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{{#Wiki_filter:&Wu.W A.." SA..o,.ov H. a Elc* 0"W- -&*WUMAE 3881 V"WErnWVO RoadHff" SC 20WOa: 843W ? 14F: 843 857 1319Serial: RNP.W113.0089 10 CFR 50.90AUG 2 2 2013ATTN: Document CWrol DeskU.S. Regulaory Commission wasimngton, DC 2058-0001 H. B. RO8INSON STEAM ELECTRIC PLANT, UNIT NO. 2DOCKET NO. 50-261/RENEWED LICENSE NO. DPR-23SUPPLEMENTAL SUBMITTAL TO CORRECT TS PAGES REGARDING REQUEST FORREVISION TO STEAM GENERATOR PROGRAM INSPECTION FREQUENCIES AND TUBESAPE LECION AM. 6PP!AIQN QpE MMAWN ALTERNATE REPARN RTEIByl,*t daled 29,2012, (Pgncyw*
Docmens Access and Management Sytem(AAMS) M u No. WLI2S );d wtAo 10 CFRW5.90, Carolina Power and LightCormpn requested an amendmetqto he ifB. Rb: no Steami6 6" c" ~stU NO.rewwedfaclly opsrutln Ucane bPft-23.lAppendlx A, T~chhkcI Spcfctot(TSY SOctlo5.5.9, Steamn Generator (5(3) Program.By leter dated February 4,2013, (ADAMS Accession No. ML13017A288) the NRC stffreqwiesed oddltjonl Informatli (RAJ) needed to continue its review of the proposed licemeBy etter I d Apt", 2013 (ADAMAoessa'aon No. MbLt&123Ai221)
Duke Energy Progress, Inc. formerly known as CaroWnaPowwnd Light Company provided It response to the NRCsrequest for additional information.
Atteched please find reilacment TS pages (pages 5.0-13 and 5.0-28)for the co n d TSpages in A#ment 2 to the 9,2013 letter. The eplaemen of these page does notaffect the concusions of elther* 10-CFR 50.92 No $ Oa Hazards Consderation imaem"InaIo ortlhe Envirompiotol~
Cakk ofmncnluided VAIft u losur to. the April9;W2013 submittal leter. There awe no other changes or addition to the Abd emrs to April 9, 2013lettW:r h presesn the proposed TS page markups, toe retyped TS pages, and mark.ed upTS Buse pag (for Wnform on otyThis documnent conlltains no new Regulatory Commitmenft.
In accordance w*th10 COR 50i1(ti) aop ofl thsaplcain sbe poiddthstsib SaeOfSouth Carolina.
f you' haew an tiiosredI p uir~lt, please contact Mr. RichadIiil$we~
upryso -ces g/ tryPr~rs~
t~438-9i29 H11" United StlMt Nuclear Regulatory Commi*Aon Sewd: FRNP.x13-0069 Poew 2 of 21 declae under penalty of pe"ur tha fth foregong ts Mme a" correct.
Executed On:______
sin-eel,Sharon WheI!)Pavytou**
-WK _ Suipport services
-NuclearSWP/$c
==Attachment:==
Rp"lacemen Pages for TS Page 5.0-13 anid 5.0-28 of Afttachment 2 of RNP-RAil 3-0030.cc:M.- Af,. E. Jenkins.
MangrW nfecftiou an Radioactiv Wast Mangeen Section (SC)Mr V. M. McCrea, NRC Regom IfMr. S. P. ungm, NRC Prje Manaer, NRR NRCResident Inspecto.
HORSEPMr. A. Wln, Attorney General (SC)
Unftd $Wms Nodge Regpdioy Comm*WwAttschmnt bo Ser: RNP4WAI3-OOS 3 PsgW, xincudnt Vcoverpeg*
ATTACHMENT ftpkmvnwi Pap* for TS Paoes &.0. 13 anW 5.0-28of Attachment 2 of RNP-RAI3-0030 Programs and Manuals5.55.5 PBoWns and MA ... ..5.5.9 amDO1SO Mal EfggNM(continued)
C. Provision for SG tube pluggin criteia.
Tubes found by Inservice inspection to contain flaws with a depth equal to or exceeding the following criterta sal be plugged:
47% of the nominal tube wall thickness If the nextinspection inlerval of that tube Is< 12 month and a 2% reduction In theplugging criteria for each 12 month period until the next inspection of the Itube.The following anler tube plugging criteria shall be applied as analternative to the precd citeria:Tube with -h edloed flaws located greater than 18.11 inches belowthe top of the tubhe do not require plugging.
Tubes with service-induced flaws located in the portion of the tube from the top of thetubesheet to 18.11 inches below the top of the tubeshest shall be pluggedupon daetctio.
: d. fPvso for S itube inspections.
Periodic SG ue inspections Shall beperfore.
The number and portions of the Iubes Inspected and methodsof inspection shall be performed wth the objectve of detecting flaws of anytype (e.g., volumetric flaws, axial and ia cracks) that may beeiset awon the length of the tube, from the ftu 4*ubhtW weld at thetube Inlet to the tube4otubesheet weld at the tube outlet and that maysatisfy the applicable tube plugg criteria.
The tub4otubesheht wekl isnot part of the tube. In addition to fmeen the requirements of d.1, d.2, andd.3 below, the Inspection scope, inspection
: methods, and Inspection Intervals shal be such as to ensure that SQ tube integrity Is maintained until the neod SO Inspection.
A degradation aseasment shall be performed to dOemine the type and location of flews to which the tubes may besusceptible ard, based on this assessment, to determine which inspection methods need to be employed and at what locations.
: 1. Inspect 100% of the tubes in each SG during the firstefueling outage following SG Installation.
: 2. After toe first refueling outage following SG installation, inspect eachSO at West every 48 effecti full power monft or at least everyother refueling outae (Whichever results In more *equentinspections).
In additin, the minimum number of tubes inspected ateach scheduled Inspection shall be te number of tubes in at SOsdvided by the number of SG inspection ouages sheduled in eachInspecion period as defined In a, b, and c below. If a degradation aseesIete indicates the potential for a type of degradation to occurat a location not previous Inspected with a technique capable ofdetecting Othi type of degradation at Othi location and that may satisfyrvNO AMA I5Ao.HOMP5.0-13Aftvwxftnent No.
Reportng Requirements 5.65.6 Rbork Rakaum-nta (cotnud5.8.7 Tendon IvMO M FfRema, Notification of a pending sample tendon test, along with detailedacceptice
: criteria, shae be submted to the NRC at last two monthprior to the actual testb. A report containing the sample tendon test eveaation shall besubmitted to the NRC within six monft of condkci te test5.8.8 StM eE nom TUS .mscionMA report shall be suWbmitd within 180 days after the initial entry into MODE 4followin completion of an Inspection performed in accordance with theSpecification 5.5.9, Stam Generator (SO) Program.
The report shell incluie:a. The scope of inspectons performed on each $0.b. Degradation mehnssfound.
: c. 1u em tchniques utilized for each degradation mechanism.
: d. Location, orientation (If linewa),
and measured sizes (If available) ofservice Induced indications.
: e. Number of tube plugged during the Inspection outage for eachdegadation mechanism.
: f. The number vnd percentage of tubes plugged to date, and the effctivepluggng percentaep In each steam geerwator.
: g. The results of condition monitoring, inclufd Ot results of tube pulls anisu test.h. The primary to econdry leakage rate observd In each SG (If It is notpractical to th leakage to an niiulu SG, the entire primary tosecondary leakage should be conservatively assumed to be from one SG)during the cycle preceting the Inspection that Is the subject of the repor.I. The aluMl accident induced leakage rate from the portion of the tubesbelow 18.1 Inchxem fom the top of the tubesheet for the most limitingaccident in the most lmiting SG. In addition, If the calculated accidentinduced lakap rate from the most imitng ascldent is les than 1.87times the maximum operational primary to secondary lakag rate. thereport should describe how it was determined, andH SE Unit No. 25.0-28Amerximent No.}}

Revision as of 08:52, 4 July 2018

H.B. Robinson Unit 2, Supplemental Submittal to Correct TS Pages Re Request for Revision to Steam Generator Program Inspection Frequencies & Tube Sample Selection & Application of Permanent Alternate Repair Criteria
ML13249A028
Person / Time
Site: Robinson Duke Energy icon.png
Issue date: 08/22/2013
From: Wheeler-Peavyhouse S A
Duke Energy Progress
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RNP-RA/13-0089
Download: ML13249A028 (5)
v • d • e


Text

&Wu.W A.." SA..o,.ov H. a Elc* 0"W- -&*WUMAE 3881 V"WErnWVO RoadHff" SC 20WOa: 843W ? 14F: 843 857 1319Serial: RNP.W113.0089 10 CFR 50.90AUG 2 2 2013ATTN: Document CWrol DeskU.S. Regulaory Commission wasimngton, DC 2058-0001 H. B. RO8INSON STEAM ELECTRIC PLANT, UNIT NO. 2DOCKET NO. 50-261/RENEWED LICENSE NO. DPR-23SUPPLEMENTAL SUBMITTAL TO CORRECT TS PAGES REGARDING REQUEST FORREVISION TO STEAM GENERATOR PROGRAM INSPECTION FREQUENCIES AND TUBESAPE LECION AM. 6PP!AIQN QpE MMAWN ALTERNATE REPARN RTEIByl,*t daled 29,2012, (Pgncyw*

Docmens Access and Management Sytem(AAMS) M u No. WLI2S );d wtAo 10 CFRW5.90, Carolina Power and LightCormpn requested an amendmetqto he ifB. Rb: no Steami6 6" c" ~stU NO.rewwedfaclly opsrutln Ucane bPft-23.lAppendlx A, T~chhkcI Spcfctot(TSY SOctlo5.5.9, Steamn Generator (5(3) Program.By leter dated February 4,2013, (ADAMS Accession No. ML13017A288) the NRC stffreqwiesed oddltjonl Informatli (RAJ) needed to continue its review of the proposed licemeBy etter I d Apt", 2013 (ADAMAoessa'aon No. MbLt&123Ai221)

Duke Energy Progress, Inc. formerly known as CaroWnaPowwnd Light Company provided It response to the NRCsrequest for additional information.

Atteched please find reilacment TS pages (pages 5.0-13 and 5.0-28)for the co n d TSpages in A#ment 2 to the 9,2013 letter. The eplaemen of these page does notaffect the concusions of elther* 10-CFR 50.92 No $ Oa Hazards Consderation imaem"InaIo ortlhe Envirompiotol~

Cakk ofmncnluided VAIft u losur to. the April9;W2013 submittal leter. There awe no other changes or addition to the Abd emrs to April 9, 2013lettW:r h presesn the proposed TS page markups, toe retyped TS pages, and mark.ed upTS Buse pag (for Wnform on otyThis documnent conlltains no new Regulatory Commitmenft.

In accordance w*th10 COR 50i1(ti) aop ofl thsaplcain sbe poiddthstsib SaeOfSouth Carolina.

f you' haew an tiiosredI p uir~lt, please contact Mr. RichadIiil$we~

upryso -ces g/ tryPr~rs~

t~438-9i29 H11" United StlMt Nuclear Regulatory Commi*Aon Sewd: FRNP.x13-0069 Poew 2 of 21 declae under penalty of pe"ur tha fth foregong ts Mme a" correct.

Executed On:______

sin-eel,Sharon WheI!)Pavytou**

-WK _ Suipport services

-NuclearSWP/$c

Attachment:

Rp"lacemen Pages for TS Page 5.0-13 anid 5.0-28 of Afttachment 2 of RNP-RAil 3-0030.cc:M.- Af,. E. Jenkins.

MangrW nfecftiou an Radioactiv Wast Mangeen Section (SC)Mr V. M. McCrea, NRC Regom IfMr. S. P. ungm, NRC Prje Manaer, NRR NRCResident Inspecto.

HORSEPMr. A. Wln, Attorney General (SC)

Unftd $Wms Nodge Regpdioy Comm*WwAttschmnt bo Ser: RNP4WAI3-OOS 3 PsgW, xincudnt Vcoverpeg*

ATTACHMENT ftpkmvnwi Pap* for TS Paoes &.0. 13 anW 5.0-28of Attachment 2 of RNP-RAI3-0030 Programs and Manuals5.55.5 PBoWns and MA ... ..5.5.9 amDO1SO Mal EfggNM(continued)

C. Provision for SG tube pluggin criteia.

Tubes found by Inservice inspection to contain flaws with a depth equal to or exceeding the following criterta sal be plugged:

47% of the nominal tube wall thickness If the nextinspection inlerval of that tube Is< 12 month and a 2% reduction In theplugging criteria for each 12 month period until the next inspection of the Itube.The following anler tube plugging criteria shall be applied as analternative to the precd citeria:Tube with -h edloed flaws located greater than 18.11 inches belowthe top of the tubhe do not require plugging.

Tubes with service-induced flaws located in the portion of the tube from the top of thetubesheet to 18.11 inches below the top of the tubeshest shall be pluggedupon daetctio.

d. fPvso for S itube inspections.

Periodic SG ue inspections Shall beperfore.

The number and portions of the Iubes Inspected and methodsof inspection shall be performed wth the objectve of detecting flaws of anytype (e.g., volumetric flaws, axial and ia cracks) that may beeiset awon the length of the tube, from the ftu 4*ubhtW weld at thetube Inlet to the tube4otubesheet weld at the tube outlet and that maysatisfy the applicable tube plugg criteria.

The tub4otubesheht wekl isnot part of the tube. In addition to fmeen the requirements of d.1, d.2, andd.3 below, the Inspection scope, inspection

methods, and Inspection Intervals shal be such as to ensure that SQ tube integrity Is maintained until the neod SO Inspection.

A degradation aseasment shall be performed to dOemine the type and location of flews to which the tubes may besusceptible ard, based on this assessment, to determine which inspection methods need to be employed and at what locations.

1. Inspect 100% of the tubes in each SG during the firstefueling outage following SG Installation.
2. After toe first refueling outage following SG installation, inspect eachSO at West every 48 effecti full power monft or at least everyother refueling outae (Whichever results In more *equentinspections).

In additin, the minimum number of tubes inspected ateach scheduled Inspection shall be te number of tubes in at SOsdvided by the number of SG inspection ouages sheduled in eachInspecion period as defined In a, b, and c below. If a degradation aseesIete indicates the potential for a type of degradation to occurat a location not previous Inspected with a technique capable ofdetecting Othi type of degradation at Othi location and that may satisfyrvNO AMA I5Ao.HOMP5.0-13Aftvwxftnent No.

Reportng Requirements 5.65.6 Rbork Rakaum-nta (cotnud5.8.7 Tendon IvMO M FfRema, Notification of a pending sample tendon test, along with detailedacceptice

criteria, shae be submted to the NRC at last two monthprior to the actual testb. A report containing the sample tendon test eveaation shall besubmitted to the NRC within six monft of condkci te test5.8.8 StM eE nom TUS .mscionMA report shall be suWbmitd within 180 days after the initial entry into MODE 4followin completion of an Inspection performed in accordance with theSpecification 5.5.9, Stam Generator (SO) Program.

The report shell incluie:a. The scope of inspectons performed on each $0.b. Degradation mehnssfound.

c. 1u em tchniques utilized for each degradation mechanism.
d. Location, orientation (If linewa),

and measured sizes (If available) ofservice Induced indications.

e. Number of tube plugged during the Inspection outage for eachdegadation mechanism.
f. The number vnd percentage of tubes plugged to date, and the effctivepluggng percentaep In each steam geerwator.
g. The results of condition monitoring, inclufd Ot results of tube pulls anisu test.h. The primary to econdry leakage rate observd In each SG (If It is notpractical to th leakage to an niiulu SG, the entire primary tosecondary leakage should be conservatively assumed to be from one SG)during the cycle preceting the Inspection that Is the subject of the repor.I. The aluMl accident induced leakage rate from the portion of the tubesbelow 18.1 Inchxem fom the top of the tubesheet for the most limitingaccident in the most lmiting SG. In addition, If the calculated accidentinduced lakap rate from the most imitng ascldent is les than 1.87times the maximum operational primary to secondary lakag rate. thereport should describe how it was determined, andH SE Unit No. 25.0-28Amerximent No.
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