ML20141H353

Forwards RAI Re Revised Steam Generator Tube Rupture Analysis for Byron Station,Units 1 & 2 & Braidwood Station Units 1 & 2

ML20141H353
Person / Time
Site:	Byron, Braidwood
Issue date:	05/20/1997
From:	Dick G NRC (Affiliation Not Assigned)
To:	Johnson I COMMONWEALTH EDISON CO.
References
TAC-M97315, TAC-M97316, TAC-M97317, TAC-M97318, NUDOCS 9705230280
Download: ML20141H353 (6)

Text

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( a May 20, 1997

. Ms. Irene M. Johnson, Acting Manager Nuclear Regulatory Services Commonwealth Edison Company =

Executive Towers West III e 1400 Opus Place, Suite 500 3 Downers Grove, IL 60515 q

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING THE REVISED STEAM #

GENERATOR TUBE RUPTURE ANALYSIS - BYRON AND BRAIDWOOD STATIONS (TAC NOS. H97315, M97316, M97317 AND M97318)  !;

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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. We issued a request for additional information (RAI) on February 11, 1997, and Comed provided its response on March 20, 1997. During the course of our review, we have e identified the need for further information as discussed in the enclosed RAI. I Please provide your response to the request so that we may continue our review [

of your submittals. ij b

Sincerely,  : F I

Original signed by:

'.i George F. Dick, Jr., Project Manager l Project Directorate III-2  :

Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation Docket Ncs. STN 50-454, STN 50-455,  ;

STN 50-456, STN 50-457  ;

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Enclosure:

RAI /

cc w/ encl: See next page

,?istribution:. ..

' ockat Filet , . -PUBLICf PDIII-2 R/F J. Roe, JWR E. Adensam, EGA1 R. Capra C. Moore G. Dick R. Lanksbury, RIII OGC, 015B18 ACRS, T2E26 C. Jackson, 08E23 S. Bailey R. Assa J. Lyons, 08D1 .j 2300G1 MN DOCUMENT NAME: BRAID-BY\BB97315.RAI 4;\ E To receive a copy of this document,indicateg ip: *C" = Copy without hfosures *E" = Copy with enclosures *N = No copy OFFICE ~ PM:PDIII-2ij $ th:Pk/1-2 l U SRXB(AX l D:PDIII-2 l NAME G. Dick )hh CMcoM J. Lydnh k.Capra V l DATE 05/if/97 ' .

05/[(/97 05/2 0/97 05/w/97 y 9705230200 970520

• 0FFICIAL RECORD COPY PDR ADOCK 05000454 P PDR

+

.

• May 20, 1997 cm 6 . Ms. Irene M. Johnson, Acting Manager Nuclear Regulatory Services Commonwealth Edison Company Executive Towers West Ill 1400 Opus Place, Suite 500 Downers Grove, IL 60515

SUBJECT:

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

Dear Ms. Johnson:

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

and 2, and Braidwood Station, Units 1 and 2. We issued a request for l

additional information (RAI) on February 11, 1997, and Comed provided its l response on March 20, 1997. During the course of our review, we have  ;

identified the need for further information as discussed in the enclosed RAI.

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

Sincerely, i l

l Original signed by:

George F. Dick, Jr., Project Manager Project Directorate IT.I-2 Division of Reactor Projects - III/IV i

Office of Nuclear Reactor Regulation Docket Nos. STN 50-454, STN 50-455, STN 50-456, STN 50-457

Enclosure:

RAI cc w/ encl: See next page Distribution:

Docket File PUBLIC PDIII-2 R/F J. Roe, JWR E. Adensam, EGA1 R. Capra C. Moore G. Dick R. Lanksbury, RIII OGC, 015B18 ACRS, T2E26 T.. Jackson, 08E23 S. Bailey R. Assa J. Lyons, 08D1 DOCUMENT NAME: BRAID-BY\BB97315.RAI T3 teceive a copy of this document, irdcateAthe b @: *C" = Copy without

$losures *E" = Copy with enclosures *N* = No copy 0FFICE PM:PCIll-20 E th:PR S-2 l U SRXB(& l D':PDIII-2 l NAME G. Dick M1A CMooM J. Ly6nk R.Capra y DATE 05/9797 ' 05/L( /97 05/20/97 05/w/97 0FFICIAL REC 0KO COPY

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,y *4 UNITED STATES

, , j p

j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30666-0001

+4*****4 May 20, 1997 Ms. Irene M. Johnson, Acting Manager Nuclear Regulatory Services Commonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite 500 Downers Grove, IL 60515 l

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 2, and Braidwood Station, Units 1 and 2. We issued a request for additional information (RAI) on February 11, 1997, and Comed provided its response on March 20, 1997. During the course of our review, we have  ;

identified the need for further information as discussed in the enclosed RAI. i Please provide your response to the request so that we may continue our review of your submittals.

1 Sincerely, I I

LP r l I

Georg F. Dick, Jr., roject Manager Proje t Directorate 11-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation Docket Nos. STN 50-454, STN S0-455, STN 50-456, STN 50-457

Enclosure:

RAI cc w/ encl: See next page

~. - - - .

1

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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 Attorno General Joseph Gallo 500 South Second Street Gallo & Ross Springfield, Illinois 62701 1250 Eye St., N.W.

Suite 302 EIS Review Caordinator Washington, DC 20005 U.S. Environmental Protection Agency 77 W. Jackson Blvd.

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 Comonwealth Edison Company Suite 1390 Byron Station Manager Chicago, Illinois 60601 4450 North German Church Road Byron, Illinois 61010 U.S. Nuclear Regulatory Comission Byron Resident Inspectors Office Kenneth Graesser, Site Vice President 4448 North German Church Road Byron Station Byron, Illinois 61010-9750 Comonwealth Edison Station 4450 N. German Church Road Regional Administrator, Region III Byren,, Illinois 61010 U.S. Nuclear Regulatory Comission 801 Warrenville Road U.S. Nuclear Regulatory Comission Lisle, Illinois 00532-4351 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 Commonwealth Edison Company

. Braidwood Station Manager Rt. 1, Box 84 Braceville., Illinois 60407 Ms. Bridget Little Rorem Appleseed Coordinator 117 North Linden Street Essex, Illinois 60935 .

Document Control Desk-Licensing Commonwealth Edison Company 1400 Opus Place, Suite 400 Downers Grove, Illinois 60515

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-Mr. H. G. Stanley Site Vice President Braidwood Station

- Commonwealth Edison Company RR 1, Box 84 Braceville, IL 60407 i

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. . E0 VEST FOR ADDITIONAL INFORMATION  !

l REVISED STEAM GENERATOR TUBE RUPTURE ANALYSIS ]

COMMONWEALTH EDIS0N COMPANY BYRON STATION. UNITS 1 AND 2: BRA 1DWOOD 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 A.1 in the licensee's March 20, 1997, submittal i indicates that there is a requirement to choose a cycle Tave that is consistent with the analyzed Tave window. Where is the requirement (to choose a Tave greater than 575 F) contained?

2. The response to question A.2 in the licensee's March 20, 1997, submittal indicates that there is significant conservatism in the initial conditions and analysis approach. Please provide a more detailed discussion of the conservatism in the initial conditions and analysis approach. Please include a specific discussion of the following issues:

The limiting case for the old analysis is used for the new analysis.

Justify why this is acceptable considering the plant now has new emergency operating procedures (E0Ps), new steam generators, and a new analysis method. Be sure to justify why the sir;gle failures chosen for the different cases remains bounding considering the changes in the procedures, plant configuration, and analysis methods.

Page 9 of the original submittal (November 13,1996) states that the secondary mass and 3ressure are derived from the revised nominal Tave.

Why is the use of tie nominal Tave more appropriate than a conservative value?

3. The response to question A.3 of the March 20, 1997, submittal indicates that the 1973 standard decay heat curve is used; however, the safety evaluation for the referenced topical report indicates that 120 percent of the 1971 ANS decay heat rate is to be used. Please describe why the 1973 standard decay heat curve is acceptable.

4. With regard to the choice of initial power level in the accident analysis, the discussion 3rovided in response to question A.5 of the March 20, 1997, submittal and t1e discussion in the original submittal November 13, 1996) is not consistent with the discussion in the topical report and the safety evaluation for the topical report. Please provide a more rigorous justification for the initial power chosen. Include a complete discussion of the different effects contained in both the topical report and the submittals for this ast .iption. Include the effects for both the original and the replacement steam generators.

5. Please explain why the initial steam generator volumes are different for

! the OTAT and the low 3ressurizer pressure cases in Figure 7 of the November 13, 1996, su)mittal.

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6. The November 13, 1996, submittal indicates that the analysis assumptions are being revised because the E0Ps are being modified. Please verify that the equipment and instrumentation relied on to identify and mitigate the tube rupture is all safety-related.

ENCLOSURE l