ML16222A351

Submittal of End of Cycle 17 Steam Generator Tube Inspection Report

ML16222A351
Person / Time
Site:	Millstone
Issue date:	08/02/2016
From:	Stanley B Dominion Nuclear Connecticut
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
16-222
Download: ML16222A351 (19)

Text

Dominion Nuclear Connecticut, Inc.

Rope Ferry Rd., Waterford, CT 06385 Mailing Addre~.~: P.O. Box 128 Waterford, CT 06385 dam.com U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 AUG.0 2 2016 DOMINION NUCllEAR CONNECT~ClllT, !NC.

MlllSTONE POWER STAT~ON lllNiT 3 Serial No.

NSS&L/MLC Docket No.

License No.

!END OF CYCClE 17 STEAM GENERATOR TlllBE iNSPECTiON REPORT 16-222 RO 50-423 NPF-49 In accordance with the Millstone Power Station Unit 3 Technical Specification (TS)

Section 6.9.1. 7, Dominion Nuclear Connecticut, Inc. hereby submits the End of Cycle 17 (EOC17) Steam Generator (SG) Tube Inspection report. The report is submitted within_

180 days after initial entry into MODE 4 following completion of the spring 2016' SG inspections performed in accordance with TS 6.8.4.g, "Steam Generator (SG) Program."

Initial entry into Mode 4 occurred on May 10, 2016. contains the EOC17 SG Tube Inspection report. Enclosure 2 contains a list of acronyms.

The report addresses the following reporting requirements:

a. The scope of inspections performed on each SG,

b. Degradation mechanisms found,

c. Nondestructive examination techniques utilized for each degradation mechanism,

d. Location, orientation (if linear), and measured sizes (if available) of service induced indications,

e. Number of tubes plugged during the inspection outage for each degradation mechanism,

f. The number and percentage of tubes plugged to date and the effective plugging percentage in each steam generator,

g. The results of condition monitoring, including the results of tube pulls and in-situ

testing,

h. The primary to secondary LEAKAGE rate observed in each SG (if it is not practical to assign the LEAKAGE to an individual SG, the entire primary to secondary LEAKAGE should be conservatively assumed to be from one SG) during the cycle preceding the inspection which is the subject of the report,

i.

The calculated accident induced leakage rate from the portion of the tubes below 15.2 inches from the top of the tubesheet for the most limiting accident in the most limiting SG. In addition, if the calcuiated accident induced leakage rate from the most limiting accident is less than 2.49 times the maximum operational primary to secondary leakage rate, the report should describe how it was determined; and

Serial No.16-222 Docket No. 50-423 Page 2 of 2

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.

If you have any questions or require additional information, please contact Mr. Jeffry A.

Langan at (860) 444-5544.

Sincerely,

~~-1;:

B. L. Stanley Director, Nuclear Safety and Licensing - Millstone

Enclosures:

1) Millstone Power Station Unit 3, End of Cycle 17 Steam Generator Tube Inspection Report

2) Acronyms Commitments made in this letter: None cc:

U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 R. V. Guzman Senior Project Manager - Millstone Power Station U. S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08 C2 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station

ENCLOSURE1 Serial No.16-222 Docket No. 50-423 END OF CYCLE 17 STEAM GENERATOR TUBE INSPECTION REPORT MILLSTONE POWER STATION UNIT 3 DOMINION NUCLEAR CONNECTICUT, INC. (DNC)

Serial No.16-222 Docket No. 50-423, Page 1 of 14 i ~

End of Cycle 17 Steam Generator Tube Inspection Report Transmittal of this report satisfies f\\.IJillstone Power Station Unit 3 (MPS3) Technical Specification (TS) 6.9.1.7 which specifies that a report shall be submitted within 180 days after the initial entry into MODE 4 following completion of an inspection performed in accordance with TS 6.8.4.g, Steam Generator (SG) Program. During the MPS3 spring 2016 refueling outage (3R17), SG inspections were completed in accordance with TS 6.8.4.g.

Initial entry into Mode 4 occurred on May 10, 2016; therefore, this report is required to be submitted to the NRC by November 6, 2016.

This enclosure provides a summary of the SG primary side inspections performed during 3R17 and specific responses to each TS 6.9.1.7 reporting requirement.

contains a list of acronyms.

Introduction MPS3 is a four loop Westinghouse pressurized water reactor with Westinghouse Model F SGs. Each SG was fabricated with 5626 U-bend thermally treated lnconel 600 tubes. The tubing is nominally 0.688 inches outside diameter with a 0.040 inch nominal wall thickness.

During SG fabrication, the tubes' were hydraulically expanded over the full depth of the 21.23 inch thick tubesheet. The tubesheet was drilled on a square pitch with 0.98 inch spacing. There are 59 rows and 122 columns in each SG. The radius of the row 1 U-bends is 2.20 inches.

U-bends in rows 1 through 10 were stress relieved after being formed. Secondary side tube support structures include a flow distribution baffle, seven plate supports with broached holes on the vertical section of the tubes and six anti-vibration bars (AVBs) on the U-bend section of the tubes.

The SGs have accrued 23.28 Effective Full Power Years (EFPY) of operation as of the end of Cycle (EOC) 17 (April 2016). MPS3 has the capacity to generate a maximum calculated gross output of approximately 1,296 MWe and operates with a hot leg temperature of 618°F.

EOC17 SG Tube Inspection Report This section provides responses to each of the reporting requirements specified in MPS3 TS 6.9.1.7. Bold wording represents TS verbiage. The required information is provided immediately following the restatement of each reporting requirement.

A report shall be submitted within 180 days after the initial entry into MODE 4 following completion of an inspection performed in accordance with TS 6.8.4.g, Steam Generator (SG) Program. T~e report shall include:

i I

a. The scope of inspections performed on each SG,

Serial No.16-222 Docket No. 50-423, Page 2 of 14 One hundred p1ercent of the operationa' tubes in SG B and SG* D, a total of 1-'I, 136 tubes or approximately 50% of the total population of tubes, were inspected full length using eddy current examination techniques. The majority of the tubing length was examined with bobbin probes. The Li-bends of rows 1 and 2 (481 in-service tubes) were examined by either Motorized Rotating Probe Coil (MRPC) technique or an array coil probe technique in addition to the bobbin probe examination of the straight legs of the tubes. An additional augmented sample of 528 tube locations was examined with a MRPC probe. The augmented sample inspections were performed in areas of special interest including hot leg expansion transitions, tube overexpansion locations within the hot leg* tubesheet, dents, as well as locations where. the bobbin probe response was ambiguous. An additional augmented sample of 12,657 tube locations was inspected with an array coil probe. The array coil probe sample included 100% of the hot leg top-of-tubesheet (TTS) locations (11, 136 tubes) and approximately 13% of the cold leg TTS locations (1,504 tubes). The extent of the TTS examinations was from the first support structure detected above the secondary face of the tubesheet to 15.2 inches below the secondary face of the tubesheet.

During 3R17, secondary side activities were performed in SGs A, B, C, and D and included the following:

• Deposit Minimization Treatment (DMT) which is a soft chemical cleaning technique.

e High pressure sludge lancing.

• Post-sludge lancing visual examination of the TTS annulus and no-tube lane to assess as-left material condition and cleanliness and to identify and remove any retrievable foreign,objects.

(t Visual investigation of accessible locations having eddy current indications potentially related to foreign objects, and if present, removal of those retrievable foreign objects.

e Secondary side upper internal examinations within SG B as follows:

o Steam drum visual inspections to evaluate the material condition and cleanliness of key components such as moisture separators, drain systems, and interior surfaces.

o Drop down examinations (through the primary separators) of the upper tube bundle and AVB supports.

o Visual inspections of feed ring internal interface for flow assisted corrosion.*

o Visual* inspections of upper tube support plate (TSP) to assess material conditions and cleanliness.

b. Degradation mechanism's found, Serial No.16-222 Docket No. 50-423, Page 3 of 14 The existing degradation mechanisms found during 3R17 included AVB wear, T6P wear, volumetric indications from fabrication, and volumetric degradation from foreign object wear. A summary of the eddy current test (ECT) result is provided in Table 1.

c. Nondestructive : examination techniques utilized for each degradatioru meclhanism 7 Table 2 identifies the examination techniques used for each identified degradation mechanism.

d. Location, orientation (if linear), and measured sizes (if available) of service induced indications, Tables 3 through 8 identify the AVB wear and non-AVB wear volumetric indications reported during 3R17.

e. Number of tubes plugged during the inspection outage for each degradation mechanism, Based on the inspection results, no tubes were plugged during the 3R17 outage.

f. The number and percentage of tubes plugged to date and the effective plugging percentage in each steam generator.

The total number of tubes plugged to date and the effective plugging percentage in each SG are summarized below.

Number and Percentage of Tubes Plugged To Date SG.A S~B SG.C SG D Prior to 3R17 49 25 22 91 During 3R17 0

0 0

0 Total After 3R17 49 25 22 91 Percentage 0.871 0.444 0.391 1.617 Overall Percentaqe 0.831 Since no sleeving has been performed in the MPS3 SGs, the effective plugging percentage is the same as the actual plugging percentage.

g. The results of condition monitoring, including the results of tube pulls and in-situ

testing,

• No tubes were pulled and no in-situ pressure tests were performed. The condition monitoring assessment concluded that the structural integrity, operational leakage, and

Serial No.16-222 Docket No. 50-423, Page 4 of 14 accident induced leakage performance criteria were not exceeded during the operating interval preceding 3R17.

h. The primary to secondary LEAKAGE rate observed in each SG (if it is not practical to assign the LEAKAGE to an individual SG, the entire primary to secondary LEAKAGE should be conservatively assumed to be from one SG) during the cycle preceding the inspection which ns the subject of the report, No primary to secondary SG leakage was reported during Cycle 17.

i. The calculated accident induced leakage irate from the portion of the tubes be!ow 15.2 inches from the top of the tubesheet for the most ~imiting accident il1l tthe most limiting SG. in addition, if the calculated accident induced leakage rate from the most limiting accident is less than 2.49 times the maximum operatio111a!

primary to secondary leakage rate, the report should describe how it was determined; For the purposes of the condition monitoring assessment, and in accordance with the permanent alternate repair criteria, the accident leakage attributed to degradation within the tubesheet below the H* dimension must be estimated by applying a factor of 2.49 to the operational leakage. There was no recordable operational leakage during Cycle 17; hence, the leakage from this degradation during a limiting accident would have been zero (i.e., 2.49 x 0).

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.

Tube slippage monitoring was performed on SG B and SG D using the bobbin coil data during 3R17. There was no detection of slippage during the 3R17 examination.

Table 1 ECT Examiriation Summary for 3R17 SGA SG B Number of Tubes lnservice at start of 3R17 5577 5601 Number of Tubes Inspected F/L w/Bobbin Probe N/A 4518 Number of Tubes Inspected w/Bobbin Probe Hot Leg Straights N/A 1083 (Rows 1 throuqh 9)

Number of Tubes Inspected w/Bobbin Probe Cold Leg Candy Canes N/A 840 (Rows 3 throuqh 9)

Number of Tubes Inspected w/Bobbin Probe Cold Leg Straights N/A 243 (Rows 1 and 2)

Previously Pluaaed Tubes 49 25 Number of Tubes Incomplete w/Bobbin Probe due to Obstruction N/A 0

Number of Examinations w/MRPC (Total):j:

N/A 533 o Row 1 and 2 U-Bends N/A 240

" Hot Leg Misc. Special Interest - Diagnostic Exams and from N/A 222 Previous History o Cold Leg Misc. Special Interest - Diagnostic Exams and from N/A 24 Previous Historv o U-bend. Special Interest - Diagnostic Exams and from N/A 5

Previous History

• Other Extent-Based Exams (e.q., foreiqn object boundinq)

N/A 42 Number of Examinations w/ARRAY (Total)

N/A 6356 Hot Leq Tubesheet (Baffle Plate)*

N/A 4362 Hot Leq Tubesheet (Non-Baffle)*

N/A 1239 Cold Leo Tubesheet (Baffle Plate)*

N/A 632 Cold Leo Tubesheet (Non-Baffle)*

N/A 120 Foreiqn Object Wear Boundinq N/A 0

Row 1 and 2 U-Bends N/A 3

Hot Leg OXP/OVR Array Exam Sample Size **

N/A 100%

Cold Leq OXP/OVR Arrav Exam Sample Size **

N/A 21%

Tubes w/ Max AVB Wear> 40 % ***

N/A 0

Tubes w/ Max AVB Wear >20% but <40% ***

N/A 12 Tubes w/ Max AVB Wear <20% ***

N/A 42 Tubes w/ Max TSP Wear> 40 %

N/A 0

Tubes w/ Max TSP Wear >20% but <40%

N/A 0

Tubes w/ Max TSP Wear <20%

N/A 2

Tubes w/ Max Non-Structure Vol. Deg. > 40 %

N/A 0

Tubes w/ Max Non-Structure Vol. Deg. >20% but <40%

N/A 7

Tubes w/ Max Non-Structure Vol. Deg. <20%

N/A 1

Total Tubes Pluaaed as a Result of this Inspection:

N/A 0

Serial No.16-222 Docket No. 50-423, Page 5 of 14 SGC SG D Total 5604 5535 22317 N/A 4452 8970 N/A 1083 2166 N/A 845 1685 N/A 238 481 22 91 187 N/A 0

0 N/A 459 992 N/A 224 464 N/A 192 414 N/A 16 40 N/A 11 16 N/A 16 58 N/A 6320 12676 N/A 4290 8652 N/A 1245 2484 N/A 631 1263 N/A 121 241 N/A 17 17 16****

19 N/A 100%

100%

N/A 19%

20%

N/A 0

0 N/A 23 35 N/A 77 119 N/A 0

0 N/A 2

2 N/A 0

2 N/A 0

0 N/A 6

13 N/A 1

2 N/A 0

0 Values provided in the total and the sub-bullets correspond to the number of examinations performed.

Within the cutout region, the upper extent of the array probe exam was the second support (i.e., 02H or 02C).

Percent sample is based on the number of OXPs/OVRs located within the upper 15.2 inches of the tubesheet.

Tubes with multiple AVB wear i~dications are counted only once in the highest depth category.

The U-bends of two low row tubes in SG D were inspected with both +Point' and array coil probes.

Classification Existing Existing Existing Existing Existing Existing Potential Potential Potential Potential Potential Potential Potential Table 2 Serial No.16-222 Docket No. 50-423, Page 6 of 14 Degradation Mechanisms and Inspection Techniques Degradation Mechanism Location Probe Type Tube Wear Anti-Vibration Bars Bobbin - Detection and Sizing Tube Wear Tube Support Plate Bobbin - Detection

+Point'-: Sizing Tube Wear Bobbin, Array and +Point' -

Freespan and TIS Detection (foreign objects)

+Point' - Sizing IGA/SGG Tube Ends N/A*

FAG Feed Ring and J Tube to Feed Visual Inspection Ring Interface Tube Wear Flow Distribution Baffle Bobbin - Detection

+Point' - Sizing ODSCG Hot Leg Top-of-Tubesheet Array - Detection PWSGG and Sludge Region

+Point' - Detection and Sizing Bulges, Dents, Manufacturing Array - Detection ODSGG Anomalies, and Above-

+Point' - Detection and Sizing PWSGG Tubesheet Overexpansions (OVR)

Tubesheet Array - Detection PWSGG Overexpansions (OXP)

+Point' - Detection and Sizing ODSGG Row 1 and 2 U-bends Array - Detection PWSGG

+Point' - Detection and Sizing FAG Moisture Separators Visual Inspection Plug Installation Plugs Visual Inspection Problems Tube Slippage Within Tubesheet Bobbin Detection

• Inspection for this mechanism was not necessary under the permanent alternate repair criteria.

Row Col Location 1

37 03C + 0.33" 30 52 05H -0.58" 1

119 TSC + 3.84" 1

120 TSC + 3.85" 1

121 TSC + 6.40" 15 99 03H - 0.65" 29 65 08C - 0.81" 29 109 04H - 0.53" 32

• 30 06H - 1.00" 44 98 02H + 15.81" Table 3 3R17 Volumetric Degradation Summary SG B (Excludes AVB Wear)

Maximum foreign Object Depth 3R17 Signal History Comment Cause

(%TW)

!Remaining?

14 No signal change since TSP Wear NA previous inspection 13 No signal change since TSP Wear NA previous inspection 30 No signal change since Foreign Object No previous inspection 23 No signal change since Foreign Object No previous inspection 9

No signal change since Foreign Object No previous inspection 32 No signal change since Foreign Object No previous inspection 28 No signal change since Foreign Object No previous inspection 25 No signal change since Foreign Object No previous inspection 37 No signal change since Foreign Object No previous inspection 21 Present in Baseline Fabrication NA Serial No.16-222 Docket No. 50-423, Page 7 of 14 Plugged?

No No No No No No No No No No

Row Col 17 24 35 73 24 89 27 39 46 99 52 42 52 91 58 50 58 51 Table 4: 3R17 Volumetric Degradation Summary SG D (Excludes AVB Weaur)

Maximum Foreign Object Location Depth 3R17 Signal History Comment Cause

(%TW)

Remaining?

07C- 0.67" 31 Small signal present in TSP Wear NA previous inspection 04H - 0.48" 22 No signal change since TSP Wear NA previous inspection 06C - 0.74" 21 No signal change since Foreign Object No previous inspection 08C- 0.90" 27 No signal change since Foreign Object No previous inspection 01H + 0.51" 26 No signal change since Foreign Object No previous inspection 01 H + 0.57" 24 No signal change since Foreign Object No previous inspection 01H + 2.47" 31 No signal change since Foreign Object No previous inspection 01C + 0.42" 17 No signal change since Foreign Object No previous inspection 01C + 0.55" 25 No signal change since Foreign Object No previous inspection Serial No.16-222 Docket No. 50-423, Page 8 of 14 Plugged?

No No No No No No No No No

SG Row SGB 30 SGB 30 SGB 32 SGB 33 SGB 33 SGB 33 SGB 33 SGB 33 SGB 33 SGB 34 SGB 34 SGB 34 I

SGB 34 SGB 34 SGB 34 SGB 34 SGB 35 SGB 35 SGB 35 SGB 35 SGB 36 SGB 36 SGB 36 SGB 36 SGB 36 SGB 36 SGB 37 SGB 37 SGB 37 SGB 37 SGB 38

. SGB 38 SGB 38 SGB 39 SGB 39 SGB 39 SGB 39 Table 5 Serial No.16-222 Docket No. 50-423, Page 9 of 14 AVB Wear Listings, Steam Generator B-Repeat Indications Col AVB

%TW SG Row Col AVB

%TW 12 AV5 15 SGB 40 23 AV5 13 12 AV2 11 SGB 40 23 AV4 12 108 AV4 14 SGB 40 23 AV2 12 12 AV5 17 SGB 40 23 AV3 11 12 AV2 15 SGB 40 24 AV4 18 39 AV3 10 SGB 40 24 AV3 17 109 AV3 18 SGB 40 24 AV5 12 109 AV2 13 SGB 41 34 AV4 33 109 AV6 8

SGB 41 34 AV5 31 18 AV4 8

SGB 41 34 AV3

• 15 18 AV3 9

SGB 41 34 AV2 16 109 AV3 19 SGB 41 34 AV6 12 109 AV5 13 SGB 41 50 AV4 27 109 AV6 8

SGB 41 50 AV3 16 109 AV2 9

SGB 41 69 AV5 30 110 AV3 10 SGB 41 69 AV4 17 103 AV6 7

SGB 41 69 AV3 10 106 AV4 15 SGB 41 77 AV5 20 106 AV6 9

SGB 41 77 AV3 14 106 AV3 10 SGB 41 77 AV4 14 22 AV6 9

SGB 42 19 AVl 10 39 AV5 18 SGB 42 21 AV5 25 39 AV6 13 SGB 42 21 AV4 21 39 AV3 11 SGB 42 21 AV2 15 39 AV2 10 SGB 42 21 AV6 14 67 AV6 8

SGB 42 21 AV3 11 100 AV4 11 SGB 42 33 AV2 13 103 AV2 10 SGB 42 96 AV2 20 104 AV3 13 SGB 42 96 AV4 12 104 AV4 10 SGB 42 96 AV3 13 104 AV4 23 SGB 42 96 AV5 9

104 AV3 13 SGB 42 98 AV2 30 104 AV5 11 SGB 42 98 AV3 31 30 AV2 11 SGB 42 98 AV5 10 30 AV5 10 SGB 43 86 AV4 10 30 AV4 10 SGB 43 100 AV4 26 96 AV3 11 SGB 43 100 AV3 22

SG Row SGB 43 SGB 4S SGB 46 SGB 48 SGB 49 SGB 49 SGB 49 SGB so SGB so SGB so SGB so SGB so SGB so SGB so SGB so SGB Sl Col AVB

%TW SG 100 AV6 10 SGB 22 AV6 10 SGB 99 AV4 12 SGB 2S AV6 7

SGB 27 AVl 11 SGB 27 AVS 13 SGB 27 AV2 10 SGB 29 AV2 18 SGB 29 AV6 12 SGB 72 AV3 13 SGB 88 AV3 22 SGB 88 AV2 18 SGB 88 AV4 16 SGB 88 AVS 12 SGB 88 AV6 7

SGB 91 AVS lS SGB Table 6 Row Sl Sl S4 S4 S4 S4 54 54 54 56 56 56 56 57 58 59 Serial No.16-222 Docket No. 50-423, Page 10 of 14 Col AVB

%TW 91 AV4 11 91 AV6 9

3S AVS 13 3S AV2 12 3S AV4 10 3S AV6 10 36 AV5 31 36 AV6 15 45 AV2 10 41 AV3 9

42 AV6 11 71 AV2 10 81 AVl 11 70 AV2 11 75 AV5 21 65 AV2 13 AVB Wear Listings, Steam Generator~ - New Indications SG Row Col AVB

%TW SGB 34 71 AV3 11 SGB 36 39 AV4 11 SGB 42 98 AVl 10 SGB 42 98 AV4 10 SGB 54 37 AVl 12 SGB 55 84 AV6 14 SGB 58 74 AV4 10

SG Row SGD 9

SGD 23 SGD 26 SGD 28 SGD 28 SGD 28 SGD 28 SGD 29 SGD 29 SGD 30 SGD 30 SGD 30 SGD 31 SGD 31 SGD 31 SGD 32 SGD 33 SGD 33 SGD 33 SGD 33 SGD 34 SGD 35 SGD 35 SGD 35 SGD 35 SGD 35 SGD 35 SGD 35 SGD 35 SGD 35 SGD 36 SGD 36 SGD 37 SGD 37 SGD 37 SGD 37 SGD 37 Table 7 Serial No.16-222 Docket No. 50-423, Page 11 of 14 AVB Wear Listings, Steam Generator D-Repeat Indications Col AVB

• %TW SG Row

. Co!*

AVB

%TW 121 AV6 13 SGD 37 103 AV5 15 10 AV6 10 SGD 37 103 AV2 12 8

AV6

.15 SGD 37 103 AV3 11 8

AV6 14 SGD 37 106 AV4 33 8

AVl 13 SGD 37 106 AV5 24 114 AV2 29 SGD 37 106 AV3 23 114 AV5 11 SGD 37 106 AV6 16 113 AV2 17 SGD 37 106 AVl 13 113 AV5 17 SGD 38 21 AV5 13 113 AV2

,13 SGD 38 21 AV6 8

114 AV6 22 SGD 38 98 AV4 17 114 AVl 11 SGD 38 98 AV2 12 99 AV2 10 SGD 40 32 AV2 13 99 AV5 11 SGD 40 99 AV5 31 99 AV6 10 SGD 40 99 AV4 28 112 AV5 11 SGD 40 99 AV2 14 86 AV3 11 SGD 40 99 AV3 10 86 AV4 14 SGD 40 100 AV4 15 109 AV5 20 SGD 40 100 AV6 14 109 AV2 12 SGD 40 100 AV5 18 109 AV2 12 SGD 40 101 AV3 16 99 AV5 13 SGD 40 101 AV5 14 99 AV2 13 SGD 40 101 AV6 11 102 AV5 15 SGD 40 101 AV4 12

' 103 AV5 16 SGD 40 102 AV4 25 107 AV4 10 SGD 40 102 AV5 19 108 AV3 15 SGD 40 102 AV3 14 108 AV4 11 SGD 40 102 AV6 10 109 AV4 16 SGD 40 103 AV4 35 109 AV5 10 SGD 40 103 AV5 29 82 AV3 13 SGD 40 103 AV3 27 97 AV2 12 SGD 40 103 AV2 22 93 AV3 18 SGD 40 103 AV6 17 93 AV2 13 SGD 40 103 AVl 15 101 AV2 20 SGD 41 26 AV6 32 101 AV3 15 SGD 41 26 AV5 32 101 AV4 14 SGD 41 26 AV2 17

SG Row tol AVB

%TW.

SGD 41 29 AV4 11 SGD 41 29 AV6 9

SGD 41 30 AV4 21 SGD 41 30 AV5 16 SGD 41 30 AV3 15 SGD 41 30 AV2 10 SGD 41 31 AV2 13 SGD 41 39 AV5 30 SGD 41 39 AV4 25 SGD 41 39 AV3 25 SGD 41 39 AV2 21 SGD 41 39 AV6 11 SGD 41 78 AV3 23 SGD 41 78 AV4 21 SGD 41 78 AV5 15 SGD 41 78 AV2 10 SGD 41 87 AV3 9

SGD 41 90 AVl 16 SGD 41 90 AV3 11 SGD 42 103 AV2 13 SGD 43 20 AV6 10 SGD 43 25 AV5 10 SGD 43 33 AV3 13 SGD 43 95 AV5 16 SGD 43 95 AV4 11 SGD 43 100 AV4 20 SGD 43 100 AV6 11 SGD 43 100 AV5 11 SGD 43 102 AV6 12 SGD 43 102 AV5 14 SGD 44 21 AV1 13 SGD 45 22 AV6 12 SGD 45 41 AV3 18 SGD 45 47 AV6 12 SGD 45 96 AV3 12 SGD 45 96 AV2 11 SGD 47 24 AV1 11 SGD 47 96 AV5 15 SGD 47 98 AV5 12 SGD 48 25 AV6 10

.SG Row SGD

• 48 SGD 49 SGD 49 SGD 49 SGD 49 SGD 49 SGD 49 SGD 49 SGD 49 SGD 49 SGD 49 SGD 49 SGD 49 SGD 49 SGD 49 SGD 49 SGD 50 SGD 50 SGD 50 SGD 50 SGD 50 SGD 51 SGD 52 SGD 52 SGD 52 SGD 52 SGD 52 SGD 52 SGD 52 SGD 52 SGD 52 SGD 53 SGD 53 SGD 53 SGD 53 SGD 53 SGD 54 SGD 54 SGD 54 SGD 54 Serial No.16-222 Docket No. 50-423, Page 12 of 14 Col AVB

%TW 96 AV5 18 62 AV3 30 62 AV2 23 62 AVl 20 62 AV4 16 66 AV2 32 66 AV3 17 66 AVl 14 67 AV2 25 67 AV3 23 69 AV2 9

70 AV2 14 86 AV3 11 95 AV2 20 95 AV3 19 95 AV4 16 28 AV6 11 80 AV3 13 80 AV2 11 83 AV2 20 83 AV3 10 89 AV6 14 33 AV5 11 67 AV4 20 67 AV5 17 69 AV2 13 87 AV5 15 87 AV6 16 88 AV4 17 88 AV2 16 88 AV1 12 33 AV6 15 35 AV5 18 35 AV6 13 35 AV4 12 70 AV2 13 49 AV3 23 49 AV2 16 49 AV4 12 87 AV1 13

-SG.

... R()W C:<ll -

.. AVB.* -. %TW..

SGD 55 40 AV6 21 SGD 55 75 AV6 19 SGD 55 84 AV5 25

• ~q

-~()W SGD 55 SGD 56 SGD 58 Serial No.16-222 Docket No. 50-423, Page 13of14

. Col.

'AVB

%TW*:.

84 AV6 10 43 AVl 11 59 AVl 11

Table 8 Serial No.16-222 Docket No. 50-423, Page 14 of 14 AVB Wear Lisi:ings, Steam Generator D-New Indications SG Row Col AVB

%TW SGD 24 117 AV1 20 SGD 25 93 AV5 10 SGD 25 115 AV1 10 SGD 26 115 AV1 15 SGD 26 116 AV1 10 SGD 27 115 AV1 17 SGD 27 115 AV6 13 SGD 36 34 AV2 11 SGD 36 88 AV2 12 SGD 36 88 AV3 11 SGD 36 88 AV5 11 SGD 38 95 AV5 14 SGD 40 102 AV2 10 SGD 42 19 AV5 16 SGD 45 41 AV4 11 SGD 45 92 AV2 12 SGD 45 96 AV5 11 SGD 48 94 AV6 14 SGD 49

.67 AV4 12 SGD 50 83 AV1 16 SGD 50 90 AV1 13 SGD 51 87 AV5 12 SGD 52 67 AV3 10 SGD 52 8.8 AV3 11 SGD 53 34 AV6 12 SGD 53 36 AV6 10

ENCLOSURE 2 ACRONYMS MILLSTONE POWER STATION UNIT 3 DOMINION NUCLEAR CONNECTICUT, INC. (DNC)

Serial No.16-222 Docket No. 50-423

Acronyms AVB Anti-Vibration Bar OVR BET Bottom of the Expansion Transition OXP BLG Bulge PID c

Column PLG CL Cold Leg PLP DDH Ding or Dent Signal - Reviewed in PTE History PWR DDI Distorted Dent or Ding Indication PWSCC DDS Ding or Dent Signal - Non*-

Confirming w/RPC R

DNG Ding RAD DNT Dent Indication RBD ECT Eddy Current Test RIC EFPY Effective Full Power Years RRT EPRI Electric Power Research Institute S/N ETSS Examination Technique SAi Specification Sheet sec F/L Full Length SCI FAC Flow Accelerated Corrosion SG FDB Flow Distribution Baffle SLG FO Foreign Object SSI FOTS Foreign Object Tracking System SVI HL Hot Leg TEC IGA lntergranular Attack TEH INF Indication Not Found TFH INR Indication Not Reportable LPI Loose Part Indication TFS LPR Loose Part Removed LPS Loose Part Signal TSC MRPC Motorized Rotating Pancake Coil TSH NDD No Detectable Degradation TSP NDE Nondestructive Examination TTS NDF No Degradation Found TWD NEI Nuclear Energy Institute*

%TW NOH Non-quantifiable Indication -

VOL Reviewed in History NQI Non-quantifiable Indication OA Operational Assessment ODS CC Outer Diameter Stress Corrosion Cracking Serial No.16-222 Docket No. 50-423, Page 1 of 1 Above Tubesheet Over Expansion Over Expansion Positive Identification Tube is plugged Possible Loose Part Partial Tubesheet Expansion Pressurized Water Reactor Primary Water Stress Corrosion Cracking Row Retest Analyst Discretion Retest - Bad Data Retest - Incomplete Retest-Restricted Tube Signal-to-Noise Ratio Single Axial Indication Stress Corrosion Cracking Single Circumferential Indication Steam Generator Sludge Secondary Side Inspection Single Volumetric Indication Tube End Cold Leg Tube End Hot Leg Tangential Flaw-Like Signal - Reviewed in History Tangential Flaw-Like Signal - Non-Confirming w/RPC Top of Tubesheet Cold Leg Top of Tubesheet Hot Leg Tube Support Plate

_, Top of Tubesheet Through-Wall Depth Percent Through-Wall Volumetric Indication