ML14119A377

Enclosure 1 to RS-14-034 - Update Transmittal 2 (Annex B) Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic

ML14119A377
Person / Time
Site:	Braidwood
Issue date:	02/13/2014
From:	Buchta A Exelon Generation Co, Stevenson & Associates
To:	Office of Nuclear Reactor Regulation
References
RS-14-034 12Q0108.10-R-001, Rev. 0
Download: ML14119A377 (64)

Text

U.S. Nuclear Regulatory Commission Supplemental Response to 50.54(f) Letter NTTF Recommendation 2.3: Seismic March 31, 2014 ENCLOSURE 1 Updated Transmittal # 2 (Annex B) Seismic Walkdown Report In Response To The 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Braidwood Station, Unit 1, Correspondence No. RS-14-034 (187 Pages)

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,FUKUSH'I MA-NAiMR-EM: TASIK kORC REOMNDTO.3: SEISMI it KkIWOO OOO DTEMIT 2 (ANEB PRAUDWKUD N:UCLEAR OER SU 35100 Suhou ut 53,- Bcvife 19l-is

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Braidwood Station Unit I Correspondence No. RS-14-034 Annex B SEISMIC WALKDOWN REPORT IN RESPONSE TO THE 50.54(f) INFORMATION REQUEST REGARDING FUKUSHIMA NEAR-TERM TASK FORCE RECOMMENDATION 2.3: SEISMIC for the BRAIDWOOD NUCLEAR POWER STATION UNIT I 35100 South Route 53, Braceville, Illinois, 60407 Facility Operating License No. NPF-72 NRC Docket No. STN 50-456 Correspondence No.: RS-12-159 Exeton.

Exelon Generalion Company, LLC (Exelon)

PO Box 805398 Chicago, IL 60880-5398 Prepared by.

Stevenson & Associates 1661 Fedav MDdrve, Suite 150 Mount Prospect IL 60056 Report Number: 1200108.10-R.001, Rev. 0 Pdld Name Preparee:

Mailenm Delaney

Reviewe, Tony Perez Apprier Tony Perez Per Review Tem Leader Lead Responsible Engineer.

Branch Manager Senior Managr Design Engineering:

Corporatec n:

Bruce Lory Thomas Bortolin Ray Belair Phil Roush

.Jefrey S. Clark 11/13F2012

'1111312012 11113/20.12

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Braidwood Station Unit 1 Correspondence No. RS-14-034 Annex B Document

Title:

SEISMIC WALKDOWN REPORT IN RESPONSE TO THE 50.54(f) INFORMATION REQUEST REGARDING FUKUSHIMA NEAR-TERM TASK FORCE RECOMMENDATION 2.3: SEISMIC'for the BRAIDWOOD NUCLEAR POWER STATION UNIT I Document Type: Report Report Number: 12Q0108.10-R-001 Project Name:

NTTF R2.3 Seismic Walkdowns for Exelon - Braidwood Job No.: 12Q0108.10 Client:

Exeton This document has been prepared in accordance with the S&A Quality Assurance Program Manual, Revision 17 and project requirements:

Initial Issue: Revision 0 Prepared by: Marlene Delaney A(

Date: 11/13/2012 Reviewed by: Tony Perez Date: 11/13/2012 Approved by: Tony Perez Date: 11/13/2012

Braidwood Station Unit 1 Correspondehce No. RS-14-034 Annex B Contents List of Tables iii Executive S um m ary.......................................

.................. iv 1

Introduction.............

1.1 Purpose..................

1

1.2 Background

1-1 1.3 Plant Overview.....

I...............

1-1 1.4 A p p ro ach.........

..... 1-2 1.5 Conclusion

................... 1-2 2.

Seism ic Licen ig

.Ba is........................

............................................. 2-1 2.1 O verview ".............................

.......... 2-1 2.2 Safe Shutdown, Earthqake.

(S.E).....

2.3 De:signutow aSfSeismic

.CategoryI S§S

.... 2-1 3 Pesrsýonnel,.Qualificý.iio,6 3-1

31. Overview........................

.3.

O ver vin e w., ~ i~ C...

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3.2 W alkdow*

n Personnl 3.-.......1.........

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32. Stvenson Associat esoe.i.

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9 apl~f Requir.ed Itemsfori the Five. Saet unction~s 4-1 4....:.SW W. L.:

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owns:and Area.Walk.......s.5..

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3-Coifg~uration Verification.......

' * *15 ::I

• i:

• 5 :.2 a dver1seeism

-Sp. i -i.tera tii,.

ns.............

Braidwood Station Unit 1 Correspondencm No. RSA14-034 Annex B 5.2.5 Other Adverse Seism ic Conditions.....................................

,......................... 5-4 5.2.6 Conditions Identified during Seismic Walkdowns.......................................

5-4 5.3 Area Walk-Bys............................

5-4 5.3.1 Seismically-Induced Flooding/Spray Interactions 5-5 5.3.2 Seismically-Induced Fire Interactions..

....................................... 5-6 5.3.3 Conditions Identified during Area Walk-bys......................

5-6 "s

• F....

5.4 Supplemental Information on electricalcabinet internal inspections.......... 5,6 Licensing Basis Evaluations......................................

6-1 IPEEE Vulnerabilities Resolution Report.......................................

7-1 Peer Review..............

.... 8-1 References.................

.......... 1 6

7 8

9 ApPendices A

B.B

..*.G Project Personnel Resumes and SWE Certificates............

Al1..

.~~~iiae

.A.1 Equipm ent Lists.B-.......................................

I...............

................. 04l Seismic Walkdo*n Checklists(ý Wps)

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Per e e R.po................

F4 IP E

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Braidwood Station Unit 1 Correspondence No. RS-14-034 Annex B List of Tables Table. 2-1. List of Codes, Standards, and Specifications.........

2-3 Table 3-1. Personnel R6les.............................................

3-1 Table 5-1. Anchorage Configuration Confirmation...............................

5-3 Table 5-2. Conditions Identified during Seismic Walkdowns........................................

5-8 Table 5-3. Conditions Identified during Area Walk-Bys 59 Table B-i. Base List 1...........

B-3 Table B-2. Base, List 2...

B-22 Table B*3. SW EL I..................

B '24 Table B-4.- SWEL 2............ *.......

B-31 Table C-1. 'Summaryof Seismic Walkdown Checklists

....... C2 Table D.-.

Summa~ryof:Area Walk-By Checkl*ists D-72

e.

e,

.n LstE-able'E-1. -Inacessible and Deferre quip,.ment List.....

E-2

.ctio List...

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i. nSpecn. !iiE" Table

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Braidwood Station Unit 1 Correspondence No. RS-14-034 Annex B Executive Summary The purpose of this report is to provide information as requested by the Nuclear

.Regulatory Commission (NRC) in its March 01

.*.1 2etteir.issiued" u

to "al power reactor licensees and holders of construction permits in-abtiye*,or.deferred.stdtus:-,(Ref. 6) In particular, this report prid es information requestedt6" aiddreSs Einclosure3, Recommendation 2.3:I Sesmic,.of the March 12, 2012 Retter:.Q(Ref]6)

Following the accident at the Fukushima Dai-ichi nuclear powe*:plant.Iresulting from the March i1 '2011l G'eat T hokk Earthquake and 6

ets mi~the.NR*'

ohou Erthua.:,Onq:subsequent tsuinamie established the NearTerm Task F.rce(e 16 ComrissiOn.direction The

§t8

.6ýýý'ý8ý66-(NiTTF),in-tsp'risýe o -6Th NTTF issued a.report.- Re)oý,co edactjofols'iEh.bh.cing;Reac'tRor Saf*-leiyj the.21S Ce~ntury* -TheNear`

Term :Task !Fo~rcd:e vie of Inghjtsi *f~rrthe Feaushirna WDlichi Acc'ident,thaitimade 'a series~orrecommeidajtionssoe o which wee obe ctied upon'.withou uý.'inncess'cry,delay." (Ref...1 nMrh12 202 h'Rise letter.to6 all power re

actor liCe6se6d 10"accoance with WCFR5o(f). The5: 50.54(f).

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Braidwood Station Unit 1 Correspondence No. RS-14-034 Annex B Seismic Licensing Basis The Seismic Licensing Basis is briefly described in Section 2 of this report. The maximum horizontal'and vertical ground accelerations at thefoundation level are 20% of gravity-forithie safe. shutdown earthquake (SSE). (Ref. 2 section 3.7.1.1)

Personnel Qualifications" SPers.o.n.nel qalifiai"ns.are discussed in Section 3 of this-report. The personnel who performed the-.keytit.Vies -required to fulfill the objectives and requirements:of lthe 50.54(f).let6r are qua'.li'fifed and ýtrained.as re.quired in the'EPRlguidance document.

(Ref..1) Th6sep:eirso nnel are respbnsible.,for:

.Selecti ng the.SSCs that should be placed.on the Seismic Walkdown Equipment List (SWEL),

o..

Performing",te Seismic Walkdowns and Area Walk-Bys,

.Pfporming the. sism'ic licensing.basis evaluations, as applicable,

. Identifying t*helist*ofuplarit-specificvulnerabilities identified durihg the IPEEE pro*ram and describingthe acptions taien to erniriiate or reduce them, S-Performingihe peer reviews ISelection of SSCs Selectionbof SSisi's disocuýssedin ;Section.:4:of this. report. The-process ids~J toý 1 0.

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a., -;of qi.'m h i t( _)i the itemsthat'.r.re in l.

cd **tin"t-everall Seismic:WalIkdI*n*'iuiEment iist WEL) is desc*ibedi~n*.adeta iiin, tl~e;EPRu'guidace.p document,.Section 3: Selection of !SSss(Ref.

.).:.T.he;WE-wo groupsbf items, wh'ch.are:described atehigb'l thIe-foll6vWih

~ bti&'

sampil of Required Items. for.,the Fv aeyFntos-SE Scr6en #1 narrowed th.scopeof.8SCsin the plant to, tose; that are d'esignedýt*

iserhic': Category I reqýirmnsb6u6te ~

a sejsrnic licensing ba~sis.

S6r6en #2 narrowevid the

'~opf

%S8s by sel'ecting. only those that do'not regularly undergoinspectonsic-onfirm.that their. confiouration continues to be con~istn wth I6,.p nt licensin@ basis7 S~ren

1. ~n'aro-d the' "coe f SS0s included on :SWEL. 1 dssonly-th~os

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Braidwood Station Unit I Correspondence No. RS-14-034 Annex B Equipment enhanced due to vulnerabilities identified during the IPEEE program Spent Fuel Pool Related Items -SWEL 2 SCreen #1 and'Screen #2 were used to Inarr6w the scope of spent fuel pool related SSCs to' those thatnhave~a seismic licirn~sing ba'sis:aýnd those that are appropriate for an equipment *wva(kl*wn process. Scr.een'#3was a proces*s intended to result in SWEL 2 that suffi'ciedntly. ropresents'.the -brroadr;p.opulatiin of-spent fuel pool seismic Categoqry 'equipmpnt'and,ýsystems to meet jhe objectives of the 5Q054(f letter, and included the fillowin.gf sampie seiectibn attribuites:

• Avariety6ftYpe'sfsystems o z e

Major*new orreplacement-e.quipment

• Ayarietv.oftypes of equipment SA'Variety6f *ei.nvironments Screen #4 iddr*eiified it6msi.of the.- spent-fuel pool that{c doldpotpent!ialy 'ca!se a rapid

• ri...pteppoql 'evei'if' h:t sareýrpot Seismic Cate&6:

L Rapi rain-downi S'def.ined 'aswul eringwiofithe

.!IieVtl"oa the top of the f..e.. assembli s:within 72 huisft6-r'he-i uth. -Anytes idenrtified as ha~vinglig tepteiaforpdl dyainng Te~s~t I'"

pool were ito bb -dde-d tb :SWEL 2.

For.Braid.wood Unit:1, thVSEL is -comprised of

• SWE L 1 res. ultedA with-100. items forw\\a~lkdown.

• SWEL.2're-sulte-d wth'2Rtms'for walkown..

NNoitems-ass8odiated:dwith s.e.t'.fue.-.pool rapid drain-downare c luded on SWEL Seismic.Walkdowns: n ara*W*E

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Braidwood Station Unit I Correspondence No. RS-14-034 Annex B 9

Significantly degraded equipment in the area Potential seismic interaction 0

A yisual assessment (from.thefloor) of cable/conduit raceways and HVAC ducting,(e.g., condition of1suppo.rts or fill conditions of cable trays)

Potential adverse interactions that could cause flooding/spray and-fire in the area erOther housekeeping items, including temporary installations

.b t e o f,.

.n t h e The seismic Walkdownteaminspected 1605 of the 121.Components On the SWEL.

(comprised of SWEL 1 and SW*L 2). Walkdowns for 16 components were deferred due to accessibility -issues such as being located"in containment orenergized equipcmet.

The 16 remaining items will be inspectedduing aunit outage.or another time when the

' equipment iaccbssible, as deqiýied, Anchoragoeverificationwas required.f~r a minimm u

.of31...*6p6onent.s:(,.

(Re

.1) A-tot.i of 42..:**hoage.co.nfig*ir*

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confiried tbe irisfaiilled in. accordance -with the estation doumentatidn"and an additional 6 anc*or configurations wil be confirmed as the 16.deferred items ar qinspected.

Following the. compol.tion. bf. theiohlinid.eseismic waikdo6wns,: the, ind ustry,was m.ade aware that the NRCstaff.h~d clarified a posiironi o opening-le.tricaca inet(.tinrbt

'for

othe a,.ýdverse seisme.iic cQn..i.ion;s, S u6pýlemental inspections of 28 el. nrical:caine'tsare planned and will bieacdlmop*Jet asrequired during a uqniT Qutage or ho6th e w6en.

theb eqdiprhentbl'e cpm....e..sq acee6ssible*.. Thue list-of:., electricala nb'nets aongt.the"-

Mile[tbne coipletion0'ihe!due iseprovid d-in T*.*IE-2.% "

with th During the s.eis*micwalkdowns*.att*the Braidwood'Unit.i twenty-.one (21) Issue Reports

.(iRs)Were issue'.

ýA~fter evaluti.*i.through the CARPit was determined-'Mth***on6ef the

.issueseniiedin.the.Rs we're,. a&.erse.sei.ric.conditions.

S6is'mricLi6ensi*hq Basis, Eva uiations The!.PRIguidance.document,.S6etion 5: Seismic 1icensing Basis Evaluatidn poides a dtaile i

ddtcumet seismice--o cetsi ic g

sis evaluations

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i g"-

h. '=..

"e.,.",7 "ry

t

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~ ~ ~ ~ ~ ~ o

• .orm:..

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.'.tw--.'i".

e... :.,*

sigri:

ig

.li*cen.p:'..,"

i:

n

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e.'"

A:'.

, -c.

r.r,-

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• .'.*-*, "..*':.-.:'*..\\.

• • ,.-...f.,,..h'.t*i fi..*

i:...'.j d *,, *.:"d'ri.;g.th.::" lk i.'e".

d,.

,.f..li.,t

.::"': ",% ;s.nl.".i-c' W:-

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i,* : ::

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n t...o th b C A:.*`*`:.*

`:.t...*;`,*. * : `.. `.*;*:;*.`:.`.

v `*:.**.,'.

i * : *..*:,

' '... "*:,:"::;*:.:*'::i *.b "[*.:, *..t..:..:.`.:`.;..=*,*.::***

`.:,`*.:.1..:..*.*4`*

• .**.`

Braidwood Station Unit 1 Correspondence No. RS-14-034 Annex B documented within the IR. Tables 52.anld 5-3 in the report provide the IR, a summary of the condition, and the action completion status.

IPEEE EVulnerabilities IPEEE vulnerabilities:are addressed in Section 7and Appendix G of-this report. No vulnerabilietis were identified 'as '-result oQftthe effort that addressed theIndividual Plant Ekamrination o. f EoxteiralE.vents:'(lPEEE), (Re). 3 and 5) However, plant improvements weroeidentifiebdin section 7-of Rere*rinbe*3.

Table G-1 provid es the list of p* n.t improvemen.ts, the IPEiEE oropnsd resolution, the actual resolution and resolutiondate.

Peer*.Reviews Axliper reviewteam consistingof at least~two individuals was assembled and peer revie*es weepertfrmed in acc'*rdice with section 6: PeerReviews of the EPRI Oel gpo~e~i*r ew processincluded thefoillowing a6tiVyi:ite Review of.thel se§bcti6n`- f SSts.in cluded fobn the -SWEL Reviewi of. aqw ample of the checklists. preopared for the Seismic Walkdowns and A~rea:M sak-Rev.ibewofliQe*nsing b.asis evaluatioans,- as app'licable 43

'Review of thde deisinsfdr en*teing the potentially adverse conditions into the CAP4pro~deS9..

Review of Ite submittal:repo.r Providd*da.. stt rpimpry rep6rtbf:the p 6eer review* process.inthe. submittal repbort...

.secdtion ";:8 of tihs re!6 n!*P"ns

'ny of he

.ever.

The. Peer*oRevyiew.

determbind a~~h' 66bjectivesedbtt'"b"t

"'and" "b e

tsohf he 50'54(f) -letter are "met. Furthe'r, it

'w"si"conci&~de b'y. "-h er ieview~* that th*e eff orscorpleted'and documyeted vwithi Vthirpor are,in accordan e.1ith the EPRIguidanedocument...

Sumnmary niruiay, seism!ibcwal*kd*ownq havb.eenpoe ath Braidod Generating..*

,t{atio

i;Ei2*it';*i inih a rdaiq dwth theel d s d

't

'd firi odoaos resudlt'bf-'

l potentially degraded, non"doiig or unnlye

,odtih "d~

~

a rel of te es i akd~wshy 44oietee the drr~octivdctid'programn:

it'e4-'

4-4' o e"identified.6condiions are plete ando bcumented withinthe cAP L

E i7*lu atloils.--of.,tl den ied*i'j'jd"-!*'-=-,

d`,.:t;,"*v

".;Thes

`t-lutin de.~

th 'SeMis'mic Wlkdowns iesiultedý With bnO adersn n...sim..satal.tio Ad ther adverse.,

'~--...

a: dveiseols>;o,

• ,seilsim-i in'te*6:*r.ad n*bn

'o:

er qpqchoragecondi ions; h

'.isriii'd:"

orditionsass'b'..

ci.t...d. m!ih items on tSilyWatk-B ys eule itho ad verse,seismiicqonditions -associated with, othe ~Ss Oce~dirth vicdiihit of Ile~

SWELitem(%

'4..

'4 4 Thd: Seismic.V Iakd own6s i den ti fi d 2 1: mio codtiosdhe*t~ntbmn

• : ~~~~~~~~.....

.,:...,....:<i,.".;....-,.,....../..:::...

3

..donditiost Siismi W,

" *a l*ld"n.ieniieroe ided, nJd to-he:6,m..

d:.

I nnlzd condition ha reurd eithay'rhI -- ediat& or fbloW-on~action-N inndo

neWly` identife prtecinor.ii~in'etrshv resute-d f th'enfffo-fts tb adresthe-50 4()ltter d

e-

ýollow on activitie's requireid to *cormplete th'e ekfforts -toalddre-ss E'nclosure 3,ofthe4'

.,..-...et...include.in'sp*

ection. of.f 6items deferred du*

-ti n c. ssibilnaity as-ii@ it r:

.4i,,,

4";:.7:i:

.7-.,*..':i/.;'.:,:"

4.

"--4"*" *> "

i

. :;"

4...........'........

,-4..,........

4,4 4'4 4

.'.c " - 4,

z <,

4.

Braidwood Station Unit 1 Correspondence No. RS-14-034 Annex B supplemental inspections of 28 electrical cabinets. Area Walk-Bys will be Completed, as requited, during these follow-on activities..

All IPEEE plant improvements and associated actions:are complete.

To addre'ss items deferred due to. inaccessibility and theýsupplemental inspections of electricalcabinets, listed in tables E*I and E-2, fdoiow-on Seism'iC W.WIkdowns and.

SUppliementaelnternal Inspec-tio'ns* wee'cnduct*d:durin-g"the last quarter-of20*162. :No degraded, nohconfrming or unanaly.zedcdnditi ns that r*iquired either immediateor f011o6-on actions were -identified:'.

Annex A to this report provides:

1)Additional informatio obtind firorn thefollow-on inspectons. The. itemns infpected

_ p 2)Sttus'update ntecniini~~tfld~rn h

r viou wlkdowns 666,wAlk-

.1~~~

diin durti in the folp-crir-'ý.inspe'ctions a4re ys, an anyýd*ditinilcond itions.identiie -

listed on.TableA-2 and'A5 Follow;-on

activities,,-in add ition. to.:those :documenti feas 4.a p

-artof A-nne'xA, a'e requ6ired to address `CommitmentNo's, 1 and:2:bff nc os~ure, 3 fEx'eloh I tieV.t'NC"10 day4 aes,, nstito i'NRC

• Re;s*u f InfbhiationPij.urs*uant ito OC 44 5.5(f

g-

.rdingas Force:tl'ReNea,,b

'the.Se sý,.*smpec.t o'ebf Rbcom"end n2.3 Q-f tbiW

.*iT-err s*Ei

'h Fr e

o."6V "

I

-iht' nthFukush i-ihi Accident," da*tedNo"v12,i1

. b-r 2,02...59).

The§'foll6W-n actiVitieswl include dociý,ppqt t'o~ 'of'he seismcwarn

~

i~o f6aac6sSinbl d

rred abihble E-1 of fourteen 14l essi e-tha

'thelhiritil ýrepo-ftrt (tW"iv'- (2) apre 'dtd

'~ -

suidna J'int~ii'alinsecg i

Iih (8),6etIc

~frit jist6-dih Tale~ E_2'ý 6f the initi'al repiort (En.oue ft" aoeEeg Itr~'leN 4 FS12 4~5).T~s

."i.:.:...*"...

tnp,cto~

ke orplte,-d 'b~jthe coriirriif'rniit date -of Fa6ll 26, 3 7(I ARi 7)' 2rhtse. t ems spec onsensreofq pi aelsein-1an E

2 of inxA, asnd w.il*bedocu rip'ectioris in Tab egs 4E-andE-,ae b' npletd b (Fajl,4.201 3).

.*4 4

Annex, B to this repomLprvides d4; 3)Adiditional.J infoMation obtain'oed from ý,th folowon ins h§cipn~isted in Tables'AE-1 and....o. An:

A (nlsr fE eo etrt h

.RC..........4

). Them.

44.2 14)4e

S a e:, on: -

,~ nq § n.,n,

Th.re.arenoremaining

~~.followr.on activitiesre*qiu Iroc tipe

016teI, efto.rts to address Cmitment"s 1 & ojEcoue3oExonltrtoheNRC (ýSA-2-159y 2:*

.e4A:

i.4oL,*b

NR

.4.

4..

.4.

.4.t' ixhcl

• 4.

4.

..4 ritiff tt "I::i*.

&., 2ýav

~te~an re,'c`.-u ejLp

/:::x, Yo:;::

M d Ih, Ahhbx.B-

4.

4*

of E

'oh444,ý,

4 4

.4

>"J.

.44 "

4 4

4:-'

• -44

-4 4.- 4.4 4 44 4'

,!! ii

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• 4,

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.'-..4. ".=..

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4"4' 4'*

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4 4 4 4

4444

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• .i

4.

4,

4. 4 44' 4 4:*

.4*:*

4..::*..*}*:.

Braidwood Station Unit I Correspondence No. RS-14-034 Annex B I

Introduction-1.1 PURPOSE" The purpo se of this report is to provide information as requested by the Nuclear Regulatory.Commission (N RC)in its March 12, 2012 letter issued to all power reactor licen sees and h7olde.,rs of construction. permits in active or deferred status. (Ref. 6) In SparicUiar,"this report.proyvides informa tion requested to address Enclsosure 3, SRecommendation 2.3:Seismiciofthe-Mar*l* 12,.:2012 letter. (Ref..6)

1.2 BACKGROUND

Following 7the accideht at the Fuku~shirha. Dai-ichi nuclear power plant resulting from the March:161, 1,,ýGreatToou

'k lent-tsunamii theNR Mc 20 aEarhh-quakeand subseq u

establishedltheiNea r T*ermWTask Force.(NTF)inres ponse tCommissiorn-dire'dtion. The NfTTF issued a report-ecommrnedatios. for Enhanbh'gReact&r a*Sety in the 2.1s C* htur'y Thee Neanr-TertiTask.Force R

.i2f, 3A.sight§ 'frothe usi.,.h"Ldn e sahi id ii nh..

titset re"EI

• 5 8.[i::/' i :" "o~

. '.n:"6...

S,..-,..:*..P

egM*;

id-atee.--jiii*,*.0.1..2;.::h**...-........................................

Ac~dnttht r~dea eies of reomedains soeo hidh weret to qbeadt nhes ilowithout uhn-cas.-ry.d)y.*""(Ref.. 1).

March;1 2 012 theN R. i.suea.

letter to all poweý.r r!eactdr-i'censeesýin ac'd

'yih A 1,ý b.54(f) letter"requbsts infor

.a.i.b t oassur eta ceri.

repo-rrrirai are addressed b~ llUq..

ucear power plns Rf. )Te5.4f tr~requ~rQ§,s;i atLalUS ntdeicapwrpat o efr sg!is~iqi wIkdowns, ooderitif Y.a a~res,,,

nors"

afo o

vn..

ar"ddo ve rify t hi ci:.rtnt is

-'.";.::,..*,;.*,ng

• "-,.qf q a j !y e

.:.% /_.y.

with;-;e'd~t esidb~hsn ak This reportdocdniripa, the -seismic. w~al~kdo~wns.

Me.rn&~ Brpi. wod ti ni 1 P6e in p rt to tI

,1E.V--'

.d..'"IS rating "r'.

- iA on'.

j.-

.resp...e.

leterissue`d bythe NRC T-".Nuclea Er Isu(

)supp.rted, by" in erated,..W,,

th' NRC t sdn for.

d in s eiic kdows as required in' te lis.ic.

(Ref)

Te gd pppirbcdue 9pr~ d'by ;NEI anhd enidosd b.y, the NRC*

W~lkdon Guiance or Resýolution fFusimNa-$rnTkFoc R~o..nato 23.

tesmp datdJun&2012 h efi ith, fq ~

e oa thed "EPRI gupid.'ah-e 4dcriet- (6.

1) j,:EXOI6n'BraidWoodia ut:~dti

.Q d

'is 90 dance as the I~ssfrlee~icwakon nd.i.eor Rf1

1. PAtOVERVIEW Thei Braid~kobd n uclear. pow~er-pahcoitsftw nearl ietia,.,

g~e!eqratq

~s n tdo prsu

'terrdos(

R (NSS'S) '6fidl 4Ur~ine~genrci6ra'Jto~

nish"db lii'~r.

en fre iolm post tesod con ret istrucitio n WihK a ca0rbon Ite with&

"Oitirit~r6e6drn p:Drovidedtot` cnta *t*he "eer ased n a ýmajor accidepntw ntd'for "pressure.

, "...',.i.":-.

'::U-.

- p-2

".* "",i.

. 2 '..

...' *.. ? :;. -, :.

,= "..:,.

.., -.. *.,,j-:*:.' :,"

:...- ;:*'-'.; -y *l '. "-,

• * " ". " " m.. /- '"*.

4*,.,.,;-.

j,"

Braidwood Station Unit 1 Correspondence No. RS-14-034 Annex B suppression" devices. Sargent & Lundy was responsible for containment design. (Ref. 2 section 1.1).

The Braidwood Station is located in northeasternllinois, nearthe town of.Braidwood and near the *a6nakee River Cool..in bgi for tdhe.

s ed

• ir a n"ma e cooling pond of approximately 2500 acbros e

o-nstrubcedoera previosy strip-mined area. 'Essential service cooling is probvided :byý a 99-acr*

aujiliary-CcoOlingp'nd which is integral.with the.main pond. The f6UeI IQ6ding*gdates" for, the.-t w units were October 1986 and December 1987. fo;r Units 1 and2, :respe.ctively. The '.co*resppndingdaetbs.for commercial operation were. July !.988 andOctober....1988..(Ref. 2 secti*n 1.1) 1.4 APPROACH.

The EPRI guidaince ddcument is used kforthe Braidwood.Generating:S~tation. Unit 1 engineeringwalkdowris and evaluationSddesribed,.in th'is" re*p*

natIn d accorda.e with Refer~.n~c1 the 'foll0ing.topicsare d*.dd*Sed inithe,subsequent sections 'of his report:.

S.ismic'licensing"BPsis Personnel Qualifications

• :.Sel~ectin;6fnsSs"-

S.Seismic Waikdown and Areawalk.-By's.

6ie-nsing Basis Evaluations.

• IPEEE Vulnerabilities'Resolution Report

• Per Review 1.5 CoNcLUsiONi

S"eisric.Rdio.ws" hay-oee rr ea..t.e raidWo6d Generating Station Uniti.n accord anc.,e th Cddhe NRC dotial ly. egr..ad ond".inrn{i*dn R en.ifife.

a lt oftheseismic &walkd own's Janon ormnsgi detrm.ne,

-"yd:66d!

-" d-haveb~e~ rd ifo tecrrective ýactiono"ri'

.......~~ ~

~~~~~~~~..........

Sisi.*....*,iib..................s~e~t*.i,.i..

J;it~**~

• Bs

~Eval1ubtions,bf the id~tifie-d.c6nditin ar coplt an dounn6 it~

A

.:.. * *.T.hese r.

ai;i~wt6ion**

d*eterh~if.

oi~iincteeisr'nic~aldow.hs reutdwthe rSi6. loatdv

,;te:::'*'"?::;"

rs**;"':":'"-

resulted with no~ adverse seimi Acniin asoit dwith o ither SS hihs lo

!CAt-th vc n I

t..he.E i m The~Sisic aldonsidetiie 2 minor codiionsOther thano Othese mirdýi r ailo ragdition th Siosmia; dws;dntfe no deaddncofrigr un lye cni ion tat requirýd t

eithert imeite orfllwo ato NYldo address thn50 54(f) etter.

5954(

Iý rinlue ainpcino "tesdfrd dui ewit sibdppi~nnfhsp;-th:ecions Wa~kof 28

,i elec -fria caint

-e,\\Aad d

Bs~,l fdnorm nplt6Aa r~e~diied,'du!q.i these folo on.

p.tik'iti d,

h r.,i Adbt r

• ,o ic uhh4ydddp,_

a Aur et.1 6

bi, rA

.A.*.:,,..?..

'1 A' A'.A A"-

'.A' A "

':A,=..A A A A

,,A.'..jA' a'Bys~

wtllbe

• i50,.,a5....

.,.b.:......

. '.°..i.:!

/ :.-.:.:: "..,'-:,:;iii::'

iiiiiii:i i:.*!-*:;;;~ i.:,i

"

:.b,:.e."......

y:.."

b d*

b*,

.,".... "."t..

-d r

l6WiI 7; - :... <

J:.-,:r-equi.

.

.i the e r

( : to es cl

,:.:i,..,

5

()

et r i.n..'.,...ld.,

e',h-.

!,..on

.:1-.,id;ý~

~ r~

'-,d '

6..§.,,

i l,.:

i...*:'~.*;ty.

,:.qn.

.W"i

,q t

...... :*ý.......,

,- ý..

.. t-a.s....*2..:,..*

• • "" :qQ:

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• .""iect.i':.:on

L.{,:,:.

s:,:...;,*

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e":

*..i,*'.

"* ;. * *brin g

,es.=..

,* "*.'* ' _m...

:=-..

• ,t,:u'%,*' *,t : :'i.

ýe q y

.",-:.,.*::"*2";P;'.,,,:

a"dtf*

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s.[.-

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Braidwood Station Unit 1 Correspondence No. RS-14-034 Annex B 2

Seismic Licensing B.asis 2.1 OVERVIEW This section of the report summarizes the seismic licensing basis for the Braidwood Generating St'ation Unit 1 and Unit 2. The safe shutdown earthquake and a summary of the codes, standards, and methods used in the design of Seismic Category I S.SCs are p pr esented. This.section does not. establish or change thle seismic licensing basis of the facility and is intended to provide a fundamental understanding of the seisnjic licensing basis bf the facility.

2.2 SAýFE SHUTDoWN EARTHQUAKE (SSE)

The maximum horizontal and 'vertical ground accelerations at the foundation level are 20%"6f gravity for the safe shutdown earthquake (SSE). (Ref, 2 section 3.7.1.1)'

2.3 DESI'GN,0OF SEISMIC CATEGORY I SSCs

...A full description 6f the Safe Shutdown EarthqUake.along with the codes, standards, and met*od-s uS.6d in the *design*.ofthe Se".ismic Catie6ry 1 SSqs for rr.mee[ting the s:eismic licensig bass requiuremen~ts is provided in the followingg Bgaidwood' Station UFSR sedtidns:

• .3.2" Cassification of Structures, Components, and'Systems.

• 3.7 Seisriic De.ig.

Attachi.men*t 3.7A ýAReevaluation and Validation.of. the.,Byron/BraidW6od Seismic.

D.ýesign Basis Deign fCtepy Structures-

• 3.9 Mechanical SýSytems andQCmoet

• .10 Sesi QualificAti~nbhf.Seismic CAtgr I Insrm ntaio

.dEl

.i~

EquipMent,32 -Claissifibcation '6f Stuctipei nents',j hdýS 6rsv~

,-:i~ k-;:!

o n.s**iý

• .**stiýtsis;::

":~b;

ýunzdiers: hesi smic Th'~

FA etin hudb referred J,

ufi6fsingf basis Dsi SumaryofSeismic Desia Test epn ed spcra-whic are defined at the' gr d su J~,ei;,r.pe iirSectldin

.,espon.e rpe.ca

.tirýie. his*toresy*e n

Br~dwod it Fundation eve!

nrae

• '.,~

,,,.,o,,,,-

e

-ov I Ioh I"YIP.........

qu p

..q.sr.

c_ i

... :.......i n a i,,.:.:

"~ ~

(vi~ or

' h:: td f"" v :i. :;.or::i.0... '..'.. si"-:*

'eb m c

~~~~~~~~~~~~p U.: 0",'Pa rt:-

,'*!"'-:.i":

Braidwood Station Unit 1 Correspondence No. RS-14-034 Annex B earthquake (OBE). The comparisons between the free field seismic design:motion

• applied at thelsurface anrathe corresponding foundation (rock) spectra for 2%, 3%, 4%,

5%, and 7%Mdamping ratios are shown in UFSAR Figures 3.7-21. through 3.7-40.for the Braidv' ood site. (Ref. -2section3.7.1.1)

.Duing the.review of.the-FSAR for anOperating License, the Byron/Braidwood seismic design was reevaluated using,the.Regulatory Guideb1.60 spectra without the application of a.deconvo6ution* *a.iysis.*

UFSARAtachmeýnt 3.7A contains the specific NRIc questions/res6poInss on seis.micdesign; These questions"an-d responses document the hi Strica evolution of certain~a§c s*cof thelýByroniBra*iw.od 'seisric design.[=SAR Attach mehnt '3 *7A*also ýprid s 6th~e;dtais` a reuJlts: f1 tis reevaiu"aion. it is" concluded thtj"thepres§ent. seismic de§"*i.ýdf.2Byron/Brdidi*oo0d is'conseryative. Based On -the ree~v.alu.ation: described in UF.SR:At.A hent**.

ethe Byron/Braidwood seismic design basi isis-acceptabiie :anrd wilolitheriefore be used forall future.seismic evaluations.

• (Ref. 2sec io'n 3.7;1:-)

Seismic Class I stru:ctuures.are:

de gnedfo" seisinic.fo rces cailculated from, the

,entio6n*.dsp.qtra is!i*ng a. :r*e.spoise spectrum.re-jiepd of qr~aIysis.

he. diredtional compon.

rthq emotions (w 0hrizontal dine. ctiýoen':w!thi..verTica dmr6ction)om Aythe squ are-root-sumohe-squae

.(SRiS) 'mr*t*bI.

Tr evaluation76f S*eis*icCla.s* Iqomponent'sln Stfucture Response

• sp.ect~ra..(SR i..aare u-e'd. -'Fo-r;iho:raiz-eontaliois, ISRSare gen*

euiri an.iprbt' a..ý

.ati60ý m'histor

'b (ise h';t of mthematical: odelg.-.hat re resent the pianrit.igr'sriobUrs

}(ReX..3)

To dti Othe foudatior.(n, the-soil. rock ýprbfile :above the t-

"h J*:

t" b

found ation was modeled as a c

t he grou nd.,suifacqspe ectra-consis ent timethieoriesereap!pj*:i-e bt ih'ground su 6, and the-fo6hdationlevel' notionIwas bt'in,'d-us~igthe.. A.K.E:progra m.a.m Fr.allof. te strCuctur606-6ndd opbr r~dk Ufudt6nebil-mtioni was cise d ireodtlv-t6.bixcit6 the fiedbaemod

.u...rvo.:C6,des.adn--Stindrds 44-72 1

4 77 Th.e information presentg6d bilo~w ',has be66n extract8 from bthe section.8 o';f."eferen 66

-2.' Tis -sectioh~jnfsummrizes the codes spcfctoS,~

st'da of pratie,-ahdtother

.. 'accep~ppicbl~i thnt dhs,,,iaeee, esign and conistructionoi h olwn

,Containment the appicable codes -standairdsý and specifictiohsfor the' cotimna e 1 hogh' 23 ih'nTal21beo.

• Containmentý Internal Structures allof-the items listed' inl~ 2-1Jblw r

&p~liakl for hecon ftaimet internal struc-tures.-

• • SfeltyýRelatedd Stridct~i&d.Qutside-: "fCbrntaint

-1 :i fjthe 'itemisted in*

P7 7I,..

-Q,;V F:A Fordt-~

freinicaedyl~t~~u~' te applic.able't cdes; stan'da-rds, j~b~ific~tons are 1though 1

'9 an -1T ghr.~23 inJ~e2-blw

-"i L77 *L t":"* f:*

/

.q77

• i 7

'7-!

...2

.

74..

4

,,7 7

.7

.4.'

.7"*..-

p are-,

E ns d

• e

" - ".. " ",e.n e'..

r

Braidwood Station Unit I Correspondence No. RS-14-034 Annex B Table 2-1. List of Standards, Codes, and Specifications UFSAR Table.3.8-2 -List of S 6~cifications., Codes. and Standards T a l

3.-

2 -

Lis of

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Braidwood Station Unit 1 Correspondence No. RS-14-034 Annex B UFSAR Thhle 3~ List nf ~nPc~r~ti6n~ God~ rind

~nrl~rc~

Specification.

Specificatidn or Reference

.standard Title Nurmber

. Designation 21 ANSI. N45.2:5 ProPosed Suppl e.menntary.Q.A.: Requirements for Install tionInS pection and Testing of Structural" Concrete*a*nd Structu ralS.teel. D uring Construction

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Cd.e.Req kir.ements for Nucleair Safety Re ated

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24 A1S.Specfidatiifdrdesign S.of -

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Braidwood Station Unit 1 Correspondence.No. RS-14-034 Annex B 3

Personnel QualificatiOns 3.1 OVERVIEW This section opfthe report identifies the personnel that participated in the NTTF 2.3 Seismic Walkdown efforts?. A descrip'titon.ofthe:i esponrsibiiities of eaci Seismic Walkdo\\Vn participant's role(s) is. pr6vide*d in Section2 o2-the EPRI guidance document.

(Ref. 1) ý,Resumes included in Appen'dx-A.provide d.detaif on each per*son's qualifications for his or her rote.,

3.2 YWALKDOWN PERSONNEL Tabl*e3-1 below summarizes.thetnames-.-nd. correspofding.roles of personnel who participated in the NTTF 2.3.,.Seismic Walkdowneffort.

Tale".3-1.'Personnel Roles,.:

Equipment-i ic Licensg E

r Na e.

to

.aPlant W. lk...n Bai.

IPEE n0nee ra Review~n e

r PRý:ewer Operations.ngineer

.Reiewer Reviewer A. erez X

T.K..R.

PGzaX X.

I oIL~y

-,X D.

W(x~di X

T.B r~

i ia(-Exe."l

÷" ":"

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Braidwood Station Unit 1 Correspondence No. RS-14-034 Annex B 3.2.1 Stevenson &.Associates Personnel The following provides a synopsis of each individual's background and experiences.

AntonioPerez,.P.E.: Mr. Perez is a Senior Engineer III and serves as the General Man gri og f -the.S&A Hudson, WI office. He'earned his Bachelor.of Science degree in Mechanic.a.Engireering at Michigah Technological UnniverSity and isla lice-rsed Professional Engineer in, the' states of Wisconsin and Minnesota. :Mr. Perez has: over 15 years Of experiencein projbt management,- projectringineeriig, equipoment design, and mechaniical."systems 'design andl has served in the nuclear powyer industry for over 1:

years:., He has.texrssi.e experience. in Program and Design Engineering and has" held positiorns sucha S: MOV Engineer; Rkesponsibl Design Engineer, Design Engineering Supervisor-and 9STA Tirainee in the nuclear rpo.wer indcustry. Mr. Perez has successfully comeed".the Near.Term" Ta..s."k Force.T Recommendation:2.3' -. P6nt*'Seismic Wa]kdowns Training-ourse.

Kim HFull-MrH..ull is a'-Senior.Engine~er Ill!i.n1 fhe.S&A Hudson, WI office. He earneld his Mst~e~r*~fSdienc~edegree.;in_,**ch.iciaEngineeriridtMijbchigan State Univier]ty-.

r.

Hu!Ibhtasbver.30 yayearsof; ex':p'erienc6e:in the*.nucla Ci4*pýndqusiir an*

d has!held.,

pbsjii'on s-uch as Shift T i-Pca Ad*ys0r; rncipa!Erfg ir ieer,.Seniors Uc.o. -and Desi~ Si visorý.He, has 'an. extensive Mechanical d "t b

ackgroun n laIeso nU.6'ar powe pge

.ln if&ib a.insWith aanthprougl undt in-g

-zonfigu*r6ti.n contreolmanagiemet~along 4with.deign."andl icensing. basi bf nuc earptower;p.

Mr, Hul!; has s*Ucce*;Sfilf!conmpl~et-d thejNear Term Task Force Recomrmendation 2:3-5lant;Seismi cWalkdown TrainingCourse.,,

TK RE-.: Mr. Ra

irEngineer I h

Phoenix, AZ iffe.,He.ha* o'er28 arex.erience in the nuclear p

-d 0

jdi:istty** ith -eXpft"ise in p!ant:sýyst-rims lani desgn enginee tng. C nturrently, Mý

• 'R Iis 6e6die' n

atl i6i gieerrp

,6fr g

in

uj~ft P~-uuhh Siu~oMri Anysis (Q& 48r two, Taiw~an' nuclea5rsýtati6in§(PWRýarid.BWR.Tis fot in~isuppjort o,)f.'.th~'plaý'Int'Safe.

-6

, p (using GES QRT otherzaVlabIbte6tinh

'.qa an rlycatter.6ha ysi~sý Mr.

Ram.pws involved in resolving. S

-t f

se Ci0ties )Millsto n-e-;P Pisdd Pi gnm He lihe doesf nFoliciis rely haterng issues To r~ep acb outliers, Mr.. Ram. ~6eopedado i~~'ed developmentof.m.difti p*sackagensinc'iUdnig replacement reay.selec dr-tio, Aq'y te sting sped

-icati*on prepara

nd seismic, tisits

• fo*relayqi-f.iti, AS a sys ems.manager M..

ar, d

ivrcnd th p-rsu6 r;sliti`ns *forany desigjintenance'oro atio*ial ist* tb,'

equipment Afej has,dee opdts ~n 5 icireaker and te~eti~

ppe..men rlm i

ins.,oveetin pn i

6iteq~pges-Mr,,.qahs Intrae wIt Nq i n tiheirt bienn 16aI Corpbien" eig ai AY:

"j q

,,,,,N v "m ý as 11_..

Inspections:(DI n wit NPO int4he6~irbienniPal evlutions M' Ran has4M gre i randEltricalEgne*r om teUniversi tyof Cincinntii "an _

.n

'MBA frofi Bwing ý,Qrpen State., UniversiW2 Heis 'a. ic~eds 0i

'esIna Egine

(~~ectrical).n inOiM a

as comiplete'd4;asik~mdonthtrain~ing course'in BWR IOffice She Mha sela*arBelor of S}c inivi Engineer III inthe S&,4Chicago,

~*id:~

",ii engineeri an as mhore-hah 30:,years of experience1 in, thwula poyv She is-a l1ene 'Sricra

• M l

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Sf

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, ';.:;;'.V.

Braidwood Station Unit I Correspondence No. RS-14-034 Annex B Engineer in the State of Illinois and has a licensed Professional Engineer in several states. She is a SQUG Qualified Seismic Capability Engineer (SCE) and has completed the NTTF Recommendation 2.3 Training Course (SWE). In addition to her involvement in design and analysis of structures, systems, and components at nuclear power plants, she has performed SQUG walkdowns at various nuclear power plants.

Phil Gazda, P.E., S.E.: Mr. Gazda is a Senior Consultant and serves as the Vice President of S&A as well as the Office Manager of the S&A Chicago, IL Office. He is an advanced degree structural engineering graduate and has more than 35 years of experience in the nuclear power plant industry. He is a licensed Structural Engineer in the State of Illinois and has a licensed Professional Engineer in several states. He is a SQUG Qualified Seismic Capability Engineer (SCE) and has completed the NTTF Recommendation 2.3 Training Course (SWE). In addition to his involvement in design and analysis of structures, systems, and components at nuclear power plants, he has been involved in SQUG and IPEEE walkdowns and assessments at ten nuclear plants and led the CoinEd team performing the SQUG program at Zion Station. Mr. Gazda has also been the moderator for three SQUG qualification training classes provided for utility engineers. In addition, Mr. Gazda was the Project Manager for the seismic assessment of HVAC ducts at another utility based on EPRI document Seismic Evaluation Guidelines for HVAC Duct and Damper Systems Revision to 1007896.

Bruce Lory Mr. Lory is a Senior Engineer III in the S&A Chicago, IL Office. He has a Bachelor of Science degree in mechanical engineering and has more than 30 years of experience in the nuclear power plant industry. He is a SQUG Qualified Seismic Capability Engineer (SCE) and is the instructor of the Fundamentals of Equipment Seismic Qualification training course for EPRI, and is the co-instructor of the Fukushima Seismic Waikdown training course in response to NTTF 2.3. In addition, he has been involved with equipment modifications for Extended Power Uprates (EPU), as well as Seismic Qualification (SQ) and Environmental Qualification (EQ) of equipment/components at numerous nuclear power plants.

Walter Diordievic, P.E. Mr. Djordjevic is a Senior Consultant and serves as President of S&A with specialization in the dynamic analysis and design of structures and equipment for seismic, blast, fluid, and wind loads. He has managed and led seismic walkdowns and fragility analyses of structures and components for use in probabilistic risk assessments. Mr. Djordjevic has 37 years of seismic experience serving the nuclear industry. Mr. Djordjevic performed and managed more than 20 USI A-46 and IPEEE projects in response to the requirements of Generic Letters 87-02 and 88-20. Mr.

Djordjevic has a Master of Science in Structural Engineering from the Massachusetts Institute of Technology. He has received industry training as a Seismic Capability Engineer (EPRI SQUG training), EPRI IPEEE Add-on, Seismic Fragility and Seismic Walkdown Engineer (SWE).

3.3 ADDITIONAL PERSONNEL Exelon plant Operations staff members Messrs. R. Richard and D. Shaw reviewed the SWEL. Mr. Richard is a previously licensed Senior Reactor Operator (SRO) at Braidwood Station with numerous years of experience in various aspects of plant operations. Mr. Shaw is a previously licensed SRO at Byron Station with numerous years of experience in various aspects of plant operations.

Various additional station personnel also provided support to the SWEL preparer to help identify major equipment or system modifications, equipment and systems located in 3-3

Braidwood Station Unit 1 Correspondence No. RS-14-034 Annex B different environments, and equipment and systems that would be accessible for inspection during the plant walkdowns, in accordance with Reference 1.

Exelon Engineering staff member Mr. T. Bortolini performed the IPEEE Vulnerabilities Review based, in part, on the Braidwood IPEEE submittal along with subsequent correspondence and station records. (Ref. 3) Mr. Bortolini is a Structural Engineer in the Exelon Engineering Department. He has over 38 years of engineering experience and has worked at Braidwood since 1998. Mr. Bortolini has completed the NTTF Recommendation 2.3 Training Course (SWE).

3-4

Braidwood Station Unit 1 CoWrespondence No. RS-14-034 Annex B 4

Selection of SSCs 4.1 OVERVIEW Tlhis section of the report describes the process used to.select structures, systems, and componen ts, :(SSCs) that wereinclutded in the S*ismicMiWalkdown. Equipii ment List (SWEL)."

The, ctuaI quq erietulists"that were deveioped in this processa*re found in Appendi B nkreafi~s

,Table' B-i BaseT List 1 Table.B-2, Base"List2

• Table B-.4,. SWEL 2 4.2 SWEL DEvELO NT Th e.. selection of0.s

-s p-essdes.ribed rin EPRI Technical.Report.1025286ismic

• W~all~dc*w,:,

idahefot.:Rd*uti.bn.f:Fuklijsira.Ne.ar-Term MTaskForce Rebomrnn po::

Sismic, *dted :Ju 2

2 'waS-utiliz6edto.dev'elop the SWEL for

• Bridw6od,*Gen.eratir 'g"Stti'r'i Jri.

The:SWELE is* c:

rd of Awo groups 6fite,,s s:-

~ ~~~..

'*rri' prisq

• • SW:EL.-]

is a samp***

ieof items to safliy shut down the reactorand a

maintain

.... tinmet ihtegi jy

• SWE 2 isa, list of spent fuelbpopi relateditm 4.2.1

'..14

..SamPP*;.

f Items fOrMtieFive: SafdtyFunctioS-.-:.

Th c

fbrselectingra sap.le opf SSC.sfor-Sowuttfni doWn the iactor and ijigntaiiinlqontainmn intgrity, beg~n;,with-th~e com~p'bsite Seismic5 Inivdal1~

E "diiation for-Exteirnal Evns PEEýubesPaW ipmentr Lit 6SEL

.(e.3)

Tk"'0 1PE PLwstensbetdt he foloii r6urscreens, to e id ethi ems

.':-Ito e sf 15' t.'

't '...

totbe includedo the. fis esi kdown-Equpje' List( (WE1:

1.*Screen

.Seismic:Ca*tebry As esriedir RfeenceI hol~y tms ta hav eie simc1 licensing, basis.

bae d-inRryr in ARe. hapeti,vneeedntda Ias `efin" th B

'UF""

h~inaieile sismqlcnshgb sis (Re 2) pIetjja enl

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t l

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s iE detrminaion-ws mad hruh: tv~w f

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.Braidwood Station Unit 1 Correspondence No. RS-14-034 Annex B

2.

Screen #2 - Equipment or Systems This screen narrowed the scope. of.items to include only those that do not regularly undergo inspections to Confirm that their, configuration is consistent with.the.plant Sicensing basis. Tiis-screen fu~the reducedithe IPEEE SPEL of any Safety category I structuires Containment Penetrations, Safety. Category I Piping Systems, cable/conduit raceways and*HVAC ductwork.

3.

Screen #3: -Support for the FiveSafety Functions This screen narrowed. the scope of items included on'the SWEL 1 to only those associated with maintaininrgthe following five safety functions:

A

.Reactor Reactiv.ty1Control (RRC)

B.

Reactor Coolant Pressure Control (RCPC)

C.

Reactor Coolant Inventory Control (RCIC)

D.

Dec*a Heat-Removal (DHR)

E.

Containment Function-(CF,

' Thie fir~t oi~U npiins :are as-ociated with bringing the trea o-tr a safe shu tdown Condiiin.i The fiftfh functionis asociatecd wih maihaning c6ntinrie t: intýerity.

As'described in Appendix.E oft Rfeece.1. the safety functio

.fachit'ema on'the

-LL EESPELr H2id.

ntified,Ite1 is dno that:items*.On EL with a.specificsafety

~ rotine-.systems. Items.with -a safety f..unction.

d*Esign.ti.'E.f-S.port System HVAC' S t System A:

er; S.upor' SystefnDC P6ovW&,.5Engine~ered. agety Features Actuatibn Sys~tem -._(ES FAS) or,

'Cooling-Water' Ia eafotieo upr y tems.

ltswith aisb saet-y. fu'nction qC odpby.*f pH*,,u.

A-P e*

.rt

~

~

~

~

'7 t

[.:(

AS.)::or.

System DC Powr nginedSi e y.eaturqs ActuationF

.'Cooling: Wate -suppoift least 6ne 6.f the 'five safeityi frinctiohn 6~v

the,

."sp.ecf-i sfty functi" p

.Js,!

not ind ofnth

'}gi6 safety funtion'(s) is not.re~quir ~b~frnce1. '-

The4 rslta6nt equipmentklist after zScreen #3,.ý-d'fined.ýr

.PIgiaiC,.

docum'entM a s Ba'se Li s A~'ndi 'di-n-Q.dlude' App i B ý(R&f:Ai

4. screen

-i4-Sample fýa~b~i This screen iinen ed-t6'resu iti a SWEJL 1 tht s~ufficently.e.rsetroa p

'of la6tSeismic Ctg6rY "f

1).,

a.g"y

".. '.nt...

tms to~r~et he oj~cive Aj te~RCO4(f) letterP-T~he. folowing~ atfibt' wr t

h ~ b ejtV

ý cosderdinhe seetinprocess fo1tm'n~~donSE i:

A ariety ofitypes of sseii The, systemi detfe f~ac.Witemo SWEL 1'Te-e,6upetnldOb SWELT19`is a M

rpsnativ sa I -f t

j~~ quihn'nuo e1 n SW q~pp.Jeýsap ~psevprp ýýyste.,

mh~

~oirljoe or' multiple: sfty functin Futýethe &ý,ysteyibi,represen, 0 iric'luidd bo~th",

frontline and supotsystem&is' list~ Pn~fe~& 1 dpnA E: yfr to Support,.Safety F

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re re ena~v~ s~ peifse e~alsy ~, :.t~ t, e[fo m :on :;o ;.:

4.--

Braidwood Station Unit 1 Correspondence No. RS-14-034 Annex B The equipment included on SWEL 1 includes several items that have been modified or replaced over the past several years. Each item on SWEL 1 that is new or replaced is identified.

C.

A variety of types of equipment The equipment class is identified for each item on SWEL 1. The equipment included on SWEL 1 is a representative sample from each of the classes of equipment listed in Reference 1 Appendix B: Classes of Equipment. Where appropriate, at least one piece of equipment from each class is included on SWEL 1.

Screening #1, #2, and #3 resulted in no equipment in the following classes:

(12) Air Compressors (13) Motor Generators.

D.

A variety of environments The location for each item is identified on SWEL 1. The equipment included on SWEL 1 is a representative sample from a variety of environments (locations) in the station.

E.

Equipment enhanced due to vulnerabilities identified during the IPEEE program The equipment included on SWEL 1 includes several items that were enhanced as a result of the IPEEE program. Each item on SWEL 1 that was enhanced as a result of the IPEEE program is identified.

F.

Contribution to risk In selecting items for SWEL 1 that met the attributes above, some items with similar attributes were selected based on their higher risk significance. To determine the relative risk significance, the Risk Achievement Worth (RAW) and Fussell-Vesely importance for a Loss of Off-Site Power (LOOP) scenario from the internal plant PRA were used. Additionally, the list of risk-significant components for the LOOP PRA were compared with the draft SWEL 1 to confirm that a reasonable sample of risk-significant components (relevant for a seismic event) were included on SWEL 1. (Ref. 7) 4.2.2 SWEL 2 - Spent Fuel Pool Related Items The process for selecting a sample of SSCs associated with the spent fuel pool (SFP) began with a review of the station design and licensing basis documentation for the SFP and the interconnecting SFP cooling system. The following four screens narrowed the scope of SSCs to be included on the second Seismic Walkdown Equipment List (SWEL 2):

1. Screen #1 - Seismic Category I Only those items identified as Seismic Category 1 (Safety Category I) are to be included on SWEL 2 with exception to the SFP structure. As described in Reference 1, the adequacy of the SFP structure is assessed by analysis as a Seismic Category 1 structure. Therefore, the SFP structure is assumed to be seismically adequate for the purposes of this program and is not included in the scope of items included on SWEL 2.

4-3

.Braidwood Station Unit 1 Correspondence No. RS-14-034 Annex B Per the Braidwood UFSAR Chapters 3 and 9, portions of the SFP SSCs are classified as. SafetyCategory I and are screened into the SWEL 2 list. These Safety Category I SSCs include; the Spent Fuel Pit Heat Exchanger, Spent: Fuei Pit Pump, Refueling Water Purification Pump QA,.associated instrumentati0h, piping and.

manual/check valves. Development of the Bra6idwood Unit 1 SWEL-2. list'includes colmponnts associated with the common (Unit 0) Refueling Water Purification Pump OA. Note; these pump's motors, aie Safety Category I I, even though the Refueling W.ater'Purification Pump OA has an ESF power source. There are no Motor, Air orFluid operated valves in the Safety Category I SSC flow paths.

2.

Screenh#2.- Equipment or Systems This screen considers only those items associated with the SFP.that are appropriate for an equipment ivalkdown priocess.

3.

Screien4#3 - Sampl~eConsider.ations This:screeni repr*sents atprocss that.is intended to.result in a SWEL-2 that sufficiently represents a. broad.iopilation of SFP Seismic Category 1. (Safety.

category )equipment and.systemns :to meet the objectives of the.NRC 50'54(f) letter. The following attributes were considered in.the. evelo0ment of SWEL 2:

A.

A.variety of types of.sYstems T'he syser'm"is..identifie.d. for each item on SWEL 2. The equipment included on SwEL.isja represenrtative.sample"of the systems associated with h 'e

.SP and,its cooling;'*system.

TheS.SFPp *ump, Ref uelingri g:.Wter*Purification"Pump(OA, ard SFP h**it exc6ha'hger are' inc Ued d"'d oite'SWEL--2 list. Ae ntieanl o f ii*s*rumientation, manIul valves, andcheck vayles ar*ea*lsbincluded.

B.

Major~new andcl replacement equipment-he _eqyip.ment incled onE.

.sud i.clude i.e.":rn. that have been mpdifid ye plce ovrrthe yas

~e era-er-s".- Ho'ee,.a review was

'..rf6f....d thtoih 'bon o*

f tero..sedquipme.nt pohSWEL;2hasbeen m" o'd ifie"d or t~ie -Iab e'd C.

A

.Avariejty

'oftypes of equipmert T...pqiprneit casssone-p ie.fe m

feachmls W

2, 7s-equipmen inclu'ded, on%,SWEL..2 i§axr.present a.tiye sam~ple_ frp6neah'o he6.ss a mr6~risI...a]tlds.Oferpence 'ofA- ~uipi&tiise of Eo~ipr~nt. Where

-,The.lassts types6 oepmentby.l ude; '(5). Hor zotal cluapsis(2) il1),*nsand-

• .Heatb cg Exb g

tstrumenrt..Ral~s-(il9) Temper atue_.es.ors 6andhd(0).

ThePbcidofb-f'r e6ch item is *identified'on ýSWEL 2. Theý..equip-e e'~lud*n on j'Wf e

st*ane e from atia...vOi e n

" "l' catem-st ph a

tedBwith the.

system.-.All;

.-. "A ad-i or. Fuel.ln 4"

.i."ilding.*.,

a

.d

L,

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/':.

.?'

".. 7.

./ :* ;::

5.

.t*'".

';' *'.1':

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,.I.

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,?.:.

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.,':

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Braidwood Station Unit 1 Correspondence No. RS-14-034 AnnexKB

4.

Scrieen #4 - Rapid Drain-Down This screen idehtifies items that could allow the spent fuel pool to drain rapidly.

Consistent with Reference 1, the scope of items lincluded in this screen is limited to the hydraulic linbs:connected to the SFP and the equipment connected to. those lines, For the purposes of this program it is assumed the SEP gates-are installed and the SEP cooling-sysiem is in its normal alignment for power operations. The SFP gates are passive. devices that are. integral:to the SFP. As such, they are considered capable of withstanding a desig n basis earthquake without failure and do nrot allow fr a-rapididrain-down of theSEP."

The SSCs~identifie'dtinrithis screen are not limited to Seismic'Catego6r 1 (Safety Ct~egobry I) items, ýLut is'limrited to those items that could allow rapid d'rain-driwn of the SFP.*Rapid1 dra' i in.-dowh iýs definted as llow'ering of..te waterlevel to the tufp of the fu6l.a~s.enrhlies withirn72;hours after the ec1r.tquake..

Exce6pts from !the? Braidwood UFSAR *9 1 3.2" Sysieim Descripti'o'.n ldocument the designfeatures which :preclude.rap~idramndown.of the spent.uel Pit.

I'ss&6-~

t blewo6c6iq0§ytr The Sa.ety. Catgory.*e ft.ipool cooling system s nLing M-63.

cons istsif:.-* *oiet6bii".trains:The* spentfuelpooi.

g system >(piping,v pu

'I s:alestn d 'htexc'hangets) is Safety C or Il,Q!ity Gpup C;. ThIe 3-inch piin.g.f*orm'.the.refuelingw a.te

'st o".ra t-

"1 ;6o.the-refueling water purification pu.mp" Ith pupid,a its'asoiated'pip!ing and v alveq s areSafety..Ct.goiryl pQuality Gr.oup CA2-inch"Sa"fe*t*y,6 QualitIGu Clinromth e. isc*i.hge _ofthe

• i c

S j e y f

-"th-s.: :

d!'

h*fg i

refuelng_

4"Ne jurfication.`pump totth" u

p..spentp funtl-riosol e'..Ths is the Catgr I w;ýater makeu

ircit>Tgba

.y.

This

-mau sem.

p ar water-rrhakYups, o-

.ja q

z

rytta, no nCategr t 'tk

• eswter;frOrn both prmr ater. stbrageJ t

-ank andjrut st h6 aertro th l~ent.Uel popo Water filterand!the:th*

i ieturn:headers6D Mi. 63; n adition, primary WateR piaq...e.added rt e speri-fe p aa, ire hse connection in*.

.fuel h n b n Inmma, t

r-e"ources om up waer avalal&

a irarunoae nCagryIsrck4 a bo at Saety.Ctegry

_y*

sourcle,ý an an unoae iýjroeto1 aey Cat~egr I oe'ytr.-ref y8 a.o. e':he a fec spd*

9p :pp.

to" of...

... Bh tc skimrn~

syst~s

~meet tis regýpqpui ment.

N ro pijig hi th~ool6Ahd bl

".'b leato ekcept th.e. s' et.fpu in.,:'

66.6'".-

g pipe Thi q-oe'nt o

a anyti.spoh-d'n I ti the"b-sj I.

ehý t fu4l` pio p There L1*2,eis.et-thi `.....

g.-

errangete iaaid;eq durremei

,down of t S

't--

the,4-6 transfe canaln Syst~

e Ind an, rrbt eIS' f'

n: thsnidnte.

iontke090e11e,.oldbe carge leavps at.le-at 2n fee 6e 6

h n

Ti he 1

1, s1&i fel in stor~agei7

.:Po" torq' i

.a-if e

-i 4*n pr e.

. "A ap!ngscp nnoe

-t

-w

.. ' rpts,,-frorf; i

wo ONýA -.

afoty3 Eva uati

,scuss t a n

.r I.

'd.

-" ~

~

~

~

~~qn

...... _,.O*;npty,ýan:: 00*

ýi 64i Ig J"1P"

i.

• ~~ý

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• t:fapý H.-

ym a., t n -.-.

Pee.:**O:

n, uh e

poo wE.'

e.

o.

.e.r.....,.

bt 0te'th~tbn'..*This

.:'~~~~

in 11-

_t

-r:

z:!

e!-.

• 'P I

• • !.::~per l :i..soragp -,-,.:*i' i.

i

-:

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.::. "...-:, ' :" *:, ")...

i i I,.: :... *.:? : Y :i-.ii'4

_.-1:::

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L' i"

Braidwood Stdtion Unit 1 Correspondence No. RS-14-034 Annex B This incident is not considered a rapid. drain down transient. The gate is a structural element, seismically designed as part of the SFP structural.analysis, and is a

,passive barrier with no active domlnonents."

There are no rapid drain-down considerations included in the Braidwood Unit 1

• SWEL 2 list.

4 44 4

4 4

-. 44 44>

4 4-4-':~

4-3 444 4444 4

4 4t 4

4 4

4~4 44 44 4

.4 4

4-44 4

4.4

44.

4 44 4

]:

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44

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4444 44 444 4-

'4 4 4 44444 4-4.44

~444 ~

4 - k.

4~4 44 4

4,

Braidwood Station Unit I Correspondence No. RS-14-034 Annex B 5"

Seismic Walkdowns and: Area Walk-Bys 5.1 OVERVIEW Seismic Walkdowns and Area Walk-Bys were. conducted by.two (2),persoon teams of trained Seismic Wakdomwn Engineers (SWEs), in.-acciordance with the EPRI guidance document during the week of July, 6"2012. The, Seismic.Walkdowns and:Area Walk-By's are discuss'ed -in'.re6t.detail int1he fo11owing sub-sections.

§CniIstentwith -the EPRi.guid anced ocum ent, Section.4: Seisi-.Walkdo.ns.and Area Walk-Bys," the.S*Es used heir.engineering judgment,ýbased on their.experienee..and training,-to identify n ipotitaly.a v~rSq:S.isrrnic conditions. ýWhere ne`ded týhe,,engineers were irovided he'latitOdt.

'oIy'u'bhriew-ot exi tngI aaly_

to infor;thir judgment...

The :SWE*s condoucteQ te 6

Seismic dWalkd ow aýndA Area Wa*I together -as.a team.

i~i-the :evaatidns, tleSWES adtil"d icsbydicO dth§ir.d oibs vtidns and mjudgerits Wit1 ahohr h resu Itg of the.Seismi Waldin9,6nd:Areqa..

alkByS rpre

ein-are-.based q 0

6* pr.e hens.ive agreenieh.:of theSWEs.

5.2 SEISMIc W.LKDOWN The'Se'isrri.icWlkdo s fqcUs-e.d on* he.seismic.adeq"u.cybf theeitS 0n the:SWEL as pro'Adismi inW~ppe WndiBq hi~ r rt TheSesi akois soaiedth potentiai.for ein'rl5VyS s to'cause adpvoersq seismic interactiorisiththe SWEL items.

The Seism.c Wa.[kdown.s.o.used:on ethe 6fo11dwng adJverrseesmcc.ionditigns.ass.ocated wit ihsb~~

oteW'o i pg:;a j it:

SAdversean.-ragecon::dit'ons Advers-e.sisepi ls-paticl.-interact ons*.

• Other, 'derseseismic condition Th~re fif tffhe `S fisiic Walkdb.wn's:h'a've beaen ýdo'u'm entedd teSis:i Wilkdow" C l-rd*h:

ls' j4d in h ge ppe C

.. ~~~~~

~

u Seir~i6~Wlkdwi's erej-performed adaWcompledtd :for'105b Adt~

1 tm identifiedo the BradwdUni ISEL;-The 'ompleteddS.WC§'qYp,ýprqoVi ed in,

"". C "f -

't. ' dditia;l'- y"

'h -`-. hfd..

d' '

.mth

• "*-CS' Is to p p p_*ý.-. o Alhm ls"r,-,o..V-...-

provide v6a yqyl

&6-d'bfhe itethii,0l5h: wi~h "n'cmm t noted on the SWC Drawringsq thohI~6dd~#

j~;qd6f6he SWCs!ýutIare-not'in-clUded, wit t~e S~sbecause-th~yi 1e~Jl 6eridyab od c

6cue trughhsaoi' doppmen mana gerteiitsys emf.

Seismica W~kdowns ara dqferred for th min~ing 16imsta unit outageo'r.

tpproriate ti h

te i

sble Tsld nt be walk

" :F*

5

~*'*jl

,*'.)ca s

• =.<.:.'p' l'i: ':*

P j'

F-p

" (4 :i -.'..:

..":.!:: (ti*

,n.,

.:..oim e w en w o en;!?::¢:.::'":"-

is, cc

e.

,.-:.....;q.... -,..,S

_'i:..

.-:'i:...

...... ;,are :c~ed *L

• Braidwood Station Unit 1 Correspondence No. RS-14-034 Annex B down during the 180-day period following the issuance of the 10CFR50,54(f) letter due to their. being inaccessible.- 'Inaccessibility-of this equipment was either based on the location of the equipment-(environment that posed personnel safety concerns while the udnitis.ppirating) or due to" the electrical safety hazards posed while the equipment is operatirng. Appendix E of this'.report identifies the inaccessible equipment along with the Plan for. future Seismic Walkdowns.

Thefollowing ubse'stions desc*ibe thebapproach followed by the.SWEs to identify potenii~ly adverse anchorage, conditions, adverse seisric interac(tions, and other adverse seismic conditions during the seismic Walkdowns.

5.2.1 Adverse-.Anchoirage Conditionrs Guidln*Cefor k

identiying arnChorage, that Could be degradfed, nonc, onforming, or e

un

i. lzbyd"'relied on*6isul inpetions of. the.anchor d i ve)jification, of ?,a nchorage co~

• tio'nX.*e.fs!.fr-th~e§ tw:typies-6f~eVaiua~tic~ns a~re providedlin theif0llowiring.

two subsectfions...:

The.vaiaiip of vpotetially-adverse anchorage-conditions described in this subsection a

ppiiýtqPi)0e anch or~pe connecions' that attach te

."iditified-itemn of e6qipment to the civii ýtructUr-e.6Onhich A -s inoiuntd Foexmple;, %the weld'ed co'rihdbibrst atsecure th'bsof a MotoriCbrhtro[Ce~nt6`r(WCd) toý'tliieI steel e dtn~iterit~in the condretefloobr would be evaluated-ithis suubsection. Evaluation ofbetoheconections that.seCure.

c~mofens~ithn heM1 is 'coverediater in the swubsection

-ýth 52 Vsa ndtns.sInsped tion s.

The'prps of Tevuan cios wasto identify -wlete any of the folowing p*..ti...1ý.dverseanbhrE.-..ncn.t.ions Were. present:

• Bntbroenmissing,-or-loos hardwar pi. ware 0..o.rosidl -tha-f-is.,: :

moreh,41an mIl c oiatn

V:- bi~ caks inte cnrtner the ahchors'

'Qth teot~tiall11 adves sesi ctonditions:

Based r~onethe r

viua of n

thecvisualinp0ectioh,' the' WE j

.u.d th*ewanbhora"ge

'*..nt;Ib aednon conforming,6ra,.*

unanalyz

." Its

d.

is..

• l in'~i~c~tion

~v~e docum nted on ntpemSW!g, as p

'r,.,V p rintý.y 'h 'r

~ s c e~

.evi erce p. f de.

r'. d nonconforming,

.,r u a -

• c."

it*

t

• i".

.L.:..:;.G i~i*si0g tqf,.ý~ -

• e:ntpic

.n";.._

riiiigý s-Q rf,,a 6**exdati..,.

a.s""ý

.J di..*..

cnthe,6che~cklist 6d:a'n %

a icensing, bai evlioh vashbi nesry weifiwa

"'"'-1

-on

't lo

ýi,

..s

-no... ss....

th..a..i d d.

fo m ng r A

tnt-d-6~r ~e~ficidt dnothjbiredi i'.'P s

5.2.3-c

.Iy:,thn q(.

Gie:*,

'.c -...

n.

_tfi In

' trphe'.,.

othr,

alnbh rdo..,r.

d6-ti

.frf:s"5%~un~

f i-ocme ab or t, Oi*>,

he.

. ". -. : :', *::, *::.:*;*',.,*;:.::..-;. i,.. :;.,;*r **.": : ::. :**z:-'*.'*-

'!.* ;, : ~ii:"".',::*: ;i*"':.. >> "",-

• .5

Braidwood Station Unit 1 Correspondence No. RS-14-034 Annex B Line-mounted equipment (e.g., valves mounted on pipelines without separate anchorage) was not evaluated for anchorage adequacy and was not counted in establishing the 50% sample size.

Examples of documentation that was considered to verify that the anchorage installation configuratio-ns are cOhsistent 'with the plant documentation include the following:

Design drawings Seismic qualification reports of analyses or Shake table tests IPEEE or-USI A-46 program documentation, as:applicable The Tab*le. CQl of Appendix C indicates the anchorage verification status for components as follows:

N/A: ;ornponentstiha~tare line-mounted, and/orarenot directly banchoedd(with separate.aan rag:)t the civilI structur e an her~efdre dre t count ihe a:6ch6rage cohfirat.~r tota l.

Y:components th~ are an6hored t:6the -civil struc'ture,whidh were coflredto

" Consistent withd*e§dsni awings and/or other rplant'd6cumrentation' N: c0rOnrsthat ?re aqpýc*o*red tdth1e civil :stifictur.e fo which anchorage 'drawings were noti ieh~ti i~d and/or retrieved See Tble 5-1 bei6w Iforithe aa6outibg, of the..50.%/, apdhoar.ae configuratio*.n c~~~nfi~~~~mati~~~~nsr.

~(df~

niiuIS~6rm nApni

~he-specificý rawings used for each, anchdra'ge Verific.tidn'bonfimion.

I%. Anha C

guration o ni rtin S R~giet SWEL.

No ofSE..

I-.,.

s.qon.

irm?

ItemsConf.irmed

.e m s *.

It.. d o fj d,. :

Noteýs:

ii (6) fp6horage V_)4icti:

have be'e'n~

rf'roea ad will becpq'4ieted asoqutlined in: ApdIx.,

,,5;.24.-.AdverseS Sesmic Spatia Itercin

'An 8dVerse Seismic spatial-interactiois th py icalinlraction -betw,6n.th~e.$WELJtemr

':ahd~aheqftSSC;6'9'~aiesi

-I ltr e' "boio betweeh the tWOAd~n

neatqa, An

-ins6't'-n k6§ p6irf6t med inth~e,area; cdjb~pnt.tb and l:s'ulr~rou'ndirig 'the,SWEL'iteinto

'iiynsihiitrtion co~hditidh; that' cud ad~sl'f6th'a~bjlity- 'of titWLiItem tjo pefoh V-'rtndef'it rlted'func!,ionsi

't a..

inte

'of.ia ergeafb efectst at hajcovh6siderb6d are'asifollows::

Th'heeypps-of eismic AP i

Atii, Fa Fi ru're" and faIng of SS0 (Sisii Ii oý6r

• ~ ~~- Flxblt fatachedý line an ables N>i~

lit t

I nes' A6

21..'.-

3 1 '

?,'

..S (C ***'7(I..>.:.

.*;:t*::,*< *=:-'"'*k **:.!:.*

':**q!*'

.i.-***'

• .:,f :'.-

A A

I.: 1,:"

A. :4n pe

!a s'ef r

edn.hAa e

a In oa'Aurru d

gth

S E : tm t;.

Braidwood Station Unit 1 Correspondence No. RS-14-034 Annex B Detailed guidance for evaluating each of.these types of seismic spatial interactions is described in EPRI guidance document, Appendix D: Seismic Spatial Interaction.

The Seismic Walkdown Engineers exer.cised their judgment to identify seismic interaction hazards.. Section 5.2.6 provides a summary of issues identified during the Seismic Walkdowns.

5.2.5 Other Adverse Seismic COnditions In addition to adverse ahchorage conditions and adverse seismicinteriactions, described above, other po*nttially adverse seismic conditions that could challenge the seismic adequacy'of.a SWE.L item could have been'present. Examples of the types of conditions that could pose potentially adverse seismic conditi6ns include the following:

Degraded Conditions Loose :r'rhissing fasteners that secure internal or external components to eq uipment

.L~arhge, heavy.components mounted on a cabinet that are not typically included by the oigin"dlfal equipm~en~t manu~factu rer&

gi.a piJ e

n.

m.

a u

t r

r Cabinet doors or panels that are -not latchedsor fastened t

'Other.adverse-conditionsS Any identified othber adverse seismic conditions are documented on the items' SWC, as.

app.licable.

5,.2.6' Conditions Identified during SeismicWalkdowns Table 5-2 ý,provides. a sumr.maryofthe conditions identified during the equipmentSei.smic WiIkdowhsn-Thie:equipmerbt 'Seismic Waa

,kdwns resulted in a,total -of four (4).cornditions identifi~d. wýhid'h v.w'ere-enteOred inito the station's CA.

Th~e condition s wer assessed and itwa~s concIu~ded -thatthe conditions §wbold -not: piryrVet~the' associated eupnnt'fo peprf,,,R,.

feitysa ft,-reitd 6.fuidtit'(s) The :Cdh iti6siied'by

'.e SWEs durng" the.qeupemesC*..Se6isi

.Wwar t

lentS~s~c*,.,.alkduowns wr;:conclud~ed.,to.not'b lhia'd~erse seimi

~53 ARE WALK-BY$

The purpos e of the Area WaIkýBys is*,to identify potentia-iy'ad1ere :seismic-dititn-ass.ioea wtother, SS'C*located in the vici ye.teS:E'tm:V~~it*.

g6~e~l~ deft~e."a th6r~o c~na ntypthe,'SWEL'iterds.; iciriityis.

Ttnerb"Hll), tefi' thlý vi

'nnlh WLitm fteorni ~~yarge~eg, ge feet from thcitTinginity JSWE-ite m.;Ia-of.the-Ate Wals per e dB.U f

o tat dditional area,walk-bys

l h'e t........

cpmole'ted,, as' re n peo 00V* to tor Qr*

0@-

6:",

T..

d ered dingAeat Jf,, o1ig: -

il" An'choragbecoinditions (if Visible vithom'it,'peiiing equipment)',:

n 00::

-qLl

.0 nt 2.*

="*, -, °*.:% ** ' " " ':= ' *;

- -,'*."~'

t

• "... * =....

r

'b

' =

.* :-... ' t..

t -....

b*

r;..

,,. i

Braidwood Station Unit 1 Correspondence No. RS-14-034 Annex B A visual assessment (from the floor) of cable/conduit raceways. and HVAC ducting (e.g., condition of supports or fill conditions of-cable trays)

Potentially ad.verse seismic interactions including those that could cause flooding, spray; and.fires in the-area 0

Other housekeeping items that could cause adverse seismic interaction (in.clu.d ing t

a.

(inc g temporary nsta ations and equiprmen( storage),

Scaffold clearances and-tie offs were reviewed to meet Exelon'Standard NES-MS-.04.1,Rev. 6 Seissmic Prequalified Sc*afo'ds 0 Seismic housbkeeping was examined to ieet station procedure BwAP 1100-23, Seismic Housekeepinrg Requiremenrts for the Temporary Storagepof Materials in a t. egory-I Area4."

The Area Walk-Bys are.inten.d t.idientify adverse seismoic conditionhs that are readily identified b. vsua...insp6cti6n, wi*tfo*htecessan iystoping to qpen cabiinet:br t.ainagan extended lok. *Therefore,..theArea W ak-B,to *ignifin~:.tss tir*e thanith.tb.k :to'-

conduct the.Seisp.ni6.Wlkdowns describeda..bov.e for a'.SWEL it....i. -If.ra p Ontialy' adverse seismic cdnditidn '.s yidlen.itified dunig. th.e Are alk..

y, then additional:time was taken;, as necessary t.to evaupateade.q It=ly whetherteareiwas.an adverse conditin..

and t1odo.q'ui:cumn`t.aitay. findings.

The resiu-.ts ofithe A6Are'a ;Walk-Bys. :iare-.docoumente(d.on 't-heAW~s inclu'ded inAppOndix-D

.of'..this r'-epor,:-..A.*# pseparate ;AW.ws**.filled out. fr each area inspected. A single AWC was. completed for arias whEire mo..e..thn one.SWEL dtm* wa*sloca ed.

AddNnal detaili.for:-e valu ating the pbtential for adverse seismic p au

• gj.s iiýpr, te e

• titai.f0r ades6wCS$cingý'a( t-ns0.68t.¢ saeusi6.0 ding spray or.fire intdhe&aor e provide.d: in"; the-follown':.

. siet"ons."

5.3.1 SeisimicailiyInduced :Fl)-di/lSpl y Interactions S6ismicaily-indubbd fli dIn intoactibns ar th:. effect.of pQssible'rupues f

yesselorpiping s"ts*thatcr"uep**

siraya',. fiood 6**sb,.ade water int**the*rbda here.

...SWEL itC

"!iems i

• arelcte~d. ::!.This t1yp~e of `se*isrrdc it~eracti6.4n~sc.n:sd~ed;u m:tbe*,

J' 5 't t-

ý666s dufd'qring ~the I PEEEprogram Those 'o".prior..ev luations.

. were o"". i. er",

-.,,Js..--..

.ý.e, ' -.- f...*tion o k.:

_ h::

i, for:.t-. A,%.

a

.k.Bs.

neaieabf patclar.n rd-to.the.irud.

istrs aded'fire piro'te:` p7i'pýid'gth long

• i~~i**:un

po te spans *'

-:

If a~deq:'"

uate

• ' ;"seis mnic.supports,.ale 'presenitor.tlh&*:"'

• *:*" ":"&..ar..e-.-;.i.:;:*.-: *::.:*i,*sol._tion,:.....

0-

-XI YAO.L f~ailues.

hayeber be~~

fl~

ob' hq e r~tn-g frm rriole ea mpc

". ss fru:

e nt ut -comrn" n.

"".. %,bobsep.ved ii "lur ah eocct"ir d u

• 9 f xie a 'ders "

~~~~i S"esri rnho mrtibbon ipe. s..- n.,

a ahbliping.,sisic,

~~o:and

'fa I'd",spp p-s Enpesweie ne~m

.bb flo npray 'ictratigh~, coud occur~include.the hý,0 ad s?

s~Mpipin wit indqut 7lea1.c dro~

Ise~

"-'4 io, pie.mep i clag, t nead.d p g cou p

l.t igs s

ar6 f a

fail~

~ ~~~~~~~~fl

' "i "h"6

-A dt'::

:.*:i.:;if:!::i:;' :

floqding or~spray ofeqire 5 t

• org~ unsupport,,qd asan of thrae fir p iotin piping, 4

_5

°"4

4

.

,4s p

4 ~....;4 4,*

..."4'"

. c :.

.":'*' '-('-*".'.'.::

4 4.":

4

'i:'.

g r:...:.....

~4

' 4 4 4.- l' i

+/-.

.4. :....

4; 4,"....

.4

+/-

4.:

J 4

• 4 4,

4

• Braidwood Station Unit 1 Correspondence No. RS-14-034 Annex B Flexible headers with stiffly supported branch lines Non-Seismic Category I..anks.

The SWEs exercised theirjudgment to identify.only those seismically-induced interactions that'could'lead'to flooding or spray.

5.3.2 Seismically-InducedFire Interactions Seismically-induced fire interactions can.occur when equipment or systems containing hazardous/flammable material fail or rupture. This type of seismic interaction was considereddduring the lPEEE program..Those prior evaluations were considered,- as applicable; asinf6irmati6r for thei Area Walk-Bys.

Examplres where. seismically.-induce.d.fire :interactions could occur include the following:

Hazardous/bflammnable, material Stored in inad'eqatelyanchoied drums, incde.uatpy. anchried s.leves, or0unlocked cabinets Natural gas lines and theirattachment to equipment or buildings e s c n a n g '!..

e ic a ls...

Bottles c6ntaining"acetylene or simiar flarm.mable chemica Hydrogen. ines and bottles.

Another :exan:ple.where seishiica iy-iriduced *ire-i.nte'ractiOn.could'ojccur is when there is relative'motion hetween '"high voltagei:jte) q.eOiipmeht'(e;4, '4160 volt transformer) and aadjacent suppgort, structure-we they. havedifferent, oundations. Ths~reative motion can cnause high.voltage.bu.br, whichpalss betw~dn"'the t.o* sh6.-&ut '.

aglainstthegrou..nd.ed bis. ii."sctsurouiding the bu*b*rs and caus.a fire.

The*

• `Sei6mic WalkdoEnd-Ergie6ers* *,erised d

.theijudgment to identiIfy onlythose seismi*ni*l-inc ud*`.intera.tions-th*at c6uld. lead.t.fires.

5;133Condition -tIdentified'durnin'g-Areac Ia-y

• Tabl*5 -3..tathe tend-b.ftthis"section.:providsea-summary of-the *onditionS idjletiffi-d SdU

_the Area -Walk-B-ys Seveteen.(1, o

ntefiedd-rig, t iA ea diA e

&Arita cton e

conidtins iwe re.eplqys N

sesmdlk"B dcd46 Noe4'6i:~w'r idnife drhteArse saek-mi t

"CA t'

W' 11c on on.

E..I.S i

Folowngthe odnp~ino iWnieses~i~~kon lutheionduioestyw miade yar i th'te Co ingff hsd'cayn.rac,~

~j~ions wernJ op~ng ielecria cdbgirk t4

Nt-o' other seismi

'6idton.

-hdps fo'r 6pite,'

cainet isWbl inpec

.c.

.h ii..

4

'd fi

-4'

'd ti4

-d-6inn g'

B S"

NI 6N' d

4 L

C.i

-T R

0-,IN:

,,4'**

v2.

44:

4;V

'-:t 4

4:"

• '44 }'-' -.'

4-.'

-4.

"4..'

'.' 4 S-"...

'4. -".5A,-

4.UPPLEMENTA-4',i E'

-I R'

h6`N

.Q-,_' '-.h-d.`,;.

..-l!'.-.:.-.f.*

`& -

r..

rip...

e i m i pop..

ions:...-

j, e p..p.

ý

,..,,<t..k.-:.

,for..p rig..t

:_.... se..* -...........-.

s. -.

s

.,to

.:.,..c.

e c e j,..

..:...i. :"*;*:

b f:

-: ' ",* * ~ j,.:-.* *:, `:., ;:."*.`:;{*..`.*..*.;*:*....,``*.:.`* :* * / ;`*. `- :.:.*..* :: *....

....... -., ;.&-.. :*d, e....l.

• . i hfp;-i r.ha...,com oen s bo..eind.a...e. uat e.c:.s ur~ef*..-. :..

• ?.:

11: : ::::."..

ht*'-.:

i

.,,.:,,,h,

-uýiagQapaj

• : i" ' '*. ::..,-:: : '" ",*i:,..*

Qte *,*hirdia§steners.f.sie' Lt-ca.n t.t~

e!e~r..np..;~

n..

v..*".

, *..i.

• ." * * ?'

[

Braidwood Station Unit 1 Correspondence No..RS-14-034 Annex B Appendix E of this report includes Table E-2 which identifies components in the specified equipment classes that would be considered as electrical Cabinets:

1.

Motor Control Centers and Wall-Mounted Contactors

2.

'Low Voltage Switchgear, and Breaker. Panels

3.

MediumVoltageiMetal-Clad Switchgear

4.

Transformers

14. Distribution Panels andAutomatic Transfer Switches

16. Battery. Chargers and Inverters

20. Instrumentation and Control Panels Components that are.identified on Table E-1 (inaccessible. and Aderred components) ar'e not listed on."Table E-.toaVoid redundancYý.. Table. E-2 iridicates internal accessibility of each cabinet. Cabinets'

.h.aveb66een idn tiefeda.requiringthese suipplem-enital intee.rnal,inspection's are tho~s607.ith 'oors 6r panel wtla c ie~s or.

thumbscrews and can: b--eia i y opened d-uringrnormal irit6Aerance'act~vte.

Als~o provided for eachocabinetis a~rpsdi`

liet";n 6schfie ule,,for peorming these internal ins'pectidhs and the associ.ýted stt~ioni'trackinig hjnuber (I'ýlR-b numer)

The SeismicWalkdown "C*eckliits (SWC)-forthe6rompo.ensi ;idenified.in Table E-2 that can be opened fori i*trna*ia.i*

ci~h*`wilberevised:t~the)imeie walk'dowri toindicate'th Iesul se:inte~rial.inspectionS.

of i. "u"p:em"e."..

w. a I

'.I I.

Braidwood Station Unit 1 Correspondence No. RS-14-034 Annex B Table 5-2. Conditions Identified during Seismic Walkdowns Actions Action Complete Item ID Description of Issue Request ID Yes/No (See

-(IR)

Notes 1 & 2) 1VX07J

'Junction box IVXO7J was not mounted per the 1389727 design drawing (Item on SWEL)

(WNo 1.560290)

N 1DOO1TB Tank 1DO0ITB (Diesel..Oil Storage Tank) has hairline, cracks at2.of theo 12-anchor bolts (Found

.1.389743 in areaw.

walk-by.of-Tank'i! DO0.1TD)

• IDC01E OpenS-hdok on one chhain at one iiht nroom 13395981 Yes 1DC02E Open.S-hook on one..cihain at one light in roomn 1395992 Yes Notes:

1) "Yes" indicates that any corrective6 actions resulting from.the issue are! complete

2) "No indijcates that ainy core.dtiveiacti ns. resultingfr*om the issue arei NOTdomplete; Actions are tracked by the IR number in the station C6rriective Action Program.

5-8 C

C C

C CC C

C C

-C~

C rCCL~

.7~>

~ -r

'C E

Braidwood Station Unit 1 Correspondence No. RS-14-034 Annex B Table 5-3. Conditions Identified during Area Walk-Bys Actions Acti.on Complete Item ID/Area Description of Issue Request Yes/No.(See SID (IR)

Notes 1l& 2)

Unit 1 Diesel Oil'Storage Tank..DOiTD, (Diesel Oil. Storage Tank Room (Area.Walk-Tank).ihas.:hairline :rackszat 2 ofthe 12 1389755 No by 12) anchor bolts(Item on44SWEL)

Duringthe.aea.wak-.by~ in the Unit 1 Aux Eledtric.Equipmen~t Room, a

Unit 1 Auxiliary Electric teri'ioarynMESAC was,not properly EquipmentRoom (Are~a

-shiimed atthe.base. The shims were 1389428 Yes Wa~lk-by"3)

'int r*endedt it i::igtb[i

w`e~re:`s`eTe to itght: buit l~r.oose. The

...unit was anchored at the opwith ropes to aV6id4 tipJping.i.

O it ropes unit 1 Fuel Hani nig

.D..ig.

the-a.wa.k*byinthe Fuel Building adjacent to, Hardging.Uidrat El.41-0","adjacent truck b*ay Areý"'Wak-by to th'tudjUck*b*ay.

ca i4 "s

30)q..

appared tpbe.in iolatidi*.BwAP

..1 100-23 *S*ismic Ho; s

.*ig.1390326 Yes

'R bureents for;t~ Tpr~ay Stor~ge ofrMaterials in Categ'ir

~~~Areas

.Unit 1T MEERkRoom

. -ri-ng Fuku"himaSeisrnii.Walkdownsa (Area Wakby5derijpl,ýff 'Id poev dun

.AproximtitblI1", from fr6Are 13976 Ys

_1 vE2Yl i.it** nit 1:.E.

I..

El 451 of Bh iu Buling:

.Unit 'lRW,ST Tii9

.ael*

s, e

ah* ha i

(ra ak-by 3,9Y imuIp-a~

ntef&rdiecly below.!the F~S atc'h.- likel fromi 13908311 Yes previus by s rain. Ther wasnro-wpaterc obthe' copoets in the tunnel SEIMI TuringL. FukUShima' 4 wS6isi Walk,, owns,

• H U..

• • b /~

• b.[lf":th

di i1*;i"i"'::

"'I d

~p4$EIEP~~G~AUX~

-d~yq tirrfo lin~gs and aý

15.B*DG Io"'e h

notmatbe 136

ý1 u n ethý'.minimum require-mý:ento B

`11 00ý-23. 4miesej itemsare l.ocated near~

'Cl4RM~

- ~~ 4 461,'ihth6 A6~

• d fIg t r.' i tr :n"n :~ eefu a..i 44 4

4 44~

4-,-,,

4-4 4-

'~-~':~'

4;4~

4 44444 44 4,.4 44~

4~4 4

444 4~ 44 4

44 444 4

~44 44,,4 44.

44' 4-4-

4 4

4~4--

444 4 4

4-44

'4 44 4<~

4-44.~

4.'44 4-4-

4 4

4 4-,

~44444 4-4

~

4444 44 44 444 44-4 4

4 4444~

4 4

444 44

Braidwood Station Unit I Correspondence No. RS-14-034 Annex B Actions Action Complete Item ID/Area Description of Issue Request Yes/No.(See ID (IR).

Notes I & 2)

During Fuku shima Seismic WalkdoWns'a Shaw Knack tool storage box'was.found SEISMIC.

approximately 3" away fromt safety, HOUSEKEEPING AUX related Bglck\\wallE5A-1i40 wliich does not BLDG:U.nit 1 Aux Bldg meet the 12' minimui requiýirementfs.of 1397680 Yes El 401 Column U-17 BIw.AP:.,100-23.(Seis'micHouskeeping).

This box is located neairC0lumnn U-17 at Elevation h401'. inAux Building.

SEISMIC "Duing F ki"hiia.Seismic HOUSEkEEPING AUX an" sOP:S's.oibsi"'e stora-ge'dcbiniet" BLDG:Unit 1 Aux Bldg approximately:5',higohwas*found less.

El.346' 15' south of than 12..orh6eight lus-1"from azIsafety s-is reItedbl~ckaJl i--erdquirer ts1of 1397642 Yes BwA:P '1-100 (seism6ic hbb~bkeeping)

"15..s5 souL th of: CGoqlun S1i8 8iat-El 346'. in Aux'Bluilding.,.

SEISMIC'ý -During':F:kui6ýimaS:ismiic'Walkd'owns HOU.SEKEEPING AUX "a RP.' tr "a 6'

BLDG:Unt1 Aux Bldg.

hih Was oindlss th'an-12"' or height

El 346.

15' south of

i*pus 12 f*rom2-h sai f

b

• 6&i13I.ckW6Il 1397636.

Yes

..S"18..

2

."r'B'.AP:

11"00_-23*(*iic H 9 `'qus ekepirg 15' sg t fClmn 5-.

• 18.a El.

i46 Bu i B inild SEISMIC.:":

-. 'h..

u.DSdisfmhibu-Ni Wi.dwhs.S HOUSEKEP I NG AUW"X

-anRP s'torage abkil ap'roxirhateý1y 6' L

Uiit1AuBas.found less. than'12-.rh ight-l346 1-12"fromýafety:

r6lated-;13Ib bk6ll..

1397627' Yes Column - 5 2A 45`per requiinrqits of

- 11..

'b i,~ ~

~

~ -- (8'

'i k.:

23 (eisic Hus4ping) P scihou ColmnQ 5 tJ ý 340jn'Au* BUildin SEISMIC....'.

D iUkusii2a sei*smric Wak0'~inS HOUSEKEEPiNG -AUX..two I*.storage cabinets Ip'roximately B LDGUnit 1 AXB.dg i6fang -,werefl 2ndlI-tlan*p 2-or,.

• cEl.346 Clumn ISI-1 j7 I A gh 2'_p from sftqty1'*-dee Wa2'8prquri~1'3976 19 Yes B.,wAP, 1'100.;'23'(Seis;mi 4'oukeepihg),:

.near.,Column. S.-.1,7Tat..El 3_46'.:n!u*.--:

l:......

.Build 'Ag.-

b.-

i d.:

"L i. :i.-:.":..:';L b -...":*. :..i: *:./...i*:.~ :,. "..'.*,...; i

.i

'-'I-

Braidwood Station Unit 1 Correspondence No. RS-14-034 Annex B Actions Action Complete Item ID/Area Description of Issue Request Yes/No (See ID (IR)

Notes 1 & 2)

SEISMIC During Fukushima Seismic'Walkdowns a HOUSEKEEPING.AUX.

S.haw Knaack tool storage box was BLDG:Unit 1 Aux Bldg found less -than 1" away from safety El 364 at Column P-21 related Block wail which does not meet th*e 12" minimum reqeuiremenfs of BwAP

'1600-23 (Seismi.cHousekeeping). This box.is located near Column. L-15: at Eleyation 346',in AuxBuilding.

SEISMIC During Fukushima seismic. Walkd6wns HOUSEKEEPING AUX tw oMM Mb M

ta ra " cabin*ts(caustic.or BLDG:*Unit -.1 Aux: Bldg acid) approximateiy 5,6,. hi5h were El 401i" ait elev, ator:

found ilss than 12" or height p us 12 "

1941Y ifrj*Sae./.*iaie.B.0k**!l.** 9.:er.

1397941 Yes fro safey elaedBlockw a~ll 5A-59 per-

rqequrmenights e..APs t100b-23 ('.Seismic

.H ekleepin of.a.t 0fhele*ator door at.El 401'inAux:Building.

.SEISMIC'.

DburiRg. F hiSia 'Sei*sic Walkdbwns HOLUSEKEEPING AUX

"&n

-. A Pitstogragie:

c e

prpximaely..6 LDG:'*

nitf 1 Aux Bldg.

.high s

f*n.lestha2ii'.2or heigltt El 426.(61umn U-18 '"pu1.i2.-:'fronmsafettYreatebd"B.'ckwan.

,1397957 Yes

ý6A-7p~

'iir"hments of BWAP 1100-23.,(Seismiic He keeping er SISMIC

';D:'.'r-i.-'.

.us"u-hi."-.a.ev-imi ak'w..n.-..sko'w,'

H, U~~K EPNgU a

~

ray storage cabie., bee B.LDn nit

.A B*dg o., ýpprpxiai.tely ýiý5' high EI26oumU18

~

6d~thn-pr~hight vpus 1990 Ye's

-cl.~~~~~~2",frcii~

Safety:related Bl6*kva'l,6A-.74.

..: ]

pe.ieuiei ensof

• e BwAP,11-002.

eismi Hueeepin ) ne~ar, bu mn U-18 OrAuseBuldn 5-li 4

1

TziblCrrso~dne o~-1-344"

alLB-Person..."ri~""l oles-e~

4.

L0

Sf Taint I4on4&'

Table B3 Peisoryinel Roeismi-W t8on-CEcl~

or u-1, "4

~ ~

~

~

~

~

~

~

~

~

en Thbl354 Cid dIid

.drn

.~i akdwsB-

"4444 ik.

4"a k"4, b4 -'I

%Table B4D.

Smr~yo Are Wl-Cheoklists:.BD1 4

Bili

Braidwood Station Unit 1 Correspondence No. RS-14-034 Annex B BI Introduction BI.1 PURPOSE This updated transmittal report is being provided in compliance with the requirements contained in Enclosure 3 of the NRC 50.54(f) letter dated March 12, 2012 (Ref. 6). This new report section, Annex B, contains the results of the follow-on inspection activities that have been completed to address commitments contained in Exelon letter to the NRC, "180-day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f)

Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated November 27, 2012 (RS-12-159). Annex B includes additional follow-on seismic walkdown results associated with NRC Commitments 1 and 2 listed in Enclosure 3 of the above Exelon letter. Annex A of this report was issued as Enclosure 1 of the Exelon letter to the NRC "180-day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f)

Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated December 11, 2013 (RS-13-174).

This update also includes the current status of conditions found during the initial and follow-on seismic walkdowns and area walk-bys as documented in Tables 5-2 and Table 5-3, respectively, from Enclosure 1 of the above Exelon letter to the NRC (RS-12-159) and Table A5-2 from Annex A (Enclosure I of Exelon letter to the NRC, RS-1 3-174).

Commitment I of Enclosure 3 of Exelon letter to the NRC (RS-1 2-159) will be closed as the result of this Annex B. This update documents the completion of the items listed in Table AE-1 of Annex A (Enclosure 1 of Exelon letter to the NRC (RS-13-174)) in accordance with the original completion commitment of outage Al R17 (Fall 2013).

Commitment 2 of Enclosure 3 of Exelon letter to the NRC (RS-12-159) will be closed as the result of this Annex B. This update documents the completion of the items listed in Table AE-2 of Annex A (Enclosure 1 of Exelon letter to the NRC (RS-1 3-174)), in accordance with the original completion commitment date of outage A1 R17 (Fall 2013).

Note: All inspections, listed in Tables E-1 and E-2 of Enclosure I of the Exelon letter to the NRC (RS-12-159), have been completed. All items that were not documented in Annex A (Enclosure I of RS-13-174) are documented in this Annex B.

This Annex B, which includes updates to each report section where the status has changed or new information is available, is in accordance with Section 8 of EPRI Technical Report 1025286, "Seismic Walkdown Guidance For Resolution of Fukushima Near Term Task Force Recommendation 2.3 Seismic" (Ref. 1).

It should be noted that this report follows the same structure as the previous transmittal; however, every section begins with a "B" to differentiate it from the previous report.

B13-1

W-

4.

Bawood ýStation WUnt 1

2 orrespondence, No RS, 14 034.

A nnex B i:

!i

(

V..

See ecton 12io En 1s~~

of E-xelorn" lette'r' to th~e NRC-`(RS-.12-15

BI.3: -PLAWT O!ERIW

,See.Sectfin 1. 6fqd Ecoure I of-Exel6hnl tt6r to_ th~ NRCý (R& -15)

BIW; APPROACH' SeSection-1.4 fEc~ueio E.lo ltetheý N RC (RS-i215)

.61.5 C6NdLUSION,.

All Seismfic Walkdownhs sch~dul.d forA1R1i7 have b"ee 6"rip~

athBridwoodd4 Nu c a I.

-Wer.

Statio*n*,if -1 All f""rte 4

tn i

c' pievioLisly 'd~frd due -tb-iacce§§ibjlit--aioný ithN ýll ight'.(8) df

ýthe reriainihg sL!6p lýmerit_

- 7" ch dulefbt-Al RI'Were

ýSuo e.'erl:..

n' ef d

t N

• ~

W_.

e.

.w m

.o....

r...,e.

v~~~7&r~~e idetiie d~lk uniii Volk-;wo~atiiie ofBys e co-n letter d,_5 Nt 1

fS-215)v corectd.W exbhe-btforone41)

N NreR-ajo' sR qiepd(R)td been 5-3g ofe.

Enclsur I 3d-14 for a peious idnId &on666dition, 64horto trh irequiir red daesg dereii e'atnges.- Tee3)nwsuRertwregereduring the~ follow-ontie;,,

wk'do-t s pr of 6

AlinexA l

(rcdrei 1oEeonltrtoheNC 74).

sevecn ()iw isnsu Repoi~~ddrtsietfe drn h akd6W-ns walkdwn prf~e fork Al n~etin, ite nt6beE-16ý(A andl4, E-of Encl osure.

I fteEeo trt h NRC'ke~ RS12-159%

o'hav 6eýNRCo'RShpl2te by the pend cof Octae A fRei 7 (Faollj 203J l

.: S ? ti wer f*E no ch en..

te"s d

in" f Ajexon A (Enctlosure (1of El*

e5n letter to t e

NRC, 7,

i s A nnex.B.*,

• R

,_~4o sp et&'4 r6:r f6 :.ton:

.to r.- r':,."di a o:

d' owen&:

a!

-...... e

• .By~weeaso:co~mp eteon-as.e u red unng.

sbe e po.rfs'a-s"ol w

-0o*.

.Tk.upeg date,:nnd Io§m, tugs".orf!naa6 ze C.O.:eI

)in:t a":i***it$-i{.*s.

at t:.ý see n n"ewi, s......

u

e. ep rs"dn e rie x'..

"a e s.1ý jnd a

l,13,& 2 L

..X11**ii :iedp §, Wte.ihe Tdbeit-I*S!:

o:

2;*)i

6Yehci our-cii*:a o i

hrc ea. ie Won-let e to*:o~g.*ii:-

th '

.?-P

-24 9

W666 b.-.*:

b

17.

(Fall 203)

All ifem t~at:

w fe~ot, o'dfijn

,fd e.in i:,;~ ::..A

.(.En cl osu ro Wotetrt

.'**!;RS-13

-17 t4) ')m:~i:;:.evdin this.A niin"n:~ er:o!tak.ie~i*ddsg

,.'i i...0g:,* nges: i reo.c 3).ne.,n:s~

ex,*R p B s. e,

.n:r d.d.iigth;flo *c B1-2

Braidwood Station Unit 1 Correspondence No. RS-14-034 Annex B 82 Seismic Licensing Basis See Section 2 of Enclosure 1 of Exelon letter to the NRC (RS-12-159), no new licensing basis evaluations resulted from the follow-on walkdown activities.

B2-1

Braidwood Station Unit 1 Correspondence No. RS-14-034 Annex B B3 Personnel Qualifications B3.1 OVERVIEW This section of the report identifies the additional personnel that participated in the NTTF 2.3 Seismic Walkdown efforts. A description of the responsibilities of each Seismic Walkdown participant's role(s) is provided in Section 2 of the EPRI guidance document (Ref. 1).

Resumes provided in Appendix A of Enclosure I of Exelon letter to the NRC (RS-12-159),

Appendix AA of Enclosure 1 of Exelon letter to the NRC (RS-1 3-174), and Appendix BA of this Annex B provide detail on each person's qualifications for his or her role.

B3.2 WALKDOWN PERSONNEL Table B3-1 below summarizes the names and corresponding roles of personnel who participated in the NTTF 2.3 Seismic Walkdown effort.

Table B3-1. Personnel Roles Equipment Plant Seismic L

Eqimnt Pat Walkdown Licensing IPEEE Peer Name Selection Basis ieer Reer Engineer Operations Engineer Reviewe Reviewer Reviewer (SWE)

Reviewer A. Perez X

K. Hull X

T.K. Ram XM1>

M. Delaney X

X X***

P. Gazda X

X X**

B. Lory X(2)

W. Djordjevic X

R. Richard (Exelon)(31)

X D. Shaw (Exelon X

Contractor)

T. Bortolini (Exelon) (3)

X X

X M. Wodarcyk X

X J. Griffith*

X X

R. Campbell (Exelon)*

X X

A. Zare (Exelon)*

X X

B. Weight (Exelon)*

X X

Notes:

1. Peer Review Team member for SWEL review only.

Additional Personnel for follow-on inspections for Annex B.

2. Peer Review Team Leader.

• • Peer Reviewer for Annex B

3. Individual has retired.

• • • Peer Review Team Leader for Annex B B3-1

, 7'~

K; Br~iidw'o~d.StatlonLJI ii

'Annex.

B

83. _tyehson' &.MsociatesiPersornnel

,J im Griith;.P. E..Mr Grifit is iE gh i':;1-:htS AC 'dao a

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ne engrirein

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`0fsi~lEgneri leSe6 Wiscons-ir'.,Hieis a S.QU-GA'0aified S~isib

ý pilt EigneY~E~d lh as-cm 6

~ede tbe ~T~h~ehpredati6n3 fr~ainingýcu~-6u.rge(.SWE -In addititon 16his

-Irole ni design n ah anl Is' oftru6t

,,sJy-stern;`

tt 10rp'a.plns M Gr'iffifh-:ha's~nanyero e5epe~nend r

'&king do'I no~t t

nuler ~ovwerý.

~an~t, 'Mr.sp

~Ye~k a ntumerous nuc f

nspot of. tonstruction, d~esign,'dol~tage, -and -lkd~~

b ctvitie inIdn-SQU.GWakdowns.

See Seti~h 32~ I ~ Encloure I f xelon letter6 toheN~RC (RS -9.adSeto A32:6f.ý nnexd 3A:.6.609r 1.6 Extte16)a eto

'A-

bsnrl (hE r, 6 eo'_Ex-elon ltr to.the NRC,`RS-i 13-174)1&~ othei bi.3-AbbiTiONALP-ERSONNEL Rik Ca~bl:

~eonEg~~rngtafmebe M..Rikampbl proedflow-ýon sippl~m~n~l Wlkdori for thIs n\\hnex' B.r.:. Carmpb

-is an eletia nieri h

ExplpnIEngirpeeing Dea Iet.e ha wqred ý tBVr'on sinice 18.*e has cpmpleted tlmI6 NTT Ro edion 2.-3 Tra ining Course SE-):

Arm ae: M.Zareis a

.ýStru)cturýal.-En!gineer-Iin the Exelon Engineering Department. She has

-aI'br6 Science, eg-ree in civil enginerig and a-Mster of Science degree in civil/str&5fu ral -engineering. Se has worke at LSallesince 2011. She ha§Ssuccess ul v copee:1irhcEaitos Training and th e'-emTs orce R ecommendation 2.3

. Rat Sismic.Walkdowns; Traininh Course SEý Bryan Weat:MWei eih iaStf niernthe ýExelon.Engineering Department. He h'soe3 years of engineering experience and has worked at resden frteps years. Mr.Weigýh-t copeedteNTFRcmendati-on2.'3 Training Copurse(S.WE) in 62012an t QU Triing in-2009. 'Mr.Weight patcptdint te seismhic walkdowns; an~d area.walk-b.y s as a Seismic Waldn Enine (S WE at Dr n

an Bridw o bd Generating Stati ons. He-al so peformie'd %th'e PE'EEVulnerabilities.Revie -mbased, in part, on the Drede tPE sb ital aog with 'bsiequent c~rrespondence aind sta1tion r'ecords.

B33-2

Braidwoad Station Unit 1 Correspondence No. RS-i4-034 Annex B 84 Selection of SSCs Two inaccessible seismic walkdown items were replaced with identical accessible items during the follow-on walkdowns. OVC05YA was replaced with OVC21YA and 1VP01AA was replaced with 1VP01AC. See Table BC-I in this Annex B.

See Section 4 of Enclosure 1 of Exelon letter to the NRC (RS-1 2-159), no further changes were made to the SWEL for the follow-on walkdowns.

B4-1

Braidwood Station Unit 1 Correspondence No. RS-14-034 Annex B B5 Seismic Walkdowns and Area Walk-Bys B5.1 OVERVIEW Seismic Walkdowns and Area Walk-Bys were conducted by two (2) person teams of trained Seismic Walkdown Engineers (SWEs), in accordance with the EPRI guidance.

The Seismic Walkdowns and Area Walk-Bys are discussed in more detail in the following sub-sections.

Consistent with the EPRI guidance document, Section 4: Seismic Walkdowns and Area Walk-Bys, the SWEs used their engineering judgment, based on their experience and training, to identify potentially adverse seismic conditions. Where needed, the engineers were provided the latitude to rely upon new or existing analyses to inform their judgment.

The SWEs conducted the Seismic Walkdowns and Area Walk-Bys together as a team.

During the evaluations, the SWEs actively discussed their observations and judgments with each other. The results of the Seismic Walkdowns and Area Walk-Bys reported herein are based on the comprehensive agreement of the SWEs.

B5.2 SEISMIC WALKDOWNS The Seismic Walkdowns focused on the seismic adequacy of the items listed in Table AE-1 provided in Annex A (Enclosure 1 of Exelon Letter to the NRC RS-13-174). The key examination factors that were considered during the Seismic Walkdowns are documented in Section 5.2 of Enclosure 1 of the Exelon letter to the NRC (RS-12-159).

The results of the follow-on Seismic Walkdowns were documented in Appendix BC of this Annex B, using the Seismic Walkdown Checklist (SWC) template provided in the EPRI guidance document. Seismic walkdowns were performed and SWCs were completed for twelve (12) of sixteen (16) items identified on Table E-1 of Enclosure 1 of Exelon letter to the NRC (RS-12-159). Two (2) were previously completed as documented in Annex A (Enclosure 1 of Exelon letter to the NRC, RS-1 3-174). The final two (2) items were replaced with identical items due to accessibility issues. Photos have been included with most SWCs to provide a visual record of the item along with any comments noted on the SWC. Drawings and other plant records are cited in some of the SWCs, but are not included with the SWCs because they are readily retrievable documents through the station's document management system.

The following subsections describe the approach followed by the SWEs to identify potentially adverse anchorage conditions, adverse seismic interactions, and other adverse seismic conditions during the Seismic Walkdowns.

B5.2.1 Adverse Anchorage Conditions See Section 5.2.1 of Enclosure 1 of Exelon letter to the NRC (RS-1 2-159), no adverse anchorage conditions were identified during the follow-on walkdowns.

B5-1

Braidwood Station Unit1 Correspondence No. RS-14-034 Annex B B5.2.2 Visual Inspections See Section 5.2.2 of Enclosure 1 of Exelon letter to the NRC (RS-1 2-159), no adverse anchorage conditions were identified by the visual inspections performed during the follow-on walkdowns.

B5.2.3 Configuration Verification See Section 5.2.3 of Enclosure 1 of Exelon letter to the NRC (RS-12-159), no adverse anchorage configurations were identified during the follow-on walkdowns.

B5.2.4 Adverse Seismic Spatial Interactions See Section 5.2.4 of Enclosure 1 of Exelon letter to the NRC (RS-1 2-159), no adverse seismic spatial interactions were identified during the follow-on walkdowns.

B5.2.5 Other Adverse Seismic Conditions See Section 5.2.5 of Enclosure 1 of Exelon letter to the NRC (RS-1 2-159), no other adverse seismic conditions were identified during the follow-on walkdowns.

B5.2.6 Conditions Identified during Seismic Walkdowns Table B5-2 provides a summary of the conditions identified during the equipment Seismic Walkdowns and the follow-on walkdowns. The equipment Seismic Walkdowns resulted in a total of four (4) conditions identified in Enclosure 1 of Exelon letter to the NRC (RS-12-159), four (4) additional conditions in the follow-on walkdowns as a part of Annex A (Enclosure 1 of Exelon letter to the NRC, RS-13-174) and seven (7) additional conditions in the follow-on walkdowns as a part of this Annex B which were entered into the station's CAP. The conditions were assessed and it was concluded that the conditions would not prevent the associated equipment from performing its safety-related function(s). The conditions identified by the SWEs during the equipment Seismic Walkdowns and follow-on walkdowns were concluded to not be adverse seismic conditions. See Table B5-2 for a summary and status of the conditions identified.

Two (2) SWCs note that not all middle anchorage was visible during the walkdowns of certain control panels and cabinets:

1AP06E - Front and rear welds in all cubicles were accessible and were viewed.

Some middle welds in 12 of the cabinets were accessible and were viewed.

o Based on the acceptable quality of anchorage viewed and found to be installed per Detail 47 on Safety-related drawing 20E-0-3391C, it is reasonable to conclude that inaccessible welds at the middle of each cubicle (which would have been installed concurrently with the anchorage that was accessible) also exist and are of acceptable quality.

1RD05E - Plug welds at front and back of each cabinet cubicle were accessible and were viewed.

Based on the acceptable quality of the anchorage viewed and found to be installed per Detail 40 on Safety-Related drawing 20E-0-3391D, it is reasonable to conclude that inaccessible plug welds at the middle of each cabinet cubicle (which would have been installed concurrently with the anchorage viewed) also exist and are of acceptable quality.

B5-2

~BraidWdod Station Uit 1 Correspondec No.

&'14-0341

-3,:.A

.tARA WALKý-BYS Thirt~een(1 3) additional Area WaMlk 'bys efore fo radod nt

-r dotunme'nted in this; r.ep ort' Thie key, 6examninairon factors thaitSwere' tconsidrduinAeaWl-y

~re ocu~entd in~ndosur I o theExeln ltter tto the N RC&(S1219 Teiresufs of ;the a'dditidnnal Area6' WakBirdcmne nte-Area1 Walk-B Checklists (AWVCs) included nApendix. B;o this AieB

eaaeACwsfle

~6t or 'aharainspected A singI6AWC~w'a c:ýeedfrremwer orethan on 'SWEL1tem V5I w

at& d

.c e

B5e 3.1 6Ndti n

d r I~

Ire 'A'lak alkB No~con Identifisw d 'du.res Nocnditons e

ne id tjied duringý teAe-al-p associatedwitht tel folw-on

'wa'lkdo'wn~s.

~Du~n"~theprevousseimic alkownrcoditios were :identified 'an entered fit o CAPý-.All,conditionis wi§ere cbo~d as l,.igt~d'irTifa L3oEli 1-6~h-,k nlte tohNR (S-1 5)d TbA573o Anx A(elhetteto' the NRCR--

No'cndii~nar Ii steinthis ArinexB.

B5.

SUPLEENTL NFORNATION ONrELE TRICA CABINET INTERWA NPCIN Follow-o6n 'walkd6;Wkn~scom'plete-d the' -sup;-plem'entai intbinal inso~ectiohs' of 6'ight,(8),of -the oQpe tm on Table&E-2 of'Endld§urei 1 VfE~o etteýtpi'th e -NC R(RS1

5)

No

~d--r co' diti~ns We'rýe idenitifi~d d ig. tese suppennilienaisetii:

SeiicWald~w Q~~klstsSW~~foth' eiht 8) uppemental cabine inspect ions were comnpleted 'bnd docUrmnei~e in Appendix BC. of1 tis-AnexB Theý completion. of thes egh () nspections1 in c~onjunction with, thpih h(8 npcin ompetdi Annex A resolval ofteriibm rsne i al of nlsure 1 of ýExelon These checklists reference the, previous SWVCs ofrEnclosure I of:Exelon letter to the Note:,-Ques§tion 11 b,: "Are 6dja~e&ht cabinets securedmtoget..he r?" wS'asee No oU for-11 f.r

a. feestan ing cabines bserve d.uring ts u*pe-plment*

al,-.c, bi. etih s**..-s.*.'tins, with,.

a. comiment below stating the cabinet wa's freestanding.1 This does lnot 'indicate an ad.'ver's'e geisrbic conrditifn tA is merely mle'aint 'to state there are no adjacdent aiest which the inspected iteim :may'be secured, Table B.5-2.iCo~nditions Identified during Seismic Walkdowns______

Acti.Ons Complete IeIQDescription of Issue Action Request Yes/No Ite IDID (IR)

(See Notes)

J unction box 1IVXO7J was not mounted per. the I VX07J design drawi ng (Item on SWEL) 1389727 Yes The anchorage was evaluated in calculation 7.16. 1O.2-BRW-12-0294-SRev._0,_and found to be&_____

B5-3

i

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'_'L "R~4Q 4--

- ~~

~Ann 3.....

0 I

. I A -ctions CMompete Iterm ID ecion of lssqeý q

cipRqet YsN

.Notes)

-acceptable easqs..WOd 156 02O:as oted inT able5.,"......

2h" b' ben' V~cle

.Uj~t dR ig rawing fr JUnction 06 VOJt

."~ ~ ~ p a e 2.l# en:#an.

d:-. f. ";

'B,

.:,-k,:ý 1,.;

VX. 7

' ::,.- t -,

b*...."

...d.. uet as-but taioragecondi

.ios'.-'-,.

158 8309, EC 39f.73is,6re.ated totrcackthe&ra*w.ingrevision EC396173 No required t6 "doi f Vthe a-4Lbuiltc, uditios

'Tarik1 IQOO1TB i6 Ol trae an) a 1:3897.4 1DO64Of1TB hIrin"'-6cra~cks-at2-b-th 12 lnhrbolts, (Found i aj.ea wakby'-d 6f~ni 1 J

-E03900 19Ye l1OCOI E Ipe S 6o n n cl t

elght inro m13 5 8 Yefs 1DCO2SE Oi

-ook -on one~chain at one igh inr1

'13959,92Ye Topýfastene eds tot e repIaced 1436163 IAPI2EYes WR 41658.3

-Wire coyar in the -northeast corner of the panel is

.1434632 1 PL08J only partially enigaged W

163 e

Screwdriver found obn the floor inside the rear cabinet iAR38E 1433712 The re~solution of this condition is contain~ed withinYe the IR noted.

It wais obse~ivd: that theirear oficubicle 5 was.

1AP05E missing th.e two bOltst tat would-fasite'n it tod the1540 adjaienit cubicle. This is not a seismiic concern. See No*

WO 01677341 IR~and SWC.

It Was bbserved that the heat shrink at"the cable jacket dbes, not fully contact the cable jacket.

insgulation at the rear 6f swItchgear cubicles 4, 8, 9, 1598 1APO5E 10, 11 and 18. This is niot a seismic concern. See IR and S.WO.

Yes*

The resolution of this condition is-contained within the IR noted.

B5-4

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~

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oe'

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hbbf'Jc th uie jn al~ti-ha\\.'

Ti.I 1.N5o3 bo seiom i

u n.d erd. This r..tv.seismic.concern.

W,.01,67*734 0..

fro i ths cubi6l"t. 'Thi's isnoitia

?pjsI c cocent1601

.Scbtae~ It adSW.

replaceýidh j in v-R'i 8 fd p

er W R6in (SUPLMENAL 0044199anhfd WR s~

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WR 00443198 aShipn t

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most pare uebxs e

00DC4I:11.

anadSW 1528873.

.8.No (SUPPLEMENTAL) 091/031Tp5hsbe6eoe fo h

pr R042273 e

fseholqrsn~.

a dý cabl t-sSlaed Operator'for valve is in contact with gQusset plate and.

'1560094 gratilngfor adjacent gallery. Trimming of gusset 1 Y08 plate and, grating to provide adeq~uate clearance ECR.411528 requ'ired..Ys W0 01674809-.

WOclosed 11/4/2013.

.01 Notes:

1) "Yes" indicates that any corrective actions resulting from the issue are comrplete

2) "No ".Indicates that a~ny corrective actions resultin.g. fro~m the issue are -NOT complete. Actions are tracked by the IR number in the station Corrective Action Program.

• Denotes new item identified during follow-on walkdowins as'a part of this Annex B.

135-5'

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"sin66:C

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.. Re-iew of the submittlrpr

• P~rovide ýa summary ýreport o'f the peer review process in the submoittal report.

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