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{{#Wiki_filter:Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 May 20,2014 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555-0001
{{#Wiki_filter:Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 May 20,2014 10 cFR 5A.4 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 1 Facility Operating License No. NPF-90 NRC Docket No.50-390


==Subject:==
==Subject:==
10 cFR 5A.4 Watts Bar Nuclear Plant, Unit 1 Facility Operating License No. NPF-90 NRC Docket No.50-390 REVISION O OF THE CYCLE 13 GORE OPERATING LIII'IITS REPORT (coLR)Pursuant to Watts Bar Nuclear Plant Technical Specifications Section 5.9.5.d, Tennessee Valley Authority (TVA) has enclosed Revision 0 of the Unit 1 Cycle 13 COLR. The analytical methods used to determine the core operating limits were previously reviewed and approved by the NRC.There are no regulatory commitments contained in this letter or the enclosure.
REVISION       O OF THE CYCLE 13 GORE OPERATING LIII'IITS REPORT (coLR)
Should you have questions regarding this submittal, please contact Russell A. Stroud at (423)365-1435.Respectfully,%,,44*"k 6nristopner R. church /Site Vice President Watts Bar Nuclear Plant Watts Bar Nuclear Plant, Unit 1, Cycle 13 Core Operating Limits Report Revision 0 March 2014
Pursuant to Watts Bar Nuclear Plant Technical Specifications Section 5.9.5.d, Tennessee Valley Authority (TVA) has enclosed Revision 0 of the Unit 1 Cycle 13 COLR. The analytical methods used to determine the core operating limits were previously reviewed and approved by the NRC.
There are no regulatory commitments contained in this letter or the enclosure. Should you have questions regarding this submittal, please contact Russell A. Stroud at (423) 365-1435.
Respectfully,
%,,44*"k 6nristopner R. church           /
Site Vice President Watts Bar Nuclear Plant


==Enclosure:==
==Enclosure:==
Watts Bar Nuclear Plant, Unit 1, Cycle 13 Core Operating Limits Report Revision 0 March 2014


U.S. Nuclear Regulatory Commission Page 2 cc (Enclosure):
U.S. Nuclear Regulatory Commission Page 2 cc (Enclosure):
NRC Regional Administrator - Region ll NRR Project Manager - Watts Bar Nuclear Plant NRC Senior Resident lnspector - Watts Bar Nuclear Plant, Unit 1 Enclosure Watts Bar Nuclear Plant, Unit 1, Cycle 13 Core Operating Limits Report Revision 0 March 2014 Prepared by: QA Record 136 140320 800 WATTS BAR NUCLEAR PIANT, UNIT 1, CYCLE 13 CORE OPERATING LIMITS REPORT Revision 0 March 2014 Date LJ/C L,!,^tu*u ,n., ,@nase' oai-f, +14q Reviewed by: 3r.t m .E'rc,l* ^ t I /25 /zo*Manager, PWR Nuclear Fuels Engineering Approved by: 0.P b,eokar*n PORC Chairman Plant Manager Revision Date of PORC Approval PORC Meeting Number Affected Paqes Reason fnr Revision 0 3'27, tt{{14{all initial issue Unit 1 Watts Bar Cycle 13 Revision 0 Page 1 of 10 1.0 2.0 Unit I WATTS BAR BOL ARO HZP EOL RTP CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Watts Bar Unit 1 Cycle 13 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.I.7 Control Bank Insertion Limits 3.2.1 Heat Flux Hot Channel Factor (Fq(Z))3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (Far)3.2.3 Axial Flux Difference (AFD)3.5.1 Accumulators 3.5.4 Refueling Water Storage Tank (RWST)3.9.I BoronConcentration OPERATINGLIMITS The cycle-specific parameter limits for the specifications listed in section 1.0 are presented in the following subsections.
NRC Regional Administrator - Region ll NRR Project Manager - Watts Bar Nuclear Plant NRC Senior Resident lnspector - Watts Bar Nuclear Plant, Unit 1
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: Beginning of Cycle Life A11 Rods Out Hot Zero Thermal Power End of Cycle Life Rated Thermal Power Cycle 13 Revision 0 Page 2 of 10 2.1 MODERATOR TEMPERATURE COEF'F'ICIENT . MTC (LCO 3.1.4)2.1.1 The MTC limits are: The AROIHZP - MTC shall be less positive than or equal to 0 AldldoF (upper limil.With the measured BOL/ARO/HZP - MTC more positive than -1.17 x l0-5 Ak/ldoF (as-measured MTC limit), establish confrol rod withdrawal limits to ensure the MTC remains less positive than or equal to 0 AldldoF (upper limit) for all times in core life.The EOL/ARO/RTP - MTC shall be less negative than or equal to 4.5 x 104 LklW"F (lowerlimi!.
 
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 104 Ak/ldoF.2.1.3 The 60 ppm surveillance limit is: The measured 60 ppm /ARO/RTP-MTC should be less negative than or equal to 4.28x 104 Ak/l/oF.2.2 SHUTDOWN BAIIK INSERTION LIMTTS (LCO 3.1.6)2.2.1 The shutdown banks shall be withdrawn to a position greater than or eqtnlto 225 steps withdrawn.
Enclosure Watts Bar Nuclear Plant, Unit 1, Cycle 13 Core Operating Limits Report Revision 0 March 2014
2.3 CONTROL BArYK INSERTION LrLrTS (LCO 3.1.4 2.3.1 The control banks are fully withdrawn or shall be limited in physical insertion as shown in Figure 1.2.3.2Eachcontrol bank shall be considered fully withdrawn from the core at greater than or equal to 225 steps.2.3.3 Thecontrol banks shall be operated in sequence by withdrawal of Bank A, Bank B, Bank C, and Bank D. The confrol banla shall be sequenced in reverse order upon insertion.
 
Cycle 13 Revision 0 Unit I WATTS BAR Page 3 of l0 2.3.4Each control bank not fully withdrawn from the core shall be operated with the following overlap as a fimction of park position.2.4 Unit I WATTS BAR HEAT FLUX HOT CHANNEL FACTOR -Fo(Z) (LCO 3.2.1)Fa(Z) s [CFQ/ P]
QA Record 136 140320 800 WATTS BAR NUCLEAR PIANT, UNIT 1, CYCLE 13 CORE OPERATING LIMITS REPORT Revision 0 March 2014 Prepared by:
* K(Z) for P > 0.5 Fq(Z)< [CFQ/0.s]
Reviewed by:
* K(z) forP( 0.5 Where P : Thermal Power / Rated Thermal Power 2.4.1 CFQ =2.50 2.4.2 K(Z) is provided in Figure 2.2A3 F aw (Z) = Fq"(Z)
Manager, PWR Nuclear Fuels Engineering 3r.t     m .E'rc,l*
                                                                ^   t I /25 Date
                                                                              /zo*
LJ/C                              L,!,^tu*u                      ,n.,      ,
@nase'                                                              oai-Approved by:
0.P b,eokar*n PORC Chairman f, +14q Plant Manager Date of   PORC PORC     Meeting     Affected Revision    Approval  Number       Paqes       Reason fnr Revision 0       3'27, tt{ {14{             all       initial issue Unit 1                                                                             Cycle 13 Watts Bar                                   Page 1 of 10                           Revision 0
 
1.0   CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Watts Bar Unit 1 Cycle 13 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.I.7   Control Bank Insertion Limits 3.2.1   Heat Flux Hot Channel Factor (Fq(Z))
3.2.2   Nuclear Enthalpy Rise Hot Channel Factor (Far) 3.2.3   Axial Flux Difference (AFD) 3.5.1   Accumulators 3.5.4   Refueling Water Storage Tank (RWST) 3.9.I   BoronConcentration 2.0    OPERATINGLIMITS 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            A11 Rods Out HZP            Hot Zero Thermal Power EOL            End of Cycle Life RTP            Rated Thermal Power Unit I                                                                                    Cycle 13 WATTS BAR                                Page 2 of 10                                   Revision 0
 
2.1   MODERATOR TEMPERATURE COEF'F'ICIENT . MTC (LCO 3.1.4) 2.1.1 The MTC limits are:
The AROIHZP - MTC shall be less positive than or equal to 0 AldldoF (upper limil.
With the measured BOL/ARO/HZP - MTC more positive than -1.17 x l0-5 Ak/ldoF (as-measured MTC limit), establish confrol rod withdrawal limits to ensure the MTC remains less positive than or equal to 0 AldldoF (upper limit) for all times in core life.
The EOL/ARO/RTP - MTC shall be less negative than or equal to 4.5 x 104 LklW"F (lowerlimi!.
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 104 Ak/ldoF.
2.1.3 The 60 ppm surveillance limit is:
The measured 60 ppm /ARO/RTP-MTC should be less negative than or equal to 4.28x 104 Ak/l/oF.
2.2   SHUTDOWN BAIIK INSERTION LIMTTS (LCO 3.1.6) 2.2.1 The shutdown banks shall be withdrawn to     a position greater than or eqtnlto 225 steps withdrawn.
2.3   CONTROL BArYK INSERTION LrLrTS (LCO 3.1.4 2.3.1 The control banks are fully withdrawn or shall be limited in physical insertion   as shown in Figure 1.
2.3.2Eachcontrol bank shall be considered fully withdrawn from the core at greater than or equal to 225 steps.
2.3.3 Thecontrol banks shall be operated in sequence by withdrawal of Bank A, Bank B, Bank C, and Bank D. The confrol banla shall be sequenced in reverse order upon insertion.
Unit I                                                                                    Cycle 13 WATTS BAR                               Page 3 of l0                                 Revision 0
 
2.3.4Each control bank not fully withdrawn from the core shall be operated with the following overlap as a fimction of park position.
Park Position (steps)            Bank Overlap (steps)            B ank Difference (steps) 225                                109                            116 226                                110                            116 227                                lll                            116 228                                tt2                            116 229                                I l3                          116 230                                114                            116 231                                115                            I l6 2.4   HEAT FLUX HOT CHANNEL FACTOR -Fo(Z) (LCO 3.2.1)
Fa(Z) s [CFQ/ P]
* K(Z)     for P > 0.5 Fq(Z)< [CFQ/0.s]
* K(z) forP( 0.5 Where P : Thermal Power / Rated Thermal Power 2.4.1 CFQ =2.50 2.4.2 K(Z) is provided in Figure 2.
2A3   F aw (Z) = Fq"(Z)
* W(Z)1P for P > 0.5 Fq*(Z) = Fq"(4
* W(Z)1P for P > 0.5 Fq*(Z) = Fq"(4
* W(4t0.5 for P < 0.5 where: W(Z) values are provided in Table A.l. The table provides suffrcient information to determine W(Z) versus core height for all cycle burnups.2.4.4 Part power W(Z) values are only required to be used when the part power surveillance is performed using the moveable incore detector system.2.4.5 Faw(Z) Penalty Factor The Faw(Z) penalty factor is provided in Table A.2.Park Position (steps)225 226 227 228 229 230 231 Bank Overlap (steps)109 110 lll tt2 I l3 114 115 B ank Difference (steps)116 116 116 116 116 116 I l6 Cycle 13 Revision 0 Page 4 of 10 2.5 NUCLEAR ENTHALPY RrSE HOT CHAI\NEL FACTOR- FasN (LCO 3.2.2)F**iF*** * ( 1 +PF * ( 1-P))where P = Thermal Power / Rated Thermal Power F*"* = 1.65 forMA-2 fuel, and PF = 0.3 2.6 AXrAL FLUX DIFFERENCE - AFD (LCO 3.2.3)2.6.1 The AFD limits for Cycle 13 are provided in Figure 3.2.7 REFITELTNG BORON CONCENTRATION (LCO 3.9.1)2.7.1 The refueling boron concentration shall be ) 2000 ppm.2.8 ACCUMULATORS (LCO 3.5.1)2.8.1 There are 704 tritium producing bumable absorber rods (TPBARs) in the reactor core for Cycle 13.2.9 REFUELTNG WATER STORAGE TAIIK - RWST (LCO 3.5.4)2.9. 1 There are 704 tritium producing bumable absorber rods (TPBARs) in the reactor core for Cycle 13.Unit I WATTS BAR Cycle 13 Revision 0 Page 5 of l0 250 225 200 50 25 Unit I WATTS BAR? L7s G, a-I E=ffio tn 4 lr!F 9=" L25-F 6 o o.o.H 100 tn-z 6 61?ot)c, re 22sl i t (0.197, 2251 t 4 a z - - -.D //.r,,,.'-...,.?
* W(4t0.5 for P < 0.5 where: W(Z) values are provided in Table A.l. The table provides suffrcient information to determine W(Z) versus core height for all cycle burnups.
/ /., I)i 3 il /., 2 il + De'4'-'...-,, Z 1,,,,,., ......',.I ,7^l/-D ii/o l,., i, lrl f:',,. ". ::.':::",:, i, l-I (0.0, 190),:^/i I' " - ;.' -'---*' l -"'"* "
2.4.4 Part power W(Z) values are only required to be used when the part power surveillance is performed using the moveable incore detector system.
* i- " t.:*i'**"i"-*" ,,t *7/!, t^/\NK ql-i,,...,,.
2.4.5 Faw(Z) Penalty Factor The Faw(Z) penalty factor is provided in Table A.2.
",,.,",.,,,,,,,,/i--*7,---'
Unit I                                                                                 Cycle 13 WATTS BAR                                  Page 4   of 10                             Revision 0
i *--T*-"**:", 7:1/::: iil -,,..,..,,,.,...."....).....,.............,.
 
',i ,^/, I/tlf t.1^l//'i//'1*******1 i t^/),,/ii/t , i/1 4"i ,i1//T,-1 1i ,,j,,,,,,,,,,,,,,,,,,,,, -,, !=/1 1 ,^1 t lix t.t I^/1 1 1 , i Cycle 13 Revision 0 0.0 o.2 0,4 0.5 0.8 1.0 FRAC.tloN OF RATEDTHERMAT POWER Figure I Control Bank Insertion Limits Versus Thermal Power Four Loop Operation Fully withdrawn region shall be the condition where shutdown and control ba::ks are at a position within the interval of 2225 and,323l steps withdrawn Page 6 of l0 1.1 1.2 1.0 0.9 0.8 o.7 0.6 0.5 o.4 0.3 o.2 0.1 0 L (t)=o o-{.o lJ-E (I).N-(tr E L o=2 0 468 Core Height (feet)Figure 2 K(Z) - Normalized Fq(Z) as a Function of Core Height 10 12 Unit I WATTS BAR Cycle 13 Revision 0 E--Heioht K{ZI lo I6 000 1.000 000 1.oo0 I 12,ooo 0.9256 Page 7 of l0 1 F1z, 1-I (7 , 10r-I 00)r 0)r I\IF i ACCeptaDre Operation\I I\""*ptd Speratiol Gt-r--]--_l unacceptaDle r--l ooeration L-I\t--t I\I\I\I\I\@-50 40 20 -10 0 10 20 30 40 50 Flux Difierence (Al) %Figure 3 Axial Flux Difference Acceptable Operation Limits as a function of Rated Thermal Power (RAOC)120 110 100 90 80 40 30 20 10 Unit 1 WATTS BAR b=o L70 E E o foo E'g (U fso o s Cycle 13 Revision 0 Page 8 of l0 Unit I WATTS BAR Table A.1 Fq*(Z):Fqt(Z)*W(Z)
2.5   NUCLEAR ENTHALPY RrSE HOT CHAI\NEL FACTOR- FasN (LCO 3.2.2)
Cycle 13 Revision 0 Height (ft)Max W(z)at 150 MWDA{TU (30%Power)Max W(z)at 150 MWDA{TU (7s%Power)Max W(z)at 150 MWDA{TU (t00%Power)Max W(z)at 2000 MWDA{TU (100o/o Power)Max W(z)at 10000 MWDA/ITU (r00%Power)Max W(z)at 16000 MWDA{TU (100%Power)12.0748 r.0000 1.0000 1.0000 1.0000 1.0000 1.0000 11.8736 1.0000 r.0000 1.0000 1.0000 1.0000 r.0000 11.6723 1.0000 1.0000 1.0000 1.0000 1.0000 1,0000 tt.47tt 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 u.2698 r.0000 1.0000 1.0000 r.0000 1.0000 1,0000 11.0686 r.0000 1.0000 1.0000 1.0000 1,0000 1.0000 10.8673 1.2647 1.2807 l.213l 1.2352 r.r969 r.2189 10.6661 1.2510 1.2622 1.2096 1.2341 1.1900 1.2116 10.4648 1.2336 1.2391 1.2037 r.2309 1.1851 1.2002 10.2636 1.21,40 1.2178 1.1968 1.2308 r.r786 1.1952 r0.0623 1.2019 1.2038 1.1950 1.2293 l.l714 1.1755 9.8611 l.l9l9 1.1919 1.1952 1.2263 l.162l 1.1692 9.6598 1.1805 1.1789 1.1945 1.2239 1.1557 1.1610 9.4586 1.1660 1.1637 l.l9l4 1.2187 1.1596 1.1524 9.2573 1.1507 1.1482 1.1874 t.ztm 1.1639 l.l47l 9.0s61 r.1367 1.1349 1.1850 1.2096 l.l6g0 1.1493 8.8549 1.1220 l.l2l7 1.1808 1.2132 1.1735 1.1529 8.6536 l.l14l t.tt44 t.t796 1.2179 1.1829 1.1588 8.4524 1.1228 1.r233 1.1939 1.2225 1.1985 1.1790 8.251r 1.1222 1.1329 1.2079 t.224r l.2l15 1.1970 8.0499 1.1097 1.1402 1.2185 r.2234 1.2215 1.2rr8 7.8486 1.0909 1.1461 r.2266 1.2197 1.2292 1.2247 7.il74 1.0804 1.1503 1.23t9 1.2153 1.2343 1.23s0 7.4/,61 1.0707 1.1530 1.2346 1.2175 1.2368 1.2428 7.24/i9 1.0623 1.1538 1.2349 1.2168 1.2368 1.2479 7.0436 1.0566 1.1523 1.2327 1.2134 1.234d 1.2506 6.8/,24 r.0517 1.1492 1.2287 1.2086 1.2298 r.2s08 6.6411 1.0477 1.1458 1.2231 1.2024 1.2231 1.2489 6.4399 1.0441 1.1415 1.2157 1.1943 t.ztu 1.2452 6.2386 1.0417 1.1374 1.2080 1.1843 1.2037 1.2393 6.0374 r.0406 1.1343 1.2015 1.17s1 l.l9l5 t.2312 s.8362 r.0396 1.1307 1.1942 1.1667 1.1772 l.22ll s.6349 r.0384 1.1263 1.1858 1.r583 1.1il9 1.2089 5.4337 1.0394 1.1236 1.1792 1.1525 1.1616 1.1949 5.2324 1.0414 t.t2t4 1.1727 1.1499 1.r583 l.l83l 5.0312 1.0434 1.1187 1.1654 1.1479 1.1539 1.1801 4.8299 L4477 1.1180 1.1598 1.1450 l.l52l 1.1794 4.6287 1.0549 l.ll97 1.1567 t.t4t4 1.1529 1.1767 4.4274 1.0508 1.1196 1.1522 1.1370 1.1526 1.1733 4.2262 1.0666 1.1196 1.t470 r.1320 1.1519 1.1689 4.0249 1.0721 1.1175 l.l4l4 1.1267 r.1505 1.1636 3.8237 1.07il 1.1150 1.1343 1.1202 r.1498 1.1578 3.6224 r.0829 1.1145 1.1292 l.ll5l 1.1509 1.1514 3.4212 1.0962 1.1204 1.1309 1.ll52 1.1553 1.14s1 3.2199 1.1il2 1.1274 r.1336 l.1162 1.1516 1.1455 3.0r87 t.l2s1 1.1335 1.1350 1.1255 l.lu6 1.1499 2.8175 1.1418 1.1420 l.l3gg l.l4/,g 1.1724 1.1631 2.6162 1.1663 t.1579 1.1499 1.1685 1.1893 1.1823 2.4150 l.l9g5 1.1810 r.r683 1.1919 1.2088 r.2004 2.2137 1.2337 1.2061 1.1887 1.2153 1.2280 r.2r80 2.012s r.2681 1.2310 1.2088 1.2383 1.2466 1.2351 1.8112 1.3021 1.2555 1.2282 1.250s L2A4 1.2514 1.6100 1.3376 1.2793 1.2466 1.2816 l.28ll 1.2666 r.4087 1.3702 1.3008 1.2631 1.3005 1.2958 1,2800 1.2075 1.3989 1.3184 1.2765 1.3163 1.3073 1.2903 1.0062 1.0000 1.0000 1.0000 1.0000 r.0000 1.0000 0.8050 1.0000 1.0000 1.0000 r.0000 1,0000 1.0000 0.6037 1.0000 1.0000 1.0000 1.0000 1.0000 1,0000 0,4025 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 0.2012 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 0.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Page 9 of 10 Table A.2 Fo*(Z) Penalty Factor Core Burnup GrnwD/IvITfI)
F**iF***       * ( 1 +PF * ( 1-P))
Fa"(J Penalty Factor All Elurnrrps 1.O?OO Note: 1. The Penalty Factor, which is applied to Faw(Z) for compliance with Surveillance Requirement 3.2.1.2.a,is the maximum factor by which Fq*(Z) is expected to increase per 3l Effective Full Power Days (EFPD) starting from the bumup at which the fowlZ; was deterrrined.
where P = Thermal Power / Rated Thermal Power F*"*     = 1.65 forMA-2 fuel, and PF       = 0.3 2.6   AXrAL FLUX DIFFERENCE - AFD (LCO 3.2.3) 2.6.1 The AFD limits for Cycle 13 are provided in Figure 3.
Unit I WATTS BAR Cycle 13 Revision 0 Page l0 of l0}}
2.7   REFITELTNG BORON CONCENTRATION (LCO 3.9.1) 2.7.1 The refueling boron concentration shall be ) 2000 ppm.
2.8   ACCUMULATORS (LCO 3.5.1) 2.8.1 There are 704 tritium producing bumable absorber rods (TPBARs) in the reactor core for Cycle 13.
2.9   REFUELTNG WATER STORAGE TAIIK                 - RWST (LCO 3.5.4) 2.9. 1 There are 704 tritium producing bumable absorber rods (TPBARs) in the reactor core for Cycle 13.
Unit I                                                                             Cycle  13 WATTS BAR                               Page 5 of l0                           Revision 0
 
250 re                                                                                              i 22sl                                                                            t 225                                                                                                                                             Z t  4az -  - -.D //.r,,,.'-...,.? / /., 1,,,,,., ......',.
(0.197, 2251                              3 il /.,
I
                                                                                                                                  )
i 2 il + De'4'-'...-,,
I
                                                                                                                                                              ,7
                                                                                                                                                                                      ^l 200
                                                                                                                                                                                  /-
D o
ii/
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0        2          468                            10            12 Core Height (feet)
Figure 2 K(Z) - Normalized Fq(Z) as a Function of Core Height Unit I                                                                       Cycle  13 WATTS BAR                         Page 7 of l0                              Revision 0
 
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40 30 20 10
            -50 40          -30    10             0         10           20 30     40     50 Flux Difierence (Al) %
Figure 3 Axial Flux Difference Acceptable Operation Limits as a function of Rated Thermal Power (RAOC)
Unit 1                                                                                     Cycle 13 WATTS BAR                               Page 8    of l0                                  Revision 0
 
Table A.1 Fq*(Z):Fqt(Z)*W(Z)
Max W(z) Max W(z)   Max W(z) Max W(z) Max W(z) Max W(z) at 150   at 150      at 150  at 2000  at 10000  at 16000 MWDA{TU   MWDA{TU    MWDA{TU  MWDA{TU   MWDA/ITU MWDA{TU Height    (30%      (7s%       (t00%    (100o/o  (r00%    (100%
(ft)  Power)    Power)      Power)    Power)    Power)    Power) 12.0748   r.0000   1.0000     1.0000   1.0000   1.0000   1.0000 11.8736   1.0000   r.0000     1.0000   1.0000   1.0000   r.0000 11.6723   1.0000   1.0000     1.0000   1.0000   1.0000   1,0000 tt.47tt   1.0000   1.0000     1.0000   1.0000   1.0000   1.0000 u.2698     r.0000   1.0000     1.0000   r.0000   1.0000   1,0000 11.0686   r.0000   1.0000     1.0000   1.0000   1,0000   1.0000 10.8673   1.2647   1.2807     l.213l   1.2352   r.r969   r.2189 10.6661   1.2510   1.2622     1.2096   1.2341   1.1900   1.2116 10.4648   1.2336   1.2391     1.2037   r.2309   1.1851   1.2002 10.2636   1.21,40   1.2178     1.1968   1.2308   r.r786   1.1952 r0.0623   1.2019   1.2038     1.1950   1.2293   l.l714   1.1755 9.8611   l.l9l9   1.1919     1.1952   1.2263   l.162l   1.1692 9.6598   1.1805   1.1789     1.1945   1.2239   1.1557   1.1610 9.4586   1.1660   1.1637     l.l9l4   1.2187   1.1596   1.1524 9.2573   1.1507   1.1482     1.1874   t.ztm     1.1639   l.l47l 9.0s61   r.1367   1.1349     1.1850   1.2096   l.l6g0   1.1493 8.8549   1.1220   l.l2l7     1.1808   1.2132   1.1735   1.1529 8.6536   l.l14l   t.tt44     t.t796   1.2179   1.1829   1.1588 8.4524   1.1228   1.r233     1.1939   1.2225   1.1985   1.1790 8.251r   1.1222   1.1329     1.2079   t.224r   l.2l15   1.1970 8.0499   1.1097   1.1402     1.2185   r.2234   1.2215   1.2rr8 7.8486   1.0909   1.1461     r.2266   1.2197   1.2292   1.2247 7.il74   1.0804   1.1503     1.23t9   1.2153   1.2343   1.23s0 7.4/,61   1.0707   1.1530     1.2346   1.2175   1.2368   1.2428 7.24/i9   1.0623   1.1538     1.2349   1.2168   1.2368   1.2479 7.0436   1.0566   1.1523     1.2327   1.2134   1.234d   1.2506 6.8/,24   r.0517   1.1492     1.2287   1.2086   1.2298   r.2s08 6.6411     1.0477   1.1458     1.2231   1.2024   1.2231   1.2489 6.4399     1.0441   1.1415     1.2157   1.1943   t.ztu     1.2452 6.2386     1.0417   1.1374     1.2080   1.1843   1.2037   1.2393 6.0374     r.0406   1.1343     1.2015   1.17s1   l.l9l5   t.2312 s.8362     r.0396   1.1307     1.1942   1.1667   1.1772   l.22ll s.6349     r.0384   1.1263     1.1858   1.r583   1.1il9   1.2089 5.4337     1.0394   1.1236     1.1792   1.1525   1.1616   1.1949 5.2324     1.0414   t.t2t4     1.1727   1.1499   1.r583   l.l83l 5.0312     1.0434   1.1187     1.1654   1.1479   1.1539   1.1801 4.8299     L4477     1.1180     1.1598   1.1450   l.l52l   1.1794 4.6287     1.0549   l.ll97     1.1567   t.t4t4   1.1529   1.1767 4.4274     1.0508   1.1196     1.1522   1.1370   1.1526   1.1733 4.2262     1.0666   1.1196     1.t470   r.1320   1.1519   1.1689 4.0249     1.0721   1.1175     l.l4l4   1.1267   r.1505   1.1636 3.8237     1.07il   1.1150     1.1343   1.1202   r.1498   1.1578 3.6224     r.0829   1.1145     1.1292   l.ll5l   1.1509   1.1514 3.4212     1.0962   1.1204     1.1309   1.ll52   1.1553   1.14s1 3.2199     1.1il2   1.1274     r.1336   l.1162   1.1516   1.1455 3.0r87     t.l2s1   1.1335     1.1350   1.1255   l.lu6     1.1499 2.8175     1.1418   1.1420     l.l3gg   l.l4/,g   1.1724   1.1631 2.6162     1.1663   t.1579     1.1499   1.1685   1.1893   1.1823 2.4150     l.l9g5   1.1810     r.r683   1.1919   1.2088   r.2004 2.2137     1.2337   1.2061     1.1887   1.2153   1.2280   r.2r80 2.012s     r.2681   1.2310     1.2088   1.2383   1.2466   1.2351 1.8112   1.3021   1.2555     1.2282   1.250s   L2A4     1.2514 1.6100   1.3376   1.2793     1.2466   1.2816   l.28ll   1.2666 r.4087   1.3702   1.3008     1.2631   1.3005   1.2958   1,2800 1.2075   1.3989   1.3184     1.2765   1.3163   1.3073   1.2903 1.0062   1.0000   1.0000     1.0000   1.0000   r.0000   1.0000 0.8050     1.0000   1.0000     1.0000   r.0000   1,0000   1.0000 0.6037     1.0000   1.0000     1.0000   1.0000   1.0000   1,0000 0,4025     1.0000   1.0000     1.0000   1.0000   1.0000   1.0000 0.2012     1.0000   1.0000     1.0000   1.0000   1.0000   1.0000 0.0000     1.0000   1.0000     1.0000   1.0000   1.0000   1.0000 Unit I                                                                            Cycle  13 WATTS BAR                          Page 9 of   10                               Revision 0
 
Table A.2 Fo*(Z) Penalty Factor Core                 Fa"(J Burnup                 Penalty GrnwD/IvITfI)                 Factor All Elurnrrps             1.O?OO Note:
: 1. The Penalty Factor, which is applied to Faw(Z) for compliance with Surveillance Requirement 3.2.1.2.a,is the maximum factor by which Fq*(Z) is expected to increase per 3l Effective Full Power Days (EFPD) starting from the bumup at which the fowlZ; was deterrrined.
Unit I                                                                                 Cycle 13 WATTS BAR                               Page l0 of l0                               Revision 0}}

Revision as of 05:04, 4 November 2019

Revision 0 of the Cycle 13 Core Operating Limits Report (COLR)
ML14141A084
Person / Time
Site: Watts Bar Tennessee Valley Authority icon.png
Issue date: 05/20/2014
From: Church C
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML14141A084 (13)


Text

Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 May 20,2014 10 cFR 5A.4 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 1 Facility Operating License No. NPF-90 NRC Docket No.50-390

Subject:

REVISION O OF THE CYCLE 13 GORE OPERATING LIII'IITS REPORT (coLR)

Pursuant to Watts Bar Nuclear Plant Technical Specifications Section 5.9.5.d, Tennessee Valley Authority (TVA) has enclosed Revision 0 of the Unit 1 Cycle 13 COLR. The analytical methods used to determine the core operating limits were previously reviewed and approved by the NRC.

There are no regulatory commitments contained in this letter or the enclosure. Should you have questions regarding this submittal, please contact Russell A. Stroud at (423) 365-1435.

Respectfully,

%,,44*"k 6nristopner R. church /

Site Vice President Watts Bar Nuclear Plant

Enclosure:

Watts Bar Nuclear Plant, Unit 1, Cycle 13 Core Operating Limits Report Revision 0 March 2014

U.S. Nuclear Regulatory Commission Page 2 cc (Enclosure):

NRC Regional Administrator - Region ll NRR Project Manager - Watts Bar Nuclear Plant NRC Senior Resident lnspector - Watts Bar Nuclear Plant, Unit 1

Enclosure Watts Bar Nuclear Plant, Unit 1, Cycle 13 Core Operating Limits Report Revision 0 March 2014

QA Record 136 140320 800 WATTS BAR NUCLEAR PIANT, UNIT 1, CYCLE 13 CORE OPERATING LIMITS REPORT Revision 0 March 2014 Prepared by:

Reviewed by:

Manager, PWR Nuclear Fuels Engineering 3r.t m .E'rc,l*

^ t I /25 Date

/zo*

LJ/C L,!,^tu*u ,n., ,

@nase' oai-Approved by:

0.P b,eokar*n PORC Chairman f, +14q Plant Manager Date of PORC PORC Meeting Affected Revision Approval Number Paqes Reason fnr Revision 0 3'27, tt{ {14{ all initial issue Unit 1 Cycle 13 Watts Bar Page 1 of 10 Revision 0

1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Watts Bar Unit 1 Cycle 13 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.I.7 Control Bank Insertion Limits 3.2.1 Heat Flux Hot Channel Factor (Fq(Z))

3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (Far) 3.2.3 Axial Flux Difference (AFD) 3.5.1 Accumulators 3.5.4 Refueling Water Storage Tank (RWST) 3.9.I BoronConcentration 2.0 OPERATINGLIMITS 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 A11 Rods Out HZP Hot Zero Thermal Power EOL End of Cycle Life RTP Rated Thermal Power Unit I Cycle 13 WATTS BAR Page 2 of 10 Revision 0

2.1 MODERATOR TEMPERATURE COEF'F'ICIENT . MTC (LCO 3.1.4) 2.1.1 The MTC limits are:

The AROIHZP - MTC shall be less positive than or equal to 0 AldldoF (upper limil.

With the measured BOL/ARO/HZP - MTC more positive than -1.17 x l0-5 Ak/ldoF (as-measured MTC limit), establish confrol rod withdrawal limits to ensure the MTC remains less positive than or equal to 0 AldldoF (upper limit) for all times in core life.

The EOL/ARO/RTP - MTC shall be less negative than or equal to 4.5 x 104 LklW"F (lowerlimi!.

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 104 Ak/ldoF.

2.1.3 The 60 ppm surveillance limit is:

The measured 60 ppm /ARO/RTP-MTC should be less negative than or equal to 4.28x 104 Ak/l/oF.

2.2 SHUTDOWN BAIIK INSERTION LIMTTS (LCO 3.1.6) 2.2.1 The shutdown banks shall be withdrawn to a position greater than or eqtnlto 225 steps withdrawn.

2.3 CONTROL BArYK INSERTION LrLrTS (LCO 3.1.4 2.3.1 The control banks are fully withdrawn or shall be limited in physical insertion as shown in Figure 1.

2.3.2Eachcontrol bank shall be considered fully withdrawn from the core at greater than or equal to 225 steps.

2.3.3 Thecontrol banks shall be operated in sequence by withdrawal of Bank A, Bank B, Bank C, and Bank D. The confrol banla shall be sequenced in reverse order upon insertion.

Unit I Cycle 13 WATTS BAR Page 3 of l0 Revision 0

2.3.4Each control bank not fully withdrawn from the core shall be operated with the following overlap as a fimction of park position.

Park Position (steps) Bank Overlap (steps) B ank Difference (steps) 225 109 116 226 110 116 227 lll 116 228 tt2 116 229 I l3 116 230 114 116 231 115 I l6 2.4 HEAT FLUX HOT CHANNEL FACTOR -Fo(Z) (LCO 3.2.1)

Fa(Z) s [CFQ/ P]

  • K(Z) for P > 0.5 Fq(Z)< [CFQ/0.s]
  • K(z) forP( 0.5 Where P : Thermal Power / Rated Thermal Power 2.4.1 CFQ =2.50 2.4.2 K(Z) is provided in Figure 2.

2A3 F aw (Z) = Fq"(Z)

  • W(Z)1P for P > 0.5 Fq*(Z) = Fq"(4
  • W(4t0.5 for P < 0.5 where: W(Z) values are provided in Table A.l. The table provides suffrcient information to determine W(Z) versus core height for all cycle burnups.

2.4.4 Part power W(Z) values are only required to be used when the part power surveillance is performed using the moveable incore detector system.

2.4.5 Faw(Z) Penalty Factor The Faw(Z) penalty factor is provided in Table A.2.

Unit I Cycle 13 WATTS BAR Page 4 of 10 Revision 0

2.5 NUCLEAR ENTHALPY RrSE HOT CHAI\NEL FACTOR- FasN (LCO 3.2.2)

F**iF*** * ( 1 +PF * ( 1-P))

where P = Thermal Power / Rated Thermal Power F*"* = 1.65 forMA-2 fuel, and PF = 0.3 2.6 AXrAL FLUX DIFFERENCE - AFD (LCO 3.2.3) 2.6.1 The AFD limits for Cycle 13 are provided in Figure 3.

2.7 REFITELTNG BORON CONCENTRATION (LCO 3.9.1) 2.7.1 The refueling boron concentration shall be ) 2000 ppm.

2.8 ACCUMULATORS (LCO 3.5.1) 2.8.1 There are 704 tritium producing bumable absorber rods (TPBARs) in the reactor core for Cycle 13.

2.9 REFUELTNG WATER STORAGE TAIIK - RWST (LCO 3.5.4) 2.9. 1 There are 704 tritium producing bumable absorber rods (TPBARs) in the reactor core for Cycle 13.

Unit I Cycle 13 WATTS BAR Page 5 of l0 Revision 0

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i 0.0 o.2 0,4 0.5 0.8 1.0 FRAC.tloN OF RATEDTHERMAT POWER Figure I Control Bank Insertion Limits Versus Thermal Power Four Loop Operation Fully withdrawn region shall be the condition where shutdown and control ba::ks are at a position within the interval of 2225 and,323l steps withdrawn Unit I Cycle 13 WATTS BAR Page 6 of l0 Revision 0

1.2 1.1 1.0 E--

0.9 0.8 L

(t) o

= o.7 o-

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= o.4 0.3 o.2 0.1 0

0 2 468 10 12 Core Height (feet)

Figure 2 K(Z) - Normalized Fq(Z) as a Function of Core Height Unit I Cycle 13 WATTS BAR Page 7 of l0 Revision 0

120 110 1 F1z, 1 00)r

-I (7 0)r

, 10r -I 100 I \

90 80 I

unacceptaDle I

r IF ACCeptaDre Operation i \

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Figure 3 Axial Flux Difference Acceptable Operation Limits as a function of Rated Thermal Power (RAOC)

Unit 1 Cycle 13 WATTS BAR Page 8 of l0 Revision 0

Table A.1 Fq*(Z):Fqt(Z)*W(Z)

Max W(z) Max W(z) Max W(z) Max W(z) Max W(z) Max W(z) at 150 at 150 at 150 at 2000 at 10000 at 16000 MWDA{TU MWDA{TU MWDA{TU MWDA{TU MWDA/ITU MWDA{TU Height (30% (7s% (t00% (100o/o (r00% (100%

(ft) Power) Power) Power) Power) Power) Power) 12.0748 r.0000 1.0000 1.0000 1.0000 1.0000 1.0000 11.8736 1.0000 r.0000 1.0000 1.0000 1.0000 r.0000 11.6723 1.0000 1.0000 1.0000 1.0000 1.0000 1,0000 tt.47tt 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 u.2698 r.0000 1.0000 1.0000 r.0000 1.0000 1,0000 11.0686 r.0000 1.0000 1.0000 1.0000 1,0000 1.0000 10.8673 1.2647 1.2807 l.213l 1.2352 r.r969 r.2189 10.6661 1.2510 1.2622 1.2096 1.2341 1.1900 1.2116 10.4648 1.2336 1.2391 1.2037 r.2309 1.1851 1.2002 10.2636 1.21,40 1.2178 1.1968 1.2308 r.r786 1.1952 r0.0623 1.2019 1.2038 1.1950 1.2293 l.l714 1.1755 9.8611 l.l9l9 1.1919 1.1952 1.2263 l.162l 1.1692 9.6598 1.1805 1.1789 1.1945 1.2239 1.1557 1.1610 9.4586 1.1660 1.1637 l.l9l4 1.2187 1.1596 1.1524 9.2573 1.1507 1.1482 1.1874 t.ztm 1.1639 l.l47l 9.0s61 r.1367 1.1349 1.1850 1.2096 l.l6g0 1.1493 8.8549 1.1220 l.l2l7 1.1808 1.2132 1.1735 1.1529 8.6536 l.l14l t.tt44 t.t796 1.2179 1.1829 1.1588 8.4524 1.1228 1.r233 1.1939 1.2225 1.1985 1.1790 8.251r 1.1222 1.1329 1.2079 t.224r l.2l15 1.1970 8.0499 1.1097 1.1402 1.2185 r.2234 1.2215 1.2rr8 7.8486 1.0909 1.1461 r.2266 1.2197 1.2292 1.2247 7.il74 1.0804 1.1503 1.23t9 1.2153 1.2343 1.23s0 7.4/,61 1.0707 1.1530 1.2346 1.2175 1.2368 1.2428 7.24/i9 1.0623 1.1538 1.2349 1.2168 1.2368 1.2479 7.0436 1.0566 1.1523 1.2327 1.2134 1.234d 1.2506 6.8/,24 r.0517 1.1492 1.2287 1.2086 1.2298 r.2s08 6.6411 1.0477 1.1458 1.2231 1.2024 1.2231 1.2489 6.4399 1.0441 1.1415 1.2157 1.1943 t.ztu 1.2452 6.2386 1.0417 1.1374 1.2080 1.1843 1.2037 1.2393 6.0374 r.0406 1.1343 1.2015 1.17s1 l.l9l5 t.2312 s.8362 r.0396 1.1307 1.1942 1.1667 1.1772 l.22ll s.6349 r.0384 1.1263 1.1858 1.r583 1.1il9 1.2089 5.4337 1.0394 1.1236 1.1792 1.1525 1.1616 1.1949 5.2324 1.0414 t.t2t4 1.1727 1.1499 1.r583 l.l83l 5.0312 1.0434 1.1187 1.1654 1.1479 1.1539 1.1801 4.8299 L4477 1.1180 1.1598 1.1450 l.l52l 1.1794 4.6287 1.0549 l.ll97 1.1567 t.t4t4 1.1529 1.1767 4.4274 1.0508 1.1196 1.1522 1.1370 1.1526 1.1733 4.2262 1.0666 1.1196 1.t470 r.1320 1.1519 1.1689 4.0249 1.0721 1.1175 l.l4l4 1.1267 r.1505 1.1636 3.8237 1.07il 1.1150 1.1343 1.1202 r.1498 1.1578 3.6224 r.0829 1.1145 1.1292 l.ll5l 1.1509 1.1514 3.4212 1.0962 1.1204 1.1309 1.ll52 1.1553 1.14s1 3.2199 1.1il2 1.1274 r.1336 l.1162 1.1516 1.1455 3.0r87 t.l2s1 1.1335 1.1350 1.1255 l.lu6 1.1499 2.8175 1.1418 1.1420 l.l3gg l.l4/,g 1.1724 1.1631 2.6162 1.1663 t.1579 1.1499 1.1685 1.1893 1.1823 2.4150 l.l9g5 1.1810 r.r683 1.1919 1.2088 r.2004 2.2137 1.2337 1.2061 1.1887 1.2153 1.2280 r.2r80 2.012s r.2681 1.2310 1.2088 1.2383 1.2466 1.2351 1.8112 1.3021 1.2555 1.2282 1.250s L2A4 1.2514 1.6100 1.3376 1.2793 1.2466 1.2816 l.28ll 1.2666 r.4087 1.3702 1.3008 1.2631 1.3005 1.2958 1,2800 1.2075 1.3989 1.3184 1.2765 1.3163 1.3073 1.2903 1.0062 1.0000 1.0000 1.0000 1.0000 r.0000 1.0000 0.8050 1.0000 1.0000 1.0000 r.0000 1,0000 1.0000 0.6037 1.0000 1.0000 1.0000 1.0000 1.0000 1,0000 0,4025 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 0.2012 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 0.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Unit I Cycle 13 WATTS BAR Page 9 of 10 Revision 0

Table A.2 Fo*(Z) Penalty Factor Core Fa"(J Burnup Penalty GrnwD/IvITfI) Factor All Elurnrrps 1.O?OO Note:

1. The Penalty Factor, which is applied to Faw(Z) for compliance with Surveillance Requirement 3.2.1.2.a,is the maximum factor by which Fq*(Z) is expected to increase per 3l Effective Full Power Days (EFPD) starting from the bumup at which the fowlZ; was deterrrined.

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