ML13120A504
| ML13120A504 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 04/10/2013 |
| From: | Arizona Public Service Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Z05778, 102-06689-TNW/RKR/CJS | |
| Download: ML13120A504 (16) | |
Text
PVNGS Technical Requirements Manual (TRM)
Revision 57 ReplacementPagesand InsertionInstructions The following LDCRs are included in this change:
LDCR 10-R012 removes Unit 3 Post-Accident Sampling System (PASS) containment isolation valve (ClV) RDB UV-407 from the TRM Component List T7.0.300, Containment Isolation Valves. License Amendment 136 authorized abandonment of PASS, however, a number of the PASS valves remain physically connected. DMWO 2778159 removed the Unit 3 valve during the past Unit 3 outage.
LDCR 12-R001 removes overpressure protection valves AFB PSV-0106 and 0107 from ClVs AFB UV-034 and 35 from TRM Component List T7.0.300, Containment Isolation Valves. The valves were replaced by a pressure equalizing line from the valve bonnets to the process piping under DMWO 3588553.
LDCR 12-R005 updates the applicable industry standard edition date for Unit 1 (ASTM E185-79) and Units 2 and 3 (ASTM E185-82) in TRM Appendix TA, Reactor Coolant System Pressure and Temperature Limits Report (PTLR), Section TA6.2, Evaluation of Surveillance Data Credibility.
LDCR 12-R006 corrects the description of the responsible organizations for the Inservice Inspection (ISI) and Inservice Testing (IST) programs in TRM Section 5.0.500.8, Inservice Inspection and Testing Programs.
LDCR 12-R008 deletes the High Pressure Safety Injection (HPSI), Low Pressure Safety Injection (LPSI) and Containment Spray pump miniflow differential pressure test requirements from the TRM (Sections 5.0.500.8.e, 5.0.500.8.f and 5.0.500.8.g). The TRM requirements were redundant to Inservice Testing requirements defined in Technical Specification 5.5.8.
Instructions RemovePa.qe:
InsertNew Pa.qe:
Cover Page Cover Page List of Effective Pages, List of Effective Pages, Pages 1, 2, 3 and 4 Pages 1, 2, 3 and 4 T5.0.500-11 T5.0.500-11 through through T5.0.500-18 T5.0.500-17 T7.0.300-1 T7.0.300-1 T7.0.300-3 T7.0.300-3 TRM Appendix TA TA-12 TA-12 Stephenson, Carl J(Z05778)
Digitally signed by Stephenson, Carl J(Z05778)
DN: cn=Stephenson, Carl J(Z05778)
Reason: I attest to the accuracy and integrity of this document Date: 2013.04.05 11:27:45 -07'00'
TechnicalRequirements Manual Revision 57 April 10, 2013 3tpn"'-e-'-enson J,Z0S,,,,DigitallysignedbySteph Carl I
DN:cn=Stephenson,CarlJ(Z05778)
I_ason: Iattestto the accuracyand CarlJ(ZO5778),o,_o,,,,,o t
Date: 2013.04.05 11:11:41-07'00' PALOVERDEUNITS1, 2, 3
TechnicalRequirements Manual LIST OF EFFECTIVEPAGES Page No.
Revision No.
Page No.
Revision No.
TOCpage i 33 T3.3.103-1 51 TOCpage ii 48 T3.3.103-2 54 TOCpage iii 33 T3.3.103-3 13 TOCpage iv 52 T3.3.103-4 13 TI.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 56 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-I 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 55 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 PALOVERDEUNITS 1, 2, 3 1
Rev 57 04/10/13
Technical RequirementsManual LIST OF EFFECTIVEPAGES Page No.
Revision No.
Page No.
Revision No.
T3.5.203-2 35 T3.9.200-2 29 T3.6.100-I 48 T3.9.201-I 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-I 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-I 46 T3 8 101-I 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.I00-1 0
T3.9.200-1 46 T5.0,200-1 0
PALOVERDEUNITS 1, 2, 3 2
Rev 57 04/10/13
Technical RequirementsManual LIST OF EFFECTIVEPAGES Page No.
Revision No.
Page No.
Revision No.
T5.0.300-1 0
T6.0.100-22 53 T5.0.400-1 0
T6.0.100-23 53 T5.0.500-I 53 T6.0.I00-24 53 T5.0.500-2 24 T6.0.100-25 53 T5.0.500-3 0
T6.0.100-26 53 T5.0.500-4 53 T6.0.100-27 53 T5.0.500-5 0
T6.0.100-28 53 T5.0.500-6 0
T6.0.100-29 53 T5.0.500-7 0
T6.0.100-30 53 T5.0.500-8 22 T6.0.100-31 53 T5.0.500-9 0
T6.0.100-32 53 T5.0.500-10 0
T6.0.100-33 53 T5.0.500-11 57 T6.0.100-34 53 T5.0.500-12 57 T6.0 100-35 53 T5.0.500-13 57 T6.0 100-36 53 T5.0.500-14 57 T6.0 100-37 53 T5.0.500-15 57 T7 0 100-1 52 T5.0.500-16 57 T7 0 100-2 52 T5.0.500-17 57 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 57 T6 0 100-2 40 T7 0 300-2 41 T6 0 100-3 40 T7 0 300-3 57 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.I00-18 53 TA-I 52 T6.0.100-19 53 TA-2 52 T6.0.I00-20 53 TA-3 52 T6.0.100-21 53 TA-4 52 PALOVERDEUNITS1, 2, 3 3
Rev 57 04/10/13
Technical RequirementsManual LIST OF EFFECTIVEPAGES Page No.
Revision No.
Page No.
Revision No.
TA-5 52 TA-6 52 TA-7 52 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 PALOVERDEUNITS 1, 2, 3
4 Rev 57 04/10/13
Programs and Manuals TRM5.0,500 5.0.500 Programs and Manuals (continued) 5.0.500.7 Reactor Coolant PumpFlywheel Inspection Program The purpose of the Reactor Coolant PumpFlywheel Inspection Program is to provide for the inspection of each reactor coolant pumpflywheel.
The PVNGSProgram 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 (ISl) and Inservice Testing (IST) Programs is to provide controls for ASMEinspection and testing of ASMECode Class 1, 2 and 3 components.
The PVNGS Engineering Programs group is the program owner for ISl and the j
PVNGSComponentPrograms group is the program owner for IST.
I 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 ASMEBoiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR50, Section 50.55a(g).
b.
Inservice Testing shall be performed in accordance with the ASMECode for Operation and Maintenance of Nuclear Power Plants (ASMEOMCode) and applicable Addenda as required by 10 CFR50.55a(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 ASMEBoiler and Pressure Vessel Code and applicable Addenda shall be applicable as specified in PVNGSITS 5.5.8.a for ITS and TRMrequirements.
- 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 ASMEOMCode and applicable Addenda for the inservice testing activities required by the ASMEOMCode and applicable Addenda shall be as specified in PVNGSITS 5.5.8a for ITS and TRMrequirements.
(continued)
PALOVERDEUNITS 1, 2, 3 T5.0.500-11 Rev 57 4/10/13
ProgramsandManuals TRM5.0.500 5.0.500 Programs and Manuals (continued) 5.0.500.9 SteamGenerator (SG) Tube Surveillance Program I
The purpose of the Steam Generator Tube Surveillance Programis to provide controls for the Inservice Inspection of steam generator tubes to ensure that structural integrity of this portion of the RCSis maintained.
The PVNGSSystem Engineering Group is the program owner.
The program requirements are specified in ITS 5.5.9.
5.0.500.10 SecondaryWater Chemistry Program The purpose of the SecondaryWater Chemistry Programis to provide controls for monitoring secondarywater chemistry to inhibit SG tube degradation and low pressure turbine disc stress corrosion cracking.
The PVNGSChemistry group is the programowner.
Programrequirements are specified in PVNGSTS 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 TRMfilter ventilation
- systems, The PVNGSElectrical Maintenance (HVAC) group is the program owner.
Program requirements for the Control RoomEssential Filtration System (CREFS)and ESFPumpRoomExhaust Air Cleanup System (ESF PREACS)are specified in PVNGSTS 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. Whentesting pursuant to PVNGSTS SR 3.7.11,2, TS SR 3.7.13.2, TSR3.6.100.2 and TSR 3.9.104.2, the CREFS,PREACS,HPCSand FBEVSshall be demonstrated OPERABLEat least once per 18 months or:
(continued)
PALOVERDEUNITS1, 2, 3 T5.0.500-12 Rev57 4/10/13
Programs and Manuals TRM5.0.500 5.0.500 Programs and Manuals (continued)
(a) after any maintenance affecting the airflow distribution or integrity of the HEPAor charcoal adsorberfilter 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. Whentesting the CREFS,PREACS,HPCSand FBEVSpursuant to PVNGSTS SR 3.7.11.2, TS SR 3.7.13.2, TSR3.6.100.2 and TSR3.9.104.2, 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 NRCGeneric 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 CREFSand PREACSpursuant to PVNGSTS 5.5.11.c, the HPCSpursuant to PVNGSTRMTSR3.6.100.2, and the FBEVS pursuant to TRMTSR3.9.104.2, 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 ASTMD3803-1989, at a temperature of 30°C and relative humidity specified as follows:
Penetration RH CREFS
<2.5%
70%
ESFPREACS/FBEVS <2.5%
70%
<2.5%
70%
- 4. After each complete or partial replacement of a HEPAfilter bank for the HPCSand FBEVSby verifying that the HEPAfilter banks remove greater than or equal to 99.0% of the DOPwhen they are tested in-place in accordance with ANSl N510-1980.
The system flowrates for the HPCSand FBEVSare as specified below +/-
10%:
HPCS 50 CFM FBEVS 6000 CFM (continued)
PALOVERDEUNITS 1, 2, 3 T5.0.500-13 Rev 57 4/10/13
ProgramsandManuals TRM5.0.500 5.0.500 Programs and Manuals (continued)
- 5. After each complete or partial replacement of a charcoal adsorber bank for the HPCSand FBEVSby 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 ANSl N510-1980. The system flowrates for the HPCSand FBEVSare as specified below +/-
10%:
For the HPCSand FBEVS,demonstrate at least once per 18 months that the pressure drop across the combined HEPAfilters, the prefilters, and the charcoal adsorbers is as specified below when tested in accordance with Regulatory Guide 1.52, Revision 2 and ANSl 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 ANSl N510-1980:
Ventilation System Wattage HPCS 0.5 kW
- 8. The provisions of TLCO3.0.100.3 and TSR3.0.100.3 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 GasandStorageTankRadioactivity MonitoringProgram The purpose of the Explosive Gasand Storage Tank Radioactivity Monitoring Programis to provide control for potentially explosive gas mixtures contained in the WasteGas Holdup System, and for the quantity of radioactivity contained in gas storage tanks and unprotected outdoor liquid storage tanks. The PVNGSChemistry group is the programowner.
(continued)
PALOVERDEUNITS 1, 2, 3 T5.0.500-14 Rev 57 4/10/13
Programsand Manuals TRM5.0,500 5.0.500 Programsand Manuals(continued)
The program requirements are specified in ITS 5.5.12.
Refer to TRMspecifications 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 Programis to ensure the acceptability of fuel oil prior to addition to storage tanks.
The PVNGSChemistry group is the programowner.
The programrequirements are specified in ITS 5.5.13.
5.0.500.14 Technical Specifications (TS) BasesControl Program The purpose of the Technical Specifications BasesControl Program is to provide a meansfor processing changesto the Basesof the PVNGSITS.
Nuclear Regulatory Affairs is the programowner, Programrequirements are specified in ITS 5.5.14.
5.0.500.15 Safety Function Determination Program(SFDP)
The purpose of the Safety function Determination Programis to ensure that a loss of safety function is detected and appropriate actions taken, The PVNGSOperations group is the programowner.
Programrequirements are specified in ITS 5.5.15.
5.0.500.16 ContainmentLeakageRate Testing Program The purpose of the ContainmentLeakageRate Testing Programis to implementthe required containment leakage rate testing.
The PVNGSProgramEngineering group is the programowner, In addition to the programrequirements specified in ITS 5.5.16, the following also applies:
- a. DemonstrateCONTAINMENT INTEGRITYafter each closing of each penetration subject to Type B testing, except containment air locks, if openedfollowing a Type A or B test, by leak rate testing in accordancewith ITS 5.5.16.
(continued)
PALOVERDEUNITS1, 2, 3 T5.0.500-15 Rev57 4/10/13
Programsand Manuals TRM5.0.500 5.0.500 Programsand Manuals(continued)
- 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 0.01La when pressurized to Pa.
C. The provisions of TLCO3.0.100.3 and TSR3.0.100.3 are applicable to the requirements of T5.0,500.16 a and b, 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 madeto 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 CFRParts 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 PCPare contained in the PVNGSQA 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 ManagementProgram(CRMP)provides a proceduralized risk-informed assessmentto managethe risk associated with equipment inoperability.
The programapplies to technical specification structures, systems, and componentsfor (continued)
PALOVERDEUNITS1, 2, 3 T5.0.500-16 Rev57 4/10/13
ProgramsandManuals TRM5.0.500 5.0,500 Programs and Manuals (continued) 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 I 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.
c.
Provisions for performing an assessment after entering the plant configuration described by the LCOAction Statement for unplanned entry into the LCOAction 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 LCOAction Statement.
e.
Provisions for considering other applicable risk-significant contributors such as Level 2 issues and external
- events, qualitatively or quantitatively.
(continued)
PALOVERDEUNITS1, 2, 3 T5.0.500-17 Rev57 4/10/13
Containment Isolation Valves TRM7.0.300 T7.0 COMPONENT LISTS T7.0.300 CONTAINMENT ISOLATIONVALVES 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.
VALVENO ITS 3.6.3 PENETRATI VALVESRECEIVINGCONTAINMENT ISOLATION Condition ON (CIAS)
RDA-UV023 A
9 Containment radwaste sump pumpto LRS holdup tank RDB-UV024 A
9 Containment radwaste sump pump to LRS holdup tank RDB-UV407 A
9 Containment radwaste sump post-accident sampling (Unit 1 only) system II SGB-HV200ca_
A 11 Downcomerfeedwater chemical injection SGB-HV201_a)
A 12 Downcomerfeedwater chemical injection SIA-UV 708_a)
A 23 Containment recirc sump to post-accident sampling system HCB-UV044 A
25A Containment air radioactivity monitor (inlet)
HCA-UV045 A
25A Containment air radioactivity monitor (inlet)
HCA-UV046 A
25B Containment air radioactivity monitor (outlet)
HCB-UV047 A
25B Containment air radioactivity monitor (outlet)
GAA-UV002 A
29 Nitrogen to steam generator and reactor drain tank GAA-UV001 A
30 Nitrogen to SI tanks HPA-UV001 A
35 Containment to hydrogen recombiner HPA-UV003 A
35 Containment to hydrogen recombiner HPA-UV024 A
35 Hydrogen control system HPB-UV002 A
36 Containment to hydrogen recombiner HPA-UV005 A
38 Containment to hydrogen recombiner HPB-UV004 A
36 Hydrogen recombiner return to containment (inlet)
HPA-UV023 A
38 Hydrogen control system HPB-UV006 A
39 Hydrogen recombiner return to containment (inlet)
CHA-UV516 A
40 Letdown line from RCloop 2B to regenerative heat exchanger and letdown heat exchanger CHB-UV523 A
40 Letdown line from RCloop 2B to regenerative heat exchanger and letdown heat exchanger CHB-UV924 A
40 Letdown line to post-accident sampling system SSB-UV201 A
42A Pressurizer liquid sample line (continued) a.
Not Type C Tested PALOVERDEUNITS 1, 2, 3 T7.0.300-1 Rev 57 4/10/13
ContainmentIsolation Valves TRM7.0,300 T7.0 COMPONENT LISTS ITS 3.6.3 VALVES RECEIVING VALVE NO PENETRATION Condition CONTAINMENTSPRAY (CSAS)
IAA-UV-O02 A
31 Service air to reactor containment inst.
air NCB-UV-401 A
33 NCwater to RCPmotor bearing lube oil and air coolers NCB-UV-403 A
34 NCwater to RCPmotor bearing lube oil and air coolers NCA-UV-402 A
34 NCwater to RCPmotor bearing lube oil andair coolers CHB-UV-505 A
43 RCpumpseal bleedoff CHA-UV-506 A
43 RCpumpseal bleedoff VALVE NO ITS 3.6.3 PENETRATION CONTAINMENTISOLATION Condi ti on SAFETY/RELIEF VALVES I
AFA-PSV-0108
_a_c_
A 75 Overpressureprotection for ClV AFC-UV-036 I
AFA-PSV-0109 calcb_
A 76 Overpressureprotection for CIV AFA-UV-037 NCE-PSV-0617 (c_
A 34 Overpressureprotection for penetration 34 SIA-PSV151ca_
A 23 Containmentreci rcul ation sumpto containment spray, LPSI and HPSlheaders 1A & 1B SIB-PSV140cal A
24 Containmentrecirculation sumpto containment spray, LPSl and HPSIheaders 2A & 2B SIB-PSV189ca_
A 26 Fromshutdowncooling RCLoop2 (Also covered by ITS 3.4.13)
SIA-PSV179Ca_
A 27 Fromshutdowncooling RCLoop i (Also covered by ITS 3,4.13)
SIE-PSV474 A
28 Safety injection drain relief a.
Not Type C Tested b.
Valve installation per DMWO00741855 c.
Valve installation per DMWO00830780 PALOVERDEUNITS 1, 2, 3 T7.0.300-3 Rev 57 4/10/13
TRMAppendixTA PTLR Evaluation of Charpy energy versus temperature for the unirradiated and irradiated condition is presented in References6, 7, and 8.
Basedon engineering judgment, the scatter in the data presented is small enoughto permit the unambiguousdetermination of the 30 ft-lb temperature and the upper shelf energy of the PVNGSUnits 1, 2, and 3 surveillance materials.
Thus, the PVNGSsurveillance programmeets this criterion.
Criterion 3:
Whenthere are two or moresets of surveillance data from one
- reactor, the scatter of _RTN_Tvalues about a best-fit line drawn as described in Regulatory Position 2.1 normallyshould 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 exceedtwice those values.
Even if the data fail this criterion for use in shift calculations, they maybe credible for determining decrease in upper shelf energy if the upper shelf can be clearly determined, following the definition given in ASTME185-82.
The surveillance programfor PVNGSis basedon ASTME185-79for Unit 1 and I
ASTME185-82for Unit 2 & 3 which presents criteria for monitoring changesin I
the fracture toughness properties of reactor vessel beltline materials.
References6, 7, and 8 describe the post-irradiation evaluations of PVNGS surveillance materials.
The credibility results shownin Tables TA6-2, TA6-3 and TA6-4 for Units 1, 2, and 3, respectively, present the shift measurementsavailable to date.
Those values are comparedto predictions based on a chemistry factor determined following Position 1.1 of Regulatory Guide 1.99.
In all cases, the difference betweenthe measuredand predicted shift is less than 17°F for the surveillance plates and less than 28°F for the surveillance welds.
Therefore, this criterion is met for the PVNGSUnits 1, 2, and 3 surveillance program plate andweld materials.
(continued)
Palo Verde Units 1, 2, 3 TA-12 Rev57 4/10/13