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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] |
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N 9 4.18 STEAM GENERATOR TUBING SURVEILLANCE !
6" !
!A J plicability ,
i j Applies to the surveillance of tubing of each steam generator. I Objective A"
., 30 ensure integrity of the steam generator tubing through a defined inservice surveillanc9 program, and to minimize exposure of personnel to ;
4 radiation during performance of the surveillanco program, j m.
Specification -l i
4.18.1 Baseline inspection i 4
c The first steam generator tubing inspection performed according to i Specifications 4.18.2 and 4.18.3.a shall be cunsidered as constituting the .!
baseline condition for subsequent inspections.
4.18.2 Cxamination Methods
- a. Inservice inspection of steam gene *ator tubing shall include ,
non-destructive examination by eddy-current testing or other i equivalent technioues. The inspection equipment shall provide a sensitivity that will detect defects with a penetration of 20 percent or more of the minimum allowable +
as-manufactured tube wall thickness except for a sleeved ,
tube.at the lower sleeve end, i
- b. For examination of the sleeved steam generator tubing at the
' lower sleeve end, the indications will be compared to those +
obtained during the baseline sleeved tube inspection, i Significant deviations between these indications will be ,
considered sufficient evidence to warrant designation as a -
degraded tube. Direct quantification of the 40 percent through-wall plugging limit is available with eddy-current <
testing. >
4.18.3 Selection and Testina The steam generator sample size is specified in Table 4.18-1. The steam l generator tube minimum-sample size, inspection result classification. and >
the corresponding ection required shall be as specified in Table 4.18-2. l The inservice inspedion of steam generator tubes shall be performed at the ,
frequencies specified in Specification 4.18.4 and the inspected tubes shall .
be verified acceptable per the acceptance criteria of Specification 4.18.5.
The tubes selected for each inservice inspection shall include at least 3% of the total number of tubes in both steam generators; the tubes selected for these inspections shall be selected on a random basis except: ;
t i
Amendment No. 24, #1, 86, 166 110j ,
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t A tube inspection (pursuant to Specification 4.18.5.a.9) shall'be performed on each selected tube. If any selected tube does not ,
' permit the passage of the eddy current probe for a tube '
inspection, this shall be recorded and an adjacent' tube shall be
- . selected and subjected to a tube inspection. t
- 3. Tubes in the following groups may be excluded from the first c random sample if all tubes in a group in both steam generators are inspected. The inspection may be -
- c. concentrated on those portions of the tubes where s imperfections were previously found. No credit will be L taken for these tubes in meeting minimum sample size '
[ requirements. Where only a portion of the tube is it inspected, the remainder of the tube will be subjected to !
l the random inspection.
(1) Group A-1: Tubes within one, two or three rows of the open inspection lane.
(2) Group A-2: Unplugged tubes with sleeves installed. ,
(3) Group A-3: Tubes in the wedge-shaped group on either side of the lane region (Group M 1) as :
defined by figure 4.18.1.
- b. The second and third sample inspections during each inservice '
inspection as required by Table 4.18-2 may be less than a full l tube inspection by concentrating the inspection on those areas of the tube sheet array and on those portions of the tubes where tubes with imperfections were previously found.
L The results of each sample .spection shall be classified into one of the '
following three categories:
Category Inspection Results C-1 Less than 5% of the total tubes inspected are degraded tubes and none of the inspected tubes -i are defective. ,
C-2 One or more tubes, but not more ,
than 1% of the total tubes inspected, are defective, or between 5% and 10% of the total tubes inspected are degraded tubes.
C-3 More than 10% of the total -
tubes inspected are degraded '
s tubes or more than 1% of the i inspected tubes are defective.
I
~ Amendment No. 2A, AI, 86, 106 110k l
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NOTES: (1) In all inspections, previously degraded tubes whose degradations have not been spanned by a sleeve must exhibit significant (>10%) further wall penetrations to be included in the above percentage calculations, t (2) Where special inspections are performed pursuant to 4.18.3.a.3, defective or degraded tubes found as a h result of the inspection shall be included in determining the Inspection Results Category for that r
special inspection but need not be included in determining the Irspection Results Category for the general steam ge h rator inspection.-
!' 4.18.4 Inspection Intervals The above-required inservice inspections of steam generator tubes shall be performed at the following frequencies:
- a. The baseline inspection shall be performed during the first refueling shutdown. Subsequent inservice inspections shall be i performed at intervals of not less than 10 nor more than 24 calendar months after the previous inspection. If the results of two consecutive inspections for a given group
- of tubes following i service under all volatile treatment (AVT) conditions fall into the'C-1 category or if two consecutive inspections demonstrate that previously observed degradation has not continued and no additional degradation has occurred, the inspection interval for that group may be extended to a maximum of 40 months.
- b. If the results of the inservice inspection of a steam generator performed in accordance with Table 4.18-2 at 40-month intervals l for a given group
- of tubes fall in Category C-3, subsequent inservice inspections shall be performed at intervals of not less than 10 nor more than 20 calendar months after the previous i inspection. The increase in inspection frequency shall apply until a subsequent inspection meets the conditions specified in i 4.18.4.a and the interval can be extended to 40 maaths, f
- c. Additional unscheduled inservice inspections shall be performed on each steam generator in accordance with the first sample i L inspection specified in Table 4.18-2 during the shutdown l subsequent to any of the following conditions:
- 1. Primary-to-secondary leakage in excess of the limits of Specification 3.1.6.3.b (Inservice inspection not required if leaks originate from tube-to-tubesheet welds. If the le uing tube is from either Group A-1 or A-3 as defined in Specification 4.18.3.a.3, all of the tubes in the affected group in this steam generator may be inspected in lieu of
- A group of tubes means: (a) All tubes inspected pursuant to 4.18.3.a.3, or .
(b) All tubes in a steam generator less those inspected pursuant to 4.18.3.a.3. ;
Amendment No. 24, AZ, 26, 106 1101
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i the first sample inspection specified in Table 4.18-2. If the degradation mechanism which caused the leak is limited to a specific portion of the tube length, the inspretion per this paragraph may be limited to the affected portion of the q tube length. If.the results of this-inspection fall into i the C-3 category, all of the tubes in the same group in the '
other steam generator will also be similarly inspected.) ,
i ,
- 2. A seismic occurrence greater than the Operating Basis Earthquake,
- 3. A loss-of-coolant accident requiring actuation of the engineered safeguards, or
- 4. A main steam line or feedwater line break.
4.18.5 Acceptance Criteria
- a. As used in this specification:
- 1. Tubina or Tube means that portion of the tube or sleeve '
which forms the primary system to secondary system pressure boundary.
- 2. Imperfection means an exception to the dimensions, finish or contour of a tube from that required by fabrication drawings or specifications. Eddy current testing indications below 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections.
- 3. Degradation means a service-iriduced cracking, wastage, wear -
or general corrosion occurring on either the inside or outside of a tube. ,
- 4. Dearaded ' lube means a tube containing imperfections 5 20% of the nominal wall thickness caused by degradation, except. "
- where all degradation has been spanned by the installation L of a slesve.
- 5. % Dearadation means the percentage of the tube wall thickness affected or removed by degradation.
- 6. Defect means an imperfection of such severity that it exceeds the plugging limit except where the imperfection has been spanned by the installation of a sleeve. A tube '
containing a defect in its pressure boundary is defective.
n 7. Pluggina Limit means the imperfection depth at or beyond which the tube shall be restored to serviceability by the installation of a sleeve or removed from service because it .
may become unserviceable prior to the next inspection; it-is equal to 40% of the nominal tube wall thickness. -
Amendment No. 24 AI, 86, 106 110m ,
11
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- 8. Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural
, integrity in the event of an Operating Basis Earthquake, a l L loss-of-roolant accident, or a steam line or feedwater line ;
break as specified in Specification 4.18.4.c.
[ 9. Tube Inspection means an inspection of the steam generator i tube from the point of entry completely to the ooint of' exit, t.
[. b. The steam generator shall be determir.ed operable after completing i the corresponding actions (plug or sleeve all tubes exceeding the
- plugging limit and all tubes containing throu0 -wall h cracks) i 4
- . required by Table 4.18-2. I :
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Ame'dment n No. 24, AI, 86, 105, 110ml
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