ML13308B217

Enclosure 1 - Cycle No. 26 and 1R26 2013 Refueling Outage Inservice Inspection: Interval 4, Period 3 and Interval 5, Period 1, Owner'S Activity Report (OAR-1)

ML13308B217
Person / Time
Site:	Monticello
Issue date:	10/08/2013
From:	Deopere R Northern States Power Co, Xcel Energy
To:	Office of Nuclear Reactor Regulation
Shared Package
ML13308B206	List: L-MT-13-102, Cycle 26 Inservice Inspection and In-Vessel Visual Inspection Summary Reports ML13308B217 ML13308B218 ML13308B219 ML13308B220 ML13308B221
References
L-MT-13-102 OAR-1
Download: ML13308B217 (7)

Text

ENCLOSURE I INSERVICE INSPECTION

SUMMARY

REPORT MONTICELLO NUCLEAR GENERATING PLANT CYCLE NO. 26 AND 1R26 2013 REFUELING OUTAGE Inservice Inspection: Interval 4, Period 3 and Interval 5, Period 1 Owner's Activity Report (OAR-I)

(6 pages follow)

Xce Energy-Xcel Energy, Inc.

Northern States Power Co. - Minnesota 414 Nicollet Mall Minneapolis, MN 55401 INSERVICE INSPECTION

SUMMARY

REPORT Monticello Nuclear Generating Plant Unit 1 2807 West County Road 75 Monticello, MN 55362 Commercial Service Date: June 30, 1971 Cycle No. 26 Refueling Outage Outage Dates: March 2, 2013 to July 19, 2013 Period 3 (ending August 31, 2012)

Period 1 (beginning September 1, 2012)

Report Date: October 8, 2013

Monticello Nuclear Generating Plant Cycle 26 Summary Report Inservice Inspection 2013 Refueling Outage TABLE OF CONTENTS SECTIONS PAGES

1. Summary 1

2. Form OAR-i, Owner's Activity Report for Cycle 26 1

3. Table 1, Items with Flaws or Relevant Conditions 1 That Required Evaluation for Continued Service

4. Table 2, Abstract of Repair/Replacement Activities Required for Continued Service

Monticello Nuclear Generating Plant Cycle 26 Summary Report Inservice Inspection 2013 Refueling Outage SECTION 1.

SUMMARY

Page 1 of 1 In accordance with the ASME Section XI Code and requirements of authorized alternative Code Case N-532-51, this report provides the following:

" Form OAR- , Owner's Activity Report

" Table 1, Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service

" Table 2, Abstract of Repair/Replacement Activities Required for Continued Service This information is applicable to Inservice Inspection (ISI) activities performed during operating Cycle 26 at Monticello Nuclear Generating Plant (MNGP) Unit 1, including the 26th refueling outage. Cycle 26 began May 25, 2011, immediately following completion of the 25th refueling outage.

Examinations and tests for Cycle 26 were scheduled and conducted in accordance with the 4th Interval ISI Plan through August 31, 2012 and were applicable to the 3rd Period of the 4th ISI Interval. Beginning on September 1, 2012 Cycle 26 examinations and tests were scheduled and conducted in accordance with the 5th Interval ISI Plan and were applicable to the 1st Period of the 5th ISI Interval.

1NRC Letter to NSPM, "Monticello Nuclear Generating Plan - Relief from the Requirements of the American Society of Mechanical Engineers Code for the Fifth 10-Year Inservice Inspection Program Interval (TAC Nos. ME8068, ME8070 and ME807 1), dated February 26, 2013, ADAMS Accession No. ML13035A158.

Monticello Nuclear Generating Plant Cycle 26 Summary Report Inservice Inspection 2013 Refueling Outage SECTION 2. FORM OAR-I Page 1 of 1 FORM OAR-I OWNER'S ACTIVITY REPORT Report Number MNGP 1 R26 OAR-1 Plant Monticello Nuclear Generating Plant, 2807 West County Road 75, Monticello, Minnesota 55362 Unit No. Commercial service date June 30, 1971 Refueling outage no. 1R26 (if applicable)

Current inspection interval 4 th Inspection Interval ending 8/31/2012m 5 h Inspection Interval beginning 9/1/2012 (1st, 2nd. 3rd. 4th, other)

Current inspection period 3 rd Inspection Period. 4th Interval: 1s Inspection Period, 5th Interval (1st, 2nd, 3rd)

Edition and addenda of Section XI applicable to the inspection plans 1995 Ed. 1996 Add (4th Int): 2007 Ed. 2008 Add (5th Int.)

Date and revision of inspection plans 4 th Interval, Rev.4, 6/5/2010: 5th Interval, Rev.0, 9/1/2012 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans 4 th Interval, 2001 Edition, No Addenda: 5th Interval, same as inspection plan Code Cases used for inspection and evaluation: N-491-2 (4th Int). N-498-4 (4th Int), N-513-3. N-546 (4t" Int), N-613-1, (ifapplicable, including cases modified by Case N-532 and later revisions)

N-686 (4th Int), N-702 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 VI,2P , 2.c*'1*F0 (refueling outage number) conform to the requirements of Section Xl.

Signed:

• ISI Program Owner Date 0/4/2-01-a 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 HSBCT of Hartford, 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 the 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 the report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

2

~ - 4(&,* ( Commission NB11863 ANI, MN 004028-CO Inspector's Signature (National Board Number and Endorsements)

Date LtC-/W//?

Monticello Nuclear Generating Plant Cycle 26 Summary Report Inservice Inspection 2013 Refueling Outage SECTION 3. TABLE 1 Page 1 of 1 TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Category and Item Number Item Description Evaluation Description Comp. ID: C-3C, C-31D Linear indications in shroud shelf H-9 weld B-N-2/B 13.30 Shroud Shelf Analytical evaluation performed in conjunction with B-N-2/B13.40 CAP AR# 01375496, and EC-21839 H-9 Weld Determined to be acceptable.

Comp. ID: C-3E, C-31F Linear indications in shroud shelf H-8 weld.

B-N-2/B 13.40 Shroud Shelf Analytical evaluation performed in conjunction with CAP AR# 01375496, and EC-21839 H-8 Weld Determined to be acceptable.

Linear indications in shroud support leg H-10 weld.

Comp. ID: C-7A through C-7Q Analytical evaluation performed in conjunction with B-N-2/1313.40 Shroud Support Legs CAP AR# 01177677, 01282530, 01283709, 01283715, and 01377599 and EC-21854.

H-10 Weld Determined to be acceptable.

Loose upper retaining nut.

ISO#-.ISI-13142-40-B Engineering evaluation performed in conjunction with F-A/F1.20b Comp. ID: H- 8, TWH-48 CAP AR# 01373467.

Strut I Clamp Determined to be acceptable.

Subsequently tightened under Work Order 475275 CAP AR# - acronyms for "Corrective Action Program - Action Request Number" EC - acronym for "Engineering Change", used to document and accept vendor analytical evaluation(s)

Monticello Nuclear Generating Plant Cycle 26 Summary Report Inservice Inspection 2013 Refueling Outage SECTION 4. TABLE2 Page 1 of 1 TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Item Description Date RepairlReplacement Code Class Description of Work Completed Plan Number 3 Division 1 Residual Heat Replaced due to 9/2/2011 2011-26-002 Removal (RHR) Room through-wall tubing Cooling Coil V-AC-5 leakage. Interim acceptance and continued operation per Code Case N-513-3 until replacement.

3 Division 2 RHR Room Replaced due to 1/6/2012 2011-26-008 Cooling Coil V-AC-4 through-wall tubing leakage. Interim acceptance and continued operation per Code Case N-513-3 until replacement.

2 Fuel Pool Cooling Support Legacy installation 7/18/2012 2011-26-012 FPWH-1 11 damage corrected by replacement of support items 3 RHR Service Water Stuffing Box replaced 5/3/2012 2012-26-028 (RHRSW) Pump P-109A due to through-wall Stuffing Box corrosion defect 3 Spare RHRSW Pump Weld repair of eroded 9/27/2012 2012-26-039 P-109 areas and associated linear indications 3 High Pressure Coolant Replaced due to 12/1/2012 2012-26-041 Injection (HPCI) Room through-wall tubing Cooling Coil V-AC-8 leakage. Interim acceptance and continued operation per Code Case N-513-3 until replacement.

3. RHRSW Valve CV-1728 Replaced valve body 4/23/2013 2013-26-053 and disc due to internal cavitation erosion

3. Division 1 Emergency Replacement of 4/20/2013 2013-26-065 Service Water Piping piping degraded by Microbiologically Induced Corrosion (MIC)

Main Steam Isolation Valve Replacement of 7/19/2013 2013-26-074 AO-2-80C bonnet due to steam cutting damage caused by packing leakage.