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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211K6241999-08-31031 August 1999 Proposed Tech Specs,Changing ISFSI License Conditions 6,7 & 8 & TS 3/4.1 by Permitting Inclusion of Bpras & Thimble Plug Devices in Sf Assemblies Stored in TN-40 Casks ML20206R0621999-05-13013 May 1999 Proposed Tech Specs,Removing Plant Organization Structure Requirement ML20205S3331999-04-20020 April 1999 Proposed Tech Specs Changing Implementation Date for Relocation from TS to UFSAR of Requirements in TS 3.1.E & Flooding Shutdown Requirements in TS 5.1 ML20205Q0351999-04-12012 April 1999 Proposed Tech Specs,Relocating Shutdown Margin Requirements from TS to COLR ML20204H3601999-03-19019 March 1999 Proposed Tech Specs Removing Dates of Two NRC SERs & Correcting Dates of One SER Listed in Section 2.C.4, Fire Protection ML20207F2901999-03-0101 March 1999 Proposed Revised Tech Specs Incorporating Combustion Engineering SG Welded Tube Sleeve TR Rev ML20203A2181999-02-0505 February 1999 Proposed Tech Specs,Changing TS 4.12, SG Tube Surveillance to Incorporate Changes to Abb C-E Sleeve Design Assumptions & Installation Techniques ML20196B9721998-11-25025 November 1998 Proposed Tech Specs,Allowing Limited Inoperability of Bast Level Channels & Transfer Logic Channels to Provide for Required Testing & Maint of Associated Components ML20155G6321998-11-0303 November 1998 Proposed Tech Specs B.3.1-7 & B.3.1-7a,rev 133A Re Reactor Coolant Sys ML20154S2101998-10-23023 October 1998 Proposed Tech Specs Clarifying Conditions That Constitute Operable Irpi Sys Channels ML20151U3651998-09-0404 September 1998 Proposed Tech Specs TS.3.1-5,TS.4.18-1 & B.4.18-1,clarifying SRs & LCOs for Operability for Reactor Coolant Vent Sys ML20237B5061998-08-12012 August 1998 Proposed Tech Specs Re Conformance of Administrative Controls Section 6 to Guidance of Std Tech Specs ML20236T6041998-07-20020 July 1998 Proposed Tech Specs Incorporating Elevated F* SG Tube Repair Criteria ML20249A7641998-06-11011 June 1998 Proposed Tech Specs Re Conformance of Administrative Controls Section 6 to Guidance of Std ML20216G0371998-04-13013 April 1998 Proposed Tech Specs 3.3 Re Engineered Safety Features ML20216D0591998-03-0606 March 1998 Proposed Tech Specs Updating Heatup & Cooldown Rate Curves, Incorporating Use of Pressure & Temp Limits Rept & Changing Pressurizer PORVs Operability Temp ML20217P0061998-03-0404 March 1998 Proposed Tech Specs Re Status of Relocated Requirements ML20217N9771998-03-0202 March 1998 Proposed Tech Specs 3.8.D Re Spent Fuel Pool Special Ventilation Sys ML20217P1431998-03-0202 March 1998 Proposed Tech Specs Re Conformance of Administrative Controls Section 6 to Guidance of Std ML20202E5691998-02-10010 February 1998 Proposed Tech Specs 1-1 Re One Time Reduction of Mode 6 Reactor Coolant Sys Boron Concentration ML20198N8301998-01-15015 January 1998 Proposed Tech Specs Pages Allowing Use of Moveable Incore Detector Thimble Reduction for Unit 1,cycle 19 ML20198P0791998-01-0808 January 1998 Proposed Tech Specs Pages Re Suppl 5 to 951214 LAR on Conformance of Administrative Controls Section 6 to Guidance of STS ML20198B1471997-12-29029 December 1997 Proposed TS marked-up & Revised Pages,Incorporating Changes Associated w/951214 LAR ML20212F0471997-10-28028 October 1997 Proposed Tech Specs Pages Revising TS Section 4.12,allowing Use of voltage-based SG Tube Repair Criteria ML20217F4761997-10-0303 October 1997 Suppl Proposed Tss,Allowing Use of New SG Tube Sleeve Designs & Installation & Exam Techniques ML20211H7581997-10-0101 October 1997 Proposed Tech Specs Re Physical Mods to Turbine Bldg Cooling Water Header Isolation Logic ML20217C5861997-09-26026 September 1997 Proposed Tech Specs Changes to TS 3.4.B to Change Minimum Conditions for AFW & Permit Startup Operations to Continue W/Inoperable Turbine Driven AFW Pump or Associated Sys Valves Due to Inability to Complete IST Requirements ML20216E4561997-09-0404 September 1997 Proposed Tech Specs,Supporting Conformance to TS Overtime Controls to NRC Guidance Issued 950409 ML20216D1141997-09-0202 September 1997 Proposed Tech Specs,Incorporating Use of New SG Tube Sleeve Designs & Installation & Exam Techniques ML20217M6191997-08-15015 August 1997 Proposed Tech Specs Incorporating C-E SG Welded Sleeve TR, CEN-629-P,Rev 1 ML20149J0251997-06-30030 June 1997 Tech Spec Change Pages B.3.8-2 & B.3.8-5 to Amend Re Spent Fuel Pool Personnel Access Doors ML20141F5011997-05-15015 May 1997 Proposed Tech Specs 3.1.C, Reactor Coolant Sys Leakage & 4.12, SG Tube Surveillance ML20141A0871997-05-0707 May 1997 Proposed Tech Specs Re Spent Fuel Pool Special Ventilation Sys ML20137T2081997-04-10010 April 1997 Proposed Tech Specs,Clarifying Amend Request Re Conformance of Administrative Controls Section 6 to Guidance of STS ML20135F7481997-03-0707 March 1997 Proposed Tech Specs Re Cooling Water Sys Emergency Intake Design Basis ML20135A9401997-02-21021 February 1997 Proposed Tech Specs,Allowing Use of Credit for Soluble Boron in Spent Fuel Pool Criticality Analyses ML20134L8901997-02-12012 February 1997 Proposed Tech Specs 3.3-3 Re Safety Injection Pump Low Temp Operations ML20134J6281997-02-0606 February 1997 Proposed Tech Specs 3.3 Re Engineered Safety Features ML20134E9421997-01-29029 January 1997 Proposed Tech Specs Revising Prairie Island Design Bases Re Cooling Water Emergency Intake ML20135A8251996-11-27027 November 1996 Proposed Tech Specs Incorporating New SG Tube Sleeve Designs & Installation & Exam Techniques ML20135A5091996-11-25025 November 1996 Proposed Tech Specs Implementing Mods Proposed by Suppl to License Amend Request & Revising TS Pp in Final Form to Reflect Changes Proposed by Suppl ML20134H3771996-11-0606 November 1996 Proposed Tech Specs of Appendix a Re Cooling Water Sys ML20134E4551996-10-25025 October 1996 Proposed Tech Specs Changing TS 4.4.A, Containment Leakage Tests, Bases to TS Section B.4.4, Containment Sys Tests & Adding TS.6.5.J, Containment Leakage Rate Testing Program ML20129E2591996-09-24024 September 1996 Proposed Tech Specs,Changing TS 4.12 to Incorporate Revised Acceptance Criteria for SG Tubes W/Degradation in Tubesheet Region ML20117P4311996-09-11011 September 1996 Proposed Tech Specs,Revising Plant TS Governing Cw Sys ML20117B2381996-08-15015 August 1996 Proposed Tech Specs 3.3.B.2 Re Containment Cooling Sys & Bases to Conform to Supporting Analyses ML20115G8121996-07-15015 July 1996 Proposed Tech Specs Re Moveable Incore Detector Thimble Reduction ML20095J7951995-12-14014 December 1995 Proposed Tech Specs for Conformance of Administrative Controls Section 6 to Guidance of STS ML20094S2791995-11-28028 November 1995 Proposed Tech Specs Re Radiological Effluent TS Conformance ML20087F3571995-08-0909 August 1995 Proposed Tech Specs Table TS 3.15-1,Pages 1 & 2 & Bases Page B.3.15-1 Marked Up to Implement License Amend Request 1999-08-31
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211K6241999-08-31031 August 1999 Proposed Tech Specs,Changing ISFSI License Conditions 6,7 & 8 & TS 3/4.1 by Permitting Inclusion of Bpras & Thimble Plug Devices in Sf Assemblies Stored in TN-40 Casks ML20206R0621999-05-13013 May 1999 Proposed Tech Specs,Removing Plant Organization Structure Requirement ML20205S3331999-04-20020 April 1999 Proposed Tech Specs Changing Implementation Date for Relocation from TS to UFSAR of Requirements in TS 3.1.E & Flooding Shutdown Requirements in TS 5.1 ML20205Q0351999-04-12012 April 1999 Proposed Tech Specs,Relocating Shutdown Margin Requirements from TS to COLR ML20204H3601999-03-19019 March 1999 Proposed Tech Specs Removing Dates of Two NRC SERs & Correcting Dates of One SER Listed in Section 2.C.4, Fire Protection ML20207F2901999-03-0101 March 1999 Proposed Revised Tech Specs Incorporating Combustion Engineering SG Welded Tube Sleeve TR Rev ML20203A2181999-02-0505 February 1999 Proposed Tech Specs,Changing TS 4.12, SG Tube Surveillance to Incorporate Changes to Abb C-E Sleeve Design Assumptions & Installation Techniques ML20196B9721998-11-25025 November 1998 Proposed Tech Specs,Allowing Limited Inoperability of Bast Level Channels & Transfer Logic Channels to Provide for Required Testing & Maint of Associated Components ML20155G6321998-11-0303 November 1998 Proposed Tech Specs B.3.1-7 & B.3.1-7a,rev 133A Re Reactor Coolant Sys ML20154S2101998-10-23023 October 1998 Proposed Tech Specs Clarifying Conditions That Constitute Operable Irpi Sys Channels ML20195F1391998-10-0808 October 1998 Non-proprietary Version of Rev 1 to NSPNAD-97002, Steam Line Break Methodology ML20151U3651998-09-0404 September 1998 Proposed Tech Specs TS.3.1-5,TS.4.18-1 & B.4.18-1,clarifying SRs & LCOs for Operability for Reactor Coolant Vent Sys ML20237B5061998-08-12012 August 1998 Proposed Tech Specs Re Conformance of Administrative Controls Section 6 to Guidance of Std Tech Specs ML20151Z9181998-08-0303 August 1998 Rev 0 to 5AWI 6.1.2, Design Outputs,Review & Verification ML20151Z9011998-08-0303 August 1998 Rev 2 to 5AWI 6.1.0, Design Change General ML20236T6041998-07-20020 July 1998 Proposed Tech Specs Incorporating Elevated F* SG Tube Repair Criteria ML20249A7641998-06-11011 June 1998 Proposed Tech Specs Re Conformance of Administrative Controls Section 6 to Guidance of Std ML20216G0371998-04-13013 April 1998 Proposed Tech Specs 3.3 Re Engineered Safety Features ML20248M1421998-04-0606 April 1998 Draft NRC Insp Manual Temporary Instruction 2515/XXX Fire Protection Functional Insp (Fpfi) ML20216D0591998-03-0606 March 1998 Proposed Tech Specs Updating Heatup & Cooldown Rate Curves, Incorporating Use of Pressure & Temp Limits Rept & Changing Pressurizer PORVs Operability Temp ML20217P0061998-03-0404 March 1998 Proposed Tech Specs Re Status of Relocated Requirements ML20217N9771998-03-0202 March 1998 Proposed Tech Specs 3.8.D Re Spent Fuel Pool Special Ventilation Sys ML20217P1431998-03-0202 March 1998 Proposed Tech Specs Re Conformance of Administrative Controls Section 6 to Guidance of Std ML20202E5691998-02-10010 February 1998 Proposed Tech Specs 1-1 Re One Time Reduction of Mode 6 Reactor Coolant Sys Boron Concentration ML20198N8301998-01-15015 January 1998 Proposed Tech Specs Pages Allowing Use of Moveable Incore Detector Thimble Reduction for Unit 1,cycle 19 ML20198P0791998-01-0808 January 1998 Proposed Tech Specs Pages Re Suppl 5 to 951214 LAR on Conformance of Administrative Controls Section 6 to Guidance of STS ML20151Z9561998-01-0505 January 1998 Rev 0 to 5AWI 6.1.7, Design Change Work Orders ML20198B1471997-12-29029 December 1997 Proposed TS marked-up & Revised Pages,Incorporating Changes Associated w/951214 LAR ML20212F0471997-10-28028 October 1997 Proposed Tech Specs Pages Revising TS Section 4.12,allowing Use of voltage-based SG Tube Repair Criteria ML20151Z9441997-10-20020 October 1997 Rev 0 to 5AWI 6.1.6, Design Review & Approval ML20217F4761997-10-0303 October 1997 Suppl Proposed Tss,Allowing Use of New SG Tube Sleeve Designs & Installation & Exam Techniques ML20211H7581997-10-0101 October 1997 Proposed Tech Specs Re Physical Mods to Turbine Bldg Cooling Water Header Isolation Logic ML20217C5861997-09-26026 September 1997 Proposed Tech Specs Changes to TS 3.4.B to Change Minimum Conditions for AFW & Permit Startup Operations to Continue W/Inoperable Turbine Driven AFW Pump or Associated Sys Valves Due to Inability to Complete IST Requirements ML20216E4561997-09-0404 September 1997 Proposed Tech Specs,Supporting Conformance to TS Overtime Controls to NRC Guidance Issued 950409 ML20216D1141997-09-0202 September 1997 Proposed Tech Specs,Incorporating Use of New SG Tube Sleeve Designs & Installation & Exam Techniques ML20217M6191997-08-15015 August 1997 Proposed Tech Specs Incorporating C-E SG Welded Sleeve TR, CEN-629-P,Rev 1 ML20149J0251997-06-30030 June 1997 Tech Spec Change Pages B.3.8-2 & B.3.8-5 to Amend Re Spent Fuel Pool Personnel Access Doors ML20141F5011997-05-15015 May 1997 Proposed Tech Specs 3.1.C, Reactor Coolant Sys Leakage & 4.12, SG Tube Surveillance ML20141A0871997-05-0707 May 1997 Proposed Tech Specs Re Spent Fuel Pool Special Ventilation Sys ML20137T2081997-04-10010 April 1997 Proposed Tech Specs,Clarifying Amend Request Re Conformance of Administrative Controls Section 6 to Guidance of STS ML20137W3621997-03-17017 March 1997 Rev 2 to Test Procedure TR-228, Three Hour Fire Test of One and Three Hour Versawrap Raceway Fire Barrier Sys for Conduits & Cable Trays ML20135F7481997-03-0707 March 1997 Proposed Tech Specs Re Cooling Water Sys Emergency Intake Design Basis ML20135A9401997-02-21021 February 1997 Proposed Tech Specs,Allowing Use of Credit for Soluble Boron in Spent Fuel Pool Criticality Analyses ML20134L8901997-02-12012 February 1997 Proposed Tech Specs 3.3-3 Re Safety Injection Pump Low Temp Operations ML20134J6281997-02-0606 February 1997 Proposed Tech Specs 3.3 Re Engineered Safety Features ML20134E9421997-01-29029 January 1997 Proposed Tech Specs Revising Prairie Island Design Bases Re Cooling Water Emergency Intake ML20136H0101997-01-29029 January 1997 Rev 12 to Abnormal Procedure AB-3, Earthquakes ML20135A8251996-11-27027 November 1996 Proposed Tech Specs Incorporating New SG Tube Sleeve Designs & Installation & Exam Techniques ML20135A5091996-11-25025 November 1996 Proposed Tech Specs Implementing Mods Proposed by Suppl to License Amend Request & Revising TS Pp in Final Form to Reflect Changes Proposed by Suppl ML20138G8751996-11-0808 November 1996 Rev 2 to TN-40 Cask Unloading Procedure 1999-08-31
[Table view] |
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- i Exhibit B Prairie Island Nuclear Generating Plant License Amendment Request Dated February 5,1999 Proposed Changes Marked Up On Existing Technical Specification Pages l
Exhibit B consists of existing Technical Specification pages with the proposed changes highlighted on those pages. The pages affected by this License Amendment Request are listed below:
TS.4.12-4 TS.4.12-5 A
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r 9903110214 990301 DR ADOCK 0 g2
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TS.4.12-4 REV 137 8/13/98 D. Accentance Criteria
. '1. As'used in this Specification:
(a) Imoerfection 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.
'(b) Degradation means a service-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a tube.
(c) Deuraded Tube means a tube containing imperfections 220% of the nominal wall thickness caused by degradation.
(d) % Degradation means the percentage of the tube wall thickness affected or removed by degradation.
(e) Defect means an imperfection of such severity that it exceeds the repair limit. A tube containing a defect is defective.
(f) Egonir Limit means the imperfection depth at or beyond which the tube shall be removed from service by plugging or repaired by sleeving because it may become unserviceable prior to the next inspection and is equal to 50% of the nominal tube wall thickness. If significant general tube thinning occurs, this criteria.will be reduced to 40% wall penetration. This definition does not apply to the portion of the tube in the I
tubesheet below the F* or EF* distance provided the tube is not degraded (i.e., no indications of cracks) within the F* or EF* i distance for F* or EF* tubes. The repair limit for the l pressure boundary region of any sleeve is 3425% of the nominal sleeve wall thickness. This definition does not apply to tube support plate intersections for which the voltage-based repair >
criteria are being applied. Refer to Specification 4.12.D.4 l for the repair limit applicable to these intersections. l l
(g) 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 loss-of-coolant accident, or a steam line or feedwater line break. ,
l (h) Tube Insoection means an inspection of the steam generator tube from the point of entry (hot leg side) completely around the U-bend to the top support of the cold leg.
(i) Sleevinn is the repair of degraded tube regions using a new Alloy 690 tubing sleeve inserted inside the parent tube and sealed at each end by velding or by replacing the lower veld in a full depth tubesheet sleeve with a hard rolled joint. The new sleeve becomes,the pressure boundary spanning the original degraded tube region.
t l t TS.4.12-5 REV 137 8/13/98
)
(j) F* Distance is the distance from the bottom of the hardroll j transition toward the bottom of the tubesheet that has been l
. . conservatively determined to be 1.07 inches (not including eddy I current uncertainty). The F* distance applies to roll expanded l regions below the midplane of the tubesheet l l
(k) F* Tube is a tube with degradation, below the F* distance. !
equal to or greater than 40% and not degraded (i.e., no j indications of cracking) within the F* distance.
(1) EF* Distance is the distance from the bottom of the upper hardroll transition toward the bottom of the tubesheet that has been conservatively determined to be 1.62 inches (not including eddy current uncertainty). EF* distance applies to roll ~
expanded regions when the top of the additional roll expansion is 2.0 inches or greater down from the top of the tubesheet (m) EF* Tube is a tube with degradation, below the EF* distance, equal to or greater than 40%, and not degraded (i.e., no indications of cracking) within the EF* distance.
- 2. The steam generator shall be determined OPERABLE after completing the corresponding actions (plug or repair by sleeving all tubes exceeding the repair limit and all tubes containing through-wall cracks or ;
classify as F* or EF* tubes) required by Tables TS.4.12-1 and TS.4.12-2.
- 3. Tube repair, after Octcher 1, 1007Ab'il15f,Ti999, using Comhustion Engineering welded sleeves shall be in accordance with the methods described in the following:
CEN-629-P, Revision GD3IP, " Repair of Westinghouse Series 44 and 51 ,
Steam Generator Tubes Using Leak Tight Sleeves":
GE"-520-P. f.ddcadu: 1, Rcvicien 1. "Rcpair of Ucctinghoucc Scrico 'd end-51 Ctcan Ccacrator Tubcc "cing Lech Tight Ciccvcc" ,
- 4. Inbe Suenort Plate Repair Limit is used for the disposition of a j steam generator tube for continued service that is experiencing predominantly axially oriented outside diameter stress corrosion I cracking confined within the thickness of'the tube support plates. l At tube support plate intersections. the repair limit is based on maintaining steam generator serviceability as described below:
- a. Steam ger.erator tubes, whose degradation is attributed to outside I diameter stress corrosion cracking within the bounds of the tube j support plate with bobbin voltages less than or equal to 2.0 volts l will be allowed to remain in service. !
I
- b. Steam generator tubes, whose degradation is attributed to out. %
diameter stress corrosion cracking within the bounds of the tube support plate with a bobbin voltage greater than 2.0 volts, will be repaired or plugged, except as noted in Specification 4.12.D.4.c below.
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Exhibit C ;
i Prairie Island Nuclear Generating Plant License Amendment Request Dated February 5,1999 Revised Technical Specification Pages j Exhibit C consists of revised pages for the Prairie Island Nuclear Generating Plant Technical Specifications with the proposed changes incorporated. The revised pages are listed below:
5 TS.4.12-4 TS.4.12-5 ;
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4 I
o t m- m --
\ . a TS.4.12-4 REV D. Accentance Criteria
. 'I. As'used in this Specification:
(a) Imoerfection 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.
(b) Degradation means a service-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a tube.
(c) Dgeraded Tube means a tube containing imperfections 220% of the nominal wall thickness caused by degradation.
(d) % Degradation means the percentage of the tube wall thickness affected or removed by degradation.
(e) Defect means an imperfection of such severity that it exceeds the repair limit. A tube containing a defect is defective.
(f) Reoair TAmit means the imperfection depth at or beyond which the tube shall be removed from service by plugging or repaired by sleeving because it may become unserviceable prior to the next inspection and is equal to 50% of the nominal tube wall thickness. If significant general tube thinning occurs, this criteria vill be reduced to 40% wall penetration. This definition does not apply to the portion of the tube in the tubesheet below the F* or EF* distance provided the tube is not degraded (i.e., no indications of cracks) within the F* or EF' distance for F' or EF' tubes. The repair limit for the pressure boundary region of any sleeve is 25% of the nominal l sleeve wall thickness. This definition does not apply to tube support plate intersections for which the voltage-based repair criteria are being applied. Refer to Specification 4.12.D.4 for the repair limit applicable to these intersections.
(g) Unserviceable describes the condition of a tube if it leaks or '
contains a defect large enough to affect its structural l
integrity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feedwater line break. .
(h) Tube Insoection means an inspection s2 the steam generator tube from the point of entry (hot leg side) completely around the U-bend to the top support of the cold leg.
(i) Sleeving is the repair of degraded tube regions using a new i Alloy 690 tubing sleeve inserted inside the parent tube and sealed at each end by welding or by replacing the lower veld in .
a full depth tubesheet sleeve with a hard rolled joint. The j new sleeve becomes the pressure boundary spanning the original 1 degraded tube region. j
{T ~ ,
s,.-a l
sh
REV j (j) l 7' Distance is the distance from the bottom of the hardroll i transition toward the bottom of the tubesheet that has been j conservatively determined to be 1.07 inches (not including eddy current uncertainty). The F* distance applies to roll expanded regions below the midplane of the tubesheet (k) F* Tube is a. tube with degradation, belev the F* distance, equal to or greater than 40%, and not degraded (i.e., no indications of cracking) within the F* distance.
(1) EF* Distance is the distance from the bottem of the upper hardroll transition toward the bottom of the tubesheet that has been conservatively. determined to be 1.62 inches (not including eddy current uncertainty). EF* distance applies to roll expanded regions when the top of the additional roll expansion is 2.0 inches or greater down from the top of the tubesheet (m) .EF* Tube is a tube with degradation, below the EF* distance, equal to or greater than 40%, and not degraded (i.e., no l indications of cracking) within the EF* distance.
- 2. The steam generator shall be determined OPERABLE after completing the corresponding actions (plug or repair by sleeving all tubes exceeding the repair limit and all tubes containing through-wall cracks or l classify as F* or EF* tubes) required by Tables TS.4.12-1 and ',!
TS.4.12-2.
r
- 3. Tube repair, after April 1, 1999, using Combustion Engineering l l velded sleeves shall be in accordance with the methods described in 6 the following: :
CEN-629-P, Revision 03-P, " Repair of Westinghouse Series 44 and 51 l Steam Generator Tubes Using Leak Tight Sleeves"- ;
J
- 4. Tube Sunoort Plate Renair Limit is used for the disposition of a -l steam generator tube for continued service that is experiencing predominantly axially oriented outside diameter stress corrosion cracking confined within the thickness of the tube support plates.
At tube support plate intersections, the repair limit is based on maintaining steam generator serviceability as described below:
- a. Steam generator tubes, whose degradation is attributed to outside diameter stress corrosion cracking within the bounds of the tube support plate with bobbin voltages less than or equal to 2.0 volts will be allowed to remain in service.
i
- b. Steam generator tubes, whose degradation is attributed to outside :
diameter stress corrosion cracking within the bounds of the tube ;
support plate with a bobbin voltage greater than 2.0 volts, will be I repaired or plugged. except as noted in Specification 4.12.D.4.c ,
below. 1 l
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