ML20249A609

Submits Response to NRC RAI Re SGTR Dose Evaluations

ML20249A609
Person / Time
Site:	Byron, Braidwood
Issue date:	06/10/1998
From:	Graesser K COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BYRON-98-0183, BYRON-98-183, NUDOCS 9806170138
Download: ML20249A609 (2)

Text

i Commonwealth litison Company l

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Ilyton Generating sration 4450 North German Churc h Road fly ron,II.610ln979 6 l'

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June 10,1998.

i LTR: BYRON 98-0183 FILE: 2.01.0700 U. S. Nuclear Regulatory Commission Washington, D.C 20555 '

ATTN: Document Control Desk

Subject:

Comed Response to NRC RAI Regarding SGTR Dose Evaluations Byron Station Unit 2 Facility Operating License NPF-66 NRC Docket No. 50-455 Braidwood Station Unit 2

. Facility Operating License NPF-77 NRC Docket No. 50457

References:

1.

Comed letter to NRC dated November 13,1996, transmitting a revised steam generator tube rupture analysis for Byron and Braidwood Stations, Units 1 and 2 2.

Comed letten to NRC dated April 13,1998, transmitting Unit 2 information regarding revised Steam Generator Tube Rupture Analysis Dose Evaluations

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3.

NRC letter to Comed dated May 12,1998, transmitting Request for AdditionalInformation concerning revised Steam Generator Tube Rupture Analysis for Unit 2 In Reference 1, Comed submitted a revised Steam Generator Tube Rupture (SGTR) analysis for Byron and Braidwood Stations, Units 1 and 2. In Reference 2, Comed submitted dose evaluation information for Byron Unit 2 and Braidwood Unit 2 to support NRC evaluation the Reference 1 analysis. In Reference 3, NRC requested information concerning actions to be taken to ensure the Unit 2 auxiliary feedwater (AFW) flow rate used in the revised SGTR analysis is consistent with plant

. configuration.

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The Byron Unit 1 AFW flow control valves (AF005 valves) were modified during the -

. Steam Generator Replacement outage (completed 3/9/98) to ensure AFW flow is limited

' to 464 gpm consistent with the tr/ised SGTR analysis. The modification consisted of.

' AF005 valve trim replacement. The same modification will be performed for Braidwood Unit 1 during their Steam Generator Replacement outage (AIK07) scheduled to begin

' 9/5/98. Byron Unit 2 will be modified during the next refueling outage (B2R08) -

scheduled to begin 11/8/99. Braidwood Unit 2 will be modified during the next refueling outage (A2R07) scheduled to begin 5/1/99. Upon completion of these modifications, all Byron and Braidwood units will have AFW flows consistent with the revised SGTR analysis.

'If you need any additional information concerning this response, please contact this office.

L Sincerely, K. L. Graesser Site Vice President Byron Nuclean Power Station KLG/LZ/rp Regional Administrator-RIII-cc:

Byron Project Manager - NRR Braidwood Project Manager - NRR Byron Senior Resident Inspector-Braidwood Senior Resident Inspector Office of Nuclear Safety -IDNS r

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