ML20196G040

Suppl to 970130 Application for Amends to Licenses NPF-37, NPF-66,NPF-72 & NPF-77,revising TS for Containment & RCS Vol.Encl marked-up Improved TS Pages Were Not Included in Original Submittal

ML20196G040
Person / Time
Site:	Byron, Braidwood
Issue date:	04/25/1997
From:	Hosmer J COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20196G046	List: ML20196G040 ML20196G050
References
NUDOCS 9705130291
Download: ML20196G040 (4)

Text

,.

Orm nonwealth Edison Company o

, !4@hyte Place

, Downem Grove, II. 60515--5701 April 25,1997 United States Nuclear Regulatory Commission Washington, D.C. 20555 Attention:

Document Control Desk

Subject:

Byron Nuclear Power Station, Units 1 and 2 Facility Operating Licenses NPF-37 and NPF-66 NRC Docket Numbers: 50-454 and 50-455 Braidwood ' Nuclear Power Station, Units 1 and 2 Facility Operating Licenses NPF-72 and NPF-77 NRC Docket Numbers: 50-456 and 50-457 i

Supplement to Technical Specification Amendment Pertammg l

to Primary Containment and Reactor Coolant System Volume

Reference:

J. Hosmer letter to NRC dated January 30,1997, Transmitting Technical Specification Amendment Request for Primary Containment and Reactor Coolant System Volume The Reference letter transmitted the Commonwealth Edison Company (Comed's) request l

to amend the Technical Specifications for Byron and Braidwood Units 1 and 2 regarding the primary containment and reactor coolant system volume associated with the Unit 1 Steam Generator Replacement. As stated in the Reference letter, the Marked-Up Improved Technical Specification pages were not included in the transmittal, but would be submitted at a later date. The attached supplements that package.

Enclosed is:

s A Y Attachment A:

Section E Description of the revised requirements Attachment B-1 A:

Byron Marked-Up ITS pages Attachment B-2A:

Braidwood Marked-Up ITS pages 9705130291 970425 DR ADOCK 05000454 PDR I

k:nia--bybwd.stmgen:parcsits. doc t l

l A Unicom Company

l l

1

. U.S. Nuclear Regulatory Commission April 25,1997 l

l I affirm that this transmittal is true and correct to the best of my knowledge, information and belief.

If you have any questions, please contact this office.

4 Sincerely, OFFICIAL SEAL

JACQUELINE T EVANS

/

ll NOTARY PUGUC, STATE OF ILLINots h

John B. Hosmer J

uv coamassow exmts:uns.v7 Engineering Vice President

^'~ ' ' ' ' ' ' ' ~ ~ ~ ~ ~ ~ ~ ~ " ' ' * * ^ " ' '

~

Signed before me on this d[ day of SzM

,1997 by

?Z#ar & [ bvrg

/- ota(f Public cc:

S. Burgess, Senior Resident Inspector - Byron Station I

C. Phillips, Senior Resident Inspector - Braidwood Station G. Dick, Byron /Braidwood Project Manager - NRR A. B. Beach, Regional Administrator - RIII Oflice of Nuclear Safety - IDNS l

i k:nla.bybwd.stmgen parcsits.ckx2 l

l

ATTACHMENT A E.

DESCRIPTION OF THE REVISED REQUIREMENT (Cont.)

Revision to ITS (Attachments B-la and B-2a)

Section 5.5.16, " Containment Leakage Rate Testing Program", in the Administrative Controls portion ofITS, will be revised to insert additional clarification of the unit specific values of P.

following steam generator replacement activities. For Byron, the value of P. will be revised as follows (existing words in italics):

...P., is 44.4psig for Unit 1 prior to Cycle 9 and 47.8 psig for Cycle 9 and afler (44.4 psig for Unit 2).

j For Braidwood, the value of P. will be revised as follows (existing words in italics):

..P., is 44.4 psig for Unit 1 prior to Cycle 8 and 47.8 psig for Cycle 8 and after (44.4 psig for Unit 2).

As would be required by the ITS Bases Control Program, changes to the Bases section are included with this License Amendment Request.

Bases sections, B 3.6.1, " Containment", B 3.6.2," Containment Air Locks", B 3.6.4,

" Containment Pressure", and B 3.6.6, " Containment Spray and Cooling Systems", will be revised l

in the " Applicable Safety Analyses" portion to provide clarification of the unit specific values of P. following steam generator replacement activities. For Byron, the specific value of P. which is currently stated as 44.4 psig for both Units 1 and 2 will be revised as follows:

)

. 44.4 psig for Unit 1 prior to Cycle 9 and 47.8 psig for Cycle 9 and after (44.4 psig for Unit 2)

For Braidwood, the specific value of P. which is currc.tly stated as 44.4 psig for both Units 1 and 2 will be revised as follows:

. 44.4 psig for Unit 1 prior to Cycle 8 and 47.8 psig for Cycle 8 and after (44.4 psig forUnit 2)

Bases section B 3.6.5, " Containment Air Temperature" will be revised to change the maximum l

containment air temperature from 318 *F to 319.7 "F.

l Bases section B 3.6.6, " Containment Spray and Cooling Systems" will be revised to change the j

j maximum containment air temperature from 318 *F to 319.7 F.

i j

J

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ATTACHMENT B-1a l

MARKED UP PAGES FOR PROPOSED CHANGES TO IMPROVED l

TECHNICAL SPECIFICATIONS OF l

FACILITY OPERATING LICENSES.

NPF-37, NPF-66 l

?

a BYRON STATION UNITS 1 & 2 REVISED PAGES:

)

i 5.0-35

)

l B 3.6-2 l

B 3.6-8 B 3.6-34 B 3.6-38 B 3.6-44 t-l l

l l

i 1

i I

i r

I l.

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