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| number = ML080730244
| number = ML080730244
| issue date = 03/12/2008
| issue date = 03/12/2008
| title = Core Operating Limits Report (Colr) for Cycle 9, Revision 0
| title = Core Operating Limits Report (COLR) for Cycle 9, Revision 0
| author name = Brandon M K
| author name = Brandon M
| author affiliation = Tennessee Valley Authority
| author affiliation = Tennessee Valley Authority
| addressee name =  
| addressee name =  
Line 15: Line 15:


=Text=
=Text=
{{#Wiki_filter:U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001  
{{#Wiki_filter:March 12, 2008 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 1 - CORE OPERATING LIMITS REPORT (COLR) FOR CYCLE 9, REVISION 0 The purpose of this letter is to provide Revision 0 of the Cycle 9 COLR in accordance with WBN Technical Specification 5.9.5.d. This revision was effective as of March 5, 2008.
There are no regulatory commitments associated with this submittal. If you have any questions concerning this letter, please contact me at (423) 365-1824.
Sincerely, Original signed by C. Riedl for M. K. Brandon Manager, Site Licensing and Industry Affairs


Gentlemen:  
==Enclosure:==
 
In the Matter of the ) Docket No. 50-390 Tennessee Valley Authority ) 


WATTS BAR NUCLEAR PLANT (WBN) UNI T 1 - CORE OPERATING LIMITS REPORT (COLR) FOR CYCLE 9, REVISION 0 The purpose of this letter is to provide Revision 0 of the Cycle 9 COLR in accordance with WBN Technical Specification 5.9.5.d. This revision wa s effective as of March 5, 2008.
Watts Bar Nuclear Plant Unit 1, Cycle 9 Core Operating Limits Report, Revision 0 cc: See Page 2
There are no regulatory commitments associated with this submittal. If you have any questions concerning this letter, pleas e contact me at (423) 365-1824. 


Sincerely,
U.S. Nuclear Regulatory Commission Page 2 March 12, 2008 Enclosure cc (Enclosure):
NRC Resident Inspector Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381 ATTN: Margaret H. Chernoff, Senior Project Manager U.S. Nuclear Regulatory Commission Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation MS O-8 H4-A 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


M. K. Brandon Manager, Site Licensing
Enclosure Watts Bar Nuclear Plant Unit 1 Cycle 9 Core Operating Limits Report, Revision 0


and Industry Affairs
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'HN) 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 1                                                                                          Cycle 9 WATTS BAR                                      Page 2 of 10                                  Revision 0


==Enclosure:==
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 'k/k/qF (upper limit). With the measured BOL/ARO/HZP - MTC more positive than -1.00 x 10-5
                'k/k/qF (as-measured MTC limit), establish control rod withdrawal limits to ensure the MTC remains less positive than or equal to 0 'k/k/qF (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 'k/k/qF (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 'k/k/qF.
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 'k/k/qF.
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


Watts Bar Nuclear Plant Unit 1, Cycle 9 Core Operating Limits Report, 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)                    Bank Overlap (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) d [CFQ / P]
* K(Z)        for P > 0.5 FQ(Z) d [CFQ / 0.5]
* K(Z)      for P d 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.
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.1. The table provides sufficient information to determine W(Z) versus core height for all cycle burnups.
Unit 1                                                                                          Cycle 9 WATTS BAR                                        Page 4 of 10                              Revision 0


cc: See Page 2 U.S. Nuclear Regulatory Commission Page 2
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 - F'HN (LCO 3.2.2)
F'HN d F'HRTP * ( 1 + PF * ( 1-P))
where P = Thermal Power / Rated Thermal Power F'HRTP = 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 t 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


Enclosure
COLR for Watts Bar Unit 1, Cycle 9 250 225 (0.197, 225)                          (0.703, 225) 200 BANK B ROD BANK STEP POSITION (STEPS WITHDRAWN)
(1.0, 177) 175        (0.0, 180) 150 BANK C 125 100 BANK D 75 (0.0, 64) 50 25 (0.227, 0) 0 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 t 225 and d 231 steps withdrawn.
Unit 1                                                                                        Cycle 9 WATTS BAR                                      Page 6 of 10                                Revision 0


cc (Enclosure):
COLR for Watts Bar Unit 1, Cycle 9 1.2 1.1 1.0 0.9 0.8 Normalized FQ
NRC Resident Inspector Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381
* Power 0.7 0.6                                            Core Height    K(Z) 0.000      1.000 6.000      1.000 12.000      0.9256 0.5 0.4 0.3 0.2 0.1 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


ATTN: Margaret H. Cher noff, Senior Project Manager  U.S. Nuclear Regulatory Commission Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation MS O-8 H4-A Washington, DC 20555-0001
COLR for Watts Bar Unit 1, Cycle 9 120 110
(-12, 100)        (7, 100) 100 90                                            Acceptable Operation 80          Unacceptable                                                        Unacceptable Operation                                                          Operation
  % of Rated Thermal Power 70 60 50
(-28, 50)                                      (21, 50) 40 30 20 10 0
                                    -50  -40      -30        -20        -10      0      10      20        30    40        50 Flux Difference (' I) %
Figure 3 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 0


U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303
COLR for Watts Bar Unit 1, Cycle 9 Table A.1 FQW(Z) = FQC(Z)
 
* W(Z)
Enclosure Watts Bar Nuclear Plant Unit 1 Cycle 9 Core Operating Li mits Report, Revision 0
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              1.2007            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            1.2691 6.0000        1.1915          1.1699              1.1688            1.1816            1.2573 5.8000        1.1816          1.1610              1.1589            1.1721            1.2437 5.6000        1.1725          1.1518              1.1485            1.1649            1.2268 5.4000        1.1644          1.1457              1.1417            1.1587            1.2095 5.2000        1.1560          1.1425              1.1395            1.1538            1.2027 5.0000        1.1520          1.1405              1.1380            1.1522            1.2031 4.8000        1.1500          1.1384              1.1369            1.1539            1.2041 4.6000        1.1470          1.1354              1.1360            1.1593            1.2030 4.4000        1.1433          1.1319              1.1343            1.1633            1.2009 4.2000        1.1390          1.1277              1.1321            1.1669            1.1975 4.0000        1.1342          1.1233              1.1296            1.1703            1.1936 3.8000        1.1287          1.1179              1.1265            1.1727            1.1876 3.6000        1.1243          1.1142              1.1252            1.1765            1.1841 3.4000        1.1225          1.1136              1.1285            1.1847            1.1874 3.2000        1.1261          1.1164              1.1336            1.1928            1.1902 3.0000        1.1289          1.1259              1.1411            1.2001            1.1986 2.8000        1.1405          1.1423              1.1574            1.2160            1.2086 2.6000        1.1631          1.1622              1.1811            1.2403            1.2199 2.4000        1.1858          1.1829              1.2040            1.2628            1.2384 2.2000        1.2086          1.2057              1.2271            1.2851            1.2564 2.0000        1.2313          1.2286              1.2500            1.3069            1.2736 1.8000        1.2528          1.2507              1.2725            1.3276            1.2904 1.6000        1.2746          1.2719              1.2940            1.3470            1.3063 1.4000        1.3005          1.2912              1.3136            1.3643            1.3205 1.2000        1.3291          1.3078              1.3303            1.3785            1.3320 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                                                                                               Cycle 9 WATTS BAR                                         Page 9 of 10                                 Revision 0
 
COLR for Watts Bar Unit 1, Cycle 9   Unit 1 Cycle 9 WATTS BAR Page 2 of 10 Revision 0 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 (F Q (Z))3.2.2  Nuclear Enthalpy Rise Hot Channel Factor (FH 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 LIMITSThe 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 COLR for Watts Bar Unit 1, Cycle 9  Unit 1 Cycle 9 WATTS BAR Page 3 of 10 Revision 0 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 k/k/ F (upper limit). With the measured BOL/ARO/HZP - MTC more positive than -1.00 x 10
-5k/k/F (as-measured MTC limit), establish control rod withdrawal limits to ensure the MTC remains less positive than or equal to 0 k/k/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 10-4k/k/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
-4k/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
-4k/k/ 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.
COLR for Watts Bar Unit 1, Cycle 9  Unit 1 Cycle 9 WATTS BAR Page 4 of 10 Revision 0 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)            Bank Overlap (steps)      Bank Difference(steps) 225                      109                  116 226                      110                  116 227                      111                  116 228                      112                  116


229                      113                  116 230                      114                  116 231                      115                  1162.4  HEAT FLUX HOT CHANNEL FACTOR  - F Q(Z)  (LCO 3.2.1)
COLR for Watts Bar Unit 1, Cycle 9 Table A.2 FQW(Z) Penalty Factor W
F Q (Z) [CFQ/ P]
Core               F Q (Z)
* K(Z)  for P > 0.5 F Q (Z) [CFQ/ 0.5]
B urnup              Penalty (M W D/M TU)             F actor All Burnups              1.0200 Note:
* K(Z)  for P  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.
: 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.
2.4.3 F Q C (Z) = F Q M (Z)
Unit 1                                                                                      Cycle 9 WATTS BAR                                    Page 10 of 10                              Revision 0}}
* 1.0815 where:  F Q M(Z) is the measured value of F Q(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 F Q W(Z) = F Q C (Z)
* W(Z) where:  W(Z) values are provided in Table A.1. The table provides sufficient information to determine W(Z) versus core height for all cycle burnups.
COLR for Watts Bar Unit 1, Cycle 9   Unit 1  Cycle 9 WATTS BAR Page 5 of 10 Revision 0 2.4.5 F Q W(Z)   Penalty Factor The F Q W(Z) penalty factor is provided in Table A.2. 2.5 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR - FH N (LCO 3.2.2)
FH N FH RTP * ( 1 + PF * ( 1-P)) where P = Thermal Power / Rated Thermal Power FH RTP  = 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  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.
COLR for Watts Bar Unit 1, Cycle 9  Unit 1  Cycle 9 WATTS BAR Page 6 of 10 Revision 0 (0.0, 180)(0.197, 225)(0.703, 225)(0.0, 64)(1.0, 177)
(0.227, 0)
BANK DBANK CBANK B 0 25 50 751001251501752002252500.00.10.20.30.40.50.60.70.80.91.0FRACTIONAL OF RATED THERMAL POWERROD BANK STEP POSITION (STEPS WITHDRAWN)
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.
COLR for Watts Bar Unit 1, Cycle 9  Unit 1  Cycle 9 WATTS BAR Page 7 of 10 Revision 0 Figure 2 K(Z) - Normalized F Q(Z) as a Function of Core Height024681012 0 0.2 0.4 0.1 0.3 0.5 0.6 0.7 0.9 1.1 0.8 1.0 1.2 Core Height K(Z) 0.000              1.000 6.000              1.000  12.000              0.9256Core Height (feet)Normalized F Q
* Power COLR for Watts Bar Unit 1, Cycle 9  Unit 1  Cycle 9 WATTS BAR Page 8 of 10 Revision 0 Figure 3 Figure 3 Axial Flux Difference Acceptable Operation Limits as a  Function of Rated Thermal Power (RAOC) 0 10 20 30 40 50 60 70 80 90100110 120-50-40-30-20-1001020304050Flux Difference (I) %% of Rated Thermal Powe r(7, 100)(-12, 100)(-28, 50)Unacceptable OperationAcceptable Operation(21, 50)Unacceptable Operation COLR for Watts Bar Unit 1, Cycle 9  Unit 1  Cycle 9 WATTS BAR Page 9 of 10 Revision 0 Table A.1 F Q W(Z) = F Q C(Z)
* W(Z)
Height (ft) Max W(z) at 150 MWD/MTU Max W(z) at 2000 MWD/MTU Max W(z) at 4000 MWD/MTU Max W(z) at 10000 MWD/MTU Max W(z) at 18000 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 1.2007 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 1.2691 6.0000 1.1915 1.1699 1.1688 1.1816 1.2573 5.8000 1.1816 1.1610 1.1589 1.1721 1.2437 5.6000 1.1725 1.1518 1.1485 1.1649 1.2268 5.4000 1.1644 1.1457 1.1417 1.1587 1.2095 5.2000 1.1560 1.1425 1.1395 1.1538 1.2027 5.0000 1.1520 1.1405 1.1380 1.1522 1.2031 4.8000 1.1500 1.1384 1.1369 1.1539 1.2041 4.6000 1.1470 1.1354 1.1360 1.1593 1.2030 4.4000 1.1433 1.1319 1.1343 1.1633 1.2009 4.2000 1.1390 1.1277 1.1321 1.1669 1.1975 4.0000 1.1342 1.1233 1.1296 1.1703 1.1936 3.8000 1.1287 1.1179 1.1265 1.1727 1.1876 3.6000 1.1243 1.1142 1.1252 1.1765 1.1841 3.4000 1.1225 1.1136 1.1285 1.1847 1.1874 3.2000 1.1261 1.1164 1.1336 1.1928 1.1902 3.0000 1.1289 1.1259 1.1411 1.2001 1.1986 2.8000 1.1405 1.1423 1.1574 1.2160 1.2086 2.6000 1.1631 1.1622 1.1811 1.2403 1.2199 2.4000 1.1858 1.1829 1.2040 1.2628 1.2384 2.2000 1.2086 1.2057 1.2271 1.2851 1.2564 2.0000 1.2313 1.2286 1.2500 1.3069 1.2736 1.8000 1.2528 1.2507 1.2725 1.3276 1.2904 1.6000 1.2746 1.2719 1.2940 1.3470 1.3063 1.4000 1.3005 1.2912 1.3136 1.3643 1.3205 1.2000 1.3291 1.3078 1.3303 1.3785 1.3320 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 COLR for Watts Bar Unit 1, Cycle 9  Unit 1  Cycle 9 WATTS BAR Page 10 of 10 Revision 0 Table A.2 F Q W(Z) Penalty Factor Note:1.The Penalty Factor, which is applied to F Q W(Z) for compliance with Surveillance Requirement 3.2.1.2.a, is the maximum factor by which F Q W(Z) is expected to increase per 31 Effective Full Power Days (EFPD) starting from the burnup at which the F Q W(Z) was determined. Core F Q W(Z)Burnup Penalty(MWD/MTU)FactorAll Burnups1.0200}}

Latest revision as of 19:42, 14 November 2019

Core Operating Limits Report (COLR) for Cycle 9, Revision 0
ML080730244
Person / Time
Site: Watts Bar Tennessee Valley Authority icon.png
Issue date: 03/12/2008
From: Brandon M
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML080730244 (13)
v • d • e


Text

March 12, 2008 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 1 - CORE OPERATING LIMITS REPORT (COLR) FOR CYCLE 9, REVISION 0 The purpose of this letter is to provide Revision 0 of the Cycle 9 COLR in accordance with WBN Technical Specification 5.9.5.d. This revision was effective as of March 5, 2008.

There are no regulatory commitments associated with this submittal. If you have any questions concerning this letter, please contact me at (423) 365-1824.

Sincerely, Original signed by C. Riedl for M. K. Brandon Manager, Site Licensing and Industry Affairs

Enclosure:

Watts Bar Nuclear Plant Unit 1, Cycle 9 Core Operating Limits Report, Revision 0 cc: See Page 2

U.S. Nuclear Regulatory Commission Page 2 March 12, 2008 Enclosure cc (Enclosure):

NRC Resident Inspector Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381 ATTN: Margaret H. Chernoff, Senior Project Manager U.S. Nuclear Regulatory Commission Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation MS O-8 H4-A 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 0

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'HN) 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 1 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 'k/k/qF (upper limit). With the measured BOL/ARO/HZP - MTC more positive than -1.00 x 10-5

'k/k/qF (as-measured MTC limit), establish control rod withdrawal limits to ensure the MTC remains less positive than or equal to 0 'k/k/qF (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 'k/k/qF (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 'k/k/qF.

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 'k/k/qF.

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) Bank Overlap (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) d [CFQ / P]

  • K(Z) for P > 0.5 FQ(Z) d [CFQ / 0.5]
  • K(Z) for P d 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.

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.1. The table provides sufficient information to determine W(Z) versus core height for all cycle burnups.

Unit 1 Cycle 9 WATTS BAR 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 - F'HN (LCO 3.2.2)

F'HN d F'HRTP * ( 1 + PF * ( 1-P))

where P = Thermal Power / Rated Thermal Power F'HRTP = 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 t 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) (0.703, 225) 200 BANK B ROD BANK STEP POSITION (STEPS WITHDRAWN)

(1.0, 177) 175 (0.0, 180) 150 BANK C 125 100 BANK D 75 (0.0, 64) 50 25 (0.227, 0) 0 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 t 225 and d 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 Normalized FQ

  • Power 0.7 0.6 Core Height K(Z) 0.000 1.000 6.000 1.000 12.000 0.9256 0.5 0.4 0.3 0.2 0.1 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

(-12, 100) (7, 100) 100 90 Acceptable Operation 80 Unacceptable Unacceptable Operation Operation

% of Rated Thermal Power 70 60 50

(-28, 50) (21, 50) 40 30 20 10 0

-50 -40 -30 -20 -10 0 10 20 30 40 50 Flux Difference (' I) %

Figure 3 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 0

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 1.2007 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 1.2691 6.0000 1.1915 1.1699 1.1688 1.1816 1.2573 5.8000 1.1816 1.1610 1.1589 1.1721 1.2437 5.6000 1.1725 1.1518 1.1485 1.1649 1.2268 5.4000 1.1644 1.1457 1.1417 1.1587 1.2095 5.2000 1.1560 1.1425 1.1395 1.1538 1.2027 5.0000 1.1520 1.1405 1.1380 1.1522 1.2031 4.8000 1.1500 1.1384 1.1369 1.1539 1.2041 4.6000 1.1470 1.1354 1.1360 1.1593 1.2030 4.4000 1.1433 1.1319 1.1343 1.1633 1.2009 4.2000 1.1390 1.1277 1.1321 1.1669 1.1975 4.0000 1.1342 1.1233 1.1296 1.1703 1.1936 3.8000 1.1287 1.1179 1.1265 1.1727 1.1876 3.6000 1.1243 1.1142 1.1252 1.1765 1.1841 3.4000 1.1225 1.1136 1.1285 1.1847 1.1874 3.2000 1.1261 1.1164 1.1336 1.1928 1.1902 3.0000 1.1289 1.1259 1.1411 1.2001 1.1986 2.8000 1.1405 1.1423 1.1574 1.2160 1.2086 2.6000 1.1631 1.1622 1.1811 1.2403 1.2199 2.4000 1.1858 1.1829 1.2040 1.2628 1.2384 2.2000 1.2086 1.2057 1.2271 1.2851 1.2564 2.0000 1.2313 1.2286 1.2500 1.3069 1.2736 1.8000 1.2528 1.2507 1.2725 1.3276 1.2904 1.6000 1.2746 1.2719 1.2940 1.3470 1.3063 1.4000 1.3005 1.2912 1.3136 1.3643 1.3205 1.2000 1.3291 1.3078 1.3303 1.3785 1.3320 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 Cycle 9 WATTS BAR Page 9 of 10 Revision 0

COLR for Watts Bar Unit 1, Cycle 9 Table A.2 FQW(Z) Penalty Factor W

Core F Q (Z)

B urnup Penalty (M W D/M TU) F actor 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

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