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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML17300B3791999-10-0808 October 1999 Proposed Tech Specs,Waiving Requirement to Perform SR 3.8.4.8 for Unit 1 Channels A,B & C on One Time Basis ML17300B3521999-09-29029 September 1999 Revised Bases Pages,Providing Addl Discussion of Options Available to Exit Required Action G of TS 3.8.1 & Revised Page for TS 3.3.7 ML17300B3321999-09-14014 September 1999 Marked-up Tech Specs Pages to TS 5.5.2 & 5.6.2,making Noted Administrative Changes ML17313B0601999-08-31031 August 1999 Rev 1 to PVNGS TS Bases Implemented Between Aug 1998 & Jul 1999 ML17313A9571999-05-26026 May 1999 Proposed Tech Specs,Reducing Spurious Reactor Trip Hazards Associated with Setpoints While Maintaining Plant Protection ML17313A4181998-06-0909 June 1998 Proposed Improved Tech Specs Sections 3.5.1 & 3.5.2,revising Safety Injection tanks-operating & Safety Injection Tanks Shutdown ML17313A1141997-11-0707 November 1997 Improved TS Pages for Section 3.0, LCO & SR Applicability, Section 3.1, Reactivity Control & Section 3.2, Power Distribution Limits. Generic Change to NUREG-1432,Rev 1 Incorporated Into Section 3.0 & 3.1 ML17312B6411997-08-28028 August 1997 Proposed Tech Specs,Allowing one-time Extension of Required Surveillance Interval for Msi Sys Portion Only of ESFAS Logic ML20217Q6801997-08-22022 August 1997 Proposed Tech Specs,Clarifying Wording in TS Bases 3/4.6.1.4, Internal Pressure ML20141H7831997-07-18018 July 1997 Proposed Improved Tech Specs Section 3.8, Electrical Power Sys ML20141H7461997-07-18018 July 1997 Proposed Tech Specs,Providing Addl Info Re Improved TS Section 3.4, Rcs ML17312B0311996-11-0606 November 1996 Proposed Tech Specs 3/4.8.1.1 Re A.C. Sources - Operating ML17300B2651996-06-17017 June 1996 Proposed Tech Specs,Changing Section 1.10 & 3.2.8 & Associated Bases for Obtaining Thyroid Dcfs Used in Definition of Dose Equivalent I-131 ML17312A6491996-04-0101 April 1996 Proposed Tech Specs,Revising TS 3/4.9.6 to Temporarily Allow Use of Hoist Instead of Refueling Machine for Movement of Fuel Assembly at Core Location A-07 ML17312A6401996-03-26026 March 1996 Proposed Tech Specs 3/4.9.6,increasing Refueling Machine Overload Cut Off Limit to 2,000 Lb,In 50 Lb Increments,For Removal of Stuck Fuel Assembly from Core Location A-06 ML17312A6321996-03-26026 March 1996 Proposed Tech Specs,Revising TS 3/4.9.6 to Relocate Refueling Machine Overload Cut Off Limit from TS 3/4.9.6 to Plant UFSAR Per Criteria in 10CFR50.36 & Rev 1 of NUREG-1432 STS for C-E Plants. ML17312A6371996-03-23023 March 1996 Proposed Tech Specs,Revising TS SR 4.8.2.1.e, DC Sources, to Suspend Provision of TS 4.0.1 & 4.0.4 for Battery Capacity Testing Requirements Until Entry Into Mode 4 Following Sixth Refueling Outage ML17312A5011996-01-17017 January 1996 Revised Page 5-1 Changing Section 5.2.2 to Include Description of Material Used for Control Element Assemblies ML17311B3221995-12-20020 December 1995 Proposed Tech Specs,Reducing Setpoint for MSIS & Rt on Low SG Pressure ML17311B0301995-07-0303 July 1995 Proposed Tech Specs Re Temp Method to Respond to Sustained Degraded Switchyard Voltage ML17311A9771995-06-21021 June 1995 Proposed Tech Specs,Modifying Tables 3.3-4 & 3.3-5 of Section 3/4.3.2 of Esfa Sys Instrumentation ML17311A8651995-05-0202 May 1995 Proposed TS 3.1.2.6,Figure 3.1-1, Min Borated Water Vols, Relocating Elevations That Correspond to Min Required Water Vols for Spent Fuel Pool Into Site Procedures ML17311A8231995-04-18018 April 1995 Proposed Tech Specs Section 3/4.4.4 Re Sleeving Process for SG Tube Repair ML17311A5631994-12-28028 December 1994 Proposed TS Sections 3.9.6 & 4.9.6.1 Re Refueling Machine ML17311A5021994-12-0707 December 1994 Proposed Tech Specs,Changing Note 5 to Table 4.3-1 of TS 3/4.3.1 to Allow Verification of Shape Annealing Matrix Elements Used in Core Protection Calculators ML17311A4341994-11-30030 November 1994 Proposed TS 3/4.4.2,changing Pressurizer Code Safety Valve Lift Setting from 2,500 Psia to 2,475 Psia in LCOs 3.4.2.1 & 3.4.2.2 ML17311A3851994-10-31031 October 1994 Proposed Tech Spec Sections 3.9.6 & 4.9.6.1, Refueling Machine. ML17311A3341994-10-0909 October 1994 Proposed Tech Specs Suspending TS 4.0.1 & 4.0.4 for Battery Capacity Testing Requirements Until Mode 4 Following Fifth Refueling Outage ML17311A2171994-08-18018 August 1994 Proposed Tech Specs Adding Analytical Method Suppl Entitled, Calculative Methods for CE Large Break LOCA Evaluation Model for Analysis of CE & W Designed Nsss. ML17310B4511994-07-12012 July 1994 Proposed Tech Specs Amend to Add One Action Statement to Table 3.3-3,entry 8 ML17310B4151994-07-0101 July 1994 Proposed Tech Specs Re Reactor Coolant Cold Leg Temperature Vs Core Power Level of TS 3.2.6 ML17310B4331994-06-20020 June 1994 Proposed Tech Specs Sections 5.3.1 & 5.6.1, & New TS Section 3/4.9.13 & Bases 3/4.9.13 ML17310B4091994-06-17017 June 1994 Proposed Tech Specs Removing Five Tables of Component Lists Per GL-91-08 ML17310B1661994-03-28028 March 1994 Proposed Tech Specs Re Min Condensate Storage Tank Indicated Level ML17310B0611994-02-18018 February 1994 Proposed Tech Specs Figure 3.2-1,Section 3/4.1.1.4 & Bases 3/4.1.1.4,establishing Min Temp for Criticality at 545 F for Facilities ML17310B0001994-01-19019 January 1994 Proposed Tech Specs of AF Automatic Actuation Logic Surveillance Frequency Extension ML17310A8361993-11-16016 November 1993 Proposed Tech Specs Table 4.2-4, Min Staffing Requirements for PVNGS Emergencies, in Support of Proposed Rev to Emergency Plan ML17310A7351993-10-26026 October 1993 Proposed Tech Specs Changing Maximum Nominal Enrichment of Fuel Allowed to Be Used in Reactor Core ML17310A6161993-09-0808 September 1993 Proposed Tech Specs Section 6.9.1.10 Re Sys 80 Inletflow Distribution to List of Methods Used to Determine Core Operating Limits ML17310A5211993-08-0505 August 1993 Proposed Tech Specs Requesting to Change Word Pressurizer to RCS for Item #4 in Both Tables 3.3-10 & 4.3-7 ML17310A5151993-08-0505 August 1993 Proposed Tech Specs Changing Surveillance Frequency from Monthly to Quarterly for Channel Functional Tests for RPS & ESFAS Instrumentation ML17310A4211993-06-30030 June 1993 Proposed Tech Specs Requesting Addl Operating Margin in Time Response of Turbine Driven AF Pump to SG Low Level Signal ML17310A2981993-05-20020 May 1993 Proposed TS 4.7.9 Re SR to Ensure Operability of Snubbers ML17306B2671993-01-25025 January 1993 Proposed Tech Specs,Reflecting Revised Train a Kw Value to Be Rejected & Load Designation & Incorporation of Provisions Discussed in 920508 Ltr Re DG Full Load Rejection Testing ML17306B1451992-11-20020 November 1992 Proposed Tech Specs Revising TS 3.2.1 Lhr, & TS 3.2.4, DNBR Margin, Increasing Action from 1 H to 4 H for COLSS Allowed Out of Svc Time Before Requirements Based on More Restrictive Core Protection Calculator Limits Apply ML17306A6491992-04-13013 April 1992 Proposed TS 3.4.8.3 Re RCS - Overpressure Protection Sys ML17306A4731992-02-14014 February 1992 Proposed Tech Specs Re Implementation of Generic Ltr 89-01, Implementation of Programmatic Controls for Radiological Effluent TS in Administrative Controls Section of TS & Relocation of Procedural Details of RETS to Odcm.... ML17306A4031992-01-16016 January 1992 Proposed Tech Specs Amend to TS Section 3.6.3,table 3.6-1 Deleting Type C Testing Requirements for Eight Valves ML17306A3701991-12-30030 December 1991 Proposed Tech Spec Table 6.2-1 Re Min Shift Crew Composition ML17306A3781991-12-30030 December 1991 Proposed Tech Spec Section 3.6.1.7 Re Containment Purge Supply & Exhaust Valves 1999-09-29
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17300B3791999-10-0808 October 1999 Proposed Tech Specs,Waiving Requirement to Perform SR 3.8.4.8 for Unit 1 Channels A,B & C on One Time Basis ML17300B3521999-09-29029 September 1999 Revised Bases Pages,Providing Addl Discussion of Options Available to Exit Required Action G of TS 3.8.1 & Revised Page for TS 3.3.7 ML17300B3321999-09-14014 September 1999 Marked-up Tech Specs Pages to TS 5.5.2 & 5.6.2,making Noted Administrative Changes ML17313B0601999-08-31031 August 1999 Rev 1 to PVNGS TS Bases Implemented Between Aug 1998 & Jul 1999 ML17313B0081999-07-14014 July 1999 Rev 2 to Inservice Insp Program Summary Manual for PVNGS Unit 1. ML17313A9571999-05-26026 May 1999 Proposed Tech Specs,Reducing Spurious Reactor Trip Hazards Associated with Setpoints While Maintaining Plant Protection ML17313A7511998-12-16016 December 1998 Rev 2 to ISI Program Summary Manual, for PVNGS Unit 3 ML17313A4181998-06-0909 June 1998 Proposed Improved Tech Specs Sections 3.5.1 & 3.5.2,revising Safety Injection tanks-operating & Safety Injection Tanks Shutdown ML17313A1141997-11-0707 November 1997 Improved TS Pages for Section 3.0, LCO & SR Applicability, Section 3.1, Reactivity Control & Section 3.2, Power Distribution Limits. Generic Change to NUREG-1432,Rev 1 Incorporated Into Section 3.0 & 3.1 ML17312B6411997-08-28028 August 1997 Proposed Tech Specs,Allowing one-time Extension of Required Surveillance Interval for Msi Sys Portion Only of ESFAS Logic ML20217Q6801997-08-22022 August 1997 Proposed Tech Specs,Clarifying Wording in TS Bases 3/4.6.1.4, Internal Pressure ML20141H7831997-07-18018 July 1997 Proposed Improved Tech Specs Section 3.8, Electrical Power Sys ML20141H7461997-07-18018 July 1997 Proposed Tech Specs,Providing Addl Info Re Improved TS Section 3.4, Rcs ML17312B0311996-11-0606 November 1996 Proposed Tech Specs 3/4.8.1.1 Re A.C. Sources - Operating ML17300B2651996-06-17017 June 1996 Proposed Tech Specs,Changing Section 1.10 & 3.2.8 & Associated Bases for Obtaining Thyroid Dcfs Used in Definition of Dose Equivalent I-131 ML17312A9451996-05-14014 May 1996 Rev 3 to Significant Condition Investigation. ML17312A6491996-04-0101 April 1996 Proposed Tech Specs,Revising TS 3/4.9.6 to Temporarily Allow Use of Hoist Instead of Refueling Machine for Movement of Fuel Assembly at Core Location A-07 ML17312A6401996-03-26026 March 1996 Proposed Tech Specs 3/4.9.6,increasing Refueling Machine Overload Cut Off Limit to 2,000 Lb,In 50 Lb Increments,For Removal of Stuck Fuel Assembly from Core Location A-06 ML17312A6321996-03-26026 March 1996 Proposed Tech Specs,Revising TS 3/4.9.6 to Relocate Refueling Machine Overload Cut Off Limit from TS 3/4.9.6 to Plant UFSAR Per Criteria in 10CFR50.36 & Rev 1 of NUREG-1432 STS for C-E Plants. ML17312A6371996-03-23023 March 1996 Proposed Tech Specs,Revising TS SR 4.8.2.1.e, DC Sources, to Suspend Provision of TS 4.0.1 & 4.0.4 for Battery Capacity Testing Requirements Until Entry Into Mode 4 Following Sixth Refueling Outage ML17312A5691996-03-0505 March 1996 Revised Pages to ISI Program Summary Manual ML17312A5011996-01-17017 January 1996 Revised Page 5-1 Changing Section 5.2.2 to Include Description of Material Used for Control Element Assemblies ML17311B3221995-12-20020 December 1995 Proposed Tech Specs,Reducing Setpoint for MSIS & Rt on Low SG Pressure ML17311B3181995-12-20020 December 1995 Revised Pages to ISI Program Summary Manual ML17311B0301995-07-0303 July 1995 Proposed Tech Specs Re Temp Method to Respond to Sustained Degraded Switchyard Voltage ML17311A9771995-06-21021 June 1995 Proposed Tech Specs,Modifying Tables 3.3-4 & 3.3-5 of Section 3/4.3.2 of Esfa Sys Instrumentation ML17311A8651995-05-0202 May 1995 Proposed TS 3.1.2.6,Figure 3.1-1, Min Borated Water Vols, Relocating Elevations That Correspond to Min Required Water Vols for Spent Fuel Pool Into Site Procedures ML17311A8231995-04-18018 April 1995 Proposed Tech Specs Section 3/4.4.4 Re Sleeving Process for SG Tube Repair ML17312A9381995-02-0303 February 1995 Corrective Action Program. ML17311A5631994-12-28028 December 1994 Proposed TS Sections 3.9.6 & 4.9.6.1 Re Refueling Machine ML17311A5021994-12-0707 December 1994 Proposed Tech Specs,Changing Note 5 to Table 4.3-1 of TS 3/4.3.1 to Allow Verification of Shape Annealing Matrix Elements Used in Core Protection Calculators ML17311A4341994-11-30030 November 1994 Proposed TS 3/4.4.2,changing Pressurizer Code Safety Valve Lift Setting from 2,500 Psia to 2,475 Psia in LCOs 3.4.2.1 & 3.4.2.2 ML17311A3851994-10-31031 October 1994 Proposed Tech Spec Sections 3.9.6 & 4.9.6.1, Refueling Machine. ML17311A3341994-10-0909 October 1994 Proposed Tech Specs Suspending TS 4.0.1 & 4.0.4 for Battery Capacity Testing Requirements Until Mode 4 Following Fifth Refueling Outage ML17311A2171994-08-18018 August 1994 Proposed Tech Specs Adding Analytical Method Suppl Entitled, Calculative Methods for CE Large Break LOCA Evaluation Model for Analysis of CE & W Designed Nsss. ML17310B4511994-07-12012 July 1994 Proposed Tech Specs Amend to Add One Action Statement to Table 3.3-3,entry 8 ML17310B4151994-07-0101 July 1994 Proposed Tech Specs Re Reactor Coolant Cold Leg Temperature Vs Core Power Level of TS 3.2.6 ML17310B4331994-06-20020 June 1994 Proposed Tech Specs Sections 5.3.1 & 5.6.1, & New TS Section 3/4.9.13 & Bases 3/4.9.13 ML17310B4091994-06-17017 June 1994 Proposed Tech Specs Removing Five Tables of Component Lists Per GL-91-08 ML17310B1661994-03-28028 March 1994 Proposed Tech Specs Re Min Condensate Storage Tank Indicated Level ML17310B0911994-03-0202 March 1994 SG Tube Insp Plan. ML17310B0771994-02-24024 February 1994 PVNGS Unit 1 Cycle 5 Startup Rept. ML17310B0611994-02-18018 February 1994 Proposed Tech Specs Figure 3.2-1,Section 3/4.1.1.4 & Bases 3/4.1.1.4,establishing Min Temp for Criticality at 545 F for Facilities ML17310B0251994-01-27027 January 1994 Unit 2 Steam Generator Tube Insp Plan Addendum. ML17310B0001994-01-19019 January 1994 Proposed Tech Specs of AF Automatic Actuation Logic Surveillance Frequency Extension ML17310A8361993-11-16016 November 1993 Proposed Tech Specs Table 4.2-4, Min Staffing Requirements for PVNGS Emergencies, in Support of Proposed Rev to Emergency Plan ML17310A7421993-10-27027 October 1993 Revised Unit 1 SG Tube Insp Plan. ML17310A7351993-10-26026 October 1993 Proposed Tech Specs Changing Maximum Nominal Enrichment of Fuel Allowed to Be Used in Reactor Core ML17310A6501993-09-17017 September 1993 Unit 1 SG Tube Insp Plan. ML17310A6161993-09-0808 September 1993 Proposed Tech Specs Section 6.9.1.10 Re Sys 80 Inletflow Distribution to List of Methods Used to Determine Core Operating Limits 1999-09-29
[Table view] |
Text
FUNCTIONAL UNIT TABLE 3.3-1 REACTOR PROTECTIVE INSTRUMENTATION TOTAL NO.CHANNELS OF CHANNELS TO TRIP MINIMUM CHANNELS OPERABLE APPLICABLE MODES ACTION c H=0 U03 CI4 O'Do'O Ah)KQI 0$Vl'4 Q>>->>OO UOM OQ 03 TRIP GENERATION A.Process 1.Pressurizer Pressure-High 4 2.Pressurizer Pressure-Low 4 3.Steam Generator Level-Low 4/SG 4.Steam Generator Level-High 4/SG 5.Steam Generator Pressure-Low 4/SG 6.Containment Pressure-High 4 7.Reactor Coolant Flow-Low 4/SG 8.Local Power Density-High 9.DNBR" Low B.Excore Neutron Flux l.Variable Overpower Trip 2.Logarithmic Power Level-High a.Startup and Operating b.Shutdown C.Core Protection Calculator System 1.CEA Calculators 2.Core Protection Calculators 2 3 2 (b)2/SG 3/SG 2/SG 3/SG 2/SG 3/SG 2 3 2/SG 3/SG 2 (c)(d)3 2 (c)(d)3 2 (a)(d)2 3 1 2 (e)2 (c)(d)3 1 2 l.2 1 2 1, 2 1, 2, 3", 4*1 2 1, 2 1 2 1 2 1 2 3*4*5*3, 4, 5 1, 2 1, 2 2¹3¹3¹3¹2¹2¹2¹3¹3¹6, 7 2¹3¹A 9~
0 I~~a,~
\TABLE 3.3-1 (Continued)
REACTOR PROTECTIVE INSTRUHENTATION FUNCTIONAL UNIT D.Supplementary Protection System Pressurizer Pressure-High II.RPS LOGIC TOTAL NO.OF CllANNELS 4 (f)CHANNELS TO TRIP HINIHUH CBANNELS OPERABLE APPLICABLE HODES 1 2 ACTION A A.Hatrix Logic B.Initiation Logic I I I.RPS ACTUATION DEVICES A.Reactor Trip Breaker B.Hanual Trip 6 6 4 (f)4 (f)4 (f)4 (f)1 1 2 2 3 3 1 2 3A'*5$$l 1$2~3A 4A 5A 1, 2 3*4A 5*1, 2 I 3A 4*5*1"0 I 8 M'5 8 5
~~'.I I 1'1
~.~%ONT)OLLED BY USE%..TABLE 3.3-1 Continued)
ACTION STATEMENTS 2.Within 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />s: a)All full-length and part-length CEA groups are withdrawn to and subsequently maintained at the"Full Out" position, except during surveillance testing pursuant to the requirements of Specifica-tion 4.1.3.1.2 or for control when CEA group 5 may be inserted no further than 127.5 inches withdrawn.
b)c)The"RSP/CEAC Inoperable" addressable constant in the CPCs is set to be indicated that both CEAC's are inoperable.
4 The Control Element Drive Mechanism Control System (CEDMCS)is placed in and subsequently maintained in the"Standby" mode except during CEA'group 5 motion permitted by a)above, when the CEDMCS may be operated in either the"Manual Group" or."Manual Individual" mode.ACTION 7 ACTION 8 AcYxo<9 3.At least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, all full-length and part-length CEAs are verified fully withdrawn except during surveillance testing pursuant to Specification 4.1.3.1.2 or during insertion of CEA group 5.as permitted by 2.a)above, then verify at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> that the inserted CEAs are aligned within 6.'6 inches (indicated position)of all other, CEAs in its group.With three or more auto restarts, excluding periodic auto restarts (Code 30 and Code 33), of one non-bypassed calculator during a 12-hour interval, demonstrate calculator OPERABILITY by performing a CHANNEL FUNCTIONAL TEST within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore an inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open an affected reactor trip breaker within the next hour.wi<<Q<<4a.<uw oa.c of oPKQaRAR<aeea%g anah<<Lss 4m~44-g<<v e ew~~~ma%a OPER~4%.<<a.<<Iui<<.o
~~M>~SNo<<a Vv,<<<<<<e,opax a%~~+~4 QPKR.~~"o<<aalu~Wa44aW'ES Woe<<;a O<<CAP<<LA eke<<;Q.ac.ca<<
4<<'~Qccs~i~i~<<~~4 W4x.PALO VERDE-UNIT 1 3/4 3-8 AMENDMENT NO.24 l4 k' 0 C)(m C7 m I A=~4J iYI~U: IgQl 8]l FUNCTIONAL UNIT I.TRIP GENERATION A.Process 1.Pressurizer Pressure-High 4 2.Pressurizer Pressure-Low 4 3.Steam Generator Level-.Low 4/SG 4.Steam Generator Level-High 4/SG 5.Steam Generator Pressure-Low 4/SG 6.Containment Pressure-High 7.Reactor Coolant Flow-Low 8.'ocal Power Density-High 9.DNBR-Low B.Excore Neutron Flux l.Variable Overpower Trip 2.Logarithmic Power Level-High a.Startup and Operating 4 4/SG 4 4 b.Shutdown 2 3 2 (b).2/SG 3/SG 2/SG 3/SG 2/SG 3/SG 2 3 2/SG"".3/SG 2 (c)(d)-3 2 (c)(d)3 2.(a)(d)3 2 3 0 2 TABLE 3.3-1 REACTOR PROTECTIVE INSTRUMENTATION MINIMUM TOTAL NO.CHANNELS CHANNELS OF CHANNELS TO TRIP OPERABLE APPLICABLE MODES 1 2 1 2 1 2 1 2 1, 2, 3", 4" 1 2 1 2 l.2 1 2 1, 2 1 2 3*4A'*3, 4, 5 ACTION 2¹3¹2¹3¹2¹2¹3¹2¹3¹4 A~U Cy C.Core Protection Calculator System l.CEA Calculators 2.Core Protection Calculators 1 2 (e)2 (c)(d)1, 2 1, 2 6, 7 2¹3¹ V'(~~l 1 (C)m FUNCTIONAL UNIT TABLE 3.3-1 (Continued)
REACTOR PROTECTIVE INSTRUMENTATION I TOTAL HO..CHANNELS OF CHANNELS TO TRIP HINIHUH CHANNELS'PPLIC(BLE OPERABLE'ODES ACTION Fc Q ru lQ~Ql tA 0.Supplementary Protection System Pressurizer Pressure-High II.RPS LOGIC A.Hatrix Logic B.Initiation Logic I I I.RPS ACTUATION OEVICES A.Reactor Trip Breaker B.tianual.Trip 4 (f)4 4 (f)4 (f)4 (f)4 (f)1 1 2 2 2 2'2 3 3 4 4 A',Q 5 p I U QU 1, 2 1 2 3*4*5*1, 2 3*4*5*1.2 5 3*4*5*Q 1, 2 5 3*4*5*Q 0 i(-)~4 GNTRGLLEG BY USER TABLE 3.3-1 Continued REACTOR PROTECTIVE INSTRUMENTATION ACTION 7 ACTION 8@<AX.Q~9 ACTION STATEMENTS 2.Within 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />s: a)All full-length and part-length CEA groups are withdrawn to and subsequently maintained at the"Full Out" position, except during surveillance testing pursuant to the requirements of Specifica-tion 4.1.3.1.2 or for control when CEA group 5 may be inserted no further than 127.5 inches withdrawn.
b).The"RSPT/CEAC Inoperable" addressable constant in the CPCs is set to indicate that both CEACs are inoperable.
c)The Control Element Drive Mechanism Control System (CEDMCS)is placed in and subsequently maintained in the"Standby" mode except during CEA group 5 motion permitted by a)above, when the CEDMCS may be operated in either the"Manual Group" or"Manual Individual" mode.3.At least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, all full-length'and part-length CEAs are verified fully withdrawn except during surveillance testing pursuant to Specification 4.1.3.1.2 or during insertion of CEA group 5 as permitted by 2.a)above, then verify at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> that the inserted CEAs are aligned within 6.6 inches (indicated position)of all other CEAs in its group.With three or more auto restarts, excluding periodic auto restarts (Code 30 and Code 33), of one non-bypassed calculator during a 12-hour interval, demonstrate calculator OPERABILITY by performing a CHANNEL FUNCTIONAL TEST within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore an inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open an affected reactor trip breaker within the next hour.c4q.mu.snag.q o+Q~~+gp ck~<clL,s cd.Kc ss 4+~w 4W~~~w~~~c~~ca%~+PR9~~UK c'c-%~os~<~~~X ko oPKR<Qgq c4a4u s~iLiw'El, kavgg or op~ct'4e~ga~a,~AM~4M~44ou<.PALO VERDE-UNIT 2 3/4 3-8 AMENDMENT HO.19 0'v L FUNCTIONAL UNIT I.TRIP GENERATION A..Process TABLE 3.3"1 REACTOR PROTECTIVE INSTRUMENTATION TOTAL NO.CHANNELS OF CHANNELS TO TRIP MINIMUM CHANNELS APPLICABLE OPERABLE MODES ACTION 1.Pressurizer Pressure-High 4 2.Pressurizer Pressure-Low 3.Steam Generator Level-Low 4/SG 4.Steam Generator Level-High 4/SG 5.Steam Generator Pressure-Low 4/SG 6.Containment Pressure-High.4 7.Reactor Coolant Flow-Low 4/SG 8.Local" Power Density-High 4 9.DNBR-Low 4 B.Excore Neutron Flux 2 2 (b)2/SG 2/SG 2/SG 2 2/SG 2 (c)(d)2 (c)(d)3 3/SG 3/SG 3/SG 3." 3/SG 3 l.2 1, 2 2¹3¹1, 2 2¹3¹1, 2 3¹1, 2, 3", 4" 2 , 3 1 2 2¹3¹1, 2 2¹3¹1,2~2,3.A 0 0 U Ql C (h l..Variable Overpower Trip 2.Logarithmic Power Level-High a.Startup and Operating b.Shutdown C.Core Protection Calculator System 1.CEA Calculators 2.Core Protection Calculators 2 (a)(d)3 2 3 0 2 1 2 (e)2 (c)(d)-3 1, 2 1,'2 3A'A 5A 3, 4, 5 1 2 1 2 2¹3¹2¹6, 7 2', 3", 7
TABLE 3.3-1 (Continued)
REACTOR PROTECTIVE INSTRUMENTATION FUNCTIONAL UNIT.D.Suppl ementary Protecti on System Pressurizer Pressure-High II.RPS LOGIC TOTAL NO.CHANNELS OF CHANNELS TO TRIP 4 (f)MINIMUM CHANNELS OPERABLE APPLICABLE MODES 1;2 ACTION A.Matrix Logic B.Initiation Logic I I I.RPS'ACTUATION DEVICES A.Reactor Trip Breaker B.Manual Trip 4 (f)4 (f)4 (f)4 (f)2 2 2 2 3 3 1, 2 3*4*5'A 1, 2 3)c 4*5*1, 2 3IC" 4 III 5IIc 1, 2 3 III 4 8 5 III 1 O'T 8 5 8 f R rn Q I (0 t
~~\~~4'~t I I QR INFORMATION ONL 2.TABLE 3.3-1 (Continued REACTOR PROTECTIVE INSTRUMENTATION ACTION STATEMENTS Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> the ONBR margin required by Specifica-tion 3.2.4b (COLSS in service)or 3.2.4d (COLSS out of service)is satisfied and the Reactor Power Cutback System is disabled, and Within 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />s: a)All full-length and part-length CEA groups must abc withdrawn within the limits of Specifica-tions 3.1.3.5, 3.l.3.6b, and 3.1.3.7b, except during surveillance testing pursuant to the requirements of Specification 4.1.3.1.2.Specifi-cation 3.1.3.6b allows CEA Group 5 insertion to no further than 127.5 inches withdrawn.
a ACTION 7 b)The"RSPT/CEAC Inoperable" addressable constant*in the CPCs-is set to indicate that both CEAC's are inoperable.
r c)The Control Element Drive Mechanism Control System (CEDMCS)is placed in and subsequently maintained in the"Standby" mode except during CEA motion permitted by Specifications 3.1.3.5, 3.1.3.6b and 3.l.3.7b, when the CEOMCS may be.operated in either the"Manual Group" or"Manual Individual" mode.3.CEA position surveillance must meet the requirements of Specifications 4.1.3.1.1, 4.1.3.5, 4.1.3.6 and 4.1.3.7 except during surveillance testing pursuant, to Specification 4.1.3.1.2.
With three or more auto restarts, excluding periodic auto restarts (Code 30 and Code 33), of one non-bypassed calculator during a 12"hour interval, demonstrate calculator OPERABILITY by performing a CHANNEL FUNCTIONAL TEST within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.ACTION 8-With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement,, restore an inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open an affected reactor trip breaker within the next hour.~i~'>>'a a.>>uw 4a.a af O'PKRkb'LE.
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