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| {{#Wiki_filter:TABLE 1.1 FREQUENCY NOTATION NOTATION FREQUENCY S At least once per 12 hours. | | {{#Wiki_filter:}} |
| D At least once per 24 hours.
| |
| W At least once per 7 days.
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| M At least once per 31 days.
| |
| Q At least once per 92 days.
| |
| SA At least once per 184 days.
| |
| R At least once per 18 months.
| |
| S/U Prior to each reactor startup.
| |
| N.A. Not applicable.
| |
| P Completed prior to each release.
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| SFCP In accordance with the Surveillance Frequency Control Program TURKEY POINT - UNITS 3 & 4 1-7 AMENDMENT NOS. 263 AND 258
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| | |
| 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL SHUTDOWN MARGIN - Tavg GREATER THAN 200F LIMITING CONDITION FOR OPERATION 3.1.1.1 The SHUTDOWN MARGIN shall be within the limits specified in the COLR.
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| APPLICABILITY: MODES 1, 2*, 3, and 4.
| |
| ACTION:
| |
| With the SHUTDOWN MARGIN not within limits, immediately initiate and continue boration at greater than or equal to 16 gpm of a solution containing greater than or equal to 3.0 wt% (5245 ppm) boron or equivalent until the required SHUTDOWN MARGIN is restored.
| |
| SURVEILLANCE REQUIREMENTS 4.1.1.1.1 The SHUTDOWN MARGIN shall be determined to be within the limits specified in the COLR:
| |
| : a. Within 1 hour after detection of an inoperable control rod(s) and at least once per 12 hours thereafter while the rod(s) is inoperable. If the inoperable control rod is immovable or untrippable, the above required SHUTDOWN MARGIN shall be verified acceptable with an increased allowance for the withdrawn worth of the immovable or untrippable control rod(s);
| |
| : b. When in MODE 1 or MODE 2 with Keff greater than or equal to 1 by verifying that control bank withdrawal is within the limits of Specification 3.1.3.6 in accordance with the Surveillance Frequency Control Program;
| |
| : c. When in MODE 2 with Keff less than 1, within 4 hours prior to achieving reactor criticality by verifying that the predicted critical control rod position is within the limits of Specification 3.1.3.6;
| |
| : d. Prior to initial operation above 5% RATED THERMAL POWER after each fuel loading, by consideration of the factors of Specification 4.1.1.1.1e. below, with the control banks at the maximum insertion limit of Specification 3.1.3.6; and
| |
| *See Special Test Exceptions Specification 3.10.1.
| |
| TURKEY POINT - UNITS 3 & 4 3/4 1-1 AMENDMENT NOS. 263 AND 258
| |
| | |
| REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
| |
| : e. In accordance with the Surveillance Frequency Control Program, when in MODE 3 or 4 by consideration of the following factors:
| |
| : 1) Reactor Coolant System boron concentration,
| |
| : 2) Control rod position,
| |
| : 3) Reactor Coolant System average temperature,
| |
| : 4) Fuel burnup based on gross thermal energy generation,
| |
| : 5) Xenon concentration, and
| |
| : 6) Samarium concentration.
| |
| 4.1.1.1.2 When in Mode 1 or 2, the overall core reactivity balance shall be compared to predicted values to demonstrate agreement within 1% k/k in accordance with the Surveillance Frequency Control Program. This comparison shall consider at least those factors stated in Specification 4.1.1.1.1e, above. The predicted reactivity values shall be adjusted (normalized) to correspond to the actual core conditions prior to exceeding a fuel burnup of 60 EFPD after each fuel loading.
| |
| TURKEY POINT - UNITS 3 & 4 3/4 1-2 AMENDMENT NOS. 263 AND 258
| |
| | |
| REACTIVITY CONTROL SYSTEMS SHUTDOWN MARGIN - Tavg LESS THAN OR EQUAL TO 200F LIMITING CONDITION FOR OPERATION 3.1.1.2 The SHUTDOWN MARGIN shall be within the limit specified in the COLR.
| |
| APPLICABILITY: MODE 5.
| |
| ACTION:
| |
| With the SHUTDOWN MARGIN not within limits, immediately initiate and continue boration at greater than or equal to 16 gpm of a solution containing greater than or equal to 3.0 wt% (5245 ppm) boron or equivalent until the required SHUTDOWN MARGIN is restored.
| |
| SURVEILLANCE REQUIREMENTS 4.1.1.2 The SHUTDOWN MARGIN shall be determined to be within the limit specified in the COLR:
| |
| : a. Within 1 hour after detection of an inoperable control rod(s) and at least once per 12 hours thereafter while the rod(s) is inoperable. If the inoperable control rod is immovable or untrippable, the SHUTDOWN MARGIN shall be verified acceptable with an increased allowance for the withdrawn worth of the immovable or untrippable control rod(s); and
| |
| : b. In accordance with the Surveillance Frequency Control Program by consideration of the following factors:
| |
| : 1) Reactor Coolant System boron concentration,
| |
| : 2) Control rod position,
| |
| : 3) Reactor Coolant System average temperature,
| |
| : 4) Fuel burnup based on gross thermal energy generation,
| |
| : 5) Xenon concentration, and
| |
| : 6) Samarium concentration.
| |
| TURKEY POINT - UNITS 3 & 4 3/4 1-3 AMENDMENT NOS. 263 AND 258
| |
| | |
| REACTIVITY CONTROL SYSTEMS 3/4.1.2 BORATION SYSTEMS FLOW PATH - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.1 As a minimum, one of the following boron injection flow paths shall be OPERABLE and capable of being powered from an OPERABLE emergency power source:
| |
| : a. A flow path from the boric acid storage tanks via a boric acid transfer pump and a charging pump to the Reactor Coolant System if the boric acid storage tank in Specification 3.1.2.4a. is OPERABLE, or
| |
| : b. The flow path from the refueling water storage tank via a charging pump to the Reactor Coolant System if the refueling water storage tank in Specification 3.1.2.4b. is OPERABLE.
| |
| APPLICABILITY: MODES 5 and 6.
| |
| ACTION:
| |
| With none of the above flow paths OPERABLE or capable of being powered from an OPERABLE emergency power source, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.
| |
| SURVEILLANCE REQUIREMENTS 4.1.2.1 At least one of the above required flow paths shall be demonstrated OPERABLE:
| |
| : a. In accordance with the Surveillance Frequency Control Program by verifying that the temperature of the rooms containing flow path components is greater than or equal to 62F when a flow path from the boric acid tanks is used, and
| |
| : b. In accordance with the Surveillance Frequency Control Program by verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
| |
| TURKEY POINT - UNITS 3 & 4 3/4 1-7 AMENDMENT NOS. 263 AND 258
| |
| | |
| REACTIVITY CONTROL SYSTEMS SURVEI LLANCE REQUIREMENTS 4.1.2.2 The above required flow paths shall be demonstrated OPERABLE:
| |
| : a. In accordance with the Surveillance Frequency Control Program by verifying that the temperature of the rooms containing flow path components is greater than or equal to 62F when a flow path from the boric acid tanks is used;
| |
| : b. In accordance with the Surveillance Frequency Control Program by verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position;
| |
| : c. In accordance with the Surveillance Frequency Control Program by verifying that the flow path required by Specification 3.1.2.2a. and c. delivers at least 16 gpm to the RCS.
| |
| TURKEY POINT - UNITS 3 & 4 3/4 1-9 AMENDMENT NOS. 263 AND 258
| |
| | |
| REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCE - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.4 As a minimum, one of the following borated water sources shall be OPERABLE:
| |
| : a. A Boric Acid Storage System with:
| |
| : 1) A minimum indicated borated water volume of 2,900 gallons per unit,
| |
| : 2) A boron concentration between 3.0 wt% (5245 ppm) and 4.0 wt.% (6993 ppm), and
| |
| : 3) A minimum boric acid tanks room temperature of 62F.
| |
| : b. The refueling water storage tank (RWST) with:
| |
| : 1) A minimum indicated borated water volume of 20,000 gallons,
| |
| : 2) A boron concentration between 2400 ppm and 2600 ppm, and
| |
| : 3) A minimum solution temperature of 39F.
| |
| APPLICABILITY: MODES 5 and 6.
| |
| ACTION:
| |
| With no borated water source OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.
| |
| SURVEI LLANCE REQUIREMENTS 4.1.2.4 The above required borated water source shall be demonstrated OPERABLE:
| |
| : a. In accordance with the Surveillance Frequency Control Program by:
| |
| : 1) Verifying the boron concentration of the water,
| |
| : 2) Verifying the indicated borated water volume, and
| |
| : 3) Verifying that the temperature of the boric acid tanks room is greater than or equal to 62F, when it is the source of borated water.
| |
| TURKEY POINT - UNITS 3 & 4 3/4 1-11 AMENDMENT NOS. 263 AND 258
| |
| | |
| REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS 4.1.2.5 Each borated water source shall be demonstrated OPERABLE:
| |
| : a. In accordance with the Surveillance Frequency Control Program by:
| |
| : 1) Verifying the boron concentration in the water,
| |
| : 2) Verifying the indicated borated water volume of the water source, and
| |
| : 3) Verifying that the temperature of the boric acid tanks room is greater than or equal to 62F, when it is the source of borated water.
| |
| : b. By verifying the RWST temperature is within limits whenever the outside air temperature is less than 39F or greater than 100F at the following frequencies:
| |
| : 1) Within one hour upon the outside temperature exceeding its limit for 23 consecutive hours, and
| |
| : 2) At least once per 24 hours while the outside temperature exceeds its limits.
| |
| TURKEY POINT - UNITS 3 & 4 3/4 1-15 AMENDMENT NOS. 263 AND 258
| |
| | |
| REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)
| |
| : d. With one full length rod inoperable due to causes other than addressed by ACTION a, above, or misaligned from its group step counter demand position by more than the Allowed Rod Misalignment of Specification 3.1.3.1, POWER OPERATION may continue provided that within one hour either:
| |
| : 1. The rod is restored to OPERABLE status within the Allowed Rod Misalignment of Specification 3.1.3.1, or
| |
| : 2. The remainder of the rods in the bank with the inoperable rod are aligned to within the Allowed Rod Misalignment of Specification 3.1.3.1 of the inoperable rod while maintaining the rod sequence and insertion limits of Specification 3.1.3.6; the THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation, or
| |
| : 3. The rod is declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied. POWER OPERATION may then continue provided that:
| |
| a) The THERMAL POWER level is reduced to less than or equal to 75% of RATED THERMAL POWER within one hour and within the next 4 hours the power range neutron flux high trip setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER. THERMAL POWER shall be maintained less than or equal to 75% of RATED THERMAL POWER until compliance with ACTIONS 3.1.3.1.d.3.c and 3.1.3.1.d.3.d below are demonstrated, and b) The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours, and c) A power distribution map is obtained from the movable incore detectors and N
| |
| FQ (Z) and F H are verified to be within their limits within 72 hours, and d) A reevaluation of each accident analysis of Table 3.1-1 is performed within 5 days; this reevaluation shall confirm that the previously analyzed results of these accidents remain valid for the duration of operation under these conditions.
| |
| SURVEILLANCE REQUIREMENTS 4.1.3.1.1 The position of each full length rod shall be determined to be within the Allowed Rod Misalignment of the group step counter demand position in accordance with the Surveillance Frequency Control Program (allowing for one hour thermal soak after rod motion) except during time intervals when the Rod Position Deviation Monitor is inoperable, then verify the group positions at least once per 4 hours.
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| 4.1.3.1.2 Each full length rod not fully inserted in the core shall be determined to be OPERABLE by movement of at least 10 steps in any one direction in accordance with the Surveillance Frequency Control Program.
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| TURKEY POINT - UNITS 3 & 4 3/4 1-17 AMENDMENT NOS. 263 AND 258
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| | |
| REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS 4.1.3.2.1 Each analog rod position indicator shall be determined to be OPERABLE by verifying that the Demand Position Indication System and the Analog Rod Position Indication System agree within the Allowed Rod Misalignment of Specification 3.1.3.1 (allowing for one hour thermal soak after rod motion) in accordance with the Surveillance Frequency Control Program except during time intervals when the Rod Position Deviation Monitor is inoperable, then compare the Demand Position Indication System and the Analog Rod Position Indication System at least once per 4 hours.
| |
| 4.1.3.2.2 Each of the above required analog rod position indicator(s) shall be determined to be OPERABLE by performance of a CHANNEL CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST performed in accordance with the Table 4.1-1.
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| TURKEY POINT - UNITS 3 & 4 3/4 1-21 AMENDMENT NOS. 263 AND 258
| |
| | |
| TABLE 4.1-1 ROD POSITION INDICATOR SURVEILLANCE REQUIREMENTS Functional Unit Check Calibration Operational Test Individual Rod Position SFCP SFCP SFCP Demand Position SFCP N/A SFCP TURKEY POINT - UNITS 3 & 4 3/4 1-22 AMENDMENT NOS. 263 AND 258
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| | |
| REACTIVITY CONTROL SYSTEMS POSITION INDICATION SYSTEM - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.3.3 The group step counter demand position indicator shall be OPERABLE and capable of determining within
| |
| +/- 2 steps the demand position for each shutdown and control rod not fully inserted.
| |
| APPLICABILITY: MODES 3* **, 4* **, and 5* **
| |
| ACTION:
| |
| With less than the above required group step counter demand position indicator(s) OPERABLE, open the reactor trip system breakers.
| |
| SURVEILLANCE REQUIREMENTS 4.1.3.3.1 Each of the above required group step counter demand position indicator(s) shall be determined to be OPERABLE by movement of the associated control rod at least 10 steps in any one direction in accordance with the Surveillance Frequency Control Program.
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| 4.1.3.3.2 OPERABILITY of the group step counter demand position indicator shall be verified in accordance with Table 4.1-1.
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| * With the Reactor Trip System breakers in the closed position.
| |
| ** See Special Test Exceptions Specification 3.10.5.
| |
| TURKEY POINT - UNITS 3 & 4 3/4 1-23 AMENDMENT NOS. 263 AND 258
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| | |
| REACTIVITY CONTROL SYSTEMS ROD DROP TIME LIMITING CONDITION FOR OPERATION 3.1.3.4 The individual full-length (shutdown and control) rod drop time from the fully withdrawn position shall be less than or equal to 2.4 seconds from beginning of decay of stationary gripper coil voltage to dashpot entry with:
| |
| : a. Tavg greater than or equal to 500F, and
| |
| : b. All reactor coolant pumps operating.
| |
| APPLICABILITY: MODES 1 and 2.
| |
| ACTION:
| |
| With the drop time of any full-length rod determined to exceed the above limit, restore the rod drop time to within the above limit prior to proceeding to MODE 1 or 2.
| |
| SURVEILLANCE REQUIREMENTS 4.1.3.4 The rod drop time of full-length rods shall be demonstrated through measurement prior to reactor criticality:
| |
| : a. For all rods following each removal of the reactor vessel head,
| |
| : b. For specifically affected individual rods following any maintenance on or modification to the Control Rod Drive System which could affect the drop time of those specific rods, and
| |
| : c. In accordance with the Surveillance Frequency Control Program.
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| TURKEY POINT - UNITS 3 & 4 3/4 1-24 AMENDMENT NOS. 263 AND 258
| |
| | |
| REACTIVITY CONTROL SYSTEMS SHUTDOWN ROD INSERTION LIMIT LIMITING CONDITION FOR OPERATION 3.1.3.5 All shutdown rods shall be fully withdrawn.
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| APPLICABILITY: MODES 1* and 2* **
| |
| ACTION:
| |
| With a maximum of one shutdown rod not fully withdrawn, except for surveillance testing pursuant to Specification 4.1.3.1.2, within 1 hour either:
| |
| : a. Fully withdraw the rod, or
| |
| : b. Declare the rod to be inoperable and apply Specification 3.1.3.1.
| |
| SURVEILLANCE REQUIREMENTS 4.1.3.5 Each shutdown rod shall be determined to be fully withdrawn:
| |
| : a. Within 15 minutes prior to withdrawal of any rods in control banks A, B, C, or D during an approach to reactor criticality, and
| |
| : b. In accordance with the Surveillance Frequency Control Program thereafter.
| |
| *See Special Test Exceptions Specifications 3.10.2 and 3.10.3.
| |
| **With Keff greater than or equal to 1.0 TURKEY POINT - UNITS 3 & 4 3/4 1-25 AMENDMENT NOS. 263 AND 258
| |
| | |
| REACTIVITY CONTROL SYSTEMS CONTROL ROD INSERTION LIMITS LIMITING CONDITION FOR OPERATION 3.1.3.6 The control banks shall be limited in physical insertion specified in the Rod Bank Insertion Limits curve, defined in the CORE OPERATING LIMITS REPORT.
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| APPLICABILITY: MODES 1* and 2* **
| |
| ACTION:
| |
| With the control banks inserted beyond the above insertion limits, except for surveillance testing pursuant to Specification 4.1.3.1.2 either:
| |
| : a. Restore the control banks to within the limits within 2 hours, or
| |
| : b. Reduce THERMAL POWER within two hours to less than or equal to that fraction of RATED THERMAL POWER which is allowed by the bank position specified in the Rod Bank Insertion Limits curve, defined in the CORE OPERATING LIMITS REPORT, or
| |
| : c. Be in at least HOT STANDBY within 6 hours.
| |
| SURVEILLANCE REQUIREMENTS 4.1.3.6 The position of each control bank shall be determined to be within the insertion limits in accordance with the Surveillance Frequency Control Program, except during time intervals when the Rod Insertion Limit Monitor is inoperable, then verify the individual rod positions at least once per 4 hours.
| |
| * See Special Test Exceptions Specifications 3.10.2 and 3.10.3.
| |
| ** With Keff greater than or equal to 1.0 TURKEY POINT - UNITS 3 & 4 3/4 1-26 AMENDMENT NOS. 263 AND 258
| |
| | |
| POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS 4.2.1.1 The indicated AFD shall be determined to be within its limits during POWER OPERATION above 50% of RATED THERMAL POWER by:
| |
| : a. Monitoring the indicated AFD for each OPERABLE excore channel:
| |
| : 1) In accordance with the Surveillance Frequency Control Program when the alarm used to monitor the AFD is OPERABLE, and
| |
| : 2) At least once per hour for the first 6 hours after restoring the alarm used to monitor the AFD to OPERABLE status.*
| |
| : b. Monitoring and logging the indicated AFD for each OPERABLE excore channel at least once per hour for the first 24 hours and at least once per 30 minutes thereafter, when the alarm used to monitor the AFD is inoperable. The logged values of the indicated AFD shall be assumed to exist during the interval preceding each logging.
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| 4.2.1.2 The target flux difference of each OPERABLE excore channel shall be determined by measurement in accordance with the Surveillance Frequency Control Program. The provisions of Specification 4.0.4 are not applicable.
| |
| 4.2.1.3 In accordance with the Surveillance Frequency Control Program, the target flux difference shall be updated by either determining the target flux difference pursuant to Specification 4.2.1.2 above or by linear interpolation between the most recently measured value and the predicted value at the end of the cycle life. The provisions of Specification 4.0.4 are not applicable.
| |
| * Performance of a functional test to demonstrate OPERABILITY of the alarm used to monitor the AFD may be substituted for this requirement.
| |
| TURKEY POINT - UNITS 3 & 4 3/4 2-2 AMENDMENT NOS. 263 AND 258
| |
| | |
| POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS 4.2.2.1 If [FQ]P as predicted by approved physics calculations is greater than [FQ]L and P is greater than PT* as defined in 4.2.2.2, FQ(Z) shall be evaluated by MIDS (Specification 4.2.2.2), BASE LOAD (Specification 4.2.2.3) or RADIAL BURNDOWN (Specification 4.2.2.4) to determine if FQ is within its limit [FQ]P = Predicted FQ).
| |
| If [FQ]P, is less than [FQ]L or P is less than PT, FQ(Z) shall be evaluated to determine if FQ(Z) is within its limit as follows:
| |
| : a. Using the movable incore detectors to obtain power distribution map at any THERMAL POWER greater than 5% of RATED THERMAL POWER.
| |
| : b. Increasing the measured FQ(Z) component of the power distribution map by 3% to account for manufacturing tolerances and further increasing the value by 5% to account for measurement uncertainties. Verifying that the requirements of Specification 3.2.2 are satisfied.
| |
| L
| |
| : c. FM (Z)
| |
| Q F Q (Z)
| |
| M Where F Q (Z) is the measured FQ(Z) increased by the allowance for manufacturing tolerances and measurement uncertainty and L (Z) is the FQ limit defined in 3.2.2.
| |
| FQ M
| |
| : d. Measuring F Q (Z) according to the following schedule:
| |
| : 1. Prior to exceeding 75% of RATED THERMAL POWER,** after refueling,
| |
| : 2. In accordance with the Surveillance Frequency Control Program.
| |
| : e. With the relationship specified in Specification 4.2.2.1.c above not being satisfied:
| |
| : 1) Calculate the percent F M(Z) exceeds its limit by the following expression:
| |
| Q M
| |
| F (Z)
| |
| Q 1 X 100 for P 0.5 L
| |
| [FQ ] X K(Z)/P M
| |
| F (Z)
| |
| Q 1 X 100 for P 0.5 L
| |
| [FQ ] X K(Z)/0.5
| |
| * PT = Reactor power level at which predicted FQ would exceed its limit.
| |
| ** During power escalation at the beginning of each cycle, power level may be increased until a power level for extended operation has been achieved and power distribution map obtained.
| |
| TURKEY POINT - UNITS 3 & 4 3/4 2-4 AMENDMENT NOS. 263 AND 258
| |
| | |
| POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued)
| |
| : 2) The following action shall be taken:
| |
| a) Comply with the requirements of Specification 3.2.2 for F M Q (Z) exceeding its limit by the percent calculated above.
| |
| 4.2.2.2 MIDS Operation is permitted at power above PT where PT equals the ratio of [FQ]L divided by [FQ]P if the following Augmented Surveillance (Movable Incore Detection System, MIDS) requirements are satisfied:
| |
| : a. The axial power distribution shall be measured by MIDS when required such that the limit of [FQ]L/P times K(Z) is not exceeded. Fj(Z) is the normalized axial power distribution from thimble j at core elevation (Z).
| |
| : 1) If Fj(Z) exceeds [Fj(Z)]s* as defined in the bases by 4%, immediately reduce thermal power one percent for every percent by which [Fj(Z)]s is exceeded.
| |
| : 2) If Fj(Z) exceeds [Fj(Z)]s by > 4% immediately reduce thermal power below PT.
| |
| Corrective action to reduce Fj(Z) below the limit will permit return to thermal power not to exceed current PL** as defined in the bases.
| |
| : b. Fj(Z) shall be determined to be within limits by using MIDS to monitor the thimbles required per Specification 4.2.2.2.c at the following frequencies.
| |
| : 1. In accordance with the Surveillance Frequency Control Program, and
| |
| : 2. Immediately following and as a minimum at 2, 4 and 8 hours following the events listed below and in accordance with the Surveillance Frequency Control Program thereafter.
| |
| : 1) Raising the thermal power above PT, or
| |
| : 2) Movement of control-bank D more than an accumulated total of 15 steps in any one direction.
| |
| : c. MIDS shall be operable when the thermal power exceeds PT with:
| |
| : 1) At least two thimbles available for which Rj and j as defined in the bases have been determined.
| |
| * [Fj(Z)]s is the alarm setpoint for MIDS.
| |
| ** PL is reactor thermal power expressed as a fraction of the Rated Thermal Power that is used to calculate
| |
| [Fj(Z)]s.
| |
| TURKEY POINT - UNITS 3 & 4 3/4 2-5 AMENDMENT NOS. 263 AND 258
| |
| | |
| POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued)
| |
| : 2. At least two movable detectors available for mapping Fj(Z).
| |
| : 3. The continued accuracy and representativeness of the selected thimbles shall be verified by using the most recent flux map to update the R for each selected thimble. The flux map must be updated in accordance with the Surveillance Frequency Control Program.
| |
| where:
| |
| R = Total peaking factor from a full flux map ratioed to the axial peaking factor in a selected thimble.
| |
| j - The thimble location selected for monitoring.
| |
| 4.2.2.3 Base Load Base Load operation is permitted at powers above PT if the following requirements are satisfied:
| |
| : a. Either of the following preconditions for Base Load operation must be satisfied.
| |
| : 1. For entering Base Load operation with power less than PT, a) Maintain THERMAL POWER between PT/1.05 and PT for at least 24 hours, b) Maintain the AFD (Delta-I) to within a +/- 2% or +/- 3% target band for at least 23 hours per 24-hour period.
| |
| c) After 24 hours have elapsed, take a full core flux map to determine F M (Z)
| |
| Q unless a valid full core flux map was taken within the time period specified in 4.2.2.1d.
| |
| d) Calculate PBL per 4.2.2.3b.
| |
| : 2. For entering Base Load operation with power greater than PT, a) Maintain THERMAL POWER between PT and the power limit determined in 4.2.2.2 for at least 24 hours, and maintain Augmented Surveillance requirements of 4.2.2.2 during this period.
| |
| b) Maintain the AFD (Delta-I) to within a +/- 2% or +/- 3% target band for at least 23 hours per 24-hour period, TURKEY POINT - UNITS 3 & 4 3/4 2-6 AMENDMENT NOS. 263 AND 258
| |
| | |
| POWER DISTRIBUTION LIMITS 3/4.2.5 DNB PARAMETERS LIMITING CONDITION FOR OPERATION 3.2.5 The following DNB-related parameters shall be maintained within the following limits:
| |
| : a. Reactor Coolant System Tavg is less than or equal to the limit specified in the COLR
| |
| : b. Pressurizer Pressure is greater than or equal to the limit specified in the COLR*, and
| |
| : c. Reactor Coolant System Flow 270,000 gpm APPLICABILITY: MODE 1.
| |
| ACTION:
| |
| With any of the above parameters exceeding its limit, restore the parameter to within its limit within 2 hours or reduce THERMAL POWER to less then 5% of RATED THERMAL POWER within the next 4 hours.
| |
| SURVEILLANCE REQUIREMENTS 4.2.5.1 Reactor Coolant System Tavg and Pressurizer Pressure shall be verified to be within their limits in accordance with the Surveillance Frequency Control Program 4.2.5.2 RCS flow rate shall be monitored for degradation in accordance with the Surveillance Frequency Control Program.
| |
| 4.2.5.3 The RCS flow rate indicators shall be subjected to a CHANNEL CALIBRATION in accordance with the Surveillance Frequency Control Program.
| |
| 4.2.5.4 After each fuel loading, and in accordance with the Surveillance Frequency Control Program, the RCS flow rate shall be determined by precision heat balance after exceeding 90% RATED THERMAL POWER. The measurement instrumentation shall be calibrated within 90 days prior to the performance of the calorimetric flow measurement. The provisions of 4.0.4 are not applicable for performing the precision heat balance flow measurement.
| |
| * Limit not applicable during either a THERMAL POWER ramp in excess of 5% of RATED THERMAL POWER per minute or a THERMAL POWER step in excess of 10% of RATED THERMAL POWER.
| |
| TURKEY POINT - UNITS 3 & 4 3/4 2-14 AMENDMENT NOS. 263 AND 258
| |
| | |
| TABLE 4.3-1 TURKEY POINT - UNITS 3 & 4 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS TRIP ANALOG ACTUATING MODES FOR CHANNEL DEVICE WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED
| |
| : 1. Manual Reactor Trip N.A. N.A. N.A. SFCP(11) N.A. 1, 2, 3*, 4*, 5*
| |
| : 2. Power Range, Neutron Flux
| |
| : a. High Setpoint SFCP SFCP(2, 4), SFCP(a), (b) N.A. N.A. 1, 2 SFCP(3, 4),
| |
| (a), (b)
| |
| SFCP(4, 6),
| |
| (a), (b)
| |
| SFCP(4)
| |
| : b. Low Setpoint SFCP SFCP(4) S/U(1) N.A. N.A. 1***, 2 3/4 3-8
| |
| : 3. Intermediate Range, SFCP SFCP(4) S/U(1) N.A. N.A. 1***, 2 Neutron Flux
| |
| : 4. Source Range, Neutron Flux SFCP SFCP(4) S/U(1), N.A. N.A. 2**,3, 4, 5 SFCP(9)
| |
| : 5. Overtemperature T SFCP SFCP(a), (b) SFCP(a), (b) N.A. N.A. 1, 2 (a), (b) (a), (b)
| |
| : 6. Overpower T SFCP SFCP SFCP N.A. N.A. 1, 2
| |
| : 7. Pressurizer Pressure--Low SFCP SFCP SFCP N.A. N.A. 1 AMENDMENT NOS. 263 AND 258
| |
| : 8. Pressurizer Pressure--High SFCP SFCP SFCP N.A. N.A. 1, 2
| |
| : 9. Pressurizer Water Level--High SFCP SFCP SFCP N.A. N.A. 1 (a), (b) (a), (b)
| |
| : 10. Reactor Coolant Flow--Low SFCP SFCP SFCP N.A. N.A. 1
| |
| : 11. Steam Generator Water Level-- SFCP SFCP(a), (b) SFCP(a), (b) N.A. N.A. 1, 2 Low-Low
| |
| | |
| TABLE 4.3-1 TURKEY POINT - UNITS 3 & 4 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS TRIP ANALOG ACTUATING MODES FOR CHANNEL DEVICE WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED
| |
| : 12. Steam Generator Water SFCP SFCP(a), (b) SFCP(a), (b) N.A. N.A. 1, 2 Level--Low Coincident with Steam/Feedwater Flow Mismatch
| |
| : 13. Undervoltage - 4.16 kV N.A. SFCP N.A. N.A. N.A. 1 Busses A and B
| |
| : 14. Underfrequency - Trip of N.A. SFCP N.A. N.A. N.A. 1 Reactor Coolant Pump 3/4 3-9 Breakers(s) Open
| |
| : 15. Turbine Trip (a), (b)
| |
| : a. Emergency Trip Header N.A. SFCP N.A. S/U(1, 10) N.A. 1 Pressure
| |
| : b. Turbine Stop Valve N.A. SFCP N.A. S/U(1, 10) N.A. 1 Closure
| |
| : 16. Safety Injection Input from ESF N.A. N.A. N.A. SFCP N.A. 1, 2 AMENDMENT NOS. 263 AND 258
| |
| : 17. Reactor Trip System Interlocks
| |
| : a. Intermediate Range Neutron Flux, P-6 N.A. SFCP(4) SFCP N.A. N.A. 2**
| |
| : b. Low Power Reactor Trips Block, P-7 N.A. SFCP(4) SFCP N.A. N.A. 1 (includes P-10 input and Turbine Inlet Pressure)
| |
| : c. Power Range Neutron Flux, P-8 N.A. SFCP(4) SFCP N.A. N.A. 1
| |
| | |
| TABLE 4.3-1 TURKEY POINT - UNITS 3 & 4 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS TRIP ANALOG ACTUATING MODES FOR CHANNEL DEVICE WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED
| |
| : 17. Reactor Trip System Interlocks (Continued)
| |
| : d. Power Range Neutron Flux, P-10 N.A. SFCP(4) SFCP N.A. N.A. 1, 2
| |
| : 18. Reactor Coolant Pump N.A. N.A. N.A. SFCP N.A. 1 Breaker Position Trip
| |
| : 19. Reactor Trip Breaker N.A. N.A. N.A. SFCP(7, 11) N.A. 1, 2, 3*, 4*, 5*
| |
| 3/4 3-10 20. Automatic Trip and Inter-lock Logic N.A. N.A. N.A. N.A. SFCP(7,14) 1, 2, 3*, 4*, 5*
| |
| : 21. Reactor Trip Bypass Breaker N.A. N.A. N.A. SFCP(13), N.A. 1, 2, 3*, 4*, 5*
| |
| SFCP(15)
| |
| AMENDMENT NOS. 263 AND 258
| |
| | |
| TABLE 4.3-1 (Continued)
| |
| TABLE NOTATIONS
| |
| * When the Reactor Trip System breakers are closed and the Control Rod Drive System is capable of rod withdrawal.
| |
| ** Below P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.
| |
| *** Below P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.
| |
| (a) If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
| |
| (b) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTS) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTS are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the surveillance procedures (field settings) to confirm channel performance. The NTS and methodologies used to determine the as-found and the as-left tolerances are specified in UFSAR Section 7.2.
| |
| (1) If not performed in previous 31 days.
| |
| (2) Comparison of calorimetric to excore power level indication above 15% of RATED THERMAL POWER (RTP). Adjust excore channel gains consistent with calorimetric power level if the absolute difference is greater than 2%. Below 70% RTP, downward adjustments of NIS excore channel gains to match a lower calorimetric power level are not required. The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.
| |
| (3) Single point comparison of incore to excore AXIAL FLUX DIFFERENCE above 15% of RATED THERMAL POWER. Recalibrate if the absolute difference is greater than or equal to 3%. The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.
| |
| (4) Neutron detectors may be excluded from CHANNEL CALIBRATION.
| |
| (5) This table Notation number is not used.
| |
| (6) Incore-Excore Calibration, above 75% of RATED THERMAL POWER (RTP). If the quarterly surveillance requirement coincides with sustained operation between 30% and 75% of RTP, calibration shall be performed at this lower power level. The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.
| |
| (7) Each train shall be tested in accordance with the Surveillance Frequency Control Program.
| |
| (8) DELETED (9) Quarterly surveillance in MODES 3*, 4*, and 5* shall also include verification that permissive P-6 and P-10 are in their required state for existing plant conditions by observation of the permissive annunciator window. Quarterly surveillance shall include verification of the High Flux at Shutdown Alarm Setpoint of 1/2 decade above the existing count rate.
| |
| (10) Setpoint verification is not applicable.
| |
| (11) The TRIP ACTUATING DEVICE OPERATIONAL TEST shall include independent verification of the OPERABILITY of the undervoltage and shunt trip attachment of the Reactor Trip Breakers.
| |
| TURKEY POINT - UNITS 3 & 4 3/4 3-11 AMENDMENT NOS. 263 AND 258
| |
| | |
| TABLE 4.3-2 TURKEY POINT - UNITS 3 & 4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS TRIP ANALOG ACTUATING MODES CHANNEL DEVICE FOR WHICH CHANNEL CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST # IS REQUIRED
| |
| : 1. Safety Injection 3/4 3-32
| |
| : a. Manual Initiation N.A. N.A. N.A. SFCP N.A. 1, 2, 3
| |
| : b. Automatic Actuation N.A. N.A. N.A. N.A. SFCP(1) 1, 2, 3(3)
| |
| Logic and Actuation Relays
| |
| : c. Containment Pressure-- N.A. SFCP N.A. N.A. SFCP(1) 1, 2, 3 High
| |
| : d. Pressurizer Pressure-- SFCP SFCP SFCP(5) N.A. N.A. 1, 2, 3(3)
| |
| AMENDMENT NOS. 263 AND 258 Low
| |
| : e. High Differential SFCP SFCP SFCP(5) N.A. N.A. 1, 2, 3(3)
| |
| Pressure Between the Steam Line Header and any Steam Line (a)(b)
| |
| : f. Steam Line Flow--High SFCP SFCP SFCP(5)(a)(b) N.A N.A 1, 2, 3(3)
| |
| Coincident with:
| |
| Steam Generator Pressure--Low SFCP SFCP(a)(b) SFCP(5)(a)(b) N.A. N.A. 1, 2, 3(3) or Tavg--Low SFCP SFCP SFCP(5) N.A. N.A. 1, 2, 3(3)
| |
| | |
| TABLE 4.3-2 (Continued)
| |
| ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS TURKEY POINT - UNITS 3 & 4 TRIP ANALOG ACTUATING MODES CHANNEL DEVICE FOR WHICH CHANNEL CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST # IS REQUIRED
| |
| : 2. Containment Spray
| |
| : a. Automatic Actuation N.A. N.A. N.A. N.A. SFCP(1) 1, 2, 3, 4 Logic and Actuation Relays
| |
| : b. Containment Pressure-- N.A. SFCP N.A. SFCP SFCP(1) 1, 2, 3 High-High Coincident with:
| |
| Containment Pressure--
| |
| High N.A. SFCP N.A. SFCP SFCP(1) 1, 2, 3 3/4 3-33
| |
| : 3. Containment Isolation
| |
| : a. Phase A Isolation
| |
| : 1) Manual Initiation N.A. N.A. N.A. SFCP N.A. 1, 2, 3, 4
| |
| : 2) Automatic Actua- N.A. N.A. N.A. N.A. SFCP(1) 1, 2, 3, 4 tion Logic and AMENDMENT NOS. 263 AND 258 Actuation Relays
| |
| : 3) Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.
| |
| : b. Phase B Isolation
| |
| : 1) Manual Initiation N.A. N.A. N.A. SFCP N.A. 1, 2, 3, 4
| |
| : 2) Automatic Actua- N.A. N.A. N.A. N.A. SFCP(1) 1, 2, 3, 4 tion Logic and Actuation Relays
| |
| | |
| TABLE 4.3-2 (Continued)
| |
| ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TURKEY POINT - UNIT 3 & 4 SURVEILLANCE REQUIREMENTS TRIP ANALOG ACTUATING MODES CHANNEL DEVICE ACTUATION FOR WHICH CHANNEL CHANNEL CHANNEL OPERATIONAL OPERATIONAL LOGIC SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST TEST # IS REQUIRED
| |
| : 3. Containment Isolation (Continued)
| |
| : 3) Containment N.A. SFCP N.A. SFCP SFCP(1) 1, 2, 3 Pressure--High-High Coincident with: Containment Pressure--High N.A. SFCP N.A. SFCP SFCP(1) 1, 2, 3
| |
| : c. Containment Venti-lation Isolation 3/4 3-34
| |
| : 1) Containment N.A. N.A. N.A. SFCP N.A. 1, 2, 3, 4 Isolation Manual Phase A or Manual Phase B
| |
| : 2) Automatic Actua- N.A. N.A. N.A. N.A. N.A.
| |
| tion Logic and Actuation Relays AMENDMENT NOS. 263 AND 258
| |
| : 3) Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.
| |
| : 4) Containment Radio- SFCP SFCP SFCP N.A. N.A. 1, 2, 3, 4 activity--High
| |
| : 4. Steam Line Isolation
| |
| : a. Manual Initiation N.A. N.A. N.A. SFCP N.A. 1, 2, 3
| |
| : b. Automatic Actuation N.A. N.A. N.A. N.A. SFCP(1) 1, 2, 3(3)
| |
| Logic and Actuation Relays
| |
| | |
| TABLE 4.3-2 (Continued)
| |
| ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TURKEY POINT - UNITS 3 & 4 SURVEILLANCE REQUIREMENTS TRIP ANALOG ACTUATING MODES CHANNEL DEVICE FOR WHICH CHANNEL CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST # IS REQUIRED
| |
| : 4. Steamline Isolation (Continued)
| |
| : c. Containment Pressure-- N.A. SFCP N.A. SFCP SFCP(1) 1, 2, 3 High-High Coincident with:
| |
| Containment Pressure-- N.A. SFCP N.A SFCP SFCP(1) 1, 2, 3 High (a)(b)
| |
| : d. Steam Line Flow--High SFCP(3) SFCP SFCP(5)(a)(b) N.A. N.A. 1, 2, 3 Coincident with:
| |
| 3/4 3-35 Steam Generator Pressure--Low SFCP(3) SFCP(a)(b) SFCP(5)(a)(b) N.A. N.A. 1, 2, 3 or Tavg--Low SFCP(3) SFCP SFCP(5) N.A. N.A. 1, 2, 3
| |
| : 5. Feedwater Isolation
| |
| : a. Automatic Actuation N.A. N.A. N.A. N.A. SFCP 1, 2, 3 Logic and Actuation Relays AMENDMENT NOS. 263 AND 258
| |
| : b. Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.
| |
| (a)(b)
| |
| : c. Steam Generator Water SFCP SFCP SFCP(a)(b) N.A. N.A. 1, 2, 3 Level--High-High
| |
| : 6. Auxiliary Feedwater (2)
| |
| : a. Automatic Actuation N.A. N.A. N.A. N.A. SFCP 1, 2, 3 Logic and Actuation Relays
| |
| : b. Steam Generator SFCP SFCP(a)(b) SFCP(a)(b) N.A. N.A. 1, 2, 3 Water Level--Low-Low
| |
| | |
| TABLE 4.3-2 (Continued)
| |
| ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TURKEY POINT - UNITS 3 & 4 SURVEILLANCE REQUIREMENTS TRIP ANALOG ACTUATING MODES CHANNEL DEVICE FOR WHICH CHANNEL CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST # IS REQUIRED
| |
| : 6. Auxiliary Feedwater (Continued)
| |
| : c. Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.
| |
| : d. Bus Stripping N.A. SFCP N.A. SFCP N.A. 1, 2, 3
| |
| : e. Trip of All Main N.A. N.A. N.A. SFCP N.A. 1. 2 Feedwater Pump Breakers.
| |
| : 7. Loss of Power 3/4 3-36
| |
| : a. 4.16 kV busses A N.A. SFCP N.A. SFCP N.A. 1, 2, 3, 4 and B (Loss of Voltage)
| |
| : b. 480V Load Centers SFCP SFCP N.A. SFCP(1) N.A. 1, 2, 3, 4 3A, 3B, 3C, 3D and 4A, 4B, 4C, 4D Undervoltage AMENDMENT NOS. 263 AND 258 Coincident with:
| |
| Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.
| |
| : c. 480V Load Centers SFCP SFCP N.A. SFCP(1) N.A. 1, 2, 3, 4 3A, 3B, 3C, 3D and 4A, 4B, 4C, 4D Degraded Voltage
| |
| | |
| 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION STARTUP AND POWER OPERATION LIMITING CONDITION FOR OPERATION 3.4.1.1 All reactor coolant loops shall be in operation.
| |
| APPLICABILITY: MODES 1 and 2.
| |
| ACTION:
| |
| With less than the above required reactor coolant loops in operation, be in at least HOT STANDBY within 6 hours.
| |
| SURVEILLANCE REQUIREMENTS 4.4.1.1 The above required reactor coolant loops shall be verified in operation and circulating reactor coolant in accordance with the Surveillance Frequency Control Program.
| |
| TURKEY POINT - UNITS 3 & 4 3/4 4-1 AMENDMENT NOS. 263 AND 258
| |
| | |
| REACTOR COOLANT SYSTEM HOT STANDBY LIMITING CONDITION FOR OPERATION 3.4.1.2 All of the reactor coolant loops listed below shall be OPERABLE with all reactor coolant loops in operation when the Reactor Trip breakers are closed and two reactor coolant loops listed below shall be OPERABLE with at least one reactor coolant loop in operation when the Reactor Trip breakers are open:*
| |
| : a. Reactor Coolant Loop A and its associated steam generator and reactor coolant pump,
| |
| : b. Reactor Coolant Loop B and its associated steam generator and reactor coolant pump, and
| |
| : c. Reactor Coolant Loop C and its associated steam generator and reactor coolant pump.
| |
| APPLICABILITY: MODE 3 ACTION:
| |
| : a. With less than the above required reactor coolant loops OPERABLE, restore the required loops to OPERABLE status within 72 hours or be in HOT SHUTDOWN within the next 12 hours.
| |
| : b. With less than three reactor coolant loop in operation and the Reactor Trip breakers in the closed position, within 1 hour open the Reactor Trip breakers.
| |
| : c. With no reactor coolant loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required reactor coolant loop to operation.
| |
| SURVEILLANCE REQUIREMENTS 4.4.1.2.1 At least the above required reactor coolant pumps, if not in operation, shall be determined OPERABLE by verifying correct breaker alignments and indicated power availability in accordance with the Surveillance Frequency Control Program.
| |
| 4.4.1.2.2 The required steam generators shall be determined OPERABLE by verifying secondary side water level to be greater than or equal to 10% in accordance with the Surveillance Frequency Control Program.
| |
| 4.4.1.2.3 The required reactor coolant loops shall be verified in operation and circulating reactor coolant in accordance with the Surveillance Frequency Control Program.
| |
| * All reactor coolant pumps may be deenergized for up to 1 hour provided: (1) no operations are permitted that would cause dilution of the Reactor Coolant System boron concentration, and (2) core outlet temperature is maintained at least 10°F below saturation temperature.
| |
| TURKEY POINT - UNITS 3 & 4 3/4 4-2 AMENDMENT NOS. 263 AND 258
| |
| | |
| REACTOR COOLANT SYSTEM 3/4.4.3 PRESSURIZER LIMITING CONDITION FOR OPERATION 3.4.3 The pressurizer shall be OPERABLE with a water volume of less than or equal to 92% of indicated level, and at least two groups of pressurizer heaters each having a capacity of at least 125 kW and capable of being supplied by emergency power.
| |
| APPLICABILITY: MODES 1, 2, and 3.
| |
| ACTION:
| |
| : a. With only one group of pressurizer heaters OPERABLE, restore at least two groups to OPERABLE status within 72 hours** or be in at least HOT STANDBY within the next 6 hours and in HOT SHUTDOWN within the following 6 hours.
| |
| : b. With the pressurizer otherwise inoperable, be in at least HOT STANDBY with the Reactor Trip System breakers open within 6 hours and in HOT SHUTDOWN within the following 6 hours.
| |
| SURVEILLANCE REQUIREMENTS 4.4.3.1 The pressurizer water volume shall be determined to be within its limit in accordance with the Surveillance Frequency Control Program.
| |
| 4.4.3.2 The capacity of each of the above required groups of pressurizer heaters shall be verified to be at least 125 kw in accordance with the Surveillance Frequency Control Program.
| |
| ** 14 days if the inoperability is associated with an inoperable diesel generator. l TURKEY POINT - UNITS 3 & 4 3/4 4-9 AMENDMENT NOS. 263 AND 258
| |
| | |
| TABLE 4.4-4 TURKEY POINT - UNITS 3 & 4 REACTOR COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS TYPE OF MEASUREMENT SAMPLE AND ANALYSIS MODES IN WHICH SAMPLE AND ANALYSIS FREQUENCY AND ANALYSIS REQUIRED
| |
| : 1. NOT USED
| |
| : 2. Tritium Activity SFCP. 1, 2, 3, 4 Determination
| |
| : 3. Isotopic Analysis for a) SFCP. 1, 2, 3, 4 DOSE EQUIVALENT I-131 b) One sample between 2 and 6 hours following a THERMAL POWER change exceeding 15% of the RATED THERMAL POWER within a 1 hour period.
| |
| 3/4 4-22
| |
| : 4. Radiochemical Isotopic SFCP 1, 2, 3, 4 Determination Including Gaseous Activity
| |
| : 5. Isotopic Analysis for DOSE SFCP 1, 2, 3, 4 EQUIVALENT XE-133
| |
| : 6. NOT USED AMENDMENT NOS. 263 AND 258
| |
| | |
| REACTOR COOLANT SYSTEM 3/4.4.9 PRESSURE TEMPERATURE LIMITS REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION 3.4.9.1 The Reactor Coolant System (except the pressurizer) temperature and pressure shall be limited in accordance with the limit lines shown on Figures 3.4-2 and 3.4-3 during heatup, cooldown, criticality, and inservice leak and hydrostatic testing with:
| |
| : a. A maximum heatup of 100F in any 1-hour period,
| |
| : b. A maximum cooldown of 100F in any 1-hour period, and
| |
| : c. A maximum temperature change of less than or equal to 5F in any 1-hour period during inservice hydrostatic and leak testing operations above the heatup and cooldown limit curves.
| |
| APPLICABILITY: At all times.
| |
| ACTION:
| |
| With any of the above limits exceeded, restore the temperature and/or pressure to within the limit within 30 minutes; perform an engineering evaluation to determine the effects of the out-of-limit condition on the structural integrity of the Reactor Coolant System; determine that the Reactor Coolant System remains acceptable for continued operation or be in at least HOT STANDBY within the next 6 hours and reduce the RCS Tavg and pressure to less than 200F and 500 psig, respectively, within the following 30 hours.
| |
| SURVEILLANCE REQUIREMENTS 4.4.9.1.1 The Reactor Coolant System temperature and pressure shall be determined to be within the limits in accordance with the Surveillance Frequency Control Program during system heatup, cooldown, and inservice leak and hydrostatic testing operations.
| |
| 4.4.9.1.2 The reactor vessel material irradiation surveillance specimens shall be removed and examined, to determine changes in material properties, as required by 10 CFR Part 50, Appendix H. The results of these examinations shall be used to update Figures 3.4-2 and 3.4-3.
| |
| TURKEY POINT - UNITS 3 & 4 3/4 4-23 AMENDMENT NOS. 263 AND 258
| |
| | |
| I REACTOR COOLANT SYSTEM PRESSURIZER LIMITING CONDITION FOR OPERATION 3.4.9.2 The pressurizer temperature shall be limited to:
| |
| : a. A maximum heatup of 100F in any 1-hour period,
| |
| : b. A maximum cooldown of 200F in any 1-hour period, and
| |
| : c. A maximum spray water temperature differential of 320F.
| |
| APPLICABILITY: At all times.
| |
| ACTION:
| |
| With the pressurizer temperature limits in excess of any of the above limits, restore the temperature to within the limits within 30 minutes; perform an engineering evaluation to determine the effects of the out-of-limit condition on the structural integrity of the pressurizer; determine that the pressurizer remains acceptable for continued operation or be in at least HOT STANDBY within the next 6 hours and reduce the pressurizer pressure to less than 500 psig within the following 30 hours.
| |
| SURVEILLANCE REQUIREMENTS 4.4.9.2 The pressurizer temperatures shall be determined to be within the limits in accordance with the Surveillance Frequency Control Program during system heatup or cooldown. The spray water temperature differential shall be determined to be within the limit in accordance with the Surveillance Frequency Control Program during auxiliary spray operation.
| |
| TURKEY POINT - UNITS 3 & 4 3/4 4-26 AMENDMENT NOS. 263 AND 258
| |
| | |
| REACTOR COOLANT SYSTEM OVERPRESSURE MITIGATING SYSTEMS SURVEILLANCE REQUIREMENTS 4.4.9.3.1 Each PORV shall be demonstrated OPERABLE by:
| |
| : a. Performance of an ANALOG CHANNEL OPERATIONAL TEST* on the PORV actuation channel, but excluding valve operation, within 31 days prior to entering a condition in which the PORV is required OPERABLE and in accordance with the Surveillance Frequency Control Program thereafter when the PORV is required OPERABLE.
| |
| : b. Performance of a CHANNEL CALIBRATION on the PORV actuation channel in accordance with the Surveillance Frequency Control Program; and
| |
| : c. Verifying the PORV block valve is open in accordance with the Surveillance Frequency Control Program when the PORV is being used for overpressure protection.
| |
| : d. While the PORVs are required to be OPERABLE, the backup nitrogen supply shall be verified OPERABLE in accordance with the Surveillance Frequency Control Program.*
| |
| 4.4.9.3.2 The 2.20 square inch vent shall be verified to be open in accordance with the Surveillance Frequency Control Program** when the vent(s) is being used for overpressure protection.
| |
| 4.4.9.3.3 Verify the high pressure injection flow path to the RCS is isolated in accordance with the Surveillance Frequency Control Program by closed valves with power removed or by locked closed manual valves.
| |
| * Not required to be met until 12 hours after decreasing RCS cold leg temperature to 275F.
| |
| ** Except when the vent pathway is provided with a valve which is locked, sealed, or otherwise secured in the open position, then verify these valves open in accordance with the Surveillance Frequency Control Program.
| |
| 3/4.4.10 DELETED TURKEY POINT - UNITS 3 & 4 3/4 4-28 AMENDMENT NOS. 263 AND 258
| |
| | |
| 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS LIMITING CONDITION FOR OPERATION 3.5.1 Each Reactor Coolant System (RCS) accumulator shall be OPERABLE.
| |
| APPLICABILITY: MODES 1, 2, and 3*.
| |
| ACTION:
| |
| : a. With one accumulator inoperable, except as a result of boron concentration not being within limits, restore the inoperable accumulator to OPERABLE status within 1 hour or be in at least HOT STANDBY within the next 6 hours and reduce pressurizer pressure to less than 1000 psig within the following 6 hours.
| |
| : b. With one accumulator inoperable due to the boron concentration not being within the limits, restore boron concentration back to the required limits within 72 hours, or be in at least HOT STANDBY within 6 hours and reduce pressurizer pressure to less than 1000 psig within the following 6 hours.
| |
| SURVEILLANCE REQUIREMENTS 4.5.1.1 Each accumulator shall be demonstrated OPERABLE:
| |
| : a. In accordance with the Surveillance Frequency Control Program by:
| |
| : 1) Verifying the borated water volume in each accumulator is between 6520 and 6820 gallons, and
| |
| : 2) Verifying that the nitrogen cover pressure in each accumulator is between 600 and 675 psig, and
| |
| : 3) Verifying that each accumulator isolation valve is open by control room indication (power may be restored to the valve operator to perform this surveillance if redundant indicator is inoperable).
| |
| *Pressurizer pressure above 1000 psig.
| |
| TURKEY POINT - UNITS 3 & 4 3/4 5-1 AMENDMENT NOS. 263 AND 258
| |
| | |
| EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS
| |
| : g. By verifying the correct position of each electrical and/or mechanical position stop for the following ECCS throttle valves:
| |
| : 1) Within 4 hours following completion of each valve stroking operation or maintenance on the valve when the ECCS components are required to be OPERABLE, and
| |
| : 2) In accordance with the Surveillance Frequency Control Program.
| |
| RHR System Valve Number HCV-*-758 MOV-*-872 TURKEY POINT - UNITS 3 & 4 3/4 5-8 AMENDMENT NOS. 263 AND 258
| |
| | |
| EMERGENCY CORE COOLING SYSTEMS 3/4.5.4 REFUELING WATER STORAGE TANK LIMITING CONDITION FOR OPERATION 3.5.4 For single Unit operation, one refueling water storage tank (RWST) shall be OPERABLE or for dual Unit operation two RWSTs shall be OPERABLE with:
| |
| : a. A minimum indicated borated water volume of 320,000 gallons per RWST,
| |
| : b. A boron concentration between 2400 ppm and 2600 ppm,
| |
| : c. A minimum solution temperature of 39°F, and
| |
| : d. A maximum solution temperature of 100°F.
| |
| APPLICABILITY: MODES 1, 2, 3, and 4.
| |
| ACTION:
| |
| With less than the required number of RWST(s) OPERABLE, restore the tank(s) to OPERABLE status within 1 hour or be in at least HOT STANDBY within 6 hours and in COLD SHUTDOWN within the following 30 hours.
| |
| SURVEILLANCE REQUIREMENTS 4.5.4 The required RWST(s) shall be demonstrated OPERABLE:
| |
| : a. In accordance with the Surveillance Frequency Control Program by:
| |
| : 1) Verifying the indicated borated water volume in the tank, and
| |
| : 2) Verifying the boron concentration of the water.
| |
| : b. By verifying the RWST temperature is within limits whenever the outside air temperature is less than 39°F or greater than 100°F at the following frequencies:
| |
| : 1) Within one hour upon the outside temperature exceeding its limit for consecutive 23 hours, and
| |
| : 2) At least once per 24 hours while the outside temperature exceeds its limit.
| |
| TURKEY POINT - UNITS 3 & 4 3/4 5-10 AMENDMENT NOS. 263 AND 258
| |
| | |
| 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.*
| |
| APPLICABILITY: MODES 1, 2, 3, and 4.
| |
| ACTION:
| |
| Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within 1 hour or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
| |
| SURVEILLANCE REQUIREMENTS 4.6.1.1 CONTAINMENT INTEGRITY shall be demonstrated:
| |
| : a. In accordance with the Surveillance Frequency Control Program by verifying that all penetrations** not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their closed positions;
| |
| : b. By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3.
| |
| * Exception may be taken under Administrative Controls for opening of valves and airlocks necessary to perform surveillance, testing requirements and/or corrective maintenance. In addition, Specification 3.6.4 shall be complied with.
| |
| ** Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed or otherwise secured in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days.
| |
| TURKEY POINT - UNITS 3 & 4 3/4 6-1 AMENDMENT NOS. 263 AND 258
| |
| | |
| CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:
| |
| : a. Following each closing, at the frequency specified in the Containment Leakage Rate Testing Program, by verifying that the seals have not been damaged and have seated properly by vacuum testing the volume between the door seals in accordance with approved plant procedures.
| |
| : b. By conducting overall air lock leakage tests in accordance with the Containment Leakage Rate Testing Program.
| |
| : c. In accordance with the Surveillance Frequency Control Program by verifying that only one door in each air lock can be opened at a time.
| |
| TURKEY POINT - UNITS 3 & 4 3/4 6-4 AMENDMENT NOS. 263 AND 258
| |
| | |
| CONTAINMENT SYSTEMS INTERNAL PRESSURE LIMITING CONDITION FOR OPERATION 3.6.1.4 Primary containment internal pressure shall be maintained between -2 and +1 psig.
| |
| APPLICABILITY: MODES 1, 2, 3, and 4.
| |
| ACTION:
| |
| With the containment internal pressure outside of the limits above, restore the internal pressure to within the limits within 1 hour or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
| |
| SURVEILLANCE REQUIREMENTS 4.6.1.4 The primary containment internal pressure shall be determined to be within the limits in accordance with the Surveillance Frequency Control Program.
| |
| TURKEY POINT - UNITS 3 & 4 3/4 6-5 AMENDMENT NOS. 263 AND 258
| |
| | |
| CONTAINMENT SYSTEMS AIR TEMPERATURE LIMITING CONDITION FOR OPERATION 3.6.1.5 Primary containment average air temperature shall not exceed 125F and shall not exceed 120°F by more than 336 equivalent hours* during a calendar year.
| |
| APPLICABILITY: MODES 1, 2, 3, and 4.
| |
| ACTION:
| |
| With the containment average air temperature greater than 125F or greater than 120F for more than 336 equivalent hours* during a calendar year, reduce the average air temperature to within the applicable limit within 8 hours, or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
| |
| SURVEILLANCE REQUIREMENTS 4.6.1.5 The primary containment average air temperature shall be the arithmetical average of the temperatures at the following locations and shall be determined in accordance with the Surveillance Frequency Control Program:
| |
| Approximate Location
| |
| : a. 0 Azimuth 58 feet elevation
| |
| : b. 120 Azimuth 58 feet elevation
| |
| : c. 240 Azimuth 58 feet elevation
| |
| * Equivalent hours are determined from actual hours using the time-temperature relationships that support the environmental qualification requirements of 10 CFR 50.49.
| |
| TURKEY POINT - UNITS 3 & 4 3/4 6-6 AMENDMENT NOS. 263 AND 258
| |
| | |
| CONTAINMENT SYSTEMS CONTAINMENT VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.1.7 Each containment purge supply and exhaust isolation valve shall be OPERABLE and:
| |
| : a. The containment purge supply and exhaust isolation valves shall be sealed closed to the maximum extent practicable but may be open for purge system operation for pressure control, for environmental conditions control, for ALARA and respirable air quality considerations for personnel entry and for surveillance tests that require the valve to be open.
| |
| : b. The purge supply and exhaust isolation valves shall not be opened wider than 33 or 30 degrees, respectively (90 degrees is fully open).
| |
| APPLICABILITY: MODES 1, 2, 3, AND 4.
| |
| ACTION:
| |
| : a. With a containment purge supply and/or exhaust isolation valve(s) open for reasons other than given in 3.6.1.7.a above, close the open valve(s) or isolate the penetration(s) within 4 hours, otherwise be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
| |
| : b. With a containment purge supply and/or exhaust isolation valve(s) having a measured leakage rate exceeding the limits of Specification 4.6.1.7.2, restore the inoperable valve(s) to OPERABLE status or isolate the penetrations such that the measured leakage rate does not exceed the limits of Specification 4.6.1.7.2 within 24 hours, otherwise be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
| |
| SURVEILLANCE REQUIREMENTS 4.6.1.7.1 Each containment purge supply and exhaust isolation valve shall be verified to be sealed closed or open in accordance with Specification 3.6.1.7.a in accordance with the Surveillance Frequency Control Program.
| |
| 4.6.1.7.2 In accordance with the Surveillance Frequency Control Program, each containment purge supply and exhaust isolation valve shall be demonstrated OPERABLE by verifying that the measured leakage rate is less than or equal to 0.05 La when pressurized to Pa.
| |
| 4.6.1.7.3 In accordance with the Surveillance Frequency Control Program, the mechanical stop on each containment purge supply and exhaust isolation valve shall be verified to be in place and that the valves will open no more than 33 or 30 degrees, respectively.
| |
| TURKEY POINT - UNITS 3 & 4 3/4 6-11 AMENDMENT NOS. 263 AND 258
| |
| | |
| CONTAINMENT SYSTEMS 3/4.6.2.3 RECIRCULATION pH CONTROL SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.3 The Recirculation pH Control System shall be OPERABLE.
| |
| APPLICABILITY: MODES 1, 2, 3, and 4.
| |
| ACTION:
| |
| With the Recirculation pH Control System inoperable, restore the buffering agent to OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the next 72 hours.
| |
| SURVEILLANCE REQUIREMENTS 4.6.2.3 The Recirculation pH Control System shall be demonstrated OPERABLE:
| |
| : a. In accordance with the Surveillance Frequency Control Program by:
| |
| : 1. Verifying that the buffering agent baskets are in place and intact;
| |
| : 2. Collectively contain > 7500 pounds (154 cubic feet) of sodium tetraborate decahydrate, or equivalent.
| |
| 3/4.6.3 DELETED TURKEY POINT - UNITS 3 & 4 3/4 6-15 AMENDMENT NOS. 263 AND 258
| |
| | |
| PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.7.1.3 The condensate storage tank (CST) system shall be demonstrated OPERABLE by verifying the indicated water volume is within its limit when the tank is the supply source for the auxiliary feedwater pumps in accordance with the Surveillance Frequency Control Program.
| |
| TURKEY POINT - UNITS 3 & 4 3/4 7-7 AMENDMENT NOS. 263 AND 258
| |
| | |
| PLANT SYSTEMS SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.7.1.4 The specific activity of the Secondary Coolant System shall be less than or equal to 0.10 microCurie/gram DOSE EQUIVALENT I-131.
| |
| APPLICABILITY: MODES 1, 2, 3, and 4.
| |
| ACTION:
| |
| With the specific activity of the Secondary Coolant System greater than 0.10 microCurie/gram DOSE EQUIVALENT I-131, be in at least HOT STANDBY within 6 hours and in COLD SHUTDOWN within the following 30 hours.
| |
| SURVEILLANCE REQUIREMENTS 4.7.1.4 The specific activity of the Secondary Coolant System shall be determined to be within the limit by performing the sampling and analysis described in Table 4.7-1.
| |
| TURKEY POINT - UNITS 3 & 4 3/4 7-8 AMENDMENT NOS. 263 AND 258
| |
| | |
| TABLE 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS TYPE OF MEASUREMENT SAMPLE AND ANALYSIS AND ANALYSIS FREQUENCY
| |
| : 1. Gross Radioactivity SFCP Determination
| |
| : 2. Isotopic Analysis for DOSE a) Once per 31 days, when-EQUIVALENT I-131 Concentration ever the gross radio-activity determination indicates concentrations greater than 10% of the allowable limit for radioiodines.
| |
| b) Once per 6 months, when-ever the gross radio-activity determination indicates concentrations less than or equal to 10%
| |
| of the allowable limit for radioiodines.
| |
| TURKEY POINT - UNITS 3 & 4 3/4 7-9 AMENDMENT NOS. 263 AND 258
| |
| | |
| SURVEILLANCE REQUIREMENTS (Continued)
| |
| : b. 1) In accordance with the Surveillance Frequency Control Program verify that each valve (manual, power-operated, or automatic) servicing safety-related equipment that is not locked, sealed, or otherwise secured in position is in its correct position.
| |
| : 2) In accordance with the Surveillance Frequency Control Program verify by a performance test the heat exchanger surveillance curves.*
| |
| : c. In accordance with the Surveillance Frequency Control Program during shutdown, by verifying that:
| |
| : 1) Each automatic valve servicing safety-related equipment actuates to its correct position on a SI test signal, and
| |
| : 2) Each Component Cooling Water System pump starts automatically on a SI test signal.
| |
| : 3) Interlocks required for CCW operability are OPERABLE.
| |
| *Technical specification 4.7.2.b.2 is not applicable for entry into MODE 4 or MODE 3, provided that:
| |
| : 1) Surveillance 4.7.2.b.2 is performed no later than 72 hours after reaching a Reactor Coolant System Tavg of 547F, and
| |
| : 2) MODE 2 shall not be entered prior to satisfactory performance of this surveillance.
| |
| TURKEY POINT - UNITS 3 & 4 3/4 7-15 AMENDMENT NOS. 263 AND 258
| |
| | |
| PLANT SYSTEMS 3/4.7.4 ULTIMATE HEAT SINK LIMITING CONDITION FOR OPERATION 3.7.4 The ultimate heat sink shall be OPERABLE with an average supply water temperature less than or equal to 104F.
| |
| APPLICABILITY: MODES 1, 2, 3, and 4.
| |
| ACTION:
| |
| With the requirements of the above specification not satisfied, be in at least HOT STANDBY within 12 hours and in COLD SHUTDOWN within the following 30 hours. This ACTION shall be applicable to both units simultaneously.
| |
| SURVEILLANCE REQUIREMENTS 4.7.4 The ultimate heat sink shall be determined OPERABLE:
| |
| : a. In accordance with the Surveillance Frequency Control Program by verifying the average supply water temperature* is less than or equal to 104F.
| |
| : b. At least once per hour by verifying the average supply water temperature* is less than or equal to 104F, when water temperature exceeds 100F.
| |
| *Portable monitors may be used to measure the temperature.
| |
| TURKEY POINT - UNITS 3 & 4 3/4 7-17 AMENDMENT NOS. 263 AND 258
| |
| | |
| ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS 4.8.1.1.1 Each of the above required startup transformers and their associated circuits shall be:
| |
| : a. Determined OPERABLE in accordance with the Surveillance Frequency Control Program by verifying correct breaker alignments, indicated power availability, and
| |
| : b. Demonstrated OPERABLE in accordance with the Surveillance Frequency Control Program while shutting down, by transferring manually unit power supply from the auxiliary transformer to the startup transformer.
| |
| TURKEY POINT - UNITS 3 & 4 3/4 8-5 AMENDMENT NOS. 263 AND 258
| |
| | |
| ELECTRICAL POWER SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) 4.8.1.1.2 Each diesel generator shall be demonstrated OPERABLE*:
| |
| : a. In accordance with the Surveillance Frequency Control Program by:
| |
| : 1) Verifying the fuel volume in the day and skid-mounted fuel tanks (Unit 4-day tank only),
| |
| : 2) Verifying the fuel volume in the fuel storage tank,
| |
| : 3) Verifying the lubricating oil inventory in storage,
| |
| : 4) Verifying the diesel starts and accelerates to reach a generator voltage and frequency of 3950-4350 volts and 60 + 0.6 Hz. In accordance with the Surveillance Frequency Control Program, these conditions shall be reached within 15 seconds after the start signal from normal conditions. For all other starts, warmup procedures, such as idling and gradual acceleration as recommended by the manufacturer may be used. The diesel generator shall be started for this test by using one of the following signals:
| |
| a) Manual, or b) Simulated loss-of-offsite power by itself, or c) Simulated loss-of-offsite power in conjunction with an ESF Actuation test signal, or d) An ESF Actuation test signal by itself.
| |
| : 5) Verifying the generator is synchronized, loaded** to 2300 - 2500 kW (Unit 3), 2650-2850 kW (Unit 4)***, operates at this loaded condition for at least 60 minutes and for Unit 3 until automatic transfer of fuel from the day tank to the skid mounted tank is demonstrated, and the cooling system is demonstrated OPERABLE.
| |
| : 6) Verifying the diesel generator is aligned to provide standby power to the associated emergency buses.
| |
| * All diesel generator starts for the purpose of these surveillances may be proceeded by a prelube period as recommended by the manufacturer.
| |
| ** May include gradual loading as recommended by the manufacturer so that the mechanical stress and wear on the diesel engine is minimized.
| |
| ***Momentary transients outside these load bands do not invalidate this test.
| |
| TURKEY POINT - UNITS 3 & 4 3/4 8-6 AMENDMENT NOS. 263 AND 258
| |
| | |
| ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
| |
| : h. In accordance with the Surveillance Frequency Control Program or after any modifications which could affect diesel generator interdependence by starting all required diesel generators simultaneously and verifying that all required diesel generators provide 60 +/- 0.6 Hz frequency and 3950-4350 volts in less than or equal to 15 seconds: and
| |
| : i. In accordance with the Surveillance Frequency Control Program, by draining each fuel oil storage tank, removing the accumulated sediment and cleaning the tank.*
| |
| : j. At least once per 10 years, for Unit 4 only, by performing a pressure test of those portions of the diesel fuel oil system designed to Section III, subsection ND of the ASME Code in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda.
| |
| 4.8.1.1.3 Reports - (Not Used)
| |
| * A temporary Class III fuel storage system containing a minimum volume of 38,000 gallons of fuel oil may be used for up to 10 days during the performance of Surveillance Requirement 4.8.1.1.2i for the Unit 3 storage tank while Unit 3 is in Modes 5, 6, or defueled. If the diesel fuel oil storage tank is not returned to service within 10 days, Technical Specification 3.8.1.1 Action b and 3.8.1.2 Action apply to Unit 4 and Unit 3 respectively.
| |
| TURKEY POINT - UNITS 3 & 4 3/4 8-10 AMENDMENT NOS. 263 AND 258
| |
| | |
| ONSITE POWER DISTRIBUTION SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.3.2 As a minimum, the following electrical busses shall be energized in the specified manner:
| |
| : a. One train of A.C. emergency busses associated with the unit (3.8.3.1a. or b.) consisting of one 4160-volt and three 480-volt A.C. emergency busses load centers* and three (four for Unit 4 Train A) vital sections of motor control center busses,
| |
| : b. Two 120-volt A.C. vital busses for the unit energized from their associated inverters** connected to their respective D.C. busses, and
| |
| : c. Three 125-volt D.C. busses energized from their associated battery banks.
| |
| APPLICABILITY MODES 5*** and 6***.
| |
| ACTION:
| |
| With any of the above required electrical busses not energized in the required manner, immediately suspend all operations involving CORE ALTERATIONS, positive reactivity changes, or movement of irradiated fuel, initiate corrective action to energize the required electrical busses in the specified manner as soon as possible, and within 8 hours, depressurize and vent the RCS through at least a 2.2 square inch vent.
| |
| SURVEI LLANCE REQUIREMENTS 4.8.3.2 The specified busses shall be determined energized in the required manner by verifying correct breaker alignment and indicated voltage on the busses in accordance with the Surveillance Frequency Control Program.
| |
| * With the opposite unit in MODE 1, 2, 3, or 4, the 480-volt load centers can only be cross-tied upon issuance of an engineering evaluation to prevent exceeding required electrical components maximum design ratings and to ensure availability of the minimum required equipment.
| |
| ** A backup inverter may be used to replace the normal inverter provided the normal inverter on the same DC bus for the opposite unit is not replaced at the same time.
| |
| *** CAUTION - If the opposite unit is in MODES 1, 2, 3, or 4, see the corresponding Limiting Condition for Operation 3.8.3.1.
| |
| TURKEY POINT - UNITS 3 & 4 3/4 8-23 AMENDMENT NOS. 263 AND 258
| |
| | |
| 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION LIMITING CONDITION FOR OPERATION 3.9.1 The boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained uniform and sufficient to ensure that the more restrictive of the following reactivity conditions is met; either:
| |
| : a. A Keff of 0.95 or less, or
| |
| : b. A boron concentration of greater than or equal to 2300 ppm.
| |
| APPLICABILITY: MODE 6.*
| |
| ACTION:
| |
| With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes and initiate and continue boration at greater than or equal to 16 gpm of a solution containing greater than or equal to 3.0 wt% (5245 ppm) boron or its equivalent until Keff is reduced to less than or equal to 0.95 or the boron concentration is restored to greater than or equal to 2300 ppm, whichever is the more restrictive.
| |
| SURVEILLANCE REQUIREMENTS 4.9.1.1 The more restrictive of the above two reactivity conditions shall be determined prior to:
| |
| : a. Removing or unbolting the reactor vessel head, and
| |
| : b. Withdrawal of any full-length control rod in excess of 3 feet from its fully inserted position within the reactor vessel.
| |
| 4.9.1.2 The boron concentration of the Reactor Coolant System and the refueling canal shall be determined by chemical analysis in accordance with the Surveillance Frequency Control Program.
| |
| 4.9.1.3 Valves isolating unborated water sources** shall be verified closed and secured in position by mechanical stops or by removal of air or electrical power in accordance with the Surveillance Frequency Control Program.
| |
| * The reactor shall be maintained in MODE 6 whenever fuel is in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.
| |
| ** The primary water supply to the boric acid blender may be opened under administrative controls for makeup.
| |
| TURKEY POINT - UNITS 3 & 4 3/4 9-1 AMENDMENT NOS. 263 AND 258
| |
| | |
| REFUELING OPERATIONS 3/4.9.2 INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.9.2 As a minimum, one primary Source Range Neutron Flux Monitor with continuous visual indication in the control room and audible indication in the containment and control room, and one of the remaining three Source Range Neutron Flux Monitors (one primary or one of the two backup monitors) with continuous visual indication in the control room shall be OPERABLE.
| |
| APPLICABILITY: MODE 6.
| |
| ACTION:
| |
| : a. With one of the above required monitors inoperable or not operating, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes.
| |
| : b. With both of the above required monitors inoperable or not operating, determine the boron concentration of the Reactor Coolant System at least once per 12 hours.
| |
| SURVEILLANCE REQUIREMENTS 4.9.2 Each required Source Range Neutron Flux Monitor shall be demonstrated OPERABLE by performance of:
| |
| : a. A CHANNEL CHECK in accordance with the Surveillance Frequency Control Program,
| |
| : b. An ANALOG CHANNEL OPERATIONAL TEST within 8 hours prior to the initial start of CORE ALTERATIONS, and
| |
| : c. An ANALOG CHANNEL OPERATIONAL TEST in accordance with the Surveillance Frequency Control Program.
| |
| TURKEY POINT - UNITS 3 & 4 3/4 9-2 AMENDMENT NOS. 263 AND 258
| |
| | |
| REFUELING OPERATIONS 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS LIMITING CONDITION FOR OPERATION 3.9.4 The containment building penetrations shall be in the following status:
| |
| : a. The equipment door closed and held in place by a minimum of four bolts.
| |
| : b. A minimum of one door in each airlock is closed, or, both doors of the containment personnel airlock may be open if:
| |
| : 1) at least one personnel airlock door is capable of being closed.
| |
| : 2) The plant is in MODE 6 with at least 23 feet of water above the reactor vessel flange, and
| |
| : 3) a designated individual is available outside the personnel airlock to close the door.
| |
| : c. Each penetration providing direct access from the containment atmosphere to the outside atmosphere shall be either:*
| |
| : 1) Closed by an isolation valve, blind flange, or manual valve, or
| |
| : 2) Be capable of being closed by an OPERABLE automatic containment ventilation isolation valve.
| |
| APPLICABILITY: During movement of recently irradiated fuel within the containment.
| |
| ACTION:
| |
| With the requirements of the above specification not satisfied, immediately suspend all operations involving movement of recently irradiated fuel in the containment building.
| |
| SURVEILLANCE REQUIREMENTS 4.9.4 Each of the above required containment building penetrations shall be determined to be either in its closed/isolated condition or capable of being closed by an OPERABLE automatic containment ventilation isolation valve within 100 hours prior to the start of and in accordance with the Surveillance Frequency Control Program during movement of recently irradiated fuel in the containment building by:
| |
| : a. Verifying the penetrations are in their closed/isolated condition, or
| |
| : b. Testing the containment ventilation isolation valves per the applicable portions of Specification 4.6.4.2.
| |
| *Exception may be taken under Administrative Controls for opening of certain valves and airlocks necessary to perform surveillance or testing requirements.
| |
| TURKEY POINT - UNITS 3 & 4 3/4 9-4 AMENDMENT NOS. 263 AND 258
| |
| | |
| REFUELING OPERATIONS 3/4.9.10 REFUELING CAVITY WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.10 Refueling cavity water level shall be maintained > 23 feet above the top of the reactor vessel flange.
| |
| APPLICABILITY: During movement of irradiated fuel assemblies within containment.
| |
| ACTION:
| |
| With the refueling cavity water level not within limit, suspend movement of irradiated fuel assemblies within containment immediately.
| |
| SURVEILLANCE REQUIREMENTS 4.9.10 Verify refueling cavity water level is > 23 feet above the top of the reactor vessel flange within 2 hours prior to the start of and in accordance with the Surveillance Frequency Control Program thereafter during movement of irradiated fuel assemblies within containment.
| |
| TURKEY POINT - UNITS 3 & 4 3/4 9-10 AMENDMENT NOS. 263 AND 258
| |
| | |
| REFUELING OPERATIONS 3/4.9.14 SPENT FUEL STORAGE LIMITING CONDITION FOR OPERATION 3.9.14 The following conditions shall apply to spent fuel storage:
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| : a. The minimum boron concentration in the Spent Fuel Pit shall be 2300 ppm.
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| : b. The combination of initial enrichment, burnup, and cooling time of each fuel assembly stored in the Spent Fuel Pit shall be in accordance with Specification 5.5.1.
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| APPLICABILITY: At all times when fuel is stored in the Spent Fuel Pit.
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| ACTION:
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| : a. With boron concentration in the Spent Fuel Pit less than 2300 ppm, suspend movement of spent fuel in the Spent Fuel Pit and initiate action to restore boron concentration to 2300 ppm or greater.
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| : b. With condition b not satisfied, suspend movement of additional fuel assemblies into the Spent Fuel Pit and restore the spent fuel storage configuration to within the specified conditions.
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| : c. The provisions of Specification 3.0.3 are not applicable.
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| SURVEI LLANCE REQUIREMENTS 4.9.14.1 The boron concentration of the Spent Fuel Pit shall be verified to be 2300 ppm or greater in accordance with the Surveillance Frequency Control Program.
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| 4.9.14.2 A representative sample of inservice Metamic inserts shall be visually inspected in accordance with the Metamic Surveillance Program described in UFSAR Section 16.2. The surveillance program ensures that the performance requirements of Metamic are met over the surveillance interval.
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| TURKEY POINT - UNITS 3 & 4 3/4 9-13 AMENDMENT NOS. 263 AND 258
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| 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN LIMITING CONDITION FOR OPERATION 3.10.1 The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 may be suspended for measurement of control rod worth and SHUTDOWN MARGIN provided reactivity equivalent to at least the highest estimated control rod worth is available for trip insertion from OPERABLE control rod(s).
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| APPLICABILITY: MODE 2.
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| ACTION:
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| : a. With any full-length control rod not fully inserted and with less than the above reactivity equivalent available for trip insertion, immediately initiate and continue boration at greater than or equal to 16 gpm of a solution containing greater than or equal to 3.0 wt% (5245 ppm) boron or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.
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| : b. With all full-length control rods fully inserted and the reactor subcritical by less than the above reactivity equivalent, immediately initiate and continue boration at greater than or equal to 16 gpm of a solution containing greater than or equal to 3.0 wt% (5245 ppm). boron or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.
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| SURVEILLANCE REQUIREMENTS 4.10.1.1 The position of each full-length control rod either partially or fully withdrawn shall be determined in accordance with the Surveillance Frequency Control Program.
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| 4.10.1.2 Each full-length control rod not fully inserted shall be demonstrated capable of full insertion when tripped from at least the 50% withdrawn position within 7 days prior to reducing the SHUTDOWN MARGIN to less than the limits of Specification 3.1.1.1.
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| TURKEY POINT - UNITS 3 & 4 3/4 10-1 AMENDMENT NOS. 263 AND 258
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| SPECIAL TEST EXCEPTIONS 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION 3.10.2 The group height, insertion, and power distribution limits of Specifications 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.2.1, and 3.2.4 may be suspended during the performance of PHYSICS TESTS provided:
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| : a. The THERMAL POWER is maintained less than or equal to 85% of RATED THERMAL POWER, and
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| : b. The limits of Specifications 3.2.2 and 3.2.3 are maintained and determined at the frequencies specified in Specification 4.10.2.2 below.
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| APPLICABILITY: MODE 1.
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| ACTION:
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| With any of the limits of Specification 3.2.2 or 3.2.3 being exceeded while the requirements of Specifications 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.2.1, and 3.2.4 are suspended, either:
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| : a. Reduce THERMAL POWER sufficient to satisfy the ACTION requirements of Specifications 3.2.2 and 3.2.3, or
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| : b. Be in HOT STANDBY within 6 hours.
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| SURVEILLANCE REQUIREMENTS 4.10.2.1 The THERMAL POWER shall be determined to be less than or equal to 85% of RATED THERMAL POWER in accordance with the Surveillance Frequency Control Program during PHYSICS TESTS.
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| 4.10.2.2 The requirements of the below listed specifications shall be performed in accordance with the Surveillance Frequency Control Program during PHYSICS TESTS:
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| : a. Specifications 4.2.2.1 and 4.2.2.5, and
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| : b. Specification 4.2.3.3.
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| TURKEY POINT - UNITS 3 & 4 3/4 10-2 AMENDMENT NOS. 263 AND 258
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| SPECIAL TEST EXCEPTIONS 3/4.10.3 PHYSICS TESTS LIMITING CONDITION FOR OPERATION 3.10.3 The limitations of Specifications 3.1.1.3, 3.1.1.4, 3.1.3.1, 3.1.3.5, and 3.1.3.6 may be suspended during the performance of PHYSICS TESTS provided:
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| : a. The THERMAL POWER does not exceed 5% of RATED THERMAL POWER,
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| : b. The Reactor Trip Setpoints on the OPERABLE Intermediate and Power Range channels are set at less than or equal to 25% of RATED THERMAL POWER, and
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| : c. The Reactor Coolant System lowest operating loop temperature (Tavg) is greater than or equal to 531F.
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| APPLICABILITY: MODE 2.
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| ACTION:
| |
| : a. With the THERMAL POWER greater than 5% of RATED THERMAL POWER, immediately open the Reactor trip breakers.
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| : b. With a Reactor Coolant System operating loop temperature (Tavg) less than 531F, restore Tavg to within its limit within 15 minutes or be in at least HOT STANDBY within the next 15 minutes.
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| SURVEILLANCE REQUIREMENTS 4.10.3.1 The THERMAL POWER shall be determined to be less than or equal to 5% of RATED THERMAL POWER in accordance with the Surveillance Frequency Control Program during PHYSICS TESTS.
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| 4.10.3.2 Each Intermediate and Power Range channel shall be subjected to an ANALOG CHANNEL OPERATIONAL TEST within 12 hours prior to initiating PHYSICS TESTS.
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| 4.10.3.3 The Reactor Coolant System temperature (Tavg) shall be determined to be greater than or equal to 531F in accordance with the Surveillance Frequency Control Program during PHYSICS TESTS.
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| 3/4.10.4 (This specification number is not used)
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| TURKEY POINT - UNITS 3 & 4 3/4 10-3 AMENDMENT NOS. 263 AND 258
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| SPECIAL TEST EXCEPTIONS 3/4.10.5 POSITION INDICATION SYSTEM - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.10.5 The limitations of Specification 3.1.3.3 may be suspended during the performance of individual full-length shutdown and control rod drop time measurements provided;
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| : a. Only one shutdown or control bank is withdrawn from the fully inserted position at a time, and
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| : b. The rod position indicator is OPERABLE during the withdrawal of the rods.
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| APPLICABILITY: MODES 3, 4, and 5 during performance of rod drop time measurements.
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| ACTION:
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| With the Position Indication Systems inoperable or with more than one bank of rods withdrawn, immediately open the Reactor trip breakers.
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| SURVEILLANCE REQUIREMENTS 4.10.5 The above required Position Indication Systems shall be determined to be OPERABLE within 24 hours prior to the start of and in accordance with the Surveillance Frequency Control Program thereafter during rod drop time measurements by verifying the Demand Position Indication System and the Analog Rod Position Indication System agree:
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| : a. Within 12 steps when the rods are stationary, and
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| : b. Within 24 steps during rod motion.
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| TURKEY POINT - UNITS 3 & 4 3/4 10-4 AMENDMENT NOS. 263 AND 258
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| ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued)
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| : 3. If crack indications are found in any portion of a SG tube not excluded above, then the next inspection for each affected and potentially affected SG for the degradation mechanism that caused the crack indication shall not exceed 24 effective full power months or one refueling outage (whichever results in more frequent inspections). If definitive information, such as from examination of a pulled tube, diagnostic non-destructive testing, or engineering evaluation indicates that a crack-like indication is not associated with a crack(s), then the indication need not be treated as a crack.
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| : e. Provisions for monitoring operational primary-secondary leakage.
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| : k. Control Room Envelope Habitability Program A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Emergency Ventilation System (CREVS), CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge. The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent (TEDE) for the duration of the accident.
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| The program shall include the following elements:
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| : a. The definition of the CRE and the CRE boundary.
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| : b. Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance.
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| : c. Requirements for (i) determining the unfiltered air inleakage past the CRE boundary into the CRE in accordance with the testing methods and at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and (ii) assessing CRE habitability at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0.
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| : d. Measurement, at designated locations, of the CRE pressure relative to external areas adjacent to the CRE boundary during the pressurization mode of operation of the CREVS, operating at the flow rate required by Surveillance Requirement 4.7.5.d, at a Frequency of 18 months. Additionally, the supply fans (trains A and B) will be tested on a staggered test basis (defined in Technical Specification definition 1.29 every 36 months).
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| The results shall be trended and the CRE boundary assessed every 18 months.
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| : e. The quantitative limits on unfiltered air inleakage into the CRE. These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph c. The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences. Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis.
| |
| : f. The provisions of Specification 4.0.2 are applicable to the Frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively.
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| TURKEY POINT - UNITS 3 & 4 6-13 AMENDMENT NOS. 263 AND 258
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| ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT*
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| 6.9.1.3 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the radiological environmental monitoring program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the Offsite Dose Calculation Manual (ODCM), and in (2) 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.
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| The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.
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| 6.9.1.4 RADIOACTIVE EFFLUENT RELEASE REPORT**
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| The Radioactive Effluent Release Report covering the operation of the unit shall be submitted in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I, Section IV.B.1.
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| 6.9.1.5 DELETED
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| *A single submittal may be made for a multiple unit station.
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| **A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.
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| TURKEY POINT - UNITS 3 & 4 6-16 AMENDMENT NOS. 263 AND 258
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| | |
| ADMINISTRATIVE CONTROLS PEAKING FACTOR LIMIT REPORT 6.9.1.6 The W(Z) function(s) for Base-Load Operation corresponding to a 2% band about the target flux difference and/or a 3% band about the target flux difference, the Load-Follow function Fz(Z) and the augmented surveillance turnon power fraction PT shall be provided to the U.S. Nuclear Regulatory Commission, whenever PT is <1.0. In the event, the option of Baseload Operation (as defined in Section 4.2.2.3) will not be exercised, the submission of the W(Z) function is not required. Should these values (i.e., W(Z), Fz(Z) and PT) change requiring a new submittal or an amended submittal to the Peaking Factor Limit Report, the Peaking Factor Limit Report shall be provided to the NRC Document Control desk with copies to the Regional Administrator and the Resident Inspector within 30 days of their implementation, unless otherwise approved by the Commission.
| |
| The analytical methods used to generate the Peaking Factor limits shall be those previously reviewed and approved by the NRC. If changes to these methods are deemed necessary they will be evaluated in accordance with 10 CFR 50.59 and submitted to the NRC for review and approval prior to their use if the change is determined to involve an unreviewed safety question or if such a change would require amendment of previously submitted documentation.
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| CORE OPERATING LIMITS REPORT 6.9.1.7 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT (COLR) before each reload cycle or any remaining part of a reload cycle for the following:
| |
| : 1. Reactor Core Safety Limits for Specification 2.1.1.
| |
| : 2. Overtemperature T, Note 1 of Table 2.2-1 for Specification 2.2.1, determination of values K1, K2, K3, T', P', 1, 2, 3, 4, 5, 6, and the breakpoint and slope values for the f1 (I).
| |
| : 3. Overpower T, Note 3 of Table 2.2-1 for Specification 2.2.1, determination of values for K4, K5, K6, T, 7 and f2 (I).
| |
| : 4. Shutdown Margin - Tavg >200°F for Specification 3/4.1.1.1.
| |
| : 5. Shutdown Margin - Tavg <200°F for Specification 3/4.1.1.2.
| |
| : 6. Moderator Temperature Coefficient for Specification 3/4.1.1.3.
| |
| : 7. Axial Flux Difference for Specification 3.2.1.
| |
| : 8. Control Rod Insertion Limits for Specification 3.1.3.6.
| |
| : 9. Heat Flux Hot Channel Factor - FQ(Z) for Specification 3/4.2.2.
| |
| : 10. All Rods Out position for Specification 3.1.3.2.
| |
| : 11. Nuclear Enthalpy Rise Hot Channel Factor for Specification 3/4.2.3.
| |
| : 12. DNB Parameters for Specification 3.2.5, determination of values for Reactor Coolant System Tavg and Pressurizer Pressure.
| |
| The analytical methods used to determine the AFD limits shall be those previously reviewed and approved by the NRC in:
| |
| : 1. WCAP-10216-P-A, RELAXATION OF CONSTANT AXIAL OFFSET CONTROL FQ SURVEILLANCE TECHNICAL SPECIFICATION, June 1983.
| |
| : 2. WCAP-8385, POWER DISTRIBUTION CONTROL AND LOAD FOLLOWING PROCEDURES -
| |
| TOPICAL REPORT, September 1974.
| |
| TURKEY POINT - UNITS 3 & 4 6-17 AMENDMENT NOS. 263 AND 258
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| | |
| ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued)
| |
| The analytical methods used to determine FQ (Z), FH and the K(Z) curve shall be those previously reviewed and approved by the NRC in:
| |
| : 1. WCAP-9220-P-A, Rev. 1, Westinghouse ECCS Evaluation Model - 1981 Version, February 1982.
| |
| : 2. WCAP-10054-P-A, (proprietary), Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code, August 1985.
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| TURKEY POINT - UNITS 3 & 4 6-18 AMENDMENT NOS. 263 AND 258
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| | |
| ADMINISTRATIVE CONTROLS STEAM GENERATOR TUBE INSPECTION REPORT 6.9.1.8 A report shall be submitted within 180 days after the initial entry into MODE 4 following completion of an inspection performed in accordance with Specification 6.8.4.j, Steam Generator (SG) Program. The report shall include:
| |
| : a. The scope of inspections performed on each SG,
| |
| : b. Degradation mechanisms found,
| |
| : c. Nondestructive examination techniques utilized for each degradation mechanism,
| |
| : d. Location, orientation (if linear), and measured sizes (if available) of service induced indications,
| |
| : e. Number of tubes plugged during the inspection outage for each degradation mechanism,
| |
| : f. The number and percentage of tubes plugged to date, and the effective plugging percentage in each steam generator,
| |
| : g. The results of condition monitoring, including the results of tube pulls and in-situ testing, and
| |
| : h. The primary to secondary leakage rate observed in each SG (if it is not practical to assign the leakage to an individual SG, the entire primary to secondary leakage should be conservatively assumed to be from one SG) during the cycle preceding the inspection which is the subject of the report,
| |
| : i. The calculated accident induced leakage rate from the portion of the tubes below 18.11 inches from the top of the tubesheet for the most limiting accident in the most limiting SG. In addition, if the calculated accident induced leakage rate from the most limiting accident is less than 1.82 times the maximum operational primary to secondary leakage rate, the report should describe how it was determined, and
| |
| : j. The results of monitoring for tube axial displacement (slippage). If slippage is discovered, the implications of the discovery and corrective action shall be provided.
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| SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator of the Regional Office of the NRC within the time period specified for each report as stated in the Specifications within Sections 3.0, 4.0, or 5.0.
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| 6.10 DELETED TURKEY POINT - UNITS 3 & 4 6-20 AMENDMENT NOS. 263 AND 258
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| | |
| ADMINISTRATIVE CONTROLS 6.11 DELETED 6.12 HIGH RADIATION AREA 6.12.1 Pursuant to paragraph 20.1601(c) of 10 CFR Part 20, in lieu of the control device or alarm signal required by paragraph 20.1601(a), each high radiation area, as defined in 10 CFR Part 20, in which the intensity of radiation is greater than 100 mrem/hr but equal to or less than 1000 mrem/hr at 30 cm (12 in.) from the radiation source or from any surface which the radiation penetrates shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP). Individuals qualified in radiation protection procedures (e.g., Health Physics Technician) or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates equal to or less than 1000 mrem/hr, provided they are otherwise following plant radiation protection procedures for entry into such high radiation areas.
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| Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
| |
| : a. A radiation monitoring device which continuously indicates the radiation dose rate in the area; or
| |
| : b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel have been made knowledgeable of them; or
| |
| : c. An individual qualified in radiation protection procedures with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the Health Physics Shift Supervisor in the RWP.
| |
| 6.12.2 In addition to the requirements of Specification 6.12.1, areas accessible to personnel with radiation levels greater than 1000 mrem/hr at 30 cm (12 in.) and less than 500 rads/hr at 1 meter from the radiation source or from any surface which the radiation penetrates shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the shift supervisor on duty and/or health physics supervision. Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work areas and the maximum allowable stay time for individuals in that area. In lieu of the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area.
| |
| For individual high radiation areas accessible to personnel with radiation levels of greater than 1000 mrem/hr and less than 500 rads/hr that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and where no enclosure can be reasonably constructed around the individual area, that individual area shall be barricaded, conspicuously posted, and a flashing light shall be activated as a warning device.
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| 6.13 DELETED TURKEY POINT - UNITS 3 & 4 6-21 AMENDMENT NOS. 263 AND 258}}
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