ML13217A054: Difference between revisions

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{{#Wiki_filter:PVNGSTechnical Specification Bases(TSBases)Revision58Replacement PagesandInsertion Instructions Thefollowing LDCRsareincludedinthischange:LDCR11-B002reflectschangesapprovedbyNRCLicenseAmendment 191,datedApril11,2013,relatedtoTSBasesSection3.7.4,Atmospheric DumpValves(ADVs),thatrequiresfourADVlinesbeOPERABLEwheninModes1,2,3,andinMode4whenthesteamgenerators arebeingusedforheatremoval.RelatedLDCR07-R002removessimilarrequirements forADVoperability thathadbeenincludedintheTechnical Requirements Manual(TRM)asaninterimaction,untilthelicenseamendment wasapproved.
{{#Wiki_filter:PVNGS Technical Specification Bases (TS Bases)Revision 58 Replacement Pages and Insertion Instructions The following LDC R s are included in this change: LDCR 11-B002 reflects changes approved by NRC License Amendment 191, dated April 11, 2013, related to TS Bases Section 3.7.4, Atmospheric Dump Valves (ADVs), that requires four ADV lines be OPERABLE when in Modes 1,2, 3, and in Mode 4 when the steam generators are being used for heat removal.Related LDCR 07-R002 removes similar requirements for ADV operability that had been included in the Technical Requirements Manual (TRM)as an interim action, until the license amendment was approved.LDCR 12-B006 clarified TS Bases Sections 3.4.8, RCS Loops-MODE 5, Loops Not Fill e d , and 3.9.5, SDC and Coolant Circulation
LDCR12-B006clarified TSBasesSections3.4.8,RCSLoops-MODE5,LoopsNotFilled,and3.9.5,SDCandCoolantCirculation
-Low Water L e vel , to indicate that Containment Spray (CS)pumps are not to be used for normal operations if the water level is at or below the top of the hot-leg pipe (103'-1")due to concerns of potential air entrainment and gas binding of the CS pump.The LDCR also updated the Reference section of the Bases for each specification.
-LowWaterLevel,toindicatethatContainment Spray(CS)pumpsarenottobeusedfornormaloperations ifthewaterlevelisatorbelowthetopofthehot-legpipe(103'-1")duetoconcernsofpotential airentrainment andgasbindingoftheCSpump.TheLDCRalsoupdatedtheReference sectionoftheBasesforeachspecification.
Instructions Remove Paqe: Insert New Paqe: Cover Page Cover Page List of Effective Pages List of Effective Pages 1/2 through 7/8 1/2 through 9/Blank B 3.4.8-1 B 3.4.8-2 B 3.4.8-1/B 3.4.8-2 B 3.4.8-3 Blank B 3.4.8-3/B 3.4.8-4 B 3.7.4-1 B 3.7.4-2 B 3.7.4-1/B 3.7.4-2 through through B 3.7.4-5 Blank B 3.7.4-5/B 3.7.4-6 B 3.9.5-1 B 3.9.5-2 B 3.9.5-1/B 3.9.5-2 B 3.9.5-3 B 3.9.5-4 B 3.9.5-3/B 3.9.5-4 PVNGS Palo Verde Nuclear Generating Station Units 1, 2, and 3 Technical Sp"" ec l ficatlon Bases Revision 58 July 03, 2 0 13-_-_.-¢'e_'_'enson o,g,t0,,.s,goe0byS,o..
Instructions RemovePaqe:InsertNewPaqe:CoverPageCoverPageListofEffective PagesListofEffective Pages1/2through7/81/2through9/BlankB3.4.8-1B3.4.8-2B3.4.8-1/B3.4.8-2B3.4.8-3BlankB3.4.8-3/B3.4.8-4B3.7.4-1B3.7.4-2B3.7.4-1/B3.7.4-2throughthroughB3.7.4-5BlankB3.7.4-5/B3.7.4-6B3.9.5-1B3.9.5-2B3.9.5-1/B3.9.5-2B3.9.5-3B3.9.5-4B3.9.5-3/B3.9.5-4 PVNGSPaloVerdeNuclearGenerating StationUnits1,2,and3Technical Sp""eclficatlonBasesRevision58July03,2013-_-_.-¢'e_'_'enson o,g,t0,,.s,goe0byS,o..
......Cor,_,zo_,, I DN: cn=Stephenson, Carl J(ZO5778)Reason: I attest to the accuracy and integrity of Carl J(Z05778)th,,_.......Date: 20!3.06.28 09:16:1 7-0 7'00' TECHNICAL SPECIFICATION BASES LIST OF EFFECTIVE PAGES Page Rev.Page Rev No.No.No.No.B 2 1 i-i 0 B 3 1 3-2 0 B 2 1 i-2 0 B 3 1 3-3 0 B 2 1 i-3 37 B 3 1 3-4 0 B 2 1 i-4 21 B 3 1 3-5 0 B 2 1 i-5 54 B 3 1 3-6 56 B 2 1 2-I 0 B 3 1 4-i 0 B 2 1 2-2 31 B 3 1 4-2 31 B 2 1 2-3 0 B 3 1 4-3 0 B 2 1 2-4 54 B 3 1 4-4 0 B 3 0-i 49 B 3 1 4-5 0 B 3 0-2 0 B 3 1 5-i 0 B 3 0-3 0 B 3 1 5-2 52 B 3 0-4 0 B 3 1 5-3 52 B 3 0-5 42 B 3 1 5-4 52 B 3 0-6 48 B 3 1 5-5 52 B 3 0-7 48 B 3 1 5-6 52 B 3 0-8 42 B 3 1 5-7 52 B 3 0-9 42 B 3 1 5-8 52 B 3 0-i0 42 B 3 1 5-9 52 B 3 0-ii 42 B 3 1 5-10 56 B 3 0-12 42 B 3 1 5-11 56 B 3 0-13 42 B 3 1 5-12 56 B 3 0-14 49 B 3 1 6-i 0 B 3 0-15 50 B 3 1 6-2 46 B 3 0-16 50 B 3 1 6-3 42 B 3 0-17 50 B 3 1 6-4 42 B 3 0-18 49 B 3 1 6-5 56 B 3 0-19 49 B 3 1 6-6 46 B 3 0-20 49 B 3 1 7-i 57 B 3 0-21 49 B 3 1 7-2 0 B 3 0-22 49 B 3 1 7-3 53 B 3 1 i-I 28 B 3 1 7-4 48 B 3 1 i-2 0 B 3 1 7-5 25 B 3 1 i-3 43 B 3 1 7-6 0 B 3 1 i-4 43 B 3 1 7-7 0 B 3 1 I-5 27 B 3 1 7-8 56 B 3 1 i-6 56 B 3 1 7-9 56 B 3 1 2-I 28 B 3 1 8-i 52 B 3 1 2-2 0 B 3 1 8-2 52 B 3 1 2-3 43 B 3 1 8-3 52 B 3 1 2-4 28 B 3 1 8-4 52 B 3 1 2-5 0 B 3 1 8-5 56 B 3 1 2-6 43 B 3 1 9-i 0 B 3 1 2-7 12 B 3 1 9-2 0 B 3 1 2-8 47 B 3 1 9-3 0 B 3 1 2-9 56 B 3 1 9-4 0 B 3 1 3-I 0 B 3 1 9-5 56 PALO VERDE UNITS i, 2, AND 3 1 Revision 58 July 03, 2013 TECHNICAL SPECIFICATION BASES LIST OF EFFECTIVE PAGES Page Rev.Page Rev No.No.No.No.B 3 1 9-6 56 B 3.2 5-i 52 B 3 1 i0-i 0 B 3.2 5-2 i0 B 3 i i0-2 53 B 3.2 5-3 0 B 3 1 i0-3 0 B 3.2 5-4 52 B 3 1 i0-4 37 B 3.2 5-5 0 B 3 1 i0-5 56 B 3.2 5-6 56 B 3 1 i0-6 0 B 3.2 5-7 0 B 3 1 ii-i 0 B 3.3.1-i 35 B 3 1 ii-2 53 B 3.3.1-2 53 B 3 1 Ii-3 0 B 3 3.1-3 53 B 3 1 ii-4 53 B 3 3.1-4 53 B 3 1 ii-5 0 B 3 3 i-5 53 B 3 2 i-i 53 B 3 3 i-6 53 B 3 2 i-2 i0 B 3 3 i-7 53 B 3 2 i-3 53 B 3 3 i-8 53 B 3 2 i-4 0 B 3 3 i-9 53 B 3 2 i-5 0 B 3 3 i-i0 53 B 3 2 I-6 0 B 3 3 i-ii 53 B 3 2 i-7 56 B 3 3 1-12 53 B 3 2 i-8 56 B 3 3 1-13 53 B 3 2 2-i 52 B 3 3 1-14 53 B 3 2 2-2 i0 B 3 3 1-15 53 B 3 2 2-3 0 B 3 3 1-16 53 B 3 2.2-4 52 B 3 3 1-17 53 B 3 2.2-5 1 B 3 3 1-18 53 B 3 2.2-6 0 B 3 3 1-19 53 B 3 2.2-7 56 B 3 3 1-20 53 B 3 2.3-i 52 B 3 3 1-21 53 B 3 2.3-2 i0 B 3 3 1-22 53 B 3 2 3-3 0 B 3 3 1-23 53 B 3 2 3-4 52 B 3 3 1-24 53 B 3 2 3-5 0 B 3 3 1-25 53 B 3 2 3-6 0 B 3 3 1-26 53 B 3 2 3-7 0 B 3 3 1-27 53 B 3.2 3-8 56 B 3 3 1-28 53 B 3.2 3-9 56 B 3 3 1-29 53 B 3.2 3-i0 0 B 3 3 1-30 53 B 3.2 4-i 52 B 3 3 1-31 53 B 3.2 4-2 i0 B 3 3 1-32 53 B 3 2 4-3 0 B 3 3 1-33 53 B 3 2 4-4 52 B 3 3 1-34 53 B 3 2 4-5 53 B 3.3 1-35 53 B 3 2 4-6 53 B 3.3 1-36 53 B 3 2 4-7 53 B 3.3 1-37 53 B 3 2 4-8 56 B 3.3 1-38 53 B 3 2 4-9 56 B 3.3 1-39 53 B 3 2 4-I0 31 B 3.3 1-40 56 PALO VERDE UNITS i, 2, AND 3 2 Revision 58 July 03, 2013 TECHNICAL SPECIFICATION BASES LIST OF EFFECTIVE PAGES Page Rev.Page Rev No.No.No.No.B 3 3 1-41 56 B 3 3 4-7 0 B 3 3 1-42 56 B 3 3 4-8 0 B 3 3 1-43 56 B 3 3 4-9 0 B 3 3 1-44 56 B 3 3 4-I0 0 B 3 3 1-45 53 B 3 3 4-Ii 0 B 3 3 1-46 56 B 3 3 4-12 0 B 3 3]-47 57 B 3 3 4-13 56 B 3 3]-48 56 B 3 3 4-14 56 B 3 3 1-49 56 B 3 3 4-15 56 B 3 3 1-50 53 B 3 3 5-I 0 B 3 3 1-51 53 B 3 3 5-2 0 B 3 3 2-i 50 B 3 3 5-3 0 B 3 3 2-2 0 B 3 3 5-4 35 B 3 3 2-3 1 B 3 3 5-5 0 B 3 3 2-4 35 B 3 3 5-6 0 B 3 3 2-5 35 B 3 3 5-7 0 B 3 3 2-6 51 B 3 3 5-8 31 B 3 3 2-7 35 B 3 3 5-9 54 B 3 3 2-8 35 B 3 3 5-I0 54 B 3 3 2-9 50 B 3 3 5-ii 54 B 3 3 2-i0 38 B 3 3 5-12 1 B 3 3 2-ii 42 B 3 3 5-13 0 B 3 3 2-12 42 B 3 3 5-14 0 B 3 3 2-13 56 B 3 3 5-15 35 B 3 3 2-14 56 B 3 3 5-16 51 B 3 3 2-15 56 B 3 3 5-17 35 B 3 3 2-16 56 B 3 3 5-18 54 B 3 3 2-17 56 B 3 3 5-19 54 B 3 3 2-18 35 B 3 3 5-20 54 B 3 3 3-i 53 B 3 3 5-21 35 B 3 3 3-2 53 B 3 3 5-22 35 B 3 3 3-3 53 B 3 3 5-23 52 B 3 3 3-4 53 B 3 3 5-24 38 B 3 3 3-5 53 B 3 3 5-25 42 B 3 3 3-6 53 B 3 3 5-26 56 B 3 3 3-7 53 B 3 3 5-27 56 B 3 3 3-8 53 B 3 3 5-28 56 B 3 3 3-9 53 B 3 3 5-29 56 B 3 3 3-i0 56 B 3 3 5-30 35 B 3 3 3-Ii 56 B 3 3 6-I 0 B 3 3 3-12 56 B 3 3 6-2 0 B 3 3 4-i 0 B 3 3 6-3 0 B 3 3 4-2 0 B 3 3 6-4 0 B 3 3 4-3 0 B 3 3 6-5 31 B 3 3 4-4 0 B 3 3 6-6 0 B 3 3 4-5 0 B 3 3 6-7 27 B 3 3 4-6 31 B 3 3 6-8 27 PALO VERDE UNITS i, 2, AND 3 3 Revision 58 July 03, 2013 TECHNICAL SPECIFICATION BASES LIST OF EFFECTIVE PAGES Page Rev.Page Rev No.No.No.No.B 3.3.6-9 0 B 3 3 I0-i0 57 B 3.3.6-10 0 B 3 3 i0-ii 50 B 3.3.6-11 0 B 3 3 10-12 50 B 3.3.6-12 0 B 3 3 10-13 50 B 3.3.6-13 0 B 3 3 10-14 50 B 3.3.6-14 0 B 3 3 10-15 50 B 3 3.6-15 0 B 3 3 10-16 50 B 3 3.6-16 0 B 3 3 10-17 50 B 3 3 6-17 27 B 3 3 10-18 50 B 3 3 6-18 0 B 3.3 10-19 56 B 3 3 6-19 56 B 3.3.10-20 56 B 3 3 6-20 0 B 3.3.10-21 50 B 3 3 6-21 56 B 3.3.10-22 32 B 3 3 6-22 46 B 3 3.11-I 0 B 3 3 7-i 2 B 3 3 ii-2 2 B 3 3 7-2 2 B 3 3 ii-3 2 B 3 3 7-3 0 B 3 3 ii-4 42 B 3 3 7-4 0 B 3 3 ii-5 42 B 3 3 7-5 0 B 3 3 Ii-6 56 B 3 3 7-6 42 B 3 3 ii-7 56 B 3 3 7-7 0 B 3 3 12-i 15 B 3 3.7-8 56 B 3 3 12-2 50 B 3 3.7-9 56 B 3 3 12-3 37 B 3 3 8-i 0 B 3 3 12-4 37 B 3 3 8-2 44 B 3 3 12-5 56 B 3 3 8-3 0 B 3 3 12-6 56 B 3.3 8-4 0 B 3 4 i-i i0 B 3.3 8-5 0 B 3 4 i-2 53 B 3.3 8-6 56 B 3 4 i-3 0 B 3 3 8-7 56 B 3 4 i-4 0 B 3 3 8-8 56 B 3 4 i-5 56 B 3 3 9-i 48 B 3.4.2-I 7 B 3 3 9-2 48 B 3.4.2-2 57 B 3 3 9-3 55 B 3.4 3-i 52 B 3 3 9-4 55 B 3.4 3-2 52 B 3 3 9-5 56 B 3.4 3-3 0 B 3 3 9-6 56 B 3.4 3-4 52 B 3 3 9-7 56 B 3 4 3-5 52 B 3 3 i0-i 0 B 3 4 3-6 0 B 3 3 i0-2 0 B 3 4 3-7 56 B 3.3.10-3 0 B 3 4 3-8 52 B 3.3.10-4 0 B 3 4 4-i 0 B 3.3.10-5 18 B 3 4 4-2 50 B 3.3.10-6 0 B 3 4 4-3 7 B 3.3.10-7 0 B 3 4 4-4 56 B 3.3.10-8 14 B 3.4 5-i 0 B 3.3.10-9 14 B 3.4 5-2 38 PA L O VERDE UNITS i, 2, AND 3 4 Revision 58 July 03, 2013 TECHNICAL SPECIFICATION BASES LIST OF EFFECTIVE PAGES Page Rev.Page Rev No.No.No.No.B 3 4 5-3 38 B 3 4 13-8 52 B 3 4 5-4 56 B 3 4 13-9 56 B 3 4 5-5 56 B 3 4 13-I0 56 B 3 4 6-i 0 B 3 4 13-ii 55 B 3 4 6-2 6 B 3 4 14-i 0 B 3 4 6-3 52 B 3 4 14-2 34 B 3 4 6-4 6 B 3 4 14-3 34 B 3.4 6-5 56 B 3 4 14-4 38 B 3.4 7-i 0 B 3 4 14-5 38 B 3.4 7-2 6 B 3 4 14-6 38 B 3.4 7-3 52 B 3 4 14-7 56 B 3.4 7-4 54 B.3 4 14-8 56 B 3.4 7-5 0 B 3 4 15-i 0 B 3.4 7-6 56 B 3 4 15-2 48 B 3.4 7-7 52 B 3 4 15-3 0 B 3.4 8-i 0 B 3 4 15-4 0 B 3.4 8-2 58 B 3 4 15-5 56 B 3.4 8-3 58 B 3 4 15-6 56 B 3.4 8-4 58 B 3 4 15-7 54 B 3.4 9-i 41 B 3 4 16-i 2 B 3.4 9-2 31 B 3 4 16-2 i0 B 3.4 9-3 41 B 3 4 16-3 0 B 3.4 9-4 41 B 3 4 16-4 42 B 3.4 9-5 56 B 3 4 16-5 56 B 3.4 9-6 56 B 3 4 16-6 56 B 3.4 i0-I 53 B 3 4 17-i 0 B 3.4 I0-2 7 B 3 4 17-2 27 B 3.4 i0-3 0 B 3 4 17-3 42 B 3 4 i0-4 54 B 3 4 17-4 42 B 3 4 Ii-i 0 B 3 4 17-5 57 B 3 4 ii-2 53 B 3 4 17-6 56 B 3 4 ii-3 0 B 3 4 18-i 38 B 3 4 11-4 52 B 3 4 18-2 40 B 3 4 11-5 56 B 3.4 18-3 38 B 3 4 11-6 54 B 3 4 18-4 38 B 3 4 12-i 1 B 3 4 18-5 38 B 3 4 12-2 34 B 3 4 18-6 38 B 3 4 12-3 48 B 3 4 18-7 38 B 3 4 12-4 56 B 3 4 18-8 38 B 3 4 12-5 31 B 3 5 i-i 0 B 3 4 13-i 0 B 3 5 i-2 53 B 3 4 13-2 55 B 3 5 i-3 7 B 3 4 13-3 55 B 3 5 i-4 0 B 3 4 13-4 52 B 3 5 i-5 0 B 3 4 13-5 55 B 3 5 i-6 0 B 3 4 13-6 55 B 3 5 i-7 1 B 3 4 13-7 52 B 3 5 I-8 1 PALO VERDE UNITS i, 2, AND 3 5 Revision 58 July 03, 2013 TECHNICAL SPECIFICATION BASES LIST OF EFFECTIVE PAGES Page Rev.Page Rev No.No.No.No.B 3.5.1-9 57 B 3 6 2-4 0 B 3 5.1-i0 56 B 3 6 2-5 0 B 3 5.2-i 0 B 3 6 2-6 0 B 3 5.2-2 53 B 3 6 2-7 0 B 3 5.2-3 53 B 3 6 2-8 57 B 3 5.2-4 0 B 3 6 3-I 36 B 3 5.2-5 0 B 3 6 3-2 43 B 3 5.2-6 0 B 3 6 3-3 49 B 3 5.2-7 1 B 3 6 3-4 43 B 3 5.2-8 22 B 3 6 3-5 43 B 3 5.2-9 57 B 3 6 3-6 43 B 3 5.2-i0 56 B 3 6 3-7 43 B 3 5 3-i 0 B 3 6 3-8 43 B 3 5 3-2 48 B 3 6 3-9 43 B 3 5 3-3 0 B 3 6 3-i0 43 B 3 5 3-4 0 B 3 6 3-ii 43 B 3 5 3-5 0 B 3 6.3-12 43 B 3 5 3-6 2 B 3 6.3-13 43 B 3 5 3-7 2 B 3 6.3-14 43 B 3.5 3-8 56 B 3 6.3-15 43 B 3.5 3-9 56 B 3 6.3-16 56 B 3.5 3-i0 56 B 3 6.3-17 56 B 3.5 4-i 15 B 3 6.3-18 56 B 3.5 4-2 0 B 3 6.3-19 56 B 3.5 4-3 42 B 3 6.4-i 53 B 3.5 5-i 54 B 3 6.4-2 38 B 3.5 5-2 54 B 3 6.4-3 56 B 3.5 5-3 55 B 3 6.5-i 0 B 3.5 5-4 54 B 3 6.5-2 1 B 3.5 5-5 51 B 3 6.5-3 56 B 3 5 5-6 51 B 3 6 5-4 0 B 3 5 5-7 51 B 3 6 6-i 0 B 3 5 5-8 56 B 3 6 6-2 0 B 3 5 5-9 56 B 3 6 6-3 53 B 3 5 6-i 0 B 3 6 6-4 7 B 3 5 6-2 1 B 3 6 6-5 1 B 3 5 6-3 0 B 3 6 6-6 56 B 3 5 6-4 56 B 3 6 6-7 56 B 3 5 6-5 56 B 3 6 6-8 56 B 3 6 i-i 0 B 3 6 6-9 54 B 3 6 I-2 53 B 3.7 i-i 50 B 3 6 I-3 0 B 3.7 i-2 50 B 3 6 i-4 29 B 3.7 I-3 34 B 3 6 i-5 29 B 3.7 i-4 34 B 3 6 2-i 45 B 3.7 i-5 54 B 3 6 2-2 53 B 3.7 i-6 54 B 3 6 2-3 0 B 3.7 2-i 40 PALO VERDE UNITS i, 2, AND 3 6 Revision 58 July 03, 2013 TECHNICAL SPECIFICATION BASES LIST OF EFFECTIVE PAGES Page Rev.Page Rev No.No.No.No.B 3.7 2-2 42 B 3 7 I0-2 1 B 3 7 2-3 40 B 3 7 i0-3 1 B 3 7 2-4 40 B 3 7 i0-4 56 B 3 7 2-5 40 B 3 7 ii-i 50 B 3 7 2-6 40 B 3 7 ii-2 50 B 3 7 2-7 40 B 3 7 ii-3 51 B 3 7 2-8 54 B 3 7 ii-4 55 B 3 7 2-9 54 B 3 7 ii-5 50 B 3.7 3-i 1 B 3 7 ii-6 55 B 3.7 3-2 1 B 3 7 ii-7 57 B 3.7 3-3 37 B 3 7 ii-8 56 B 3.7 3-4 0 B 3 7 ii-9 50 B 3 7 3-5 54 B 3 7 12-i 1 B 3 7 4-i 58 B 3 7 12-2 21 B 3 7 4-2 58 B 3 7 12-3 55 B 3 7 4-3 58 B 3 7 12-4 56 B 3 7 4-4 58 B 3 7 13-i 0 B 3 7 4-5 58 B 3 7 13-2 0 B 3.7 4-6 58 B 3 7 13-3 0 B 3.7 5-i 0 B 3 7 13-4 57 B 3.7 5-2 0 B 3 7 13-5 56 B 3.7 5-3 40 B 3 7 14-i 0 B 3.7 5-4 27 B 3 7 14-2 21 B 3.7 5-5 42 B 3 7 14-3 56 B 3.7 5-6 42 B 3 7 15-I 3 B 3 7 5-7 9 B 3 7 15-2 56 B 3 7 5-8 56 B 3 7 16-i 7 B 3 7 5-9 56 B 3 7 16-2 0 B 3 7 5-i0 56 B 3.7 16-3 56 B 3 7 5-ii 54 B 3.7 16-4 0 B 3 7 6-i 54 B 3.7 17-i 52 B 3 7 6-2 54 B 3.7 17-2 3 B 3 7 6-3 55 B 3.7 17-3 3 B 3 7 6-4 56 B 3.7 17-4 3 B 3 7 7-i 0 B 3.7 17-5 3 B 3 7 7-2 1 B 3.7 17-6 52 B 3 7 7-3 1 B 3 8 I-I 35 B 3 7 7-4 56 B 3 8 I-2 2 B 3 7 7-5 56 B 3 8 I-3 34 B 3 7 8-i 1 B 3 8 i-4 34 B 3 7 8-2 1 B 3 8 i-5 20 B 3 7 8-3 1 B 3 8 I-6 57 B 3 7 8-4 56 B 3 8 i-7 42 B 3 7 9-I 0 B 3 8 I-8 50 B 3 7 9-2 44 B 3 8 i-9 42 B 3 7 9-3 56 B 3 8 i-i0 43 B 3 7 i0-i i0 B 3 8 i-ii 50 PALO VERDE UNITS i, 2, AND 3 7 Revision 58 July 03, 2013 TECHNICAL SPECIFICATION BASES LIST OF EFFECTIVE PAGES Page Rev.Page Rev No.No.No.No.B 3.8 1-12 48 B 3 8 3-5 54 B 3 8 1-13 48 B 3 8 3-6 56 B 3 8 1-14 48 B 3 8 3-7 56 B 3 8 1-15 48 B 3 8 3-8 41 B 3 8 1-16 41 B 3 8 3-9 56 B 3 8 1-17 41 B 3 8 3-i0 54 B 3 8 1-18 41 B 3 8 4-i 0 B 3 8 1-19 41 B 3 8 4-2 37 B 3 8 1-20 41 B 3 8 4-3 0 B 3 8 1-21 41 B 3 8 4-4 2 B 3 8 1-22 41 B 3 8.4-5 2 B 3 8 1-23 57 B 3 8.4-6 56 B 3 8 1-24 50 B 3 8.4-7 56 B 3 8 1-25 56 B 3 8.4-8 56 B 3.8 1-26 56 B 3 8.4-9 56 B 3.8 1-27 56 B 3 8.4-i0 56 B 3.8 1-28 56 B 3 8.4-ii 48 B 3.8 1-29 53 B 3 8.5-i 1 B 3.8 1-30 56 B 3 8.5-2 1 B 3.8 1-31 50 B 3 8.5-3 21 B 3.8 1-32 56 B 3 8.5-4 21 B 3 8 1-33 56 B 3 8.5-5 2 B 3 8 1-34 56 B 3 8.5-6 2 B 3 8 1-35 50 B 3 8 6-i 0 B 3 8 1-36 56 B 3 8 6-2 0 B 3 8 1-37 45 B 3 8 6-3 56 B 3 8 1-38 56 B 3 8 6-4 56 B 3 8 1-39 56 B 3 8 6-5 37 B 3 8 1-40 56 B 3 8 6-6 37 B 3 8 1-41 56 B 3 8 6-7 48 B 3 8 1-42 56 B 3 8 7-i 48 B 3 8 1-43 56 B 3 8 7-2 48 B 3 8 1-44 56 B 3 8 7-3 53 B 3 8 1-45 56 B 3.8 7-4 53 B.3 8 1-46 56 B 3.8 7-5 56 B.3 8 1-47 45 B 3.8 8-i 1 B.3 8 1-48 53 B 3.8 8-2 1 B 3 8 2-i 0 B 3.8 8-3 21 B 3 8 2-2 0 B 3.8 8-4 56 B 3 8 2-3 0 B 3.8 8-5 56 B 3 8 2-4 21 B 3 8 9-i 51 B 3 8 2-5 21 B 3 8 9-2 0 B 3 8 2-6 0 B 3 8 9-3 51 B 3 8 3-i 0 B 3 8 9-4 0 B 3 8 3-2 0 B 3 8 9-5 0 B 3 8 3-3 50 B 3 8 9-6 0 B 3 8 3-4 0 B 3 8 9-7 0 PALO VERDE UNITS i, 2, AND 3 8 Revision 58 July 03, 2013 TECHNICAL SPECIFICATION BASES LIST OF EFFECTIVE PAGES Page Rev.Page Rev No.No.No.No.B 3 8 9-8 0 B 3 8 9-9 0 B 3 8 9-10 56 B 3 8 9-11 51 B 3 8 i0-I 0 B 3 8 10-2 21 B 3 8 10-3 48 B 3 8 10-4 56 B 3 9 I-i 34 Corrected B3 91-2 0 B 3 9 i-3 0 B 3 9 1-4 56 B 3 9 2-1 48 B 3 9 2-2 15 B 3 9 2-3 56 B 3 9 2-4 56 B 3 9 3-1 18 B 3 93-2 19 B 3 9 3-3 27 B 3 93-4 19 B 3 9 3-5 56 B.3 9 3-6 56 B 3 9 4-i 0 B 3 9 4-2 54 B3 94-3 0 B 3 94-4 56 B3 95-i 0 B 3 9 5-2 58 B 3 9 5-3 58 B 3 9 5-4 58 B 3 9 6-i 0 B3 96-2 0 B 3 9 6-3 56 B 3 9 7-i 0 B3 97-2 0 B 3 9 7-3 56 PALO VERDE UNITS I, 2, AND 3 9 Revision 58 July 03, 2013 This page intentionally blank RCS Loops-MODE 5, Loops Not Filled B 3.4.8 B 3.4 REACTOR COOLANT SYSTEM (RCS)B 3.4.8 RCS Loops-MODE 5, Loops Not Filled BASES BACKGROUND In MODE 5 with the RCS loops not filled, the primary function of the reactor coolant is the removal of decay heat and transfer of this heat to the Shutdown Cooling (SDC)heat exchangers
......Cor,_,zo_,,
.The Steam Generators (SGs)are not available as a heat sink when the loops are not filled.The secondary function of the reactor coolant is to act as a carrier for the soluble neutron poison, boric acid.In MODE 5 with loops not filled, only the SDC System can be used for coolant circulation
IDN:cn=Stephenson, CarlJ(ZO5778)
.The number of trains in operation can vary to suit the operational needs.The intent of this LCO is to provide forced flow from at least one SDC train for decay heat removal and transport and to require that two paths be available to provide redundancy for heat removal.APPLICABLE In MODE 5, RCS circulation is considered in determining SAFETY ANALYSES the time available for mitigation of the accidental boron dilution event.The SDC trains provide this circulation
Reason:Iattesttotheaccuracyandintegrity ofCarlJ(Z05778) th,,_.......Date:20!3.06.2809:16:17-07'00' TECHNICAL SPECIFICATION BASESLISTOFEFFECTIVE PAGESPageRev.PageRevNo.No.No.No.B21i-i0B313-20B21i-20B313-30B21i-337B313-40B21i-421B313-50B21i-554B313-656B212-I0B314-i0B212-231B314-231B212-30B314-30B212-454B314-40B30-i49B314-50B30-20B315-i0B30-30B315-252B30-40B315-352B30-542B315-452B30-648B315-552B30-748B315-652B30-842B315-752B30-942B315-852B30-i042B315-952B30-ii42B315-1056B30-1242B315-1156B30-1342B315-1256B30-1449B316-i0B30-1550B316-246B30-1650B316-342B30-1750B316-442B30-1849B316-556B30-1949B316-646B30-2049B317-i57B30-2149B317-20B30-2249B317-353B31i-I28B317-448B31i-20B317-525B31i-343B317-60B31i-443B317-70B31I-527B317-856B31i-656B317-956B312-I28B318-i52B312-20B318-252B312-343B318-352B312-428B318-452B312-50B318-556B312-643B319-i0B312-712B319-20B312-847B319-30B312-956B319-40B313-I0B319-556PALOVERDEUNITSi,2,AND31Revision58July03,2013 TECHNICAL SPECIFICATION BASESLISTOFEFFECTIVE 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PAGESPageRev.PageRevNo.No.No.No.B3.3.6-90B33I0-i057B3.3.6-100B33i0-ii50B3.3.6-110B3310-1250B3.3.6-120B3310-1350B3.3.6-130B3310-1450B3.3.6-140B3310-1550B33.6-150B3310-1650B33.6-160B3310-1750B336-1727B3310-1850B336-180B3.310-1956B336-1956B3.3.10-20 56B336-200B3.3.10-21 50B336-2156B3.3.10-22 32B336-2246B33.11-I0B337-i2B33ii-22B337-22B33ii-32B337-30B33ii-442B337-40B33ii-542B337-50B33Ii-656B337-642B33ii-756B337-70B3312-i15B33.7-856B3312-250B33.7-956B3312-337B338-i0B3312-437B338-244B3312-556B338-30B3312-656B3.38-40B34i-ii0B3.38-50B34i-253B3.38-656B34i-30B338-756B34i-40B338-856B34i-556B339-i48B3.4.2-I7B339-248B3.4.2-257B339-355B3.43-i52B339-455B3.43-252B339-556B3.43-30B339-656B3.43-452B339-756B343-552B33i0-i0B343-60B33i0-20B343-756B3.3.10-30B343-852B3.3.10-40B344-i0B3.3.10-518B344-250B3.3.10-60B344-37B3.3.10-70B344-456B3.3.10-814B3.45-i0B3.3.10-914B3.45-238PALOVERDEUNITSi,2,AND34Revision58July03,2013 TECHNICAL SPECIFICATION BASESLISTOFEFFECTIVE PAGESPageRev.PageRevNo.No.No.No.B345-338B3413-852B345-456B3413-956B345-556B3413-I056B346-i0B3413-ii55B346-26B3414-i0B346-352B3414-234B346-46B3414-334B3.46-556B3414-438B3.47-i0B3414-538B3.47-26B3414-638B3.47-352B3414-756B3.47-454B.3414-856B3.47-50B3415-i0B3.47-656B3415-248B3.47-752B3415-30B3.48-i0B3415-40B3.48-258B3415-556B3.48-358B3415-656B3.48-458B3415-754B3.49-i41B3416-i2B3.49-231B3416-2i0B3.49-341B3416-30B3.49-441B3416-442B3.49-556B3416-556B3.49-656B3416-656B3.4i0-I53B3417-i0B3.4I0-27B3417-227B3.4i0-30B3417-342B34i0-454B3417-442B34Ii-i0B3417-557B34ii-253B3417-656B34ii-30B3418-i38B3411-452B3418-240B3411-556B3.418-338B3411-654B3418-438B3412-i1B3418-538B3412-234B3418-638B3412-348B3418-738B3412-456B3418-838B3412-531B35i-i0B3413-i0B35i-253B3413-255B35i-37B3413-355B35i-40B3413-452B35i-50B3413-555B35i-60B3413-655B35i-71B3413-752B35I-81PALOVERDEUNITSi,2,AND35Revision58July03,2013 TECHNICAL SPECIFICATION BASESLISTOFEFFECTIVE PAGESPageRev.PageRevNo.No.No.No.B3.5.1-957B362-40B35.1-i056B362-50B35.2-i0B362-60B35.2-253B362-70B35.2-353B362-857B35.2-40B363-I36B35.2-50B363-243B35.2-60B363-349B35.2-71B363-443B35.2-822B363-543B35.2-957B363-643B35.2-i056B363-743B353-i0B363-843B353-248B363-943B353-30B363-i043B353-40B363-ii43B353-50B36.3-1243B353-62B36.3-1343B353-72B36.3-1443B3.53-856B36.3-1543B3.53-956B36.3-1656B3.53-i056B36.3-1756B3.54-i15B36.3-1856B3.54-20B36.3-1956B3.54-342B36.4-i53B3.55-i54B36.4-238B3.55-254B36.4-356B3.55-355B36.5-i0B3.55-454B36.5-21B3.55-551B36.5-356B355-651B365-40B355-751B366-i0B355-856B366-20B355-956B366-353B356-i0B366-47B356-21B366-51B356-30B366-656B356-456B366-756B356-556B366-856B36i-i0B366-954B36I-253B3.7i-i50B36I-30B3.7i-250B36i-429B3.7I-334B36i-529B3.7i-434B362-i45B3.7i-554B362-253B3.7i-654B362-30B3.72-i40PALOVERDEUNITSi,2,AND36Revision58July03,2013 TECHNICAL SPECIFICATION BASESLISTOFEFFECTIVE PAGESPageRev.PageRevNo.No.No.No.B3.72-242B37I0-21B372-340B37i0-31B372-440B37i0-456B372-540B37ii-i50B372-640B37ii-250B372-740B37ii-351B372-854B37ii-455B372-954B37ii-550B3.73-i1B37ii-655B3.73-21B37ii-757B3.73-337B37ii-856B3.73-40B37ii-950B373-554B3712-i1B374-i58B3712-221B374-258B3712-355B374-358B3712-456B374-458B3713-i0B374-558B3713-20B3.74-658B3713-30B3.75-i0B3713-457B3.75-20B3713-556B3.75-340B3714-i0B3.75-427B3714-221B3.75-542B3714-356B3.75-642B3715-I3B375-79B3715-256B375-856B3716-i7B375-956B3716-20B375-i056B3.716-356B375-ii54B3.716-40B376-i54B3.717-i52B376-254B3.717-23B376-355B3.717-33B376-456B3.717-43B377-i0B3.717-53B377-21B3.717-652B377-31B38I-I35B377-456B38I-22B377-556B38I-334B378-i1B38i-434B378-21B38i-520B378-31B38I-657B378-456B38i-742B379-I0B38I-850B379-244B38i-942B379-356B38i-i043B37i0-ii0B38i-ii50PALOVERDEUNITSi,2,AND37Revision58July03,2013 TECHNICAL SPECIFICATION BASESLISTOFEFFECTIVE PAGESPageRev.PageRevNo.No.No.No.B3.81-1248B383-554B381-1348B383-656B381-1448B383-756B381-1548B383-841B381-1641B383-956B381-1741B383-i054B381-1841B384-i0B381-1941B384-237B381-2041B384-30B381-2141B384-42B381-2241B38.4-52B381-2357B38.4-656B381-2450B38.4-756B381-2556B38.4-856B3.81-2656B38.4-956B3.81-2756B38.4-i056B3.81-2856B38.4-ii48B3.81-2953B38.5-i1B3.81-3056B38.5-21B3.81-3150B38.5-321B3.81-3256B38.5-421B381-3356B38.5-52B381-3456B38.5-62B381-3550B386-i0B381-3656B386-20B381-3745B386-356B381-3856B386-456B381-3956B386-537B381-4056B386-637B381-4156B386-748B381-4256B387-i48B381-4356B387-248B381-4456B387-353B381-4556B3.87-453B.381-4656B3.87-556B.381-4745B3.88-i1B.381-4853B3.88-21B382-i0B3.88-321B382-20B3.88-456B382-30B3.88-556B382-421B389-i51B382-521B389-20B382-60B389-351B383-i0B389-40B383-20B389-50B383-350B389-60B383-40B389-70PALOVERDEUNITSi,2,AND38Revision58July03,2013 TECHNICAL SPECIFICATION BASESLISTOFEFFECTIVE PAGESPageRev.PageRevNo.No.No.No.B389-80B389-90B389-1056B389-1151B38i0-I0B3810-221B3810-348B3810-456B39I-i34Corrected B391-20B39i-30B391-456B392-148B392-215B392-356B392-456B393-118B393-219B393-327B393-419B393-556B.393-656B394-i0B394-254B394-30B394-456B395-i0B395-258B395-358B395-458B396-i0B396-20B396-356B397-i0B397-20B397-356PALOVERDEUNITSI,2,AND39Revision58July03,2013 Thispageintentionally blank RCSLoops-MODE5,LoopsNotFilledB3.4.8B3.4REACTORCOOLANTSYSTEM(RCS)B3.4.8RCSLoops-MODE5,LoopsNotFilledBASESBACKGROUND InMODE5withtheRCSloopsnotfilled,theprimaryfunctionofthereactorcoolantistheremovalofdecayheatandtransferofthisheattotheShutdownCooling(SDC)heatexchangers
.The flow provided by one SDC train is adequate for decay heat removal and for boron mixing.RCS loops-MODE 5 (loops not filled)have been identified in 10 CFR 50.36 (c)(2)(ii) as important contributors to risk reduction.LCO The purpose of this LCO is to require a minimum of two SDC trains be OPERABLE and one of these trains be in operation.An OPERABLE train is one that is capable of transferring heat from the reactor coolant at a controlled rate.Heat cannot be removed via the SDC System unless forced flow is used.A minimum of one running SDC pump meets the LCO requirement for one train in operation.An additional SDC train is required to be OPERABLE to meet the single failure criterion.(continued)
.TheSteamGenerators (SGs)arenotavailable asaheatsinkwhentheloopsarenotfilled.Thesecondary functionofthereactorcoolantistoactasacarrierforthesolubleneutronpoison,boricacid.InMODE5withloopsnotfilled,onlytheSDCSystemcanbeusedforcoolantcirculation
PALO VERDE UNITS 1,2 , 3 B 3.4.8-1 REVISION 0 RCS Loops-MODE 5, Loops Not Filled B 3.4.8 BASES (continued)
.Thenumberoftrainsinoperation canvarytosuittheoperational needs.TheintentofthisLCOistoprovideforcedflowfromatleastoneSDCtrainfordecayheatremovalandtransport andtorequirethattwopathsbeavailable toprovideredundancy forheatremoval.APPLICABLE InMODE5,RCScirculation isconsidered indetermining SAFETYANALYSESthetimeavailable formitigation oftheaccidental borondilutionevent.TheSDCtrainsprovidethiscirculation
LCO Note 1 permits all SDC pumps to be de-energized
.TheflowprovidedbyoneSDCtrainisadequatefordecayheatremovalandforboronmixing.RCSloops-MODE5(loopsnotfilled)havebeenidentified in10CFR50.36(c)(2)(ii) asimportant contributors toriskreduction
_1 hour per (continued) 8 hour period.The circumstances for stopping both SDC pumps are to be limited to situations when the outage time is short and the core outlet temperature is maintained
.LCOThepurposeofthisLCOistorequireaminimumoftwoSDCtrainsbeOPERABLEandoneofthesetrainsbeinoperation
>IO°F below saturation temperature
.AnOPERABLEtrainisonethatiscapableoftransferring heatfromthereactorcoolantatacontrolled rate.HeatcannotberemovedviatheSDCSystemunlessforcedflowisused.AminimumofonerunningSDCpumpmeetstheLCOrequirement foronetraininoperation
.The 10 degrees F is considered the actual value of the necessary difference between RCS core outlet temperature and the saturation temperature associated with RCS pressure to be maintained during the time the pumps would be de-energized
.Anadditional SDCtrainisrequiredtobeOPERABLEtomeetthesinglefailurecriterion
.The instrument error associated with determining this difference is less than 10 degrees F.(There are no special restrictions for instrumentation use.)Therefore, the indicated value of the difference between RCS core outlet temperature and the saturation temperature associated with RCS pressure must be greater than or equal to i 20 degrees F in order to use the provisions of the Note allowing the pumps to be de-energized
.(continued)
, (Ref.1)The Note prohibits boron dilution or draining operations when SDC forced flow is stopped.Note 2 allows one SDC train to be inoperable for a period of 2 hours provided that the other train is OPERABLE and in operation.This permits periodic surveillance tests to be performed on the inoperable train during the only time when these tests are safe and possible.An OPERABLE SDC train is composed of an OPERABLE SDC pump (CS or LPSI)capable of providing flow to the SDC heat exchanger for heat removal.SDC pumps are OPERABLE if they are capable of being powered and are able to provide flow, if required.Note that the CS pumps shall not be used for normal operations if the water level is at or below the top of the hot-leg pipe (103'1")due to concerns of potential air entrainment and gas binding of the CS pump (Ref , 2).APPLICABILITY In MODE 5 with loops not filled, this LCO requires core heat removal and coolant circulation by the SDC System.Operation in other MODES is covered by: LCO 3.4.4,"RCS Loops-MODES 1 and 2";LCO 3.4.5,"RCS Loops-MODE 3";LCO 3.4.6,"RCS Loops-MODE 4";LCO 3.4 , 7,"RCS Loops-MODE 5, Loops Filled";LCO 3.9.4,"Shutdown Cooling (SDC)and Coolant Circulation
PALOVERDEUNITS1,2,3B3.4.8-1REVISION0 RCSLoops-MODE5,LoopsNotFilledB3.4.8BASES(continued)
-High Water Level" (MODE 6);and (continued)
LCONote1permitsallSDCpumpstobede-energized
PALO VERDE UNITS 1,2,3 B 3.4.8-2 REVISION 58 RCS Loops-MODE 5, Loops Not Filled B 3,4.8 BASES (continued)
_1hourper(continued) 8hourperiod.Thecircumstances forstoppingbothSDCpumpsaretobelimitedtosituations whentheoutagetimeisshortandthecoreoutlettemperature ismaintained
APPLICABILITY LCO 3.9.5,"Shutdown Cooling (SDC)and Coolant (continued)
>IO°Fbelowsaturation temperature
.The10degreesFisconsidered theactualvalueofthenecessary difference betweenRCScoreoutlettemperature andthesaturation temperature associated withRCSpressuretobemaintained duringthetimethepumpswouldbede-energized
.Theinstrument errorassociated withdetermining thisdifference islessthan10degreesF.(Therearenospecialrestrictions forinstrumentation use.)Therefore, theindicated valueofthedifference betweenRCScoreoutlettemperature andthesaturation temperature associated withRCSpressuremustbegreaterthanorequaltoi20degreesFinordertousetheprovisions oftheNoteallowingthepumpstobede-energized
,(Ref.1)TheNoteprohibits borondilutionordrainingoperations whenSDCforcedflowisstopped.Note2allowsoneSDCtraintobeinoperable foraperiodof2hoursprovidedthattheothertrainisOPERABLEandinoperation
.Thispermitsperiodicsurveillance teststobeperformed ontheinoperable trainduringtheonlytimewhenthesetestsaresafeandpossible.AnOPERABLESDCtrainiscomposedofanOPERABLESDCpump(CSorLPSI)capableofproviding flowtotheSDCheatexchanger forheatremoval.SDCpumpsareOPERABLEiftheyarecapableofbeingpoweredandareabletoprovideflow,ifrequired.NotethattheCSpumpsshallnotbeusedfornormaloperations ifthewaterlevelisatorbelowthetopofthehot-legpipe(103'1")duetoconcernsofpotential airentrainment andgasbindingoftheCSpump(Ref,2).APPLICABILITY InMODE5withloopsnotfilled,thisLCOrequirescoreheatremovalandcoolantcirculation bytheSDCSystem.Operation inotherMODESiscoveredby:LCO3.4.4,"RCSLoops-MODES 1and2";LCO3.4.5,"RCSLoops-MODE3";LCO3.4.6,"RCSLoops-MODE4";LCO3.4,7,"RCSLoops-MODE5,LoopsFilled";LCO3.9.4,"Shutdown Cooling(SDC)andCoolantCirculation
-HighWaterLevel"(MODE6);and(continued)
PALOVERDEUNITS1,2,3B3.4.8-2REVISION58 RCSLoops-MODE5,LoopsNotFilledB3,4.8BASES(continued)
APPLICABILITY LCO3.9.5,"Shutdown Cooling(SDC)andCoolant(continued)
Circulation
Circulation
-LowWaterLevel"(MODE6),ACTIONSA.IIfaSDCtrainisinoperable, redundancy forheatremovalislost.Actionmustbeinitiated immediately torestoreasecondtraintoOPERABLEstatus.TheCompletion Timereflectstheimportance ofmaintaining theavailability oftwopathsforheatremoval.B.1andB.2IfnoSDCtrainisOPERABLEorinoperation, exceptasprovidedinNOTEI,alloperations involving thereduction ofRCSboronconcentration mustbesuspended
-Low Water Level" (MODE 6), ACTIONS A.I If a SDC train is inoperable, redundancy for heat removal is lost.Action must be initiated immediately to restore a second train to OPERABLE status.The Completion Time reflects the importance of maintaining the availability of two paths for heat removal.B.1 and B.2 If no SDC train is OPERABLE or in operation, except as provided in NOTE I, all operations involving the reduction of RCS boron concentration must be suspended.Action to restore one SDC train to OPERABLE status and operation must be initiated immediately
.ActiontorestoreoneSDCtraintoOPERABLEstatusandoperation mustbeinitiated immediately
.Boron dilution requires forced circulation for proper mixing and the margin to criticality must not be reduced in this type of operation.The immediate Completion Time reflects the importance of maintaining operation for decay heat removal.SURVEILLANCE SR 3.4.8.1 REQUIREMENTS This SR requires verification that one SDC train is in operation and circulating reactor cool ant at a flow rate of greater than or equal to 3780 gpm.Verification includes flow rate, temperature, or pump status monitoring, which help ensure that forced flow is providing decay heat removal.The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.SR 3.4.8.2 Verification that the required number of trains are OPERABLE ensures that redundant paths for heat removal are available and that an additional train can be placed in operation, if needed, to maintain decay heat removal and reactor coolant circulation
.Borondilutionrequiresforcedcirculation forpropermixingandthemargintocriticality mustnotbereducedinthistypeofoperation
.Verification is performed by verifying proper breaker alignment and indicated power available to the required pumps.The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.(continued)
.Theimmediate Completion Timereflectstheimportance ofmaintaining operation fordecayheatremoval.SURVEILLANCE SR3.4.8.1REQUIREMENTS ThisSRrequiresverification thatoneSDCtrainisinoperation andcirculating reactorcoolantataflowrateofgreaterthanorequalto3780gpm.Verification includesflowrate,temperature, orpumpstatusmonitoring, whichhelpensurethatforcedflowisproviding decayheatremoval.TheSurveillance Frequency iscontrolled undertheSurveillance Frequency ControlProgram.SR3.4.8.2Verification thattherequirednumberoftrainsareOPERABLEensuresthatredundant pathsforheatremovalareavailable andthatanadditional traincanbeplacedinoperation, ifneeded,tomaintaindecayheatremovalandreactorcoolantcirculation
PALO VERDE UNITS 1,2,3 B 3.4.8-3 REVISION 58 RCS Loops-MODE 5 , Loops Not Filled B 3.4.8 BASES (continued)
.Verification isperformed byverifying properbreakeralignment andindicated poweravailable totherequiredpumps.TheSurveillance Frequency iscontrolled undertheSurveillance Frequency ControlProgram.(continued)
REFERENCES 1.PVNGS Calculation 13-JC-SH-0200, Section 2.9.2.PVNGS Calculation 13-MC-SI-0250, Appendix C.PALO VERDE UNITS 1,2 , 3 B 3.4.8-4 REVISION 58 ADVs B 3 , 7.4 B 3.7 PLANT SYSTEMS B 3.7,4 Atmospheric Dump Valves (ADVs)BASES BACKGROUND The ADVs provide a safety grade method for cooling the unit to Shutdown Cooling (SDC)System entry conditions, should the preferred heat sink via the Steam Bypass Control System (SBCS)to the condenser and/or atmosphere not be available , as discussed in the UFSAR, Section 10.3 (Ref.1).The ADVs have the capacity to achieve and maintain safe shutdown conditions following design basis accidents involving a loss of offsite power and/or closure of the Main Steam Isolation Valves (MSIVs)following receipt of a Main Steam Isolation Signal (MSIS).This is done in conjunction with the Auxiliary Feedwater System providing cooling water from the Condensate Storage Tank (CST).The ADVs may also be required to meet the design cooldown rate during a normal cooldown.Four ADV lines are provided.Each ADV line consists of one normally closed ADV and an associated, normally open block valve.Two ADV lines per steam generator are required to meet the single failure assumptions following a design basis accident that may render one steam generator (SG)unavailable for heat removal.The ADV block valves permit testing of the ADVs while a unit is at power.The safety analyses, however, do not credit block valve operation as a means of isolation of a failed open ADV.The ADVs are equipped with pneumatic controllers to permit control of the cooldown rate.The ADVs are provided with a pressurized gas supply of bottled nitrogen that, on a loss of pressure in the normal instrument air supply, automatically supplies nitrogen to operate the ADVs.The nitrogen supply is sized to provide sufficient pressurized gas to operate the ADVs for the time required for Reactor Coolant System (RCS)cooldown to the Shutdown Cooling (SDC)System entry conditions, as described in UFSAR Appendix 5C,"Natural Circulation Cooldown Analysis." The Appendix 5C analysis is based on the assumptions and conditions in the NRC's Branch Technical Position (BTP)RSB 5-1 ,"Design Requirements of the Residual Heat Removal System." RSB 5-I is an attachment (continued)
PALOVERDEUNITS1,2,3B3.4.8-3REVISION58 RCSLoops-MODE5,LoopsNotFilledB3.4.8BASES(continued)
PALO VERDE UNITS 1,2,3 B 3.7.4-1 REVISION 58 ADVs B 3.7.4 BASES BACKGROUND (continued) to Standard Review Plan (SRP)5.4.7,"Residual Heat Removal (RHR)System," and identifies RHR System requirements that ensure conformance with General Design Criteria (GDC)34,"Residual Heat Removal." The PVNGS RSB 5-1 cooldown scenario described in UFSAR Appendix 5C is based on a natural circulation cooldown with both steam generators (SGs)available, using safety-grade equipment, assuming a loss of offsite power, a limiting single failure (assumed to be a diesel generator failure), and with minimal operator actions outside the control room , as approved by the NRC.The RSB 5-1 cooldown duration wa s established during actual testing performed in January 1986, and was confirmed through subsequent analyses to address steam generator replacement and power uprates.A description of the ADVs is found in Reference 1.The ADVs require both Direct Current (DC)sources and class Alternating Current (AC)instrument power to be considered OPERABLE.In addition, non-safety related hand wheels are provided for local manual operations although hand wheels are not required for ADV OPERABILITY or credited in the accident analysis.APPLICABLE The design basis of the ADVs is established by the SAFETY ANALYSES capability to cool the unit to SDC System entry conditions
REFERENCES 1.PVNGSCalculation 13-JC-SH-0200, Section2.9.2.PVNGSCalculation 13-MC-SI-0250, AppendixC.PALOVERDEUNITS1,2,3B3.4.8-4REVISION58 ADVsB3,7.4B3.7PLANTSYSTEMSB3.7,4Atmospheric DumpValves(ADVs)BASESBACKGROUND TheADVsprovideasafetygrademethodforcoolingtheunittoShutdownCooling(SDC)Systementryconditions, shouldthepreferred heatsinkviatheSteamBypassControlSystem(SBCS)tothecondenser and/oratmosphere notbeavailable
.The design must also accommodate credible single failures that may render as many as two ADVs (i.e., one on each steam generator) incapable of opening on demand.This design is adequate to cool the unit to SDC System entry conditions with only one ADV and one SG, utilizing the cooling water supply available in the CST.Cooldown scenarios using a single ADV may require a combination of the available nitrogen supply and local manual operation or other actions.Alternatives for cooldown and for ADV operation beyond the RSB 5-1 scenario have been evaluated using probabilistic risk analysis (PRA)as part of the resolution of Unresolved Safety Issue (USI)A-45,"Shutdown Decay Heat Removal Requirements
,asdiscussed intheUFSAR,Section10.3(Ref.1).TheADVshavethecapacitytoachieveandmaintainsafeshutdownconditions following designbasisaccidents involving alossofoffsitepowerand/orclosureoftheMainSteamIsolation Valves(MSIVs)following receiptofaMainSteamIsolation Signal(MSIS).Thisisdoneinconjunction withtheAuxiliary Feedwater Systemproviding coolingwaterfromtheCondensate StorageTank(CST).TheADVsmayalsoberequiredtomeetthedesigncooldownrateduringanormalcooldown.FourADVlinesareprovided.EachADVlineconsistsofonenormallyclosedADVandanassociated, normallyopenblockvalve.TwoADVlinespersteamgenerator arerequiredtomeetthesinglefailureassumptions following adesignbasisaccidentthatmayrenderonesteamgenerator (SG)unavailable forheatremoval.TheADVblockvalvespermittestingoftheADVswhileaunitisatpower.Thesafetyanalyses, however,donotcreditblockvalveoperation asameansofisolation ofafailedopenADV.TheADVsareequippedwithpneumatic controllers topermitcontrolofthecooldownrate.TheADVsareprovidedwithapressurized gassupplyofbottlednitrogenthat,onalossofpressureinthenormalinstrument airsupply,automatically suppliesnitrogentooperatetheADVs.Thenitrogensupplyissizedtoprovidesufficient pressurized gastooperatetheADVsforthetimerequiredforReactorCoolantSystem(RCS)cooldowntotheShutdownCooling(SDC)Systementryconditions, asdescribed inUFSARAppendix5C,"NaturalCirculation CooldownAnalysis."
." USI A-45 was subsumed into the Individual Plant Examination (IPE)which used PRA techniques and was submitted to the NRC in response to Generic Letter 88-20.The IPE considered various operator actions and the use of non-safety related equipment, and concluded that there are no significant heat removal vulnerabilities at PVNGS.(continued)
TheAppendix5Canalysisisbasedontheassumptions andconditions intheNRC'sBranchTechnical Position(BTP)RSB5-1,"DesignRequirements oftheResidualHeatRemovalSystem."RSB5-Iisanattachment (continued)
PALO VERDE UNITS 1,2,3 B 3.7.4-2 REVISION 58 ADVs B 3.7.4 BASES APPLICABLE SAFETY ANALYSES Operator actions to locally operate the ADVs are not credited (continued) in the UFSAR Chapter 15 accident analyses but are described in the EOPs;non-safety related equipment such as the supplemental nitrogen supply could also be used during extended cooldown situations
PALOVERDEUNITS1,2,3B3.7.4-1REVISION58 ADVsB3.7.4BASESBACKGROUND (continued) toStandardReviewPlan(SRP)5.4.7,"Residual HeatRemoval(RHR)System,"andidentifies RHRSystemrequirements thatensureconformance withGeneralDesignCriteria(GDC)34,"Residual HeatRemoval."ThePVNGSRSB5-1cooldownscenariodescribed inUFSARAppendix5Cisbasedonanaturalcirculation cooldownwithbothsteamgenerators (SGs)available, usingsafety-grade equipment, assumingalossofoffsitepower,alimitingsinglefailure(assumedtobeadieselgenerator failure),
.The design basis accident analyses also account for a single failure that may render one ADV incapable of being closed remotely, after it is opened by control room operators.This type of postulated failure yields more adverse radiological consequences for certain analyses, because it creates a pathway for radioisotope discharges to the environment
andwithminimaloperatoractionsoutsidethecontrolroom,asapprovedbytheNRC.TheRSB5-1cooldowndurationwasestablished duringactualtestingperformed inJanuary1986,andwasconfirmed throughsubsequent analysestoaddresssteamgenerator replacement andpoweruprates.Adescription oftheADVsisfoundinReference 1.TheADVsrequirebothDirectCurrent(DC)sourcesandclassAlternating Current(AC)instrument powertobeconsidered OPERABLE.Inaddition, non-safety relatedhandwheelsareprovidedforlocalmanualoperations althoughhandwheelsarenotrequiredforADVOPERABILITY orcreditedintheaccidentanalysis.APPLICABLE ThedesignbasisoftheADVsisestablished bytheSAFETYANALYSEScapability tocooltheunittoSDCSystementryconditions
.For accident mitigation the safety analyses do not credit isolation of a failed open ADV by either local manual hand wheel operation or closure of its associated block valve.The safety analyses in the UFSAR assume that plant operators will use the ADVs to cool down an affected unit to SDC System entry conditions, following accidents accompanied by a loss of offsite power and/or closure of the MSIVs.Initiation of operator action is typically assumed to occur 30 minutes following the initiation of an event;however , to conservatively bound maximum potential dose consequences for Steam Generator Tube Rupture (SGTR)events, initiation of this operator action is assumed to occur two minutes following reactor trip.Prior to the operator action, the Main Steam Safety Valves (MSSVs)are credited in the analyses to maintain SG pressure and temperature near the MSSV setpoints.The limiting design basis event for nitrogen supply capacity is the RSB 5-1 natural circulation cooldown scenario described above.This scenario includes an initial period of 4 hours at hot standby conditions followed by natural circulation cooldown for 9.3 hours until SDC entry conditions are achieved.Each ADV is required to have a nitrogen supply that supports ADV operation for a total of 13.3 hours , Limiting design basis accidents with respect to RCS heat removal and ADV steam flow capacity include those that may render one SG unavailable, with a coincident loss of offsite power and a single active component failure (i.e., main steam line breaks upstream of the MSIVs, and feedwaterline breaks).(continued)
.Thedesignmustalsoaccommodate crediblesinglefailuresthatmayrenderasmanyastwoADVs(i.e.,oneoneachsteamgenerator) incapable ofopeningondemand.ThisdesignisadequatetocooltheunittoSDCSystementryconditions withonlyoneADVandoneSG,utilizing thecoolingwatersupplyavailable intheCST.Cooldownscenarios usingasingleADVmayrequireacombination oftheavailable nitrogensupplyandlocalmanualoperation orotheractions.Alternatives forcooldownandforADVoperation beyondtheRSB5-1scenariohavebeenevaluated usingprobabilistic riskanalysis(PRA)aspartoftheresolution ofUnresolved SafetyIssue(USI)A-45,"Shutdown DecayHeatRemovalRequirements
PALO VERDE UNITS 1,2,3 B 3.7.4-3 REVISION 58 ADVs B 3.7.4 BASES APPLICABLE SAFETY ANALYSES The limiting design basis event with respect to offsite (continued) radiological consequences is a SGTR with a coincident loss of offsite power, a coincident RCS iodine spike, and a single failed open ADV on the affected SG (SGTRLOPSF)
."USIA-45wassubsumedintotheIndividual PlantExamination (IPE)whichusedPRAtechniques andwassubmitted totheNRCinresponsetoGenericLetter88-20.TheIPEconsidered variousoperatoractionsandtheuseofnon-safety relatedequipment, andconcluded thattherearenosignificant heatremovalvulnerabilities atPVNGS.(continued)
.To determine bounding radiological consequences, an ADV is assumed to stick open during operator action that occurs two minutes after trip, and remains open for the duration of the cooldown.For this SGTRLOPSF case, plant operators will direct auxiliary feedwater flow to the affected SG after the accident has occurred.The steam released through the ADVs is contaminated, however, because of primary-to-secondary leakage that transports radioisotopes from the RCS to the SG.The ADVs satisfy Criterion 3 of 10 CFR 50.36 (c)(2)(ii)
PALOVERDEUNITS1,2,3B3.7.4-2REVISION58 ADVsB3.7.4BASESAPPLICABLE SAFETYANALYSESOperatoractionstolocallyoperatetheADVsarenotcredited(continued) intheUFSARChapter15accidentanalysesbutaredescribed intheEOPs;non-safety relatedequipment suchasthesupplemental nitrogensupplycouldalsobeusedduringextendedcooldownsituations
.LCO Four ADV lines are required to be OPERABLE, two on each SG to ensure a design basis accident that renders one SG unavailable for heat removal (in combination with a coincident loss of offsite power and a single active component failure)would not prevent control room operators from remotely opening an ADV on the unaffected SG.Failure to meet the LCO can result in an inability to cool the affected unit to SDC System entry conditions when the SBCS is unavailable
.ThedesignbasisaccidentanalysesalsoaccountforasinglefailurethatmayrenderoneADVincapable ofbeingclosedremotely, afteritisopenedbycontrolroomoperators
.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.I In MODES 1, 2, and 3, and in MODE 4, when a SG is being APPLICABILITY relied upon for heat removal , the ADVs are required to be OPERABLE.In MODES 5 and 6, there is insufficient heat available to produce steam that could be released through the ADVs, and design basis accidents such as main steam line breaks, feedwater line breaks, and SGTRs are not credible events.(continued)
.Thistypeofpostulated failureyieldsmoreadverseradiological consequences forcertainanalyses, becauseitcreatesapathwayforradioisotope discharges totheenvironment
PALO VERDE UNITS 1,2,3 B 3.7.4-4 REVISION 58 BASES ACTIONS A.1 The condition for this ACTION is modified by a Note that states separate Condition entry is allowed for each SG.This is acceptable because only one SG is required for RCS heat removal after a design basis accident, and because this Condition provides the appropriate Required Action and Completion Time for one inoperable ADV line on each SG.With one ADV line on a SG inoperable, action must be taken to restore that ADV line to OPERABLE status within 7 days to meet the LCO for each SG that has entered this Condition.The 7-day Completion Time takes into consideration the redundant capability afforded by the remaining OPERABLE ADV lines, the safety grade MSSVs , and the non-safety grade backup of the SBCS.B.1 With two or more ADV lines inoperable with both ADV lines inoperable on one or more SGs, action must be taken to restore one ADV line on each SG to OPERABLE status within 24 hours.The 24 hour Completion Time is reasonable to repair inoperable ADV lines, based on the availability of the Steam Bypass Control System and MSSVs, and the low probability of an event occurring during this period that requires the ADV I i nes.NOTE: Entry into Condition B for all four ADV lines simultaneously inoperable is not intended for voluntary removal of redundant systems or components from service in lieu of other alternatives that would not result in redundant systems or components being inoperable
.Foraccidentmitigation thesafetyanalysesdonotcreditisolation ofafailedopenADVbyeitherlocalmanualhandwheeloperation orclosureofitsassociated blockvalve.ThesafetyanalysesintheUFSARassumethatplantoperators willusetheADVstocooldownanaffectedunittoSDCSystementryconditions, following accidents accompanied byalossofoffsitepowerand/orclosureoftheMSIVs.Initiation ofoperatoractionistypically assumedtooccur30minutesfollowing theinitiation ofanevent;however,toconservatively boundmaximumpotential doseconsequences forSteamGenerator TubeRupture(SGTR)events,initiation ofthisoperatoractionisassumedtooccurtwominutesfollowing reactortrip.Priortotheoperatoraction,theMainSteamSafetyValves(MSSVs)arecreditedintheanalysestomaintainSGpressureandtemperature neartheMSSVsetpoints
.ThelimitingdesignbasiseventfornitrogensupplycapacityistheRSB5-1naturalcirculation cooldownscenariodescribed above.Thisscenarioincludesaninitialperiodof4hoursathotstandbyconditions followedbynaturalcirculation cooldownfor9.3hoursuntilSDCentryconditions areachieved.EachADVisrequiredtohaveanitrogensupplythatsupportsADVoperation foratotalof13.3hours,Limitingdesignbasisaccidents withrespecttoRCSheatremovalandADVsteamflowcapacityincludethosethatmayrenderoneSGunavailable, withacoincident lossofoffsitepowerandasingleactivecomponent failure(i.e.,mainsteamlinebreaksupstreamoftheMSIVs,andfeedwaterline breaks).(continued)
PALOVERDEUNITS1,2,3B3.7.4-3REVISION58 ADVsB3.7.4BASESAPPLICABLE SAFETYANALYSESThelimitingdesignbasiseventwithrespecttooffsite(continued) radiological consequences isaSGTRwithacoincident lossofoffsitepower,acoincident RCSiodinespike,andasinglefailedopenADVontheaffectedSG(SGTRLOPSF)
.Todetermine boundingradiological consequences, anADVisassumedtostickopenduringoperatoractionthatoccurstwominutesaftertrip,andremainsopenforthedurationofthecooldown.ForthisSGTRLOPSF case,plantoperators willdirectauxiliary feedwater flowtotheaffectedSGaftertheaccidenthasoccurred.ThesteamreleasedthroughtheADVsiscontaminated, however,becauseofprimary-to-secondary leakagethattransports radioisotopes fromtheRCStotheSG.TheADVssatisfyCriterion 3of10CFR50.36(c)(2)(ii)
.LCOFourADVlinesarerequiredtobeOPERABLE, twooneachSGtoensureadesignbasisaccidentthatrendersoneSGunavailable forheatremoval(incombination withacoincident lossofoffsitepowerandasingleactivecomponent failure)wouldnotpreventcontrolroomoperators fromremotelyopeninganADVontheunaffected SG.FailuretomeettheLCOcanresultinaninability tocooltheaffectedunittoSDCSystementryconditions whentheSBCSisunavailable
.AnADVisconsidered OPERABLEwhenitiscapableofproviding acontrolled reliefofthemainsteamflow,andiscapableoffullyopeningandclosingondemand.IInMODES1,2,and3,andinMODE4,whenaSGisbeingAPPLICABILITY relieduponforheatremoval,theADVsarerequiredtobeOPERABLE.InMODES5and6,thereisinsufficient heatavailable toproducesteamthatcouldbereleasedthroughtheADVs,anddesignbasisaccidents suchasmainsteamlinebreaks,feedwater linebreaks,andSGTRsarenotcredibleevents.(continued)
PALOVERDEUNITS1,2,3B3.7.4-4REVISION58 BASESACTIONSA.1Thecondition forthisACTIONismodifiedbyaNotethatstatesseparateCondition entryisallowedforeachSG.Thisisacceptable becauseonlyoneSGisrequiredforRCSheatremovalafteradesignbasisaccident, andbecausethisCondition providestheappropriate RequiredActionandCompletion Timeforoneinoperable ADVlineoneachSG.WithoneADVlineonaSGinoperable, actionmustbetakentorestorethatADVlinetoOPERABLEstatuswithin7daystomeettheLCOforeachSGthathasenteredthisCondition
.The7-dayCompletion Timetakesintoconsideration theredundant capability affordedbytheremaining OPERABLEADVlines,thesafetygradeMSSVs,andthenon-safety gradebackupoftheSBCS.B.1WithtwoormoreADVlinesinoperable withbothADVlinesinoperable ononeormoreSGs,actionmustbetakentorestoreoneADVlineoneachSGtoOPERABLEstatuswithin24hours.The24hourCompletion Timeisreasonable torepairinoperable ADVlines,basedontheavailability oftheSteamBypassControlSystemandMSSVs,andthelowprobability ofaneventoccurring duringthisperiodthatrequirestheADVIines.NOTE:EntryintoCondition BforallfourADVlinessimultaneously inoperable isnotintendedforvoluntary removalofredundant systemsorcomponents fromserviceinlieuofotheralternatives thatwouldnotresultinredundant systemsorcomponents beinginoperable
.(continued)
.(continued)
PALOVERDEUNITS1,2,3B3.7.4-5REVISION58 ADVsB3.7.4BASESACTIONSC.1andC.2(continued)
PALO VERDE UNITS 1,2,3 B 3.7.4-5 REVISION 58 ADVs B 3.7.4 BASES ACTIONS C.1 and C.2 (continued)
IftheADVlinescannotberestoredtoOPERABLEstatuswithintheassociated Completion Time,theunitmustbeplacedinaMODEinwhichtheLCOdoesnotapply.Toachievethisstatus,theunitmustbeplacedinatleastMODE3within6hours,andinMODE4,withoutrelianceonItheSGforheatremoval,within24hours.TheallowedCompletion Timesarereasonable, basedonoperating experience, toreachtherequiredunitconditions fromfullpowerconditions inanorderlymannerandwithoutchallenging unitsystems.SURVEILLANCE SR3.7.4.1REQUIREMENTS Toperformacontrolled cooldownoftheRCS,theADVsmustbeabletobeopenedandthrottled throughtheirfullrange.ThisSRensurestheADVsaretestedthroughafullcontrolcycle.Performance ofinservice testingoruseofanADVduringaunitcooldownmaysatisfythisrequirement
If the ADV lines cannot be restored to OPERABLE status within the associated Completion Time, the unit must be placed in a MODE in which the LCO does not apply.To achieve this status, the unit must be placed in at least MODE 3 within 6 hours , and in MODE 4, without reliance on I the SG for heat removal , within 24 hours.The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.SURVEILLANCE SR 3.7.4.1 REQUIREMENTS To perform a controlled cooldown of the RCS, the ADVs must be able to be opened and throttled through their full range.This SR ensures the ADVs are tested through a full control cycle.Performance of inservice testing or use of an ADV during a unit cooldown may satisfy this requirement
.TheSurveillance Frequency iscontrolled undertheSurveillance Frequency ControlProgram.REFERENCES 1.UFSAR,Section10.3.(continued)
.The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.REFERENCES 1.UFSAR, Section 10.3.(continued)
PALOVERDEUNITS1,2,3B3.7.4-6REVISION58 SDCandCoolantCirculation
PALO VERDE UNITS 1,2,3 B 3.7.4-6 REVISION 58 SDC and Coolant Circulation
-LowWaterLevelB3.9.5B3.9REFUELING OPERATIONS B3,9.5ShutdownCooling(SDC)andCoolantCirculation
-Low Water Level B 3.9.5 B 3.9 REFUELING OPERATIONS B 3 , 9.5 Shutdown Cooling (SDC)and Coolant Circulation
-LowWaterLevelBASESBACKGROUND ThepurposesoftheSDCSysteminMODE6aretoremovedecayheatandsensibleheatfromtheReactorCoolantSystem(RCS),asrequiredbyGDC34,toprovidemixingofboratedcoolant,toprovidesufficient coolantcirculation tominimizetheeffectsofaborondilutionaccident, andtopreventboronstratification (Ref.1).HeatisremovedfromtheRCSbycirculating reactorcoolantthroughtheSDCheatexchanger(s),
-Low Water Level BASES BACKGROUND The purposes of the SDC System in MODE 6 are to remove decay heat and sensible heat from the Reactor Coolant System (RCS), as required by GDC 34, to provide mixing of borated coolant, to provide sufficient coolant circulation to minimize the effects of a boron dilution accident, and to prevent boron stratification (Ref.1).Heat is removed from the RCS by circulating reactor coolant through the SDC heat exchanger(s), where the heat is transferred to the Essential Cooling Water System via the SDC heat exchanger(s)
wheretheheatistransferred totheEssential CoolingWaterSystemviatheSDCheatexchanger(s)
.The coolant is then returned to the RCS via the RCS cold leg(s).Operation of the SDC System for normal cooldown or decay heat removal is manually accomplished from the control room.The heat removal rate is adjusted by controlling the flow of reactor coolant through the SDC heat exchanger(s) and bypassing the heat exchanger(s)
.ThecoolantisthenreturnedtotheRCSviatheRCScoldleg(s).Operation oftheSDCSystemfornormalcooldownordecayheatremovalismanuallyaccomplished fromthecontrolroom.Theheatremovalrateisadjustedbycontrolling theflowofreactorcoolantthroughtheSDCheatexchanger(s) andbypassing theheatexchanger(s)
.Mixing of the reactor coolant is maintained by this continuous circulation of reactor coolant through the SDC System, APPLICABLE If the reactor coolant temperature is not maintained below SAFETY ANALYSES 200°F, boiling of the reactor coolant could result.This could lead to inadequate cooling of the reactor fuel due to the resulting loss of coolant in the reactor vessel.Additionally
.Mixingofthereactorcoolantismaintained bythiscontinuous circulation ofreactorcoolantthroughtheSDCSystem,APPLICABLE Ifthereactorcoolanttemperature isnotmaintained belowSAFETYANALYSES200°F,boilingofthereactorcoolantcouldresult.Thiscouldleadtoinadequate coolingofthereactorfuelduetotheresulting lossofcoolantinthereactorvessel.Additionally
, boiling of the reactor coolant could lead to a reduction in boron concentration in the coolant due to the boron plating out on components near the areas of the boiling activity, and because of the possible addition of water to the reactor vessel with a lower boron concentration than is required to keep the reactor subcritical
,boilingofthereactorcoolantcouldleadtoareduction inboronconcentration inthecoolantduetotheboronplatingoutoncomponents neartheareasoftheboilingactivity, andbecauseofthepossibleadditionofwatertothereactorvesselwithalowerboronconcentration thanisrequiredtokeepthereactorsubcritical
.The loss of reactor coolant and the reduction of boron concentration in the reactor coolant would eventually challenge the integrity of the fuel cladding, which is a fission product barrier.Two trains of the SDC System are required to be OPERABLE , and one train is required to be in operation in MODE 6, with the water level<23 ft above the top of the reactor vessel flange, to prevent this challenge.
.Thelossofreactorcoolantandthereduction ofboronconcentration inthereactorcoolantwouldeventually challenge theintegrity ofthefuelcladding, whichisafissionproductbarrier.TwotrainsoftheSDCSystemarerequiredtobeOPERABLE,andonetrainisrequiredtobeinoperation inMODE6,withthewaterlevel<23ftabovethetopofthereactorvesselflange,topreventthischallenge.
SDC and Coolant Circulation
SDCandCoolantCirculation
-Low Water Level satisfies Criterion 2 of 10 CFR 50.36 (c)(2)(ii)
-LowWaterLevelsatisfies Criterion 2of10CFR50.36(c)(2)(ii)
.(continued)
.(continued)
PALOVERDEUNITS1,2,3B3.9.5-IREVISION0 SDCandCoolantCirculation
PALO VERDE UNITS 1,2,3 B 3.9.5-I REVISION 0 SDC and Cool ant Circulation
-LowWaterLevelB3.9.5BASESLCOInMODE6,withthewaterlevel<23ftabovethetopofthereactorvesselflange,bothSDCloopsmustbeOPERABLE.Additionally, oneloopoftheSDCSystemmustbeinoperation inordertoprovide:a.Removalofdecayheat;b.Mixingofboratedcoolanttominimizethepossibility ofacriticality; andc.Indication ofreactorcoolanttemperature
-Low Water Level B 3.9.5 BASES LCO In MODE 6, with the water level<23 ft above the top of the reactor vessel flange, both SDC loops must be OPERABLE.Additionally, one loop of the SDC System must be in operation in order to provide: a.Removal of decay heat;b.Mixing of borated coolant to minimize the possibility of a criticality; and c.Indication of reactor coolant temperature
.AnOPERABLESDCtrainiscomposedofanOPERABLESDCpump(LPSIorCS)capableofproviding flowtotheSDCheatexchanger forheatremoval.SDCpumpsareOPERABLEiftheyarecapableofbeingpoweredandareabletoprovideflow,ifrequired.NotethattheCSpumpsshallnotbeusedfornormaloperations ifthewaterlevelisatorbelowthetopofthehot-legpipe(103'1")duetoconcernsofpotential airentrainment andgasbindingoftheCSpump(Ref.2).BothSDCpumpsmaybealignedtotheRefueling WaterTank(RWT)tosupportfillingtherefueling cavityorforperformance ofrequiredtesting.TheLCOismodifiedbyaNotethatallowsarequiredoperating SDClooptoberemovedfromserviceforupto1hourineach8hourperiod,providednooperations arepermitted thatwouldcauseareduction oftheRCSboronconcentration
.An OPERABLE SDC train is composed of an OPERABLE SDC pump (LPSI or CS)capable of providing flow to the SDC heat exchanger for heat removal.SDC pumps are OPERABLE if they are capable of being powered and are able to provide flow, if required.Note that the CS pumps shall not be used for normal operations if the water level is at or below the top of the hot-leg pipe (103'1")due to concerns of potential air entrainment and gas binding of the CS pump (Ref.2).Both SDC pumps may be aligned to the Refueling Water Tank (RWT)to support filling the refueling cavity or for performance of required testing.The LCO is modified by a Note that allows a required operating SDC loop to be removed from service for up to 1 hour in each 8 hour period, provided no operations are permitted that would cause a reduction of the RCS boron concentration
.Boronconcentration reduction isprohibited becauseuniformconcentration distribution cannotbeensuredwithoutforcedcirculation
.Boron concentration reduction is prohibited because uniform concentration distribution cannot be ensured without forced circulation
.Thispermitsoperations suchascoremappingoralterations inthevicinityofthereaGtorvesselhotlegnozzles,surveillance testingofECCSpumps,andRCStoSDCisolation valvetesting.Duringthis1hourperiod,decayheatisremovedbynaturalconvection tothelargemassofwaterintherefueling cavity.ThisLCOismodifiedbyaNotethatallowsoneSDClooptobeinoperable foraperiodof2hoursprovidedtheotherloopisOPERABLEandinoperation
.This permits operations such as core mapping or alterations in the vicinity of the reaGtor vessel hot leg nozzles, surveillance testing of ECCS pumps , and RCS to SDC isolation valve testing.During this 1 hour period, decay heat is removed by natural convection to the large mass of water in the refueling cavity.This LCO is modified by a Note that allows one SDC loop to be inoperable for a period of 2 hours provided the other loop is OPERABLE and in operation.Prior to declaring the loop inoperable, consideration should be given to the existing plant configuration
.Priortodeclaring theloopinoperable, consideration shouldbegiventotheexistingplantconfiguration
.This consideration should include that the core time to boil is not short, there is no draining operation to further reduce RCS water level and that the capacity exists to inject borated water into the reactor vessel.This permits surveillance tests to be performed on the non-operating loop during a time when these tests are safe and possible.(continued)
.Thisconsideration shouldincludethatthecoretimetoboilisnotshort,thereisnodrainingoperation tofurtherreduceRCSwaterlevelandthatthecapacityexiststoinjectboratedwaterintothereactorvessel.Thispermitssurveillance teststobeperformed onthenon-operating loopduringatimewhenthesetestsaresafeandpossible.(continued)
PALO VERDE UNITS 1,2,3 B 3.9.5-2 REVISION 58 SDC and Cool ant Circulation
PALOVERDEUNITS1,2,3B3.9.5-2REVISION58 SDCandCoolantCirculation
-Low Water Level B 3.9.5 BASES APPLICABILITY Two SDC loops are required to be OPERABLE, and one SDC loop must be in operation in MODE 6, with the water level<23 ft above the top of the reactor vessel flange, to provide decay heat removal.Requirements for the SDC System in other MODES are covered by LCOs in Section 3.4 , Reactor Coolant System.MODE 6 requirements, with a water level_23 ft above the reactor vessel flange, are covered in LCO 3.9.4,"Shutdown Cooling and Coolant Circulation
-LowWaterLevelB3.9.5BASESAPPLICABILITY TwoSDCloopsarerequiredtobeOPERABLE, andoneSDCloopmustbeinoperation inMODE6,withthewaterlevel<23ftabovethetopofthereactorvesselflange,toprovidedecayheatremoval.Requirements fortheSDCSysteminotherMODESarecoveredbyLCOsinSection3.4,ReactorCoolantSystem.MODE6requirements, withawaterlevel_23ftabovethereactorvesselflange,arecoveredinLCO3.9.4,"Shutdown CoolingandCoolantCirculation
-High Water Level." ACTIONS A.1 and A.2 If one SDC loop is inoperable, action shall be immediately initiated and continued until the SDC loop is restored to OPERABLE status and to operation, or until_>23 ft of water level is established above the reactor vessel flange.When the water level is established at>23 ft above the reactor vessel flange, the Applicability will change to that of LCO 3.9.4,"Shutdown Cooling and Coolant Circulation
-HighWaterLevel."ACTIONSA.1andA.2IfoneSDCloopisinoperable, actionshallbeimmediately initiated andcontinued untiltheSDCloopisrestoredtoOPERABLEstatusandtooperation, oruntil_>23ftofwaterlevelisestablished abovethereactorvesselflange.Whenthewaterlevelisestablished at>23ftabovethereactorvesselflange,theApplicability willchangetothatofLCO3.9.4,"Shutdown CoolingandCoolantCirculation
-High Water Level ," and only one SDC loop is required to be OPERABLE and in operation.An immediate Completion Time is necessary for an operator to initiate corrective actions.B.1 If no SDC loop is in operation or no SDC loops are OPERABLE, there will be no forced circulation to provide mixing to I establish uniform boron concentrations
-HighWaterLevel,"andonlyoneSDCloopisrequiredtobeOPERABLEandinoperation
.Reduced boron concentrations can occur by the addition of water with lower boron concentration than that contained in the RCS.Therefore, actions that reduce boron concentration shall be suspended immediately
.Animmediate Completion Timeisnecessary foranoperatortoinitiatecorrective actions.B.1IfnoSDCloopisinoperation ornoSDCloopsareOPERABLE, therewillbenoforcedcirculation toprovidemixingtoIestablish uniformboronconcentrations
.B.2 If no SDC loop is in operation or no SDC loops are OPERABLE, action shall be initiated immediately and continued without interruption to restore one SDC loop to OPERABLE status and operation.Since the unit is in Conditions A and B concurrently, the restoration of two OPERABLE SDC loops and one operating SDC loop should be accomplished expeditiously
.Reducedboronconcentrations canoccurbytheadditionofwaterwithlowerboronconcentration thanthatcontained intheRCS.Therefore, actionsthatreduceboronconcentration shallbesuspended immediately
.B.3 If no SDC loop is in operation or no SDC loops are OPERABLE, all containment penetrations providing direct access from (continued)
.B.2IfnoSDCloopisinoperation ornoSDCloopsareOPERABLE, actionshallbeinitiated immediately andcontinued withoutinterruption torestoreoneSDClooptoOPERABLEstatusandoperation
PALO VERDE UNITS 1,2,3 B 3.9.5-3 REVISION 58 SDC and Coolant Circulation
.SincetheunitisinConditions AandBconcurrently, therestoration oftwoOPERABLESDCloopsandoneoperating SDCloopshouldbeaccomplished expeditiously
-Low Water Level B 3.9.5 BASES ACTIONS B.3 (Continued) the containment atmosphere to the outside atmosphere must be closed within 4 hours.With the SDC loop requirements not met, the potential exists for the coolant to boil and release radioactive gas to the containment atmosphere
.B.3IfnoSDCloopisinoperation ornoSDCloopsareOPERABLE, allcontainment penetrations providing directaccessfrom(continued)
.Closing containment penetrations that are open to the outside atmosphere ensures that dose limits are not exceeded.The Completion Time of 4 hours is reasonable, based on the low probability of the coolant boiling in that time.SURVEILLANCE SR 3.9.5.1 REQUIREMENTS This Survei I Iance demonstrates that one SDC loop i s operating and circulating reactor coolant at a flowrate of greater than or equal to 3780 gpm.The flow rate is determined by the flow rate necessary to provide sufficient decay heat removal capability and to prevent thermal and boron stratification in the core.In addition, this Surveillance demonstrates that the other SDC loop is OPERABLE.In addition, during operation of the SDC loop with the water level in the vicinity of the reactor vessel nozzles, the SDC loop flow rate determination must also consider the SDC pump suction requirements
PALOVERDEUNITS1,2,3B3.9.5-3REVISION58 SDCandCoolantCirculation
.The Surveillance Frequency is control led under the Surveillance Frequency Control Program.SR 3.9.5.2 Verification that the required pump that is not in operation is OPERABLE ensures that an additional SDC pump can be placed in operation, if needed , to maintain decay heat removal and reactor coolant circulation
-LowWaterLevelB3.9.5BASESACTIONSB.3(Continued) thecontainment atmosphere totheoutsideatmosphere mustbeclosedwithin4hours.WiththeSDClooprequirements notmet,thepotential existsforthecoolanttoboilandreleaseradioactive gastothecontainment atmosphere
.Verification is performed by verifying proper breaker alignment and power available to the required pump.The Surveillance Frequency i s control led under the Survei I Iance Frequency Control Program.REFERENCES 1.UFSAR, Section 5.4.7.2.PVNGS Calculation 13-MC-SI-0250, Appendix C.PALO VERDE UNITS 1,2,3 B 3.9.5-4 REVISION 58}}
.Closingcontainment penetrations thatareopentotheoutsideatmosphere ensuresthatdoselimitsarenotexceeded.TheCompletion Timeof4hoursisreasonable, basedonthelowprobability ofthecoolantboilinginthattime.SURVEILLANCE SR3.9.5.1REQUIREMENTS ThisSurveiIIancedemonstrates thatoneSDCloopisoperating andcirculating reactorcoolantataflowrateofgreaterthanorequalto3780gpm.Theflowrateisdetermined bytheflowratenecessary toprovidesufficient decayheatremovalcapability andtopreventthermalandboronstratification inthecore.Inaddition, thisSurveillance demonstrates thattheotherSDCloopisOPERABLE.Inaddition, duringoperation oftheSDCloopwiththewaterlevelinthevicinityofthereactorvesselnozzles,theSDCloopflowratedetermination mustalsoconsidertheSDCpumpsuctionrequirements
.TheSurveillance Frequency iscontrolledundertheSurveillance Frequency ControlProgram.SR3.9.5.2Verification thattherequiredpumpthatisnotinoperation isOPERABLEensuresthatanadditional SDCpumpcanbeplacedinoperation, ifneeded,tomaintaindecayheatremovalandreactorcoolantcirculation
.Verification isperformed byverifying properbreakeralignment andpoweravailable totherequiredpump.TheSurveillance Frequency iscontrolledundertheSurveiIIanceFrequency ControlProgram.REFERENCES 1.UFSAR,Section5.4.7.2.PVNGSCalculation 13-MC-SI-0250, AppendixC.PALOVERDEUNITS1,2,3B3.9.5-4REVISION58}}

Revision as of 01:44, 14 July 2018

Palo Verde, Units 1, 2, and 3, Enclosure 1 - Technical Specifications Bases, Revision 58
ML13217A054
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 07/03/2013
From: Stephenson C J
Arizona Public Service Co
To:
Office of Nuclear Reactor Regulation
References
102-06731-TNW/RKR/CJS
Download: ML13217A054 (26)
v • d • e


Text

PVNGS Technical Specification Bases (TS Bases)Revision 58 Replacement Pages and Insertion Instructions The following LDC R s are included in this change: LDCR 11-B002 reflects changes approved by NRC License Amendment 191, dated April 11, 2013, related to TS Bases Section 3.7.4, Atmospheric Dump Valves (ADVs), that requires four ADV lines be OPERABLE when in Modes 1,2, 3, and in Mode 4 when the steam generators are being used for heat removal.Related LDCR 07-R002 removes similar requirements for ADV operability that had been included in the Technical Requirements Manual (TRM)as an interim action, until the license amendment was approved.LDCR 12-B006 clarified TS Bases Sections 3.4.8, RCS Loops-MODE 5, Loops Not Fill e d , and 3.9.5, SDC and Coolant Circulation

-Low Water L e vel , to indicate that Containment Spray (CS)pumps are not to be used for normal operations if the water level is at or below the top of the hot-leg pipe (103'-1")due to concerns of potential air entrainment and gas binding of the CS pump.The LDCR also updated the Reference section of the Bases for each specification.

Instructions Remove Paqe: Insert New Paqe: Cover Page Cover Page List of Effective Pages List of Effective Pages 1/2 through 7/8 1/2 through 9/Blank B 3.4.8-1 B 3.4.8-2 B 3.4.8-1/B 3.4.8-2 B 3.4.8-3 Blank B 3.4.8-3/B 3.4.8-4 B 3.7.4-1 B 3.7.4-2 B 3.7.4-1/B 3.7.4-2 through through B 3.7.4-5 Blank B 3.7.4-5/B 3.7.4-6 B 3.9.5-1 B 3.9.5-2 B 3.9.5-1/B 3.9.5-2 B 3.9.5-3 B 3.9.5-4 B 3.9.5-3/B 3.9.5-4 PVNGS Palo Verde Nuclear Generating Station Units 1, 2, and 3 Technical Sp"" ec l ficatlon Bases Revision 58 July 03, 2 0 13-_-_.-¢'e_'_'enson o,g,t0,,.s,goe0byS,o..

......Cor,_,zo_,, I DN: cn=Stephenson, Carl J(ZO5778)Reason: I attest to the accuracy and integrity of Carl J(Z05778)th,,_.......Date: 20!3.06.28 09:16:1 7-0 7'00' TECHNICAL SPECIFICATION BASES LIST OF EFFECTIVE PAGES Page Rev.Page Rev No.No.No.No.B 2 1 i-i 0 B 3 1 3-2 0 B 2 1 i-2 0 B 3 1 3-3 0 B 2 1 i-3 37 B 3 1 3-4 0 B 2 1 i-4 21 B 3 1 3-5 0 B 2 1 i-5 54 B 3 1 3-6 56 B 2 1 2-I 0 B 3 1 4-i 0 B 2 1 2-2 31 B 3 1 4-2 31 B 2 1 2-3 0 B 3 1 4-3 0 B 2 1 2-4 54 B 3 1 4-4 0 B 3 0-i 49 B 3 1 4-5 0 B 3 0-2 0 B 3 1 5-i 0 B 3 0-3 0 B 3 1 5-2 52 B 3 0-4 0 B 3 1 5-3 52 B 3 0-5 42 B 3 1 5-4 52 B 3 0-6 48 B 3 1 5-5 52 B 3 0-7 48 B 3 1 5-6 52 B 3 0-8 42 B 3 1 5-7 52 B 3 0-9 42 B 3 1 5-8 52 B 3 0-i0 42 B 3 1 5-9 52 B 3 0-ii 42 B 3 1 5-10 56 B 3 0-12 42 B 3 1 5-11 56 B 3 0-13 42 B 3 1 5-12 56 B 3 0-14 49 B 3 1 6-i 0 B 3 0-15 50 B 3 1 6-2 46 B 3 0-16 50 B 3 1 6-3 42 B 3 0-17 50 B 3 1 6-4 42 B 3 0-18 49 B 3 1 6-5 56 B 3 0-19 49 B 3 1 6-6 46 B 3 0-20 49 B 3 1 7-i 57 B 3 0-21 49 B 3 1 7-2 0 B 3 0-22 49 B 3 1 7-3 53 B 3 1 i-I 28 B 3 1 7-4 48 B 3 1 i-2 0 B 3 1 7-5 25 B 3 1 i-3 43 B 3 1 7-6 0 B 3 1 i-4 43 B 3 1 7-7 0 B 3 1 I-5 27 B 3 1 7-8 56 B 3 1 i-6 56 B 3 1 7-9 56 B 3 1 2-I 28 B 3 1 8-i 52 B 3 1 2-2 0 B 3 1 8-2 52 B 3 1 2-3 43 B 3 1 8-3 52 B 3 1 2-4 28 B 3 1 8-4 52 B 3 1 2-5 0 B 3 1 8-5 56 B 3 1 2-6 43 B 3 1 9-i 0 B 3 1 2-7 12 B 3 1 9-2 0 B 3 1 2-8 47 B 3 1 9-3 0 B 3 1 2-9 56 B 3 1 9-4 0 B 3 1 3-I 0 B 3 1 9-5 56 PALO VERDE UNITS i, 2, AND 3 1 Revision 58 July 03, 2013 TECHNICAL SPECIFICATION BASES LIST OF EFFECTIVE PAGES Page Rev.Page Rev No.No.No.No.B 3 1 9-6 56 B 3.2 5-i 52 B 3 1 i0-i 0 B 3.2 5-2 i0 B 3 i i0-2 53 B 3.2 5-3 0 B 3 1 i0-3 0 B 3.2 5-4 52 B 3 1 i0-4 37 B 3.2 5-5 0 B 3 1 i0-5 56 B 3.2 5-6 56 B 3 1 i0-6 0 B 3.2 5-7 0 B 3 1 ii-i 0 B 3.3.1-i 35 B 3 1 ii-2 53 B 3.3.1-2 53 B 3 1 Ii-3 0 B 3 3.1-3 53 B 3 1 ii-4 53 B 3 3.1-4 53 B 3 1 ii-5 0 B 3 3 i-5 53 B 3 2 i-i 53 B 3 3 i-6 53 B 3 2 i-2 i0 B 3 3 i-7 53 B 3 2 i-3 53 B 3 3 i-8 53 B 3 2 i-4 0 B 3 3 i-9 53 B 3 2 i-5 0 B 3 3 i-i0 53 B 3 2 I-6 0 B 3 3 i-ii 53 B 3 2 i-7 56 B 3 3 1-12 53 B 3 2 i-8 56 B 3 3 1-13 53 B 3 2 2-i 52 B 3 3 1-14 53 B 3 2 2-2 i0 B 3 3 1-15 53 B 3 2 2-3 0 B 3 3 1-16 53 B 3 2.2-4 52 B 3 3 1-17 53 B 3 2.2-5 1 B 3 3 1-18 53 B 3 2.2-6 0 B 3 3 1-19 53 B 3 2.2-7 56 B 3 3 1-20 53 B 3 2.3-i 52 B 3 3 1-21 53 B 3 2.3-2 i0 B 3 3 1-22 53 B 3 2 3-3 0 B 3 3 1-23 53 B 3 2 3-4 52 B 3 3 1-24 53 B 3 2 3-5 0 B 3 3 1-25 53 B 3 2 3-6 0 B 3 3 1-26 53 B 3 2 3-7 0 B 3 3 1-27 53 B 3.2 3-8 56 B 3 3 1-28 53 B 3.2 3-9 56 B 3 3 1-29 53 B 3.2 3-i0 0 B 3 3 1-30 53 B 3.2 4-i 52 B 3 3 1-31 53 B 3.2 4-2 i0 B 3 3 1-32 53 B 3 2 4-3 0 B 3 3 1-33 53 B 3 2 4-4 52 B 3 3 1-34 53 B 3 2 4-5 53 B 3.3 1-35 53 B 3 2 4-6 53 B 3.3 1-36 53 B 3 2 4-7 53 B 3.3 1-37 53 B 3 2 4-8 56 B 3.3 1-38 53 B 3 2 4-9 56 B 3.3 1-39 53 B 3 2 4-I0 31 B 3.3 1-40 56 PALO VERDE UNITS i, 2, AND 3 2 Revision 58 July 03, 2013 TECHNICAL SPECIFICATION BASES LIST OF EFFECTIVE PAGES Page Rev.Page Rev No.No.No.No.B 3 3 1-41 56 B 3 3 4-7 0 B 3 3 1-42 56 B 3 3 4-8 0 B 3 3 1-43 56 B 3 3 4-9 0 B 3 3 1-44 56 B 3 3 4-I0 0 B 3 3 1-45 53 B 3 3 4-Ii 0 B 3 3 1-46 56 B 3 3 4-12 0 B 3 3]-47 57 B 3 3 4-13 56 B 3 3]-48 56 B 3 3 4-14 56 B 3 3 1-49 56 B 3 3 4-15 56 B 3 3 1-50 53 B 3 3 5-I 0 B 3 3 1-51 53 B 3 3 5-2 0 B 3 3 2-i 50 B 3 3 5-3 0 B 3 3 2-2 0 B 3 3 5-4 35 B 3 3 2-3 1 B 3 3 5-5 0 B 3 3 2-4 35 B 3 3 5-6 0 B 3 3 2-5 35 B 3 3 5-7 0 B 3 3 2-6 51 B 3 3 5-8 31 B 3 3 2-7 35 B 3 3 5-9 54 B 3 3 2-8 35 B 3 3 5-I0 54 B 3 3 2-9 50 B 3 3 5-ii 54 B 3 3 2-i0 38 B 3 3 5-12 1 B 3 3 2-ii 42 B 3 3 5-13 0 B 3 3 2-12 42 B 3 3 5-14 0 B 3 3 2-13 56 B 3 3 5-15 35 B 3 3 2-14 56 B 3 3 5-16 51 B 3 3 2-15 56 B 3 3 5-17 35 B 3 3 2-16 56 B 3 3 5-18 54 B 3 3 2-17 56 B 3 3 5-19 54 B 3 3 2-18 35 B 3 3 5-20 54 B 3 3 3-i 53 B 3 3 5-21 35 B 3 3 3-2 53 B 3 3 5-22 35 B 3 3 3-3 53 B 3 3 5-23 52 B 3 3 3-4 53 B 3 3 5-24 38 B 3 3 3-5 53 B 3 3 5-25 42 B 3 3 3-6 53 B 3 3 5-26 56 B 3 3 3-7 53 B 3 3 5-27 56 B 3 3 3-8 53 B 3 3 5-28 56 B 3 3 3-9 53 B 3 3 5-29 56 B 3 3 3-i0 56 B 3 3 5-30 35 B 3 3 3-Ii 56 B 3 3 6-I 0 B 3 3 3-12 56 B 3 3 6-2 0 B 3 3 4-i 0 B 3 3 6-3 0 B 3 3 4-2 0 B 3 3 6-4 0 B 3 3 4-3 0 B 3 3 6-5 31 B 3 3 4-4 0 B 3 3 6-6 0 B 3 3 4-5 0 B 3 3 6-7 27 B 3 3 4-6 31 B 3 3 6-8 27 PALO VERDE UNITS i, 2, AND 3 3 Revision 58 July 03, 2013 TECHNICAL SPECIFICATION BASES LIST OF EFFECTIVE PAGES Page Rev.Page Rev No.No.No.No.B 3.3.6-9 0 B 3 3 I0-i0 57 B 3.3.6-10 0 B 3 3 i0-ii 50 B 3.3.6-11 0 B 3 3 10-12 50 B 3.3.6-12 0 B 3 3 10-13 50 B 3.3.6-13 0 B 3 3 10-14 50 B 3.3.6-14 0 B 3 3 10-15 50 B 3 3.6-15 0 B 3 3 10-16 50 B 3 3.6-16 0 B 3 3 10-17 50 B 3 3 6-17 27 B 3 3 10-18 50 B 3 3 6-18 0 B 3.3 10-19 56 B 3 3 6-19 56 B 3.3.10-20 56 B 3 3 6-20 0 B 3.3.10-21 50 B 3 3 6-21 56 B 3.3.10-22 32 B 3 3 6-22 46 B 3 3.11-I 0 B 3 3 7-i 2 B 3 3 ii-2 2 B 3 3 7-2 2 B 3 3 ii-3 2 B 3 3 7-3 0 B 3 3 ii-4 42 B 3 3 7-4 0 B 3 3 ii-5 42 B 3 3 7-5 0 B 3 3 Ii-6 56 B 3 3 7-6 42 B 3 3 ii-7 56 B 3 3 7-7 0 B 3 3 12-i 15 B 3 3.7-8 56 B 3 3 12-2 50 B 3 3.7-9 56 B 3 3 12-3 37 B 3 3 8-i 0 B 3 3 12-4 37 B 3 3 8-2 44 B 3 3 12-5 56 B 3 3 8-3 0 B 3 3 12-6 56 B 3.3 8-4 0 B 3 4 i-i i0 B 3.3 8-5 0 B 3 4 i-2 53 B 3.3 8-6 56 B 3 4 i-3 0 B 3 3 8-7 56 B 3 4 i-4 0 B 3 3 8-8 56 B 3 4 i-5 56 B 3 3 9-i 48 B 3.4.2-I 7 B 3 3 9-2 48 B 3.4.2-2 57 B 3 3 9-3 55 B 3.4 3-i 52 B 3 3 9-4 55 B 3.4 3-2 52 B 3 3 9-5 56 B 3.4 3-3 0 B 3 3 9-6 56 B 3.4 3-4 52 B 3 3 9-7 56 B 3 4 3-5 52 B 3 3 i0-i 0 B 3 4 3-6 0 B 3 3 i0-2 0 B 3 4 3-7 56 B 3.3.10-3 0 B 3 4 3-8 52 B 3.3.10-4 0 B 3 4 4-i 0 B 3.3.10-5 18 B 3 4 4-2 50 B 3.3.10-6 0 B 3 4 4-3 7 B 3.3.10-7 0 B 3 4 4-4 56 B 3.3.10-8 14 B 3.4 5-i 0 B 3.3.10-9 14 B 3.4 5-2 38 PA L O VERDE UNITS i, 2, AND 3 4 Revision 58 July 03, 2013 TECHNICAL SPECIFICATION BASES LIST OF EFFECTIVE PAGES Page Rev.Page Rev No.No.No.No.B 3 4 5-3 38 B 3 4 13-8 52 B 3 4 5-4 56 B 3 4 13-9 56 B 3 4 5-5 56 B 3 4 13-I0 56 B 3 4 6-i 0 B 3 4 13-ii 55 B 3 4 6-2 6 B 3 4 14-i 0 B 3 4 6-3 52 B 3 4 14-2 34 B 3 4 6-4 6 B 3 4 14-3 34 B 3.4 6-5 56 B 3 4 14-4 38 B 3.4 7-i 0 B 3 4 14-5 38 B 3.4 7-2 6 B 3 4 14-6 38 B 3.4 7-3 52 B 3 4 14-7 56 B 3.4 7-4 54 B.3 4 14-8 56 B 3.4 7-5 0 B 3 4 15-i 0 B 3.4 7-6 56 B 3 4 15-2 48 B 3.4 7-7 52 B 3 4 15-3 0 B 3.4 8-i 0 B 3 4 15-4 0 B 3.4 8-2 58 B 3 4 15-5 56 B 3.4 8-3 58 B 3 4 15-6 56 B 3.4 8-4 58 B 3 4 15-7 54 B 3.4 9-i 41 B 3 4 16-i 2 B 3.4 9-2 31 B 3 4 16-2 i0 B 3.4 9-3 41 B 3 4 16-3 0 B 3.4 9-4 41 B 3 4 16-4 42 B 3.4 9-5 56 B 3 4 16-5 56 B 3.4 9-6 56 B 3 4 16-6 56 B 3.4 i0-I 53 B 3 4 17-i 0 B 3.4 I0-2 7 B 3 4 17-2 27 B 3.4 i0-3 0 B 3 4 17-3 42 B 3 4 i0-4 54 B 3 4 17-4 42 B 3 4 Ii-i 0 B 3 4 17-5 57 B 3 4 ii-2 53 B 3 4 17-6 56 B 3 4 ii-3 0 B 3 4 18-i 38 B 3 4 11-4 52 B 3 4 18-2 40 B 3 4 11-5 56 B 3.4 18-3 38 B 3 4 11-6 54 B 3 4 18-4 38 B 3 4 12-i 1 B 3 4 18-5 38 B 3 4 12-2 34 B 3 4 18-6 38 B 3 4 12-3 48 B 3 4 18-7 38 B 3 4 12-4 56 B 3 4 18-8 38 B 3 4 12-5 31 B 3 5 i-i 0 B 3 4 13-i 0 B 3 5 i-2 53 B 3 4 13-2 55 B 3 5 i-3 7 B 3 4 13-3 55 B 3 5 i-4 0 B 3 4 13-4 52 B 3 5 i-5 0 B 3 4 13-5 55 B 3 5 i-6 0 B 3 4 13-6 55 B 3 5 i-7 1 B 3 4 13-7 52 B 3 5 I-8 1 PALO VERDE UNITS i, 2, AND 3 5 Revision 58 July 03, 2013 TECHNICAL SPECIFICATION BASES LIST OF EFFECTIVE PAGES Page Rev.Page Rev No.No.No.No.B 3.5.1-9 57 B 3 6 2-4 0 B 3 5.1-i0 56 B 3 6 2-5 0 B 3 5.2-i 0 B 3 6 2-6 0 B 3 5.2-2 53 B 3 6 2-7 0 B 3 5.2-3 53 B 3 6 2-8 57 B 3 5.2-4 0 B 3 6 3-I 36 B 3 5.2-5 0 B 3 6 3-2 43 B 3 5.2-6 0 B 3 6 3-3 49 B 3 5.2-7 1 B 3 6 3-4 43 B 3 5.2-8 22 B 3 6 3-5 43 B 3 5.2-9 57 B 3 6 3-6 43 B 3 5.2-i0 56 B 3 6 3-7 43 B 3 5 3-i 0 B 3 6 3-8 43 B 3 5 3-2 48 B 3 6 3-9 43 B 3 5 3-3 0 B 3 6 3-i0 43 B 3 5 3-4 0 B 3 6 3-ii 43 B 3 5 3-5 0 B 3 6.3-12 43 B 3 5 3-6 2 B 3 6.3-13 43 B 3 5 3-7 2 B 3 6.3-14 43 B 3.5 3-8 56 B 3 6.3-15 43 B 3.5 3-9 56 B 3 6.3-16 56 B 3.5 3-i0 56 B 3 6.3-17 56 B 3.5 4-i 15 B 3 6.3-18 56 B 3.5 4-2 0 B 3 6.3-19 56 B 3.5 4-3 42 B 3 6.4-i 53 B 3.5 5-i 54 B 3 6.4-2 38 B 3.5 5-2 54 B 3 6.4-3 56 B 3.5 5-3 55 B 3 6.5-i 0 B 3.5 5-4 54 B 3 6.5-2 1 B 3.5 5-5 51 B 3 6.5-3 56 B 3 5 5-6 51 B 3 6 5-4 0 B 3 5 5-7 51 B 3 6 6-i 0 B 3 5 5-8 56 B 3 6 6-2 0 B 3 5 5-9 56 B 3 6 6-3 53 B 3 5 6-i 0 B 3 6 6-4 7 B 3 5 6-2 1 B 3 6 6-5 1 B 3 5 6-3 0 B 3 6 6-6 56 B 3 5 6-4 56 B 3 6 6-7 56 B 3 5 6-5 56 B 3 6 6-8 56 B 3 6 i-i 0 B 3 6 6-9 54 B 3 6 I-2 53 B 3.7 i-i 50 B 3 6 I-3 0 B 3.7 i-2 50 B 3 6 i-4 29 B 3.7 I-3 34 B 3 6 i-5 29 B 3.7 i-4 34 B 3 6 2-i 45 B 3.7 i-5 54 B 3 6 2-2 53 B 3.7 i-6 54 B 3 6 2-3 0 B 3.7 2-i 40 PALO VERDE UNITS i, 2, AND 3 6 Revision 58 July 03, 2013 TECHNICAL SPECIFICATION BASES LIST OF EFFECTIVE PAGES Page Rev.Page Rev No.No.No.No.B 3.7 2-2 42 B 3 7 I0-2 1 B 3 7 2-3 40 B 3 7 i0-3 1 B 3 7 2-4 40 B 3 7 i0-4 56 B 3 7 2-5 40 B 3 7 ii-i 50 B 3 7 2-6 40 B 3 7 ii-2 50 B 3 7 2-7 40 B 3 7 ii-3 51 B 3 7 2-8 54 B 3 7 ii-4 55 B 3 7 2-9 54 B 3 7 ii-5 50 B 3.7 3-i 1 B 3 7 ii-6 55 B 3.7 3-2 1 B 3 7 ii-7 57 B 3.7 3-3 37 B 3 7 ii-8 56 B 3.7 3-4 0 B 3 7 ii-9 50 B 3 7 3-5 54 B 3 7 12-i 1 B 3 7 4-i 58 B 3 7 12-2 21 B 3 7 4-2 58 B 3 7 12-3 55 B 3 7 4-3 58 B 3 7 12-4 56 B 3 7 4-4 58 B 3 7 13-i 0 B 3 7 4-5 58 B 3 7 13-2 0 B 3.7 4-6 58 B 3 7 13-3 0 B 3.7 5-i 0 B 3 7 13-4 57 B 3.7 5-2 0 B 3 7 13-5 56 B 3.7 5-3 40 B 3 7 14-i 0 B 3.7 5-4 27 B 3 7 14-2 21 B 3.7 5-5 42 B 3 7 14-3 56 B 3.7 5-6 42 B 3 7 15-I 3 B 3 7 5-7 9 B 3 7 15-2 56 B 3 7 5-8 56 B 3 7 16-i 7 B 3 7 5-9 56 B 3 7 16-2 0 B 3 7 5-i0 56 B 3.7 16-3 56 B 3 7 5-ii 54 B 3.7 16-4 0 B 3 7 6-i 54 B 3.7 17-i 52 B 3 7 6-2 54 B 3.7 17-2 3 B 3 7 6-3 55 B 3.7 17-3 3 B 3 7 6-4 56 B 3.7 17-4 3 B 3 7 7-i 0 B 3.7 17-5 3 B 3 7 7-2 1 B 3.7 17-6 52 B 3 7 7-3 1 B 3 8 I-I 35 B 3 7 7-4 56 B 3 8 I-2 2 B 3 7 7-5 56 B 3 8 I-3 34 B 3 7 8-i 1 B 3 8 i-4 34 B 3 7 8-2 1 B 3 8 i-5 20 B 3 7 8-3 1 B 3 8 I-6 57 B 3 7 8-4 56 B 3 8 i-7 42 B 3 7 9-I 0 B 3 8 I-8 50 B 3 7 9-2 44 B 3 8 i-9 42 B 3 7 9-3 56 B 3 8 i-i0 43 B 3 7 i0-i i0 B 3 8 i-ii 50 PALO VERDE UNITS i, 2, AND 3 7 Revision 58 July 03, 2013 TECHNICAL SPECIFICATION BASES LIST OF EFFECTIVE PAGES Page Rev.Page Rev No.No.No.No.B 3.8 1-12 48 B 3 8 3-5 54 B 3 8 1-13 48 B 3 8 3-6 56 B 3 8 1-14 48 B 3 8 3-7 56 B 3 8 1-15 48 B 3 8 3-8 41 B 3 8 1-16 41 B 3 8 3-9 56 B 3 8 1-17 41 B 3 8 3-i0 54 B 3 8 1-18 41 B 3 8 4-i 0 B 3 8 1-19 41 B 3 8 4-2 37 B 3 8 1-20 41 B 3 8 4-3 0 B 3 8 1-21 41 B 3 8 4-4 2 B 3 8 1-22 41 B 3 8.4-5 2 B 3 8 1-23 57 B 3 8.4-6 56 B 3 8 1-24 50 B 3 8.4-7 56 B 3 8 1-25 56 B 3 8.4-8 56 B 3.8 1-26 56 B 3 8.4-9 56 B 3.8 1-27 56 B 3 8.4-i0 56 B 3.8 1-28 56 B 3 8.4-ii 48 B 3.8 1-29 53 B 3 8.5-i 1 B 3.8 1-30 56 B 3 8.5-2 1 B 3.8 1-31 50 B 3 8.5-3 21 B 3.8 1-32 56 B 3 8.5-4 21 B 3 8 1-33 56 B 3 8.5-5 2 B 3 8 1-34 56 B 3 8.5-6 2 B 3 8 1-35 50 B 3 8 6-i 0 B 3 8 1-36 56 B 3 8 6-2 0 B 3 8 1-37 45 B 3 8 6-3 56 B 3 8 1-38 56 B 3 8 6-4 56 B 3 8 1-39 56 B 3 8 6-5 37 B 3 8 1-40 56 B 3 8 6-6 37 B 3 8 1-41 56 B 3 8 6-7 48 B 3 8 1-42 56 B 3 8 7-i 48 B 3 8 1-43 56 B 3 8 7-2 48 B 3 8 1-44 56 B 3 8 7-3 53 B 3 8 1-45 56 B 3.8 7-4 53 B.3 8 1-46 56 B 3.8 7-5 56 B.3 8 1-47 45 B 3.8 8-i 1 B.3 8 1-48 53 B 3.8 8-2 1 B 3 8 2-i 0 B 3.8 8-3 21 B 3 8 2-2 0 B 3.8 8-4 56 B 3 8 2-3 0 B 3.8 8-5 56 B 3 8 2-4 21 B 3 8 9-i 51 B 3 8 2-5 21 B 3 8 9-2 0 B 3 8 2-6 0 B 3 8 9-3 51 B 3 8 3-i 0 B 3 8 9-4 0 B 3 8 3-2 0 B 3 8 9-5 0 B 3 8 3-3 50 B 3 8 9-6 0 B 3 8 3-4 0 B 3 8 9-7 0 PALO VERDE UNITS i, 2, AND 3 8 Revision 58 July 03, 2013 TECHNICAL SPECIFICATION BASES LIST OF EFFECTIVE PAGES Page Rev.Page Rev No.No.No.No.B 3 8 9-8 0 B 3 8 9-9 0 B 3 8 9-10 56 B 3 8 9-11 51 B 3 8 i0-I 0 B 3 8 10-2 21 B 3 8 10-3 48 B 3 8 10-4 56 B 3 9 I-i 34 Corrected B3 91-2 0 B 3 9 i-3 0 B 3 9 1-4 56 B 3 9 2-1 48 B 3 9 2-2 15 B 3 9 2-3 56 B 3 9 2-4 56 B 3 9 3-1 18 B 3 93-2 19 B 3 9 3-3 27 B 3 93-4 19 B 3 9 3-5 56 B.3 9 3-6 56 B 3 9 4-i 0 B 3 9 4-2 54 B3 94-3 0 B 3 94-4 56 B3 95-i 0 B 3 9 5-2 58 B 3 9 5-3 58 B 3 9 5-4 58 B 3 9 6-i 0 B3 96-2 0 B 3 9 6-3 56 B 3 9 7-i 0 B3 97-2 0 B 3 9 7-3 56 PALO VERDE UNITS I, 2, AND 3 9 Revision 58 July 03, 2013 This page intentionally blank RCS Loops-MODE 5, Loops Not Filled B 3.4.8 B 3.4 REACTOR COOLANT SYSTEM (RCS)B 3.4.8 RCS Loops-MODE 5, Loops Not Filled BASES BACKGROUND In MODE 5 with the RCS loops not filled, the primary function of the reactor coolant is the removal of decay heat and transfer of this heat to the Shutdown Cooling (SDC)heat exchangers

.The Steam Generators (SGs)are not available as a heat sink when the loops are not filled.The secondary function of the reactor coolant is to act as a carrier for the soluble neutron poison, boric acid.In MODE 5 with loops not filled, only the SDC System can be used for coolant circulation

.The number of trains in operation can vary to suit the operational needs.The intent of this LCO is to provide forced flow from at least one SDC train for decay heat removal and transport and to require that two paths be available to provide redundancy for heat removal.APPLICABLE In MODE 5, RCS circulation is considered in determining SAFETY ANALYSES the time available for mitigation of the accidental boron dilution event.The SDC trains provide this circulation

.The flow provided by one SDC train is adequate for decay heat removal and for boron mixing.RCS loops-MODE 5 (loops not filled)have been identified in 10 CFR 50.36 (c)(2)(ii) as important contributors to risk reduction.LCO The purpose of this LCO is to require a minimum of two SDC trains be OPERABLE and one of these trains be in operation.An OPERABLE train is one that is capable of transferring heat from the reactor coolant at a controlled rate.Heat cannot be removed via the SDC System unless forced flow is used.A minimum of one running SDC pump meets the LCO requirement for one train in operation.An additional SDC train is required to be OPERABLE to meet the single failure criterion.(continued)

PALO VERDE UNITS 1,2 , 3 B 3.4.8-1 REVISION 0 RCS Loops-MODE 5, Loops Not Filled B 3.4.8 BASES (continued)

LCO Note 1 permits all SDC pumps to be de-energized

_1 hour per (continued) 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period.The circumstances for stopping both SDC pumps are to be limited to situations when the outage time is short and the core outlet temperature is maintained

>IO°F below saturation temperature

.The 10 degrees F is considered the actual value of the necessary difference between RCS core outlet temperature and the saturation temperature associated with RCS pressure to be maintained during the time the pumps would be de-energized

.The instrument error associated with determining this difference is less than 10 degrees F.(There are no special restrictions for instrumentation use.)Therefore, the indicated value of the difference between RCS core outlet temperature and the saturation temperature associated with RCS pressure must be greater than or equal to i 20 degrees F in order to use the provisions of the Note allowing the pumps to be de-energized

, (Ref.1)The Note prohibits boron dilution or draining operations when SDC forced flow is stopped.Note 2 allows one SDC train to be inoperable for a period of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> provided that the other train is OPERABLE and in operation.This permits periodic surveillance tests to be performed on the inoperable train during the only time when these tests are safe and possible.An OPERABLE SDC train is composed of an OPERABLE SDC pump (CS or LPSI)capable of providing flow to the SDC heat exchanger for heat removal.SDC pumps are OPERABLE if they are capable of being powered and are able to provide flow, if required.Note that the CS pumps shall not be used for normal operations if the water level is at or below the top of the hot-leg pipe (103'1")due to concerns of potential air entrainment and gas binding of the CS pump (Ref , 2).APPLICABILITY In MODE 5 with loops not filled, this LCO requires core heat removal and coolant circulation by the SDC System.Operation in other MODES is covered by: LCO 3.4.4,"RCS Loops-MODES 1 and 2";LCO 3.4.5,"RCS Loops-MODE 3";LCO 3.4.6,"RCS Loops-MODE 4";LCO 3.4 , 7,"RCS Loops-MODE 5, Loops Filled";LCO 3.9.4,"Shutdown Cooling (SDC)and Coolant Circulation

-High Water Level" (MODE 6);and (continued)

PALO VERDE UNITS 1,2,3 B 3.4.8-2 REVISION 58 RCS Loops-MODE 5, Loops Not Filled B 3,4.8 BASES (continued)

APPLICABILITY LCO 3.9.5,"Shutdown Cooling (SDC)and Coolant (continued)

Circulation

-Low Water Level" (MODE 6), ACTIONS A.I If a SDC train is inoperable, redundancy for heat removal is lost.Action must be initiated immediately to restore a second train to OPERABLE status.The Completion Time reflects the importance of maintaining the availability of two paths for heat removal.B.1 and B.2 If no SDC train is OPERABLE or in operation, except as provided in NOTE I, all operations involving the reduction of RCS boron concentration must be suspended.Action to restore one SDC train to OPERABLE status and operation must be initiated immediately

.Boron dilution requires forced circulation for proper mixing and the margin to criticality must not be reduced in this type of operation.The immediate Completion Time reflects the importance of maintaining operation for decay heat removal.SURVEILLANCE SR 3.4.8.1 REQUIREMENTS This SR requires verification that one SDC train is in operation and circulating reactor cool ant at a flow rate of greater than or equal to 3780 gpm.Verification includes flow rate, temperature, or pump status monitoring, which help ensure that forced flow is providing decay heat removal.The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.SR 3.4.8.2 Verification that the required number of trains are OPERABLE ensures that redundant paths for heat removal are available and that an additional train can be placed in operation, if needed, to maintain decay heat removal and reactor coolant circulation

.Verification is performed by verifying proper breaker alignment and indicated power available to the required pumps.The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.(continued)

PALO VERDE UNITS 1,2,3 B 3.4.8-3 REVISION 58 RCS Loops-MODE 5 , Loops Not Filled B 3.4.8 BASES (continued)

REFERENCES 1.PVNGS Calculation 13-JC-SH-0200, Section 2.9.2.PVNGS Calculation 13-MC-SI-0250, Appendix C.PALO VERDE UNITS 1,2 , 3 B 3.4.8-4 REVISION 58 ADVs B 3 , 7.4 B 3.7 PLANT SYSTEMS B 3.7,4 Atmospheric Dump Valves (ADVs)BASES BACKGROUND The ADVs provide a safety grade method for cooling the unit to Shutdown Cooling (SDC)System entry conditions, should the preferred heat sink via the Steam Bypass Control System (SBCS)to the condenser and/or atmosphere not be available , as discussed in the UFSAR, Section 10.3 (Ref.1).The ADVs have the capacity to achieve and maintain safe shutdown conditions following design basis accidents involving a loss of offsite power and/or closure of the Main Steam Isolation Valves (MSIVs)following receipt of a Main Steam Isolation Signal (MSIS).This is done in conjunction with the Auxiliary Feedwater System providing cooling water from the Condensate Storage Tank (CST).The ADVs may also be required to meet the design cooldown rate during a normal cooldown.Four ADV lines are provided.Each ADV line consists of one normally closed ADV and an associated, normally open block valve.Two ADV lines per steam generator are required to meet the single failure assumptions following a design basis accident that may render one steam generator (SG)unavailable for heat removal.The ADV block valves permit testing of the ADVs while a unit is at power.The safety analyses, however, do not credit block valve operation as a means of isolation of a failed open ADV.The ADVs are equipped with pneumatic controllers to permit control of the cooldown rate.The ADVs are provided with a pressurized gas supply of bottled nitrogen that, on a loss of pressure in the normal instrument air supply, automatically supplies nitrogen to operate the ADVs.The nitrogen supply is sized to provide sufficient pressurized gas to operate the ADVs for the time required for Reactor Coolant System (RCS)cooldown to the Shutdown Cooling (SDC)System entry conditions, as described in UFSAR Appendix 5C,"Natural Circulation Cooldown Analysis." The Appendix 5C analysis is based on the assumptions and conditions in the NRC's Branch Technical Position (BTP)RSB 5-1 ,"Design Requirements of the Residual Heat Removal System." RSB 5-I is an attachment (continued)

PALO VERDE UNITS 1,2,3 B 3.7.4-1 REVISION 58 ADVs B 3.7.4 BASES BACKGROUND (continued) to Standard Review Plan (SRP)5.4.7,"Residual Heat Removal (RHR)System," and identifies RHR System requirements that ensure conformance with General Design Criteria (GDC)34,"Residual Heat Removal." The PVNGS RSB 5-1 cooldown scenario described in UFSAR Appendix 5C is based on a natural circulation cooldown with both steam generators (SGs)available, using safety-grade equipment, assuming a loss of offsite power, a limiting single failure (assumed to be a diesel generator failure), and with minimal operator actions outside the control room , as approved by the NRC.The RSB 5-1 cooldown duration wa s established during actual testing performed in January 1986, and was confirmed through subsequent analyses to address steam generator replacement and power uprates.A description of the ADVs is found in Reference 1.The ADVs require both Direct Current (DC)sources and class Alternating Current (AC)instrument power to be considered OPERABLE.In addition, non-safety related hand wheels are provided for local manual operations although hand wheels are not required for ADV OPERABILITY or credited in the accident analysis.APPLICABLE The design basis of the ADVs is established by the SAFETY ANALYSES capability to cool the unit to SDC System entry conditions

.The design must also accommodate credible single failures that may render as many as two ADVs (i.e., one on each steam generator) incapable of opening on demand.This design is adequate to cool the unit to SDC System entry conditions with only one ADV and one SG, utilizing the cooling water supply available in the CST.Cooldown scenarios using a single ADV may require a combination of the available nitrogen supply and local manual operation or other actions.Alternatives for cooldown and for ADV operation beyond the RSB 5-1 scenario have been evaluated using probabilistic risk analysis (PRA)as part of the resolution of Unresolved Safety Issue (USI)A-45,"Shutdown Decay Heat Removal Requirements

." USI A-45 was subsumed into the Individual Plant Examination (IPE)which used PRA techniques and was submitted to the NRC in response to Generic Letter 88-20.The IPE considered various operator actions and the use of non-safety related equipment, and concluded that there are no significant heat removal vulnerabilities at PVNGS.(continued)

PALO VERDE UNITS 1,2,3 B 3.7.4-2 REVISION 58 ADVs B 3.7.4 BASES APPLICABLE SAFETY ANALYSES Operator actions to locally operate the ADVs are not credited (continued) in the UFSAR Chapter 15 accident analyses but are described in the EOPs;non-safety related equipment such as the supplemental nitrogen supply could also be used during extended cooldown situations

.The design basis accident analyses also account for a single failure that may render one ADV incapable of being closed remotely, after it is opened by control room operators.This type of postulated failure yields more adverse radiological consequences for certain analyses, because it creates a pathway for radioisotope discharges to the environment

.For accident mitigation the safety analyses do not credit isolation of a failed open ADV by either local manual hand wheel operation or closure of its associated block valve.The safety analyses in the UFSAR assume that plant operators will use the ADVs to cool down an affected unit to SDC System entry conditions, following accidents accompanied by a loss of offsite power and/or closure of the MSIVs.Initiation of operator action is typically assumed to occur 30 minutes following the initiation of an event;however , to conservatively bound maximum potential dose consequences for Steam Generator Tube Rupture (SGTR)events, initiation of this operator action is assumed to occur two minutes following reactor trip.Prior to the operator action, the Main Steam Safety Valves (MSSVs)are credited in the analyses to maintain SG pressure and temperature near the MSSV setpoints.The limiting design basis event for nitrogen supply capacity is the RSB 5-1 natural circulation cooldown scenario described above.This scenario includes an initial period of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at hot standby conditions followed by natural circulation cooldown for 9.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> until SDC entry conditions are achieved.Each ADV is required to have a nitrogen supply that supports ADV operation for a total of 13.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> , Limiting design basis accidents with respect to RCS heat removal and ADV steam flow capacity include those that may render one SG unavailable, with a coincident loss of offsite power and a single active component failure (i.e., main steam line breaks upstream of the MSIVs, and feedwaterline breaks).(continued)

PALO VERDE UNITS 1,2,3 B 3.7.4-3 REVISION 58 ADVs B 3.7.4 BASES APPLICABLE SAFETY ANALYSES The limiting design basis event with respect to offsite (continued) radiological consequences is a SGTR with a coincident loss of offsite power, a coincident RCS iodine spike, and a single failed open ADV on the affected SG (SGTRLOPSF)

.To determine bounding radiological consequences, an ADV is assumed to stick open during operator action that occurs two minutes after trip, and remains open for the duration of the cooldown.For this SGTRLOPSF case, plant operators will direct auxiliary feedwater flow to the affected SG after the accident has occurred.The steam released through the ADVs is contaminated, however, because of primary-to-secondary leakage that transports radioisotopes from the RCS to the SG.The ADVs satisfy Criterion 3 of 10 CFR 50.36 (c)(2)(ii)

.LCO Four ADV lines are required to be OPERABLE, two on each SG to ensure a design basis accident that renders one SG unavailable for heat removal (in combination with a coincident loss of offsite power and a single active component failure)would not prevent control room operators from remotely opening an ADV on the unaffected SG.Failure to meet the LCO can result in an inability to cool the affected unit to SDC System entry conditions when the SBCS is unavailable

.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.I In MODES 1, 2, and 3, and in MODE 4, when a SG is being APPLICABILITY relied upon for heat removal , the ADVs are required to be OPERABLE.In MODES 5 and 6, there is insufficient heat available to produce steam that could be released through the ADVs, and design basis accidents such as main steam line breaks, feedwater line breaks, and SGTRs are not credible events.(continued)

PALO VERDE UNITS 1,2,3 B 3.7.4-4 REVISION 58 BASES ACTIONS A.1 The condition for this ACTION is modified by a Note that states separate Condition entry is allowed for each SG.This is acceptable because only one SG is required for RCS heat removal after a design basis accident, and because this Condition provides the appropriate Required Action and Completion Time for one inoperable ADV line on each SG.With one ADV line on a SG inoperable, action must be taken to restore that ADV line to OPERABLE status within 7 days to meet the LCO for each SG that has entered this Condition.The 7-day Completion Time takes into consideration the redundant capability afforded by the remaining OPERABLE ADV lines, the safety grade MSSVs , and the non-safety grade backup of the SBCS.B.1 With two or more ADV lines inoperable with both ADV lines inoperable on one or more SGs, action must be taken to restore one ADV line on each SG to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Completion Time is reasonable to repair inoperable ADV lines, based on the availability of the Steam Bypass Control System and MSSVs, and the low probability of an event occurring during this period that requires the ADV I i nes.NOTE: Entry into Condition B for all four ADV lines simultaneously inoperable is not intended for voluntary removal of redundant systems or components from service in lieu of other alternatives that would not result in redundant systems or components being inoperable

.(continued)

PALO VERDE UNITS 1,2,3 B 3.7.4-5 REVISION 58 ADVs B 3.7.4 BASES ACTIONS C.1 and C.2 (continued)

If the ADV lines cannot be restored to OPERABLE status within the associated Completion Time, the unit must be placed in a MODE in which the LCO does not apply.To achieve this status, the unit must be placed in at least MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> , and in MODE 4, without reliance on I the SG for heat removal , within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.SURVEILLANCE SR 3.7.4.1 REQUIREMENTS To perform a controlled cooldown of the RCS, the ADVs must be able to be opened and throttled through their full range.This SR ensures the ADVs are tested through a full control cycle.Performance of inservice testing or use of an ADV during a unit cooldown may satisfy this requirement

.The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.REFERENCES 1.UFSAR, Section 10.3.(continued)

PALO VERDE UNITS 1,2,3 B 3.7.4-6 REVISION 58 SDC and Coolant Circulation

-Low Water Level B 3.9.5 B 3.9 REFUELING OPERATIONS B 3 , 9.5 Shutdown Cooling (SDC)and Coolant Circulation

-Low Water Level BASES BACKGROUND The purposes of the SDC System in MODE 6 are to remove decay heat and sensible heat from the Reactor Coolant System (RCS), as required by GDC 34, to provide mixing of borated coolant, to provide sufficient coolant circulation to minimize the effects of a boron dilution accident, and to prevent boron stratification (Ref.1).Heat is removed from the RCS by circulating reactor coolant through the SDC heat exchanger(s), where the heat is transferred to the Essential Cooling Water System via the SDC heat exchanger(s)

.The coolant is then returned to the RCS via the RCS cold leg(s).Operation of the SDC System for normal cooldown or decay heat removal is manually accomplished from the control room.The heat removal rate is adjusted by controlling the flow of reactor coolant through the SDC heat exchanger(s) and bypassing the heat exchanger(s)

.Mixing of the reactor coolant is maintained by this continuous circulation of reactor coolant through the SDC System, APPLICABLE If the reactor coolant temperature is not maintained below SAFETY ANALYSES 200°F, boiling of the reactor coolant could result.This could lead to inadequate cooling of the reactor fuel due to the resulting loss of coolant in the reactor vessel.Additionally

, boiling of the reactor coolant could lead to a reduction in boron concentration in the coolant due to the boron plating out on components near the areas of the boiling activity, and because of the possible addition of water to the reactor vessel with a lower boron concentration than is required to keep the reactor subcritical

.The loss of reactor coolant and the reduction of boron concentration in the reactor coolant would eventually challenge the integrity of the fuel cladding, which is a fission product barrier.Two trains of the SDC System are required to be OPERABLE , and one train is required to be in operation in MODE 6, with the water level<23 ft above the top of the reactor vessel flange, to prevent this challenge.

SDC and Coolant Circulation

-Low Water Level satisfies Criterion 2 of 10 CFR 50.36 (c)(2)(ii)

.(continued)

PALO VERDE UNITS 1,2,3 B 3.9.5-I REVISION 0 SDC and Cool ant Circulation

-Low Water Level B 3.9.5 BASES LCO In MODE 6, with the water level<23 ft above the top of the reactor vessel flange, both SDC loops must be OPERABLE.Additionally, one loop of the SDC System must be in operation in order to provide: a.Removal of decay heat;b.Mixing of borated coolant to minimize the possibility of a criticality; and c.Indication of reactor coolant temperature

.An OPERABLE SDC train is composed of an OPERABLE SDC pump (LPSI or CS)capable of providing flow to the SDC heat exchanger for heat removal.SDC pumps are OPERABLE if they are capable of being powered and are able to provide flow, if required.Note that the CS pumps shall not be used for normal operations if the water level is at or below the top of the hot-leg pipe (103'1")due to concerns of potential air entrainment and gas binding of the CS pump (Ref.2).Both SDC pumps may be aligned to the Refueling Water Tank (RWT)to support filling the refueling cavity or for performance of required testing.The LCO is modified by a Note that allows a required operating SDC loop to be removed from service for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in each 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period, provided no operations are permitted that would cause a reduction of the RCS boron concentration

.Boron concentration reduction is prohibited because uniform concentration distribution cannot be ensured without forced circulation

.This permits operations such as core mapping or alterations in the vicinity of the reaGtor vessel hot leg nozzles, surveillance testing of ECCS pumps , and RCS to SDC isolation valve testing.During this 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period, decay heat is removed by natural convection to the large mass of water in the refueling cavity.This LCO is modified by a Note that allows one SDC loop to be inoperable for a period of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> provided the other loop is OPERABLE and in operation.Prior to declaring the loop inoperable, consideration should be given to the existing plant configuration

.This consideration should include that the core time to boil is not short, there is no draining operation to further reduce RCS water level and that the capacity exists to inject borated water into the reactor vessel.This permits surveillance tests to be performed on the non-operating loop during a time when these tests are safe and possible.(continued)

PALO VERDE UNITS 1,2,3 B 3.9.5-2 REVISION 58 SDC and Cool ant Circulation

-Low Water Level B 3.9.5 BASES APPLICABILITY Two SDC loops are required to be OPERABLE, and one SDC loop must be in operation in MODE 6, with the water level<23 ft above the top of the reactor vessel flange, to provide decay heat removal.Requirements for the SDC System in other MODES are covered by LCOs in Section 3.4 , Reactor Coolant System.MODE 6 requirements, with a water level_23 ft above the reactor vessel flange, are covered in LCO 3.9.4,"Shutdown Cooling and Coolant Circulation

-High Water Level." ACTIONS A.1 and A.2 If one SDC loop is inoperable, action shall be immediately initiated and continued until the SDC loop is restored to OPERABLE status and to operation, or until_>23 ft of water level is established above the reactor vessel flange.When the water level is established at>23 ft above the reactor vessel flange, the Applicability will change to that of LCO 3.9.4,"Shutdown Cooling and Coolant Circulation

-High Water Level ," and only one SDC loop is required to be OPERABLE and in operation.An immediate Completion Time is necessary for an operator to initiate corrective actions.B.1 If no SDC loop is in operation or no SDC loops are OPERABLE, there will be no forced circulation to provide mixing to I establish uniform boron concentrations

.Reduced boron concentrations can occur by the addition of water with lower boron concentration than that contained in the RCS.Therefore, actions that reduce boron concentration shall be suspended immediately

.B.2 If no SDC loop is in operation or no SDC loops are OPERABLE, action shall be initiated immediately and continued without interruption to restore one SDC loop to OPERABLE status and operation.Since the unit is in Conditions A and B concurrently, the restoration of two OPERABLE SDC loops and one operating SDC loop should be accomplished expeditiously

.B.3 If no SDC loop is in operation or no SDC loops are OPERABLE, all containment penetrations providing direct access from (continued)

PALO VERDE UNITS 1,2,3 B 3.9.5-3 REVISION 58 SDC and Coolant Circulation

-Low Water Level B 3.9.5 BASES ACTIONS B.3 (Continued) the containment atmosphere to the outside atmosphere must be closed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.With the SDC loop requirements not met, the potential exists for the coolant to boil and release radioactive gas to the containment atmosphere

.Closing containment penetrations that are open to the outside atmosphere ensures that dose limits are not exceeded.The Completion Time of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is reasonable, based on the low probability of the coolant boiling in that time.SURVEILLANCE SR 3.9.5.1 REQUIREMENTS This Survei I Iance demonstrates that one SDC loop i s operating and circulating reactor coolant at a flowrate of greater than or equal to 3780 gpm.The flow rate is determined by the flow rate necessary to provide sufficient decay heat removal capability and to prevent thermal and boron stratification in the core.In addition, this Surveillance demonstrates that the other SDC loop is OPERABLE.In addition, during operation of the SDC loop with the water level in the vicinity of the reactor vessel nozzles, the SDC loop flow rate determination must also consider the SDC pump suction requirements

.The Surveillance Frequency is control led under the Surveillance Frequency Control Program.SR 3.9.5.2 Verification that the required pump that is not in operation is OPERABLE ensures that an additional SDC pump can be placed in operation, if needed , to maintain decay heat removal and reactor coolant circulation

.Verification is performed by verifying proper breaker alignment and power available to the required pump.The Surveillance Frequency i s control led under the Survei I Iance Frequency Control Program.REFERENCES 1.UFSAR, Section 5.4.7.2.PVNGS Calculation 13-MC-SI-0250, Appendix C.PALO VERDE UNITS 1,2,3 B 3.9.5-4 REVISION 58

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