ML042190042

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Draft Request for Additional Information, Amendment Request Dated 10/06/2003 to Revise Technical Specifications for Full Implementation of Alternate Source Term
ML042190042
Person / Time
Site: Seabrook NextEra Energy icon.png
Issue date: 08/06/2004
From: Scott Wall
NRC/NRR/DLPM/LPD1
To: Clifford J
NRC/NRR/DLPM/LPD1
Wall, S. NRR/DLPM 415-2855
References
TAC MC1097
Download: ML042190042 (3)


Text

August 6, 2004 MEMORANDUM TO: James W. Clifford, Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM: Scott P. Wall, Project Manager, Section 2 /RA/

Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation

SUBJECT:

SEABROOK STATION, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NO. MC1097)

The attached draft request for information (RAI) was transmitted on August 6, 2004, to Mr. Michael OKeefe of FPL Energy Seabrook, LLC (FPLES or the licensee). This draft RAI was transmitted to facilitate the technical review being conducted by NRR and to support a conference call with the licensee to discuss the RAI.

This RAI is related to the licensees amendment request for Seabrook Station (Seabrook) dated October 6, 2003. The proposed amendment would revise Seabrooks Technical Specifications for full implementation of an alternate source term. This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensee's request.

Docket No. 50-443

Attachment:

RAI

MEMORANDUM TO: James W. Clifford, Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM: Scott P. Wall, Project Manager, Section 2 /RA/

Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation

SUBJECT:

SEABROOK STATION, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NO. MC1097)

The attached draft request for information (RAI) was transmitted on August 6, 2004, to Mr. Michael OKeefe of FPL Energy Seabrook, LLC (FPLES or the licensee). This draft RAI was transmitted to facilitate the technical review being conducted by NRR and to support a conference call with the licensee to discuss the RAI.

This RAI is related to the licensees amendment request for Seabrook Station (Seabrook) dated October 6, 2003. The proposed amendment would revise Seabrooks Technical Specifications for full implementation of an alternate source term. This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensee's request.

Docket No. 50-443

Attachment:

RAI DISTRIBUTION PUBLIC PDI-2 Reading JClifford SWall ACCESSION NO.: ML042190042 OFFICE PDI-2/PM NAME SWall DATE 8/6/04 OFFICIAL RECORD COPY

REQUEST FOR ADDITIONAL INFORMATION RELATED TO ALTERNATE SOURCE TERM AMENDMENT REQUEST SEABROOK STATION DOCKET NO. 50-443 TAC NO. MC1097 By letter dated October 6, 2003, FPL Energy Seabrook, LLC (FPLES or the licensee) submitted an amendment request for Seabrook. The proposed amendment would revise Seabrooks Technical Specifications for full implementation of an alternate source term (AST).

The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information the licensee provided that supports the proposed amendment and requests the following additional information to clarify the submittal.

1. Regulatory Guide 1.183, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors," provides assumptions acceptable to the NRC staff for evaluating the radiological consequences of design basis accidents at pressurized-water reactors and states the following:

"The density used in converting volumetric leak rates (e.g., gpm) to mass leak rates (e.g., lbm/hr) should be consistent with the basis of surveillance tests used to show compliance with leak rate technical specifications. These tests are typically based on cool liquid. Facility instrumentation used to determine leakage is typically located on lines containing cool liquids. In most cases, the density should be assumed to be 1.0 gm/cc (62.4 lbm/ft3)."

Provide the density values used for the event analyses discussed in Section 2, "Radiological Consequences - Event Analyses," of Enclosure 2 of the October 6, 2003, submittal. Explain the basis for these values (i.e. based on cool versus hot liquid).

Attachment