ML20203C550

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Summary of 971120 Meeting W/Southern Nuclear Operating Co to Discuss Matters Related to Steam Generator Replacement Projects Proposed for Both Farley Nuclear Units.List of Attendees Enclosed
ML20203C550
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 12/05/1997
From: Gleaves W
NRC (Affiliation Not Assigned)
To:
NRC (Affiliation Not Assigned)
References
TAC-M72415, TAC-M72416, NUDOCS 9712150340
Download: ML20203C550 (34)


Text

..

t 1 December'5, 1997 i LICENSEE: Southem Nuclear Operating Company FACILITIES: Joseph M. Farley, Units 1 and 2

SUBJECT:

MEETING

SUMMARY

- MEETING OF NOVEMBER 20,1997 (TAC NOS.

M72415 AND M72416)

REFERENCE:

Meeting Notice by J. l Zimmerman, October 31,1997

. On November 20,1997, the NRC staff met with Southem Nuclear Operating Company (SNC) personnel to discuss matters related to the steam generator replacement projects proposed for both Farley nuclear units. Enclosure 1 is the list of meeting participants. Enclosure 2 is the licensee's meeting handout materials.

The licensee requested the meeting to present an overview of the Farley steam generator replacement project. SNC discussed the schedule, scope, and licensing and engineering plans for Units 1 and 2. The current Westinghouse Model 51 steam generators will be replaced with a Westinghouse Model 54F design. The replaced Model 51 steam generators will be stored at the Farley site until final decommissioning.

The NRC staff discussed issues related to the 10 CFR 50.59 evaluations that will be used to implement the replacement project at Farley. The staff agreed that the actual replacement can be done under 10 CFR 50.59 but that certain tech spec changes will have to be reviewed and approved by the staff to enable operation with the new steam generators.

ORIGINAL SIGNED BY:

William Gleaves, Project Manager Project Directorate Il-2 Division of Nuclear Reactor Projects - t/II Office of Nuclear Reactor Regulation Docket Nos. 50-348 anc 50-364

Enclosures:

1. List of participants
2. Meeting handouts cc w/encls 1 and 2: See next page Distribution:

See next page To receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" =

C:py with attachmentlenclosure "N" = No copy *See previous concurrence OFFICE PM:PDil-2 l LA:PDil-2* l PM:PDil-2* l D:PD114 c] _

NAME W.Gleavedicr16 L. Berry J.Zimmerman H.BerkbM9 DATE tt/ ///97 12/2/97 12/*3/97 n D.'/9 P DOCUMENT NAME: G:\FARLEY\FAR72415. SUM OFFICIAL RECORD COPY P"1M Mjha IlllllKlli, plV @PE RE WJB NW

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    • 280 3 4 UNITED STATES

-! } NUCLEAR REGULATORY COMMISSION o WASHINJTON, D.C. 30666-0001

% ,, [$ December 5, 1997 LICENSEE: Southern Nuclear Operating Company FACILITIES: Joseph M. Farley, Units 1 and 2 SUBJECT; MEETING

SUMMARY

- MEETING OF NOVEMBER 20,1997 (TAC NOS.

M72415 AND M72416)

REFERENCE:

Meeting Notice by J. l. Zimmerman, October 31,1997 On November 20,1997, the NRC staff met with Southem Nuc8 ear Operating Company (SNC) personnel to discuss matters related to the steam generator rep:acement projects proposed for both Farley nuclear units. Enclosure 1 is the list of meeting participants. Enclosure 2 is the licensee's meeting handout materials.

The licensee requested the meeting to present an overview of the Farley steam generator replacement project. SNC discussed the schedule, scope, and licensing and enginearing plans for Units 1 and 2. The current Westinghouse Model 51 steam generators will be replaced with a Westinghouse Model 54F design. The replaced Model 51 steam generators will be stored at the Farley site until final decommissioning.

The NRC staff diccussed issues related to the 10 CFR 50.59 evaluatiens that will be used to implement the replacement project at Farley. The staff agreed that the actual replacement can be done under 10 CFR 50.59 but that certain tech spec changes will have to be reviewed and approved by the staff to enable operation with the new steam generators.

William Gles s, Project Manager Project Directorate ll-2 Division of Nuclear Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364 l

Enclosures:

1. List of participants
2. Meeting handouts cc w/encls 1 and 2: See next page I

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, Joseph M. Farley Nuclear Plant i

B oc:  ;

Mr. D. N. Morey . .

Mr. R. D. Hill, Jr. Vice President - Farley Project General Manager - _

Southem Nuclear Operating Southern Nuclear Operating Company Company, Inc.

Post Office Box 470 P. O. Box 1295 Ashford,- Alabama 36312 Birmingham, Alabama 35201 ,

Mr. Mark Ajiuni, Licens!ng Manager Southem Nuclear Operating Company Post Office Box 1295 Birmingham l Alabama 35201 1295 Mr. M. Stanford Blanton Balch and Bingham Law Firm Post Office Box 306 1710 Sixth Avenue North Birmingham, Alabama 35201 i Mr. J. D. Woodard Executive Vice President Southern Nuclear Operating Company Pcat Office Box 1295 Birmingham, Alabama 35201 State Health Officer Alabama Department of Public Health

, 434 Monroe Street Montgomery, Alabama 36130-1701 Chairman Houston County Commission Post Office Box 6406 Dothan, Alabama 36302 Regional Administrator, Region il U.S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth Street, S.W., Suite 23T85 Atlanta, Georgia 30303 Resident inspector

. .U.S. Nuclear Regulatory Commission 7388 N. State Highway 95 Columbia, Alabama 36319 ~

1 4 Y ^ 6 ..

Distribution for Meetina Summary:

MARD COPY WITli ALL ENCLOSURES MMst2 PUBLIC -

PD 112 Rdg.

OGC ACRS EMAIL.

SUMMARY

WITH ENCLOSURE 1 S. Collins /F. Miraglia R. Zimmerman B. Boger T. Martin (e-mail SLM3)

H. Berkow W. Gleaves L. Berry

.l. Zimmerman T. Ross A. Keim J. Davis A. Lee E. Debec M. Shualbl C. Liang L. Trocine J. Johnson, Ril P. Skinner, Rll i

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f f LIST OF PARTICIPANTS MEETING WITH SOUTHERN NUCLEAR CORPORATIQB NOVEMBER 20.1997 4

NAME AFFILIATION Hert Berkow NRC/NRR/ Project Directorate ll 2 William Gleaves NRC/NRR/ Project Directorate ll 2 Jacob Zimmerman NRC/NRR/ Project Directorate 112 Thierry Ross NRC/NRR/RGN-il Andrea Keim NRC/NRR/EMCB Jim Davis NRC/NRR/EMCB Arnold Lee NRC/NRR/EMCB Er;c Debec NRC/NRR/EMCB Mohammed Shuaibi NRC/NRR/SRXB Chu-yu Liang NRC/NRR/SRXB Dave Morey SNC John Garlington SNC Howard Mahan SNC Farley Project Mark Ajtuni SNC Farley Project Doug S. McComb SNC-Farley SGRP Thomas A. Billman W SG Project Manager, Pensacola i Chris Byrd SCS Engineering J. V. Smith Bechtel Engineering J. M. McLemore Bechtel Project Manager Der'nis Klein Bechtel Licensing Mike Watson W Engineering Larry Markie W SGR Project Manager, Pittsburgh Enclosure 1 1

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COMPANY Energy to Serve YourWorld" Southern Nuclear Operating Company Joseph M. Farley Nuclear Plant - Units 1 and 2 Steam Generator Replacement Project i Presentation to the 1 Nuclear Regulatory Commission 1

l November 20,1997 toca os ,r.

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Provide an overview of Souther.1 Nuclear's plan to replace the steam generators (SGs) at Farley Nuclear Plant.

Unit 1 SG replacement: Spring 2000 -

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July 25,1997 SG Replacement Project corporate approval l (Project start date)
January 1,1999 Primary Licensing Submittal for Unit 1 and j l Unit 2 to NRC for approval l #%

February 1,1999 Security Plan update to NRC [^k .' _

a l March 1,A999,s w- . n ..w nReviseda,lSI:

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i Scope of Farley SG Replacement l  !

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[ . Impacts to systems such as RCS, FW, AFW, MS and SGBD are minimal. ,

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No power uprate coincident with SG replacement. KT4 s e,

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s SNC SG Replacement Organization Dave Morey Vice President Farley Project I

1 Richard Hill ---

John Garlinaton ___ Vacant Jim McGowan General Manager SG Replacement Nuclear Support Manager Farley Nuclear Plant Project Manager General Manager SAER

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I i 3 Replacement Team - Bechtel _ 1 l

  . Scope                                                                                                                                                     '

L -- SG removal i SG installation Engineering and licensing support SG storage facility

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Replacement Philosophy - i i ! . Implement SG replacement under 50.59 i i ! . Primary licensing submittal to include: j - Overview of SG replacement program ' Items requiring NRC approval Summary of replacement SG design and analyses l Summary _of component / system _ analyses and evaluations _ - l Summaryg of isOpp6rting; accident anslyses 4x

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Tech. Spec.Chanaes~ - [ . Deletion of items associated with the existing SGs F* repair criteria ! - Sleeving repair criteria l - Voltage based altemate repair criteria , i n"h. l . Additional changes to current Tech. Specs. I - RPS,and,ESFAS_SG_ m, e . . water level _setpoints __; n_ SGitube? inspection:cnteria! m M y fl O 5.3 l - - RCSSpesififactivity:!- DEI liniitsibi12 i= J"'i l l RCS leakage limit foreSG;tGbe Idhkig6T6fA150 giid yV}:' i One time extension tkSG insNctionisctivitie'sMNi _ m c_:i, w: j . i Subm.ttal:w.ll

                    - _, m ,

i assume J

                                    .    .s proved Tech.; Specs::a,re
                                                                                          .m..

in place b[ i \ - n

                                                                                                                                                                    ~
   .lSI Program Changes                                                                                                                                          -

ISI Program changes may be needed to support SG replacement. l Examples include: 1

                             ~                                                                                                                                        i l   . Update to ISI Program (3rd cycle interval)                                                                                                                      ,

e

6 l
  • Relief from SG iSI requirements during SG replacemsnt outages '

i ~ l 1

   . Weld joint configuration,is. sue,s specifically.related to installation m
geometry ,F uny.-v; e .d ' .
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                                                                                                                                       <=_s    m2,:ma Revise Relief Request RR-07-for             .m primary; nozzle;
                                                                                                . 4           . s, safe ,end, weld configuration                               n u. am ;~ . t ;x fcs, c9 m, s

r ': 2 -

                                                     ' _-                a       %         . m. 4            '

L t. ' ' - a: , l . Revise Relief Request,RR-08 ons.steam nozzle inner radius

                                     .                                                       1     .
                                                                                                       .             .    ~

l examinstion ?vv g s c c c rge. M_ J_r F WC :. M.. . i i i

I

                                                                                                                                                                                                                                       ~

Changes :o Prior Commitmeni:s

  . SNC will perform a review of its commitment database to determine if changes are required. This includes Generic i_etters,                                                                                                                                                                    -
Bulletins, SERs and other forms of NRC correspondence.
  . Changes to NRC commitments will be performed in accordance with SNC's commitment change program.                                                                                                                                        /

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i Analyses and Evaluations - System and component analyses and evaluations will document

continued compliance with applicable codes and licensing criteria.

These include: l . NSSS Design Transients i e NSSS Systems # 4 4  ; Impact of SG replacement on NSSS fluid systems 1 RCSymid-loop operation R E" ~~r1 D f~~ i i i - NSS5}7 BOP fluid systems'intirface's 4 j vT l NSSS control systems f e i f c- ,

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             .                                                                                ~ ji '*"J.                        };

Reactor internals and RCS loop piping and supports SGdhermalehydraulic,and, structural analysesd  ; LBB analys ,is'(loop piping and pressurizer surge line) i l 1

                                                                                                                                       =         l

Analyses and Evaluations (Cont'd.) l

  . NSSS Accident Analyses LOCA analysis Non-LOCA transients (FSAR Chap.15 events and ATWS)

SG tube rupture transient ,. MSLB mass and energy releases f;

=. .

i ' ' i.

  . Nuclear Fuel / Core Design c,. - - ,

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  . Radiological EvaliJations T"        l=

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                                                                                                 =
n ._

CA s 1

  . Containment P/T analysisc!LOCA'5ind'MSLB '~~1 A "O "~~      .,                  .                        t -            .
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Equipment Qualification ~

                                                                                    ~
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  . Post-LCiCA? Hydrogen Generatiorigrr W,s?'id as                                                                                                                      ;
  . BOP Systems

4 l i Licensina Summary b

   = 50.59 process for replacement i
   . Licensing submittal with miminum TS changes
   . Builds on recently completed Power Uprate Submittal                                                                                                                                                                       .
. ISI Program change ~s minimized E ,
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    . All forged vessel pressure boundary t

i 1

    . 405 SS Tube support plates                                                                                                                               .

j . Tube to tubesheet joint

    . Feedn.ng                                                                                                                                      ,
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t 4 Design Changes to Be implemented Under 50.59 i ! . Replacement of SGs in accordance with ASME Section XI i l

       . Construction of old steam generator storage facility t
       . Steam generator platform modifications 4
                                                                                                                                                                                                  ;e:' -

m s c . Steam generator snubber el. .imination " 1 l i a

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4 Other items to Be implemented. Under 50.59 6 l

      . Temporary features associated with SG installation SG haul route J                                                                                                                                                                                                                                     !

i

      . Control of heavy loads                                                                                                                                                  ,

n i 5  ::: ,

      . FSAR changes required by SG replacement
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l Post Modification Inspection and Testing  ? I i ! . Baseline ISI of field welds

  . SG thermal and hydraulic performance
  . RCS flow rate                                                                                                                                            -
=

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Summary 4 t i i i t I l 1  : a  : 4 P l John Garlington " v

          ,,        ~ -.        ~x, m m mProject Managers ,

4 e

          %{K,SteamiGenerator,!

n , - 4 ia . 2 s.- ~ : , E. Replacement ProjecF,1Jf a x_ j

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1 Project Schedule - l Activities 1997 1998 1999 2000 2001 Q1 Q2 03 04 Q1 02 Q3 04 Q1 02 Q3 Q4 Q1 02 03 04 Q1 Q2 Q3 Q4  ; SG Replacement Project u 7/25/97 Approval g Unit 1 RSG Fabrication .-  : amma mummmmmmmmmmms 2/18/00 Unit 2 RSG Fabrication t 12/1/00 Primary Licensing Submittal ummmmmmmmmmms - 4 Activities  ! Primary License Submittal to E ' NRC e'^7"' ' ~ ^ i 1 "' ~ "

                                                         ~ ~~ F                1 jfjf9g '"
                                                                                    -              '""'.                      ~~

Submittal of Security Plan; ii  ; - a . Revision -

                          " ~ "
                                     " -                   ,       mp             2/1/99: .       -                  

i ' " " ' " -~ -- " ^ , Submittal of Revised ISI . Program ~,- ,ex r..._

                                                                               -.u,3/1/99 w  _         ._
                                                                                                       - r ' ~' r
                                                                   '               t           -1                                  t-NRC Review                                     '
                                                      .a
                                                            . _ ,        -   EEmumEEEEEEEEE  -

! _-- ,,_. y. , , NRC Approval  ! a4 /1/00 1 l g' f pp {}(f ~f g j y ,  : Unit Outage 1 SG Replacemerytp*Ds ' 7' V.q/ffgfg,um, ! Unit 2 SG Replacement . t l Outage 3/3/01 i 1 i 4 1

l

  • t NRC Interface i I' Existing interfaces will be maintained and used for SG replacement.

! e SNC Nuclear Engineering and Licensing (NEL) interface with the NRC Project Manager r?.

r. i
    .       FNP site interface with the NRC Resident inspectoNs h
                                                                                                                                                                                             +                                             ;

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    .       SNC SQReplacsment
                                        ~

Projectisupports NEli and the FNPtsite

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