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Category:Fuel Cycle Reload Report
MONTHYEARL-2023-053, Core Operating Limits Report for Cycle 232023-04-0505 April 2023 Core Operating Limits Report for Cycle 23 SBK-L-21108, Core Operating Limits Report for Cycle 222021-11-0404 November 2021 Core Operating Limits Report for Cycle 22 SBK-L-20077, Core Operating Limits Report for Cycle 212020-06-0101 June 2020 Core Operating Limits Report for Cycle 21 SBK-L-18172, Core Operating Limits Report for Cycle 202018-10-16016 October 2018 Core Operating Limits Report for Cycle 20 SBK-L-17066, Core Operating Limits Report for Cycle 192017-04-12012 April 2017 Core Operating Limits Report for Cycle 19 SBK-L-15191, Core Operating Limits Report for Cycle 182015-10-22022 October 2015 Core Operating Limits Report for Cycle 18 SBK-L-15063, Core Operating Limits Report for Cycle 172015-03-24024 March 2015 Core Operating Limits Report for Cycle 17 SBK-L-14076, Core Operating Limits Report for Cycle 172014-05-15015 May 2014 Core Operating Limits Report for Cycle 17 SBK-L-12207, Submittal of Core Operating Limits Report for Cycle 162012-09-27027 September 2012 Submittal of Core Operating Limits Report for Cycle 16 SBK-L-11162, Cycle 15 Startup Report2011-08-25025 August 2011 Cycle 15 Startup Report SBK-L-11077, Core Operating Limits Report for Cycle 152011-04-14014 April 2011 Core Operating Limits Report for Cycle 15 SBK-L-10124, Submittal of Revised Core Operating Limits Report for Cycle 142010-07-0707 July 2010 Submittal of Revised Core Operating Limits Report for Cycle 14 SBK-L-10033, Cycle 14 Startup Report2010-02-22022 February 2010 Cycle 14 Startup Report SBK-L-09224, Submittal of Cycle 14 Core Operating Limits Report2009-10-17017 October 2009 Submittal of Cycle 14 Core Operating Limits Report SBK-L-08010, Submittal of Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2008-07-31031 July 2008 Submittal of Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications SBK-L-08066, Core Operating Limits Report for Cycle 132008-04-22022 April 2008 Core Operating Limits Report for Cycle 13 SBK-L-07027, Core Operating Limits Report for Cycle 122007-02-0505 February 2007 Core Operating Limits Report for Cycle 12 SBK-L-07009, Cycle 12 Startup Report2007-01-29029 January 2007 Cycle 12 Startup Report SBK-L-06208, Core Operating Limits Report for Cycle 122006-10-26026 October 2006 Core Operating Limits Report for Cycle 12 SBK-L-06099, Revision to Cycle 11 Core Operating Limits Report2006-05-0101 May 2006 Revision to Cycle 11 Core Operating Limits Report ML0216402372002-05-31031 May 2002 Cycle 9 Core Operating Limits Report 2023-04-05
[Table view] Category:Letter
MONTHYEARML24254A2552024-09-25025 September 2024 Alternative Request No. 4A-01 for the Fourth 10-Year Inservice Inspection Interval L-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes ML24239A5382024-09-20020 September 2024 Issuance of Amendment No. 175 One-Time Allowable Outage Time Extension to the Technical Specification 3.8.1.1, A.C. Sources – Operating, Limiting Condition for Operation L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes IR 05000443/20240052024-08-29029 August 2024 Updated Inspection Plan for Seabrook Station (Report 05000443/2024005) ML24232A1142024-08-21021 August 2024 Correction to Amendment No. 174 to Update the Period of Applicability (Poa) for the Pressure-Temperature Limits (PTL) and Low Temperature Overpressure Protection (LTOP) Curves L-2024-141, Third Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit2024-08-15015 August 2024 Third Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Be L-2024-137, Second Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent .2024-08-12012 August 2024 Second Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent . IR 05000443/20240022024-08-0606 August 2024 Integrated Inspection Report 05000443/2024002 and Independent Spent Fuel Storage Installation Inspection Report 07200063/2024001 ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review L-2024-127, Supplement to Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent2024-08-0505 August 2024 Supplement to Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite.2024-07-16016 July 2024 Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite. ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter L-2024-098, Preparation and Scheduling of Operator Licensing Examinations2024-06-12012 June 2024 Preparation and Scheduling of Operator Licensing Examinations L-2024-084, Relief Request 4A-01, Rev 1 - Revision to Relief Request for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld2024-05-30030 May 2024 Relief Request 4A-01, Rev 1 - Revision to Relief Request for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld IR 05000443/20240102024-05-29029 May 2024 Biennial Problem Identification and Resolution Inspection Report 05000443/2024010 IR 05000443/20240112024-05-24024 May 2024 Age-Related Degradation Inspection Report 05000443/2024011 IR 05000443/20240012024-05-13013 May 2024 Integrated Inspection Report 05000443/2024001 L-2024-061, NextEra Energy Seabrook, LLC, License Amendment Request - One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite Transmission Network and the Onsite Class 1E Distribut2024-05-10010 May 2024 NextEra Energy Seabrook, LLC, License Amendment Request - One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite Transmission Network and the Onsite Class 1E Distributio ML24046A0512024-05-0707 May 2024 Issuance of Amendment No. 174 to Update the Period of Applicability (Poa) for the Pressure-Temperature Limits (PTL) and Low Temperature Overpressure Protection (LTOP) Curves ML24127A0632024-05-0606 May 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-078, 2023 Annual Radioactive Effluent Release Report2024-05-0101 May 2024 2023 Annual Radioactive Effluent Release Report L-2024-077, 2023 Annual Radiological Environmental Operating Report2024-04-30030 April 2024 2023 Annual Radiological Environmental Operating Report IR 05000443/20245012024-04-22022 April 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000443/2024501 L-2024-058, Condition Prohibited by Technical Specifications - Transformer Bushing Failure - Offsite AC Sources2024-04-19019 April 2024 Condition Prohibited by Technical Specifications - Transformer Bushing Failure - Offsite AC Sources SBK-L-24030, 2023 Annual Environmental Operating Report2024-04-12012 April 2024 2023 Annual Environmental Operating Report L-2024-011, and Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2024-03-13013 March 2024 and Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications ML24067A2622024-03-0808 March 2024 Issuance of Amendment No. 173 Revise Technical Specification 3/4.8.1 to Allow Replacement of Reserve Auxiliary Transformer (Emergency Circumstances) L-2024-038, to Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source2024-03-0808 March 2024 to Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source L-2024-037, to Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source2024-03-0606 March 2024 to Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source L-2024-035, Supplement to Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source2024-03-0505 March 2024 Supplement to Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source ML24065A2522024-03-0505 March 2024 Notice of Enforcement Discretion for Seabrook Station, Unit No. 1 (EPID: L-2024-033) L-2024-033, Request for Enforcement Discretion - Technical Specification (TS) 3/4.8.1.1 Ac. Sources Required Action Completion Time to Replace ED-X-3-B2024-03-0404 March 2024 Request for Enforcement Discretion - Technical Specification (TS) 3/4.8.1.1 Ac. Sources Required Action Completion Time to Replace ED-X-3-B L-2024-032, Emergency License Amendment Request- One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source2024-03-0404 March 2024 Emergency License Amendment Request- One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source L-2024-019, Relief Request 4A-01- Request for an Alternative to the Requirements of the ASME Code for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld2024-02-28028 February 2024 Relief Request 4A-01- Request for an Alternative to the Requirements of the ASME Code for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld IR 05000443/20230062024-02-28028 February 2024 Annual Assessment Letter for Seabrook Station (Report 05000443/2023006) L-2024-016, Radiological Emergency Plan (Ssrep), Revision 822024-02-13013 February 2024 Radiological Emergency Plan (Ssrep), Revision 82 IR 05000443/20230042024-02-12012 February 2024 Integrated Inspection Report 05000443/2023004 ML24009A1152024-01-29029 January 2024 – Exemption from Select Requirements of 10 CFR Part 73 (EPID L 2023 LLE-0043 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) ML24022A0652024-01-22022 January 2024 Senior Reactor and Reactor Operator Initial License Examinations L-2024-003, NextEra Energy Seabrook, LLC - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2024-01-11011 January 2024 NextEra Energy Seabrook, LLC - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report ML23312A1822023-12-22022 December 2023 Issuance of Amendment No. 172 Revision to Cooling Tower Service Water Loop or Cell Requirements L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-180, Submittal of Changes to the Technical Specification Bases2023-12-13013 December 2023 Submittal of Changes to the Technical Specification Bases L-2023-177, Supplement to Seabrook Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Seabrook Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule 2024-09-25
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NEXTera ENERGY1 May 15, 2014 Docket No. 50-443 SBK-L-14076 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 -0001 Seabrook Station Core Operating Limits Report for Cycle 17 Pursuant to Technical Specification 6.8.1.6.c, NextEra Energy Seabrook, LLC has enclosed the latest revision of the Seabrook Station Core Operating Limits Report (COLR) for cycle 17.If you have any questions regarding this information, please contact me at (603) 773-7512.Sincerely, NextEra Energy Seabrook, LLC Licensing cc: NRC Region I Administrator J. G. Lamb, NRC Project Manager NRC Senior Resident Inspector-A--0 6 /7 1 -NextEra Energy Seabrook, LLC.626 Lafayette Rd, Seabrook, NH 03874 ENCLOSURE TO SBK-L-14076 1.0 Core Operating Limits Report (COLR)This Core Operating Limits Report for Seabrook Station Unit 1, Cycle 17 has been prepared in accordance with the requirements of Technical Specification 6.8.1.6.The Technical Specifications affected by this report are: 1) 2.2.1 Limiting Safety System Settings 2) 2.1 Safety Limits 3) 3.1.1.1 Shutdown Margin Limit for MODES 1, 2, 3, 4 4) 3.1.1.2 Shutdown Margin Limit for MODE 5 5) 3.1.1.3 Moderator Temperature Coefficient
- 6) 3.1.2.7 Minimum Boron Concentration for MODES 4, 5, 6 7) 3.1.3.5 Shutdown Rod Insertion Limit 8) 3.1.3.6 Control Rod Insertion Limits 9) 3.2.1 Axial Flux Difference
- 10) 3.2.2 Heat Flux Hot Channel Factor 11) 3.2.3 Nuclear Enthalpy Rise Hot Channel Factor 12) 3.2.5 DNB Parameters
- 13) 3.5.1.1 Boron Concentration Limits for MODES 1, 2, 3 14) 3.5.4 Boron Concentration Limits for MODES 1, 2, 3, 4 15) 3.9.1 Boron Concentration Limits for MODE 6 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 Technical Specification 6.8.1.6.2.1 Limiting Safety System Settings: (Specification 2.2.1)2.1.1 Cycle Dependent Overtemperature AT Trip Setpoint Parameters and Function Modifier: 2.1.1.1 K 1 = 1.210 2.1.1.2 K 2 = 0.021 / OF 2.1.1.3 K 3 = 0.0011 / psig T = Measured RCS Tavg (°F), and T = Indicated RCS Tavg at RATED THERMAL POWER (Calibration temperature for AT instrumentation, _< 589.1 'F).P) = Nominal RCS operating pressure, 2235 psig 6-1.1 SSTR Rev. 140 2.1.1.4 Channel Total Allowance (TA) = N.A.2.1.1.5 Channel Z = N.A.2.1.1.6 Channel Sensor Error (S) = N.A.2.1.1.7 Allowable Value -The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than 0.5% of AT span. Note that 0.5% of AT span is applicable to OTAT input channels AT, Tavg and Pressurizer Pressure;0.25% of AT span is applicable to Al.2.1.1.8 f, (AI) is a function of the indicated difference between top and bottom detectors of the power-range neutron ion chambers; with nominal gains to be selected based on measured instrument response during plant startup tests calibrations such that: (1) For qt -qb between -20% and +8%, fl(AI) > 0; where qt and qb are percent RATED THERMAL POWER in the upper and lower halves of the core, respectively, and qt + qb is the total THERMAL POWER in percent RATED THERMAL POWER;(2) For each percent that the magnitude of qt -qb exceeds -20%, the AT Trip Setpoint shall be automatically reduced by > 2.87% of its value at RATED THERMAL POWER.(3) For each percent that the magnitude of qt -qb exceeds +8%, the AT Trip Setpoint shall be automatically reduced by > 1.71% of its value at RATED THERMAL POWER.See Figure 5.2.1.1.9 -11 = 0 seconds 2.1.1.10 T2 2=0seconds 2.1.1.11 3 <2 seconds 2.1.1.12 T4 28seconds 2.1.1.13 T5 4 seconds 2.1.1.14 T6<2seconds 6-1.2 SSTR Rev. 140 2.1.2 Cycle Dependent Overpower AT Trip Setpoint Parameters and Function Modifier: 2.1.2.1 K 4 = 1.116 2.1.2.2 K 5 = 0.020 / -F for increasing average temperature and K 5 = 0.0 for decreasing average temperature.
2.1.2.3 K 6 = 0.00175/°FforT>T11 and K 6 =0.0forT<T", where: T = Measured Tavg (fF), and T11 = Indicated Tavg at RATED T1HERMAL POWER (Calibration temperature for AT instrumentation, < 589.1 'F).2.1.2.4 Channel Total Allowance (TA) = N.A.2.1.2.5 Channel Z = N.A.2.1.2.6 Channel Sensor Error (S) = N.A.2.1.2.7 Allowable Value -The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than 0.5% of AT span. Note that 0.5% of AT span is applicable to OPAT input channels AT and Tavg.2.1.2.8 f 2 (AI) is disabled.2.1.2.9 -r as defined in 2.1.1.9, above.2.1.2.10 T2 as defined in 2.1.1.10, above.2.1.2.11 T 3 as defined in 2.1.1.11, above.2.1.2.12 T6 as defined in 2.1.1.14, above.2.1.2.13 T 7 - 10 seconds. It is recognized that exactly equal values cannot always be dialed into the numerator and denominator in the protection system hardware, even if the nominal values are the same (10 seconds).
Thus given the inequality sign in the COLR (greater than or equal to) the intent of the definition of this time constant applies primarily to the rate time constant (i.e. the Tau value in the numerator).
The lag time constant (denominator Tau value) may be less than 10 seconds or less than the value of the numerator Tau value (e.g., if the numerator is set at 10.5, the denominator may be set to 10 or 9.5) and still satisfy the intent of the anticipatory protective feature.6-1.3 SSTR Rev. 140 2.2 Safety Limits: (Specification 2.1.1)2.2.1 In Modes I and 2, the combination of Thermal Power, reactor coolant system highest loop average temperature and pressurizer pressure shall not exceed the limits in Figure 6.2.3 Shutdown Margin Limit for MODES 1, 2,3, and 4: (Specification 3.1.1.1)2.3.1 The Shutdown Margin shall be greater than or equal to 1.3% AK/K, in MODES 1, 2 and 3.2.3.2 The Shutdown Margin shall be greater than or equal to 2.3% AK/K, in MODE 4.2.3.3 The Boric Acid Storage System boron concentration shall be greater than or equal to 7000 ppm.2.4 Shutdown Margin Limit for MODE 5: (Specification 3.1.1.2)2.4.1 The Shutdown Margin shall be greater than or equal to 2.3% AK/K.2.4.2 The RCS boron concentration shall be greater than or equal to 2000 ppm when the reactor coolant loops are in a drained condition.
2.4.3 The Boric Acid Storage System boron concentration shall be greater than or equal to 7000 ppm.2.5 Moderator Temperature Coefficient: (Specification 3.1.1.3)2.5.1 The Moderator Temperature Coefficient (MTC) shall be less positive than+4.891 x 10 5 AK/K/OF for Beginning of Cycle Life (BOL), All Rods Out (ARO), Hot Zero Thermal Power conditions.
2.5.2 MTC shall be less negative than -5.5 x 10-4 AK/K/0 F for End of Cycle Life (EOL), ARO, Rated Thermal Power conditions.
2.5.3 The 300 ppm ARO, Rated Thermal Power MTC shall be less negative than -4.6 x 10-4 AK/K/°F (300 ppm Surveillance Limit).2.5.4 The Revised Predicted near-EOL 300 ppm MTC shall be calculated using the algorithm contained in WCAP 13749-P-A:
Revised Predicted MTC = Predicted MTC + AFD Correction
-3 PCM/degree F If the Revised Predicted MTC is less negative than the SR 4.1.1.3.b 300 ppm surveillance limit and all the benchmark data contained in the surveillance procedure are met, then an MTC measurement in accordance with SR 4.1.1.3.b is not required to be performed.
6-1.4 SSTR Rev. 140 2.6 Minimum Boron Concentration for MODES 4, 5, 6 (Specification 3.1.2.7)2.6.1 The Boric Acid Storage System boron concentration shall be greater than or equal to 7000 ppm.2.7 Shutdown Rod Insertion Limit: (Specification 3.1.3.5)2.7.1 The shutdown rods shall be fully withdrawn.
The fully withdrawn position is defined as the interval within 225 steps withdrawn to the mechanical fully withdrawn position inclusive.
2.8 Control Rod Insertion Limits: (Specification 3.1.3.6)2.8.1 The control rod banks shall be limited in physical insertion as specified in Figure 1.Control Bank A shall be at least 225 steps withdrawn.
2.9 Axial Flux Difference: (Specification 3.2.1)2.9.1 The indicated AFD must be within the Acceptable Operation Limits specified in Figure 2.2.10 Heat Flux Hot Channel Factor: (Specification 3.2.2)2.10.1 FRQ = 2.50 2.10.2 K(Z) is specified in Figure 3.2.10.3 W(Z) is specified in Table 1.The W(Z) data is applied over the cycle as follows: BU < 150 MWD/MTU, linear extrapolation of 150 and 3000 MWD/MTU W(Z) data 150 _< BU < 6500 MWD/MTU, quadratic interpolation of 150, 3000, and 10000 MWD/MTU data 6500 _< BU <18000 MWD/MTU, quadratic interpolation of 3000, 10000, and 18000 MWD/MTU W(Z) data BU > 18000 MWD/MTU, linear extrapolation of 10000 and 18000 MWD/MTU W(Z) data Note: The FQ(Z) surveillance exclusion zone is specified by Technical Specification 4.2.2.2.g 2.10.4 The FMQ(Z) penalty factor is 1.02.6-1.5 SSTR Rev. 140 2.11 Nuclear Enthalpy Rise Hot Channel Factor: (Specification 3.2.3)2.11.1 FN F HFN(RTP)x( I +PFx( I -P))where P = THERMAL POWER / RATED THERMAL POWER.2.11.2.a For F Na measured by the fixed incore detectors:
FN A(RTP) = 1.584.2.11.2.b For FN AH measured by the movable incore detectors:
FN A(RTP) = 1.584.2.11.3 Power Factor Multiplier for FNAH = PF = 0.3.2.12 DNB Parameters (Specification 3.2.5)2.12.1 The Reactor Coolant System Tavg shall be less than or equal to 595.1 degrees F.2.12.2 The Pressurizer Pressure shall be greater than or equal to 2185 PSIG.Note: Technical Specification Bases 3/4.2.5, "DNB Parameters" indicates that the limits on DNB-related parameters assure consistency with the normal steady-state envelope of operation assumed in the transient and accident analyses.
Operating procedures include allowances for measurement and indication uncertainty so that the limits in the COLR for Tavg and pressurizer pressure are not exceeded.
Consistent with the Bases, the values of these DNB parameters are the limiting Tavg and pressurizer pressure assumed in the transient and accident analyses.2.13 Accumulator Boron Concentration Limits for MODES 1,2,3 (Specification 3.5.1.1)2.13.1 Each Accumulator shall have a boron concentration between 2300 and 2600 ppm.2.14 Refueling Water Storage Tank Boron Concentration Limits for MODES 1, 2, 3, 4 (Specification 3.5.4)2.14.1 The RWST shall have a boron concentration between 2400 and 2600 ppm.2.15 Refueling Boron Concentration Limits for MODE 6 (Specification 3.9.1)2.15.1 The Refueling Boron Concentration during Cycle 17 shall be greater than or equal to 2235 ppm.2.15.2 The Boric Acid Storage System boron concentration shall be greater than or equal to 7000 ppm.6-1.6 SSTR Rev. 140 Figure 1: Control Bank Insertion Limits Versus Thermal Power 225 (0,173,225) 200 Bank B (0.7_225)(0.0,188)S175 150 100 125 *_.__'___""_
0 ' D 50 25__0.0 0.2 0.4 0.6 0.8 1.0 Fraction of Rated Thermal Power 6-1.7 SSTR Rev. 140 Figure 2: Axial Flux Difference Operating Limits Versus Thermal Power 0 M cc EU cc-60 40 20 -10 0 10 20 30 40 50 60 Axial Flux Difference
(%DI)Note: %DJ = %AI 6-1.8 SSTR Rev. 140 Figure 3: K(Z) Versus Core Height 1.2 (0.0,1.000)
(6.0,1.000) 1' (12.00,0.925) 0.8 N 0.6 0.4 0.2 0 1 2 3 4 5 6 7 8 9 10 11 12 Core Height (Feet)6-1.9 SSTR Rev. 140 Figure 4: Deleted 6-1.10 SSTR Rev. 140 Figure 5: fl(AI) Function 1- 0.1,60 1-60-40 -20 0 20 40-, Al Band (percent~
o 60 6-1.11 SSTR Rev. 140 Figure 6: Safety Limits 680O 660CD -2250 psia 620 E c-)F- 2000 psia 58 5 600 580 Fraction of Rated Thermal Power 6-1.12 SSTR Rev. 140 Table 1: W(Z,BU) versus Axial Height (Sheet I of 2)HEIGHT (Z) W(Z,BU) W(Z,BU) W(Z,BU) W(Z,BU)(Feet) 150 3000 10000 18000 MWD/MTU MWD/MTU MWD/MTU MWD/MTU<1.0 1.2 1.4 1.6 1.8 2.0 2.2 2.4 2.6 2.8 3.0 3.2 3.4 3.6 3.8 4.0 4.2 4.4 4.6 4.8 5.0 5.2 5.4 5.6 5.8 6.0 6.2 6.4 6.6 6.8 7.0 7.2 7.4 7.6 7.8 8.0 8.2 8.4 8.6 8.8 1.0000 1.4220 1.4063 1.3882 1.3681 1.3467 1.3244 1.3012 1.2776 1.2582 1.2448 1.2355 1.2280 1.2213 1.2141 1.2062 1.1976 1.1885 1.1786 1.1681 1.1570 1.1453 1.1330 1.1201 1.1077 1.1031 1.1035 1.1054 1.1086 1.1115 1.1133 1.1141 1.1138 1.1123 1.1095 1.1058 1.1027 1.1011 1.1013 1.1022 1.0000 1.3854 1.3689 1.3502 1.3299 1.3111 1.2928 1.2743 1.2596 1.2444 1.2310 1.2200 1.2084 1.1960 1.1870 1.1806 1.1745 1.1676 1.1601 1.1520 1.1433 1.1339 1.1239 1.1133 1.1027 1.0996 1.1015 1.1050 1.1114 1.1180 1.1234 1.1277 1.1309 1.1327 1.1336 1.1323 1.1311 1.1349 1.1387 1.1431 1.0000 1.2714 1.2620 1.2508 1.2382 1.2245 1.2101 1.1952 1.1801 1.1666 1.1561 1.1488 1.1435 1.1377 1.1323 1.1289 1.1266 1.1238 1.1206 1.1171 1.1131 1.1087 1.1036 1.0972 1.0983 1.1081 1.1214 1.1340 1.1459 1.1567 1.1661 1.1741 1.1805 1.1853 1.1885 1.1892 1.1894 1.1941 1.1976 1.2010 1.0000 1.2844 1.2743 1.2624 1.2491 1.2348 1.2197 1.2042 1.1883 1.1724 1.1569 1.1472 1.1470 1.1491 1.1511 1.1526 1.1537 1.1541 1.1537 1.1525 1.1503 1.1473 1.1431 1.1401 1.1454 1.1569 1.1652 1.1727 1.1799 1.1872 1.1937 1.1983 1.2012 1.2023 1.2017 1.1993 1.1955 1.1903 1.1828 1.1835 6-1.13 SSTR Rev. 140 Table 1: W(Z,BU) versus Axial Height (Sheet 2 of 2)HEIGHT (Z) W(Z,BU) W(Z,BU) W(Z,BU) W(Z,BU)(Feet) 150 3000 10000 18000 MWD/MTU MWD/MTU MWD/MTU MWD/MTU 9.0 1.1097 1.1533 1.2080 1.1891 9.2 1.1295 1.1705 1.2180 1.1928 9.4 1.1554 1.1913 1.2290 1.2020 9.6 1.1786 1.2170 1.2492 1.2133 9.8 1.1992 1.2425 1.2736 1.2343 10.0 1.2185 1.2652 1.2971 1.2647 10.2 1.2363 1.2876 1.3183 1.2947 10.4 1.2536 1.3131 1.3366 1.3201 10.6 1.2716 1.3374 1.3527 1.3405 10.8 1.2876 1.3526 1.3629 1.3568>1 1.0 1.0000 1.0000 1.0000 1.0000 Note: The FQ(Z) surveillance exclusion zone is specified Specification 4.2.2.2.g by Technical 6-1.14 SSTR Rev. 140