L-MT-11-046, Cycle 25 Inservice Inspection Summary Report

Cycle 25 Inservice Inspection Summary Report

ML112351222
Person / Time
Site:	Monticello
Issue date:	08/23/2011
From:	O'Connor T Northern States Power Co, Xcel Energy
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
L-MT-11-046
Download: ML112351222 (24)

Text

Monticello Nuclear Generating Plant 2807 W County Road 75 Monticello, MN 55362 August 23,2011 L-MT-11-046 10 CFR 50.55a 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 Cycle 25 lnservice lnspection Summaw Report Pursuant to 10 CFR 50.55a, the Northern States Power Company - a Minnesota corporation (NSPM), dlbla as Xcel Energy, is providing the enclosed lnservice lnspection (ISI) Summary Report (Owner's Activity Report, Form OAR-1) for the Monticello Nuclear Generating Plant (MNGP). Also enclosed within this submittal is a summary of the comprehensive in-vessel visual inspections (IWI) of the reactor vessel internal components performed in accordance with the Boiling Water Reactor Vessel lnternals Projects (BWRVIP), BWRVIP-94, "BWR Vessel and lnternals Project Program Implementation Guide".

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-532-4, "Repair IReplacement Activity Documentation Requirements and lnservice Summary Report Preparation and Submission,Section XI, Division 1". This code case is applied as an alternative to the requirements of ASME Boiler and Pressure Vessel Code,Section XI, Article IWA-4000 and IWA-6000, as approved by Regulatory Guide 1.147, "lnservice lnspection Code Case Acceptability, ASME Section XI, Division 1, Revision 16".

This Owner's Activity Report is contained in Enclosure 1. It provides an overview of the inservice examination results performed during Cycle 25 (including the 2011 Refueling Outage) for the fourth 10-year IS1 interval. The report also includes a summary of repair and replacement activities during the same time period. The applicable provisions of the ASME Code Case require that this report be submitted within 90 days from the end of the outage.

Additionally, the IS1 Summary Report also provides amended information to the previously submitted Cycle 24 IS1 Summary Report, including a supplemental NIS-1 Form and a supplemental NIS-2 Form.

Document Control Desk L-MT-11-046 Page 2 of 2 The summary of I W I inspections conducted in accordance with BWRVIP-94 is provided in Enclosure 2.

Should you have questions regarding this letter, please contact Mr. Richard Loeffler at (763) 295-1247.

Summaty of Commitments commitments and does not revise any existing resident, Monticello Nuclear Generating Plant tates Power Company - Minnesota

Enclosures:

(2) cc: Administrator, Region Ill, USNRC Resident Inspector, Monticello, USNRC Project Manager, Monticello, USNRC BWRVIP Project Manager, USNRC

ENCLOSURE 1 MONTICELLO NUCLEAR GENERATING PLANT INSERVICE INSPECTION

SUMMARY

REPORT (11 pages follow)

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. 25 Refueling Outage Report Date: August 17,2011

Monticello Nuclear Generating Plant Cycle 25 Summary Report Insewice Inspection 2011 Refueling Outage TABLE OF CONTENTS SECTIONS PAGES

1. Summary 1

2. Form OAR-1, Owner's Activity Report for Cycle 25 1

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

4. Table 2, Abstract of RepairIReplacement Activities Required for Continued Service

5. Form NIS-1 for Cycle 24, Supplemental Information

6. NIS-2 Summary and Form for Cycle 24 Supplemental Information

Monticello Nuclear Generating Plant Cycle 25 Summary Report Inservice Inspection 2011 Refueling Outage SECTION 1.

SUMMARY

Page 1 of 1 In accordance with the ASME Section XI Code and alternative requirements of Code Case N-532-4, 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 0 Table 2, Abstract of RepairIReplacement Activities Required for Continued Service This information is applicable to Inservice Inspection (ISI) activities performed during operating Cycle 25 at Monticello Nuclear Generating Plant (MNGP)

Unit 1, including the 25th refbeling outage. Cycle 25 began May 10,2009, immediately following completion of the 24th refueling outage.

All examinations and tests for Cycle 25 were scheduled and conducted in accordance with the 4th Interval IS1 Plan. Exams and tests were credited to the 2nd and 3rd Period of the 4th IS1 Interval, as applicable.

This report also provides supplemental RepairIReplacement (RIR) infomation for the Cycle 24 IS1 Summary Report submitted in August 2009. The 24th reheling outage began March 14,2009 and concluded on May 10,2009.

Monticello Nuclear Generating Plant Cycle 25 Summary Report Inservice Inspection 2011 Refueling Outage SECTION 2. FORM OAR-1 Page 1 of 1 FORM OAR-? OWNER'S ACTIVITY REPORT Report Number MNGP 1R25 OAR-1 Plant Monticello Nuclear Generating Plant, 2807 West Countv Road 75, Monticello, Minnesota 55362 Unit No. I Commercial service date June 30. 1971 Refueling outage no. 1R25 (if applicable)

Current inspection interval 4th Inspection Interval (lst, 2nd, 3rd, 4th, other)

Current inspection period 3rd Inspection Period (Ist, 2nd, 3rd)

Edition and addenda of Section XI applicable to the inspection plans 1995 Edition with 1996 Addenda Date and revision of inspection plans Revision 4, dated 61512010 Edition and Addenda of Section XI applicable to repairlreplacement activities, if different than the inspection plans 2001 Edition, No Addenda Code Cases used: N-307-3, N-323-1, N-460, N-491-2, N-498-4, N-513-3, N-532-4, N-546, N-552, N-598, N-623, N-661, N-686, N-702, N-705 (if applicable)

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 repairlreplacement activities and evaluations supporting the completion of 1R 25 (refueling outage number) conform to the requirements of Section XI.

Signed: Date e/r7/zor I I 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 the State or Province of Minnesota and employed by Hartford Steam Boiler ins^. & ins^. Com~anv 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 the activities represented by this report in accordance with the requirements of Section XI.

By signing this certificate neither the lnspector nor his employer makes any warranty, expressed or implied, concerning the repair1 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.

Commissions NBI 1863 A,N,I, MN 004028-CO Inspector's Signature National Board, State, Province, and Endorsements Date AY 6-Q 3 . r ( 7 , LU I

Monticello Nuclear Generating Plant Cycle 25 Summary Report Inservice Inspection 2011 Refueling Outage SECTION 3. 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 ISO#: ISI-13142-62 Engineering evaluation performed in conjunction with CAP AR# 1281071. Bent items, lack of thread Comp. ID: H- 2, FPWH-111 engagement I Restraint Hanger 1 Determined to be acceptable "as-is".

]SO#: ISI-13142-42-A Engineering evaluation performed in conjunction with CAP AR# 1262741, Bent rod and improper setting F-AIFI . 2 0 ~ Comp. ID: H- 6, PSH-104 on hanger PSH-104.

Spring IClamp Determined to be acceptable "as-is".

lSO#: ISI-97005-C Engineering evaluation performed in conjunction with CAP AR# 1274943, Arc strike on restraint.

F-AIFI .40a Comp. ID: H-10, RCAKR-22A Restraint , Determined to be acceptable "as-is".

Engineering evaluation performed in conjunction with Comp. ID: C-7x CAP AR# s 1177677, 1282530, 1283709 and 1283715. Linear indications in shroud support leg Shroud Support Legs welds.

H-10 Weld Determined to be acceptable "as-is".

Comp. ID: C-3C, C-3D Engineering evaluation performed in conjunction with CAP AR# 1280490, H-8lH9 Weld Inspection, linear Shroud Shelf indications.

H-9 Weld Determined to be acceptable "as-is".

Comp. ID: C-3E, C-3F Engineering evaluation performed in conjunction with CAP AR# 1280490, H-8lH9 Weld Inspection, linear Shroud Shelf indications.

I I H-8 Weld I Determined to be acceptable "as-is". I Engineering evaluation performed in conjunction with Comp. ID: T-200 CAP AR# 1223696, Leak discovered on SLC Tank T-200 Standby Liquid Control Tank Determined to be acceptable for operation until the next scheduled refueling outage per Code Case N-705 and Relief Request 18. (repaired in 1R25)

CAP AR# - acronyms for "Corrective Action Program - Action Request Number"

Monticello Nuclear Generating Plant Cycle 25 Summary Report Inservice Inspection 2011 Refueling Outage SECTION 4. Page 1 of 1 TABLE 2 ABSTRACT OF REPAIWREPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Item Description Date RepairlReplacement Code Class Description of Work Completed Plan Number 3 Division1 RHR Service Replaced piping and 41112011 2010-25-016 Water Piping fittings in the Intake Structure and Tunnel due to internal corrosion. Previous use of Code Case N-661.

3 Division 2 Emergency Replaced piping and 3/27/2011 2010-25-017 Service Water Piping fittings in the Intake Structure due to internal corrosion.

Previously repaired for through-wall leakage at weld.

(Reference R/R Plan 2010-25-024) 3 Division 2 Emergency Repaired through-wall 7/29/2010 2010-25-024 Service Water Piping weld defect.

2 Standby Liquid Control Replaced bottom due 5/8/2011 2011-25-042 Storage Tank T-200 to through-thickness cracking. Previous use of Code Case N-705 and Relief Request 18.

3 Division 2 RHR Service Linear surface 3/21/2011 201 1-25-043 Water Piping indication identified near replacement weld, mechanically removed 2lMC Primary Containment Rounded surface 4/7/20 11 2011-25-050, Rev.1 Penetration X-I OIA indications near replacement weld, mechanically removed.

1 Main Steam D Piping Linear surface 4/22/2011 2011-25-057 indication identified at strain gauge removal area, buffed out.

Monticello Nuclear Generating Plant Cycle 25 Summary Report Inservice Inspection 2011 Refueling Outage SECTION 5. FORM NIS-1 INFORMATION - SUPPLEMENT Page 1of 2 Form NIS-1 Owner's Data Report for Inservice Inspections

(**Supplement to Submittal for Cycle 24,2009 RFO**)

As required by the Provisions of the ASME Code Rules

1. Owner: Xcel Energy. Inc. I Northern States Power Company - Minnesota Address: 414 Nicollet Mall. Mpls. MN 55401

2. Plant: Monticello Nuclear Generating Plant Address: Monticello, MN 55362

3. Plant Unit: 1 4. Owner (Certificate of Authorization): NIA

5. Commercial Service Date: 6130171 6. National Board No. for Unit: NIA

7. Components Inspected:

Manufacturer Component or Manufacturer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No.

8. Examination Dates: 04/28/2007 to 0511012009 .

9. Inspection Interval: 05/01/2003 to 0513112012 .

10. Applicable Edition of Section XI: 1995 Addenda: 1996 .

11. Abstract of Examinations.

0 See Report Sections 5 and 6 for supplemental Cycle 24 Form NIS-2

12. Abstract of Conditions Noted.

See Report Sections 5 and 6 for supplemental Cycle 24 Form NIS-2

13. Abstract of Corrective Measures Recommended and Taken.

0 See Report Sections 5 and 6 for supplemental Cycle 24 Form NIS-2

Monticello Nuclear Generating Plant Cycle 25 Summary Report I Inservice Inspection 2011 Refueling Outage SECTION 5. FORM NIS-1 INFORMATION - SUPPLEMENT Page 2 of 2

(**Supplement to Submittal for Cycle 24,2009 RFOk*)

We certify that the statements made in this report are correct and the examinations and corrective measures taken conform to the rules of the ASME Code,Section XI.

Certification of Authorization No. (if applicable) N/A Expiration Date N/A SHIES EWERCo -MI N N IJuurj~g~

Date ~ / 1 7 20 1 1 Signed dbn. Y C E L E N ~ IN& ~ ~ ~ , By Owner Section XI IS1 Coordinator PjC W R ~ A .PE~Q-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 ,UVC~-J-.7-4 and employed by P rrj 12 . t ~s A poi L ~k 2+2 QF c T of 1~ fl i- h-n d L L! /JII/L~CTICW 1- have inspected the components described in this Owner's Report during the period 4 1 2 y / o 7 to 8-1/7 ,

and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's 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.

Commissions / t / f l/&iJ/I, /qL / L ~ P ~ d ~ Q ~ ~ f - f d National Board, State, Province, Endorsements

Monticello Nuclear Generating Plant Cycle 25 Summary Report Inservice Inspection 2011 Refueling Outage SECTION 6. FORM NIS-2 INFORMATION - SUPPLEMENT Page 1 of 3

(**Supplement to Submittal for Cycle 24,2009 RFO**)

Cycle 24 NIS-2 Summary Addendum and Form NIS-2 for R/R 2009-24-057 RJRITEM WORK COMPONENT WORK DESCRIPTION NUMBER DOCUMENT OR SYSTEM 2009-24-057 WO-359192 AO-2387 Replaced 4 fasteners per EC-14182 (2 pages to follow)

Monticello Nuclear Generating Plant Cycle 25 Summary Report Inservice Inspection 2011 Refueling Outage RepairlReplacement Plan No.:2009-24-057

1. Owner NSP-Minnesota,an Xcel Energy Company Date 8/15/2011 Name 414 Nicollet Mall, Minneapolis, MN 55401 Sheet 1 of 2 Address

2. Plant Monticello Nuclear Generating Plant Unit I Name 2807 West County Road 75, Monticello, MN 55362 WO-359192, EC- 14 182 Address Repair Organization P,O. No., Job No. etc.

3. Work Performed By NSPM/Xcel Energy Type Code Symbol Stamp n/a Company Name Authorization No. n/a 2807 West County Rd. 75, Monticeli~,MN 55362 Expiration Date n/a Address

4. ldentification of System Primary Containment (PCT), AO-2387, Class 2

5. (a) Applicable Construction Code B31.1 , 1967E/NoAdd Edition / Addenda (b) Applicable Edition of Section XI Used for RepairIReplacementActivity 2001 Edition, No Addenda (c) Applicable Section XI Code Case(s) n/a

6. ldentification of Components Corrected, ASME Code Name of Name of Manufacturer National Other Removed, or Stamped Component Manufacturer Serial No. Board No. ldentification Year Built Installed YES NO A 0-2387 Fisher n/a n/a n/a 1969 removed Studs A 0-2387 Nova n/a n/a n/a 2009 installed Studs AO-2387 Nuts Fisher n/a n/a n/a f969 removed rn AO-2387 Nuts Nova n/a n/a n/a 2009 installed 0 0

7. Description of Work Like for like replacement of (4) studs and (8) nuts

8. Tests Conducted: Hydrostatic Cj Pneumatic CI] Nominal Operating Pressure [7 Exempt Other CZj Pressure ' psi Test Temp . O F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8-112 In x 11 in, (2) information in items 1 through 6 on this report Is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form. (See 4 Awl-09.04.03 [ASME Section XI RepairlReplacement Program] for further documentation guidance.)

Approval: PCR 01 148046 J

Monticello Nuclear Generating Plant Cycle 25 Summary Report Inservice Inspection 2011 Refueling Outage RepairIReplacement Plan No.: 2009-24-057 I

9. Remarks . (Applicable Manufacturer's Data Reports to be Attached)

Like for like replacement of studs and nuts in supporf of EC-14782 during a valve PA4 No PM? or PSI required for bolting replacement.

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code,Section XI.

Signed ) , 1SI ? r o r w )WNE(L

~ Date 8/l$/=,r Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of oiler-and Pressure Vessel Inspectors and the State or Province of Minnesota and employed by Hartford Steam Boiler lnsp & Ins Companv of Connecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period 3 /go / z o 10 to 8 - / / 6 / ~ 5 j / I and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the lnspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in the Owner's Report. Furthermore, neither the lnspector nor his employer SHALL be liable in any manner for any personal injury of property damage or a loss of any kind arising from or connected with this inspection.

&th<- &-hr Commissions Pfl /id%..? AdU, / L f r J d ~i / ~ r f - c ~

Inspector's Signature National Board, Province and Endorsements Date 6l / b / I /

ENCLOSURE 2 MONTICELLO NUCLEAR GENERATING PLANT BWRVlP INSPECTION

SUMMARY

REPORT (9 pages follow)

Xcel Energy, Inc.

Northern States Power Co. - Minnesota 414 Nicollet Mall Minneapolis, MN 55401 BVVRVIP RF025 IVVI

SUMMARY

REPORT Monticello Nuclear Generating Plant Unit 1 2807 West County Road 75 Monticello, MN 55362 Commercial Service Date: June 30,1971 Report Date: August 17, 201 1

Monticello Nuclear Generating Plant Cycle 25 I W I Summary Report BWRVIP lnspection Program 201 1 Refueling Outage Page 1 of 8 RF025 lVVl BWRVIP Summary Report Comprehensive in-vessel visual inspections (IWI) of reactor vessel internal components were conducted to ensure continued integrity of the Reactor Pressure Vessel (RPV) internals. Additionally, enhanced visual inspections (EVT-1) were performed per recommendations set forth in Boiling Water Reactor Vessel lnternals Projects (BWRVIP) guideline BWRVIP-03, "Reactor Pressure Vessel and lnternals Examination Guidelines." The I W I was performed in accordance with MNGP procedure PEI-02.05.05, "Visual Examination of Monticello Reactor Vessel Inspection,"

Revision 4, as directed by the MNGP IS1 Program Owner and BWRVIP Program Owner. Examinations were performed by teams of Westinghouse camera handlers and I W I Level 111111personnel performing the examinations from the refueling bridge.

The bottom head drain line inspection was performed by EPRl to meet BWRVIP requirements outlined in BWRVIP-205, "Bottom Head Drain Line Inspection and Evaluation Guidelines." The bottom head drain line UT was performed in accordance with FP-PE-NDE-427, "Ultrasonic testing of the Monticello Bottom Head Drain Line Using Remote Tooling."

Westinghouse Level Ill personnel performed independent review of all of the recorded I W I examinations. Owner review of the recorded IWI examinations was performed by MNGP ISlllWl personnel.

Examinations performed during RF025 are listed in the following pages. The new indications and their resolutions can be found in the Table BWRVIP-1 below. The BWRVIP required inspections were performed in accordance with BWRVIP guidelines.

Monticello Nuclear Generating Plant Cycle 25 I W I Summary Report BWRVlP Inspection Program 201 1 Refueling Outage Page 2 of 8 Table BWRVIP-I: RF025 lndications c

Component Resolution Guide Rod lndication on the guide rod lndication evaluated and at 175 degree location. accepted for continued (CAP 0 1280462) service through the next cycle in Condition Evaluation for CAP 01280462, lndication will be re-examined in next outage in 2013.

Shroud Support lndication discovered on lndication evaluated and Leg H10 weld at 90 degree accepted for continued location. (CAP 01282530) service through the next cycle in Engineering Change (EC) 18051, lndication will be re-examined in next outage in 2013.

Shroud Support lndication discovered on lndication evaluated and Leg H I 0 weld at 330 degree accepted for continued location. (CAP 01283709) service through the next cycle in EC 18051. lndication will be re-examined in next outage in 2013.

Shroud Support lndication discovered on lndication evaluated and Leg H10 weld at 350 degree accepted for continued location. (CAP 01283715) service through the next cycle in EC 18051. lndication will be re-examined in next outage in 2013.

Shroud Support lndications discovered on lndications evaluated and PlateIBaffle Plate H8 and H9 welds on lower accepted for continued plenum side. service in EC I8051, (CAP 01280490) EC 18095 and EC 18067.

lndications will be re-examined in next outage in 2013.

Legacy FMEICAP All FME removed from vessel.

01280284

Monticello Nuclear Generating Plant Cycle 25 I W I Summary Report BWRVIP lnspection Program 2011 Refueling Outage Page 3 of 8 lVVl Inspection Summary Core Spray Piping a EVT-1 examination of the CSP-PI-90, Thermal Sleeve to T-box (hidden weld).

e EVT-1 examination of the CSP-PI-270, Thermal Sleeve to T-box (hidden weld).

a EVT-1 examination of the CSP-P2-90, T-box to Cover Plate.

e EVT-1 examination of the CSP-P2-270, T-box to Cover Plate.

a EVT-1 examination of the P3a, b, c, d, T-box to Pipe welds at 80°, 100°, 260°,

and 280".

• EVT-1 examination of the P5, Downcomer to Sliding Sleeve welds at 13", 166",

193", and 346".

a EVT-1 examination of the P6, Sliding Sleeve to Outer Sleeve welds at 13", 166",

193", and 346".

a EVT-1 examination of the P7, Downcomer to Sliding Sleeve welds at 13", 166",

193", and 346".

a EVT-1 examination of the P8a, Pipe to Collar welds at 13", 166", 193", and 346".

e EVT-1 examination of the P8b, Collar to Shroud welds at 13", 166", 193",

and 346".

a EVT-1 examination of the previous indication on P3A.

m VT-3 examination of the Piping Clamp Assemblies at 90" and 270".

Core Spray Sparger o EVT-1 examination of the CSS-S1-A and D, Sparger T-box Cover Plate at 13" and 346".

e EVT-1 examination of the CSS-S2-A-1 and 2, Sparger T-box to Sparger Pipe at 11" and 15 ".

Monticello Nuclear Generating Plant Cycle 25 I W I Summary Report BWRVIP lnspection Program 201 1 Refueling Outage Page 4 of 8 Core Spray Sparaer (Continuedl a EVT-1 examination of the CSS-S2-D-1 and 2, Sparger T-box to Sparger Pipe at 344" and 348".

a VT-1 examination of the CSS-AS3A and B, Sparger Nozzles from 272" to 87".

a VT-1 examination of the CSS-DS3A and B, Sparger Nozzles from 272" to 87".

a VT-1 examination of the CSS-AS3C-1 and 2, Sparger Drain Plug welds.

a EVT-1 examination of the CSS-S4-A-1 and 2, Sparger End Cap welds at 87" and 272".

a EVT-1 examination of the CSS-S4-D-1 and 2, Sparger End Cap welds at 87" and 272".

a VT-1 examination of the CSS-SB-xxx, upper and lower Sparger Brackets at 13",

54", 87", 272", 306", and 346".

Top Guide Assembly a VT-1 examination of the Top Guide Aligner Pins and Sockets at 72" and 162".

a EVT-1 and VT-3 examination of Top Guide Cells 38-07, 34-35, 34-19, 30-39, 18-35, 18-19, 14-11, and 14-07.

a VT-3 examination of the Top Guide accessible areas.

Shroud Support Inspection a EVT-1 examination of the H8 and H9 at 0" and 180".

a VT-3 examination of previous indications on H I 0 at lo0, 30°, 60°, 120°, 150°,

170°, 190°, 210°, 240°, 270°, and 300".

a VT-3 examination of accessible areas of the H8 and H9 above and below the Shroud Support Plate.

a VT-3 examination of accessible areas of the Shroud Support Plate.

Monticello Nuclear Generating Plant Cycle 25 IWI Summary Report BWRVIP lnspection Program 201 1 Refueling Outage Page 5 of 8 Shroud Support lnspection (Continued) a VT-3 examination of the Shroud Support Legs at 10°, 30°, 60°, 90°, 120°, 150°,

170°, 190°, 210°, 240°, 270°, 300°, 330°, and 350".

Control Rod Guide Tubes e VT-3 examination of Guide Tubes in cell locations 38-07, 34-35, 34-19, 30-39, 18-35, 18-19, 14-11, and 14-07.

Core Plate 0 VT-3 examination of accessible Core Plate areas in cell locations 38-07, 34-35, 34-19, 30-39, 18-35, 18-19, 14-11, and 14-07.

Jet Pumps a VT-1 examination of the WD-1 wedges on Jet Pumps 1 through 20.

a EVT-1 examination of the RS-1, RS-2, and RS-3, Riser welds on Jet Pumps 6 through 10.

e EVT-1 examinations of the RS-4 and RS-5 Riser Sleeve to Riser welds on Jet Pumps 14 through 20.

e EVT-1 examination of the RS-8, RS-9, RS-10, and RS-11 Riser Brace Yokes to Riser welds on Jet Pumps 1 through 20.

a EVT-1 examination of the MX-1, MX-2, and MX-4, Inlet Mixer welds on Jet Pumps 15 through 20.

0 EVT-1 examination of the DF-1 and DF-2 Diffuser welds on Jet Pumps 16 through 20.

0 EVT-1 examination of the AD-2, AD-3a, and AD-3b Diffuser Adapter welds on Jet Pumps 16 through 20.

a VT-1 examination of the Riser Brace Pad to Vessel attachment welds on Jet Pumps 1 through 20.

Monticello Nuclear Generating Plant Cycle 25 IWI Summary Report BWRVIP Inspection Program 2011 Refueling Outage Page 6 of 8 Drv Tubes 0 VT-1 examination of Intermediate Range Monitors (IRMs) at core locations 20-33,28-23, 20-41, 12-41, 36-41, 12-09, 28-25 and 20-25.

o VT-1 examination of Source Range Monitors (SRMs) at core locations 12-25, 28-17, 36-09 and 36-33.

RPV Attachments o VT-3 examination of the Feedwater Sparger End Brackets and attachment welds at 0, 90°, 180°, and 270".

0 VT-3 examination of Surveillance Sample Holder Upper Brackets at 30°, 120°,

and 300".

@ VT-3 examination of Surveillance Sample Holder 120".

VT-1 examination of Surveillance Sample Holder Lower Brackets at 30°, 120°,

and 300".

o VT-I examination of the Guide Rod Bracket Vessel attachment welds at 175" and 355".

o VT-3 examination of the Guide Rod Brackets at 195" and 355".

o VT-3 examination of the Steam Dryer Support Bracket and weld at 35", 145",

215", and 325".

Bottom Head Drain Line 0 UT of Bottom Head Drain Line REW31-2-ED.

Monticello Nuclear Generating Plant Cycle 25 I W I Summary Report BWRVIP lnspection Program 2011 Refueling Outage Page 7 of 8 RF025 lnspection Results Core Spray Piping a Examination of previously recorded indication on Core Spray Piping weld P3A at 90" showed no change.

@ No new relevant indications.

Core Spray Sparger Examination of the Core Spray Spargers revealed no relevant indications.

Top Guide Assembly a Examination of the Top Guide Assembly revealed no relevant indications.

Shroud Support lnspection a Examination of previously recorded indications on H I 0 at l o 0 , 30°, 60°, 120°,

150°, 170°, 190°, 210°, 240°, 270°, and 300" showed no change.

e Examinations of previously recorded indications on H I 0 revealed new relevant indications at 90".

• VT-3 examination of the Shroud Support Legs revealed new indications at 330" and 350".

e During examinations of previously recorded indications on H10, new relevant indications were reported on the H-8 and H-9 welds on the underside of the Shroud Support Plate.

Control Rod Guide Tubes e Examination of accessible Control Rod Guide Tubes revealed no relevant indications.

Monticello Nuclear Generating Plant Cycle 25 I W I Summary Report BWRVIP Inspection Program 201 1 Refueling Outage Page 8 of 8 Core Plate e Examination of accessible areas of the Core Plate revealed no relevant indications.

Jet Pumps e Examination of previously recorded indication on Jet Pump 8 Restrainer Bracket showed no change.

No new relevant indications.

Dry Tubes Examination of accessible SRM's and IRM's revealed no relevant indications.

RPV Attachments Examination of the 175" Guide Rod revealed a relevant indication.

Bottom Head Drain Line a Examination of Bottom Head Drain Line REW31-2-ED revealed no relevant indications, results were acceptable.