ML17262B037

Summary of 920916 Meeting W/Util at NRC Headquarters Re Util Current Plans for SG Replacement at Plant

ML17262B037
Person / Time
Site:	Ginna
Issue date:	10/06/1992
From:	Andrea Johnson Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
TAC-M84004, NUDOCS 9210160107
Download: ML17262B037 (98)

Text

~R RECy Wp0 Cy A

~O

<<+*++

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 October 6, 1992 Docket No. 50-244 LICENSEE:

Rochester Gas and Electric Corporation FACILITY:

R.

E. Ginna Nuclear Power Plant

SUMMARY

OF MEETING WITH ROCHESTER GAS AND ELECTRIC CORPORATION ON STEAM GENERATOR REPLACEMENT, SEPTEMBER 16, 1992 (TAC NO. M84004)

Rochester Gas and Electric Corporation (RG&E), in a Nuclear Regulatory Commission (NRC) meeting on September 16, 1992, at NRC Headquarters, presented their current plans for steam generator (SG) replacement at the Ginna plant.

RG&E made the decision to continue nuclear power generation with the Ginna plant in mid June

1992, when filing a report with the New York State Public Service Commission.

RG&E has been actively exploring procurement options since early July 1992, and determining costs and risks since early August 1992.

RG&E's decisions to date are a result of their Integrated Resource Plan (IRP), which includes a conservative 15-year plan to the expiration of the Ginna operating license in September 2009.

A copy of the meeting agenda and discussion material is included in Enclosure 2.

Enclosure 1 is a list of meeting attendees.

RG&E's final decision however, to procure new SGs is targeted for sometime before the end of December 1992 (two bidders, Westinghouse and Babcock and Wilcox).

RG&E's schedule would then include SG fabrication from January 1993 to January 1996, preliminary engineering and preparation for plant design/installation from January to June 1993, detail design engineering from July 1993 to January

1995, pre-outage modifications from March 1995 to February

1996, and SG installation from March to June 1996.

The major issue presented by RG&E in the September 16th meeting was SG replacement by new SGs, including SG transport, containment integrity, SG drop potential, effects on UFSAR/Technical Specifications, ALARA, and acceptance testing/examinations.

RG&E also discussed the status of their existing Westinghouse Series 44 (Inconel 600)

SGs.

RG&E discussed their evaluation of two potential options for SG replacement:

(1) one-piece (full SG assembly) through the containment

dome, and (2) two piece (steam drum separated from the "U" tube bundle) through the equipment hatch.

Options applicable to other plants were not applicable for the Ginna plant.

RG&E's current preference is one-piece SG replacement through the containment dome opening directly over each of two existing SG locations.

RG&E's preference is based on minimizing containment handling and movement, shorter outage schedule (74 vs 84 days),

less expensive, less radiation exposure (300 man-rem vs 400 man-rem),

and installation of a full shop assembly.

The removal and replacement would be accomplished using a large mobile crane.

RGEE went on to discuss the potential containment roof construction

openings, SG rigging and liner plate reinstallation weld details.

9210160107 921006 PDR ADOCK 05000244" P

PDR, ImC HU.'(iXiVifiii~CCRC 8~

I

/

P"

(

/

g" October 6, 1992 RGS.E also discussed using principally a 10 CFR 50.59 review process (facility

changes, tests and experiments conducted without prior Commission approval).

RG&E discussed using a licensing approach where necessary, i.e.,

a license amendment per 10 CFR 50.90 and 50.91, to deal with essential Technical Specification

changes, and appropriate NRC inspection/review of safety evaluations and responses to NRC questions.

Enclosures:

1.

List of Attendees 2.

Meeting Agenda and Discussion Material Original signed by Allen R. Johnson, Project Manager Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor -Regulation, i

cc w/enclosures:

See next page DISTRIBUTION w

Enclosures:

'Docket Fil e >

A. Thadani NRC--5 Local.PDRs J.

Calvo PDI-3 Reading G, Lainas T. Hurley A. Johnson F. Miraglia T. Clark J.

Partlow OGC W. Russell E. Jordan S.

Varga G. Holahan J.

Richardson ACRS(10)

V. HcCree J. Durr, RI W. Hodges, RI J. Linville R. Cooper, RI J. Strosnider R. Jones DISTRIBUTION w o

Enclosures:

B. Liaw G.

Bagchi R.

Rothman C.

Tan W. Butler G. Johnson E. Murphy J.

Guttmann J.

Caruso H. Abelson T. Hoslak, SRI F. Orr J.

Cunningham T, Essig J.

Lee J.

Craig E. Akstulewicz J. O'rien K. Desai G. Hornseth W. Lazarus, RI 0FFIGE LA P

NAME PM: PDI-AJohnson PD PDI-3 WButler DATE (0

92 LO 92 6 /4/92 OFFICIAL RECORD COPY Document Name:

HTGSUM,GI

>h V

U

October 6, 1992 RGLE also discussed using principally a 10 CFR 50.59 review process (facility

changes, tests and experiments conducted without prior Commission approval).

RGEE discussed using a licensing approach where necessary, i.e.,

a license amendment per 10 CFR 50.90 and 50.91, to deal with essential Technical Specification

changes, and appropriate NRC inspection/review of safety evaluations and responses to NRC questions.

Enclosures:

1.

List of Attendees 2.

Heeting Agenda and Discussion Haterial A

en R. Johnson, roject Hanager roject Directora e 1-3 D'vision of Re or Projects - I/II 0

c ear Reactor Regulation cc w/enclosures:

See next page

V

)

i' h

Dr. Robert C. Mecredy R.E.

Ginna Nuclear Power Plant CC:

Thomas A. Hoslak, Senior Resident Inspector R.E.

Ginna Plant U.S. Nuclear Regulatory Commission 1503 Lake Road

Ontario, New York 14519 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Hs.

Donna Ross Division of Policy Analysis 8 Planning New York State Energy. Office Agency Building 2 Empire State Plaza

Albany, New York 12223 Charlie Donaldson, Esq.

Assistant Attorney General pew York Department of Law 120 Broadway New York, New York 10271 Nicholas S.

Reynolds Winston 8 Strawn 1400 L St.

N.W.

Washington, DC 20005-3502 Hs. Thelma Wideman

Director, Wayne County Emergency Management Office Wayne County Emergency Operations Center 7370 Route 31

Lyons, New York 14489 Hs. Mary Louise Heisenzahl Administrator, Monroe County Office of Emergency Preparedness ill West Fall Road, Room 11 Rochester, New Yor k 14620

)

Y~

ENCLOSURE 1

Se tember 16 1992 GINNA S.G.

Re lacement Meetin List of Meetin Attendees

~Name Title Al Johnson Project Manager NRR/DRP/PD I-3 Phone No.

301-504-1497 Bob Mecredy, Vice President RG&E R.

E. Ginna Nuclear Production 716-724-8069 John F. Smith, Director S/G Replacement George Wrobel, Manager Nuclear Safety

& Licensing Brian Flynn Engineer Bill Papproth Bechtel Project Manager Steve Routh Project Engineer Lynn Connor Geoff Hornseth Materials Engineer William Lazarus Section Chief Tom Moslak SRI-Ginna Kulin D. Desai Jim O'rien Goutam Bagchi R.

Rothman Section Chief Chen P.

Tan RG&E RG&E RG&E Bechtel Bechtel STS NRR/DET/EMCB NRC-RI NRC-RI NRR/DST/SRXB NRR/ADAR/PDLR NRR/DET/ESGB NRR/DET/ESGB NRR/DET/ESGB 716-724-8863 716-724-8070 716-546-2700 Ext. 4805 301-417-5662 301-417-5945 301-652-2500 301-504-2756 215-337-5231 315-524-6935 301-504-2835 301-504-1134 301-504-2733 301-504-3306 301-504-3315

ENCLOSURE 2

GINNASTATION STEAM GENERTAOR REPLACEMENT NRC PRESENTATION SEPTEMBER 16, 1992 WASHINGTON, D.C.

ROBERTC. MECREDY GEORGE J. WROBEL JOHN F. SMFIH

~

)

t

~

>'I K

44.

~ INTRODUCTION WROBEL

~ STATUS OF EXISTING STEAM GENERATORS SMITH

~ REPLACEMENT STATUS SIVKXH

~ OVERVIEW OF DECISION IMMGNGPROCESS MECREDY

~ EVALUATIONOF REPLACEMENT METHODS SIVIITH

~ LICENSING CONSIDERATIONS WROBEL

~ SCHEDULE

~ OPEN DISCUSSION

0 4 ~

1>

~

INTROD TI N

~ INFOKNATIONALMEETING

~ DISCUSS CURRENT PLANS FOR S/G REPLACEMENT

~ NO FORIVIALACTIONREQVKRED BY NRC AT THIS TIME

~ REPLACEMENT DECISION NOT YET IVER@)E

~

J

TATU F EXISTIN E

44 TEAM GENERATORS

~ REPAIR STATUS

~ 1992 DEFECTS

~ PRESSURE&'OSS

~ TUBE SUPPORT PLATE DEFECTS

~ DEFECT PROJECTIONS

C

REPAIR STATU S/G-A S/G-B UNREPAIRED TUBES 2520 (77.3%)

1813 (55.6%)

PLUGGED TUBES 185 (5.7%)

313 (9.6%)

SLEEVED TUBES 555 (17,0%)

1134 (34.8%)

3260 (100%)

3260 (100%)

4 J

4

1992 DEFE T DEFECT TYPE S/G-A S/G-8 ROLL TW&lSITION 189 63 CREVICE 34 11S OTHER 3

TOTAL 226 1S6

,tt

GINNA STATION SG PRESSURE HISTORY 780 760 p

740 S

I G

720 700

~

~

~ ~

~ ~

0

~ ~ sf+

~

~

~

~

s

~ t t'

~ 0%

~a

~g

~4

~

gp

~1

~ Q

~

~ ~

<<0

<<<<0 <<0 0

~

~

r. r.

o

~

~ 5

~

~

~

A ~

At o 1

s

~ e 0

~ 0

%o 750 600

¹ 450 300 S

150 680 TUASINE VWO V V 1979 1981 1983 1986 1987 1989 1991 1993 YEAR RGE 3/91 SG PRESSURE PLG'Ds EQ PLG'D V REFuaLiNO

L

~

C g1 t

E P

RT PLATE DEFE T

~ NO TSP DEFECTS FOK'G) TO DATE

~ INSPECTION PROGRAlVI INCLUDES:

- 20% FULLLENGTH BOBBINCOIL

- SELECTED MjRPC INSPECTION OF TSP NO. 1 AND NO. 6

~ SIGNIFICS'SP DEFECTS

- REDUCED OUTPUT

- EAIUY RETIREMENT

~

11'\\

'4 s\\

STEAM GENERATOR TUBESHEET DEFECTS 250 DEFECTS 200 150 100 50 0

1985 1987 1989 1991 1998 1995 1997 1999 2001 2003 2005 2007 2009

~ A-B/G mm B-S/G JANUARY 18, 1991 FIGURE 9

~

~

STEAM GENERATOR TSP DEFECTS 1200 DEFECTS 1000 800 800 400 200 1991 1993 1995 1997 1999 2001 2003 2005 2007 2009

~ A-B/8 IB-S/G JANUARY 18, 1991 PIOURB 10

k

'I 7%

P

REPLACEMENT STATU

~ MEMBER OF STEAM GENERATOR REPLACEMENT GROUP

~ BIDS RECEIVED IN JANUARY 1992

~ SHORT LIST OF BIDDERS

~ NEGOTIATINGWITHBRW AZG) VVFSTINGHOUSE

~ CURRENTLY NOT PLANINGTO UPRATE

~ PLAN TO ADD ADDITIONALSURFACE AREA

~ REPLACF28XZA'ECISION BY 1/1/93

k P

J ll P$

4

VERVIEW F DECI I N MAKIN PR ES

~ INTEGRATED RESOURCE PLAN

~ RGE DECISION lVhVCINGPROCESS

~ COMPETITIONFROM NUG'S APG) IPP'S

k

~

1I

INTEGRATED:RE URGE PLAN-k l4a CX D

O.

0 0

E E

C$

E C

tO C

C4 l7 v5 C

f

)~@i:~~~<<

>~Pp$ C.~

gP YA4%is's.e.<e.'iw

.A@v~

ACR

'.~'ae>> "~.". ~w... <<su.>r.x::~cb~>cc.::cwl~v,"

~..p...aud 7

w/

4 BlBctl tc gefH9fgf)gr'( pJgpqj)q(",;

oncl"l&ng8 DSM plpn Octobe." 'f99'} PSC,:

Ir.tt':,"-,;-

I C

"5 Jje'i" pJ8flnlAg pBt"lo(:

XC U

5

F ~

"ia INTEGRATED RE CF. PL Businesp Deqiiion:

<:sc wmaw:em>.+A~~Ar+~~w~~m w+Nut'~>~i..v.;.-.a~..i.~a-.x.u: ~~~:c.m c%.

r:.".

~ 1 f/'MA'f.'ong-ravO%'"GSAi pit:i <

IAdUBtf'Igf'@VS'tSNCf f'Sf'."AtloA GI88t:l Slt'll'i': 0'Sfi"";-"lists"":

C.IAA.'-': 8"88)~'88f'Nfa",:::.

t-'5!p RGB&'A::

,lj

1

~ ~

4'

,:-';,::-:,.199$ :P~,

i SUMME'R Lo@54':..'NPai i'xistiricj::8 Expe5Yc4, ~$8rvs".-:

Required Capability wIra DSM Required Capabilityw/DSM, ri.........

~ '

P

'4

,C, l

19S2 1%8 1994 1995 1996 1M7 19M 1999 2000

%01 Year

-C

~

&2 SSOS SO'Ol 28ih SOOS SOO7 SO'I Ate solo gl

~

gj system Gilboa Green Mounta:.".

Hydro Quebe".

k:.')'c! o Stabon."

Stabon Station 28 Qiscellaneo Niagara NUcle-":

Ginna Nine MiI.".

Fitzpatr jwlr

<~/

g~g Coal R0%5ll 'l

=.=:

Re~I~'uh5ell

'-'usselll

~ '.";;

Beebe f

8585M 13

'Nrce &

At@@My Cog On E". Oi 06wBQQ 6 3NNPJSUM.-LOPE,'myo ss

gg,

Sr p'/

PJ

~76.

at ~A 11

~C~~;~

Ek/4'tiAO,::,F'l-:0::

i,=-

n-s't r.

l:ter',tsrt.'01 A'SVAMo0ssAtm+si~~;QhavA>>~

r'IIueejII-:-:"'-

':I

=-2.:, --'='4

'~

tIV c~g:::-;::.'::

p.i Lief':UH&8"-"::

J4J

.S/

I'5PIWCli'::. "

I-mPAg:

l6%'

01%i:.'aI:ubb@re:

u~.v:..m+~.vkecc.

1rw

.I S

0

0).C 0 PPH8%~

I'i"'PIRc% 'O'C':

00 1'0

$ 1 00 19.90 (mtItioas.j atsa4lSJMmit t't.

J.

ACO44 PN 1t

~

4

~ ~

$ 40

,7'0

<s70

<97:

1889,=,'- 196';

I I

2000 2005 20tO

,\\

Jl I~

/ ~

4 g r

GIMME I Annual Capri'a~l &pendJ Sure" gC

. '1990:(m'illloas')

$ QO It I

lt I

iso

'M,11AÃtt

%Yhr.L C.~~

I.;

C~+

Ig.

r grt gggypf/I' +IIv"!

I, r

'\\t r Tt

'$.20

~I r

810

':?"

'I tr. "

~.. ~.:lf,. ~

~ 't I iC I

I 209.>

2006 20',0 J

~

Mi \\'Q,.~

~

~

5,I 8~f gi I 55 5

cf'.

k.

5 55, 5 ~

~ I 5i t

C 54(.5',i.a ~ 1;,"'" ~ ~4'~555 NTEGRATED

~~+55i55'a pkRbv~'~WC55t.5~

" JW~~>:-.';Waist..~s 5:-.n,tC "u:g~tt~~tt.;t55;

,. ernat~ves t

ja',s

./C'C

'(c nev! coa,'"fir'sd gsnsrRtlc.".:

.-- nev! gaa-fASQ gsplSrRtie",p cogeneratio<

technologi~;:";

increased deman.!

elcfe f'nanaaeme'r:::.

/F, long-term catpacii~

cont-', ec'i'p 5

I I

5 I

~ I

l%

CE PL

II TfI

) V j i.>>.p

-X:-.; A hZt

~

t 4

~>

Glll08, I@'~~i

'sUIIIJ.'ontin'":"::

operatic; C'68i 2 U U"':

cleclclc'team gB":

replac.:

n IC Y>

IW~Ee

-=-:.NL4~

~yyNjf'-W'.

+/h'tV ~ AN@'t'ai.faA OAYdCAVA44%OCTAtAkA+k&.VA1AA~~P).'th.::1Ãl PX..r~Q',Oht.'Cl',

C:LKr AVJZ

~

~RDI.

DSf~"

RU4S)'>'-:-":

"R'ui's'st) gee~A.T

'M@4 "j-lk""I:~9-

"~ 0 VNi::-:::

8gr-."f p45'-"-':l':-.='r J

N'k~'iiQI4I:

%l:-:'-"'~1'p

>a-i;

~ <

. f!

ps('frj::.

I:

C:

P fr I

j t;

II II II I

INTEGRATED rl hÃ:

. 1""~3.;M.~VC:

~X,~~n~ou~'~.~~~1~

corItr~jp'.:.:;:

888l3ee":":).-"'

""5 i

~

\\

retire b-200G:;.

86 G'l ASS;,

2OQ,:I A

bu:::

I 1

)I II l

retal

'f.

80 C",

200' I

)

I

"-"===. P:L Af~":

d /NP"i.

T

~M mS~S ij'iaa~irC;%a+. ear:Z:O..-:Aazkaakia~:;.C:W r

,, rRINQ:f-".> ':g~g:"

fA

~ ~

Ug t()

't88:": M

".:,'1'1; 1%r

.gi'/g'7g l

I>

.:C;

-.'f~~~

i ff A

f

'f J

r tf'--:

f&,

f~l.

.f

~

'ff:Jff*

IN

.. /ion

~~"

,:/PP

-" explore f

f 4

f""~;!...Oa~D4 4$$k/'91/QR ~

deiermin.- cost!; a@i;'riel!K gf

'A'eplacernen';

decieo-':".

'Ik/81fS'" ~

I

.I ff

.!'EGRATED RESQ

-,E'='.PZ f.;

i em8.:SNn8::84~<.'iw'/4N@ff-'

CAANit@. qytCYPt+ffPjj~dg~ijfygffy~~V' procureme'r'ii optlot';:'::

"F7'f:1/Sk ip

~Pi rf'.

f,C

.'4!

'f/

fr.

f,'4

t\\

,C

>:I

EVALUATI N F REPLACEMENT METHODS

~ POTENTIALOPTIONS

~ TWO-PIECE

~ ONE-PIECE

~ CURRENT PREFERENCE

ct

'I Q

$4

P TENTIAL PTION

~ ONE-PIECE THRU CONTAPtMENT ROOF

~ TWO-PIECE THRU EQUIPMENT HATCH

~ ONE-PIECE THRU EQUIPMENT HATCH

~ ONE-PIECE 1'HRU CONTAPMENT WALL

~ TWO-PIECE THRU CONTAINMENTWALL

~ LAST THREE OPTIONS NOT FEASIBLE FOR GINNA

~ OPTIONS ONE AI'G) TWO FEASIBLE FOR GINNA

~

~

/

ke

., R. E. Ginna SGR Study

)

rr Figure 4.3.1 TWO-PIECE STEAM GENERATOR RIGGING TO CONSTRUCTION TII6LLEf CONTAISKHT TO CONSTRUCTION TROLLEf T/RUNUAf RAILS EL.33I'0'TE COT.

I. STEA

'EL ELo2ll'-4' sa a oo so S ePI CNN OOCTNRR I NISSILE SRIELO TG RERAINEL.2B'-R'MtAY 8EANS I rroNpN Woo II TRANSPORTER, EL.2TO'-0 Bechtel Job No. 21175 4.3-7 2117$.0000tudy%lnnaSGR

~

~

at I',a

~ T a

TW -PIE E TEAM ENERATOR REPLACEMENT

~ REMOVALSEQUENCE

- AUXILIARYLIFTINGDEVICE INSTALLEDON TOP OF EXISTING BRIDGE CRAXE

- VESSELS SEVERED AT TEV&lSITIONCONE AM)RCS NOZZLES

- EVALUATETHE NEED FOR PIPING RESTRAlWTS

- STEAM DRUMS REMOVED AI'6) STORED INSIDE CONTAINIVKNT

- COVER PLATES INSTALLEDON LOWER ASSEMBLY TW&fSITIONCONE Al'G) ALLNOZZLE OPENINGS

- DECON OF LOWER ASSEMBLY

- LOWER ASSEMBLIES REMOVEDTHRU EQUIPMENT HATCH

- LOWER ASSEMBLIES TW&lSPORTED TO FINALSTORAGE LOCATION

~

e

TW -PIECE REPLACEMENT CONT'D

~ INSTALLATIONSEQUENCE

- APPROXIMATELYTHE REVERSE OF REMOVAL

- LOWER ASSEMBLIES MOVED FROM STORAGE LOCATION TO AREA NEAR EQUIPMENT HATCH

- LOWER ASSEMBLIES RIGGED INTO CONTAINMENT

- STEAM DRUMS WITHNEW MOIS'I"URESEPERATING EQUIPMENT RIGGED ONTO LOWER ASSEMBLIES

- DRUM WELDED TO LOWER ASSEMBLY

- PIPING WELDED

- PRIIWWY/SECONDARYSIDE %HA)RO'S

- INSULATIONINSTALLED

~

~

)J g1 4

NE-PIE E TEAM ENERAT R REPLA EMENT

~ ONE-PIECE S/G REPLACED THRU ANOPENING INTHE ROOF OF CONTAPMENT

~ OPENING DIRECTLYOVER EACH STEAM GENERATOR

~ S/G REMOVED WITHLARGE MOBILECIVZGE

~ REMOVALSEQUENCE

~ INSTALLATIONSEQUENCE

e C,

1 f-q ~

ONE-PIE E TEAMGENERAT R REPLACEMENT CONT'D

~ REMOVALSEQUENCE

- LMLPSONTWPlSI-LIFl'SSEMBLEDIN PMGCING LOT AI'G)

LOADTESTED

- TOWER CRANE ASSEMBLED ADJACENT TO CONTAPVrG<NT

- TRAIMSI-LIFTMOVEDTO AREA ADJACENT TO CONTAPtMENT

- TI&NSI-LIFTPOSITIONED ON SPECIALLYDESIGNED FOUM)ATION

- CONCRETE OPENINGS WlRE SAWED UP TO LINER PLATE

- CONCRETE CHIPPED BACKTO EXPOSE REBAR

- LINER PLATE CUT AM)CONCRETE/LINER REMOVED

- SECOND LIFTINGTRUNION INSTALLEDON EACH S/G

- S/G CONNECTED TO TRANSI-LIFT

- PIPING RESTRAPKD gF NECESSARY) MW CUT

- S/G REMOVED BY RAISING HOOK Ut'A'ILLS/G CLEARS CONTAPMENT

- S/G LOWERED BY LOWERING HOOK AM)tuDSING BOOM

- S/G DOWN ENDED AI'6) LOWERED ONTO TRANSPORTER

- S/G T1UWSPORTED TO STORAGE LOCATION

4

~

iC A

NE-PIE E TEAM ENERAT R REPLACEMENT CONT'D

~ INSTALLATIONSEQUENCE

- ESSENTIALLYTHE REVERSE OF THE REMOVALPROCESS

- PIPE WELDINGTHE SAITH< AS THE TWO-PIECE

- VESSEL HYDROTESTED IN 'I'HE SHOP THEREFORE ONLY NEW WELDS REQUIjRE TESTING IN FIELD

- INSULATIONSTARTS AS SOON AS VESSELS ARE SET

- ROOF LINER PLATE REINSTALLEDAI'G) TESTED

- REBAR REINSTALLED

- CONCRETE PLACED

- STRUC'IVRALINTEGRITYTEST PREFORIMZD

A V

R. E GlnneR ~ - updited ~g~gy g~

FIGURE 4.2Q Bechtsf Job Nos. 21 175 and 21l48

r

~

~

R. E. Glnna SGR Sfudy Figure 4Z.2 CONTAINMENTROOF CONSTRUCTION OPENINGS (Page 1 of 2)

N AZ 60'ONTAIQKHT JI IIIIIIII I

I 30'-0 L. sTH GEN l\\\\llIl AZ 125 1

1I

\\

1

\\

lIIIl 1IIIIIIIIIII I

J AZ 240'

~

~

~

~ L tie hf47C'.2-27 l111L4%4~ ++

e t

R E Ginna SGR Study Figure 4.2.3 CONTAINMENTROOF OPENING CONSTRUCTION SEQUENCE REIVIVE VIA IlIRA 8'AIER AIO JlCEIIAHER~

O'DEEt CUI Vll DIAIOO SAV EXtAIOED

/

VIK If'IRL DttlH CUl VIA VIRE SAV~el ~ REBAR IS LAYERSI SEQKIII ID 6E REIOVEO CUI LIIER tLAIE

'DRASIVE SAR CUl

'5 CTION B

ALL DltIll II% SAV CUl 2'-0'it CONCRElE PLUG PLAN

~t SIEt 0 SIft'I'IEt0 CONCRDE PLUG RENOVAL SEOUENCE BOW Job Na 21175 42-2Q IIIMCfftfSNaetylCSSISS.OM

t J

J(

~

R. E. Glnna SGR Stvdy Figure 4.2.2 CONTAININENTROOF CONSTRUCTION OPENINGS (Page 2 of 2)

TO CRANE CONC PLUG RDNVAL FHQK Sjll GBI 30m 0r COHTAIQKHT COtIC PLUG EL.366'-0 EL.319'-0'I

'-0'9'-0'~Sp go SPRING Lll~k EL 330'-8 SECTION A

Bechlsf Job No. 21175 42-28 seen.mss~~ ~

~,

R. E. Glnna SGR Stvdy - Updated February 1gg2 Final Revision May 1gg2 FIGURE 4.2-1 ONE PIECE STEAM GENERATOR RIGGING (Page 1 of 2)

I I

Bechtel Job Noa 21175 and 21748 Page 4.2-24

~

~ )

~'

R. E. Glnna SGR Study - Updated Februey 1992 Final Revision May 1992 FIGURE 4.2-4 ONE PIECE STEAM GENERATOR RIGGING (Page 2 of 2)

I I

I Bechtel Job Noa 21175 and 21748 Page 4.2-25

~

I 4

J

R. E. Ginna SGR Stucty Figure 4.2.4 LINER PLATE REINSTALLATIONWELD DETAIL 0,

0'g:

~

oP EXIST. LINER E BACKING BAR TACK WELDED TO INSIDE OF EXIST LINER E FROM OUTSIDE NEM LINER R. MITH STIFF TO MATCH EXIST. STIFF Bechtel Job No. 21175 0II744$ 0%aalP1%aaakM

C y

\\

.a ~r giv~8~

NT PREFEREN E

~ ONE PIECE REPLACEMENT FOR THE FOLLOWINGREASONS IES IN CONTAINMENTHANDLINGAI'6) MOVEMENT

~ SHORTER SCHEDULE (74 VS 84 DAYS)

~ LESS EXPENSIVE (15 TO 20%)

~ LESS WQ)IATIONEXPOSURE (300R VS 400R)

~ 100% SHOP ASSEMBLY

\\'

LI EN IN APPR A HE

~ LICENSE AI!ltKNDMENT

~ 10CFR50.59

0 l'

II 4 M I'L~j y~'i

LICEN IN APPROACHE NT'D LICENSE MdZNDMENT

~ PER 10CFR 50.90 AM) 50.91

~ SUBMITTALOF SAFETY ANALYSISREPORT

~ RESPONSES TO FORMM NRC QUESTIONS

~ NO SIGNIFICANTK.WARDS DETEKVGNATION

~ TECHNICALSPECIFICATION CEG&l'GES

~ FACILITYCEB&fGE PACKAGES AND ASSOCIATED SAFETY

. EVALUATIONSINCLUDINGCW&GES TO THE UFSAR)

~ PRESENTATIONS TO THE NRC ON SELECTED SUBJECTS, PROCESSES, TECHNIQUES, PROJECT STATUS, ETC

~ APPROACH USED FOR EARLYS/G REPLACEMENTS:

- SURRY 1 AI'G) 2

- TURKEYPOINT 3 AM)4

- ROBINSON 2

- POINT BEACH 1

- D.C. COOK 2

e Ai

~C

LICENSIN APPROACHES C NT'D 10CFR50.59

~ COMPREHENSIVE SAFETY EVALUATIONCOVERING THE ENTIRE PROJECT

~ SUPPORTING STUDIES, REPORTS, CALCULATIONS,ETC

~ MINORTECHNICALSPECIFICATION CEG&IGES

- SUBMI'ITEDSEPERATELY, AS REQUIRED

- FOR EXAMPLE,TRIP SETPOINT FOR S/G LEVELMAY CIRCE

~ PRESENTATIONS TO THE NRC ON SELECTED SUBJECTS, PROCESSES, TECHNIQUES, PROJECT STATUS, ETC.

~ NRC INSPECTION/REVIEW OF SAFETY EVALUATION, RESPONSES TO NRC QUESTIONS

~ APPROACH USED FOR ALLRECENT S/G REPLACEMENTS:

- INDIANPOINT 3

- PALISADES

- MILLSTONE2

- NORTH Al'PlA 1 (PLANNED)

- V.C.SUMtMER (PLANNED)

e

~C

OR I T

BE ADDRES ED

~ S/G TWWSPORT

~

CONTAINMENT INTEGRITY

~ S/G DROP POTENTIAL

~ EFFECTS ON UFSAR/TECH SPECS ACCEPTANCE TESTING/EXAMINATIONS

~ ~

HED E

~ REPLACEMENT DECISION 9/92 - 1/93

~ S/G FABRICATION 1/93 - 1/96

~ RFP FOR DESIGN/INSTALLATION 1/93 - 6/93 DETAILDESIGN 7/93 - 1/95

~ PRE OUTAGE MODIFICATIONS 3/95 - 2/96

~ S/G INSTALLATION 3/96 - 6/96

s E