ML16222A351

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Submittal of End of Cycle 17 Steam Generator Tube Inspection Report
ML16222A351
Person / Time
Site: Millstone Dominion icon.png
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)
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Text

Dominion Nuclear Connecticut, Inc.

Rope Ferry Rd., Waterford, CT 06385 AUG .0 2 2016 Mailing Addre~.~: P.O. Box 128 Waterford, CT 06385 dam.com U. S. Nuclear Regulatory Commission Serial No.16-222 Attention: Document Control Desk NSS&L/MLC RO Washington, DC 20555 Docket No. 50-423 License No. NPF-49 DOMINION NUCllEAR CONNECT~ClllT, !NC.

MlllSTONE POWER STAT~ON lllNiT 3

!END OF CYCClE 17 STEAM GENERATOR TlllBE iNSPECTiON REPORT 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

Serial No.16-222 Docket No. 50-423 ENCLOSURE1 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 Enclosure 1, 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. Enclosure 2 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 Enclosure 1, 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.

Serial No.16-222 Docket No. 50-423 Enclosure 1, Page 3 of 14

b. Degradation mechanism's found, 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 Enclosure 1, 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.

Serial No.16-222 Docket No. 50-423 Enclosure 1, Page 5 of 14 Table 1 ECT Examiriation Summary for 3R17 SGA SG B SGC SG D Total Number of Tubes lnservice at start of 3R17 5577 5601 5604 5535 22317 Number of Tubes Inspected F/L w/Bobbin Probe N/A 4518 N/A 4452 8970 Number of Tubes Inspected w/Bobbin Probe Hot Leg Straights N/A 1083 N/A 1083 2166 (Rows 1 throuqh 9)

Number of Tubes Inspected w/Bobbin Probe Cold Leg Candy Canes N/A 840 N/A 845 1685 (Rows 3 throuqh 9)

Number of Tubes Inspected w/Bobbin Probe Cold Leg Straights N/A 243 N/A 238 481 (Rows 1 and 2)

Previously Pluaaed Tubes 49 25 22 91 187 Number of Tubes Incomplete w/Bobbin Probe due to Obstruction N/A 0 N/A 0 0 Number of Examinations w/MRPC (Total):j: N/A 533 N/A 459 992 o Row 1 and 2 U-Bends N/A 240 N/A 224 464

" Hot Leg Misc. Special Interest - Diagnostic Exams and from N/A 222 N/A 192 414 Previous History o Cold Leg Misc. Special Interest - Diagnostic Exams and from N/A 24 N/A 16 40 Previous Historv o U-bend. Special Interest - Diagnostic Exams and from N/A 5 N/A 11 16 Previous History

  • Other Extent-Based Exams (e.q., foreiqn object boundinq) N/A 42 N/A 16 58 Number of Examinations w/ARRAY (Total) N/A 6356 N/A 6320 12676
  • Hot Leq Tubesheet (Baffle Plate)* N/A 4362 N/A 4290 8652
  • Hot Leq Tubesheet (Non-Baffle)* N/A 1239 N/A 1245 2484
  • Cold Leo Tubesheet (Baffle Plate)* N/A 632 N/A 631 1263

. Cold Leo Tubesheet (Non-Baffle)* N/A 120 N/A 121 241

  • Foreiqn Object Wear Boundinq N/A 0 N/A 17 17
  • Row 1 and 2 U-Bends N/A 3 16**** 19
  • Hot Leg OXP/OVR Array Exam Sample Size ** N/A 100% N/A 100% 100%

.. Cold Leq OXP/OVR Arrav Exam Sample Size ** N/A 21% N/A 19% 20%

Tubes w/ Max AVB Wear> 40 % *** N/A 0 N/A 0 0 Tubes w/ Max AVB Wear >20% but <40% *** N/A 12 N/A 23 35 Tubes w/ Max AVB Wear <20% *** N/A 42 N/A 77 119 Tubes w/ Max TSP Wear> 40 % N/A 0 N/A 0 0 Tubes w/ Max TSP Wear >20% but <40% N/A 0 N/A 2 2 Tubes w/ Max TSP Wear <20% N/A 2 N/A 0 2 Tubes w/ Max Non-Structure Vol. Deg. > 40 % N/A 0 N/A 0 0 Tubes w/ Max Non-Structure Vol. Deg. >20% but <40% N/A 7 N/A 6 13 Tubes w/ Max Non-Structure Vol. Deg. <20% N/A 1 N/A 1 2 Total Tubes Pluaaed as a Result of this Inspection: N/A 0 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.

Serial No.16-222 Docket No. 50-423 Enclosure 1, Page 6 of 14 Table 2 Degradation Mechanisms and Inspection Techniques Degradation Classification Mechanism Location Probe Type Existing Tube Wear Anti-Vibration Bars Bobbin - Detection and Sizing Bobbin - Detection Existing Tube Wear Tube Support Plate

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

Tube Wear Existing Freespan and TIS Detection (foreign objects)

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

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

+Point' - Sizing ODSCG Hot Leg Top-of-Tubesheet Array - Detection Potential PWSGG and Sludge Region +Point' - Detection and Sizing Bulges, Dents, Manufacturing Array - Detection ODSGG Anomalies, and Above-Potential +Point' - Detection and Sizing PWSGG Tubesheet Overexpansions (OVR)

Array - Detection Tubesheet Potential PWSGG +Point' - Detection and Sizing Overexpansions (OXP)

ODSGG Array - Detection Potential Row 1 and 2 U-bends PWSGG +Point' - Detection and Sizing Potential FAG Moisture Separators Visual Inspection Plug Installation Potential Plugs Visual Inspection Problems Potential Tube Slippage Within Tubesheet Bobbin Detection

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

Serial No.16-222 Docket No. 50-423 Enclosure 1, Page 7 of 14 Table 3 3R17 Volumetric Degradation Summary SG B (Excludes AVB Wear)

Maximum foreign Object Row Col Location Depth 3R17 Signal History Comment Cause Plugged?

!Remaining?

(%TW)

No signal change since 1 37 03C + 0.33" 14 TSP Wear NA No previous inspection No signal change since 30 52 05H -0.58" 13 TSP Wear NA No previous inspection No signal change since 1 119 TSC + 3.84" 30 Foreign Object No No previous inspection No signal change since 1 120 TSC + 3.85" 23 Foreign Object No No previous inspection No signal change since 1 121 TSC + 6.40" 9 Foreign Object No No previous inspection No signal change since 15 99 03H - 0.65" 32 Foreign Object No No previous inspection No signal change since 29 65 08C - 0.81" 28 Foreign Object No No previous inspection No signal change since 29 109 04H - 0.53" 25 Foreign Object No No previous inspection

  • 30 No signal change since 32 06H - 1.00" 37 Foreign Object No No previous inspection 44 98 02H + 15.81" 21 Present in Baseline Fabrication NA No

Serial No.16-222 Docket No. 50-423 Enclosure 1, Page 8 of 14 Table 4: 3R17 Volumetric Degradation Summary SG D (Excludes AVB Weaur)

Maximum Foreign Object Row Col Location Depth 3R17 Signal History Comment Cause Plugged?

Remaining?

(%TW)

Small signal present in 17 24 07C- 0.67" 31 TSP Wear NA No previous inspection No signal change since 35 73 04H - 0.48" 22 TSP Wear NA No previous inspection No signal change since 24 89 06C - 0.74" 21 Foreign Object No No previous inspection No signal change since 27 39 08C- 0.90" 27 Foreign Object No No previous inspection No signal change since 46 99 01H + 0.51" 26 Foreign Object No No previous inspection No signal change since 52 42 01 H + 0.57" 24 Foreign Object No No previous inspection No signal change since 52 91 01H + 2.47" 31 Foreign Object No No previous inspection No signal change since 58 50 01C + 0.42" 17 Foreign Object No No previous inspection ... - ---*- *-

No signal change since 58 51 01C + 0.55" 25 Foreign Object No No previous inspection

Serial No.16-222 Docket No. 50-423 Enclosure 1, Page 9 of 14 Table 5 AVB Wear Listings, Steam Generator B- Repeat Indications SG Row Col AVB %TW SG Row Col AVB %TW SGB 30 12 AV5 15 SGB 40 23 AV5 13 SGB 30 12 AV2 11 SGB 40 23 AV4 12 SGB 32 108 AV4 14 SGB 40 23 AV2 12 SGB 33 12 AV5 17 SGB 40 23 AV3 11 SGB 33 12 AV2 15 SGB 40 24 AV4 18 SGB 33 39 AV3 10 SGB 40 24 AV3 17 SGB 33 109 AV3 18 SGB 40 24 AV5 12 SGB 33 109 AV2 13 SGB 41 34 AV4 33 SGB 33 109 AV6 8 SGB 41 34 AV5 31 SGB 34 18 AV4 8 SGB 41 34 AV3

  • 15 SGB 34 18 AV3 9 SGB 41 34 AV2 16 SGB 34 109 AV3 19 SGB 41 34 AV6 12 I

SGB 34 109 AV5 13 SGB 41 50 AV4 27 SGB 34 109 AV6 8 SGB 41 50 AV3 16 SGB 34 109 AV2 9 SGB 41 69 AV5 30 SGB 34 110 AV3 10 SGB 41 69 AV4 17 SGB 35 103 AV6 7 SGB 41 69 AV3 10 SGB 35 106 AV4 15 SGB 41 77 AV5 20 SGB 35 106 AV6 9 SGB 41 77 AV3 14 SGB 35 106 AV3 10 SGB 41 77 AV4 14 SGB 36 22 AV6 9 SGB 42 19 AVl 10 SGB 36 39 AV5 18 SGB 42 21 AV5 25 SGB 36 39 AV6 13 SGB 42 21 AV4 21 SGB 36 39 AV3 11 SGB 42 21 AV2 15 SGB 36 39 AV2 10 SGB 42 21 AV6 14 SGB 36 67 AV6 8 SGB 42 21 AV3 11 SGB 37 100 AV4 11 SGB 42 33 AV2 13 SGB 37 103 AV2 10 SGB 42 96 AV2 20 SGB 37 104 AV3 13 SGB 42 96 AV4 12 SGB 37 104 AV4 10 SGB 42 96 AV3 13 SGB 38 104 AV4 23 SGB 42 96 AV5 9

. SGB 38 104 AV3 13 SGB 42 98 AV2 30 SGB 38 104 AV5 11 SGB 42 98 AV3 31 SGB 39 30 AV2 11 SGB 42 98 AV5 10 SGB 39 30 AV5 10 SGB 43 86 AV4 10 SGB 39 30 AV4 10 SGB 43 100 AV4 26 SGB 39 96 AV3 11 SGB 43 100 AV3 22

Serial No.16-222 Docket No. 50-423 Enclosure 1, Page 10 of 14 SG Row Col AVB %TW SG Row Col AVB %TW SGB 43 100 AV6 10 SGB Sl 91 AV4 11 SGB 4S 22 AV6 10 SGB Sl 91 AV6 9 SGB 46 99 AV4 12 SGB S4 3S AVS 13 SGB 48 2S AV6 7 SGB S4 3S AV2 12 SGB 49 27 AVl 11 SGB S4 3S AV4 10 SGB 49 27 AVS 13 SGB S4 3S AV6 10 SGB 49 27 AV2 10 SGB 54 36 AV5 31 SGB so 29 AV2 18 SGB 54 36 AV6 15 SGB so 29 AV6 12 SGB 54 45 AV2 10 SGB so 72 AV3 13 SGB 56 41 AV3 9 SGB so 88 AV3 22 SGB 56 42 AV6 11 SGB so 88 AV2 18 SGB 56 71 AV2 10 SGB so 88 AV4 16 SGB 56 81 AVl 11 SGB so 88 AVS 12 SGB 57 70 AV2 11 SGB so 88 AV6 7 SGB 58 75 AV5 21 SGB Sl 91 AVS lS SGB 59 65 AV2 13 Table 6 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

Serial No.16-222 Docket No. 50-423 Enclosure 1, Page 11 of 14 Table 7 AVB Wear Listings, Steam Generator D- Repeat Indications SG Row Col AVB * %TW SG Row ' -

. Co!* AVB %TW SGD 9 121 AV6 13 SGD 37 103 AV5 15 SGD 23 10 AV6 10 SGD 37 103 AV2 12 SGD 26 8 AV6 .15 SGD 37 103 AV3 11 SGD 28 8 AV6 14 SGD 37 106 AV4 33 SGD 28 8 AVl 13 SGD 37 106 AV5 24 SGD 28 114 AV2 29 SGD 37 106 AV3 23 SGD 28 114 AV5 11 SGD 37 106 AV6 16 SGD 29 113 AV2 17 SGD 37 106 AVl 13 SGD 29 113 AV5 17 SGD 38 21 AV5 13 SGD 30 113 AV2 ,13 SGD 38 21 AV6 8 SGD 30 114 AV6 22 SGD 38 98 AV4 17 SGD 30 114 AVl 11 SGD 38 98 AV2 12 SGD 31 99 AV2 10 SGD 40 32 AV2 13 SGD 31 99 AV5 11 SGD 40 99 AV5 31 SGD 31 99 AV6 10 SGD 40 99 AV4 28 SGD 32 112 AV5 11 SGD 40 99 AV2 14 SGD 33 86 AV3 11 SGD 40 99 AV3 10 SGD 33 86 AV4 14 SGD 40 100 AV4 15 SGD 33 109 AV5 20 SGD 40 100 AV6 14 SGD 33 109 AV2 12 SGD 40 100 AV5 18 SGD 34 109 AV2 12 SGD 40 101 AV3 16 SGD 35 99 AV5 13 SGD 40 101 AV5 14 SGD 35 99 AV2 13 SGD 40 101 AV6 11 SGD 35 102 AV5 15 SGD 40 101 AV4 12 SGD 35 ' 103 AV5 16 SGD 40 102 AV4 25 SGD 35 107 AV4 10 SGD 40 102 AV5 19 SGD 35 108 AV3 15 SGD 40 102 AV3 14 SGD 35 108 AV4 11 SGD 40 102 AV6 10 SGD 35 109 AV4 16 SGD 40 103 AV4 35 SGD 35 109 AV5 10 SGD 40 103 AV5 29 SGD 36 82 AV3 13 SGD 40 103 AV3 27 SGD 36 97 AV2 12 SGD 40 103 AV2 22 SGD 37 93 AV3 18 SGD 40 103 AV6 17 SGD 37 93 AV2 13 SGD 40 103 AVl 15 SGD 37 101 AV2 20 SGD 41 26 AV6 32 SGD 37 101 AV3 15 SGD 41 26 AV5 32 SGD 37 101 AV4 14 SGD 41 26 AV2 17

Serial No.16-222 Docket No. 50-423 Enclosure 1, Page 12 of 14 SG Row tol AVB %TW. .SG Row Col AVB %TW SGD 41 29 AV4 11 SGD

  • 48 96 AV5 18 SGD 41 29 AV6 9 SGD 49 62 AV3 30 SGD 41 30 AV4 21 SGD 49 62 AV2 23 SGD 41 30 AV5 16 SGD 49 62 AVl 20 SGD 41 30 AV3 15 SGD 49 62 AV4 16 SGD 41 30 AV2 10 SGD 49 66 AV2 32 SGD 41 31 AV2 13 SGD 49 66 AV3 17 SGD 41 39 AV5 30 SGD 49 66 AVl 14 SGD 41 39 AV4 25 SGD 49 67 AV2 25 SGD 41 39 AV3 25 SGD 49 67 AV3 23 SGD 41 39 AV2 21 SGD 49 69 AV2 9 SGD 41 39 AV6 11 SGD 49 70 AV2 14 SGD 41 78 AV3 23 SGD 49 86 AV3 11 SGD 41 78 AV4 21 SGD 49 95 AV2 20 SGD 41 78 AV5 15 SGD 49 95 AV3 19 SGD 41 78 AV2 10 SGD 49 95 AV4 16 SGD 41 87 AV3 9 SGD 50 28 AV6 11 SGD 41 90 AVl 16 SGD 50 80 AV3 13 SGD 41 90 AV3 11 SGD 50 80 AV2 11 SGD 42 103 AV2 13 SGD 50 83 AV2 20 SGD 43 20 AV6 10 SGD 50 83 AV3 10 SGD 43 25 AV5 10 SGD 51 89 AV6 14 SGD 43 33 AV3 13 SGD 52 33 AV5 11 SGD 43 95 AV5 16 SGD 52 67 AV4 20 SGD 43 95 AV4 11 SGD 52 67 AV5 17 SGD 43 100 AV4 20 SGD 52 69 AV2 13 SGD 43 100 AV6 11 SGD 52 87 AV5 15 SGD 43 100 AV5 11 SGD 52 87 AV6 16 SGD 43 102 AV6 12 SGD 52 88 AV4 17 SGD 43 102 AV5 14 SGD 52 88 AV2 16 SGD 44 21 AV1 13 SGD 52 88 AV1 12 SGD 45 22 AV6 12 SGD 53 33 AV6 15 SGD 45 41 AV3 18 SGD 53 35 AV5 18 SGD 45 47 AV6 12 SGD 53 35 AV6 13 SGD 45 96 AV3 12 SGD 53 35 AV4 12 SGD 45 96 AV2 11 SGD 53 70 AV2 13 SGD 47 24 AV1 11 SGD 54 49 AV3 23 SGD 47 96 AV5 15 SGD 54 49 AV2 16 SGD 47 98 AV5 12 SGD 54 49 AV4 12 SGD 48 25 AV6 10 SGD 54 87 AV1 13

Serial No.16-222 Docket No. 50-423 Enclosure 1, Page 13of14

-SG. .. .R()W C:<ll - . .AVB.* - . %TW.. *~q -~()W . Col. 'AVB %TW*: .

SGD 55 40 AV6 21 SGD 55 84 AV6 10 SGD 55 75 AV6 19 SGD 56 43 AVl 11 SGD 55 84 AV5 25 SGD 58 59 AVl 11

Serial No.16-222 Docket No. 50-423 Enclosure 1, Page 14 of 14 Table 8 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

Serial No.16-222 Docket No. 50-423 ENCLOSURE 2 ACRONYMS MILLSTONE POWER STATION UNIT 3 DOMINION NUCLEAR CONNECTICUT, INC. (DNC)

Serial No.16-222 Docket No. 50-423 Enclosure 2, Page 1 of 1 Acronyms AVB Anti-Vibration Bar OVR Above Tubesheet Over Expansion BET Bottom of the Expansion Transition OXP Over Expansion BLG Bulge PID Positive Identification c Column PLG Tube is plugged CL Cold Leg PLP Possible Loose Part DDH Ding or Dent Signal - Reviewed in PTE Partial Tubesheet Expansion History PWR Pressurized Water Reactor DDI Distorted Dent or Ding Indication PWSCC Primary Water Stress Corrosion DDS Ding or Dent Signal - Non*- Cracking Confirming w/RPC R Row DNG Ding RAD Retest Analyst Discretion DNT Dent Indication RBD Retest - Bad Data ECT Eddy Current Test RIC Retest - Incomplete EFPY Effective Full Power Years RRT Retest- Restricted Tube EPRI Electric Power Research Institute S/N Signal-to-Noise Ratio ETSS Examination Technique SAi Single Axial Indication Specification Sheet F/L sec Stress Corrosion Cracking Full Length SCI Single Circumferential Indication FAC Flow Accelerated Corrosion SG Steam Generator FDB Flow Distribution Baffle SLG Sludge FO Foreign Object SSI Secondary Side Inspection FOTS Foreign Object Tracking System SVI Single Volumetric Indication HL Hot Leg TEC Tube End Cold Leg IGA lntergranular Attack TEH Tube End Hot Leg INF Indication Not Found TFH Tangential Flaw-Like Signal - Reviewed INR Indication Not Reportable in History LPI Loose Part Indication TFS Tangential Flaw-Like Signal - Non-LPR Loose Part Removed Confirming w/RPC LPS Loose Part Signal TSC Top of Tubesheet Cold Leg MRPC Motorized Rotating Pancake Coil TSH Top of Tubesheet Hot Leg NDD No Detectable Degradation TSP Tube Support Plate NDE Nondestructive Examination ' TTS _, Top of Tubesheet NDF No Degradation Found TWD Through-Wall Depth NEI Nuclear Energy Institute* %TW Percent Through-Wall NOH Non-quantifiable Indication - VOL Volumetric Indication Reviewed in History NQI Non-quantifiable Indication OA Operational Assessment ODS CC Outer Diameter Stress Corrosion Cracking

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