L-05-179, Supplement to Responses to Request for Additional Information Dated March 28, 2005 in Support of License Amendment Request Nos. 317 and 190

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Supplement to Responses to Request for Additional Information Dated March 28, 2005 in Support of License Amendment Request Nos. 317 and 190
ML053220247
Person / Time
Site: Beaver Valley
Issue date: 11/14/2005
From: Lash J
FirstEnergy Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-05-179
Download: ML053220247 (3)


Text

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FENOCRoute Beaver Valley Power Station 168 PO. Box 4 FrstEnergy Nuclear Operating Company Shippingport, PA 15077-0004 James [I. Lash 724-682-5234 Site Vice President Far: 724-643-8069 November 14, 2005 L-05-179 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001

Subject:

Beaver Valley Power Station, Unit Nos. 1 and 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412, License No. NPF-73 Supplement to Responses to Request for Additional Information dated March 28, 2005 in Support of License Amendment Request Nos. 317 and 190 By letter dated March 28, 2005, the U.S. Nuclear Regulatory Commission (NRC) issued a request for additional information (RAI) relative to FirstEnergy Nuclear Operating Company (FENOC) license amendment requests 317 and 190 (Reference 1). Responses to this RAI where provided in Attachment A of FENOC letter L-05-079 dated May 12, 2005 (Reference 2). Question 3(b) of the March 28, 2005 RAI requested information such that the NRC staff could perform an independent analysis of the mass and energy release from a loss of coolant accident (LOCA) after one hour for a net positive suction head (NPSH) analysis. During meetings held the week of November 7, 2005, the staff verbally requested information to supplement the response provided to Question 3(b) of the March 28, 2005 RAI. Attachment A of this letter provides the requested supplemental information.

The supplemental information contained in this transmittal has no impact on the proposed Technical Specification changes or the no significant hazards consideration, transmitted by Reference 1.

No new commitments are contained in this submittal. If you have questions or require additional information, please contact Mr. Gregory A. Dunn, Manager, Fleet Licensing at 330-315-7243.

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Beaver Valley Power Station, Unit Nos. 1 and 2 Supplement to Responses to Request for Additional Information dated March 28, 2005 in Support of License Amendment Request Nos. 317 and 190 L-05-179 Page 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on November 14, 2005.

Sincerely, mes H. Lash

Attachment:

A. Supplemental Information for responses to RAI dated March 28, 2005

References:

1. FENOC Letter L-04-073, License Amendment Requests 317 and 190, dated June 2, 2004.
2. FENOC Letter L-05-079, Responses to a Request for Additional Information in Support of License Amendment Request Nos. 317 and 190, dated May 12, 2005.

c: Mr. T. G. Colburn, NRR Senior Project Manager Mr. P. C. Cataldo, NRC Senior Resident Inspector Mr. S. J. Collins, NRC Region I Administrator Mr. D. A. Allard, Director BRP/DEP Mr. L. E. Ryan (BRP/DEP)

L-05-179 Attachment A Supplemental Information for responses to RAI dated March 28, 2005 The following information is provided to supplement the response to Question 3(b) of the March 28, 2005 RAI which was provided in Attachment A of FENOC letter L-05-079 dated May 12, 2005. This information was verbally requested by the staff during meetings held the week of November 7, 2005.

The information is provided such that the NRC staff could perform an independent analysis of the mass and energy release from a loss of coolant accident (LOCA) after one hour for a net positive suction head (NPSH) analysis. The tables below provide the requested data for containment sump temperature vs. time and the containment assumptions for back-pressure vs. time for a LOCA event applicable to BVPS Unit No. 1.

Containment Sump Temperature Time (seconds) Temperature (F) 2,900 186 6,000 162 10,000 158 20,000 148 Assumed Containment Back-Pressure Time Pressure (psia) 0 to 1273 seconds 60 1273 to 1547.89 seconds 27 1547.89 seconds to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 25 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 14.7