ML20137C014

Forwards RAI Re Primary Containment & RCS Volume for Byron Units 1 & 2 & Braidwood Units 1 & 2.Requests Propose to Revise TSs to Incorporate Effect of Increased RCS Volume Resulting from Planned Replacement of SG at Plants

ML20137C014
Person / Time
Site:	Byron, Braidwood
Issue date:	03/20/1997
From:	Dick G NRC (Affiliation Not Assigned)
To:	Johnson I COMMONWEALTH EDISON CO.
References
TAC-M97851, TAC-M97852, TAC-M97853, TAC-M97854, NUDOCS 9703240127
Download: ML20137C014 (3)

Text

. _ _ _ __ _._._ -

March 20, 1997 E l

' Ms. Irene M. Johnson, Acting Manager I Nuclear Regulatory Services  ;

Commonwealth Edison Company  :

Executive Towers West III  ;

1400 Opus Place, Suite 500 i Downers Grove, IL 60515 l

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING THE PRIMARY  ;

CONTAINMENT AND REACTOR COOLANT SYSTEM VOLUME - BYRON AND BRAIDWOOD (TAC NOS. M97851, M97852, M97853 AND M97854)

Dear Ms. Johnson:

1 On January 30, 1997, Commonwealth Edison Company (Comed) submitted requests for license amendments for Byron, Units 1 and 2, and Braidwood, I Units 1 and 2. The requests propose to revise the technical specifications j to incorporate the effect of the increased reactor coolant system volume l

resulting from the planned replacement of the steam generators at Byron, j Unit 1, and Braidwood, Unit 1. During the course of our review, we have l identified the need for further information as discussed in the enclosed l

request for additional information (RAI). Please provide your response to the request so that we may continue our review of your submittal.

Sincerely, Original signed by:

George F. Dick, Jr., Senior 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 p

Enclosure:

RAI g j M h kidk b I b.. ,

cc w/ encl: See next page ( l Distribution: L Docket; File > PUBLIC PDIII-2 R/F CMoore JRoe JWR EAdensam EGA1 RCapra CBerlinger 08H7 OGC 015B18 GDick WLong 08H7 SBailey RLanksbury, RIII ACRS T2E26 i DOCUMENT NAME: EB97P51.RAI l To receive a copy of this docyment, indicata[in the lion: "C" = Copy withoutgelosuresJE" = Copy with enclosures *N" = No copy 0FFICE PM:PDIII-/2slF Lh:PMII-2 l u SCSB( //fp D:PDIII-2 l c, l NAME GDICK M(l CM0 JRE\ CBERblNGET RCAPRA o _

DATE 03//a /97' N 03/ $/97 03/M/97 ed 03/zo/97 AFF1OI Al RECORD COPY 21100' 970:240127 970220 PDR ADOCK 05000454 P PDR

3 i

. I. Johnson Byron /Braidwood Power Stations

{ Commonwealth Edison Company F

cc:

l 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 l Pittsburgh, Pennsylvania 15230

Attorney General

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

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

j Michael I. Miller, Esquire Chicago, Illinois 60604-3590 l Sidley and Austin i

One First National Plaza Illinois Department of Chicago, Illinois 60603 Nuclear Safety j Office of Nuclear Facility Safety

! Howard A. Learner 1035 Oeter Park Drive i Environmental law and Policy Springfield, Illinois 62704

. Center of the Midwest l 203 North LaSalle Street Commonwealth Edison Company i Suite 1390 Byron Station Manager Chicago, Illinois 60601 4450 North German Church Road

! Byron, Illinois 61010

U.S. Nuclear Regulatory Commission l Byron Resident Inspectors Office Kenneth Graesser, Site Vice President ,

j 4448 North German Church Road Byron Station i 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 Regulatory Commission

Lisle, Illinois 60532-4351 Braidwood Resident Inspectors Office

! Rural Route #1, Box 79  ;

j Ms. Lorraine Creek Braceville, Illinois 60407 i Rt. 1, Box 182 i Manteno, Illinois 60950 Mr. Ron Stephens

! Illinois Emergency Services i Chairman, Ogle County Board and Disaster Agency i Post Office Box 357 110 East Adams Street Oregon, Illinois 61061 Springfield, Illinois 62706  ;

Mrs. Phillip B. Johnson Chaiman i 1907 Stratford Lane Will County Board of Supervisors 1 Rockford, Illinois 61107 Will County Board Courthouse

! Joliet, Illinois 60434 i

i l

l i

O RE0 VEST FOR ADDITIONAL INFORMATION REVISED STEAM GENERATOR TUBE RUPTURE ANALYSIS l COMMONWEALTH EDIS0N 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 The licen'ee's application of January 30, 1997, requests changes to the Technica' Specifications (TS) to reflect an increased containment peak  ;

accident pressure due to the steam generator (SG) replacement. The application states that new SGs will result in an increase in the primary coolant inventory. This will increase the amount of steam released into the containment for a design-basis accident / loss-of-coolant accident (DBA-LOCA).

There will also be an increase in the heat transfer rate between the primary i and secondary side in the SG, and the SGs will operate at a higher pressure.

The application further states that a base calculation was performed with CONTEMPT-B&W using the mass and energy release for the original SGs and then.

with the mass and energy release for the replacement SGs. The incremental increase in peak containment pressure was then applied to the original peak accident pressure value. In order for the staff to continue the review, the licensee is requested to provide responses to the following:

1. Was the Updated Final Safety Analysis Report (UFSAR) analytical  !

methodology used for the mass and energy analyses? If not, provide an UFSAR-quality description of the methodology and ,

confirm that the UFSAR will be updated with that information. '

Also confirm that the methodology is conservative with respect to the original licensing methodology or conforms to the Standard Review Plan (SRP), Section 6.2.1.3.

2. Provide a discussion of results of the CONTEMPT analysis using the mass and energy inputs associated with the replacement SGs. If the peak accident pressures exceed the value that results from adding the incremental increase to the current 44.4 psi TS figure, explain the difference.

3. Provide a discussion of the potential main steamline break (MSLB) containment temperature profile effect of the replacement SGs, and the need to address the environmental qualification of equipment in containment and steamlir.e spaces.

4. Confirm that any other previous plant modifications that could affect the calculated peak accident pressure have been considered and are reflected in the Pa calculation.

ENCLOSURE