ML092300230

Inservice Inspection Owner'S Activity Report

ML092300230
Person / Time
Site:	Surry
Issue date:	08/07/2009
From:	Stanley B Virginia Electric & Power Co (VEPCO)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
09-499
Download: ML092300230 (7)

Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 August 7, 2009 U.S. Nuclear Regulatory Commission Serial No.: 09-499 Attention: Document Control Desk S&L/TJN: R0 Washington, D.C. 20555-0001 Docket No.: 50-280 License No.: DPR-32 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

SURRY POWER STATION UNIT 1 INSERVICE INSPECTION OWNER'S ACTIVITY REPORT As allowed by ASME Code Case N-532-4, "Alternative Requirements to Repair and Replacement Documentation Requirements and Inservice Summary Report Preparation and Submission as Required by IWA-4000 and IWA-6000,Section XI, Division 1", the Form OAR-1 for Surry Unit 1 refueling outage S1R22 is enclosed. This document contains in Tables 1 and 2 the reporting requirements for the second refueling outage of the second period in the fourth ten-year inservice inspection interval for Surry Unit 1 from December 2, 2007 through the duration of the S1R22 refueling outage that was completed on May 11, 2009. The second period ends on October 13, 2010.

Should you have any questions regarding this submittal, please contact Mr. Trace Niemi at (757) 365-2848.

Very truly yours, B. L.SStanley Director Nuclear Station (S&L)

Surry Power Station Commitments made in this letter: None

Attachment:

1. Owner's Activity Report (Form OAR-I), Surry Unit 1 Refueling Outage S1 R22, Second Period of the Fourth Ten-Year ISI Interval

Serial No.09-499 Docket No. 50-280 Page 2 of 2 cc: U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center, 23 T85 61 Forsyth Street, SW Atlanta, Georgia 30303-8931 NRC Senior Resident Inspector Surry Power Station Ms. K. R. Cotton NRC Project Manager U. S. Nuclear Regulatory Commission Mail Stop 16E15 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 Mr. R. A. Smith Authorized Nuclear Inspector Surry Power Station

Serial No.09-499 Docket No. 50-280 Attachment Owner's Activity Report (Form OAR-I)

Surry Unit 1 Refueling Outage S1R22 Second Period of the Fourth Ten-Year ISI Interval Virginia Electric and Power Company (Dominion)

CASE CASES OF ASME BOILER AND PRESSURE VESSEL CODE N-532-4 FORM OAR-1 OWNER'S ACTIVITY REPORT Report Numberi: 1-4-2-2 (Unit 1, 4 th Interval, 2 nd Period, 2 nd Report)

Plant Surry Power Station, 5570 Hog Island Road, SurrV, VA 23883 Unit No. 1 Commercial service date 12/22/1972 Refueling outage no. S1 R22 (if applicable)

Current inspection interval 4 th (1sl, 2 na, 3 r0, 4 t, other)

Current inspection period 2 nd (1st, 2 nl, 3 rc)

Edition and Addenda of Section XI applicable to the inspection plans 1998 Edition, 2000 Addenda Date and revision of inspection plans Surry Unit 1, 4th Interval ISi Plan, Revision 6t", January 1, 2009.

Edition and Addenda of Section XAapplicable to repair/replacement activities, if different than the inspection plans Code Cases used: N-532-4 (if applicable)

CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests meet the Inspection Plan as required by the ASME Code, Section Xl; and (c) the repair/replacement activities and evaluations supporting the completion of S1 R22 conform to the requirements of Section XA.

(refueling outage number)

Signed _ -Da i&' te 7 44 0 Owner or Owner's Desnee, Title f CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Virginia and employed by H.S.B I&I of CT have inspected the items described in this Owner's Activity Report, and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or co~nnected th mction.

V-"(.i 21$ ý' Commissions VA883(R)

• spector's Sigat-ure" National Board, State, Province and Endorsements Date 7-31 Page 1 of 4

CASE CASES OF ASME BOILER AND PRESSURE VESSEL CODE N-532-4 FORM OAR-1 OWNER'S ACTIVITY REPORT Table 1 Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination Item Description Evaluation Description Category and Item Number F-A, F1.1OB 2-RC-59/1-RC-H006 One support bolt had 1/8" gap between washer and base plate but was not loose. A second bolt was found to be loose. The line was evaluated and determined that deadweight, thermal, and seismic stresses were acceptable. The two concrete anchors bolts were tightened (W038102537460, CR331773).

2-CH-93/1-CH-HOOI Rod hanger support bolt with nut F-A, Fl.10A was not completely tight to the side of the clevis. Engineering evaluation concluded that the support was acceptable (CR331940).

F-A, F1.10B* 2-RC-53/1-RC-H010 Missing bolt on pipe rack support structure. Engineering evaluation showed that the missing bolt would not prevent the support structure from performing its design function (CR332111). The missing bolt was replaced (WO 38102540046).

[Cross-ref. R/R Plan # 2008-444, Table 2]

F-A, F1.20C 30-SHP-3/1-SHP-HOOIB Load indicator plate missing from spring can. Engineering evaluation showed that the cold load reading

• waswithin tolerance and was acceptable (CR332697).

F-A, F1.40B 2-SI-70/1-SI-HO12 Bent rod and insufficient thread engagement found on support.

Engineering evaluation indicated that the support was acceptable (CR332901).

F-A, F 1.1OA 10-RH-16/l-RH-H008 Gaps in box support do not match drawings. Engineering evaluation showed that the support fully qualified, and did not require any repairs (CR332067).

F-A, F1.1OC 12-SI-47/1-SI-H033B Spring hanger had: 1) 0.200" gap between plate and wall; 2) right hand middle bolt washer on "Detail A" can be spun; 3) load indicator for the spring was above top of the scale. Engineering evaluation: 1) acceptable as is, 2) found this condition operable but degraded and Page 2 of 4

CASE CASES OF ASME BOILER AND PRESSURE VESSEL CODE N-532-4 FORM OAR-1 OWNER'S ACTIVITY REPORT created WO to torque the bolt with the loose washer, and 3) the cold load for the spring hanger was acceptable (CR333068, W038102551641).

F-A, F1.20B 2-SI-74/1-SI-H015 Missing bolt on pipe rack support structure. Engineering evaluation showed that the missing bolt would not prevent the support structure from performing its design function (CR333079). The missing bolt was replaced (W038102540046).

[Cross-ref. R/R Plan # 2008-444, Table 2]

F-A, F1.1OC 4-RC-34/1-RC-HOO1 Missing load indicator plate on spring support. Engineering evaluation showed that the cold load reading was acceptable (CR333888).

F-A, F1.1OC 3-RC-35/1-RC-H010 Missing load indicator plate on spring support. Engineering evaluation showed that the cold load reading was acceptable (CR333891).

Owner Commitments RHR Heat Exchangers, 1-RH-E-IA As-left thinned areas in the hub of Areas adjacent to RHR Heat and 1-RH-E-1B the main flange (CR332395).

Exchanger shell weld Engineering evaluation indicated ASME Category C-A, C1.10 that all excavated areas for both heat exchangers were acceptable.

Boric Acid Corrosion Control RHR Heat Exchanger A, 1-RH-E- 1A Main flange connection of RHR Program Bolting Heat Exchanger, 1-RH-E- IA with degraded bolts (CR332725).

IWA-5250 System Leakage Test Engineering evaluation results Program showed that the structural integrity (Areas adjacent to RHR Heat of the main flange connection will Exchanger shell weld be maintained until the end of the ASME Category C-A, C 1.10) next fuel cycle. [Cross-ref. RfR Plan

1. 2008-409, Table 2]

R-A, Ri. 13 Recirculation Spray Service Water Low UT thickness reading on Piping Recirculation Spray Service Water piping. Engineering assessed the minimum wall thickness for the Service Water piping, and determined that the reading was acceptable (CR332897).

Scope expansion initially required but after further review by engineering the support was acceptable in the as found condition.

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CASE CASES OF ASME BOILER AND PRESSURE VESSEL CODE N-532-4 FORM OAR-1 OWNER'S ACTIVITY REPORT Table 2 Abstract of Repair/Replacement Activities Required for Continued Service Code Class Item Description Description of Work Date Repair/Replacement Completed Plan Number I 01-RC-HCV-1557B Replace Fasteners 05/07/2009 2008-397 1IWF** 01-RC-PP-2.00-RC- Install Cap Screw on 05/02/2009 2008-444 PIPE-53-1502 Support H-010 2 01-RH-E-lA Perform Base-metal Repair 04/30/2009 2008-254 2 01-RH-E-1A Replace Fasteners 04/25/2009 2008-409 2 01 -RH-E- 1.B Perform Base-metal Repair 05/07/2009 2008-255 3 01-SW-573 Repair Weld 03/11/2008 2008-075 3 01-VS-E-4C Repair Endbell to Chiller 11/15/2008 2008-322 3 01-SW-PCV-100D Replace Valve Body and 02/01/2009 2008-332 Fasteners 3*** 01-WS-PP-48.00- Weld Repair as Required 05/03/2009 2008-447 WS-PIPE-2-10 3 01-SW-934 Weld Repair as Required 05/10/2008 2008-324 3 01-SW-PCV-100E Replace Valve Body and 02/25/2009 2009-003 Fasteners

• • Class I Support

• • • Relief Request SPT-008 submitted 05/08/2009; verbally approved by the NRC Acting Project Manager Jon Thompson (05/08/09)

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