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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217B1791999-10-0404 October 1999 Revised TS Re Control Room,Penetration Room & Containment Purge Filtration Sys & Radiation Monitoring Instrumentation, Reflecting Agreements Reached in 990909 & 16 Discussions ML20209B8161999-06-30030 June 1999 Proposed Tech Specs Chapters 3.4,3.5,3.6,3.7,4.0 & 5.0, Converting to ITS ML20196J8731999-06-30030 June 1999 Proposed Tech Specs Correcting Errors,Per 990222 TS Amend Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation ML20207D6421999-05-31031 May 1999 Proposed Conversion to ITSs for Chapter 3.3 ML20206H0001999-04-30030 April 1999 Proposed Revs to Previously Submitted Tech Specs with LAR Related to RAI on Conversion to ITS ML20206F4421999-04-30030 April 1999 Proposed Revs to Previously Submitted Tech Specs with LAR Related to RAI Re Conversion to Its,Chapter 3.8 ML20206B4721999-04-21021 April 1999 Corrected Proposed TS Pages 5.5-6,5.5-7,5.5-8 & 5.5-9, Replacing Current W Model 51 SGs with W Model 54F ML20205G8571999-04-0202 April 1999 Proposed Ts,Increasing Dei Limit from 0.15 to Uci/Gram IAW 10CFR50.90 ML20205A2401999-03-19019 March 1999 Proposed Tech Specs Table 3.3-6,re Cr,Penetration Room & Containment Purge Filtration Sys & Radiation Monitoring Instrumentation ML20207C2451999-02-22022 February 1999 Proposed TS Amends to Clarify SR Refs to ANSI N510 Sections 10,12 & 13 to ASME N510-1989,with Errata Dtd Jan 1991 & to Add Footnote Which Refs FNP FSAR for Relevant Testing of Details ML20203A7711999-02-0303 February 1999 Proposed Tech Specs Pages Re Conversion to Its,Chapter 3.4 ML20196B6241998-11-20020 November 1998 Proposed Tech Specs Pages Re Conversion to Improved TS, Chapters 3.6.& 5.0 ML20155J4561998-11-0606 November 1998 Proposed Tech Specs Re Nuclear Instrumentation Sys Power Range Daily Surveillance Requirement ML20154K2521998-10-12012 October 1998 Proposed Tech Specs Section 6,providing Recognition of Addl Mgt Positions Associated with SG Replacement Project & Providing Ability to Approve Procedures Re Project Which May Affect Nuclear Safety ML20237D4111998-08-20020 August 1998 Proposed Tech Specs Reflecting Conversion to Improved TS Re Discussion of Changes & Significant Hazards Evaluations ML20217N4801998-05-0101 May 1998 Proposed Tech Specs Bases Pages Re Safety Limits,Reactivity Control Systems & Afs ML20217Q7261998-03-20020 March 1998 Proposed Tech Specs Re Power Update Implementation,Replacing Page 6-19a ML20202G1311998-02-12012 February 1998 Proposed Tech Specs Re Pressure Temp Limits Rept ML20202F1121998-02-12012 February 1998 Revised Proposed Changes to TS Page 6-19a for Power Uprate ML20198H3661998-01-0707 January 1998 Proposed Tech Specs Pages,Adding Note to Specifically Indicate Normal or Emergency Power Supply May Be Inoperable in Modes 5 or 6 Provided That Requirements of TS 3.8.1.2 Are Satisfied ML20198E6621997-12-31031 December 1997 Proposed Tech Specs Changing Nis IR Neutron Flux Reactor Trip Setpoint & Allowable Value ML20198E3141997-12-30030 December 1997 Proposed Tech Specs Re Auxiliary Bldg & Svc Water Bldg Battery Surveillances ML20197B6691997-12-18018 December 1997 Proposed Tech Specs Pages Re 970723 TS Amend Request Associated W/Pressure Temperature Limits Rept ML20211P5861997-10-16016 October 1997 Proposed Tech Specs Pages,Revising Number of Allowable Charging Pumps Capable of Injecting in RCS When Temperature of One or More of RCS Cold Leg Temperatures Is Less than 180 F ML20211J1501997-09-30030 September 1997 Proposed Tech Specs,Correcting Page 20 of 970723 TS Amend Request to Relocate RCS Pressure & Temperature Limits from TS to Pressure & Temperature Limit Rept ML20217C0341997-09-25025 September 1997 Revised Proposed Ts,Providing Addl Info Re 970630 Submittal, Titled, Jfnp TS Change Request - Credit for B for Spent Fuel Storage ML20211A6891997-09-17017 September 1997 Proposed Tech Specs Re Primary Coolant Specific Activity ML20216D0031997-09-0303 September 1997 Proposed Tech Specs Re Moveable Incore Detector Sys ML20149K1001997-07-23023 July 1997 Proposed Tech Specs,Relocating RCS P/T Limits from TS to Proposed P/T Limits Rept IAW Guidance Provided by GL 96-03, Relocation of P/T Limit Curves & LTOP Sys Limits ML20148R7521997-06-30030 June 1997 Proposed Tech Specs,Incorporating Requirements Necessary to Change Basis for Prevention of Criticality in Fuel Storage Pool.Change Eliminates Credit for Boraflex as Neutron Absorbing Matl in Fuel Storage Pool Criticality Analysis ML20148Q1041997-06-30030 June 1997 Proposed Tech Specs,Revising & Clarifying Requirements for CR Emergency & Penetration Room Filtration Sys,Required Number of Radiation Monitoring Instrumentation Channels & Deleting Containment Purge Exhaust Filter Spec ML20148K7501997-06-13013 June 1997 Proposed Tech Specs Changing TS 3/4.9.13, Storage Pool Ventilation (Fuel Movement) ML20140A3931997-05-28028 May 1997 Proposed Tech Specs,Clarifying That Testing of Each Shared EDG to Comply W/Sr 4.8.1.1.2.e Is Only Required Once Per Five Years on a Per EDG Basis,Not on Per Unit Basis ML20148E5921997-05-27027 May 1997 Proposed Tech Specs Pages Revising Applicable Modes for Source Range Nuclear Instrumentation & Providing Allowances for an Exception to Requirements for State of Power Supplies for RHR Discharge to Charging Pump Suction Valves ML20148F2381997-05-27027 May 1997 Corrected TS Bases Page B 3/4 1-3 That Incorporates Changes from COLR & Elimination of Containment Spary Additive Sys TS Amends ML20138B9251997-04-23023 April 1997 Proposed Tech Specs,Revising TS Pages to Include Footnote Concerning Filter Pressure Drop Testing & Mechanical Heater Testing ML20137H6091997-03-25025 March 1997 Proposed Tech Specs Re Primary Coolant Specific Activity ML20136F8231997-03-0707 March 1997 Proposed Tech Specs 3/4.6.3 Re Containment Isolation Valves Surveillance Requirements ML20135C6731997-02-24024 February 1997 Proposed Tech Specs Re Surveillance Requirements of Control Room,Penetration Room & Containment Purge Filtration Systems ML20135C4941997-02-24024 February 1997 Proposed Tech Specs Re SG Tube Laser Welded Sleeves.Voltage Based Alternate Repair Criteria Is Approved Prior to Laser Welded Sleeve Amend ML20135C8641997-02-14014 February 1997 Proposed Tech Specs Revising Specified Max Power Level & Definition of Rated Thermal Power ML20134J4051997-02-0606 February 1997 Proposed Tech Specs,Providing Addl Info Re voltage-based Repair Criteria for SG Tubing ML20133G5801997-01-10010 January 1997 Proposed Tech Specs Re Generic Laser Weld Sleeving & Deleting One Cycle Implementation of L* Which Expired at Last Unit 2 Outage ML20138G9581996-12-26026 December 1996 Proposed Tech Specs Reflecting Guidance Contained in GL 95-05, SG Tube Support Plate Voltage-Based Repair Criteria, Using Revised Accident Leakage Limit of 20 Gpm & Using Probability of Detection That Is Voltage Dependent ML20134N9211996-11-18018 November 1996 Proposed Tech Specs Bases B 3/4 2-5 Re RCS Total Flow Rate Surveillance ML20134K5551996-11-15015 November 1996 Proposed Tech Specs 3.6.2.2 Re Spray Additive Sys ML20134G9601996-11-11011 November 1996 Proposed Tech Specs Amending License NPF-8 to Replace Farley Specific Laser Welded Sleeve Requirements Currently in TS W/Generic Laser Welded Sleeve Process ML20149L8991996-11-0606 November 1996 Revised Technical Specification Pages for Plant Units 1 & 2 ML20128M4821996-10-0808 October 1996 Proposed Tech Specs Reflecting Deletion of Cycle Specific L* Repair Criteria Which Expires at Start of Next Unit 2 Refueling Outage ML20128F8821996-09-30030 September 1996 Proposed Tech Specs Change Request Relocating cycle-specific Core Operating Parameter Limits to Colr.Proposed Changes Based on Guidance Found in NRC GL 88-16,WOG-90-016, NUREG-1431 & COLR Approved by NRC 1999-06-30
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217B1791999-10-0404 October 1999 Revised TS Re Control Room,Penetration Room & Containment Purge Filtration Sys & Radiation Monitoring Instrumentation, Reflecting Agreements Reached in 990909 & 16 Discussions ML20209B8161999-06-30030 June 1999 Proposed Tech Specs Chapters 3.4,3.5,3.6,3.7,4.0 & 5.0, Converting to ITS ML20196J8731999-06-30030 June 1999 Proposed Tech Specs Correcting Errors,Per 990222 TS Amend Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation ML20207D6421999-05-31031 May 1999 Proposed Conversion to ITSs for Chapter 3.3 ML20206H0001999-04-30030 April 1999 Proposed Revs to Previously Submitted Tech Specs with LAR Related to RAI on Conversion to ITS ML20206F4421999-04-30030 April 1999 Proposed Revs to Previously Submitted Tech Specs with LAR Related to RAI Re Conversion to Its,Chapter 3.8 ML20206B4721999-04-21021 April 1999 Corrected Proposed TS Pages 5.5-6,5.5-7,5.5-8 & 5.5-9, Replacing Current W Model 51 SGs with W Model 54F L-99-170, Snoc Jfnp Startup Test Rept Unit 1 Cycle 16. with1999-04-20020 April 1999 Snoc Jfnp Startup Test Rept Unit 1 Cycle 16. with ML20205S9641999-04-20020 April 1999 Snoc Jfnp Startup Test Rept Unit 1 Cycle 16. with ML20205G8571999-04-0202 April 1999 Proposed Ts,Increasing Dei Limit from 0.15 to Uci/Gram IAW 10CFR50.90 ML20205A2401999-03-19019 March 1999 Proposed Tech Specs Table 3.3-6,re Cr,Penetration Room & Containment Purge Filtration Sys & Radiation Monitoring Instrumentation ML20205A3101999-02-28028 February 1999 Analysis of Capsule Z from Alabama Power Co Jm Farley Unit 2 Reactor Vessel Radiation Surveillance Program ML20207C2451999-02-22022 February 1999 Proposed TS Amends to Clarify SR Refs to ANSI N510 Sections 10,12 & 13 to ASME N510-1989,with Errata Dtd Jan 1991 & to Add Footnote Which Refs FNP FSAR for Relevant Testing of Details ML20203A7711999-02-0303 February 1999 Proposed Tech Specs Pages Re Conversion to Its,Chapter 3.4 ML20205T0011998-12-23023 December 1998 Rev 17 to FNP-0-M-011, Odcm ML20205T0081998-12-23023 December 1998 Rev 18 to FNP-0-M-011, Odcm ML20196B6241998-11-20020 November 1998 Proposed Tech Specs Pages Re Conversion to Improved TS, Chapters 3.6.& 5.0 ML20155J4561998-11-0606 November 1998 Proposed Tech Specs Re Nuclear Instrumentation Sys Power Range Daily Surveillance Requirement ML20154K2521998-10-12012 October 1998 Proposed Tech Specs Section 6,providing Recognition of Addl Mgt Positions Associated with SG Replacement Project & Providing Ability to Approve Procedures Re Project Which May Affect Nuclear Safety ML20151V6991998-09-11011 September 1998 Snoc Jm Farley Nuclear Plant Startup Test Rept Unit 2 Cycle 13. with ML20237D4111998-08-20020 August 1998 Proposed Tech Specs Reflecting Conversion to Improved TS Re Discussion of Changes & Significant Hazards Evaluations ML20217N4801998-05-0101 May 1998 Proposed Tech Specs Bases Pages Re Safety Limits,Reactivity Control Systems & Afs ML20205S9971998-04-19019 April 1998 Rev 16 to FNP-0-M-011, Odcm ML20217Q7261998-03-20020 March 1998 Proposed Tech Specs Re Power Update Implementation,Replacing Page 6-19a ML20202G1311998-02-12012 February 1998 Proposed Tech Specs Re Pressure Temp Limits Rept ML20202F1121998-02-12012 February 1998 Revised Proposed Changes to TS Page 6-19a for Power Uprate ML20198H3661998-01-0707 January 1998 Proposed Tech Specs Pages,Adding Note to Specifically Indicate Normal or Emergency Power Supply May Be Inoperable in Modes 5 or 6 Provided That Requirements of TS 3.8.1.2 Are Satisfied ML20198E6621997-12-31031 December 1997 Proposed Tech Specs Changing Nis IR Neutron Flux Reactor Trip Setpoint & Allowable Value ML20198E3141997-12-30030 December 1997 Proposed Tech Specs Re Auxiliary Bldg & Svc Water Bldg Battery Surveillances ML20197B6691997-12-18018 December 1997 Proposed Tech Specs Pages Re 970723 TS Amend Request Associated W/Pressure Temperature Limits Rept ML20212B1791997-10-31031 October 1997 1 SG ARC Analyses in Support of Full Cycle Operation ML20211P5861997-10-16016 October 1997 Proposed Tech Specs Pages,Revising Number of Allowable Charging Pumps Capable of Injecting in RCS When Temperature of One or More of RCS Cold Leg Temperatures Is Less than 180 F ML20211J1501997-09-30030 September 1997 Proposed Tech Specs,Correcting Page 20 of 970723 TS Amend Request to Relocate RCS Pressure & Temperature Limits from TS to Pressure & Temperature Limit Rept ML20217C0341997-09-25025 September 1997 Revised Proposed Ts,Providing Addl Info Re 970630 Submittal, Titled, Jfnp TS Change Request - Credit for B for Spent Fuel Storage ML20211A6891997-09-17017 September 1997 Proposed Tech Specs Re Primary Coolant Specific Activity ML20216D0031997-09-0303 September 1997 Proposed Tech Specs Re Moveable Incore Detector Sys ML20149K1001997-07-23023 July 1997 Proposed Tech Specs,Relocating RCS P/T Limits from TS to Proposed P/T Limits Rept IAW Guidance Provided by GL 96-03, Relocation of P/T Limit Curves & LTOP Sys Limits ML20148Q1041997-06-30030 June 1997 Proposed Tech Specs,Revising & Clarifying Requirements for CR Emergency & Penetration Room Filtration Sys,Required Number of Radiation Monitoring Instrumentation Channels & Deleting Containment Purge Exhaust Filter Spec ML20148R7521997-06-30030 June 1997 Proposed Tech Specs,Incorporating Requirements Necessary to Change Basis for Prevention of Criticality in Fuel Storage Pool.Change Eliminates Credit for Boraflex as Neutron Absorbing Matl in Fuel Storage Pool Criticality Analysis ML20148K7501997-06-13013 June 1997 Proposed Tech Specs Changing TS 3/4.9.13, Storage Pool Ventilation (Fuel Movement) ML20140A3931997-05-28028 May 1997 Proposed Tech Specs,Clarifying That Testing of Each Shared EDG to Comply W/Sr 4.8.1.1.2.e Is Only Required Once Per Five Years on a Per EDG Basis,Not on Per Unit Basis ML20148F2381997-05-27027 May 1997 Corrected TS Bases Page B 3/4 1-3 That Incorporates Changes from COLR & Elimination of Containment Spary Additive Sys TS Amends ML20148E5921997-05-27027 May 1997 Proposed Tech Specs Pages Revising Applicable Modes for Source Range Nuclear Instrumentation & Providing Allowances for an Exception to Requirements for State of Power Supplies for RHR Discharge to Charging Pump Suction Valves ML20138B9251997-04-23023 April 1997 Proposed Tech Specs,Revising TS Pages to Include Footnote Concerning Filter Pressure Drop Testing & Mechanical Heater Testing ML20198T4921997-03-31031 March 1997 Small Bobbin Probe (0.640) Qualification Test Rept ML20137H6091997-03-25025 March 1997 Proposed Tech Specs Re Primary Coolant Specific Activity ML20136F8231997-03-0707 March 1997 Proposed Tech Specs 3/4.6.3 Re Containment Isolation Valves Surveillance Requirements ML20135C4941997-02-24024 February 1997 Proposed Tech Specs Re SG Tube Laser Welded Sleeves.Voltage Based Alternate Repair Criteria Is Approved Prior to Laser Welded Sleeve Amend ML20135C6731997-02-24024 February 1997 Proposed Tech Specs Re Surveillance Requirements of Control Room,Penetration Room & Containment Purge Filtration Systems ML20135C8641997-02-14014 February 1997 Proposed Tech Specs Revising Specified Max Power Level & Definition of Rated Thermal Power 1999-06-30
[Table view] |
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- l Enclosure 3 Joseph M. Farley Nuclear Plant Steam Generator Fa Technical Specification Changes Page Change Instructions Unit 2 Remove Page B_eplace Page 3/4 4-12b 3/4 4-12b B 3/4 4-3a B 3/4 4-3b l
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1 l
9604240357 960422 PDR ADOCK 05000364 P PDR
REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)
- 11. F* Distance is the discance of the expanded portion of a tube which provides a sufficient length of undegraded tube expansion to resist pullout of the tube from the
-tubesheet. The F* distance is equal to 1.54 inches plus allowance for eddy current uncertainty measurement and is measured down from the top of the tubesheet or the bottom of the roll transition, whichever is lower in elevation.
- 12. F* Tube is a tubes a) with degradation equal to or greater than 40% below the F* distance, and b) which has no indication of imperfections greater than or equal to 20% of nominal wall thickness within the F* distance, and c) that remains inservice.
] 13. Tube Exoansion is that portion of a tube which has been increased in diameter by a rolling process such that no crevice exists between the outside diameter of the tube and the hole in the tubesheet.
- 14. Tube Sucoort Plate Repair Limit is used for the disposition of an alloy 600 steam generator tube for continued service that is experiencing predominately
, axially oriented outside diameter stress corrosion '
i d
cracking confined within the thickness of the tube support plates. At tube support plate intersections, the repair ILmit is based on maintaining steam generator tube
- serviceability as described below
- a. Steam generator tubes, whose degradation is I attributed to outside diameter stress corrosion i cracking within the bounds of the tube support plate with bobbin voltages less than or equal to the lower voltage repair limit (2.0 volts), will be allowed to remain in service.
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 the lower voltage repair limit [2.0 volts), will be repaired or plugged except as noted in 4.4.6.4.a.14.c below. ,
1 4
. FARLEY-UNIT 2 3/4 4-12b AMENDMENT NO.
. _ ._ , .. ~~ -- _. - - - . . _-
4 REACTOR COOLANT SYSTEM BASES
- 3. The tube plugging limit continues to apply to the portion of the tube in the entire upper joint region and in the lower roll expansion. As noted above, the sleeve plugging limit applies to i these areas also.
- 4. .The tube plugging limit continues to apply to that portion of the tube above the top of the upper joint.
- b. Laser Welded
- 1. Indications of degradation in the length of the sleeve between the weld joints must be evaluated against the sleeve plugging 2 limit.
-2. Indication of tube degradation of any type including a complete break in the tube between the upper weld joint and the lower weld joint does not require that the tube be removed from service.
- 3. At the weld joint, degradation must be evaluated in both the sleeve and tube.
- 4. In a joint with more than one weld, the weld closest to the end i
of the sleeve represents the joint to be inspected and the lLait of the sleeve inspection.
s
- 5. The tube plugging limit continues to apply to the portion of the tube above the upper weld joint and below the lower weld joint.
F* tubes do not have to be plugged or repaired provided the remainder of i the tube within the tubesheet that is above the F* distance is not degraded. The F* distance is equal to 1.54 inches plus allowance for eddy
, current uncertainty measurement and is measured down from the top i of the tubesheet or the bottom of the roll transition, whichever is lower I j in elevation.
Steam generator tube inspections of operating plants have demonstrated the capability to reliably detect wastage type degradation that has penetrated 1
20% of the original tube wall thickness.
Whenever the results of any steam generator tubing inservice inspection 4 f all into category c-3, these results will be reported to the commission l pursuant to 10 cFR 50.73 prior to resumption of plant operation. Such cases will be considered by the commission on a case-by-case basis and may result in a requirement for analysis, laboratory examinations, tests, j additional addy-current inspection, and revision to the Technical specifications, if necessary.
FARLEY-UNIT 2 B3/4 4-3b AMENDMENT NO.
l
Enclosure 4 Joseph M. Farley Nuclear Plant Steam Generator F*
Technical Specification Changes Marked -Un Pages i
s
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. m : u :e:2 m m m SURVIII.IMCE REQUIRD(INTS Icontinued)
- 10. Preservice'!nspection leeans an inspection of the full length of each tube in each steam generater perferned by eddy current techniques prior to service to establish a baseline conditica of the tubing. This inspection ,shall be performed after the field hydrostatie test and prior to taltial pcutA 0FEAATICW using the equipshant and techniques expected to be used during subsequent inservice inspectierts.
M* Distance is the distance of the expanded pertio at~ ch provides a sufficient length See'bsed A. tube expansion aalat pu11eut .
graded tube frou the tubesheet. The F* dista equal to 1.19 inches and is measured d ye4 e top of sheet er the fAfrs' roll transition, whichever is be
, .n.
- 12. F* Tube is a tube:
al with degradation equal te er greater than 400 below
' the F* distance, and b) which has no indication of imperfections greater thaa er equal to 200 of nominal well thiekness within the F' distance, and c) that l remains inservice.
- 13. Tube Empansion is that parties of a tube which has been '
lacreased in diameter by a rolling process such that no crevise saists between the outside diameter of ths tube and the hele in the tubesheet.
- 14. Tube support Plate Fluccine Limit is usN for the disposities of a steam generator tube for continued
- service that is experiencing outside diameter stress cerrosies cracklag confined within the thickness of the tube support plates. These criteria are applicable for the sieventh operating cycle caly. At tube support plate intersections, the repair limit is based en malataining steam generater tube serviceability as I
described below
, 4. Degradation attributed to outside diameter strose i '
cerrosies cracking withis the.beunda ei the tube support plate with bobbia voltage less than er equal to 2.0 volts will be allowed te renais in service.
i
- b. Degradatica attributed to outside diameter stress corrosita cracking within the beunes of the tube support plate with a bobbia voltage greater than 2.0 volts will. be repaired or plegged essept as noted is 4.4.6.4.a.14.s below.
TARI.EY-UNIT 2 3/4 4 12b i
MGNDMENT Iso. 10$'
e 1 .
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A Insert A 11, F* Distance is the distance of the expanded portion of a tube which provides a sufficient length of undegraded tube expansion to resist pullout of the' tube from the tubesheet. The F* distance is equal to 1,54 inches plus allowance for eddy current uncertainty measurement and is measured down f rom the top of the tubesheet or the bottom of the roll transition, whichever is lower in elevation.
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_ . . _ _ . ~ . ~ . -- - _ -. - ... . -.- . -_ . - - - - - - _ . . - -
. MacT04 COOLANT $YSTN SA$t$ .
i
- a. Mechanical i 1. Indications of degradation in the entire length of the sleeve 1 l pust be evaluated against the sleeve plugging limit. l 4
i i 2. . Indication of tube degradation of any type including a i
- complete guillotine break. In the tube between ths bottoa of the !
3 upper joint and the top of the lower roll expansion does not require that the tube be removed free service. .
s a
- 3. The tube plugging limit continues to apply to the partion of the tube in the entire upper joint region and in the lower roll ;
- expansion. As noted above, the sleeve plugging Itait applies 1 to these areas also, i 4. The tube plugging limit continues to apply to that portion of
, the tube above the top of the upper joint.
j .
l b. Laser Welded .
i
- 1. Indications of degradation in the length of the sleeve between
, the weld joints must be evaluated against the sleeve pinging limit. * ,
]
- 2. Indication of tube degradation of any type including a _'
i complete break in the tube between the upper weld joint and the
! lower weld joint does not require that the tube be removed from service. -
l 3. At the weld joint, degradation must be evaluated in both the l l sleeve and tube. l
- 4. In a joint with more than one weld, the weld closest to the end 4 . of the sleeve represents the joint to be inspected and the
, limit of the sleeve inspection.
- . 5. The tube plugging limit continues to apply to the portion of the tube above the up'ser veld joint and below the lower weld joint.
l F' tubes do not have to be plugged or repaired provided the receinder of the i tube within the tubesheet tiat is above the F* distance is not degraded. The F*
i distance is equal tofL78 !=h:: and is asaaured down from the top of the l
f tubesheet or the bettes of the roll transition, uhtchever is lower in elevation.
! !=1 d in tht+-44: tree !: = :11r= cf crH-teh for O =7c;..
01:vatt: = = ur: at = =rt:i::ty.
j fteam pnerator tube inspections of operating plants have demonstrated the capabi' ity te reliably detect wastage type degradation that has penetrated 205 of the original tube wall thickness. j l
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' l FAAl.EY-UNIT I 83/4 4-3a AMDOtENT N0. 94 i .--
l i
t.s4 hek.s pLs al6 a.nc e. 6 r edy curre ni ocedady '
eneasure a &
9 9
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