ML091310168: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
(One intermediate revision by the same user not shown) | |||
Line 2: | Line 2: | ||
| number = ML091310168 | | number = ML091310168 | ||
| issue date = 05/06/2009 | | issue date = 05/06/2009 | ||
| title = | | title = Core Operating Limits Report (COLR) for Cycle 9, Revision 1 | ||
| author name = Skaggs M | | author name = Skaggs M | ||
| author affiliation = Tennessee Valley Authority | | author affiliation = Tennessee Valley Authority | ||
Line 16: | Line 16: | ||
=Text= | =Text= | ||
{{#Wiki_filter:Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 MAY 0 6 20O9 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Gentlemen: | {{#Wiki_filter:Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 MAY 0 6 20O9 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Gentlemen: | ||
In the Matter of the ) Docket No. 50-390 Tennessee Valley Authority | In the Matter of the ) Docket No. 50-390 Tennessee Valley Authority ) | ||
WATTS BAR NUCLEAR PLANT (WBN) UNIT I - CORE OPERATING LIMITS REPORT (COLR) FOR CYCLE 9, REVISION 1 The purpose of this letter is to provide Revision 1 of the Cycle 9 COLR in accordance with WBN Technical Specification 5.9.5.d. Revision 1 updates the axial flux difference limits and was in effect as of April 23, 2009. | |||
If you have any questions concerning this letter, please contact Mike Brandon, Site Licensing and Industry Affairs Manager, at (423) 365-1824.Sincerely, Mike Skaggs Site Vice President Watts Bar Nuclear Plant cc: See Page 2 | There are no regulatory commitments associated with this submittal. If you have any questions concerning this letter, please contact Mike Brandon, Site Licensing and Industry Affairs Manager, at (423) 365-1824. | ||
Sincerely, Mike Skaggs Site Vice President Watts Bar Nuclear Plant cc: See Page 2 | |||
U.S. Nuclear Regulatory Commission Page 2 HAY 0 6 2009 Enclosure cc (Enclosure): | |||
NRC Resident Inspector Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381 U.S. Nuclear Regulatory Commission Mr. John G. Lamb, Senior Project Manager Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation MS 0-8 H1A Washington, DC 20555-0001 U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 | |||
Enclosure Watts Bar Nuclear Plant Unit 1 Cycle 9 Core Operating Limits Report, Revision 1 | |||
COLR for. Watts Bar Unit 1, Cycle 9 QA Record L36 090,42.1 807 WATTS: BAR NUCLEAR PLANT,. UNIT 1, CYCLE 9 CORE OPERATING LIMITS REPORT Revision 1 April, 2009 Prepared by: | |||
IdA & I Mý/ | |||
Nuclear Fuel Date Ve-rified.by: | |||
Nuclear Fuel Date Reviewed by:~ 63~ | |||
Manager,, Nular Fuel Design Date Reactor Engineering Supervisor Date | |||
,Approved by: . . .. | |||
PORC:Chairman | |||
... /. Date Plant Manager Date Date of PORC PORC Meeting Affected: | |||
Revision. Approval Number Pages Reason for Revision 0 3-5-08 4222 1-10 Initial issue i q-p-i** ,9 .. 8.9.. | |||
1,.81 Revise:AFD limits and W(z) values Unit 1 Cycle 9 WATTS BAR Page 1 of 10 Revision 1 | |||
LIMITS The cycle-specific parameter limits for the specifications listed in section 1.0 are presented in the following subsections. | COLR for Watts Bar Unit 1, Cycle 9 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) -for Watts-,Bar Unit 1 Cycle 9 has been,-prepared -in accordance with the requirements of the Technical Specifications 5.9.5. | ||
These limits have been developed using the NRC approved methodologies specified in the Technical Specifications Section 5.9.5.The following abbreviations are used in this section: BOL -- Beginning of Cycle Life ARO -- All Rods Out HZP -- Hot Zero Thermal Power EOL -- End of Cycle Life RTP -- Rated Thermal Power Unit I Cycle 9 WATTS BAR Page 2 of 10 Revision 0 | The Technical Specifications affected by this report are listed below: | ||
3.1.4 Moderator Temperature Coefficient (MTC) 3.1.6 Shutdown Bank Insertion Limits 3.1.7 Control Bank Insertion Limits 3.2.1 Heat Flux Hot Channel Factor (FQ(Z)) | |||
3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F &N) 3.2.3 Axial Flux Difference (AFD) 3.5.1 Accumulators 3.5.4 Refueling Water Storage Tank (RWST) 3.9.1 Boron Concentration 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in section 1.0 are presented in the following subsections. These limits have been developed using the NRC approved methodologies specified in the Technical Specifications Section 5.9.5. | |||
The following abbreviations are used in this section: | |||
BOL -- Beginning of Cycle Life ARO -- All Rods Out HZP -- Hot Zero Thermal Power EOL -- End of Cycle Life RTP -- Rated Thermal Power Unit I Cycle 9 WATTS BAR Page 2 of 10 Revision 0 | |||
COLR for Watts Bar Unit 1, Cycle 9 2.1 MODERATOR TEMPERATURE COEFFICIENT - MTC (LCO 3.1.4) 2.1.1 The MTC limits are: | |||
BANK INSERTION LIMITS (LCO 3.1.7)2.3.1 The control banks are fully withdrawn or shall be limited in physical insertion as shown in Figure 1.2.3.2 Each control bank shall be considered fully withdrawn from the core at greater than or equal to 225 steps.Unit 1 WATTS BAR | The BOL/ARO/HZP - MTC shall be less positive than or equal to 0 Ak/k/0 F (upper limit). With the measured BOL/ARO/HZP - MTC more positive than -1.00 x 10-5 Ak/k/°F (as-measured MTC limit), establish control rod withdrawal limits to ensure the MTC remains less positive than or equal to 0 Ak/k/0 F (upper limit) for all times in core life. | ||
2.3.4. Each control ,bank not fully withdrawn from the core shall be operated with the following overlap as a function of park position.Park Position (steps) | The EOL/ARO/RTP - MTC shall be less negative than or equal to | ||
* K(Z)for P > 0.5 FQ(Z) _[CFQ/0.5] | -4.5 x 10-4 Ak/k/0 F (lower limit). | ||
* K(Z) | 2.1.2 The 300 ppm surveillance limit is: | ||
The measured 300 ppm /ARO/RTP-MTC should be less negative than or equal to | |||
-3.75 x 10-4 Ak/k/°F. | |||
2.1.3 The 60 ppm surveillance limit is: | |||
The measured 60 ppm /ARO/RTP-MTC should be less negative than or equal to | |||
-4.28 x 10-4 Ak/k/ 0 F. | |||
2.2 SHUTDOWN BANK INSERTION LIMITS (LCO 3.1.6) 2.2.1 The shutdown banks shall be withdrawn to a position greater than or equal to 225 steps withdrawn. | |||
2.3 CONTROL BANK INSERTION LIMITS (LCO 3.1.7) 2.3.1 The control banks are fully withdrawn or shall be limited in physical insertion as shown in Figure 1. | |||
2.3.2 Each control bank shall be considered fully withdrawn from the core at greater than or equal to 225 steps. | |||
Unit 1 Cycle 9 WATTS BAR Page 3 of 10 Revision 0 | |||
COLR for Watts Bar Unit 1, Cycle 9 2.3.3 The control banks shall be operated in sequence by withdrawal of Bank A, Bank B, Bank C, and Bank D. The control banks shall be sequenced in reverse order upon insertion. | |||
2.3.4. Each control ,bank not fully withdrawn from the core shall be operated with the following overlap as a function of park position. | |||
Park Position (steps) BankOverlap (steps) Bank Difference(steps) 225 109 116 226 110 116 227 111 116 228 112 116 229 113 116 230 114 116 231 115 116 2.4 HEAT FLUX HOT CHANNEL FACTOR - FQ(Z) (LCO 3.2.1) | |||
FQ(Z) _ [CFQ / P] | |||
* K(Z) for P > 0.5 FQ(Z) _[CFQ/0.5] | |||
* K(Z) forP*_0.5 Where P = Thermal Power / Rated Thermal Power 2,4.l CFQ = 2.50 214.2 K(Z) is provided in Figure 2. | |||
2.4.3 FQc(Z) = FQM(Z) | |||
* 1.0815 where: FQM(Z) is the measured value of FQ(Z) obtained from incore flux map results and 1.0815 is a factor that accounts for fuel manufacturing tolerances and flux map measurement uncertainty. | * 1.0815 where: FQM(Z) is the measured value of FQ(Z) obtained from incore flux map results and 1.0815 is a factor that accounts for fuel manufacturing tolerances and flux map measurement uncertainty. | ||
2.4.4 FQw(Z) = FQc(Z) | 2.4.4 FQw(Z) = FQc(Z) | ||
* W(Z)where: W(Z) values are provided in Table A.I. The table provides sufficient information to determine W(Z) versus core height for all cycle bumups.Cycle 9 z Page 4 of 10 Revision 0 | * W(Z) where: W(Z) values are provided in Table A.I. The table provides sufficient information to determine W(Z) versus core height for all cycle bumups. | ||
-AFD (LCO 3.2.3)2.6.1 The AFD limits for Cycle 9 are provided in Figure 3.2.7 REFUELING BORON CONCENTRATION (LCO 3.9.1)2.7.1 The refueling boron concentration shall be | Unit 1 Cycle 9 WATTS BAI z Page 4 of 10 Revision 0 | ||
Unit 1 WATTS BAR | |||
COLR for Watts Bar Unit 1, Cycle 9 2.4.5 FQw(Z) Penalty Factor The FQw(Z) penalty factor is provided in Table A.2. | |||
* W(Z)Max W(z) at 150 Max W(z) at 2000 Max W(z) at 4000 Max W(z) at 10000 Max W(z) at 18000 Height (ft) MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU 12.0000 1.0000 1.0000 1.0000 1.0000 1.0000 11.8000 1.0000 1.0000 1.0000 1.0000. 1.0000 11.6000 1.0000 1.0000 1.0000 1.0000 1.0000 11.4000 1.0000 1.0000 1.0000 1.0000 1.0000 11.2000 1.0000 1.0000 1.0000 1.0000 1,0000 11.0000 1.0000 1.0000 1.0000 1.0000 1.0000 10.8000 1.3158 1.3647 1.3317 1.2020 1.1787 10.6000 1.3136 .1.3556 1.3261 1.1932 1.1745 10.4000 1.3103 1.3436 1.3177 1.1854 1.1703 10.2000 1.3090 1.3295 1.3089 1.1793 1.1644 10.0000 1.3033 1.3142 1.2978 1.1723 1.1600 9.8000 1.2973 1.2965 1.2842 1.1678 1,1558 9.6000 1.2904 1.2817 1.2710 1.1641 1.1555 9.4000 1:2801 1.2715 .1.2619 1.1604 1.1590 9.2000 1.2679 1.2609 1.2571 1.1592 1.1620 9.0000 1.2575 1.2502 1.2509 1.1584 1.1728 8.8000 1.2542 1.2447 1.2475 1.1628 1.1843 8.6000 1.2550 1.2454 .1.2475 1.1741 1.2001 8.4000 , 1,2601 1.2480 1.2471 1.1861 1.2220 8.2000 1.2620 1.2479 1.2438 1.1970 1.2399 8.0000 1.2619 1,2460 1.2381 1.2057 1.2553 7.8000 1.2597 1.2422 1.2319 1.2121 1.2682 7.6000 1.2554 1.2367 1.2282 1.2164 1.2781 7.4000 , 1.2491 1.2293 1.2269 1.2184 1.2851 7.2000 1.2409 1.2203 1.2228 1.2183 1.2893 7.0000 1.2341 1.2131 1.2168 1.2161 1.2906 6.8000 1.2283 1.2067 1.2095 1.2125 1.2892 6.6000 1.2214 1.1991 1.2008 1.2074 1.2850 6.4000 1.2123 1.1896 1.1902 1.2006 1.2783 6.2000 1.2016 1.1785 1.1782 1.1921 1.2690 6.0000 1.1915 1.1699 1.1688 1.1816 1,2574 5.8000 1.1816 .1.1610 1.1588 1.1722 1.2435 5.6000 1.1724 1.1518 1.1488 1.1648 1.2273 5.4000 1.1644 1.1447 1.1415 1.1587 1.2093 5.2000 1.1564 1.1371 1.1342 1.1541 1.1943 5.0000 1.1475 1.1291 1.1285 1.1483 1.1897 4.8000 1.1374 1.1213 1.1229 1.1433 1.1876 4.6000 1.1268 1.1136 1.1163 1.1398 1.1827 4.4000 1.1163 .1.1051 1.1092 1.1365 1.1771 4.2000 1.1069 1.0962 1.1017 1.1345 1.1704.4.0000 1.0971 1.0869 1.0937 1.1325 1.1629 3.8000 1.0871 1.0774 1.0857 1.1295 1.1548 3.6000 1.0764 1.0677 1.0772 1.1281 1.1460 3.4000 1.0663 1.0583 1.0697 1.1307 1.1373 3.2000 1.0642 1.0550 1.0710 1.1324 1.1318 3.0000 1.0662 1.0636 1.0820 1.1376 1.1357 2.8000 1.0731 1.0810 1,0998 1.1461 1.1491 2.6000 1.0850 1.0968 1.1167 1.1588 .. 1.1665 2.4000 1.1019 1.1137 1.1344 1.1782 1.1830 2.2000 1.1187 1.1309 1.1522 1.1971 1.1991 2.0000 1.1350 1.1472 1.1699 1.2152 1.2147 1.8000 1.1524 .1,1658 1.1864 1.2330 1.2297 1.6000 1.1744 1.1906 1.2036 1.2496 1.2439 1.4000 1.2024 1.2205 .1.2261, 1.2644 1.2564 1.2000 1.2282 1.2480 1.2520 1.2764 1.2664 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 0.8000 1.0000 1.0000 1.0000 1.0000 1.0000 0.6000 1.0000 1.0000 1.0000 1.0000 .1.0000 0.4000 1.0000 1.0000 1.0000 1.0000 1.0000 0.2000 1.0000 1.0000 1.0000 1.0000 1.0000 0.0000 1.0000 1.0000 1.0000 1.0000 1.0000'Unit 1 WATTS BAR | 2.5 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR - FAHN (LCO 3.2.2) | ||
Factor All Burnups 1.0200 Note: 1. The Penalty Factor, which is applied to FQw(Z) for compliance with Surveillance Requirement 3.2.1.2.a, is the maximum factor by which FQw(Z) is expected to increase per 31 Effective Full Power Days (EFPD) starting from the burnup at which the FQw(Z) was determined. | N R F6H < FAHRTP *( + PF *(l-P)) | ||
Unit 1 WATTS BAR | where P = Thermal Power / Rated Thermal Power FAHRTP = 1.65 for RFA-2 fuel, and PF =0.3 2.6 AXIAL FLUX DIFFERENCE - AFD (LCO 3.2.3) 2.6.1 The AFD limits for Cycle 9 are provided in Figure 3. | ||
2.7 REFUELING BORON CONCENTRATION (LCO 3.9.1) 2.7.1 The refueling boron concentration shall be Ž 2000 ppm. | |||
2.8 ACCUMULATORS (LCO 3.5.1) 2.8.1 ;There are 368 tritium producing burnable absorber rods (TPBARs) in the reactor core for Cycle 9. | |||
2.9 REFUELING WATER STORAGE TANK - RWST (LCO 3.5.4) 2.9.1 There are 368 tritium producing burnable absorber rods (TPBARs) in the reactor core for Cycle 9. | |||
Unit 1 Cycle 9 WATTS BAR Page 5 of 10 Revision 0 | |||
COLR for Watts Bar Unit 1, Cycle 9 250 225-(0.197: 225) (0.73, 225)1 200-BANK BI | |||
ý(1.0, 177) 175- I 180) a. | |||
w, 150. | |||
I--- | |||
0, z0~ | |||
0 | |||
]BANK C[ | |||
0W125 I-- | |||
'- 100' z | |||
0 ]BANK D4 75' (0.0, 64) 50 25 H(0.227, 0)ý 0 iiirrrflrrll 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 FRACTIONAL OF RATED THERMAL POWER Figure 1 Control Bank Insertion Limits Versus Thermal Power Four Loop Operation | |||
* Fully withdrawn region shall be the condition where shutdown and control banks are at a position within the interval of > 225 and < 231 steps withdrawn. | |||
Unit 1 Cycle 9 WATTS BAR Page 6 of 10 Revision 0 | |||
COLR for Watts Bar Unit 1, Cycle 9 1.2 1.1 1.0 - ----- _ | |||
0.9 0.8 4 4 .1- 4- 4-4-~-4-+-4.- | |||
___ I ~ 4 + + 4- 4 4 ~ + 4-0 0.7 | |||
_0 a) 0.6 Core Height K(Z) 0.000 1.000 N 6.000 1.000 12.000 0.9256 1 1 r 1 0.5 0 | |||
Z 0.4 4-4-4-4-4-4-4-4-4 0.3 0.2 0.1 I- 4- 4 4 4 I 4- + 4- 4 4 0 | |||
0 2 4 6 8 10 12 Core Height (feet) | |||
Figure 2 K(Z) - Normalized FQ(Z) as a Function of Core Height Unit 1 Cycle 9 WATTS BAR Page 7 of 10 Revision 0 | |||
COLR for Watts Bar Unit 1, Cycle 9 120 110 100 90 80 0 | |||
70 E | |||
-C 60 4-50 0 | |||
40 30 20 10 0 | |||
-50 -30 -10 10 30 50 Flux Difference (AI) % | |||
Figure 3 Axial Flux Difference Acceptable Operation Limits as a Function of Rated Thermal Power (RAOC) | |||
Unit 1 Cycle 9 WATTS BAR Page 8 of 10 Revision 1 | |||
COLR for Watts Bar Unit 1, Cycle 9 Table A.1 FQw(Z) = FQC(Z) | |||
* W(Z) | |||
Max W(z) at 150 Max W(z) at 2000 Max W(z) at 4000 Max W(z) at 10000 Max W(z) at 18000 Height (ft) MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU 12.0000 1.0000 1.0000 1.0000 1.0000 1.0000 11.8000 1.0000 1.0000 1.0000 1.0000. 1.0000 11.6000 1.0000 1.0000 1.0000 1.0000 1.0000 11.4000 1.0000 1.0000 1.0000 1.0000 1.0000 11.2000 1.0000 1.0000 1.0000 1.0000 1,0000 11.0000 1.0000 1.0000 1.0000 1.0000 1.0000 10.8000 1.3158 1.3647 1.3317 1.2020 1.1787 10.6000 1.3136 . 1.3556 1.3261 1.1932 1.1745 10.4000 1.3103 1.3436 1.3177 1.1854 1.1703 10.2000 1.3090 1.3295 1.3089 1.1793 1.1644 10.0000 1.3033 1.3142 1.2978 1.1723 1.1600 9.8000 1.2973 1.2965 1.2842 1.1678 1,1558 9.6000 1.2904 1.2817 1.2710 1.1641 1.1555 9.4000 1:2801 1.2715 .1.2619 1.1604 1.1590 9.2000 1.2679 1.2609 1.2571 1.1592 1.1620 9.0000 1.2575 1.2502 1.2509 1.1584 1.1728 8.8000 1.2542 1.2447 1.2475 1.1628 1.1843 8.6000 1.2550 1.2454 . 1.2475 1.1741 1.2001 8.4000 , 1,2601 1.2480 1.2471 1.1861 1.2220 8.2000 1.2620 1.2479 1.2438 1.1970 1.2399 8.0000 1.2619 1,2460 1.2381 1.2057 1.2553 7.8000 1.2597 1.2422 1.2319 1.2121 1.2682 7.6000 1.2554 1.2367 1.2282 1.2164 1.2781 7.4000 , 1.2491 1.2293 1.2269 1.2184 1.2851 7.2000 1.2409 1.2203 1.2228 1.2183 1.2893 7.0000 1.2341 1.2131 1.2168 1.2161 1.2906 6.8000 1.2283 1.2067 1.2095 1.2125 1.2892 6.6000 1.2214 1.1991 1.2008 1.2074 1.2850 6.4000 1.2123 1.1896 1.1902 1.2006 1.2783 6.2000 1.2016 1.1785 1.1782 1.1921 1.2690 6.0000 1.1915 1.1699 1.1688 1.1816 1,2574 5.8000 1.1816 . 1.1610 1.1588 1.1722 1.2435 5.6000 1.1724 1.1518 1.1488 1.1648 1.2273 5.4000 1.1644 1.1447 1.1415 1.1587 1.2093 5.2000 1.1564 1.1371 1.1342 1.1541 1.1943 5.0000 1.1475 1.1291 1.1285 1.1483 1.1897 4.8000 1.1374 1.1213 1.1229 1.1433 1.1876 4.6000 1.1268 1.1136 1.1163 1.1398 1.1827 4.4000 1.1163 . 1.1051 1.1092 1.1365 1.1771 4.2000 1.1069 1.0962 1.1017 1.1345 1.1704 | |||
.4.0000 1.0971 1.0869 1.0937 1.1325 1.1629 3.8000 1.0871 1.0774 1.0857 1.1295 1.1548 3.6000 1.0764 1.0677 1.0772 1.1281 1.1460 3.4000 1.0663 1.0583 1.0697 1.1307 1.1373 3.2000 1.0642 1.0550 1.0710 1.1324 1.1318 3.0000 1.0662 1.0636 1.0820 1.1376 1.1357 2.8000 1.0731 1.0810 1,0998 1.1461 1.1491 2.6000 1.0850 1.0968 1.1167 1.1588 .. 1.1665 2.4000 1.1019 1.1137 1.1344 1.1782 1.1830 2.2000 1.1187 1.1309 1.1522 1.1971 1.1991 2.0000 1.1350 1.1472 1.1699 1.2152 1.2147 1.8000 1.1524 . 1,1658 1.1864 1.2330 1.2297 1.6000 1.1744 1.1906 1.2036 1.2496 1.2439 1.4000 1.2024 1.2205 . 1.2261, 1.2644 1.2564 1.2000 1.2282 1.2480 1.2520 1.2764 1.2664 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 0.8000 1.0000 1.0000 1.0000 1.0000 1.0000 0.6000 1.0000 1.0000 1.0000 1.0000 . 1.0000 0.4000 1.0000 1.0000 1.0000 1.0000 1.0000 0.2000 1.0000 1.0000 1.0000 1.0000 1.0000 0.0000 1.0000 1.0000 1.0000 1.0000 1.0000 | |||
'Unit 1 Cycie 9 WATTS BAR Page 9 of 10 Revision 1 | |||
q COLR for Watts Bar Unit 1, Cycle 9 Table A.2 FQW(Z) Penalty Factor Core FQW(Z) | |||
Burnup Penalty (MWD/MTU) Factor All Burnups 1.0200 Note: | |||
: 1. The Penalty Factor, which is applied to FQw(Z) for compliance with Surveillance Requirement 3.2.1.2.a, is the maximum factor by which FQw(Z) is expected to increase per 31 Effective Full Power Days (EFPD) starting from the burnup at which the FQw(Z) was determined. | |||
Unit 1 Cycle 9 WATTS BAR Page 10 of 10 Revision 0}} |
Latest revision as of 07:05, 14 November 2019
ML091310168 | |
Person / Time | |
---|---|
Site: | Watts Bar ![]() |
Issue date: | 05/06/2009 |
From: | Skaggs M Tennessee Valley Authority |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
Download: ML091310168 (13) | |
Text
Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 MAY 0 6 20O9 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Gentlemen:
In the Matter of the ) Docket No. 50-390 Tennessee Valley Authority )
WATTS BAR NUCLEAR PLANT (WBN) UNIT I - CORE OPERATING LIMITS REPORT (COLR) FOR CYCLE 9, REVISION 1 The purpose of this letter is to provide Revision 1 of the Cycle 9 COLR in accordance with WBN Technical Specification 5.9.5.d. Revision 1 updates the axial flux difference limits and was in effect as of April 23, 2009.
There are no regulatory commitments associated with this submittal. If you have any questions concerning this letter, please contact Mike Brandon, Site Licensing and Industry Affairs Manager, at (423) 365-1824.
Sincerely, Mike Skaggs Site Vice President Watts Bar Nuclear Plant cc: See Page 2
U.S. Nuclear Regulatory Commission Page 2 HAY 0 6 2009 Enclosure cc (Enclosure):
NRC Resident Inspector Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381 U.S. Nuclear Regulatory Commission Mr. John G. Lamb, Senior Project Manager Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation MS 0-8 H1A Washington, DC 20555-0001 U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303
Enclosure Watts Bar Nuclear Plant Unit 1 Cycle 9 Core Operating Limits Report, Revision 1
COLR for. Watts Bar Unit 1, Cycle 9 QA Record L36 090,42.1 807 WATTS: BAR NUCLEAR PLANT,. UNIT 1, CYCLE 9 CORE OPERATING LIMITS REPORT Revision 1 April, 2009 Prepared by:
IdA & I Mý/
Nuclear Fuel Date Ve-rified.by:
Nuclear Fuel Date Reviewed by:~ 63~
Manager,, Nular Fuel Design Date Reactor Engineering Supervisor Date
,Approved by: . . ..
PORC:Chairman
... /. Date Plant Manager Date Date of PORC PORC Meeting Affected:
Revision. Approval Number Pages Reason for Revision 0 3-5-08 4222 1-10 Initial issue i q-p-i** ,9 .. 8.9..
1,.81 Revise:AFD limits and W(z) values Unit 1 Cycle 9 WATTS BAR Page 1 of 10 Revision 1
COLR for Watts Bar Unit 1, Cycle 9 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) -for Watts-,Bar Unit 1 Cycle 9 has been,-prepared -in accordance with the requirements of the Technical Specifications 5.9.5.
The Technical Specifications affected by this report are listed below:
3.1.4 Moderator Temperature Coefficient (MTC) 3.1.6 Shutdown Bank Insertion Limits 3.1.7 Control Bank Insertion Limits 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))
3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F &N) 3.2.3 Axial Flux Difference (AFD) 3.5.1 Accumulators 3.5.4 Refueling Water Storage Tank (RWST) 3.9.1 Boron Concentration 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in section 1.0 are presented in the following subsections. These limits have been developed using the NRC approved methodologies specified in the Technical Specifications Section 5.9.5.
The following abbreviations are used in this section:
BOL -- Beginning of Cycle Life ARO -- All Rods Out HZP -- Hot Zero Thermal Power EOL -- End of Cycle Life RTP -- Rated Thermal Power Unit I Cycle 9 WATTS BAR Page 2 of 10 Revision 0
COLR for Watts Bar Unit 1, Cycle 9 2.1 MODERATOR TEMPERATURE COEFFICIENT - MTC (LCO 3.1.4) 2.1.1 The MTC limits are:
The BOL/ARO/HZP - MTC shall be less positive than or equal to 0 Ak/k/0 F (upper limit). With the measured BOL/ARO/HZP - MTC more positive than -1.00 x 10-5 Ak/k/°F (as-measured MTC limit), establish control rod withdrawal limits to ensure the MTC remains less positive than or equal to 0 Ak/k/0 F (upper limit) for all times in core life.
The EOL/ARO/RTP - MTC shall be less negative than or equal to
-4.5 x 10-4 Ak/k/0 F (lower limit).
2.1.2 The 300 ppm surveillance limit is:
The measured 300 ppm /ARO/RTP-MTC should be less negative than or equal to
-3.75 x 10-4 Ak/k/°F.
2.1.3 The 60 ppm surveillance limit is:
The measured 60 ppm /ARO/RTP-MTC should be less negative than or equal to
-4.28 x 10-4 Ak/k/ 0 F.
2.2 SHUTDOWN BANK INSERTION LIMITS (LCO 3.1.6) 2.2.1 The shutdown banks shall be withdrawn to a position greater than or equal to 225 steps withdrawn.
2.3 CONTROL BANK INSERTION LIMITS (LCO 3.1.7) 2.3.1 The control banks are fully withdrawn or shall be limited in physical insertion as shown in Figure 1.
2.3.2 Each control bank shall be considered fully withdrawn from the core at greater than or equal to 225 steps.
Unit 1 Cycle 9 WATTS BAR Page 3 of 10 Revision 0
COLR for Watts Bar Unit 1, Cycle 9 2.3.3 The control banks shall be operated in sequence by withdrawal of Bank A, Bank B, Bank C, and Bank D. The control banks shall be sequenced in reverse order upon insertion.
2.3.4. Each control ,bank not fully withdrawn from the core shall be operated with the following overlap as a function of park position.
Park Position (steps) BankOverlap (steps) Bank Difference(steps) 225 109 116 226 110 116 227 111 116 228 112 116 229 113 116 230 114 116 231 115 116 2.4 HEAT FLUX HOT CHANNEL FACTOR - FQ(Z) (LCO 3.2.1)
FQ(Z) _ [CFQ / P]
- K(Z) for P > 0.5 FQ(Z) _[CFQ/0.5]
- K(Z) forP*_0.5 Where P = Thermal Power / Rated Thermal Power 2,4.l CFQ = 2.50 214.2 K(Z) is provided in Figure 2.
2.4.3 FQc(Z) = FQM(Z)
- 1.0815 where: FQM(Z) is the measured value of FQ(Z) obtained from incore flux map results and 1.0815 is a factor that accounts for fuel manufacturing tolerances and flux map measurement uncertainty.
2.4.4 FQw(Z) = FQc(Z)
- W(Z) where: W(Z) values are provided in Table A.I. The table provides sufficient information to determine W(Z) versus core height for all cycle bumups.
Unit 1 Cycle 9 WATTS BAI z Page 4 of 10 Revision 0
COLR for Watts Bar Unit 1, Cycle 9 2.4.5 FQw(Z) Penalty Factor The FQw(Z) penalty factor is provided in Table A.2.
2.5 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR - FAHN (LCO 3.2.2)
N R F6H < FAHRTP *( + PF *(l-P))
where P = Thermal Power / Rated Thermal Power FAHRTP = 1.65 for RFA-2 fuel, and PF =0.3 2.6 AXIAL FLUX DIFFERENCE - AFD (LCO 3.2.3) 2.6.1 The AFD limits for Cycle 9 are provided in Figure 3.
2.7 REFUELING BORON CONCENTRATION (LCO 3.9.1) 2.7.1 The refueling boron concentration shall be Ž 2000 ppm.
2.8 ACCUMULATORS (LCO 3.5.1) 2.8.1 ;There are 368 tritium producing burnable absorber rods (TPBARs) in the reactor core for Cycle 9.
2.9 REFUELING WATER STORAGE TANK - RWST (LCO 3.5.4) 2.9.1 There are 368 tritium producing burnable absorber rods (TPBARs) in the reactor core for Cycle 9.
Unit 1 Cycle 9 WATTS BAR Page 5 of 10 Revision 0
COLR for Watts Bar Unit 1, Cycle 9 250 225-(0.197: 225) (0.73, 225)1 200-BANK BI
ý(1.0, 177) 175- I 180) a.
w, 150.
I---
0, z0~
0
]BANK C[
0W125 I--
'- 100' z
0 ]BANK D4 75' (0.0, 64) 50 25 H(0.227, 0)ý 0 iiirrrflrrll 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 FRACTIONAL OF RATED THERMAL POWER Figure 1 Control Bank Insertion Limits Versus Thermal Power Four Loop Operation
- Fully withdrawn region shall be the condition where shutdown and control banks are at a position within the interval of > 225 and < 231 steps withdrawn.
Unit 1 Cycle 9 WATTS BAR Page 6 of 10 Revision 0
COLR for Watts Bar Unit 1, Cycle 9 1.2 1.1 1.0 - ----- _
0.9 0.8 4 4 .1- 4- 4-4-~-4-+-4.-
___ I ~ 4 + + 4- 4 4 ~ + 4-0 0.7
_0 a) 0.6 Core Height K(Z) 0.000 1.000 N 6.000 1.000 12.000 0.9256 1 1 r 1 0.5 0
Z 0.4 4-4-4-4-4-4-4-4-4 0.3 0.2 0.1 I- 4- 4 4 4 I 4- + 4- 4 4 0
0 2 4 6 8 10 12 Core Height (feet)
Figure 2 K(Z) - Normalized FQ(Z) as a Function of Core Height Unit 1 Cycle 9 WATTS BAR Page 7 of 10 Revision 0
COLR for Watts Bar Unit 1, Cycle 9 120 110 100 90 80 0
70 E
-C 60 4-50 0
40 30 20 10 0
-50 -30 -10 10 30 50 Flux Difference (AI) %
Figure 3 Axial Flux Difference Acceptable Operation Limits as a Function of Rated Thermal Power (RAOC)
Unit 1 Cycle 9 WATTS BAR Page 8 of 10 Revision 1
COLR for Watts Bar Unit 1, Cycle 9 Table A.1 FQw(Z) = FQC(Z)
- W(Z)
Max W(z) at 150 Max W(z) at 2000 Max W(z) at 4000 Max W(z) at 10000 Max W(z) at 18000 Height (ft) MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU 12.0000 1.0000 1.0000 1.0000 1.0000 1.0000 11.8000 1.0000 1.0000 1.0000 1.0000. 1.0000 11.6000 1.0000 1.0000 1.0000 1.0000 1.0000 11.4000 1.0000 1.0000 1.0000 1.0000 1.0000 11.2000 1.0000 1.0000 1.0000 1.0000 1,0000 11.0000 1.0000 1.0000 1.0000 1.0000 1.0000 10.8000 1.3158 1.3647 1.3317 1.2020 1.1787 10.6000 1.3136 . 1.3556 1.3261 1.1932 1.1745 10.4000 1.3103 1.3436 1.3177 1.1854 1.1703 10.2000 1.3090 1.3295 1.3089 1.1793 1.1644 10.0000 1.3033 1.3142 1.2978 1.1723 1.1600 9.8000 1.2973 1.2965 1.2842 1.1678 1,1558 9.6000 1.2904 1.2817 1.2710 1.1641 1.1555 9.4000 1:2801 1.2715 .1.2619 1.1604 1.1590 9.2000 1.2679 1.2609 1.2571 1.1592 1.1620 9.0000 1.2575 1.2502 1.2509 1.1584 1.1728 8.8000 1.2542 1.2447 1.2475 1.1628 1.1843 8.6000 1.2550 1.2454 . 1.2475 1.1741 1.2001 8.4000 , 1,2601 1.2480 1.2471 1.1861 1.2220 8.2000 1.2620 1.2479 1.2438 1.1970 1.2399 8.0000 1.2619 1,2460 1.2381 1.2057 1.2553 7.8000 1.2597 1.2422 1.2319 1.2121 1.2682 7.6000 1.2554 1.2367 1.2282 1.2164 1.2781 7.4000 , 1.2491 1.2293 1.2269 1.2184 1.2851 7.2000 1.2409 1.2203 1.2228 1.2183 1.2893 7.0000 1.2341 1.2131 1.2168 1.2161 1.2906 6.8000 1.2283 1.2067 1.2095 1.2125 1.2892 6.6000 1.2214 1.1991 1.2008 1.2074 1.2850 6.4000 1.2123 1.1896 1.1902 1.2006 1.2783 6.2000 1.2016 1.1785 1.1782 1.1921 1.2690 6.0000 1.1915 1.1699 1.1688 1.1816 1,2574 5.8000 1.1816 . 1.1610 1.1588 1.1722 1.2435 5.6000 1.1724 1.1518 1.1488 1.1648 1.2273 5.4000 1.1644 1.1447 1.1415 1.1587 1.2093 5.2000 1.1564 1.1371 1.1342 1.1541 1.1943 5.0000 1.1475 1.1291 1.1285 1.1483 1.1897 4.8000 1.1374 1.1213 1.1229 1.1433 1.1876 4.6000 1.1268 1.1136 1.1163 1.1398 1.1827 4.4000 1.1163 . 1.1051 1.1092 1.1365 1.1771 4.2000 1.1069 1.0962 1.1017 1.1345 1.1704
.4.0000 1.0971 1.0869 1.0937 1.1325 1.1629 3.8000 1.0871 1.0774 1.0857 1.1295 1.1548 3.6000 1.0764 1.0677 1.0772 1.1281 1.1460 3.4000 1.0663 1.0583 1.0697 1.1307 1.1373 3.2000 1.0642 1.0550 1.0710 1.1324 1.1318 3.0000 1.0662 1.0636 1.0820 1.1376 1.1357 2.8000 1.0731 1.0810 1,0998 1.1461 1.1491 2.6000 1.0850 1.0968 1.1167 1.1588 .. 1.1665 2.4000 1.1019 1.1137 1.1344 1.1782 1.1830 2.2000 1.1187 1.1309 1.1522 1.1971 1.1991 2.0000 1.1350 1.1472 1.1699 1.2152 1.2147 1.8000 1.1524 . 1,1658 1.1864 1.2330 1.2297 1.6000 1.1744 1.1906 1.2036 1.2496 1.2439 1.4000 1.2024 1.2205 . 1.2261, 1.2644 1.2564 1.2000 1.2282 1.2480 1.2520 1.2764 1.2664 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 0.8000 1.0000 1.0000 1.0000 1.0000 1.0000 0.6000 1.0000 1.0000 1.0000 1.0000 . 1.0000 0.4000 1.0000 1.0000 1.0000 1.0000 1.0000 0.2000 1.0000 1.0000 1.0000 1.0000 1.0000 0.0000 1.0000 1.0000 1.0000 1.0000 1.0000
'Unit 1 Cycie 9 WATTS BAR Page 9 of 10 Revision 1
q COLR for Watts Bar Unit 1, Cycle 9 Table A.2 FQW(Z) Penalty Factor Core FQW(Z)
Burnup Penalty (MWD/MTU) Factor All Burnups 1.0200 Note:
- 1. The Penalty Factor, which is applied to FQw(Z) for compliance with Surveillance Requirement 3.2.1.2.a, is the maximum factor by which FQw(Z) is expected to increase per 31 Effective Full Power Days (EFPD) starting from the burnup at which the FQw(Z) was determined.
Unit 1 Cycle 9 WATTS BAR Page 10 of 10 Revision 0