ML20202C716

Forwards RAI Re Rv Insp Shell Weld Indication Evaluation for Plant,Unit 2,per 971015 Submittal

ML20202C716
Person / Time
Site:	Braidwood
Issue date:	11/03/1997
From:	Dick G NRC (Affiliation Not Assigned)
To:	Johnson I COMMONWEALTH EDISON CO.
References
TAC-M99784, NUDOCS 9712040037
Download: ML20202C716 (5)

Text

. . . . - - - - -- . -

,. - _ . - . . - - - . . -. - . ,~ _-

l- ,. - f D/L  !

,' ? November;3, 1997. MMM '

Ms. Irene M. johnson, Acting Manager -

@f {/g =  ;

Nuclear Regulatory Services Commonwealth Edison Company 3ppy gE 'd Executive Towers West til ~

N( D 01 ' -

1400 Opus Place, Suite 500 Pust;C 00Cutfry7 g  ;

Downers Grove, IL 60515 - >

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING REACTOR VESSE8 INSPECTION SHELL WELD INDICATION EVALUATION - BRAIDWOOD j

- STATION, UNil 2 (TAC NO. M99784) ,

Dear Ms. Johnson:

By letter dated October 15,1997, Commonwealth Edison Company (Comed) submi'ted ..s -;

evaluation G J flaw found during the 10-ye_ar inservice inspection of tne Braidwood, Unit 2, ,

reactor vessel. Comed concluded that the flaw indication detected ir; the nozzle-shell to- ,

intermediate-shell weld (Weld #2rtV 01-004) is acceptable for service without repair or replacemant. However, pursuant to the provisions of the American Scciety of Mechanical

- Engineers (ASME) Boiler and Pressure Vessel Code (Cooe),Section XI,1983 Edition through

- Summer 1983 Addends, paragraph IWB-3125(b), Comed submitted ths evaluation for NRC staff review.

During the course of our review, we have identified the need for fur 1her information as discussed in the enclosed request for additional information (RAl). Please indicate when we may expect a response to the RAI so that we may schedule the completion of our review of your submittsl.

Sincerely, ORIGINAL SIGNED BY:

George F. Dick, Jr., Senior Project Manager

' Project Directorate lil 2 :3

Division of Reactor Projects .lll/lV -

t

~ Office of Nuclear Reactor Rcgulation i Docket No. STN 50-457- ~ _ DISTRIBUTION l Docket: 'PDill-2 r/f m m PUBLICl_

Enclosure:

F. . EAdensam ~ RCapra GDick

' OGC- ACRS' SBailey -

" cc w/ encl:- See next page RLanksbury, Rill Sheng IT

[ ,

. -nW'O / n. '

yJ 57120 PDR G

g K705000457 971103 lllll PDR i DOCUMENT NAME: ~ G:\CMNTJR\ BRAID \BR99784.RAl-

- Ia recetwa a copy of this document. indica B(n the)om: "C" = Copy wthout one as *E" = Copy wth enclosures "N" = No copy i OFFICE PM:PD3-2I , E L4Ei43 ElVICI V D:PD3-2 --

NAME' GDICK > ll i '

V.blO6RE M 3AN RCAPRA 6 DATE , 16/33/97 - 10/fl /97 - id//$/97 10/a3/97

- OFFICIAL RECORD COPY

. . _ [ 4 6 N. 2

n

' ~

November 3, 1997

. Ms. Irene M. Johnson, Acting Manager Nuclear Regulatory Services

Oommonwealth Edison Company Executive Towers West 111 1400 Opus Plact, Suite 500 Downers Grove,IL 60515

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING REACTOR VESSEL INSPECTION SHELL WELD INDICATION EVALUATION - BRAIDWOOD STATION, UNIT 2 (TAC NO. M99784)

Dear Ms. Johnson:

By letter dated October 15,1937, Commonwealth Edison Company (Comed) submitted its evaluation of a flaw found during the 10-year inservice inspection of the Braidwood, Unit 2, reactor vessel. Comed concluded that the flaw indication detected in the nozzle-shell to intermediate-shell weld (Weld #2RV-01-004) is acceptable for service without repair or replacement. However, pursuant to the provisions of the American Society of Mechanical Engineers (ASME) Foiler and Pressure Vessel Code (Code),Section XI,1983 Edition through Summer 1983 Addenda, paragraph IWB-3125(b), Comed r abmitted the evaluation for NP.C staff review.

During the course of our review, we have identified the need for further information as discussed in the enclosed request for additional information (RAI) Please indicate when we may expect a response to the RAI so that we may schedule the completion of our review of your rubmittal.

Sincerely, ORIGINAL SIGNED BY:

George F. Dick, Jr., Senior Project Manager Project Directorate 111-2 Division of Reactor Projects -lilllV Office of Nuclear Reactor Regulation Docket No. STN 50-457 DISTRIBUTION Docket PUBLIC PDill-2 r/f

Enclosure:

RAI EAdensam RCapra GDick OGC ACRS SBailey cc w/ encl: See next page RLanksbury, Rll! Sheng DOCUMENT NAME: G:\CMNTJR\ BRAID \BR99784.RAI /

T4 receive a copy of this document. indica D(n thepos: *C" = Copy without enckpurgs *E* = Copy with enclosures "N" = No copy 2FICE PM:PD3-2fl , E L M 3-2 EffCW' / [ l D:PD3-2 -

NAME GDICK h dh WO6RE KMdlMAN RCAPRA 6 DATE 16/tJ/97

• 10/f)197 1$/8/97 19/oS/97 OFFICIAL RECORD COPY C________ __ _ _ __________ _ __________.________ ____ __ __ __._______ _ _ _ _ _ _ _ _ _

~

n.

, #3 f "%g e o l'a UNITED STATES

, -g g- NUCLEAR REGULATORY COMMISSION o '# WASHINGTON, D.C. 30665 0001

'4' e . , 4 November 3, 1997 2

Ms. Irene M. Johnson, Acting Mar,ager Nuclear Regulatory Services Commonwealth Edison Company Executiva Towers West 111 1400 Opus Place, Suite 500 Downers Grove,IL 60515

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING REACTOR VESSEL INSPECTION SHELL WELD INDICATION EVALUATION - BRAIDWOOD STATION, UNIT 2 (TAC NO. M99784)

Dear Ms. Johnson:

By letter dated October 15,1997, Commonwealth Edison Company (Comed) submitted its

• evaluation of a flaw found during the 10-year inservice inspection of the Braidwood, Unit 2, reactor vessel. Comed concluded that the flaw indication detected in the nozzle-shell to intermediate-shell weld (Weld #2RV-01-004)is acceptable for service without repair er replacement. However, oursuant to the provisions of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code),Section XI,1983 Edition through Summer 1983 Addenda, paragraph IWB-3125(b), Comed submitted the evaluation for NRC staff review, During the course of our review, we have identified the need for further information as discussed in the enclosed request for additionalinformation (RAI), Please indicate when we rnay expect a response to the RAI so that we may schedule the completion of our review of your submittal.

Sincerely, 9 '

J j] . j

</t f $lV ,

GeorSe F. Dick, Jr., Se or Project Manager Project Directorate 111-2 Division of Reactor Projects - Ill/IV Office of Nuclear Reactor Regulation Docket No. STN 50-457

Enclosure:

RAI cc w/ encl: See next page l

1 .. . V #

l L* 7. - '

^1.' Johnson < Braidwood Station -

Commor: wealth Edison Company ' Unit Nos.1 and 2 oc:

Michael Miller, Esquire U.S. Nuclear Regulatory Commission

- Sidley and Austin Braidwood Resident inspectors Omce one First National Plaza Rural Route #1, Box 7g Chicago, Illinois 60603 Braceville, Illinois 60407 Regional Administrator Mr. Ron Stephens U.S. NRC, Region ill- lilinois Emergency Services 801 Warrenville Road and Disaster Agency Lisle, Illinois 60532-4351 110 East Adams Street Springfield, Illinois 62706 lilinois Department of Nuclear Safety Chairman Omco of Nuclear Facility Safety Will County Board of Supervisors

~ 1035 Outer Park Drive Will County Board Courthouse Springfield, Illinois 62704 Joliet, Illinois 60434 Document Control Desk Licensing . Ms. Lorraine Creek Commonwealth Edison Company Rt.1, Box 1r j 1400 Opus Place, Suite 400 Manteno,Illinoir 60950 Downers Grove, Illinois 60515 Attomey General

Mr. William P. Poirier 500 South Second Street Westinghouse Electric Corporation Springfield, Illinois 62701 Energy Systems Business Unit Post Office Box 355 Bay 236 West George L. Edgar Pittsburgh, Pennsylvania 15230 Morgan, Lewis and Bochius 1800 M Street, N.W.

--Joseph Gallo Washington, DC 20036 Gallo & Ross

.1250 Eye St., N.W., Suite 302 Commonwealth Edison Company Washington, DC 20005 Braidwood Station Manager Rt.1, Box 84

.Ms. Bridget Little Rorem Braceville, Illinois 60407 Appleseed Coordinator 11'i North Linden Street EIS Review Coordinator Essex, Illinois: 60g35 U.S. Environmental Protection Agency 77 W. Jackson Blvd.

I Howard A. Leamer _ _ Chicago, Illinois 60604-35g0 Environmental Law and Policy Centerof the Midwest Mr. H. G. Stanley 203 North LaSalle Street- Site Vice President i ' Suite 13g0- Braidwood Station Chicago, Illinois 60601 Commonwealth Edison Company RR #1, Box 84 1 i Braceville,IL 60407 x -- - - - . . -. . - . . _ , . _ . _ _ _ - . - _ - , . - . - - . - , , . , - .

. REQUEST FOR ADDITIONAL INFORMATION, REACTOR VESSEL INSPECTION SHELL WELD INDICATION EVALUATION COMMONWEALTH EDISON COMPANY BRAIDWOOD STATION. UNIT 2 DOCKET E'O STN 50-457 The licensea's evaluation was done using the " Handbook on Flaw Evaluation for Zion, Byron, and Braldwood Reactor Pressure Vessels"(WCAP-12045 and 12046). Specifically, the licensee performed the flaw evaluation using Figure A-2.5 (WCAP-12046). This figure was generated based on Table 4 2 of WCAP-12045. Table 4 2 tabulated the critical flaw sizes for flaws of various shapes and orientations under different loading conditions. As part of the review, the staff intends to verify at least one case. The case selected is for the continuous circumferential flaw under the transient (N/U/T)"inadsertent Depressurization." Consequently, the licensee is requested to provide:

(1) the temperature and pressure distributions for the transient " inadvertent Depressurizationf (2) the worst stress profile at the location of the crack during this transient and the corresponding stress intensity factor for an assumed crack of depth 95 percent of the vessel wall thiciaess, and (3) the K, and K values used for this weld in finding the critical flaw size.

ENCLOSURE

-_ -_ - - _ - _ _ _ - _ _ _ _ _ - _ _ _ _ _ _ - .