ML11333A126
| ML11333A126 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 12/07/2011 |
| From: | V Sreenivas Plant Licensing Branch II |
| To: | Heacock D Virginia Electric & Power Co (VEPCO) |
| Sreenivas V, 415-2597 | |
| References | |
| TAC ME7245 | |
| Download: ML11333A126 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 7, 2011 Mr. David A. Heacock President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
NORTH ANNA POWER STATION, UNIT NO.2,
SUMMARY
OF CONFERENCE CALL REGARDING THE 2011 STEAM GENERATOR TUBE INSPECTION RESULTS (TAC NO. ME7245)
Dear Mr. Heacock:
The U.S. Nuclear Regulatory Commission (NRC) staff formally reviews all steam generator (SG) inservice inspection summary reports submitted by licensees in accordance with the plant's Technical Specification requirements. The NRC staff also participates in conference calls with most licensees when approximately 70 percent of the SG tube inspections are completed. On October 5, 2011, the NRC staff participated in a conference call with Virginia Electric and Power Company representatives regarding the ongoing SG tube inspection activities for North Anna Power Station, Unit No.2. The summary of the conference call is enclosed.
Please contact me at (301) 415-2597, if you have any questions regarding this issue.
Sincerely,
. Sreenivas, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-339
Enclosure:
Summary of Conference Call cc w/encl: Distribution via Listserv
SUMMARY
OF CONFERENCE CALL WITH NORTH ANNA POWER STATION, UNIT NO.2 REGARDING THE 2011 STEAM GENERATOR TUBE INSPECTION RESULTS DOCKET NO. 50-339 On October 5, 2011, the Nuclear Regulatory Commission (NRC) staff participated in a conference call with representatives of Virginia Electric and Power Company, LLC (the licensee), regarding their ongoing steam generator (SG) tube inspection activities at North Anna Power Station (NAPS),
Unit No.2. A summary of the conference call is enclosed. The NRC staff provided an agenda to the licensee via email on October 4, 2011 (Agencywide Documents Access Management System (ADAMS) Accession No. ML11277A286).
NAPS Unit No.2 has three Model 54F Westinghouse recirculating SGs, which are designated A, B, and C. Each SG contains 3592 thermally treated Inconel 690 tubes, which have a nominal outside diameter of 0.875 inches and a nominal wall thickness of 0.050 inches. The tubes have been hydraulically expanded into the tubesheet and the stainless steel Type 405 tube support plates contain broached quatrefoil holes. These replacement SGs began operation in 1995.
Additional clarifying information or information not included in the document provided by the licensee is summarized below:
- At the time of the call, the SG inspections had already been completed.
There was zero primary-to-secondary leakage detected in the previous operating cycle.
No secondary side pressure tests were performed during the current outage.
No exceptions were taken to the industry guidelines.
The inspection scope in the current outage was 100-percent bobbin coil examination from tube end to tube end in SGs A and C. An inspection was also performed to detect loose parts and loose part wear using a rotating pancake coil (RPC) probe on approximately 570 tubes in both the hot-leg and cold-leg of SGs A and C. The 570 tubes represent a 50-percent sample of the peripheral tubes (5 tubes deep) on the hot-leg and cold-leg of SGs A and C. In addition, approximately 350 additional tubes, internal to the tube bundle, were RPC tested on the hot-leg side of SGs A and C, also screening for loose parts and loose part wear. The bobbin coil examination was also used to detect loose parts.
No new dents or dings were found by the inspections in SGs A and C and historical dents and dings showed no indication of growth.
No tubes were plugged and no in-situ pressure testing or tubes pulls were performed.
Enclosure
-2
- Secondary side inspections of SGs A and C included visual examination of the steam drum, J-nozzles, and feedring, as well as ultrasonic testing examination offeedring. Additionally, the primary and secondary moisture separators were visually inspected in SGs A and C.
December 7, 2011 Mr. David A. Heacock President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
NORTH ANNA POWER STATION, UNIT NO.2,
SUMMARY
OF CONFERENCE CALL REGARDING THE 2011 STEAM GENERATOR TUBE INSPECTION RESULTS (TAC NO. ME7245)
Dear Mr. Heacock:
The U.S. Nuclear Regulatory Commission (NRC) staff formally reviews all steam generator (SG) inservice inspection summary reports submitted by licensees in accordance with the plant's Technical Specification requirements. The NRC staff also participates in conference calls with most licensees when approximately 70 percent of the SG tube inspections are completed. On October 5, 2011, the NRC staff participated in a conference call with Virginia Electric and Power Company representatives regarding the ongoing SG tube inspection activities for North Anna Power Station, Unit No.2. The summary of the conference call is enclosed.
Please contact me at (301) 415-2597, if you have any questions regarding this issue.
Sincerely, IRA!
V. Sreenivas, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-339
Enclosure:
Summary of Conference Call cc w/encl: Distribution via Listserv DISTRIBUTION:
Public LPL2-1 R/F RidsAcrsAcnw_MailCTR Resource VCusumano, NRR RidsNrrDorlLpl2-1 Resource RidsOgcRpResource KKarwoski, NRR RidsNrrDssStsb Resource RidsNrrPMNorthAnna (hard copy)
AJohnson, NRR RidsRgn2MailCenter RidsNrrLAMO'Brien (hard copy)
RidsNrr/De/EsgbResource memo transmitted 10/17/11 OFFICIAL RECORD COPY LPL2-1/BC LPL2-1/PM GKulesa Sreenivas 12/7/11 1217111