ML13179A318

Electronic Transmission, Draft Request for Additional Information Regarding 2012 Steam Generator Tube Inspection Reports

ML13179A318
Person / Time
Site:	Beaver Valley
Issue date:	07/01/2013
From:	Peter Bamford Plant Licensing Branch 1
To:	Veronica Rodriguez Plant Licensing Branch 1
Bamford P
References
TAC MF0592, TAC MF1499
Download: ML13179A318 (4)

Text

July 1, 2013 MEMORANDUM TO: Veronica Rodriguez, Acting Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Peter Bamford, Project Manager /ra/

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

SUBJECT:

BEAVER VALLEY POWER STATION, UNIT NO. 2 - ELECTRONIC TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING 2012 STEAM GENERATOR TUBE INSPECTION REPORTS (TAC NOS. MF0592 AND MF1499)

The attached draft request for additional information (RAI) was transmitted by electronic transmission on June 27, 2013, to Mr. Phil Lashley, at FirstEnergy Nuclear Operating Company, LLC (FENOC, the licensee). This draft RAI was transmitted to facilitate the technical review being conducted by the Nuclear Regulatory Commission (NRC) staff and to support a conference call (if needed) with FENOC in order to clarify the licensees reports summarizing the results of the 2012 steam generator tube inspections at Beaver Valley Power Station, Unit 2.

The draft RAI is related to the licensees submittals dated January 24, 2013, and April 23, 2013.

The draft questions were sent to ensure that they were understandable, the regulatory basis was clear, and to determine if the information was previously docketed. Additionally, review of the draft RAI would allow FENOC to evaluate and agree upon a schedule to respond to the RAI.

This memorandum and the attachment do not represent an NRC staff position.

Docket No. 50-412

Enclosure:

As stated

July 1, 2013 MEMORANDUM TO: Veronica Rodriguez, Acting Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Peter Bamford, Project Manager /ra/

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

SUBJECT:

BEAVER VALLEY POWER STATION, UNIT NO. 2 - ELECTRONIC TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING 2012 STEAM GENERATOR TUBE INSPECTION REPORTS (TAC NOS. MF0592 AND MF1499)

The attached draft request for additional information (RAI) was transmitted by electronic transmission on June 27, 2013, to Mr. Phil Lashley, at FirstEnergy Nuclear Operating Company, LLC (FENOC, the licensee). This draft RAI was transmitted to facilitate the technical review being conducted by the Nuclear Regulatory Commission (NRC) staff and to support a conference call (if needed) with FENOC in order to clarify the licensees reports summarizing the results of the 2012 steam generator tube inspections at Beaver Valley Power Station, Unit 2.

The draft RAI is related to the licensees submittals dated January 24, 2013, and April 23, 2013.

The draft questions were sent to ensure that they were understandable, the regulatory basis was clear, and to determine if the information was previously docketed. Additionally, review of the draft RAI would allow FENOC to evaluate and agree upon a schedule to respond to the RAI.

This memorandum and the attachment do not represent an NRC staff position.

Docket No. 50-412

Enclosure:

As stated DISTRIBUTION:

Public RidsNrrPMBeaverValley Resource LPL1-2 R/F Accession No.: ML13179A318

• via memo OFFICE LPL1-2/PM ESGB/BC NAME PBamford PKlein for GKulesa*

DATE 7/1/13 6/20/2013 OFFICIAL RECORD COPY

DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING 2012 STEAM GENERATOR TUBE INSPECTION REPORTS FIRST ENERGY NUCLEAR OPERATING COMPANY BEAVER VALLEY POWER STATION, UNIT 2 DOCKET NO. 50-412 By letters dated January 24, 2013 (Agencywide Documents Access and Management System (ADAMS) Package Accession Number ML130280632), and April 23, 2013 (ADAMS Accession Number ML13114A050), FirstEnergy Nuclear Operating Company, Inc (FENOC, the licensee) submitted information summarizing the results of the 2012 steam generator (SG) tube inspections at Beaver Valley Power Station, Unit 2. These inspections were performed during the sixteenth refueling outage (2R16). In addition, the NRC staff summarized discussions about the 2012 inspections in a letter dated November 13, 2012 (ADAMS Accession Number ML12310A066). The U.S. Nuclear Regulatory Commission (NRC) staff is currently reviewing the submittals and has determined that the additional information requested below is needed to complete its review.

Regarding the letter dated January 24, 2013:

Enclosure A: Voltage-Based Repair Criteria 90-Day Report

1. Some plants that have implemented the voltage-based repair criteria have had instances of extreme voltage growth. This has led to additional rotating probe inspections and repair of some tubes based on the nature of the indications at the tube support elevation (e.g., one dominant crack versus a network of cracks).

Please discuss whether this operating experience was included in your assessment of the flaws at the tube support elevations.

2, On page 2-1 it was indicated that no circumferential or axial indication extending outside the top support plate (TSP) were identified by +Point inspection at the TSP distorted signal indication (DSI) locations. Please clarify. Was it the intent of this sentence to indicate tube support plates?

Enclosure B: Steam Generator F* (F Star) Report

3. In your assessment of accident induced leakage in the F* report, you compare the leakage from the sleeves to the acceptance limit. Please confirm that you combined all sources of accident induced leakage (from sleeves, plugs, and other degradation mechanisms) and then compared the total leakage to the accident induced leakage limit.

4. The F* report does not appear to report the cumulative number of indications detected in the tubesheet region as a function of elevation within the tubesheet, as required by TS 5.6.6.2.4.(b). Please discuss.

DRAFT Regarding the letter dated April 23, 2013:

5. Regarding Note 4 of Table 2RCS-SG21A, please confirm that the 6 tubes being referred to only have indications at the tube support plate elevations and that one other tube with an axial outside diameter stress corrosion cracking indication also had a circumferential primary water stress corrosion crack.

6. In the section related to the reporting requirements of TS 5.6.6.2.1.a (scope of inspections performed on each SG) a visual inspection of the SG A steam drum region is described. In the paragraph titled SG A Feedwater Header, the report states that no anomalies were reported. Please clarify or expand upon what is meant by no anomalies.

7. In the section related to the reporting requirements of TS 5.6.6.2.1.a (scope of inspections performed on each SG) a divider plate weld (steam generator channel head) inspection is mentioned. Please provide the results of this inspection.