ML22003A183

Refueling Outage Unit 2 R32 Owners Activity Report for Class 1, 2, 3 and Mc Inservice Inspections

ML22003A183
Person / Time
Site:	Prairie Island
Issue date:	01/03/2022
From:	Domingos C Northern States Power Company, Minnesota, Xcel Energy
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-Pl-21-050
Download: ML22003A183 (5)

Text

(l Xcel Energy*

Janu ary 3, 2022 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-00 01 Prairie Island Nuclear Generating Plant, Unit 2 Docket Nos. 50-306 Renewed F acility Operating License No. DPR-60 1717 Wakonade Drive Welch, MN 55089 L-Pl-21-050 10 CFR 50.55a Refueling Outage Unit 2 R32 Owner's Activity Report for Class 1, 2, 3 and MC lnservice Inspections Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM"), hereby submits the lnservice Inspection Summary report for inspections conducted prior to and during the Prairie Island Nuclear Generating Plant (PINGP) refueling outage U2R32 that concluded on November 1, 2021.

The Enclosure to this letter contains Form OAR-1, "Owner's Activity Report" for lnservice Inspections for Class 1, 2, 3 and MC components.

Summary of Commitments mak mmitments and no revisions to existing commitments.

l Christopher P. Domingos Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company -Minnesota Enclosure cc: Administrator, Region Ill, USNRC Project Manager, Prairie Island, USNRC Resident Inspector, Prairie Island, USNRC ENCLOSURE

FORM OAR-1, OWNERS ACTIVITY REPORT FOR INSERVICE INSPECTION, FOR CLASS 1, 2, 3 AND MC COMPONENTS

3 pages follow FORM OAR-1 OWNER'S ACTIVITY REPORT Prairie Island Nuclear Generating Plant As required by the provisions of ASME Code Case N-532 - 5

Report Number 2R32

Plant -~P~ra=i~ri~e~l=sl~a~n~d~N~u=c~le=a=r_G~e~n~e~ra=t~in=g~P~l~a~n~t,_1~7~1~7_W~a=k=o~n~a=de~ ~ri~ve~E=a~s~t,_W~e~lc~h~, ~M~i~n~n~es~o~t=a~, ~5~5~08~9~----

Unit No. 2 ------ Commercial service date 12/21/1974 ---------- Refueling outage no. ---=2,_,_R_,_,3=2,_

Current inspection interval _5 th ISi Inspection Interval for class 1, 2, and 3. 3rd IWE Inspection Interval for class MC

Current inspection period_ 2nd ISi Inspection Period for class 1, 2, and 3. 2nd IWE Inspection period for class MC

Edition and Addenda of Section XI applicable to the inspection plans 2007 Edition - 2008 Addenda for class 1, 2, and 3. 2013 Edition for class MC __ _

Date and revision of inspection plans __ 8/23/21 Rev. 11 for class 1, 2, and 3. 2/24/20 Rev. 12 for class MC

Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans Same as Inspection Plan for class 1,2, and 3. 2007 Edition - 2008 Addenda for class MC

Code Cases used for inspection and evaluation : N-513-3, N-532-5, N-716-1, N-722-1, N-729-6,

CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this Owner's Activity 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 refueling outage number 2R32 conform to the requirements of Section XI.

Signed ~ w/l.A..,,--NOE Level Ill Q.rorOwner'sDesignee, 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 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 property damage or a loss of any kind arising from or connected with this inspection.

TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Category and Item Description Evaluation Description Item Number B-E, B4.30 Reactor Vessel Closure Head 21 RX VESSEL, Non-relevant indications of debris, rust stains and streaks, surface

, corrosion. Accepted as non-relevant QIM 501000057111 and EC 608000000784 C-H,C7.10 SP 2168.3 RHR Pit Pressure Test 2RH-1-2, 1 tsp dry, white BA at body to bonnet. Accepted by evaluation QIM 501000056832.

C-H, C7.10 SP 2168.3 RHR Pit Pressure Test 2RH-1-4, 1 tsp dry, white BA at body to bonnet. Accepted by evaluation QIM 501000056832.

C-H, C7.10 SP 2168.3 RHR Pit Pressure Test 2RH-2-2, 2 cups, white/ brown BA, body to bonnet. Accepted by removal and examination of one stud QIM 501000056832.

C-H, C7.10 SP 2168.3 RHR Pit Pressure Test 2RH-3-4, 1 tsp dry, white/ brown BA, body to bonnet Accepted by evaluation QIM 501000056832.

C-H, C7.10 SP 2168.16 Chemical and Volume 2VC-28-2, Tbsp dry, white, at body to bonnet.

Control Pressure Test Accepted by evaluation QIM 501000055889 C-H, C7.10 SP 2168.16 Chemical and Volume 2VC-28-3, Tbsp dry, white, at body to bonnet.

Control Pressure Test Accepted by evaluation QIM 501000055889 F-A, F1.20c Aux Feedwater Support 2-AFWH-7 4, Cold setting is not within the 10%

+/- range. Accepted by evaluation QIM 501000057131 and EC 608000000803.

F-A, F1.30b Cooling Water Support 2-CWH-36, Indication of corrosion. Accepted by evaluation QIM 501000056739 and EC 608000000803.

F-A, F1.30b Cooling Water Support 2-CWH-605, Hanger rods are loose and not carrying load. Accepted by evaluation QIM 501000056653 and EC 608000000803.

F-A, F1.10c Reactor Coolant Support 2-RRCH-264, Loose jam nut on the turnbuckle between the spring can and the cross member.

Accepted by evaluation QIM 501000057258 and EC 608000000803.

F-A, F1.10c Safety Injection Support 2-RSIH-345, Spring can misalignment.

Accepted by evaluation QIM 501000057009 and EC 608000000803.

F-A, F1.40 Steam Generator Snubber Support 21 S/G02, Part of the lock washer missing on the bottom left stud. Accepted by evaluation QIM 501000057130 and EC 608000000803.

F-A, F1.10b Safety Injection Support 100-2SIS-3A, 0.3 in. Gap between the base plate and concrete wall. Non-relevant indication. QIM 501000056902 and EC 608000000803.

TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Plant ID# Item Description Description of Work Completed Date R/R Plan Class Completed #

21 Steam Installed several tube plugs due to 1 234-011 Generator vibrational wear noted during ET. 11/11/2021 2-31-032 22 Steam Installed several tube plugs due to 1 234-012 Generator vibrational wear noted during ET. 11/11/2021 2-31-033 21 SG MS HDR Relief Valve to Pipe Flange All studs used with Hydranuts will be 2 RS-21-14 Fasteners replaced. 11/12/2021 2-31-036 21 SG MS HDR Relief Valve to Pipe Flange All studs used with Hydranuts will be 2 RS-21-19 Fasteners replaced. 11/12/2021 2-31-037 21 SG MS HDR Relief Valve to Pipe Flange All studs used with Hydra nuts will be 2 RS-21-20 Fasteners replaced. 11/12/2021 2-31-038