ML100680422
| ML100680422 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 02/25/2010 |
| From: | Stanley B Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 10-078 | |
| Download: ML100680422 (9) | |
Text
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 February 25, 2010 U.S. Nuclear Regulatory Commission Serial No.:
10-078 Attention: Document Control Desk S&LITJN:
RO Washington, D.C. 20555-0001 Docket No.: 50-281 License No.: DPR-37 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
SURRY POWER STATION UNIT 2 INSERVICE INSPECTION OWNER'S ACTIVITY REPORT (OAR)
As allowed by ASME Code Case N-532-4, "Alternative Requirements to Repair and Replacement Documentation Requirements and Inservic~e Summary Report Preparation and Submission as Required by IWA-4000 and IWA-6000, Section Xl, Division 1", the Form OAR-I, for Surry Unit 2 refueling outage.'S2R22,. 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 2 from May 22, 2008 through the duration of the $2R22 refueling outage that was completed on November 30, 2009. The second period ends on May 9, 2011.
Should you have any questions regarding this submittal, please contact Mr. Trace Niemi at (757) 365-2848.
Very truly yours, 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 2 Refueling Outage $2R22, Second Period of the Fourth Ten-Year ISI Interval
/i0W2
Serial No.10-078 Docket No. 50-281 Page 2 of 2 cc:
U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center Suite 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.10-078 Docket No. 50-281 Attachment Owner's Activity Report (Form OAR-I)
Surry Unit 2 Refueling Outage S2R22 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: 2-4-2-2 (Unit 2. 4 h Interval, 2 nd Period, 2 nd Report)
Plant Surry Power Station, 5570 Hoaq Island Road, Surrv, VA 23883 Unit No.
2 Commercial service date 05/01/1973 Refueling outage no.
S2R22 (if applicable)
Current inspection interval 4th
( 1 st, 2n T,
3 r0, 4 other)
Current inspection period 2 ndo (1st, 2 no, 3 r"),
Edition and Addenda of Section XI applicable to the inspection plans 1998 Edition, 2000 Addenda Date and revision of inspection plans Surry Unit 2. 4ý' Interval ISI Plan, Revision 7th, July 1,2009.
Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans Code Cases used:
Complete listing can be found in Revision 7 of the ISI Plan (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 XI; and (c) the repair/replacement activities and evaluations supporting the completion of S2R22 conform to the requirements of Section XI.
(refueling outage number)
Signed
- JifDate I* /C Owner or Owner's Designed, Title 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 XI.
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 connectedv'h tý ton
?k*.-.- -tz,-L-"'-* Commissions VA883(R)
In'pecdor's Sign ture National Board, State, Province and Endorsements Date
- /
0.
Page 1 of 6
CASE N-532-4 CASES OF ASME BOILER AND PRESSURE VESSEL CODE 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, F1.30C 6-CC-159/1-CC-H031 Lateral constraint spring support was identified to have movement obstruction of both struts and misalignment and binding of the spring can. Engineering evaluation showed that the subject spring support is considered fully functional. No corrective measures required. (CR355619).
F-A, F1.30B 24-WS-126-,10/2-WS-H014 Exfoliation was found on one of the four nuts, its washers, and lower support plates. Support has no physical damage or reduction in material thickness. Engineering determined that condition does not affect support functionality. No corrective measures required.
(CR356028).
F-A, F1.20A 10-SI-363/2-SI-H005 The subject hanger has one anchor bolt missing on the base plate.
Engineering evaluation indicated that the hanger was fully qualified and would perform its intended design function. No corrective m easures required. (CR356040).
F-A, Fl. lOB 4-RC-315/2-'RC-H032 The support was identified with a missing weld. Engineering evaluation indicated that the support was qualified in its existing condition due to significant design margin. No corrective measures required. An adjustment was made to add a flare bevel weld at the missing weld location.
(W038102664408, CR356256, CA151712).
[Cross reference, RR 2009-148, Table 2]
F-A, F1.20B 14-WFPD-1 17/2-WFPD-H006 Two loose nuts were identified in the support. The bolts and nuts are in the vertical plane and are intact.
Engineering evaluation indicated that the loose nuts do not have an impact on the ability of support to perform its intended function. No corrective measures were required.
The loose nuts were adjusted prior to Page 2 of 6
CASE N-532-4 CASES OF ASME BOILER AND PRESSURE VESSEL CODE FORM OAR-1 OWNER'S ACTIVITY REPORT the unit starting up (W038102668539, CR356708, CA151956).
F-A, F1.10C 2-CH-393/2-CH-HOO1 The spring hanger was identified to have a bent pipe clamp.
Engineering has determined that the support is fully functional. No corrective measures required.
(CR356611).
F-A, F1.40C 2-RC-498/2-RC-H001 The support was identified with a bent U-clamp, three nuts having improper thread engagement and moderate degradation of support plate. Engineering determined that the bent U-clamp and minor surface oxidation of the support plate have
- no impact on the ability of the support to perform its intended function. The three nuts with improper thread engagement do not have any affects on the support. No corrective measures required.
(CR357478, CA152446).
AUG, AUG-25*
4-RC-314/1-10 Two linear indications were identified on the subject weld (one 0.8" in the weld toe, and one 0.7" linear on the center line). The indications were removed using a controlled mechanical removal technique. Engineering evaluation results showed that the structural integrity of the line is acceptable (CEM-0055). Expanded scope examinations were required as a result of these indications. The expanded scope examinations were satisfactory (W038102680871, CR357794, CA152631, CA152633)
[Cross reference, RR 2009-164, Table 2]
F-A, F1.30C 6-WAPD-102/2-WAPD-H002 The spring support load exceeded the 10% criteria. Engineering reviewed the support and pipe stress calculations, and conducted conservative assessment of the piping configuration and determined the setting would have no adverse impact on the piping, adjacent supports, or the containment penetration. Therefore, the spring can remains fully functional in the as-found condition. No corrective measures required. The support was adjusted to the designed load setting Page 3 of 6
CASE N-532-4 CASES OF ASME BOILER AND PRESSURE VESSEL CODE FORM OAR-1 OWNER'S ACTIVITY REPORT (W038102677379, CR357433).
[Cross reference, RR 2009-165, Table 2].
Owner Commitments RHR Heat Exchanger, 2-RH-E-lA As-left thinned areas in the hub of Areas adjacent to RHR Heat the main flange (CR357130). Two Exchanger shell weld separate engineering evaluations ASME Category C-A, C1.10 were conducted on areas adjacent to the heat exchanger shell weld (Weld 17A02). Results of these engineering evaluations indicated that all excavated areas were acceptable. (CEM-0004, SIA0901311.302)
Owner Commitments RHR Heat Exchanger, 2-RH-E-1A, Asý-left thinned areas in the RHR Heat Exchanger Reinforcement.
Reinforcement Plate Weld 1-A05 reinforcement plate weld.
Plate Weld E..Engineering evaluation indicated ASME Category C-B, C2.31 that all excavated area for the subject weld was acceptable.
(CEM-0004, CR357130)
IWA-5250 System Leakage Test:
RHR/02-RH-MOV-2700 Valve 02-RH-MOV-2700 was Program identified as having a dry boric acid at the body bonnet joint. An engineering evaluation using Code Case N-566-2 showed that the structural integrity of the valve will be maintained (CR355932,
_CA151508)).
F-A, Fl. 1OA 10-RH-117/2-RH-HO09A The subject support was identified with a bent rod.. Engineering reviewed the result of the examination and determined that the bent rod had no impact on the ability of the support to perform its intended function. No corrective measures required. (CR357488).
C-F-I, C5.30, 2-SI-274/1-25 While performing a surface' examination on the subject weld, two rejectable indications were found (on the base metal of the elbow). The indications were removed using a controlled mechanical removal technique. Per ASME XI Code Interpretation, XI-1-95-42, no scope expansion was required (W038102683896, CR358151, CA152785)
[Cross reference, RR 2009-167, Table 2]
F-A, Fl.1OC 2-CH-387/2-CH-HOO1.
The support was identified with a load indicator plate being misaligned and binding on the can body.
Engineering reviewed the examination result and determined Page 4 of 6
CASE N-532-4 CASES OF ASME BOILER AND PRESSURE VESSEL CODE FORM OAR-1 OWNER'S ACTIVITY REPORT that the load indicator rotation has not exhibited signs of a misalignment that would affect the function of the support. Material loss on the load indicator does not adversely affect the support. As a result, the support is acceptable as is.
No corrective measures required.
___(CR356247)
Owner Commitment 14-RH-i 18-602/2-RH-33 Valve A through-wall leak was indentified RHR System at the valve to pipe socket weld.
02-RH--33-VALVE off Line Based on visual observation, the pin 14"-RH-I 18-602 hole leak appears to be due to workmanship and localized, and has not propagated.
An engineering calculation showed that a pinhole flaw of this nature in the toe of the weld will not adversely impact the structural integrity of the piping system (CA156797, ACE017868, CEM0049)
[Cross reference, RR 2009-137, Table 2]
Augmented examination exempted from ANII. Expanded scope was required as a result of indications.
Page 5 of 6
CASE N-532-4 CASES OF ASME BOILER AND PRESSURE VESSEL CODE 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 1**
2-RC-PP-4-RC-Repair Weld 11/17/2009 2009-148 PIPE-315-1502 (2-RC-H032) 1"*
4-RC-314-1502 Repair Weld by Grinding 12/07/2009 2009-164 2
2-RH-E-1B Repair Welds 11/16/2009 2009-045 2**
2-RH-33 Appendix IX - Mechanical 11/14/2009 2009-137 Clamp ***
2 2-RH-E-1B Replace Elbow 11/24/2009 2009-113 2
SI-274-1502 Repair Weld by Grinding 01/06/2010 2009-167 2
2-RH-E-1A Weld Repair.
01/14/2010 2009-044 2
2-FW-PP-WSPD-Repair Hanger 12/18/2009 2009-157 PIPE-117-601 I
2 1-CC-E-1D Weld Repair
.12/08/2009 2009-139 3**
2-FW-PP-6.00-Adjust SupportCold Load 11/23/2009 2009-165 WAPD-PIPE-102-Setting 601 3
2-SW-PP-3-WS-Replace Fiberglass Pipe 01/14/2010 2009-171 PIPE-2-9107
- Cross reference Table 1
- ** Correct through-wall leak Page 6 of 6