 I
1 1
XBANK D
75-50 25 0
1A 0
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. 49
Attachment to ULNRC-05561 Callaway Cycle 17 COLR Rev. 0 2.5 Heat Flux Hot Channel Factor - FQ(Z)
(Specification 3.2.1)
FQ(Z) <.
K(Z) for P > 0.5 P
FQRTP FO(Z) <
- K(Z) for P < 0.5 0.5 THERMAL POWER w here:
P =
RATED THERMAL POWER 2.5.1 FQRT =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 bumups up to 20000 MWD/MTU 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 bumups 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 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 lI/P, when P is > 0.5. When P is _ 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 Fo(z) limit at part power conditions.
Table A.2 shows the burnup dependent FQ penalty factors for Cycle 17. These values shall be used to increase FQW(z) when required by Technical Specification Surveillance Requirement 3.2.1.2. A 2% penalty factor should be used at all cycle bumups that are outside the range of Table A.2.
"* Refer to Table A.la of Addendum I for w(z) values for evaluating the startup testing flux map at 150 MWD/MTU burnup and 45 +/- 5% RTP.
6 Curve Book Figure 13-1, Rev. 49
Attachment to ULNRC-05561 Callaway Cycle 17 COLR Rev. 0 2.5.4 The uncertainty, UFQ, to be applied to measured FQ(Z) shall be calculated by the following UFQ = U,* U where:
U= Base F. measurement uncertainty = 1.05 when PDMS is inoperable (Uq, is defined by PDMS when OPERABLE)
U,= Engineering uncertainty factor = 1.03 7
Curve Book Figure 13-1, Rev. 49
Attachment to ULNRC-05561 Callaway Cycle 17 COLR Rev. 0 Table A. 1 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 L11895 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. 49
Attachment to ULNRC-05561 Callaway Cycle 17 COLR Rev. 0 Table A. I 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. 49
Attachment to ULNRC-05561 Callaway Cycle 17 COLR Rev. 0 Table A.2 F. Penalty Factors as a Function of Cycle Burnup Cycle 17 Bumup 5131 5303 5475 5647 FoW(z) Penalty Factor (%)
2.27 2.35 2.24 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. 49
Attachment to ULNRC-05561 Callaway Cycle 17 COLR Rev. 0 1.20 1.10 1.00 0.90 0.80 0.70 N
0.60 0
I 0.50 0.40 0.30 0.20 0.10 0.00
`I 7'!T*7FTV 11 11 1 1771 LPiI.I 1I 1 ! 1 1 1
- 1' 1,1 1(0, 1.00) 1+/-~i~
~(6,
- 1. 00)
II I i I I I!
ii ill I lI i I I I I I I I I, I ý i t 17 i 71 i I
1 1 i
I I I I I i I I ; ;
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I 1 7 :171I 17 r
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111 I M i I I I ý ; I ! I I I I I I I i I i i i I
1 :
I I l I ! I ; I ji I i I ý 1 I,i I !
I I Iii!
ii i
j
, 1 1
~-
-v----
FQ Elevation (ft.)
K (z) 1.00 1.00 0.925 I I i i
It lli
! ; ; ! : 1 1 2.50 2.50 2.31 0.0 6.0 12.0 4I I
I 7:
7-7 i.
! I
. :, : : q !., - : ; ; :,
- ; j ; 1 : 1 1 :, : j i 1,
- i ii:Iii!l;;ll;';
I
-~
I
~
~
0 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. 49
Attachment to ULNRC-05561 Callaway Cycle 17 COLR 2.6 Nuclear Enthalpy Rise Hot Channel Factor - F,,N (Specification 3.2.2)
FAN <5 FllTw [I + PFH(I -P)]
THERMAL POWER where:
P =
RATED THERMAL POWER Rev. 0 2.6.1 2.6.2 FHRTP= 1.59 PFa, = 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. 49
Attachment to ULNRC-05561 Callaway Cycle 17 COLR Rev. 0 120 110 100 90 0A4 04 EA4 p
04 s0 70 60 50 40 30 (i
1 -30, 50%)l E(+26, 50%)*!l 20 10 0
-50
-40
-30
-20
-10 0
10 20 30 40 50 AXIAL FLUX DIFFERENCE (% DELTA-I)
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. 49
Attachment to ULNRC-05561 Callaway Cycle 17 COLR Rev. 0 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.
14 Curve Book Figure 13-1, Rev. 49
Attachment to ULNRC-05561 Callaway Cycle 17 COLR Rev. 0 680 660 640 U--
> 620 C---
600 580 560 I'-
T
- ,.~
r 9.
Un* cceptable 2, 135 psia OpE ration 2*-* 50 ppsia Ac ;eptable Op eration 0
.4
.6
.8 FRACTION OF RATED THERMAL POWER 1.2 Figure 5 Callaway Cycle 17 Reactor Core Safety Limits 15 Curve Book Figure 13-1, Rev. 49
Attachment to ULNRC-05561 Callaway Cycle 17 COLR 2.9 Reactor Trip System Overtemperature AT Setpoint Parameter Values (Specification 3.3.1)
Rev. 0 Parameter Overtemperature AT reactor trip setpoint Overtemperature AT reactor trip setpoint Tavg coefficient Overtemperature AT reactor trip setpoint pressure coefficient Nominal T,,g 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 fQ(AI) = -0.0325 t21% + (q - qb)}
when 0
when 0.02973 {(q, - qb) - 8%}
when Value K, = 1.1950 K2 = 0.0251/-F K3 = 0.001 16/psig T' < 585.3 OF P'= 2235 psig "t* > 9 sec T, < 3 sec
-13 = 0 sec t, > 28 sec t5 < 4 sec T6 = 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.
16 Curve Book Figure 13-1, Rev. 49
Attachment to ULNRC-05561 Callaway Cycle 17 COLR 2.10 Reactor Trip System Overpower AT Setpoint Parameter Values (Specification 3.3. 1)
Rev. 0 Parameter Overpower AT reactor trip setpoint Overpower AT reactor trip setpoint T.vg rate/lag coefficient Overpower AT reactor trip setpoint Tvg heatup coefficient Nominal Tovg 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 fý(AI) = 0 for all Al.
Value K4 = 1.1073 K5 = 0.02/°F for increasing T...
0/*F for decreasing Tavg K6 = 0.0015/°F for T > T"
=0/'F for T < T" T" < 585.30 F
. > 8 sec 1 2 < 3 sec 13 = 0 sec T6 = 0 SeC T7 > 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 17 Curve Book Figure 13-1, Rev. 49
Attachment to ULNRC-05561 Callaway Cycle 17 COLR Rev. 0 APPENDIX A AAproved 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 1 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 1 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.
18 Curve Book Figure 13-1, Rev. 49
Attachment to ULNRC-05561 Callaway Cycle 17 COLR Rev. 0 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-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-1 1397, "Revised Thermal Design Procedure."
- 6.
WCAP-14565-P-A, "VIPRE-01 Modeling and Qualification for Fressurized 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-1085 1-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-1085], '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 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 19 Curve Book Figure 13-1, Rev. 49
Attachment to ULNRC-05561 Callaway Cycle 17 COLR Rev. 0 Pressurized Water Reactor Cores," Jule 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-13524-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-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. 49
Attachment to ULNRC-05561 Addendum 1 NF-SCP-08-69
- 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.
Table A.la W(z) versus Core Height for Partial Power Operation (45% Power, 150 MWD/MTU)
(Top and Bottom 8% Excluded)
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 1.6267 1.17 1.6046 1.33 1.5800 1.50 1.5534 1.67 1.5250 1.83 1.4957 2.00 1.4659 2.17 1.4355 2.33 1.4052 2.50 1.3749 2.67 1.3440 2.83 1.3129 3.00 1.2890 3.17 1.2721 3.33 1.2576 3.50 1.2431 3.67 1.2275 3.83 1.2115 4.00 1.1971 4.17 1.1842 4.33 1.1720 4.50 1.1594 4.67 1.1462 4.83 1,1327 5.00 1.1188 5.17 1.1045 5.33 1.0899 5.50 1.0747 21 Curve Book Figure 13-1, Rev. 49
Attachment to ULNRC-05561 Addendum 1 NF-SCP-08-69 Table A.la W(z) versus Core Height for Partial Power Operation (45% Power, 150 MWD/MTU)
(Top and Bottom 8% Excluded)
Height (feet)
W(z)**
5.67 1.0622 5.83 1.0585 6.00 1.0574 6.17 1.0593 6.33 1.0602 6.50 1.0603 6.67 1.0603 6.83 1.0605 7.00 1.0604 7.17 1.0591 7.33 1.0564 7.50 1.0524 7.67 1.0473 7.83 1.0415 8.00 1.0339 8.17 1.0259 8.33 1.0210 8.50 1.0168 8.67 1.0120 8.83 1.0099 9.00 1.0155 9.17 1.0278 9.33 1.0368 9.50 1.0427 9.67 1.0498 9.83 1.0576 10.00 1.0697 10.17 1.0871 10.33 1.1109 10.50 1.1377 10.67 1.1633 10.83 1.1873 11.00 1.2005 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 22 Curve Book Figure 13-1, Rev. 49