ML20141H399

Forwards RAI Re Revised SG Tube Rupture Analysis for Plants, Units 1 & 2

ML20141H399
Person / Time
Site:	Byron, Braidwood
Issue date:	07/18/1997
From:	Dick G NRC (Affiliation Not Assigned)
To:	Johnson I COMMONWEALTH EDISON CO.
References
TAC-M97315, TAC-M97316, TAC-M97317, TAC-M97318, NUDOCS 9707230094
Download: ML20141H399 (6)

Text

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July 18, 1997 Ms. Irene M. Johnson, Acting Manager l

. Nuclear Regulatory Services 1 Commonwealth Edison Company '

Executive Towers West III 1400 Opus Place, Suite 500 Downers Grove, IL 60515

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SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING THE REVISED STEAM GENERATOR TUBE RUPTURE ANALYSIS - BYRON AND ~BRAIDWOOD STATIONS (TAC NOS. M97315, M97316, M97317, AND M97318)

Dear Ms. Johnson:

On November 13, 1996, Commonwealth Edison Company (Comed)' submitted its revised steam generator tube rupture analysis for Byron Station, Units 1 and

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l 2, and Braidwood Station, Units 1 and 2. The NRC issued requests for additional information (RAI) on February 11 and May 20,1997. Comed provided responses to the RAls on March 20 and June 24, 1997. During the course of the review, the staff has identified the need for further information as discussed during a telephone conversation on July 9, 1997, and documented in the enclosed RAI. Please provide your. response to the request so that we may continue our review of your submittals.

Sincerely, ORIGINAL SIGNED BY C. SHIRAKI FOR:

George F. Dick, Jr., Project Manager Project Directorate III-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket Nos. STN 50-454, STN 50-455, STN 50-456, STN 50-457 f

Enclosure:

RAI I cc w/ enc 1: See next page h DISTRIBUTION:

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'4 DATE 07/i'l/97 07//6/97 07/4 /97 0FFICIAL RECORD COPY 9707230094 970718 PDR ADOCK 05000454 P PDR

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. i 4 July 18, 1997 i

hN Ms. Irene M. Johnson, Acting Manager i Nuclear Regulatory Services l

Commonwealth Edison Company I Executive Towers West III l 1400 Opus Place, Suite 500 Downers Grove, IL 60515 )

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SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGAP, DING THE REVISED STEAM 2

GENERATOR TUBE RUPTURE ANALYSIS - BYRON AND BRAID 5l000 STATIONS (TAC NOS. M97315, M97316, M97317, AND M97318)

Dear Ms. Johnson:

On November 13, 1996, Commonwealth Edison Company (Comed) submitted its revised steam generator tube rupture analysis for Byron Station, Units 1 and

, 2, and Braidwood Station, Units 1 and 2. The NRC issued requests for ,

f additional information (RAI) on February 11 and May 20,,1997. Comed provided 1 responses to the RAIs on March 20 and June 24, 1997. During the course of the l review, the staff has identified the need for further information as discussed

!- during a telephone conversation on July 9, 1997, and documented in the  !

4-enclosed RAI. Please provide your response to the request so that we may continue our review of your submittals.

Sincerely,

l i ORIGINAL SIGNED M C. SHIRAKI FOR:

a ..

! George F. Dick, Jr., Project Manager

Project Directorate III-2 i

i Division of Reactor Projects.III/IV 1 Office of Nuclear Reacter Regulation  ;

Docket Nos. STN 50-454, STN 50-455, j- STN 50-456, STN 50-457 i

Enclosure:

RAI I

j. cc w/ enc 1: See next page I- DISTRIBUTION:  !

Docket PUBLIC PDIII-2 r/f JRoe, JWR EAdensam, EGA1  :

RCapra-- GDick CMoore OGC RLanksbury, RDL  !

SBailey GWest RAssa ACRS DOCUMENT tGME: G:\CHNTRJ\ BRAID-BY\BB97315.RAI To troelve a copy'of thle document,indlooo in the box: *C" = copy without enclosures *E" - Copy with enclosures "N" = Nu copy 0FFICE PM: PD3-j2/ lE LA:PD3 '2. [ lE PD:PD3-2n ,. le ,

NAME GDick Tff A CMoore'd/ Ll @ RCapra & N '

DATE 07/\1/97 07/!6 /97 9 07/fp,/97 0FFICIAL RECORD COPY B

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, s* NUCLEAR REGULATO1Y COMMISSION t WASHINGTON, D.C. 2066dke001 l

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July 18, 1997 l Ms. Irene M. Johnson, Acting Manager Nuclear Regulatory Services Commonwealth Edison Company Executive Towers West III l 1400 Opus Place, Suite 500 Dceners Grove, IL 60515- 1 i

SUBJECT:

. REQUEST FOR ADDITIONAL INFORMATION REGARDING THE REVISED STEAM 4

' GENERATOR TUBE RUPTURE ANALYSIS-- BYRON AND BRAIDWOOD STATIONS  !

(TAC NOS. M97315, M97316, M97317, AND M97318) t  :

i

Dear Ms. Johnson:

! On November 15, 1996, Commonwen1th Edison Company (Comed) submitted its

revised steam generator tube rupture innalysis for Byron Station, Units 1 and 4

i~

2, and Braidwood Station, Units 1 and.2. The'NRC issued. requests for .

t additional information (RAI) on February 11 and May 20, 1997. Comed provided i responset to the RAIs on March 20 and June 24, 1997. During the course of tne j review, the staff has identified the need for further information es discussed l during a telephone conversation on July 9,1997, and documented in the

enclosed RAI. Please provide your response to the request so that we ma.y 4 1 continue our review of your 'submittals. )1 7

Sincerely,

./kr George F. Dick, Jr., Project Manager i Project Directorato III-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket Nos. STN 50-454, STN 50-455, i STN 50-456, STN '50-457

Enclosure:

RAI l cc w/ encl: See next page j 1

6 I. Johnson - Byron /Braidwood Power Stations Commonwealth Edison Company cc:

Mr. William P. Poirier, Director George L.. Edgar

. Westinghouse Electric Corporation Morgan, Lewis and Bochius

. Energy Systems Business Unit 1800 M Street, N.W.

Post Office Box 355, Bay 236 West Washington, DC 20036 Pittsburgh, Pennsylvania 15230 Attorney General Joseph Gallo 500 South Second Street Gallo & Ross Springfield, Illinois 62701 1250 Eye St., N.W.

Suite 302- EIS Review Coordinator

. Washington, DC 20005 U.S. Environmental Protection Agency 77 W. Jackson Blvd. 4 Michael I. Miller, Esquire Chicago, Illinois 60604-3590 Sidley and Austin One First National Plaza Illinois Department of Chicago, Illinois 60603 Nuclear Safety Office of Nuclear Facility Safety Howard A. Learner 1035 Outer Park Drive Environmental law and Policy Springfield, Illinois 62704 Center of the Midwest 203 North LaSalle Street Commonwealth Edison Company Suite 1390 Byron Station Manager Chicago, Illinois 60601 4450 North German Church Road Byron, illinois 61010 U.S. Nuclear Regulatory Commission

, ~ Byron Resident Inspectors Office Kenneth Graesser, Site Vice President 4448 North German Church Road Byron Station Byron, Illinois 61010-9750 Commonwealth Edison Station 4450 N. German Church Road Regional Administrator, Region III Byron, Illinois 61010 U.S. Nuclear Regulatory Commission 801 Warrenville Road U.S. Nuclear P,egulatory Commission Lisle, Illinois 60532-4351 Braidwood Resident Inspectors Office Rural Route #1, Box 79 Ms. Lorraine Creek Braceville, Illinois 60407 Rt. 1, Box 182 Manteno, Illinois 60950 Mr. Ron Stephens Illinois Emergency. Services Chairman, Ogle County Board and Disaster Agency Post Office Box 357 110 East Adams Street Oregon, Illinois 61061 Springfield, Illinois 62706 Mrs. Phillip B. Johnson Chairman 1907 Stratford Lane Will County Board of Supervisors Rockford, Illinois 61107 Will County Board Courthouse Joliet, Illinois 60434 i

i

l-I Commonwealth Edison Company Braidwood Station Manager Rt. 1 Box 84 Bracev111e, Illinois 60407 i Ms. Bridget Little Rorem Appleseed Coordinator 117 North Linden Street l Essex, Illinois 60935 Document Control Desk-Licensing l Commonwealth Edison Company 1400 Opus Place, Suite 400 Downers Grove, Illinois 60515 Mr. H. G. Stanley Site Vice President Braidwood Station Commonwealth Edison Company RR 1 Box 84 Braceville, IL 60407

4 RE0 VEST FOR ADDITIONAL INFORMATION REVISED STEAM GENERATOR TUBE RUPTURE ANALYSIS COMMONWEALTH EDISON COMPANY BYRON STATION. UNITS 1 AND 2: BRAIDWOOD STATION. UNITS 1 AND 2 DOCKET NOS. STN 50-454. STN 50-455. STN 50-456. AND'STN 50-457

1. The response to question B.3 in the licensee's March 20, 1997, submittal provided the sensitivity of operator response times that exceeded the ant. lysis response times. Please complete a similar analysis for Crew No. 1. The analysis should include: (a) a case for the overall response time and other cases where Crew No.1 exceeded the analysis response times; and (b) a composite analysis of cases that exceeded the analysis response times.

2. The response to question B.4 in-the licensee's March 20, 1997, submittal

,orovided a table (Table B.4) of observed operator times for various steps of the steam generator response effort. Please provide the' margin to overfill for each cell in the table.

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