ML23073A182

Inservice Inspection Owner'S Activity Report (OAR)

ML23073A182
Person / Time
Site:	Surry
Issue date:	03/14/2023
From:	Grady C Virginia Electric & Power Co (VEPCO)
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
23-065
Download: ML23073A182 (1)

Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 March 14, 2023 United States Nuclear Regulatory Commission Serial No.23-065 Attention: Document Control Desk SPS-LIC/MSG RO Washington, DC 20555-0001 Docket No. 50-280 License No. DPR-32 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION OWNER'S ACTIVITY REPORT (OAR)

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 Report (Form OAR-1) for Surry Unit 1 refueling outage S1 R31, which ended on December 17, 2022. 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 1.

If you have any questions concerning this information, please contact Mr. Bret Rickert at (757) 365-2719.

Cathy Grady Director Station Safety & Licensing Surry Power Station

Attachment:

Owner's Activity Report (Form OAR-1), Surry Unit 1 Refueling Outage S1 R31, Third Period of the Fifth ISi Interval Commitments made in this letter: None

Serial No.: 23-065 Docket No.: 50-280 Page 2 of 2 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.: 23-065 Docket No.: 50-280

Attachment:

Page 1 of 4 ATTACHMENT OWNER'S ACTIVITY REPORT (FORM OAR-1 ),

SURRY UNIT 1 REFUELING OUTAGE 51 R31, THIRD PERIOD OF THE FIFTH ISi INTERVAL VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION ENERGY VIRGINIA)

Serial No.: 23-065 Docket No.: 50-280

Attachment:

Page 2 of 4 CASE CASES OF ASME BOILER AND PRESSURE VESSEL CODE N-532-5 FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number 1-5-3-2 (Unit 1. 5th Interval. 3rd Period, 2nd Report)

Plant Surry Power Station, 5570 Hog Island Road. Surry, VA 23883 Unit No. _ _ _ _ _~-=1~~---- Commercial service date _ ___,,,1=2/'-"2=2,__,/1'""9_,_7=-2_ _ Refueling outage no. _ ___.,,S=1~R=3"'- (lf applicable)

Current inspection interval - - - - - - - - - - - - - - - ~_ ______,S=t'--'-h--~~--------------

(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 1, 5th Interval ISI Plan, Revision 7 November, 2021 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans N/A Code cases used for inspection and evaluation: _ __.,,S=e=e..,,S=u~rry__,___,,U~n=it'--'l,,_,..,,5=th-'-=In=t.,_,I=S=I_,_P=la,.,.,n,_.'-"Re,,_v~.7~S=ec=t=io~n~6~f=o~r=co=m-'--'=pl=et=e'-'l=is.,_t=of'--'c=o=d=e-"c=as=e=s'----

(lf 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 SlR31 confotm to the requirefflts of Section XI. (refueling outage number)

Signed ~J7. JcJ-. I ISi Progam Owner Owner or Owner's Deslgnee, litle Date ~ / 'Ji.

-~~~~~~--.....----------------

Q/ ':AJ 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 Inspection and Insurance Company of Connecticut 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 ~ damage or a loss of any kind arising from or connected with this inspection.

• 1//4 ° - /' Commissions _ _(_,$ _°i_l_~-----"c'--+,_J:-__,,~N-1_ ' \ ~ - - - - - - - - -

(National Board Number and Endorsement)

Serial No.: 23-065 Docket No.: 50-280

Attachment:

Page 3 of 4 Page 1 of 1 CASE CASES OF ASME BOILER AND PRESSURE VESSEL CODE N-532-5 FORM OAR-1 OWNER'S ACTIVITY REPORT Table 1 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 01-RC-R-1-VESSEL-LINTERNAL During the MRP-227, Reactor Vessel Internals, and 10-year ISi Examinations that occurred in the S1R31 outage. The following was observed with regards to the thermal shield: thermal shield flexure 30 degrees- Crack like indication in the vicinity of the inner flexure weld CR 1212741; thermal shield flexure 210 degrees- Crack-like indication in the vicinity of the outer flexure weld CR 1212744; thermal shield flexure 270 degrees-Crack-like indication in the vicinity of the outer flexure weld CR 1212743; thermal shield support block cap screw lock bar weld 195 degrees-Indication on lock bar weld on Cap Screw 195L -

CR 1212740; and thermal shield support block 75 degrees- Anomaly noted on left side of thermal shield support block- CR 1212700. PWROG-21021-P, Revision 1, Thermal Shield Support Block Cap Screw and Flexure Degradation Safety Assessment, October 2022, contains a qualitative one-cycle safety assessment for the degradation of thermal shield support block cap screws and thermal shield flexures. The report concludes that there is no safety concern with operation for one cycle with any number of degraded TSSB cap screws and flexures. Westinghouse has evaluated the Surry specific findings in Westinghouse Letter VPA-RV010-TM-CA-000001, Surry Unit 1 Fall 2022 Outage - Disposition of As Found Conditions for the Thermal Shield Supports and Justification for Return to Service and concluded that it is acceptable to operate for one cycle. The anomaly discovered on the 75 degrees thermal shield support block is not evaluated in PWROG-21021-P. Westinghouse also evaluated this condition and concluded that the anomaly does not present a safety concern. These conditions are documented in ETE-SU-2022-0049, Surry Unit 1 MRP-227-1-A Reactor Vessel Internals Examinations Engineering Evaluation- Phase II (CR1213488 -

Results of Surry Unit 1 MRP-227 Phase 2 (Fall 2022)).

Serial No.: 23-065 Docket No.: 50-280

Attachment:

Page 4 of 4 Page 1 of 1 CASE CASES OF ASME BOILER AND PRESSURE VESSEL CODE N-532-5 FORM OAR-1 OWNER'S ACTIVITY REPORT Table 2 Abstract of Repair/replacement Activities Required for Continued Service Code Class Item Description Date Repair/Replacement Description of Work Completed Plan Number 3 01-CC-PP-6.00-CC-PIPE- Modify Support (1-CC-H001) on 01- 11/24/2022 2022-119 76-151 CC-PP-6.00-CC-PIPE-76-151 3 01-SW-PP-24.00-WS-PIPE Perform weld repairs on 01-SW-PP- 11/26/2022 2022-122 32-10 24.00-WS-PIPE-32-10.

3 01-SW-PP-24.00-WS-PI PE Perform weld repairs on 01-SW-PP- 12/5/2022 2022-128 36-10 24.00-WS-PIPE-36-10