ML13308B218

Enclosure 2- BWRVIP Inspection Summary Report

ML13308B218
Person / Time
Site:	Monticello
Issue date:	10/08/2013
From:	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 BWRVIP RFO26 IVVI
Download: ML13308B218 (10)

Text

ENCLOSURE 2 Monticello Nuclear Generating Plant BWRVIP Inspection Summary Report (10 pages follow)

XcelEnergy Xcel Energy, Inc.

Northern States Power Co. - Minnesota 414 Nicollet Mall Minneapolis, MN 55401 BWRVIP RF026 IVVI

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

"'l ii.

Supervisor, 1%

Approved By:

Manager, Program Engineering Report Date: October 8, 2013

Monticello Nuclear Generating Plant Cycle 26 IVVI Summary Report BWRVIP Inspection Program 2013 Refueling Outage Page 1 of 9 RF026 IWI BWRVIP Summary Report Comprehensive in-vessel visual inspections (IVVI) 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 Internals Projects (BWRVIP) guideline BWRVIP-03, "Reactor Pressure Vessel and Internals Examination Guidelines". The in-vessel visual inspection (IVVI) was performed by qualified personnel and equipment supplied by the Westinghouse Electric Company. The IVVI was performed in accordance with MNGP procedure PEI-02.05.05, "Visual Examination of Monticello Reactor Vessel Inspection"' Revision 5, as directed by the MNGP ISI Program Owner and BWRVIP Program Owner. Examinations were performed by teams of Westinghouse camera handlers and IVVI Level Il/111 personnel performing the examinations from the refueling bridge.

Westinghouse Level III personnel performed independent review of all recorded IVVI examinations. Owner review of the recorded IVVI examinations was performed by MNGP ISI/IVWI personnel.

Examinations performed during RF026 are listed in the following pages. All new indications and their resolutions can be found in the Table BWRVIP-1. The BWRVIP required inspections were performed in accordance with BWRVIP guidelines. The steam dryer examination was performed in accordance with the manufacturer recommended inspection plans.

Monticello Nuclear Generating Plant Cycle 26 IVVI Summary Report BWRVIP Inspection Program 2013 Refueling Outage Page 2 of 9 Table BWRVIP-1: RF026 Indications Component Indication/CAP Resolution Shroud Support Indication discovered on Indication evaluated and Leg H10 weld at 300 degree accepted for continued location on the jet pump service through the next cycle 18 side. (CAP01377599) in Engineering Change (EC) 21854. Indication will be re-examined in next outage.

Shroud Support Areas cleaned on H8 on Indication evaluated and Plate/Baffle Plate lower plenum side at 68 accepted for continued and 218 degree locations, service through the next cycle Indications from RF025 in Engineering Change (EC) confirmed as relevant. 21839. Indication will be re-(CAP 1375496) examined in next outage.

Shroud Support Areas cleaned on H9 on Indication evaluated and Plate/Baffle Plate lower plenum side at 142 accepted for continued and 292 degree locations, service through the next cycle Indications from RF025 in Engineering Change (EC) confirmed as relevant. 21839. Indication will be re-(CAP 1375496) examined in next outage.

N/A Foreign Material (CAP All FME removed from vessel.

01375153)

Monticello Nuclear Generating Plant Cycle 26 IVVI Summary Report BWRVIP Inspection Program 2013 Refueling Outage Page 3 of 9 IVVI Inspection Summary Core Spray Piping

• EVT-1 examination of the CSP-P1-090, Thermal Sleeve to T-box (hidden weld).

• EVT-1 examination of the CSP-P1-270, Thermal Sleeve to T-box (hidden weld).

• EVT-1 examination of the CSP-P2-090, T-box to Cover Plate.

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

" EVT-1 examination of the P3a, b, c, d, T-box to Pipe welds at 0800, 1000, 2600, and 2800.

• EVT-1 examination of the P4-Da, b, c, d header pipe to upper elbow weld at 3460.

• EVT-1 examination of the P5, Downcomer to Sliding Sleeve welds at 0130, 166', 1930, and 3460.

• EVT-1 examination of the P6, Sliding Sleeve to Outer Sleeve welds at 0130, 1660, 1930, and 3460.

• EVT-1 examination of the P7, Downcomer to Sliding Sleeve welds at 0130, 166', 1930, and 3460.

• EVT-1 examination of the P8a, Pipe to Collar welds at 0130, 1660, 1930, and 3460.

• EVT-1 examination of the P8b, Collar to Shroud welds at 0130, 166', 1930, and 3460.

• EVT-1 examination of the previous indication on P3A

• VT-1 examination of the Piping Clamp Assemblies at 0900 and 2700.

• EVT-1 and VT-3 of the Core Spray Piping Brackets at 0300, 1500, 2100, and 3300.

Monticello Nuclear Generating Plant Cycle 26 IVVI Summary Report BWRVIP Inspection Program 2013 Refueling Outage Page 4 of 9 Core Spray Sparger

- EVT-1 examination of the CSS-S1-A, B, C & D, Sparger T-box Cover Plate at 0130, 1660, 1930, and 3460.

• EVT-1 examination of the CSS-$2-1 & 2, Sparger T-box to Sparger Pipe at 0130, 1660, 1930, and 3460.

• VT-1 examination of the CSS-AS3A & B, Sparger Nozzles from 2720 to 0870.

• VT-1 examination of the CSS-BS3A & B, Sparger Nozzles from 0920 to 2670

• VT-1 examination of the CSS-CS3A & B, Sparger Nozzles from 0920 to 2670

• VT-1 examination of the CSS-DS3A & B, Sparger Nozzles from 2720 to 0870

• VT-1 examination of the CSS-S3C-1 & 2, Sparger Drain Plug welds on CS Spargers A, B, C, & D.

- EVT-1 examination of the CSS-S4-A-1 & 2, Sparger End Cap welds at 0870 aind 2720.

• EVT-1 examination of the CSS-S4-B-1 & 2, Sparger End Cap welds at 0920 aind 2670.

• EVT-1 examination of the CSS-S4-C-1 & 2, Sparger End Cap welds at 0920 and 267'.

- EVT-1 examination of the CSS-S4-D-1 & 2, Sparger End Cap welds at 0870 and 272'

• VT-1 examination of the CSS-SB-xxx, upper and lower Sparger Brackets at 0130, 0540, 0870, 930, 1260, 1660, 1930, 2340, 2670, 2720, 3060, and 3460.

Shroud Support Inspection

• EVT-1 examination of the top side of H8 and H9 (All accessible).

• Hydrolazing and examination (VT-3) of the bottom side of H8 at 0680 and 2100.

• Hydrolazing and examination (VT-3) of the bottom side of H9 at 1420 and 2920

Monticello Nuclear Generating Plant Cycle 26 IVVI Summary Report BWRVIP Inspection Program 2013 Refueling Outage Page 5 of 9

• VT-3 examination of previous indications on H10 at 0100, 0300, 0600, 900, 1200, 1500, 1700, 1900, 2100, 2400, 2700, 3000, 3300 and 3500.

• VT-3 examination of the Shroud Support Legs at 0100, 0300, 0600, 900, 1200, 1500, 1700, 1900, 2100, 2400, 2700, 3000, 330', and 3500.

Control Rod Guide Tubes and Fuel Support Castings

• VT-3 examination of Guide Tubes in cell locations 06-31, 06-35, 10-43, 18-15, 18-27, 22-03, 22-11, 22-51, 26-03, 26-19, 26-35, 30-03, 34-27, 38-11, 38-39, 42-15, and 42-43.

- EVT-1 examination of Fuel Support Casting orifice tack welds in cell locations 06-31, 06-35, 10-43, 18-15, 18-27, 22-03, 22-11, 22-51, 26-03, 26-19, 26-35, 30-03, 34-27, 38-11, 38-39, 42-15, and 42-43.

Core Plate

• VI-3 examination of accessible Core Plate areas. (13 locations)

Jet Pumps "VT-I examination of the WD-1 wedges on Jet Pumps 3 & 4.

"EVT-1 examination of the RS-1, RS-2, and RS-3, Riser welds on Jet Pumps 15-20.

• EVT-1 examinations of the RS-4 and RS-5 Riser Sleeve to Riser welds on Jet Pumps 3 & 4.

SEVI--1 examination of the RS-8, RS-9, RS-1 0, and RS-1 1 Riser Brace Yokes to Riser welds on Jet Pumps 3 & 4.

• EVT-1 examination of the MX-1, MX-2, and MX-4, Inlet Mixer welds on Jet Pumps 1-4.

• EVT-1 examination of the IN-5 Inlet Mixer clamps on Jet Pumps 1-4

" EVT-1 examination of the DF-1 and DF-2 Diffuser welds on Jet Pumps 1-5 and DF-2 Diffuser weld on Jet Pump 6.

Monticello Nuclear Generating Plant Cycle 26 IVVI Summary Report BWRVIP Inspection Program 2013 Refueling Outage Page 6 of 9

• EVT-1 examination of the AD-1, AD-2, AD-3a, and AD-3b Diffuser Adapter welds on Jet Pumps 1-6.

"VT-1 examination of the Riser Brace RB-1 and RB-2 welds on Jet Pumps 1-4.

• UT of jet pump beams BB-1, BB-2 and BB-3 on Jet Pumps 1-20 Steam Dryer

• VT-1 of RSD-A2-Hi and H2 (Outer Hood 2 horizontal welds)

"VT-1 of RSD-A3-H1 and H2 (Outer Hood 3 horizontal welds)

• VT-1 of RSD-A6-H1 and H2 (Outer Hood 6 horizontal welds)

• VT-1 of RSD-A7-Hi and H2 (Outer Hood 7 horizontal welds)

• VT-1 of RSD-A2-Vi (Outer Hood 2 vertical weld)

"VT-1 of RSD-A3-V1 (Outer Hood 3 vertical weld)

• VT-1 of RSD-A4-V1 (Outer Hood 4 vertical weld)

"VT-1 of RSD-A6-Vl (Outer Hood 6 vertical weld)

• VT-1 of RSD-A7-V1 (Outer Hood 7 vertical weld)

"VT-1 of RSD-A8-V1 (Outer Hood 8 vertical weld)

• VT-1 of RSD-LR-BRKT-035 (Top and bottom lifting rod bracket welds at 350)

"VT-1 of RSD-LR-BRKT-145 (Top and bottom lifting rod bracket welds at 145')

"VT-1 of RSD-LR-BRKT-215 (Top and bottom lifting rod bracket welds at 2150)

"VT-1 of RSD-LR-BRKT-325 (Top and bottom lifting rod bracket welds at 3250)

• VT-1 of RSD-LR-LE-035 (Lifting eye at 350)

• VT-1 of RSD-LR-LE-145 (Lifting eye at 1450)

"VT-1 of RSD-LR-LE-215 (Lifting eye at 215 0 )

Monticello Nuclear Generating Plant Cycle 26 IVVI Summary Report BWRVIP Inspection Program 2013 Refueling Outage Page 7 of 9 "VT-1 of RSD-LR-LE-325 (Lifting eye at 3250)

"VT-1 of RSD-LR-SR-035 (Lifting rod weld to support ring at 350)

• VT-1 of RSD-LR-SR-145 (Lifting rod weld to support ring at 1450)

"VT-1 of RSD-LR-SR-215 (Lifting rod weld to support ring at 215')

• VT-1 of RSD-LR-SR-325 (Lifting rod weld to support ring at 3250)

"VT-1 of RSD-SRCP-035-090 (Support ring cover plate weld from 350-900)

"VT-1 of RSD-SRCP-090-0145 (Support ring cover plate weld from 90'-1450)

"VT-1 of RSD-SRCP-215-270 (Support ring cover plate weld from 215'-2700)

• VT-1 of RSD-SRCP-270-325 (Support ring cover plate weld from 2700-3250)

" VT-3 of RSD-SR-VLSI-035 (Accessible areas of support ring block that interfaces with support bracket at 350)

• VT-3 of RSD-SR-VLSI-145 (Accessible area of support ring block that interfaces with support bracket at 1450)

• VT-3 of RSD-SR-VLSI-215 (Accessible area of support ring block that interfaces with support bracket at 2150)

• VT-3 of RSD-SR-VLSI-325 (Accessible area of support ring block that interfaces with support bracket at 3250)

• VT-3 of RSD-UPR-0-90 (Accessible areas of upper section of the steam dryer from 0-900)

- VT-3 of RSD-UPR-180-270 (Accessible areas of upper section of the steam dryer from 180-270')

- VT-3 of RSD-UPR-270-360 (Accessible areas of upper section of the steam dryer from 270-3600)

• VT-3 of RSD-UPR-90-180 (Accessible areas of upper section of the steam dryer from 90-1800)

Monticello Nuclear Generating Plant Cycle 26 IVVI Summary Report BWRVIP Inspection Program 2013 Refueling Outage Page 8 of 9 RF026 Inspection Results Core Spray Piping

- Examination of previously recorded indication on Core Spray Piping weld P3A at 900 (previously repaired) showed no change.

• No new relevant indications Core Spray Sparer

- No relevant indications.

Shroud Support Inspection

- Examination of previously recorded indications on H10 at 0100, 0300, 0600, 900 1200, 1500, 1700, 1900, 2100, 2400, 2700, 300', 3300, and 3500 showed no change.

• Examinations of H10 revealed a previously unreported relevant indication at 3000.

- During RF025, indications were reported on the bottom side of the H8 and H9 Shroud Support Plate welds. Attempts to clean and examine the welds to determine relevancy were unsuccessful. A default determination of relevancy was made. During RF026 two sample locations for each of the two welds were hydrolazed with a high pressure waterjet system. Relevant indications were reported after the cleaning and comparisons with indications evident prior to cleaning concluded that the indications reported in RF025 were relevant.

Control Rod Guide Tubes and Fuel Support Castings

- No relevant indications.

Core Plate

• No relevant indications.

Jet Pumps

• No relevant indications.

Monticello Nuclear Generating Plant Cycle 26 IVVI Summary Repoit BWRVIP Inspection Program 2013 Refueling Outage Page 9 of 9

,Replacement Steam Dryer

• No relevant indications.