Proposed Tech Specs,Permitting Delay of Scheduled three-yr Inspections of Flywheels on All Four RCPs Until Completion of 2R13 Refueling Outage,Scheduled for Winter of 1998-99| ML20141H262 |
| Person / Time |
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| Site: |
Arkansas Nuclear  |
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| Issue date: |
04/18/1997 |
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| From: |
ENTERGY OPERATIONS, INC. |
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| To: |
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| Shared Package |
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| ML20141H260 |
List: |
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| References |
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| NUDOCS 9705230255 |
| Download: ML20141H262 (3) |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20216G0881999-09-19019 September 1999
Proposed Tech Specs Pages,Changing TS 4.18.5.a.9 & Associated Bases for One Cycle of Operation Through End of Cycle 16 for Suppl Use of OTSG Repair Roll Technology
ML20216G0721999-09-17017 September 1999
Proposed Tech Specs,Revising Once Through SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Volumetric Integranular Attack
ML20212F5851999-09-17017 September 1999
Proposed Tech Specs Pages,Changing TS by Revising Curie Limits for Radioactive Gas Storage Tanks
ML20211P0061999-09-0707 September 1999
Proposed TS in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria
ML20211B3291999-08-19019 August 1999
Proposed TS 4.18.3.a.4 Clarification Supporting Tube End Cracking Alternative Repair Criteria
ML20211C1701999-08-18018 August 1999
Proposed Tech Specs Revising ESAS Low RCS Pressure Setpoint to Ensure That TS Adequately Bounds Safety Analysis
ML20211C4101999-08-18018 August 1999
Proposed Tech Specs Removing Requiremets for Tube Repair (Sleeving) & Clarifying Requirements for Preservice & ISI of Tubes to Facilitate Replacement of Original SGs
ML20210K5121999-07-29029 July 1999
Proposed Tech Specs,Revising Requirements Associated with Plant Station Batteries & DC Sources to 125 Vdc Switchyard Distribution Sys
ML20210K3571999-07-29029 July 1999
Proposed Tech Specs Revising SRs Pertaining to ISI Requirements for SG Tube Circumferential Cracking at top-of-tubesheet During 2P99 Planned mid-cycle Outage
ML20209H5811999-07-14014 July 1999
Proposed Tech Specs Revising RB Structural Integrity Requirements Re ISI Reporting for Containment Structures, Tendons & Anchorages
ML20209H8701999-07-14014 July 1999
Proposed Tech Specs 6.2.2 & 6.2.2.h,replacing Functional Description of Operations Staff Middle Manager with Ref to Functional Description Assistant Operations Manager & Revising TS Table 6.2-1 Item 5 & TS 6.2.2.f
ML20209H9721999-07-14014 July 1999
Proposed Tech Specs Changes for Elimination of Programmatic Requirements Associated with PASS & Regulatory Relief from PASS Requirements of NUREG-0737 & RG 1.97
ML20195D2371999-06-0101 June 1999
Proposed Tech Specs Re Surveillance Requirements & Applicable Bases Relevant to ISI Requirements for Portions of once-through SG (OTSG) Tubes Adjacent to Primary Cladding Region of tube-to Tubesheet Roll
ML20206T2651999-05-14014 May 1999
Proposed Tech Specs Revising SG Tubing SRs
ML20206Q1281999-05-10010 May 1999
Proposed Tech Specs Bases,Page B 2-2,discussing Guidance to Be Used When Applying Later Editions & Addendas of ASME Code to RCS Components
ML20205P4081999-04-0909 April 1999
Proposed Tech Specs Changes,Revising Reactor Bldg Structural Integrity Requirements
ML20205P6291999-04-0909 April 1999
Proposed Tech Specs Changes,Revising Battery Requirements
ML20205P3731999-04-0909 April 1999
Revised Proposed TS Page 5-1 Re Design Features Conversion
ML20205P6931999-04-0909 April 1999
Proposed Tech Specs Change,Adding Specification 3.0.6 & Associated Bases to ANO-2
ML20207C0631999-02-25025 February 1999
Proposed Tech Specs Change Revising Action 2 Associated with Table 3.3-1, Reactor Protective Instrumentation. Change Adds Footnote to Action 2 Allowing Startup with Functional Units Associated with Channel D Excore Inoperable
ML20207M7561999-02-24024 February 1999
Proposed Tech Specs,Allowing Startup & Continued Operation of Plant with Channel D Detector Until New Detector Is Installed During mid-cycle Outage Scheduled for Nov 1999
ML20198K1341998-12-17017 December 1998
Corrected Tech Specs Pages to 980629 Application for Amend to License NPF-6
ML20198A3661998-12-0808 December 1998
Proposed Tech Specs B3/4 6-3 & B3/4 6-4,deleting All Requirements Associated with Sodium H Addition Sys & Adding New Requirements for Trisodium Phosphate to Be Stored in Containers Located on Floor of Cb
ML20196B4381998-11-24024 November 1998
Proposed Tech Specs Pages,Changing Administrative Controls Section to Implement Consolidated QA Plan Manual & Clarifying Responsibilities on STA Position on Shift
ML20153D8491998-09-17017 September 1998
Proposed Tech Specs 2.2.1,3.3.1.1 & 3.3.2.1 Re Operating Bypass Setpoint
ML20236Y5081998-08-0606 August 1998
Proposed Tech Specs Section 3.3.4.B Re Sodium Hydroxide Tank Limits
ML20236Y5251998-08-0606 August 1998
Proposed Tech Specs Section 3.1.3.2,revising Action Requirements for CEA Position Indicator Channels
ML20236Y5951998-08-0606 August 1998
Proposed Tech Specs,Revising Requirements Associated W/Units 1 & 2 Control Room Emergency Ventilation Sys
ML20236Q2781998-07-13013 July 1998
Proposed Tech Specs Re Safety Limits & Limiting Safety Settings
ML20236G6921998-06-29029 June 1998
Proposed Tech Specs,Revising TS 3.4.2 & TS 3.4.12 Re Reactor Coolant Sys Safety Valves & Low Temp Overpressure Protection
ML20236G5421998-06-29029 June 1998
Proposed Tech Specs,Revising Surveillance Testing Requirements for Unit 2 Direct Current Electrical Distribution Sys
ML20236G4911998-06-29029 June 1998
Proposed Tech Specs Re MSSVs & Pressurizer Safety Valves
ML20236G5631998-06-29029 June 1998
Proposed Tech Specs,Revising Table 3.3-4 to Provide Range of Acceptable Values for 4160 Volt Bus Loss of Voltage Values
ML20217M2621998-04-30030 April 1998
Proposed Tech Specs Re DG Load Rejection Testing
ML20217N6141998-04-30030 April 1998
Proposed Tech Specs 1.6.1,revising Definition of Quadrant Power Tilt
ML20217M4871998-04-28028 April 1998
Proposed Tech Specs Changing Order of Channel Rotation During Outage for Scheduling Flexibility,While Still Requiring Rotation Schedule to Be Established for Operating Cycle
ML20217P8141998-04-0101 April 1998
Proposed Tech Specs Re Upper Tubesheet Volumetric Indications to Remain in Svc for Cycle 15
ML20216J7841998-03-17017 March 1998
Proposed Tech Specs Bases Change Concerning Plant Protection Sys Matrix Logic Testing
ML20203D1061998-02-18018 February 1998
Proposed Tech Specs Revising Surveillance Testing Requirements for Emergency Feedwater Sys
ML20202G9771998-02-0909 February 1998
Proposed Tech Specs Pages,Allowing Use of Repair Roll Technology (Reroll) for Upper Tubesheet Region of SGs
ML20197A8421997-12-12012 December 1997
Proposed Tech Specs Re Establishment of Alternate Repair Criteria for Outer Diameter Intergranular Attack in Upper Tubesheet of Unit 1 SGs
ML20211C6441997-09-23023 September 1997
Proposed Tech Specs,Modifying RPS & ESFAS Trip Setpoint & Allowable Values for SG Low Pressure
ML20211C8911997-09-23023 September 1997
Proposed Tech Specs Reducing Min Required Reactor Coolant Sys Flow Rate Requirements Until ANO-2 SGs Are Replaced
ML20151J3371997-07-28028 July 1997
Proposed Tech Specs,Modifying Actions Associated W/Ts Table 3.3-1 for Reactor Protective Instrumentation & Table 3.3-3 for Esfa Sys Instrumentation
ML20149K0551997-07-21021 July 1997
Proposed Tech Specs,Revising Surveillance Testing Requirements for Facility EFW Sys as Specified in Specification 4.7.1.2
ML20141C5641997-06-18018 June 1997
Proposed Tech Specs Changes Restoring Table 2 to Table II & Revision to One of Offsite Dose Calculation Manual, Pages Previously Submitted.Also Includes Amended Pages Modified to Amends Issued Since Change Request Submitted
ML20141A8001997-05-0808 May 1997
Proposed Tech Specs 3/4.3.1 & 3/4.3.2 Requesting Removal of Reference to CE NPSD-576
ML20138H8521997-05-0202 May 1997
Proposed Tech Specs,Submitting Rev to Original TS Change Request to Reduce Limit Specified in Section 3.1.6.3.b for Leakage Through SG Tubes of Any One Sg,Per SG Tube Insp Surveillance Requirements
ML20138D6411997-04-24024 April 1997
Proposed Tech Specs Revising Requirements for Sample Scope Initial Size & Expansion for Inservice Insp of Steam Generator Tube Sleeves
ML20141H2621997-04-18018 April 1997
Proposed Tech Specs,Permitting Delay of Scheduled three-yr Inspections of Flywheels on All Four RCPs Until Completion of 2R13 Refueling Outage,Scheduled for Winter of 1998-99
1999-09-07
[Table view]
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217N3171999-10-19019 October 1999
Rev 1,change 024-01-0 to OP-1903.011, Emergency Response Notifications
ML20217J7641999-10-0505 October 1999
Rev 1 to Unit 1 Technical Requirement Manual, Replacing Index Page
ML20216G0881999-09-19019 September 1999
Proposed Tech Specs Pages,Changing TS 4.18.5.a.9 & Associated Bases for One Cycle of Operation Through End of Cycle 16 for Suppl Use of OTSG Repair Roll Technology
ML20212F5851999-09-17017 September 1999
Proposed Tech Specs Pages,Changing TS by Revising Curie Limits for Radioactive Gas Storage Tanks
ML20216G0721999-09-17017 September 1999
Proposed Tech Specs,Revising Once Through SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Volumetric Integranular Attack
ML20211P0061999-09-0707 September 1999
Proposed TS in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria
ML20211B3291999-08-19019 August 1999
Proposed TS 4.18.3.a.4 Clarification Supporting Tube End Cracking Alternative Repair Criteria
ML20211C4101999-08-18018 August 1999
Proposed Tech Specs Removing Requiremets for Tube Repair (Sleeving) & Clarifying Requirements for Preservice & ISI of Tubes to Facilitate Replacement of Original SGs
ML20211C1701999-08-18018 August 1999
Proposed Tech Specs Revising ESAS Low RCS Pressure Setpoint to Ensure That TS Adequately Bounds Safety Analysis
ML20210N5541999-08-0404 August 1999
Rev 28,Permanent Change 4 to OP-1903.061, Communication Equipment Test
ML20210N5571999-08-0404 August 1999
Rev 23,Permanent Change 5 to OP-1903.011, Emergency Response/Notifications
ML20210K5121999-07-29029 July 1999
Proposed Tech Specs,Revising Requirements Associated with Plant Station Batteries & DC Sources to 125 Vdc Switchyard Distribution Sys
ML20210K3571999-07-29029 July 1999
Proposed Tech Specs Revising SRs Pertaining to ISI Requirements for SG Tube Circumferential Cracking at top-of-tubesheet During 2P99 Planned mid-cycle Outage
ML20209H5811999-07-14014 July 1999
Proposed Tech Specs Revising RB Structural Integrity Requirements Re ISI Reporting for Containment Structures, Tendons & Anchorages
ML20209H8701999-07-14014 July 1999
Proposed Tech Specs 6.2.2 & 6.2.2.h,replacing Functional Description of Operations Staff Middle Manager with Ref to Functional Description Assistant Operations Manager & Revising TS Table 6.2-1 Item 5 & TS 6.2.2.f
ML20209H9721999-07-14014 July 1999
Proposed Tech Specs Changes for Elimination of Programmatic Requirements Associated with PASS & Regulatory Relief from PASS Requirements of NUREG-0737 & RG 1.97
ML20195D2371999-06-0101 June 1999
Proposed Tech Specs Re Surveillance Requirements & Applicable Bases Relevant to ISI Requirements for Portions of once-through SG (OTSG) Tubes Adjacent to Primary Cladding Region of tube-to Tubesheet Roll
ML20206T2651999-05-14014 May 1999
Proposed Tech Specs Revising SG Tubing SRs
ML20206Q1281999-05-10010 May 1999
Proposed Tech Specs Bases,Page B 2-2,discussing Guidance to Be Used When Applying Later Editions & Addendas of ASME Code to RCS Components
ML20206J8021999-05-0404 May 1999
PC-03 to Procedure/Work Plan 1904-002, Offsite Dose Projections Rdacs Computer Method
ML20205P6931999-04-0909 April 1999
Proposed Tech Specs Change,Adding Specification 3.0.6 & Associated Bases to ANO-2
ML20205P3731999-04-0909 April 1999
Revised Proposed TS Page 5-1 Re Design Features Conversion
ML20205P6431999-04-0909 April 1999
Revised Proposed Technical Requirement Manual Pages
ML20205P4081999-04-0909 April 1999
Proposed Tech Specs Changes,Revising Reactor Bldg Structural Integrity Requirements
ML20205P6291999-04-0909 April 1999
Proposed Tech Specs Changes,Revising Battery Requirements
ML20207C0631999-02-25025 February 1999
Proposed Tech Specs Change Revising Action 2 Associated with Table 3.3-1, Reactor Protective Instrumentation. Change Adds Footnote to Action 2 Allowing Startup with Functional Units Associated with Channel D Excore Inoperable
ML20207M7561999-02-24024 February 1999
Proposed Tech Specs,Allowing Startup & Continued Operation of Plant with Channel D Detector Until New Detector Is Installed During mid-cycle Outage Scheduled for Nov 1999
ML20198K1341998-12-17017 December 1998
Corrected Tech Specs Pages to 980629 Application for Amend to License NPF-6
ML20198A3661998-12-0808 December 1998
Proposed Tech Specs B3/4 6-3 & B3/4 6-4,deleting All Requirements Associated with Sodium H Addition Sys & Adding New Requirements for Trisodium Phosphate to Be Stored in Containers Located on Floor of Cb
ML20196B4381998-11-24024 November 1998
Proposed Tech Specs Pages,Changing Administrative Controls Section to Implement Consolidated QA Plan Manual & Clarifying Responsibilities on STA Position on Shift
ML20196C9761998-11-24024 November 1998
Rev 1 to Unit 2 Technical Requirements Manual
ML20154D6681998-10-0101 October 1998
Rev 28 to Procedure/Work Plan 1904.002, Offsite Dose Projections Rdacs Computer Method
ML20153D8491998-09-17017 September 1998
Proposed Tech Specs 2.2.1,3.3.1.1 & 3.3.2.1 Re Operating Bypass Setpoint
ML20153H1651998-08-12012 August 1998
Rev 0 to ANO Units 1 & 2 Technical Requirements Manual
ML20236Y5251998-08-0606 August 1998
Proposed Tech Specs Section 3.1.3.2,revising Action Requirements for CEA Position Indicator Channels
ML20236Y5081998-08-0606 August 1998
Proposed Tech Specs Section 3.3.4.B Re Sodium Hydroxide Tank Limits
ML20236Y5951998-08-0606 August 1998
Proposed Tech Specs,Revising Requirements Associated W/Units 1 & 2 Control Room Emergency Ventilation Sys
ML20236Q2781998-07-13013 July 1998
Proposed Tech Specs Re Safety Limits & Limiting Safety Settings
ML20236G6921998-06-29029 June 1998
Proposed Tech Specs,Revising TS 3.4.2 & TS 3.4.12 Re Reactor Coolant Sys Safety Valves & Low Temp Overpressure Protection
ML20236G5421998-06-29029 June 1998
Proposed Tech Specs,Revising Surveillance Testing Requirements for Unit 2 Direct Current Electrical Distribution Sys
ML20236G5631998-06-29029 June 1998
Proposed Tech Specs,Revising Table 3.3-4 to Provide Range of Acceptable Values for 4160 Volt Bus Loss of Voltage Values
ML20236G4911998-06-29029 June 1998
Proposed Tech Specs Re MSSVs & Pressurizer Safety Valves
ML20199F7211998-05-22022 May 1998
Rev 8 to Simulator Mod Control,Training Desk Guide 6.3
ML20217N6141998-04-30030 April 1998
Proposed Tech Specs 1.6.1,revising Definition of Quadrant Power Tilt
ML20217M2621998-04-30030 April 1998
Proposed Tech Specs Re DG Load Rejection Testing
ML20217M4871998-04-28028 April 1998
Proposed Tech Specs Changing Order of Channel Rotation During Outage for Scheduling Flexibility,While Still Requiring Rotation Schedule to Be Established for Operating Cycle
ML20217P8141998-04-0101 April 1998
Proposed Tech Specs Re Upper Tubesheet Volumetric Indications to Remain in Svc for Cycle 15
ML20216J7841998-03-17017 March 1998
Proposed Tech Specs Bases Change Concerning Plant Protection Sys Matrix Logic Testing
ML20203D1061998-02-18018 February 1998
Proposed Tech Specs Revising Surveillance Testing Requirements for Emergency Feedwater Sys
ML20202G9771998-02-0909 February 1998
Proposed Tech Specs Pages,Allowing Use of Repair Roll Technology (Reroll) for Upper Tubesheet Region of SGs
1999-09-07
[Table view] |
Text
1
, REACTOR COOLANT SYSTEM i
3/4'.4.10 STRUCTURAL INTEGRITY ASME CODE CLASS 1, 2 AND 3 COMPONENTS LIMITING CONDITION FOR OPERATION 3.4.10.1 The structural integrity of ASME Code Class 1, 2 and 3 components shall be mainta's.ed in accordance with Specification 4.4.10.1. ,
l APPLICABILITY: ALL MODES l
)
ACTION:
- a. With the structural integrity of any ASME Code Class 1 componentis) not conforming to the above requirements, restore {
the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature more than 50*F above the minimum temperature required by NDT considerations.
- b. With the structural integrity of any ASME Code Class 2 !
component (s) not conforming to the above requirements, restore !
the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to !
increasing the Reactor Coolant System temperature above 200*F.
- c. With the structural integrity of any ASME Code Class 3 component (s) not conforming to the above requirements, restore the structural integrity of the affected component to within its limit or isolate the affected component from service.
SURVEILLANCE REQUIREMENTS 4.4.10.1 In addition to the requirements of Specification 4.0.5, each Reactor Coolant Pump flywheel shall be inspected per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975.*
i
- The ultrasonic volumetric examination of the areas of higher stress !
concentration at the bore and keyway of the flywheels for all four reactor !
coolant pumps nay be extended through completion of the 2R13 refueling outage.
9705230255 970418 PDR ADOCK 05000368 P PDR ARKANSAS - UNIT 2 3/4 4-26 Amendment No. M4,46 ,
e e a e
s MARKUP OF CURRENT ANO-2 TECHNICAL SPECIFICATIONS (FOR INFORMATION ONLY) i l
l i
. REACTOR COOLANT SYSTEM 3/4'.4.10 STRUCTURAL INTEGRITY ASME CODE CLASS 1, 2 AND 3 COMPONENTS LIMITING CONDITION FOR OPERATION 3.4.10.1 The structural integrity of ASME Code Class 1, 2 and 3 components shall be naintained in accordance with Specification 4.4.10.1.
APPLICABILITY: ALL MODES ;
ACTION:
- a. With the structural integrity of any ASME Code Class 1 component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature more than 50*F above the minimum temperature required by NDT considerations.
- b. With the structural integrity of any ASME Code Class 2 component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within i its limit or isolate the affected component (s) prior to j increasing the Reactor Coolant System temperature above 200*F.
- c. With the structural integrity of any ASME Code Class 3 component (s) not conforming to the above requirements, restore the structural integrity of the affected component to within its limit or isolate the affected component from service.
l l
SURVEILLANCE REQUIREMENTS 4.4.10.1 In addition to the requirements of Specification 4.0.5, each Reactor Coolant Pump flywheel shall be inspected per the recommendations of .
Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August I 1975.*
- For reactor ccolant pump 2P3J?., t-he-The ultrasonic volumetric examination of the areas of higher stress concentration at the bore and keyway of the gywheels for all four reactor coolant pumps may be extended through goInpletion of the GRF2 2R13 refueling outage.
ARKANSAS - UNIT 2 3/4 4 26 Amendment No. -144,-146,