L-MT-15-064, Cycle 27 Inservice Inspection Summary Report

Cycle 27 Inservice Inspection Summary Report

ML15239A823
Person / Time
Site:	Monticello
Issue date:	08/26/2015
From:	Gardner P Northern States Power Co, Xcel Energy
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-MT-15-064
Download: ML15239A823 (8)

Text

'(l Xcel Energy* Monticello Nuclear Generating Plant 2807 W County Road 75 Monticello, MN 55362 August26,2015 L-MT-15-064 10 CFR 50.55a(g)

U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket 50-263 Renewed Facility Operating License No. DPR-22

Subject:

Cycle 27 lnservice Inspection Summary Report

Reference:

NRC Letter to NSPM, "Monticello Nuclear Generating Plant- Relief from the Requirements of the American Society of Mechanical Engineers Code for the Fifth 10-Year lnservice Inspection Program Interval (TAC Nos.

ME8068, ME8070 and ME8071 ), dated February 26, 2013, ADAMS Accession No. ML13035A158.

Pursuant to 10 CFR 50.55a, "Codes and standards," paragraph (g), "lnservice inspection requirements," Northern States Power Company - a Minnesota corporation (NSPM), d/b/a as Xcel Energy, hereby submits the enclosed lnservice Inspection (lSI)

Summary Report and Form OAR-1 "Owner's Activity Report" for the Monticello Nuclear Generating Plant (MNGP).

The Owner's Activity Report has been prepared in accordance with the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI Code Case N-532-5, "Repair I Replacement Activity Documentation Requirements and lnservice Inspection Summary Report Preparation and Submission,Section XI, Division 1." This code case is an alternative to the requirements of ASME Boiler and Pressure Vessel Code,Section XI, Articles IWA-4000 and IWA-6000, as initially authorized by the U.S. Nuclear Regulatory Commission (see Reference) for MNGP Fifth Interval lSI 10 CFR 50.55a Request RR-006 and accepted by Regulatory Guide 1.147, Revision 17 as of August 2014.

The Owner's Activity Report is included in the Enclosure and provides an overview of inservice examination results and repair/replacement activities performed during Cycle 27, including the 2015 Refueling Outage (1 R27). The activities are applicable to the Fifth 10-year lSI Interval that began on September 1, 2012.

If you have any questions or require additional information, please contact Mr. Andrew Kouba at (763) 271-7251.

Document Control Desk L-MT-15-064 Page 2 of 2 Summary of Commitments This letter makes no new commitments and no revisions to existing commitments.

Peter A. Gardner Site Vice President, Monticello Nuclear Generating Plant Northern States Power Company- Minnesota Enclosure cc: Administrator, Region Ill, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC Minnesota Department of Commerce

fl Xcel 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. 27 Refueling Outage Outage Dates: April12, 2015 to May 30, 2015 Inservice.Inspection: IntervalS (September 1, 2012- May 31, 2022)

Period 1 (September 1, 2012- August 31, 2015)

, (~l9jlfre . .*

~c Reviewed By:

-ra:...' j ~* '~/~,<

Prograni , lStl!rogr~fitQ\VI1§.r Tom Jones Approved By:

Supervisor, Materials Inspection & Repafr: . .

Approved By: ~~!

Gary Sherwood Manager, Program Engineering ANII: ~t:d~f* Kurt Suleski Hartford Steani B-oiler :: CT Report Date: August 14.2015

Monticello Nuclear Generating Plant Cycle 27 Summary Report Inservice Inspection 2015 Refueling Outage TABLE OF CONTENTS SECTIONS PAGES

1. Summary 1

2. Form OAR-1, Owner's Activity Report for Cycle 27 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 1 Required for Continued Service

Monticello Nuclear Generating Plant Cycle 27 Summary Report Inservice Inspection 2015 Refueling Outage SECTION 1.

SUMMARY

Page 1 of1 In accordance with the ASME Section XI Code and requirements of authorized alternative Code Case N-532-5 1, this report provides the following:

• Form OAR-1, 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 (lSI) activities performed during operating Cycle 27 at Monticello Nuclear Generating Plant (MNGP) Unit 1, including the 27th refueling outage. Cycle 27 began July 19, 2013, immediately following completion of the 26th refueling outage.

Examinations and tests for Cycle 27 were scheduled and conducted in accordance with the 5th Interval lSI Plan and were applicable to the 1st Period of the 5th lSI Interval.

1 NRC 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 ME8071), dated February :26, 2013, ADAMS Accession No. ML13035Al58.

Monticello Nuclear Generating Plant Cycle 27 Summary Report Inservice Inspection 2015 Refueling Outage SECTION 2. FORMOAR-1 Page 1 of 1 FORM OAR-1 OWNER'S ACTIVITY REPORT ReportNumber __~M~N~G~P_1uR~2~7~0~A~R~-~1_______________________________________________________

Plant Monticello Nuclear Generating Plant. 2807 West County Road 75. Monticello. Minnesota 55362 Unit No. ------------- Commercial service date _ ___,J'""u"'n""e_,3"'0"-._,_1"""97,_1.:___ Refueling outage no. _______,_1,_,R=-27,______

(if applicable}

1 Current inspection interva1____,5'-h--'l'-"ns,p,_,e~c,ti-"'o'-'-n-"ln_,_,t,._erv,_,_,a,_l- - - - - - - - - - - - - - - - - - - - - - - - - -

(1st, 2nd, 3rd, 4th, other)

Current inspection period _..!...1s_t!.!.ln!i!s~pe~c,t""io"'n'-'P~e"-!.r"-'io~d~--------------------------

(1st, 2nd, 3rd)

Edition and addenda of Section XI applicable to the inspection plans 2007 Edition. 2008 Addenda 1

Date and revision of inspection plans _5,__h!.!.ln,_,te,rv-"-""ai"-'-'R""e""'v.,0"--"'9/'-'1'-'/2.,0'--'1-=2'----------------------

Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans (same)

Code Cases used for inspection and evaluation:._,_,N'-'-6"-1'-"3'--1_,_,_.N_,_-_,_7""0.,_2._,N~---'7--'1""6_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___

(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 __1"-R"!'2"'7'""(2,0'-:1-"-5-"R.,_F-"'O:.~.l.,----

(rerueling outage number) conform to the requirements of Section XI.

Signed: I ~3 ... = , lSI Program Owner Date _______-=B+-p'--l-lf+-/---=15"=----------

Owner or Owne~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 HSB Global Services 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 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.

~JLxr._*

-=*=""'---"-1/------.~<----<-===.:.L---------

lnspecto~s Signature Commission ----------'N,_,B""1,_1,_,8"'6""3__.A_,_,_,N""'I'--'-"M,_N'"'0"-'0'-'4-"'02.,8"--""c""o__________

(National Board Number and Endorsements)

Date_ __,J-----/_I_'t...!,/_t._'r

Monticello Nuclear Generating Plant Cycle 27 Summary Report Inservice Inspection 2015 Refueling Outage SECTION 3. TABLE 1 Page 1 of1 TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Category and Item Number Item Description Evaluation Description 8-N-2/813.30 Comp. ID: C-3C, C-3D Successive examination was performed for linear indications in shroud shelf H-9 weld. No significant Shroud Shelf (Support Plate) changes identified. (CAP AR-01476395, 01478721, H-9 Weld to Reactor Vessel and 01478744)

Analytical evaluation performed in 2013 under CAP 2

AR-01375496 and EC-21839 , superseding initial evaluation in 2011, remains applicable.

Acceptable.

8-N-2/8 13.40 Comp. ID: C-3E, C-3F Successive examination was performed for linear indications in shroud shelf H-8 weld. No significant Shroud Shelf (Support Plate) changes identified. (CAP AR-01476394, 01478720, H-8 Weld to Core Shroud and 01478744)

Analytical evaluation performed in 2013 under CAP 2

AR-01375496 and EC-21839 , superseding initial evaluation in 2011, remains applicable.

Acceptable.

8-N-2/813.40 Comp. ID: C-3E, C-3F Newly identified linear indications in Access Hole Cover welds.

oo and 180° Access Hole Cover welds on the Shroud Analytical evaluation performed in conjunction with Shelf (Support Plate) CAP AR-01477790 and EC-25627.

Acceptable.

CAP AR-01480527 for tracking evaluation submittal to NRC.

CAP AR - acronyms for "Corrective Action Program -Action Request" EC- acronym for "Engineering Change", used to document and accept vendor analytical evaluation(s) 2 NSPM submittal letter to NRC, "Cycle 26 Inservice Inspection and In- Vessel Visual Inspection Summary Reports" dated October 11, 2013, ADAMS Accession Number ML13308B206, and Enclosures 4, 6, and 8.

Monticello Nuclear Generating Plant Cycle 27 Summary Report Inservice Inspection 2015 Refueling Outage SECTION 4. TABLE2 Page 1 of1 TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Item Description Date Repair/Replacement Code Class Description of Work Completed Plan Number 3 Division 2 Emergency Replacement of disc 4/29/2015 2015-27-022, Rev.1 Service Water due to a broken integral stem.

Valve ESW-1-2 2 Reactor Core Isolation Weld repair of areas 5/30/2015 2015-27-036 Cooling (RCIC) eroded from steam Valve A0-13-22 leakage at gasketed joint. Replacement of hinge pin assembly and retainer fasteners.