L-MT-17-059, 2017 Refueling Outage 90-Day Lnservice Inspection (ISI) Summary Report

2017 Refueling Outage 90-Day Lnservice Inspection (ISI) Summary Report

ML17223A091
Person / Time
Site:	Monticello
Issue date:	08/09/2017
From:	Gardner P Northern States Power Company, Minnesota, Xcel Energy
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-MT-17-059
Download: ML17223A091 (9)

Text

2807 West County Road 75 Monticello, MN 55362 (l Xcel Energy*

RESPONSIBLE BY NATURE 800.895.4999 xcelenergy. com August 9, 2017 L-MT-17-059 10 CFR 50.55a(g)

ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket No. 50-263 Renewed Facility Operating License No. DPR-22 2017 Refueling Outage 90-Day lnservice Inspection (lSI) Summary Report Pursuant to 10 CFR 50.55a(g), Northern States Power Company - a Minnesota corporation (NSPM), doing business 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 authorized by the U.S. Nuclear Regulatory Commission (NRC) through Regulatory Guide 1.147, "lnservice Inspection Code Case Acceptability, ASME Section XI, Division 1,"Revision 17, 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 28, including the 2017 Refueling Outage (1 R28). The activities are applicable to the Fifth 10-year lSI Interval that began on September 1, 2012.

Included with the OAR-1 form are Tables 1 and 2 entitled "Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service" and "Abstract of Repair I Replacement Activities Required for Continued Service", respectively, in accordance with ASME Code Case N-532-5 for Cycle 28.

L-MT-17-059 Document Control Desk Page 2 of 2 Summary of Commitments There are no new commitments and no revisions to existing commitments in this letter.

Peter A. Gar Site Vice President, Monticello Nuclear Generating Plant Northern States Power Company- Minnesota Enclosure cc: NRC Regional Administrator, Region Ill NRC Project Manager NRC Resident Inspector

ENCLOSURE Monticello Nuclear Generating Plant Owner's Activity Report Form OAR-1 6 pages follow

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. 28 Refueling Outage Outage Dates: April14, 2017 to May 14, 2017 lrlservice Inspection: Interval 5 (September 1, 2012- May 31, 2022)

Period2 (September 1, 2015 -August 31, 2019)

Prepared By:

Richard Deopere Program Engineer, lSI Program Owner .

Reviewed By: . ~~..J~ Tom Jones Program Engineer, Site NDE Level III.*

Approved By: ~d~~:

~Randy Garding  : ..**.

F~' lru;P'cti"' & Rq>*i*

Approved By:

Paul Young Manager, Program Engineering ANII: ~-f}it-L~A'* Kurt Suleski TheHartford Stean1Boiledrispection and Insurance Company *.

Report Date: August 7, 2017

Monticello Nuclear Generating Plant Cycle 28 Summary Report Inservice Inspection 2017 Refueling Outage TABLE OF CONTENTS SECTIONS PAGES

1. Summary 1

2. Form OAR-1, Owner's Activity Report for Cycle 28 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 28 Summary Report Inservice Inspection 2017 Refueling Outage SECTION 1.

SUMMARY

Page 1 of 1 In accordance with the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI and approved alternative requirements of 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 28 at Monticello Nuclear Generating Plant (MNGP) Unit 1, including the 28th refueling outage. Cycle 28 began May 30, 2015, immediately following completion of the 27th refueling outage.

Examinations and tests for Cycle 28 were scheduled and conducted in accordance.

with the 5th Interval lSI Plan and were applicable to the 2nd Period of the 5th lSI Interval.

1 NRC Regulatory Guide 1.147, Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1, Revision 17, August 2014.

Monticello Nuclear Generating Plant Cycle 28 Summary Report Inservice Inspection 2017 Refueling Outage SECTION 2. FORMOAR-1 Page 1 of1 FORM OAR-1 OWNER'S ACTIVITY REPORT ReportNumber __~M~N~G~P~1~R~2~8~0~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.>.....!.;19""'7'-1'---- Refueling outage no._ ____,1'""R""2""8'----

Qf applicable) 1 Current inspection interval __,5"-h_,l.!.!n£Jsp~e~c"'ti"'-o!.!.n_,ln~t£erv!..l!.Ea,_l- - - - - - - - - - - - - - - - - - - - - - - - - -

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

Current inspection period ----'2,_"_d.!.!ln_,s,p""e""ct,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 Date and revision of inspection plans _5,_1_h:..:.ln~te""rv-'-a"'I"--'-'R""e,v.'-'-1..._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;::,-5!.,!1_,3:::,-3~N~-6~1'-"3"'--1.!..L...!.N:!:-.!.,;70~2=.....cN:!:-'-71~6~-------------

<it 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 __17R"'"2""8,.._f2,.,0'--:1-"-:7_,_R,_F-'CO':'-cl,--

<retueling outage number)

Signed: , lSI Program Owner Date _ ___,.,_~=.::;;pw'J\--:t'"',__-'7-1}1--2._0_1;....7'----------

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 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.

- ~-k: .-= ':.: .~: : =. .J;(l:.="'- 1-':LLJ.""""""""=,...------ Commission -------'N'"'-B"'-1'-1""'8""6""3'-'A,.,_,N""'I'-""M"-'N.....,0"""0""4""02:::8<..:-c,_o"'-----------

Inspector's Signature (National Board Number and Endorsements)

Monticello Nuclear Generating Plant Cycle 28 Summary Report Inservice Inspection 2017 Refueling Outage SECTION 3. TABLE1 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 D-B, D1.202 Pressure Retaining Component Through-wall leakage was evaluated for continued online operation using Code Case N-513-3. Reference CAP AR 01509469 and V-AC-8A cooling coil for High Pressure EC-26677.

Coolant Injection (HPCI) Room, Emergency Service Water System, Coil subsequently replaced during Cycle 28 online maintenance Division 1 window.

D-B, 01.203 Pressure Retaining Component ID pit due to MIC with remaining wall thickness less than minimum required wall thickness (not through-wall) was evaluated for ESW1-3"-HBD, supply piping for continued online operation using N-513-3. Reference CAP AR Emergency Filtration Train - 01553131 and EC-28387.

Emergency Service Water system, Division 1 Piping subsequently replaced in Refueling Outage 28 (RF0-28).

F-A, F1.20 Class 2 Piping Support Slightly bent rod, identified during a pre-service inspection for an unrelated RF0-28 repair/replacement activity, was determined not Support PSH-116, variable spring to be a service induced condition, and was evaluated by support for High Pressure Coolant engineering for continued service. Reference CAP AR 01558248.

Injection (HPCI) steam supply piping.

CAP AR- acronyms for "Corrective Action Program -Action Request" EC - acronym for "Engineering Change", used to document and accept vendor evaluation(s) 2 Flaw (pressure boundary leakage) was identified during normal plant operation, not during performance of a system leakage test (IWD-5222) and the noted Examination Category and Item Number.

3 Flaw (below minimum wall thickness pit on inside diameter (I D) of the piping due to Microbiologically Influenced Corrosion(MIC)) was identified by non-destructive examinations performed for the Service Water- MIC Program, not during performance of a system leakage test (IWD-5222) and the noted Examination Category and Item Number.

Monticello Nuclear Generating Plant Cycle 28 Summary Report Inservice Inspection 2017 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 Emergency Service Repair (cut/cap) of 12/30/2015 2015-28-012, Rev.1 Water, Division 1 cooling coil tubing due to through-wall V-AC-8A, HPCI Room leakage.

cooling coil 3 Emergency Service Replacement of 4/27/2016 2016-28-013 Water, Division 1 cooling coil due to V-AC-8A, HPCI Room through-wall leakage. Code cooling coil Case N-513-3 was implemented prior to replacement.

3 Emergency Service Replacement of 8/23/2016 2016-28-025 Water, Division 1 cooling coil due to V-AC-5, Residual Heat through-wall leakage.

Removal A (RHR-A) room cooling coil 3 Emergency Service Replacement of 9/24/2016 2016-28-027 Water, Division 2 cooling coil due to through-wall V-AC-4, Residual Heat leakage.

Removal B (RHR-B) room cooling coil 3 Emergency Filtration Replacement of 4/21/2017 2017-28-040 Train - Emergency piping due MIC Service Water, pitting with Division 1 remaining wall thickness less than ESW1-3"-HBD, supply required minimum piping wall. Code Case N-513-3 was implemented prior to replacement.

2 Residual Heat Removal Two unacceptable, 4/22/2017 2017-28-043 A (RHR-A), Division 1 axial linear surface RHR Heat Exchanger indications on the E-200A, shell-side inlet shell-side inlet nozzle-to-reinforcement nozzle were ring weld removed by mechanical means (blending).