ML082070199

Order EA-03-009 Sixty-Day Report Reactor Pressure Vessel Head Inspection Results

ML082070199
Person / Time
Site:	Surry
Issue date:	07/18/2008
From:	Jernigan D Virginia Electric & Power Co (VEPCO)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
08-0327, EA-03-009
Download: ML082070199 (5)

Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 July 18, 2008 U.S. Nuclear Regulatory Commission Serial No. 08-0327 Attention: Document Control Desk SS&LITJN R1 11555 Rockville Pike Docket No. 50-281 Rockville, Maryland 20852 License No. DPR-37 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

SURRY POWER STATION UNIT 2 ORDER EA-03-009 SIXTY-DAY REPORT REACTOR PRESSURE VESSEL HEAD INSPECTION RESULTS On February 20, 2004, the NRC issued the First Revised Order (EA-03-009) establishing interim inspection requirements for reactor pressure vessel (RPV) heads.

In accordance with the Order's inspection and reporting requirements, this letter provides the results of the visual examination of the reactor vessel upper head surface (including 360 degrees around each RPV head penetration nozzle) to identify any evidence of boron or corrosive product. This examination was performed during the Surry Power Station Unit 2 spring 2008 refueling outage.

If you have any questions or require additional information, please contact Mr. Trace Niemi at (757) 365-2848.

Sincerely, Z.E. Jernigan, Site Vice President

)urry Power Station Commitments made in this letter: None

Attachment:

Sixty-Day Report - Reactor Pressure Vessel Head Inspection Results -

Surry Power Station Unit 2

Serial No. 08-0327 Docket No. 50-281 RPVH Inspection Results Page 2 of 2 CC: U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center Suite 23T85 61 Forsyth Street, SW Atlanta, Georgia 30303 NRC Senior Resident Inspector Surry Power Station Mr. S. P. Lingam NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, Maryland 20852 Mr. R. A. Smith Authorized Nuclear Insurance Inspector Surry Power Station

Attachment Order EA-03-009 Sixty-Day Report - Reactor Pressure Vessel Head Inspection Results Surry Power Station Unit 2 Virginia Electric and Power Company (Dominion)

Serial No. 08-0327 Docket No. 50-281 60-Day RPVH Visual Inspection Results Page 1 of 2 Sixty-Day Report- Reactor Pressure Vessel Head Inspection Results Surry Power Station Unit 2 Introduction During the Surry Unit 2 spring 2008 refueling outage (S2R21), Virginia Electric and Power Company (Dominion) performed an examination of the reactor vessel upper head to meet the First Revised NRC Order EA-03-009 issued February 20, 2004. This examination consisted of a bare metal visual examination of the head surface, including 360 degrees around each reactor pressure vessel (RPV) head penetration nozzle to identify any evidence of boron or corrosive product.

Inspections The examination method used remote VT-2 examination to inspect the vessel head surface and penetration areas behind the shroud. Direct VT-2 examination was performed on the vessel head surface outside the shroud down to the vessel flange. For Control Rod Drive Mechanism (CRDM) penetrations, the area of interest was 360 degrees around each of the penetrations protruding through the vessel head including the annulus (crevice between the vessel head and the penetrations). For the vessel upper head, the area of interest was the metal surface of the head between and around the penetrations including the head surface down to the transition area at the vessel head flange.

Examination results Penetrations An initial inspection was performed in the as found condition. The inspection was performed 360 degrees around each penetration annulus. Compressed air (max. 60 psi) was used to remove loose debris around penetrations which were considered masked. Three penetrations, #30, #50, and #59, required additional evaluation following debris removal using compressed air. No evidence of leakage was identified in these inspections.

Head Surface A visual examination was performed on the head surface with no evidence of boric acid residue. Some regions contained debris and discoloration but were determined to not be masking an examination of the head surface.

100% examination of the head surface was not possible due to interference with the shroud support structure; however, examination included those areas of the RPV head upslope and downslope from the support structure interference, and examination of greater than 95% of the head surface was achieved.

Serial No. 08-0327 Docket No. 50-280 60-Day RPVH Visual Inspection Results Page 2 of 2 Summary In summary, 100% of the annulus regions for the head penetrations and greater than 95%

of the vessel head surface were examined using the bare metal visual examination technique with no evidence of leakage or surface degradation.