RNP-RA/14-0038, Refueling Outage 28 Steam Generator Tube Inspection Report

Refueling Outage 28 Steam Generator Tube Inspection Report

ML14127A066
Person / Time
Site:	Robinson
Issue date:	04/29/2014
From:	Peavyhouse S Duke Energy Progress
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RNP-RA/14-0038
Download: ML14127A066 (7)

Text

Sharon W. Peavyhouse H. B. Robinson Steam Electric Plant Unit2 KNERGY ENERGY Director- Nuclear OrganizationEffectiveness Duke Energy Progress 3581 West Entrance Road Hartsville, SC 29550 0: 843 857 1584 F: 843 857 1319 Sharon.Peavyhouse@duke-energy.com TS 5.6.8 Serial: RNP-RA/14-0038 APR 2 9 2014 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/RENEWED LICENSE NO. DPR-23 REFUELING OUTAGE 28 STEAM GENERATOR TUBE INSPECTION REPORT Ladies and Gentlemen:

In accordance with the H. B. Robinson Steam Electric Plant (HBRSEP), Unit No. 2, Technical Specifications (TS) Section 5.6.8, "Steam Generator Tube Inspection Report," Duke Energy Progress, Inc., submits the attached report.

The attachment to this letter provides the steam generator tube inspection report information for Refueling Outage 28 (R028) required by TS Section 5.6.8.

There are no regulatory commitments made in this submittal. If you have any questions regarding this submittal, please contact Mr. R. Hightower at (843) 857-1329.

Sincerely, Sharon W. Peavyhouse Director - Nuclear Organization Effectiveness SWP/msc Enclosure Attachment .

cc: Mr. V. M. McCree, NRC, Region II Mr. S. P. Lingam; NRC Project Manager, NRR NRC Resident Inspector, HBRSEP, Unit No. 2

United States Nuclear Regulatory Commission Enclosure to Serial: RNP-RA/14-0038 Page 1 of 3 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 REFUELING OUTAGE 28 STEAM GENERATOR TUBE INSPECTION REPORT Pursuant to H. B. Robinson Technical Specification 5.6.8 the following information is provided:

a. The scope of inspections performed on each SG The SG Tube Inspection Programincluded the use of multi-frequency Bobbin Coil Rotating Pancake (PAN), Rotating Plus Point (+Pt)and Array X-Probe (XP) probes.

Bobbin Probe Examination Full length examination with bobbin probe of 50% of in-service tubes, including:

• Tubes adjacentto plugged tubes

" Tubes with priorbobbin/RPC PLPabove HTS/CTS

" Tubes with bobbin indicationsfrom the prior inspection (R026)

• 2-Sigma tubes identified in the DegradationAssessment

" Tubes planned in the Rows 1-2 and Row 9 U-bend arrayinspection

• Tubes planned to be preventatively plugged

" Additional tubes to make up a 50% sample Array Probe Examination Examination with arrayprobe (X-probe) of the following:

" Hot leg tubesheet to ist TSP (HTE-O1H) of 100% of in-service tubes

" Cold leg tubesheet to 1st TSP (CTE-01C, or CTE-FBC for tubes in the FBC cutout region) of tubes in a two-tube pattern around the periphery and adjacentto the no-tube lane (i.e. rows 1-2)

• U-bend (06H-06C) of 50% of the in-service tubes in rows 1 and 2

" U-bend (06H-06C) of 20% of the in-service tubes in row 9

• Bobbin dent indications> 4.0 volts (called in RF026 or the current outage)

• Special interest (bobbin I-codes, PLP)

" Bounding of confirmed PLP (1 tube bounding)

• Array exams not requiredfor secondary side loose parts (perDuke Energy steam generatorengineer)

MRPC Probe Examination Examination with MRPC probe:

• U-bend (06H-06C) for tubes in rows 1-2 not able to be inspected due to availabilityof arrayprobes.

• Selected Indications for technology bridging.

Visual Inspections

• All Plugs were visually inspected

" Primarybowl cladding was visually inspectedfor all steam generators

b. Degradation mechanisms found a) Anti-vibration Bar (A VB) wear b) Transientforeign object damage (loose part not present) c) CircumferentialPrimary Water Stress CorrosionCracking (PWSCC) at hot-leg tube ends

United States Nuclear Regulatory Commission Enclosure to Serial: RNP-RA/14-0038 Page 2 of 3

c. Non-destructive examination techniques utilized for each degradation mechanism The Non-destructive examination techniques utilized bobbin coil for the detection of A VB wear and the X probe was utilized to characterizethe wear indications.

d. Location, orientation (if linear), and measured sizes (if available) of service induced indications The complete listing for service-induced indicationsis attached.

e. Number of tubes plugged during the inspection outage for each active degradation mechanism A total of four tubes were plugged. The four tubes had been identified for plugging due to previously identified manufacturingimperfections as requiredto support the H* licensing requirements. No tubes were recommended for repair due to current inspection results.

f. The number and percentage of tubes plugged to date, and the effective plugging percentage in each steam generator The HBRSEP, Unit No. 2, steam generators were replacedin 1984 with Westinghouse Model 44F steam generatorswith alloy 600 thermally treated tubes. The current analysis supports up to 6% tube plugging. Priorto RO-28 there were 44 plugged tubes. With the 4 tubes plugged in RO-28 there are a total of 48 plugged tubes out of a populationof 9642 for the three steam generators. This brings the total plugging to 0.5% as compared to the analysis limit of 6%.

Steam A B C Total Generator*

Plugs present 7 21 16 44 priorto EOC 28 Plugs added in 2 2 0 4 EOC 28 Total Plugs 9 23 16 48

% Plugged 0.3 10.7 0.5 0.5

• There are 3214 tubes per generator.

g. The results of condition monitoring, including the results of tube pulls and in-situ pressure testing The condition monitoring report describes a condition monitoring and operational assessment evaluation for Robinson Unit 2 at R028. The evaluation was performed according to NEI 97-06 using the recommended practices of the EPRI Steam GeneratorIntegrity Assessment Guidelines. The degradation forms evaluated at R028 were wear at A VB locations and wear due to foreign objects at the top of tubesheet and neartube supportplates. PWSCC degradationnear HL tube ends was detected and is covered separatelyin an NRC-approved alternaterepaircriterion.

The worst case AVB wear Non-destructive Examination (NDE)depth projected for R028 in the R026 Condition Monitoring and OperationalAssessment (CMOA) was 35 %TW. The deepest AVB wear indicationactually seen during R028 was 28 %TW. Foreignobject wear was predicted to grow minimally in the

United States Nuclear Regulatory Commission Enclosure to Serial: RNP-RA/14-0038 Page 3 of 3 R026 CMOA. This was true of wear indicationsthat were detected during R026.

But as expected, severalnew instances of foreign object wear were detected at R028. The largest foreign object wear indication detected at R028 was 34

%TW. No foreign objects remain at locations with wear. Therefore, the previous operationalassessment was conservatively bounding for all wear types observed in R026 and R028.

All condition monitoring requirements were met. ProjectedEnd of Cycle (EOC) 30 worst case burst pressuresmeet the limiting structuralintegrityperformance requirementof three times normal operatingpressure of 4,350 psi with at least 0.95 probabilitywith 50% confidence. There is no leakage projectedat normal operatingpressure or accidentconditions at R030. Operationalassessment structuraland leakage integrity requirements are demonstrated.

Primarybowl cladding inspections identified no abnormalconditions.

Plug visual inspections identified no abnormalconditions.

No in-situ pressure testing was required. No tube pulls were performed.

h. Evaluation of Primary to Secondary Leakage Rate There was no leakage within detectable limits.

i. The calculated accident induced leakage rate from the portion of the tubes below 18.11 inches from the top of the tubesheet for the most limiting accident in the most limiting SG.

There was no leakage within detectable limits and no calculatedleakage.

j. The results of monitoring for tube axial displacement (slippage). If slippage is discovered, the implications of the discovery and corrective action shall be provided.

No tube slippage was identified.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/14-0038 Page 1 of 3 SG - A Service Induced Degradation H.B. Robinson 2 RF028 RNP 20131001 11/11/2013 10:09:52

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15 6 .68 105 PCT 20 09 01H -. 72 -. 53 0.37 0.19 01H HTE .720 ZYAXA 32 HI I

23 14 .73 113 PCT 21 010 HTS -. 07 .16 0.37 0.23 01H HTE .720 ZYAXA 26 HI I

31 21 .64 80 PCT 20 07 HTS -. 09 .14 0.37 0.23 01H HTE .720 ZYAXA 26 HI I

37 24 .24 47 PCT 14 019 CTS 19.41 19.61 0.37 0.20 FBC CTE .720 ZYAXA 29 Cl I

31 30 .47 113 PCT 18 08 HTS -. 02 .16 0.37 0.18 01H HTE .720 ZYAXA 32 HI I

8 40 3.28 39 SCI 2 HTE .00 91H HTE .720 ZYAXA 20 HI 33 41 .86 82 PCT 22 09 HTS -. 09 .12 0.37 0.21 0IH HTE .720 ZYAXA 26 HI 27 42 .90 97 PCT 23 015 03H -. 86 -. 65 0.37 0.21 03H 03H .720 ZYAXA 33 HI 27 44 .61 99 PCT 20 018 05C -. 88 -. 67 0.37 0.21 85C 05C .720 ZYAXA 25 Cl 45 47 .25 155 PCT 14 06 CTS 11.51 11.69 0.37 0.18 FBC CTE .720 ZYAXA 29 CI 41 53 .73 64 PCT 21 06 HTS -. 07 .14 0.37 0.21 01H HTE .720 ZYAXA 26 HI 24 54 .82 86 PCT 22 019 03H -. 79 -. 55 0.45 0.23 03H 03H .720 ZYAXA 33 HI 40 68 .56 161 PCT 19 06 CTS .44 .74 0.45 0.31 FBC CTE .720 ZYAXA 29 Cl 1 86 .39 60 PCT 16 012 CTS .61 .81 0.37 0.20 FBC CTE .720 ZYAXA 29 CI 1 87 .17 92 PCT 12 04 CTS 1.03 1.21 0.38 0.18 FBC CTE .720 ZYAXA 29 Cl 18 88 .62 78 PCT 20 019 FBH .21 .44 0.37 0.23 01H HTE .720 ZYAXA 26 HI

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Tubes: 16 Records: 16 I ST Max

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/14-0038 Page 2 of 3 SG - B Service Induced Degradation H.B. Robinson 2 RF028 RNP 20131001 11/11/2013 10:13:24

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21 17 .72 98 PCT 19 P22 02H -. 46 0.37 0.29 02H 02H .720 ZYAXA 23 HI I

1 21 1.06 57 PCT 24 05 04C -. 81 -. 58 0.45 0.23 04C 80C .720 ZYAXA 36 CI I

41 28 .58 60 PCT 19 05 03H -. 47 0.45 0.23 03H 03H .720 ZYAXA 23 HI I

41 30 .47 68 PCT 11 P2 02A .04 HTE CTE .720 ZBAGB 20 C1 38 33 2.43 93 PCT 34 04 HTS .12 0.59 0.31 01H HTE .720 ZYAXA 23 HI 35 36 .57 101 PCT 13 P2 03A -. 24 HTE CTE .720 ZBAGB 20 Cl 44 38 .47 156 PCT 11 P2 04A -. 11 HTE CTE .720 ZBAGB 20 C1 2 41 .21 120 PCT 13 03 CTS .72 .86 0.37 0.14 01C CTE .720 ZYAXA 36 Cl 3 43 .31 113 PCT 15 013 CTS .68 .88 0.30 0.20 CTS CTE .720 ZYAXA 36 CI 4 43 .96 61 PCT 23 019 03C -. 76 -. 55 0.45 0.21 03C 03C .720 ZYAXA 36 CI 34 44 1.20 106 PCT 26 05 HTS .04 0.52 0.23 01H HTE .720 ZYAXA 23 HI 10 46 .74 86 PCT 21 012 HTS 3.21 0.52 0.33 01H HTE .720 ZYAXA 23 HI 16 46 1.12 101 PCT 25 04 02H -. 62 0.52 0.23 02H 81H .720 ZYAXA 23 HI 4 47 .20 111 PCT 13 016 CTS .70 .84 0.38 0.14 CTS CTE .720 ZYAXA 36 CI 5 48 .34 111 PCT 16 013 03H 51.00 0.45 0.27 04H 03H .720 ZYAXA 23 HI 5 48 .30 136 PCT 15 09 CTS .94 1.14 0.37 0.20 CTS CTE .720 ZYAXA 36 Cl 5 49 .51 67 PCT 18 09 CTS .85 1.05 0.37 8.20 CTS CTE .720 ZYAXA 36 Cl 34 52 .79 65 PCT 22 06 HTS .02 0.45 0.23 01H HTE .720 ZYAXA 23 HI e1 53 .65 117 PCT 18 P24 04A .70 .97 0.22 0.27 06C 06H .720 ZYAXA 27 HI 11 53 .56 89 PCT 19 016 CTS .76 1.10 0.45 0.35 CTS CTE .720 ZYAXA 36 CI 34 61 .72 86 PCT 21 014 05C -1.06 -. 88 0.37 0.18 05C 05C .720 ZYAXA 36 CI 27 65 .33 122 PCT 15 015 03H .08 0.37 0.27 03H 03H .720 ZYAXA 23 HI 8 89 .99 110 PCT 24 02 HTS -. 02 .19 0.45 0.21 01H HTE .720 ZYAXA 27 HI

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Tubes: 25 Records: 26 1 ST Hex

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/14-0038 Page 3 of 3 SG - C Service Induced Degradation H.B. Robinson 2 RF028 RNP 20131201 11111/2013 10:16:29

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39 41 .96 88 PCT 23 05 03H -. 61 -. 40 0.45 0.22 03H 03H .720 ZYAXA 26 HI I

45 42 .75 128 PCT 15 P2 02A .02 HTE CTE .720 ZBAGB 19 CI I

11 43 .66 126 PCT 20 Q6 03H -. 64 8.52 0.28 N3H03H .728 ZYAXA 31 HN I

15 45 .28 122 PCT 14 016 02H -. 75 0.52 0.26 02H 02H .720 ZYAXA 31 Nj I

37 45 1.88 69 PCT 28 P2 03A .00 HTE CTE .720 ZBAGB 19 CI 37 45 1.69 34 PCT 27 P2 CW .00 HTE CTE .720 ZBAGB 19 CI I

10 49 .72 86 PCT 21 016 G5C -. 98 -. 79 8.37 8.19 05C 25C .720 ZYAXA 32 CI I

34 50 1.99 71 PCT 31 02 HTS .03 .26 0.45 8.23 01H HTE .720 ZYAXA 26 HI I

40 52 .38 143 PCT 9 P2 04A .00 HTE CTE .720 ZBAGB 19 CI I

28 61 .86 100 PCT 20 P25 01A -1.33 -1.02 0.22 0.31 06H 086 .720 ZYAXA 26 Cl I

35 61 .27 167 PCT 6 P2 01A -. 15 HTE CTE .720 ZBAGB 19 CI 35 61 1.32 142 PCT 23 P2 02A .00 HTE CTE .720 ZBAGB 19 CI 35 61 1.42 53 PCT 24 P2 03A .23 HTE CTE .720 ZBAGB 19 CI 35 61 .12 13 PCT 2 P2 04A -. 02 HTE CTE .720 ZBAGB 19 CI 1 36 63 .57 76 PCT 19 08 04H -. 72 -. 48 0.37 0.24 04H 04H .720 ZYAXA 26 HI 1 30 69 .35 87 PCT 16 0ll 02H -. 78 -. 66 0.30 0.13 02H 02H .720 ZYAXA 26 HI 30 71 .63 68 PCT 20 06 03H -. 56 -. 44 0.45 0.12 03H 03H .720 ZYAXA 26 HI 30 72 .86 86 PCT 22 015 03H -. 58 -. 42 0.37 0.16 03H 03H .720 ZYAXA 26 HI 35 73 .61 87 PCT 13 P2 04A .00 HTE CTE .720 ZBAGB 19 C1 33 75 .56 73 PCT 19 06 03H -. 76 -. 58 0.37 0.18 03H 03H .720 ZYAXA 26 HI 8 76 1.12 96 PCT 25 017 04H -. 85 -. 66 0.37 0.20 04H 04H .720 ZYAXA 26 HI 32 78 .44 133 PCT 10 P2 03A .00 HTE CTE .720 ZBAGB 19 C1 19 82 .92 94 PCT 23 01 02H -. 50 -. 32 0.38 0.18 02H 02H .720 ZYAXA 26 HI 8 85 .52 73 PCT 18 014 03H -. 54 -. 42 0.37 0.12 03H 03H .720 ZYAXA 26 HI 3 91 .69 65 PCT 21 06 HTS .20 .48 0.30 0.28 01H HTE .720 ZYAXA 26 HI

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Tubes: 27 Records: 31 1 ST Max