ML042460071

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Draft Request for Additional Information
ML042460071
Person / Time
Site: Seabrook NextEra Energy icon.png
Issue date: 09/02/2004
From: Scott Wall
NRC/NRR/DLPM/LPD1
To: Dan Collins
NRC/NRR/DLPM/LPD1
Wall, S. NRR/DLPM 415-2855
References
TAC MC2364
Download: ML042460071 (2)


Text

September 2, 2004 MEMORANDUM TO:

Daniel S. Collins, Acting 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. MC2364)

By letter dated August 18, 2004, the Nuclear Regulatory Commission (NRC) staff issued a request for additional information (RAI) regarding the FPL Energy Seabrook, LLC (FPLE or the licensee), application to increase the licensed thermal power level at Seabrook Station, Unit No. 1.

The NRC staff determined that additional information was needed. The attached RAIs were transmitted on September 1, 2004, to Mr. Michael OKeefe (FPLE) as additional RAIs to the August 18, 2004, letter.

Docket No. 50-443

Attachment:

RAI

MEMORANDUM TO:

Daniel S. Collins, Acting 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. MC2364)

By letter dated August 18, 2004, the Nuclear Regulatory Commission (NRC) staff issued a request for additional information (RAI) regarding the FPL Energy Seabrook, LLC (FPLE or the licensee), application to increase the licensed thermal power level at Seabrook Station, Unit No. 1.

The NRC staff determined that additional information was needed. The attached RAIs were transmitted on September 1, 2004, to Mr. Michael OKeefe (FPLE) as additional RAIs to the August 18, 2004, letter.

Docket No. 50-443

Attachment:

RAI DISTRIBUTION PUBLIC PDI-2 Reading DCollins SWall RLobel ACCESSION NO.: ML042460071 OFFICE PDI-2/PM NAME SWall DATE 9/1/04 OFFICIAL RECORD COPY

Attachment REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED STRETCH POWER UPRATE (SPU) AMENDMENT SEABROOK STATION, UNIT NO. 1 (SEABROOK)

DOCKET NO. 50-443 Containment Assessment 96.

In support of LAR Section 6.4.1, "Loss of Coolant Accident (LOCA) Mass and Energy Release," justify the use of equipment qualification temperatures for the acceptance criterion for containment LOCA calculations. Why is this acceptable to demonstrate structural adequacy?

97.

In Section 6.4.1.1.7, "Acceptance Criteria for Analyses," FPLE states that the criteria for sources of heat for the LOCA mass and energy release calculations is stated as Appendix K Paragraph I.A. However, the decay heat is stated in 6.4.1.1.8, "Mass and Energy Release Data," as being calculated from Reference 6.4-5, "American National Standard for Decay Heat Power in Light Water Reactors." These are different models.

Please explain the inconsistency.

98.

In Section 6.4.4.2, "Input Parameters and Assumptions," and Section 6.4.4.4, "Results,"

FPLE gives Reference 6.4-1, "Westinghouse LOCA Mass and Energy Release Model for Containment Design -March 1979 Version," as a reference for main steam line break mass and energy release guidance. Reference 6.4-1 refers to LOCAs. Verify that this is the correct reference.

99.

State the version of the GOTHIC computer code was used for the Seabrook containment analysis. Verify that GOTHIC was used consistent with the NRC safety evaluation report for Kewaunee dated September 29, 2003.