Text

Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection.
	ML12082A135
Person / Time
Site:	Byron, Braidwood
Issue date:	03/22/2012
From:	Gullott D; Exelon Nuclear, Exelon Nuclear Generation Corp
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	RS-12-028
	Download: ML12082A135 (53)
	v • d • e

Exelon Exelon Generation Company, LLC Company, LLC www.exeloncorp.com Exelon.

4300 Winfield Road 4300 Winfield Road Nuclear Warrenville, IL 60555 Warrenville, IL 60555 RS-12-028 10 CFR 50.90 March 22,2012 March 22, 2012 U. S. Nuclear Regulatory Commission Commission ATTN: Document Document Control Control Desk Washington, DC 20555-0001 20555-0001 Braidwood Station, Units 11 and 2 Facility Operating License Nos. NPF-72 NPF-72 andand NPF-77 NPF-77 NRC Docket Nos. STN 50-456 and and STN STN 50-457 50-457 Byron Station, Units 1 and 2 FacilityOperating Facility Operating License License Nos.

Nos. NPF-37 and NPF-66 NPF-66 NRC Docket NRC Docket Nos.

Nos. STN STN 50-454 and STN STN 50-45 50-45

Subject:

Application Application to to Revise Revise Technical Specifications Specifications to to Adopt Adopt TSTF-510, TSTF-510, "Revisionto "Revision to Steam Steam Generator Generator Program Inspection Frequencies Frequencies and and Tube Tube Sample Selection" Selection" In accordance In accordance with with 1010 CFR 50.90, "Application for amendment "Application for amendment of license, construction construction permit, or early site permit," Exelon Generation permit, Generation Company, Company,LLC, LLC, (EGC)

(EGC) isis submitting submitting aa request for request for an an amendment amendmenttotothe theTechnical TechnicalSpecifications Specifications(TS)

(TS)forforBraidwood BraidwoodStation, Station, Units 1 and 2, and Units and Byron Byron Station, Station, Units Units 11 and and 2.

2.

The proposed amendmentamendmentwould would modify modify TSTS requirements regarding steam generator generator tube inspections inspections and and reporting reporting asasdescribed describedininTSTF-510, TSTF-510,Revision Revision2,2,"Revision "Revisionto to Steam Generator Program Program Inspection Inspection Frequencies and Tube Tube Sample Sample Selection;"

Selection;"

however, EGC is proposing proposing certain certain variations variations and anddeviations deviationsfromfromTSTF-51 TSTF-510 0 as as discussed inin Attachment discussed Attachment 1. 1.

Attachment 11 provides Attachment providesaadescription descriptionand andassessment assessment of of the the proposed proposed changes, changes, the requested confirmation requested confirmation of applicability, and plant-specific applicability, and plant-specific verifications.

verifications. Attachments Attachments 22 and 3 provide provide thethe existing existing TSTS pages pages marked up to to show show the the proposed changes changes for for the Braidwood Station Braidwood Station and and the the Byron Station, respectively.

Byron Station, respectively. Attachments Attachments 44 andand55provide provide existing TS existing TS Bases Bases pages pages marked marked up up to to show show the proposed proposed changes changesfor forthe theBraidwood Braidwood Station and the Byron Station, respectively.

Byron Station, respectively. The TS BasesBasespages pagesare areprovided providedfor forNRC NRC information only information only and and do not require NRC NRC approval.

The proposed change change has hasbeen beenreviewed reviewedby bythe theBraidwood BraidwoodStation Stationand andByron Byron Station Station Plant Operations Review Committees and approved approved by by their their respective respective Nuclear NuclearSafety Safety Review Boards Review Boards in in accordance accordance with the requirements of of the EGC EGC Quality Assurance Assurance Program.

March 22,2012 March 22, 2012 U. S.

U. S. Nuclear Regulatory Commission Page 2 Approval of Approval ofthe theproposed proposed amendment amendment is requested requested by byMarch March 22, 22, 2013, 2013, to to support support implementation during the Byron Byron Unit Unit 2 spring 2013 2013 (B2R17)

(B2R17) andandBraidwood BraidwoodUnitUnit 11fall fall 2013 (A(Al1R17)

R17)refueling refuelingoutages.

outages. Once approved, the the amendment amendmentshallshall be beimplemented implemented within30 within 30 days days for for Byron, Byron, Units Units 11 and and 2, 2, and within within 60 days for Braidwood, Braidwood, Units 1 and 2.

In accordance In accordance withwith 10 CFR 50.91, 50.91, "Notice "Notice for public comment; State State consultation,"

consultation,"

paragraph (b),

paragraph (b), aa copy copy of of this application, application, with attachments, is with attachments, is being being provided provided toto the the designated State deSignated StateOfficial.

Official.

There are no regulatory commitments contained in this letter.

Should have any questions Should questions regarding regarding this this submittal, submittal, please pleasecontact contactMs.

Ms.Lisa Lisa A.

A. Simpson Simpson at (630) 657-2815.

I declare under penalty of perjurythat of perjury thatthe the foregoing foregoingisistrue trueand andcorrect.

correct. Executed on the 22nd day day ofof Month Month 2012.

2012.

Respectfully, David M.M. Gullott Manager -- Licensing Manager Licensing Exelon Generation Generation Company, LLC Attachments:

1) Evaluation of Evaluation of Proposed Proposed Changes Changes

2) Proposed Technical Proposed Technical Specification Specification Changes Changesfor forBraidwood Braidwood Station, Station, Units Units 11 and and 22

3) Proposed Technical Specification Changes for Byron Station, Proposed Technical Specification Changes for Byron Station, Units 1 and 2 Units 1 and 2

4) Proposed Technical Technical Specification Specification Bases Bases Changes Changesfor forBraidwood Braidwood Station, Station, Units Units 11 and and 22

5) Proposed Technical Proposed Technical Specification Specification Bases Bases Changes Changesfor forByron Byron Station, Station, Units Units 1 and and 22 cc: NRC Regional Administrator, Region Region IIIIII NRC NRC Senior Resident Inspector, Inspector, Braidwood Station Braidwood NRC Senior Resident Inspector, NRC Inspector, Byron Byron Station NRC Project Manager, NRR -- Braidwood NRC Braidwood and and Byron Byron Stations Stations Illinois Emergency Management Illinois Emergency Management AgencyAgency--Division Division of Nuclear Safety Safety

ATTACHMENT 11 ATTACHMENT Evaluationof Evaluation of Proposed Proposed Changes

1.0 DESCRIPTION

2.0 ASSESSMENT 2.1 Applicabilityof Applicability ofPublished Published Safety Evaluation Evaluation 2.2 Optional Optional Changes and Variations Changes and Variations

3.0 REGULATORY ANALYSIS

3.1 No Significant Hazards Consideration Consideration Determination Determination 4.0 ENVIRONMENTAL EVALUATION Page 11 of Page of 66

ATTACHMENT 11 Evaluationof Evaluation ofProposed Proposed ChangesChanges

1.0 DESCRIPTION

The proposed change change revises revisesTechnical TechnicalSpecifications Specifications(TS) (TS) 3.4.19, 3.4.19, "Steam "SteamGenerator Generator(SG) (SG)

Tube Integrity,"

Integrity," TSTS5.5.9, 5.5.9, "Steam "Steam Generator Generator (SG)(SG) Program,"

Program," and and TS TS 5.6.9, 5.6.9, "Steam Generator (SG) Tube (SG) Tube Inspection InspectionReport."

Report." TheThe proposed proposed changes changes are needed needed to to address addressimplementation implementation issues associated associated withwith the inspection periods, and address inspection periods, address other other administrative changes and administrative changes clarifications. In clarifications. In addition, addition,the theproposed proposed amendment amendment deletes the current current TS allowance to use ABBCombustion ABB CombustionEngineering EngineeringInc. Inc.TIG TIGwelded weldedsleeves sleevesas as aa steam generator generator tubetube repair repair method. As method. As aa result result ofof this change, therethere are areno noavailable available SG SG tubetuberepair repairmethods; methods; therefore, therefore, the proposed amendment deletes deletes TS TS 5.5.9.f, 5.5.9.f, TS 5.5.9.c.2, TS 5.5.9.c.3, and references to tube repair and sleeves repair sleeves in in various various TS.

TS.

The proposed amendment is consistent with with TSTF-510, Revision Revision 2, 2, "Revision "Revision to Steam Steam Generator Program Generator ProgramInspection InspectionFrequencies Frequencies and andTube Tube Sample Sample Selection,"

Selection," except except as discussed discussed below.

2.0 ASSESSMENT 2.1 Applicabilityof Applicability ofPublished Published Safety Evaluation Evaluation Exelon Generation Company, Exelon Company, LLC, LLC, (EGC) has has reviewed reviewed TSTF-510, TSTF-510,Revision Revision2,2,"Revision "Revisionto to Steam Generator Generator Program Program Inspection Inspection Frequencies Frequencies and and Tube Tube Sample SampleSelection,"

Selection," and and thethemodel model safety evaluation dated October 27, 2011 (76 27,2011 (76 FRFR 66763),

66763), as aspart partof of the theFederal FederalRegister RegisterNotice Notice for Availability. As As described described in in the the subsequent subsequent paragraphs, EGC EGC hashas concluded concluded that the justifications presented justifications presented in in TSTF-51 TSTF-5100 and and the the model safety evaluation prepared prepared by by the theNRCNRC areare applicable to Braidwood Station, Units Units 11 and and 2,2, and andByron ByronStation, Station,Units Units11and and2,2,and andjustify justifythis this amendment for amendment for the incorporation incorporation of the changeschangesto tothe theBraidwood Braidwood Station Stationand andthe theByron ByronStation Station TS.

2.2 Optional Changes and Optional Changes and Variations Variations EGC is proposing the following variationsfrom following variations fromthe theTS TSchanges changes described described in in the TSTF-510, TSTF-510, Revision 2, Revision 2, or the applicable parts parts ofof the NRC's NRC's model model safety safetyevaluation evaluation dateddated October 27, 2011.

1. For Braidwood Unit

1. Unit 22 and Byron Unit 2, EGC will implement the will implement the proposed proposed TSTF-510 TSTF-510 third inspection third inspection period during during thethe current period, period, thereby increasing the the current current period period duration from from 60 60 EFPM EFPM to to 72 72 EFPM.

EFPM. As As aa result, result, Byron Byron UnitUnit 2 has has completed completed two two SGSG inspections underunder the requirements requirements of of the the current current TS TS 5.5.9.d.2.

5.5.9.d.2. Braidwood BraidwoodUnit Unit 22 has has completed one one SG SG inspection inspection and andhashasone oneplanned plannedinspection inspectionduringduringthetheBraidwood Braidwood Unit 22 fall Unit fall2012 2012 refueling refuelingoutage outage (A2R16).

(A2R16). Increasing Increasingthe theinspection inspectionperiodperiodfrom from 60 EFPM to 72 EFPM also increases increasesthe thenumber numberofofrefueling refuelingoutages outageswithin withinthetheperiod period from three to four.

from three four. Therefore, Therefore, SG SG inspections inspections performed performed under underthe the current current sampling sampling requirements do not meet meet thethe minimum minimum sampling requirements of the proposed proposed TS5.5.9.d.2.

TS 5.5.9.d.2.

The proposed proposedminimumminimum inspection inspection sample samplefor for the the third third inspection inspection period period is is 33%

33% forfor Byron Unit 22 and Byron Unit and Braidwood Braidwood Unit Unit 22 as as a result of of three three planned plannedinspections inspectionswithin within the the four refueling refueling outages outages period to meet the 100% 100% inspection requirement for areas areas potentially susceptible to degradation potentially susceptible degradation that that were were inspected inspectedby bythetheplus-point plus-pointprobe.

probe.

Page Page 22of6 of 6

ATTACHMENT 11 ATTACHMENT Evaluation of Evaluation of Proposed Proposed Changes Changes The inspections that did not meet the proposed proposed 33% 33% minimum minimum sample sample werewere sampled sampledat at 25%. EGC will sample the remaining 2S%. EGC will sample the remaining population in population in future outages to complete outages to complete 100% of 100% of the affected areasareasprior prior toto the the endendof ofthe thethird third inspection inspection period.

period. ByronByronUnitUnit22completed completed 100% fullfull length length bobbin bobbin coil coilinspections inspections in in each each of the the first first two two refueling refueling outages outages in the third third inspection period. Braidwood BraidwoodUnit Unit 22completed completed100% 100%full fulllength lengthbobbin bobbincoilcoil inspections in inspections in the the first first refueling refueling outageoutageand andisisplanning planning100% 100%full fulllength lengthbobbin bobbincoilcoil inspections in the second second refueling refueling outageoutageof of the the third third inspection inspection period.

period. Braidwood Braidwood Unit 22 and Unit and Byron Unit Unit 22 areare planning 100% 100% full full length bobbin coil inspections inspections during during each future future inspection inspection in in the the third third inspection inspection period.period.

Both Byron Both Byron Unit Unit 11 and and Braidwood Braidwood Unit Unit11completed completed 100% inspection of tubes tubes identified identified with existing with existing andand potential potential damage damage mechanisms mechanisms during during thethe first first inspection period. The The second and second and subsequent subsequentinspection inspectionperiods periodswill will implement implement the the proposed TSTF-510, proposed TSTF-S1 0, Revision 2, inspection inspection periods.

periods.

EGC willwillfully fullyimplement implementthe theminimum minimumsamplingsamplingrequirements requirements and and inspection periods periods in in the subsequent subsequent inspection inspection periods periods in in accordance accordancewith with the the proposed proposed TS 5.5.9.d.2.

S.S.9.d.2.

EGC proposes to revise the

2. EGC the existing existing requirements of of TS 5.5.9.c.2 S.S.9.c.2 and and TSTS 5.5.9.f.2 S.S.9.f.2 by by deleting the ABB Combustion Engineering Inc. (Westinghouse) TIG ABB Combustion TIG welded sleeving sleeving methodology. There repair methodology. Thereare areno noABBABB Combustion Combustion Engineering Engineering Inc. Inc. (Westinghouse)

(Westinghouse)

TIG-welded sleeves TIG-welded sleeves currently currently installed in in the Braidwood Braidwood Station, Unit Unit 2, and and Byron Byron Station, Unit Unit 2, 2, SGs.

SGs. EGC EGC has hasbeen beeninformed informedby bythethesleeve sleevevendor vendorthat thatTIG TIGwelded welded sleeves are sleeves are no no longer longer commercially commercially available.available. As As a result result ofof this change, there there areare no no available SG tube repair repair methods methodsat atBraidwood Braidwood Station Station or or Byron Byron Station; Station; therefore, the the proposed amendment deletes deletes TS TS 5.5.9.f, 5.5.9.c.2, TS S.S.9.c.3, S.S.9.f, TS S.S.9.c.2, 5.5.9.c.3, and references to tube repair and sleevessleeves in in various various TS.

3. One of the improvements improvements in in TSTF-510 TSTF-51 0 was was to revise revise references referencestoto"tube "tuberepair repaircriteria" criteria" to "tube plugging [or repair] criteria." The WaG repair] criteria." WOG Standard Standard TS mark- mark-up up of TS Section 5.5.9, "Steam S.S.9, "Steam Generator Generator(SG) (SG)Program,"

Program," provided provided in in TSTF-510, Revision Revision 2, contained three versions of of paragraph paragraph 5.S.9.d.25.5.9.d.2 (one (oneeacheachfor for600MA 600MAtubing, tubing, 600TT 600TTtubing, tubing, and and tubing). All 690TT tubing). All three versions versions contain contain the thefollowing following statement:

statement:

If a degradation assessment assessmentindicates indicatesthe thepotential potentialfor for aa type type of of degradation degradation to occur at a location location not previously inspected with a technique technique capablecapableof of detecting this type of of degradation at this location and that may may satisfy satisfy the the applicable tube repair criteria, the minimum repaircriteria, minimum number number of of locations locations inspected with such with such a capable inspection inspection technique during during the remainder remainder of of the inspection period inspection periodmay maybe be prorated.

prorated. (emphasis added)

TSTF has determined that this paragraph contains an administrative The TSTF administrative error. error. The The italicized phrase italicized phrase in in paragraph 5.5.9.d.2 5.S.9.d.2 (above)

(above) shouldshouldstate state"tube"tubeplugging plugging[or [orrepair]

repair]

criteria,"consistent criteria," consistent with withthe theother otherchanges changes made in TSTF-S10, TSTF-510, RevisionRevision 2. 2. EGC EGC has has corrected this administrative error in in the the submitted mark-up for for TSTS S.S.9.d.2.

5.5.9.d.2. This This change meets change meetsthe theoriginal original intent intent ofof TSTF TSTF 510.S10.

Page 33 of Page of 6

ATTACHMENT 11 Evaluationof Evaluation of Proposed Proposed ChangesChanges

4. Revised (clean) TS pages pagesare arenot notincluded included in in this amendment request given given the the outstanding Braidwood Braidwood and Byron Byron amendment request request for for Permanent Permanent Alternate Alternate Repair Repair Criteriadated Criteria datedMarch March20, 20,2012, 2012, which whichwillwillimpact impactsome someofofthe thesame same TS TS pages. Providing Providing only mark-ups only mark-upsof ofthe theproposed proposedTS TS changes changes satisfies satisfies thethe requirements requirements of 10 CFR 50.90 50.90 in that in that the the mark-mark-upsups fully fullydescribe describe thethe changes changes desired. This Thisisisan anadministrative administrative deviation fromfrom the the NRC's NRC's model model application application dated October 27,2011, 27, 2011, withwith no no impact on NRC's model the NRC's model safety safety evaluation evaluation published published in inthe the same same Federal Federal Register notice. notice. AsAs aa result of result of this this deviation, deviation, the contents contents and and numbering numbering of of the the attachments attachmentsfor forthis this amendment requestrequest differ from the differ from the attachments attachments specified in in the NRC's model application. Mark-ups Mark-ups of ofthe the proposed proposed TS changes changes for Braidwood Station for Braidwood Stationand andByron Byron Station are Station are provided provided in inAttachments Attachments22and and 3,3, respectively.

respectively. Attachments Attachments 22 and and 33 also also provide mark-ups of the four four TS TS pages pages impacted impacted by by the the proposed proposed TSTF-510 request and the outstanding request for Permanent Alternate Repair Criteria Alternate Repair Criteria(Le.,

(i.e.,TS TSpages pages 5.5-8, 5.5-9, 5.5-10, and 5.5-9,5.5-10, and 5.6-7).

5.6-7).Additionally, Additionally, mark-mark-ups ups ofof the the proposed proposed changes to to the TS Bases pages Bases pagesfor forBraidwood BraidwoodStation Stationand andByron ByronStation Stationare areprovided provided in in Attachments Attachments 44 and 5, respectively.

and respectively. Attachments Attachments 4 and and 55 also also provide provide mark-ups mark-ups of of the the one one TS TS Bases page impacted page impacted by by the the proposed proposedTSTF-51 TSTF-510 0 request requestand andthetheoutstanding outstandingrequest requestfor for Permanent Alternate Permanent AlternateRepairRepairCriteria Criteria (i.e.,

(i.e., TSTSBases Basespage pageBB3.4.19-3).

3.4.19-3). The The proposed proposed changes to changes tothe theTSTSBases Basesare areprovided providedfor forNRC NRCinformation information only only and and do donot notrequire require NRC NRC approval. Changes approval. Changesto tothe the Bases Baseswill willbe beincorporated incorporated in in accordance accordance with with the TS Bases Bases Control Program.

3.0 REGULATORY ANALYSIS

3.1 No Significant No Significant Hazards Hazards Consideration Determination Determination EGC requests adoption of an approved change EGC change to to the the standard standardtechnical technical specifications specifications (STS) (STS) into the into the plant specific Technical Specifications SpeCifications (TS) (TS) for Braidwood Braidwood Station, Units 1 and 2, and and Byron Station, Byron Station, Units Units 11 and and 2, 2, to revise TS 5.5.9, "Steam "Steam Generator Generator(SG) (SG)Program,"

Program,"TS TS5.6.9, 5.6.9, "Steam Generator Generator (SG) (SG) Tube Inspection Inspection Report,"

Report," and TS TS 3.4.19, 3.4.19, "Steam "Steam Generator GeneratorTube Tube Integrity,"totoaddress Integrity," address inspection periods and and other other administrative administrative changes changesand andclarifications.

clarifications.

As required required by 10 CFR 50. 50.91 91 (a), an analysis analysis ofof the the issue issueofofno nosignificant significant hazards hazardsconsideration consideration is presented presented below:

below:

1. Does the proposed proposed change changeinvolveinvolve aasignificant significant increase increase in in the the probability consequences probability or consequences of of an accident previously evaluated?

Response: No. No.

The proposed proposed change changerevises revisesthe theSteam SteamGenerator Generator(SG) (SG)Program Programtotomodify modify the the frequency of verification verificationof ofSGSGtubetube integrity integrityand andSG SG tube tube sample sample selection. AA steam steam generator generator tube tube rupture rupture (SGTR)

(SGTR) event is one of the design deSign basis basis accidents accidents that that areare analyzed as as part part of of a plant's licensing licensing basis. The Theproposed proposedSG SGtube tubeinspection inspectionfrequency frequency and sample selection criteria will continue to ensure sample selection criteria will continue to ensure that the SG tubes that the SG tubes are inspected such that the probability probability of ofaaSGTR SGTRisisnot notincreased.

increased. The consequences consequencesof ofaaSGTR SGTRare are bounded by the conservative assumptions in the design basis accident analysis. The The proposed change change will not cause will not cause the consequences consequences of of aa SGTR SGTR to to exceed exceed those those assumptions.

assumptions. Therefore, Therefore,ititisisconcluded concludedthatthatthis thischange changedoes doesnot notinvolve involvea asignificant significant increase increase inin the the probability probability or or consequences consequences of of an an accident accidentpreviously previously evaluated.

evaluated.

Page Page 44 of of 66

ATTACHMENT 1 ATTACHMENT Evaluationof Evaluation ofProposed Proposed Changes Changes

2. Does

2. Does the proposed proposed change changecreatecreatethe thepossibility possibilityof ofaanew newor ordifferent different kindkind ofof accident accident from from any accident previously previously evaluated?

evaluated?

Response: No.

Response

The proposed changes The changes to to the the Steam SteamGenerator GeneratorProgram Programwill introduce any will not introduce any adverse adverse changes to changes to the the plant plant design design basisbasisor orpostulated postulatedaccidents accidentsresulting resultingfrom from potential potential tube tube degradation. The degradation. The proposed proposedchange changedoes doesnot notaffect affectthethedesign designofofthe theSGsSGsorortheir theirmethod methodof of operation. In operation. In addition, addition, the the proposed change does does notnot impact impact anyany other other plant plant system system or or component.

Therefore, itit isis concluded Therefore, concluded that that this this change change does not not create create the the possibility possibility of a new or different kind different kindof ofaccident accident from fromany any accident accident previously previously evaluated.

evaluated.

3. Does the proposed

3. proposed change changeinvolve involve aasignificant significant reduction reduction in in aa margin margin of of safety?

safety?

Response: No. No.

The SG tubes in in pressurized pressurized water water reactors reactors are areananintegral integralpart partof of the thereactor reactorcoolant coolant pressure boundary pressure boundary and, as assuch, such,are arerelied reliedupon uponto tomaintain maintain the the primary primary system's system's pressure pressure and inventory.

inventory. As part of the reactor coolant of the coolant pressure pressure boundary, the SG tubes are are unique unique inin that they are also relied upon as aa heat heat transfer transfer surface surface between between the theprimary primary and and secondary secondary systems suchsuch thatthat residual residual heat heat cancan be beremoved removedfrom from thethe primary primary system. In In addition, addition, the the SG tubes tubes also also isolate isolatethe theradioactive radioactivefission fission products productsinin the theprimary primary coolant coolant from from the the secondary system.

secondary system. InInsummary, summary,the thesafety safetyfunction function of of aaSG SGisismaintained maintainedby byensuring ensuringthe the of its integrity of its tubes.

Steam generator generatortube tubeintegrity integrity is is aa function function of the design, design, environment, environment, and and the thephysical physical condition condition of ofthethetube.

tube. The proposed change change does doesnot notaffect affect tube tube design design or oroperating operating environment. The Theproposed proposedchange changewill willcontinue continuetotorequire requiremonitoring monitoring of of the the physical physical condition condition of of thethe SGSG tubes such such thatthat there therewill will not be aa reduction reduction in in the the margin margin of of safety safety compared to to the current current requirements.

The proposed amendmentamendment deletes deletesthe thecurrent current TSTS 5.5.9.c.2 5.5.9.c.2and andTS TS5.5.9.f.2 5.5.9.f.2 allowance allowance to to use use ABB Combustion Engineering ABB Combustion Engineering Inc. Inc.TIG TIGwelded weldedsleeves sleeves asas a steam generator generator tube tuberepair repair method. ThereThereare arenonoABB ABBCombustion CombustionEngineeringEngineeringInc. Inc.(Westinghouse)

(Westinghouse)TIG-welded TIG-welded sleeves sleevescurrently currently installed installed in in the theBraidwood Braidwood Station,Station, Unit Unit 2, 2, and andByronByron Station, Station, UnitUnit 2, 2, SGs.

SGs.

EGC has has been been informed informed by by the sleeve sleeve vendorvendor that that TIG TIG welded sleeves sleeves areareno nolonger longer commercially available. As a result of this change, there commercially available. there are are nono available available SG SG tube tuberepair repair methods methods for for Braidwood Braidwood StationStation or or Byron ByronStation.

Station. The The proposed amendment amendment deletes deletes TS 5.5.9.f, TS 5.5.9.c.2, TS 5.5.9.c.3, and references to to tube repair repair andand sleeves sleevesin in various various TS. Removing Removing the theability ability for tube repair methods is conservative; therefore, the proposed proposed change changedoes doesnot notinvolve involveaasignificant significantreduction reductionininaamargin marginof ofsafety.

safety.

Therefore, itit is concluded that the the proposed proposedchange changedoes doesnotnotinvolve involvea asignificant significantreduction reduction in a margin margin of of safety.

safety.

Based Based onon the the above, above, EGC EGC concludes concludes that that thethe proposed proposedchangechangepresents presentsnonosignificant significanthazards hazards consideration consideration under under the the standards standardsset setforth forthinin10 10CFR CFR50.92(c),

50.92(c),and, and,accordingly, accordingly,a afindingfindingofof "no significant Significant hazards hazards consideration" consideration"isisjustified.

justified.

Page Page 55of of 66

ATTACHMENT 11 Evaluationof Evaluation of Proposed Proposed Changes Changes 4.0 ENVIRONMENTAL EVALUATION The proposed proposed change changewouldwould change changea arequirement requirementwith withrespect respecttotoinstallation installationororuse useofofa afacility facility component located within the restricted within the restricted area, area, as as defined defined inin 10 10 CFR CFR 20, 20, or or would change change an an inspection or inspection or surveillance surveillance requirement.

requirement. However, However, the proposed proposed changechangedoesdoesnotnotinvolve involve(i)(i) aa significant hazards significant hazards consideration, (ii) (ii) a significant change in the types significant change types or or significant significant increase increase in in the amounts amounts of of any any effluent effluent that may may be be released releasedoffsite, offsite,oror(iii)

(iii) aa significant significant increase increase inin individualor individual orcumulative cumulativeoccupational occupationalradiation radiationexposure.

exposure. Accordingly, Accordingly, the the proposed change change meets the meets the eligibility criterion for eligibility criterion for categorical categorical exclusion set set forth forth inin 10 10 CFR CFR 51.22(c)(9).

51.22(c)(9).

Therefore, pursuant pursuant to to 10 10 CFR CFR 51.22(b),

51.22(b), no no environmental environmental impact impactstatement statementor orenvironmental environmental assessment need assessment needbe beprepared preparedininconnection connectionwith with the the proposed proposed change.

change.

Page Page 66 ofof 6

ATTACHMENT 2 ATTACHMENT Proposed Technical Specifications Proposed Specifications Changes Changesfor for Braidwood Braidwood Station, Station, Units Units 1 and 2 Braidwood Station, Braidwood Station, Units 1 and 2 Facility Operating Facility Operating License License Nos.

Nos. NPF-72 NPF-72 and and NPF-77 NPF-77 Mark-up of Technical Specifications Pages 3.4.19-1 3.4.19-2 5.5-7 5.5-7 5.5-8 5.5-8 5.5-9 5.5-9 5.5-10 5.5-10 5.6-6 5.6-6 5.6-7 5.6-7

SG SG Tube Tube Integrity Integrity 3.4.19 3.4.19 3.4 3.4 REACTOR REACTOR COOLANT COOLANT SYSTEM (RCS)

SYSTEM (RCS) 3.4.19 3.4.19 Steam Steam Generator Generator (SG)(SG) Tube Tube Integrity Integrity LCO LCO 3.4.19

3. 4.19 SG SG tube tube integrity integrity shall shall be be maintained.

maintained.

AND plugging I

~PIUgging AND All All SGSG tubes tubes satisfying satisfying the tube repair criteria the tube criteria shall shall bebe plugged plugged or repaired in accordance ifed-in accordance with the Steam with the Steam Generator Generator Program.

Program.

APPLICABILITY:

APPLICABILITY: MODES MODES 1,1, 2, 2, 3, 3, and and 4.

4.

ACTIONS ACTIONS

NOTE-----------------------------------------

NOTE -----------------------------------------

Separate Condition entry Separate Condition entry isis allowed allowed for for each each SGSG tube.

tube.

CONDITION CONDITION REQUIRED REQUIRED ACTION ACTION COMPLETION COMPLETION TIME TIME A. One A. or more One or more SGSG tubes tubes A.1 A.1 Verify tube integrity Verify tube integrity 77 days days satisfying the tube satisfying the tube of the affected of the affected plugging ee^ criteria

~repair criteria and and tube(s) tube(s) is is maintained maintained Iplugging plugged -er not plugged until the until the next next repaired in yep in accordance accordance refueling outage refueling or outage or with the with the Steam Steam SG tube inspection.

SG tube inspection.

Generator Program.

AND AND A.2 A.2 Plug or repair the Plug the Prior to Prior to affected tube(s) affected in tube(s) in entering MODE entering MODE 44 accordance with accordance with the the fo 11 owi ng the following the Steam Generator Steam Generator next refueling next refueling Program.

Program. outage or outage or SG SG tube inspection tube inspection B.

B. Required Action Required Action andand B.1 B.1 Be in Be in MODE MODE 3.3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 6 hours associated Completion associated Completion Time of Time of Condition Condition AA AND AND not met.

not met.

B.2 B.2 Be in Be in MODE MODE 5.5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months 36 hours OR OR SG tube SG tube integrity integrity notnot maintained.

maintained.

BRAIDWOOD -- UNITS BRAIDWOOD &

UNITS 11 & 22 3.4.19 -- 11 3.4.19 Amendment-144 Amendment -+/-44

SG SG Tube Tube Integrity Integrity 3.4.19 3.4.19 SURVEILLANCE REQUIREMENTS SURVEI LLANCE SURVEILLANCE I FREQUENCY FREQUENCY SR 3.4.19.1 Verify Verify SGSG tube tube integrity integrity in in accordance accordancewith with InIn accordance accordance the the Steam Generator Program.

Steam Generator Program. with with the the Steam Steam Generator Generator Program Program SR 3.4.19.2 SR 3.4.19.2 Verify Verify that that each inspected SG each inspected SG tube tube that that Prior to Prior to satisfies satisfies the tube repair criteria the tube is criteria is entering MODE entering MODE 44 plugged plugged or repaired i~ccordance i^r--i with the accordance with the following following a a SG SG Steam Generator Progra Steam Generator Program.

^. tube inspection tube inspection BRAIDWOOD UNITS 11 &&22 BRAIDWOOD -- UNITS 3.4.19-2 3.4.19 - 2 Amendment 444, Amendment .f44

Programs and Programs and Manuals Manuals 5.5 5.5 5.5 5.5 Programs and Programs and Manuals Manuals 5.5.9 5.5.9 Steam Generator Steam (SG) Program Generator (SG) Program A Steam A Steam Generator Generator Program Program shall shall be be established established and and implemented implemented to to ensure that ensure that SG SG tube integrity is tube integrity is maintained.

maintained. In In addition, addition, thethe Steam Generator Steam Generator Program Programshallshall include includethe following provisions:

the followings-:

a.

a. Provisions for Provisions for condition condition monitoring monitoring assessments.

assessments. Condition Condition monitoring assessment monitoring assessment means means an an evaluation evaluation of of thethe "as "as found" found" condition of condition of the the tubing tubing with with respect respect to to the the performance performance criteria for criteria for structural structural integrity integrity and and accident accident induced induced leakage. The leakage. The "as "as found" found" condition condition refers refers toto thethe condition condition of the of the tubing tubing during during an an SG SG inspection inspection outage,outage, as as determined determined from the from the inservice inservice inspection inspection resultsresults or or by by other other means, means, prior to prior to the the plugging plugging ef--or repair ' of tubes. Condition of tubes. Condition monitoring assessments shall monitoring assessments shall be be conducted conducted during during eacheach outage outage during during which the SG which the SG tubes tubes are are inspected, plugged, or repaired toto confirm confirm that that thethe performance`criteria performanc riteria are are being being met.

met. inspected inspected or or plugged plugged b.

b. Performance Performance criteria criteria for for SGSG tube tube integrity.

integrity. SG SG tube tube integrity integrity shall shall bebe maintained maintained by by meeting meeting thethe performance performance criteria for tube criteria for tube structural structural integrity, integrity, accident accident induced induced leakage, and operational leakage, and operational LEAKAGE.

LEAKAGE. ),

1.

1. Structural integrity performance Structural integrity performance cliterion:

c iterion: All All in-service service steam steam generator generator tubes tubes shal retain struc shal retain struc ural integrity over the integrity over the full full range range of of n ormal operati ormal operati conditions startup, o0 ation (including startup, conditions (including ation in in the the power power range, hot standby, range, hot standby, and and coolcool down down-ate-all

~a11 anti anti ated ated transients included in transients included in the the design design specification4 specificatio and and design basis accidents.

design basis accidents. This includes retaining This includes retaining aa safety factor of safety factor of 3.0 3.0 against against burstburst under under normal normal steady steady state state full power operation full power operation primary-to-secondary primary-to-secondary pressure pressure differential differential and and aa safety safety factor factor of of 1.4 1.4 against against burst applied to burst applied to thethe design basis accident design basis accident primary-to-secondary primary-to-secondary pressurepressure differentials.

differentials. Apart Apart from from the above requirements, the above requirements, additional additional loading loading conditions associated with conditions associated with the the design design basisbasis accidents, accidents, or or combination combination of of accidents accidents in in accordance accordance with with the the design design and licenSing basis, and licensing basis, shallshall also also be be evaluated evaluated toto determine determine if if the the associated associated loads loads contribute contribute significantly significantly to to burst burst or or collapse.

collapse. In In the the assessment assessment of of tube integrity, those tube integrity, those loadsloads that that dodo significantly significantly affect affect burst burst oror collapse collapse shall shall bebe determined determined and and assessed assessed in in combination combination with with the the loads loads due due to to pressure pressure with with a a safety safety factor factor of of 1.21.2 onon the the combined combined primary primary loads loads and 1.0 on and 1.0 axial secondary on axial secondary loads.loads.

BRAIDWOOD UNITS 11 &&22 BRAIDWOOD -- UNITS 5.5 5.5 -- 7 7 Amendment -+/-44 Amendment 4-44

Programs Programs and and Manuals Manuals 5.5 5.5 5.5 Programs 5.5 and Manuals Programs and Manuals 5.5.9 5.5.9 Steam Steam Generator Generator (SG) (SG) Program (continued)

Program (continued) 2.

2. Accident induced leakage Accident induced leakage performance performance criterion:

criterion: The The primary primary to to secondary secondary accident induced leakage accident induced leakage rate rate forfor any any design design basis accident, other basis accident, other thanthan aa SG SG tube tube rupture, rupture, shallshall not not exceed exceed the the leakage leakage rate rate assumed assumed in in the accident analysis the accident analysis in in terms terms of of total total leakage leakage rate rate for for all SGs and all SGs and leakage leakage rate rate forfor anan individual individual SG. SG.

Leakage Leakage is is not not to exceed aa total to exceed total of of 11 gpmgpm for for allall SGs.SGs.

3.

3. The operational LEAKAGE The operational LEAKAGE performance performance criteriacriteria is is specified specified in LCO 3.4.13, in LCO 3.4.13, "RCS "RCS Operational Operational LEAKAGE."

LEAKAGE."

c.

c. P ..

rOV1Slons Provisions f

for SG tube or SG ~. - crl t ube rcpalr . t erla.1' criteria.

plug jnc I

. Iplugging

~ L:Tubes found l- u-Tubes found byby inservice inservice inspection inspection to to contain contain flaws flaws in a non sleeved region with with a a depth depth equal equal to to oror exceeding exceeding 40% 40% of of the nominal wall the nominal thickness shall wall thickness shall be be plugged or repaired.

plugged -ned. The following alternate The following alternate tube tube repair criteria criteria shall shall be be applied applied as as anan alternative'to alternative 0 the the 40% 40% depth depth based based criteria:

cri teri a: plugging For For Unit Unit 2 2 during Refueling Outage during Refueling Outage 15 and the 15 and the subsequent operating cycle, subsequent operating cycle, tubestubes withwith service-service-induced flaws located induced flaws located greater greater thanthan 16.95 inches 16.95 inches below the below the top top of the tubesheet of the tubesheet do do not not require require plugging plugging-c- or repair. a-i-. Tubes Tubes with service-induced with service-induced flaws located in flaws located in the the portion portion of of the the tube tube fromfrom the the top top of of the the tubesheet tubesheet to to 16.95 inches below 16.95 inches below the the top top of of the the tubesheet tubesheet shall shall be beplugged plugged-e-f or repaired a

upon detection.

b Sl eeves found by i nser'o'i ce i nspecti on to contai n fl a~~'s

',~i tt1 a deptt1 equal to or e)~ceedi ng tt1e foll o',~i ng percentages of tt1e nomi nal sl eeve \Jall tt1i cl<ness st1all be plugged:

a-.

4-;- For Unit 2 only, TIC ',v'Clded sleeves (per TS S.S.9.f.2.i): 32%

3.

-3. Tubes ~'i tt1 a fl a'vJ ina sl eeve to tube joi nt tt1at occurs in the sleeve or in the original tube \Jall of tt1e joint shall be plugged.

BRAIDWOOD UNITS 11 &&22 BRAIDWOOD -- UNITS 5.5 5.5 -- 8 8 Amendment Amendment +66-

Programs Programs and Manuals and Manuals 5.5 5.5 5.5 5.5 Programs Programs andand Manuals Manuals 5.5.9 5.5.9 Steam Steam Generator Generator (SG)(SG) Program (continued)

Program (continued)

d. Provisions Provisions for for SGSG tube tube inspections. Periodic SG inspections. Periodic SG tube tube inspections inspections shall shall be be performed.

performed. The number and The number and portions portions of of the the tubes inspected and tubes inspected and methods methods ofof inspection inspection shall shall be be performed performed with the objective with the objective of of detecting detecting flaws flaws ofof any any type type (e.g.,

(e.g., volumetric flaws, axial volumetric flaws, axial and and circumferential circumferential cracks)cracks) that that may may bebe present present along along thethe length length ofof the the tube, tube, from from the the tube-to-tubesheet tube-to-tubesheet weld weld at at the the tube tube inlet inlet to to the the tube-to-tube-to-

'lp~lu-g-g~in-g--'ltubesheet lgging tubesheet weld~ft weld at thethe tube tube outlet, outlet, and and that that maymay satisfy satisfy the the applicable applicable tube-repair tubs criteria.

criteria. For For Unit Unit 2 2 during during Refueling Refueling Outage Outage 15 15 and and thethe subsequent subsequent operating operating cycle, cycle, portions portions of of the tube below the tube below 16.95 16.95 inches inches from from the the top top ofof the the tubesheet tubesheet are excluded from are excluded from this this requirement.

requirement.

The The tube-to-tubesheet tube-to-tubesheet weld weld isis not not part part ofof the the tube.

tube. In In addition addition to to meeting the requirements meeting the requirements of of d.1, d.1, d.2, d.2, and and d.3 d.3 below, the inspection below, the inspection scope, scope, inspection inspection methods, methods, and and A degradation derdtlon ins ection intervals inspection intervals shall shall be be such such asas to to ensure ensure that that SGSG tube tube assessment assessment 1n in egr1 egri yyis 1S main ma1n ainecptil a1ne tilthe thenext next SGSG inspection.

inspection. Aft Afi tt5-!~5ffIE~--ffl'---ffi~ttetrH-'efTsha be performed 11 be shall performed to to determine determi ne the the type type andand location location of of flaws flaws toto which which thethe tubes tubes may may be be susceptible susceptible and, and, based based on on this this assessment, assessment, to to determine determine which inspection methods which inspection methods needneed to to be be employed employed and and at at what what locations.

locations. installation Inst^llaticn

1. Inspect Inspect 100%100% ofof the the tubes tubesinineach eachSCE/,during Suring the the first first refueling refueling outage following SG outage following SG -PeEl-I-at~~

pm.'er months. The fi rst sequenti al peri od shall be considered to begin after the first inservice inspection of the SGs. In addition, inspect 50% of the tubes by the refueling outage nearest the midpoint of the period and the remaining 50% by the refueling outage nearest the end of the period. No SG shall Replace with operate for more than 72 effecti ve full pO'h'er months or three refuel i ng outages (~Jhi chever is 1ess) 'h'i thout being inspected.

Inspect 100% of the Unit 2 tubes at sequential periods of 120, 90, and, tAereafter, 60 effect; 'Ie full pO'.JCP months. The first sequential period shall be considered to begin after tAe first inservice inspection of the SGs. In addition, inspect 50% of tAe tubes by the refueling outage nearest the midpoint of the period and the remaining 50% by tAe refueling outage nearest the end of the period. No SG shall operate for more tAan 48 effecti ve full pm,'er montAs or two refuel i ng outages ('n'hi chever is 1ess) \Ji thout being inspected.

BRAIDWOOD - UNITS BRAIDWOOD &

UNITS 11 & 22 5.55 -- 99

5. Amendment Amendment i:-66

I INSERT 1

2. Unit 1, For Unit 1, after after the the first refueling outage first refueling outage following following SG SG installation, installation, inspect each each SG at least least every every7272effective effective full full power months months or or at at least leastevery everythird third refueling refueling outage (whichever results in in more frequent inspections). In In addition, addition, the minimum number of tubes inspected at at each each scheduled scheduled inspection inspection shall shall bebethethe number of tubes in all SGs divided by the number number of of SG SG inspection inspection outages outages scheduled in each inspection period as defined in a, b, c, and d below. IfIfaa degradation assessment indicates the potential for a type of degradation to occur at a location not previously inspected with with a technique capable of detecting this type of degradation at this location and and that that may may satisfy satisfy the the applicable applicabletube tube plugging criteria, the minimum number number of of locations locations inspected inspected with with such such aacapable capable inspection technique during the remainder remainder of of the the inspection inspection period period maymaybe be prorated. The prorated. The fraction fraction ofoflocations locations to to be be inspected inspected for for this this potential potential type type of of degradation at this location at the end end of of the the inspection inspection periodperiod shall shall be be no noless less than the ratio of the number of times the SG is scheduled to be inspected in the inspection period after the determination that aa new new form form of of degradation degradation could could potentially be occurring at this location divided divided by the total number of times the by the total number of times the inspected in the inspection period. Each SG is scheduled to be inspected Each inspection inspectionperiodperiod defined below may be extended up up toto 33 effective effective fullfull power powermonths monthsto toinclude includeaa SG inspection outage in an inspection period and the subsequent inspection period and the subsequent inspection inspection period begins at the conclusion of of the included included SG SG inspection inspection outage.outage.

a) After the first refueling outage following SG installation, inspect 100% of of the tubes during the the next 144 144 effective effective full full power power months.months. This constitutes the first inspection period;period; b) During the next 120 effective full power power months, months, inspect inspect 100%100%of ofthe the tubes. This This constitutes constitutes thethe second second inspection inspection period; period; c) During the next 96 effective full power power months, months, inspect inspect 100%100%of ofthe thetubes.

tubes.

This constitutes the third inspection inspection period;period; andand d) During the During the remaining remaining lifelifeof ofthe theSGs, SGs, inspect inspect 100%

100% of of the the tubes tubes every 72 effective full effective fullpower powermonths.

months. ThisThis constitutes constitutes the the fourth fourth andand subsequent subsequent inspection periods.

3. Unit 2, For Unit 2, after after the the first first refueling refueling outage outage following following SG SG installation, installation, inspect each each SG at least least every every 48 48 effective effective full full power months months or or at at least leastevery everyother otherrefueling refueling outage (whichever results in more frequent inspections). In In addition, addition, the minimum number of tubes inspected at at each each scheduled scheduled inspection inspection shallshall bebethethe number of tubes in all SGs divided by by the the number number of of SG SG inspection inspection outages outages scheduled in each inspection period period as defined in a, a, b, b, and c below. IfIfaa degradation assessment indicates indicates the potential for a type of the potential for a type ofdegradation degradationto tooccur occur at a location not previously inspected with aa technique technique capable of detectingthis capable of detecting this type of degradation at this location and and that that may may satisfy satisfy the the applicable applicabletube tube plugging criteria, the minimum number number of of locations locations inspected inspected with with such such aa capable capable inspection technique during the remainder of of the the inspection inspection period period maymaybe be prorated. The prorated. The fraction fraction ofoflocations locations to to be be inspected inspected for for this this potential potential type type of of degradation at this location at the end end of of the the inspection inspection periodperiod shall shall be be no noless less

INSERT1I (continued)

INSERT (continued) than the ratio of the the number of times the SG is scheduled scheduled to to be be inspected inspectedinin the the inspection period after the determination that aa new new form form of degradation couldcould potentially be potentially be occurring occurring at this location divided divided byby the the total total number of times the SG is scheduled to be inspected inspected in in the the inspection inspection period.

period. Each Eachinspection inspectionperiod period defined below may be extended extended up upto to33effective effective full full power months to include a SG inspection outage in an inspection period period and the subsequent subsequent inspection inspection period begins at the conclusion period conclusion of the included SG inspection outage.

a) After the first refueling outage following SG installation, inspect 100% of effective full the tubes during the next 120 effective full power power months.

months. This This constitutes the first inspection inspection period; period; b) During the next 96 effective effective full full power power months, months, inspect inspect100%

100%of ofthe thetubes.

tubes.

This constitutes the second second inspection inspection period; period; and and c) During the remaining lifelife of of the the SGs, SGs, inspect inspect 100%

100% of ofthe the tubes tubes every every7272 full power months.

effective full months. This This constitutes constitutes the the third and subsequent inspection periods.

Programs Programs and Manuals and Manuals 5.5 5.5 5.5 5.5 Programs Programs and and Manuals Manuals 5.5.9 Steam SteamGenerator Generator (SG) (SG) Program (continued)

Program (continued) affected and potentially potentially affected affected

4. 3- For For Unit Unit 1,1, if if crack indications are crack indications are ffo dd inin any any SG SG tube, tube, then then thethe next next inspection inspection forfor each each GGfor for the the degradation mechanism degradation that caused mechanism that caused the the crack crack indication indication shall not shall not exceed exceed 24 24 effective full power effective full power months months or or one one results in in more more refuelinq outaqe refueling outage (whicheve'"

(whichever'~v '~vv). For For Unit Unit 22 frequent frequent inspections during Refueling Outage during Refueling 15 ~nd Outage 15 the subsequent and the subsequent operating operating cycle,cycle, if if crack crack indications indications are are found found in in any any SG SG tubetube from inches below 16.95 inches from 16.95 below the the top top of of the the tubesheet on tubesheet on the hot leg the hot leg side side toto 16.95 inches below 16.95 inches below affected and andpotentially potentially{ the the too to of ofthethetubesheet tubesheet onon~the cold leg he cold leg side, side, then then affected the the nextnext inspection inspection for eac eac~SG SG forfor the thedegradation degradation mechanism mechanism that that caused caused the the crack crack indication indication shall shall not not exceed exceed 24 effective effective fullfull power power months months or or one one refueling refueling results in in more more outage (whichever asl-ems) outage (whichever js less)..

frequent frequ ent inspections If If definitive definitive information, such as information, such as from from examination examination of of aa pulled pulled tube, tube, diagnostic diagnostic non-destructive testing, or non-destructive testing, or engineering engineering evaluation indicates that evaluation indicates that aa crack-like crack-like indication indication is is not not associated associated with with aa crack(s),

crack(s), then then the the indication indication need need not not be be treated treated asas aa crack.

crack.

e.

e. Provisions Provisions for for monitoring monitoring operational primary to operational primary to secondary secondary LEAKAGE.

LEAKAGE.

~ Provisions for SG tube repair ffiethods. Steaffi generator tube repair ffiethods shall provide the ffieans to reestablish the RCS pressure boundary integrity of SG tubes ',Jithout reffioving the tube froffi service. For the purposes of these Specifications, tube plugging is not a repair.

+/--:- There are no approved tube repair ffiethods for the Unitt 11-SGs.

SGs.

~ All acceptable repair ffiEthods for &F44the isue;+

Unit 22SGs are cr ,ie-1i sted bel O',d.

4--;- TIG ',,'81 ded sl eevi ng as descri bed in ASS GOffibustion Engineering Inc., Technical Reports:

L* . Rot CEN ~1 P, R v** ee,

"~~=~:~ali~ ~dison Byron and ~~!~d~;Od Unit 1 and 2 Steaffi Generators Tube Repair Using Leal<

Ti ght Sl eeves, FI NAL REPeRT," April 1995; and Li censi ng Report CEN 627 P, "eperati ng Perforffiance of the ASS GENe Steaffi Generator Tube Sl eeve for Use at COffiffiomJeal th Edi son Byron and Braid~mod Units 1 and 2," January 1996; subject to the liffiitations and restrictions as noted by the NRC Staff.

BRAIDWOOD UNITS 11 &&22 BRAIDWOOD -- UNITS 5.5 5.5 -- 10 10 Amendment Amendment +/-66466

Reporting Requirements Reporting Requirements 5.6 5.6 5.6 5.6 Reporting Requirements Reporting Requirements 5.6.8 5.6.8 Tendon Tendon Surveillance Report Surveillance Report Any Any abnormal abnormal degradation degradation of of the the containment containment structure structure detected detected during during thethe tests required by tests required by the the Pre-Stressed Pre-Stressed Concrete Concrete Containment Containment Tendon Tendon Surveillance Program shall Surveillance Program shall bebe reported reported inin the the Inservice Inservice Inspection Summary Inspection Report in Summary Report in accordance accordance with with 1010 CFR CFR 50.55a 50.55a and and ASME Section XI.

ASME Section XI.

5.6.9 5.6.9 Steam Steam Generator (SG) Tube Generator (SG) Tube Inspection Inspection Report Report A report shall A report shall be be submitted submitted within within 180180 days days after after the the initial initial entry entry into MODE into MODE 44 following completion of following completion of an an inspection inspection performed performed inin accordance accordance with Specification 5.5.9, with Specification 5.5.9, Steam Steam Generator Generator (SG)

(SG) Program.

Program.

The report shall The report shall include:

include:

~ a The scope of The scope of inspections inspections performed performed onon each each SG, SG, I[Degradation Degradation I h ~

b. Active degradation mechanisms found, mechanisms found, c.

c. Nondestructive examination techniques Nondestructive examination techniques utilized utilized forfor each each degradation mechanism, degradation mechanism, d.

d. Location, Location, orientation orientation (if (if linear),

linear), and and measured measured sizes sizes (if (if available) available) ofof service service induced induced indications, indications,

. e.

e. Number of Number of tubes tubes plugged plugged or repaired e- -epa ir-ed during during the the inspection inspection outage for each outage for each active degradation mechanism, degradation mechanism,

f. ,Total nUffiber and percentage of tubes plugged or repaired to r------~/fl:a-te-;-

g.

g. The results The results of of condition condition monitoring, monitoring, including including thethe results results ofof tube pulls and tube pulls and in-situ in-situ testing, testing, fr.- The effective plugging percentage for all plugging and tube repairs in each se,

~ Repair ffiethod utilized and the nUffiber of tubes repaired by each repair method, The number and percentage of of tubes plugged plugged to date, and the

- effective plugging percentage effective plugging percentage in in each steam steam generator, generator, BRAIDWOOD -- UNITS BRAIDWOOD &

UNITS 11 & 22 55.6

.6 -- 66 Amendment Amendment -+/-6+/-

Reporting Requirements Reporting Requirements 5.6 5.6 5.6 Reporting Requirements 5.6 Reporting Requirements 5.6.9 5.6.9 Steam Steam Generator Generator (SG)

(SG) Tube Tube Inspection Inspection Report (continued)

Report (continued)

For For Unit 2 following Unit 2 completion of following completion of an an inspection inspection performed performed inin Refueling Refueling Outage Outage 1515 (and (and any any inspections inspections performed performed in in the the I subsequent subsequent operating operating cycle),

cycle), thethe operational operational primary primary to to secondary leakage rate secondary leakage rate observed observed (greater (greater than than three three gallons gallons per day) per in each day) in each steam steam generator generator (if(if it it is is not not practical practical to to assign assign the the leakage leakage to to an individual steam an individual steam generator, generator, thethe entire primary to entire primary to secondary leakage should secondary leakage should be be conservatively conservatively assumed assumed to to be be from from one one steam steam generator) during the generator) during the cycle cycle preceding the preceding the inspection inspection which which isis the the subject subject of of the the report, report, and and 7 For For Unit 2 following Unit 2 completion of following completion of an an inspection inspection performed performed inin Refueling Refueling Outage Outage 15 (and any 15 (and any inspections performed in inspections performed in the the I subsequent subsequent operating operating cycle),

cycle), the calculated accident the calculated accident induced induced leakage rate from leakage rate from the the portion portion ofof the tubes below the tubes below 16.95 16.95 inches inches from from the the top top ofof the the tubesheet tubesheet forfor the the most most limiting limiting accident accident in in the the most most limiting limiting SG.SG. InIn addition, addition, if if the the calculated calculated accident induced leakage accident induced leakage rate rate from from the the most limiting accident most limiting accident is is less less than than 3.11 times the 3.11 times the maximum maximum operational operational primary primary to to secondary secondary leakage rate, the leakage rate, report should the report should describe describe howhow it it was was determined, determined, andand 3+- For For Unit Unit 22 following completion of following completion of an an inspection inspection performed performed inin Refueling Refueling Outage Outage 1515 (and (and any any inspections inspections performed performed in in the the I subsequent subsequent operating operating cycle),

cycle), the results of the results of monitoring monitoring for for tube tube axial axial displacement displacement (slippage).

(slippage). If If slippage slippage is is discovered, discovered, the implications of the implications of the the discovery discovery andand corrective corrective action shall be action shall be provided.

provided.

BRAIDWOOD UNITS 11 &&22 BRAIDW00D -- UNITS 5.6 5.6 -- 77 Amendment Amendment .f:66.

46

THIS MARKUP THIS MARKUP OF OF TS TS PAGE PAGE 5.5-8 5.5-8 REFLECTS CHANGESC HANGES PROPOSED IN PROPOSED IN THE THE H*

H* PERMANENT ALTERNATE ALTERNATE REPAIR Programs Programs and and Manuals Manuals CRITERIA LAR CRITERiA LAR DATED MARCH 20, 20, 201x2.

2012. 5.5 5.5 5.5 Programs 5.5 Programs and and Manuals Manuals 5.5.9 5.5.9 Steam Steam Generator Generator (SG)(SG) Program (continued)

Program (continued) 2.

2. Accident induced leakage Accident induced leakage performance performance criterion: criterion: The The primary primary toto secondary secondary accident accident inducedinduced leakage leakage rate rate for for any any design design basis basis accident, accident, other other than than a a SG tube SG tube rupture, rupture, shall shall not not exceed exceed the the leakage leakage rate rate assumed assumed in in the the accident accident analysis analysis in in terms terms of total leakage of total leakage rate rate for all SGs for all SGs andand leakage leakage rate rate forfor an an individual individual SG. SG.

Leakage Leakage isis not not to exceed aa total to exceed total of of 11 gpm gpm for for all all SGs.SGs.

3.

3. The The operational operational LEAKAGELEAKAGE performance performance criteria criteria is is specified specified in in LCOLCD 3.4.13, 3.4.13, "RCS "RCS Operational Operational LEAKAGE." LEAKAGE."

c. P ..

rOV1Slons Provisions f SG tube or SG for

~. crl tu be flu^

rcpalr . t . [plugging erla.1'.

criteria plugging J

~ L-Tubes found by Tubes found by inservice inservice inspection inspection to to contain contain flaws flaws in a non sleeved region with with a a depth depth equal equal to to oror exceeding exceeding 40%40% of of the the nominal nominal wall wall thickness thickness shall shall be be plugged plugged--eor repaired. red-. The following alternate The following alternate tube tube repair criteria criteria shall shall be be applied applied as as an an alternative alternative o 0 the the 40% depth based 40% depth based criteria:

cri teri a: 14.01 1 14, J9 11 plugging plugging For Unit 2~~~~~~&+~~~~~~*

subsequent operating cycle,, tubes tubes wit service-witservice-induced induced flawsflaws located located greater greater than than ~ inches inches below the below the top top of of the the tubesheet tubesheet do do not not require require plugging or--rrepair.

plugging-e p . Tubes with Tubes with service-induced service-induced flaws located flaws located in in the the portion portion of of the the tube tube fromfrom the the top of top of the the tubesheet tubesheet to to . inches inches belowbelow the the top of top of the the tubesheet tubesheet shal shat be be plugged plugged or repaired ii e4 upon detection.

upon detection. 14.01 b -&I eeves found by i nservi ce i Aspect; OA to cOAtai Afl my's

~"i th a depth equal to or e)(ceeEi~ ng tAe fall m'l'i ng percentages of the nominal sleeve wall thickness shall be pluggeEi:

-be-p ggcd-:

4-;- For Unit 2 only, He ~I'el deS- sl eeves (per =r&

5.5.9.f.2.i): 32%

3.

-3. =rubes with a flaw in a sleeve to tube joint that occurs in the 51 eeve or in the ori 9i nal tube -wan of the joint shall be piugged.

BRAIDWOOD -- UNITS BRAIDWOOD &

UNITS 11 & 22 5.5 -- 88 5.5 Amendment 466 Amendment +/-66

THIS MARKUP MARKUP OF TS PAGE 5.5-9 REFLECTS REFLECTS CHANGESC HAN G ES PROPOSED PROPOSED ININTHETHEH* H* PERMANENT PERMANENTALTERNATE ALTERNATE REPAIR REPAIR CRITERIA LAR LAR DATED DATED MARCH MARCH 20, 2012.

20, 2012.

Programs Programs and Manuals and Manuals 5.5 5.5 5.5 Programs 5.5 Programs and and Manuals Manuals 5.5.9 5.5.9 Steam Steam Generator Generator (SG)(SG) Program (continued)

Program (continued) d.

d. Provisions Provisions for for SGSG tube tube inspections. Periodic SG inspections. Periodic SG tube tube inspections shall be inspections shall be performed.

performed. The number and The number and portions portions of of the the tubes inspected and tubes inspected and methods methods ofof inspection inspection shallshall bebe performed with performed with the the objective objective of detecting flaws of detecting flaws of of any any type type (e.g.,

(e.g., volumetric volumetric flaws, axial and flaws, axial and circumferential circumferential cracks)cracks) that that may may be be present present alongalong the length of the length of the the tube, tube, from from thethe tube-to-tubesheet tube-to-tubesheet weld weld atat the the tube tube inlet inlet toto the the tube-to-tube-to-I'-p""-Iu-g-gi:-n-g---'I plugging tubesheet tubesheet welweld at the d-...ft tube outlet, the tube outl et, and and that that may may satisfy sati sfy the the applicable applicable tube-repair tuba criteria. criteria.ForForUnit Unit 22 during Refueling Outage 15 and the subsequent operating cycle,,

3 ti ng Reyc portions portions of of the the tube tube below below . inches from the inches from the top top ofof the the tubesheet tubesheet areare excluded excluded from from thi thi equirement.

equirement.

14.01 The The tube-to-tubesheet tube-to-tubesheet weld weld isis not not pa par o he he tube.

tube. In In addition addition to to meeting meeting the requirements of the requirements of d.1, d.1, d.2, d.2, and and d.3 d.3 below, the below, the inspection inspection scope, scope, inspection inspection methods, methods, and and A degradation A ins ection intervals inspection intervals shallshall be be such such as as toto ensure ensure thatthat SGSG tube tube assessment 1n in egrl egri y 1S main y is ma1n acnea1ne ptil til the the next next SGSG inspection.

inspection. ~ Aft

. shall be performed shall be performed to to determine determine the the type type and and location location of flaws to of flaws to which the tubes which the tubes maymay bebe susceptible susceptible and,and, based based onon this assessment, to this assessment, to determine determine which inspection methods which inspection need to methods need to be be employed employed and and atat what what 1ocat ions.

locations. installation installation 1.

1. Inspect Inspect 100%

100% of of the the tubes tubes inin each each SG/during S the first refueling refueling outage following SG outage following SG -PetT+CH~~

~ Inspect 100% of the Unit 1 tubes at sequential periods of 144, 108, 72, and, thereafter, 60 effective full pmJer months. The fi rst sequenti al peri od shall be considered to begin after the first inservice inspection of the SGs. In addition, inspect 50% of

...---~.... the tubes by the refuel ing outage nearest the midpoint I , of the period and the remaining 50% by the refueling outage nearest the end of the period. No SG shall Replace with with operate for more than 72 effecti ve full pmJer months INSERT I NS E RT 11 or three refuel i ng outages ('n'hi chever is 1ess) 'n'i thout being inspected.

Inspect 100% of the Unit 2 tubes at sequential periods of 120, 90, anE!, tf':tcl"eaftcr, 60 effect; 'o'e full pO'.ier

~~!~~ere~hiof;=:lns;,~~~t!~! ~~~!~di~:~!!i~~

inspection of the SGs. In addition, inspect 50% of the tubes by the refueling outage nearest the midpoint of the peri od and the remai ni ng 50?6 b:y the refuel i ng outage nearest the enE! of the period. No SG shall operate for more than 48 effecti "Ie full pmJer months or bOlO refuel i ng outages ('.~hi chever is 1ess) ~~i thout being inspected.

BRAIDWOOD BRAIDW00D -- UNITS UNITS 11 &&22 5.5 5.5 -- 99 Amendment Amendment -+/

THIS MARKUP THiS MARKUPOF OFTSTS PAGE PAGE 5.5-10 5.5-10 REFLECTS CHANGES CHANGES PROPOSED IIN PROPOSED N THE THE H*H* PERMANENT PERMANENT ALTERNATE ALTERNATE REPAiR REPAIR CRITERIA LAR CRITERIA LAR DATED DATED MARCHMARCH 20, 20, 2012. Programs Programs andand Manuals Manuals 5.5 5.5 5.5 5.5 Programs Programs and and Manuals Manuals 5.5.9 5.5.9 Steam Steam Generator Generator (SG)

(SG) Program (conti nued)

Program (continued) affected affected and and potentially affec affected For For Unit Unit 1, 1, ifif crack crack indications indications are are fotfnd fo d inin any any SG SG tube, tube, then then thethe next next inspection inspection for for each each G Gfor for the the degradation mechanism degradation mechanism that that caused caused the the crack crack indication indication shall not shall not exceed exceed 24 24 effective effective full full powerpower months months or one or one results in in more refuelinq refueling outaqe (whicheve ~::; 3e). ForForUnit outage (whichever 10 ':::::;::;). Unit 22 frequent inspections during Refueling Outage 15 ~nd the subsequent

~rating epe-r-at- cycle,

-e-ye e, ififcrack crackindications indicationsare arefound found inin any any 114.01 114.01 SG SG tube tube frofr~6.95 inches inches below below the the top of the top of the tubesheet tuuees ee on on the the hot hot legleg side side to to ~ches nches below below /14.01 the the top top of the tubesheet of the tubesheet on on the the cold cold leg 1eg-srde side,, tthen en -140 affected and potentially the next inspection the next ins ection for for eacfA eac SG SG for for the the degradation degradation affected mec anlsm aa cause mec anism cause ee cr crickck indication indication shall shall not not exceed exceed 24 24 effective effective full full power power months months or or one one refueling refueling (results in more results in outage outage (whichever (whichever-). js less).

tequent frequentInspections inspections If If definitive information, such definitive information, such asas from from examination examination of of aa pulled tube, diagnostic pulled tube, diagnostic non-destructive non-destructive testing, testing, or or engineering evaluation indicates engineering evaluation indicates that that aa crack-like crack-like indication indication is is not not associated associated with with aa crack(s),

crack(s), then then the the indication indication need need notnot bebe treated treated as as aa crack.

crack.

e.

e. Provisions Provisions for for monitoring monitoring operational operational primaryprimary to to secondary secondary LEAKAGE LEAKAGE..

.:f-:- Provisions for SG tube repctir methods. Steam generator tube repair methods shall provide the means to reestablish the RGS* pressure boundary i ntegri ty of 5G tubes vii thout removi Rg the tube from service. For tfle purposes ef thes-e Specifications, tube plugging is not a repair.

~ There are no approved tube repair w£thods for~

Unit 1 cry Unit 1 SGs.

~ A~l acceptable repair methods for the Unit 2 5Gs are 1i sted bel moJ.

+.-- TIG ~v'el ded 51 eev; ng as descri bed i R ABB Combustion Engineering Inc., Technical Report~

Licensing Report CEN 621 P,~sion 00, "Cemmonvv'eaHh Ed; son Byron and Bra; d~Jood Unit 1 and 2 Steam Generators Tube Repair Using Leak Ti ght 51 eeves, FINAL REPORT," Apri 1 1995; and l::icensing RepOrt CEN 627 P, "Operating Performance of tAe ABS GENG Steam Generator Tube Sl eeve for tjse at GommoHn'eal th Edi son B,yron and Braidvvo8E!--ldnits 1 and 2," January 1996; subject to the limitations and restrictions as noted by the NRC-5t-a#-;-

BRAIDWOOD UNITS 11 &&22 BRAIDWOOD -- UNITS 5.5 -- 10 5.5 10 Amendment ~

Amendment

THIS MARKUP MARKUP OFOF TS REFLECTS CHANGES TS PAGE 5.6-7 REFLECTS CHANGES PROPOSED PROPOSED IINN THE H*

H* PERMANENT PE RMANENT ALTERNATE ALTERNATE REPAIR Reporting Requirements Reporting Requirements CRITERIA LAR LAR DATED DATED MARCH MARCH 20, 2012.

20, 2012. 5.6 5.6 5.6 Reporting Requirements 5.6 Reporting Requirements 5.6.9 5.6.9 Steam Steam Generator (SG) Tube Generator (SG) Inspection Report Tube Inspection Report (continued-f (continued}

For Unit 2 foll mi'i ng cOfRpl eti on of an i nspecti on perforfRed in Refueling Outage 15 (and any inspections perforfRed in the I subsequent operating cycle),, the the operational primary to operational primary to secondary leakage rate secondary leakage rate observed observed (greater (greater than than three three gallons gallons per per day) day) inin each each steam steam generator generator (if (if it it is is not not practical practical to to assign assign the leakage to the leakage to an individual steam an individual steam generator, generator, thethe entire primary to entire primary to secondary secondary leakage leakage should should bebe conservatively conservatively assumed assumed toto be be from from one one steam steam generator) generator) during during thethe cycle cycle preceding preceding thethe inspection inspection which which is is the the subject subject ofof the the report, report, and and For Uni t 2 foll mJi ng cOfRpl eti on of an i nspecti on perforfRed in Refueling Outage 15 (and any inspections perforfRCd in the I subsequent operating cycle),, the the calculated accident induced calculated accident induced leakage rate from leakage rate from the the portion portion ofof the the tubes tubesbelow below4-6 . 'nches

'nches from from the the top top ofof the the tubesheet tubesheet for the most for the limiting ac most limiting ac ' ent ent r in in the the most most limiting limiting SG.SG. In In addition, addition, if if the the calculated calculated 4.01 14.01 accident induced leakage accident induced leakage raterate from from the the most limiting accident most limiting accident is is less less than than 3.11 times the 3.11 times the maximum maximum operational operational primary primary toto secondary secondary leakage rate, the leakage rate, report should the report should describe describe howhow it it was was determined, determined, and and For Uni t 2 foll o'..'i ng cOfRpl eti on of an i nspecti on perforfRed in Refueling Outage 15 (and any inspections perforfRed in the I subsequent operating cycle),, the results of the results of monitoring monitoring for for tube tube axial axial displacement displacement (slippage).

(slippage). If If slippage slippage is is discovered, discovered, the implications of the implications the discovery of the discovery andand corrective corrective action shall be action shall be provided.

provided.

BRAIDWOOD UNITS 11 &&22 BRAIDWOOD -- UNITS 5.6 5.6 -- 77 Amendment Amendment -+/ -I&

ATTACHMENT 3 Proposed Technical Specifications Proposed SpecificationsChanges Changesfor forByron Byron Station, Station, Units Units 11 and and 22 Byron Station, Units 1 and 2 Byron Facility Operating License Nos. NPF-37 and NPF-66 Mark-upofofTechnical Mark-up TechnicalSpecifications Specifications Pages Pages 3.4.19-1 3.4.19-2 5.5-7 5.5-7 5.5-8 5.5-8 5.5-9 5.5-9 5.5-10 5.5-10 5.5-11 5.5-11 5.6-6 5.6-6 5.6-7 5.6-7

SG SG Tube Integrity Tube Integrity 3.4.19 3.4.19 3.4 3.4 REACTOR REACTOR COOLANT SYSTEM (RCS)

COOLANT SYSTEM (RCS) 3.4.19 3.4.19 Steam Steam Generator (SG) Tube Generator (SG) Integrity Tube Integrity LCO LCO 3.4.19 3.4.19 SG tube integrity SG tube integrity shall shall be be maintained.

maintained.

AND AND ugging I

~PIUgging All All SGSG tubes tubes satisfying satisfying the the tube tube 1°repair criteria shall be criteria shall be plugged plugged or repaired in accordance red--in accordance with with the the Steam Generator Steam Generator Program.

Program.

APPLICABILITY:

APPLICABILITY: MODES MODES 1,1, 2, 2, 3, 3, and and 4.

4.

ACTIONS ACTIONS

NOTE-----------------------------------------

NOTE ---------------------------------------- -

Separate Separate Condition entry is Condition entry is allowed allowed for for each each SG SG tube.

tube.

CONDITION CONDITION REQUIRED ACTION REQUIRED ACTION COMPLETION TIME COMPLETION TIME A.

A. One or more One or more SGSG tubes tubes A.l A.1 Verify Verify tube integrity tube integrity 77 days days satisfying the tube satisfying the tube of of the affected the affected

~repair criteria criteria andand tube(s) tube(s) is is maintained maintained lplugging D1: u^ggingjnotnot plugged plugged ew&- until until the next the next repaired in accordance e-in accordance refueling refueling outage or outage or with the with the Steam Steam SG tube inspection.

SG tube inspection.

Generator Program.

AND AND A.2 A.2 Plug or repair -the Pi ug er--re the Prior to Prior to affected affected tube(s) in tube(s) in entering MODE 44 entering MODE accordance accordance with the with the following following thethe Steam Generator Steam Generator next refueling next refueling Program.

Program. outage outage oror SG SG tube inspection tube inspection B. Required B. Required Action and Action and B.l B.1 Be Be inin MODE MODE 3. 3. 66 hours7.638889e-4 days 0.0183 hours 1.09127e-4 weeks 2.5113e-5 months hours associated Completion associated Completion Time of Condition Time of Condition AA AND AND not met.

not met.

B.2 B.2 Be Be inin MODE MODE 5. 5. 36 hours 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR OR SG SG tube integrity not tube integrity not maintained.

maintained.

BYRON UNITS 11 &

BYRON -- UNITS 2

& 2 3.4.19 3.4. 19 -- 1 1 Amendment Amendment ~

SG SG Tube Integrity Tube Integrity 3.4.19 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEI LLANCE SURVEILLANCE FREQUENCY FREQUENCY SR 3.4.19.1 SR 3.4.19.1 Verify Verify SG SG tube integrity in tube integrity in accordance accordance with with In In accordance accordance the the Steam Generator Program.

Steam Generator Program. with with the the Steam Steam Generator Generator Program Program SR SR 3.4.19.2 Verify Verify that that each inspected SG each inspected SG tube tube that that Prior Prior to to satisfies satisfies the tube repair criteria the tube criteria isis entering entering MODE MODE 4 4 plugged plugged or er-a repaired --i i ntccordance ccordance with the with the following following aa SG SG Steam Generator Program\

Steam Generator Progra tube inspection tube inspection plugging hugging BYRON - UNITS 1 &2 BYRON - UNITS 1 & 2 3.4.19 3.4. - 22 19 - Amendment -+/-W Amendment 4-50

Programs Programs and and Manuals Manuals 5.5 5.5 5.5 5.5 Programs and Manuals Programs and Manuals 5.5.9 5.5.9 Steam Steam Generator (SG) Program Generator (SG) Program A Steam Generator A Steam Generator Program Program shall shall be be established established and and implemented implemented to to ensure ensure that that SGSG tube tube integrity integrity is is maintained.

maintained. In In addition, addition, the the Steam Steam Generator Program shall Generator Program shall include include the the following fall owi ng provi si e&:ons:

a.

a. Provisions Provisions for condition monitoring for condition monitoring assessments.

assessments. Condition Condition monitoring assessment means monitoring assessment means an an evaluation evaluation of of thethe "as "as found" found" condition condition of of the the tubing tubing with respect to with respect to the the performance performance criteria criteria forfor structural integrity and structural integrity and accident accident induced induced leakage.

leakage. The "as found" The "as found" condition condition refers refers toto thethe condition condition of of the the tubing tubing during during an an SG SG inspection inspection outage, outage, as as determined determined from the inservice from the inservice inspection inspection results results oror byby other other means, means, prior prior toto the the plugging plugging e'-ror repair of tubes. Condition of tubes. Condition monitoring assessments shall monitoring assessments shall bebe conducted conducted during during eacheach outage outage during during which the SG which the SG tubes tubes are are inspected, plugged, or repaired to feeai-fto confirm confirm that that thethe performanc riteria performance"tri teri a are arebeing being met.

met. inspected

°np^old or or pugged plugged b.

b. Performance Performance criteria criteria for for SG SG tube tube integrity.

integrity. SG SG tube tube integrity integrity shall shall bebe maintained maintained by by meeting meeting thethe performance performance criteria criteria for for tube tube structural integrity, accident structural integrity, accident induced induced leakage, and operational leakage, and operational LEAKAGE.

LEAKAGE. ),

1.

1. Structural integrity performance Structural integrity performance cc 'terion:

"terion: All/in-All in-service steam generator service steam generator tubestubes shall shal retain retain structural struc ural integrity integrity over over the full range the full range ofof rmalrural operati operati conditions startup, o0 ation (including startup, conditions (including ation in in the the power power range, hot range, standby, and hot standby, and cool cool down down ~all -all antianti atedated transients included in transients included in the the design design specificatio specificatio and and design basis accidents.

design basis accidents. This includes retaining This includes retaining aa safety safety factor factor ofof 3.0 3.0 against under normal burst under against burst normal steady steady state full power state full power operation primary-to-secondary operation primary-to-secondary pressure pressure differential differential and and aa safety safety factor factor of of 1.4 1.4 against burst applied against burst applied to to the design basis the design basis accident accident primary-to-secondary pressure differentials.

primary-to-secondary pressure differentials. Apart Apart from from the above requirements, the above requirements, additional additional loading loading conditions associated with conditions associated with thethe design design basis basis accidents, accidents, or or combination combination of accidents in of accidents in accordance accordance with with the the design design and licensing basis, and licensing basis, shall shall also also be be evaluated evaluated to to determine determine if if the associated loads the associated loads contribute contribute significantly significantly to to burst burst or or collapse.

collapse. In In the the assessment assessment of of tube integrity, those tube integrity, loads that those loads that dodo significantly significantly affect affect burst burst oror collapse shall be collapse shall be determined determined and and assessed assessed in in combination combination with the loads with the loads due due toto pressure pressure with aa safety with safety factor factor of of 1.2 1.2 on on the the combined combined primary primary loads loads and and 1.0 on axial 1.0 on axial secondary secondary loads.

loads.

BYRON UNITS 11 &&22 BYRON -- UNITS 5.5 5.5 -- 77 Amendment Amendment .f.W.

Programs Programs and and Manuals Manuals 5.5 5.5 5.5 Programs 5.5 Programs and and Manuals Manuals 5.5.9 5.5.9 Steam Steam Generator Generator (SG)(SG) Program (continued)

Program (continued) 2.

2. Accident induced leakage Accident induced leakage performance performance criterion:

criterion: The The primary primary to to secondary secondary accident induced leakage accident induced leakage raterate for for any any design basis accident, design basis accident, other other thanthan aa SGSG tube tube rupture, rupture, shallshall not exceed the not exceed the leakage leakage raterate assumed assumed in in the the accident analysis in accident analysis in terms terms of of total total leakage leakage rate rate for for allall SGsSGs and and leakage leakage rate rate forfor anan individual individual SG. SG.

Leakage Leakage is is not not to exceed aa total to exceed total of of 11 gpm gpm for for allall SGs.

SGs.

3.

3. The The operational LEAKAGE performance operational LEAKAGE performance criteria criteria is is specifi specified ed in in LCO LCO 3.4.13, "RCS Operational 3.4.13, "RCS Operati ona 1 LEAKAGE."

LEAKAGE."

t b ~. criteria.,

SG tube

.. f u e repalr crl.terla.~ Iplugging

' plugging I c.

c. P rOV1Slons Provisions foror SG

~

4- L:Tubes Tubes foundfound byby inservice inservice inspection inspection to to contain contain flaws flaws in a non sleeved region with with a a depth depth equal equal toto or or exceeding exceeding 40% 40% ofof the the nominal nominal wallwall thickness thickness shallshall be be plugged plugged or repaired. a. The The followingalternate following alternate tube tube repair criteria shall be criteria shall be applied applied as as anan alternativ alternativ 0o the the 40% depth based 40% depth based criteria:

cri teri a: plugging plugging For For Unit Unit 2 2 during Refueling Outage during Refueling Outage 16 and the 16 and the subsequent operating cycle, subsequent operating cycle, tubes tubes with with service-service-induced flaws located induced flaws located greater greater thanthan 16.95 inches 16.95 inches below below thethe top top of of the the tubesheet tubesheet do do not not require require plugging or repair.

plugging ep. Tubes Tubes withservice-induced with service-induced flaws located in flaws located in the the portion portion of of the the tube tube fromfrom the top of the top of the the tubesheet tubesheet to to 16.95 inches below 16.95 inches below the top of the top of the the tubesheet tubesheet shall shall be be plugged plugged ~

repaired upon detection.

-ed-upon detection.

b Sl eeves found b:Y i nservi ce i nspecti on to contai n f1 a\/s

'4~i th a deptA equal to or e)(ceedi ng tAe fel--l-e foll o~~i* ng percentages of tAe nOFRi nal sl eeve ~Y'all thi ckness shall be aged bo plugged:

4-;- For Unit 2 only, TIC ~y'el ded sl eeves (per TS S.S.9.f.2.i): 32%

3. Tubes 'i~ith a flJ'iJ in a sleeve to tube joint that occurs in the sl eeve or in the ori gi nal tube h'all of the joint shall be plugged.

BYRON -- UNITS BYRON &

UNITS 11 & 22 5.5 -- 88 5.5 Amendment 472-Amendment m.

Programs Programs and and Manuals Manuals 5.5 5.5 5.5 Programs 5.5 Programs andand Manuals Manuals 5.5.9 5.5.9 Steam Steam Generator Generator (SG)(SG) Program (continued)

Program (continued) d.

d. Provisions Provisions for for SG SG tube tube inspections. Periodic SG inspections. Periodic SG tube tube inspections shall be inspections shall be performed.

performed. The The number number and and portions portions of of the the tubes inspected and tubes inspected and methods methods ofof inspection inspection shall shall be be performed performed with with the the objective objective of of detecting flaws of detecting flaws of any any type type (e.g.,

(e.g., volumetric volumetric flaws, flaws, axialaxial and and circumferential circumferential cracks) cracks) that that may may be be present present along along the length of the length of the the tube, tube, from from the the tube-to-tubesheet tube-to-tubesheet weld weld at at the the tube tube inlet inlet toto thethe tube-to-tube-to-Iplugging I tubesheet weld at the tubesheet wel~at the tube tube outlet, and that outlet, and that may may satisfy satisfy thethe applicable applicable tub tub~repair ' criteria.

criteria. For For Unit Unit 2 2 during during Refueling Refueling Outage Outage 1616 and and the the subsequent subsequent operating operating cycle, cycle, portions portions ofof the the tube tube below 16.95 inches below 16.95 inches from from the the toptop of of the the tubesheet tubesheet are are excluded excluded from from this this requirement.

requirement.

The The tube-to-tubesheet tube-to-tubesheet weld weld is is not not part part of of the the tube. tube. InIn addition addition toto meeting meeting the requirements of the requirements of d.1, d.1, d.2, d.2, andand d.3 d.3 below, below, thethe inspection inspection scope, scope, inspection inspection methods, methods, and and A degradation ins ection intervals inspection intervals shall shall be be such such as as to to ensure ensure that that SG SG tube tube assessment integrity integrity is is maintaine maintained ntil til the the next next SG SG inspection.

inspection. ~ Aff

~'i5-SffIE~--8'f--et~a8i"I-'E-TIBfTsha 11 be shall performed to be performed to determine determi ne the the type type and and location location of flaws to of flaws to which the tubes which the tubes may may bebe susceptible susceptible and,and, based based on on this assessment, to this assessment, to determine determine which inspection methods which inspection methods need need toto be be employed employed and and at at what what ocat ions.

1locations. installation Installation 1.

1. Inspect 100% of Inspect 100% of the the tubes tubes inin each each SG/,during Suring the the first first refueling refueling outage following SG outage following SG -reET+iH::efffi::ffE-

~ Inspect 100% of tAe Unit 1 tubes at sequential periods of 144, 108, 72, and, tAereafter, 60 effective full pO'r~er montAs. TAe fi rst sequenti al peri od sAall be considered to begin after the first inservice inspection of tAe SGs. In addition, inspect 50% of

....--__~ the tubes by the refueling outage nearest the midpoint of tAe period and the remaining 50% by tAe refueling outage nearest the end of the period. No SG shall operate for more tAan 72 effecti 'o'e full pO'iter montAs or three refuel i ng outages C't~Ai chever is 1ess) 'Iii thout being inspected.

BYRON -- UNITS BYRON UNITS 11 & 22& 5.55 -- 99

5. Amendment 449 Amendment .m

INSERT I1

2. Unit 1, For Unit 1, after after the the first refueling refueling outageoutage following following SG SG installation, installation, inspect each each SG at least least every every72 72effective effective full full power monthsmonths or or atatleast leastevery everythird thirdrefueling refueling outage (whichever results in more frequent inspections). In In addition, addition, the minimum number of of tubes inspected inspected at at each each scheduled scheduled inspection inspectionshall shallbebethe the number of tubes in all SGs divided divided by by the the number number of ofSGSG inspection inspectionoutages outages scheduled in each inspection period as defined in a, b, c, and d below. IfIfaa degradation assessment indicates the potential for a type of degradation to occur at a location not previously previously inspected inspected with with aa technique technique capable capableof ofdetecting detectingthis this type of degradation at at this location location and and that that maymaysatisfy satisfythe theapplicable applicabletubetube plugging criteria, the minimum number number of of locations locations inspected inspected with with such such aacapable capable inspection technique during the remainder remainder of of the the inspection inspection period period may maybe be prorated. The prorated. The fraction fraction of oflocations locations to to be be inspected inspected for forthis this potential potential type type ofof degradation at this location location at at the the endend ofof the the inspection inspection period period shall shallbebeno noless less than the ratio of the number of times the SG is scheduled to be inspected in the inspection period after the determination determination that that aa newnew formform of ofdegradation degradation could could potentially be occurring at this location location divided divided by by the the total total number numberof oftimes times the the SG is scheduled to be inspected in the inspection period. Each Each inspection inspection period period defined below may be be extended extended up up to to 33 effective effective full full power powermonths monthsto toinclude includeaa SG inspection outage in an inspection period and the subsequent in an inspection period and the subsequent inspection inspection period begins at the conclusion of of the the included included SG SG inspection inspection outage.

outage.

a) After the first refueling outage following SG installation, inspect 100% of the tubes during the next 144 effective effective full full power power months.months. This constitutes the first inspection inspection period; period; b) During the next 120 effective full power power months, months, inspectinspect 100%

100% of ofthe the tubes. This This constitutes constitutes the the second second inspection inspection period;period; c) During the next 96 effective effective full full power power months, months, inspectinspect100%100%of ofthe the tubes.

tubes.

This constitutes the third inspection inspection period;period; and and d) During the During the remaining life life of ofthe the SGs, SGs, inspect 100% 100% of the tubes tubes every every72 72 effective full effective fullpower powermonths.

months. This This constitutes constitutes the fourth fourth and and subsequent subsequent inspection periods.

3. Unit 2, For Unit 2, after after the the first refueling outage first refueling outage following following SG SG installation, installation, inspect each each SG at least least every every 48 48effective effective fullfull power months months or or atat least leastevery everyother otherrefueling refueling outage (whichever results in more frequent inspections). In In addition, addition, the minimum number of tubes inspected at at each each scheduled scheduled inspection inspection shall shall be be thethe number of tubes in all SGs divided by by the the number number of of SG SG inspection inspection outages outages scheduled in each inspection period as defined in a, b, and c below. below. IfIfaa degradation assessment assessment indicates indicates the the potential potential for for aa type type of ofdegradation degradationto tooccur occur at a location not previously inspected inspected with with aa technique technique capable capable of ofdetecting detectingthis this type of degradation at this location and that may satisfy location and that may satisfy the applicable tubethe applicable tube plugging criteria, the minimum number number of of locations locations inspected inspected with with such such aa capable capable inspection technique during the remainder remainder of of the the inspection inspection period period may may be be prorated. The prorated. The fraction fraction of oflocations locations to to be be inspected inspected for for this this potential potential type type ofof degradation at this location location at at the the end end of of the the inspection inspection period period shall shall be beno noless less

INSERT1I (continued)

INSERT (continued) than the ratio of the number of times the SG is scheduled to be inspected in the inspection period after the determination that that aa new new form form ofofdegradation degradationcouldcould potentially be occurring at this location divided divided by by the the total total number numberof oftimes timesthe the SG is scheduled to be inspected in the inspection period. Each Eachinspection inspectionperiod period defined below may be extended up to 3 effective full power months to include a SG inspection outage in an inspection period and the subsequent inspection period begins at the conclusion of of the the included included SG SG inspection inspection outage.

outage.

a) After the first refueling outage following SG installation, inspect 100% 100% of of the tubes during thethe next 120 effective effective full full power power months.

months. ThisThis constitutes the first inspection period; period; b) During the next 96 effective full power power months, months, inspect inspect 100%

100%of ofthe thetubes.

tubes.

This constitutes the second inspection inspection period; period; andand c) During the During the remaining remaining life lifeof ofthe theSGs, SGs, inspect inspect 100% of of the the tubes tubes every 72 effective full effective fullpower powermonths.

months. ThisThis constitutes constitutes the third third and and subsequent subsequent inspection periods.

Programs Programs and and Manuals Manuals 5.5 5.5 5.5 Programs 5.5 Programs and and Manuals Manuals 5.5.9 5.5.9 Steam Steam Generator Generator (SG)

(SG) Program (continued)

Program (continued)

IAspect 100% of the UAit 2 tubes at sequeAtial periods of 120, 90, aAd, thereafter, 60 effective full pmt!er mOAths. The first sequeAtial period shall be cOAsidered to begiA after the first iAservice iAspectioA of the SGs. IA additioA, iAspect 50% of the tubes by the refueliAg outage Aearest the midpoiAt of the period aAd the relflJiAiAg 50% by the refueliAg outage Aearest the eAd of the period. No SG shall operate for more thaA 48 effecti ve full pmt!er mOAths or b.u refuel i Ag outages (!,~hi chever is 1ess) ~.!i thout bei Ag inspected. affected and potentially affected For For Unit Unit 1,1, if if crack crack indications indications are are fo fo dd in in any any SG SG tube, tube, then then the the next next inspection inspection forfor each each GGforfor the the degradation mechanism degradation that caused mechanism that caused the the crack crack indication indication shall not exceed shall not exceed 2424 effective effective full full power power months months oror one one Iresults results in in more refuelinq refueling outaqe outa e (whichever-(whichever ~s less). For as-4e&&). For Unit Unit 22 frequent inspections during during Refueling Refueling Outage Outage 16 16 ~nd the subsequent nd the subsequent {

operating cycle, if operating cycle, if crack crack indications indications are are found found inin any any SG SG tube from 16.95 tube from 16.95 inches inches below below the the top top ofof the the tubesheet tubesheet on on the the hot hot leg leg side side to to 16.95 16.95 inches inches below below effected and affected and the to of the top of the the tubesheet tubesheet on on the he cold cold legleg side, side, then then potentially affected affected the the next next inspection inspection for for eac eac SGSG for for thethe degradation degradation mechanism mechanism thatthat caused caused the the crack crack indication indication shallshall not not exceed exceed 2424 effective full power effective full power months months or or one one refueling refueling results in in more outage (whichever is less).

outage (whichever ).

frequent inspections If If definitive information, such definitive information, such as as from from examination examination of of aa pulled tube, diagnostic pulled tube, diagnostic non-destructive non-destructive testing, testing, or or engineering evaluation indicates engineering evaluation indicates that that aa crack-like crack-like indication is indication is not not associated associated withwith aa crack(s),

crack(s), thenthen the the indication need indication need not not be be treated treated asas aa crack.

crack.

BYRON -- UNITS BYRON &

UNITS 11 & 22 10 5.5 -- 10 5.5 Amendment Amendment -+/-ft

Programs and Manuals Programs and Manuals 5.5 5.5 5.5 5.5 Programs and Manuals Programs and Manuals 5.5.9 5.5.9 Steam Steam Generator Generator (SG)(SG) Program (continued)

Program (continued) e.

e. Provisions Provisions for for monitoring operational primary monitoring operational primary to to secondary secondary LEAKAGE.

+:- Provisions for SG tube repair metAods. Steam generator tube repair metAods sAall provide tAe means to reestablisA tAe RCS pressure boundary i ntegri ty of SG tubes 'Ii'i tAout removi ng tAe tube from service. For tAe purposes of tAese Specifications, tube plugging is not a repair.

-+/--:- TRere are no appro'oled tube repai r metAods edn& for tAe crAbe Unit 1 SGs.

b

All acceptabl Ml-l-naeeWe ii0, t-a e repai r metAods for tAe Uni t 2 SGs are 1 i sted tcd bel m; .

b,e1e^

-i--T TIG ~Jel ded sl eevi ng as descri bed in ASS Combustion Engineering Inc., TecAnical Reports:

Licensing Report CEN 621 P, Revision 00, "CoffflloA'h'eal tA Edi son Byron and Brai d~.'ood Uni t 1 and 2 Steam Generators Tube Repair Using Leal<

TigAt Sleeves, FINAL REPORT," April 1995; and Licensing Report CEN 627 P, "Operating Performance of tAe ABB CENO Steam Generator Tube Sl eeve for Use at COfflfAom~eal tA Edi son Byron and Braid~>'Ood Units 1 and 2," January 1996; subject to tAe limitations and restrictions as noted by tAe NRC Staff.

BYRON UNITS 11 &&22 BYRON -- UNITS 5.5 5.5 -- 11 11 Amendment Amendment -l66 466

Reporting Requirements Reporting Requirements 5.6 5.6 5.6 Reporting 5.6 Reporting Requirements Requirements 5.6.8 5.6.8 Tendon Surveillance Tendon Surveillance Report Report Any abnormal Any abnormal degradation degradation ofof the the containment containment structure structure detected detected during the during the tests tests required required by by the the Pre-Stressed Pre-Stressed Concrete Concrete Containment Containment Tendon Surveillance Tendon Surveillance Program Program shall shall bebe reported reported in in the the Inservice Inservice Summary Report Inspection Summary Inspection Report in in accordance accordance with with 1010 CFR CFR 50.55a 50.55a andand ASME Section ASME Section XI.

XI.

5.6.9 5.6.9 Steam Generator Steam (SG) Tube Generator (SG) Tube Inspection Inspection Report Report A report shall A report shall bebe submitted submitted within within 180180 days days after after the the initial initial entry entry into MODE into MODE 44 following following completion completion of of an an inspection inspection performed performed inin accordance with accordance with Specification Specification 5.5.9, 5.5.9, Steam Steam Generator Generator (SG) (SG) Program.

Program.

The report shall The report shall include:

include:

IDegradation ~ The scope of The scope of inspections inspections performed performed onon each each SG, SG, b.

b. Active degradatioA mechanisms found, 4-&n-mechanisms found, c.

c. Nondestructive examination Nondestructive examination techniques techniques utilized utilized forfor each each degradation mechanism, degradation mechanism, d.

d. Location, Location, orientation (if linear),

orientation (if linear), and and measured measured sizes sizes (if(if available) available) of of service service induced induced indications, indications, e.

e. Number of tubes Number of tubes plugged plugged or repairedi-r-e8during duringthethe inspection inspection outage for each outage for each active degradation mechanism, degradation mechanism,

f. ,Total Aumber aAd perceAtage of tubes plugged or repaired a_imrcd to date; g.

g. The results of The results of condition condition monitoring, including the monitoring, including results of the results of tube pulls and tube pulls and in-situ testing, in-situ testing, fr.- The effective pluggiAg perceAtage for all pluggiAg aAd tube repairs iA each SG, and 4-T Repai r method util i zed aAd the Aumber of tubes repai red by each repair method.

I The number and and percentage of tubes plugged plugged to to date, and and the the

- effective plugging plugging percentage in in each steam generator, generator, BYRON BYRON -- UNITS UNITS 1 1 &&22 5.6 5.6 -- 66 Amendment Amendment -+/-6&

-166

Reporting Requirements Reporting Requirements 5.6 5.6 5.6 5.6 Reporting Requirements Reporting Requirements 5.6.9 5.6.9 Steam Steam Generator (SG) Tube Generator (SG) Inspection Report Tube Inspection Report (continued)

(continued)

For For Unit Unit 22 following following completion completion of of an inspection performed an inspection performed in in Refueling Refueling Outage Outage 16 (and any 16 (and inspections performed any inspections performed in in the the subsequent subsequent operating operating cycle),

cycle), thethe operational primary to operational primary to secondary secondary leakage rate observed leakage rate (greater than observed (greater three gallons than three gallons per per day) day) in in each each steam steam generator generator (if(if it it is is not not practical practical to to assign assign the the leakage leakage to to an individual steam an individual steam generator, generator, thethe entire primary entire primary to to secondary leakage should secondary leakage should bebe conservatively conservatively assumed assumed to to be be from from one one steam steam generator) generator) during the cycle during the cycle preceding the inspection preceding the inspection which which is is the the subject subject ofof the the report, report, and and lk-. For For Unit Unit 2 2 following following completion completion of of an inspection performed an inspection performed in in Refueling Refueling Outage Outage 16 (and any 16 (and inspections performed any inspections performed in in the the subsequent subsequent operating operating cycle),

cycle), thethe calculated accident induced calculated accident induced leakage rate from leakage rate from the the portion portion ofof the tubes below the tubes below 16.95 16.95 inches inches from from the the top top of the tubesheet of the tubesheet forfor the the most most limiting limiting accident accident in in the the most most limiting limiting SG.SG. InIn addition, addition, ifif the the calculated calculated accident induced accident leakage rate induced leakage rate from from the the most limiting accident most limiting accident is is less less than than 3.11 3.11 times times the the maximum maximum operational primary to operational primary to secondary leakage rate, secondary leakage rate, the the report report should should describe describe howhow it it was was determined, determined, andand

J. For For Unit Unit 2 2 following following completion completion of of an inspection performed an inspection performed in in Refueling Refueling Outage Outage 16 (and any 16 (and any inspections inspections performed performed in in the the subsequent subsequent operating operating cycle),

cycle), thethe results results of of monitoring monitoring for for tube tube axial axial displacement displacement (slippage).

(slippage). If If slippage slippage is is discovered, discovered, thethe implications implications of of the the discovery discovery andand corrective corrective action shall be action shall be provided.

provided.

BYRON -- UNITS BYRON &

UNITS 11 & 22 5.6 -- 77 5.6 Amendment Amendment m

TIT MARKUP THIS MARKUP O OFF TS PAGE 5.5-8 5.5-8 REFLECTS REFLECTS CHAN CHANGES G ES PROPOSED IIN PROPOSED N THE THE H*

H* PERMANENT ALTERNATE REPAIR CRITERIA LAR LARDATED DATEDMARCHMARCH20, 20, 2012.

2012.

Programs Programs andand Manuals Manuals CRITERIA 5.5 5.5 5.5 5.5 Programs Programs and and Manuals Manuals 5.5.9 5.5.9 Steam Steam Generator Generator (SG) (SG) Program (continued)

Program (continued) 2.

2. Accident induced leakage Accident induced leakage performance performance criterion:

criterion: The The primary primary to to secondary secondary accident induced leakage accident induced leakage rate rate for for any any design design basis basis accident, accident, other than aa SG other than SG tube tube rupture, rupture, shall shall not exceed the not exceed the leakage leakage rate rate assumed assumed in in the the accident accident analysisanalysis in in terms terms of of total total leakage leakage raterate for for all all SGsSGs andand leakage leakage raterate forfor anan individual individual SG. SG.

Leakage Leakage is is notnot to exceed aa total to exceed total of of 11 gpmgpm for for all all SGs.

SGs.

3.

3. The operational LEAKAGE The operational LEAKAGE performance performance criteriacriteria is is specified specified in in LCOLCO 3.4.13, 3.4.13, "RCS"ReS Operational Operational LEAKAGE."

LEAKAGE."

c.

c. P ..

rOV1Slons Provisions f or SG for t ube ~.

SG tube ~alr crl

. terla.1' criteria.

' Iplugging plugging I

~

4 l:Tubes found by ubes found inservice inspection by inservice inspection to to contain contain flaws flaws iR a ROR sleeved regioR with with a a depth depth equal equal toto or or exceeding exceeding 40% 40% of of the the nominal nominal wall wall thickness thickness shall shall be be plugged plugged or repaired. i-r-e4. The following alternate The following alternate tube tube repair criteria criteria shall shall be be applied applied as as an an alternativ alternativ to 0 the depth based 40% depth the 40% based criteria:

cri teri a: 14.01 1 01 plugging For For Un i t 22-fH-Jff'T!'*l-HPT~~9---HIH-f.T~--H'l+Tlfl-A-'81f>.

Unit subsequeRt operatiRg cYcle,, tubes tubes wit service-wit service-induced induced flawsflaws located located greater greater than than 9&

~ inchesinches below below the the top top ofof the the tubesheet tubesheet do do not not require require plugging plugging--r or repair.. Tubes with service-induced Tubes with service-induced flaws located in flaws located in the portion of the portion of the the tube tube from from the the top top ofof the the tubesheet tubesheet to to . inches inches below below the the top top of the tubesheet of the tubesheet shat shal bebeplugged pluggedef- r repaired

-ne-p upon detection.

-ne4-upon detection on. 14.01 b Sl eeves fouRd by i Rservi ce i Rspecti OR to cORtai R fl my's

~v'i th a depth equal to or e)(ceedi Rg the foll O'Y~i Rg perceRtages of tAe ROffli Ral sl eeve ~.*all tAi clmess sAall be plugged:

4-;-

a- For URit 2 oRly, TIC \i'elded sleeves (per TS S.S.9.f.2.i): 32%

3.

-3. Tubes ~iith a fla',J iR a sleeve to tube jOiRt tAat occurs in tAc sleeve or iR tAe origirml tube \,'all of the jOiRt sAall be plugged.

BYRON -- UNITS BYRON &

UNITS 11 & 22 5.5 -- 88 5.5 Amendment 47-9 Amendment -i THIS MARKUP MARKUP OF OF TS PAGE 5.5-05.5-9 REFLECTS REFLECTS CHANGES CHANGES PROPOSED PROPOSEDIN INTHE THEH*H* PERMA PERMANENT N ENT ALTERNATE REPAIR REPAIR Programs and Programs and Manuals Manuals CRITERIA LAR DATED MARCH MARCH 20, 2012. 2012. 5.5 5.5 5.5 5.5 Programs and Programs and Manuals Manuals 5.5.9 5.5.9 Steam Generator Steam Generator (SG) (SG) Program (continued)

Program (continued) d.

d. Provisions for Provisions for SG SG tube tube inspections.

inspections. PeriodicPeriodic SG SG tube tube inspections shall inspections shall be be performed.

performed. The The number number and and portions portions of of the tubes the tubes inspected inspected and and methods methods of of inspection inspection shall shall be be performed with performed with the the objective objective of of detecting detecting flaws flaws of of any any type type (e.g., volumetric (e.g., volumetric flaws, flaws, axialaxial andand circumferential circumferential cracks) cracks) that that may may bebe present present alongalong the the length length ofof the the tube, tube, fromfrom the the tube-to-tubesheet weld tube-to-tubesheet weld at at the the tube tube inlet inlet to to thethe tube-to-tube-to-Iplugging plugging tubesheet weld~at tubesheet weld at the the tube tube outlet, outlet, and and that that may may satisfy satisfy thethe applicable tub aoolicable criteria. For tube-repair criteria. For Unit Unit 22 during Refueling Outage 16 and tAe subsequent operating cycle, portions of portions of the the tubetube below below . inches inches from from the the toptop of of the the tubesheet tubesheet are are excluded excluded from from thi requir ment.

thi requirement.

14.01 14.01 The tube-to-tubesheet The tube-to-tubesheet weld weld is is not not pa par o0 he he tube.

tube. In In addition addition to to meeting meeting the the requirements requirements of of d.1, d.l, d.2, d.2, andand d.3 d.3 below, the below, the inspection inspection scope, scope, inspection inspection methods, methods, and and A degradation ins ection intervals infection intervals shall shall be be such such asas toto ensure ensure that that SG SG tube tube assessment integrity integrity is is maintaine maintained ytil til thethe next next SG SG inspection.

inspection. ~ Aft i¥T'*"",,,**>f+F:--fH'--fff"6f'Tif+i'++'+-Af+~sha shall be performed 11 be performed to to determine determi ne the the type type and and location location of of flaws flaws to to which which the the tubes tubes may may bebe susceptible susceptible and, and, based based on on this assessment, to this assessment, to determine determine which inspection methods which inspection methods need need to to be be employed employed and and at at what what locations.

locations.

installation

1. Inspect Inspect 100% 100% of of the the tubes tubes in in each each SGJ,during Suring the the first first refueling refueling outage following SG outage following SG .pp.fl-l-rTf~::>.fI.f:.

~ Inspect 100% of tAe Unit 1 tubes at sequential periods of 144, 108, 72, and, tAereafter, 60 effective full pO',~er montAs. TAe fi rst sequenti al peri od sAall be considered to begin after tAe first inservice inspection of tAe SGs. In addition, inspect 50% of

....--_ _-?>- tAe tubes by tAe refuel i ng outage nea rest tAe mi dpoi nt of tAe period and tAe remaining 50% by tAe refueling Replace with outage nearest tAe end of the period. No SG sAall INSERT I operate for more tAan 72 effecti ve full pO~t'er mantAs or tAree refuel i ng outages (\vAi cAever is 1ess) ~t'i tAout being inspected.

BYRON UNITS 11 &&22 BYRON -- UNITS 5.5 5.5 -- 9 9 Amendment Amendment .f7.2.

THIS MARKUP THIS MARKUPOF OFTS TS PAGE PAGE 5.5-10 5.5-10 REFLECTS CHANGES PROPOSED IN PROPOSED IN THE H* PER MANENT ALTERNATE H* PERMANENT ALTERNATE REPAIR Programs Programs and and Manuals Manuals CRITERIA LAR CRITERIA LAR DATED DATED MARCH MARCH20,2012.

20, 2012. 5.5 5.5 5.5 5.5 Programs Programs and Manuals and Manuals 5.5.9 5.5.9 Steam Steam Generator Generator (SG) (SG) Program (continued)

Program (continued)

Inspect 100% of tAe Unit 2 tubes at sequential periods of 120, 90, and, tAereafter, 60 effecti ve full po',~er montAs. The first sequential period sAall be considered to begin after tAe first inservice inspection of tAe SGs. In addition, inspect 50% of tAe tubes by tAe refueling outage nearest tAe midpoint of tAe period and tAe remaining 50% by the refueling outage nearest the end of the period. No SG shall operate for more than 48 effecti lie full pO'nter FflontAs or t~.'O refuel i ng outages (',~hi cAever is 1ess) Hi thout bei ng inspected. affected affected and potentially affected and potentially affected For For Unit Unit 1,1, ifif crack crack indications indicationsare arefofo ddinin any any SG SG tube, then the tube, then the next next inspection inspection for for each each VGGforfor the the degradation degradation mechanism that caused mechanism that caused the the crack crack indication indication shall not exceed shall not exceed 24 24 effective effective fullfull power power months months or or one one results in more refuelin refueling

. outa outage . e whichever-(whichever js less).

&4es^) . For For Unit 2 2

frequent inspections operati ng cycl e, if if crack i ndi cati ons are crack indications are found found in in any any 114.01 SG tube fro~ inches inches below below the top of the top of the the tubesheet on the hot tubesheet on`the hot leg leg side side toto 16.9~ches below 114.01 nches below 14.0 1 the top of the top of the the tubesheet tubesheet on on the the cold cold legleg si slde, e, then en affected and the next inspection the next ins ection for for each eac SG SG for for the the degradation degradation potentially affected mec anlsm aa cause mechanism causeu ee cr ck indication crack indication shall shall not not exceed exceed 24 24 effective effective fullfull power power months months or or one one refueling refueling results in more Iresults outage outage (whichever (whicheveris4&4 less).

-).

frequent frequent inspections If If definitive information, such definitive information, such asas from from examination examination of of aa pulled pulled tube, tube, diagnostic diagnostic non-destructive non-destructive testing, testing, or or engineering evaluation indicates engineering evaluation indicates thatthat aa crack-like crack-like indication indication is is not not associated associated with with aa crack(s),

crack(s), then then the the indication indication needneed notnot be be treated treated as as aa crack.

crack.

BYRON -- UNITS BYRON &

UNITS 11 & 22 5.5 -- 10 5.5 10 Amendment 472-Amendment ~

THIS MARKUP PAGE 5.6-7 REFLECTS CHANGES MARKUP OF TS PAGE CHANGES PROPOSED IN PROPOSED INTHE THEH*H* PERMANENT PERMANENTALTERNATEALTERNATE REPAIR REPAIR Reporting Requirements Reporting Requirements CRITERIA LAR CRITERIA LAP DATED MARCH 20, DATED MARCH 20, 2012. 5.6 5.6 5.6 Reporting Requirements 5.6 Reporting Requirements 5.6.9 5.6.9 Steam Steam Generator Generator (SG)(SG) Tube Tube Inspection Inspection Report Report (continued)

(continued)

For For Uni Unit t 224-&

foll mi'i ng compl eti on of an i nspecti on performed in Refueling Outage 16 (and any inspections performed in the subsequent operating cycle),, the the operational primary to operational primary to secondary leakage rate secondary leakage rate observed observed (greater (greater than than three three gallons gallons per per day) day) in in each each steam generator (if steam generator (if it it is is not not practical practical to to assign assign the leakage to the leakage to an an individual individual steam steam generator, generator, thethe entire primary to entire primary to secondary secondary leakage leakage should should bebe conservatively conservatively assumed assumed to to be be from from one one steam steam generator) generator) during during the the cycle cycle preceding preceding the the inspection inspection which which is is the the subject subject ofof the the report, report, and and k--. For For Uni Unit t 22-foll o'..*i ng compl eti on of an i nspecti on performed in Refueling Ref He! Iing Outage

. -age 16 Gut 11: (and any inspections performed in the J- 1J subsequent operating cycle), the calculated accident the calculated accident induced induced leakage leakage raterate from from the portion of the portion the tubes of the tubes below below . 'nches nches from from the the toptop of the tubesheet of the tubesheet for for the the most most limiting limiting ac ac entent in in the the most most limiting limiting SG. SG. In In addition, addition, if the calculated if the calculated ' - - - - 114,01 1 . - _.......

accident induced leakage accident induced leakage rate rate from from the the most most limiting limiting accident accident is is less less than than 3.11 3.11 timestimes thethe maximum operational primary maximum operational primary to to secondary leakage rate, secondary leakage rate, thethe report report should should describe describe howhow it it was was determined, determined, and and For Uni t 2 foll O'v{i ng compl eti on of an i nspecti on performed in Refueling Outage 16 (and any inspections performed in the subsequent operating cycle),, the results of the results of monitoring monitoring for for tube tube axial axial displacement displacement (slippage).

(slippage). If If slippage slippage is is discovered, discovered, the the implications implications of of the the discovery discovery andand corrective corrective action shall be action shall be provided.

provided.

BYRON UNITS 11 &&22 BYRON -- UNITS 5.6

5. 6 -- 77 Amendment Amendment -l-ft 472-

ATTACHMENT 4 Proposed Technical Specifications Specifications Bases BasesChanges Changesfor forBraidwood Braidwood Station, Station, Units Units 11 and and 2 Braidwood Station, Units 11 and 22 Operating License Nos.

Facility Operating NPF-72 and NPF-77 Nos. NPF-72 NPF-77 Mark-up of Mark-up of Technical Technical Specifications Specifications Bases Pages B

B 3.4.19-3 B

B 3.4.19-5 B

B 3.4.19-6 B

B 3.4.19-7

SG SG Tube Integrity Tube Integrity BB 3.4.19 3.4.19 BASES plugging 1plugging LCD LCO The The LCOLCD requires requires thatthat SG SG tube tube integrity integrity be be maintained.'

maintained. The The LCD LCO also also requires requires that that allall SGSG tubes tubes thatthat satisfy satisfy thethe repair criteria criteria be be plugged plugged or repaired i in in accordance accordance with with the Steam the Steam Generator Program.

Generator Program. plugging gging During During an an SG SG inspection, inspection, any "nspected tube any nspected tube that that satisfies satisfies the Steam the Steam Generator Program repair criteria Generator Program criteria is is repaired- or Iplugging (plugging removed removed from service by from ~~~vice by plugging.

plugging. If If aa tube tube was was determined determined to satisfyy tth~epair to satis ' criteria criteria but but waswas not not plugged~

plugged-s repaired, the tube e4, the tube maymay still still havehave tube tube integrity.

integrity.

In In the the context context of this Specification, of this Specification, aa SG SG tube tube isis defined defined as as the entire length the entire length of of the the tube, tube, including including the the tube tube wall wall and any repairs made to it,, between between the the tube-to-tubesheet tube-to-tubesheet weld weld at at the the tube tube inlet inlet and and the the tube-to-tubesheet tube-to-tubesheet weld weld at at the the tube outlet.

tube outlet. For For Unit Unit 2 2 during Refueling Outage during Refueling Outage 1515 and and thethe subsequent subsequent operating operating cycle,cycle, the the portion portion of of the the tube tube below below 16.95 16.95 inches inches from from the the toptop ofof the the tubesheet tubesheet is is excluded.

excluded. The The tube-to-tubesheet weld tube-to-tubesheet weld is is not not considered considered part part ofof the the tube.

tube.

A A SG SG tube has tube tube has tube integrity integrity when when it it satisfies satisfies the the SG SG performance criteria.

performance criteria. The The SGSG performance performance criteria criteria areare defined defined in in Specification Specification 5.5.9, 5.5.9, "Steam "Steam Generator Generator Program,"

Program,"

and and describe describe acceptable acceptable SG SG tube tube performance.

performance. The The Steam Steam Generator Program also Generator Program also provides provides the the evaluation evaluation process process forfor determining conformance with determining conformance with the the SGSG performance performance criteria.

criteria.

There There areare three three SG SG performance performance criteria:

criteria: structural structural integrity, accident induced integrity, accident induced leakage, leakage, and and operational operational LEAKAGE LEAKAGE (i .e., primary (i.e., primary to to secondary secondary LEAKAGE). Failure to LEAKAGE). Failure to meet meet anyany one one of of these these criteria criteria is is considered considered failurefailure to to meet meet the the LCO.

LCD.

The structural integrity The structural integrity performance performance criterion criterion provides provides aa margin margin of of safety safety against against tube tube burst burst or or collapse collapse under under normal normal and and accident accident conditions, conditions, and and ensures structural integrity ensures structural integrity of of the the SG SG tubes under all tubes under all anticipated anticipated transients transients included included in in the design specification.

the design speCification. Tube burst is Tube burst is defined defined as,as, "The "The gross gross structural structural failure failure of of the the tube tube wall.

wall. The The condition condition typically corresponds to typically corresponds to an an unstable unstable opening opening displacement displacement (e.g.,

(e.g., opening opening areaarea increased increased in in response response to to constant constant pressure) accompanied pressure) accompanied by by ductile (plastic) tearing ductile (plastic) tearing of of the the tube tube material material at at the the ends ends ofof thethe degradation."

degradation." Tube Tube collapse collapse is is defined defined as, "For the as, "For the load load displacement displacement curvecurve for for aa given given structure, collapse occurs structure, collapse occurs at at the the top top of of the the load load versus versus displacement displacement curve curve where where the the slope slope of of the the curve curve becomes becomes zero."

zero." The structural integrity The structural integrity performance performance criterion provides guidance criterion provides guidance on on assessing assessing loads loads that that have have aa significant effect on significant effect on burst burst or or collapse.

collapse.

BRAIDWOOD UNITS 11 &&22 BRAIDWOOD -- UNITS B B 3.4.19 3.4.19 -- 3 3 Revision Revision S4 84

SG SG Tube Integrity Tube Integrity B

B 3.4.19 3.4.19 BASES BASES APPLICABILITY APPLICABILITY Steam Steam generator generator tube integrity is tube integrity is challenged challenged when the when the pressure pressure differential differential acrossacross thethe tubes tubes is is large. Large large. Large differential pressures across differential pressures across SGSG tubes can only tubes can only bebe experienced experienced in in MODE MODE 1,1, 2,2, 3, 3, or or 4.4.

RCS RCS conditions conditions areare far far less less challenging challenging in in MODES MODES 55 and and 66 than than during during MODES MODES 1, 1, 2, 2, 3,3, and and 4.4. In In MODES MODES 55 and and 6,6, primary primary to to secondary secondary differential pressure is differential pressure is low, low, resulting resulting in in lower lower stresses and reduced stresses and reduced potential potential for for LEAKAGE.

LEAKAGE.

ACTIONS ACTIONS The The ACTIONS are modified ACTIONS are modified by by aa Note Note clarifying clarifying thatthat the the Conditions Conditions maymay be be entered entered independently independently for for each each SGSG tube.

tube.

This This isis acceptable acceptable because because thethe Required Required Actions Actions provide provide appropriate compensatory actions appropriate compensatory actions forfor each each affected affected SG SG tube.

tube.

Complying Complying with the Required with the Required Actions Actions may may allow allow for for continued continued operation, operation, andand subsequent subsequent affected affected SG SG tubes tubes areare governed governed by by subsequent Condition entry subsequent Condition entry and and application application of of associated associated Required Actions.

Required Actions.

A.l and A.2 A.1 and A.2

h. itubes r-~--:----' Condition Condition A applies if A applies if itit is is discovered discovered that that one one or or more more SGSG Iplugging Ubes exami ned in examined in anan inservice i nservi ce inspection i nspecti on satisfy sati sfy the the tube tube

. ~epair criteria criteria butbutwerewerenot plugged or repaired in not plugged-&iin accordance with the accordance with the Steam Steam Generator Generator Program Program as as required required by by SR 3.4.19.2. An SR 3.4.19.2. evaluation of An evaluation of SG SG tube tube integrity integrity of of the the affected tube(s) must affected tube(s) must bebe made. Steam generator made. Steam generator tubetube integrity integrity isis based based onon meeting meeting thethe SGSG performance performance criteri criteri plugging plugging described in described in the the Steam Steam Generator Generator Program.

Program. The The SGSG repair criteria define limits criteria define limits on on SG SG tube tube degradation degradation thatthat allow allow for for flaw growth between flaw growth between inspections inspections whilewhile still still providing providing assurance that the assurance that the SGSG performance performance criteria criteria will will continue continue to to be met.

be met. InIn order order toto determine determine ifif aa SGSG tube tube that that should should have have been plugged--&r-been plugged or repaired has tube integrity, has tube integrity, an an evaluation evaluation must must be be completed completed thatthat demonstrates demonstrates that that the the SGSG performance performance criteria will continue criteria will continue to to be be met met until until the the next next refueling refueling outage outage oror SG SG tube tube inspection.

inspection. The The tube tube integrity integrity determination is determination based on is based on the the estimated estimated condition condition of of the the tube at tube at the the time time the the situation situation is is discovered discovered and and the the growth of estimated growth estimated of the the degradation degradation prior prior to to the the next next SGSG tube inspection.

tube inspection. If If it it isis determined determined thatthat tube tube integrity integrity is is not being not being maintained, maintained, Condition Condition BBapplies.

applies.

AA Completion Completion Time Time ofof 77 days days isis sufficient sufficient to to complete complete thethe evaluation while evaluation while minimizing minimizing the the risk risk of of plant plant operation operation withwith a SG a SG tube tube that that may may not not have have tube tube integrity.

integrity.

BRAIDWOOD -- UNITS BRAIDWOOD &

UNITS 11 & 22 B 3.4.19 B 3.4.19 -- 55 Revi si on -64 Revision 4

SG SG Tube Integrity Tube Integrity B

B 3.4.19 3.4.19 BASES BASES ACTIONS (continued)

ACTIONS (continued)

If If the the evaluation evaluation determines that the determines that the affected affected tube(s) tube(s) have have tube integrity, Required tube integrity, Required Action Action A.2 allows plant A.2 allows plant operation operation to to continue continue until the next until the next refueling refueling outage outage or or SG SG inspection, inspection, whichever whichever occurs occurs first, provided the first, provided the inspection inspection interval interval continues continues to to be be supported supported by by anan operational operational assessment assessment that that reflects reflects the the affected affected tubes. However, the tubes. However, the affected affected tube(s) must be tube(s) must be plugged plugged or repaired prior prior to to entering entering MODE MODE 44 following following thethe next next refueling refueling outage outage or or SG SG inspection, inspection, whichever occurs first.

whichever occurs first. ThisThis Completion Completion Time Time is is acceptable acceptable since operation until since operation until thethe next next inspection inspection is is supported supported byby the the operational operational assessment.

assessment.

B.l B.1 and B.2 and B.2 If If the the Required Required Actions Actions and and associated associated Completion Completion Times Times of of Condition Condition A are not A are not met or if met or if SGSG tube tube integrity integrity is is notnot being being maintained, maintained, the the reactor reactor must must bebe brought brought to to MODE MODE 33 within within 66 hours7.638889e-4 days 0.0183 hours 1.09127e-4 weeks 2.5113e-5 months and MODE hours and MODE 55 within within 36 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

hours.

The allowed Completion The allowed Completion Times Times are are reasonable, reasonable, based based on on operating experience, to operating experience, to reach reach the the desired desired plant plant conditions conditions from from full power conditions full power conditions in in an an orderly orderly manner manner and and without without challenging plant systems.

challenging plant systems.

SURVEILLANCE SURVEILLANCE SR SR 3.4.19.1 3.4.19.1 REQUIREMENTS REQUIREMENTS During shutdown periods During shutdown periods the the SGs SGs are are inspected inspected as as required required by by this SR and this SR and the the Steam Steam Generator Generator Program.

Program. NEI NEI 97-06, 97-06, "Steam "Steam Generator Program Guidelines,"

Generator Program Guidelines," (Ref.

(Ref. 1),

1), and and its its referenced referenced EPRI EPRI Guidelines, Guidelines, establish the content establish the content of of the the Steam Steam Generator Program.

Generator Program. Use Use of of the the Steam Steam Generator Generator Program Program ensures that the ensures that the inspection inspection is is appropriate appropriate and and consistent consistent with accepted industry with accepted industry practices.

practices.

During During SGSG inspections inspections aa condition condition monitoring monitoring assessment assessment of of the SG the SG tubes tubes is is performed.

performed. The The condition condition monitoring monitoring assessment determines assessment determines thethe "as "as found" found" condition condition of of the the SG SG tubes. The tubes. The purpose purpose of of the the condition condition monitoring monitoring assessment assessment is to is to ensure that the ensure that the SG SG performance performance criteria criteria have have beenbeen metmet for the previous for the previous operating operating period.

period. I p uggmg The Steam The Steam Generator Generator Program Program determines determines the the sc sc pe pe of of thethe inspection and inspection and the the methods methods used used toto determine hether the determine hether the tubes contain tubes contain flaws flaws satisfying satisfying thethe tube tube repair criteria.

criteria.

Inspection scope Inspection scope (i.e.,

(i.e., which which tubes tubes oror areas areas of of tubing tubing within the within the SG SG are are toto be be inspected) inspected) is is aa function function ofof existing existing and potential and potential degradation degradation locations.

locations. The The Steam Steam Generator Generator BRAIDW00D UNITS 11 &&22 BRAIDWOOD -- UNITS B3.4.19-6 B 3.4.19 - 6 Revision 64 Revision64

SG SG Tube Integrity Tube Integrity B

B 3.4.19 3.4.19 BASES BASES SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE REQUIREMENTS (continued)

Program Program also also specifies specifies the inspection methods the inspection methods toto be be used used toto find find potential potential degradation. Inspection methods degradation. Inspection methods are are aa function of function of degradation degradation morphology, non-destructive morphology, non-destructive examination examination (NDE) (NDE) technique technique capabilities, capabilities, and and inspection inspection locations.

locations.

The Steam Generator The Steam Generator Program Program defines defines the the Frequency Frequency of of SR 3.4.19.1. The SR 3.4.19.1. Frequency is The Frequency is determined determined by by the the operational operational assessment assessment and and other other limits limits in in the the SG SG examination examination guidelines guidelines (Ref.

(Ref. 6). 6). The Steam Generator The Steam Generator Program Program uses uses information information on on existing existing degradations degradations and and growth growth rates rates to to determine determine an an inspection Frequency that inspection Frequency that provides provides reasonable reasonable assurance assurance that that the tubing the tubing willwill meet the SG meet the SG performance performance criteria criteria atat the the next next scheduled inspection. In scheduled inspection. In addition, addition, Specification Specification 5.5.95.5.9 contains prescriptive requirements contains prescriptive requirements concerning concerning inspection inspection intervals intervals to to provide provide added added assurance assurance that that the the SG SG performan performan~~=,.."....-.....,

cri teri a will criteria wi 11 be be met met between between scheduled schedul ed inspections.

i nspecti ons. +---L--r----II NSERT 2 SR 3.4.19.2 SR 3.4.19.2 plugging p^ug^n9 During During an an SG SG inspection, inspection, an 'nspected tube an inspected tube that that satisfies satisfies the Steam Generator the Steam Generator Program Program repair criteria criteria "s 's repaired or removed from removed from service service byby plugging.

plugging. The The tube tube repair criteria criteria delineated delineated in in Specification Specification 5.5.9 are intended 5.5.9 are intended toto ensure ensure that tubes accepted that tubes accepted for for continued continued service service satisfy satisfy thethe SGSG erformance

~p-Iu-g-g-in-g--' performance plugging criteria criteria with allowance with allowance for for error error in in the the flaw flaw size size urement and surement and for for future future flaw flaw growth.

growth. In In addition, addition, the the tubtub repair criteria, criteria, in in conjunction conjunction withwith other other elements elements of the Steam of the Steam Generator Generator Program, Program, ensure ensure that that the the SGSG performance criteria will performance criteria continue to will continue to be be met met until until the the next next inspection inspection of of the the subject subject tube(s). Reference 11 provides tube(s). Reference provides guidance guidance for for performing performing operational operational assessments assessments to to verify verify that that the the tubes tubes remaining remaining in in service service will will continue continue to to meet meet the the SG SG performance performance criteria.

criteria.

Steaffl geAerator tube repairs are oAly perforffled usiAg approved repair fflethods as described iA the Steaffl GeAerator Pf"e~l"'affl. plugging The Frequency of The Frequency of prior prior to to ee tering tering MODE MODE 44 following following aa SG SG inspection inspection ensuresensures that that th th urveillance urveillance has has been been completed completed and and allall tubes tubes meeting meeting the the repair criteria are plugged criteria are plugged ~

repaired prior to

^d-prior to subjecting subjecting thethe SGSG tubes tubes toto significant significant primary to primary to secondary secondary pressure pressure differential.

differential.

BRAIDWOOD UNITS 11 &&22 BRAIDWOOD -- UNITS B B 3.4.19 3.4.19 -- 77 Revision Revision-64 M

INSERT 2 Ifcrack If crack indications indications are are found in any SG tube, tube, the themaximum maximuminspection inspectioninterval intervalfor forall all affected and potentially affected affected SGs is restricted byby Specification 5.5.9 until subsequent subsequent inspections support extending the the inspection inspection interval.

interval.

THS MARKUP THIS MARKUP OF TS BASES PAGE B 3.4.19-3 REFLECTS REFLECTS CHANGES PROPOSED PROPOSEDIN INTHE THEH* H*PERMANENT PERMANENTALTE RNATE ALTERNATE SG SG Tube Integrity Tube Integrity REPAIR CRITERIA LAR DATED MARCH MARCH 20, 2012.

2012. B B 3.4.19 3.4.19 BASES plugging LCO LCO The The LCO LCO requires requires that that SG SG tube tube integrity integritybebemaintained.

maintained. The The LCO LCO also requires that also requires that all all SGSG tubes tubes that that satisfy satisfy the the repair criteria criteria be be plugged plugged or repaired in in accordance accordance with the Steam with the Steam Generator Program.

Generator Program. plugging plugging During During an an SG SG inspection, inspection, anyvinspected any 'nspected tube tube that that satisfies satisfies the Steam Generator the Steam Generator Program Program repair criteriacriteria is isrepaired

-ri or er-Iplugging Lplugging removed removed from from ?ervice service byby plugging.

plugging. If If aa tube tube was was determined determined to satisfy th to satisfy th~epair criteria criteria but but was was not not plugged-ems plugged-er repaired,, the f-e tube may the tube may still still havehave tube tube integrity.

integrity.

In In the the context context ofof this this Specification, Specification, aa SG SG tube tube isis defined defined as as the entire length the entire length of of the the tube, tube, iRcludiRg tt:le tube ~v'all aRd aRY repairs ffiade to it, between between the the tube-to-tubesheet tube-to-tubesheet weld weld at at the the tube tube inlet inlet and and the the tube-to-tubesheet tube-to-tubesheet weld weld at at the the tube outlet. For tube outlet. Unit 2 duriRg R£fueliRg Outage 15 aRd tt:le For Unit -111-he I subsequeRt SHBSeaHen- operatiRg cycle,, the portion of the portion the tube of the tube below below

~ . inches inches from from the the top top ofof the the tubesheet tubesheet is is excluded.

excluded. The The 14.01 ~tube-to-tubesheet 114.01 tube-to-tubesheet weld weld is is not not considered considered partpart ofof the the tube.

tube.

A A SG SG tube tube has has tube tube integrity integrity when when it it satisfies satisfies the the SG SG performance criteria. The performance criteria. The SGSG performance performance criteria criteria areare defined defined in in Specification Specification 5.5.9, 5.5.9, "Steam "Steam Generator Generator Program,"

Program,"

and and describe describe acceptable acceptable SG SG tube tube performance.

performance. The The Steam Steam Generator Program also Generator Program also provides provides the the evaluation evaluation process process for for determining conformance with determining conformance with the the SGSG performance performance criteria.

criteria.

There There are are three three SG SG performance performance criteria:

criteria: structural structural integrity, integrity, accident induced leakage, accident induced leakage, and and operational LEAKAGE operational LEAKAGE (i.e.,

(i.e., primary primary to to secondary secondary LEAKAGE). Failure to LEAKAGE). Failure to meet meet any any one one of of these these criteria criteria is is considered considered failure failure to to meet meet the the LCO.

LCO.

The structural integrity The structural integrity performance performance criterion criterion provides provides aa margin margin of of safety safety against against tube tube burst burst oror collapse collapse under under normal normal and and accident conditions, and accident conditions, and ensures ensures structural structural integrity integrity of of the the SG tubes under SG tubes under all all anticipated anticipated transients transients included included in in the design specification.

the design specification. Tube burst is Tube burst is defined defined as, as, "The "The gross gross structural structural failure failure ofof the the tube tube wall.

wall. The The condition condition typically corresponds to typically corresponds to an an unstable unstable opening opening displacement displacement (e.g.,

(e.g., opening area increased opening area increased in in response response to to constant constant pressure) accompanied by pressure) accompanied by ductile (plastic) tearing ductile (plastic) tearing of of the the tube tube material material at at the the ends ends ofof thethe degradation."

degradation." Tube Tube collapse collapse is is defined as, "For defined as, "For the the load load displacement displacement curvecurve for for aa given structure, collapse given structure, collapse occurs occurs at at the the top top of of the the load load versus displacement curve versus displacement curve where where the the slope slope of of the the curve curve becomes zero." The becomes zero." The structural structural integrity integrity performance performance criterion provides guidance criterion provides guidance on on assessing assessing loads loads that that have have aa significant effect on significant effect on burst burst or or collapse.

collapse.

BRAIDWOOD UNITS 11 &&22 BRAIDWOOD -- UNITS B B 3.4.19 3.4.19 -- 33 Revision Revision 84 84

ATTACHMENT ATTACHMENT 55 Proposed Technical Specifications Specifications Bases BasesChanges Changesfor forByron ByronStation, Station,Units Units 11and and 22 Units 11 and Byron Station, Units and 22 NPF-37 and NPF-66 Facility Operating License Nos. NPF-37 NPF-66 Mark-up of Technical Mark-up of Specifications Bases Pages Technical Specifications B

B 3.4.19-3 B

B 3.4.19-5 3.4.19-5 B

B 3.4.19-6 B

B 3.4.19-7 3.4.19-7

SG Tube SG Tube Integrity Integrity 3.4.19 B 3.4.19 B

BASES BASES plugging plugging LCO LCO The LCO The LCO requires requires that that SGSG tube tube integrity integrity be be maintained.

maintained. The The LCO also LCO requires that also requires that all all SGSG tubes tubes that that satisfy satisfy thethe repair criteria be criteria be plugged plugged or repaired ir-ed in in accordance accordance with with the Steam the Steam Generator Program.

Generator Program. plugging During an During an SG inspection, any SG inspection, 'nspected tube anyinspected tube thatthat satisfies satisfies the Steam the Steam Generator Generator Program Program repair criteriacriteria is is repaired or Iplugging plugging removed from removed service by from ~rvice by plugging.

plugging. If If aa tube tube waswas determined determined to satisfy to satisfy th criteria but th~repair criteria but was was not not plugged-er-plugged-er repaired, the tube 4-r-e4, the tube may may still still havehave tube tube integrity.

integrity.

In In the the context context ofof this this Specification, Specification, aa SG SG tube tube isis defined defined as as thethe entire entire length length ofof the the tube, tube, including including the the tube tube wall wall and

-IfKi any repairs made to it,, betweenbetween the the tube-to-tubesheet tube-to-tubesheet weld weld at at the the tube tube inlet inlet and and the the tube-to-tubesheet tube-to-tubesheet weld weld at at the the tube outlet.

tube outlet. For For Unit Unit 2 2 during during Refueling Refueling Outage Outage 16 16 and and the the subsequent subsequent operating cycle, the operating cycle, the portion portion of of the the tube tube below below 16.95 16.95 inches inches from from the the top top ofof the the tubesheet tubesheet is is excluded.

excluded. The The tube-to-tubesheet tube-to-tubesheet weld weld isis not not considered considered part part ofof the the tube.

tube.

A SG A SG tube tube has has tube tube integrity integrity whenwhen it it satisfies satisfies the the SG SG performance criteria. The performance criteria. The SGSG performance performance criteria criteria are are defined defined in in Specification Specification 5.5.9, 5.5.9, "Steam "Steam Generator Generator Program,"

Program,"

and and describe describe acceptable acceptable SG SG tube tube performance.

performance. The The Steam Steam Generator Program also Generator Program also provides provides the the evaluation evaluation process process forfor determining conformance with determining conformance with the the SG SG performance performance criteria.

criteria.

There There are are three three SGSG performance performance criteria:

criteria: structural structural integrity, integrity, accident induced leakage, accident induced leakage, and and operational operational LEAKAGE LEAKAGE (i.e.,

(i.e., primary primary toto secondary secondary LEAKAGE). Failure to LEAKAGE). Failure to meet meet any any one one of these criteria of these criteria is is considered considered failure failure to to meet meet the the LCO.

LCO.

The structural integrity The structural integrity performance performance criterion criterion provides provides aa margin margin of of safety safety against against tube tube burst burst oror collapse collapse underunder normal normal and and accident accident conditions, conditions, and and ensures ensures structural integrity of structural integrity of the the SG tubes under SG tubes under all all anticipated anticipated transients transients included included in in the the design specification. Tube design specification. burst is Tube burst is defined defined as, as, "The "The gross gross structural structural failure failure of of the the tubetube wall.

wall. The The condition condition typically corresponds typically corresponds to an unstable to an unstable opening opening displacement displacement (e.g.,

(e.g., opening opening area increased in area increased in response response to to constant constant pressure) accompanied by pressure) accompanied by ductile (plastic) tearing ductile (plastic) tearing of of the the tube tube material material at at the the ends ends ofof the the degradation."

degradation." Tube Tube collapse collapse is is defined defined as, "For the as, "For the load load displacement displacement curve curve forfor aa given given structure, collapse occurs structure, collapse occurs at at the the top top ofof the the load load versus versus displacement curve where displacement curve where the the slope slope of of the the curve curve becomes becomes zero." The structural zero." The structural integrity integrity performance performance criterion provides guidance criterion provides guidance on on assessing assessing loads loads that that have have aa significant effect on significant effect on burst burst oror collapse.

collapse.

BYRON BYRON -- UNITS 1 &&22 UNITS 1 B B 3.4.19 3.4.19 -- 3 3 Revision Revision +6-46

SG SG Tube Integrity Tube Integrity B 3.4.19 B 3.4.19 BASES BASES APPLICABI LITY APPLICABILITY Steam generator tube Steam generator tube integrity integrity is is challenged challenged when when the the pressure differential pressure differential across across the the tubes tubes is is large. Large large. Large differential pressures across differential pressures across SG SG tubes tubes cancan only only be be experienced experienced in in MODE MODE 1, 1, 2,2, 3, 3, or or 4.4.

RCS RCS conditions conditions are far less are far less challenging challenging in in MODES MODES 55 and and 66 than than during during MODES MODES 1,1, 2, 2, 3,3, and and 4.4. In In MODES MODES 55 andand 6,6, primary primary to to secondary differential pressure secondary differential pressure is is low, low, resulting resulting in in lower stresses and lower stresses and reduced reduced potential potential for for LEAKAGE.

LEAKAGE.

ACTIONS ACTIONS The The ACTIONS are modified ACTIONS are modified by by aa Note Note clarifying clarifying that that thethe Conditions Conditions maymay be be entered entered independently independently for for each each SGSG tube.

tube.

This This is is acceptable acceptable because because thethe Required Required Actions Actions provide provide appropriate compensatory actions appropriate compensatory actions forfor each each affected affected SG SG tube.

tube.

Complying Complying with the Required with the Required Actions Actions may may allow allow forfor continued continued operation, operation, andand subsequent subsequent affected affected SG SG tubes tubes are are governed governed by by subsequent subsequent Condition Condition entry and application entry and application of of associated associated Required Actions.

Required Actions.

A.l A.1 andand A.2 A.2 Condition Condition A applies if A applies if itit is is discovered discovered that that oneone or or more more SG SG Iplugging ~tubes examined in tubes examined in an an inservice inservice inspection inspection satisfy satisfy the the tube tube repair criteria but were criteria but were notnot plugged plugged or repaired in in accordance accordance with with the Steam Generator the Steam Generator Program Program as as required required by by SR 3.4.19.2. An SR 3.4.19.2. evaluation of An evaluation of SG SG tube tube integrity integrity of of the the affected affected tube(s) tube(s) must must bebe made. Steam generator made. Steam generator tube tube integrity integrity isis based based on on meeting meeting the the SGSG performance performance criteri criteri described described in in the the Steam Steam Generator Generator Program.

Program. The The SGSG repair criteria criteria define limits on define limits on SG SG tube tube degradation degradation that that allow allow forfor flaw growth between flaw growth between inspections inspections whilewhile still still providing providing assurance assurance that the SG that the SG performance performance criteria criteria will will continue continue to to be be met.

met. InIn order order toto determine determine if if aa SGSG tube tube that that should should havehave been plugged or repaired has been plugged tube integrity, has tube integrity, an an evaluation evaluation must must be be completed completed that that demonstrates demonstrates that that the the SGSG performance performance criteria criteria will continue to will continue to be be met met until until thethe next next refueling refueling outage outage oror SG SG tube tube inspection.

inspection. The The tube tube integrity integrity determination determination is is based based on on the the estimated estimated condition condition of of the the tube tube atat the the time time the the situation situation is is discovered discovered and and the the estimated growth of estimated growth the degradation of the degradation priorprior toto the the next next SG SG tube inspection. If tube inspection. If it it isis determined determined that that tube tube integrity integrity is is not being maintained, not being maintained, Condition Condition BBapplies.

applies.

A Completion Time A Completion Time of of 77 days days isis sufficient sufficient to to complete complete the the evaluation while evaluation while minimizing minimizing the the risk risk ofof plant plant operation operation with with aa SG SG tube that may tube that may not not have have tube tube integrity.

integrity.

BYRON UNITS 11 &&22 BYRON -- UNITS B B 3.4.19 3.4.19 -- 5 5 Revi si on *S Revision

SG SG Tube Integrity Tube Integrity B

B 3.4.19 3.4.19 BASES BASES ACTIONS (continued)

ACTIONS (continued)

If If the the evaluation evaluation determines that the determines that the affected affected tube(s) tube(s) havehave tube integrity, Required tube integrity, Required Action Action A.2 allows plant A.2 allows plant operation operation to to continue continue until until the next refueling the next refueling outage outage or or SG SG inspection, inspection, whichever occurs first, whichever occurs first, provided provided thethe inspection inspection interval interval continues continues to to be be supported supported by by anan operational operational assessment assessment that that reflects reflects the the affected affected tubes. However, the tubes. However, the affected tube(s) affected tube mustbebeplugged--e (s) must plugged or repaired

-r-epa-i re4 prior prior toto entering entering MODE MODE 4 4 following following the next refueling the next refueling outage outage oror SGSG inspection, whichever occurs inspection, whichever occurs first.

first. This This Completion Completion Time Time is is acceptable since operation acceptable since operation until until the next inspection the next inspection is is supported supported byby the the operational operational assessment.

assessment.

B.I B.1 and B.2 and B.2 If If the the Required Required Actions and associated Actions and associated Completion Completion Times Times of of Condition Condition A are not A are not met or if met or if SG SG tube tube integrity integrity is is not not being being maintained, maintained, the the reactor reactor must must be be brought brought to to MODE MODE 33 within within 66 hours7.638889e-4 days 0.0183 hours 1.09127e-4 weeks 2.5113e-5 months and MODE hours and MODE 55 within within 36 hours.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

The allowed Completion The allowed Completion Times Times are are reasonable, reasonable, basedbased onon operating experience, to operating experience, to reach reach the the desired desired plant plant conditions conditions from from full full power power conditions conditions in in an an orderly orderly manner and without manner and without challenging plant systems.

challenging plant systems.

SURVE I LLANCE SURVEILLANCE SR SR 3.4.19.1 3.4.19.1 REQUIREMENTS REQUIREMENTS During shutdown periods During shutdown periods the the SGs SGs are are inspected inspected as as required required by by this SR and this SR and the the Steam Steam Generator Generator Program.

Program. NEI NEI 97-06, 97-06, "Steam "Steam Generator Program Guidelines,"

Generator Program Guidelines," (Ref.

(Ref. 1),1), and and its its referenced referenced EPRI EPRI Guidelines, establish the Guidelines, establish the content content of of the the Steam Steam Generator Program. Use Generator Program. Use of of the the Steam Steam Generator Generator Program Program ensures that ensures that the the inspection inspection is is appropriate appropriate and and consistent consistent with accepted with accepted industry industry practices.

practices.

During SG During SG inspections inspections aa condition condition monitoring monitoring assessment assessment of of the SG the SG tubes tubes isis performed.

performed. The The condition condition monitoring monitoring assessment determines assessment determines thethe "as "as found" found" condition condition of of the the SG SG tubes. The tubes. The purpose purpose of of the the condition condition monitoring monitoring assessment assessment is to is ensure that to ensure that the the SG SG performance performance criteria criteria have have been been met met for the for the previous previ ous operating operati ng period.

peri od. I .

P uggrng plugging The Steam The Steam Generator Generator Program Program determines determines the the scope sc pe ofof the the inspection and inspection and the the methods methods used used toto determine hether the determine hether the tubes contain tubes contain flaws flaws satisfying satisfying thethe tube tube repalr criteria.

criteria.

Inspection scope Inspection scope (i.e.,

(i.e., which which tubes tubes or or areas areas ofof tubing tubing within the within the SG SG are are to to be be inspected) inspected) is is aa function function of of existing existing and potential and potential degradation degradation locations.

locations.

BYRON -- UNITS BYRON &

UNITS 11 & 22 BB 3.4.19 3.4.19 -- 66 Revi si on .§.9.

Revision

SG Tube SG Tube Integrity Integrity B 3.4.19 B 3.4.19 BASES BASES SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS (continued)

(continued)

The Steam The Steam Generator Generator Program Program also also specifies specifies the the inspection inspection methods to methods to be be used used to to find find potential potential degradation.

degradation.

Inspection methods Inspection methods are are aa function function of of degradation degradation morphology, morphology, non-destructive examination non-destructive examination (NDE) (NDE) technique technique capabilities, capabilities, and inspection and inspection locations.

locations.

The Steam The Steam Generator Generator Program Program defines defines the the Frequency Frequency of of SR 3.4.19.1.

SR 3.4.19.1. The The Frequency Frequency is is determined determined by by the the operational operational assessment and assessment and other other limits limits in in the the SGSG examination examination guidelines guidelines (Ref.

(Ref. 6).6). TheThe Steam Steam Generator Generator Program Program uses uses information information on on existing existing degradations degradations and and growth growth rates rates to to determine determine an an inspection Frequency inspection Frequency that that provides provides reasonable reasonable assurance assurance that that the tubing will the tubing meet the will meet the SG SG performance performance criteria criteria at at the the next next scheduled inspection.

scheduled inspection. In In addition, Specification 5.5.9 addition, Specification 5.5.9 contains prescriptive requirements contains prescriptive requirements concerning concerning inspection inspection interval intervals s to to provide provide addedadded assurance assurance that that thethe SG SG performance performanc;.;.::.e~~.......,...... . .

criteria criteria will will be be met met between between scheduled scheduled inspections.

inspections. INSERT I NS E RT 2 2 SR SR 3.4.19.2 3.4.19.2 Inhirmin , L..s_

Ipic^ Bing During During an an SG SG inspection, inspection, an 'nspected tube anyinspected tube that that satisfies satisfies the Steam the Generator Program Steam Generator Program repair criteria's criteria 's repaired or removed removed from from service service by by plugging.

plugging. The The tube tube repair criteria criteria delineated delineated in in Specification Specification 5.5.9 5.5.9 areare intended intended to to ensure ensure that that tubes accepted for tubes accepted for continued continued service service satisfy satisfy the the SG SG Iplugging performance criteria

-performance criteria withwith allowance allowance for for error error inin the the flaw flaw plugging slze~surement size surement andand forfor future future flaw flaw growth.

growth. In In addition, addition, the the tubtub~repair

-r-eea--i-ncrlteria, criteria, lninconjunctlon conjunctionwlth with other other elements elements of of thethe Steam Generator Program, Steam Generator Program, ensure ensure thatthat thethe SGSG performance performance criteria criteria will continue to will continue to be be met met until until the the next next inspection inspection of of the the subject subject tube(s).

tubeCs). Reference Reference 1 1 provides provides guidance guidance for performing operational for performing operational assessments assessments to to verify verify that the that tubes remaining the tubes remaining in in service service will will continue continue to to meet meet the the SG performance criteria.

SG performance criteria.

Steam generator tube repairs are only performed using approved repair red metRods as described in tRe Steam Generator

,+ h n d ^! ;L rl +

-e rG°-S°e^arn °^^eTrc^=a r

am.

P-P6gI"Jtfl. plugging plugging The Frequency of The Frequency of prior prior to to tering tering MODE MODE 4 4 following following a a SGSG inspection inspection ensures ensures that that th urveillance has th Surveillance has been been completed completed and and allall tubes meeting the tubes meeting the repair criteria criteria are are plugged plugged ~ en repaired prior

-r-ep prior toto subjecting subjecting the the SGSG tubes tubes to to significant significant primary primary to secondary pressure to secondary pressure differential.

differential.

BYRON BYRON -- UNITS 1&

UNITS 1 2

& 2 B B 3.4.19 3.4.19 -- 7 7 Revi si on Revision .§.9.

59

INSERT 2 2 If crack indications are found in in any any SG SG tube, tube, the the maximum maximuminspection inspectioninterval intervalfor forall all affected and potentially affected SGs is restricted by Specification 5.5.9 until subsequent subsequent support extending inspections support extending the the inspection inspection interval.

interval.

THIS MARKUP THIS MARKUP OF OF TS TS BASES BASES PAGE PAGE B B 3.4.19-3 3.4.19-3 REFLECTS REFLECTS CHANGES PROPOSED CHANGES PROPOSEDININTHE THEH* H*PERMANENT PERMANENTALTERNATE ALTERNATE SG Tube SG Tube Integrity Integrity REPAIR CRITERIA REPAIR CRITERIA LARLAR DATED MARCH 20, 2012. 2012. BB 3.4.19 3.4.19 BASES BASES plugging Egging LCO LCO The LCO The LCO requires requires that that SG SG tube tube integrity integrity be be maintained.

maintained. The The LCO also LCO also requires requires thatthat allall SGSG tubes tubes that that satisfy satisfy thethe repair criteria be criteria be plugged or repaired plugged--a-^ne4 in in accordancewith accordance withthethe Steam Steam Generator Program.

Generator Program. plugging plugging During an During an SGSG inspection, inspection, any any 'nspected

nspected tube tube thatthat satisfies satisfies the Steam the Steam Generator Generator Program Program repair ' criteria is criteria is repaired or

-ed-er-Iplugging plugging removed from removed from ~rvice ervice by by plugging.

plugging. IfIfa atube tube waswas determined determined to satisfy to satisfy th th~repair ' criteria but criteria but was was notnot plugged-&r-plugged-er repaired,, the f-e the tube tube may may still still havehave tube tube integrity.

integrity.

In the In context of the context of this this Specification, Specification, aa SG SG tube tube isis defined defined as the as the entire entire length length of of the the tube, tube, ;including f'el a d- ^ +,,bthe tubew&r-wall and any repairs made to it, between between the the tube-to-tubesheet tube-to-tubesheet weld at weld at the the tube tube inlet inlet and and the the tube-to-tubesheet tube-to-tubesheet weld weld atat the the tube outlet.

tube outlet. For For Unit Unit 22 during Refueling Outage l6 and the subsequent operating cycle,, the the portion portion of of the the tube tube below below

~ inches inches from from the the toptop ofof thethe tubesheet tubesheet is is excluded.

excluded. The The

~tube-to-tubesheet 14.01 tube to-tubesheet weld weld is is not not considered considered part part ofof the the tube.

tube.

A SG A SG tube tube hashas tube tube integrity integrity when when it it satisfies satisfies the the SG SG performance criteria.

performance criteria. The The SGSG performance performance criteria criteria are are defined in defined in Specification Specification 5.5.9, 5.5.9, "Steam "Steam Generator Generator Program,"

Program,"

and describe and describe acceptable acceptable SG SG tube tube performance.

performance. The The Steam Steam Generator Program also Generator Program also provides provides the the evaluation evaluation processprocess forfor determining conformance with determining conformance with the the SGSG performance performance criteria.

criteria.

There There areare three three SGSG performance performance criteria:

criteria: structural structural integrity, integrity, accident induced leakage, accident induced leakage, and and operational operational LEAKAGE LEAKAGE (i.e.,

(i.e., primary primary to to secondary secondary LEAKAGE).

LEAKAGE). FailureFailure to to meet meet any any one one of these criteria of these criteria is is considered considered failurefailure to to meet meet the the LCO.

LCO.

The structural integrity The structural integrity performance performance criterion criterion provides provides aa margin margin of of safety safety against against tube tube burst burst or or collapse collapse underunder normal normal and and accident accident conditions, conditions, and and ensures structural integrity ensures structural integrity of of the SG the SG tubes tubes under under allall anticipated transients included anticipated transients included in in the the design specification. Tube design specification. burst is Tube burst is defined defined as,as, "The "The gross gross structural structural failure failure of of the the tube tube wall.

wall. The The condition condition typically typically corresponds corresponds to to an unstable opening an unstable opening displacement displacement (e.g.,

(e.g., opening opening area increased in area increased in response response to to constant constant pressure) pressure) accompanied accompanied by by ductile (plastic) tearing ductile (plastic) tearing of of the the tube tube material material at at the the ends ends ofof thethe degradation."

degradation." Tube Tube co 11 apse is collapse is defi ned as, defined "For the as, "For the 1 oad di load sp1acement curve displacement curve forfor aa given given structure, structure, collapse collapse occursoccurs at at the the toptop ofof the the load load versus versus displacement displacement curve curve where where the slope of the slope of the curve the curve becomes becomes zero."

zero." TheThe structural integrity performance structural integrity performance criterion criterion provides guidance on provides guidance on assessing assessing loads loads that that have have aa significant significant effect effect on burst or on burst or collapse.

collapse.

BYRON BYRON -- UNITS UNITS 11 &

& 22 B B 3.4.19 3.4.19 -- 3 Revi si on Revision ::j-6.

v t e Letter Sequence Request
TAC:ME9448, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Revise Containment Requirements During Handling Irradiated Fuel and Core Alterations (Approved, Closed)
Initiation Request, Request, Request Acceptance, Acceptance Administration Questions 4 February 2013 Answers 14 February 2012 6 March 2013 Results Approval Other:
MONTHYEAR2012-08-29 [Table View]

RS-12-028, Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection.

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3.0 REGULATORY ANALYSIS

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RS-12-028, Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection.

Text

Subject:

1.0 DESCRIPTION

3.0 REGULATORY ANALYSIS

1.0 DESCRIPTION

3.0 REGULATORY ANALYSIS

Response

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