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TLCO Applicability TRM 3.0.100 T3.0 TRM LIMITING CONDITION FOR OPERATION (TLCO) APPLICABILITY TLCO 3.0.100.1 TLCOs shall be met during the MODES or other specified conditions in the Applicability, except as provided in TLCO 3.0.100.2. | TLCO Applicability TRM 3.0.100 T3.0 TRM LIMITING CONDITION FOR OPERATION (TLCO) APPLICABILITY TLCO 3.0.100.1 TLCOs shall be met during the MODES or other specified conditions in the Applicability, except as provided in TLCO 3.0.100.2. | ||
TLCO 3.0.100.2 Upon discovery of a failure to meet a TLCO, the Required Actions within the TRM of the associated Conditions shall be met, except as provided in TLCO 3.0.100.5. | TLCO 3.0.100.2 Upon discovery of a failure to meet a TLCO, the Required Actions within the TRM of the associated Conditions shall be met, except as provided in TLCO 3.0.100.5. | ||
Failure to meet a TLCO may require initiation of an operability determination to determine the impact of the failure on equipment contained within the Technical Specifications. | Failure to meet a TLCO may require initiation of an operability determination to determine the impact of the failure on equipment contained within the Technical Specifications. | ||
If the TLCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required, unless otherwise stated. | If the TLCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required, unless otherwise stated. | ||
TLCO 3.0.100.3 When a TLCO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, action shall be initiated immediately to communicate the situation to the Shift Manager and document the condition in accordance with the PVNGS corrective action program. An initial decision on whether the unit can continue to operate with the condition shall be completed within 7 hours. Further actions shall be as required by the corrective action disposition and as deemed necessary by plant management. | TLCO 3.0.100.3 When a TLCO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, action shall be initiated immediately to communicate the situation to the Shift Manager and document the condition in accordance with the PVNGS corrective action program. An initial decision on whether the unit can continue to operate with the condition shall be completed within 7 hours. Further actions shall be as required by the corrective action disposition and as deemed necessary by plant management. | ||
Exceptions to this Specification are stated in the individual Specifications. | Exceptions to this Specification are stated in the individual Specifications. | ||
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: c. When an allowance is stated in the individual value, parameter, or other Specification. | : c. When an allowance is stated in the individual value, parameter, or other Specification. | ||
This Specification shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit. | This Specification shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit. | ||
TLCO 3.0.100.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to TLCO 3.0.100.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY. | TLCO 3.0.100.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to TLCO 3.0.100.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY. | ||
Palo Verde - Units 1, 2, 3 T3.0.100-2 Rev 40 2/21/07 | Palo Verde - Units 1, 2, 3 T3.0.100-2 Rev 40 2/21/07 | ||
TSR Applicability TRM 3.0.100 TRM SURVEILLANCE REQUIREMENT (TSR) APPLICABILITY TSR 3.0.100.1 TSRs shall be met during the MODES or other specified conditions in the Applicability for individual TLCOs, unless otherwise stated in the TSR. Failure to meet a TSR, whether such failure is experienced during the performance of the TSR or between performances of the TSR, may require initiation of an operability determination to determine the impact of the failure on equipment contained within the Technical Specifications. Failure to perform a TSR within the specified Frequency shall be failure to meet the TLCO except as provided in TSR 3.0.100.3. TSRs do not have to be performed on inoperable equipment or variables outside specified limits. | TSR Applicability TRM 3.0.100 TRM SURVEILLANCE REQUIREMENT (TSR) APPLICABILITY TSR 3.0.100.1 TSRs shall be met during the MODES or other specified conditions in the Applicability for individual TLCOs, unless otherwise stated in the TSR. Failure to meet a TSR, whether such failure is experienced during the performance of the TSR or between performances of the TSR, may require initiation of an operability determination to determine the impact of the failure on equipment contained within the Technical Specifications. Failure to perform a TSR within the specified Frequency shall be failure to meet the TLCO except as provided in TSR 3.0.100.3. TSRs do not have to be performed on inoperable equipment or variables outside specified limits. | ||
TSR 3.0.100.2 The specified Frequency for each TSR is met if the TSR is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met. | TSR 3.0.100.2 The specified Frequency for each TSR is met if the TSR is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met. | ||
For Frequencies specified as "once," the above interval extension does not apply. | For Frequencies specified as "once," the above interval extension does not apply. | ||
If a Completion Time requires periodic performance on a "once per ..." basis, the above Frequency extension applies to each performance after the initial performance. | If a Completion Time requires periodic performance on a "once per ..." basis, the above Frequency extension applies to each performance after the initial performance. | ||
Exceptions to this Specification are stated in the individual Specifications. | Exceptions to this Specification are stated in the individual Specifications. | ||
TSR 3.0.100.3 If it is discovered that a TSR was not performed within its specified Frequency, then compliance with the requirement to declare the TLCO not met may be delayed, from the time of discovery, up to 24 hours or up to the limit of the specified Frequency, whichever is greater. This delay period is permitted to allow performance of the TSR. A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours and the risk impact shall be managed. | TSR 3.0.100.3 If it is discovered that a TSR was not performed within its specified Frequency, then compliance with the requirement to declare the TLCO not met may be delayed, from the time of discovery, up to 24 hours or up to the limit of the specified Frequency, whichever is greater. This delay period is permitted to allow performance of the TSR. A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours and the risk impact shall be managed. | ||
(continued) | (continued) | ||
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TSR Applicability TRM 3.0.100 TRM SURVEILLANCE REQUIREMENT (TSR) APPLICABILITY (continued) | TSR Applicability TRM 3.0.100 TRM SURVEILLANCE REQUIREMENT (TSR) APPLICABILITY (continued) | ||
TSR 3.0.100.3 If the TSR is not performed within the delay period, the (continued) TLCO must immediately be declared not met, and the applicable Condition(s) must be entered When the TSR is performed within the delay period and the Surveillance is not met, the TLCO must immediately be declared not met, and the applicable Condition(s) must be entered. | TSR 3.0.100.3 If the TSR is not performed within the delay period, the (continued) TLCO must immediately be declared not met, and the applicable Condition(s) must be entered When the TSR is performed within the delay period and the Surveillance is not met, the TLCO must immediately be declared not met, and the applicable Condition(s) must be entered. | ||
TSR 3.0.100.4 Entry into a MODE or other specified condition in the Applicability of an TLCO shall only be made when TSRs have been met within their specified Frequency, except as provided by TSR 3.0.100.3. When a TLCO is not met due to Surveillances not having been met, entry into a MODE or other Specified Condition in the Applicability shall only be made in accordance with TLCO 3.0.100.4. This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit. | TSR 3.0.100.4 Entry into a MODE or other specified condition in the Applicability of an TLCO shall only be made when TSRs have been met within their specified Frequency, except as provided by TSR 3.0.100.3. When a TLCO is not met due to Surveillances not having been met, entry into a MODE or other Specified Condition in the Applicability shall only be made in accordance with TLCO 3.0.100.4. This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit. | ||
Palo Verde - Units 1, 2, 3 T3.0.100-4 Rev 47 2/26/09 | Palo Verde - Units 1, 2, 3 T3.0.100-4 Rev 47 2/26/09 | ||
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TSR 3.1.101.2 -----------------NOTE----------------- | TSR 3.1.101.2 -----------------NOTE----------------- | ||
The provisions of TLCO 3.0.100.4 are not applicable for entry into MODE 3 or MODE 4 to perform the surveillance testing of TSR 3.1.101.2 provided the testing is performed within 24 hours after achieving normal operating pressure in the reactor coolant system. | The provisions of TLCO 3.0.100.4 are not applicable for entry into MODE 3 or MODE 4 to perform the surveillance testing of TSR 3.1.101.2 provided the testing is performed within 24 hours after achieving normal operating pressure in the reactor coolant system. | ||
Verify that the flow paths required by 18 months Specification 3.1.101 deliver at least 26 gpm for 1 charging pump and 68 gpm for two charging pumps to the Reactor Coolant System when the Reactor Coolant System is at normal operating pressure. | Verify that the flow paths required by 18 months Specification 3.1.101 deliver at least 26 gpm for 1 charging pump and 68 gpm for two charging pumps to the Reactor Coolant System when the Reactor Coolant System is at normal operating pressure. | ||
PALO VERDE UNITS 1, 2, 3 T3.1.101-3 Rev 0 8/13/98 | PALO VERDE UNITS 1, 2, 3 T3.1.101-3 Rev 0 8/13/98 | ||
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SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.1.104.1 --------------------NOTE------------------- | SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.1.104.1 --------------------NOTE------------------- | ||
Only required to be performed when the refueling water tank is the borated water source and the outside air temperature is outside the 60°F to 120°F range. | Only required to be performed when the refueling water tank is the borated water source and the outside air temperature is outside the 60°F to 120°F range. | ||
Verify that the refueling water tank 24 hours solution temperature is 60°F and 120°F. | Verify that the refueling water tank 24 hours solution temperature is 60°F and 120°F. | ||
(continued) | (continued) | ||
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TSR 3.1.104.2 --------------------NOTE------------------- | TSR 3.1.104.2 --------------------NOTE------------------- | ||
Only required to be performed when the spent fuel pool is the borated water source and irradiated fuel is present in the pool. | Only required to be performed when the spent fuel pool is the borated water source and irradiated fuel is present in the pool. | ||
Verify that the spent fuel pool solution 24 hours temperature is 60°F and 180°F. | Verify that the spent fuel pool solution 24 hours temperature is 60°F and 180°F. | ||
TSR 3.1.104.3 Verify that the boron concentration of the 7 days borated water source is 4000 ppm and 4400 ppm. | TSR 3.1.104.3 Verify that the boron concentration of the 7 days borated water source is 4000 ppm and 4400 ppm. | ||
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Borated Sources - Operating TRM 3.1.105 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.1.105.1 --------------------NOTE------------------- | Borated Sources - Operating TRM 3.1.105 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.1.105.1 --------------------NOTE------------------- | ||
Only required to be performed when irradiated fuel is present in the pool. | Only required to be performed when irradiated fuel is present in the pool. | ||
Verify spent fuel pool solution temperature 24 hours is 60°F and 180°F. | Verify spent fuel pool solution temperature 24 hours is 60°F and 180°F. | ||
TSR 3.1.105.2 Verify spent fuel pool borated water volume 7 days is greater than or equal to the minimum required volume in Figure 3.1.105-1. | TSR 3.1.105.2 Verify spent fuel pool borated water volume 7 days is greater than or equal to the minimum required volume in Figure 3.1.105-1. | ||
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Control Element Assembly - Alignment TRM 3.1.202 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME to operate with the condition shall be completed within 7 hours. Further actions shall be as required by the corrective action disposition and as deemed necessary by plant management. | Control Element Assembly - Alignment TRM 3.1.202 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME to operate with the condition shall be completed within 7 hours. Further actions shall be as required by the corrective action disposition and as deemed necessary by plant management. | ||
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.1.202.1 --------------------NOTE------------------- | SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.1.202.1 --------------------NOTE------------------- | ||
TSR 3.1.202.1 has a different applicability than ITS SR 3.1.5.4 | TSR 3.1.202.1 has a different applicability than ITS SR 3.1.5.4 Perform a CHANNEL FUNCTIONAL TEST of each 18 months reed switch position transmitter channel. | ||
Perform a CHANNEL FUNCTIONAL TEST of each 18 months reed switch position transmitter channel. | |||
Palo Verde - Units 1, 2, 3 T3.1.202-2 Rev 46 1/8/09 | Palo Verde - Units 1, 2, 3 T3.1.202-2 Rev 46 1/8/09 | ||
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APPLICABILITY: MODES 1 and 2 | APPLICABILITY: MODES 1 and 2 | ||
-------------------------NOTE---------------------------- | -------------------------NOTE---------------------------- | ||
This TLCO is not applicable while performing SR 3.1.5.3 | This TLCO is not applicable while performing SR 3.1.5.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One shutdown CEA not A.1 Restore shutdown CEA to 2 hours within limit. within limit. | ||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One shutdown CEA not A.1 Restore shutdown CEA to 2 hours within limit. within limit. | |||
B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time not met. | B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time not met. | ||
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.1.204.1 Verify each shutdown CEA is fully 12 hours withdrawn to 147.75 inches by Pulse Counter Indication and 145.25 inches by Reed Switch Position Transmitter Indication (RSPT). | SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.1.204.1 Verify each shutdown CEA is fully 12 hours withdrawn to 147.75 inches by Pulse Counter Indication and 145.25 inches by Reed Switch Position Transmitter Indication (RSPT). | ||
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APPLICABILITY: MODES 1 and 2 | APPLICABILITY: MODES 1 and 2 | ||
--------------------------NOTE----------------------------- | --------------------------NOTE----------------------------- | ||
This TLCO is not applicable while performing SR 3.1.5.3 | This TLCO is not applicable while performing SR 3.1.5.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One Regulating Group A.1 Restore Regulating Group 2 hours 1 or 2 CEA not within 1 or 2 CEA to within limit. limit. | ||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One Regulating Group A.1 Restore Regulating Group 2 hours 1 or 2 CEA not within 1 or 2 CEA to within limit. limit. | |||
B. Required Action and B.1 Enter TLCO 3.0.100.3 Immediately associated completion time not met. | B. Required Action and B.1 Enter TLCO 3.0.100.3 Immediately associated completion time not met. | ||
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.1.205.1 Verify each Regulating Group 1 & 2 CEA 12 hours is fully withdrawn as specified in the COLR. | SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.1.205.1 Verify each Regulating Group 1 & 2 CEA 12 hours is fully withdrawn as specified in the COLR. | ||
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-------------------------------------NOTE------------------------------------- | -------------------------------------NOTE------------------------------------- | ||
Refer to PVNGS Improved Technical Specifications LCO 3.2.3 for additional requirements. | Refer to PVNGS Improved Technical Specifications LCO 3.2.3 for additional requirements. | ||
CONDITION REQUIRED ACTION COMPLETION TIME | CONDITION REQUIRED ACTION COMPLETION TIME | ||
-------------NOTE------------- A.1 Verify that the 30 minutes Condition A is due to a Core Operating misalignment of either a part Limit Supervisory strength or full strength CEA. system (COLSS) | -------------NOTE------------- A.1 Verify that the 30 minutes Condition A is due to a Core Operating misalignment of either a part Limit Supervisory strength or full strength CEA. system (COLSS) | ||
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------------------------------------NOTE-------------------------------------- | ------------------------------------NOTE-------------------------------------- | ||
The provisions of Specification 3.0.100.3 are not applicable. | The provisions of Specification 3.0.100.3 are not applicable. | ||
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more radiation A.1 Adjust the setpoint(s) 4 hours monitoring channel to within the limit. | CONDITION REQUIRED ACTION COMPLETION TIME A. One or more radiation A.1 Adjust the setpoint(s) 4 hours monitoring channel to within the limit. | ||
alarm/trip setpoint(s) exceed the value shown in Table 3.3.101-1 B. Required Action and B.1 Declare the channel Immediately associated Completion inoperable. | alarm/trip setpoint(s) exceed the value shown in Table 3.3.101-1 B. Required Action and B.1 Declare the channel Immediately associated Completion inoperable. | ||
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: 1. The Incore Detection System contains 50 incore locations with 5 detectors in each fixed detector string. | : 1. The Incore Detection System contains 50 incore locations with 5 detectors in each fixed detector string. | ||
: 2. An OPERABLE incore location consists of a fixed detector string with a minimum of three OPERABLE rhodium detectors. | : 2. An OPERABLE incore location consists of a fixed detector string with a minimum of three OPERABLE rhodium detectors. | ||
APPLICABILITY: When the Incore Detection System is used for monitoring: | APPLICABILITY: When the Incore Detection System is used for monitoring: | ||
: a. AZIMUTHAL POWER TILT, | : a. AZIMUTHAL POWER TILT, | ||
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------------------------------------NOTE-------------------------------------- | ------------------------------------NOTE-------------------------------------- | ||
The provisions of Specification 3.0.100.3 are not applicable. | The provisions of Specification 3.0.100.3 are not applicable. | ||
CONDITION REQUIRED ACTION COMPLETION TIME A. Incore Detection System A.1 Do not use the Incore Immediately inoperable. Detection System for monitoring or calibration functions. | CONDITION REQUIRED ACTION COMPLETION TIME A. Incore Detection System A.1 Do not use the Incore Immediately inoperable. Detection System for monitoring or calibration functions. | ||
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.3.102.1 Perform a CHANNEL CHECK. Within 7 days prior to use TSR 3.3.102.2 ------------------NOTE------------------- | SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.3.102.1 Perform a CHANNEL CHECK. Within 7 days prior to use TSR 3.3.102.2 ------------------NOTE------------------- | ||
Neutron Detectors may be excluded from the CHANNEL CALIBRATION but all electronic components shall be included. Fixed incore neutron detectors shall be calibrated prior to installation in the reactor core. | Neutron Detectors may be excluded from the CHANNEL CALIBRATION but all electronic components shall be included. Fixed incore neutron detectors shall be calibrated prior to installation in the reactor core. | ||
Perform a CHANNEL CALIBRATION. 18 months PALO VERDE UNITS 1, 2, 3 T3.3.102-2 Rev 40 2/21/07 | Perform a CHANNEL CALIBRATION. 18 months PALO VERDE UNITS 1, 2, 3 T3.3.102-2 Rev 40 2/21/07 | ||
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ACTIONS | ACTIONS | ||
--------------------------------------NOTE------------------------------------ | --------------------------------------NOTE------------------------------------ | ||
The provisions of Specification 3.0.100.3 are not applicable | The provisions of Specification 3.0.100.3 are not applicable CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore the required 30 days Seismic Monitoring instrumentation to Instruments of Table OPERABLE status. | ||
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore the required 30 days Seismic Monitoring instrumentation to Instruments of Table OPERABLE status. | |||
3.3.103-1 inoperable. | 3.3.103-1 inoperable. | ||
B. Required Action and B.1 Initiate a corrective In accordance associated completion action to evaluate the with the PVNGS time of Condition A not action taken, cause of corrective met. the inoperability, and action program. | B. Required Action and B.1 Initiate a corrective In accordance associated completion action to evaluate the with the PVNGS time of Condition A not action taken, cause of corrective met. the inoperability, and action program. | ||
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SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.3.103.1 -------------------NOTE------------------ | SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.3.103.1 -------------------NOTE------------------ | ||
Applicable to Digital Recorders of Table 3.3.103-1 only. | Applicable to Digital Recorders of Table 3.3.103-1 only. | ||
Perform a CHANNEL CHECK. 31 days (continued) | Perform a CHANNEL CHECK. 31 days (continued) | ||
PALO VERDE UNITS 1, 2, 3 T3.3.103-2 Rev 54 1/26/11 | PALO VERDE UNITS 1, 2, 3 T3.3.103-2 Rev 54 1/26/11 | ||
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Seismic Monitoring TRM 3.3.103 Table 3.3.103-1 (Page 1 of 1) | Seismic Monitoring TRM 3.3.103 Table 3.3.103-1 (Page 1 of 1) | ||
Seismic Monitoring Instrumentation | Seismic Monitoring Instrumentation INSTRUMENTS AND SENSOR LOCATIONS MINIMUM INSTRUMENTS OPERABLE | ||
INSTRUMENTS AND SENSOR LOCATIONS MINIMUM INSTRUMENTS OPERABLE | |||
: 1. Force Balance Accelerometer Unit | : 1. Force Balance Accelerometer Unit | ||
: a. Tendon Gallery Floor, 55 level 1 Trigger Threshold Setpoint: 0.010 g | : a. Tendon Gallery Floor, 55 level 1 Trigger Threshold Setpoint: 0.010 g | ||
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------------------------------------NOTE-------------------------------------- | ------------------------------------NOTE-------------------------------------- | ||
The provisions of Specification 3.0.100.3 are not applicable. | The provisions of Specification 3.0.100.3 are not applicable. | ||
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore the channels 7 days meteorological to OPERABLE status. | CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore the channels 7 days meteorological to OPERABLE status. | ||
monitoring channels inoperable. | monitoring channels inoperable. | ||
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------------------NOTE------------------ | ------------------NOTE------------------ | ||
Windspeed Sensors are excluded from CHANNEL CALIBRATION. | Windspeed Sensors are excluded from CHANNEL CALIBRATION. | ||
TSR 3.3.104.2 Perform a CHANNEL CALIBRATION 6 months PALO VERDE UNITS 1, 2, 3 T3.3.104-1 Rev 46 1/8/09 | TSR 3.3.104.2 Perform a CHANNEL CALIBRATION 6 months PALO VERDE UNITS 1, 2, 3 T3.3.104-1 Rev 46 1/8/09 | ||
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-------------------------------------NOTE------------------------------------- | -------------------------------------NOTE------------------------------------- | ||
: 1. Wind speeds less than 0.6 MPH will be reported as 0. | : 1. Wind speeds less than 0.6 MPH will be reported as 0. | ||
PALO VERDE UNITS 1, 2, 3 T3.3.104-2 Rev 0 8/13/98 | PALO VERDE UNITS 1, 2, 3 T3.3.104-2 Rev 0 8/13/98 | ||
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-------------------------------------NOTE----------------------------------- | -------------------------------------NOTE----------------------------------- | ||
Separate Condition entry is allowed for each Function. | Separate Condition entry is allowed for each Function. | ||
CONDITION REQUIRED ACTION COMPLETION TIME A. With the number of A.1 Restore the inoperable 30 days OPERABLE channels one channel(s) to OPERABLE less than the Required status. | CONDITION REQUIRED ACTION COMPLETION TIME A. With the number of A.1 Restore the inoperable 30 days OPERABLE channels one channel(s) to OPERABLE less than the Required status. | ||
number of Channels in Table 3.3.105-1. | number of Channels in Table 3.3.105-1. | ||
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------------------------------------NOTE-------------------------------------- | ------------------------------------NOTE-------------------------------------- | ||
The provisions of Specification 3.0.100.3 are not applicable. | The provisions of Specification 3.0.100.3 are not applicable. | ||
CONDITION REQUIRED ACTION COMPLETION TIME A. With one or more loose- A.1 Restore the inoperable 30 days part detection system channel(s) to OPERABLE channels inoperable. status. | CONDITION REQUIRED ACTION COMPLETION TIME A. With one or more loose- A.1 Restore the inoperable 30 days part detection system channel(s) to OPERABLE channels inoperable. status. | ||
B. Required Action and B.1 Initiate a corrective In accordance associated completion action to evaluate the with the PVNGS time not met. cause of the corrective malfunction and the action program. | B. Required Action and B.1 Initiate a corrective In accordance associated completion action to evaluate the with the PVNGS time not met. cause of the corrective malfunction and the action program. | ||
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------------------------------------NOTE-------------------------------------- | ------------------------------------NOTE-------------------------------------- | ||
The provisions of Specification 3.0.100.3 are not applicable. | The provisions of Specification 3.0.100.3 are not applicable. | ||
CONDITION REQUIRED ACTION COMPLETION TIME A. Explosive gas monitoring A.1 Declare the channel Immediately instrumentation channel inoperable. | CONDITION REQUIRED ACTION COMPLETION TIME A. Explosive gas monitoring A.1 Declare the channel Immediately instrumentation channel inoperable. | ||
alarm/trip setpoint less conservative than required. | alarm/trip setpoint less conservative than required. | ||
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: 1. One volume percent oxygen, balance nitrogen, and | : 1. One volume percent oxygen, balance nitrogen, and | ||
: 2. Four volume percent oxygen, balance nitrogen. | : 2. Four volume percent oxygen, balance nitrogen. | ||
PALO VERDE UNITS 1, 2, 3 T3.3.107-2 Rev 46 1/8/09 | PALO VERDE UNITS 1, 2, 3 T3.3.107-2 Rev 46 1/8/09 | ||
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-----------------------------------NOTE--------------------------------------- | -----------------------------------NOTE--------------------------------------- | ||
Surveillance Requirements for RU-145 are specified in the ODCM. | Surveillance Requirements for RU-145 are specified in the ODCM. | ||
SURVEILLANCE FREQUENCY TSR 3.3.108.1 Perform a CHANNEL CHECK on RU-31. 12 hours TSR 3.3.108.2 Perform a CHANNEL FUNCTIONAL TEST on RU-31 92 days to include that the setpoint is 15 mR/hr and the measurement range is 10E-1 to 10E+4 mR/hr. | SURVEILLANCE FREQUENCY TSR 3.3.108.1 Perform a CHANNEL CHECK on RU-31. 12 hours TSR 3.3.108.2 Perform a CHANNEL FUNCTIONAL TEST on RU-31 92 days to include that the setpoint is 15 mR/hr and the measurement range is 10E-1 to 10E+4 mR/hr. | ||
TSR 3.3.108.3 --------------------NOTE------------------- | TSR 3.3.108.3 --------------------NOTE------------------- | ||
Testing of Actuation Logic shall include verification of the proper operation of each actuation relay. | Testing of Actuation Logic shall include verification of the proper operation of each actuation relay. | ||
Perform a CHANNEL FUNCTIONAL TEST on 18 months required FBEVAS Actuation Logic channel. | Perform a CHANNEL FUNCTIONAL TEST on 18 months required FBEVAS Actuation Logic channel. | ||
TSR 3.3.108.4 Perform a CHANNEL FUNCTIONAL TEST on 18 months required FBEVAS Manual Trip logic. | TSR 3.3.108.4 Perform a CHANNEL FUNCTIONAL TEST on 18 months required FBEVAS Manual Trip logic. | ||
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: c. If any signal is greater than the calorimetric calculation by more than 10%, then adjust the affected signal(s) to agree with the calorimetric calculation within 8% to 10%. | : c. If any signal is greater than the calorimetric calculation by more than 10%, then adjust the affected signal(s) to agree with the calorimetric calculation within 8% to 10%. | ||
: d. During any power ascension from below 80% to above 80% RTP, the calibration requirements of ITS SR 3.3.1.4 must be met (except during PHYSICS TESTS, as allowed by the Note in SR 3.3.1.4). This is accomplished by performing SR 3.3.1.4 between 75% and 80% RTP during power ascension with an acceptance criteria of -0.5% to <2% to bound the requirements for both below and above 80% RTP. | : d. During any power ascension from below 80% to above 80% RTP, the calibration requirements of ITS SR 3.3.1.4 must be met (except during PHYSICS TESTS, as allowed by the Note in SR 3.3.1.4). This is accomplished by performing SR 3.3.1.4 between 75% and 80% RTP during power ascension with an acceptance criteria of -0.5% to <2% to bound the requirements for both below and above 80% RTP. | ||
PALO VERDE UNITS 1, 2, 3 T3.3.200-2 Rev 31 6/15/04 | PALO VERDE UNITS 1, 2, 3 T3.3.200-2 Rev 31 6/15/04 | ||
| Line 520: | Line 484: | ||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ----------NOTE----------- A.1 Restore the parameter 24 hours Condition A is applicable to within its Steady during MODES 1, 2, 3, and State Limit. | ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ----------NOTE----------- A.1 Restore the parameter 24 hours Condition A is applicable to within its Steady during MODES 1, 2, 3, and State Limit. | ||
4 only. | 4 only. | ||
One or more chemistry parameter in excess of its Steady State Limit but within its Transient Limit while in MODES 1, 2, 3, and 4. | One or more chemistry parameter in excess of its Steady State Limit but within its Transient Limit while in MODES 1, 2, 3, and 4. | ||
B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time of Condition A not AND met. | B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time of Condition A not AND met. | ||
| Line 530: | Line 493: | ||
C. ----------NOTE----------- C.1 Restore the parameter 24 hours Condition C is applicable to within its Steady at all times other than State Limit. | C. ----------NOTE----------- C.1 Restore the parameter 24 hours Condition C is applicable to within its Steady at all times other than State Limit. | ||
during MODES 1, 2, 3 and 4. | during MODES 1, 2, 3 and 4. | ||
Concentration of either chloride or fluoride in the Reactor Coolant System in excess of its Steady State Limit D. Required Action and D.1 Reduce the pressurizer Immediately associated Completion pressure to 500 Time of Condition C not psia, if applicable. | Concentration of either chloride or fluoride in the Reactor Coolant System in excess of its Steady State Limit D. Required Action and D.1 Reduce the pressurizer Immediately associated Completion pressure to 500 Time of Condition C not psia, if applicable. | ||
met. | met. | ||
| Line 545: | Line 507: | ||
-------------------------------------NOTE------------------------------------- | -------------------------------------NOTE------------------------------------- | ||
: 1. Limits for Dissolved Oxygen are not applicable with Tcold 250°F. | : 1. Limits for Dissolved Oxygen are not applicable with Tcold 250°F. | ||
PALO VERDE UNITS 1, 2, 3 T3.4.101-4 Rev 0 8/13/98 | PALO VERDE UNITS 1, 2, 3 T3.4.101-4 Rev 0 8/13/98 | ||
| Line 565: | Line 526: | ||
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.4.102.1 --------------------NOTE-------------------- | SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.4.102.1 --------------------NOTE-------------------- | ||
Only required to be performed during pressurizer heatup and cooldown operations. | Only required to be performed during pressurizer heatup and cooldown operations. | ||
Verify that pressurizer heatup and cooldown 30 minutes rates are within the specified limits: | Verify that pressurizer heatup and cooldown 30 minutes rates are within the specified limits: | ||
TSR 3.4.102.2 The spray water temperature differential Each cycle of shall be determined for use. main spray when less than 4 reactor coolant pumps are operating and for each cycle of auxiliary spray operation. | TSR 3.4.102.2 The spray water temperature differential Each cycle of shall be determined for use. main spray when less than 4 reactor coolant pumps are operating and for each cycle of auxiliary spray operation. | ||
| Line 586: | Line 546: | ||
-------------------------------------NOTE------------------------------------- | -------------------------------------NOTE------------------------------------- | ||
Perform TSR 3.4.104.1, TSR 3.4.104.2 and TSR 3.4.104.3 when in MODE 5 or 6. | Perform TSR 3.4.104.1, TSR 3.4.104.2 and TSR 3.4.104.3 when in MODE 5 or 6. | ||
SURVEILLANCE FREQUENCY TSR 3.4.104.1 Verify all manual isolation valves in each 18 months vent path are locked in the open position. | SURVEILLANCE FREQUENCY TSR 3.4.104.1 Verify all manual isolation valves in each 18 months vent path are locked in the open position. | ||
TSR 3.4.104.2 Cycle each vent valve through at least one 18 months complete cycle from the control room. | TSR 3.4.104.2 Cycle each vent valve through at least one 18 months complete cycle from the control room. | ||
| Line 598: | Line 557: | ||
----------------------------------NOTE------------------------------------ | ----------------------------------NOTE------------------------------------ | ||
Changes to the reactor vessel surveillance specimen withdrawal schedule that meet the applicable ASTM standard must be submitted to the NRC with technical justification for approval prior to implementation (the NRC must verify compliance with the ASTM standard) in accordance with 10 CFR 50, Appendix H, paragraph III.B.3. Changes to the withdrawal schedule that do not meet the applicable ASTM standard must be submitted to the NRC for approval as a license amendment with information required by 10 CFR 50.91 and 50.92 (see NRC Administrative Letter 97-04 dated September 30, 1997). | Changes to the reactor vessel surveillance specimen withdrawal schedule that meet the applicable ASTM standard must be submitted to the NRC with technical justification for approval prior to implementation (the NRC must verify compliance with the ASTM standard) in accordance with 10 CFR 50, Appendix H, paragraph III.B.3. Changes to the withdrawal schedule that do not meet the applicable ASTM standard must be submitted to the NRC for approval as a license amendment with information required by 10 CFR 50.91 and 50.92 (see NRC Administrative Letter 97-04 dated September 30, 1997). | ||
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.4.200.1 The reactor vessel material irradiation Refer to PVNGS surveillance specimens shall be removed and UFSAR Section examined to determine changes in material 5.3.1.6.6 properties at the intervals required by 10 CFR Withdrawal 50, Appendix H in accordance with PVNGS UFSAR Schedule section 5.3.1.6.6 Withdrawal Schedule. The results of these examinations shall be used to update the PTLR. | SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.4.200.1 The reactor vessel material irradiation Refer to PVNGS surveillance specimens shall be removed and UFSAR Section examined to determine changes in material 5.3.1.6.6 properties at the intervals required by 10 CFR Withdrawal 50, Appendix H in accordance with PVNGS UFSAR Schedule section 5.3.1.6.6 Withdrawal Schedule. The results of these examinations shall be used to update the PTLR. | ||
PALO VERDE UNITS 1, 2, 3 T3.4.200-1 Rev 52 7/16/10 | PALO VERDE UNITS 1, 2, 3 T3.4.200-1 Rev 52 7/16/10 | ||
| Line 628: | Line 586: | ||
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.4.204.1 -------------------NOTE--------------------- | SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.4.204.1 -------------------NOTE--------------------- | ||
The provisions of this TSR are not applicable for valves UV-651, UV-652, UV-653 and UV-654 due to position indication of valves in the control room. | The provisions of this TSR are not applicable for valves UV-651, UV-652, UV-653 and UV-654 due to position indication of valves in the control room. | ||
Each reactor Coolant System pressure Within 72 hours isolation valve shall be demonstrated following a OPERABLE by verifying leakage to be within system response its limit. to an Engineered Safety Feature actuation signal. | Each reactor Coolant System pressure Within 72 hours isolation valve shall be demonstrated following a OPERABLE by verifying leakage to be within system response its limit. to an Engineered Safety Feature actuation signal. | ||
PALO VERDE UNITS 1, 2, 3 T3.4.204-1 Rev 46 1/8/09 | PALO VERDE UNITS 1, 2, 3 T3.4.204-1 Rev 46 1/8/09 | ||
| Line 638: | Line 595: | ||
Safety Injection Tanks TRM 3.5.200 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.5.200.1 -------------------NOTE------------------ | Safety Injection Tanks TRM 3.5.200 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.5.200.1 -------------------NOTE------------------ | ||
Nitrogen vent valves may be cycled as necessary to maintain the required nitrogen cover pressure in accordance with PVNGS Improved Technical Specifications 3.5.1 and 3.5.2. | Nitrogen vent valves may be cycled as necessary to maintain the required nitrogen cover pressure in accordance with PVNGS Improved Technical Specifications 3.5.1 and 3.5.2. | ||
Verify the required safety injection tank 12 hours nitrogen vent valves are closed when pressurizer pressure is 430 psia. | Verify the required safety injection tank 12 hours nitrogen vent valves are closed when pressurizer pressure is 430 psia. | ||
TSR 3.5.200.2 -------------------NOTE------------------ | TSR 3.5.200.2 -------------------NOTE------------------ | ||
Nitrogen vent valves may be cycled as necessary to maintain the required nitrogen cover pressure in accordance with PVNGS Improved Technical Specifications 3.5.1 and 3.5.2. | Nitrogen vent valves may be cycled as necessary to maintain the required nitrogen cover pressure in accordance with PVNGS Improved Technical Specifications 3.5.1 and 3.5.2. | ||
Verify that power is removed from the 31 days required nitrogen vent valves when pressurizer pressure is 1500 psia. | Verify that power is removed from the 31 days required nitrogen vent valves when pressurizer pressure is 1500 psia. | ||
TSR 3.5.200.3 Verify that the SIT nitrogen vent valves 18 months can be opened when the SITS are isolated. | TSR 3.5.200.3 Verify that the SIT nitrogen vent valves 18 months can be opened when the SITS are isolated. | ||
| Line 686: | Line 641: | ||
TSR 3.5.202.2 Conduct a flow balance test and verify that ------NOTE------ | TSR 3.5.202.2 Conduct a flow balance test and verify that ------NOTE------ | ||
the flow rates meet the requirements listed Perform during in Table 3.5.202-1. shutdown. | the flow rates meet the requirements listed Perform during in Table 3.5.202-1. shutdown. | ||
Following completion of modifications (that alter the subsystem flow characteristics) to the ECCS subsystems. | Following completion of modifications (that alter the subsystem flow characteristics) to the ECCS subsystems. | ||
(continued) | (continued) | ||
| Line 746: | Line 700: | ||
------------------------------------NOTE------------------------------------- | ------------------------------------NOTE------------------------------------- | ||
All three PVNGS Units (Units 1, 2, and 3) shall simultaneously comply with the REQUIRED ACTION(s) when the shared portion of the hydrogen recombiner(s) is the cause of a CONDITION. | All three PVNGS Units (Units 1, 2, and 3) shall simultaneously comply with the REQUIRED ACTION(s) when the shared portion of the hydrogen recombiner(s) is the cause of a CONDITION. | ||
CONDITION REQUIRED ACTION COMPLETION TIME A. One hydrogen A.1 Restore hydrogen 30 days recombiner inoperable. recombiner to OPERABLE status. | CONDITION REQUIRED ACTION COMPLETION TIME A. One hydrogen A.1 Restore hydrogen 30 days recombiner inoperable. recombiner to OPERABLE status. | ||
B. Two hydrogen B.1 Verify by 1 hour recombiners administrative means inoperable. that the hydrogen AND control function is maintained. Every 12 hours thereafter AND B.2 Restore one hydrogen 7 days recombiner to OPERABLE status. | B. Two hydrogen B.1 Verify by 1 hour recombiners administrative means inoperable. that the hydrogen AND control function is maintained. Every 12 hours thereafter AND B.2 Restore one hydrogen 7 days recombiner to OPERABLE status. | ||
| Line 784: | Line 737: | ||
-----------------------------------NOTE--------------------------------------- | -----------------------------------NOTE--------------------------------------- | ||
The provisions of TLCO 3.0.100.3 are not applicable. | The provisions of TLCO 3.0.100.3 are not applicable. | ||
CONDITION REQUIRED ACTION COMPLETION TIME A. With a sealed source A.1 Withdraw the sealed Immediately having removable source from use. | CONDITION REQUIRED ACTION COMPLETION TIME A. With a sealed source A.1 Withdraw the sealed Immediately having removable source from use. | ||
contamination in excess of the above limit. AND A.2.1 Decontaminate and Prior to repair the sealed returning the source. sealed source to use OR A.2.2 Dispose of the sealed In accordance source. with Commission Regulations PALO VERDE UNITS 1, 2, 3 T3.7.102-1 Rev 0 8/13/98 | contamination in excess of the above limit. AND A.2.1 Decontaminate and Prior to repair the sealed returning the source. sealed source to use OR A.2.2 Dispose of the sealed In accordance source. with Commission Regulations PALO VERDE UNITS 1, 2, 3 T3.7.102-1 Rev 0 8/13/98 | ||
| Line 792: | Line 744: | ||
Each category of sealed sources (excluding startup sources and fission detectors previously subjected to core flux) shall be tested for leakage and/or contamination, at the frequencies described below, by the licensee or other persons specifically authorized by the Commission or an Agreement State. | Each category of sealed sources (excluding startup sources and fission detectors previously subjected to core flux) shall be tested for leakage and/or contamination, at the frequencies described below, by the licensee or other persons specifically authorized by the Commission or an Agreement State. | ||
The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample. | The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample. | ||
SURVEILLANCE FREQUENCY TSR 3.7.102.1 SOURCES IN USE - Leakage or contamination test sealed sources containing radioactive material: | SURVEILLANCE FREQUENCY TSR 3.7.102.1 SOURCES IN USE - Leakage or contamination test sealed sources containing radioactive material: | ||
: a. With a half-life greater than 30 days 6 months (excluding Hydrogen 3), and | : a. With a half-life greater than 30 days 6 months (excluding Hydrogen 3), and | ||
| Line 811: | Line 762: | ||
-----------------------------------NOTE---------------------------------- | -----------------------------------NOTE---------------------------------- | ||
Separate Condition entry is allowed for each SG. | Separate Condition entry is allowed for each SG. | ||
CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of TSR A.1 Document the condition in Immediately 3.7.200.1 not met. the corrective action program and initiate an operability determination, as necessary, to determine the impact on equipment in the technical specifications. | CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of TSR A.1 Document the condition in Immediately 3.7.200.1 not met. the corrective action program and initiate an operability determination, as necessary, to determine the impact on equipment in the technical specifications. | ||
B. One ADV line per SG B.1. Restore the ADV line to 7 days inoperable. OPERABLE status. | B. One ADV line per SG B.1. Restore the ADV line to 7 days inoperable. OPERABLE status. | ||
| Line 889: | Line 839: | ||
-------------------------------------NOTE------------------------------------- | -------------------------------------NOTE------------------------------------- | ||
The provisions of TLCO 3.0.100.3 are not applicable. | The provisions of TLCO 3.0.100.3 are not applicable. | ||
CONDITION REQUIRED ACTION COMPLETION TIME A. Cathodic Protection A.1 Restore to OPERABLE 30 days System Inoperable. | CONDITION REQUIRED ACTION COMPLETION TIME A. Cathodic Protection A.1 Restore to OPERABLE 30 days System Inoperable. | ||
B. Required Action and B.1 Initiate a corrective In accordance associated Completion action to evaluate the with the PVNGS Time of Condition A not cause of the corrective met. malfunction and the action program. | B. Required Action and B.1 Initiate a corrective In accordance associated Completion action to evaluate the with the PVNGS Time of Condition A not cause of the corrective met. malfunction and the action program. | ||
| Line 902: | Line 851: | ||
---------------------------NOTE----------------------------- | ---------------------------NOTE----------------------------- | ||
The scope of these protective devices excludes those circuits for which credible fault currents would not exceed the electrical penetration design rating. | The scope of these protective devices excludes those circuits for which credible fault currents would not exceed the electrical penetration design rating. | ||
APPLICABILITY: MODES 1, 2, 3 and 4. | APPLICABILITY: MODES 1, 2, 3 and 4. | ||
PALO VERDE UNITS 1, 2, 3 T3.8.101-1 Rev 46 1/8/09 | PALO VERDE UNITS 1, 2, 3 T3.8.101-1 Rev 46 1/8/09 | ||
Containment Penetration Conductor Overcurrent Protection Devices TRM 3.8.101 ACTIONS | Containment Penetration Conductor Overcurrent Protection Devices TRM 3.8.101 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore the protection 72 hours containment penetration device(s) to OPERABLE conductor overcurrent status. | ||
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore the protection 72 hours containment penetration device(s) to OPERABLE conductor overcurrent status. | |||
protective devices inoperable. OR A.2.1 Deenergize the 72 hours circuit(s) and declare the affected system or component inoperable. | protective devices inoperable. OR A.2.1 Deenergize the 72 hours circuit(s) and declare the affected system or component inoperable. | ||
AND A.2.2 Verify the backup At least once circuit breaker to be per 7 days tripped or the inoperable circuit breaker racked out. | AND A.2.2 Verify the backup At least once circuit breaker to be per 7 days tripped or the inoperable circuit breaker racked out. | ||
| Line 921: | Line 867: | ||
: 2. For each circuit breaker found inoperable during these functional tests, an additional representative sample of at least 10% of all the circuit breakers of the inoperable type shall also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested. | : 2. For each circuit breaker found inoperable during these functional tests, an additional representative sample of at least 10% of all the circuit breakers of the inoperable type shall also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested. | ||
For lower voltage circuit breakers, testing of these circuit breakers shall consist of injecting a current with a value equal to 300% of the setpoint (pickup) of the long-term delay trip element, 150% of the setpoint (pickup) of the short-time delay trip element, and verifying that the circuit breaker operates within the time delay band width for that current specified by the manufacturer. The instantaneous element shall be tested (continued) | For lower voltage circuit breakers, testing of these circuit breakers shall consist of injecting a current with a value equal to 300% of the setpoint (pickup) of the long-term delay trip element, 150% of the setpoint (pickup) of the short-time delay trip element, and verifying that the circuit breaker operates within the time delay band width for that current specified by the manufacturer. The instantaneous element shall be tested (continued) | ||
PALO VERDE UNITS 1, 2, 3 T3.8.101-3 Rev 12 3/30/01 | PALO VERDE UNITS 1, 2, 3 T3.8.101-3 Rev 12 3/30/01 | ||
| Line 928: | Line 873: | ||
(continued) by injecting a current for a frame size of 250 amps or less with tolerances of +40%/-25% and a frame size of 400 amps or greater of +/-25% and verifying that the circuit breaker trips instantaneously with no apparent time delay. | (continued) by injecting a current for a frame size of 250 amps or less with tolerances of +40%/-25% and a frame size of 400 amps or greater of +/-25% and verifying that the circuit breaker trips instantaneously with no apparent time delay. | ||
Molded case circuit breaker testing shall also follow this procedure except that generally no more than two trip elements, time delay and instantaneous, will be involved. Circuit breakers found inoperable during functional testing shall be restored to OPERABLE status prior to resuming operation. | Molded case circuit breaker testing shall also follow this procedure except that generally no more than two trip elements, time delay and instantaneous, will be involved. Circuit breakers found inoperable during functional testing shall be restored to OPERABLE status prior to resuming operation. | ||
PALO VERDE UNITS 1, 2, 3 T3.8.101-4 Rev 0 8/13/98 | PALO VERDE UNITS 1, 2, 3 T3.8.101-4 Rev 0 8/13/98 | ||
| Line 975: | Line 919: | ||
satisfied. | satisfied. | ||
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.9.103.1 -------------------NOTE--------------------- | SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.9.103.1 -------------------NOTE--------------------- | ||
Applicable only during crane operation | Applicable only during crane operation Crane interlocks and physical stops which 7 days prevent crane travel with loads in excess of 2000 pounds over fuel assemblies shall be demonstrated OPERABLE. | ||
Crane interlocks and physical stops which 7 days prevent crane travel with loads in excess of 2000 pounds over fuel assemblies shall be demonstrated OPERABLE. | |||
PALO VERDE UNITS 1, 2, 3 T3.9.103-1 Rev 0 8/13/98 | PALO VERDE UNITS 1, 2, 3 T3.9.103-1 Rev 0 8/13/98 | ||
| Line 1,020: | Line 962: | ||
------------------------------------NOTE-------------------------------------- | ------------------------------------NOTE-------------------------------------- | ||
The provisions of Specifications 3.0.100.3 are not applicable. | The provisions of Specifications 3.0.100.3 are not applicable. | ||
CONDITION REQUIRED ACTION COMPLETION TIME A. The quantity of A.1 Suspend all additions Immediately radioactive material in of radioactive material any outside temporary to the tank. | CONDITION REQUIRED ACTION COMPLETION TIME A. The quantity of A.1 Suspend all additions Immediately radioactive material in of radioactive material any outside temporary to the tank. | ||
tank or the reactor makeup water tank exceeds AND the above limit. | tank or the reactor makeup water tank exceeds AND the above limit. | ||
| Line 1,032: | Line 973: | ||
------------------------------------NOTE-------------------------------------- | ------------------------------------NOTE-------------------------------------- | ||
The provisions of Specifications 3.0.100.3 and 3.0.100.4 are not applicable. | The provisions of Specifications 3.0.100.3 and 3.0.100.4 are not applicable. | ||
CONDITION REQUIRED ACTION COMPLETION TIME A. Concentration of oxygen A.1 Reduce the oxygen 48 hours in the waste gas holdup concentration to within system > 2% by volume but the limit. | CONDITION REQUIRED ACTION COMPLETION TIME A. Concentration of oxygen A.1 Reduce the oxygen 48 hours in the waste gas holdup concentration to within system > 2% by volume but the limit. | ||
4% by volume. | 4% by volume. | ||
| Line 1,050: | Line 990: | ||
------------------------------------NOTE-------------------------------------- | ------------------------------------NOTE-------------------------------------- | ||
The provisions of Specification 3.0.100.3 are not applicable. | The provisions of Specification 3.0.100.3 are not applicable. | ||
CONDITION REQUIRED ACTION COMPLETION TIME A. Quantity of radioactive A.1 Suspend all additions Immediately material in any gas of radioactive material storage tank exceeds to the tank. | CONDITION REQUIRED ACTION COMPLETION TIME A. Quantity of radioactive A.1 Suspend all additions Immediately material in any gas of radioactive material storage tank exceeds to the tank. | ||
limit. | limit. | ||
| Line 1,066: | Line 1,005: | ||
--------------------------NOTES-------------------------- | --------------------------NOTES-------------------------- | ||
The provisions of TLCO 3.0.100.3 are not applicable. | The provisions of TLCO 3.0.100.3 are not applicable. | ||
CONDITION REQUIRED ACTION COMPLETION TIME A. Any, but not more than A.1 Restore the inoperable 14 days one-half of the Function instrument(s) to X fire detection OPERABLE status. | CONDITION REQUIRED ACTION COMPLETION TIME A. Any, but not more than A.1 Restore the inoperable 14 days one-half of the Function instrument(s) to X fire detection OPERABLE status. | ||
instruments in any fire zone shown in Table 3.11.100-1 inoperable. | instruments in any fire zone shown in Table 3.11.100-1 inoperable. | ||
B. Required Action and ------------NOTE----------- | B. Required Action and ------------NOTE----------- | ||
Completion Time of Required Action B.1 is not Condition A not met. applicable if the instrument(s) are located inside containment. | Completion Time of Required Action B.1 is not Condition A not met. applicable if the instrument(s) are located inside containment. | ||
B.1 Establish a fire watch Within 1 hour patrol to inspect the zone(s) and at least with the inoperable once per hour instruments thereafter. | B.1 Establish a fire watch Within 1 hour patrol to inspect the zone(s) and at least with the inoperable once per hour instruments thereafter. | ||
OR (continued) | OR (continued) | ||
| Line 1,080: | Line 1,017: | ||
------------NOTE------------ | ------------NOTE------------ | ||
Required Actions B.2.1, B.2.2 and B.2.3 are applicable for instrument(s) located inside containment. | Required Actions B.2.1, B.2.2 and B.2.3 are applicable for instrument(s) located inside containment. | ||
B.2.1 Establish a fire watch Within 1 hour patrol to inspect the and at least Containment zone(s) with once per 8 the inoperable hours instrument(s). thereafter OR B.2.2 Monitor the containment Within 1 hour air temperature using and at least the locations listed in once per hour the Bases for Technical thereafter. | B.2.1 Establish a fire watch Within 1 hour patrol to inspect the and at least Containment zone(s) with once per 8 the inoperable hours instrument(s). thereafter OR B.2.2 Monitor the containment Within 1 hour air temperature using and at least the locations listed in once per hour the Bases for Technical thereafter. | ||
Specification SR 3.6.5.1. | Specification SR 3.6.5.1. | ||
| Line 1,148: | Line 1,084: | ||
------------------------NOTES------------------------- | ------------------------NOTES------------------------- | ||
The provisions of TLCO 3.0.100.3 are not applicable. | The provisions of TLCO 3.0.100.3 are not applicable. | ||
CONDITION REQUIRED ACTION COMPLETION TIME A. One pump and/or one water A.1 Restore the inoperable 7 days supply inoperable. equipment to OPERABLE status. | CONDITION REQUIRED ACTION COMPLETION TIME A. One pump and/or one water A.1 Restore the inoperable 7 days supply inoperable. equipment to OPERABLE status. | ||
OR (continued) | OR (continued) | ||
| Line 1,194: | Line 1,129: | ||
--------------------------NOTES-------------------------- | --------------------------NOTES-------------------------- | ||
The provisions of TLCO 3.0.100.3 are not applicable. | The provisions of TLCO 3.0.100.3 are not applicable. | ||
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the A.1 Establish a continuous 1 hour required spray and/or fire watch with backup sprinkler systems fire suppression inoperable in areas in equipment. | CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the A.1 Establish a continuous 1 hour required spray and/or fire watch with backup sprinkler systems fire suppression inoperable in areas in equipment. | ||
which redundant systems or components could be damaged. | which redundant systems or components could be damaged. | ||
| Line 1,260: | Line 1,194: | ||
--------------------------NOTES-------------------------- | --------------------------NOTES-------------------------- | ||
The provisions of TLCO 3.0.100.3 are not applicable. | The provisions of TLCO 3.0.100.3 are not applicable. | ||
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the A.1 Establish a continuous 1 hour required CO2 systems fire watch with backup inoperable in areas in fire suppression which redundant systems equipment. | CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the A.1 Establish a continuous 1 hour required CO2 systems fire watch with backup inoperable in areas in fire suppression which redundant systems equipment. | ||
or components could be damaged. | or components could be damaged. | ||
| Line 1,282: | Line 1,215: | ||
--------------------------NOTES-------------------------- | --------------------------NOTES-------------------------- | ||
The provisions of TLCO 3.0.100.3 are not applicable. | The provisions of TLCO 3.0.100.3 are not applicable. | ||
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the fire A.1 Provide a gated wye on 1 hour hose stations shown in the nearest OPERABLE hose Table 3.11.104-1 station. One outlet of inoperable where the fire the wye shall be hose is the primary means connected to the standard of fire suppression. length of hose provided for the OPERABLE hose station. The second outlet of the wye shall be connected to a length of hose sufficient to provide coverage for the area left unprotected by the inoperable hose station. | CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the fire A.1 Provide a gated wye on 1 hour hose stations shown in the nearest OPERABLE hose Table 3.11.104-1 station. One outlet of inoperable where the fire the wye shall be hose is the primary means connected to the standard of fire suppression. length of hose provided for the OPERABLE hose station. The second outlet of the wye shall be connected to a length of hose sufficient to provide coverage for the area left unprotected by the inoperable hose station. | ||
(continued) | (continued) | ||
| Line 1,310: | Line 1,242: | ||
--------------------------NOTES-------------------------- | --------------------------NOTES-------------------------- | ||
The provisions of TLCO 3.0.100.3 a are not applicable. | The provisions of TLCO 3.0.100.3 a are not applicable. | ||
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the yard A.1 Have sufficient 1 hour fire hydrants shown in additional lengths of Table 3.11.105-1 2-1/2 inch diameter hose inoperable. located in an OPERABLE, equipped emergency response vehicle to provide service from an OPERABLE yard fire hydrant adjacent to the unprotected area(s). | CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the yard A.1 Have sufficient 1 hour fire hydrants shown in additional lengths of Table 3.11.105-1 2-1/2 inch diameter hose inoperable. located in an OPERABLE, equipped emergency response vehicle to provide service from an OPERABLE yard fire hydrant adjacent to the unprotected area(s). | ||
B. Equipped emergency B.1 Have another equipped 1 hour response vehicle emergency response inoperable. vehicle OPERABLE. | B. Equipped emergency B.1 Have another equipped 1 hour response vehicle emergency response inoperable. vehicle OPERABLE. | ||
| Line 1,337: | Line 1,268: | ||
--------------------------NOTES-------------------------- | --------------------------NOTES-------------------------- | ||
The provisions of TLCO 3.0.100.3 are not applicable. | The provisions of TLCO 3.0.100.3 are not applicable. | ||
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the A.1 Establish a continuous 1 hour required Halon systems fire watch with backup inoperable in areas in fire suppression which redundant systems equipment. | CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the A.1 Establish a continuous 1 hour required Halon systems fire watch with backup inoperable in areas in fire suppression which redundant systems equipment. | ||
or components could be damaged. | or components could be damaged. | ||
| Line 1,360: | Line 1,290: | ||
--------------------------NOTES-------------------------- | --------------------------NOTES-------------------------- | ||
The provisions of TLCO 3.0.100.3 are not applicable. | The provisions of TLCO 3.0.100.3 are not applicable. | ||
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the A.1 Establish a continuous 1 hour required fire-rated fire watch* on at least assemblies (including one side of the sealing devices) affected assembly. | CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the A.1 Establish a continuous 1 hour required fire-rated fire watch* on at least assemblies (including one side of the sealing devices) affected assembly. | ||
inoperable. | inoperable. | ||
| Line 1,401: | Line 1,330: | ||
PALO VERDE UNITS 1, 2, 3 T5.0.300-1 Rev 0 8/13/98 | PALO VERDE UNITS 1, 2, 3 T5.0.300-1 Rev 0 8/13/98 | ||
Procedures TRM 5.0.400 T5.0 ADMINISTRATIVE CONTROLS T5.0.400 Procedures Refer to PVNGS Improved Technical Specifications Section 5.4 | Procedures TRM 5.0.400 T5.0 ADMINISTRATIVE CONTROLS T5.0.400 Procedures Refer to PVNGS Improved Technical Specifications Section 5.4 (continued) | ||
(continued) | |||
PALO VERDE UNITS 1, 2, 3 T5.0.400-1 Rev 0 8/13/98 | PALO VERDE UNITS 1, 2, 3 T5.0.400-1 Rev 0 8/13/98 | ||
| Line 1,483: | Line 1,410: | ||
: 4. | : 4. | ||
* means control tendon. | * means control tendon. | ||
(continued) | (continued) | ||
PALO VERDE UNITS 1, 2, 3 T5.0.500-9 Rev 0 8/13/98 | PALO VERDE UNITS 1, 2, 3 T5.0.500-9 Rev 0 8/13/98 | ||
| Line 1,598: | Line 1,524: | ||
T5.0.600.2 Startup Reports The requirement to submit startup reports to the NRC has been deleted. However, appropriate testing and retention of startup test records will continue to be performed in accordance with the requirements of 10 CFR 50, Appendix B, and the PVNGS Quality Assurance Program. Records will be maintained in accordance with the requirements of PVNGS UFSAR Section 1.8. | T5.0.600.2 Startup Reports The requirement to submit startup reports to the NRC has been deleted. However, appropriate testing and retention of startup test records will continue to be performed in accordance with the requirements of 10 CFR 50, Appendix B, and the PVNGS Quality Assurance Program. Records will be maintained in accordance with the requirements of PVNGS UFSAR Section 1.8. | ||
(continued) | (continued) | ||
PALO VERDE UNITS 1, 2, 3 T5.0.600-1 Rev 37 8/17/06 | PALO VERDE UNITS 1, 2, 3 T5.0.600-1 Rev 37 8/17/06 | ||
| Line 1,793: | Line 1,718: | ||
: d. Corrosion of metals exposed to Containment Spray System and Emergency Core Cooling Systems solutions. | : d. Corrosion of metals exposed to Containment Spray System and Emergency Core Cooling Systems solutions. | ||
To evaluate the potential for hydrogen accumulation in containment following a LOCA, the hydrogen generation as a function of time following the initiation of the accident is calculated. Conservative assumptions recommended in Reference 3 are used to maximize the amount of hydrogen calculated. | To evaluate the potential for hydrogen accumulation in containment following a LOCA, the hydrogen generation as a function of time following the initiation of the accident is calculated. Conservative assumptions recommended in Reference 3 are used to maximize the amount of hydrogen calculated. | ||
TLCO Two hydrogen recombiners shared among the three units must be OPERABLE. This ensures operation of at least one hydrogen recombiner in the event of a worst case single active failure. | TLCO Two hydrogen recombiners shared among the three units must be OPERABLE. This ensures operation of at least one hydrogen recombiner in the event of a worst case single active failure. | ||
Operation with at least one hydrogen recombiner ensures that the post LOCA hydrogen concentration can be prevented from exceeding the flammability limit. | Operation with at least one hydrogen recombiner ensures that the post LOCA hydrogen concentration can be prevented from exceeding the flammability limit. | ||
| Line 1,819: | Line 1,743: | ||
: 3) operation of the recombiner to include a functional test at 1200°F (+/-50°F) for at least 4 hours. Operating experience has shown that these components usually pass the Surveillance when performed at the 12 month Frequency. | : 3) operation of the recombiner to include a functional test at 1200°F (+/-50°F) for at least 4 hours. Operating experience has shown that these components usually pass the Surveillance when performed at the 12 month Frequency. | ||
Therefore, the Frequency was concluded to be acceptable from a reliability standpoint. | Therefore, the Frequency was concluded to be acceptable from a reliability standpoint. | ||
REFERENCES 1. 10 CFR 50.44. | REFERENCES 1. 10 CFR 50.44. | ||
: 2. 10 CFR 50, Appendix A, GDC 41. | : 2. 10 CFR 50, Appendix A, GDC 41. | ||
| Line 1,833: | Line 1,756: | ||
The acceptance criteria specified in the 2001 Edition, 2003 Addenda, of the ASME OM Code, Subsection ISTD are to be used in the visual inspection to determine the functionality of the snubbers. | The acceptance criteria specified in the 2001 Edition, 2003 Addenda, of the ASME OM Code, Subsection ISTD are to be used in the visual inspection to determine the functionality of the snubbers. | ||
(continued) | (continued) | ||
PALO VERDE UNITS 1, 2, 3 T6.0.100-26 Rev 53 11/10/10 | PALO VERDE UNITS 1, 2, 3 T6.0.100-26 Rev 53 11/10/10 | ||
| Line 1,844: | Line 1,766: | ||
Background See TS Bases B 3.7.4 Applicable See UFSAR Chapter 15. | Background See TS Bases B 3.7.4 Applicable See UFSAR Chapter 15. | ||
Safety Analyses TLCO Two ADVs are required to be OPERABLE on each SG to ensure that a single failure would not prevent the capability to remotely open at least one ADV on the affected SG following a steam generator tube rupture with a loss of offsite power (SGTRLOP, UFSAR 15.6.3.3). At least one ADV on the affected SG would be needed to prevent overfill and (continued) | Safety Analyses TLCO Two ADVs are required to be OPERABLE on each SG to ensure that a single failure would not prevent the capability to remotely open at least one ADV on the affected SG following a steam generator tube rupture with a loss of offsite power (SGTRLOP, UFSAR 15.6.3.3). At least one ADV on the affected SG would be needed to prevent overfill and (continued) | ||
PALO VERDE UNITS 1, 2, 3 T6.0.100-27 Rev 53 11/10/10 | PALO VERDE UNITS 1, 2, 3 T6.0.100-27 Rev 53 11/10/10 | ||
| Line 1,853: | Line 1,774: | ||
A.1 If the requirements of TSR 3.7.200 are not met, the condition must be documented in the corrective action program and an operability determination must be initiated as necessary to determine the impact on equipment in the TSs. This action is required to assure compliance with the TSs. | A.1 If the requirements of TSR 3.7.200 are not met, the condition must be documented in the corrective action program and an operability determination must be initiated as necessary to determine the impact on equipment in the TSs. This action is required to assure compliance with the TSs. | ||
B.1 If one of the two required ADV lines on a SG is inoperable, Required Action B is to restore the ADV line to OPERABLE status within 7 days. The 7 day Completion Time is acceptable because (1) when one ADV on either or both SGs is inoperable, the single failure backup is no longer available, but the primary success path for accident mitigation continues to be available by the remaining OPERABLE ADVs; (2) the heat removal function of the ADVs can also be provided by the steam bypass control valves to the condensers and atmosphere when offsite power (continued) | B.1 If one of the two required ADV lines on a SG is inoperable, Required Action B is to restore the ADV line to OPERABLE status within 7 days. The 7 day Completion Time is acceptable because (1) when one ADV on either or both SGs is inoperable, the single failure backup is no longer available, but the primary success path for accident mitigation continues to be available by the remaining OPERABLE ADVs; (2) the heat removal function of the ADVs can also be provided by the steam bypass control valves to the condensers and atmosphere when offsite power (continued) | ||
PALO VERDE UNITS 1, 2, 3 T6.0.100-28 Rev 53 11/10/10 | PALO VERDE UNITS 1, 2, 3 T6.0.100-28 Rev 53 11/10/10 | ||
| Line 1,861: | Line 1,781: | ||
D.1 See TS Bases B 3.7.4, Action A.1 E.1 See TS Bases B 3.7.4, Action B.1 Surveillance TSR 3.7.200.1 Requirements The nitrogen accumulator tank pressure must be verified to have a pressure of at least 615 psig indicated to ensure that it has sufficient pressurized gas to operate the ADVs for 4 hours at hot standby plus 9.3 hours of operation to reach cold shutdown under natural circulation conditions in the event of failure of the normal control air system, as described in UFSAR 10.3.2.2.4. | D.1 See TS Bases B 3.7.4, Action A.1 E.1 See TS Bases B 3.7.4, Action B.1 Surveillance TSR 3.7.200.1 Requirements The nitrogen accumulator tank pressure must be verified to have a pressure of at least 615 psig indicated to ensure that it has sufficient pressurized gas to operate the ADVs for 4 hours at hot standby plus 9.3 hours of operation to reach cold shutdown under natural circulation conditions in the event of failure of the normal control air system, as described in UFSAR 10.3.2.2.4. | ||
(continued) | (continued) | ||
PALO VERDE UNITS 1, 2, 3 T6.0.100-29 Rev 53 11/10/10 | PALO VERDE UNITS 1, 2, 3 T6.0.100-29 Rev 53 11/10/10 | ||
| Line 1,876: | Line 1,795: | ||
T3.8.101 Containment Penetration Conductor Overcurrent Protective Devices Containment electrical penetrations and penetration conductors are protected by either deenergizing circuits not required during reactor operation or by demonstrating the OPERABILITY of primary and backup overcurrent protection circuit breakers during periodic surveillance. The circuit breakers will be tested in accordance with NEMA Standard Publication No. AB-2-1980. For a frame size of 250 amperes or less, the field tolerances of the high and low setting of the injected current will be within +40%/-25% of the setpoint (pickup) value. For a frame size of 400 amperes or greater, the field tolerances will be +/-25% of the setpoint (pickup) value. The circuit breakers should not be affected when tested within these tolerances. | T3.8.101 Containment Penetration Conductor Overcurrent Protective Devices Containment electrical penetrations and penetration conductors are protected by either deenergizing circuits not required during reactor operation or by demonstrating the OPERABILITY of primary and backup overcurrent protection circuit breakers during periodic surveillance. The circuit breakers will be tested in accordance with NEMA Standard Publication No. AB-2-1980. For a frame size of 250 amperes or less, the field tolerances of the high and low setting of the injected current will be within +40%/-25% of the setpoint (pickup) value. For a frame size of 400 amperes or greater, the field tolerances will be +/-25% of the setpoint (pickup) value. The circuit breakers should not be affected when tested within these tolerances. | ||
The surveillance requirements applicable to lower voltage circuit breakers provide assurance of breaker reliability by testing at least one (continued) | The surveillance requirements applicable to lower voltage circuit breakers provide assurance of breaker reliability by testing at least one (continued) | ||
PALO VERDE UNITS 1, 2, 3 T6.0.100-30 Rev 53 11/10/10 | PALO VERDE UNITS 1, 2, 3 T6.0.100-30 Rev 53 11/10/10 | ||
| Line 1,899: | Line 1,817: | ||
Movement of spent fuel casks containing irradiated fuel assemblies is not within the scope of the Applicability of this technical specification. The movement of dry casks containing irradiated fuel assemblies will be done with a single-failure-proof handling system and with transport equipment that would prevent any credible accident that could result in a release of radioactivity. | Movement of spent fuel casks containing irradiated fuel assemblies is not within the scope of the Applicability of this technical specification. The movement of dry casks containing irradiated fuel assemblies will be done with a single-failure-proof handling system and with transport equipment that would prevent any credible accident that could result in a release of radioactivity. | ||
(continued) | (continued) | ||
PALO VERDE UNITS 1, 2, 3 T6.0.100-33 Rev 53 11/10/10 | PALO VERDE UNITS 1, 2, 3 T6.0.100-33 Rev 53 11/10/10 | ||
| Line 1,918: | Line 1,835: | ||
T3.11.100 FIRE DETECTION INSTRUMENTATION OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires and that fire suppression systems, that are actuated by fire detectors, will discharge extinguishing agent in a timely manner. Prompt detection and suppression of fires will reduce the potential for damage to safety-related equipment and is an integral element in the overall facility fire protection program. | T3.11.100 FIRE DETECTION INSTRUMENTATION OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires and that fire suppression systems, that are actuated by fire detectors, will discharge extinguishing agent in a timely manner. Prompt detection and suppression of fires will reduce the potential for damage to safety-related equipment and is an integral element in the overall facility fire protection program. | ||
(continued) | (continued) | ||
PALO VERDE UNITS 1, 2, 3 T6.0.100-35 Rev 53 11/10/10 | PALO VERDE UNITS 1, 2, 3 T6.0.100-35 Rev 53 11/10/10 | ||
| Line 1,928: | Line 1,844: | ||
T3.11.101, 102, 103, 104, 105, and 106 FIRE SUPPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that adequate fire suppression capability is available to confine and extinguish fires occurring in any portion of the facility where safety-related equipment is located. The fire suppression system consists of the water system, spray and/or sprinklers, CO2, Halon, fire hose stations, and yard fire hydrants and associated emergency response vehicles. The collective capability of the fire suppression systems is adequate to minimize potential damage to safety related equipment and is a major element in the facility fire protection program. | T3.11.101, 102, 103, 104, 105, and 106 FIRE SUPPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that adequate fire suppression capability is available to confine and extinguish fires occurring in any portion of the facility where safety-related equipment is located. The fire suppression system consists of the water system, spray and/or sprinklers, CO2, Halon, fire hose stations, and yard fire hydrants and associated emergency response vehicles. The collective capability of the fire suppression systems is adequate to minimize potential damage to safety related equipment and is a major element in the facility fire protection program. | ||
(continued) | (continued) | ||
PALO VERDE UNITS 1, 2, 3 T6.0.100-36 Rev 53 11/10/10 | PALO VERDE UNITS 1, 2, 3 T6.0.100-36 Rev 53 11/10/10 | ||
| Line 1,963: | Line 1,878: | ||
& PKD-H14 | & PKD-H14 | ||
: 21. ESF Switchgear Room Essential AHU HJB-Z03 PHB-M3205 | : 21. ESF Switchgear Room Essential AHU HJB-Z03 PHB-M3205 | ||
: 22. LPSI Pump SIB-P01 Breaker Control PBB-SO4F | : 22. LPSI Pump SIB-P01 Breaker Control PBB-SO4F (continued) | ||
(continued) | |||
PALO VERDE UNITS 1, 2, 3 T7.0.100-1 Rev 52 7/16/10 | PALO VERDE UNITS 1, 2, 3 T7.0.100-1 Rev 52 7/16/10 | ||
| Line 1,999: | Line 1,912: | ||
: 51. LPSI Pump "B" Recirc SIB-UV-668 PHB-M3611 | : 51. LPSI Pump "B" Recirc SIB-UV-668 PHB-M3611 | ||
: 52. LPSI Pump "B" Suction from RWT SIB-HV-692 PHB-M3805 | : 52. LPSI Pump "B" Suction from RWT SIB-HV-692 PHB-M3805 | ||
: 53. SD Cooling LPSI Pump "B" Suction SIB-UV-652 PHB-M3611 | : 53. SD Cooling LPSI Pump "B" Suction SIB-UV-652 PHB-M3611 (continued) | ||
(continued) | |||
PALO VERDE UNITS 1, 2, 3 T7.0.100-2 Rev 52 7/16/10 | PALO VERDE UNITS 1, 2, 3 T7.0.100-2 Rev 52 7/16/10 | ||
| Line 2,048: | Line 1,959: | ||
: 22. E-PBB-S04H 4.16 KV Feeder Breaker to 480V Load Center PGB-L34 PBB-S04H | : 22. E-PBB-S04H 4.16 KV Feeder Breaker to 480V Load Center PGB-L34 PBB-S04H | ||
: 23. E-PBB-S04J 4.16KV Feeder Breaker to 480V Load Center PGB-L32 PBB-S04J | : 23. E-PBB-S04J 4.16KV Feeder Breaker to 480V Load Center PGB-L32 PBB-S04J | ||
: 24. E-PBB-S04N 4.16KV Feeder Breaker to 480V Load Center PGB-L36 PBB-SO4N | : 24. E-PBB-S04N 4.16KV Feeder Breaker to 480V Load Center PGB-L36 PBB-SO4N (continued) | ||
(continued) | |||
PALO VERDE UNITS 1, 2, 3 T7.0.200-1 Rev 52 7/16/10 | PALO VERDE UNITS 1, 2, 3 T7.0.200-1 Rev 52 7/16/10 | ||
| Line 2,084: | Line 1,993: | ||
: 53. RC Loop to Shutdown Cooling Valve SIB-UV-652 PHB-M3604 | : 53. RC Loop to Shutdown Cooling Valve SIB-UV-652 PHB-M3604 | ||
: 54. RC Loop to Shutdown Cooling Valve SID-UV-654 PKD-B44 | : 54. RC Loop to Shutdown Cooling Valve SID-UV-654 PKD-B44 | ||
: 55. LPSI Header B to RC Loop 2A Valve SIB-UV-615 PHB-M3606 | : 55. LPSI Header B to RC Loop 2A Valve SIB-UV-615 PHB-M3606 (continued) | ||
(continued) | |||
PALO VERDE UNITS 1, 2, 3 T7.0.200-2 Rev 52 7/16/10 | PALO VERDE UNITS 1, 2, 3 T7.0.200-2 Rev 52 7/16/10 | ||
| Line 2,270: | Line 2,177: | ||
Palo Verde Units 1, 2, 3 TA-i Rev 52 07/16/10 | Palo Verde Units 1, 2, 3 TA-i Rev 52 07/16/10 | ||
TRM Appendix TA PTLR TABLE OF CONTENTS TA1.0 Reactor Coolant System Pressure and Temperature Limits Report TA-1 TA2.0 Operating Limits............................................. TA-1 TA2.1 RCS Pressure and Temperature Limits (LCO 3.4.3)........ TA-2 TA2.2 RCS Loops - Mode 4 (LCO 3.4.6)......................... TA-2 TA2.3 RCS Loops - Mode 5, Loops Filled (LCO 3.4.7)........... TA-2 TA2.4 Pressurizer Safety Valves - Mode 4 (LCO 3.4.11)........ TA-2 TA2.5 Low Temperature Overpressure Protection System (LCO 3.4.13)........................................... TA-2 TA3.0 Neutron Fluence.............................................. TA-8 TA4.0 Reactor Vessel Material Surveillance Program................. TA-8 TA5.0 Adjusted Reference Temperature............................... TA-8 TA6.0 Application of Reactor Vessel Surveillance Data.............. TA-9 TA6.1 Applicability to Adjusted Reference Temperature........ TA-9 TA6.2 Evaluation of Surveillance Data Credibility........... TA-10 TA6.3 Derivation of Chemistry Factors from Surveillance Data TA-15 TA7.0 References.................................................. TA-15 | TRM Appendix TA PTLR TABLE OF CONTENTS TA1.0 Reactor Coolant System Pressure and Temperature Limits Report TA-1 TA2.0 Operating Limits............................................. TA-1 TA2.1 RCS Pressure and Temperature Limits (LCO 3.4.3)........ TA-2 TA2.2 RCS Loops - Mode 4 (LCO 3.4.6)......................... TA-2 TA2.3 RCS Loops - Mode 5, Loops Filled (LCO 3.4.7)........... TA-2 TA2.4 Pressurizer Safety Valves - Mode 4 (LCO 3.4.11)........ TA-2 TA2.5 Low Temperature Overpressure Protection System (LCO 3.4.13)........................................... TA-2 TA3.0 Neutron Fluence.............................................. TA-8 TA4.0 Reactor Vessel Material Surveillance Program................. TA-8 TA5.0 Adjusted Reference Temperature............................... TA-8 TA6.0 Application of Reactor Vessel Surveillance Data.............. TA-9 TA6.1 Applicability to Adjusted Reference Temperature........ TA-9 TA6.2 Evaluation of Surveillance Data Credibility........... TA-10 TA6.3 Derivation of Chemistry Factors from Surveillance Data TA-15 TA7.0 References.................................................. TA-15 Palo Verde Units 1, 2, 3 TA-ii Rev 52 07/16/10 | ||
Palo Verde Units 1, 2, 3 TA-ii Rev 52 07/16/10 | |||
TRM Appendix TA PTLR TABLE OF CONTENTS List of Figures Page TA2-1 RCS Heatup Limits through 32 EFPY...........................TA-6 TA2-2 RCS Cooldown Limits through 32 EFPY.........................TA-7 List of Tables Page TA2-1 RCS Heatup and Cooldown Rate Limits through 32 EFPY.........TA-3 TA2-2 Limiting RCS Temperatures through 32 EFPY...................TA-3 TA2-3 RCS Heatup P/T Limits through 32 EFPY.......................TA-4 TA2-4 RCS Cooldown P/T Limits through 32 EFPY.....................TA-5 TA3-1 Summary of Fluence and Fluence Factors......................TA-8 TA5-1 Summary of Limiting ART and RTPTS Values .....................TA-9 TA6-1 Base Metal Materials Selected for Surveillance Program.....TA-11 TA6-2 Unit 1 Credibility of Surveillance Measurements............TA-13 TA6-3 Unit 2 Credibility of Surveillance Measurements............TA-14 TA6-4 Unit 3 Credibility of Surveillance Measurements............TA-14 | TRM Appendix TA PTLR TABLE OF CONTENTS List of Figures Page TA2-1 RCS Heatup Limits through 32 EFPY...........................TA-6 TA2-2 RCS Cooldown Limits through 32 EFPY.........................TA-7 List of Tables Page TA2-1 RCS Heatup and Cooldown Rate Limits through 32 EFPY.........TA-3 TA2-2 Limiting RCS Temperatures through 32 EFPY...................TA-3 TA2-3 RCS Heatup P/T Limits through 32 EFPY.......................TA-4 TA2-4 RCS Cooldown P/T Limits through 32 EFPY.....................TA-5 TA3-1 Summary of Fluence and Fluence Factors......................TA-8 TA5-1 Summary of Limiting ART and RTPTS Values .....................TA-9 TA6-1 Base Metal Materials Selected for Surveillance Program.....TA-11 TA6-2 Unit 1 Credibility of Surveillance Measurements............TA-13 TA6-3 Unit 2 Credibility of Surveillance Measurements............TA-14 TA6-4 Unit 3 Credibility of Surveillance Measurements............TA-14 Palo Verde Units 1, 2, 3 TA-iii Rev 52 07/16/10 | ||
Palo Verde Units 1, 2, 3 TA-iii Rev 52 07/16/10 | |||
TRM Appendix TA PTLR TA1.0 Reactor Coolant System Pressure and Temperature Limits Report (PTLR) | TRM Appendix TA PTLR TA1.0 Reactor Coolant System Pressure and Temperature Limits Report (PTLR) | ||
| Line 2,285: | Line 2,188: | ||
The pressure-temperature limit curves comply with Appendix G to 10 CFR Part 50 requirements that the temperature of the closure head flange and vessel flange regions must be at least 120°F higher than the limiting RTNDT for these regions. This RTNDT limit applies during normal operation, including heatup and cooldown, when the core is not critical and the vessel pressure exceeds 625 psia, (20% of the pre-service hydrostatic test pressure of 3125 psia). | The pressure-temperature limit curves comply with Appendix G to 10 CFR Part 50 requirements that the temperature of the closure head flange and vessel flange regions must be at least 120°F higher than the limiting RTNDT for these regions. This RTNDT limit applies during normal operation, including heatup and cooldown, when the core is not critical and the vessel pressure exceeds 625 psia, (20% of the pre-service hydrostatic test pressure of 3125 psia). | ||
Refer to the Technical Specifications for LCOs and surveillance requirements applicable to RCS pressure and temperature limits. Specific TS LCO limits relocated from the Technical Specifications into this PTLR are given below. | Refer to the Technical Specifications for LCOs and surveillance requirements applicable to RCS pressure and temperature limits. Specific TS LCO limits relocated from the Technical Specifications into this PTLR are given below. | ||
(continued) | (continued) | ||
Palo Verde Units 1, 2, 3 TA-1 Rev 52 07/16/10 | Palo Verde Units 1, 2, 3 TA-1 Rev 52 07/16/10 | ||
TRM Appendix TA PTLR | TRM Appendix TA PTLR TA2.1 RCS Pressure and Temperature Limits (LCO 3.4.3) | ||
TA2.1 RCS Pressure and Temperature Limits (LCO 3.4.3) | |||
RCS heatup and cooldown rates for Units 1, 2 and 3 through 32 EFPY shall be equal to or less than the values shown in Table TA2-1. Limiting RCS temperature requirements through 32 EFPY are specified in Table TA2-2. The RCS pressure and temperature for vessel head boltup, inservice hydrostatic and leak testing through 32 EFPY shall be limited as specified on Figure TA2-1 (or Table TA2-3) for RCS heatup, and Figure TA2-2 (or Table TA2-4) for RCS cooldown. A gradual change in reactor coolant system temperature of +/-10ºF in any 1-hour period is the maximum permitted during inservice hydrostatic and leak testing. | RCS heatup and cooldown rates for Units 1, 2 and 3 through 32 EFPY shall be equal to or less than the values shown in Table TA2-1. Limiting RCS temperature requirements through 32 EFPY are specified in Table TA2-2. The RCS pressure and temperature for vessel head boltup, inservice hydrostatic and leak testing through 32 EFPY shall be limited as specified on Figure TA2-1 (or Table TA2-3) for RCS heatup, and Figure TA2-2 (or Table TA2-4) for RCS cooldown. A gradual change in reactor coolant system temperature of +/-10ºF in any 1-hour period is the maximum permitted during inservice hydrostatic and leak testing. | ||
TA2.2 RCS Loops - Mode 4 (LCO 3.4.6) | TA2.2 RCS Loops - Mode 4 (LCO 3.4.6) | ||
| Line 2,301: | Line 2,201: | ||
TA2.5 Low Temperature Overpressure Protection System (LCO 3.4.13) | TA2.5 Low Temperature Overpressure Protection System (LCO 3.4.13) | ||
The LTOP enable temperature for RCS heatup and cooldown through 32 EFPY is 221°F as specified in Table TA2-2. | The LTOP enable temperature for RCS heatup and cooldown through 32 EFPY is 221°F as specified in Table TA2-2. | ||
(continued) | (continued) | ||
Palo Verde Units 1, 2, 3 TA-2 Rev 52 07/16/10 | Palo Verde Units 1, 2, 3 TA-2 Rev 52 07/16/10 | ||
| Line 2,312: | Line 2,211: | ||
Table TA2-2 PVNGS Units 1, 2 and 3 Limiting RCS Temperatures through 32 EFPY Requirement RCS Temperature(1) | Table TA2-2 PVNGS Units 1, 2 and 3 Limiting RCS Temperatures through 32 EFPY Requirement RCS Temperature(1) | ||
Minimum Boltup Temperature 80°F Minimum Hydrostatic Test Temperature 181.4°F Lowest Service Temperature 153.2°F Minimum Flange Limit (Hydrostatic Test) 163.2°F Minimum Flange Limit (Normal Operation) 193.2°F LTOP Heatup and Cooldown Enable Temperature 221°F (1) Corrected for instrument uncertainty. | Minimum Boltup Temperature 80°F Minimum Hydrostatic Test Temperature 181.4°F Lowest Service Temperature 153.2°F Minimum Flange Limit (Hydrostatic Test) 163.2°F Minimum Flange Limit (Normal Operation) 193.2°F LTOP Heatup and Cooldown Enable Temperature 221°F (1) Corrected for instrument uncertainty. | ||
(continued) | (continued) | ||
Palo Verde Units 1, 2, 3 TA-3 Rev 52 07/16/10 | Palo Verde Units 1, 2, 3 TA-3 Rev 52 07/16/10 | ||
| Line 2,319: | Line 2,217: | ||
(°F)(1) (psia) @10°F/hr @20°F/hr @30°F/hr @40°F/hr @50°F/hr @75°F/hr (psia) 80 680.6 680.6 680.6 671.1 650.2 622.2 602.2 954.4 83.2 690.2 690.2 690.2 676.2 650.2 622.2 602.2 967.2 93.2 727.2 727.2 705.2 676.2 650.2 622.2 602.2 1016.2 103.2 772.2 772.2 710.2 676.2 650.2 622.2 602.2 1075.2 113.2 826.2 826.2 735.2 681.2 650.2 622.2 602.2 1148.2 123.2 893.2 893.2 778.2 700.2 653.2 622.2 602.2 1237.2 133.2 974.2 974.2 839.2 738.2 672.2 627.2 602.2 1346.2 143.2 1074.2 1074.2 918.2 790.2 705.2 645.2 602.2 1478.2 153.2 1195.2 1195.2 1018.2 862.2 754.2 676.2 604.2 1640.2 163.2 1344.2 1335.2 1142.2 954.2 819.2 721.2 617.2 1838.2 171.5 1494.8 1467.5 1269.5 1049.0 889.9 772.8 638.0 2039.1 172.1 1507.0 1478.3 1279.9 1057.0 896.0 777.3 598.0 2053.6 173.2 1525.2 1494.2 1295.2 1068.2 904.2 783.2 600.2 2080.2 183.2 1747.2 1689.2 1484.2 1213.2 1014.2 865.2 637.2 2375.2 186.7 1841.7 1772.5 1565.4 1275.5 1062.2 902.0 655.4 2500.0 193.2 2017.2 1927.2 1716.2 1391.2 1151.2 970.2 689.2 203.2 2347.2 2217.2 1998.2 1610.2 1320.2 1101.2 757.2 207.0 2500.0 2351.5 2129.3 1713.2 1399.2 1162.4 790.6 211.2 2500.0 2274.2 1827.0 1486.6 1230.0 827.6 213.2 2343.2 1881.2 1528.2 1262.2 845.2 213.2 2327.2 1865.2 1512.2 1246.2 829.2 217.3 2500.0 1998.9 1616.3 1327.8 874.7 223.2 2191.2 1766.2 1445.2 940.2 230.8 2500.0 2008.6 1634.4 1045.8 233.2 2085.2 1694.2 1079.2 243.2 2474.2 2000.2 1250.2 243.7 2500.0 2018.8 1260.8 253.2 2372.2 1461.2 256.0 2500.0 1533.4 263.2 1719.2 273.2 2034.2 283.2 2418.2 284.9 2500.0 (1) Corrected for instrument uncertainty and for RCS pressure and elevation effects. | (°F)(1) (psia) @10°F/hr @20°F/hr @30°F/hr @40°F/hr @50°F/hr @75°F/hr (psia) 80 680.6 680.6 680.6 671.1 650.2 622.2 602.2 954.4 83.2 690.2 690.2 690.2 676.2 650.2 622.2 602.2 967.2 93.2 727.2 727.2 705.2 676.2 650.2 622.2 602.2 1016.2 103.2 772.2 772.2 710.2 676.2 650.2 622.2 602.2 1075.2 113.2 826.2 826.2 735.2 681.2 650.2 622.2 602.2 1148.2 123.2 893.2 893.2 778.2 700.2 653.2 622.2 602.2 1237.2 133.2 974.2 974.2 839.2 738.2 672.2 627.2 602.2 1346.2 143.2 1074.2 1074.2 918.2 790.2 705.2 645.2 602.2 1478.2 153.2 1195.2 1195.2 1018.2 862.2 754.2 676.2 604.2 1640.2 163.2 1344.2 1335.2 1142.2 954.2 819.2 721.2 617.2 1838.2 171.5 1494.8 1467.5 1269.5 1049.0 889.9 772.8 638.0 2039.1 172.1 1507.0 1478.3 1279.9 1057.0 896.0 777.3 598.0 2053.6 173.2 1525.2 1494.2 1295.2 1068.2 904.2 783.2 600.2 2080.2 183.2 1747.2 1689.2 1484.2 1213.2 1014.2 865.2 637.2 2375.2 186.7 1841.7 1772.5 1565.4 1275.5 1062.2 902.0 655.4 2500.0 193.2 2017.2 1927.2 1716.2 1391.2 1151.2 970.2 689.2 203.2 2347.2 2217.2 1998.2 1610.2 1320.2 1101.2 757.2 207.0 2500.0 2351.5 2129.3 1713.2 1399.2 1162.4 790.6 211.2 2500.0 2274.2 1827.0 1486.6 1230.0 827.6 213.2 2343.2 1881.2 1528.2 1262.2 845.2 213.2 2327.2 1865.2 1512.2 1246.2 829.2 217.3 2500.0 1998.9 1616.3 1327.8 874.7 223.2 2191.2 1766.2 1445.2 940.2 230.8 2500.0 2008.6 1634.4 1045.8 233.2 2085.2 1694.2 1079.2 243.2 2474.2 2000.2 1250.2 243.7 2500.0 2018.8 1260.8 253.2 2372.2 1461.2 256.0 2500.0 1533.4 263.2 1719.2 273.2 2034.2 283.2 2418.2 284.9 2500.0 (1) Corrected for instrument uncertainty and for RCS pressure and elevation effects. | ||
(2) A gradual change in reactor coolant system temperature of +/-10ºF in any 1-hour period is the maximum permitted during inservice hydrostatic and leak testing. | (2) A gradual change in reactor coolant system temperature of +/-10ºF in any 1-hour period is the maximum permitted during inservice hydrostatic and leak testing. | ||
(continued) | (continued) | ||
Palo Verde Units 1, 2, 3 TA-4 Rev 52 07/16/10 | Palo Verde Units 1, 2, 3 TA-4 Rev 52 07/16/10 | ||
TRM Appendix TA PTLR Table TA2-4 PVNGS Unit 1, 2 and 3 RCS Cooldown P/T Limits through 32 EFPY Indicated Indicated RCS Pressure (psia)(1) @ Cooldown Rate Temperature Isothermal @10F/hr @20F/hr @30F/hr @40F/hr @50F/hr @75F/hr @100F/hr (F)(1) 80 680.6 612.3 589.0 527.1 469.5 416.6 329.2 237.6 83.2 690.2 623.2 601.2 541.2 485.2 433.2 329.2 272.2 90.9 718.6 655.4 638.0 583.4 533.5 492.2 402.8 372.6 91.3 720.1 657.2 598.0 585.7 536.1 495.4 406.8 378.1 93.2 727.2 665.2 607.2 596.2 548.2 510.2 425.2 403.2 99.6 756.1 698.0 644.5 638.0 597.1 559.7 501.1 493.2 99.9 757.5 699.6 646.3 598.0 599.4 562.1 504.7 497.5 103.2 772.2 716.2 665.2 619.2 624.2 587.2 543.2 543.2 104.7 780.4 725.6 676.1 631.3 638.0 604.8 565.0 565.0 104.9 781.6 727.0 677.7 633.1 598.0 607.3 568.2 568.2 107.6 795.8 743.4 696.7 654.2 622.1 638.0 606.3 606.3 107.8 796.8 744.4 698.0 655.6 623.6 598.0 608.7 608.7 109.8 807.8 757.0 712.6 671.9 642.1 621.6 638.0 638.0 109.9 808.5 757.9 713.6 673.0 643.4 623.2 598.0 598.0 113.2 826.2 778.2 737.2 699.2 673.2 661.2 645.2 645.2 123.2 893.2 854.2 823.2 798.2 781.2 776.2 776.2 776.2 133.2 974.2 947.2 929.2 918.2 918.2 918.2 918.2 918.2 143.2 1074.2 1060.2 1057.2 1057.2 1057.2 1057.2 1057.2 1057.2 153.2 1195.2 1195.2 1195.2 1195.2 1195.2 1195.2 1195.2 1195.2 163.2 1344.2 1344.2 1344.2 1344.2 1344.2 1344.2 1344.2 1344.2 173.2 1525.2 1525.2 1525.2 1525.2 1525.2 1525.2 1525.2 1525.2 183.2 1747.2 1747.2 1747.2 1747.2 1747.2 1747.2 1747.2 1747.2 193.2 2017.2 2017.2 2017.2 2017.2 2017.2 2017.2 2017.2 2017.2 203.2 2347.2 2347.2 2347.2 2347.2 2347.2 2347.2 2347.2 2347.2 207.1 2500.0 2500.0 2500.0 2500.0 2500.0 2500.0 2500.0 2500.0 (1) Corrected for instrument uncertainty and for RCS pressure and elevation effects. | TRM Appendix TA PTLR Table TA2-4 PVNGS Unit 1, 2 and 3 RCS Cooldown P/T Limits through 32 EFPY Indicated Indicated RCS Pressure (psia)(1) @ Cooldown Rate Temperature Isothermal @10F/hr @20F/hr @30F/hr @40F/hr @50F/hr @75F/hr @100F/hr (F)(1) 80 680.6 612.3 589.0 527.1 469.5 416.6 329.2 237.6 83.2 690.2 623.2 601.2 541.2 485.2 433.2 329.2 272.2 90.9 718.6 655.4 638.0 583.4 533.5 492.2 402.8 372.6 91.3 720.1 657.2 598.0 585.7 536.1 495.4 406.8 378.1 93.2 727.2 665.2 607.2 596.2 548.2 510.2 425.2 403.2 99.6 756.1 698.0 644.5 638.0 597.1 559.7 501.1 493.2 99.9 757.5 699.6 646.3 598.0 599.4 562.1 504.7 497.5 103.2 772.2 716.2 665.2 619.2 624.2 587.2 543.2 543.2 104.7 780.4 725.6 676.1 631.3 638.0 604.8 565.0 565.0 104.9 781.6 727.0 677.7 633.1 598.0 607.3 568.2 568.2 107.6 795.8 743.4 696.7 654.2 622.1 638.0 606.3 606.3 107.8 796.8 744.4 698.0 655.6 623.6 598.0 608.7 608.7 109.8 807.8 757.0 712.6 671.9 642.1 621.6 638.0 638.0 109.9 808.5 757.9 713.6 673.0 643.4 623.2 598.0 598.0 113.2 826.2 778.2 737.2 699.2 673.2 661.2 645.2 645.2 123.2 893.2 854.2 823.2 798.2 781.2 776.2 776.2 776.2 133.2 974.2 947.2 929.2 918.2 918.2 918.2 918.2 918.2 143.2 1074.2 1060.2 1057.2 1057.2 1057.2 1057.2 1057.2 1057.2 153.2 1195.2 1195.2 1195.2 1195.2 1195.2 1195.2 1195.2 1195.2 163.2 1344.2 1344.2 1344.2 1344.2 1344.2 1344.2 1344.2 1344.2 173.2 1525.2 1525.2 1525.2 1525.2 1525.2 1525.2 1525.2 1525.2 183.2 1747.2 1747.2 1747.2 1747.2 1747.2 1747.2 1747.2 1747.2 193.2 2017.2 2017.2 2017.2 2017.2 2017.2 2017.2 2017.2 2017.2 203.2 2347.2 2347.2 2347.2 2347.2 2347.2 2347.2 2347.2 2347.2 207.1 2500.0 2500.0 2500.0 2500.0 2500.0 2500.0 2500.0 2500.0 (1) Corrected for instrument uncertainty and for RCS pressure and elevation effects. | ||
(continued) | (continued) | ||
Palo Verde Units 1, 2, 3 TA-5 Rev 52 07/16/10 | Palo Verde Units 1, 2, 3 TA-5 Rev 52 07/16/10 | ||
| Line 2,331: | Line 2,227: | ||
(1) Corrected for instrument uncertainty and for RCS pressure and elevation effects. | (1) Corrected for instrument uncertainty and for RCS pressure and elevation effects. | ||
(2) A gradual change in reactor coolant system temperature of +/-10ºF in any 1-hour period is the maximum permitted during inservice hydrostatic and leak testing. | (2) A gradual change in reactor coolant system temperature of +/-10ºF in any 1-hour period is the maximum permitted during inservice hydrostatic and leak testing. | ||
(continued) | (continued) | ||
Palo Verde Units 1, 2, 3 TA-6 Rev 52 07/16/10 | Palo Verde Units 1, 2, 3 TA-6 Rev 52 07/16/10 | ||
| Line 2,338: | Line 2,233: | ||
(1) Corrected for instrument uncertainty and for RCS pressure and elevation effects. | (1) Corrected for instrument uncertainty and for RCS pressure and elevation effects. | ||
(2) A gradual change in reactor coolant system temperature of +/-10ºF in any 1-hour period is the maximum permitted during inservice hydrostatic and leak testing. | (2) A gradual change in reactor coolant system temperature of +/-10ºF in any 1-hour period is the maximum permitted during inservice hydrostatic and leak testing. | ||
(continued) | (continued) | ||
Palo Verde Units 1, 2, 3 TA-7 Rev 52 07/16/10 | Palo Verde Units 1, 2, 3 TA-7 Rev 52 07/16/10 | ||
TRM Appendix TA PTLR | TRM Appendix TA PTLR TA3.0 Neutron Fluence The design value of peak fast neutron fluence through 32 EFPY for determining the limiting reactor vessel beltline material adjusted reference temperature is 3.29E+19 n/cm2 (E > 1.0 MeV) and corresponds to the fluence at the vessel clad-to-base metal interface. For conservatism, this peak fluence is assumed to apply to each of the PVNGS reactor vessel beltline plates and welds; i.e., | ||
TA3.0 Neutron Fluence The design value of peak fast neutron fluence through 32 EFPY for determining the limiting reactor vessel beltline material adjusted reference temperature is 3.29E+19 n/cm2 (E > 1.0 MeV) and corresponds to the fluence at the vessel clad-to-base metal interface. For conservatism, this peak fluence is assumed to apply to each of the PVNGS reactor vessel beltline plates and welds; i.e., | |||
no reduction factor is applied to account for axial or azimuthal variations from the peak value. | no reduction factor is applied to account for axial or azimuthal variations from the peak value. | ||
A summary of fast neutron fluence and fluence factors through 32 EFPY determined at the 1/4T and 3/4T locations in the vessel wall is given in Table TA3-1. These fluence values are used to calculate the adjusted reference temperature at PVNGS Units 1, 2 and 3. | A summary of fast neutron fluence and fluence factors through 32 EFPY determined at the 1/4T and 3/4T locations in the vessel wall is given in Table TA3-1. These fluence values are used to calculate the adjusted reference temperature at PVNGS Units 1, 2 and 3. | ||
Table TA3-1 Summary of Fluence and Fluence Factors Location 1/4T f (n/cm2)(1) 1/4T ff(2) 3/4T f (n/cm2)(1) 3/4T ff(2) | Table TA3-1 Summary of Fluence and Fluence Factors Location 1/4T f (n/cm2)(1) 1/4T ff(2) 3/4T f (n/cm2)(1) 3/4T ff(2) | ||
Intermediate Shell 1.681E+19 1.1431 4.390E+18 0.7711 Lower Shell 1.910E+19 1.1770 6.438E+18 0.8766 (1) f = fast neutron fluence (2) ff = fluence factor TA4.0 Reactor Vessel Material Surveillance Program The PVNGS reactor vessel material surveillance program, as described in Section 5.3 of the PVNGS Updated Final Safety Analysis Report (UFSAR), is in compliance with 10 CFR Part 50, Appendix H Reactor Vessel Material Surveillance Program Requirements. The surveillance capsule withdrawal schedules are presented in UFSAR Tables 5.3-13 through 5.3-19A and summarized in WCAP-16835 (Ref. 3). Test results and analyses of withdrawn surveillance specimens were reported in References 6, 7, and 8. | Intermediate Shell 1.681E+19 1.1431 4.390E+18 0.7711 Lower Shell 1.910E+19 1.1770 6.438E+18 0.8766 (1) f = fast neutron fluence (2) ff = fluence factor TA4.0 Reactor Vessel Material Surveillance Program The PVNGS reactor vessel material surveillance program, as described in Section 5.3 of the PVNGS Updated Final Safety Analysis Report (UFSAR), is in compliance with 10 CFR Part 50, Appendix H Reactor Vessel Material Surveillance Program Requirements. The surveillance capsule withdrawal schedules are presented in UFSAR Tables 5.3-13 through 5.3-19A and summarized in WCAP-16835 (Ref. 3). Test results and analyses of withdrawn surveillance specimens were reported in References 6, 7, and 8. | ||
TA5.0 Adjusted Reference Temperature A summary of limiting adjusted reference temperatures associated with PVNGS beltline materials at the 1/4T and 3/4T locations along with RTPTS values through 32 EFPY is given in Table TA5-1. Conservatively, the most limiting (highest) adjusted reference temperature value from the three PVNGS units is | TA5.0 Adjusted Reference Temperature A summary of limiting adjusted reference temperatures associated with PVNGS beltline materials at the 1/4T and 3/4T locations along with RTPTS values through 32 EFPY is given in Table TA5-1. Conservatively, the most limiting (highest) adjusted reference temperature value from the three PVNGS units is (continued) | ||
(continued) | |||
Palo Verde Units 1, 2, 3 TA-8 Rev 52 07/16/10 | Palo Verde Units 1, 2, 3 TA-8 Rev 52 07/16/10 | ||
TRM Appendix TA PTLR | TRM Appendix TA PTLR applied to all three units. Chemistry factors and adjusted reference temperatures for PVNGS are determined in accordance with Regulatory Guide 1.99 (Ref. 9). | ||
applied to all three units. Chemistry factors and adjusted reference temperatures for PVNGS are determined in accordance with Regulatory Guide 1.99 (Ref. 9). | |||
Table TA5-1 Summary of Limiting ART and RTPTS Values 1/4T ART PVNGS Location Material 3/4T ART (°F) RTPTS (°F) | Table TA5-1 Summary of Limiting ART and RTPTS Values 1/4T ART PVNGS Location Material 3/4T ART (°F) RTPTS (°F) | ||
(°F) | (°F) | ||
| Line 2,363: | Line 2,251: | ||
TA6.0 Application of Reactor Vessel Surveillance Data TA6.1 Applicability to Adjusted Reference Temperature Data from the reactor vessel surveillance program or from other supplemental sources were not used to determine the adjusted reference temperature (ART) values for the PVNGS beltline materials described in Section 5. The surveillance program data from each of the three Palo Verde units were evaluated for credibility; chemistry factors were also derived for those surveillance materials. (This assessment is further detailed in Report WCAP-16835 [Ref. 3].) | TA6.0 Application of Reactor Vessel Surveillance Data TA6.1 Applicability to Adjusted Reference Temperature Data from the reactor vessel surveillance program or from other supplemental sources were not used to determine the adjusted reference temperature (ART) values for the PVNGS beltline materials described in Section 5. The surveillance program data from each of the three Palo Verde units were evaluated for credibility; chemistry factors were also derived for those surveillance materials. (This assessment is further detailed in Report WCAP-16835 [Ref. 3].) | ||
Chemistry factors determined following Position 1.1 of Regulatory Guide 1.99 are shown to be conservative relative to those derived from surveillance plate and weld measurements for each of the PVNGS units. Therefore, no credit is taken for those credible results in the calculation of ART. | Chemistry factors determined following Position 1.1 of Regulatory Guide 1.99 are shown to be conservative relative to those derived from surveillance plate and weld measurements for each of the PVNGS units. Therefore, no credit is taken for those credible results in the calculation of ART. | ||
(continued) | (continued) | ||
Palo Verde Units 1, 2, 3 TA-9 Rev 52 07/16/10 | Palo Verde Units 1, 2, 3 TA-9 Rev 52 07/16/10 | ||
TRM Appendix TA PTLR | TRM Appendix TA PTLR Each new set of surveillance results, as new data becomes available, will be evaluated to ascertain that the Position 1.1 chemistry factors remain conservative relative to the surveillance results. This will ensure that the existing RCS P/T limits remain conservative for continued plant operation or will be revised as needed to provide conservative RCS pressure-temperature limits. | ||
Each new set of surveillance results, as new data becomes available, will be evaluated to ascertain that the Position 1.1 chemistry factors remain conservative relative to the surveillance results. This will ensure that the existing RCS P/T limits remain conservative for continued plant operation or will be revised as needed to provide conservative RCS pressure-temperature limits. | |||
TA6.2 Evaluation of Surveillance Data Credibility Regulatory Guide 1.99 describes general procedures acceptable to the NRC staff for calculating the effects of neutron radiation embrittlement of low-alloy steels used in the PVNGS reactor vessels when credible surveillance capsule data is available. Position C.2 of Regulatory Guide 1.99 describes the method for calculating the adjusted reference temperature and Charpy upper-shelf energy of reactor vessel beltline materials using surveillance capsule data. | TA6.2 Evaluation of Surveillance Data Credibility Regulatory Guide 1.99 describes general procedures acceptable to the NRC staff for calculating the effects of neutron radiation embrittlement of low-alloy steels used in the PVNGS reactor vessels when credible surveillance capsule data is available. Position C.2 of Regulatory Guide 1.99 describes the method for calculating the adjusted reference temperature and Charpy upper-shelf energy of reactor vessel beltline materials using surveillance capsule data. | ||
The methods of Position C.2 apply when two or more credible surveillance data sets become available from each unit. | The methods of Position C.2 apply when two or more credible surveillance data sets become available from each unit. | ||
| Line 2,377: | Line 2,262: | ||
Revision 2 of Regulatory Guide 1.99 defines five requirements that must be met for surveillance data to be judged credible. The purpose of the following discussion is to apply these credibility requirements to PVNGS to show that the reactor vessel surveillance data are credible. | Revision 2 of Regulatory Guide 1.99 defines five requirements that must be met for surveillance data to be judged credible. The purpose of the following discussion is to apply these credibility requirements to PVNGS to show that the reactor vessel surveillance data are credible. | ||
Criterion 1: Materials in the capsules should be those judged most likely to be controlling with regard to radiation embrittlement. | Criterion 1: Materials in the capsules should be those judged most likely to be controlling with regard to radiation embrittlement. | ||
(continued) | (continued) | ||
Palo Verde Units 1, 2, 3 TA-10 Rev 52 07/16/10 | Palo Verde Units 1, 2, 3 TA-10 Rev 52 07/16/10 | ||
TRM Appendix TA PTLR | TRM Appendix TA PTLR The beltline region of the reactor vessel is defined in Appendix G(II)(F) to 10 CFR Part 50, Fracture Toughness Requirements, as: | ||
The beltline region of the reactor vessel is defined in Appendix G(II)(F) to 10 CFR Part 50, Fracture Toughness Requirements, as: | |||
Beltline or beltline region of the reactor vessel means the region of the reactor vessel (shell material including welds, heat affected zones, and plates or forgings) that directly surrounds the effective height of the active core and adjacent regions of the reactor vessel that are predicted to experience sufficient neutron radiation damage to be considered in the selection of the most limiting material with regard to radiation damage. | Beltline or beltline region of the reactor vessel means the region of the reactor vessel (shell material including welds, heat affected zones, and plates or forgings) that directly surrounds the effective height of the active core and adjacent regions of the reactor vessel that are predicted to experience sufficient neutron radiation damage to be considered in the selection of the most limiting material with regard to radiation damage. | ||
Table TA6-1 identifies the Units 1, 2, and 3 reactor vessel base metal beltline plate materials selected for the PVNGS surveillance program. | Table TA6-1 identifies the Units 1, 2, and 3 reactor vessel base metal beltline plate materials selected for the PVNGS surveillance program. | ||
| Line 2,393: | Line 2,275: | ||
Therefore, the PVNGS Units 1, 2, and 3 surveillance material meets the intent of this criterion. | Therefore, the PVNGS Units 1, 2, and 3 surveillance material meets the intent of this criterion. | ||
Criterion 2: Scatter in the plots of Charpy energy versus temperature for the irradiated and unirradiated conditions should be small enough to permit the determination of the 30 ft-lb temperature and upper shelf energy unambiguously. | Criterion 2: Scatter in the plots of Charpy energy versus temperature for the irradiated and unirradiated conditions should be small enough to permit the determination of the 30 ft-lb temperature and upper shelf energy unambiguously. | ||
(continued) | (continued) | ||
Palo Verde Units 1, 2, 3 TA-11 Rev 52 07/16/10 | Palo Verde Units 1, 2, 3 TA-11 Rev 52 07/16/10 | ||
TRM Appendix TA PTLR | TRM Appendix TA PTLR Evaluation of Charpy energy versus temperature for the unirradiated and irradiated condition is presented in References 6, 7, and 8. Based on engineering judgment, the scatter in the data presented is small enough to permit the unambiguous determination of the 30 ft-lb temperature and the upper shelf energy of the PVNGS Units 1, 2, and 3 surveillance materials. Thus, the PVNGS surveillance program meets this criterion. | ||
Evaluation of Charpy energy versus temperature for the unirradiated and irradiated condition is presented in References 6, 7, and 8. Based on engineering judgment, the scatter in the data presented is small enough to permit the unambiguous determination of the 30 ft-lb temperature and the upper shelf energy of the PVNGS Units 1, 2, and 3 surveillance materials. Thus, the PVNGS surveillance program meets this criterion. | |||
Criterion 3: When there are two or more sets of surveillance data from one reactor, the scatter of RTNDT values about a best-fit line drawn as described in Regulatory Position 2.1 normally should be less than 28°F for welds and 17°F for base metal. Even if the fluence range is large (two or more orders of magnitude), the scatter should not exceed twice those values. Even if the data fail this criterion for use in shift calculations, they may be credible for determining decrease in upper shelf energy if the upper shelf can be clearly determined, following the definition given in ASTM E 185-82. | Criterion 3: When there are two or more sets of surveillance data from one reactor, the scatter of RTNDT values about a best-fit line drawn as described in Regulatory Position 2.1 normally should be less than 28°F for welds and 17°F for base metal. Even if the fluence range is large (two or more orders of magnitude), the scatter should not exceed twice those values. Even if the data fail this criterion for use in shift calculations, they may be credible for determining decrease in upper shelf energy if the upper shelf can be clearly determined, following the definition given in ASTM E 185-82. | ||
The surveillance program for PVNGS Units 1, 2, and 3 is based on ASTM E185-79, which presents criteria for monitoring changes in the fracture toughness properties of reactor vessel beltline materials. References 6, 7, and 8 describe the post-irradiation evaluations of PVNGS surveillance materials. | The surveillance program for PVNGS Units 1, 2, and 3 is based on ASTM E185-79, which presents criteria for monitoring changes in the fracture toughness properties of reactor vessel beltline materials. References 6, 7, and 8 describe the post-irradiation evaluations of PVNGS surveillance materials. | ||
The credibility results shown in Tables TA6-2, TA6-3 and TA6-4 for Units 1, 2, and 3, respectively, present the shift measurements available to date. Those values are compared to predictions based on a chemistry factor determined following Position 1.1 of Regulatory Guide 1.99. In all cases, the difference between the measured and predicted shift is less than 17ºF for the surveillance plates and less than 28ºF for the surveillance welds. Therefore, this criterion is met for the PVNGS Units 1, 2, and 3 surveillance program plate and weld materials. | The credibility results shown in Tables TA6-2, TA6-3 and TA6-4 for Units 1, 2, and 3, respectively, present the shift measurements available to date. Those values are compared to predictions based on a chemistry factor determined following Position 1.1 of Regulatory Guide 1.99. In all cases, the difference between the measured and predicted shift is less than 17ºF for the surveillance plates and less than 28ºF for the surveillance welds. Therefore, this criterion is met for the PVNGS Units 1, 2, and 3 surveillance program plate and weld materials. | ||
(continued) | (continued) | ||
Palo Verde Units 1, 2, 3 TA-12 Rev 52 07/16/10 | Palo Verde Units 1, 2, 3 TA-12 Rev 52 07/16/10 | ||
| Line 2,412: | Line 2,290: | ||
Monitor 38 131.7 0.8697 114.1 114.5 - 0.4 Material 230 131.7(1) 0.9629 129.2 126.8 + 2.4 (1) Chemistry factor based on 0.174 Cu and 0.665 Ni using Table 2 of Regulatory Guide 1.99, Rev. 2. | Monitor 38 131.7 0.8697 114.1 114.5 - 0.4 Material 230 131.7(1) 0.9629 129.2 126.8 + 2.4 (1) Chemistry factor based on 0.174 Cu and 0.665 Ni using Table 2 of Regulatory Guide 1.99, Rev. 2. | ||
(2) ff = fluence factor = f(0.28 - 0.1*log f) | (2) ff = fluence factor = f(0.28 - 0.1*log f) | ||
(continued) | (continued) | ||
Palo Verde Units 1, 2, 3 TA-13 Rev 52 07/16/10 | Palo Verde Units 1, 2, 3 TA-13 Rev 52 07/16/10 | ||
| Line 2,426: | Line 2,303: | ||
Plate F-6411-2 230 10.2 0.9726 6.3 9.9 - 3.6 Longitudinal Plate F-6411-2 142 10.2 0.7090 13.1 7.2 + 5.9 Transverse 230 10.2 0.9726 9.2 9.9 - 0.7 Weld 142 29.6 0.7090 27.5 21.0 + 6.5 (Heat 4P7869) 230 29.6 0.9726 24.1 28.8 - 4.7 Correlation 142 131.7 (1) 0.7090 82.5 93.4 - 10.9 Monitor Material 230 131.7(1) 0.9726 141.8 128.1 + 13.7 (1) Chemistry Factor based on 0.174 Cu and 0.665 Ni using Table 2 of Regulatory Guide 1.99, R02. | Plate F-6411-2 230 10.2 0.9726 6.3 9.9 - 3.6 Longitudinal Plate F-6411-2 142 10.2 0.7090 13.1 7.2 + 5.9 Transverse 230 10.2 0.9726 9.2 9.9 - 0.7 Weld 142 29.6 0.7090 27.5 21.0 + 6.5 (Heat 4P7869) 230 29.6 0.9726 24.1 28.8 - 4.7 Correlation 142 131.7 (1) 0.7090 82.5 93.4 - 10.9 Monitor Material 230 131.7(1) 0.9726 141.8 128.1 + 13.7 (1) Chemistry Factor based on 0.174 Cu and 0.665 Ni using Table 2 of Regulatory Guide 1.99, R02. | ||
(2) ff = fluence factor = f(0.28 - 0.1*log f) | (2) ff = fluence factor = f(0.28 - 0.1*log f) | ||
(continued) | (continued) | ||
Palo Verde Units 1, 2, 3 TA-14 Rev 52 07/16/10 | Palo Verde Units 1, 2, 3 TA-14 Rev 52 07/16/10 | ||
TRM Appendix TA PTLR | TRM Appendix TA PTLR Criterion 4: The irradiation temperature of the Charpy specimens in the capsule should match the vessel wall temperature at the cladding/base metal interface within +/- 25°F. | ||
Criterion 4: The irradiation temperature of the Charpy specimens in the capsule should match the vessel wall temperature at the cladding/base metal interface within +/- 25°F. | |||
All reactor vessel surveillance specimen capsule holders are attached to the inside vessel wall cladding in the beltline region at PVNGS. This capsule holder attachment method meets the design and inspection requirements of the ASME Code, Sections III and XI. The location of the specimens relative to the reactor vessel beltline provides assurance that the reactor vessel wall and the specimens experience equivalent operating conditions such that the temperatures will not differ by more than 25°F. Hence this criterion is met. | All reactor vessel surveillance specimen capsule holders are attached to the inside vessel wall cladding in the beltline region at PVNGS. This capsule holder attachment method meets the design and inspection requirements of the ASME Code, Sections III and XI. The location of the specimens relative to the reactor vessel beltline provides assurance that the reactor vessel wall and the specimens experience equivalent operating conditions such that the temperatures will not differ by more than 25°F. Hence this criterion is met. | ||
Criterion 5: The surveillance data for the correlation monitor material in the capsule should fall within the scatter band of the data base for that material. | Criterion 5: The surveillance data for the correlation monitor material in the capsule should fall within the scatter band of the data base for that material. | ||
| Line 2,441: | Line 2,315: | ||
TA7.0 References | TA7.0 References | ||
: 1. PVNGS Units 1, 2, and 3 Technical Specification 5.6.9, Reactor Coolant System Pressure and Temperature Limits Report. | : 1. PVNGS Units 1, 2, and 3 Technical Specification 5.6.9, Reactor Coolant System Pressure and Temperature Limits Report. | ||
: 2. CE Owners Group Topical Report CE NPSD-683-A, Revision 6, Development of a RCS Pressure and Temperature Limits Report for the Removal of P/T | : 2. CE Owners Group Topical Report CE NPSD-683-A, Revision 6, Development of a RCS Pressure and Temperature Limits Report for the Removal of P/T (continued) | ||
(continued) | |||
Palo Verde Units 1, 2, 3 TA-15 Rev 52 07/16/10 | Palo Verde Units 1, 2, 3 TA-15 Rev 52 07/16/10 | ||
TRM Appendix TA PTLR | TRM Appendix TA PTLR Limits and LTOP Requirements from the Technical Specifications, April 2001. | ||
Limits and LTOP Requirements from the Technical Specifications, April 2001. | |||
: 3. Westinghouse Report WCAP-16835, Revision 0, Palo Verde Nuclear Generating Station Units 1, 2 and 3, Basis for RCS Pressure-Temperature Limits Report, June 2008. | : 3. Westinghouse Report WCAP-16835, Revision 0, Palo Verde Nuclear Generating Station Units 1, 2 and 3, Basis for RCS Pressure-Temperature Limits Report, June 2008. | ||
: 4. APS letter No. 102-05960 to NRC, Request for Technical Specification Amendment to Relocate the Reactor Coolant System Pressure and Temperature Limits and the Low Temperature Overpressure Protection Enable Temperatures, dated February 19, 2009. Supplemented by APS Letter No. 102-06112, Response to Request for Additional Information for Technical Specification Amendment and Exemption from 10 CFR 50, Appendix G, to Relocate the Reactor Coolant System Pressure and Temperature Limits and the Low Temperature Overpressure Protection Enable Temperatures, dated December 22, 2009. | : 4. APS letter No. 102-05960 to NRC, Request for Technical Specification Amendment to Relocate the Reactor Coolant System Pressure and Temperature Limits and the Low Temperature Overpressure Protection Enable Temperatures, dated February 19, 2009. Supplemented by APS Letter No. 102-06112, Response to Request for Additional Information for Technical Specification Amendment and Exemption from 10 CFR 50, Appendix G, to Relocate the Reactor Coolant System Pressure and Temperature Limits and the Low Temperature Overpressure Protection Enable Temperatures, dated December 22, 2009. | ||
| Line 2,456: | Line 2,326: | ||
: 8. APS letter no. 102-05348 to NRC, Palo Verde Nuclear Generating Station Unit 3 Analysis of Reactor Vessel Material Surveillance Capsule at 230°, September 26, 2005 (transmittal of WCAP-16449-NP, Analysis of Capsule 230° from Arizona Public Service Company Palo Verde Unit 3 Reactor Vessel Radiation Surveillance Program, August 2005). | : 8. APS letter no. 102-05348 to NRC, Palo Verde Nuclear Generating Station Unit 3 Analysis of Reactor Vessel Material Surveillance Capsule at 230°, September 26, 2005 (transmittal of WCAP-16449-NP, Analysis of Capsule 230° from Arizona Public Service Company Palo Verde Unit 3 Reactor Vessel Radiation Surveillance Program, August 2005). | ||
: 9. Regulatory Guide 1.99, Revision 2, Radiation Embrittlement of Reactor Vessel Materials, U.S. Nuclear Regulatory Commission, May 1998. | : 9. Regulatory Guide 1.99, Revision 2, Radiation Embrittlement of Reactor Vessel Materials, U.S. Nuclear Regulatory Commission, May 1998. | ||
Palo Verde Units 1, 2, 3 TA-16 Rev 52 07/16/10}} | Palo Verde Units 1, 2, 3 TA-16 Rev 52 07/16/10}} | ||
Latest revision as of 06:01, 11 March 2020
| ML110610758 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 01/26/2011 |
| From: | Stephenson C Arizona Public Service Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML110610758 (275) | |
Text
Technical Requirements Manual Revision 54 January 26, 2011 Stephenson, Digitally signed by Stephenson, Carl J(Z05778)
DN: cn=Stephenson, Carl J(Z05778)
Carl J(Z05778)
Reason: I attest to the accuracy and integrity of this document Date: 2011.01.25 08:35:37 -07'00' PALO VERDE UNITS 1, 2, 3
TABLE OF CONTENTS T1.0 USE AND APPLICATION Definitions.................................................. T1.1.100-1 Logical Connectors........................................... T1.2.100-1 Completion Times............................................. T1.3.100-1 Frequency.................................................... T1.4.100-1 T2.0 SAFETY LIMITS................................................ T2.0.100-1 T3.0 TRM Limiting Condition for Operation (TLCO) APPLICABILITY.... T3.0.100-1 TRM Surveillance Requirement (TSR) Applicability............. T3.0.100-3 T3.1 REACTIVITY CONTROL SYSTEMS T3.1.100 Flow Paths - Shutdown ............................. T3.1.100-1 T3.1.101 Flow Paths - Operating ............................ T3.1.101-1 T3.1.102 Charging Pumps - Shutdown ......................... T3.1.102-1 T3.1.103 Charging Pumps - Operating ........................ T3.1.103-1 T3.1.104 Borated Sources - Shutdown ........................ T3.1.104-1 T3.1.105 Borated Sources - Operating ....................... T3.1.105-1 T3.1.200 Shutdown Margin - Reactor Trip Breakers Closed .... T3.1.200-1 T3.1.201 Shutdown Margin - Reactor Trip Breakers Open ...... T3.1.201-1 T3.1.202 Control Element Assembly - Alignment .............. T3.1.202-1 T3.1.203 Control Element Assembly - Drop Time .............. T3.1.203-1 T3.1.204 Shutdown Control Element Assembly Insertion Limits ............................................ T3.1.204-1 T3.1.205 Regulating Control Element Assembly Group Insertion Limits .................................. T3.1.205-1 T3.2 POWER DISTRIBUTION LIMITS T3.2.200 Azimuthal Power Tilt - Tq ......................... T3.2.200-1 T3.3 INSTRUMENTATION T3.3.100 Supplementary Prot. System (SPS) Instrumentation .. T3.3.100-1 T3.3.101 Radiation Monitoring Instrumentation .............. T3.3.101-1 T3.3.102 Incore Detectors .................................. T3.3.102-1 T3.3.103 Seismic Monitoring ................................ T3.3.103-1 T3.3.104 Meteorological Instrumentation .................... T3.3.104-1 T3.3.105 Post Accident Monitoring Instrumentation .......... T3.3.105-1 T3.3.106 Loose-Part Detection Instrumentation .............. T3.3.106-1 T3.3.107 Explosive Gas Monitoring System ................... T3.3.107-1 T3.3.108 Fuel Bldg Ess. Vent. Actuation Signal (FBEVAS) .... T3.3.108-1 T3.3.200 RPS Instrumentation - Operating ................... T3.3.200-1 T3.3.201 ESFAS Logic and Manual Trip ....................... T3.3.201-1 (continued)
PALO VERDE UNITS 1, 2, 3 i Rev 33 4/20/05
TABLE OF CONTENTS (continued)
T3.4 REACTOR COOLANT SYSTEM (RCS)
T3.4.100 Auxiliary Spray System ............................ T3.4.100-1 T3.4.101 RCS Chemistry ..................................... T3.4.101-1 T3.4.102 Pressurizer Heatup and Cooldown Limits ............ T3.4.102-1 T3.4.103 Structural Integrity .............................. T3.4.103-1 T3.4.104 RCS Vents (Reactor Head Vents) .................... T3.4.104-1 T3.4.200 RCS Pressure and Temperature (P/T) Limits ......... T3.4.200-1 T3.4.201 Pressurizer ....................................... T3.4.201-1 T3.4.202 Pressurizer Vents ................................. T3.4.202-1 T3.4.203 RCS Operational LEAKAGE ........................... T3.4.203-1 T3.4.204 RCS PIV Leakage ................................... T3.4.204-1 T3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)
T3.5.200 Safety Injection Tanks ............................ T3.5.200-1 T3.5.201 Shutdown Cooling System ........................... T3.5.201-1 T3.5.202 ECCS - Operating .................................. T3.5.202-1 T3.5.203 ECCS - Shutdown ................................... T3.5.203-1 T3.6 CONTAINMENT SYSTEMS T3.6.100 Hydrogen Purge Cleanup System ..................... T3.6.100-1 T3.6.200 Pre-stressed Concrete Containment Tendon .......... T3.6.200-1 T3.6.201 Containment Spray Systems ......................... T3.6.201-1 T3.6.300 Hydrogen Recombiners .............................. T3.6.300-1 T3.7 PLANT SYSTEMS T3.7.100 Steam Generator Pressure and Temp. Limitations .... T3.7.100-1 T3.7.101 Snubbers .......................................... T3.7.101-1 T3.7.102 Sealed Source Contamination ....................... T3.7.102-1 T3.7.200 Atmospheric Dump Valves (ADVs) .................... T3.7.200-1 T3.7.201 AFW System ........................................ T3.7.201-1 T3.7.202 Essential Cooling Water (EW) System ............... T3.7.202-1 T3.7.203 Essential Spray Pond System (ESPS) ................ T3.7.203-1 T3.7.204 Essential Chilled Water (EC) System ............... T3.7.204-1 T3.7.205 Cont. Room Emergency Air Temp. Cont. Sys. (CREATCS)T3.7.205-1 T3.7.206 Fuel Storage Pool Water Level ..................... T3.7.206-1 T3.7.207 Secondary Specific Activity ....................... T3.7.207-1 T3.8 ELECTRICAL POWER SYSTEMS T3.8.100 Cathodic Protection ............................... T3.8.100-1 T3.8.101 Cont. Penetration Cond. Overcurrent Prot. Devices . T3.8.101-1 T3.8.102 MOV Thermal Overload Prot. and Bypass Devices ..... T3.8.102-1 T3.8.200 AC Sources - Shutdown ............................. T3.8.200-1 (continued)
PALO VERDE UNITS 1, 2, 3 ii Rev 48 7/22/09
TABLE OF CONTENTS (continued)
T3.9 REFUELING OPERATIONS T3.9.100 Decay Time ........................................ T3.9.100-1 T3.9.101 Communications .................................... T3.9.101-1 T3.9.102 Refueling Machine ................................. T3.9.102-1 T3.9.103 Crane Travel - Spent Fuel Pool Storage Building ... T3.9.103-1 T3.9.104 Fuel Building Essential Ventilation System (FBEVS) T3.9.104-1 T3.9.200 Boron Concentration ............................... T3.9.200-1 T3.9.201 Containment Penetrations .......................... T3.9.201-1 T3.10 RADIOACTIVE EFFLUENTS T3.10.200 Liquid Holdup Tanks ............................... T3.10.200-1 T3.10.201 Explosive Gas Mixture ............................. T3.10.201-1 T3.10.202 Gas Storage Tanks ................................. T3.10.202-1 T3.11 FIRE PROTECTION T3.11.100 Fire Detection Instrumentation (formerly TS 3.3.3.7) ............................. T3.11.100-1 T3.11.101 Fire Suppression Water System (formerly TS 3.7.11.1) ............................ T3.11.101-1 T3.11.102 Spray and/or Sprinkler Systems (formerly TS 3.7.11.2) ............................ T3.11.102-1 T3.11.103 CO2 Systems (formerly TS 3.7.11.3) ................ T3.11.103-1 T3.11.104 Fire Hose Stations (formerly TS 3.7.11.4) ......... T3.11.104-1 T3.11.105 Yard Fire Hydrants and associated emergency response vehicle (formerly TS 3.7.11.5) ........... T3.11.105-1 T3.11.106 Halon Systems (formerly TS 3.7.11.6) .............. T3.11.106-1 T3.11.107 Fire-Rated Assemblies (formerly TS 3.7.12) ........ T3.11.107-1 T4.0 DESIGN FEATURES.............................................. T4.0.100-1 T5.0 ADMINISTRATIVE CONTROLS T5.0.100 Responsibility .................................... T5.0.100-1 T5.0.200 Organization ...................................... T5.0.200-1 T5.0.300 Unit Staff Qualification .......................... T5.0.300-1 T5.0.400 Procedures ........................................ T5.0.400-1 T5.0.500 Programs and Manuals .............................. T5.0.500-1 T5.0.600 Reporting Requirements ............................ T5.0.600-1 T5.0.700 High Radiation Areas .............................. T5.0.700-1 T6.0 TRM SPECIFICATION BASES...................................... T6.0.100-1 (continued)
PALO VERDE UNITS 1, 2, 3 iii Rev 33 4/20/05
TABLE OF CONTENTS (continued)
T7.0 COMPONENT LISTS T7.0.100 Remote Shutdown Disconnect Switches ............... T7.0.100-1 T7.0.200 Remote Shutdown Control Circuits .................. T7.0.200-1 T7.0.300 Containment Isolation Valves ...................... T7.0.300-1 T7.0.400 MOV Thermal Overload Protection and Bypass Devices T7.0.400-1 T7.0.500 Containment Penetration Overcurrent Prot. Devices . T7.0.500-1 Appendix TA Reactor Coolant System Pressure and Temperature Limits Report (PTLR) TA-i PALO VERDE UNITS 1, 2, 3 iv Rev 52 7/16/10
Technical Requirements Manual LIST OF EFFECTIVE PAGES Page No. Revision No. Page No. Revision No.
TOC page i 33 T3.3.103-1 51 TOC page ii 48 T3.3.103-2 54 TOC page iii 33 T3.3.103-3 13 TOC page iv 52 T3.3.103-4 13 T1.1.100-1 0 T3.3.104-1 46 T1.2.100-1 0 T3.3.104-2 0 T1.3.100-1 0 T3.3.105-1 46 T1.4.100-1 0 T3.3.105-2 48 T2.0.100-1 0 T3.3.105-3 48 T3.0.100-1 47 T3.3.106-1 46 T3.0.100-2 40 T3.3.106-2 14 T3.0.100-3 23 T3.3.107-1 0 T3.0.100-4 47 T3.3.107-2 46 T3.1.100-1 0 T3.3.108-1 0 T3.1.100-2 0 T3.3.108-2 0 T3.1.101-1 0 T3.3.200-1 46 T3.1.101-2 54 T3.3.200-2 31 T3.1.101-3 0 T3.3.201-1 0 T3.1.102-1 0 T3.4.100-1 28 T3.1.103-1 1 T3.4.101-1 0 T3.1.104-1 0 T3.4.101-2 0 T3.1.104-2 0 T3.4.101-3 0 T3.1.105-1 46 T3.4.101-4 0 T3.1.105-2 0 T3.4.102-1 0 T3.1.105-3 50 T3.4.102-2 0 T3.1.200-1 46 T3.4.103-1 53 T3.1.200-2 24 T3.4.104-1 28 T3.1.201-1 0 T3.4.104-2 0 T3.1.202-1 53 T3.4.200-1 52 T3.1.202-2 46 T3.4.201-1 46 T3.1.203-1 29 T3.4.202-1 46 T3.1.204-1 33 T3.4.203-1 46 T3.1.205-1 33 T3.4.204-1 46 T3.2.200-1 53 T3.5.200-1 46 T3.3.100-1 46 T3.5.200-2 0 T3.3.100-2 10 T3.5.200-3 0 T3.3.101-1 40 T3.5.201-1 16 T3.3.101-2 46 T3.5.201-2 47 T3.3.101-3 18 T3.5.202-1 46 T3.3.101-4 18 T3.5.202-2 39 T3.3.101-5 52 T3.5.202-3 47 T3.3.102-1 21 T3.5.202-4 0 T3.3.102-2 40 T3.5.203-1 46 PALO VERDE UNITS 1, 2, 3 1 Rev 54 1/26/11
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T3.5.203-2 35 T3.9.200-2 29 T3.6.100-1 48 T3.9.201-1 46 T3.6.100-2 0 T3.10.200-1 40 T3.6.200-1 22 T3.10.201-1 0 T3.6.200-2 22 T3.10.201-2 0 T3.6.201-1 47 T3.10.202-1 40 T3.6.300-1 48 T3.10.202-2 0 T3.6.300-2 48 T3.11.100-1 40 T3.7.100-1 27 T3.11.100-2 38 T3.7.100-2 27 T3.11.100-3 38 T3.7.101-1 46 T3.11.100-4 38 T3.7.101-2 46 T3.11.100-5 38 T3.7.102-1 0 T3.11.100-6 38 T3.7.102-2 0 T3.11.100-7 38 T3.7.102-3 0 T3.11.100-8 38 T3.7.200-1 42 T3.11.100-9 38 T3.7.200-2 53 T3.11.101-1 40 T3.7.201-1 46 T3.11.101-2 46 T3.7.202-1 46 T3.11.101-3 46 T3.7.203-1 46 T3.11.101-4 39 T3.7.204-1 46 T3.11.101-5 46 T3.7.205-1 46 T3.11.102-1 46 T3.7.205-2 46 T3.11.102-2 4 T3.7.206-1 0 T3.11.102-3 4 T3.7.207-1 46 T3.11.102-4 4 T3.8.100-1 46 T3.11.102-5 18 T3.8.100-2 0 T3.11.103-1 46 T3.8.101-1 46 T3.11.103-2 49 T3.8.101-2 40 T3.11.104-1 44 T3.8.101-3 12 T3.11.104-2 4 T3.8.101-4 0 T3.11.104-3 4 T3.8.102-1 0 T3.11.104-4 18 T3.8.102-2 0 T3.11.105-1 46 T3.8.200-1 0 T3.11.105-2 4 T3.9.100-1 0 T3.11.105-3 18 T3.9.101-1 0 T3.11.106-1 40 CORRECTED T3.9.102-1 0 T3.11.106-2 49 T3.9.102-2 0 T3.11.107-1 40 CORRECTED T3.9.103-1 0 T3.11.107-2 4 T3.9.104-1 0 T3.11.107-3 4 T3.9.104-2 0 T4.0.100-1 0 T3.9.104-3 0 T5.0.100-1 0 T3.9.200-1 46 T5.0.200-1 0 PALO VERDE UNITS 1, 2, 3 2 Rev 54 1/26/11
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T5.0.300-1 0 T6.0.100-21 53 T5.0.400-1 0 T6.0.100-22 53 T5.0.500-1 53 T6.0.100-23 53 T5.0.500-2 24 T6.0.100-24 53 T5.0.500-3 0 T6.0.100-25 53 T5.0.500-4 53 T6.0.100-26 53 T5.0.500-5 0 T6.0.100-27 53 T5.0.500-6 0 T6.0.100-28 53 T5.0.500-7 0 T6.0.100-29 53 T5.0.500-8 22 T6.0.100-30 53 T5.0.500-9 0 T6.0.100-31 53 T5.0.500-10 0 T6.0.100-32 53 T5.0.500-11 54 T6.0.100-33 53 T5.0.500-12 54 T6.0.100-34 53 T5.0.500-13 11 T6.0.100-35 53 T5.0.500-14 20 T6.0.100-36 53 T5.0.500-15 53 T6.0.100-37 53 T5.0.500-16 53 T7.0.100-1 52 T5.0.500-17 8 T7.0.100-2 52 T5.0.500-18 8 T7.0.100-3 0 T5.0.600-1 37 T7.0.200-1 52 T5.0.600-2 37 T7.0.200-2 52 T5.0.700-1 34 T7.0.200-3 0 T6.0.100-1 40 T7.0.300-1 50 T6.0.100-2 40 T7.0.300-2 41 T6.0.100-3 40 T7.0.300-3 32 T6.0.100-4 40 T7.0.300-4 43 T6.0.100-5 46 T7.0.300-5 32 T6.0.100-6 40 T7.0.300-6 32 T6.0.100-7 54 T7.0.300-7 32 T6.0.100-8 46 T7.0.300-8 32 T6.0.100-9 40 T7.0.400-1 0 T6.0.100-10 40 T7.0.400-2 0 T6.0.100-11 40 T7.0.400-3 0 T6.0.100-12 40 T7.0.400-4 51 T6.0.100-13 46 17.0.400-5 0 T6.0.100-14 46 T7.0.500-1 0 T6.0.100-15 53 TA-i 52 T6.0.100-16 53 TA-ii 52 T6.0.100-17 53 TA-iii 52 T6.0.100-18 53 TA-1 52 T6.0.100-19 53 TA-2 52 T6.0.100-20 53 TA-3 52 PALO VERDE UNITS 1, 2, 3 3 Rev 54 1/26/11
Technical Requirements Manual LIST OF EFFECTIVE PAGES Page No. Revision No. Page No. Revision No.
TA-4 52 TA-5 52 TA-6 52 TA-7 52 TA-8 52 TA-9 52 TA-10 52 TA-11 52 TA-12 52 TA-13 52 TA-14 52 TA-15 52 TA-16 52 PALO VERDE UNITS 1, 2, 3 4 Rev 54 1/26/11
Logical Connectors TRM 1.2.100 T1.0 USE AND APPLICATION 1.2 Logical Connectors Refer to PVNGS Improved Technical Specification 1.2.
Palo Verde - Units 1, 2, 3 T1.2.100-1 Rev 0 8/10/98
Completion Times TRM 1.3.100 T1.0 USE AND APPLICATION 1.3 Completion Times Refer to PVNGS Improved Technical Specification 1.3.
Palo Verde - Units 1, 2, 3 T1.3.100-1 Rev 0 8/13/98
Frequency TRM 1.4.100 T1.0 USE AND APPLICATION 1.4 Frequency Refer to PVNGS Improved Technical Specification 1.4.
Palo Verde - Units 1, 2, 3 T1.4.100-1 Rev 0 8/13/98
Safety Limits TRM 2.0.100 T2.0 Safety Limits Refer to PVNGS Improved Technical Specification 2.0.
Palo Verde - Units 1, 2, 3 T2.0.100-1 Rev 0 8/13/98
TLCO Applicability TRM 3.0.100 T3.0 TRM LIMITING CONDITION FOR OPERATION (TLCO) APPLICABILITY TLCO 3.0.100.1 TLCOs shall be met during the MODES or other specified conditions in the Applicability, except as provided in TLCO 3.0.100.2.
TLCO 3.0.100.2 Upon discovery of a failure to meet a TLCO, the Required Actions within the TRM of the associated Conditions shall be met, except as provided in TLCO 3.0.100.5.
Failure to meet a TLCO may require initiation of an operability determination to determine the impact of the failure on equipment contained within the Technical Specifications.
If the TLCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required, unless otherwise stated.
TLCO 3.0.100.3 When a TLCO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, action shall be initiated immediately to communicate the situation to the Shift Manager and document the condition in accordance with the PVNGS corrective action program. An initial decision on whether the unit can continue to operate with the condition shall be completed within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />. Further actions shall be as required by the corrective action disposition and as deemed necessary by plant management.
Exceptions to this Specification are stated in the individual Specifications.
Where corrective measures are completed that permit operation in accordance with the TLCO or ACTIONS, completion of the actions required by TLCO 3.0.100.3 is not required.
TLCO 3.0.100.3 is only applicable in MODES 1, 2, 3, and 4.
(continued)
Palo Verde - Units 1, 2, 3 T3.0.100-1 Rev 47 2/26/09
TLCO Applicability TRM 3.0.100 T3.0 TLCO APPLICABILITY (continued)
TLCO 3.0.100.4 When a TLCO is not met, entry into a MODE or other specified condition in the Applicability shall only be made:
- a. When the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time; or
- b. After performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering the MODE or other specified condition in the Applicability, and establishment of risk management actions, if appropriate; exceptions to this Specification are stated in the individual Specifications, or
- c. When an allowance is stated in the individual value, parameter, or other Specification.
This Specification shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.
TLCO 3.0.100.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to TLCO 3.0.100.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.
Palo Verde - Units 1, 2, 3 T3.0.100-2 Rev 40 2/21/07
TSR Applicability TRM 3.0.100 TRM SURVEILLANCE REQUIREMENT (TSR) APPLICABILITY TSR 3.0.100.1 TSRs shall be met during the MODES or other specified conditions in the Applicability for individual TLCOs, unless otherwise stated in the TSR. Failure to meet a TSR, whether such failure is experienced during the performance of the TSR or between performances of the TSR, may require initiation of an operability determination to determine the impact of the failure on equipment contained within the Technical Specifications. Failure to perform a TSR within the specified Frequency shall be failure to meet the TLCO except as provided in TSR 3.0.100.3. TSRs do not have to be performed on inoperable equipment or variables outside specified limits.
TSR 3.0.100.2 The specified Frequency for each TSR is met if the TSR is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.
For Frequencies specified as "once," the above interval extension does not apply.
If a Completion Time requires periodic performance on a "once per ..." basis, the above Frequency extension applies to each performance after the initial performance.
Exceptions to this Specification are stated in the individual Specifications.
TSR 3.0.100.3 If it is discovered that a TSR was not performed within its specified Frequency, then compliance with the requirement to declare the TLCO not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified Frequency, whichever is greater. This delay period is permitted to allow performance of the TSR. A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the risk impact shall be managed.
(continued)
Palo Verde - Units 1, 2, 3 T3.0.100-3 Rev 23 5/30/03
TSR Applicability TRM 3.0.100 TRM SURVEILLANCE REQUIREMENT (TSR) APPLICABILITY (continued)
TSR 3.0.100.3 If the TSR is not performed within the delay period, the (continued) TLCO must immediately be declared not met, and the applicable Condition(s) must be entered When the TSR is performed within the delay period and the Surveillance is not met, the TLCO must immediately be declared not met, and the applicable Condition(s) must be entered.
TSR 3.0.100.4 Entry into a MODE or other specified condition in the Applicability of an TLCO shall only be made when TSRs have been met within their specified Frequency, except as provided by TSR 3.0.100.3. When a TLCO is not met due to Surveillances not having been met, entry into a MODE or other Specified Condition in the Applicability shall only be made in accordance with TLCO 3.0.100.4. This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.
Palo Verde - Units 1, 2, 3 T3.0.100-4 Rev 47 2/26/09
Flow Paths - Shutdown TRM 3.1.100 T3.1 REACTIVITY CONTROL SYSTEMS T3.1.100 Flow Paths - Shutdown TLCO 3.1.100 As a minimum, one of the following boron injection flow paths shall be OPERABLE:
- a. If only the spent fuel pool in TLCO 3.1.104.a. is OPERABLE, a flow path from the spent fuel pool via a gravity feed connection and a charging pump to the Reactor Coolant System.
- b. If only the refueling water tank in Specification 3.1.104.b. is OPERABLE, a flow path from the refueling water tank via either a charging pump, a high pressure safety injection pump, or a low pressure safety injection pump to the Reactor Coolant System.
APPLICABILITY: MODES 5 and 6.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. None of the above flow A.1 Suspend CORE Immediately paths OPERABLE. ALTERATIONS AND A.2 Suspend positive Immediately reactivity changes.
PALO VERDE UNITS 1, 2, 3 T3.1.100-1 Rev 0 8/13/98
Flow Paths - Shutdown TRM 3.1.100 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.1.100.1 At least one of the above required flow 31 days paths shall be demonstrated OPERABLE 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.
PALO VERDE UNITS 1, 2, 3 T3.1.100-2 Rev 0 8/13/98
Flow Paths - Operating TRM 3.1.101 T3.1 REACTIVITY CONTROL SYSTEMS T3.1.101 Flow Paths - Operating TLCO 3.1.101 At least two of the following three boron injection flow paths shall be OPERABLE:
- a. A gravity feed flow path from either the refueling water tank or the spent fuel pool through CH-536 (RWT Gravity Feed Isolation Valve) and a charging pump to the Reactor Coolant System,
- b. A gravity feed flow path from the refueling water tank through CH-327 (RWT Gravity Feed/Safety Injection System Isolation Valve) and a charging pump to the Reactor Coolant System,
- c. A flow path from either the refueling water tank or the spent fuel pool through CH-164 (Boric Acid Filter Bypass Valve), utilizing gravity feed and a charging pump to the Reactor Coolant System.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required boron A.1 Restore the required 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> injection flow path boron injection flow inoperable. paths to OPERABLE.
(continued)
PALO VERDE UNITS 1, 2, 3 T3.1.101-1 Rev 0 8/13/98
Flow Paths - Operating TRM 3.1.101 ACTIONS (continued)
B. Required Action and B.1 Enter TLCO 3.0.100.3. Immediately associated completion time of Condition A not met.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.1.101.1 Verify that each valve (manual, power- 31 days operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
(continued)
PALO VERDE UNITS 1, 2, 3 T3.1.101-2 Rev 54 01/26/11
Flow Paths - Operating TRM 3.1.101 SURVEILLANCE REQUIREMENTS (continued)
TSR 3.1.101.2 -----------------NOTE-----------------
The provisions of TLCO 3.0.100.4 are not applicable for entry into MODE 3 or MODE 4 to perform the surveillance testing of TSR 3.1.101.2 provided the testing is performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after achieving normal operating pressure in the reactor coolant system.
Verify that the flow paths required by 18 months Specification 3.1.101 deliver at least 26 gpm for 1 charging pump and 68 gpm for two charging pumps to the Reactor Coolant System when the Reactor Coolant System is at normal operating pressure.
PALO VERDE UNITS 1, 2, 3 T3.1.101-3 Rev 0 8/13/98
Charging Pumps - Shutdown TRM 3.1.102 T3.1 REACTIVITY CONTROL SYSTEMS T3.1.102 Charging Pumps - Shutdown TLCO 3.1.102 At least one charging pump or one high pressure safety injection pump or one low pressure safety injection pump in the boron injection flow path required OPERABLE pursuant to TRM Specification 3.1.100 shall be OPERABLE and capable of being powered from an OPERABLE emergency power source.
APPLICABILITY: MODES 5 and 6.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. With no charging pump or A.1 Suspend CORE Immediately high pressure safety ALTERATIONS injection pump or low pressure safety injection AND pump OPERABLE or capable A.2 Suspend positive Immediately of being powered from an OPERABLE emergency power reactivity changes.
source.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Refer to PVNGS Improved Technical Specifications LCO 5.5.8.
PALO VERDE UNITS 1, 2, 3 T3.1.102-1 Rev 0 8/13/98
Charging Pumps - Operating TRM 3.1.103 T3.1 REACTIVITY CONTROL SYSTEMS T3.1.103 Charging Pumps - Operating TLCO 3.1.103 At least two charging pumps shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required charging A.1 Restore at least two 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> pump inoperable. charging pumps to OPERABLE status.
B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated completion time of Condition A not AND met.
B.2 Restore at least two 7 days charging pumps to OPERABLE status C. Required Action and C.1 Be in MODE 5. 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> associated Completion Time of Condition B not met.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Refer to PVNGS Improved Technical Specifications LCO 5.5.8.
PALO VERDE UNITS 1, 2, 3 T3.1.103-1 Rev 1 9/18/98
Borated Sources - Shutdown TRM 3.1.104 T3.1 REACTIVITY CONTROL SYSTEMS T3.1.104 Borated Sources - Shutdown TLCO 3.1.104 As a minimum, one of the following borated water sources shall be OPERABLE:
- a. The spent fuel pool
- b. The refueling water tank APPLICABILITY: MODES 5 and 6.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. With no borated water A.1 Suspend CORE ALTERATIONS Immediately sources OPERABLE AND A.2 Suspend positive Immediately reactivity changes.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.1.104.1 --------------------NOTE-------------------
Only required to be performed when the refueling water tank is the borated water source and the outside air temperature is outside the 60°F to 120°F range.
Verify that the refueling water tank 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> solution temperature is 60°F and 120°F.
(continued)
PALO VERDE UNITS 1, 2, 3 T3.1.104-1 Rev 0 8/13/98
Borated Sources - Shutdown TRM 3.1.104 SURVEILLANCE REQUIREMENTS (continued)
TSR 3.1.104.2 --------------------NOTE-------------------
Only required to be performed when the spent fuel pool is the borated water source and irradiated fuel is present in the pool.
Verify that the spent fuel pool solution 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> temperature is 60°F and 180°F.
TSR 3.1.104.3 Verify that the boron concentration of the 7 days borated water source is 4000 ppm and 4400 ppm.
TSR 3.1.104.4 Verify that the contained volume of the 7 days borated water source is 33,500 gallons.
PALO VERDE UNITS 1, 2, 3 T3.1.104-2 Rev 0 8/13/98
Borated Sources - Operating TRM 3.1.105 T3.1 REACTIVITY CONTROL SYSTEMS T3.1.105 Borated Sources - Operating TLCO 3.1.105 The spent fuel pool shall be OPERABLE APPLICABILITY: MODES 1, 2, 3, and 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Spent fuel pool A.1 Restore to OPERABLE 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable. status.
B. Required Action and B.1 Enter TLCO 3.0.100.3 Immediately associated completion time of Condition A not met.
Palo Verde - Units 1, 2, 3 T3.1.105-1 Rev 46 1/8/09
Borated Sources - Operating TRM 3.1.105 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.1.105.1 --------------------NOTE-------------------
Only required to be performed when irradiated fuel is present in the pool.
Verify spent fuel pool solution temperature 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is 60°F and 180°F.
TSR 3.1.105.2 Verify spent fuel pool borated water volume 7 days is greater than or equal to the minimum required volume in Figure 3.1.105-1.
TSR 3.1.105.3 Verify that the spent fuel pool boron 7 days concentration is 4000 ppm and 4400 ppm.
Palo Verde - Units 1, 2, 3 T3.1.105-2 Rev 0 8/13/98
Borated Sources - Operating TRM 3.1.105 FIGURE 3.1.105-1.
Minimum Borated Water Volume Palo Verde - Units 1, 2, 3 T3.1.105-3 Rev 50 12/10/09
Shutdown Margin - Reactor Trip Breakers Closed TRM 3.1.200 T3.1 REACTIVITY CONTROL SYSTEMS T3.1.200 Shutdown Margin - Reactor Trip Breakers Closed TLCO 3.1.200 Refer to PVNGS Improved Technical Specification 3.1.2.
APPLICABILITY: Refer to PVNGS Improved Technical Specification 3.1.2.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of TSR A.1 Document the condition Immediately 3.1.200.1 not met. in accordance with the PVNGS corrective action program and initiate an operability determination, as necessary, to determine the impact on equipment in the technical specifications.
Palo Verde - Units 1, 2, 3 T3.1.200-1 Rev 46 1/8/09
Shutdown Margin - Reactor Trip Breakers Closed TRM 3.1.200 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.1.200.1 With the reactor trip breakers closed and the CEA drive system capable of CEA withdrawal, the SHUTDOWN MARGIN shall be determined to be greater than or equal to that specified in the CORE OPERATING LIMITS REPORT by:
- a. Verifying that the predicted critical Prior to CEA position is within the limits of achieving PVNGS ITS LCO 3.1.7. reactor criticality
- b. Comparison of the SHUTDOWN MARGIN Prior to initial consideration factors with the CEA operation above groups at the Transient Insertion Limits 5% RATED THERMAL of PVNGS ITS LCO 3.1.7. POWER after each fuel loading Palo Verde - Units 1, 2, 3 T3.1.200-2 Rev 24 7/25/03
TRM 3.1.201 TRM specification number 3.1.201 is not utilized and this page is intentionally left blank.
Palo Verde - Units 1, 2, 3 T3.1.201-1 Rev 0 8/13/98
Control Element Assembly - Alignment TRM 3.1.202 T3.1 REACTIVITY CONTROL SYSTEMS T3.1.202 Control Element Assembly - Alignment TLCO 3.1.202 At least one CEA Reed Switch Position Transmitter indicator channel shall be OPERABLE for each shutdown, regulating or part strength CEA not fully inserted.
APPLICABILITY: MODES 3, 4, and 5 (with the reactor trip breakers closed).
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Less than the above A.1 Enter TLCO 3.0.100.3 Immediately required position indicator channels(s)
OPERABLE in MODES 3 or 4.
B. Less than the above B.1 Action shall be Immediately required position initiated immediately indicator channel(s) to communicate the OPERABLE in MODE 5 situation to the Shift Manager and document the condition in accordance with the PVNGS corrective action program. An initial decision on whether the unit can continue (continued)
Palo Verde - Units 1, 2, 3 T3.1.202-1 Rev 53 11/10/10
Control Element Assembly - Alignment TRM 3.1.202 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME to operate with the condition shall be completed within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />. Further actions shall be as required by the corrective action disposition and as deemed necessary by plant management.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.1.202.1 --------------------NOTE-------------------
TSR 3.1.202.1 has a different applicability than ITS SR 3.1.5.4 Perform a CHANNEL FUNCTIONAL TEST of each 18 months reed switch position transmitter channel.
Palo Verde - Units 1, 2, 3 T3.1.202-2 Rev 46 1/8/09
Control Element Assembly - Drop Time TRM 3.1.203 T3.1 REACTIVITY CONTROL SYSTEMS T3.1.203 Control Element Assembly - Drop Time TLCO 3.1.203 The individual full strength (shutdown and regulating) CEA drop time, from a fully withdraw position, shall be 4 seconds. Time is measured from when the electrical power is interrupted to the CEA drive mechanism until the CEA reaches its 90% insertion position with:
- Tcold greater than or equal to 550 degrees F
- All reactor coolant pumps operating APPLICABILITY: MODES 1 and 2.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Drop time exceeds limit. A.1. Restore to within Prior to limit. proceeding to MODE 1 or 2.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY
NOTE------
TSR 3.1.203.1 Verify that the full strength CEA drop Refer to PVNGS time is 4.0 seconds for specifically ITS SR 3.1.5.5 affected individual CEAs. ----------------
Following any maintenance on or modification to the CEA drive system which could affect the drop time of those specific CEAs.
Palo Verde - Units 1, 2, 3 T3.1.203-1 Rev 29 4/15/04
Shutdown CEA Insertion Limits TRM 3.1.204 T3.1 REACTIVITY CONTROL SYSTEMS T3.1.204 Shutdown Control Element Assembly (CEA) Insertion Limits TLCO 3.1.204 All Shutdown CEAs shall be fully withdrawn to 147.75 inches by Pulse Counter Indication and 145.25 inches by Reed Switch Position Transmitter Indication (RSPT).
APPLICABILITY: MODES 1 and 2
NOTE----------------------------
This TLCO is not applicable while performing SR 3.1.5.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One shutdown CEA not A.1 Restore shutdown CEA to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> within limit. within limit.
B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.1.204.1 Verify each shutdown CEA is fully 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> withdrawn to 147.75 inches by Pulse Counter Indication and 145.25 inches by Reed Switch Position Transmitter Indication (RSPT).
Palo Verde - Units 1, 2, 3 T3.1.204-1 Rev 33 4/20/05
Regulating CEA Insertion Limits TRM 3.1.205 T3.1 REACTIVITY CONTROL SYSTEMS T3.1.205 Regulating Control Element Assembly (CEA) Groups Insertion Limits TLCO 3.1.205 Regulating Groups 1 and 2 CEAs shall be limited to the insertion limits specified in the COLR.
APPLICABILITY: MODES 1 and 2
NOTE-----------------------------
This TLCO is not applicable while performing SR 3.1.5.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One Regulating Group A.1 Restore Regulating Group 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 1 or 2 CEA not within 1 or 2 CEA to within limit. limit.
B. Required Action and B.1 Enter TLCO 3.0.100.3 Immediately associated completion time not met.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.1.205.1 Verify each Regulating Group 1 & 2 CEA 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is fully withdrawn as specified in the COLR.
Palo Verde - Units 1, 2, 3 T3.1.205-1 Rev 33 4/20/05
Azimuthal Power Tilt - Tq TRM 3.2.200 T3.2 POWER DISTRIBUTION LIMITS T3.2.200 Azimuthal Power Tilt - Tq TLCO 3.2.200 Refer to PVNGS Improved Technical Specifications LCO 3.2.3 APPLICABILITY: Refer to PVNGS Improved Technical Specifications LCO 3.2.3 ACTIONS
NOTE-------------------------------------
Refer to PVNGS Improved Technical Specifications LCO 3.2.3 for additional requirements.
CONDITION REQUIRED ACTION COMPLETION TIME
NOTE------------- A.1 Verify that the 30 minutes Condition A is due to a Core Operating misalignment of either a part Limit Supervisory strength or full strength CEA. system (COLSS)
(When COLSS is being used to A. Measured Tq not within the monitor the core limit in the COLR with power distribution COLSS in service. per PVNGS Improved Technical OR Specifications 3.2.1 and 3.2.4) is Measured Tq > 0.03 with detecting the COLSS out of service misalignment.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Refer to PVNGS Improved Technical Specifications LCO 3.2.3.
Palo Verde - Units 1, 2, 3 T3.2.200-1 Rev 53 11/10/10
Supplementary Protection System Instrumentation TRM 3.3.100 T3.3 INSTRUMENTATION T3.3.100 Supplementary Protection System (SPS) Instrumentation TLCO 3.3.100 Three RPS Supplementary Protection System (Pressurizer Pressure - High) channels shall be OPERABLE.
APPLICABILITY: MODES 1 and 2.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One of the required SPS A.1 Restore an inoperable 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> trip channels channel to OPERABLE inoperable. status B. Required Action and B.1 Enter TLCO 3.0.100.3 Immediately associated Completion Time not met.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.3.100.1 Perform a CHANNEL CHECK on each channel. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> TSR 3.3.100.2 Perform a CHANNEL FUNCTIONAL TEST with 92 days setpoint allowable value 2414 psia.
(continued)
PALO VERDE UNITS 1, 2, 3 T3.3.100-1 Rev 46 1/8/09
Supplementary Protection System Instrumentation TRM 3.3.100 SURVEILLANCE REQUIREMENTS (continued)
TSR 3.3.100.3 Perform a CHANNEL CALIBRATION on each 18 months channel.
TSR 3.3.100.4 Verify RPS RESPONSE TIME is within limits. 18 months on a STAGGERED TEST BASIS.
PALO VERDE UNITS 1, 2, 3 T3.3.100-2 Rev 10 9/28/00
Radiation Monitoring Instrumentation TRM 3.3.101 T3.3 INSTRUMENTATION T3.3.101 Radiation Monitoring Instrumentation TLCO 3.3.101 The Radiation Monitoring Instrumentation shall be OPERABLE with the minimum number of channels according to Table 3.3.101-1.
APPLICABILITY: According to Table 3.3.101-1 ACTIONS
NOTE--------------------------------------
The provisions of Specification 3.0.100.3 are not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more radiation A.1 Adjust the setpoint(s) 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> monitoring channel to within the limit.
alarm/trip setpoint(s) exceed the value shown in Table 3.3.101-1 B. Required Action and B.1 Declare the channel Immediately associated Completion inoperable.
Time not met.
(continued)
PALO VERDE UNITS 1, 2, 3 T3.3.101-1 Rev 40 2/21/07
Radiation Monitoring Instrumentation TRM 3.3.101 ACTIONS (continued)
C. Main Steam Line Area C.1 Restore the inoperable 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> channels inoperable. channel(s) to OPERABLE status.
OR C.2.1 Initiate the 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> preplanned alternative program to monitor the appropriate parameter(s).
AND C.2.2 Initiate a corrective In accordance action to evaluate the with the PVNGS action taken, the corrective action cause of the program.
inoperability, and plans and schedule for restoring the channel to OPERABLE status.
(continued)
PALO VERDE UNITS 1, 2, 3 T3.3.101-2 Rev 46 1/8/09
Radiation Monitoring Instrumentation TRM 3.3.101 ACTIONS (continued)
D. New Fuel Area Monitor D.1 Perform area surveys Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> RU-19 channel of the monitored area inoperable. with portable monitoring instrumentation.
PALO VERDE UNITS 1, 2, 3 T3.3.101-3 Rev 18 3/13/02
Radiation Monitoring Instrumentation TRM 3.3.101 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.3.101.1 Perform a CHANNEL CHECK on the New Fuel 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Area monitor, and Main Steam Line monitors.
TSR 3.3.101-2 Deleted TSR 3.3.101.3 Perform a CHANNEL FUNCTIONAL TEST on the 92 days New Fuel Area monitor and Main Steam Line monitors and verify that their setpoints meet the requirements of Table 3.3.101-1.
TSR 3.3.101.4 Perform a CHANNEL CALIBRATION. 18 months PALO VERDE UNITS 1, 2, 3 T3.3.101-4 Rev 18 3/13/02
Radiation Monitoring Instrumentation TRM 3.3.101 Table 3.3.101-1 (Page 1 of 1)
Radiation Monitoring Instrumentation Radiation Monitoring Applicable Minimum Alarm/Trip Measurement Instrument MODES Channels Setpoint Range OPERABLE Area Monitor RU-19 (New With fuel 1 15 mR/hr 10 E-1 to Fuel Area) in the 10 E4 mR/hr storage pool or building Main Steam Line Area 1,2,3,4 1 Three (3) 1.5 E0 to Monitors RU-139 A & B times 1.0 E7 background mR/hr in Rem/hr Main Steam Line Area 1,2,3,4 1 Three (3) 1.5 E0 to Monitors RU-140 A & B times 1.0 E7 background mR/hr in Rem/hr PALO VERDE UNITS 1, 2, 3 T3.3.101-5 Rev 52 7/16/10
Incore Detectors TRM 3.3.102 T3.3 INSTRUMENTATION T3.3.102 Incore Detectors TLCO 3.3.102 The Incore Detection System shall be OPERABLE with:
- a. 75% of incore locations, and
- b. 75% of all incore detectors with at least one incore detector in each quadrant at each level, and
- c. Sufficient OPERABLE incore detectors to perform at least six tilt estimates with at least one tilt estimate at each of three levels.
NOTE------------------------------
- 1. The Incore Detection System contains 50 incore locations with 5 detectors in each fixed detector string.
- 2. An OPERABLE incore location consists of a fixed detector string with a minimum of three OPERABLE rhodium detectors.
APPLICABILITY: When the Incore Detection System is used for monitoring:
- a. AZIMUTHAL POWER TILT,
- b. Radial Peaking Factors,
- c. Local Power Density,
- d. DNB Margin PALO VERDE UNITS 1, 2, 3 T3.3.102-1 Rev 21 1/31/03
Incore Detectors TRM 3.3.102 ACTIONS
NOTE--------------------------------------
The provisions of Specification 3.0.100.3 are not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. Incore Detection System A.1 Do not use the Incore Immediately inoperable. Detection System for monitoring or calibration functions.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.3.102.1 Perform a CHANNEL CHECK. Within 7 days prior to use TSR 3.3.102.2 ------------------NOTE-------------------
Neutron Detectors may be excluded from the CHANNEL CALIBRATION but all electronic components shall be included. Fixed incore neutron detectors shall be calibrated prior to installation in the reactor core.
Perform a CHANNEL CALIBRATION. 18 months PALO VERDE UNITS 1, 2, 3 T3.3.102-2 Rev 40 2/21/07
Seismic Monitoring TRM 3.3.103 T3.3 INSTRUMENTATION T3.3.103 Seismic Monitoring TLCO 3.3.103 The Seismic Monitoring Instrumentation shown in Table 3.3.103-1 shall be OPERABLE.
APPLICABILITY: At all times.
ACTIONS
NOTE------------------------------------
The provisions of Specification 3.0.100.3 are not applicable CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore the required 30 days Seismic Monitoring instrumentation to Instruments of Table OPERABLE status.
3.3.103-1 inoperable.
B. Required Action and B.1 Initiate a corrective In accordance associated completion action to evaluate the with the PVNGS time of Condition A not action taken, cause of corrective met. the inoperability, and action program.
plans for restoring the instrument to OPERABLE status.
(continued)
PALO VERDE UNITS 1, 2, 3 T3.3.103-1 Rev 46 1/8/09
Seismic Monitoring TRM 3.3.103 ACTIONS (continued)
C. Seismic event ( 0.02g) C.1 Perform TSR 3.3.103.2 5 days on each seismic monitoring instrument actuated AND C.2 Retrieve data from Immediately actuated instruments and perform analysis to determine the magnitude of the vibratory ground motion.
AND C.3 Initiate a corrective In accordance action to evaluate the with the PVNGS magnitude, frequency corrective spectrum, and action program.
resultant effect upon facility features important to safety.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.3.103.1 -------------------NOTE------------------
Applicable to Digital Recorders of Table 3.3.103-1 only.
Perform a CHANNEL CHECK. 31 days (continued)
PALO VERDE UNITS 1, 2, 3 T3.3.103-2 Rev 54 1/26/11
Seismic Monitoring TRM 3.3.103 SURVEILLANCE REQUIREMENTS (continued)
TSR 3.3.103.2 Perform a CHANNEL FUNCTIONAL TEST. 6 months TSR 3.3.103.3 Perform a CHANNEL CALIBRATION. 18 months PALO VERDE UNITS 1, 2, 3 T3.3.103-3 Rev 13 4/6/01
Seismic Monitoring TRM 3.3.103 Table 3.3.103-1 (Page 1 of 1)
Seismic Monitoring Instrumentation INSTRUMENTS AND SENSOR LOCATIONS MINIMUM INSTRUMENTS OPERABLE
- 1. Force Balance Accelerometer Unit
- a. Tendon Gallery Floor, 55 level 1 Trigger Threshold Setpoint: 0.010 g
- b. Containment Building floor, 140 level 1 Trigger Threshold Setpoint: 0.020 g
- c. Containment Building floor, 80 level 1 Trigger Threshold Setpoint: 0.020 g
- d. Control Building floor, 74 level 1 Trigger Threshold Setpoint: 0.010 g
- e. Control Building floor, 160 level 1 Trigger Threshold Setpoint: 0.020 g
- f. 25 E. of Turbine Bldg. W. side x 189 1 9 S. of Turbine Bldg. S. Side on ground (Ref. Plant N.)
Trigger Threshold Setpoint: 0.010 g
- 2. Digital Recorders:
- a. Control Room Area, 140 level 1
- b. Control Room Area, 140 level 1
- c. Control Room Area, 140 level 1
- d. Control Room Area, 140 level 1
- e. Control Room Area, 140 level 1
- f. Control Room Area, 140 level 1 PALO VERDE UNITS 1, 2, 3 T3.3.103-4 Rev 13 4/6/01
Meteorological Instrumentation TRM 3.3.104 T3.3 INSTRUMENTATION T3.3.104 Meteorological Instrumentation TLCO 3.3.104 The meteorological monitoring instrumentation channels shown in Table 3.3.104-1 shall be OPERABLE.
APPLICABILITY: At all times.
ACTIONS
NOTE--------------------------------------
The provisions of Specification 3.0.100.3 are not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore the channels 7 days meteorological to OPERABLE status.
monitoring channels inoperable.
B. Required Action and B.1 Initiate a corrective In accordance associated completion action to evaluate the with the PVNGS time not met. cause of the corrective malfunction and the action program.
plans for restoring the channel(s) to OPERABLE status.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.3.104.1 Perform a CHANNEL CHECK 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
NOTE------------------
Windspeed Sensors are excluded from CHANNEL CALIBRATION.
TSR 3.3.104.2 Perform a CHANNEL CALIBRATION 6 months PALO VERDE UNITS 1, 2, 3 T3.3.104-1 Rev 46 1/8/09
Meteorological Instrumentation TRM 3.3.104 Table 3.3.104-1 (Page 1 of 1)
Meteorological Monitoring Instrumentation INSTRUMENT LOCATION MINIMUM OPERABLE
- 1. WIND SPEED
- a. 01 to 50 mph Nominal Elev. 35 feet 1
- b. 01 to 50 mph Nominal Elev. 200 feet 1
- 2. WIND DIRECTION
- a. 0° - 360° - 180° Nominal Elev. 35 feet 1
- b. 0° - 360° - 180° Nominal Elev. 200 feet 1
- 3. AIR TEMPERATURE - DELTA T
- a. -6°F to 6°F Nominal Elev. 35 feet - 200 feet 1
NOTE-------------------------------------
- 1. Wind speeds less than 0.6 MPH will be reported as 0.
PALO VERDE UNITS 1, 2, 3 T3.3.104-2 Rev 0 8/13/98
Post Accident Monitoring Instrumentation TRM 3.3.105 T3.3 INSTRUMENTATION T3.3.105 Post Accident Monitoring Instrumentation TLCO 3.3.105 The post-accident monitoring instrumentation channels shown in Table 3.3.105-1 shall be OPERABLE.
APPLICABILITY: MODES 1, 2 and 3.
ACTIONS
NOTE-----------------------------------
Separate Condition entry is allowed for each Function.
CONDITION REQUIRED ACTION COMPLETION TIME A. With the number of A.1 Restore the inoperable 30 days OPERABLE channels one channel(s) to OPERABLE less than the Required status.
number of Channels in Table 3.3.105-1.
B. Required Action and B.1 Document the condition Immediately associated completion in accordance with the time not met. PVNGS corrective action program and initiate an operability determination, as necessary, to determine the impact on equipment in the technical specifications.
C. With the number of C.1 Restore the inoperable 7 days OPERABLE channels two channel(s) to OPERABLE less than the Required status.
number of Channels in Table 3.3.105-1.
(continued)
PALO VERDE UNITS 1, 2, 3 T3.3.105-1 Rev 46 1/8/09
Post Accident Monitoring Instrumentation TRM 3.3.105 ACTIONS (continued)
D. Required Action and D.1 Document the condition Immediately associated completion in accordance with the time not met. PVNGS corrective action program and initiate an operability determination, as necessary, to determine the impact on equipment in the technical specifications.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.3.105.1 Perform a CHANNEL CHECK for each required 31 days instrumentation channel that is normally energized.
TSR 3.3.105.2 Perform a CHANNEL CALIBRATION 18 months PALO VERDE UNITS 1, 2, 3 T3.3.105-2 Rev 48 7/22/09
Post Accident Monitoring Instrumentation TRM 3.3.105 Table 3.3.105-1 (Page 1 of 1)
Post-Accident Monitoring Instrumentation FUNCTION REQUIRED NUMBER OF CHANNELS
- 1. Refueling Water Storage Tank Water 2 Level
- 2. Auxiliary Feedwater Flow Rate 2
- 3. Pressurizer Safety Valve Position 1 per valve Indicator
- 4. Containment Water Level (Narrow 2 Range)
- 5. Containment Hydrogen Monitor 2 PALO VERDE UNITS 1, 2, 3 T3.3.105-3 Rev 48 7/22/09
Loose-Part Detection Instrumentation TRM 3.3.106 T3.3 INSTRUMENTATION T3.3.106 Loose-Part Detection Instrumentation TLCO 3.3.106 The loose-part detection system shall be OPERABLE with all sensors specified in Table 3.3.106-1.
APPLICABILITY: MODES 1 and 2.
ACTIONS
NOTE--------------------------------------
The provisions of Specification 3.0.100.3 are not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. With one or more loose- A.1 Restore the inoperable 30 days part detection system channel(s) to OPERABLE channels inoperable. status.
B. Required Action and B.1 Initiate a corrective In accordance associated completion action to evaluate the with the PVNGS time not met. cause of the corrective malfunction and the action program.
plans for restoring the channel(s) to OPERABLE status.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.3.106.1 Perform a CHANNEL CHECK. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> TSR 3.3.106.2 Perform a CHANNEL FUNCTIONAL TEST 31 days TSR 3.3.106.3 Perform a CHANNEL CALIBRATION 18 months PALO VERDE UNITS 1, 2, 3 T3.3.106-1 Rev 46 1/8/09
Loose-Part Detection Instrumentation TRM 3.3.106 Table 3.3.106-1 (Page 1 of 1)
Loose Parts Sensor Locations INSTRUMENT LOOSE PARTS SENSOR LOCATIONS NUMBER JSVNYE-1 Upper Vessel A JSVNYE-2 Upper Vessel B JSVNYE-3 Lower Vessel A (Incore Nozzle)
JSVNYE-4 Lower Vessel B (Incore Nozzle)
JSVNYE-5 SG-1A JSVNYE-6 SG-1B JSVNYE-7 SG-2A JSVNYE-8 SG-2B PALO VERDE UNITS 1, 2, 3 T3.3.106-2 Rev 14 5/4/01
Explosive Gas Monitoring System TRM 3.3.107 T3.3 INSTRUMENTATION T3.3.107 Explosive Gas Monitoring System TLCO 3.3.107 Two explosive gas monitoring instrumentation Oxygen Monitoring channels shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of T3.10.201 are not exceeded. This includes the following instruments:
- a. Oxygen monitor (surge tank)
APPLICABILITY: During Gaseous Radwaste System Operation.
ACTIONS
NOTE--------------------------------------
The provisions of Specification 3.0.100.3 are not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. Explosive gas monitoring A.1 Declare the channel Immediately instrumentation channel inoperable.
alarm/trip setpoint less conservative than required.
B. One required channel B.1. Obtain and analyze grab Daily inoperable samples.
AND B.2 Restore the inoperable 30 days channel to OPERABLE status (continued)
PALO VERDE UNITS 1, 2, 3 T3.3.107-1 Rev 0 8/13/98
Explosive Gas Monitoring System TRM 3.3.107 ACTIONS (continued)
C. Required Action and C.1 Initiate a corrective In accordance associated Completion action to evaluate why with the PVNGS Time of Condition B not this inoperability was corrective met. not corrected in a action program.
timely manner.
D. Two channels inoperable D.1 Obtain and analyze grab Every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> samples. during degassing operations AND Daily during other operations SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.3.107.1 Perform a CHANNEL CHECK. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> TSR 3.3.107.2 Perform a CHANNEL FUNCTIONAL TEST. 31 days TSR 3.3.107.3 Perform a CHANNEL CALIBRATION1 on each 92 days channel
NOTE-------------------------------------
The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:
PALO VERDE UNITS 1, 2, 3 T3.3.107-2 Rev 46 1/8/09
Fuel Building Essential Ventilation Actuation Signal (FBEVAS)
TRM 3.3.108 T3.3 INSTRUMENTATION T3.3.108 Fuel Building Essential Ventilation Actuation Signal (FBEVAS)
TLCO 3.3.108 One FBEVAS channel shall be OPERABLE.
APPLICABILITY: During movement of irradiated fuel in the fuel building.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Actuation Logic, Manual A.1 Place one OPERABLE Fuel Immediately Trip or radiation monitor Building Essential inoperable. Ventilation train in operation.
OR A.2 Suspend movement of Immediately irradiated fuel assemblies in the fuel building.
PALO VERDE UNITS 1, 2, 3 T3.3.108-1 Rev 0 8/13/98
Fuel Building Essential Ventilation Actuation Signal (FBEVAS)
TRM 3.3.108 SURVEILLANCE REQUIREMENTS
NOTE---------------------------------------
Surveillance Requirements for RU-145 are specified in the ODCM.
SURVEILLANCE FREQUENCY TSR 3.3.108.1 Perform a CHANNEL CHECK on RU-31. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> TSR 3.3.108.2 Perform a CHANNEL FUNCTIONAL TEST on RU-31 92 days to include that the setpoint is 15 mR/hr and the measurement range is 10E-1 to 10E+4 mR/hr.
TSR 3.3.108.3 --------------------NOTE-------------------
Testing of Actuation Logic shall include verification of the proper operation of each actuation relay.
Perform a CHANNEL FUNCTIONAL TEST on 18 months required FBEVAS Actuation Logic channel.
TSR 3.3.108.4 Perform a CHANNEL FUNCTIONAL TEST on 18 months required FBEVAS Manual Trip logic.
TSR 3.3.108.5 Perform a CHANNEL CALIBRATION on RU-31. 18 months PALO VERDE UNITS 1, 2, 3 T3.3.108-2 Rev 0 8/13/98
RPS Instrumentation - Operating TRM 3.3.200 T3.3 INSTRUMENTATION T3.3.200 RPS Instrumentation - Operating TLCO 3.3.200 Refer to PVNGS Improved Technical Specifications 3.3.1.
APPLICABILITY: Refer to PVNGS Improved Technical Specifications 3.3.1.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more core A.1 Perform CHANNEL 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> protection calculator FUNCTIONAL TEST on (CPC) channels with a affected CPC(s).
valid cabinet high temperature alarm. AND A.2 Perform CHANNEL FUNCTIONAL TEST on 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> affected CEACs.
B. Requirements of Condition B.1 Document the condition Immediately A or the following NOTE in accordance with the not met. PVNGS corrective action program and initiate an operability determination, as necessary, to determine the impact on equipment in the technical specifications.
PALO VERDE UNITS 1, 2, 3 T3.3.200-1 Rev 46 1/8/09
RPS Instrumentation - Operating TRM 3.3.200 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY
NOTE-------------------------------------
When performing ITS SR 3.3.1.4, between 20% and 80% of RATED THERMAL POWER, compare the linear power level, the CPC delta T power and the CPC nuclear power signals to the calorimetric calculation, and:
- a. If any signal is within -0.5% to 10% of the calorimetric then do not calibrate except as required during initial power ascension after refueling and except as otherwise noted in item d.
- b. If any signal is less than the calorimetric calculation by more than 0.5%, then adjust the affected signals(s) to agree with the calorimetric calculation.
- c. If any signal is greater than the calorimetric calculation by more than 10%, then adjust the affected signal(s) to agree with the calorimetric calculation within 8% to 10%.
- d. During any power ascension from below 80% to above 80% RTP, the calibration requirements of ITS SR 3.3.1.4 must be met (except during PHYSICS TESTS, as allowed by the Note in SR 3.3.1.4). This is accomplished by performing SR 3.3.1.4 between 75% and 80% RTP during power ascension with an acceptance criteria of -0.5% to <2% to bound the requirements for both below and above 80% RTP.
PALO VERDE UNITS 1, 2, 3 T3.3.200-2 Rev 31 6/15/04
ESFAS Logic and Manual Trip TRM 3.3.201 T3.3 INSTRUMENTATION T3.3.201 ESFAS Logic and Manual Trip TLCO 3.3.201 Refer to PVNGS Improved Technical Specifications 3.3.6.
APPLICABILITY: Refer to PVNGS Improved Technical Specifications 3.3.6.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Two or more ESFAS A.1 Perform an evaluation to In accordance subgroup relay determine the adequacy of with the PVNGS failures per unit in the interval for SR 3.3.6.2. corrective a 12 month period. The evaluation should action program.
consider the design, maintenance, and testing of all ESFAS subgroup relays.
If it is determined that the SR interval is inadequate for detecting a single relay failure, the SR interval should be decreased. The revised interval should be such that an ESFAS subgroup relay failure can be detected prior to occurrence of a second failure.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Refer to PVNGS Improved Technical Specification 3.3.6 PALO VERDE UNITS 1, 2, 3 T3.3.201-1 Rev 0 8/13/98
Auxiliary Spray System TRM 3.4.100 T3.4 REACTOR COOLANT SYSTEM (RCS)
T3.4.100 Auxiliary Spray System TLCO 3.4.100 Both auxiliary spray valves shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One auxiliary spray valve A.1 Restore valve to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable. OPERABLE status.
B. Both auxiliary spray B.1 Restore at least one 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> valves inoperable. valve to OPERABLE status.
C. Required Action and C.1 Enter TLCO 3.0.100.3 Immediately associated completion time of condition A or B not met.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.4.100.1 Verify that power is available to each 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> auxiliary spray valve.
TSR 3.4.100.2 Verify CH-HV-524 and CH-HV-532 are locked 31 days open.
TSR 3.4.100.3 Cycle the auxiliary spray valves. 18 months PALO VERDE UNITS 1, 2, 3 T3.4.100-1 Rev 28 3/26/04
RCS Chemistry TRM 3.4.101 T3.4 Reactor Coolant System (RCS)
T3.4.101 RCS Chemistry TLCO 3.4.101 The Reactor Coolant System chemistry shall be maintained within the limits specified in Table 3.4.101-1.
APPLICABILITY: At all times.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ----------NOTE----------- A.1 Restore the parameter 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Condition A is applicable to within its Steady during MODES 1, 2, 3, and State Limit.
4 only.
One or more chemistry parameter in excess of its Steady State Limit but within its Transient Limit while in MODES 1, 2, 3, and 4.
B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A not AND met.
B.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> OR One or more chemistry parameters in excess of its Transient Limit while in MODES 1, 2, 3, and 4.
(continued)
PALO VERDE UNITS 1, 2, 3 T3.4.101-1 Rev 0 8/13/98
RCS Chemistry TRM 3.4.101 ACTIONS (continued)
C. ----------NOTE----------- C.1 Restore the parameter 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Condition C is applicable to within its Steady at all times other than State Limit.
during MODES 1, 2, 3 and 4.
Concentration of either chloride or fluoride in the Reactor Coolant System in excess of its Steady State Limit D. Required Action and D.1 Reduce the pressurizer Immediately associated Completion pressure to 500 Time of Condition C not psia, if applicable.
met.
AND OR D.2 Perform an engineering In accordance Concentration of either evaluation to with the PVNGS chloride or fluoride in determine the effects corrective the Reactor Coolant of the out-of-limit action program System in excess of its condition on the Transient Limit while structural integrity other than during MODES of the Reactor Coolant 1, 2, 3 and 4. System.
AND D.3 Determine that the Prior to Reactor Coolant System increasing the remains acceptable for pressurizer continued operation. pressure above 500 psia or prior to proceeding to MODE 4.
PALO VERDE UNITS 1, 2, 3 T3.4.101-2 Rev 0 8/13/98
RCS Chemistry TRM 3.4.101 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.4.101.1 The Reactor Coolant System chemistry shall 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> be determined to be within the limits by sample and analysis of those parameters specified in Table 3.4.101-1.
PALO VERDE UNITS 1, 2, 3 T3.4.101-3 Rev 0 8/13/98
RCS Chemistry TRM 3.4.101 Table 3.4.101-1 (Page 1 of 1)
RCS Chemistry Limits Surveillance Limits.
PARAMETER STEADY STATE LIMIT TRANSIENT LIMIT Dissolved Oxygen1 0.10 ppm 1.00 ppm Chloride 0.15 ppm 1.50 ppm Fluoride 0.10 ppm 1.00 ppm
NOTE-------------------------------------
- 1. Limits for Dissolved Oxygen are not applicable with Tcold 250°F.
PALO VERDE UNITS 1, 2, 3 T3.4.101-4 Rev 0 8/13/98
Pressurizer Heatup and Cooldown Limits TRM 3.4.102 T3.4 REACTOR COOLANT SYSTEM (RCS)
T3.4.102 Pressurizer Heatup and Cooldown Limits TLCO 3.4.102 The pressurizer temperature shall be limited to:
- a. A maximum heatup rate of 200°F per hour, and
- b. A maximum cooldown rate of 200°F per hour.
APPLICABILITY: At all times.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Pressurizer temperature A.1 Restore temperature to 30 minutes limits in excess of within limits.
specified values.
AND A.2 Perform an engineering In accordance evaluation to determine with the PVNGS the effects of the out- corrective of-limit condition on action program.
the structural integrity of the pressurizer AND A.3 Determine pressurizer In accordance remains acceptable for with the PVNGS continued operation. corrective action program.
(continued)
PALO VERDE UNITS 1, 2, 3 T3.4.102-1 Rev 0 8/13/98
Pressurizer Heatup and Cooldown Limits TRM 3.4.102 ACTIONS (continued)
B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A not AND met.
B.2 Reduce pressurizer 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> pressure to < 500 psig.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.4.102.1 --------------------NOTE--------------------
Only required to be performed during pressurizer heatup and cooldown operations.
Verify that pressurizer heatup and cooldown 30 minutes rates are within the specified limits:
TSR 3.4.102.2 The spray water temperature differential Each cycle of shall be determined for use. main spray when less than 4 reactor coolant pumps are operating and for each cycle of auxiliary spray operation.
PALO VERDE UNITS 1, 2, 3 T3.4.102-2 Rev 0 8/13/98
Structural Integrity TRM 3.4.103 This Page Intentionally Left Blank PALO VERDE UNITS 1, 2, 3 T3.4.103-1 Rev 53 11/10/10
RCS Vents (Reactor Head Vents)
TRM 3.4.104 T3.4 REACTOR COOLANT SYSTEM (RCS)
T3.4.104 RCS Vents (Reactor Head Vents)
TLCO 3.4.104 Four reactor vessel head vent paths shall be OPERABLE.
APPLICABILITY: MODES 1, 2, and 3 MODE 4 with RCS pressure 385 psia.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Two or three required A.1 Restore required vent 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> reactor vessel head vent path(s) to OPERABLE paths inoperable. status.
B. All reactor vessel head B.1 Restore at least one 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> vent paths inoperable. path to OPERABLE status.
C. Required Action and C.1 Enter TLCO 3.0.100.3 Immediately associated Completion Time of Condition A or B not met.
PALO VERDE UNITS 1, 2, 3 T3.4.104-1 Rev 28 3/26/04
RCS Vents (Reactor Head Vents)
TRM 3.4.104 SURVEILLANCE REQUIREMENTS
NOTE-------------------------------------
Perform TSR 3.4.104.1, TSR 3.4.104.2 and TSR 3.4.104.3 when in MODE 5 or 6.
SURVEILLANCE FREQUENCY TSR 3.4.104.1 Verify all manual isolation valves in each 18 months vent path are locked in the open position.
TSR 3.4.104.2 Cycle each vent valve through at least one 18 months complete cycle from the control room.
TSR 3.4.104.3 Verify flow through the reactor coolant 18 months system vent paths during venting.
PALO VERDE UNITS 1, 2, 3 T3.4.104-2 Rev 0 8/13/98
RCS Pressure and Temperature (P/T) Limits TRM 3.4.200 T3.4 REACTOR COOLANT SYSTEM (RCS)
T3.4.200 RCS Pressure and Temperature (P/T) Limits TLCO 3.4.200 Refer to PVNGS Improved Technical Specifications 3.4.3.
APPLICABILITY: Refer to PVNGS Improved Technical Specifications 3.4.3.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of TSR A.1 Document the condition Immediately 3.4.200.1 not met. in accordance with the PVNGS corrective action program and initiate an operability determination, as necessary, to determine the impact on equipment in the technical specifications.
NOTE------------------------------------
Changes to the reactor vessel surveillance specimen withdrawal schedule that meet the applicable ASTM standard must be submitted to the NRC with technical justification for approval prior to implementation (the NRC must verify compliance with the ASTM standard) in accordance with 10 CFR 50, Appendix H, paragraph III.B.3. Changes to the withdrawal schedule that do not meet the applicable ASTM standard must be submitted to the NRC for approval as a license amendment with information required by 10 CFR 50.91 and 50.92 (see NRC Administrative Letter 97-04 dated September 30, 1997).
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.4.200.1 The reactor vessel material irradiation Refer to PVNGS surveillance specimens shall be removed and UFSAR Section examined to determine changes in material 5.3.1.6.6 properties at the intervals required by 10 CFR Withdrawal 50, Appendix H in accordance with PVNGS UFSAR Schedule section 5.3.1.6.6 Withdrawal Schedule. The results of these examinations shall be used to update the PTLR.
PALO VERDE UNITS 1, 2, 3 T3.4.200-1 Rev 52 7/16/10
Pressurizer TRM 3.4.201 T3.4 REACTOR COOLANT SYSTEM (RCS)
T3.4.201 Pressurizer TLCO 3.4.201 Refer to PVNGS Improved Technical Specifications 3.4.9.
APPLICABILITY: Refer to PVNGS Improved Technical Specifications 3.4.9.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of TSR A.1 Document the condition Immediately 3.4.201.1 not met. in accordance with the PVNGS corrective action program and initiate an operability determination, as necessary, to determine the impact on equipment in the technical specifications.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.4.201.1 The emergency power supply for the 18 months pressurizer heaters shall be demonstrated OPERABLE by verifying that on an Engineered Safety Features Actuation test signal concurrent with a loss-of-offsite power:
The pressurizer heaters are automatically shed from the emergency power sources and; The pressurizer heaters can be reconnected to their respective buses manually from the control room.
PALO VERDE UNITS 1, 2, 3 T3.4.201-1 Rev 46 1/8/09
Pressurizer Vents TRM 3.4.202 T3.4 REACTOR COOLANT SYSTEM T3.4.202 Pressurizer Vents TLCO 3.4.202 Refer to PVNGS Improved Technical Specifications 3.4.12.
APPLICABILITY: Refer to PVNGS Improved Technical Specifications 3.4.12.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of TSR A.1 Document the condition Immediately 3.4.202.1 not met. in accordance with the PVNGS corrective action program and initiate an operability determination, as necessary, to determine the impact on equipment in the technical specifications.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.4.202.1 Verify all manual isolation valves in each 18 months vent path are locked in the open position (when in MODE 5 or 6).
PALO VERDE UNITS 1, 2, 3 T3.4.202-1 Rev 46 1/8/09
RCS Operational LEAKAGE TRM 3.4.203 T3.4 REACTOR COOLANT SYSTEM T3.4.203 RCS Operational LEAKAGE TLCO 3.4.203 Refer to PVNGS Improved Technical Specification 3.4.14.
APPLICABILITY: Refer to PVNGS Improved Technical Specification 3.4.14.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of TSR A.1 Document the condition Immediately 3.4.203.1 or 3.4.203.2 in accordance with the not met. PVNGS corrective action program and initiate an operability determination, as necessary, to determine the impact on equipment in the technical specifications.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.4.203.1 Monitor the containment sump inventory and 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> discharge.
TSR 3.4.203.2 Monitor the reactor head flange leakoff 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> system.
PALO VERDE UNITS 1, 2, 3 T3.4.203-1 Rev 46 1/8/09
RCS PIV Leakage TRM 3.4.204 T3.4 REACTOR COOLANT SYSTEM T3.4.204 RCS PIV Leakage TLCO 3.4.204 Refer to PVNGS Improved Technical Specifications LCO 3.4.15.
APPLICABILITY: Refer to PVNGS Improved Technical Specifications LCO 3.4.15.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of TSR A.1 Document the condition Immediately 3.4.204.1 not met. in accordance with the PVNGS corrective action program and initiate an operability determination, as necessary, to determine the impact on equipment in the technical specifications.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.4.204.1 -------------------NOTE---------------------
The provisions of this TSR are not applicable for valves UV-651, UV-652, UV-653 and UV-654 due to position indication of valves in the control room.
Each reactor Coolant System pressure Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> isolation valve shall be demonstrated following a OPERABLE by verifying leakage to be within system response its limit. to an Engineered Safety Feature actuation signal.
PALO VERDE UNITS 1, 2, 3 T3.4.204-1 Rev 46 1/8/09
Safety Injection Tanks TRM 3.5.200 T3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)
T3.5.200 Safety Injection Tanks TLCO 3.5.200 Refer to PVNGS Improved Technical Specifications LCOs 3.5.1 and 3.5.2 APPLICABILITY: Refer to PVNGS Improved Technical Specifications LCOs 3.5.1 and 3.5.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of TSR A.1 Document the condition Immediately 3.5.200.1, 3.5.200.2, in accordance with the 3.5.200.3, 3.5.200.4 or PVNGS corrective 3.5.200.5 not met. action program and initiate an operability determination, as necessary, to determine the impact on equipment in the technical specifications.
PALO VERDE UNITS 1, 2, 3 T3.5.200-1 Rev 46 1/8/09
Safety Injection Tanks TRM 3.5.200 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.5.200.1 -------------------NOTE------------------
Nitrogen vent valves may be cycled as necessary to maintain the required nitrogen cover pressure in accordance with PVNGS Improved Technical Specifications 3.5.1 and 3.5.2.
Verify the required safety injection tank 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> nitrogen vent valves are closed when pressurizer pressure is 430 psia.
TSR 3.5.200.2 -------------------NOTE------------------
Nitrogen vent valves may be cycled as necessary to maintain the required nitrogen cover pressure in accordance with PVNGS Improved Technical Specifications 3.5.1 and 3.5.2.
Verify that power is removed from the 31 days required nitrogen vent valves when pressurizer pressure is 1500 psia.
TSR 3.5.200.3 Verify that the SIT nitrogen vent valves 18 months can be opened when the SITS are isolated.
TSR 3.5.200.4 Verify that each safety injection tank isolation valve opens automatically under each of the following conditions:
- 1. Prior to exceeding an actual or 18 months simulated RCS pressure signal of 515 psia, and
- 2. Upon receipt of a safety injection actuation (SIAS) test signal 18 months (continued)
PALO VERDE UNITS 1, 2, 3 T3.5.200-2 Rev 0 8/13/98
Safety Injection Tanks TRM 3.5.200 SURVEILLANCE REQUIREMENTS (continued)
TSR 3.5.200.5 Verify OPERABILITY of RCS-SIT 18 months differential pressure alarm by simulating RCS pressure greater than 715 psia with SIT pressure less than 600 psig.
PALO VERDE UNITS 1, 2, 3 T3.5.200-3 Rev 0 8/13/98
Shutdown Cooling System TRM 3.5.201 T3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)
T3.5.201 Shutdown Cooling System TLCO 3.5.201 Two independent shutdown cooling subsystems shall be OPERABLE, with each subsystem comprised of:
- a. One OPERABLE low pressure safety injection pump, and
- b. An independent OPERABLE flow path capable of taking suction from the RCS hot leg and discharging coolant through the shutdown cooling heat exchanger and back to the RCS through the cold leg injection lines.
APPLICABILITY: MODES 1, 2, and 3.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One shutdown cooling A.1 Restore the inoperable 7 days subsystem inoperable. subsystem to OPERABLE STATUS B. Required Action and B.1 Continue action to Immediately associated Completion restore the required Time of Condition A not subsystems to OPERABLE met. status.
AND B.2 Verify the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> functionality of the inoperable subsystem C. Required Action and C.1 Be in MODE 3 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> associated Completion Time of Condition B not AND met.
C.2 Be in MODE 4 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> (continued)
PALO VERDE UNITS 1, 2, 3 T3.5.201-1 Rev 16 8/30/01
Shutdown Cooling System TRM 3.5.201 ACTIONS (continued)
D. Both shutdown cooling D.1 Restore one subsystem 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> subsystems inoperable. to OPERABLE status.
E. Required Actions and E.1 Continue action to Immediately associated Completion restore the required time of Condition D not subsystems to OPERABLE met. status.
AND E.2 Verify the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> functionality of one inoperable subsystem.
F. Required Actions and F.1 Be in MODE 3 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> associated Completion time of Condition E not AND met.
F.2 Be in MODE 4 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> G. Both shutdown cooling G.1 Initiate action to Immediately subsystems inoperable restore the required and both reactor subsystems to OPERABLE coolant loops status.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.5.201.1 Establish shutdown cooling flow (during 18 months shutdown) from the RCS hot legs, through the shutdown cooling heat exchangers, and returning to the RCS cold leg.
TSR 3.5.201.2 Verify shutdown cooling system suction 31 days piping is full of water.
PALO VERDE UNITS 1, 2, 3 T3.5.201-2 Rev 47 2/26/09
ECCS - Operating TRM 3.5.202 T3.5.202 ECCS - Operating TLCO 3.5.202 Refer to PVNGS Improved Technical Specifications 3.5.3.
APPLICABILITY: Refer to PVNGS Improved Technical Specifications 3.5.3.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ECCS actuates and injects A.1 Initiate a corrective In accordance water into the Reactor action to evaluate the with the PVNGS Coolant System. circumstances of the corrective actuation and the total action program.
accumulated actuation cycles to date. The current value of the usage factor for each affected injection nozzle shall be provided in this corrective action whenever its value exceeds 0.70.
B. Requirements of TSR B.1 Document the condition Immediately 3.5.202.1, 3.5.202.2 in accordance with the 3.5.202.3 or 3.5.202.4 PVNGS corrective action not met. program and initiate an operability determination, as necessary, to determine the impact on equipment in the technical specifications.
PALO VERDE UNITS 1, 2, 3 T3.5.202-1 Rev 46 1/8/09
ECCS - Operating TRM 3.5.202 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.5.202.1 Conduct a visual inspection to verify that Prior to no loose debris (rags, trash, clothing, establishing etc.) is present in the containment which containment could be transported to the containment sump OPERABILITY, for and cause restriction of the pump suctions all accessible during LOCA conditions. areas of the containment.
AND Daily and during the final entry, for areas in containment affected by a containment entry, when the containment is OPERABLE.
TSR 3.5.202.2 Conduct a flow balance test and verify that ------NOTE------
the flow rates meet the requirements listed Perform during in Table 3.5.202-1. shutdown.
Following completion of modifications (that alter the subsystem flow characteristics) to the ECCS subsystems.
(continued)
PALO VERDE UNITS 1, 2, 3 T3.5.202-2 Rev 39 1/26/07
ECCS - Operating TRM 3.5.202 SURVEILLANCE REQUIREMENTS (continued)
TSR 3.5.202.3 Verify the correct position of each Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> electrical and/or mechanical position stop following for the following ECCS throttle valves: completion of each valve LPSI System Valve Number Hot Leg Injection stroking Valve Number operation or maintenance on
- 1. SIB-UV 615, SIA-HV 306 1. SIC-HV-321 the valve when
- 2. SIB-UV-625, SIB-HV 307 2. SID-HV 331 the ECCS
- 3. SIA-UV 635 subsystems are
- 4. SIA-UV 645 required to be OPERABLE TSR 3.5.202.4 Verify ECCS pump suction piping is full of 31 days water PALO VERDE UNITS 1, 2, 3 T3.5.202-3 Rev 47 2/26/09
ECCS - Operating TRM 3.5.202 Table 3.5.202-1 (Page 1 of 1)
ECCS Flow Rates SOURCE PARAMETER REQUIRED FLOWRATE HPSI System Single Pump Injection Lines - Sum of the flow 816 gpm rates, excluding the highest flow rate LPSI System Single Pump Injection Loop 1 - Total flow 4800 +/- 200 gpm Injection Legs 1A and 1B - When Within 200 gpm tested individually, with the of each other other leg isolated Injection Loop 2 - Total flow 4800 +/- 200 gpm Injection Legs 2A and 2B - When Within 200 gpm tested individually, with the of each other.
other leg isolated Simultaneous Hot Leg Hot Leg 525 gpm.
and Cold Leg Injection
- Single Pump Cold Leg - Sum of flowrates 525 gpm.
Total Pump Flowrate 1200 gpm.
PALO VERDE UNITS 1, 2, 3 T3.5.202-4 Rev 0 8/13/98
ECCS - Shutdown TRM 3.5.203 T3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)
T3.5.203 ECCS - Shutdown TLCO 3.5.203 Refer to PVNGS Improved Technical Specifications 3.5.4.
APPLICABILITY: Refer to PVNGS Improved Technical Specifications 3.5.4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ECCS actuates and injects A.1 Initiate a corrective In accordance water into the Reactor action to evaluate the with the PVNGS Coolant System. circumstances of the corrective actuation and the total action program.
accumulated actuation cycles to date. The current value of the usage factor for each affected injection nozzle shall be provided in this corrective action whenever its value exceeds 0.70.
B. Requirements of TSR B.1 Document the condition Immediately 3.5.203.1 not met. in accordance with the PVNGS corrective action program and initiate an operability determination, as necessary, to determine the impact on equipment in the technical specifications.
PALO VERDE UNITS 1, 2, 3 T3.5.203-1 Rev 46 1/8/09
ECCS - Shutdown TRM 3.5.203 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.5.203.1 The following TSRs are applicable: In accordance with applicable TSR 3.5.202.1 TSR 3.5.202.2 TSR 3.5.202.3 TSRs TSR 3.5.202.4 PALO VERDE UNITS 1, 2, 3 T3.5.203-2 Rev 35 8/31/05
Hydrogen Purge Cleanup System TRM 3.6.100 T3.6 CONTAINMENT SYSTEMS T3.6.100 Hydrogen Purge Cleanup System TLCO 3.6.100 A containment hydrogen purge cleanup system, shared among the three units, shall be OPERABLE and capable of being powered from a minimum of one OPERABLE emergency bus.
APPLICABILITY: MODES 1 and 2 with less than two hydrogen recombiners OPERABLE.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Containment hydrogen A.1 Restore the hydrogen 30 days purge cleanup system purge cleanup system to inoperable and only one OPERABLE status.
B. Required Action and B.1 Enter TLCO 3.0.100.3 Immediately associated Completion Time of Condition A not met.
PALO VERDE UNITS 1, 2, 3 T3.6.100-1 Rev 28 3/26/04
Hydrogen Purge Cleanup System TRM 3.6.100 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.6.100.1 Initiate flow through the HEPA filters and 31 days charcoal adsorbers and verify that the system operates for at least 15 minutes.
TSR 3.6.100.2 Perform required hydrogen purge cleanup In accordance system filter testing in accordance with the with the TRM TRM Ventilation Filter Testing Program VFTP (VFTP) (Reference TRM 5.0.500.11).
PALO VERDE UNITS 1, 2, 3 T3.6.100-2 Rev 0 8/13/98
Pre-Stressed Concrete Containment Tendon Surveillance TRM 3.6.200 T3.6 CONTAINMENT SYSTEMS T3.6.200 Pre-Stressed Concrete Containment Tendon Surveillance TLCO 3.6.200 The acceptance criteria of the Pre-Stressed Concrete Containment Tendon Surveillance Program shall be met.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Acceptance criteria not A.1 Restore containment 15 days met (except for the vessel to the required average of all measured level of integrity.
pre-stressing forces requirements). AND A.2 Perform an Engineering In accordance Evaluation of the with the PVNGS containment vessel corrective structural integrity. action program (continued)
PALO VERDE UNITS 1, 2, 3 T3.6.200-1 Rev 22 3/7/03
Pre-Stressed Concrete Containment Tendon Surveillance TRM 3.6.200 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B. Acceptance criteria not B.1 Restore containment 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> met for the average of vessel to the required all measured pre- level of integrity.
stressing forces requirements. AND B.2 Perform an engineering In accordance evaluation of the with the PVNGS containment vessel corrective structural integrity action program C Required Action and C.1 Be in MODE 3 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND C.2 Be in MODE 5 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.6.200.1 Testing shall be performed in accordance In accordance with with the Pre-Stressed Concrete the Pre-Stressed Containment Tendon Surveillance Program Concrete (Reference TRM 5.0.500.6). Containment Tendon Surveillance Program PALO VERDE UNITS 1, 2, 3 T3.6.200-2 Rev 22 3/7/03
Containment Spray Systems TRM 3.6.201 T3.6 CONTAINMENT SYSTEMS T3.6.201 Containment Spray Systems TLCO 3.6.201 Refer to PVNGS Improved Technical Specifications 3.6.6 APPLICABILITY: Refer to PVNGS Improved Technical Specifications 3.6.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of TSR A.1 Document the condition Immediately 3.6.201.1 not met. in accordance with the PVNGS corrective action program and initiate an operability determination, as necessary, to determine the impact on equipment in the technical specifications.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.6.201.1 Verify containment spray system suction 31 days piping is full of water.
PALO VERDE UNITS 1, 2, 3 T3.6.201-1 Rev 47 2/26/09
Hydrogen Recombiners TRM 3.6.300 T3.6 CONTAINMENT SYSTEMS T3.6.300 Hydrogen Recombiners TLCO 3.6.300 Two hydrogen recombiners shared among the three units shall be OPERABLE.
APPLICABILITY: MODES 1 and 2.
ACTIONS
NOTE-------------------------------------
All three PVNGS Units (Units 1, 2, and 3) shall simultaneously comply with the REQUIRED ACTION(s) when the shared portion of the hydrogen recombiner(s) is the cause of a CONDITION.
CONDITION REQUIRED ACTION COMPLETION TIME A. One hydrogen A.1 Restore hydrogen 30 days recombiner inoperable. recombiner to OPERABLE status.
B. Two hydrogen B.1 Verify by 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> recombiners administrative means inoperable. that the hydrogen AND control function is maintained. Every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter AND B.2 Restore one hydrogen 7 days recombiner to OPERABLE status.
C. Required Action and C.1 Enter TLCO 3.0.100.3. Immediately associated Completion Time not met.
PALO VERDE UNITS 1,2,3 T3.6.300-1 REV 48 7/22/09
Hydrogen Recombiners TRM 3.6.300 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.6.300-1 Visually examine each hydrogen recombiner 6 months enclosure and verify there is no evidence of abnormal conditions.
TSR 3.6.300-2 Perform a functional test for each hydrogen 6 months recombiner.
TSR 3.6.300-3 Perform a CHANNEL CALIBRATION to include a 12 months System Functional Test for each hydrogen recombiner.
PALO VERDE UNITS 1,2,3 T3.6.300-2 REV 48 7/22/09
Steam Generator Pressure and Temperature Limitations TRM 3.7.100 T3.7 PLANT SYSTEMS T3.7.100 Steam Generator Pressure and Temperature Limitations TLCO 3.7.100 The temperature of the secondary coolant in the steam generators shall be greater than 120°F in Units 1 and 3, or 70°F in Unit 2, when the pressure of the secondary coolant in the steam generator is greater than 230 psig in Units 1 and 3, or 650 psig in Unit 2.
APPLICABILITY: At all times.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. With the requirements of A.1 Reduce the steam 30 minutes the above specification generator pressure to not satisfied. less than or equal to 230 psig in Units 1 and 3, or 650 psig in Unit 2.
AND Prior to increasing its A.2 Perform an engineering temperature evaluation to determine above 200°F.
the effect of the overpressurization on the structural integrity of the steam generator. Determine that the steam generator remains acceptable for continued operation PALO VERDE UNITS 1, 2, 3 T3.7.100-1 Rev 27 2/24/04
Steam Generator Pressure and Temperature Limitations TRM 3.7.100 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.7.100.1 Verify that the pressure in the secondary Once per 12 side of the steam generators is less than hours when the 230 psig in Units 1 and 3, or 650 psig in temperature of Unit 2. the secondary coolant is less than 120°F in Units 1 and 3, or 70°F in Unit 2.
PALO VERDE UNITS 1, 2, 3 T3.7.100-2 Rev 27 2/24/04
Snubbers TRM 3.7.101 T3.7 PLANT SYSTEMS T3.7.101 Snubbers TLCO 3.7.101 All hydraulic and mechanical snubbers shall be able to perform their associated safety function(s). The only snubbers excluded from this requirement are those installed on nonsafety-related systems and then only if their failure or failure of the system on which they are installed, would have no adverse effect on any safety-related system.
APPLICABILITY: MODES 1, 2, 3 and 4.
MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more snubbers A.1.1 Enter TS LCO 3.0.8 IF Immediately unable to perform their the restrictions for associated safety utilizing TS LCO 3.0.8 function(s). described in the LCO 3.0.8 TS Bases are met.
OR A.1.2 Declare the supported Immediately system inoperable and follow the appropriate ACTION statement for that system.
AND A.2 Upon failure to meet the functional test 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> acceptance criteria, perform an engineering evaluation on the attached component.
PALO VERDE UNITS 1, 2, 3 T3.7.101-1 Rev 46 1/8/09
Snubbers TRM 3.7.101 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.7.101.1 Each snubber shall be demonstrated able to In accordance perform their associated safety function(s) with the in accordance with the requirements of the requirements of ASME OM Code 2001 Edition and ASME OMb CODE- the ASME OM 2003 Addenda, Subsection ISTD. Preservice Code.
and Inservice Examination and Testing of Subsection Dynamic Restraints (Snubbers) in Light-Water ISTD.
Reactor Nuclear Power Plants, and approved relief requests. Preservice and inservice examinations must be performed using the VT-3 visual examination method described in IWA-2213.
PALO VERDE UNITS 1, 2, 3 T3.7.101-2 Rev 46 1/8/09
Sealed Source Contamination TRM 3.7.102 T3.7 PLANT SYSTEMS T3.7.102 Sealed Source Contamination TLCO 3.7.102 Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material shall be free of greater than or equal to 0.005 microcuries of removable contamination.
APPLICABILITY: At all times.
ACTIONS
NOTE---------------------------------------
The provisions of TLCO 3.0.100.3 are not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. With a sealed source A.1 Withdraw the sealed Immediately having removable source from use.
contamination in excess of the above limit. AND A.2.1 Decontaminate and Prior to repair the sealed returning the source. sealed source to use OR A.2.2 Dispose of the sealed In accordance source. with Commission Regulations PALO VERDE UNITS 1, 2, 3 T3.7.102-1 Rev 0 8/13/98
Sealed Source Contamination TRM 3.7.102 SURVEILLANCE REQUIREMENTS
NOTE-------------------------------------
Each category of sealed sources (excluding startup sources and fission detectors previously subjected to core flux) shall be tested for leakage and/or contamination, at the frequencies described below, by the licensee or other persons specifically authorized by the Commission or an Agreement State.
The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample.
SURVEILLANCE FREQUENCY TSR 3.7.102.1 SOURCES IN USE - Leakage or contamination test sealed sources containing radioactive material:
- a. With a half-life greater than 30 days 6 months (excluding Hydrogen 3), and
- b. In any form other than gas. 6 months TSR 3.7.102.2 STORED SOURCES NOT IN USE - Each sealed Prior to use or source and fission detector shall be leakage transfer to or contamination tested. another licensee unless tested within the previous 6 months.
AND Prior to use if received without a certificate indicating the last test date (continued)
PALO VERDE UNITS 1, 2, 3 T3.7.102-2 Rev 0 8/13/98
Sealed Source Contamination TRM 3.7.102 SURVEILLANCE REQUIREMENTS (continued)
TSR 3.7.102.3 Startup source and fission detectors shall Within 31 days be leakage or contamination tested. prior to being subjected to core flux or installed in the core AND Following repair or maintenance to the source or detector.
TSR 3.7.102.4 A report shall be prepared and submitted to Annually the Commission if sealed source or fission detector leakage tests reveal the presence of greater than or equal to 0.005 microcuries of removable contamination.
PALO VERDE UNITS 1, 2, 3 T3.7.102-3 Rev 0 8/13/98
Atmospheric Dump Valves (ADVs)
TRM 3.7.200 T3.7 PLANT SYSTEMS T3.7.200 Atmospheric Dump Valves (ADVs)
TLCO 3.7.200 Two ADV lines per steam generator (SG) shall be OPERABLE.
APPLICABILITY: MODES 1, 2, and 3 MODE 4 when SG is being relied upon for heat removal.
ACTIONS
NOTE----------------------------------
Separate Condition entry is allowed for each SG.
CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of TSR A.1 Document the condition in Immediately 3.7.200.1 not met. the corrective action program and initiate an operability determination, as necessary, to determine the impact on equipment in the technical specifications.
B. One ADV line per SG B.1. Restore the ADV line to 7 days inoperable. OPERABLE status.
C. Required Action and C.1 Enter TLCO 3.0.100.3 Immediately associated Completion Time of Condition B not met.
D. Two ADV lines on D.1 See TS 3.7.4, Condition A. See TS 3.7.4, one SG inoperable. Condition A.
E. Two ADV lines on E.1 See TS 3.7.4, Condition B. See TS 3.7.4, both SGs Condition B.
PALO VERDE UNITS 1, 2, 3 T3.7.200-1 Rev 42 07/12/07
Atmospheric Dump Valves (ADVs)
TRM 3.7.200 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.7.200.1 Verify that the nitrogen accumulator 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> tank is at a pressure 615 PSIG indicated.
PALO VERDE UNITS 1, 2, 3 T3.7.200-2 Rev 53 11/10/10
AFW System TRM 3.7.201 T3.7 PLANT SYSTEMS T3.7.201 AFW System TLCO 3.7.201 Refer to PVNGS Improved Technical Specifications 3.7.5.
APPLICABILITY: Refer to PVNGS Improved Technical Specifications 3.7.5.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of TSR A.1 Document the condition Immediately 3.7.201.1 not met. in accordance with the PVNGS corrective action program and initiate an operability determination, as necessary, to determine the impact on equipment in the technical specifications.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.7.201.1 Verify that all manual valves in the suction 31 days lines from the primary AFW supply tank (condensate storage tank CTE-T01) to each essential AFW pump, and the manual discharge line valve of each AFW pump are locked, sealed or otherwise secured in the open position.
PALO VERDE UNITS 1, 2, 3 T3.7.201-1 Rev 46 1/8/09
Essential Cooling Water (EW) System TRM 3.7.202 T3.7 PLANT SYSTEMS T3.7.202 Essential Cooling Water (EW) System TLCO 3.7.202 Refer to PVNGS Improved Technical Specifications 3.7.7.
APPLICABILITY: Refer to PVNGS Improved Technical Specifications 3.7.7.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of TSR A.1 Document the condition Immediately 3.7.202.1 not met. in accordance with the PVNGS corrective action program and initiate an operability determination, as necessary, to determine the impact on equipment in the technical specifications.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.7.202.1 Verify that each valve (manual, power- ------NOTE------
operated, or automatic) servicing safety- Perform during related equipment that is locked, sealed, or shutdown.
otherwise secured in position, is in its ----------------
correct position. 18 months PALO VERDE UNITS 1, 2, 3 T3.7.202-1 Rev 46 1/8/09
Essential Spray Pond System (ESPS)
TRM 3.7.203 T3.7 PLANT SYSTEMS T3.7.203 Essential Spray Pond System (ESPS)
TLCO 3.7.203 Refer to PVNGS Improved Technical Specifications 3.7.8.
APPLICABILITY: Refer to PVNGS Improved Technical Specifications 3.7.8.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of TSR A.1 Document the condition Immediately 3.7.203.1 not met. in accordance with the PVNGS corrective action program and initiate an operability determination, as necessary, to determine the impact on equipment in the technical specifications.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.7.203.1 Verify that each valve (manual, power- ------NOTE------
operated, or automatic) servicing safety- Perform during related equipment that is locked, sealed, or shutdown.
otherwise secured in position, is in its ----------------
correct position. 18 months PALO VERDE UNITS 1, 2, 3 T3.7.203-1 Rev 46 1/8/09
Essential Chilled Water (EC) System TRM 3.7.204 T3.7 PLANT SYSTEMS T3.7.204 Essential Chilled Water (EC) System TLCO 3.7.204 Refer to PVNGS Improved Technical Specifications 3.7.10.
APPLICABILITY: Refer to PVNGS Improved Technical Specifications 3.7.10.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of TSR A.1 Document the condition Immediately 3.7.204.1 not met. in accordance with the PVNGS corrective action program and initiate an operability determination, as necessary, to determine the impact on equipment in the technical specifications.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.7.204.1 Verify that each valve (manual, power- ------NOTE------
operated, or automatic) servicing safety- Perform during related equipment that is locked, sealed, or shutdown.
otherwise secured in position, is in its ----------------
correct position. 18 months PALO VERDE UNITS 1, 2, 3 T3.7.204-1 Rev 46 1/8/09
Control Room Emergency Air Temperature Control System (CREATCS)
TRM 3.7.205 T3.7 PLANT SYSTEMS T3.7.205 Control Room Emergency Air Temperature Control System (CREATCS)
TLCO 3.7.205 The control room air temperature shall be maintained less than or equal to 80°F.
APPLICABILITY: All MODES ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Control room air A.1 Reduce the air 30 days temperature greater than temperature to less 80°F. than or equal to 80°F.
B. Required Action and B.1 Enter TLCO 3.0.100.3. Immediately associated Completion Time of Condition A not met in MODES 1, 2, 3, or 4.
C. Required Action and C.1 Action shall be Immediately associated Completion initiated immediately Time of Condition A not to communicate the met in MODE 5, MODE 6, situation to the Shift Manager and document the condition in accordance with the PVNGS corrective action program. An initial decision on whether the unit (continued)
PALO VERDE UNITS 1, 2, 3 T3.7.205-1 Rev 46 1/8/09
Control Room Emergency Air Temperature Control System (CREATCS)
TRM 3.7.205 ACTION CONDITION REQUIRED ACTION COMPLETION TIME can continue to operate with the condition shall be completed within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.
Further actions shall be as required by the corrective action disposition and as deemed necessary by plant management.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.7.205.1 Verify that the control room air temperature 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is less than or equal to 80°F.
PALO VERDE UNITS 1, 2, 3 T3.7.205-2 Rev 46 1/8/09
Fuel Storage Pool Water Level TRM 3.7.206 T3.7 PLANT SYSTEMS T3.7.206 Fuel Storage Pool Water Level TLCO 3.7.206 Refer to PVNGS Improved Technical Specifications 3.7.14.
APPLICABILITY: Refer to PVNGS Improved Technical Specifications 3.7.14.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required Action and ----------NOTE---------
associated Completion TLCO 3.0.100.3 is not Time of ITS 3.7.14 applicable.
Condition A not met. -----------------------
A.1 Suspend crane Immediately operations with loads in the fuel storage areas.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Refer to PVNGS Improved Technical Specifications LCO 3.7.14.
PALO VERDE UNITS 1, 2, 3 T3.7.206-1 Rev 0 8/13/98
Secondary Specific Activity TRM 3.7.207 T3.7 PLANT SYSTEMS T3.7.207 Secondary Specific Activity TLCO 3.7.207 Refer to PVNGS Improved Technical Specifications 3.7.16.
APPLICABILITY: Refer to PVNGS Improved Technical Specifications 3.7.16.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of TSR A.1 Document the condition Immediately 3.7.207.1 not met. in accordance with the PVNGS corrective action program and initiate an operability determination, as necessary, to determine the impact on equipment in the technical specifications.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.7.207.1 Verify that the gross activity of the 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> secondary coolant system is within the limit by performing a Gross Activity Determination PALO VERDE UNITS 1, 2, 3 T3.7.207-1 Rev 46 1/8/09
Cathodic Protection TRM 3.8.100 T3.8 ELECTRICAL POWER SYSTEMS T3.8.100 Cathodic Protection TLCO 3.8.100 The Cathodic Protection System associated with the Diesel Generator Fuel Oil Storage Tanks shall be OPERABLE.
APPLICABILITY: At all times.
ACTIONS
NOTE-------------------------------------
The provisions of TLCO 3.0.100.3 are not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. Cathodic Protection A.1 Restore to OPERABLE 30 days System Inoperable.
B. Required Action and B.1 Initiate a corrective In accordance associated Completion action to evaluate the with the PVNGS Time of Condition A not cause of the corrective met. malfunction and the action program.
plans for restoring the system to OPERABLE status.
PALO VERDE UNITS 1, 2, 3 T3.8.100-1 Rev 46 1/8/09
Cathodic Protection TRM 3.8.100 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.8.100.1 Verify that the Cathodic Protection 61 days rectifiers are OPERABLE and have been inspected in accordance with Regulatory Guide 1.137.
TSR 3.8.100.2 Verify that the Cathodic Protection is 12 months OPERABLE and providing adequate protection against corrosion in accordance with Regulatory Guide 1.137.
PALO VERDE UNITS 1, 2, 3 T3.8.100-2 Rev 0 8/13/98
Containment Penetration Conductor Overcurrent Protection Devices TRM 3.8.101 T3.8 ELECTRICAL POWER SYSTEMS T3.8.101 Containment Penetration Conductor Overcurrent Protection Devices TLCO 3.8.101 Primary and backup containment penetration conductor overcurrent protective devices associated with each containment electrical penetration circuit shall be OPERABLE.
NOTE-----------------------------
The scope of these protective devices excludes those circuits for which credible fault currents would not exceed the electrical penetration design rating.
APPLICABILITY: MODES 1, 2, 3 and 4.
PALO VERDE UNITS 1, 2, 3 T3.8.101-1 Rev 46 1/8/09
Containment Penetration Conductor Overcurrent Protection Devices TRM 3.8.101 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore the protection 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> containment penetration device(s) to OPERABLE conductor overcurrent status.
protective devices inoperable. OR A.2.1 Deenergize the 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> circuit(s) and declare the affected system or component inoperable.
AND A.2.2 Verify the backup At least once circuit breaker to be per 7 days tripped or the inoperable circuit breaker racked out.
B. Required Action and B.1 Enter TLCO 3.0.100.3. Immediately Associated Completion Time not met.
PALO VERDE UNITS 1, 2, 3 T3.8.101-2 Rev 40 2/21/07
Containment Penetration Conductor Overcurrent Protection Devices TRM 3.8.101 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.8.101.1 Perform a CHANNEL CALIBRATION of the 18 months protective relays associated with the medium voltage (4-15 KV) circuit breakers by selecting, on a rotating basis, at least 10%
of the circuit breakers of each voltage level.
TSR 3.8.101.2 Perform an integrated system functional test1 18 months of medium and lower voltage circuit breakers by selecting, on a rotating basis, at least 10% of the circuit breakers of each voltage level2.
NOTE-------------------------------------
- 1. An integrated system functional test includes simulated automatic actuation of the system and verifying that each relay and associated circuit breakers and control circuits function as designed.
- 2. For each circuit breaker found inoperable during these functional tests, an additional representative sample of at least 10% of all the circuit breakers of the inoperable type shall also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested.
For lower voltage circuit breakers, testing of these circuit breakers shall consist of injecting a current with a value equal to 300% of the setpoint (pickup) of the long-term delay trip element, 150% of the setpoint (pickup) of the short-time delay trip element, and verifying that the circuit breaker operates within the time delay band width for that current specified by the manufacturer. The instantaneous element shall be tested (continued)
PALO VERDE UNITS 1, 2, 3 T3.8.101-3 Rev 12 3/30/01
Containment Penetration Conductor Overcurrent Protection Devices TRM 3.8.101
NOTE--------------------------------------
(continued) by injecting a current for a frame size of 250 amps or less with tolerances of +40%/-25% and a frame size of 400 amps or greater of +/-25% and verifying that the circuit breaker trips instantaneously with no apparent time delay.
Molded case circuit breaker testing shall also follow this procedure except that generally no more than two trip elements, time delay and instantaneous, will be involved. Circuit breakers found inoperable during functional testing shall be restored to OPERABLE status prior to resuming operation.
PALO VERDE UNITS 1, 2, 3 T3.8.101-4 Rev 0 8/13/98
MOV Thermal Overload Protection and Bypass Devices TRM 3.8.102 T3.8 ELECTRICAL POWER SYSTEMS T3.8.102 MOV Thermal Overload Protection and Bypass Devices TLCO 3.8.102 The thermal overload protection and bypass devices, integral with the motor starter, of each valve used in safety systems shall be OPERABLE.
APPLICABILITY: Whenever the motor-operated valve is required to be OPERABLE.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. With the thermal overload A.1 Take administrative 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> protection for one or action to continuously more of the required bypass the thermal valves not bypassed overload.
continuously or under accident conditions, as applicable, by an OPERABLE integral bypass device.
B. Required Action and B.1 Declare the affected Immediately associated Completion valve(s) inoperable and Time of Condition A not apply the appropriate met. REQUIRED ACTION(s) for the affected valves.
PALO VERDE UNITS 1, 2, 3 T3.8.102-1 Rev 0 8/13/98
MOV Thermal Overload Protection and Bypass Devices TRM 3.8.102 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.8.102.1 Perform a CHANNEL FUNCTIONAL TEST of the 18 months bypass circuitry for those thermal overloads which are normally in force during plant AND operation and bypassed under accident conditions. Following maintenance on the valve motor starter TSR 3.8.102.2 Verify that the thermal overload protection 18 months is bypassed for those thermal overloads which are continuously bypassed and AND temporarily placed in force only when the valve motors are undergoing periodic or Following maintenance testing. maintenance on the valve motor starter AND Following any periodic testing during which the thermal overload device was temporarily placed in force.
PALO VERDE UNITS 1, 2, 3 T3.8.102-2 Rev 0 8/13/98
AC Sources - Shutdown TRM 3.8.200 T3.8 ELECTRICAL POWER SYSTEMS T3.8.200 AC Sources TLCO 3.8.200 Refer to PVNGS Improved Technical Specifications 3.8.2.
APPLICABILITY: Refer to PVNGS Improved Technical Specifications 3.8.2.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of PVNGS ITS A.1 Suspend all crane Immediately LCO 3.8.2 not met. operation with loads over the fuel storage pool.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Refer to PVNGS Improved Technical Specifications LCO 3.8.2.
PALO VERDE UNITS 1, 2, 3 T3.8.200-1 Rev 0 8/13/98
Decay Time TRM 3.9.100 T3.9 REFUELING OPERATIONS T3.9.100 Decay Time TLCO 3.9.100 The reactor shall be subcritical for at least 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />.
APPLICABILITY: During movement of irradiated fuel in the reactor pressure vessel.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Reactor subcritical for A.1 Suspend all operations Immediately less than 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />. involving movement of irradiated fuel in the reactor pressure vessel.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.9.100.1 Verify (by date and time of subcriticality) Prior to that the reactor has been subcritical for at movement of least 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />. irradiated fuel in the reactor pressure vessel PALO VERDE UNITS 1, 2, 3 T3.9.100-1 Rev 0 8/13/98
Communications TRM 3.9.101 T3.9 REFUELING OPERATIONS T3.9.101 Communications TLCO 3.9.101 Direct communications shall be maintained between the control room and personnel at the refueling station.
APPLICABILITY: During CORE ALTERATIONS.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Direct communications A.1 Suspend all CORE Immediately between the control room ALTERATIONS.
and personnel at the refueling station cannot be maintained.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.9.101.1 Demonstrate direct communication between the 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> control room and personnel at the refueling machine. AND Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> prior to the start of CORE ALTERATIONS.
PALO VERDE UNITS 1, 2, 3 T3.9.101-1 Rev 0 8/13/98
Refueling Machine TRM 3.9.102 T3.9 REFUELING OPERATIONS T3.9.102 Refueling Machine TLCO 3.9.102 The refueling machine shall be used for movement of fuel assemblies and shall be OPERABLE with:
- a. A minimum capacity of 3590 pounds, and
- b. An overload cut off limit of 1600 pounds.
APPLICABILITY: During movement of fuel assemblies within the refueling cavity.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. The requirements for the A.1 Suspend use of the Immediately refueling machine refueling machine from OPERABILITY not operations involving satisfied. the movement of fuel assemblies.
PALO VERDE UNITS 1, 2, 3 T3.9.102-1 Rev 0 8/13/98
Refueling Machine TRM 3.9.102 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.9.102.1 The refueling machine used for movement of Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> fuel assemblies shall be demonstrated prior to the OPERABLE by performing a load test of at start of least 3590 pounds and demonstrating an movement of fuel automatic load cut off when the refueling assemblies.
machine load exceeds 1600 pounds.
PALO VERDE UNITS 1, 2, 3 T3.9.102-2 Rev 0 8/13/98
Crane Travel - Spent Fuel Pool Storage Building TRM 3.9.103 T3.9 REFUELING OPERATIONS T3.9.103 Crane Travel - Spent Fuel Pool Storage Building TLCO 3.9.103 Loads in excess of 2000 pounds shall be prohibited from travel over fuel assemblies in the storage pool.
APPLICABILITY: With fuel assemblies in the storage pool.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the above A.1 Place the crane load in Immediately specification not a safe condition.
satisfied.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.9.103.1 -------------------NOTE---------------------
Applicable only during crane operation Crane interlocks and physical stops which 7 days prevent crane travel with loads in excess of 2000 pounds over fuel assemblies shall be demonstrated OPERABLE.
PALO VERDE UNITS 1, 2, 3 T3.9.103-1 Rev 0 8/13/98
Fuel Building Essential Ventilation System (FBEVS)
TRM 3.9.104 T3.9 PLANT SYSTEMS T3.9.104 Fuel Building Essential Ventilation System (FBEVS)
TLCO 3.9.104 Two FBEVS trains shall be OPERABLE.
APPLICABILITY: During movement of irradiated fuel assemblies in the fuel building.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One FBEVS train A.1 Verify the OPERABLE Immediately inoperable. FBEVS is capable of being powered from an emergency power source.
AND A.2 Restore FBEVS train to 7 days OPERABLE status.
(continued)
PALO VERDE UNITS 1, 2, 3 T3.9.104-1 Rev 0 8/13/98
Fuel Building Essential Ventilation System (FBEVS)
TRM 3.9.104 ACTIONS (continued)
B. Required Action and B.1 Place OPERABLE FBEVS Immediately associated Completion train into operation.
Time of Condition A not met. OR B.2 Suspend all operations Immediately involving movement of irradiated fuel assemblies in the fuel building.
C. Two FBEVS inoperable. C.1 Suspend movement of Immediately irradiated fuel assemblies in the fuel building.
PALO VERDE UNITS 1, 2, 3 T3.9.104-2 Rev 0 8/13/98
Fuel Building Essential Ventilation System (FBEVS)
TRM 3.9.104 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.9.104.1 Operate each FBEVS train for at least 15 31 days minutes.
TSR 3.9.104.2 Perform required Fuel Building Essential In accordance Ventilation filter testing in accordance with the TRM with the TRM Ventilation Filter Testing VFTP Program (VFTP) (Reference TRM 5.0.500.11).
TSR 3.9.104.3 Verify each FBEVS train actuates on an 18 months actual or simulated signal and directs it exhaust bank through the HEPA filters and charcoal adsorber banks.
TSR 3.9.104.4 Verify one FBEVS train can maintain a 18 months on a measurable negative pressure with respect to STAGGERED TEST atmospheric pressure, during operation. BASIS.
PALO VERDE UNITS 1, 2, 3 T3.9.104-3 Rev 0 8/13/98
Boron Concentration TRM 3.9.200 T3.9 REFUELING OPERATIONS T3.9.200 Boron Concentration TLCO 3.9.200 Refer to PVNGS Improved Technical Specification LCO 3.9.1.
APPLICABILITY: Refer to PVNGS Improved Technical Specification LCO 3.9.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of TSR A.1 Document the condition Immediately 3.9.200.1 not met. in accordance with the PVNGS corrective action program and initiate an operability determination, as necessary, to determine the impact on equipment in the technical specifications.
PALO VERDE UNITS 1, 2, 3 T3.9.200-1 Rev 46 1/8/09
Boron Concentration TRM 3.9.200 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.9.200.1 Determine that the boron concentration is Prior to within the limits specified in the COLR. removing or unbolting the reactor vessel head AND Prior to withdrawal of any full strength CEA in excess of 3 feet from its fully inserted position within the reactor pressure vessel PALO VERDE UNITS 1, 2, 3 T3.9.200-2 Rev 29 4/15/04
Containment Penetrations TRM 3.9.201 T3.9 REFUELING OPERATIONS T3.9.201 Containment Penetrations TLCO 3.9.201 Refer to PVNGS Improved Technical Specifications 3.9.3.
APPLICABILITY: Refer to PVNGS Improved Technical Specifications 3.9.3.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of TSR A.1 Document the condition Immediately 3.9.201.1 not met. in accordance with the PVNGS corrective action program and initiate an operability determination, as necessary, to determine the impact on equipment in the technical specifications.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.9.201.1 Verify that each of the containment Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> penetrations required by PVNGS ITS LCO 3.9.3 prior to the is in its required status. start of CORE ALTERATIONS AND Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to the start of movement of irradiated fuel in the containment building.
PALO VERDE UNITS 1, 2, 3 T3.9.201-1 Rev 46 1/8/09
Liquid Holdup Tanks TRM 3.10.200 T3.10 RADIOACTIVE EFFLUENTS T3.10.200 Liquid Holdup Tanks TLCO 3.10.200 The quantity of radioactive material contained in each outside temporary tank and the reactor makeup water tank shall be limited to less than or equal to 60 curies, excluding tritium and dissolved or entrained noble gases.
APPLICABILITY: At all times.
ACTIONS
NOTE--------------------------------------
The provisions of Specifications 3.0.100.3 are not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. The quantity of A.1 Suspend all additions Immediately radioactive material in of radioactive material any outside temporary to the tank.
tank or the reactor makeup water tank exceeds AND the above limit.
A.2 Reduce the tank 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> contents to within the limit.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.10.200.1 Verify the quantity of radioactive material 7 days contained in each outside temporary tank and the reactor makeup water tank is within the limit by analyzing a representative sample of the tanks contents when radioactive materials are being added to the tank.
PALO VERDE UNITS 1, 2, 3 T3.10.200-1 Rev 40 2/21/07
Explosive Gas Mixture TRM 3.10.201 T3.10 RADIOACTIVE EFFLUENTS T3.10.201 Explosive Gas Mixture TLCO 3.10.201 The concentration of oxygen in the waste gas holdup system shall be limited to 2% by volume.
APPLICABILITY: Whenever waste gas holdup system is in service.
ACTIONS
NOTE--------------------------------------
The provisions of Specifications 3.0.100.3 and 3.0.100.4 are not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. Concentration of oxygen A.1 Reduce the oxygen 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> in the waste gas holdup concentration to within system > 2% by volume but the limit.
4% by volume.
B. Concentration of oxygen B.1 Suspend all additions Immediately
> 4% by volume. of waste gases to the system.
AND B.2 Reduce concentration of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> oxygen to 4% by volume.
(continued)
PALO VERDE UNITS 1, 2, 3 T3.10.201-1 Rev 0 8/13/98
Explosive Gas Mixture TRM 3.10.201 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY TSR 3.10.201.1 Verify the concentration of oxygen in the Continuously waste gas holdup system is within the limit by continuously monitoring the waste gases in the waste gas holdup system using the instruments required OPERABLE by TRM specification T3.3.107.
PALO VERDE UNITS 1, 2, 3 T3.10.201-2 Rev 0 8/13/98
Explosive Gas Mixture TRM 3.10.202 T3.10 RADIOACTIVE EFFLUENTS T3.10.202 Gas Storage Tanks TLCO 3.10.202 The quantity of radioactivity contained in each gas storage tank shall be limited to less than or equal to 170,000 curies noble gases (considered as Xe-133).
APPLICABILITY: At all times.
ACTIONS
NOTE--------------------------------------
The provisions of Specification 3.0.100.3 are not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. Quantity of radioactive A.1 Suspend all additions Immediately material in any gas of radioactive material storage tank exceeds to the tank.
limit.
AND A.2 Reduce tank contents to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> within the limit.
PALO VERDE UNITS 1, 2, 3 T3.10.202-1 Rev 40 2/21/07
Explosive Gas Mixture TRM 3.10.202 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.10.202.1 Verify the quantity of radioactive material contained in each gas storage tank is within the limit:
- 1. When radioactive materials are being 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> added to the tank and the quantity of radioactivity contained in the tank is greater than one-half of the specified limit
- 2. When radioactive materials are being 7 days added to the tank and the quantity of radioactivity contained in the tank is less than or equal to one-half of the specified limit PALO VERDE UNITS 1, 2, 3 T3.10.202-2 Rev 0 8/13/98
Fire Detection Instrumentation TRM 3.11.100 T3.11 FIRE PROTECTION T3.11.100 Fire Detection Instrumentation (formerly TS 3.3.3.7)
TLCO 3.11.100 As a minimum, the fire detection instrumentation for each Fire Protection Evaluation Report (FPER) detection zone shown in Table 3.11.100-1 shall be OPERABLE.
APPLICABILITY: Whenever equipment protected by the fire detection instrument is required to be OPERABLE.
ACTIONS
NOTES--------------------------
The provisions of TLCO 3.0.100.3 are not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. Any, but not more than A.1 Restore the inoperable 14 days one-half of the Function instrument(s) to X fire detection OPERABLE status.
instruments in any fire zone shown in Table 3.11.100-1 inoperable.
B. Required Action and ------------NOTE-----------
Completion Time of Required Action B.1 is not Condition A not met. applicable if the instrument(s) are located inside containment.
B.1 Establish a fire watch Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> patrol to inspect the zone(s) and at least with the inoperable once per hour instruments thereafter.
OR (continued)
PALO VERDE UNITS 1, 2, 3 T3.11.100-1 Rev 40 2/21/07
Fire Detection Instrumentation TRM 3.11.100 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME
NOTE------------
Required Actions B.2.1, B.2.2 and B.2.3 are applicable for instrument(s) located inside containment.
B.2.1 Establish a fire watch Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> patrol to inspect the and at least Containment zone(s) with once per 8 the inoperable hours instrument(s). thereafter OR B.2.2 Monitor the containment Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> air temperature using and at least the locations listed in once per hour the Bases for Technical thereafter.
Specification SR 3.6.5.1.
OR B.2.3 Monitor the containment Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> air temperature using and the locations listed in continuously Bases for Technical thereafter.
Specification SR 3.6.5.1 with the plant computer, multi-point recorder and audio annunciator.
(continued)
PALO VERDE UNITS 1, 2, 3 T3.11.100-2 Rev 38 10/18/06
Fire Detection Instrumentation TRM 3.11.100 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C. More than one-half of ------------NOTE------------
the Function X fire Required Action C.1 is not detection instruments applicable if the in any fire zone shown instrument(s) are located in Table 3.11.100-1 inside containment.
inoperable. ----------------------------
C.1 Establish a fire watch Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> OR patrol to inspect the and at least Any Function Y fire zone(s) with the once per hour detection instruments inoperable instrument(s). thereafter.
shown in Table OR 3.11.100-1 inoperable.
NOTE-----------
OR Required Action C.2.1, C.2.2, Any two or more and C.2.3 are applicable for adjacent fire instrument(s) located inside detection instruments containment.
shown in Table ----------------------------
3.11.100-1 inoperable. C.2.1 Establish a fire watch Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> patrol to inspect that and at least Containment Zone with the once per 8 inoperable instrument(s). hours thereafter.
OR C.2.2 Monitor the containment Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> air temperature using the and at least locations listed in the once per hour Bases for Technical thereafter.
Specification SR 3.6.5.1.
OR C.2.3 Monitor the containment Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> air temperature using the and locations listed in the continuously Bases for Technical thereafter.
Specification SR 3.6.5.1 with the plant computer, multi-point recorder and audio annunciator.
PALO VERDE UNITS 1, 2, 3 T3.11.100-3 Rev 38 10/18/06
Fire Detection Instrumentation TRM 3.11.100 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.11.100.1 Perform a CHANNEL FUNCTIONAL TEST of each 12 months of the required fire detection instruments which are accessible during plant operation.
TSR 3.11.100.2 Perform a CHANNEL FUNCTIONAL TEST of each Each COLD of the required fire detection SHUTDOWN, unless instruments which are not accessible performed in the during plant operation. previous 12 months.
TSR 3.11.100.3 Demonstrate that the NFPA Standard 72D 12 months supervised circuits supervision associated with the detector alarms of each of the required fire detection instruments is OPERABLE.
PALO VERDE UNITS 1, 2, 3 T3.11.100-4 Rev 38 10/18/06
Fire Detection Instrumentation TRM 3.11.100 Table 3.11.100-1 (Formerly TS Table 3.3-11) (Page 1 of 5)
FIRE DETECTION INSTRUMENTS FIRE ELEVATION INSTRUMENT LOCATION TOTAL NUMBER OF ZONE INSTRUMENTS*
HEAT FLAME SMOKE (X/Y) (X/Y) (X/Y)
BUILDING - CONTROL 1 74 Essential Chiller Rm. Train A 24/0 2 74' Essential Chiller Rm. Train B 21/0 3A 74 Cable Shaft - Train A 1/0 3B 74 Cable Shaft - Train B 1/0 86A 74-156 4" Deadspace Compartment Train A 0/1 0/3 86B 74-156 4" Deadspace Compartment Train B 0/1 0/3 4A 100' Cable Shaft- Train A 1/0 4B 100' Cable Shaft - Train B 1/0 5A 100' ESF Switchgear Room Train A 0/5 0/5 5B 100' ESF Switchgear Room Train B 0/5 0/5 6A 100' DC Equip. Rm. - Train A (Channel C) 2/0 6B 100' DC Equip. Rm. - Train B (Channel D) 2/0 7A 100' DC Equip. Rm. - Train A (Channel A) 2/0 7B 100' DC Equip. Rm. - Train B (Channel B) 2/0 8A 100' Battery Rm. Train A (Channel C) 0/2 0/2 8B 100' Battery Rm. Train B (Channel D) 0/2 0/2 9A 100 Battery Rm. - Train A (Channel A) 0/2 0/2 9B 100 Battery Rm. - Train B (Channel B) 0/2 0/2 10A 100 Remote Shutdown Rm. Train A 0/1 1/1 10B 100 Remote Shutdown Rm. Train B 0/1 1/1 11A 120 Cable Shaft - Train A 1/0 11B 120 Cable Shaft - Train B 1/0 14 120 Lower Cable Spreading Rm.
System 1 0/1 0/6 System 2 0/1 0/6 System 3 0/1 0/8 System 4 0/1 0/8 System 5 0/1 0/8 System 6 0/1 0/8 PALO VERDE UNITS 1, 2, 3 T3.11.100-5 Rev 38 10/18/06
Fire Detection Instrumentation TRM 3.11.100 Table 3.11.100-1 (Formerly TS Table 3.3-11)(Continued) (Page 2 of 5)
BUILDING - CONTROL (Continued) 15A 140 Cable Shaft - Train A 1/0 15B 140 Cable Shaft - Train B 1/0 17 140 Control Rm. MCB's & Relay Cabinets 116/0 18A 160 Cable Shaft - Train A 1/0 18B 160 Cable Shaft - Train B 1/0 20 160 Upper Cable Spreading Rm.
System 1 0/1 0/12 System 2 0/1 0/8 System 3 0/1 0/8 System 4 0/1 0/8 System 5 0/1 0/8 BUILDING - DIESEL GENERATOR 21A 100 Diesel Generator - Train A 0/3 0/4 21B 100 Diesel Generator - Train B 0/3 0/4 22A 100 Diesel Generator Control Rm. - Train 1/0 A
22B 100 Diesel Generator Control Rm. - Train 1/0 B
24A 115 Combustion Air Intake Rm. - Train A 1/0 24B 115 Combustion Air Intake Rm. - Train B 1/0 23A 131 Fuel Oil Day Tank Train A 0/1 23B 131 Fuel Oil Day Tank Train B 0/1 25A 131 Exhaust Silencer Rm. Train A 3/0 25B 131 Exhaust Silencer Rm. Train B 3/0 BUILDING - FUEL 28 100 Spent Fuel Pool Cooling and Cleanup 3/0 Pump Areas PALO VERDE UNITS 1, 2, 3 T3.11.100-6 Rev 38 10/18/06
Fire Detection Instrumentation TRM 3.11.100 Table 3.11.100-1 (Formerly TS Table 3.3-11)(Continued) (Page 3 of 5)
BUILDING - AUXILIARY 88A 51-6 & 87A West Corridors 6/0 88B 51-6 & 87B East Corridors 6/0 32A 51-6 & 40 LPSI Pump Rm. - Train A 0/2 32B 51-6 & 40 LPSI Pump Rm. - Train B 0/2 34A 70 ECW Pump Rm. - Train A 2/0 34B 70 ECW Pump Rm. - Train B 2/0 35A 70 Shutdown Cooling Hr. x Chgr. 4/0 Train A 35B 70 Shutdown Cooling Hr. x Chgr. 4/0 Train B 36 70 Reactor Makeup and Boric Acid 1/0 Makeup Room 37C 70 & 88 Piping Penetration Rm. - Train A 5/0 37D 70 & 88 Piping Penetration Rm. - Train B 4/0 37B 70 Corridors - East 11/0 37A 70 Corridors - West 11/0 39A 88 Pipeways - Train A 8/0 39B 88 Pipeways - Train B 8/0 42A 100 Elect. Penetration Rm. - Tr. A 0/1 0/25 (Chan. C) 42B 100 Elect. Penetration Rm. - Tr. B 0/1 0/24 (Chan. B) 42C 100 Corridors - East & Southeast 0/2 3/35 42D 100 Corridor - West 0/1 2/29 46A 100 Charging Pump and Valve Gallery 0/3 Rm. - Train A 46B 100 Charging Pump and Valve Gallery 0/3 Rm. - Train B 46E 100 Charging Pump and Valve Gallery 0/3 Rm. - Train E PALO VERDE UNITS 1, 2, 3 T3.11.100-7 Rev 38 10/18/06
Fire Detection Instrumentation TRM 3.11.100 Table 3.11.100-1 (Formerly TS Table 3.3-11)(Continued) (Page 4 of 5)
BUILDING - AUXILIARY (Continued) 47A 120 Elect. Penetration Rm. - Tr. A (Chan. A) 0/1 0/28 47B 120 Elect. Penetration Rm. - Tr. B (Chan. D) 0/1 0/24 48 120 ECW Surge Tanks Corridor - Tr. A & B 3/0 50B 120 Valve Gallery 1/0 51B 120 Spray Chemical Storage Tk. Rm. 1/0 52A 120 Central corridor - West 0/1 5/17 52D 120 Central Corridor- East 0/1 7/18 54 120 Reactor Trip Switchgear Rm. 1/0 6/0 56B 140 Storage and Elect. Equip. Rm. - East 6/0 57J 140 Radiation Protection Offices, Locker 18/0 Rooms.
BUILDING - CONTAINMENT**
66A & 100 & Southwest and Southeast Perimeter 1/0 66B 120 67A & 100 Northwest and Northeast Perimeter 1/0 67B 66A 120 Southwest Perimeter 1/0 66B 120 Southeast Perimeter 1/0 67A & 120 Northwest and Northeast Perimeter 1/0 67B 63A 120' No. 1 RCPs and SG Area 6/0 63B 120' No. 2 RCPs and SG Area 6/0 66A & 140' Southwest, Southeast, Northwest, and 1/0 66B Northeast Perimeters 67A &
67B 63A 140' No. 1 RCPs and SG Area 5/0 63B 140' No. 2 RCPs and SG Area 5/0 70 140' Refueling Pool and Canal Area 4/0 71A 140' North Preaccess Normal AFU 2/0 71B 140' South Preaccess Normal AFU 2/0 PALO VERDE UNITS 1, 2, 3 T3.11.100-8 Rev 38 10/18/06
Fire Detection Instrumentation TRM 3.11.100 Table 3.11.100-1 (Formerly TS Table 3.3-11)(Continued) (Page 5 of 5)
MAIN STEAM SUPPORT STRUCTURE 72 80' Turbine Driven Aux. Feedpump Rm. 0/3 73 80' Motor Driven Aux. Feedpump Rm. 1/1 74A 100, 120 Main Steam Isol. & Dump Valve Area 0/6
& 140 North 74B 100, 120 Main Steam Isol. & Dump Valve Area 0/6
&140 South OUTSIDE AREAS 83 Condensate Storage Tank Pump 2/0 House 84A Spray Pond Pump House - Train A 2/0 84B Spray Pond Pump House - Train B 2/0
- The fire detection instruments located within the containment are not required to be OPERABLE during the performance of Type A containment leakage rate tests.
- (x/y): x is the number of instruments associated with early fire detection and notification only.
y is the number of instruments associated with actuation of fire suppression systems and early fire detection and notification.
PALO VERDE UNITS 1, 2, 3 T3.11.100-9 Rev 38 10/18/06
Fire Suppression Water Systems TRM 3.11.101 T3.11 FIRE PROTECTION T3.11.101 Fire Suppression Water System (formerly TS 3.7.11.1)
TLCO 3.11.101 The fire suppression water system shall be OPERABLE with:
- a. Three 50% capacity fire suppression pumps, each with a capacity of at least 1350 gpm, with their discharge aligned to the fire suppression header
- b. Two separate water supply tanks, each with a minimum contained volume of 300,000 gallons (23 feet, 1.5 inches), and
- c. An OPERABLE flow path capable of taking suction from the T01-A tank and the T01-B tank and transferring the water through distribution piping with OPERABLE sectionalizing control or isolation valves to the yard hydrant curb valves, the last valve ahead of the water flow alarm device on each sprinkler or hose standpipe, and the last valve ahead of the deluge valve on each deluge or spray system required to be OPERABLE per Specifications T3.11.102, T3.11.104, and T3.11.105.
APPLICABILITY: At all times.
ACTIONS
NOTES-------------------------
The provisions of TLCO 3.0.100.3 are not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. One pump and/or one water A.1 Restore the inoperable 7 days supply inoperable. equipment to OPERABLE status.
OR (continued)
PALO VERDE UNITS 1, 2, 3 T3.11.101-1 Rev 40 2/21/07
Fire Suppression Water Systems TRM 3.11.101 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME A.2 Provide an alternate 7 days backup pump or water supply.
B. The fire suppression B.1 Establish a backup fire 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> water system inoperable suppression water for reason other than system.
Condition A.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.11.101.1 Verify the contained water supply volume 7 days of the fire suppression water system.
TSR 3.11.101.2 Verify that the electrolyte level of 7 days each fire pump diesel starting 24-volt battery is above the plates.
TSR 3.11.101.3 Verify that the overall voltage of each 31 days fire pump diesel starting 24-volt battery is greater than or equal to 24 volts.
TSR 3.11.101.4 Start the electric motor-driven pump for 31 days the fire suppression water system and operate it for at least 15 minutes on recirculation flow.
TSR 3.11.101.5 Verify that each valve (manual, power 31 days operated, or automatic) in the flow path of the fire suppression water system (except the hydrant street isolation
[CURB] valves) is in its correct position, when required to be OPERABLE.
(continued)
PALO VERDE UNITS 1, 2, 3 T3.11.101-2 Rev 46 1/8/09
Fire Suppression Water Systems TRM 3.11.101 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY TSR 3.11.101.6 Verify that the diesel fuel oil day 31 days on a storage tanks for the fire pump diesel STAGGERED TEST engines each contain at least 290 gallons BASIS (3/4 level) of fuel.
TSR 3.11.101.7 Verify that the fire pump diesel engines 31 days on a start from ambient conditions and operate STAGGERED TEST for at least 30 minutes on recirculation BASIS flow.
TSR 3.11.101.8 Verify that the specific gravity of each 92 days fire pump diesel starting 24-volt battery is appropriate for continued service of the battery.
TSR 3.11.101.9 Verify that a sample of diesel fuel from 92 days the fuel storage tank for the fire pump diesel engines, obtained in accordance with ASTM-D4057-81, is within the acceptable limits specified in Table 1 of ASTM D975-89a when checked for viscosity, water, and sediment.
TSR 3.11.101.10 Deleted TSR 3.11.101.11 Verify that each hydrant street 12 months isolation [CURB] valve (manual power operated, or automatic) in the flow path of the fire suppression water system is in its correct position, when required to be OPERABLE.
TSR 3.11.101.12 Cycle each testable valve in the flow 12 months path of the fire suppression water system through at least one complete cycle of full travel.
(continued)
PALO VERDE UNITS 1, 2, 3 T3.11.101-3 Rev 46 1/8/09
Fire Suppression Water Systems TRM 3.11.101 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY TSR 3.11.101.13 Deleted TSR 3.11.101.14 Deleted TSR 3.11.101.15 Perform a system functional test which 18 months includes simulated automatic actuation of the fire suppression water system throughout its operating sequence.
AND Verify that each fire suppression water system pump develops at least 1350 gpm at an indicated differential pressure of 125 psid by recording readings for at least 3 points on the test curve.
AND Cycle each fire suppression water system valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel.
AND Verify that each fire suppression water system pump starts sequentially to maintain the fire suppression water system pressure greater than or equal to 85 psig.
(continued)
PALO VERDE UNITS 1, 2, 3 T3.11.101-4 Rev 39 1/26/07
Fire Suppression Water Systems TRM 3.11.101 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY TSR 3.11.101.16 Perform a flow test of the fire 3 years suppression water system in accordance with Chapter 5, Section 11 of the Fire Protection Handbook, 14th Edition, published by the National Fire Protection Association.
PALO VERDE UNITS 1, 2, 3 T3.11.101-5 Rev 46 1/8/09
Spray and/or Sprinkler Systems TRM 3.11.102 T3.11 FIRE PROTECTION T3.11.102 Spray and/or Sprinkler Systems (formerly TS 3.7.11.2)
TLCO 3.11.102 The Spray and/or Sprinkler Systems listed in Table 3.11.102-1 shall be OPERABLE.
APPLICABILITY: Whenever equipment protected by the Spray/Sprinkler System is required to be OPERABLE.
ACTIONS
NOTES--------------------------
The provisions of TLCO 3.0.100.3 are not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the A.1 Establish a continuous 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> required spray and/or fire watch with backup sprinkler systems fire suppression inoperable in areas in equipment.
which redundant systems or components could be damaged.
B. One or more of the B.1 Establish an hourly 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> required spray and/or fire watch patrol.
sprinkler systems inoperable in areas in which no redundant systems or components could be damaged.
PALO VERDE UNITS 1, 2, 3 T3.11.102-1 Rev 46 1/8/09
Spray and/or Sprinkler Systems TRM 3.11.102 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.11.102.1 Verify that each valve (manual, power 31 days operated, or automatic) in the flow path of each of the required spray and/or sprinkler systems is in its correct position.
TSR 3.11.102.2 Cycle each testable valve in the flow 12 months path of each of the required spray and/or sprinkler systems through at least one complete cycle of full travel.
TSR 3.11.102.3 Perform a system functional test of each 18 months of the required spray and/or sprinkler systems which includes simulated automatic actuation of the system, and:
Verify that the automatic valves in the flow path actuate to their correct positions on a thermal/smoke test signal, and:
Cycle each valve in the flow path that is not testable during plant operations through at least one complete cycle of full travel.
TSR 3.11.102.4 Visually inspect the dry pipe spray and 18 months sprinkler headers of each of the required spray and/or sprinkler systems to verify their integrity.
TSR 3.11.102.5 Visually inspect each of the required 18 months spray and/or sprinkler systems nozzles spray area to verify the spray pattern is not obstructed.
(continued)
PALO VERDE UNITS 1, 2, 3 T3.11.102-2 Rev 4 9/24/99
Spray and/or Sprinkler Systems TRM 3.11.102 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY TSR 3.11.102.6 Perform an air flow test through each 5 years open head spray/sprinkler header of each of the required spray and/or sprinkler systems and verify that each open head spray/sprinkler nozzle is unobstructed.
PALO VERDE UNITS 1, 2, 3 T3.11.102-3 Rev 4 9/24/99
Spray and/or Sprinkler Systems TRM 3.11.102 Table 3.11.102-1 (Formerly TS Table 3.7-3)
Page 1 of 2 SPRAY AND/OR SPRINKLER SYSTEMS
- 1. Lower Cable Spreading Room Zone 14 - Control Building 120 ft Elevation
- a. System 1
- b. System 2
- c. System 3
- d. System 4
- e. System 5
- f. System 6
- 2. Upper Cable Spreading Room Zone 20 - Control Building 160 ft Elevation
- a. System 1
- b. System 2
- c. System 3
- d. System 4
- e. System 5
- 3. Diesel Generator Room, Train A, Zone 21A - Diesel Generator Building 100 ft Elevation
- 4. Diesel Generator Room, Train B, Zone 21B - Diesel Generator Building 100 ft Elevation
- 5. Fuel Oil Day Tank Vault, Train A, Zone 23A - Diesel Generator Building 131 ft Elevation
- 6. Fuel Oil Day Tank Vault, Train B, Zone 23B - Diesel Generator Building 131 ft Elevation
- 7. Low Pressure Safety Injection Pump Room, Train A, Zone 32A Auxiliary Building 40ft and 51ft 6 inch Elevation
- 8. Low Pressure Safety Injection Pump Room Train B, Zone 32B - Auxiliary Building 40ft and 51ft 6 inch Elevation
- 9. Electrical Penetration Room, Train A (Channel C) Zone 42A - Auxiliary Building 100 ft Elevation
- 10. Electrical Penetration Room, Train B (Channel B) Zone 42B - Auxiliary Building 100 ft Elevation
- 11. Charging Pumps A, B, and E Zones 46A,46B AND 46E East Corridors, Zone 42C Auxiliary Building 100 ft Elevation
- 12. West Corridors, Zone 42D Auxiliary Building 100 ft Elevation
- 13. Electrical Penetration Room, Train A (Channel A) Zone 47A - Auxiliary Building 120 ft Elevation 14 Electrical Penetration Room, Train B (Channel D) Zone 47B - Auxiliary Building 120 ft Elevation
- 15. Central Corridors, Zone 52A - Auxiliary Building 120 ft Elevation
- 16. Central Corridors, Zone 52D - Auxiliary Building 120 ft Elevation PALO VERDE UNITS 1, 2, 3 T3.11.102-4 Rev 4 9/24/99
Spray and/or Sprinkler Systems TRM 3.11.102 Table 3.11.102-1 (Formerly TS Table 3.7-3)
Page 2 of 2
- 17. Turbine Driven Auxiliary Feed Pump Room Zone 72 Main Steam Support Structure 81 ft Elevation.
- 18. Train A Compartments between Auxiliary & Control Buildings, 74 ft & 156 ft 4 inch Elevation Zone 86A
- 19. Train B Compartments between Auxiliary & Control Buildings, 74 ft & 156 ft 4 inch Elevation on Zone 86B
- 20. Train A and Train B Main Steam Support Structure, Zone 74A and Zone 74B 100 ft through 140 ft Elevation.
PALO VERDE UNITS 1, 2, 3 T3.11.102-5 Rev 18 3/13/02
CO2 Systems TRM 3.11.103 T3.11 FIRE PROTECTION T3.11.103 CO2 Systems (formerly TS 3.7.11.3)
TLCO 3.11.103 The following low pressure CO2 systems shall be OPERABLE.
- a. ESF Switchgear Room; one Train A, one Train B Zone 5A and 5B Control Building 100 ft Elevation
- b. Battery Rooms; one Train A (Channel C) one Train B (Channel D) Zone 8A and 8B Control Building 100 ft Elevation
- c. Battery Rooms; one Train A (Channel A) one Train B (Channel B) Zone 9A and 9B Control Building 100 ft Elevation APPLICABILITY: Whenever equipment protected by the CO2 is required to be OPERABLE.
ACTIONS
NOTES--------------------------
The provisions of TLCO 3.0.100.3 are not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the A.1 Establish a continuous 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> required CO2 systems fire watch with backup inoperable in areas in fire suppression which redundant systems equipment.
or components could be damaged.
B. One or more of the B.1 Establish an hourly 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> required CO2 systems fire watch patrol.
inoperable in areas in which no redundant systems or components could be damaged.
PALO VERDE UNITS 1, 2, 3 T3.11.103-1 Rev 46 1/8/09
CO2 Systems TRM 3.11.103 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.11.103.1 For each of the required CO2 systems, 7 days verify the CO2 storage tank weight to be greater than 10,000 lb and pressure to be greater than 275 psig.
TSR 3.11.103.2 For each of the required CO2 systems, 31 days verify that each valve (manual, power operated, or automatic) in the flow is in its correct position.
TSR 3.11.103.3 For each of the required CO2 systems, 18 months verify that the system, actuates manually and automatically, upon receipt of a simulated actuation signal.
TSR 3.11.103.4 For each of the required CO2 systems, 18 months visually inspect that there are no obstructions in the discharge path of the nozzles or during a Puff Test.
TSR 3.11.103.5 For each of the required CO2 systems, 54 months verify each circuit from the control panel to the fire damper actuation devices is capable of performing its intended function.
TSR 3.11.103.6 For each of the required CO2 systems, 54 months perform a functional test of associated fire dampers.
PALO VERDE UNITS 1, 2, 3 T3.11.103-2 Rev 49 11/06/09
Fire Hose Stations TRM 3.11.104 T3.11 FIRE PROTECTION T3.11.104 Fire Hose Stations (formerly TS 3.7.11.4)
TLCO 3.11.104 The fire hose stations shown in Table 3.11.104-1 shall be OPERABLE.
APPLICABILITY: Whenever equipment in the areas protected by the fire hose stations is required to be OPERABLE, except that fire hose stations located in containment shall have their containment isolation valves closed in MODES 1, 2, 3, 4, and 5*.
- If hot work or other work relating to the use of combustible material or flammable liquids is to be performed in containment during MODE 5, the fire hose stations located in containment shall have their containment isolation valves open and their containment flooding valve closed during the period that the work is being performed.
ACTIONS
NOTES--------------------------
The provisions of TLCO 3.0.100.3 are not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the fire A.1 Provide a gated wye on 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> hose stations shown in the nearest OPERABLE hose Table 3.11.104-1 station. One outlet of inoperable where the fire the wye shall be hose is the primary means connected to the standard of fire suppression. length of hose provided for the OPERABLE hose station. The second outlet of the wye shall be connected to a length of hose sufficient to provide coverage for the area left unprotected by the inoperable hose station.
(continued)
PALO VERDE UNITS 1, 2, 3 T3.11.104-1 Rev 44 1/3/08
Fire Hose Stations TRM 3.11.104 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) The hose for the unprotected area shall be stored at the OPERABLE hose station. Signs identifying the purpose and location of the fire hose and related valves shall be mounted above the hose and at the inoperable hose station.
B. One or more of the fire B.1 Provide a gated wye on 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> hose stations shown in the nearest OPERABLE hose Table 3.11.104-1 station. One outlet of inoperable where the fire the wye shall be hose is not the primary connected to the standard means of fire length of hose provided suppression. for the OPERABLE hose station. The second outlet of the wye shall be connected to a length of hose sufficient to provide coverage for the area left unprotected by the inoperable hose station.
The hose for the unprotected area shall be stored at the OPERABLE hose station. Signs identifying the purpose and location of the fire hose and related valves shall be mounted above the hose and at the inoperable hose station.
PALO VERDE UNITS 1, 2, 3 T3.11.104-2 Rev 4 9/24/29
Fire Hose Stations TRM 3.11.104 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.11.104.1 Visually inspect each of the fire hose 31 days stations shown in Table 3.11.104-1 accessible during plant operation to assure all required equipment is at the station.
TSR 3.11.104.2 Visually inspect each of the fire hose 18 months stations shown in Table 3.11.104-1 not accessible during plant operation to assure all required equipment is at the station.
TSR 3.11.104.3 Remove the hose at each of the fire hose 18 months stations shown in Table 3.11.104-1 for inspection and reracking.
TSR 3.11.104.4 Inspect all gaskets and replace any 18 months degraded gaskets in the couplings at each of the fire hose stations shown in Table 3.11.104-1.
TSR 3.11.104.5 For each of the fire hose stations shown 3 years in Table 3.11.104-1, partially open each hose station valve to verify valve operability and no flow blockage.
TSR 3.11.104.6 For each of the fire hose stations shown 3 years in Table 3.11.104-1, conduct a hose hydrostatic test at a pressure of 150 psig or at least 50 psig above maximum fire main operating pressure, whichever is greater.
PALO VERDE UNITS 1, 2, 3 T3.11.104-3 Rev 4 9/24/29
Fire Hose Stations TRM 3.11.104 Table 3.11.104-1 (Formerly TS Table 3.7-4)
FIRE HOSE STATIONS LOCATION ELEVATION HOSE RACK IDENTIFICATION Containment NE 80 HS # 01 Containment SE 80 HS # 02 Containment SW 80 HS # 03 Containment NW 80 HS # 04 Containment NE 100 HS # 05 Containment SE 100 HS # 06 Containment SW 100 HS # 07 Containment NW 100 HS # 08 Containment NE 120 HS # 09 Containment SE 120 HS # 10 Containment SW 120 HS # 11 Containment NW 120 HS # 12 Containment NE 140 HS # 13 Containment SW 140 HS # 14 Auxiliary Bldg. North Corridor-W 40 HS # 17 Auxiliary Bldg. North Corridor-E 40 HS # 18 Auxiliary Bldg. North Corridor-W 51 6 HS # 21 Auxiliary Bldg. North Corridor-E 51 6 HS # 22 Auxiliary Bldg SE 70 HS # 23 Auxiliary Bldg SW 70 HS # 24 Auxiliary Bldg NW 70 HS # 25 Auxiliary Bldg North Center Corridor 70 HS # 26 Auxiliary Bldg NE 70 HS # 27 Auxiliary Bldg NW 88 HS # 30 -Hose Removed-Auxiliary Bldg NE 88 HS # 31 Auxiliary Bldg SW 100 HS # 33 Auxiliary Bldg East Corridor 120 HS # 37 Auxiliary Bldg SW 120 HS # 38 Control Bldg SW 74 HS # 86 Control Bldg E 74 HS # 87 Control Bldg SW 100 HS # 88 Control Bldg East by Elevator 100 HS # 89 Control Bldg SW 120 HS # 90 Control Bldg SW 140 HS # 92 Control Bldg SW 160 HS # 94 Control Bldg SE 100 HS # 108 Fuel Bldg South 100 HS # 97 PALO VERDE UNITS 1, 2, 3 T3.11.104-4 Rev 18 3/13/02
Yard Fire Hydrants and Associated Emergency Response Vehicles TRM 3.11.105 T3.11 FIRE PROTECTION T3.11.105 Yard Fire Hydrants and associated emergency response vehicle (formerly TS 3.7.11.5)
TLCO 3.11.105 The yard fire hydrants shown in Table 3.11.105-1 and an associated equipped emergency response vehicle shall be OPERABLE.
APPLICABILITY: Whenever equipment in the areas protected by yard fire hydrants is required to be OPERABLE.
ACTIONS
NOTES--------------------------
The provisions of TLCO 3.0.100.3 a are not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the yard A.1 Have sufficient 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> fire hydrants shown in additional lengths of Table 3.11.105-1 2-1/2 inch diameter hose inoperable. located in an OPERABLE, equipped emergency response vehicle to provide service from an OPERABLE yard fire hydrant adjacent to the unprotected area(s).
B. Equipped emergency B.1 Have another equipped 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> response vehicle emergency response inoperable. vehicle OPERABLE.
PALO VERDE UNITS 1, 2, 3 T3.11.105-1 Rev 46 1/8/09
Yard Fire Hydrants and Associated Emergency Response Vehicles TRM 3.11.105 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.11.105.1 Visually inspect the emergency response 31 days vehicle to assure all required equipment is in the emergency response vehicles.
TSR 3.11.105.2 Visually inspect each of the yard fire 6 months hydrants shown in Table 3.11.105-1 for damage.
TSR 3.11.105.3 Conduct a hose hydrostatic test on each 12 months hose in the equipped emergency response vehicle at a pressure of 150 psig or at least 50 psig above maximum fire main operating pressure, whichever is greater.
TSR 3.11.105.4 Inspect all gaskets and replace any 12 months degraded gaskets in the couplings in the yard fire hydrants shown in Table 3.11.105-1.
TSR 3.11.105.5 Perform a flow check of each of the yard 12 months fire hydrants shown in Table 3.11.105-1 hydrant to verify its OPERABILITY.
PALO VERDE UNITS 1, 2, 3 T3.11.105-2 Rev 4 9/24/99
Yard Fire Hydrants and Associated Emergency Response Vehicles TRM 3.11.105 TABLE 3.11.105-1 YARD FIRE HYDRANTS LOCATION HYDRANT NUMBER Unit 1:
150 Plant North of Fuel Bldg. F. H. #7 100 Plant West of Rad Waste Bldg. F. H. #9 150 Plant Northwest of Fuel Bldg. F. H. #8 100' South of Control Bldg. F. H. #10 Unit 2:
150 Plant North of Fuel Bldg. F. H. #15 100 Plant West of Rad Waste Bldg. F. H. #16 150 Plant Northwest of Fuel Bldg. F. H. #17 100' South of Control Bldg. F. H. #18 Unit 3:
150 Plant North of Fuel Bldg. F. H. #23 100 Plant West of Rad Waste Bldg. F. H. #24 150 Plant Northwest of Fuel Bldg. F. H. #25 100' South of Control Bldg. F. H. #26 PALO VERDE UNITS 1, 2, 3 T3.11.105-3 Rev 18 3/13/02
Halon Systems TRM 3.11.106 T3.11 FIRE PROTECTION T3.11.106 Halon Systems (formerly TS 3.7.11.6)
TLCO 3.11.106 The following Halon systems shall be OPERABLE.
- a. Train A Remote Shutdown Panel Room, Zone 10A -
Control Building 100 ft Elevation.
- b. Train B Remote Shutdown Panel Room, Zone 10B -
Control Building 100 ft. Elevation.
APPLICABILITY: Whenever equipment protected by the Halon system is required to be OPERABLE.
ACTIONS
NOTES--------------------------
The provisions of TLCO 3.0.100.3 are not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the A.1 Establish a continuous 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> required Halon systems fire watch with backup inoperable in areas in fire suppression which redundant systems equipment.
or components could be damaged.
(continued)
PALO VERDE UNITS 1, 2, 3 T3.11.106-1 Rev 40 2/21/07 CORRECTED April 20, 2007
Halon Systems TRM 3.11.106 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B. One or more of the B.1 Establish an hourly fire 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> required Halon systems watch patrol.
inoperable in areas other than those in which redundant systems or components could be damaged.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.11.106.1 For each of the required Halon systems, 31 days verify that each valve (manual, power operated, or automatic) in the flow path is in its correct position.
TSR 3.11.106.2 For each of the required Halon systems, 6 months verify Halon storage tank weight or level to be at least 95% of full charge weight or level and pressure to be at least 90% of full charge pressure.
TSR 3.11.106.3 For each of the required Halon systems, 18 months verify the system actuates manually and automatically, upon receipt of a simulated test signal.
TSR 3.11.106.4 For each of the required Halon systems, 18 months perform a flow test through headers and nozzles to assure no blockage.
TSR 3.11.106.5 For each of the required Halon systems, 54 months verify each circuit from the control panel to the fire damper actuation devices is capable of performing its intended function.
TSR 3.11.106.6 For each of the required Halon systems, 54 months perform a functional test of associated fire dampers.
PALO VERDE UNITS 1, 2, 3 T3.11.106-2 Rev 49 11/06/09
Fire-Rated Assemblies TRM 3.11.107 T3.11 FIRE PROTECTION T3.11.107 Fire-Rated Assemblies (formerly TS 3.7.12)
TLCO 3.11.107 All fire-rated assemblies (walls, floor/ceilings, cable tray enclosures, and other fire barriers) separating safety-related fire areas or separating portions of redundant systems important to safe shutdown within a fire area and all sealing devices in fire-rated assembly penetrations (fire doors, fire dampers, cable, piping and ventilation duct penetration seals) shall be OPERABLE.
APPLICABILITY: When the equipment in an affected area is required to be OPERABLE.
ACTIONS
NOTES--------------------------
The provisions of TLCO 3.0.100.3 are not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the A.1 Establish a continuous 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> required fire-rated fire watch* on at least assemblies (including one side of the sealing devices) affected assembly.
OR A.2.1 Verify the OPERABILITY 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of the fire detectors on at least one side of the inoperable assembly.
AND (continued)
PALO VERDE UNITS 1, 2, 3 T3.11.107-1 Rev 40 2/21/07 CORRECTED April 20, 2007
Fire-Rated Assemblies TRM 3.11.107 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME A.2.2 Establish an hourly 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> fire watch* patrol.
- Closed circuit TV may be used in lieu of fire watches in radiation areas that would pose an unnecessary risk to personnel.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.11.107.1 For each of the required fire doors, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> verify that doors with automatic hold-open and release mechanisms are free of obstructions.
TSR 3.11.107.2 For each of the required fire doors, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> verify that each unlocked fire door without electrical supervision is closed.
TSR 3.11.107.3 For each of the required fire doors, 7 days verify that each locked-closed fire door is closed.
TSR 3.11.107.4 For each of the required fire doors, 6 months inspect the automatic hold-open, release and closing mechanism and latches.
TSR 3.11.107.5 For each of the required fire-rated 18 months assemblies and penetration devices, perform a visual inspection of the exposed surfaces of each fire rated assembly.
(continued)
PALO VERDE UNITS 1, 2, 3 T3.11.107-2 Rev 4 9/24/99
Fire-Rated Assemblies TRM 3.11.107 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY TSR 3.11.107.6 For each of the required fire-rated 18 months assemblies and penetration devices, perform a visual inspection of at least 10% of each type of sealed penetration.
If apparent changes in appearance or abnormal degradations are found, a visual inspection of an additional 10% of each type of sealed penetration shall be made.
This inspection process shall continue until a 10% sample with no apparent changes in appearance or abnormal degradation is found. Samples shall be selected such that each penetration seal will be inspected every 15 years.
TSR 3.11.107.7 For each of the required fire-rated 18 months assemblies and penetration devices, perform a visual inspection of 10% of the fire dampers and associated hardware, coincident with functional testing of the dampers.
TSR 3.11.107.8 For each of the required fire-rated 18 months assemblies and penetration devices, perform a functional test of at least 10%
of the fire dampers that are installed in fire barriers separating redundant trains important to safe shutdown. If any dampers fail to operate correctly, an additional 10% of the dampers shall be sampled. This process shall continue until a 10% sample is verified OPERABLE.
Samples shall be selected such that each damper will be inspected every 15 years.
TSR 3.11.107.9 For each of the required fire doors, 18 months perform a functional test.
PALO VERDE UNITS 1, 2, 3 T3.11.107-3 Rev 4 9/24/99
Design Features TRM 4.0.100 T4.0 DESIGN FEATURES Refer to PVNGS Improved Technical Specification 4.0.
PALO VERDE UNITS 1, 2, 3 T4.0.100-1 Rev 0 8/13/98
Responsibility TRM 5.0.100 T5.0 ADMINISTRATIVE CONTROLS T5.0.100 Responsibility Refer to PVNGS Improved Technical Specifications Section 5.1 (continued)
PALO VERDE UNITS 1, 2, 3 T5.0.100-1 Rev 0 8/13/98
Organization TRM 5.0.200 T5.0 ADMINISTRATIVE CONTROLS T5.0.200 Organization Refer to PVNGS Improved Technical Specifications Section 5.2 (continued)
PALO VERDE UNITS 1, 2, 3 T5.0.200-1 Rev 0 8/13/98
Unit Staff Qualifications TRM 5.0.300 T5.0 ADMINISTRATIVE CONTROLS T5.0.300 Unit Staff Qualifications Refer to PVNGS Improved Technical Specifications Section 5.3 (continued)
PALO VERDE UNITS 1, 2, 3 T5.0.300-1 Rev 0 8/13/98
Procedures TRM 5.0.400 T5.0 ADMINISTRATIVE CONTROLS T5.0.400 Procedures Refer to PVNGS Improved Technical Specifications Section 5.4 (continued)
PALO VERDE UNITS 1, 2, 3 T5.0.400-1 Rev 0 8/13/98
Programs and Manuals TRM 5.0.500 T5.0 ADMINISTRATIVE CONTROLS T5.0.500 Programs and Manuals The following programs shall be established, implemented and maintained.
5.0.500.1 Offsite Dose Calculation Manual (ODCM)
The purpose of the ODCM program is to contain the information, methodology and parameters used in calculating offsite dose as well as the related controls, monitoring activities and descriptions of the information to be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports. The Radiation Protection group is the program owner.
In addition to the program requirements specified in ITS 5.5.1, the following also applies:
- a. The Radiological Environmental Monitoring Program shall be contained in the ODCM.
5.0.500.2 Primary Coolant Sources Outside Containment The purpose of the Primary Coolant Sources Outside Containment Program is to minimize leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable. The PVNGS System Engineering (NSSS) group is the program owner.
In addition to the program requirements specified in ITS 5.5.2, the following also applies:
- a. At least once per 18 months, during shutdown, conduct an inspection of all ECCS piping outside of containment, which is in contact with recirculation sump inventory during LOCA conditions and verify that the total measured leakage from piping and components is less than 1500 ml/hr when pressurized to at least 40 psig.
- b. The provisions of TLCO 3.0.100.3 and TSR 3.0.100.3 are applicable to the inspection performed in T5.0.500.2a.
(continued)
PALO VERDE UNITS 1, 2, 3 T5.0.500-1 Rev 53 11/10/10
Programs and Manuals TRM 5.0.500 5.0.500 Programs and Manuals (continued) 5.0.500.3 Post Accident Sampling Deleted 5.0.500.4 Radioactive Effluent Controls Program The purpose of the Radioactive Effluent Controls Program is to specify the PVNGS measures used to control radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable. The Radiation Protection group is the program owner.
In addition to the program requirements specified in ITS 5.5.4, the following also applies:
- a. Licensee-initiated major changes to the radioactive waste systems (liquid, gaseous, and solid) shall be submitted as part of the FSAR update or reported to the Commission in the Annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by PRB. The discussion of each change shall contain:
- 1. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59.
- 2. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;
- 3. A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems; (continued)
PALO VERDE UNITS 1, 2, 3 T5.0.500-2 Rev 24 7/25/03
Programs and Manuals TRM 5.0.500 5.0.500 Programs and Manuals (continued)
- 4. An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto;
- 5. An evaluation of the change, which shows the expected maximum exposures to a MEMBER OF THE PUBLIC in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the license application and amendments thereto;
- 6. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made; and
- 7. An estimate of the exposure to plant operating personnel as a result of the change.
The program elements of the Radioactive Effluent Controls Program are described in the Offsite Dose Calculation Manual (ODCM).
5.0.500.5 Component Cyclic or Transient Limit The purpose of the Component cyclic or Transient Limit Program is to track the UFSAR Section 3.9.1.1 cyclic and transient occurrences to ensure that components are maintained within the design limits. The PVNGS System Engineering (NSSS) group is the program owner.
The program requirements are specified in ITS 5.5.5.
(continued)
PALO VERDE UNITS 1, 2, 3 T5.0.500-3 Rev 0 8/13/98
Programs and Manuals TRM 5.0.500 5.0.500 Programs and Manuals (continued) 5.0.500.6 Pre-Stressed Concrete Containment Tendon Surveillance Program The purpose of the Pre-Stressed Concrete Containment Tendon Surveillance Program is to ensure containment structural integrity by providing controls for monitoring any tendon degradation and the effectiveness of the corrosion protection medium. The PVNGS Program Engineering group is the program owner.
The structural integrity of the containment vessel shall be demonstrated at the end of 1, 3, and 5 years following the initial containment vessel structural integrity test and at 5-year intervals thereafter except where relief has been authorized by the NRC. All of the acceptance testing of tendon and visual examinations of end anchorages, adjacent concrete surfaces and containment vessel surfaces shall be performed sequentially and within the same time frame.
In addition to the program requirements specified in ITS 5.5.6, the following also applies:
- a. The structural integrity of the containment vessel shall be maintained at a level consistent with the acceptance criteria in the Pre-Stressed Concrete Containment Tendon Surveillance Program while in MODES 1, 2, 3, and 4.
Refer to TRM specification T3.6.200 for specification requirements. The provisions of TLCO 3.0.100.3 and TSR 3.0.100.3 are applicable to the Pre-Stressed Concrete Containment Tendon Surveillance Program.
(continued)
PALO VERDE UNITS 1, 2, 3 T5.0.500-4 Rev 53 11/10/10
Programs and Manuals TRM 5.0.500 5.0.500 Programs and Manuals (continued)
- b. The structural integrity of the tendons shall be demonstrated by:
- 1. Determining from a random but representative sample of at least 10 tendons (6 hoop and 4 inverted U) that each group (
hoop, and inverted U) has an observed lift-off force within the predicted limits for that group. For each subsequent inspection one tendon from each group shall be kept unchanged to develop a history and to correlate the observed data. The procedure of inspection and the tendon acceptance criteria shall be as follows:
(a) If the measured prestressing force of the selected tendon in a group lies above the prescribed lower limit, the lift-off test is considered to be a positive indication of the sample tendon's acceptability; (b) If the measured prestressing force of the selected tendon in a group lies between the prescribed lower limit and 90% of the prescribed lower limit, two tendons, one on each side of this tendon, shall be checked for their prestressing forces. If the prestressing forces of these two tendons are above 95%
of the prescribed lower limits for tendons, all three tendons shall be restored to the required level of integrity, and the tendon group shall be considered acceptable. If the measured prestressing force of any two tendons falls below 95% of the prescribed lower limits of the tendons, additional lift-off testing shall be done to detect the cause and extent of such occurrence; (c) If the measured prestressing force of any tendon lies below 90% of the prescribed lower limit, the defective tendon shall be completely detensioned and additional lift-off testing shall be performed to determine the cause and extent of such occurrence; (continued)
PALO VERDE UNITS 1, 2, 3 T5.0.500-5 Rev 0 8/13/98
Programs and Manuals TRM 5.0.500 5.0.500 Programs and Manuals (continued)
(d) If the average of all measured prestressing forces for each group (corrected for average condition) is found to be less than the minimum required prestress level at anchorage location for that group, the condition shall be considered as below the acceptance criteria for containment vessel structural integrity; and (e) Unless there is degradation of the containment vessel below the acceptance criteria during the first three inspections, the sample population for subsequent inspections shall include at least 6 tendons (3 hoop and 3 inverted U).
- 2. Performing tendon detensioning, inspections, and material tests on a previously stressed tendon from each group. A randomly selected tendon from each group shall be completely detensioned in order to identify broken or damaged wires. A previously stressed tendon wire or strands from one tendon of each group shall be removed for testing and examination over the entire length to determine (which should include the broken wire if so identified) that:
(a) The tendon wires are free of corrosion, cracks, and damage; (b) There are no changes in the presence or physical appearance of the sheathing filler-grease; and (c) A minimum tensile strength of 240,000 psi (guaranteed ultimate strength of the tendon material) exists for at least three wire samples (one from each end and one at mid-length) cut from each removed wire. Failure of any one of the wire samples to meet the minimum tensile strength test is evidenced that structural integrity is below the acceptance criteria.
- 3. Performing tendon retensioning of those tendons detensioned for inspection to at least force level recorded prior to detensioning or the predicted value, whichever is greater, with the tolerance within minus zero to plus 6%, except that (continued)
PALO VERDE UNITS 1, 2, 3 T5.0.500-6 Rev 0 8/13/98
Programs and Manuals TRM 5.0.500 5.0.500 Programs and Manuals (continued) the final seating force shall be such that the stress in the wire or strand shall not exceed 70% of the guaranteed ultimate tensile strength of the tendons. During retensioning of these tendons, the stress in the tendon shall not exceed 80% of its ultimate strength, and the changes in load and elongation shall be measured simultaneously at a minimum of three approximately equally spaced levels of force between zero and the seating force.
If the elongation corresponding to a specific load differs by more than 10% from that recorded during installation, an investigation shall be made to ensure that the difference is not related to wire failures or slips of wires in anchorages; and
- 4. Verifying the OPERABILITY of the sheathing filler-grease by assuring:
(a) No voids in excess of 5% of the net duct volume, (b) Minimum grease coverage exists for the different parts of the anchorage system, and (c) The chemical properties of the filler material are within the tolerance limits specified as follows:
Water content 0 - 5% by wt.
Chlorides 0 - 10 ppm Nitrates 0 - 10 ppm Sulfides 0 - 5 ppm Reserved Alkalinity 0 - 50% of the installed value (Base Numbers) (installed value 0 - 5 for older grease)
- c. As an assurance of the structural integrity of the containment vessel, tendon anchorage assembly hardware (such as bearing plates, stressing washers, wedges, and buttonheads) of all tendons selected for inspection shall be visually examined. For those containments in multiple unit plants for which only visual inspection need be performed, tendon anchorages selected for inspection shall be visually (continued)
PALO VERDE UNITS 1, 2, 3 T5.0.500-7 Rev 0 8/13/98
Programs and Manuals TRM 5.0.500 5.0.500 Programs and Manuals (continued) examined to the extent practical without dismantling the load-bearing components of the anchorages. The surrounding concrete shall also be checked visually for indication of any abnormal condition.
- d. The exterior surface of the containment vessel shall be visually examined to detect areas of large spall, severe scaling, D-cracking in an area of 25 sq. ft. or more, other surface deterioration or disintegration, or grease leakage, each of which can be considered as evidence that the structural integrity is below the acceptance criteria.
(continued)
PALO VERDE UNITS 1, 2, 3 T5.0.500-8 Rev 22 3/7/03
Programs and Manuals TRM 5.0.500 5.0.500 Programs and Manuals (continued)
Table 5.0.500-1 (page 1 of 2)
Tendon Test Criteria Tendon Surveillance - First Year Tendon Visual Inspection Detension Tendon, Number and Remove and Test Monitor Forces Wire V32 X No V43 X No V62 X X V75* X A H13-007* X X H13-021 X No H21-037 X No H21-044 X No H32-016 X No H32-030 X X
NOTES------------------------------------
- 1. X means the tendon shown shall be inspected for the stated requirements during this surveillance.
- 2. A means the tendon shown shall be inspected for the stated requirements during the next or second surveillance.
- 3. No means that inspection is not required for that tendon.
- 4.
- means control tendon.
(continued)
PALO VERDE UNITS 1, 2, 3 T5.0.500-9 Rev 0 8/13/98
Programs and Manuals TRM 5.0.500 5.0.500 Programs and Manuals (continued)
Table 5.0.500-1 (page 2 of 2)
Tendon Test Criteria Lift-Off Force First Year U-Tendons TENDON TENDON MAXIMUM MINIMUM NUMBER END (kips) (kips)
V32 Shop 1463 1343 Field 1510 1386 V43 Shop 1436 1364 Field 1486 1364 V62 Shop 1475 1354 Field 1486 1364 V75 Shop 1527 1402 Field 1504 1380 Hoop Tendons TENDON TENDON MAXIMUM MINIMUM NUMBER END (kips) (kips)
H13-007 Shop 1428 1300 Field 1451 1321 H13-021 Shop 1515 1380 Field 1491 1358 H21-037 Shop 1505 1371 Field 1446 1317 H21-044 Shop 1484 1360 Field 1530 1403 H32-016 Shop 1411 1282 Field 1457 1324 H32-030 Shop 1473 1330 Field 1473 1330 (continued)
PALO VERDE UNITS 1, 2, 3 T5.0.500-10 Rev 0 8/13/98
Programs and Manuals TRM 5.0.500 5.0.500 Programs and Manuals (continued) 5.0.500.7 Reactor Coolant Pump Flywheel Inspection Program The purpose of the Reactor Coolant Pump Flywheel Inspection Program is to provide for the inspection of each reactor coolant pump flywheel. The PVNGS Program Engineering group is the program owner.
The program requirements are specified in ITS 5.5.7.
5.0.500.8 Inservice Inspection and Testing Programs The purpose of the Inservice Inspection (ISI) and Inservice Testing (IST) Programs is to provide controls for ASME inspection and testing of ASME Code Class 1, 2 and 3 components. The PVNGS Program Engineering group is the program owner for IST and the PVNGS Component Programs group is the program owner for ISI.
In addition to the program requirements specified in ITS 5.5.8, the following also applies:
- a. Inservice inspection shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g).
- b. Inservice Testing shall be performed in accordance with the ASME Code for Operation and Maintenance of Nuclear Power Plants (ASME OM Code) and applicable Addenda as required by 10 CFR 50.55a(f).
- c. The testing frequency specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as specified in PVNGS ITS 5.5.8.a for ITS and TRM requirements.
- d. The provisions of ITS SR 3.0.2 are applicable to ITS 5.5.8.a for performing inservice inspection and testing activities. The testing frequency specified in the ASME OM Code and applicable Addenda for the inservice testing activities required by the ASME OM Code and applicable Addenda shall be as specified in PVNGS ITS 5.5.8a for ITS and TRM requirements.
(continued)
PALO VERDE UNITS 1, 2, 3 T5.0.500-11 Rev 54 1/26/11
Programs and Manuals TRM 5.0.500 5.0.500 Programs and Manuals (continued)
- e. When testing ECCS trains pursuant to PVNGS ITS SR 3.5.3.3, verify that each of the following pumps develops the indicated differential pressure at or greater than their respective minimum allowable recirculation flow:
- 1. High pressure safety injection pump greater than or equal to 1761 psid.
- 2. Low pressure safety injection pump greater than or equal to 165 psid.
- f. When testing the Containment Spray System pursuant to PVNGS ITS SR 3.6.6.3, verify that each pump develops an indicated head differential pressure of greater than or equal to 260 psid at greater than or equal the minimum allowable recirculation flowrate.
- g. The provisions of TLCO 3.0.100.3 and TSR 3.0.100.3 are applicable to the program requirements T5.0.500.8e and T5.0.500.8.f.
5.0.500.9 Steam Generator (SG) Tube Surveillance Program The purpose of the Steam Generator Tube Surveillance Program is to provide controls for the Inservice Inspection of steam generator tubes to ensure that structural integrity of this portion of the RCS is maintained. The PVNGS System Engineering Group is the program owner.
The program requirements are specified in ITS 5.5.9.
(continued)
PALO VERDE UNITS 1, 2, 3 T5.0.500-12 Rev 54 1/26/11
Programs and Manuals TRM 5.0.500 5.0.500 Programs and Manuals (continued) 5.0.500.10 Secondary Water Chemistry Program The purpose of the Secondary Water Chemistry Program is to provide controls for monitoring secondary water chemistry to inhibit SG tube degradation and low pressure turbine disc stress corrosion cracking. The PVNGS Chemistry group is the program owner.
Program requirements are specified in PVNGS TS 5.5.10.
5.0.500.11 Ventilation Filter Testing Program (VFTP)
The purpose of the Ventilation Filter Testing Program is to implement the required testing of the TS and TRM filter ventilation systems. The PVNGS Electrical Maintenance (HVAC) group is the program owner.
Program requirements for the Control Room Essential Filtration System (CREFS) and ESF Pump Room Exhaust Air Cleanup System (ESF PREACS) are specified in PVNGS TS 5.5.11 and as supplemented herein.
Program requirements for the Hydrogen Purge Cleanup system (HPCS) and the Fuel Building Essential Ventilation System (FBEVS) are contained herein.
The following requirements apply:
- 1. When testing pursuant to PVNGS TS SR 3.7.11.2, TS SR 3.7.13.2, TSR 3.6.100.2 and TSR 3.9.104.2, the CREFS, PREACS, HPCS and FBEVS shall be demonstrated OPERABLE at least once per 18 months or:
(a) after any maintenance affecting the airflow distribution or integrity of the HEPA or charcoal adsorber filter banks, or (b) following painting, fire, or a chemical release in any ventilation zone communicating with the system that has been evaluated to have the potential to adversely affect the integrity of the filters.
- 2. When testing the CREFS, PREACS, HPCS and FBEVS pursuant to PVNGS TS SR 3.7.11.2, TS SR 3.7.13.2, TSR 3.6.100.2 and TSR (continued)
PALO VERDE UNITS 1, 2, 3 T5.0.500-13 Rev 11 12/14/00
Programs and Manuals TRM 5.0.500 5.0.500 Programs and Manuals (continued) 3.9.104.2, perform the in-place testing activities in accordance with Regulatory Positions C.5.a, C.5.c, and C.5.d of Regulatory Guide 1.52, Revision 2, March 1978 and the PVNGS VFTP. (In response to NRC Generic Letter 83-13).
- 3. After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation and when testing the CREFS and PREACS pursuant to PVNGS TS 5.5.11.c, the HPCS pursuant to PVNGS TRM TSR 3.6.100.2, and the FBEVS pursuant to TRM TSR 3.9.104.2, verify within 31 days after a representative charcoal sample is removed, being obtained in accordance with the application of Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, as described in Section 1.8 of the UFSAR, that the methyl iodide penetration is less than or equal to the value specified below, when tested in accordance with ASTM D3803-1989, at a temperature of 30°C and relative humidity specified as follows:
Penetration RH CREFS <2.5% 70%
ESF PREACS/FBEVS <2.5% 70%
HPCS <2.5% 70%
- 4. After each complete or partial replacement of a HEPA filter bank for the HPCS and FBEVS by verifying that the HEPA filter banks remove greater than or equal to 99.0% of the DOP when they are tested in-place in accordance with ANSI N510-1980.
The system flowrates for the HPCS and FBEVS are as specified below +/- 10%:
- 5. After each complete or partial replacement of a charcoal adsorber bank for the HPCS and FBEVS by verifying that the charcoal adsorbers remove greater than or equal to 99.0% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1980. The system flowrates for the HPCS and FBEVS are as specified below +/-
10%:
- 6. For the HPCS and FBEVS, demonstrate at least once per 18 months that the pressure drop across the combined HEPA filters, the prefilters, and the charcoal adsorbers is as specified below when tested in accordance with Regulatory Guide 1.52, (continued)
PALO VERDE UNITS 1, 2, 3 T5.0.500-14 Rev 20 7/5/02
Programs and Manuals TRM 5.0.500 5.0.500 Programs and Manuals (continued)
Revision 2 and ANSI N510-1980 at the system flowrate specified as follows +/- 10%:
Ventilation System Delta P Flowrate HPCS < 2.26 inches water gauge 50 CFM FBEVS 5.2 inches water gauge 6000 CFM
- 7. For the system specified below, demonstrate at least once per 18 months that the heaters dissipate at least the following specified value when tested in accordance with ANSI N510-1980:
Ventilation System Wattage HPCS 0.5 kW
- 8. The provisions of TLCO 3.0.100.3 and TSR 3.0.100.3 are applicable to the requirements of T5.0.500.11.1 (a) and (b),
T5.0.500.11.3, T5.0.500.11.4, T5.0.500.11.5, T5.0.500.11.6 and T5.0.500.11.7.
5.0.500.12 Explosive Gas and Storage Tank Radioactivity Monitoring Program The purpose of the Explosive Gas and Storage Tank Radioactivity Monitoring Program is to provide control for potentially explosive gas mixtures contained in the Waste Gas Holdup System, and for the quantity of radioactivity contained in gas storage tanks and unprotected outdoor liquid storage tanks. The PVNGS Chemistry group is the program owner.
The program requirements are specified in ITS 5.5.12.
Refer to TRM specifications T3.10.200, T3.10.201 and T3.10.202 for specification requirements.
5.0.500.13 Diesel Fuel Oil Testing Program The purpose of the Diesel Fuel Oil Testing Program is to ensure the acceptability of fuel oil prior to addition to storage tanks.
The PVNGS Chemistry group is the program owner.
The program requirements are specified in ITS 5.5.13.
(continued)
PALO VERDE UNITS 1, 2, 3 T5.0.500-15 Rev 53 11/10/10
Programs and Manuals TRM 5.0.500 5.0.500 Programs and Manuals (continued) 5.0.500.14 Technical Specifications (TS) Bases Control Program The purpose of the Technical Specifications Bases Control Program is to provide a means for processing changes to the Bases of the PVNGS ITS. Nuclear Regulatory Affairs is the program owner.
Program requirements are specified in ITS 5.5.14.
5.0.500.15 Safety Function Determination Program (SFDP)
The purpose of the Safety function Determination Program is to ensure that a loss of safety function is detected and appropriate actions taken. The PVNGS Operations group is the program owner.
Program requirements are specified in ITS 5.5.15.
5.0.500.16 Containment Leakage Rate Testing Program The purpose of the Containment Leakage Rate Testing Program is to implement the required containment leakage rate testing. The PVNGS Program Engineering group is the program owner.
In addition to the program requirements specified in ITS 5.5.16, the following also applies:
- a. Demonstrate CONTAINMENT INTEGRITY after each closing of each penetration subject to Type B testing, except containment air locks, if opened following a Type A or B test, by leak rate testing in accordance with ITS 5.5.16.
- b. Leakage rate acceptance criteria:
- 1. For the required 42 inch containment purge supply and exhaust isolation valves with resilient material seals measured leakage rate is less than or equal to 0.05 La when pressurized to Pa.
- 2. For 8 inch containment purge supply and exhaust isolation valves with resilient material seals measured leakage rate is less than or equal to 0.01 La when pressurized to Pa.
- c. The provisions of TLCO 3.0.100.3 and TSR 3.0.100.3 are applicable to the requirements of T5.0.500.16 a and b.
(continued)
PALO VERDE UNITS 1, 2, 3 T5.0.500-16 Rev 53 11/10/10
Programs and Manuals TRM 5.0.500 5.0.500 Programs and Manuals (continued) 5.0.500.17 Process Control Program (PCP)
The purpose of the Process Control Program is to contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste. The PVNGS Radiation Protection Group is the program owner.
Requirements for changes to the PCP are contained in the PVNGS QA Plan.
5.0.500.18 Technical Requirements Manual (TRM) Control Program The purpose of the Technical Requirements Manual Control Program is to provide a means for establishing controls and processing changes to the TRM. Nuclear Regulatory Affairs is the program owner.
5.0.500.19 Configuration Risk Management Program (CRMP)
The Configuration Risk Management Program (CRMP) provides a proceduralized risk-informed assessment to manage the risk associated with equipment inoperability. The program applies to technical specification structures, systems, and components for which a risk-informed Completion Time has been granted. The program shall include the following elements:
- a. Provisions for the control and implementation of a Level 1 at-power internal events PRA-informed methodology. The assessment is to be capable of evaluating the applicable plant configuration.
- b. Provisions for performing an assessment prior to entering the plant configuration described by the Limiting Conditions for Operation (LCO) Action Statement for preplanned activities.
(continued)
PALO VERDE UNITS 1, 2, 3 T5.0.500-17 Rev 8 3/17/00
Programs and Manuals TRM 5.0.500 5.0.500 Programs and Manuals (continued)
- c. Provisions for performing an assessment after entering the plant configuration described by the LCO Action Statement for unplanned entry into the LCO Action Statement.
- d. Provisions for assessing the need for additional actions after the discovery of additional equipment-out-of service conditions while in the plant configuration described by the LCO Action Statement.
- e. Provisions for considering other applicable risk-significant contributors such as Level 2 issues and external events, qualitatively or quantitatively.
(continued)
PALO VERDE UNITS 1, 2, 3 T5.0.500-18 Rev 8 3/17/00
Reporting Requirements TRM 5.0.600 T5.0 ADMINISTRATIVE CONTROLS T5.0.600 Reporting Requirements T5.0.600.1 Annual Reports In addition to the requirements of PVNGS ITS 5.6, annual reports shall also include the results of specific activity analysis in which the primary coolant exceeded the limits of PVNGS ITS 3.4.17.
The following information shall be included:
(1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than limit.
Each result should include date and time of sampling and the radioiodine concentrations:
(3) Clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radioiodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit.
T5.0.600.2 Startup Reports The requirement to submit startup reports to the NRC has been deleted. However, appropriate testing and retention of startup test records will continue to be performed in accordance with the requirements of 10 CFR 50, Appendix B, and the PVNGS Quality Assurance Program. Records will be maintained in accordance with the requirements of PVNGS UFSAR Section 1.8.
(continued)
PALO VERDE UNITS 1, 2, 3 T5.0.600-1 Rev 37 8/17/06
Reporting Requirements TRM 5.0.600 Reporting Requirements (continued)
T5.0.600.3 Operating Data Reporting Provide to the NRC, using an industry database such as the Consolidated Data Entry program, the operating data (for each calendar month) that is described in Generic Letter 97-02, Revised Contents of the Monthly Operating Report, by the last day of the month following the end of each calendar quarter.
PALO VERDE UNITS 1, 2, 3 T5.0.600-2 Rev 37 8/17/06
High Radiation Area TRM 5.0.700 T5.0 ADMINISTRATIVE CONTROLS T5.0.700 High Radiation Area Refer to PVNGS Improved Technical Specifications Section 5.7 PALO VERDE UNITS 1, 2, 3 T5.0.700-1 Rev. 34 6/15/05
TRM Specification Bases TRM 6.0.100 T3.0.100 T6.0 TRM SPECIFICATION BASES T3.0 TLCO Applicability TLCO 3.0.100.1 See ITS LCO 3.0.1 Specification Bases TLCO 3.0 100.2 See ITS LCO 3.0.2 Specification Bases TLCO 3.0 100.3 See ITS LCO 3.0.3 Specification Bases TLCO 3.0 100.4 See ITS LCO 3.0.3 Specification Bases TLCO 3.0 100.5 See ITS LCO 3.0.4 Specification Bases T3.0 TRM Surveillance Requirent (TRS) Applicability TSR 3.0.100.1 See ITS SR 3.0.1 Specification Bases TSR 3.0.100.2 See ITS SR 3.0.2 Specification Bases TSR 3.0.100.3 See ITS SR 3.0.3 Specification Bases TSR 3.0.100.4 See ITS SR 3.0.3 Specification Bases (continued)
PALO VERDE UNITS 1, 2, 3 T6.0.100-1 Rev 40 2/21/07
TRM Specification Bases TRM 6.0.100 T3.0.100 T6.0 TRM SPECIFICATION BASES T3.1.100 Flow Paths - Shutdown T3.1.101 Flow Paths - Operating T3.1.102 Charging Pumps - Shutdown T3.1.103 Charging Pumps - Operating T3.1.104 Borated Sources - Shutdown T3.1.105 Borated Sources - Operating BACKGROUND Boration equipment is needed to support reactivity control and the pressure and inventory control safety functions during normal operations and anticipated operational occurrences. A functional boration "system" consists of a borated water source, a gravity-fed suction pathway, a pump capable of being powered from an emergency power supply, and a discharge path to the RCS.
Use of redundant components within the chemical and volume control, safety injection, and spent fuel pool cooling systems enhances flexibility and reliability in meeting design requirements.
Soluble boron in the reactor coolant and control rods provide two diverse methods of core reactivity control. In accordance with the provisions of GDC 26, boration systems can reliably control the rate of reactivity changes resulting from planned, normal power changes, including xenon burnout, without exceeding acceptable fuel design limits. Each boration system is capable of maintaining the temperature-dependent shutdown margin and KN-1 requirements of the Technical Specifications during a cooldown. In addition, each boration system can add the boron equivalent of 4% k/k, not including the effects of xenon, during a plant cooldown to mode 5 considering only the borated makeup water used to compensate for thermal contraction of the coolant. Under normal conditions with letdown in service, the boration systems are also capable of making the core subcritical from a hot operating condition and holding it subcritical in the hot standby condition. In the event that Technical Specification shutdown margin requirements are not met during normal operations, the associated action statements direct the operator to initiate boration and continue until margins are restored. One boration system can add 1% k/k of (continued)
PALO VERDE UNITS 1, 2, 3 T6.0.100-2 Rev 40 2/21/07
TRM Specification Bases TRM 6.0.100 T3.1.100, T3.1.101, T3.1.102, T3.1.103, T3.1.104, T3.1.105 TRM SPECIFICATION BASES (continued) negative reactivity in less than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> assuming "typical" reactor physics parameters and nominal system performance with letdown in service.
In accordance with GDC 33, boration systems can supply reactor coolant makeup for protection against breaks in small lines connected to the reactor coolant pressure boundary. Small lines, such as those for instrument and sample connections, contain flow orifices to limit leakage rates within the capacity of available charging pumps. As part of the normal makeup, the boration systems assure that specified acceptable fuel design limits are not exceeded as a result of minor reactor coolant leakage with or without offsite electrical power.
GDC 10 and GDC 19 require in part that the reactor coolant system be designed with appropriate margin and controls to assure that specified acceptable fuel design limits are not exceeded during normal operation and anticipated operational occurrences. The operability of boration systems ensures that primary system pressure and inventory (pressurizer level) can be adequately controlled following a loss of offsite power and subsequent cooldown to cold shutdown conditions. In combination with the shutdown cooling system, boration systems are capable of supporting a natural circulation cooldown in accordance with the requirements of Branch Technical Position (BTP) RSB 5-1 as accepted for PVNGS as a Class 2 plant.
APPLICABLE None of the accidents analyzed in chapter 15 of the safety SAFETY analysis report require charging or auxiliary spray for ANALYSIS mitigation of the event. The boration systems support general design requirements, and verification that the systems can perform their safety functions is contained in design calculations separate from the accident analyses. Although these calculations are conservative with respect to expected system capability, they are based on nominal system conditions/performance, and the effects of instrument uncertainty are not included. The results of these analyses are summarized in UFSAR 9.3.4. Additional requirements and (continued)
PALO VERDE UNITS 1, 2, 3 T6.0.100-3 Rev 40 2/21/07
TRM Specification Bases TRM 6.0.100 T3.1.100, T3.1.101, T3.1.102, T3.1.103, T3.1.104, T3.1.105 TRM SPECIFICATION BASES (continued) commitments associated with natural circulation cooldown are presented in UFSAR Appendix 5C.
In addition to performance requirements, the general design criteria also place limits on the damage possible from malfunctions of the boration systems. GDC 28 requires that the rate of reactivity addition be limited so that postulated reactivity accidents do not result in yielding of reactor coolant pressure boundary materials or deformation of fuel and vessel internals that may impair core cooling. This is verified in part by the UFSAR 15.4.6 analysis for inadvertent deboration. Boration systems may also affect GDC 15, which requires that reactor coolant pressure boundary design limits shall not be exceeded during normal or anticipated operational occurrences. UFSAR 15.5.2 shows that charging pump flow is low enough to ensure that the bounding pressurizer level control system malfunction will not overpressurize the primary system.
LCO The OPERABILITY of the boration systems ensures the capability to control reactivity during power changes, maintain shutdown margin requirements, makeup for reduction in reactor coolant volume due to contraction and nominal system losses, makeup for losses due to small breaks in the RCS pressure boundary, provide reactor coolant pump seal injection, and control reactor coolant pressure through the use of auxiliary spray when required.
The charging pumps have a design flow of approximately 44 gpm, but pump inefficiencies result in a nominal charging pump discharge flow of about 42 gpm. Because of the nature of positive displacement pumps, the pump discharge flow rate does not vary significantly with reactor coolant system pressure.
The net charging flow is the total charging pump discharge flow minus the reactor coolant pump controlled bleed-off flow, which does not enter the reactor coolant system. With two pumps required to be OPERABLE, the minimum net charging flow of 26 gpm for a single pump ensures that the boron injection rate described in the basis of the Technical Specifications can be provided even in the event of a single failure. In addition, the nominal charging flow from a single pump provides adequate (continued)
PALO VERDE UNITS 1, 2, 3 T6.0.100-4 Rev 40 2/21/07
TRM Specification Bases TRM 6.0.100 T3.1.100, T3.1.101, T3.1.102, T3.1.103, T3.1.104, T3.1.105 TRM SPECIFICATION BASES (continued) makeup and auxiliary pressurizer spray for a natural circulation cooldown conducted in accordance the requirements of BTP RSB 5-1, which also postulates the single active failure of the other pump. Lastly, the OPERABILITY of two charging pumps ensures that the system can mitigate the effects of a small break in the reactor coolant system. Consideration of a single failure is not required in support of GDC 33, and the nominal net charging rate of 68 gpm from two charging pumps (i.e., 26 gpm + 42 gpm) exceeds the maximum break flow and provides sufficient makeup to prevent violation of fuel design limits during the subsequent controlled cooldown.
An OPERABLE charging pump must be powered from an OPERABLE ESF bus that can be energized from either an offsite circuit or an emergency diesel generator. Use of safety grade power supplies in combination with gravity-fed flow suction pathways provides a high level of assurance of boration system function during normal operations and following a loss of offsite power.
Requiring two of three boration flowpaths to be OPERABLE provides a high probability that at least one pathway will be available to connect the borated water source to the charging pump suction. All of the specified pathways are gravity-fed and therefore do not require use of non-class pumps to provide net positive suction head for the charging pumps. Since the VCT boron concentration is normally much less than 4000 ppm and the tank may be pressurized with a noncondensible gas, the two pathways that utilize the normal charging pump suction are not OPERABLE unless VCT outlet valve CH-501 can be closed.
Although not specified, the availability of an additional flow path from the charging pump discharge to the RCS is implied.
Actions outside the control room have been acknowledged in aligning the flowpaths. The specified flowpaths are neither fully safety grade nor single failure proof. However, the probability of a single-point vulnerability failing when called upon is low. In addition, high-pressure safety injection in combination with the reactor coolant head vents provides a diverse method of accomplishing the boration safety functions.
Overall this results in an acceptable level of functional reliability for the boration systems.
(continued)
PALO VERDE UNITS 1, 2, 3 T6.0.100-5 Rev 46 1/8/09
TRM Specification Bases TRM 6.0.100 T3.1.100, T3.1.101, T3.1.102, T3.1.103, T3.1.104, T3.1.105 TRM SPECIFICATION BASES (continued)
The Refueling Water Tank (RWT) is required per Technical Specifications to be OPERABLE in MODES 1-4 in order to provide an adequate supply of borated water for emergency core cooling systems in the event of a LOCA. The minimum RWT level required in the Technical Specifications ensures that sufficient volume is available above the high suction nozzle in order to conduct a natural circulation cooldown in accordance with the provisions of BTP RSB 5-1. That minimum level also provides adequate borated make-up for a small line break and all credited reactivity control functions. The Spent Fuel Pool (SFP) is also required to be OPERABLE in MODES 1-4 as a redundant borated water source to protect against single failure for the emergency boration function. In other analyses, failure of the RWT as a passive, seismic class 1, safety grade component is not a credible malfunction.
A cold shutdown reserve volume (CSDRV) is maintained to compensate for the change in reactor coolant volume that results from thermal contraction during cooldown to cold shutdown entry conditions with RCP controlled bleed-off isolated. The CSDRV also bounds the volumes of borated water required for postulated reactivity events. The minimum volumes required for both the RWT and SFP provide a high degree of reliability with respect to the reactivity control and safe shutdown capabilities. To account for depletion of makeup inventory during cooldown, the cold shutdown reserve volume requirements vary as a function of cold leg temperature. Once the primary has been cooled to cold shutdown conditions, borated water inventory is only required to makeup for further contraction during continued cool down to refueling conditions and to refill the pressurizer.
The requirements on temperature and boron concentration of the borated water sources are consistent with the values used in safety analysis and reactivity calculations. The upper limit spent fuel pool temperature is 180°F; however, the 2%
difference in density between water at 120° and 180° has negligible impact on the required volume of makeup water or its reactivity worth.
(continued)
PALO VERDE UNITS 1, 2, 3 T6.0.100-6 Rev 40 2/21/07
TRM Specification Bases TRM 6.0.100 T3.1.100, T3.1.101, T3.1.102, T3.1.103, T3.1.104, T3.1.105 TRM SPECIFICATION BASES (continued)
APPLICABILITY The normal makeup system contains three charging pumps, all of which are normally in service. With the RCS temperature above 210°F, a minimum of two charging pumps is required to mitigate the effects of a small line break over all of the expected operating pressures. A minimum of two boron injection systems is also required to ensure single functional capability in those events where an assumed failure renders one of the systems inoperable. With the RCS temperature below 210°F, one system is acceptable without single failure consideration based on the stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity changes.
In MODES 1-4, charging pumps are required in order to accomplish boron injection over the full range of expected reactor coolant system pressure. The provision of three charging pumps when only two are required provides for maintenance and flexibility of operation. In modes 5 and 6, the safety grade high pressure and low pressure safety injection pumps are capable of delivering the required flow rates. Since they are also energized from an emergency power supply, they are acceptable alternatives if a charging pump is not OPERABLE at low system pressures.
ACTIONS In MODES 1-4, the allowable out-of-service period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for one required boration system inoperable is consistent with those for safety related equipment. This time allows for minor component repair or corrective action without undue risk of overall facility safety during the repair period. If restoration can not be accomplished in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, enter TLCO 3.0.100.3 and initiate corrective action in accordance with PVNGS corrective action program and initiate an operability determination, as necessary to determine the impact on equipment in the technical specifications. This should include an assessment of the plant configuration and a determination of the appropriate compensatory action and/or Mode changes to maintain safe operation and compliance with design and licensing basis.
(continued)
PALO VERDE UNITS 1, 2, 3 T6.0.100-7 Rev 54 1/26/11
TRM Specification Bases TRM 6.0.100 T3.1.100, T3.1.101, T3.1.102, T3.1.103, T3.1.104, T3.1.105 TRM SPECIFICATION BASES (continued)
In MODES 5-6, the absence of an OPERABLE boration method represents a serious degradation in reactivity management controls. Suspension of core alterations and positive reactivity additions preclude the need for emergency boration until control can be re-established.
SURVEILLANCE Surveillance tests for the RWT in the Technical Specifications REQUIREMENTS as a supply of emergency core cooling water are more restrictive than those as a borated water source. Since SFP is as stable as the RWT with respect to temperature, level (volume), and boron concentration, the prescribed testing frequency is the same as for the RWT.
Based on operational experience, monthly verification of manual valve position in the boration flowpaths provides reasonable assurance that the system will function as designed, and remedial operator actions outside the control room in addition to those needed to normally align the system are not needed to initiate flow.
The charging pumps and valves in the boration flow paths are tested in accordance with the station in-service testing program.
(continued)
PALO VERDE UNITS 1, 2, 3 T6.0.100-8 Rev 46 1/8/09
TRM Specification Bases TRM 6.0.100 TRM SPECIFICATION BASES T3.1.200 Shutdown Margin - Reactor Trip Breakers Closed (See the ITS 3.1.2 Specification Bases.)
T3.1.201 This TRM specification is not used and is intentionally left blank.
T3.1.202 Control Element Assembly - Alignment (See the ITS 3.1.5 Specification Bases.)
T3.1.203 Control Element Assembly - Drop Time (See the ITS 3.1.5 Specification Bases.)
T3.1.204 Shutdown CEA Insertion Limits and T3.1.205 Regulating CEA Insertion Limits Safety analysis assumes that the Shutdown and Regulating Groups 1 & 2 CEAs are fully withdrawn any time the reactor is critical. This ensures that:
- a. The minimum shutdown margin (SDM) is maintained; and
- b. The potential effects of a CEA ejection accident are limited to acceptable limits.
CEAs are considered fully withdrawn at 147.75 inches (Pulse Counter indication) and 145.25 inches (RSPT indication) since this position supports the assumptions made in the safety analysis. The required CEA insertion position, as indicated by the RSPT, differs from the required CEA insertion position, as indicated by the Pulse Counter, to allow for the inaccuracies associated with the RSPT. The actual CEA position is required to be > 147.75 inches withdrawn and the Pulse Counter indication is considered to be the most accurate. Additionally, a CEA at its UEL (Upper Electrical Limit) satisfies the requirement for > 147.75 inches withdrawn.
Due to fuel design changes (Guardian Grid fuel assemblies), the active height of the core was raised resulting in the need for a higher fully withdrawn CEA position in order to maintain the active portion of the CEAs in a position supported by the safety analysis. Shutdown and Regulating Groups 1 & 2 CEAs are required to be fully withdrawn to meet the SDM requirements of the safety analysis. The CEA all rods out (ARO) position specified by the Core Data Book supports the CEA Guide Tube Wear Program, is a variable position based upon core life and does not violate the fully withdrawn CEA position required for the safety analysis SDM requirements.
Source documents: PVNGS CRDR #2634792, Operability Determination 266 and associated documentation, 10 CFR 50.59 #S-04-0201 (continued)
PALO VERDE UNITS 1, 2, 3 T6.0.100-9 Rev 40 2/21/07
TRM Specification Bases TRM 6.0.100 TRM SPECIFICATION BASES T3.2.200 Azimuthal Power Tilt - Tq The limitations on the AZIMUTHAL POWER TILT are provided to ensure that design safety margins are maintained. An AZIMUTHAL POWER TILT greater than the limit specified in the CORE OPERATING LIMITS REPORT with COLSS in service or 0.03 with COLSS out of service is not expected and if it should occur, operation is restricted to only those conditions required to identify the cause of the tilt. The tilt is normally calculated by COLSS. A minimum core power of 20%
of RATED THERMAL POWER is assumed by the CPCs in its input to COLSS for calculation of AZIMUTHAL POWER TILT. The 20% RATED THERMAL POWER threshold is due to the neutron flux detector system being inaccurate below 20% core power.
Core noise level at low power is too large to obtain usable detector readings.
The surveillance requirements specified when COLSS is out of service provide an acceptable means of detecting the presence of a steady-state tilt. It is necessary to explicitly account for power asymmetries because the radial peaking factors used in the core power distribution calculations are based on an untilted power distribution.
The AZIMUTHAL POWER TILT is equal to (Ptilt/Puntilt)-1.0 where:
AZIMUTHAL POWER TILT is measured by assuming that the ratio of the power at any core location in the presence of a tilt to the untilted power at the location is of the form:
Ptilt/Puntilt = 1 + Tq g cos (Theta - Thetao) where:
Tq is the peak fractional tilt amplitude at the core periphery g is the radial normalizing factor Theta is the azimuthal core location (continued)
PALO VERDE UNITS 1, 2, 3 T6.0.100-10 Rev 40 2/21/07
TRM Specification Bases TRM 6.0.100 TRM SPECIFICATION BASES Thetao is the azimuthal core location of maximum tilt Ptilt/Puntilt is the ratio of the power at a core location in the presence of a tilt to the power at that location with no tilt.
The AZIMUTHAL POWER TILT allowance used in the CPCs is defined as the value of CPC addressable constant TR-1.0.
T3.3.100 Supplementary Protection System (SPS) Instrumentation The OPERABILITY of the reactor protective and Engineered Safety Features Actuation Systems instrumentation and bypasses ensures that (1) the associated Engineered Safety Features Actuation action and/or reactor trip will be initiated when the parameter monitored by each channel or combination thereof reaches its setpoint, (2) the specified coincidence logic is maintained, (3) sufficient redundancy is maintained to permit a channel to be out of service for testing or maintenance, and (4) sufficient system functional capability is available from diverse parameters.
The OPERABILITY of these systems is required to provide the overall reliability, redundancy, and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions.
The integrated operation of each of these systems is consistent with the assumptions used in the safety analyses.
The quarterly frequency for the channel functional tests for these systems is based on the analyses presented in the NRC approved topical report CEN-327-A, "RPS/ESFAS Extended Test Interval Evaluation," and CEN-327-A, Supplement 1, and calculation 13-JC-SB-200-Rev. 01.
The verification of response time at the specified frequencies provides assurance that the protective and ESF action function associated with each channel is completed within the time limit assumed in the safety analyses. The instrumentation response times are made up of the time to generate the trip signal at the detector (sensor response time) and the time for the signal to interrupt power to the CEA drive mechanism (signal or trip delay time).
Response time may be verified by any series of sequential, overlapping or total channel measurements, including allocated sensor response time, such that the response time is verified. Allocations for sensor response times may be obtained from records of test results, vendor test data, or vendor engineering specifications. Topical Report CE NPSD-1167-A, "Elimination of (continued)
PALO VERDE UNITS 1, 2, 3 T6.0.100-11 Rev 40 2/21/07
TRM Specification Bases TRM 6.0.100 TRM SPECIFICATION BASES Pressure Sensor Response Time Testing Requirements," provides the basis and methodology for using allocated sensor response times in the overall verification of the channel response time for specific sensors identified in the Topical Report. Response time verification for other sensor types must be demonstrated by test. The allocation of sensor response times must be verified prior to placing a new component in operation and reverified after maintenance that may adversely affect the sensor response time.
T3.3.101 Radiation Monitoring Instrumentation The OPERABILITY of the radiation monitoring channels ensures that: (1) the radiation levels are continually measured in the areas served by the individual channels and (2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.
T3.3.102 Incore Detectors The OPERABILITY of the incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core.
T3.3.103 Seismic Monitoring The OPERABILITY of the seismic instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety. This capability is required to permit comparison of the measured response to that used in the design basis for the facility to determine if plant shutdown is required pursuant to Appendix A of 10 CFR Part 100. The instrumentation is consistent with the recommendations of Regulatory Guide 1.12, "Nuclear Power Plant Instrumentation for Earthquakes," Revision 2 as identified in the PVNGS FSAR.
T3.3.104 Meteorological Instrumentation The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data are available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with the recommendations of Regulatory Guide 1.23 (continued)
PALO VERDE UNITS 1, 2, 3 T6.0.100-12 Rev 40 2/21/07
TRM Specification Bases TRM 6.0.100 TRM SPECIFICATION BASES "Onsite Meteorological Programs," February 1972. Wind speeds less than 0.6 MPH cannot be measured by the meteorological instrumentation.
Surveillance requirement TSR 3.3.104.2 is modified by a NOTE to indicate that the windspeed sensors are excluded from the CHANNEL CALIBRATION. The device is fixed by design and no adjustments are possible.
T3.3.105 Post Accident Monitoring Instrumentation The OPERABILITY of the post-accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with the recommendations of Regulatory Guide 1.97, "Instrumentation for Light-Water-Cooled Nuclear Plants to Assess Plant Conditions During and Following an Accident," December 1975 and NUREG 0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations."
T3.3.106 Loose-Part Detection Instrumentation The OPERABILITY of the loose-part detection instrumentation ensures that sufficient capability is available to detect loose metallic parts in the primary system and avoid or mitigate damage to primary system components. The allowable out-of-service times and surveillance requirements are consistent with the recommendations of Regulatory Guide 1.133, "Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors," May 1981.
T3.3.107 Explosive Gas Monitoring System The explosive gas instrumentation is provided for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the GASEOUS RADWASTE SYSTEM. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.
T3.3.108 Fuel Bldg Essential Ventilation Actuation Signal (FBEVAS)
The FBEVAS is an instrumentation channel that actuates the Fuel Building Essential Ventilation System (FBEVS) to minimize radioactive material released from an irradiated fuel assembly during a Fuel Handling Accident.
TLCO 3.3.108 requires one channel of FBEVAS which includes the Actuation Logic, Manual Trip, and radiation monitor to be OPERABLE.
(continued)
PALO VERDE UNITS 1, 2, 3 T6.0.100-13 Rev 46 1/8/09
TRM Specification Bases TRM 6.0.100 TRM SPECIFICATION BASES The cross-train trip function is provided as a defense-in-depth capability and is not required for FBEVAS channel operability.
During movement of irradiated fuel assemblies in the fuel building with the required FBEVAS channel inoperable, an OPERABLE FBEVS train must be immediately placed in the emergency mode of operation (i.e., fan running, valves/dampers aligned to the post-FBEVAS mode, etc.) or movement of irradiated fuel assemblies must be suspended immediately. The first action ensures that no undetected failures preventing FBEVS system operation will occur, and that any active failure will be readily detected. If an OPERABLE FBEVS train is not placed in the emergency mode of operation, this action requires suspension of the movement of irradiated fuel assemblies in order to minimize the risk of release of radioactivity that might require the actuation FBEVS. This does not preclude the movement of fuel to a safe position.
Movement of spent fuel casks containing irradiated fuel assemblies is not within the scope of the Applicability of this technical specification. The movement of dry casks containing irradiated fuel assemblies will be done with a single-failure-proof handling system and with transport equipment that would prevent any credible accident that could result in a release of radioactivity.
T3.3.200 RPS Instrumentation - Operating (See the ITS 3.3.1 Specification Bases.)
If a valid CPC cabinet high temperature alarm is received, it is possible for an OPERABLE CPC and CEAC to be affected and not be completely reliable.
Therefore, a CHANNEL FUNCTIONAL TEST must be performed on OPERABLE CPCs and CEACs within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The Completion Time of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is adequate considering the low probability of undetected failure, the consequences of a single channel failure, and the time required to perform a CHANNEL FUNCTIONAL TEST.
T3.4.100 Auxiliary Spray System The auxiliary pressurizer spray is required to depressurize the RCS by cooling the pressurizer steam space to permit the plant to enter shutdown cooling. The auxiliary pressurizer spray is required during those periods when normal pressurizer spray is not available, such as during natural circulation and during the later stages of a normal RCS cooldown. The auxiliary pressurizer spray also distributes boron to the pressurizer when normal pressurizer spray is not available.
(continued)
PALO VERDE UNITS 1, 2, 3 T6.0.100-14 Rev 46 1/8/09
TRM Specification Bases TRM 6.0.100 TRM SPECIFICATION BASES T3.4.101 RCS Chemistry The limitations on Reactor Coolant System chemistry ensure that corrosion of the Reactor Coolant System is minimized and reduces the potential for Reactor Coolant System leakage or failure due to stress corrosion. Maintaining the chemistry within the Steady State Limits provides adequate corrosion protection to ensure the structural integrity of the Reactor Coolant System over the life of the plant. The associated effects of exceeding the oxygen, chloride, and fluoride limits are time and temperature dependent. Corrosion studies show that operation may be continued with contaminant concentration levels in excess of the Steady State Limits, up to the Transient Limits, for the specified limited time intervals without having a significant effect on the structural integrity of the Reactor Coolant System. The time interval permitting continued operation within the restrictions of the Transient Limits provides time for taking corrective actions to restore the contaminant concentrations to within the Steady State Limits.
The surveillance requirements provide adequate assurance that concentrations in excess of the limits will be detected in sufficient time to take corrective action.
T3.4.102 Pressurizer Heatup and Cooldown Limits The limitations imposed on the pressurizer heatup and cooldown rates and spray water temperature differential are provided to assure that the pressurizer is operated within the design criteria assumed for the fatigue analysis performed in accordance with the ASME Code Requirements.
T3.4.103 Intentionally Blank (continued)
PALO VERDE UNITS 1, 2, 3 T6.0.100-15 Rev 53 11/10/10
TRM Specification Bases TRM 6.0.100 TRM SPECIFICATION BASES T3.4.104 RCS Vents (Reactor Head Vents)
Reactor Coolant System vents are provided to exhaust noncondensible gases and/or steam from the primary system that could inhibit natural circulation core cooling. The OPERABILITY of at least one Reactor Coolant System vent path from the reactor vessel head ensures the capability exists to perform this function.
A vent path is the flow capability from the reactor vessel head to the reactor drain tank (RDT) or from the reactor vessel head to containment atmosphere.
The four vent paths are:
- 1. From the reactor vessel head through solenoid operated valve (SOV) HV-101, then through SOV HV-105 to the RDT.
- 2. From the reactor vessel head through SOV HV-101, then through SOV HV-106 directly to containment atmosphere.
- 4. From the reactor vessel head through SOV HV-102, then through SOV HV-106 directly to containment atmosphere.
The valve redundancy of the Reactor Coolant System vent paths serves to minimize the probability of inadvertent or irreversible actuation while ensuring that a single failure of a vent valve, power supply, or control system does not prevent isolation of the vent path.
The function, capabilities, and testing requirements of the Reactor Coolant System vent systems are consistent with the requirements of Item II.B.1 of NUREG-0737.
T3.4.200 RCS Pressure and Temperature (P/T) Limits (See the ITS 3.4.3 Specification Bases.)
T3.4.201 Pressurizer An OPERABLE pressurizer provides pressure control for the Reactor Coolant System during operations with both forced reactor coolant flow and with natural circulation flow. The minimum water level in the pressurizer assures the pressurizer heaters, which are required to achieve and maintain pressure control, remain covered with water to prevent failure, which could occur if the heaters were energized uncovered. The maximum water level in the pressurizer ensures that this parameter is maintained within the envelope of operation assumed in the safety analysis. The maximum water level also ensures that the RCS is not a hydraulically solid system and that a steam (continued)
PALO VERDE UNITS 1, 2, 3 T6.0.100-16 Rev 53 11/10/10
TRM Specification Bases TRM 6.0.100 TRM SPECIFICATION BASES bubble will be provided to accommodate pressure surges during operation. The steam bubble also protects the pressurizer code safety valves against water relief. The requirement to verify that on an Engineered Safety Features Actuation test signal concurrent with a loss-of-offsite power the pressurizer heaters are automatically shed from the emergency power sources is to ensure that the non-Class 1E heaters do not reduce the reliability of or overload the emergency power source. The requirement that a minimum number of pressurizer heaters be OPERABLE enhances the capability to control Reactor Coolant System pressure and establish and maintain natural circulation.
T3.4.202 Pressurizer Vents (See the ITS 3.4.12 specification Bases.)
T3.4.203 RCS Operational LEAKAGE (See the ITS 3.4.14 Specification Bases.)
T3.4.204 RCS PIV Leakage (See the ITS 3.4.15 Specification Bases.)
T3.5.200 Safety Injection Tanks (See the ITS 3.5.1 and 3.5.2 Specification Bases.)
T3.5.201 Shutdown Cooling System The OPERABILITY of two separate and independent shutdown cooling subsystems ensures that the capability of initiating shutdown cooling exists when required assuming the most limiting single failure occurs. The requirement to verify the functionality of an inoperable shutdown cooling subsystem minimizes the time exposure of the plant to an event requiring shutdown concurrent with the failure of a component on the other shutdown cooling subsystem.
The shutdown cooling subsystem operation is described in UFSAR 5.4.7. Many of the components comprising the shutdown cooling system have specific requirements during Modes 1-3 in the Technical Specifications (e.g., emergency core cooling, containment spray, and containment isolation). However, several components do not have specific operability requirements in Technical Specifications, and some components function differently in their shutdown cooling role than they do when performing the other functions required by Technical Specifications. These factors must be considered when determining the OPERABILITY and/or functionality of the shutdown cooling subsystems.
The safety analysis assumes that shutdown cooling may be placed in operation once cold leg temperature is less than or equal to 350°F and pressurizer pressure is less than approximately 400 psia. Additional information (continued)
PALO VERDE UNITS 1, 2, 3 T6.0.100-17 Rev 53 11/10/10
TRM Specification Bases TRM 6.0.100 TRM SPECIFICATION BASES regarding the shutdown cooling system is in UFSAR Section 9.3.4. Since the subsystem is manually initiated, temporary changes in the position of shutdown cooling system valves from their normal line up do not necessarily make them inoperable with respect to their shutdown cooling safety function.
The action for one shutdown cooling subsystem inoperable requires verification that the inoperable subsystem is still functional. Functionality requires the subsystem to be capable of performing its safety function given a transient (e.g. Small Break LOCA, SGTR). Functionality will be established utilizing the Operability Determination Program. The allowed outage time is consistent with the durations permitted for those major shutdown cooling components whose operability is controlled by Technical Specifications. The specified outage time allows a reasonable opportunity to effect repairs while providing acceptable limits for the duration of intervals where the system may not be OPERABLE. In combination with the maintenance rule requirements in 10 CFR 50.65, the allowed outage times help ensure that the shutdown cooling subsystems will be functional when required.
If the subsystem cannot be restored or functionality verified within the stated time frame, the associated ACTION places the unit in Mode 4 where the steam generators are still available for heat removal and the stored energy of the NSSS is much less than it is during power operation. While in Modes 3 and 4 continued actions to restore the subsystem to OPERABLE are required.
The action for both shutdown cooling subsystems inoperable require verification of functionality of at least one subsystem within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />. The shorter duration is consistent with the increased safety consequences that exist when the equipment required to establish cold shutdown conditions is inoperable. If at least one subsystem cannot be restored or verified functional within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />, the associated ACTION again places the unit in Mode 4 where the steam generators are available for heat removal and the stored energy in the NSSS is minimized. While in Mode 3 and 4 continued actions to restore the required subsystems to OPERABLE are required.
The surveillance requirement to place each train of shutdown cooling in service every refueling interval demonstrates that the subsystems are functional. In combination with other testing performed to support Technical Specifications, including that conducted as part of the in-service testing and inspection programs, the specified surveillances provide reasonable assurance that the system will be able to perform its intended safety functions.
(continued)
PALO VERDE UNITS 1, 2, 3 T6.0.100-18 Rev 53 11/10/10
TRM Specification Bases TRM 6.0.100 TRM SPECIFICATION BASES The SDC systems are normally in a standby, nonoperating mode. As such, flow path piping has the potential to develop voids and pockets of entrained gases.
The method of ensuring that any voids or pockets of gases are removed from the shutdown cooling suction piping is to vent the accessible suction piping high points, which is controlled by PVNGS procedures. Maintaining the shutdown cooling system suction piping full of water ensures the system will perform properly by minimizing the potential for degraded pump performance, preventing pump cavitation, and preventing pumping of noncondensible gas (e.g., air, nitrogen, or hydrogen) into the reactor vessel during SDC. The 31 day Frequency takes into consideration the gradual nature of gas accumulation in the SDC piping and the adequacy of the procedural controls governing system operation.
References:
- 1. UFSAR Sections 5.4.7 and 9.3.4
- 2. Combustion Engineering Owners Group Joint Applications Report for Low Pressure Safety Injection System AOT Extension, CE NPSD-995, dated May 1995, as submitted to NRC in APS letter no. 102-03392, dated June 13, 1995, with updates described in letter no. 102-04250 dated February 26, 1999. Also see TS amendment no. 124 dated February 1, 2000.
(continued)
PALO VERDE UNITS 1, 2, 3 T6.0.100-19 Rev 53 11/10/10
TRM Specification Bases TRM 6.0.100 TRM SPECIFICATION BASES T3.5.202 ECCS - Operating (See the ITS 3.5.3 Specification Bases.)
SURVEILLANCE TSR 3.5.202.4 REQUIREMENT Maintaining the ECCS suction piping full of water from the Refueling Water Tank and the containment sump to the ECCS pumps ensures that the system will perform properly by minimizing the potential for degraded pump performance. The 31 day frequency takes into consideration the gradual nature of gas accumulation in the ECCS piping and the adequacy of procedural controls governing system operation.
T3.5.203 ECCS - Shutdown (See the ITS 3.5.4 Specification Bases.)
T3.6.100 Hydrogen Purge Cleanup System The OPERABILITY of the equipment and systems required for the control of hydrogen gas ensures that this equipment will be available to maintain the hydrogen concentration within containment below its flammable limit during post-LOCA conditions. The purge system is capable of controlling the expected hydrogen generation associated with (1) zirconium-water reactions, (2) radiolytic decomposition of water and (3) corrosion of metals within containment. The hydrogen control system is consistent with the recommendations of Regulatory Guide 1.7, "Control of Combustible Gas Concentrations in Containment Following a LOCA," March 1971.
The use of ANSI Standard N509 (1980) in lieu of ANSI Standard N509 (1976) to meet the guidance of Regulatory Guide 1.52, Revision 2, Positions C.6.a and C.6.b, has been found acceptable as documented in Revision 2 to Section 6.5.l of the Standard Review Plan (NUREG-0800).
T3.6.200 Prestressed Concrete Containment Tendon Surveillance The prestressed concrete containment tendon surveillance program ensures the structural integrity of containment is maintained in accordance with ASME Code Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a, except where an exemption or relief has been authorized by the NRC.
(continued)
PALO VERDE UNITS 1, 2, 3 T6.0.100-20 Rev 53 11/10/10
TRM Specification Bases TRM 6.0.100 TRM SPECIFICATION BASES T3.6.201 Containment Spray System The containment system is normally in a standby, nonoperating mode. As such, flow path piping has the potential to develop voids and pockets of entrained gases. The method of ensuring that any voids or pockets of gases are removed from the containment spray suction piping is to vent the accessible suction piping high points, which is controlled by PVNGS procedures. Maintaining the containment spray system suction piping full of water ensures the system will perform properly by minimizing the potential for degraded pump performance, preventing pump cavitation, and preventing delay of spray delivery to the containment atmosphere. The 31 day Frequency takes into consideration the gradual nature of gas accumulation in the containment spray piping and the adequacy of the procedural controls governing system operation.
T3.6.300 Hydrogen Recombiners BACKGROUND The function of the hydrogen recombiners is to eliminate the potential breach of containment due to a hydrogen oxygen reaction. Per 10 CFR 50.44, "Standards for Combustible Gas Control Systems in Light-Water-Cooled Reactors" (Ref. 1),
and 10 CFR 50, GDC 41, "Containment Atmosphere Cleanup" (Ref. 2), hydrogen recombiners are required to reduce the hydrogen concentration in the containment following a Loss Of Coolant Accident (LOCA) or Main Steam Line Break (MSLB).
The recombiners accomplish this by recombining hydrogen and oxygen to form water vapor. The vapor remains in containment, thus eliminating any discharge to the environment. The hydrogen recombiners are manually initiated since flammability limits would not be reached until several days after a Design Basis Accident (DBA).
Two 100% capacity independent hydrogen recombiners are shared among the three units. Each consists of controls, a power supply, and a recombiner located in the Auxiliary Building. Recombination is accomplished by heating a hydrogen air mixture above 1150°F. The resulting water vapor and discharge gases are cooled prior to discharge from the recombiner. Air flows through the unit at 50 cfm with a 5 hp centrifugal blower in the unit providing the motive force. A single recombiner is capable of maintaining the hydrogen concentration in containment below the 4.0 volume percent (v/o) flammability limit. Two recombiners are provided to meet the requirement for redundancy and independence. Each recombiner is powered from a separate Engineered Safety Features bus.
(continued)
PALO VERDE UNITS 1, 2, 3 T6.0.100-21 Rev 53 11/10/10
TRM Specification Bases TRM 6.0.100 TRM SPECIFICATION BASES APPLICABLE The hydrogen recombiners provide for controlling the bulk SAFETY ANALYSES hydrogen concentration in containment to less than the (continued) lower flammable concentration of 4.0 v/o following a DBA.
This control would prevent a containment wide hydrogen burn, thus ensuring the pressure and temperature assumed in the analysis are not exceeded and minimizing damage to safety related equipment located in containment. The limiting DBA relative to hydrogen generation is a LOCA.
Hydrogen may accumulate within containment following a LOCA as a result of:
- a. A metal steam reaction between the zirconium fuel rod cladding and the reactor coolant;
- b. Radiolytic decomposition of water in the Reactor Coolant System (RCS) and the containment sump;
hydrogen dissolved in the reactor coolant and hydrogen gas in the pressurizer vapor space); or
- d. Corrosion of metals exposed to Containment Spray System and Emergency Core Cooling Systems solutions.
To evaluate the potential for hydrogen accumulation in containment following a LOCA, the hydrogen generation as a function of time following the initiation of the accident is calculated. Conservative assumptions recommended in Reference 3 are used to maximize the amount of hydrogen calculated.
TLCO Two hydrogen recombiners shared among the three units must be OPERABLE. This ensures operation of at least one hydrogen recombiner in the event of a worst case single active failure.
Operation with at least one hydrogen recombiner ensures that the post LOCA hydrogen concentration can be prevented from exceeding the flammability limit.
(continued)
PALO VERDE UNITS 1, 2, 3 T6.0.100-22 Rev 53 11/10/10
TRM Specification Bases TRM 6.0.100 TRM SPECIFICATION BASES APPLICABILITY In MODES 1 and 2, two hydrogen recombiners are required to control the post LOCA hydrogen concentration within containment below its flammability limit of 4.0 v/o, assuming a worst case single failure.
In MODES 3 and 4, both the hydrogen production rate and the total hydrogen produced after a LOCA would be less than that calculated for the DBA LOCA. Also, because of the limited time in these MODES, the probability of an accident requiring the hydrogen recombiners is low. Therefore, the hydrogen recombiners are not required in MODE 3 or 4.
In MODES 5 and 6, the probability and consequences of a LOCA are low, due to the pressure and temperature limitations. Therefore, hydrogen recombiners are not required in these MODES.
ACTIONS The required ACTIONS have been modified by a Note stating that all three PVNGS Units (Units 1, 2, and 3) shall simultaneously comply with the REQUIRED ACTION(s) when the shared portion of the hydrogen recombiner(s) is the cause of a CONDITION. This is necessary since the three PVNGS Units share the two hydrogen recombiners that are required by this LCO. It will be necessary for the Control Room of the Palo Verde Unit that discovers an inoperable shared portion of the hydrogen recombiner(s) to notify the other two Palo Verde Unit's Control Rooms of the inoperability.
A.1 With one containment hydrogen recombiner inoperable, the inoperable recombiner must be restored to OPERABLE status within 30 days. In this condition, the remaining OPERABLE hydrogen recombiner is adequate to perform the hydrogen control function. The 30 day Completion Time is based on the availability of the other hydrogen recombiner, the small probability of a LOCA or MSLB occurring (that would generate an amount of hydrogen that exceeds the flammability limit),
and the amount of time available after a LOCA or MSLB (should one occur) for operator action to prevent hydrogen accumulation from exceeding the flammability limit.
(continued)
PALO VERDE UNITS 1, 2, 3 T6.0.100-23 Rev 53 11/10/10
TRM Specification Bases TRM 6.0.100 TRM SPECIFICATION BASES ACTIONS B.1 and B.2 (continued)
With two hydrogen recombiners inoperable, the ability to perform the hydrogen control function via alternate capabilities must be verified by administrative means within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The alternate hydrogen control capabilities are provided by the Hydrogen Purge Cleanup System. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time allows a reasonable period of time to verify that a loss of hydrogen control function does not exist. In addition, the alternate hydrogen control system capability must be verified every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter to ensure its continued availability. Both the initial verification and all subsequent verifications may be performed as an administrative check, by examining logs or other information to determine the availability of the alternate hydrogen control system. It does not mean to perform the Surveillances needed to demonstrate OPERABILITY of the alternate hydrogen control system. If the ability to perform the hydrogen control function is maintained, continued operation is permitted with two hydrogen recombiners inoperable for up to 7 days.
Seven days is a reasonable time to allow two hydrogen recombiners to be inoperable because the hydrogen control function is maintained and because of the low probability of the occurrence of a LOCA that would generate hydrogen in amounts capable of exceeding the flammability limit.
C.1 If the inoperable hydrogen recombiner(s) cannot be restored to OPERABLE status within the required Completion Time. TLCO 3.0.100.3 must be entered immediately SURVEILLANCE SR 3.6.7.1 REQUIREMENTS This SR ensures that there are no physical problems that could affect recombiner operation. A visual inspection is sufficient to determine abnormal conditions that could cause failures. The 6 month Frequency for this SR was developed considering that the incidence of hydrogen recombiners failing the SR in the past is low.
SR 3.6.7.2 A functional test of each Hydrogen Recombiner System assures that the recombiners remain operational. The functional test shall include operating the recombiner including the air blast heat exchanger fan motor and enclosed blower motor (continued)
PALO VERDE UNITS 1, 2, 3 T6.0.100-24 Rev 53 11/10/10
TRM Specification Bases TRM 6.0.100 TRM SPECIFICATION BASES continuously for at least 30 minutes at a temperature of approximately 800°F reaction chamber temperature. The frequency recommended for this surveillance in the Improved Standard Technical Specifications (NUREG-1432, Rev. 1) is 18 months. The bases for NUREG 1432 was developed for permanently installed hydrogen recombiners. The two portable hydrogen recombiners at PVNGS are shared among the three units; therefore, the 6 month frequency from the initial licensing basis is retained for reliability considerations.
SR 3.6.7.3 Performance of a CHANNEL CALIBRATION to include a system functional test for each hydrogen recombiner ensures that the recombiners are operational and can attain and sustain the temperature necessary for hydrogen recombination. In particular, this SR requires 1) resistance checks of motors, thermocouples, and heater systems, 2) testing/calibration of all flow elements, switches, and temperature elements, and
- 3) operation of the recombiner to include a functional test at 1200°F (+/-50°F) for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Operating experience has shown that these components usually pass the Surveillance when performed at the 12 month Frequency.
Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.
REFERENCES 1. 10 CFR 50.44.
- 3. Regulatory Guide 1.7, Revision 0.
- 4. UFSAR, Section 6.2.5 T3.7.100 Steam Generator Pressure and Temperature Limitations The limitation on steam generator pressure and temperature ensures that the pressure induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits. The limitations to 120°F and 230 psig for Units 1 and 3 are based on a steam generator RTNDT of 40°F and are sufficient to prevent brittle fracture. The limitations to 70°F and 650 psig for Unit 2 are based on a steam generator RTNDT of -20°F and are sufficient to prevent brittle fracture.
(continued)
PALO VERDE UNITS 1, 2, 3 T6.0.100-25 Rev 53 11/10/10
TRM Specification Bases TRM 6.0.100 TRM SPECIFICATION BASES T3.7.101 Snubbers All snubbers are required to be able to perform their associated safety function(s) to ensure that the structural integrity of the reactor coolant system and all other safety-related systems is maintained during and following a seismic or other event initiating dynamic loads. Snubbers excluded from this inspection program are those installed on nonsafety-related systems and then only if their failure or failure of the system on which they are installed, would have no adverse effect on any safety-related system.
When one or more snubbers are unable to perform their associated safety function(s), either the supported system must be declared inoperable immediately or TS LCO 3.0.8 must be entered. TS LCO 3.0.8 may only be entered if the restrictions described in the LCO 3.0.8 TS Bases are met. TS LCO 3.0.8 is an allowance, not a requirement. When any snubber is unable to perform its associated safety function, the supported system may be declared inoperable instead of utilizing LCO 3.0.8.
Required Action A.2 must be completed whenever Condition A is entered. This Required Action emphasizes the need to perform the evaluation to determine if the components to which the nonfunctional snubbers are attached were adversely affected by the non-functionality of the snubbers in order to ensure that the component remains capable of meeting the designed service. Restoration alone per Required Action A.1.1 or A.1.2 is insufficient because higher than analyzed stresses may have occurred and may have affected the supported system.
A list of individual snubbers with detailed information of snubber location and size and of system affected shall be available at the plant in accordance with Section 50.71(c) of 10 CFR Part 50. The accessibility of each snubber shall be determined and approved by the Plant Review Board. The determination shall be based upon the existing radiation levels and the expected time to perform a visual inspection in each snubber location as well as other factors associated with accessibility during plant operations (e.g., temperature, atmosphere, location, etc.), and the recommendations of Regulatory Guides 8.8 and 8.10. The addition or deletion of any hydraulic or mechanical snubber shall be made in accordance with Section 50.59 of 10 CFR Part 50.
The acceptance criteria specified in the 2001 Edition, 2003 Addenda, of the ASME OM Code, Subsection ISTD are to be used in the visual inspection to determine the functionality of the snubbers.
(continued)
PALO VERDE UNITS 1, 2, 3 T6.0.100-26 Rev 53 11/10/10
TRM Specification Bases TRM 6.0.100 TRM SPECIFICATION BASES To provide assurance of snubber functional reliability one of the two functional testing methods specified in the 2001 Edition, 2003 Addenda, of the AMSE OM Code, Subsection ISTD, shall be utilized.
The service life of a snubber is established via manufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temperature area, etc.). The requirement to monitor the snubber service life is included in the 2001 Edition, 2003 Addenda, of the ASME OM Code, Subsection ISTD to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions. These records will provide statistical bases for future consideration of snubber service life.
T3.7.102 Sealed Source Contamination The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium.
This limitation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values.
Sealed sources are classified into three groups according to their use, with surveillance requirements commensurate with the probability of damage to a source in that group. Those sources which are frequently handled are required to be tested more often than those which are not. Sealed sources which are continuously enclosed within a shielded mechanism (i.e. sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shield mechanism.
T3.7.200 Atmospheric Dump Valves (ADVs)
Background See TS Bases B 3.7.4 Applicable See UFSAR Chapter 15.
Safety Analyses TLCO Two ADVs are required to be OPERABLE on each SG to ensure that a single failure would not prevent the capability to remotely open at least one ADV on the affected SG following a steam generator tube rupture with a loss of offsite power (SGTRLOP, UFSAR 15.6.3.3). At least one ADV on the affected SG would be needed to prevent overfill and (continued)
PALO VERDE UNITS 1, 2, 3 T6.0.100-27 Rev 53 11/10/10
TRM Specification Bases TRM 6.0.100 TRM SPECIFICATION BASES provide for heat removal. Failure to meet the LCO by having only a single OPERABLE ADV on one or both SGs would result in the loss of the single failure ADV backup on one or both SGs. An ADV is considered OPERABLE when it is capable of providing a controlled relief of the main steam flow, and is capable of fully opening and closing on demand, by remote operation.
This TLCO supplements Technical Specification (TS)
LCO 3.7.4, which requires one ADV line per SG to be OPERABLE, until TS LCO 3.7.4 can be revised.
Actions The ACTIONS table is modified by a Note indicating that separate Condition entry is allowed for each SG. This is acceptable since (1) the primary success path for accident mitigation would continue to be available by the remaining OPERABLE ADV on each SG when a single ADV is inoperable on each SG, and (2) the risk associated with continuing to operate the plant without the single failure ADV backup on both SGs for up to 7 days is much lower than the risk associated with shutting down the plant.
A.1 If the requirements of TSR 3.7.200 are not met, the condition must be documented in the corrective action program and an operability determination must be initiated as necessary to determine the impact on equipment in the TSs. This action is required to assure compliance with the TSs.
B.1 If one of the two required ADV lines on a SG is inoperable, Required Action B is to restore the ADV line to OPERABLE status within 7 days. The 7 day Completion Time is acceptable because (1) when one ADV on either or both SGs is inoperable, the single failure backup is no longer available, but the primary success path for accident mitigation continues to be available by the remaining OPERABLE ADVs; (2) the heat removal function of the ADVs can also be provided by the steam bypass control valves to the condensers and atmosphere when offsite power (continued)
PALO VERDE UNITS 1, 2, 3 T6.0.100-28 Rev 53 11/10/10
TRM Specification Bases TRM 6.0.100 TRM SPECIFICATION BASES is available, and by the main steam safety valves at all times; (3) the low probability of an accident that requires the ADVs occurring during this period; and (4) the much lower risk of continuing operation with the inoperable ADV(s) compared with the risk of shutting down the plant. In addition, each ADV may be operated locally by manual operation if the inoperability is due to failure of the remote operating controls or the pneumatic supply.
The allowed Completion Time is reasonable, based on operating experience, to restore an inoperable ADV.
C.1 If the ADV lines cannot be restored to OPERABLE status within the associated Completion Time, TLCO 3.0.100.3 must be entered immediately. This will assure that the situation is communicated to the Shift Manager and the condition is documented in the PVNGS corrective action program. An initial decision on whether the unit can continue to operate with the condition will be completed within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />. Further actions will be as required by the corrective action disposition and as deemed necessary by plant management.
D.1 See TS Bases B 3.7.4, Action A.1 E.1 See TS Bases B 3.7.4, Action B.1 Surveillance TSR 3.7.200.1 Requirements The nitrogen accumulator tank pressure must be verified to have a pressure of at least 615 psig indicated to ensure that it has sufficient pressurized gas to operate the ADVs for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at hot standby plus 9.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> of operation to reach cold shutdown under natural circulation conditions in the event of failure of the normal control air system, as described in UFSAR 10.3.2.2.4.
(continued)
PALO VERDE UNITS 1, 2, 3 T6.0.100-29 Rev 53 11/10/10
TRM Specification Bases TRM 6.0.100 TRM SPECIFICATION BASES T3.7.201 AFW System (See the ITS 3.7.5 Specification Bases.)
T3.7.202 Essential Cooling Water (EW) System (See the ITS 3.7.7 Specification Bases.)
T3.7.203 Essential Spray Pond System (ESPS)
(See the ITS 3.7.8 Specification Bases.)
T3.7.204 Essential Chilled Water (EC) System (See the ITS 3.7.10 Specification Bases.)
T3.7.205 Control Room Emergency Air Temperature Control System (CREATCS)
(See the ITS 3.7.12 Specification Bases.)
T3.7.206 Fuel Storage Pool Water Level (See the ITS 3.7.14 Specification Bases.)
T3.7.207 Secondary Specific Activity (See the ITS 3.7.16 Specification Bases.)
T3.8.100 Cathodic Protection If any other metallic structures (e.g., buildings, new or modified piping systems, conduit) are placed in the ground in the vicinity of the fuel oil storage system or if the original system is modified, the adequacy and frequency of inspections of the cathodic protection system shall be re-evaluated and adjusted in accordance with Regulatory Guide 1.137.
T3.8.101 Containment Penetration Conductor Overcurrent Protective Devices Containment electrical penetrations and penetration conductors are protected by either deenergizing circuits not required during reactor operation or by demonstrating the OPERABILITY of primary and backup overcurrent protection circuit breakers during periodic surveillance. The circuit breakers will be tested in accordance with NEMA Standard Publication No. AB-2-1980. For a frame size of 250 amperes or less, the field tolerances of the high and low setting of the injected current will be within +40%/-25% of the setpoint (pickup) value. For a frame size of 400 amperes or greater, the field tolerances will be +/-25% of the setpoint (pickup) value. The circuit breakers should not be affected when tested within these tolerances.
The surveillance requirements applicable to lower voltage circuit breakers provide assurance of breaker reliability by testing at least one (continued)
PALO VERDE UNITS 1, 2, 3 T6.0.100-30 Rev 53 11/10/10
TRM Specification Bases TRM 6.0.100 TRM SPECIFICATION BASES representative sample of each manufacturer's brand of circuit breaker. Each manufacturer's molded case and metal case circuit breakers are grouped into representative samples which are then tested on a rotating basis to ensure that all breakers are tested. If a wide variety exists within any manufacturer's brand of circuit breakers it is necessary to divide that manufacturer's breakers into groups and treat each group as a separate type of breaker for surveillance purposes. There are no surveillance requirements on fuses. For in-line fuses, the applicable surveillance would require removing the fuses from the circuit which would destroy the fuse. The test data for surveillance on the other fuses would not indicate whether the fuse was degrading which has been stated by the fuse manufacturer and Idaho National Engineering Laboratory.
T3.8.102 MOV Thermal Overload Protection and Bypass Devices The OPERABILITY of the motor-operated valves thermal overload protection and/or bypass devices ensures that these devices will not prevent safety related valves from performing their function. The surveillance requirements for demonstrating the OPERABILITY of these devices are in accordance with Regulatory Guide 1.106, "Thermal Overload Protection for Electric Motors on Motor Operated Valves," Revision 1, March 1977.
(continued)
PALO VERDE UNITS 1, 2, 3 T6.0.100-31 Rev 53 11/10/10
TRM Specification Bases TRM 6.0.100 TRM SPECIFICATION BASES T3.8.200 AC Sources - Shutdown (See the ITS 3.8.2 Specification Bases.)
T3.9.100 Decay Time The minimum requirement for reactor subcriticality prior to movement of irradiated fuel assemblies in the reactor pressure vessel ensures that sufficient time has elapsed to allow the radioactive decay of the short lived fission products. This decay time is consistent with the assumptions used in the safety analyses.
T3.9.101 Communications The requirement for communications capability ensures that refueling station personnel can be promptly informed of significant changes in the facility status or core reactivity condition during CORE ALTERATIONS.
T3.9.102 Refueling Machine The OPERABILITY requirements for the refueling machine ensure that: (1) the machine will be used for movement of fuel assemblies, (2) the machine has sufficient load capacity to lift a fuel assembly, and (3) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.
T3.9.103 Crane Travel The restriction on movement of loads in excess of the nominal weight of a fuel assembly, CEA and associated handling tool over other fuel assemblies in the storage pool ensures that in the event this load is dropped (1) the activity release will be limited to that contained in a single fuel assembly, and (2) any possible distortion of fuel in the storage racks will not result in a critical array. This assumption is consistent with the activity release assumed in the safety analyses. However, the use of a single failure-proof crane to move spent fuel cask components over irradiated fuel stored in an approved cask is allowed by this LCO.
(continued)
PALO VERDE UNITS 1, 2, 3 T6.0.100-32 Rev 53 11/10/10
TRM Specification Bases TRM 6.0.100 TRM SPECIFICATION BASES T3.9.104 Fuel Building Essential Ventilation System (FBEVS)
The limitations on the fuel building essential ventilation system ensure that all radioactive material released from an irradiated fuel assembly will be filtered through the HEPA filters and charcoal adsorber prior to discharge to the atmosphere. The OPERABILITY of this system and the resulting iodine removal capacity are consistent with the assumptions of the safety analyses.
If one FBEVS train is inoperable, action must be taken to immediately verify that the OPERABLE FBEVS is capable of being powered from an emergency power source and to restore the inoperable train to OPERABLE status within 7 days.
During this time period, the remaining OPERABLE train is adequate to perform the FBEVS function. The 7 day Completion Time is reasonable, based on the risk from an event occurring requiring the inoperable FBEVS train, and ability of the remaining FBEVS train to provide the required protection.
During movement of irradiated fuel assemblies in the fuel building, if the Required Actions of Condition A cannot be completed within the required Completion Time, the operation (i.e., fan running, valves/dampers aligned to the post-FBEVAS mode, etc.) or movement of irradiated fuel assemblies must be suspended immediately. The first action ensures that the remaining train is OPERABLE, that no undetected failures preventing system operation will occur, and that any active failure will be readily detected. If the system is not placed in the emergency mode of operation, this action requires suspension of the movement of irradiated fuel assemblies in order to minimize the risk of release of radioactivity that might require the actuation of FBEVS. This does not preclude the movement of fuel to a safe position.
Movement of spent fuel casks containing irradiated fuel assemblies is not within the scope of the Applicability of this technical specification. The movement of dry casks containing irradiated fuel assemblies will be done with a single-failure-proof handling system and with transport equipment that would prevent any credible accident that could result in a release of radioactivity.
(continued)
PALO VERDE UNITS 1, 2, 3 T6.0.100-33 Rev 53 11/10/10
TRM Specification Bases TRM 6.0.100 TRM SPECIFICATION BASES When two trains of the FBEVS are inoperable during movement of irradiated fuel assemblies in the fuel building, action must be taken to place the unit in a condition in which the LCO does not apply. This LCO involves immediately suspending movement of irradiated fuel assemblies in the fuel building. This does not preclude the movement of fuel to a safe position.
The use of ANSI Standard N509 (1980) in lieu of ANSI Standard N509 (1976) to meet the guidance of Regulatory Guide 1.52, Revision 2, Positions C.6.a and C.6.b, has been found acceptable as documented in Revision 2 to Section 6.5.1 of the Standard Review Plan (NUREG-0800).
T3.9.200 Boron Concentration (See the ITS 3.9.1 Specification Bases.)
T3.9.201 Containment Penetrations (See the ITS 3.9.3 Specification Bases.)
T3.10.200 Liquid Holdup Tanks The tanks referred to in this specification include all those outdoor radwaste tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system.
Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than 10 times the limits of 10 CFR Part 20.1001-20.2402, Appendix B, Table 2, Column 2, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.
The limit of 60 curies is based on the analyses given in Section 2.4 of the PVNGS FSAR and on the amount of soluble (not gaseous) radioactivity in the Refueling Water Tank in Table 2.4-26.
(continued)
PALO VERDE UNITS 1, 2, 3 T6.0.100-34 Rev 53 11/10/10
TRM Specification Bases TRM 6.0.100 TRM SPECIFICATION BASES T3.10.201 Explosive Gas Mixture This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas holdup system is maintained below the flammability limits of hydrogen and oxygen. (Automatic control features are included in the system to prevent the hydrogen and oxygen concentrations from reaching these flammability limits. These automatic control features include isolation of the source of hydrogen and/or oxygen, or injection of dilutants to reduce the concentration below the flammability limits.) Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.
T3.10.202 Gas Storage Tanks This specification considers postulated radioactive releases due to a waste gas system leak or failure, and limits the quantity of radioactivity contained in each pressurized gas storage tank in the GASEOUS RADWASTE SYSTEM to assure that a release would be substantially below the guidelines of 10 CFR Part 100 for a postulated event.
Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to a MEMBER OF THE PUBLIC at the nearest exclusion area boundary will not exceed 0.5 rem. This is consistent with Standard Review Plan 11.3, Branch Technical Position ETSB 11-5, "Postulated Radioactive Releases Due to a Waste Gas System Leak or Failure,"
in NUREG-0800, July 1981.
T3.11.100 FIRE DETECTION INSTRUMENTATION OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires and that fire suppression systems, that are actuated by fire detectors, will discharge extinguishing agent in a timely manner. Prompt detection and suppression of fires will reduce the potential for damage to safety-related equipment and is an integral element in the overall facility fire protection program.
(continued)
PALO VERDE UNITS 1, 2, 3 T6.0.100-35 Rev 53 11/10/10
TRM Specification Bases TRM 6.0.100 TRM SPECIFICATION BASES Fire detectors that are used to actuate fire suppression systems represent a more critically important component of a plant's fire protection program than detectors that are installed solely for early fire warning and notification.
Consequently, the minimum number of OPERABLE fire detectors must be greater.
The loss of detection capability for fire suppression systems, actuated by fire detectors, represents a significant degradation of fire protection for any area. As a result, the establishment of a fire watch patrol must be initiated at an earlier stage than would be warranted for the loss of detectors that provide only early fire warning. The establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to OPERABILITY.
When inoperable fire detection instrument(s) are inside containment, REQUIRED ACTIONs B.2 and C.2 require either (1) a fire watch patrol inspect the containment zone(s) with the inoperable instrument(s) at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or (2) monitor the containment air temperature at least once per hour at each of the 7 locations listed in the Bases for Technical Specification SR 3.6.5.1. The plant computer with the control room installed multi-point recorder and annunciator is an acceptable means of monitoring temperatures inside containment when required. The continuous monitoring of containment air temperature by the plant computer and multi-point recorder exceeds the requirement of hourly monitoring. The plant computer and multi-point recorder utilizes pre-set alarm points for each monitored location. If setpoints are exceeded, an audio annunciation is received that alerts the operator of an abnormal condition.
The fire zones listed in Table 3.3.11.100-1, Fire Detection Instruments, are discussed in Section 9B of the PVNGS UFSAR.
T3.11.101, 102, 103, 104, 105, and 106 FIRE SUPPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that adequate fire suppression capability is available to confine and extinguish fires occurring in any portion of the facility where safety-related equipment is located. The fire suppression system consists of the water system, spray and/or sprinklers, CO2, Halon, fire hose stations, and yard fire hydrants and associated emergency response vehicles. The collective capability of the fire suppression systems is adequate to minimize potential damage to safety related equipment and is a major element in the facility fire protection program.
(continued)
PALO VERDE UNITS 1, 2, 3 T6.0.100-36 Rev 53 11/10/10
TRM Specification Bases TRM 6.0.100 TRM SPECIFICATION BASES In the event that portions of the fire suppression systems are inoperable, alternate backup fire fighting equipment is required to be made available in the affected area(s) until the inoperable equipment is restored to service.
When the inoperable fire fighting equipment is intended for use as a backup means of fire suppression, a longer period of time is allowed to provide an alternate means of fire fighting than if the inoperable equipment is the primary means of fire suppression.
The surveillance requirements provide assurance that the minimum OPERABILITY requirements of the suppression systems are met. An allowance is made for ensuring a sufficient volume of C02/Halon in the CO2/Halon storage tank by verifying either the weight or the level of the tank. The interval for some required surveillances for CO2 and Halon systems is based on the statistical reliability methodology provided in Electric Power Research Institute (EPRI)
Technical Report 1006756, Fire Protection Equipment Surveillance Optimization and Maintenance Guide. Component failure will be entered into the corrective action program for analysis and trending.
In the event the fire suppression water system becomes inoperable, immediate corrective measures must be taken since this system provides the major fire suppression capability of the plant.
3.11.107 FIRE-RATED ASSEMBLIES The OPERABILITY of the fire barriers and barrier penetrations ensure that fire damage will be limited. These design features minimize the possibility of a single fire involving more than one fire area prior to detection and extinguishment. The fire barriers, fire barrier penetrations for conduits, cable trays and piping, fire dampers, and fire doors are periodically inspected and functionally tested to verify their OPERABILITY.
PALO VERDE UNITS 1, 2, 3 T6.0.100-37 Rev 53 11/10/10
Remote Shutdown Disconnect Switches TRM 7.0.100 T7.0 COMPONENT LISTS T7.0.100 REMOTE SHUTDOWN DISCONNECT SWITCHES This list identifies the remote shutdown disconnect switches that are subject to the testing requirements of TS 3.3.11, Remote Shutdown System.
SWITCH DISCONNECT SWITCH LOCATION
- 1. SG 1 line 2 Atmospheric Dump Valve Solenoid Air Isolation Valves SGB-HY- RSP 178A and SGB-HY-178R
- 2. SG 2 line 1 Atmospheric Dump Valve Solenoid Air Isolation Valves SGB-HY- RSP 185A and SGB-HY-185R
- 3. Auxiliary Spray Valve CHB-HV-203 RSP
- 4. Letdown to Regenerative Heat Exchanger Isolation, CHB-UV-515 RSP
- 5. Reactor Coolant Pump Controlled Bleedoff, CHB-UV-505 RSP
- 6. Auxiliary Feedwater Pump B to SG 1 Control Valve, AFB-HV-30 RSP
- 7. Auxiliary Feedwater Pump B to SG 2 Control Valve, AFB-HV-31 RSP
- 8. Auxiliary Feedwater Pump B to SG 1 Block Valve, AFB-UV-34 RSP
- 9. Auxiliary Feedwater Pump B to SG 2 Block Valve, AFB-UV-35 RSP
- 10. Pressurizer Backup Heaters Control Bank MRCE B10, B18, A05 (Unit 1) RSP Bank MRCE B10, B17, A05 (Unit 2) RSP Bank MRCE B11, B17, B05 (Unit 3) RSP
- 11. Safety Injection Tank 2A Vent Control SIB-HV-613 RSP
- 12. Safety Injection Tank 2B Vent Control SIB-HV-623 RSP
- 13. Safety Injection Tank 1A Vent Control SIB-HV-633 RSP
- 14. Safety Injection Tank 1B Vent Control SIB-HV-643 RSP
- 15. Safety Injection Tank Vent Valves Power Supply SIB-HS-18C RSP
- 16. SG 1 line 2 Atmospheric Dump Valve Solenoid Air Isolation Valves SGD-HY- RSP 178B and SGD-HY-178S
- 17. SG 2 line 1 Atmospheric Dump Valve Solenoid Air Isolation Valves SGD-HY- RSP 185B and SGD-HY-185S
- 18. Control BLDG Battery Room D Essential Exhaust Fan 'HJB-JO1A' PHB-M3205
- 19. Control BLDG Battery Room B Essential Exhaust Fan 'HJB-JO1B' PHB-M3205
- 20. Battery Charger D Control Room Circuits PKD-H14 PHB-M3209
& PKD-H14
- 22. LPSI Pump SIB-P01 Breaker Control PBB-SO4F (continued)
PALO VERDE UNITS 1, 2, 3 T7.0.100-1 Rev 52 7/16/10
Remote Shutdown Disconnect Switches TRM 7.0.100 T7.0 COMPONENT LISTS SWITCH DISCONNECT SWITCH LOCATION
- 23. Diesel Generator B Breaker Control PBB-S04B
- 24. Essential Spray Pond Pump SPB-P01 Breaker Control PBB-S04C
- 25. Essential Chiller ECB-E01 Breaker Control PBB-SO4G
- 26. E-PBB-SO4J 4.16KV Feeder Breaker to 480V Load Center PGB-L32 PBB-SO4J
- 27. E-PBB-SO4H 4.16KV Feeder Breaker to 480V Load Center PGB-L34 PBB-SO4H
- 28. E-PBB-SO4N 4.16KV Feeder Breaker to 480V Load Center PGB-L36 PBB-SO4N
- 29. Auxiliary Feedwater Pump AFB-P01 Breaker Control PBB-SO4S
- 30. Essential Cooling Water Pump EWB-P01 Breaker Control PBB-SO4M
- 31. E-PGB-L32B2 480V Main Supply Breaker to Load Center PGB-L32 PGB-L32B2
- 32. E-PGB-L34B2 480V Main Supply Breaker to Load Center PGB-L34 PGB-L34B2
- 33. E-PGB-L36B2 480V Main Supply Breaker to Load Center PGB-L36 PGB-L36B2
- 34. Charging Pump No. 2 CHB-P01 Supply Breaker CHB-PO1 PGB-L32C1
- 35. Diesel Engine Control Switch HS-2A DGB-CO1
- 36. Diesel Engine Control Switch HS-2B DGB-CO1
- 37. Diesel Generator Control Switch HS-2 DGB-CO1
- 38. Diesel Generator Essential Exhaust Fan HDB-J01 DGB-CO1
- 39. Diesel Generator Fuel Oil Transfer Pump DFB-P01 DGB-CO1
- 40. Battery Charger BD Control Room Circuits PKB-H16 PHB-M3425
- 41. Battery Charger B Control Room Circuits PKB-H12 PHB-M3627
- 42. 125 VDC Battery B Breaker Control Room Circuits PKB-M4201
- 43. 125 VDC Battery D Breaker Control Room Circuits PKD-M4401
- 45. Shutdown Cooling LPSI Suction SIB-UV-656 PHB-M3611
- 47. Shutdown Cooling Warmup Bypass SIB-HV-690 PHB-M3806
- 50. LPSI-SD HX "B" Bypass SIB-HV-307 PHB-M3803
- 51. LPSI Pump "B" Recirc SIB-UV-668 PHB-M3611
PALO VERDE UNITS 1, 2, 3 T7.0.100-2 Rev 52 7/16/10
Remote Shutdown Disconnect Switches TRM 7.0.100 T7.0 COMPONENT LISTS SWITCH DISCONNECT SWITCH LOCATION
- 57. VCT Outlet Isolation CHN-UV-501 NHN-M7208
- 58. RWT Gravity Feed CHE-HV-536 NHN-M7209
- 59. Shutdown Cooling Temperature Control SIB-HV-658 PHB-M3416
- 60. Shutdown Cooling Heat Exchanger Bypass Valve SIB-HV-693 PHB-M3416
- 61. 4.16 KV Bus PBB-SO4 Feeder from XFMR NBN-XO4 PBB-SO4K
- 62. 4.16 KV Bus PBB-SO4 Feeder from XFMR NBN-XO3 PBB-SO4L
- 63. Electrical Penetration Room B ACU HAB-Z06 PHB-M3640
- 67. R.C.S. Sample Isolation Valve SSA-UV-203 SSA-J04
- 68. R.C.S. Sample Isolation Valve SSB-UV-200 RSP
- 69. 125 VDC Battery A Breaker Control Room Circuits PKA-M4101
- 70. ESF Equipment Room ESS AHU Fan HJB-Z04 PHB-M3205 PALO VERDE UNITS 1, 2, 3 T7.0.100-3 Rev 0 8/13/98
Remote Shutdown Control Circuits TRM 7.0.200 T7.0 COMPONENT LISTS T7.0.200 REMOTE SHUTDOWN CONTROL CIRCUITS This list identifies the remote shutdown control circuits that are subject to the testing requirements of TS 3.3.11, Remote Shutdown System.
SWITCH CONTROL CIRCUITS LOCATION
- 1. Auxiliary Feedwater Pump B to S/G 1 Isolation Valve AFB-UV-34 RSP
- 2. Auxiliary Feedwater Pump B to S/G 1 Control Valve AFB-HV-30 RSP
- 3. Auxiliary Feedwater Pump B to S/G 2 Isolation Valve AFB-UV-35 RSP
- 4. Auxiliary Feedwater Pump B to S/G 2 Control Valve AFB-HV-31 RSP
- 5. Auxiliary Feedwater Pump AFB-PO1 PBB-SO4S
- 6. Charging Pump No. 2 CHB-PO1 PGB-L32C4
- 7. Pressurizer Auxiliary Spray Valve CHB-HV-203 RSP
- 8. Pressurizer Backup Heater Bank RSP
- 11. Volume Control Tank Outlet Isolation Valve CHN-UV-501 NHN-M7208
- 12. RWT Gravity Feed Isolation Valve CHE-HV-536 NHN-M7209
- 13. S/G 1 line 2 Atmospheric Dump Valve Controller SGB-HIC-178B RSP
- 14. S/G 1 line 2 Atmospheric Dump Valve Solenoid Air Isolation Valves SGB- RSP HY-178A and SGB-HY-178R
- 15. S/G 1 line 2 Atmospheric Dump Valve Solenoid Air Isolation Valves SGD- RSP HY-178B and SGD-HY-178S
- 16. S/G 2 line 2 Atmospheric Dump Valve Controller SGB-HIC-185B RSP
- 17. S/G 2 line 1 Atmospheric Dump Valve Solenoid Air Isolation Valves SGB- RSP HY-185A and SGB-HY-185R
- 18. S/G 2 line 1 Atmospheric Dump Valve Solenoid Air Isolation Valves SGD- RSP HY-185B and SGD-HY-185S
- 19. Diesel Generator B Output Breaker PBB-SO4B
- 20. Diesel Generator Building Essential Exhaust Fan HDB-J01 DGB-BO1
- 21. Diesel Generator B Fuel Oil Transfer Pump DFB-P01 DGB-BO1
- 22. E-PBB-S04H 4.16 KV Feeder Breaker to 480V Load Center PGB-L34 PBB-S04H
- 23. E-PBB-S04J 4.16KV Feeder Breaker to 480V Load Center PGB-L32 PBB-S04J
- 24. E-PBB-S04N 4.16KV Feeder Breaker to 480V Load Center PGB-L36 PBB-SO4N (continued)
PALO VERDE UNITS 1, 2, 3 T7.0.200-1 Rev 52 7/16/10
Remote Shutdown Control Circuits TRM 7.0.200 T7.0 COMPONENT LISTS SWITCH CONTROL CIRCUITS LOCATION
- 25. E-PGB-L32B2 480V Main Supply Breaker To Load Center PGB-L32 PGB-L32B1
- 26. E-PGB-L34B2 480V Main Supply Breaker To Load Center PGB-L34 PGB-L34B1
- 27. E-PGB-L36 480V Supply Breaker To Load Center PGB-L36 PGB-L36B1
- 28. Battery Charger PKB-H12 Supply Breaker PHB-M3627
- 29. Battery Charger PKD-H14 Supply Breaker PHB-M3209
- 30. Backup Battery Charger PKB-H16 Supply Breaker PHB-M3425
- 31. Essential Spray Pond Pump SPB-PO1 PBB-SO4C
- 32. Essential Cooling Water Pump EWB-PO1 PBB-SO4M
- 33. Essential Chilled Water Chiller ECB-EO1 PBB-SO4G
- 34. Battery Room D Essential Exhaust Fan HJB-JO1A PHB-M3206
- 35. Battery Room B Essential Exhaust Fan HJB-JO1B PHB-M3207
- 37. Electrical Penetration Room B ACU Fan HAB-ZO6 PHB-M3631
- 43. LPSI Pump B SIB-PO1 PBB-SO4F
- 44. Containment Spray Pump B Discharge to SD HX "B" Valve SIB-HV-689 PHB-M3804
- 45. LPSI Containment Spray from SD HX "B" X-tie Valve SIB-HV-695 PHB-M3810
- 46. Shutdown Cooling LPSI Suction Valve SIB-UV-656 PHB-M3605
- 47. Shutdown Cooling Warmup Bypass Valve SIB-HV-690 PHB-M3806
- 48. LPSI Containment Spray to SD HX "B" X-tie Valve SIB-HV-694 PHB-M3414
- 51. LPSI Pump B Recirc. Valve SIB-UV-668 PHB-M3609
- 53. RC Loop to Shutdown Cooling Valve SIB-UV-652 PHB-M3604
- 54. RC Loop to Shutdown Cooling Valve SID-UV-654 PKD-B44
PALO VERDE UNITS 1, 2, 3 T7.0.200-2 Rev 52 7/16/10
Remote Shutdown Control Circuits TRM 7.0.200 T7.0 COMPONENT LISTS SWITCH CONTROL CIRCUITS LOCATION
- 57. SDC "B" Temperature Control Valve SIB-HV-658 PHB-M3412
- 61. Diesel Generator "B" Emergency Start DGB-B01
- 62. Normal Offsite Power Supply Breaker PBB-S04K
- 63. Alternate Offsite Power Supply Breaker PBB-S04L
- 64. Battery "B" Breaker PKB-M4201
- 65. Battery "D" Breaker PKD-M4401
- 66. RCS Sample Isolation Valve SSA-UV-203 SSA-J04
- 67. RCS Sample Isolation Valve SSB-UV-200 SSB-J04
- 69. Shutdown Cooling Heat Exchanger Bypass Valve SIB-HV-693 PHB-M3413
- 70. Battery "A" Breaker PKA-M4101
- 71. ESF Equipment Room B Essential AHU HJB-Z04 PHB-M3222 PALO VERDE UNITS 1, 2, 3 T7.0.200-3 Rev 0 8/13/98
Containment Isolation Valves TRM 7.0.300 T7.0 COMPONENT LISTS T7.0.300 CONTAINMENT ISOLATION VALVES This list identifies the containment isolation valves that are subject to the testing requirements of TS 3.6.3, Containment Isolation Valves. All manual vent, drain, and test valves within a Containment Penetration (i.e., between the Containment Isolation Valves) will be maintained locked and closed per the locked valve administrative program or surveilled closed per Technical Specification SR 3.6.3.3 or SR 3.6.3.4.
VALVE NO ITS 3.6.3 PENETRATION VALVES RECEIVING CONTAINMENT ISOLATION Condition (CIAS)
RDA-UV 023 A 9 Containment radwaste sump pump to LRS holdup tank RDB-UV 024 A 9 Containment radwaste sump pump to LRS holdup tank RDB-UV 407 A 9 Containment radwaste sump post-accident sampling (Unit 1 & 3 system only)
SGB-HV 200(a) A 11 Downcomer feedwater chemical injection (a)
SGB-HV 201 A 12 Downcomer feedwater chemical injection (a)
SIA-UV 708 A 23 Containment recirc sump to post-accident sampling system HCB-UV 044 A 25A Containment air radioactivity monitor (inlet)
HCA-UV 045 A 25A Containment air radioactivity monitor (inlet)
HCA-UV 046 A 25B Containment air radioactivity monitor (outlet)
HCB-UV 047 A 25B Containment air radioactivity monitor (outlet)
GAA-UV 002 A 29 Nitrogen to steam generator and reactor drain tank GAA-UV 001 A 30 Nitrogen to SI tanks HPA-UV 001 A 35 Containment to hydrogen recombiner HPA-UV 003 A 35 Containment to hydrogen recombiner HPA-UV 024 A 35 Hydrogen control system HPB-UV 002 A 36 Containment to hydrogen recombiner HPA-UV 005 A 38 Containment to hydrogen recombiner HPB-UV 004 A 36 Hydrogen recombiner return to containment (inlet)
HPA-UV 023 A 38 Hydrogen control system HPB-UV 006 A 39 Hydrogen recombiner return to containment (inlet)
CHA-UV 516 A 40 Letdown line from RC loop 2B to regenerative heat exchanger and letdown heat exchanger CHB-UV 523 A 40 Letdown line from RC loop 2B to regenerative heat exchanger and letdown heat exchanger CHB-UV 924 A 40 Letdown line to post-accident sampling system SSB-UV 201 A 42A Pressurizer liquid sample line (continued)
- a. Not Type C Tested PALO VERDE UNITS 1, 2, 3 T7.0.300-1 Rev 50 12/10/09
Containment Isolation Valves TRM 7.0.300 T7.0 COMPONENT LISTS (continued)
VALVE NO ITS 3.6.3 PENETRATION VALVES RECEIVING CONTAINMENT ISOLATION Condition (CIAS)
SSA-UV 204 A 42A Pressurizer liquid sample line SSB-UV 202 A 42B Pressurizer steam space sample line SSA-UV 205 A 42B Pressurizer steam space sample line SSB-UV 200 A 42C Hot leg sample line SSA-UV 203 A 42C Hot leg sample line CHA-UV 560 A 44 Reactor Drain tank to pre-holdup ion exchanger CHB-UV 561 A 44 Reactor Drain tank to pre-holdup ion exchanger CHA-UV 580 A 45 Makeup to reactor drain tank CHA-UV 715 A 45 Makeup to reactor drain tank post accident sampling sys GRA-UV 001 A 52 RDT vent to WG surge tank GRB-UV 002 A 52 RDT vent to WG surge tank WCB-UV 63 A 60 Normal chilled water to containment ACU (inlet)
WCB-UV 61 A 61 Normal chilled water to containment ACU (outlet)
WCA-UV 62 A 61 Normal chilled water to containment ACU (outlet)
VALVES RECEIVING VALVE NO ITS 3.6.3 PENETRATION CONTAINMENT PURGE (CPIAS)
Condition [Also isolated on CIAS]
CPA-UV 002A A(a) 56 Containment purge (inlet)
(a)
CPB-UV 003A A 56 Containment purge (inlet)
CPA-UV 002B A(a) 57 Containment purge (outlet)
(a)
CPB-UV 003B A 57 Containment purge (outlet)
CPA-UV 004A A 78 Containment purge (inlet)
CPB-UV 005A A 78 Containment purge (inlet)
CPA-UV 004B A 79 Containment purge (outlet)
CPB-UV 005B A 79 Containment purge (outlet)
- a. Type C testing is not required when the valve is not a required containment isolation valve per Note 5 of LCO 3.6.3.
PALO VERDE UNITS 1, 2, 3 T7.0.300-2 Rev 41 3/14/07
Containment Isolation Valves TRM 7.0.300 T7.0 COMPONENT LISTS ITS 3.6.3 VALVES RECEIVING VALVE NO PENETRATION Condition CONTAINMENT SPRAY (CSAS)
IAA-UV-002 A 31 Service air to reactor containment inst. air NCB-UV-401 A 33 NC water to RCP motor bearing lube oil and air coolers NCB-UV-403 A 34 NC water to RCP motor bearing lube oil and air coolers NCA-UV-402 A 34 NC water to RCP motor bearing lube oil and air coolers CHB-UV-505 A 43 RC pump seal bleedoff CHA-UV-506 A 43 RC pump seal bleedoff ITS 3.6.3 CONTAINMENT ISOLATION VALVE NO PENETRATION Condition SAFETY/RELIEF VALVES AFB-PSV-0106(a)(b) A 75 Overpressure protection for CIV AFB-UV-034 AFB-PSV-0107(a)(b) A 76 Overpressure protection for CIV AFB-UV-035 (a)(b)
AFA-PSV-0108 A 75 Overpressure protection for CIV AFC-UV-036 (a)(b)
AFA-PSV-0109 A 76 Overpressure protection for CIV AFA-UV-037 (c)
NCE-PSV-0617 A 34 Overpressure protection for penetration 34 (a)
SIA-PSV 151 A 23 Containment recirculation sump to containment spray, LPSI and HPSI headers 1A & 1B SIB-PSV 140(a) A 24 Containment recirculation sump to containment spray, LPSI and HPSI headers 2A & 2B SIB-PSV 189(a) A 26 From shutdown cooling RC Loop 2 (Also covered by ITS 3.4.13)
SIA-PSV 179(a) A 27 From shutdown cooling RC Loop 1 (Also covered by ITS 3.4.13)
SIE-PSV 474 A 28 Safety injection drain relief
- a. Not Type C Tested
- b. Valve installation per DMWO 00741855
- c. Valve installation per DMWO 00830780 PALO VERDE UNITS 1, 2, 3 T7.0.300-3 Rev 32 9/9/04
Containment Isolation Valves TRM 7.0.300 T7.0 COMPONENT LISTS VALVE NO ITS 3.6.3 PENETRATION CONTAINMENT ISOLATION CHECK VALVES Condition SGE-V 642(a) A 11 Feedwater downcomer (a)
SGE-V 652 A 11 Feedwater downcomer SGE-V 653(a) A 12 Feedwater downcomer (a)
SGE-V 693 A 12 Feedwater downcomer GAE-V 015 A 29 Nitrogen to steam generator and reactor drain tank GAE-V 011 A 30 Nitrogen to SI tanks IAE-V 021 A 31 Service air to reactor containment instrument air header NCE-V 118 A 33 NC water to RCP motor bearing lube oil and air coolers HPA-V 002 A 38 Hydrogen recombiner return to containment HPB-V 004 A 39 Hydrogen recombiner return to containment CHE-V 494 A 45 Makeup to reactor drain tank WCE-V 039 A 60 Normal chilled water to containment ACU FPE-V 090 A 7 Containment fire protection SGE-V 003(a) A 8 Steam generator feedwater (a)
SGE-V 007 A 8 Steam generator feedwater (a)
SGE-V 005 A 10 Steam generator feedwater SGE-V 006(a) A 10 Steam generator feedwater (a)
SIE-V 113 A 13 HPSI to RC loop 2A SIE-V 123(a) A 14 HPSI to RC loop 2B (a)
SIE-V 133 A 15 HPSI to RC loop 1A (a)
SIE-V 143 A 16 HPSI to RC loop 1B SIE-V 114(a) A 17 LPSI to RC loop 2A (a)
SIE-V 124 A 18 LPSI to RC loop 2B SIE-V 134(a) A 19 LPSI to RC loop 1A (a)
SIE-V 144 A 20 LPSI to RC loop 1B (continued)
- a. Not Type C Tested PALO VERDE UNITS 1, 2, 3 T7.0.300-4 Rev 43 12/13/07
Containment Isolation Valves TRM 7.0.300 T7.0 COMPONENT LISTS (continued)
VALVE NO ITS 3.6.3 PENETRATION CONTAINMENT ISOLATION CHECK VALVES Condition SIA-V 164 A 21 Shutdown cooling heat exchanger 1 to CS header 1 SIB-V 165 A 22 Shutdown cooling heat exchanger 2 to CS header 2 CHE-V M70 A 41 Regenerative heat exchanger to RC loop 2A IAE-V 073 A 59 Containment service air utility station SIB-V 533(a) A 67 Long term recirculation loop 2 CHN-V 835 A 72 RC pump seal injection water to RCP 1A, 1B, 2A, 2B AFA-V 079(a) A 75 Steam generator 1 auxiliary feedwater (a)
AFB-V 080 A 76 Steam generator 2 auxiliary feedwater (a)
SIA-V 523 A 77 Long term recirculation loop 1 VALVE NO ITS 3.6.3 PENETRATION NORMALLY OPEN ESF ACTUATED CLOSED(d)
Condition SGE-UV 169(a) C 2 Main steam isolation bypass (a)
SGE-UV 183 C 3 Main steam isolation bypass SGA-UV 1133(a) C 2 Steam trap/bypass (a)
SGA-UV 1134 C 3 Steam trap/bypass SGB-UV 1135A(a) C 1 Steam trap/bypass (a)
SGB-UV 1135B C 2 Steam trap/bypass (a)
SGB-UV 1136A C 3 Steam trap/bypass SGB-UV 1136B(a) C 4 Steam trap/bypass SIA-UV 682 A 28 SI drain from drain tank (continued)
- a. Not Type C Tested
- d. The economizer and downcomer main feedwater isolation valves (MFIVs) are covered by specification 3.7.3, MFIVs.
PALO VERDE UNITS 1, 2, 3 T7.0.300-5 Rev 32 9/9/04
Containment Isolation Valves TRM 7.0.300 T7.0 COMPONENT LISTS (continued)
VALVE NO ITS 3.6.3 PENETRATION NORMALLY OPEN ESF ACTUATED CLOSED Condition SGA-UV 211(a) A 37A Steam generator blowdown sample (a)
SGB-UV 228 A 37A Steam generator blowdown sample SGA-UV 204(a) A 37B Steam generator blowdown sample (a)
SGB-UV 219 A 37B Steam generator blowdown sample SGA-UV 500P(a) A 46 Steam generator blowdown to SCCS (a)
SGB-UV 500Q A 46 Steam generator blowdown to SCCS (a)
SGB-UV 500R A 47 Steam generator blowdown to SCCS SGA-UV 500S(a) A 47 Steam generator blowdown to SCCS (a)
SGB-UV 226 A 48 SG blowdown to downcomer blowdown sample SGA-UV 227(a) A 48 SG blowdown to downcomer blowdown sample (a)
SGA-UV 220 A 49 SG blowdown to downcomer blowdown sample SGB-UV 221(a) A 49 SG blowdown to downcomer blowdown sample (a)
SGB-UV 224 A 63A SG2 blowdown sample (a)
SGA-UV 225 A 63A SG2 blowdown sample SGB-UV 222(a) A 63B SG2 blowdown sample (a)
SGA-UV 223 A 63B SG2 blowdown sample VALVE NO ITS 3.6.3 PENETRATION REQUIRED OPEN DURING ACCIDENT Condition SID-UV 654(a) A 26 From shutdown cooling RC loop 2 (a)
SIB-UV 656 A 26 From shutdown cooling RC loop 2 SIB-HV 690(a) A 26 From shutdown cooling RC loop 2 (a)
SIC-UV 653 A 27 From shutdown cooling RC loop 1 (a)
SIA-UV 655 A 27 From shutdown cooling RC loop 1 SIA-HV 691(a) A 27 From shutdown cooling RC loop 1 (a)(f)
HCC-HV 076 C 32A Containment pressure monitor HPA-HV 007A A 35 Containment to hydrogen monitor HPB-HV 008A A 36 Containment to hydrogen monitor (continued)
- a. Not Type C Tested
- f. Enter applicable Conditions and Required Actions of LCO 3.6.1, "Containment," when leakage results in exceeding the overall containment leakage rate acceptance criteria.
PALO VERDE UNITS 1, 2, 3 T7.0.300-6 Rev 32 9/9/04
Containment Isolation Valves TRM 7.0.300 T7.0 COMPONENT LISTS (continued)
VALVE NO ITS 3.6.3 PENETRATION REQUIRED OPEN DURING ACCIDENT Condition HPA-HV 007B A 38 Hydrogen monitor to containment HPB-HV 008B A 39 Hydrogen monitor to containment CHA-HV 524 A 41 Regenerative heat exchanger to RC Loop 2A (a)(f)
HCA-HV 074 C 54A Containment pressure monitor (a)(f)
HCB-HV 075 C 55A Containment pressure monitor (a)(f)
HCD-HV 077 C 62A CB pressure monitor SID-HV 331 A 67 Long-term recirculation loop 2 CHB-HV 255 A 72 RCP seal injection water to RCP 1A, 1B, 2A, 2B SIC-HV 321 A 77 Long-term recirculation loop 1 SGA-UV 134(a) C 2 Main steam to auxiliary feedwater turbine (a)
SGA-UV 134A C 2 Main steam to auxiliary feedwater turbine bypass (a)
SGA-UV 138 C 3 Main steam to auxiliary feedwater turbine (a)
SGA-UV 138A C 3 Main steam to auxiliary feedwater turbine bypass (a)
SIB-UV 616 A 13 HPSI to RC loop 2A (a)
SIA-UV 617 A 13 HPSI to RC loop 2A (a)
SIB-UV 626 A 14 HPSI to RC loop 2B (a)
SIA-UV 627 A 14 HPSI to RC loop 2B (a)
SIB-UV 636 A 15 HPSI to RC loop 1A (a)
SIA-UV 637 A 15 HPSI to RC loop 1A (a)
SIB-UV 646 A 16 HPSI to RC loop 1B SIA-UV 647(a) A 16 HPSI to RC loop 1B (a)
SIB-UV 615 A 17 LPSI to RC loop 2A (a)
SIB-UV 625 A 18 LPSI to RC loop 2B (a)
SIA-UV 635 A 19 LPSI to RC loop 1A (a)
SIA-UV 645 A 20 LPSI to RC loop 1B (a)
SIA-UV 672 A 21 Shutdown cooling heat exchanger 1 to CS header 1 (a)
SIB-UV 671 A 22 Shutdown cooling heat exchanger 2 to CS header 2 (a)
SIA-UV 673 A 23 Containment recirculation sump to CS, LPSI and HPSI headers 1A & 1B (continued)
- a. Not Type C Tested
- f. Enter applicable Conditions and Required Actions of LCO 3.6.1, "Containment," when leakage results in exceeding the overall containment leakage rate acceptance criteria.
PALO VERDE UNITS 1, 2, 3 T7.0.300-7 Rev 32 9/9/04
Containment Isolation Valves TRM 7.0.300 T7.0 COMPONENT LISTS (continued)
VALVE NO ITS 3.6.3 PENETRATION REQUIRED OPEN DURING ACCIDENT Condition SIA-UV 674(a) A 23 Containment recirculation sump to CS, LPSI and HPSI headers 1A & 1B SIB-UV 675(a) A 24 Containment recirculation sump to CS, LPSI and HPSI headers 2A & 2B SIB-UV 676(a) A 24 Containment recirculation sump to CS, LPSI and HPSI headers 2A & 2B AFB-UV 034(a) A 75 Steam generator 1 auxiliary feedwater (a)
AFC-UV 036 A 75 Steam generator 1 auxiliary feedwater AFB-UV 035(a) A 76 Steam generator 2 auxiliary feedwater (a)
AFA-UV 037 A 76 Steam generator 2 auxiliary feedwater VALVE NO ITS 3.6.3 PENETRATION MANUAL CONTAINMENT ISOLATION VALVES(e)
Condition NORMALLY CLOSED/POST-ACCIDENT CLOSED SGE-V-603(a) C 1 Nitrogen blanket supply/Nitrogen vent (a)
SGE-V-611 C 4 Nitrogen blanket supply/Nitrogen vent DWE-V 061 A 6 Containment demineralized water stations DWE-V 062 A 6 Containment demineralized water stations FPE-V 089 A 7 Fire protection containment SIE-V 463 A 28 Safety injection tank drain CHE-V 854 A 41 Chemical addition unit to regenerative hx (a)
SGE-V-293 A 46 SGB-UV-500Q Bypass line inlet SGE-V-294(a) A 47 SGA-UV-500S Bypass line inlet PCE-V 070 A 50 Fuel pool cooling PCE-V 071 A 50 Fuel pool cooling PCE-V 075 A 51 Refueling pool cleanup PCE-V 076 A 51 Refueling pool cleanup IAE-V 072 A 59 Containment service air utility station
- a. Not Type C Tested
- e. May be opened on an intermittent basis under administrative controls defined in the bases of TS 3.6.3, "Containment Isolation Valves."
PALO VERDE UNITS 1, 2, 3 T7.0.300-8 Rev 32 9/9/04
MOV Thermal Overload Protection and Bypass Devices TRM 7.0.400 T7.0 COMPONENT LISTS T7.0.400 MOV THERMAL OVERLOAD PROTECTION AND BYPASS DEVICES This list identifies the components subject to the testing requirements of TRM T3.8.102, MOV Thermal Overload Protection and Bypass Devices.
VALVE BYPASS DEVICE SYSTEM(S)
NUMBER (Accident Conditions) AFFECTED J-SIA-UV-647 HPSI A Flow Control to Reactor Coolant Valve Safety Injection Shutdown Cooling System J-SIA-UV-637 HPSI A Flow Control to Reactor Coolant Valve Safety Injection Shutdown Cooling System J-SIA-HV-604 HPSI Pump A Long Term Cooling Valve Safety Injection Shutdown Cooling System J-SIB-HV-609 HPSI Pump B Long Term Cooling Valve Safety Injection Shutdown Cooling System J-SIA-HV-657 Shutdown Clg. Temp. Control Train A Valve Safety Injection Shutdown Cooling System J-SIB-HV-658 Shutdown Clg. Temp. Control Train B Valve Safety Injection Shutdown Cooling System J-SIA-HV-685 LPSI - Ctmt Spray Pump Cross Connect A Valve Safety Injection Shutdown Cooling System J-SIB-HV-694 LPSI- Ctmt Spray Pump Cross Connect B Valve Safety Injection Shutdown Cooling System J-SIA-HV-686 Ctmt Spray A Cross Connect Valve Safety Injection Shutdown Cooling System J-SIB-HV-696 Ctmt Spray B Cross Connect Valve Safety Injection Shutdown Cooling System J-SIA-HV-688 Shutdown Clg. Heat Exchange\x11A Bypass Valve Safety Injection Shutdown Cooling System J-SIB-HV-693 Shutdown Clg. Heat Exchange\x11B Bypass Valve Safety Injection Shutdown Cooling System J-SIA-UV-617 HPSI A Flow Control To React Coolant 2A Valve Safety Injection Shutdown Cooling System J-SIA-UV-627 HPSI A Flow Control To React Coolant 2B Valve Safety Injection Shutdown Cooling System J-SIA-UV-645 LPSI Flow Control To React Coolant 1B Valve Safety Injection Shutdown Cooling System J-SIA-UV-635 LPSI Flow Control To React Coolant 1A Valve Safety Injection Shutdown Cooling System J-SIA-UV-644 Safety Injection Tank 1B Isolation Valve Safety Injection Shutdown Cooling System (continued)
PALO VERDE UNITS 1, 2, 3 T7.0.400-1 Rev 0 8/13/98
MOV Thermal Overload Protection and Bypass Devices TRM 7.0.400 T7.0 COMPONENT LISTS (continued)
VALVE BYPASS DEVICE SYSTEM(S)
NUMBER (Accident Conditions) AFFECTED J-SIA-UV-634 Safety Injection Tank 1A Isolation Valve Safety Injection Shutdown Cooling System J-SIB-UV-616 HPSI B Flow Control To React Coolant 2A Valve Safety Injection Shutdown Cooling System J-SIB-UV-626 HPSI B Flow Control To React Coolant 2B Valve Safety Injection Shutdown Cooling System J-SIB-UV-636 HPSI B Flow Control To React Coolant 1A Valve Safety Injection Shutdown Cooling System J-SIB-UV-646 HPSI B Flow Control To React Coolant 1B Valve Safety Injection Shutdown Cooling System J-SIA-UV-664 Ctmt Spray Pump A To Refueling Water Tank Safety Injection Shutdown Isolation Vlv. Cooling System J-SIB-UV-665 Ctmt Spray Pump B To Refueling Water Tank Safety Injection Shutdown Isolation Vlv. Cooling System J-SIB-UV-615 LPSI Flow Control To React Coolant 2A Valve Safety Injection Shutdown Cooling System J-SIB-UV-625 LPSI B Flow Control To React Coolant 2B Valve Safety Injection Shutdown Cooling System J-SIA-UV-666 HPSI Pump A to Refueling Water Tank Isolation Safety Injection Shutdown Cooling System J-SIB-UV-667 HPSI Pump B to Refueling Water Tank Isolation Safety Injection Shutdown Cooling System J-SIA-UV-669 LPSI Pump A To Refueling Water Tank Isolation Safety Injection Shutdown Cooling System J-SIB-UV-668 LPSI Pump B to Refueling Water Tank Isolation Safety Injection Shutdown Cooling System J-SIA-UV-672 Ctmt Spray Control Train A Valve Safety Injection Shutdown Cooling System J-SIB-UV-671 Ctmt Spray Control Train B Valve Safety Injection Shutdown Cooling System J-SIA-UV-674 Ctmt Sump Isolation Train A Valve Safety Injection Shutdown Cooling System J-SIB-UV-676 Ctmt Sump Isolation Train B Valve Safety Injection Shutdown Cooling System J-SIA-UV-673 Ctmt Sump Isolation Train A Valve Safety Injection Shutdown Cooling System (continued)
PALO VERDE UNITS 1, 2, 3 T7.0.400-2 Rev 0 8/13/98
MOV Thermal Overload Protection and Bypass Devices TRM 7.0.400 T7.0 COMPONENT LISTS (continued)
VALVE BYPASS DEVICE SYSTEM(S)
NUMBER (Accident Conditions) AFFECTED J-SIB-UV-675 Ctmt Sump Isolation Train B Valve Safety Injection Shutdown Cooling System J-SIB-UV-614 Safety Injection Tank 2A Isolation Valve Safety Injection Shutdown Cooling System J-SIB-UV-624 Safety Injection Tank 2B Isolation Valve Safety Injection Shutdown Cooling System J-SIA-HV-684 Shutdown Clg. Heat Exchange Isolation Train A Safety Injection Shutdown Cooling System J-SIB-HV-689 Shutdown Clg. Heat Exchange Isolation Train B Safety Injection Shutdown Cooling System J-SIA-HV-683 LPSI Pump A Isolation Valve Safety Injection Shutdown Cooling System J-SIB-HV-692 LPSI Pump B Isolation Valve Safety Injection Shutdown Cooling System J-SIA-HV-691 Shutdown Clg. Loop 2 Warm-Up Bypass Valve Safety Injection Shutdown Cooling System J-SIB-HV-690 Shutdown Clg. Loop 1 Warm-Up Bypass Valve Safety Injection Shutdown Cooling System J-SIA-HV-698 HPSI Pump A Discharge Valve Safety Injection Shutdown Cooling System J-SIB-HV-699 HPSI Pump B Discharge Valve Safety Injection Shutdown Cooling System J-SIA-HV-306 LPSI Pump A Header Discharge Valve Safety Injection Shutdown Cooling System J-SIB-HV-307 LPSI Pump B Header Discharge Valve Safety Injection Shutdown Cooling System J-SIA-HV-687 Ctmt Spray Isolation Train A Valve Safety Injection Shutdown Cooling System J-SIB-HV-695 Ctmt Spray Isolation Train B Valve Safety Injection Shutdown Cooling System J-SIA-HV-678 Shutdown Clg. Heat Exchange Isolation Train A Safety Injection Shutdown Cooling System J-SIB-HV-679 Shutdown Clg. Heat Exchange Isolation Train B Safety Injection Shutdown Cooling System J-EWA-UV-65 ECW Loop A To/From NCW Cross Tie Valve Essential Cooling Water System (continued)
PALO VERDE UNITS 1, 2, 3 T7.0.400-3 Rev 0 8/13/98
MOV Thermal Overload Protection and Bypass Devices TRM 7.0.400 T7.0 COMPONENT LISTS (continued)
VALVE BYPASS DEVICE SYSTEM(S)
NUMBER (Accident Conditions) AFFECTED J-EWA-UV-145 ECW Loop A To/From NCW Cross Tie Valve Essential Cooling Water System J-CTA-HV-1 Condensate Tank to Aux. Feedwater Pump Valve Condensate Transfer and Storage System J-CTA-HV-4 Condensate Tank to Aux. Feedwater Pump Valve Condensate Transfer and Storage System J-SGA-UV-134 SG-1 Aux. Feedwater Pump A Steam Supply Main Steam System J-SGA-UV-138 SG-2 Aux. Feedwater Pump A Steam Supply Main Steam System J-SGA-UV-134A SG-1 Aux. Feedwater Pump A Steam Supply Bypass Main Steam System J-SGA-UV-138A SG-2 Aux. Feedwater Pump A Steam Supply Bypass Main Steam System J-NCB-UV-401 NCWS Ctmt Isolation Valve Nuclear Cooling Water System J-NCA-UV-402 NCWS Ctmt Isolation Valve Nuclear Cooling Water System J-NCB-UV-403 NCWS Ctmt Isolation Valve Nuclear Cooling Water System J-AFB-HV-30 Aux. Feedwater Regulating Valve Auxiliary Feedwater System J-AFB-HV-31 Aux. Feedwater Regulating Valve Auxiliary Feedwater System J-AFB-UV-34 Aux. Feedwater Regulating Valve Auxiliary Feedwater System J-AFB-UV-35 Aux. Feedwater Isolation Valve Auxiliary Feedwater System J-AFA-HV-32 Aux. Feedwater Regulating Valve Auxiliary Feedwater System J-AFA-UV-37 Aux. Feedwater Isolation Valve Auxiliary Feedwater System J-AFC-UV-36 Aux. Feedwater Isolation Valve Auxiliary Feedwater System J-AFC-HV-33 Aux. Feedwater Regulating Valve Auxiliary Feedwater System J-CPA-UV-2A Ctmt Purge Refueling Mode Isolation Valve Containment Purge System J-CPB-UV-3B Ctmt Purge Refueling Mode Isolation Valve Containment Purge System J-CPA-UV-2B Ctmt Purge Refueling Mode Isolation Valve Containment Purge System J-CPB-UV-3A Ctmt Purge Refueling Mode Isolation Valve Containment Purge System J-WCA-UV-62 Normal Chill Water Return Ctmt Isolation Chilled Water System J-WCB-UV-63 Normal Chill Water Supply Ctmt Isolation Chilled Water System J-WCB-UV-61 Normal Chill Water Return Ctmt Isolation Chilled Water System J-RDA-UV-23 Ctmt Radwaste Sumps Internal Isolation Radioactive Waste Drain System J-HPA-UV-3 H2 Ctmt Train A Downstream Supply Isolation Containment Hydrogen Control Sys.
J-HPA-UV-5 H2 Ctmt Train A Return Isolation Valve Containment Hydrogen Control Sys.
(continued)
PALO VERDE UNITS 1, 2, 3 T7.0.400-4 Rev 51 3/25/10
MOV Thermal Overload Protection and Bypass Devices TRM 7.0.400 T7.0 COMPONENT LISTS VALVE BYPASS DEVICE SYSTEM(S)
NUMBER (Accident Conditions) AFFECTED J-HPB-UV-4 H2 Ctmt Train B Downstream Supply Isolation Containment Hydrogen Control Sys.
J-HPB-UV-6 H2 Ctmt Train B Return Isolation Valve Containment Hydrogen Control Sys.
J-HPB-UV-2 H2 Ctmt Train B Upstream Supply Isolation Containment Hydrogen Control Sys.
J-HPA-UV-1 H2 Ctmt Train A Upstream Supply Isolation Containment Hydrogen Control Sys.
J-GRA-UV-1 Radioactive Drain Tk Gas Surge Hdr Internal Gaseous Radwaste System Containment Isolation PALO VERDE UNITS 1, 2, 3 T7.0.400-5 Rev 0 8/13/98
Containment Penetration Conductor Overcurrent Protective Devices TRM 7.0.500 T7.0 COMPONENT LISTS T7.0.500 Containment Penetration Conductor Overcurrent Protective Devices The below referenced procedure identifies the components subject to the requirements of TRM T3.8.101.
Refer to 32DP-9ZZ12 PALO VERDE UNITS 1, 2, 3 T7.0.500-1 Rev 0 8/13/98
Technical Requirements Manual APPENDIX TA REACTOR COOLANT SYSTEM PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)
Palo Verde Nuclear Generating Station Units 1, 2, and 3 Summary of PTLR:
This reactor coolant system pressure and temperature limits report (PTLR) has been prepared in accordance with the reporting requirements of Technical Specification 5.6.9. NRC letter dated March 16, 2001, accepted report CE NPSD-683-A, Rev. 6, which provides the methodology for developing this PTLR. Application of CE NPSD-683 to PVNGS is documented in report WCAP-16835, Rev. 0.
Palo Verde Units 1, 2, 3 TA-i Rev 52 07/16/10
TRM Appendix TA PTLR TABLE OF CONTENTS TA1.0 Reactor Coolant System Pressure and Temperature Limits Report TA-1 TA2.0 Operating Limits............................................. TA-1 TA2.1 RCS Pressure and Temperature Limits (LCO 3.4.3)........ TA-2 TA2.2 RCS Loops - Mode 4 (LCO 3.4.6)......................... TA-2 TA2.3 RCS Loops - Mode 5, Loops Filled (LCO 3.4.7)........... TA-2 TA2.4 Pressurizer Safety Valves - Mode 4 (LCO 3.4.11)........ TA-2 TA2.5 Low Temperature Overpressure Protection System (LCO 3.4.13)........................................... TA-2 TA3.0 Neutron Fluence.............................................. TA-8 TA4.0 Reactor Vessel Material Surveillance Program................. TA-8 TA5.0 Adjusted Reference Temperature............................... TA-8 TA6.0 Application of Reactor Vessel Surveillance Data.............. TA-9 TA6.1 Applicability to Adjusted Reference Temperature........ TA-9 TA6.2 Evaluation of Surveillance Data Credibility........... TA-10 TA6.3 Derivation of Chemistry Factors from Surveillance Data TA-15 TA7.0 References.................................................. TA-15 Palo Verde Units 1, 2, 3 TA-ii Rev 52 07/16/10
TRM Appendix TA PTLR TABLE OF CONTENTS List of Figures Page TA2-1 RCS Heatup Limits through 32 EFPY...........................TA-6 TA2-2 RCS Cooldown Limits through 32 EFPY.........................TA-7 List of Tables Page TA2-1 RCS Heatup and Cooldown Rate Limits through 32 EFPY.........TA-3 TA2-2 Limiting RCS Temperatures through 32 EFPY...................TA-3 TA2-3 RCS Heatup P/T Limits through 32 EFPY.......................TA-4 TA2-4 RCS Cooldown P/T Limits through 32 EFPY.....................TA-5 TA3-1 Summary of Fluence and Fluence Factors......................TA-8 TA5-1 Summary of Limiting ART and RTPTS Values .....................TA-9 TA6-1 Base Metal Materials Selected for Surveillance Program.....TA-11 TA6-2 Unit 1 Credibility of Surveillance Measurements............TA-13 TA6-3 Unit 2 Credibility of Surveillance Measurements............TA-14 TA6-4 Unit 3 Credibility of Surveillance Measurements............TA-14 Palo Verde Units 1, 2, 3 TA-iii Rev 52 07/16/10
TRM Appendix TA PTLR TA1.0 Reactor Coolant System Pressure and Temperature Limits Report (PTLR)
This Pressure and Temperature Limits Report (PTLR) has been prepared in accordance with the requirements of Technical Specification (TS) 5.6.9. The following TSs are addressed in this report:
TS 3.4.3, RCS Pressure and Temperature Limits; TS 3.4.6, RCS Loops - Mode 4; TS 3.4.7, RCS Loops - Mode 5, Loops Filled; TS 3.4.11, Pressurizer Safety Valves - Mode 4; and TS 3.4.13, Low Temperature Overpressure Protection System.
TA2.0 Operating Limits Parametric limits for the above LCOs were developed using NRC-approved methods specified in Technical Specification 5.6.9 (Ref. 1). Application of the methodology approved for developing P/T limits, i.e., report CE NPSD-683-A (Ref. 2), to the Palo Verde Nuclear Generating Station is detailed in WCAP-16835 (Ref. 3).
The initial PTLR was submitted to the NRC along with the Technical Specification (TS) amendment request to relocate P/T limits to the PTLR (Ref. 4). The NRC approved the relocation of the P/T limits from TS to the PTLR in amendment no. 178 (Ref. 5). Subsequent changes to the PTLR are controlled in accordance with TS 5.6.9b and 10 CFR 50.59, and the PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for any revision or supplement thereto as required by TS 5.6.9c.
The pressure-temperature limit curves comply with Appendix G to 10 CFR Part 50 requirements that the temperature of the closure head flange and vessel flange regions must be at least 120°F higher than the limiting RTNDT for these regions. This RTNDT limit applies during normal operation, including heatup and cooldown, when the core is not critical and the vessel pressure exceeds 625 psia, (20% of the pre-service hydrostatic test pressure of 3125 psia).
Refer to the Technical Specifications for LCOs and surveillance requirements applicable to RCS pressure and temperature limits. Specific TS LCO limits relocated from the Technical Specifications into this PTLR are given below.
(continued)
Palo Verde Units 1, 2, 3 TA-1 Rev 52 07/16/10
TRM Appendix TA PTLR TA2.1 RCS Pressure and Temperature Limits (LCO 3.4.3)
RCS heatup and cooldown rates for Units 1, 2 and 3 through 32 EFPY shall be equal to or less than the values shown in Table TA2-1. Limiting RCS temperature requirements through 32 EFPY are specified in Table TA2-2. The RCS pressure and temperature for vessel head boltup, inservice hydrostatic and leak testing through 32 EFPY shall be limited as specified on Figure TA2-1 (or Table TA2-3) for RCS heatup, and Figure TA2-2 (or Table TA2-4) for RCS cooldown. A gradual change in reactor coolant system temperature of +/-10ºF in any 1-hour period is the maximum permitted during inservice hydrostatic and leak testing.
TA2.2 RCS Loops - Mode 4 (LCO 3.4.6)
The LTOP enable temperature for RCS heatup and cooldown through 32 EFPY is 221°F as specified in Table TA2-2.
TA2.3 RCS Loops - Mode 5, Loops Filled (LCO 3.4.7)
The LTOP enable temperature for RCS heatup and cooldown through 32 EFPY is 221°F as specified in Table TA2-2.
TA2.4 Pressurizer Safety Valves - Mode 4 (LCO 3.4.11)
The LTOP enable temperature for RCS heatup and cooldown through 32 EFPY is 221°F as specified in Table TA2-2.
TA2.5 Low Temperature Overpressure Protection System (LCO 3.4.13)
The LTOP enable temperature for RCS heatup and cooldown through 32 EFPY is 221°F as specified in Table TA2-2.
(continued)
Palo Verde Units 1, 2, 3 TA-2 Rev 52 07/16/10
TRM Appendix TA PTLR Table TA2-1 PVNGS Units 1, 2 and 3 RCS Heatup and Cooldown Rate Limits through 32 EFPY (Formerly TS Table 3.4.3-1)
Indicated RCS Cold Leg Heatup Rate Cooldown Rate Temperature (ºF)(1) (ºF/hr) (ºF/hr) 80º to 92º 75 30
> 92º to 100º 75 50
> 100º to 221º 75 100
> 221º 75 100 (1) Corrected for instrument uncertainty.
Table TA2-2 PVNGS Units 1, 2 and 3 Limiting RCS Temperatures through 32 EFPY Requirement RCS Temperature(1)
Minimum Boltup Temperature 80°F Minimum Hydrostatic Test Temperature 181.4°F Lowest Service Temperature 153.2°F Minimum Flange Limit (Hydrostatic Test) 163.2°F Minimum Flange Limit (Normal Operation) 193.2°F LTOP Heatup and Cooldown Enable Temperature 221°F (1) Corrected for instrument uncertainty.
(continued)
Palo Verde Units 1, 2, 3 TA-3 Rev 52 07/16/10
TRM Appendix TA PTLR Table TA2-3 PVNGS Unit 1, 2 and 3 RCS Heatup P/T Limits through 32 EFPY Indicated Pressure Indicated RCS Pressure (psia)(1) @ Heatup Rate Hydrostatic Temperature Isothermal Test(2)
(°F)(1) (psia) @10°F/hr @20°F/hr @30°F/hr @40°F/hr @50°F/hr @75°F/hr (psia) 80 680.6 680.6 680.6 671.1 650.2 622.2 602.2 954.4 83.2 690.2 690.2 690.2 676.2 650.2 622.2 602.2 967.2 93.2 727.2 727.2 705.2 676.2 650.2 622.2 602.2 1016.2 103.2 772.2 772.2 710.2 676.2 650.2 622.2 602.2 1075.2 113.2 826.2 826.2 735.2 681.2 650.2 622.2 602.2 1148.2 123.2 893.2 893.2 778.2 700.2 653.2 622.2 602.2 1237.2 133.2 974.2 974.2 839.2 738.2 672.2 627.2 602.2 1346.2 143.2 1074.2 1074.2 918.2 790.2 705.2 645.2 602.2 1478.2 153.2 1195.2 1195.2 1018.2 862.2 754.2 676.2 604.2 1640.2 163.2 1344.2 1335.2 1142.2 954.2 819.2 721.2 617.2 1838.2 171.5 1494.8 1467.5 1269.5 1049.0 889.9 772.8 638.0 2039.1 172.1 1507.0 1478.3 1279.9 1057.0 896.0 777.3 598.0 2053.6 173.2 1525.2 1494.2 1295.2 1068.2 904.2 783.2 600.2 2080.2 183.2 1747.2 1689.2 1484.2 1213.2 1014.2 865.2 637.2 2375.2 186.7 1841.7 1772.5 1565.4 1275.5 1062.2 902.0 655.4 2500.0 193.2 2017.2 1927.2 1716.2 1391.2 1151.2 970.2 689.2 203.2 2347.2 2217.2 1998.2 1610.2 1320.2 1101.2 757.2 207.0 2500.0 2351.5 2129.3 1713.2 1399.2 1162.4 790.6 211.2 2500.0 2274.2 1827.0 1486.6 1230.0 827.6 213.2 2343.2 1881.2 1528.2 1262.2 845.2 213.2 2327.2 1865.2 1512.2 1246.2 829.2 217.3 2500.0 1998.9 1616.3 1327.8 874.7 223.2 2191.2 1766.2 1445.2 940.2 230.8 2500.0 2008.6 1634.4 1045.8 233.2 2085.2 1694.2 1079.2 243.2 2474.2 2000.2 1250.2 243.7 2500.0 2018.8 1260.8 253.2 2372.2 1461.2 256.0 2500.0 1533.4 263.2 1719.2 273.2 2034.2 283.2 2418.2 284.9 2500.0 (1) Corrected for instrument uncertainty and for RCS pressure and elevation effects.
(2) A gradual change in reactor coolant system temperature of +/-10ºF in any 1-hour period is the maximum permitted during inservice hydrostatic and leak testing.
(continued)
Palo Verde Units 1, 2, 3 TA-4 Rev 52 07/16/10
TRM Appendix TA PTLR Table TA2-4 PVNGS Unit 1, 2 and 3 RCS Cooldown P/T Limits through 32 EFPY Indicated Indicated RCS Pressure (psia)(1) @ Cooldown Rate Temperature Isothermal @10F/hr @20F/hr @30F/hr @40F/hr @50F/hr @75F/hr @100F/hr (F)(1) 80 680.6 612.3 589.0 527.1 469.5 416.6 329.2 237.6 83.2 690.2 623.2 601.2 541.2 485.2 433.2 329.2 272.2 90.9 718.6 655.4 638.0 583.4 533.5 492.2 402.8 372.6 91.3 720.1 657.2 598.0 585.7 536.1 495.4 406.8 378.1 93.2 727.2 665.2 607.2 596.2 548.2 510.2 425.2 403.2 99.6 756.1 698.0 644.5 638.0 597.1 559.7 501.1 493.2 99.9 757.5 699.6 646.3 598.0 599.4 562.1 504.7 497.5 103.2 772.2 716.2 665.2 619.2 624.2 587.2 543.2 543.2 104.7 780.4 725.6 676.1 631.3 638.0 604.8 565.0 565.0 104.9 781.6 727.0 677.7 633.1 598.0 607.3 568.2 568.2 107.6 795.8 743.4 696.7 654.2 622.1 638.0 606.3 606.3 107.8 796.8 744.4 698.0 655.6 623.6 598.0 608.7 608.7 109.8 807.8 757.0 712.6 671.9 642.1 621.6 638.0 638.0 109.9 808.5 757.9 713.6 673.0 643.4 623.2 598.0 598.0 113.2 826.2 778.2 737.2 699.2 673.2 661.2 645.2 645.2 123.2 893.2 854.2 823.2 798.2 781.2 776.2 776.2 776.2 133.2 974.2 947.2 929.2 918.2 918.2 918.2 918.2 918.2 143.2 1074.2 1060.2 1057.2 1057.2 1057.2 1057.2 1057.2 1057.2 153.2 1195.2 1195.2 1195.2 1195.2 1195.2 1195.2 1195.2 1195.2 163.2 1344.2 1344.2 1344.2 1344.2 1344.2 1344.2 1344.2 1344.2 173.2 1525.2 1525.2 1525.2 1525.2 1525.2 1525.2 1525.2 1525.2 183.2 1747.2 1747.2 1747.2 1747.2 1747.2 1747.2 1747.2 1747.2 193.2 2017.2 2017.2 2017.2 2017.2 2017.2 2017.2 2017.2 2017.2 203.2 2347.2 2347.2 2347.2 2347.2 2347.2 2347.2 2347.2 2347.2 207.1 2500.0 2500.0 2500.0 2500.0 2500.0 2500.0 2500.0 2500.0 (1) Corrected for instrument uncertainty and for RCS pressure and elevation effects.
(continued)
Palo Verde Units 1, 2, 3 TA-5 Rev 52 07/16/10
TRM Appendix TA PTLR Figure TA2-1 PVNGS Units 1, 2 and 3 RCS Heatup Limits(1)(2) through 32 EFPY (Formerly TS Figure TS 3.4.3-2)
(1) Corrected for instrument uncertainty and for RCS pressure and elevation effects.
(2) A gradual change in reactor coolant system temperature of +/-10ºF in any 1-hour period is the maximum permitted during inservice hydrostatic and leak testing.
(continued)
Palo Verde Units 1, 2, 3 TA-6 Rev 52 07/16/10
TRM Appendix TA PTLR Figure TA2-2 PVNGS Units 1, 2 and 3 RCS Cooldown Limits(1)(2) through 32 EFPY (Formerly TS Figure TS 3.4.3-2)
(1) Corrected for instrument uncertainty and for RCS pressure and elevation effects.
(2) A gradual change in reactor coolant system temperature of +/-10ºF in any 1-hour period is the maximum permitted during inservice hydrostatic and leak testing.
(continued)
Palo Verde Units 1, 2, 3 TA-7 Rev 52 07/16/10
TRM Appendix TA PTLR TA3.0 Neutron Fluence The design value of peak fast neutron fluence through 32 EFPY for determining the limiting reactor vessel beltline material adjusted reference temperature is 3.29E+19 n/cm2 (E > 1.0 MeV) and corresponds to the fluence at the vessel clad-to-base metal interface. For conservatism, this peak fluence is assumed to apply to each of the PVNGS reactor vessel beltline plates and welds; i.e.,
no reduction factor is applied to account for axial or azimuthal variations from the peak value.
A summary of fast neutron fluence and fluence factors through 32 EFPY determined at the 1/4T and 3/4T locations in the vessel wall is given in Table TA3-1. These fluence values are used to calculate the adjusted reference temperature at PVNGS Units 1, 2 and 3.
Table TA3-1 Summary of Fluence and Fluence Factors Location 1/4T f (n/cm2)(1) 1/4T ff(2) 3/4T f (n/cm2)(1) 3/4T ff(2)
Intermediate Shell 1.681E+19 1.1431 4.390E+18 0.7711 Lower Shell 1.910E+19 1.1770 6.438E+18 0.8766 (1) f = fast neutron fluence (2) ff = fluence factor TA4.0 Reactor Vessel Material Surveillance Program The PVNGS reactor vessel material surveillance program, as described in Section 5.3 of the PVNGS Updated Final Safety Analysis Report (UFSAR), is in compliance with 10 CFR Part 50, Appendix H Reactor Vessel Material Surveillance Program Requirements. The surveillance capsule withdrawal schedules are presented in UFSAR Tables 5.3-13 through 5.3-19A and summarized in WCAP-16835 (Ref. 3). Test results and analyses of withdrawn surveillance specimens were reported in References 6, 7, and 8.
TA5.0 Adjusted Reference Temperature A summary of limiting adjusted reference temperatures associated with PVNGS beltline materials at the 1/4T and 3/4T locations along with RTPTS values through 32 EFPY is given in Table TA5-1. Conservatively, the most limiting (highest) adjusted reference temperature value from the three PVNGS units is (continued)
Palo Verde Units 1, 2, 3 TA-8 Rev 52 07/16/10
TRM Appendix TA PTLR applied to all three units. Chemistry factors and adjusted reference temperatures for PVNGS are determined in accordance with Regulatory Guide 1.99 (Ref. 9).
Table TA5-1 Summary of Limiting ART and RTPTS Values 1/4T ART PVNGS Location Material 3/4T ART (°F) RTPTS (°F)
(°F)
Unit 1 Inter. Shell Plate M-6701-2 116 103 123 Unit 2 Inter. Shell Plate F-765-6 74 64 78 Unit 3 Lower Shell Plate F-6411-2 65 57 68 Limiting adjusted reference temperatures are incorporated into the calculation of pressure-temperature curves and limits for heatup, cooldown, LTOP, and hydrostatic and leak tests.
Seven reactor vessel surveillance capsules have been removed from PVNGS Units 1, 2 and 3 through December 2007, with a minimum of two credible data sets available for each PVNGS unit. Even though WCAP-16835 shows that the post-irradiation surveillance capsule test results for PVNGS units are credible, the calculation of ART takes no credit for those credible results.
TA6.0 Application of Reactor Vessel Surveillance Data TA6.1 Applicability to Adjusted Reference Temperature Data from the reactor vessel surveillance program or from other supplemental sources were not used to determine the adjusted reference temperature (ART) values for the PVNGS beltline materials described in Section 5. The surveillance program data from each of the three Palo Verde units were evaluated for credibility; chemistry factors were also derived for those surveillance materials. (This assessment is further detailed in Report WCAP-16835 [Ref. 3].)
Chemistry factors determined following Position 1.1 of Regulatory Guide 1.99 are shown to be conservative relative to those derived from surveillance plate and weld measurements for each of the PVNGS units. Therefore, no credit is taken for those credible results in the calculation of ART.
(continued)
Palo Verde Units 1, 2, 3 TA-9 Rev 52 07/16/10
TRM Appendix TA PTLR Each new set of surveillance results, as new data becomes available, will be evaluated to ascertain that the Position 1.1 chemistry factors remain conservative relative to the surveillance results. This will ensure that the existing RCS P/T limits remain conservative for continued plant operation or will be revised as needed to provide conservative RCS pressure-temperature limits.
TA6.2 Evaluation of Surveillance Data Credibility Regulatory Guide 1.99 describes general procedures acceptable to the NRC staff for calculating the effects of neutron radiation embrittlement of low-alloy steels used in the PVNGS reactor vessels when credible surveillance capsule data is available. Position C.2 of Regulatory Guide 1.99 describes the method for calculating the adjusted reference temperature and Charpy upper-shelf energy of reactor vessel beltline materials using surveillance capsule data.
The methods of Position C.2 apply when two or more credible surveillance data sets become available from each unit.
Post-irradiation surveillance capsule test results for PVNGS were evaluated with respect to the credibility criteria of Regulatory Guide 1.99 Revision 2.
Results of the credibility assessment found that:
The surveillance program plates and welds are those judged to be most likely controlling with regard to radiation-induced embrittlement, Charpy data scatter does not cause ambiguity in the determination of the 30 ft-lb shift, Measured RTNDT shifts are consistent with the predicted shifts, Capsule irradiation temperature matches that of the vessel wall, and Correlation monitor data falls within the scatter band for that material and therefore meets the credibility test.
Revision 2 of Regulatory Guide 1.99 defines five requirements that must be met for surveillance data to be judged credible. The purpose of the following discussion is to apply these credibility requirements to PVNGS to show that the reactor vessel surveillance data are credible.
Criterion 1: Materials in the capsules should be those judged most likely to be controlling with regard to radiation embrittlement.
(continued)
Palo Verde Units 1, 2, 3 TA-10 Rev 52 07/16/10
TRM Appendix TA PTLR The beltline region of the reactor vessel is defined in Appendix G(II)(F) to 10 CFR Part 50, Fracture Toughness Requirements, as:
Beltline or beltline region of the reactor vessel means the region of the reactor vessel (shell material including welds, heat affected zones, and plates or forgings) that directly surrounds the effective height of the active core and adjacent regions of the reactor vessel that are predicted to experience sufficient neutron radiation damage to be considered in the selection of the most limiting material with regard to radiation damage.
Table TA6-1 identifies the Units 1, 2, and 3 reactor vessel base metal beltline plate materials selected for the PVNGS surveillance program.
Table TA6-1 Base Metal Materials Selected for Surveillance Program PVNGS Plate ID Number Plate Location (1)
Unit 1 M-4311-1 Lower Shell Unit 1(1) M-6701-2 Intermediate Shell Unit 2 F-773-1 Lower Shell Unit 3 F-6411-2 Lower Shell (1)
Unit 1 has two different base metal surveillance materials.
The weld materials for the PVNGS Units 1, 2, and 3 surveillance programs are selected to duplicate the materials in the lower shell axial weld seams. Test specimens from these materials are heat-treated to a condition representative of the final metallurgical condition of the weld metal in the completed reactor vessel. These surveillance weld metals were made with the same weld wire heat as that of the vessel beltline weld seams and are, therefore, representative of all beltline weld seams.
Intermediate shell plate M-6701-2 in Unit 1 has the highest initial RTNDT and the highest ART of all PVNGS plate materials in the beltline region.
Therefore, the PVNGS Units 1, 2, and 3 surveillance material meets the intent of this criterion.
Criterion 2: Scatter in the plots of Charpy energy versus temperature for the irradiated and unirradiated conditions should be small enough to permit the determination of the 30 ft-lb temperature and upper shelf energy unambiguously.
(continued)
Palo Verde Units 1, 2, 3 TA-11 Rev 52 07/16/10
TRM Appendix TA PTLR Evaluation of Charpy energy versus temperature for the unirradiated and irradiated condition is presented in References 6, 7, and 8. Based on engineering judgment, the scatter in the data presented is small enough to permit the unambiguous determination of the 30 ft-lb temperature and the upper shelf energy of the PVNGS Units 1, 2, and 3 surveillance materials. Thus, the PVNGS surveillance program meets this criterion.
Criterion 3: When there are two or more sets of surveillance data from one reactor, the scatter of RTNDT values about a best-fit line drawn as described in Regulatory Position 2.1 normally should be less than 28°F for welds and 17°F for base metal. Even if the fluence range is large (two or more orders of magnitude), the scatter should not exceed twice those values. Even if the data fail this criterion for use in shift calculations, they may be credible for determining decrease in upper shelf energy if the upper shelf can be clearly determined, following the definition given in ASTM E 185-82.
The surveillance program for PVNGS Units 1, 2, and 3 is based on ASTM E185-79, which presents criteria for monitoring changes in the fracture toughness properties of reactor vessel beltline materials. References 6, 7, and 8 describe the post-irradiation evaluations of PVNGS surveillance materials.
The credibility results shown in Tables TA6-2, TA6-3 and TA6-4 for Units 1, 2, and 3, respectively, present the shift measurements available to date. Those values are compared to predictions based on a chemistry factor determined following Position 1.1 of Regulatory Guide 1.99. In all cases, the difference between the measured and predicted shift is less than 17ºF for the surveillance plates and less than 28ºF for the surveillance welds. Therefore, this criterion is met for the PVNGS Units 1, 2, and 3 surveillance program plate and weld materials.
(continued)
Palo Verde Units 1, 2, 3 TA-12 Rev 52 07/16/10
TRM Appendix TA PTLR Table TA6-2 PVNGS Unit 1 Credibility of Surveillance Measurements Plate, Weld and Correlation Monitor Materials Measured Predicted Shift Difference Material Capsule CF ff(2)
Shift (°F) (CF*ff) (°F) (°F)
Plate 137 27.5 0.7216 34.2 19.8 + 14.4 M-6701-2 Longitudinal 230 27.5 0.9629 15.3 26.5 - 11.2 Plate 137 27.5 0.7216 13.0 19.8 - 6.8 M-6701-2 Transverse 230 27.5 0.9629 31.9 26.5 + 5.4 137 4.9 0.7216 - 2.8 3.5 - 6.3 Weld 38 4.9 0.8697 6.7 4.3 + 2.4 (Heat 90071) 230 4.9 0.9629 5.1 4.7 + 0.4 137 131.7(1) 0.7216 101.3 95.0 + 6.3 Correlation (1)
Monitor 38 131.7 0.8697 114.1 114.5 - 0.4 Material 230 131.7(1) 0.9629 129.2 126.8 + 2.4 (1) Chemistry factor based on 0.174 Cu and 0.665 Ni using Table 2 of Regulatory Guide 1.99, Rev. 2.
(2) ff = fluence factor = f(0.28 - 0.1*log f)
(continued)
Palo Verde Units 1, 2, 3 TA-13 Rev 52 07/16/10
TRM Appendix TA PTLR Table TA6-3 PVNGS Unit 2 Credibility of Surveillance Measurements Plate, Weld and Correlation Monitor Materials Measured Predicted Shift Difference Material Capsule CF ff(2)
Shift (°F) (CF*ff) (°F) (°F)
Plate F-773-1 137 17.5 0.7372 13.3 12.9 + 0.4 Longitudinal 230 17.5 0.9978 17.7 17.5 + 0.2 Plate F-773-1 137 17.5 0.7372 9.5 12.9 - 3.4 Transverse 230 17.5 0.9978 19.3 17.5 + 1.8 Weld 137 1.6 0.7372 0 1.2 - 1.2 (Heat 3P7317) 230 1.6 0.9978 2.5 1.6 + 0.9 (1)
Correlation 137 131.7 0.7372 116.0 97.1 + 18.9 Monitor (1)
Material 230 131.7 0.9978 132.4 131.4 + 1.0 (1) Chemistry Factor based on 0.174 Cu and 0.665 Ni using Table 2 of Regulatory Guide 1.99, R02.
(2) ff = fluence factor = f(0.28 - 0.1*log f)
Table TA6-4 PVNGS Unit 3 Credibility of Surveillance Measurements Plate, Weld and Correlation Monitor Materials Measured Predicted Shift Difference Material Capsule CF ff(2)
Shift (°F) (CF*ff) (°F) (°F)
Plate F-6411-2 230 10.2 0.9726 6.3 9.9 - 3.6 Longitudinal Plate F-6411-2 142 10.2 0.7090 13.1 7.2 + 5.9 Transverse 230 10.2 0.9726 9.2 9.9 - 0.7 Weld 142 29.6 0.7090 27.5 21.0 + 6.5 (Heat 4P7869) 230 29.6 0.9726 24.1 28.8 - 4.7 Correlation 142 131.7 (1) 0.7090 82.5 93.4 - 10.9 Monitor Material 230 131.7(1) 0.9726 141.8 128.1 + 13.7 (1) Chemistry Factor based on 0.174 Cu and 0.665 Ni using Table 2 of Regulatory Guide 1.99, R02.
(2) ff = fluence factor = f(0.28 - 0.1*log f)
(continued)
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TRM Appendix TA PTLR Criterion 4: The irradiation temperature of the Charpy specimens in the capsule should match the vessel wall temperature at the cladding/base metal interface within +/- 25°F.
All reactor vessel surveillance specimen capsule holders are attached to the inside vessel wall cladding in the beltline region at PVNGS. This capsule holder attachment method meets the design and inspection requirements of the ASME Code, Sections III and XI. The location of the specimens relative to the reactor vessel beltline provides assurance that the reactor vessel wall and the specimens experience equivalent operating conditions such that the temperatures will not differ by more than 25°F. Hence this criterion is met.
Criterion 5: The surveillance data for the correlation monitor material in the capsule should fall within the scatter band of the data base for that material.
As shown in Tables TA6-2, TA6-3, and TA6-4, the correlation monitor materials from PVNGS Units 1, 2, and 3 meet the credibility test to be within the scatter band of the database for that material.
TA6.3 Derivation of Chemistry Factors from Surveillance Data The derived chemistry factor (CF) values for each of the Palo Verde Units 1, 2, and 3 surveillance materials is provided in Tables TA6-2, TA6-3, and TA6-4.
The derived chemistry factor for the Unit 1 surveillance plate (M-6701-2) and surveillance weld (Heat 90071) are 27.5ºF and 4.9ºF, respectively. These chemistry factor values compare favorably with their respective values of 37ºF and 27.8ºF determined following Position 1.1 of Regulatory Guide 1.99.
Similar conservative results are found for Unit 2 plate (F-773-1) and surveillance weld (Heat 3P7317), and for Unit 3 plate (F-6411-2) and surveillance weld (Heat 4P7869). Therefore, chemistry factors determined following Position 1.1 of Regulatory Guide 1.99 are shown to be conservative relative to those derived from surveillance plate and weld measurements for each of the PVNGS units.
TA7.0 References
- 1. PVNGS Units 1, 2, and 3 Technical Specification 5.6.9, Reactor Coolant System Pressure and Temperature Limits Report.
- 2. CE Owners Group Topical Report CE NPSD-683-A, Revision 6, Development of a RCS Pressure and Temperature Limits Report for the Removal of P/T (continued)
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TRM Appendix TA PTLR Limits and LTOP Requirements from the Technical Specifications, April 2001.
- 3. Westinghouse Report WCAP-16835, Revision 0, Palo Verde Nuclear Generating Station Units 1, 2 and 3, Basis for RCS Pressure-Temperature Limits Report, June 2008.
- 4. APS letter No. 102-05960 to NRC, Request for Technical Specification Amendment to Relocate the Reactor Coolant System Pressure and Temperature Limits and the Low Temperature Overpressure Protection Enable Temperatures, dated February 19, 2009. Supplemented by APS Letter No. 102-06112, Response to Request for Additional Information for Technical Specification Amendment and Exemption from 10 CFR 50, Appendix G, to Relocate the Reactor Coolant System Pressure and Temperature Limits and the Low Temperature Overpressure Protection Enable Temperatures, dated December 22, 2009.
- 5. Letter, NRC to APS, Palo Verde Nuclear Generating Station, Units 1, 2, and 3 - Issuance of Amendments Re: [Relocation of RCS Pressure and Temperature Limits] (TAC NOS. ME0698, ME0699, AND ME0700), dated February 25, 2010 (Amendment No. 178).
- 6. APS letter no. 102-05242 to NRC, Palo Verde Nuclear Generating Station Unit 1 Reactor Vessel Material Surveillance Capsule at 230°, April 5, 2005 (transmittal of WCAP-16374-NP, Analysis of Capsule 230° from Arizona Public Service Company Palo Verde Unit 1 Reactor Vessel Radiation Surveillance Program, February 2005).
- 7. APS letter no. 102-05457 to NRC, Palo Verde Nuclear Generating Station Unit 2 Reactor Vessel Material Surveillance Capsule at 230°, April 4, 2006 (transmittal of WCAP-16524-NP, Analysis of Capsule 230° from Arizona Public Service Company Palo Verde Unit 2 Reactor Vessel Radiation Surveillance Program, February 2006).
- 8. APS letter no. 102-05348 to NRC, Palo Verde Nuclear Generating Station Unit 3 Analysis of Reactor Vessel Material Surveillance Capsule at 230°, September 26, 2005 (transmittal of WCAP-16449-NP, Analysis of Capsule 230° from Arizona Public Service Company Palo Verde Unit 3 Reactor Vessel Radiation Surveillance Program, August 2005).
- 9. Regulatory Guide 1.99, Revision 2, Radiation Embrittlement of Reactor Vessel Materials, U.S. Nuclear Regulatory Commission, May 1998.
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