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| {{#Wiki_filter:l:ONTRGLLEV BV'SER REACTOR COOLANT SYSTEM 3/4.4.5 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.5.1 The following Reactor Coolant System leakage detection systems shall be OPERABLE: a.-A-cpm b.-Th-Qe-seam APPLICABILITY: | | {{#Wiki_filter:l:ONTRGLLEV BV'SER REACTOR COOLANT SYSTEM 3/4. 4.5 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.5.1 The following Reactor Coolant System leakage detection systems shall be OPERABLE: |
| MODES 1, 2, 3, and 4.ACTION: two of the above required leakage detection system operation may r up to 30 days provide amples of the containment atmosphere are o a zed at least once per 24 hours when the requiired gaseo particulate ra'onitoring system is inoperab use, be in at least HOT STANDBY within t e s LD SHUTDOMN within the following 30 hours.SURVEILLANCE RE UIREMENTS 4.4.5.1 The leakage detection systems shall be demonstrated OPERABLE by: a.b.Containment atmosphere gaseous and particulate monitoring system-performance of CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies specified in Table 4.3-3, Containment sump level and flow monitoring system-performance of CHANNEL CALIBRATION at least once per 18 months.8811210159 881109 PDR ADOCK 05000523 P PDC~i'ALo vEROE'=UN[/ | | : a. -A-cpm |
| j~3/4 4-18 CGNTiRQLLEB BY UgER l b REACTOR COOLANT SYSTEM 3/4.4.5 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.5.1 The following Reactor Coolant System leakage detection systems shall be OPERABLE: b.APPLICABILITY: | | : b. Th Qe-seam APPLICABILITY: MODES 1, 2, 3, and 4. |
| NODES 1, 2, 3, and 4.ACTION:-o two of the above required leakage detection systems OP operation may c'up to 30 days provided es of the containment atmosphere are o e at least once per 24 hours when the required gaseous articulate | | ACTION: |
| 't~monitoring system is inoperabl.'se, be in at least HOT STANDBY with>n nours an'D SHUTDOWN within the following 30 hours.SURVEILLANCE RE UIREHENTS 4.4.5.1 The leakage detection systems snail be demonstrated OPERABLE by: a.Containment atmosphere gaseous and particulate monitoring system-performance of CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies specified in Table 4.3-3, b.Containment sump level and flow monitoring system-performance of CHANNEL CALIBRATION at least once per 18 months. | | two of the above required leakage detection system operation may r up to 30 days provide amples of the containment atmosphere are o a when the requiired gaseo is inoperab particulate ra use, be in at least |
| gPoNTROLLED BY USE REACTOR COOLANT SYSTEM 3/4.4.5 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.5.1 The following Reactor Coolant System leakage detection systems shall be OPERABLE: b.~~~APPLICABILITY: | | 'onitoring zed at least once per 24 hours HOT STANDBY within t e system s |
| MODES 1, 2, 3, and 4;ACTION: two of the above required leakage detection systems operation may c r up to 30 days provide mples of the containment atmosphere are ob a zed at least once per 24 hours when the required gaseou particulate ra'nito ing system is inoperabl.w>se, be in at least HOT STANDBY within the ne D SHUTDOWN within the following 30 hours.SURVEILLANCE RE UIREMENTS 4.4.5.1 The leakage detection systems shall be demonstrated OPERABLE by: a.Containment atmosphere gaseous and particulate monitoring system-performance of CHANNEL, CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies specified in Table 4.3-3, b.Containment sump level and flow monitoring system-performance of CHANNEL CALIBRATION at least once per 18 months.!PALO VERDE-UNIT 3~~3/4 4-18 | | LD SHUTDOMN within the following 30 hours. |
| -0 INSERT 3.4.5.1 The following Reactor Coolant System leakage detection system shall be OPERABLE: Either the containment atmosphere gaseous radioactivity or containment atmosphere particulate radioactivity monitoring system, and b.The containment sump level and flow monitoring system.APPLICABILITY: | | SURVEILLANCE RE UIREMENTS |
| Modes 1, 2, 3 and 4.ACTION: With either/or both the containment atmosphere gaseous radioactivity and containment atmosphere particulate radioactivity monitors INOPERABLE, operation may continue for up to 30 days provided the containment sump level and flow monitoring system is OPERABLE and gaseous and/or particulate grab samples of the containment atmosphere are obtained at least once per 12 hours and analyzed within the subsequent 3 hours;otherwise, be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.With the containment sump level and flow monitoring system INOPERABLE, operation may continue for up to 30 days provided the containment atmosphere gaseous radioactivity monitoring and the containment atmsophere particulate radioactivity monitoring systems are OPERABLE;otherwise, be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. | | : 4. 4.5. 1 The leakage detection systems shall be demonstrated OPERABLE by: |
| -~t e%-}} | | : a. Containment atmosphere gaseous and particulate monitoring system-performance of CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies specified in Table 4.3-3, |
| | : b. Containment sump level and flow monitoring system-performance of CHANNEL CALIBRATION at least once per 18 months. |
| | 8811210159 881109 PDR ADOCK 05000523 PDC P |
| | ~i'ALo vEROE'=UN[/ j~ 3/4 4-18 CGNTiRQLLEB BY UgER |
| | |
| | l b |
| | |
| | REACTOR COOLANT SYSTEM 3/4.4.5 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.5. 1 The following Reactor Coolant System leakage detection systems shall be OPERABLE: |
| | b. |
| | APPLICABILITY: NODES 1, 2, 3, and 4. |
| | ACTION: |
| | -o two of the above required leakage detection systems OP operation may c up to 30 days provided es of the containment atmosphere are o at least once per 24 hours e |
| | 't~ |
| | 'D is inoperabl an |
| | 'se,within when the required gaseous SHUTDOWN be in at articulate least HOT STANDBY the following 30 hours. |
| | with>n monitoring system nours SURVEILLANCE RE UIREHENTS 4.4.5.1 The leakage detection systems snail be demonstrated OPERABLE by: |
| | : a. Containment atmosphere gaseous and particulate monitoring system-performance of CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies specified in Table 4.3-3, |
| | : b. Containment sump level and flow monitoring system-performance of CHANNEL CALIBRATION at least once per 18 months. |
| | |
| | gPoNTROLLED BY USE REACTOR COOLANT SYSTEM 3/4. 4.5 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.5.1 The following Reactor Coolant System leakage detection systems shall be OPERABLE: |
| | b.~ |
| | ~ |
| | APPLICABILITY: ~ |
| | MODES 1, 2, 3, and 4; ACTION: |
| | two of the above required leakage detection systems operation may c r up to 30 days provide mples of the containment atmosphere are ob a when the required gaseou is inoperabl . |
| | particulate ra 'nito zed at least once per 24 hours w>se, be in at least HOT STANDBY within the ne ing system D SHUTDOWN within the following 30 hours. |
| | SURVEILLANCE RE UIREMENTS 4.4.5. 1 The leakage detection systems shall be demonstrated OPERABLE by: |
| | : a. Containment atmosphere gaseous and particulate monitoring system-performance of CHANNEL, CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies specified in Table 4.3-3, |
| | : b. Containment sump level and flow monitoring system-performance of CHANNEL CALIBRATION at least once per 18 months. |
| | !PALO VERDE - UNIT 3~~ 3/4 4-18 |
| | |
| | - 0 INSERT 3.4.5.1 The following Reactor Coolant System leakage detection system shall be OPERABLE: |
| | Either the containment atmosphere gaseous radioactivity or containment atmosphere particulate radioactivity monitoring system, and |
| | : b. The containment sump level and flow monitoring system. |
| | APPLICABILITY: Modes 1, 2, 3 and 4. |
| | ACTION: |
| | With either/or both the containment atmosphere gaseous radioactivity and containment atmosphere particulate radioactivity monitors INOPERABLE, operation may continue for up to 30 days provided the containment sump level and flow monitoring system is OPERABLE and gaseous and/or particulate grab samples of the containment atmosphere are obtained at least once per 12 hours and analyzed within the subsequent 3 hours; otherwise, be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. |
| | With the containment sump level and flow monitoring system INOPERABLE, operation may continue for up to 30 days provided the containment atmosphere gaseous radioactivity monitoring and the containment atmsophere particulate radioactivity monitoring systems are OPERABLE; otherwise, be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. |
| | |
| | t |
| | - ~ e %-}} |
|
|---|
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
l:ONTRGLLEV BV'SER REACTOR COOLANT SYSTEM 3/4. 4.5 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.5.1 The following Reactor Coolant System leakage detection systems shall be OPERABLE:
- a. -A-cpm
- b. Th Qe-seam APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
two of the above required leakage detection system operation may r up to 30 days provide amples of the containment atmosphere are o a when the requiired gaseo is inoperab particulate ra use, be in at least
'onitoring zed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> HOT STANDBY within t e system s
LD SHUTDOMN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE RE UIREMENTS
- 4. 4.5. 1 The leakage detection systems shall be demonstrated OPERABLE by:
- a. Containment atmosphere gaseous and particulate monitoring system-performance of CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies specified in Table 4.3-3,
- b. Containment sump level and flow monitoring system-performance of CHANNEL CALIBRATION at least once per 18 months.
8811210159 881109 PDR ADOCK 05000523 PDC P
~i'ALo vEROE'=UN[/ j~ 3/4 4-18 CGNTiRQLLEB BY UgER
l b
REACTOR COOLANT SYSTEM 3/4.4.5 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.5. 1 The following Reactor Coolant System leakage detection systems shall be OPERABLE:
b.
APPLICABILITY: NODES 1, 2, 3, and 4.
ACTION:
-o two of the above required leakage detection systems OP operation may c up to 30 days provided es of the containment atmosphere are o at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> e
't~
'D is inoperabl an
'se,within when the required gaseous SHUTDOWN be in at articulate least HOT STANDBY the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
with>n monitoring system nours SURVEILLANCE RE UIREHENTS 4.4.5.1 The leakage detection systems snail be demonstrated OPERABLE by:
- a. Containment atmosphere gaseous and particulate monitoring system-performance of CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies specified in Table 4.3-3,
- b. Containment sump level and flow monitoring system-performance of CHANNEL CALIBRATION at least once per 18 months.
gPoNTROLLED BY USE REACTOR COOLANT SYSTEM 3/4. 4.5 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.5.1 The following Reactor Coolant System leakage detection systems shall be OPERABLE:
b.~
~
APPLICABILITY: ~
MODES 1, 2, 3, and 4; ACTION:
two of the above required leakage detection systems operation may c r up to 30 days provide mples of the containment atmosphere are ob a when the required gaseou is inoperabl .
particulate ra 'nito zed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> w>se, be in at least HOT STANDBY within the ne ing system D SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE RE UIREMENTS 4.4.5. 1 The leakage detection systems shall be demonstrated OPERABLE by:
- a. Containment atmosphere gaseous and particulate monitoring system-performance of CHANNEL, CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies specified in Table 4.3-3,
- b. Containment sump level and flow monitoring system-performance of CHANNEL CALIBRATION at least once per 18 months.
!PALO VERDE - UNIT 3~~ 3/4 4-18
- 0 INSERT 3.4.5.1 The following Reactor Coolant System leakage detection system shall be OPERABLE:
Either the containment atmosphere gaseous radioactivity or containment atmosphere particulate radioactivity monitoring system, and
- b. The containment sump level and flow monitoring system.
APPLICABILITY: Modes 1, 2, 3 and 4.
ACTION:
With either/or both the containment atmosphere gaseous radioactivity and containment atmosphere particulate radioactivity monitors INOPERABLE, operation may continue for up to 30 days provided the containment sump level and flow monitoring system is OPERABLE and gaseous and/or particulate grab samples of the containment atmosphere are obtained at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and analyzed within the subsequent 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
With the containment sump level and flow monitoring system INOPERABLE, operation may continue for up to 30 days provided the containment atmosphere gaseous radioactivity monitoring and the containment atmsophere particulate radioactivity monitoring systems are OPERABLE; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
t
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