ML093360465

Draft Request for Additional Information

ML093360465
Person / Time
Site:	Salem
Issue date:	12/02/2009
From:	Richard Ennis Plant Licensing Branch 1
To:	Chernoff H Plant Licensing Branch 1
Ennis R, NRR/DORL, 415-1420
References
TAC ME2374, WCAP-17071-P
Download: ML093360465 (3)

Text

December 2, 2009 MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Senior Project Manager /ra/

Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

SUBJECT:

SALEM NUCLEAR GENERATING STATION, UNIT NO. 1, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NO. ME2374)

The attached draft request for information (RAI) was transmitted on December 2, 2009, to Mr. Jeff Keenan of PSEG Nuclear LLC (the licensee). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensee=s amendment request for Salem Nuclear Generating Station (Salem), Unit No. 1, dated October 8, 2009. The proposed amendment would revise Technical Specification (TS) 6.8.4.i, Steam Generator (SG) Program, by adding a one-time (interim) alternate repair criterion that excludes certain portions of the tube below the top of the SG tubesheet from periodic SG tube inspections. In addition, the proposed amendment would revise TS 6.9.10, Steam Generator Tube Inspection Report, to provide reporting requirements specific to the alternate repair criteria. The proposed amendment is supported by Westinghouse Electric Company, LLC Topical Report WCAP-17071-P, H*: Alternate Repair Criteria for the Tubesheet Expansion Region in Steam Generators with Hydraulically Expanded Tubes (Model F). H* (pronounced H star) is the length of hydraulically expanded SG tube that must remain intact within the tubesheet in order for the joint to resist pullout and leakage due to normal operating and accident conditions.

This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensees request.

Docket No. 50-272

Attachment:

Draft RAI

December 2, 2009 MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Senior Project Manager /ra/

Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

SUBJECT:

SALEM NUCLEAR GENERATING STATION, UNIT NO. 1, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NO. ME2374)

The attached draft request for information (RAI) was transmitted on December 2, 2009, to Mr. Jeff Keenan of PSEG Nuclear LLC (the licensee). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensee=s amendment request for Salem Nuclear Generating Station (Salem), Unit No. 1, dated October 8, 2009. The proposed amendment would revise Technical Specification (TS) 6.8.4.i, Steam Generator (SG) Program, by adding a one-time (interim) alternate repair criterion that excludes certain portions of the tube below the top of the SG tubesheet from periodic SG tube inspections. In addition, the proposed amendment would revise TS 6.9.10, Steam Generator Tube Inspection Report, to provide reporting requirements specific to the alternate repair criteria. The proposed amendment is supported by Westinghouse Electric Company, LLC Topical Report WCAP-17071-P, H*: Alternate Repair Criteria for the Tubesheet Expansion Region in Steam Generators with Hydraulically Expanded Tubes (Model F). H* (pronounced H star) is the length of hydraulically expanded SG tube that must remain intact within the tubesheet in order for the joint to resist pullout and leakage due to normal operating and accident conditions.

This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensee's request.

Docket No. 50-272

Attachment:

Draft RAI DISTRIBUTION PUBLIC RidsNrrDorlLpl1-2 LPLI-2 Reading RidsNrrPMSalem RidsNrrDorlDpr EMurphy, CSGB ACCESSION NO.: ML093360465 OFFICE LPLI-2/PM NAME REnnis DATE 12/2/09 OFFICIAL RECORD COPY

DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED LICENSE AMENDMENT INTERIM ALTERNATE REPAIR CRITERIA FOR STEAM GENERATOR INSPECTIONS SALEM NUCLEAR GENERATING STATION, UNIT NO. 1 DOCKET NO. 50-272 By letter dated October 8, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML092960581), PSEG Nuclear LLC (the licensee) submitted an amendment request for Salem Nuclear Generating Station (Salem), Unit No. 1. The proposed amendment would revise Technical Specification (TS) 6.8.4.i, Steam Generator (SG) Program, by adding a one-time (interim) alternate repair criterion that excludes certain portions of the tube below the top of the SG tubesheet from periodic SG tube inspections. In addition, the proposed amendment would revise TS 6.9.10, Steam Generator Tube Inspection Report, to provide reporting requirements specific to the alternate repair criteria. The proposed amendment is supported by Westinghouse Electric Company, LLC Topical Report WCAP-17071-P, H*: Alternate Repair Criteria for the Tubesheet Expansion Region in Steam Generators with Hydraulically Expanded Tubes (Model F). H* (pronounced H star) is the length of hydraulically expanded SG tube that must remain intact within the tubesheet in order for the joint to resist pullout and leakage due to normal operating and accident conditions.

The Nuclear Regulatory Commission staff has reviewed the information the licensee provided that supports the proposed amendment and would like to discuss the following issues to clarify the submittal.

1) Page 3 of Attachment 1 to the application dated October 8, 2009, suggests that the top of the tubesheet region has been inspected in the past. However, the licensee's most recent SG tube inspection report dated October 10, 2007 (ADAMS Accession No. ML072970094), doesn't seem to mention rotating coil inspections at the top of the tubesheet, apart from a few tubes that were inspected for over-expansions or bulges.

Was a general program of rotating coil inspections performed at the top of the tubesheet and, if so, what was the sample size?

Attachment