ML14091A960
| ML14091A960 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 09/25/2013 |
| From: | Stephenson C Arizona Public Service Co |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML14091A919 | List: |
| References | |
| 102-06859-TNW/DHK | |
| Download: ML14091A960 (23) | |
Text
PVNGS Technical Requirements Manual (TRM)
Revision 59 Replacement Pages and Insertion Instructions The followingLDCRsare includedin this change:
LDCR 12-R007 adds 3 credited incore instrument strings (locations J-07, R-09 and D-14) to implement new analysis of record for Inadvertent Loading of a Fuel Assembly. In addition, changes include requiring at least one operable detector string in all 4x4 arrays of fuel assemblies that contain 16 fuel assemblies. New TLCO Conditions B, C and D added to address action to be taken for inoperable detectors prior to 30 percent power and after initial power ascension above 30 percent power. Conforming changes were also made to the TRM Bases for this specification.
LDCR 13-R003 revises various TRM surveillance frequencies to reflect 18-month staggered test frequencies, consistent with Surveillance Test Risk-Informed Documented Evaluations (STRIDEs) PVN-I-0007, Revision 1 and PVN-O-0015, Revision 0. Specifically, TRM SRs 3.3.108.3, 3.3.108.4, 3.4.201.1, 3.5.200.4.2, 3.8.102.1 and 3.9.104.3 test frequencies are changed to 18-months on a staggered test basis.
Instructions Remove Paqe: Insert New Paqe:
Cover Page Cover Page List of Effective Pages, List of Effective Pages, Pages 1 through 4 Pages 1 through 4 T3.3.102-1 T3.3.102-1 T3.3.102-2 T3.3.102-2 T3.3.102-3 (new page)
T3.3.102-4 (new page)
T3.3.108-2 T3.3.108-2 T3.4.201-1 T3.4.201-1 T3.5.200-2 T3.5.200-2 T3.8.102-2 T3.8.102-2 T3.9.104-3 T3.9.104-3 T6.0.100-11 T6.0.100-11 through through T6.0.100-18 T6.0.100-18 Digitally signed by Stephenson, 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: 2013.09.11 15:23:47 -07'00'
Technical Requirements Manual Revision 59 September 25, 2013 n_-ep"enson J,Z0577_,DigitallysignedbySteph
_£ I DN:cn=Stephenson, Carl...... Carl J(Z05778)
Carl _v_v.,..oj 1 [71_ _::_,_ ,7 !_ _ R...... , ..... troth .......
,ntegrltyofth[sd Date: 2013.09.11 .......
15;12:38 o/and
-07'00' PALOVERDE UNITS1, 2, 3
Technical Requirements Manual LIST OF EFFECTIVE i
PAGES Page No. Revision No. Page No. Revision No.
TOC)agei 58 T3.3.103-1 51 TOC )age ii 48 T3.3.103-2 54 TOC )age iii 33 T3.3,103-3 13 TOC )age iv 52 T3.3.103-4 13 TI 1 100-I 0 T3.3 104-1 46 T1 2 100-1 0 T3 3 104-2 0 TI 3 100-1 0 T3 3 105-1 46 T1 4 100-1 0 T3 3 105-2 48 T2 0 100-i 0 T3 3 I05-3 48 T3 0 100-i 47 T3 3 106-I 46 T3 0 100-2 40 T3 3 106-2 14 T3 0 100-3 23 T3 3 107-1 56 T3 0 100-4 47 T3 3 107-2 46 T3 1 !00-1 0 T3 3 108-1 0 T3 1 100-2 0 T3 3 108-2 59 T3 1 101-1 0 T3 3 200-I 46 T3 1 101-2 54 T3 3 200-2 31 T3 1 101-3 0 T3 3 201-i 0 T3 1 102-1 0 T3 4 100-I 28 T3 1 103-1 1 T3 4 101-i 0 T3 1 104-i 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-I 28 T3.1.201-1 0 T3.4.104-2 55 T3.1.202-I 53 T3.4.200-I 52 T3.1.202-2 46 T3.4.201-I 59 T3.1.203-1 29 T3.4.202-I 46 T3.2.200-1 53 T3.4.203-I 46 T3.3.100-I 46 T3.4.204-I 46 T3.3.100-2 10 T3.5.200-I 46 T3.3 101-i 40 T3.5.200-2 59 T3.3 101-2 46 T3.5.200-3 0 T3.3 101-3 18 T3.5 201-I 16 T3 3 101-4 18 T3 5 201-2 47 T3 3 101-5 52 T3 5 202-i 46 T3 3 102-1 59 T3 5 202-2 39 T3 3 102-2 59 T3 5 202-3 47 T3 3 102-3 59 T3 5 202-4 0 T3 3 102-4 59 T3 5 203-I 46 PALOVERDEUNITS 1, 2, 3 1 Rev 59 09/25/13
Technical RequirementsManual LIST OF EFFECTIVEPAGES Page No. Revision No. Page No. Revision No.
T3.5,203-2 35 T3 9.201-i 46 T3 6.100-1 48 T3 10 200-1 40 T3 6 100-2 0 T3 10 201-1 0 T3 6 200-i 22 T3 10 201-2 0 T3 6 200-2 22 T3 10 202-i 40 T3 6 201-1 47 T3 10 202-2 0 T3 6 300-i 48 T3 11 100-i 40 T3 6 300-2 48 T3 11 100-2 38 T3 7 100-1 27 T3 11 100-3 38 T3 7 100-2 27 T3 11 100-4 38 T3 7 101-1 46 T3 11 100-5 38 T3 7 101-2 46 T3 11 100-6 38 T3 7 102-1 0 T3 11.100-7 38 T3 7 102-2 0 T3,11,100-8 38 T3 7 102-3 0 T3.11.100-9 38 T3 7 200-i 58 T3.11.101-I 40 T3 7 201-I 46 T3.11.101-2 46 T3 7 202-I 46 T3.11.101-3 46 T3 7 203-1 46 T3.11.101-4 39 T3.7 204-I 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-I 46 T3.11.I02-4 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-I 44 T3.8.101-3 12 T3 11 104-2 4 T3.8.101-4 0 T3 11 104-3 4 T3.8.102-I 0 T3 11 104-4 18 T3.8.102-2 59 T3 11 105-i 46 T3.8.200-1 0 T3 11 105-2 4 T3.9.100-I 0 T3 11 105-3 18 T3.9,101-1 0 T3 11 106-1 40 CORRECTED T3.9 102-I 0 T3 11 106-2 49 T3 9 102-2 0 T3 11 107-1 40 CORRECTED T3 9 103-I 0 T3 11 107-2 4 T3 9 104-I 0 T3 11 107-3 4 T3 9 104-2 0 T4 0.100-1 0 T3 9 104-3 59 T5 0.100-I 0 T3 9 200-1 46 T5 0.200-I 0 T3 9 200-2 29 T5 0.300-1 0 PALOVERDEUNITS 1, 2, 3 2 Rev 59 09/25/13
Technical RequirementsManual LIST OF EFFECTIVEPAGES Page No. Revision No. Page No. Revision No.
T5.0.400-1 0 T6 0 100-23 58 T5.0.500-1 53 T6 0 I00-24 58 T5 0 500-2 24 T6 0 100-25 58 T5 0 500-3 0 T6 0 100-26 58 T5 0 500-4 53 T6 0 100-27 58 T5 0 500-5 0 T6 0 100-28 58 T5 0 500-6 0 T6 0 100-29 58 T5 0 500-7 0 T6 0 100-30 58 T5 0 500-8 22 T6 0 100-31 58 T5 0 500-9 0 T6 0 100-32 58 T5 0 500-10 0 T6 0 100-33 58 T5 0 500-11 57 T6 0 100-34 58 T5 0 500-12 57 T6 0 100-35 58 T5 0 500-13 57 T7 0 100-i 52 T5 0 500-14 57 T7 0 100-2 52 T5 0 500-15 57 T7 0 100-3 0 T5 0 500-16 57 T7 0 200-i 52 T5 0 500-17 57 T7.0.200-2 52 T5 0 600-1 37 T7.0,200-3 0 T5 0 600-2 37 T7.0.300-I 57 T5 0 700-1 34 T7.0.300-2 41 T6 0 100-1 40 T7.0.300-3 57 T6 0 100-2 40 T7.0.300-4 43 T6 0 100-3 40 T7.0.300-5 32 T6 0 100-4 40 T7.0.300-6 32 T6 0 100-5 46 T7.0.300-7 32 T6 0 100-6 40 T7.0.300-8 32 T6 0 100-7 54 T7.0.400-I 0 T6 0 100-8 46 T7,0.400-2 0 T6,0.100-9 58 T7.0,400-3 0 T6.0.100-10 58 T7.0.400-4 51 T6.0.I00-11 59 17.0.400-5 0 T6.0.I00-12 59 T7.0,500-I 0 T6.0,I00-13 59 TA-i 52 T6.0.100-14 59 TA-ii 52 T6.0.I00-15 59 TA-iii 52 T6.0.I00-16 59 TA-1 52 T6.0.I00-17 59 TA-2 52 T6.0.100-18 59 TA-3 52 T6.0.100-19 58 TA-4 52 T6.0.100-20 58 TA-5 52 T6.0.I00-21 58 TA-6 52 T6.0.100-22 58 TA-7 52 PALOVERDEUNITS 1, 2, 3 3 Rev 59 09/25/13
Technical RequirementsManual LIST OF EFFECTIVEPAGES Page No. Revision No. Page No. Revision No.
TA-8 52 TA-9 52 TA-IO 52 TA-11 52 TA-12 57 TA-13 52 TA-14 52 TA-15 52 TA-16 52 PALOVERDE UNITSi, 2, 3 4 Rev 59 09/25/13
Incore Detectors TRM3.3.102 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, and,
- d. All 4x4 arrays of fuel assemblies that contain 16 fuel assemblies must contain at least one OPERABLE incore location.
............................. NOTE ............................
- 1. The Incore Detection System contains 53 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: Whenthe Incore Detection System is used for monitoring:
- a. AZIMUTHALPOWER TILT,
- b. Radial Peaking Factors,
- c. Local Power Density,
- d. DNBMargin PALOVERDEUNITS I, 2, 3 T3.3.102-I Rev 59 9/25/13
Incore Detectors TRM3.3.102 ACTIONS i CONDITION REQUIRED ACTION COMPLETION TIME
-NOTE A.I Do not use the Incore Immediately The provisions of Detection System for Specification 3.0.100.3 monitoring or are not applicable, calibration functions.
A. Incore Detection System inoperable per TLCO 3.3.102.a, b, or c above.
B. Incore Detector System B.1.1 Evaluate the ability of Prior to initial inoperable per TLCO the incore detector power ascension 3.3.102.d prior to system to detect above 30%power initial power ascension average power asymmetry above 30%power, of at least 10%between quadrant 4x4 groups of assemblies with the actual operable incore detector pattern, AND B.I.2 Make suitable adjustments to COLSS and CPCSto assure conservative indications of the DNBR and Peak Linear Heat Rate margins.
(continued)
PALOVERDEUNITS 1, 2, 3 T3.3.102-2 Rev 59 9/25/13
Incore Detectors TRM3.3. I02 ACTIONS(continued)
CONDITION REQUIRED ACTION COMPLETION TIME C. Incore Detector System C.I.1 Evaluate the ability of Within 7 EFPD inoperable per TLCO the incore detector 3.3.102.d after initial system to detect power ascension above average power asymmetry 30%power, of at least 10%between quadrant 4x4 groups of assemblies with the actual operable incore detector pattern, AND C.I.2 Make suitable adjustments to COLSS and CPCSto assure conservative indications of the DNBR and Peak Linear Heat Rate margins.
D. Required Action and/or D.I Enter TLCO3.0.100.3. Immediately associated Completion Time of condition B or C not met. i ,,
PALOVERDEUNITS i, 2, 3 T3.3.102-3 Rev 59 9/25/13
Incore Detectors TRM3.3.102 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 CALIBRATIONbut 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 PALOVERDEUNITS I, 2, 3 T3.3.102-4 Rev 59 9/25/13
Fuel Building Essential Ventilation Actuation Signal (_EVAS)
TRM3.3.108 SURVEILLANCE REQUIREMENTS NOTE-Surveillance Requirements for RU-145 are specified in the ODCM.
SURVEILLANCE FREQUENCY TSR 3 3.108.1 Perform a CHANNEL CHECKon 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 TESTon RU-31 92 days to include that the setpoint is _ 15 mR/hr and the measurement range is IOE-I to IOE+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 TESTon 18 months on a required FBEVIAS Actuation Logic channel. STAGGERED TEST BASIS TSR 3.3,108.4 Perform a CHANNEL FUNCTIONAL TESTon 18 months on a required FBEVASManual Trip logic. STAGGERED TEST BASIS TSR 3.3,108.5 Perform a CHANNEL CALIBRATIONon RU-31. 18 months i i PALOVERDE UNITSi, 2, 3 T3.3.108-2 Rev 59 9/25/13
Pressurizer TRM3.4.201 T3.4 REACTOR COOLANT SYSTEM(RCS)
T3.4.201 Pressurizer TLCO 3.4.201 Refer to PVNGSImproved Technical Specifications 3.4.9.
APPLICABILITY Refer to PVNGSImproved Technical Specifications 3.4.9.
ACTIONS , I 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 PVNGScorrective action program and initiate an operabi I i ty determination, as necessary, to determine the impact on equipment in the technical
, I specifications.
SURVEILLANCE REQUIREMENTS
, I SURVEILLANCE FREQUENCY TSR 3.4.201.1 The emergency power supply for the 18 months on a pressurizer heaters shall be demonstrated STAGGERED TEST OPERABLE by verifying that on an Engineered BASIS 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.
i ,
PALOVERDEUNITS i, 2, 3 T3.4.201-I Rev 59 9/25/13
SafetyInjection T nks TRM3.5.200 SURVEILLANCE REQUIREMENTS I ....
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 PVNGSImproved 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 venti valves may be cycled as necessary to maintain the required nitrogen cove_rpressure in accordance with PVNGSImproved Technical Specifications 3.5,1 and 3.5.2.
Verify that power is removed from the 31 days required nitrDgen 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.
!i TSR 3.5,200.4 Verify that each safety injection tank isolation valve opens automatically under each of the following conditions I. Prior to exceeding an actual or 18 months simulated RCSpressure signal of 515 psia, and
- 2. Upon receipt of a safety injection actuation ISIAS) test signal 18 months on a STAGGERED TEST BASIS (continued)
PALOVERDEUNITS 1, 2, 3 73.5.200-2 Rev 59 9/25/13
MOV ThermalOverloadProtection andBypassDevices TRM3,8.102 SURVEILLANCE REQUIREMENTS J i '
SURVEILLANCE FREQUENCY TSR 3.8,102.1 Perform a CHAiNNEL FUNCTIONAL TEST of the 18 months on a bypass circuitry for those thermal overloads STAGGERED TEST which are normally in force during plant BASIS operation and! bypassed under accident conditions. &ND 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 p!aced in force only when the valve motors are undergoing periodic or Following maintenance testing, maintenance on the valve motor starter AND Fol l owing any periodic testing during which the thermal overload device was temporarily placed in force.
, I, PALOVERDEUNITS i, 2, 3 T3.8.102-2 Rev 59 9/25/13
Fuel Building Essential Ventilation System(FBEVS)
TRM3.9.104 SURVEILLANCE REQUIREMENTS ,
SURVEILLANCE FREQUENCY TSR 3.9.104.1 Operate eachi FBEVStrain for at least 15 31 days minutes.
I TSR 3.9.104.2 Perform requiired Fuel Building Essential In accordance Ventilation !filter testing in accordance with the TRM with the TRMiVentilation Filter Testing VFTP Program (VFT!P) (Reference TRM5.0.500.11).
I TSR3.9.104.3 Verify each FBEVStrain actuates on an 18 months on a actual or siNulated signal and directs it STAGGERED TEST exhaust bank'ithrough the HEPAfilters and BASIS charcoal adsbrber banks.
i TSR3.9,104.4 Verify one FBEVStrain can maintain a 18 months on a measurable n_gative pressure with respect to STAGGERED TEST atmospheric pressure, during operation. BASIS.
PALOVERDEUNITS I, 2, 3 T3.9,104-3 Rev 59 9/25/13
TRMSpecifi cati on Bases TRM6.0.100 TRM SPECIFICATION BASES Pressure Sensor Response Time Testing Requirements," provides the basis and methodology for using allocaited 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 _newcomponent in operation and reverified after maintenance that may adversely affect the sensor response time.
T3.3.101 Radiation Monitoring Instrumentation The OPERABILITYof the radiation monitoring channels ensures that: (i) 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 OPERABILITYof the incore detectors with the specified minimum complement of equipment per TLCO3.3.102.a, b, and c ensures that the measurements }
obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core.
The OPERABILITYof the incore detectors with the specified minimum complement of equipment per TLCO3,3.102.a, b, and d prior to exceeding 30%power after refueling ensures that the assumptions supporting the Inadvertent Loading of a Fuel Assembly analysis are met. The provisions of TLCO3.0.100.3 apply given that the actual detector compliment may, with specific analysis, be shown to be able to detect a misloaded fuel assembly.
As an alternative to a specific analysis, performing CEASymmetry checks for at least one CEAgroup having a CEDMabove the 4x4 array of fuel assemblies for each 4x4 not in compliance with TLCO3.3.102 Condition B is an alternative method of verifying that the assumptions supporting the Inadvertent Loading of a Fuel Assembly are met. This testing is done at Hot Zero Power, xenon free conditions.
The OPERABILITYof the incore detectors with the specified minimum complement of equipment per TLCO3.3.102.a, b, and d after exceeding 30%power after refueling ensures that the assumptions supporting the Inadvertent Loading of a Fuel Assembly analysis are met. There are misloadings that are not detectable at beginning of cycle. These misloadings becomedetectable over time with a slowly changing deviation from predicted power distribution. Therefore, the (continued)
PALOVERDEUNITS 1, 2, 3 T6.0.I00-11 Rev 59 9/25/13
TRMSpecification B_ses TRM6.0,100 TRMSPECIFICATIONBASES I
specified minimum complement of equipment per TLCO3.3.102.a, b, and d requires monitoring during the cycle. The slow rate of change in the power distribution factors into the Completion Time and the applicability of TLCO3.0.100.3. Specific analysis may show that a misloaded fuel assembly is detectable given the actual equipment configuration and core conditions.
T3.3.103 Seismic Monitoring The OPERABILITYof 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 Appendi_xA of 10 CFRPart 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 OPERABILITYof the meteorological instrumentation ensures that sufficient meteorological data are avaiqable 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 "Onsite Meteorological Programs," February 1972. Wind speeds less than 0.6 MPHcannot be measured by the meteorological instrumentation.
Surveillance requirement TSR3,3.104.2 is modified by a NOTEto 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 OPERABILITYof 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,"
(continued)
PALOVERDEUNITS i, 2. 3 T6.0,100-12 Rev 59 9/25/13
TRMSpecificati on Bases TRM6.0.100 TRMSPECIFICATIONBASES T3.3.106 Loose-Part Detection Instrumentation The OPERABILITYof the loose-part detection instrumentation ensures that sufficient capability is available to detect loose metallic parts in the primary system and avoid ormitigate damageto primary system components. The allowable out-of-service times and surveillance requirements are consistent with the recommendations ofRegulatory Guide 1.133, "Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors " May 1981.
%.3.107 Explosive Gas Monitoring System The explosive gas instrumentation is provided for monitoring (and controlling) the concentrations of potentlially explosive gas mixtures in the GASEOUS RADWASTE SYSTEM. The OPERABIILITY 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 FBEVASis 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.
TLCO3.3.108 requires one channel of FBEVASwhich includes the Actuation Logic, Manual Trip, and radiation monitor to be OPERABLE.The cross-train trip function is provided as a defense-in-depth capability and is not required for FBEVASchannel operability.
During movementof irradiated fuel assemblies in the fuel building with the required FBEVASchannel inoperable, an OPERABLE FBEVStrain must be immediately placed in the emergency mode of operation (i.e., fan running, valves/dampers aligned to the post-FBEVAS mode, etc.) or movementof irradiated fuel assemblies must be suspended immediately. The first action ensures that no undetected failures preventing FBEVSsystem 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 movementof fuel to a safe position.
Movementof spent fuel casks containing irradiated fuel assemblies is not within the scope of the Applicability of this technical specification. The (continued)
PALOVERDEUNITS i, 2, 3 T6.0.I00-13 Rev 59 9/25/13
TRMSpecificati on Bases TRM6.0.100 TRMSPECIFICATIONBASES I
movement of dry casks conta%ing irradiated fuel assemblies will be done with a single-failure-proof handliing 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 CPCcabinet high itemperature alarm is received, it is possible for an OPERABLE CPCand CEACto ibe affected and not be completely reliable.
Therefore, a CHANNEL FUNCTIQNAL TESTmust be performed on OPERABLE CPCsand CEACswithin 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The iCompletion 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 probabiliity of undetected failure, the consequences of a single channel failure, and ithe time required to perform a CHANNEL FUNCTIONAL TEST.
T3.4.100 Auxiliary Spray iSystem The auxiliary pressurizer sp!ray is required to depressurize the RCSby cooling the pressurizer steam space ito permit the plant to enter shutdown cooling. The auxiliary pressurizer spray iis required during those periods when normal pressurizer spray is not avaiilable, such as during natural circulation and during the later stages of a_normal RCScooldown. The auxiliary pressurizer spray also distributes boroni to the pressurizer when normal pressurizer spray is not available.
T3.4.101 RCSChemistry The limitations on Reactor Cioolant System chemistry ensure that corrosion of the Reactor Coolant System iis minimized and reduces the potential for Reactor Coolant System leakage or faiilure 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.
(continued)
PALOVERDE UNITS1, 2, 3 T6.0.100-14 Rev 59 9/25/13
IRMSpecification _ases TRM6.0.100 TRMSPECIFICATIONBASES I
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 Heatupi and Cooldown Limits The limitations imposed on the pressurizer heatup and cooldown rates and spray water temperature differentiial are provided to assure that the pressurizer is operated within the design Qriteria assumed for the fatigue analysis performed in accordance with the ASMEICodeRequirements.
T3.4.103 Intentionally Blank T3.4.104 RCSVents (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 OPERABILIITY 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 vesse_l head through solenoid operated valve (SOV) HV-101, then through SOVHV-105 to the RDT.
- 2. From the reactor vesseil head through SOVHV-101, then through SOVHV-106 directly to containmen# atmosphere.
- 3. From the reactor vesseil head through SOVHV-I02, then through SOVHV-105 to the RDT.
- 4. From the reactor vesseil head through SOVHV-102, then through SOVHV-I06 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 consTstent with the requirements of Item II B.1 of NUREG-0737.
continued)
PALOVERDE UNITS1, 2, 3 T6.0.100-15 Rev59 9/25/13
TRMSpecification Bases TRM6.0.100 TRMSPECIFICATIONBASES i
%.4.200 RCSPressure 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 wi_h both forced reactor coolant flow and with natural circulation flow. The minimum water level in the pressurizer assures the pressurizer heaters, whiich 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 maximumwater level in the pressurizer ensures that thiis parameter is maintained within the envelope of operation assumed in the safety analysis. The maximumwater level also ensures that the RCSis not _ahydraulically solid system and that a steam bubble will be provided to alccommodatepressure surges during operation. The steam bubble also protects tihe pressurizer code safety valves against water relief. The requirement to _erify that on an Engineered Safety Features Actuation test signal concur!rent 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 enhanceslthe 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 RCSOperational LEAKAGE (See the ITS 3.4.14 Specification Bases.)
T3.4.204 RCSPIV Leakage (See the ITS 3.4.15 Specification Bases,)
T3.5.200 Safety InjectioniTanks (See the ITS 3.5.1 and 3.5.2 Specification Bases.)
T3.5,201 Shutdown Cooling System The OPERABILITYof 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.
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TRMSpecification Bases TRM6,0.100 TRMSPECIFICATIONBASES i
The shutdown cooling subsystem operation is described in UFSAR5.4.7. Many of the components comprising the shutdown cooling system have specific requirements during Modes 143 in the Technical Specifications (e.g., emergency core cooling, containment spray, and containment isolation). However, several components do not have speci!fic 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 OPERABILITYand/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 regarding the shutdown coolilng system is in UFSARSection 9.3.4. Since the subsystem is manually initiated, temporary changes in the position of shutdown cooling system valves from _heir 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 oppiortunity to effect repairs while providing acceptable limits for the dulration of intervals where the system may not be OPERABLE. In combination width the maintenance rule requirements in 10 CFR 50.65, the allowed outage times help ensure that the shutdown cooling subsystems will be functionail when required.
If the subsystem cannot be restored or functionality verified within the stated time frame, the associated ACTIONplaces the unit in Mode Q where the steam generators are still available for heat removal and the stored energy of the NSSSis much less than i_t 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 continued)
PALOVERDEUNITS I, 2, 3 T6.0,I00-17 Rev 59 9/25/13
TRMSpecification Bases TRM6.0.100 TRMSPECIFICATIONBASES 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 ACTIONagain places the unit in Mode 4 where the steam generators; are available for heat removal and the stored energy in the NSSSis minimi!zed. 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 thiat 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.
The SDCsystems 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 PVNGSprocedures. 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 preventTng 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 SDCpiping and the adequacy of the procedural controls governing system operation.
References;
- 1. UFSARSections 5.4.7 and 9.3.4
- 2. Combustion Englneering Owners Group Joint Applications Report for Low Pressure Safety Injection System AOTExtension, CE NPSD-995, dated May 1995, as submitted to NRCin APS letter no. 102-03392, dated June 13, 1995, with updates described in letter no. 102-04250 dated February 26, 1999. Also see TS amendmentno. 124 dated February I,, 2000.
(continued)
PALOVERDEUNITS 1, 2, 3 T6.0.100-18 Rev 59 9/25/13