ML101580107

2R26 Outage, SG Tube Inspection Telecon Slides

ML101580107
Person / Time
Site:	Prairie Island
Issue date:	04/28/2010
From:	Thomas Wengert Plant Licensing Branch III
To:
Wengert, Thomas J, NRR/DORL, 415-4037
References
TAC ME3558
Download: ML101580107 (26)

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2R26 NRC Phone Call April 28, 2010

Participants:

-'; ;~. Prairie Island (NSP MN)

• Kari Den Herder (SG-Engineer)

.. _; . . ~ .. ~-.-

• Sam DiPasquale{Li~ensing)

• Mike Heller (SG Project Supervisor)

• Scott Redner (ET Level III QDA)

• Jeff Ricker (Inspection & Materials Supervisor)

• Steve Skoyen (Engineering Programs Manager)

• Ben Stephens (SG Program Engineer)

• AREVA (Lynchburg)

• Jim Begley (CMOA analyst) 2

2R26 NRC Phone Call April 28,2010

• The attached information has not been validated.

In many cases, it.Is preliminary information from ongoing activities. To our knowledge, itis the best informationavailableas of 10 AM on the date prior to this report and may be changed following further review and analysis.

• NRC Discussion Points are provided in italic font and are used as a template for this presentation.

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2R26 NRC Phone Call April 28, 2010 Current Status of 2R26 SG Inspection (As of 1000 on April 27, 2010)

.Cateqory 21 SG 22SG

~

c ET Acquisition (0/0 completed) 80.4 75.3 ET Analysis (0/0 completed) 71.6 69.9

1. of Pluggable Tubes 12 9

1. of Re-Roll Candidates 248 153

1. of In Situ Candidates 0 0 4

2R26 NRC Phone Call April 28, 2010 Q1: Discuss any trends in the amount of primary-to-secondary leakage observed during the recently completed cycle.

• 21 Steam Generator maximum steady stateleakaqeby tritium was less-than detectable to < 1.1 qallons.perday over the last cycle.

• 22 Steam Generator maximum steady state leakage by tritium was less than detectable to <1 gallon per day over the last cycle.

• Steam Generator Tube Leakage is similar to leakage over the last three cycles.

5

2R26 NRC Phone Call April 28, 2010 Leak Rate U2 All available data points between 11/11/2008 anl!04l16/2010 I!U uL

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2R26 NRC Phone Call April 28, 2010 Leak Rate U2 All "vailal~l,c dala points between 1IIII/200X ,IlH,(04l16/2010

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2R26 NRC Phone Call April 28, 2010 Q2: Discuss whether any secondary side pressure tests were performed during the outage and the associated results.

--"- ~** Due to very low primary to secondary leakage, .

no pressure tests were done to look for tube leakage.

7

2R26 NRC Phone Call April 28, 2010 Q3: Discuss any exceptions taken to the industry guidelines.

• No exceptions were or will be taken from industry' guidelines.

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2R26 NRC Phone Call April 28, 2010 Q4: For each SG, provide a description of the inspections performed including the areas examined and the probes used, the scope of the inspection, and the expansion criteria.

• Prairie Island 2R26 steam generator inspection plan is attached on the following sheet.

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2R26 NRC Phone Call April 28, 2010 2R26 Steam Generator Inspection Plan

~- ~

SCOPE PROBE TYPE S/G 21 S/G 22 Full Length 0 Bobbin 100% 100%

~ Rows 1 through 4 U-Bends MRPC 100% 100%

Rows 5 through 8 U-Bends

• MRPC 33% - 33%

Hot Leg Tubesheet MRPC 100% 100%

1690 Hot Leg Roll Plugs. MRPC 25% 25%

Cold Leg Tubesheet MRPC 20% 20%

Supplemental 0 MRPC 100% 100%

Post In Situ Pressure Test MRPC 100% 100%

Plug Visual N/A 100% 100%

Baseline New Re-Rolls MRPC 100% 100%

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2R26 NRC Phone Call April 28, 2010 2R26 Steam Generator Inspection Plan (cont.)

o Except the bend portion of row 1 through 4 u-bends.

• Expansion plan defined in plant procedure 2H25.1 .

.. Plug samples and cold leg tubesheet samples are considered proactive informational sample plans that are not subject to the periodicity requirements of T.S.5.5.8.d.3.

e ADR, CUD, DEP, ONI, TSP DNT > 2.0V, Freespan ONT > 5.0V, DRI, 051, OTI, TSP INR > 1.5V, MBM, NQI, PLP (Bound MRPC PLP's), PSI, Cold Leg Thinning > 400/0 or < 400/0 and > 1.5V.

11

2R26 NRC Phone Call April 28, 2010 eQ5: For each area examined (e.g., tube supports, dents/dings, sleeves, etc), provide:

A summary of the number of indications identified to-date of each degradation mode (e.g~,numberof circumferential primary water stress corrosion crackingindjcations at the expansion transition).

For the most significant indications in each area, provide an estimate of the severity of the indication (e.g., provide the voltage, depth, and length of the indication). In particular, address whether tube integrity (structural and accident induced leakage integrity) was maintained during the previous operating cycle.

In addition, discuss whether any location exhibited a degradation mode that had not previously been observed at this location at this Unit (e.g., observed circumferential primary water stress corrosion cracking at the expansion transition for the first time at this unit).

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2R26 NRC Phone Call April 28, 2010 PI 2R26 Analysis Status Analysis Status (percent completed) as of SG 21 SG22 1000 on April 27, 2010: Hot Cold Hot Cold

~. Bobbin ~ ,

100 96.1 100 96.1 .

U-Bend MRPC 0 N/A 0 N/A Tubesheet Crevice MRPC 71.0 25.9 67.6 28.5 Hot Leg Roll Plug MRPC 0 N/A 0 N/A Supplemental MRPC 0 0 0 0 Post In Situ MRPC 0 0 0 0 Plug Visual 100 100 100 100 Baseline New Re-Rolls 0 0 0 0 13

SG 21 Analysis Results to Date Degradation Mode and Location (Indications) # Volt Depth Length New Excludes all indications below the F* and EF* Distance Mech.

Volumetric Wear at New Anti-Vibration Bars (AVB)~.:!: 1") 21 2.11 33 N/A N Volumetric Wear at Old AVB's (free span)(> 1") 49 2.94 43 N/A N Volumetric Wear at PLP's (1998 In Situ Neighbors) 2 0.70 33 N/A N Volumetric Thinning at Cold Leg Tube Support Plates* 75 3.03/1.55 36/46 N/A N Volumetric Thinning at Cold Leg Top of Tubesheet . 0 N/A N/A ... N/A N Volumetric Thinning at Hot Leg Tube Support Plates 0 N/A N/A; ..

N/A N Volumetric Thinning at Hot Leg Top of Tubesheet 0 N/A N/A N/A N Axial ODSCC at Hot Leg Sludge Pile 2 0.15/0.10 N/A 0.22/0.33 N Axial ODSCC at Hot Leg Crevice 8 0.22 N/A 0.45 N Axial ODSCC at Hot Leg Tube Support Plates 0 N/A N/A N/A N Axial PWSCC at Hot Leg Roll ExpansionslTube Ends 338 1.75/0.76 N/A 0.10/0.78 N Cire. PWSCC at Hot Leg Roll ExpansionslTube Ends 1 2.42 N/A 0.17 N Cire. ODSCC at a Re-Roll Expansion 1 0.36 N/A 38°/0.27" Y Axial PWSCC at U-bends 0 N/A N/A N/A N Cire. PWSCC at U-bends 0 N/A N/A N/A N ODSCC/PWSCC at Dents 0 N/A N/A N/A N ODSCC/PWSCC at Plugs 0 N/A N/A N/A N 14

SG 22 Analysis Results to Date Degradation Mode and Location (Indications) # Volt Depth Length New Excludes all indications below the F* and EF* Distance Mech.

Volumetric Wear at New Anti-Vibration Bars (AVB)~.:!: 1") 47 3.23 45 N/A N Volumetric Wear at Old AVB's (free span)(> 1") 32 2.71 40 N/A N Volumetric Wear at PLP's 0 N/A N/A N/A N Volumetric Thinning at Cold Leg Tube Support Plates . *122 5.03/2.46 44/56 N/A N Volumetric Thlnninqat Cold Leg Top of Tubesheet ~- O. N/A N/A N/A N.

Volumetric Thinning at Hot Leg Tube Support Plates. '0 N/A N/A

- N/A N Volumetric Thinning at Hot Leg Top of Tubesheet 0 N/A N/A N/A N Axial ODSCC at Hot Leg Sludge Pile 0 N/A N/A N/A N Axial ODSCC at Hot Leg Crevice 2 0.11 N/A 0.35 N Axial ODSCC at Hot Leg Tube Support Plates 0 N/A N/A N/A N Axial PWSCC at Hot Leg Roll ExpansionslTube Ends 210 1.51/1.16 N/A 0.10/0.68 N Circ. PWSCC at Hot Leg Roll ExpansionslTube Ends 0 N/A N/A N/A N Circ. ODSCC at a Re-Roll Expansion 0 N/A N/A N/A N Axial PWSCC at U-bends 0 N/A N/A N/A N Circ. PWSCC at U-bends 0 N/A N/A N/A N ODSCC/PWSCC at Dents 0 N/A N/A N/A N ODSCC/PWSCC at Plugs 0 N/A N/A N/A N 15

2R26 NRC Phone Call April 28, 2010 Analysis Status (Continued)

(;.~.Structural andaccident induced leakage: integrity

-: . was maintained during the previous cycle, -

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2R26 NRC Phone Call April 28, 201 0 Q6: Describe repair/plugging plans.

Pre Outage Predicted Repairs

-: SCOPE SIG 21 . S/G22 In Situ Pressure Test 5 5 AR1 - 6" Re-Roll 194 104 AR2 - 8" Re-Roll 88 43 ARE - Elevated Re-Roll 13 2 Hot Leg Roll Plugs 20 11 Cold Leg Roll Plugs 20 11 17

2R26 NRC Phone Call April 28, 2010 Planned Repairs (Based on 71 % inspected)

SCOPE * <

SIG 21 S/G22

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-- -, --' ~'- - 0 In Situ Pressure Test 0 AR1 - 6" Re-Roll 177 135 AR2 - 8" Re-Roll 58 15 ARE - Elevated Re-Roll 13 3 Hot Leg Roll Plugs 12 9 Cold Leg Roll Plugs 12 9 18

2R26 NRC Phone Call April 28, 2010 Q7: Describe in-situ pressure test and tube pull plans and results (as applicable and if available).

• We haveno.plans to pull tubes for-Unit 2, as part of a licensed repair program.

• Status - No tube pull is needed.

• We are planning on performing up to 10 In Situ tests based on inspection results.

• Status - No In Situ tests are needed.

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2R26 NRC Phone Call April 28, 2010 Q8: Discuss the following regarding loose parts:

1) what inspections are peiformeato detect loose parts.

A) All bobbin data is evaluated for possible loose parts (PLP) and PLP wear using manual analysis by primary.

'0 8) Secondary uses Computer-Data Screening (CDS) with a PL~ specificsort.frcrn'T'Sf-! + .

.: 0.3" to 07H + 2.00" and from TSC +O:3"-to 07e + 2.00" and vanous wear detection sorts from TSH -1.0" to TSC - 1.0".

C) Resolution tertiary review is conducted on all bobbin coil periphery tubes, two tubes deep for PLP's.

D) All MRPC data is evaluated for PLP's.

E) All bobbin PLP indications are tested with MRPC.

F) All MRPC PLP indications are bounded radially by one tube at the same elevation.

G) Any PLP that cannot be resolved with ECT are inspected from the secondary side for resolution.

H) Top of Tubesheet Remote Visual Inspection: Peripheral & In-bundle.

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2R26 NRC Phone Call April 28, 2010 Q8: Discuss the following regarding loose parts:

2) a description of any loose parts detected and their location within the SG (including the source or nature of the part, if known).

New MRPC PLP Indications:

SG  : HL Top ofTSH. CL Top ofTSH 21 1 0 22 2 1 Based on FOSAR experience and historical lookups, the PLP indications are most likely sludge rocks. Visual confirmation will be conducted with the FOSAR inspection.

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2R26 NRC Phone Call April 28, 2010 Q8: Discuss the following regarding loose parts:

3) if the loose parts were removed from the SG.

A). SG 21 secondary side FOSAR will be done this week.

B). SG 22 secondary side FOSAR follows sludge lancing this week.

Q8: Discuss the following regarding loose parts:

4) indications of tube damage associated with the loose parts.

There is no wear associated with any of the PLP indications.

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2R26 NRC Phone Call April 28, 2010

• Q9: Discuss the scope and results of any secondary side inspection and maintenance activities.

• FOSAR results previously discussed.

• SP 2534 Steam Generator Internals Inspection for 22 SG

• SG Steam Drum Inspection planned this week:

• Tube Bundle Wrapper

• Feedwater Ring/Thermal Sleeve

• Moisture Separation Equipment

• SG Feedwater Nozzle lSI Inspections of:

• Knuckle Region, Nozzle to Reducer and Reducer to Pipe Welds, Transition Cone Girth Weld, Feedwater Ring Hangers, and FAC Inspection of FW Tee

• Top of Tubesheet Region planned after sludge lancing.

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2R26 NRC Phone Call April 28, 2010

• Q10: Discuss any unexpected or unusual results.

• No unexpected or unusual conditions detected during 2R26.

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2R26 NRC Phone Call April 28, 2010

• Q11: Provide the schedule for steam generator related activities during the remainder of the current outage.

• 'ETexaminations are scheduled to be completed later this week.

• In-situ testing is not required at this time.

• Repairs are projected to be completed by May 6.

• Manway installation is scheduled to be completed on May 9.

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