L-PI-15-025, Inservice Inspection Summary Report Unit 1, Interval 4, Period 3, Outage 2 - Refueling Outage Dates: 10/08/2014 to 11/22/2014, Fuel Cycle 28: 01/03/2013 to 11/22/2014

Inservice Inspection Summary Report Unit 1, Interval 4, Period 3, Outage 2 - Refueling Outage Dates: 10/08/2014 to 11/22/2014, Fuel Cycle 28: 01/03/2013 to 11/22/2014

ML15049A123
Person / Time
Site:	Prairie Island
Issue date:	02/18/2015
From:	Davison K Northern States Power Co, Xcel Energy
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-PI-15-025
Download: ML15049A123 (4)

Text

Xcel Energy FEB 18 2015 L-PI-15-025 10 CFR 50.55a U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Unit 1 Docket 50-282 Renewed License No. DPR-42 lnservice Inspection Summary Report Unit 1. Interval 4. Period 3, Outage 2. Refueling Outage Dates: 10/08/2014 to 11/22/2014, Fuel Cycle 28: 01/03/2013 to 11/22/2014 During the 2014 Prairie Island Nuclear Generating Plant (PINGP) Unit 1 refueling outage, an inservice inspection (lSI) examination for the third period of the fourth interval was conducted. Form OAR-1 Owner's Activity Report (Enclosure 1) is being submitted for this time period as required by the American Society of Mechanical Engineers (ASME) Code Section XI, in accordance with the provisions of Code Case N-532-4, and is intended to satisfy the inspection reporting requirements.

The form includes a listing of items with flaws or relevant conditions that required valuation for continued service (Table 1) and an abstract of repair/replacement activities required for continued service (Table 2).

Summary of Commitments This letter contains no new commitments and no revisions to existing commitments.

Kevin Davison Site Vice President Prairie Island Nuclear Generating Plant Northern States Power Company- Minnesota

Enclosures:

(1) cc: Administrator, Region Ill, USNRC Project Manager, Prairie Island, USNRC Resident Inspector, Prairie Island, USNRC

ENCLOSURE 1 FORM OAR-1 OWNER'S ACTIVITY REPORT for Unit 1, Interval 4, Period 3, Outage 2, Refueling Outage Dates: 10/08/2014 to 11/22/2014, Fuel Cycle 28: 01/03/2013 to 11/22/2014

FORM OAR-1 OWNER'S ACTIVITY REPORT Prairie Island Nuclear Generating Plant As required by the provisions of ASME Code Case N-532-4 Report Number 1R29 Plant Prairie Island Nuclear Generating Plant. 1717 Wakonade Drive East. Welch, Minnesota, 55089 Unit No. _ __,1_ __ Commercial service date _ __,1_,2'--'/1'""'6'--'/1'""'9'-'-73"'----- Refueling outage no. _ _1'-'-R_,_,2..,9=----

Current inspection interval 4th lSI Inspection Interval for class 1, 2, and 3, 2nd IWE Inspection Interval for class MC Current inspection period 3rd lSI 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 1998 Edition - 2000 Addenda for class 1, 2, and 3, 2001 Edition - 2003 Addenda for class MC _ __

Date and revision of inspection plans --~9'-'/1_,2u/1~4'--'R~e~v~. .=.20~fo'-'-r-"c~la~ss"'-'-1,L..!2'::.J.I-"a"-'n,_d-"3"--.___,_10!:<!/_..2,6/'--'1=-2'-'-R""e'-"-v'-'.9"---'-"fo'-'-r-"c~la""'ss"'--!!.M'-'=C'---

Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans Same as Inspection Plans Code Cases used: N-307-2, N-460, N-498-41 N-532-4~ N-533-1 I N-566-1 I N-652, N-729-1 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 1R29 conform to the requirements of Section XI.

Signed

~ ~~

~ . ISIEngineer Date Z / b / 'Z. 0 I S"

-Owner or Owner's Designe~ r' 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 Minnesota and employed by HSB Global Standards 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

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• .*-.***** ** Item Nl.unber **.. *. .

1*- * *

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~- * .*-*.* *Item Descriptiorf'~';* *

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I~ .Ey~IyCitionpescripti~n *. *........**

B-P, B15.70 Class 1 Pressure Tests *-* * * > Bolted connections indications accepted by SP 1392 Bolted Connections evaluation ARs: 1450417, 1450476, 1450480.

F-A, F1.10a Rod/Clamp RC system hanger 1-RPCH-137 showed indication of misalignment. Accepted by evaluation EC 24787 and AR 1451539.

F-A, F1.10b Rupture Restraint VC system hanger 114-CVCS-1 showed indication of a skewed bolt. Accepted by evaluation EC 24787 and AR 1451543.

F-A, F1.40 Support Bracket CV-31099 1-MSH-90 which is a support bracket for MV-3204712 SG MS EQLZG MV showed indication of missing weld. Accepted by evaluation EC 24787 and AR 1453788.

F-A, F1.20b Box Hanger Sl system hanger 1-SIH-36 on line 3-SI-15A showed indication of missing weld.

Accepted by evaluation EC 24787 and AR 1452941.

F-A, F1.20b Anchor RH pipe support 1-RHRH-31 on line 8-RH-9B showed indication of welded anchor bolts and missing weld. Accepted by evaluation EC 24787 and AR 1453499.

F-A, F1.30b Seismic Restraint CC system hanger 1-CCH-281 showed indication of skewed anchor bolts.

Accepted by evaluation. EC 24787 and AR 1451533.

F-A, F1.20b Strut/Clamp AF system hanger 1-AFWH-62 showed indication of lack of thread engagement.

Threads were determined to be fully engaged. See "N" note 1451528 and EC 24787 TABLE2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE 3 035-071 D1 DSL GEN Performed weld build of eroded areas of the 10/25/2014 1-28-038 Lube Oil channel ends and covers as needed to Cooler restore sealing surfaces.

035-061 D1 DSL GEN Performed weld build of eroded areas of the Jacket Water channel ends and covers as needed to Cooler restore sealin surfaces.

3 075-011 121 Control Replaced Tubes in the condenser, cut out 3/10/2014 1-28-014 Room Chiller and reinstalled piping line segment to Condenser facilitate tube replacement, and replaced ing flange fasteners.

4-ZH-61 Safeguard Replaced Tubes in the condenser, cut out Chilled Water and reinstalled piping line segment to Piping facilitate tube replacement, and replaced Segment ng fl fasteners.