IR 05000361/2010008

IR 05000361-10-008; 01/01/2010 05/17/2010; San Onofre Nuclear Generating Station, Unit 2 Steam Generator Replacement Report; Steam Generator Replacement Activities

ML101810506
Person / Time
Site:	San Onofre
Issue date:	06/30/2010
From:	Ryan Lantz Division of Nuclear Materials Safety IV
To:	Ridenoure R Southern California Edison Co
References
IR-10-008
Download: ML101810506 (14)

Text

UNITED STATES NUC LEAR REG ULATO RY CO M M I SS I O N une 30, 2010

SUBJECT:

SAN ONOFRE NUCLEAR GENERATING STATION - UNIT 2 STEAM GENERATOR REPLACEMENT PROJECT INSPECTION REPORT 05000361/2010008

Dear Mr. Ridenoure:

On May 17, 2010, the U.S. Nuclear Regulatory Commission (NRC) completed a steam generator replacement inspection at your San Onofre Nuclear Generating Station, Unit 2 facility.

The enclosed inspection report documents the inspection findings, which were discussed on May 27, 2010, with Mr. Wharton and other members of your staff.

The inspections examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.

The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.

Based on the results of this inspection, no findings were identified. In accordance with 10 CFR 2.390 of the NRC's Rules of Practice, a copy of this letter, and its enclosure, will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records component of NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/

Ryan E. Lantz, Chief Project Branch D Division of Reactor Projects Docket No. 50-361 License No. NPF-10

Enclosure:

NRC Inspection Report 05000361/2010008 w/Attachment: Supplemental Information

Southern California Edison Company -2-

REGION IV==

Docket: 50-361 License: NPF-10 Report: 05000361/2010008 Licensee: Southern California Edison Co. (SCE)

Facility: San Onofre Nuclear Generating Station, Unit 2 Location: 5000 S. Pacific Coast Hwy San Clemente, California Dates: January 1, 2010 through May 17, 2010 Inspectors: D. Allen, Senior Project Engineer G. Warnick, Senior Resident Inspector J. Josey, Resident Inspector J. Reynoso, Resident Inspector Approved By: Ryan E. Lantz Chief, Project Branch D Division of Reactor Projects-1- Enclosure

SUMMARY OF FINDINGS

IR 05000361/2010008; 01/01/2010 - 05/17/2010; San Onofre Nuclear Generating

Station, Unit 2 Steam Generator Replacement Report; Steam Generator Replacement Activities.

The report covered a 5-month period of inspection by resident and regional inspectors. No findings were identified. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 4, dated December 2006.

NRC-Identified Findings and Self-Revealing Findings

None

Licensee-Identified Violations

None

REPORT DETAILS

Summary of Plant Status

Unit 2 began the inspection period shutdown for a scheduled refueling outage (U2C16) and steam generator replacement. The Unit 2 refueling outage was completed on April 11, 2010 and the plant returned to full power on May 17,

REACTOR SAFETY

Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity

1R19 Postmaintenance Testing

a. Inspection Scope

The inspectors used the guidance in Inspection Procedure 50001 to select and perform the following post-installation verification and testing inspection activities as part of the normal baseline inspection. Accordingly, inspection hours were charged to baseline inspection under NRC Inspection Report 05000361; 05000362/2010003. The inspectors witnessed or reviewed the results of postmaintenance testing for the following maintenance activities:

• March 26, 2010, Unit 2, post-inspection and verification of hot gap measurements for replacement steam generator activities

• April 16, 2010, Unit 2, primary to secondary leakage testing post steam generator replacement

• April 20, 2010, Unit 2, post-installation digital feedwater testing and level control stability

• May 25, 2010, Unit 2, pressurizer monitoring post steam generator replacement

• May 26, 2010, Unit 2, post steam generator replacement reactor coolant system flow acceptance test results In each case, the test procedures were reviewed to determine if the test adequately verified proper performance of the components affected by steam generator replacement and outage maintenance activities. The Updated Final Safety Analysis Report, Technical Specifications, and design-basis documents were also reviewed as applicable to determine the adequacy of the acceptance criteria listed in the test procedures.

Specific documents reviewed during this inspection are listed in the attachment.

b. Findings

No findings of significance were identified.

4OA5 Other Activities

a. Inspection Scope

The inspectors used the guidance in Inspection Procedure 50001 to select and perform the following post-installation verification and testing inspection activities, consistent with the safety significance and inspection resources and as part of normal baseline inspection efforts. Accordingly, some inspection hours were charged to baseline inspection under NRC Inspection Report 05000361; 05000362/2010003.

Containment Testing The inspectors performed system walk downs, observed the start, and conclusion of the Unit 2 containment integrated leakage rate test. The test procedure was reviewed and the inspectors verified that the potential leakage from containment at the design basis accident pressure remained within the limits stated in technical specifications. These inspections are documented in NRC Inspection Report 05000361; 05000362/2010002, Sections 1R04 and 1R19.

Steam Generator Secondary Side Leakage The inspectors reviewed the secondary side leakage test results and completed an inspection of the steam generators secondary side after the steam generators were filled to check for leakage.

Calibration and Testing of Instrumentation The inspectors observed and evaluated the calibration and testing of instrumentation for both the primary and secondary side systems impacted by the steam generator replacement in the following areas:

• Functional testing of spliced resistance temperature detector to reactor coolant system hot leg loops. These inspections are documented in NRC Inspection Report 05000361; 05000362/2010002, Section 1R19.

• Calibration and testing of steam generator E089, wide range water level transmitters following steam generator replacement Startup and Power Ascension The inspectors reviewed the startup and power ascension procedures to determine if the procedure adequately verified proper performance of the components affected by steam generator replacement and outage maintenance activities. The following inspection activities hours were charged to baseline inspection under NRC Inspection Report 05000361; 05000362/2010003,

Section 1R20: *

April 7-8, 2010, Unit 2, reactor startup and criticality following refueling

• April 10, 2010, Unit 2, main generator startup and rollup prior to unexpected trip on high volts to hertz prior to closing breaker Specific documents reviewed during this inspection are listed in the attachment.

b. Findings

No findings of significance were identified.

4OA6 Meetings

Exit Meeting Summary

On May 27, 2010, the inspectors presented the inspection results to Mr. M. Wharton, Manager, Steam Generator Replacement Project, and other members of the licensees staff. The licensee acknowledged the inspection results and observations presented. Some proprietary information was reviewed during this inspection but no proprietary information was included in this report.

ATTACHMENT:

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee Personnel

D. Axline, Technical Specialist, Nuclear Regulatory Affairs

D. Bauder, Plant Manager

G. Cook, Manager, Nuclear Regulatory Affairs

C. Harberts, Manager, Steam Generator Replacement Project

L. Hay, QA Manager, Bechtel

A. Hochevar, Station Manager, Plant Operations

E. Hubley, Director, Maintenance & Construction Services

L. Kelly, Engineer, Nuclear Regulatory Affairs

J. Madigan, Manager, Health Physics

A. Matheny, System Engineer

A. Meichler, Mechanical/System Engineering Supervisor

M. Mihalik, Areva Project Manager, Steam Generator Replacement Project

R. Nielsen, Supervisor, Nuclear Oversight

B. Power, Operations Manager, Catalina Pacific

C. Ryan, Manager, Maintenance & Construction Services

D. Schaffer, Civil Engineer

M. Wharton, Manager, Steam Generator Replacement Project

LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED

Opened and Closed

None