ML23244A014
| ML23244A014 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 08/30/2023 |
| From: | Grady C Virginia Electric & Power Co (VEPCO) |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| 23-219 | |
| Download: ML23244A014 (1) | |
Text
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 Serial No.
SPS/MMT Docket No.
License No.
INSERVICE INSPECTION OWNER'S ACTIVITY REPORT (OAR)23-219 RO 50-281 DPR-37 In accordance with the requirements of ASME Code Case N-532-5, Virginia Electric and Power Company (Dominion Energy Virginia) hereby submits the lnservice Inspection Owner's Activity R.eport (Form OAR-1) for Surry Unit 2 refueling outage S2R31, which ended on June 8, 2023. This document contains the reporting requirements for the second refueling outage of the third period in the fifth ten-year inservice inspection interval for Surry Unit 2.
if you have any questions concerning this information, please contact Mr. Bret Rickert at (757) 365-2719.
Very truly yours, C~Q~'@2d25 Cathy Grady Director Station Safety *& Licensing Surry Power Station
Attachment:
Owner's Activity Report (Form OAR-1),
Surry Unit 2
Refueling Outage S2R31, Third Period of the Fifth ISi Interval Commitments made in this letter:
None
cc:
U.S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Avenue NE Suite 1200 Atlanta, Georgia 30303-1257 NRC Senior Resident Inspector Surry Power Station Mr. J. Klos NRC Project Manager - Surry U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G9A 11555 Rockville Pike Rockville, Maryland 20852-2738 Mr. E. Miller NRC Senior Project Manager - North Anna U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G-9A 11555 Rockville Pike Rockville, MD 20852-2738 Mr. R. Richardson Authorized Nuclear Inspector Surry Power Station Serial No.: 23-219 Docket No.: 50-281 Page 2 of 2
ATTACHMENT Serial No.: 23-219 Docket No.: 50-281
Attachment:
Page 1 of 4 OWNER'S ACTIVITY REPORT (FORM OAR-1 ),
SURRY UNIT 2 REFUELING OUTAGE S2R31, THIRD PERIOD OF THE FIFTH ISi INTERVAL VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION ENERGY VIRGINIA)
CASE CASES OF ASME BOILER AND PRESSURE VESSEL CODE FORM OAR-1 OWNER'S ACTIVITY REPORT N-532-5 Report Number 2-5-3-2 (Unit 2~'itJ1 Interval, 3rd~P~e~ri~od~,~2=n=d~R~,e=.P-O~rt~) _____________________ _
Plant Surry Power Station, 5570 Hog Island Road, Surry, VA 23883 Unit No. ______ ~2~-----
Commercial service date --~O=S/~O=l/'""1'""'9.,___,73~_ Refueling outage no. __
S~2~R~3~1 __
(if applicable)
Current inspection interval -------------------,-,-----,---=5=th-'-------c..,----.----.----------------
(1st, 2nd, 3rd, 4th, other)
Current inspection period 3rd (1st, 2nd, 3rd)
Edition and Addenda of Section XI applicable to the inspection plans ____________ 2004 Edition _____________ _
Date and revision of inspection plans Surry Unit 2, 5th Int. !SI Plan, Revision 10, November 2021 Edition and Addenda of Section XI applicable to repair/replacement activities. if different than the inspection plans NA Code Cases used for inspection and evaluation: See ISi Plan for list of Code Cases (if applicable, including cases modified by case N-532 and later revisions)
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 S2R31 conform to the~uirements of Section XL (refueling outage number)
Signed a:J n, J}!).
I ISi Progam Owner Date l5 / '\\ / 'cl 2 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and employed by The Hartford Steam Boiler Insl)!;ction and Insurance Company of Connecticuthave 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 activiti~ and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any person Vil ury or property damage or a loss of any kind arising from or connected with this inspection.
_.// Ii 1
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t--i-----------.=------- Commissions ________ v _ _,___~--------------
Inspector's Signature (National Board Number and Endorsement)
Date _'!J_.J...... \\ _c-\\_\\,-.1.KJ_r_-_t,_.*c__,_. __ _
Page 1 of 1 CASES OF ASME BOILER AND PRESSURE VESSEL CODE FORM OAR-1 OWNER'S ACTIVITY REPORT Table 1 CASE N-532-5 Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination Category and Item Description Evaluation Description Item Number B-N, B13.40 02-RC-R-1-VESSEL-LINTERNAL During the MRP-227, Reactor Vessel Internals, and 10-year ISi Examinations that occurred in the S2R31 outage the following was observed:
CR1226958 S2R31 10-year ISi Indications on Control Rod Guide Tube P-6, CR1227640- S2R31 10-year ISi and MRP Clevis Radial Support Indications, CR1228243-Thermal Shield Impact Noted After Lower Internal Lift to the LISS, and CR1227666-S2R31 10-year ISi and MRP Clevis Bolt Indications. Four Clevis Cap Screws with indications 180-L-3 (180' clevis location - left side-third bolt from top) 180-L-4, 270-R-2 and 270-R-3 were dispositioned as not being a safety concern thru a one cycle justification for operation from Framatome by Framatome Engineering Information Record 51-9354200-000, Surry Unit 1 and 2 Justification for Operation with Degraded Lower Radial Support Cap Screw. The remaining indications: two indications on weld seams on CRGT P-6, four indications on the Stellite wear surface on the Clevis Insert at 270 degrees, and contact of the thermal shield and guide stud number 37 were evaluated in Westinghouse Return to Service Letter, VIR-RV010-TM-LO-000001, Surry Unit 2 Guide Tube, Lower Radial Support Clevis, Thermal Shield, and Core Barrel Indications. Westinghouse determined listed conditions to be acceptable as-is without further action. These conditions are documented in ETE-SU-2023-0027, Surry Unit 2 MRP-227-1-A Reactor Vessel Internals Examinations Engineering Evaluation-Phase II (CR1228568-Results of Surry Unit 2 MRP-227 Phase 2 (Spring 2023)).
Page 1 of 1 CASES OF ASME BOILER AND PRESSURE VESSEL CODE FORM OAR-1 OWNER'S ACTIVITY REPORT Table 2 CASE N-532-5 Abstract of Repair/replacement Activities Required for Continued Service Code Class I 2
2 3
3 Item Description 02-CN-PP-6.00-WCMU-PIPE-174-151 Description of Work LEAK SEAL ENCLOSURE INSTALLATION Date Completed 3/8/2022 02-CN-PP-6 00-WCMU-WELD SUPPORT FOR ENCLOSURE 3/8/2022 PIPE-174-151 INSTALLATION WO# 38204291380 02-CN-PP-6.00-WCMU-Piping replacement for 02-CN-PP-6.00-1 5/4/2023 PIPE-174-151 WCMU-PIPE-174-151 02-SW-PP-24.00-WS-NOE in the surrounding areas of the PIPE-133-10 weld repair after inspecting prepped area 2 feet away from discharge flange of 2-RS-E-1A.
5/20/2023 Repair/Replacement Plan Number 2022-008 2022-005 2021-173 2023-095