ML20138H901

Forwards RAI Re Proposed Reduction in Max Allowable Dose Equivalent I-131 Concentration in Plant

ML20138H901
Person / Time
Site:	Byron
Issue date:	05/02/1997
From:	Lynch M NRC (Affiliation Not Assigned)
To:	Johnson I COMMONWEALTH EDISON CO.
References
TAC-M97894, TAC-M97895, NUDOCS 9705070319
Download: ML20138H901 (3)

Text

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

l May 2, 1997 Ms. Irene Johnson, Acting Manager

, s Nuclear Regulatory Services

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

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION - PROPOSED REDUCTION IN THE I 4

MAXIMUM ALLOWABLE DOSE EQUIVALENT 10 DINE-131 CONCENTRATION IN BYRON 1 (TAC NOS. M97894 AND M97895)

Dear Ms. Johnson:

In your letter dated January 31, 1997, you requested a license amendment which would revise the Byron 1 Technical Specifications (TS). This proposed TS I revision would reduce the maximum allowable value of the primary coolant dose equivalent (DE) iodine concentration from 0.35 to 0.20 microcuries per gram of

coolant. During the course of our review, we have identified a need for additional information. Our request for additional information (RAI) is enclosed.

If you have any questions on this matter, please contact M. David Lynch at j- (301) 415-3023.

Sincerely, l

\

l Original signed by: i l

M. David Lynch, Senior Project Manager l Project Directorate III-2 i Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation 4

Docket No. STN 50-454

Enclosure:

RAI l cc: see next page b hhk Distribution: i Docket Filep T5C3; PUBLIC PDIII-2 r/f J. Roe, JWR E. Adensam, EGA1 R. Capra C. Moore G. Dick S. Bailey R. Assa D. Lynch OGC, 015B18 C. Hinson C. Miller ACRS, T2E26 7

R. Lanksbury, RIII g DCA\ i\

C~iG M-DOCUMENT NAME: G:\CMNTJR\ LYNCH \ BYRON.RAI

+

Ta receive a copy of this dgnt,indicat' in he bog: *C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy 0FFICE PJD9GI-2T D l.A: 413 -2 l6 h:PDIII-2/l6 NAME ATN j CtJoorb JR. Capra h4f DATE 05fi/ /9T "T 05/jgj97 // '65/m /97 9705070319 970502 U PDR ADOCK 05000454 P PDR

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,t. ,

, I. Johnson Byron Station 1

, : Commonwealth Edison Company Unit Nos. I and 2 )

cc:

iMichael I. Miller, Esquire Chairman, Ogle County Board Sidley and Austin Post Office Box 357 One First National Plaza Oregon, Illinois 61061' ,

Chicago, Illinois 60603 Mrs. Phillip B. Johnson Regional Administrator, Region III 1907 Stratford Lane U.S. Nuclear Regult.ory Commission .Rockford, Illinois 61107 801 Warrenville Road' Lisle, Illinois 60532-4351 Attorney General 500 South Second Street Illinois Department of Springfield, Illinois 62701 Nuclear Safety Office of Nuclear Facility Safety. EIS Review Coordinator 1035 Outer Park Drive U.S. Environmental Protection Agency Springfield, Illinois 62704 77 W. Jackson Blvd.

Chicago, Illinois 60604-3590 Document Control Desk-Licensing

-Commonwealth Edison Company Commonwealth Edison Company 1400 Opus Place, Suite 400 Byron Station Manager

' Downers Grove, Illinois 60515 4450 North German Church Road Byron, Illinois 61010 i Mr. William P. Poirier, Director  !

Westinghouse Electric-Corporation Kenneth Graesser, Site Vice President j Energy Systems Business Unit Byron Station 1 Post Office Box 355, Bay 236 West Commonwealth Edison Station Pittsburgh, Pennsylvania 15230 4450 N. German Church Road Byron, Illinois 61010 Joseph Gallo  !

Gallo & Ross 1250 Eye St., N.W.

Suite 302 Washington, DC 20005

• l Howard A. Learner Environmental law and Policy Center of the Midwest 203 North LaSalle Street Suite 1390- ,

Chicago, Illinois 60601 U.S. Nuclear Regulatory Commission I Byron' Resident. Inspectors Office 4448 North German Church Road

. Byron, Illinois 61010-9750 ,

Ms. Lorraine Creek Rt. 1, Box 182 Manteno, Illinois 60950

. ~ _ _ _ _ _ . _ . .

REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE PROPOSED REDUCTION 1 i IN THE MAXIMUM ALLOWABLE DOSE EQUIVALENT

' l 10 DINE-131 CONCENTRATION IN BYRON 1 4

DOCKET NO. STN 50-454

1. Table 6.4-la of t$e Bryon Station Updated Final Safety Analysis Report provides information regarding the values of the atmospheric dispersion factors, X/Q, which are used in dose assessments when evaluating the control room habitability for design basis accidents. State what additional parameters and assumptions were used in your calculations to determine the various values of X/Q in Table 6.4-la. These parameters should include the wind speeds at the 5,10, 20 and 40 percentile levels, values of sigma y and sigma z,.the period over which the meteorological data was acquired, the wind directions used to calculate j the X/Q values and, if appropriate, building measurements (i.e.,

diameter) and the associated building cross-sectional area. State  ;

which Murphy /Campe equation you used and your basis for the use of the applicable equation. Finally, provide the input parameters and assumptions you used in determining the maximum X/Q value over the time period of 0 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

2. Provide the following values for the steam and water in the secondary side of the Byron steam generators: ,

a. The volume of the steam (in cubic feet per generator). l

b. The volume of the liquid (in cubic feet per generator).

c. The temperature of the steam / liquid mix in the secondary side of the steam generators. '

d. The mass of the secondary coolant (in pounds per generator).

3. Section 4.8 of WCAP-14046 states that from 0 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, 416,573 pounds of steam is released to the environment from the three steam generators in the intact loops. State the amount of steam released from these intact steam generators in the time period from 2 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

Alternatively, state whether you assume that all of the steam is released during the initial two hours following the main steamline break.

l ENCLOSURE