LR-N25-0048, Steam Generator Tube Inspection Report - Twenty-seventh Refueling Outage

Steam Generator Tube Inspection Report - Twenty-seventh Refueling Outage

ML25135A078
Person / Time
Site:	Salem
Issue date:	05/15/2025
From:	Jennings J Public Service Enterprise Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N25-0048
Download: ML25135A078 (1)

Text

Jason Jennings Director, Site Regulatory Compliance, PSEG Nuclear LLC PO Box 236 Hancocks Bridge, New Jersey 08038-0221 Technical Specification 6.9.1.10 LR-N25-0048 May 15, 2025 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Salem Generating Station, Unit 2 Renewed Facility Operating License No. DPR-75 Docket No. 50-311

Subject:

Steam Generator Tube Inspection Report - Twenty-seventh Refueling Outage PSEG Nuclear LLC (PSEG) submits an updated steam generator (SG) tube inspection report consistent with the requirements of technical specification 6.9.1.10.

Salem Unit 2 entered HOT SHUTDOWN (Mode 4) on November 23, 2024, following completion of its twenty-seventh refueling outage.

The following attachments are included in this letter:

Steam Generator Tube Inspection Report TS 6.9.1.10 Explanation of Terms (acronyms)

Salem Unit 2 SG Tube Support Arrangement and Terminology Anti-Vibration Bar (AVB) Wear Tube Support Plate (TSP) Wear All SGs %TW Wear Indication Depth Distribution 2R27 Tubes Plugged for Each Degradation Mechanism o PSEG I NUCLEAR

May 15, 2025 Page 2 LR-N25-0048 There are no regulatory commitments contained in this letter.

Please contact Mr. Harry Balian at Harry.Balian@pseg.com if you have questions.

Sincerely, Jason Jennings Director, Site Regulatory Compliance Attachments (7) cc:

USNRC Regional Administrator Region 1 USNRC NRR Project Manager - Salem USNRC Senior Resident Inspector - Salem NJ Department of Environmental Protection, Bureau of Nuclear Engineering NJ Occupational Safety and Health Bureau of Boiler and Pressure Vessel Compliance SIGN

Jennings, Jason Digitally signed by Jennings, Jason Date: 2025.05.15 08:55:53 -04'00'

LR-N25-0048 Steam Generator Tube Inspection Report TS 6.9.1.10

LR-N25-0048 Page 1 of 8 PSEG Nuclear LLC Salem Unit 2 Design and Operating Parameters Salem Unit 2 is a four (4) loop Westinghouse Pressurized Water Reactor (PWR) with Framatome (also known as AREVA) Model 61/19T SGs that incorporate thermally treated Inconel 690 U-tubes. These Replacement SGs (RSGs) were placed into service in 2008 which was the start of operating cycle 17. The 61 indicates approximately 6,100 square meters of heat transfer surface area per steam generator, the 19 indicates the approximate tube Outside Diameter (OD) in millimeters, and the T corresponds to a triangular tube pitch.

The RSGs incorporate state-of-the-art features designed to improve reliability and minimize degradation. The thermally treated Inconel Alloy 690 tubing has a nominal OD of 0.750 inch and nominal wall thickness of 0.043 inch. Industry experience and laboratory testing has shown thermally treated Inconel Alloy 690 to be far more resistant to cracking than the Inconel Alloy 600 tubing found in the original SGs. There are 5048 tubes within each SG fabricated in a triangular pitch. The tubes are hydraulically expanded the full tubesheet depth and seal welded at the tubesheet primary face. Lateral tube bundle support is accomplished using eight, 410 Stainless Steel (SS) broached Tube Support Plates (TSP). The TSP holes are of a trefoil design with flat lands.

The U-bends are supported with 3 sets of Anti-Vibration Bars (AVBs) bent into a V shape.

Since a given tube will intersect the same AVB at two separate locations, the AVBs are labeled AV1 through AV6 to segregate the separate Hot-Leg (HL) and Cold-Leg (CL) intersections. AV1 is near the upper hot leg TSP, and AV6 is near the upper cold leg TSP. The first 16 rows of tubes have been thermally stressed relieved after the bending process to further reduce residual stresses in the U-bend region. A loose parts trapping screen system in installed in each of the SG upper secondary side internals, near the top of the downcomer. See Appendix B, for a general summary of the Tube Support Arrangement and Terminology.

At the time of the 2R27 SG inspection outage, the SGs accumulated a total of approximately 14.87 Effective Full Power Years (EFPY) of operation. Prior to 2R27, all 4 SGs were also inspected in refueling outage 2R22 (spring 2017). Between refueling outage 2R22 and 2R27 the SGs were operated approximately 82.356 Effective Full Power Months (EFPM), with a reactor coolant hot leg temperature of approximately 607 degrees Fahrenheit.

PSEG Nuclear LLC has no deviations for Salem Unit 2 of Mandatory or Needed (shall) requirements important to tube integrity from the EPRI Guidelines referenced by NEI 97-06. SG inspections were performed in accordance with TS 6.8.4.i, Steam Generator Program, during

LR-N25-0048 Page 2 of 8 refueling outage 2R27. Each reporting requirement of Technical Specification (TS) 6.9.1.10 is addressed below.

a. Technical Specification 6.9.1.10.a, The scope of inspections performed on each SG The 2R27 work scope included primary side Eddy Current (ECT) and visual inspections, and secondary side visual inspections. ECT examinations were performed on the in-service tubes. If not stated otherwise, the following inspections were performed on all four steam generators:

Bobbin Probe A full-length (tube end to tube end) bobbin coil probe inspection was performed on 100% of the in-service tubes.

Array Probe Tubesheet Periphery & No-Tube Lane (NTL): 3-tube deep followed by alternating columns extending approximately 10-tubes deep from the periphery. The NTL is limited to 3-tubes deep from columns 14 to 114.

Historical and newly identified foreign object items (affected/bounding tubes).

All in-service SPT (Appui) locations (6 Appui locations per tube) and in-service tubes adjacent to SPT (Appui) locations (6 Appui locations per tube).

Special Interest inspections including all PRX and BLG indications, all 2R27 bobbin TSP wear indications, select AVB wear indications for additional profile data, and deposit mapping.

Primary Side Visual Inspections All in-service tube plugs The SG channel head bowl cladding and internal surfaces in both legs including nozzle dam rings Secondary Side Inspections Water lancing of the top-of-tubesheet (TTS) from the divider lane (i.e. no tube lane or NTL)

TTS visual inspections and Foreign Object Search and Retrieval (FOSAR):

o Full length of the no tube lane (area between row 1 tubes), a minimum of three inner bundle passes (hot leg and cold leg), and completely around the annulus tube areas (shell-to-tube bundle region, including periphery tubes).

o The annulus / periphery tubes inspection included viewing into the bundle (from the annulus region).

Visual inspections of the steam drum including steam outlet nozzles, secondary separators and drains, primary moisture separator (PMS) external and internal surfaces, feed ring and J-nozzle external surfaces, internal manways and access

LR-N25-0048 Page 3 of 8 hatches, all fasteners on feed ring inspection and camera ports, and loose part trapping screens (LPTSs) on the PMS and on the downcomer,

b. Technical Specification 6.9.1.10.b, The nondestructive examination techniques utilized for tubes with increased degradation susceptibility The array probe was used at all locations where SPT (Appui) wear is potential and at locations with proximity (PRX) and bulge (BLG) indications. No degradation was identified. See response for 6.9.1.10.c.1 below for a summary of all NDE techniques used during the inspection.

c. Technical Specification 6.9.1.10.c, For each degradation mechanism found:

1. The nondestructive examination techniques utilized; The eddy current examinations were performed utilizing various eddy current probes. All examination techniques utilized were qualified for detection and sizing of the relevant degradation mechanisms. The degradation mechanisms identified during outage 2R27 were AVB wear and TSP wear.

The degradation mechanisms found during 2R27 are identified in Table 1 along with the appropriate NDE Examination Technique Specification Sheet (ETSS) utilized for each mechanism. The inspection techniques include those for the Bobbin probe and the Array probe (X-probe) which were the only ECT probes used during 2R27. The Bobbin probe was the primary means of detecting tube degradation while the array probe was used to supplement detection of loose parts/wear located at the top of tubesheet, profiling of wear flaws of interest, and on an as-needed basis as a diagnostic tool.

Table 1: Salem Unit 2 - 2R27, Nondestructive Examination Techniques Degradation Mechanism Probe EPRI ETSS Demonstrated Applicability Extended Applicability Detection Sizing AVB & TSP Wear Bobbin I-96041.1 (Rev. 8)

AVBs None Yes Yes I-96043.4 (Rev. 1)

Single land (flat) & tapered wear at broached TSPs None Yes Yes 96004.1 (Rev. 14)

AVB & TSP Wear Detection of Sizing of Appui (SPT) Wear Yes N/A 96004.3 (Rev. 14)

None Yes Yes Array I-17909.1 (Rev. 1)

AVB (axial sensitive)

Detection of Appui wear Yes Yes I-17909.4 (Rev 1)

AVB (circ sensitive)

Yes Yes I-11956.3 (Rev 3)

TSP (axial sensitive)

Detection of PLP wear with or w/o part present Yes Yes I-11956.4 (Rev 3)

TSP (circ sensitive)

Yes Yes

LR-N25-0048 Page 4 of 8

2. The location, orientation (if linear), measured size (if available), and voltage response for each indication. For tube wear at support structures less than 20 percent through-wall, only the total number of indications needs to be reported; The degradation indications detected during outage 2R27 are AVB wear and TSP wear.

Table 2 provides a summary of the total number of wear indications as well as the number of indications less than 20 %TW identified in each SG for each mechanism.

Table 2: Salem Unit 2 - 2R27, Number of Wear Indications Indications SG 21 SG 22 SG 23 SG 24 All SGs Total AVB Wear 396 293 93 245 1027 AVB Wear < 20 %TW 348 235 82 220 885 Total TSP Wear 6

7 12 18 43 TSP Wear < 20 %TW 6

7 12 18 43 The location, size and voltage for all AVB wear indications 20 %TW are contained in. All TSP wear indications were < 20%TW; however, as there are only 43 total indications the location, size and voltage for each are provided in Attachment 5.

contains the numerical distribution by indications of flaw aggregated by all SGs categorized by %TW ranges for both AVB and TSP wear.

3. A description of the condition monitoring assessment and results, including the margin to the tube integrity performance criteria and comparison with the margin predicted to exist at the inspection by the previous forward-looking tube integrity assessment; The largest depth of degradation detected during 2R27 for AVB wear was 32% TW, and for TSP wear was 13% TW. No SPT wear or Loose Part (Foreign Object) wear was detected during 2R27. All tubes inspected met the tube integrity performance criteria in TS 6.8.4.i.b. No tubes required in-situ pressure testing, and no tube pulls were required.

Table 3 provides a summary of 2R27 condition monitoring results along with the projections from the prior outage 2R22 OA projections confirming that all identified degradation in 2R27 was well below the 2R22 OA projections.

LR-N25-0048 Page 5 of 8 Table 3: Salem Unit 2 - Condition Monitoring Summary Degradation Mechanism CM Limit

(%TW)(1) 2R27 Maximum Depth (%TW) 2R22 OA Methodology 2R22 OA Projected Depth

(%TW) 2R22 to 2R27 AVB Wear 49.3 (1.0 length) 32 Probabilistic N/A (2)

TSP Wear 47.5 (1.5 length) 13 Deterministic 51.1 Notes for Table 3:

(1) The CM limit is based on the applicable ECT technique regression, uncertainty and flaw geometry/model using an NOPD bounding the prior inspection interval.

(2) AVB Wear Full Bundle Probabilistic model for 5-cycles of operation (starting from 2R22) resulted in a probability of burst (POB) projected to be 0.21% or less, which is well below the requirement of 5%.

4. The number of tubes plugged during the inspection outage; At 2R27, no tubes exhibited flaws with a depth equal to or exceeding 40% of nominal tube wall thickness (Technical Specification 6.9.4.i.c). To enhance the margin for a 5-cycle Operational Assessment (OA), Preventative Tube Plugging (PTP) criteria were implemented at 2R27, ensuring that performance criteria will be met for Cycles 28, 29, 30, 31, and 32. A total of 10 tubes were preventatively plugged, all for AVB wear.

All tubes plugged during 2R27 are listed in Attachment 7 along with the deepest wear indication in each tube.

d. Technical Specification 6.9.1.10.d, An analysis summary of the tube integrity conditions predicted to exist at the next scheduled inspection (the forward-looking tube integrity assessment) relative to the applicable performance criteria, including the analysis methodology, inputs, and results.

The only observed degradation mechanisms in the Salem Unit 2 SGs during the 2R27 inspection were tube wear at the AVB and TSP support locations. The Operational Assessment (OA) evaluated these degradation mechanisms to demonstrate reasonable assurance that the performance criteria for structural and leakage integrity will be met through Cycles 28, 29, 30, 31 and 32, until the next planned steam generator inspection at outage 2R32. All Bobbin and Array noise was monitored and reviewed at Regions of Interest (ROI) confirming that noise was not masking any degradation and no additional inspections were required at 2R27 to support the OA.

LR-N25-0048 Page 6 of 8 For all degradation mechanisms, a conservative NOPD and a conservative inspection interval of 8.0 EFPY (96 EFPM) was assumed, covering the anticipated duration of Cycles 28 through 32 of 7.058 EFPY. This also represents the maximum allowed operating interval between SG inspections consistent with Salem Unit 2 Technical Specification 6.8.4.i which has incorporated TSTF-577.

A full bundle probabilistic model for AVB Wear results in a Probability of Burst (POB) of 0.4% or less, and well less than the requirement of 5%. A deterministic analysis was provided for TSP wear. For TSP wear, a conservative Beginning-of-Cycle (BOC) flaw size of 13 %TW (equal to the largest return to service TSP wear indication) with a conservatively assumed growth/wear rate of 3.62 %TW per EFPY (for 8.0 EFPY), results in a bounding projected flaw size of 50.47 %TW which is below a conservative structural depth of 51.4 %TW, for a flaw length of 1.5 inches.

Table 4 provides a summary of the OA evaluation results for each degradation mechanism found in outage 2R27, which provide reasonable assurance the performance criteria will not be challenged over the planned 5-cycle inspection interval.

Table 4: Salem Unit 2 - Operational Assessment Summary Degradation Mechanism OA Methodology OA Structural Limit (1)

OA Projected Depth

(%TW) 2R27 to 2R32 AVB Wear Probabilistic 0.05 POB (2)

N/A (2)

TSP Wear Deterministic 51.4 (1.5 length) 50.5 (3)

Notes for Table 4:

(1) The structural limit is based on the applicable flaw geometry/model without any ECT uncertainty using an NOPD bounding the inspection interval.

(2) AVB Wear Full Bundle Probabilistic model for 5-cycles of operation over 8.0 EFPY (starting from 2R27) provides probability of survival (POS) of 0.996, 0.997, 0.999, and 0.997 for SG 21 to 24, respectively. Meaning the probability of burst (POB) was projected to be 0.4% or less (i.e. - POB = (1 - POS) x 100), which is well below the requirement of 5%.

(3) Deterministic OA projected depths for TSP wear assumes very conservative wear rate bounding the maximum observed at Salem-2 and a 5-cycle inspection interval of 8.0 EFPY bounding projected interval length of 7.058 EFPY.

e. Technical Specification 6.9.1.10.e, The number and percentage of tubes plugged to date, and the effective plugging percentage in each SG.

Table 5 provides the total number and percentage of tubes plugged to date in each steam generator. All tubes plugged during 2R27 are listed in Attachment 8.

LR-N25-0048 Page 7 of 8 Table 5: Salem Unit 2 - 2R27, Historical Tube Plugging Status Outage Steam Generator Total SG 21 SG 22 SG 23 SG 24 Pre-Service 0

0 0

0 0

2R17 1

3 1

5 10 2R18 2

5 1

8 16 2R19 29 23 0

20 72 2R20 56 34 6

37 133 2R22 4

3 5

2 14 2R27 3

6 1

0 10 Total Tubes Plugged 95 74 14 72 255 Total Percentage 1.88 1.47 0.28 1.43 1.26

f. Technical Specification 6.9.1.10.f, The results of any SG secondary side inspections In each SG, following Top of Tubesheet (TTS) water lancing (sludge lancing), visual inspections and Foreign Object Search and Retrieval (FOSAR) were performed. These inspections included the full length of the no tube lane (area between row 1 tubes), some inner bundle inspections (both HL and CL), and around the annulus tube areas (shell-to-tube bundle region, including periphery tubes). The annulus / periphery tubes inspection included view into the bundle (from the annulus region) allowing inspection between the periphery tubes into the bundle.

The purpose of these inspections was to identify and remove foreign material and to assess the effectiveness of the water lancing. Visual inspections of the SGs TTS showed that water lancing was successful in removing most of the TTS deposits (sludge, hard deposits, and foreign material). Approximately 321 pounds of sludge was removed from all four SGs and ECT sludge mapping indicated very little change in the size of the sludge pile when compared to 2R20 and 2R22 results. No Eddy Current Possible Loose Parts (PLPs) were reported in outage 2R27 and there were no loose parts wear identified on any tube. Appendix F contains a summary of the SSI findings (FOSAR). All foreign material remaining in the SG has been evaluated and determined to be acceptable for the next five cycles.

All steam drum components, including internal fasteners for the manways and camera ports, various feed ring locations, J-nozzles inside the feed ring, moisture separator equipment, flow restrictor/steam outlet nozzles, and other internal supports, were visually inspected during 2R27 in all four SGs.

LR-N25-0048 Page 8 of 8 Loose parts observed on the Loose Parts Trapping Screens (LPTS) are generally small pieces of miscellaneous metal, gasket material, graphite gasket material, foil-like pieces, etc.). All loose parts on the LPTS were removed from all 4 SGs.

The remaining loose feed ring camera port fastener in SG 21 was successfully torqued, resolving accessibility concerns. See, Updated Steam Generator Tube Inspection Report

- Twenty-second Refueling Outage (2R22) to Reflect TSTF-577 Reporting Requirements (ADAMS Accession No. ML21305A003) for additional information. All other camera ports and manway fasteners were confirmed secure. However, loose fasteners were found on the feed ring inspection ports of all four SGs, however because of the locking mechanism the bolts and covers were retained. The original equipment manufacturer of the Salem Unit 2 replacement steam generators evaluated the condition providing the conclusion not a safety significant condition and provided guidance for the disassembly and reassembly of the covers and bolts, allowing continued plant operation. The cause(s) for the loose fasteners is being evaluated/validated by the vendor with information collected during the outage.

LR-N25-0048 Explanation of Terms

LR-N25-0048 Explanation of Terms (acronyms)

Page 1 of 2 2R27:

Salem Unit 2 Refueling Outage 27 (i.e. - the 27th refueling outage)

AVB:

Anti-Vibration Bar BET:

Bottom Expansion Transition (synonymous with BHT)

BHT:

Bottom Hydraulic Transition (synonymous with BET)

BLG:

Bulge (typically within the hydraulically expanded tubesheet per PSEG reporting requirements)

BOC:

Beginning of Cycle CL:

Cold Leg CM:

Condition Monitoring DNG:

Ding (Freespan region of the tube per PSEG reporting requirements)

DNT:

Dent (At support structures per PSEG reporting requirements)

ECT:

Eddy Current EFPM:

Effective Full Power Months EFPY:

Effective Full Power Years EOL:

End of Life EPRI:

Electric Power Research Institute EPU:

Extended Power Uprate ETL:

Expansion Transition Location (PSEG reporting requirements)

ETSS:

Examination Technique Specification Sheet FBC:

Flow Baffle Coldleg (designates the Flow Distribution Baffle Plate on the Cold Leg)

FBH:

Flow Baffle Hotleg (designates the Flow Distribution Baffle Plate on the Hot leg)

FBP:

Flow Distribution Baffle Plate (synonymous with FDB)

FDB:

Flow Distribution Baffle Plate (synonymous with FBP)

FOSAR:

Foreign Object Search and Retrieval HL:

Hot Leg LPTS:

Loose Parts Trapping System LPW:

Loose Part Wear NDE:

Non-Destructive Examination NDD:

No Degradation Detected NRC:

Nuclear Regulatory Commission NTL:

No-tube Lane OA:

Operational Assessment OD:

Outside Diameter OEM:

Original Equipment Manufacturer OEX:

Over Expansion (localized variation in tube diameter within the hydraulically

LR-N25-0048 Explanation of Terms (acronyms)

Page 2 of 2 expanded tubesheet)

OXP:

Over Expansion (a hydraulic expansion occurring above the top of tubesheet)

PLP:

Possible Loose Part POB:

Probability of Burst PTP:

Preventive Tube Plugging PWR:

Pressurized Water Reactor ROI:

Region of Interest RSG:

Replacement Steam Generator SIPC:

Structural Integrity Performance Criteria SG:

Steam Generator SPT:

Appui Support SS:

Stainless Steel TEC:

Tube End Coldleg TEH:

Tube End Hotleg TS:

Technical Specification TSC:

Tubesheet Cold Leg TSH:

Tubesheet Hot Leg TTS:

Top of Tubesheet TSP:

Tube Support Plate TW:

Through-Wall Vpp:

Volts Peak to Peak Note: Acronyms provided above are similar as provided in previous reports to the NRC and may not be needed/used in every report.

LR-N25-0048 SALEM UNIT 2 SG TUBE SUPPORT ARRANGEMENT AND TERMINOLOGY

LR-N25-0048 SALEM UNIT 2 MODEL F SG TUBE SUPPORT ARRANGEMENT AND TERMINOLOGY Page 1 of 1 Salem Unit 2 SG Tube Support Arrangement AV3 AV2 AVl 08H 07H 0GH 0SH 04H 03H 02H 0lH TSH

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LR-N25-0048 ANTI-VIBRATION BAR (AVB) WEAR

LR-N25-0048 ANTI-VIBRATION BAR (AVB) WEAR Page 1 of 4 Salem Unit 2 - 2R27, SG 21 AVB Wear Indications 20 %TW Row Col

%TW Support Volts Row Col

%TW Support Volts 67 53 20 AV4 0.48 72 70 22 AV4 0.57 70 56 20 AV4 0.47 75 67 22 AV4 0.54 71 65 20 AV3 0.47 78 62 22 AV3 0.54 72 54 20 AV3 0.46 91 59 22 AV2 0.53 72 70 20 AV3 0.46 101 59 22 AV3 0.55 78 62 20 AV2 0.46 66 48 23 AV4 0.58 78 62 20 AV4 0.47 72 64 23 AV4 0.61 83 67 20 AV4 0.48 73 65 23 AV3 0.61 84 58 20 AV4 0.48 77 57 23 AV5 0.60 84 62 20 AV4 0.45 82 74 23 AV5 0.61 98 76 20 AV2 0.47 87 65 23 AV4 0.58 58 76 21 AV5 0.52 90 56 23 AV4 0.59 67 53 21 AV3 0.49 99 65 23 AV3 0.61 68 64 21 AV4 0.52 101 59 23 AV4 0.60 69 65 21 AV3 0.51 69 61 24 AV4 0.64 72 54 21 AV4 0.49 70 56 24 AV5 0.64 77 57 21 AV3 0.53 80 60 24 AV3 0.64 82 68 21 AV4 0.53 92 58 24 AV4 0.65 84 80 21 AV5 0.49 76 60 25 AV3 0.68 91 59 21 AV4 0.52 96 60 26 AV5 0.74 92 58 21 AV3 0.52 72 64 27 AV3 0.81 99 73 21 AV3 0.50 84 58 27 AV5 0.79 58 76 22 AV4 0.54 89 57 28 AV4 0.90 66 68 22 AV4 0.56 96 60 28 AV4 0.88

LR-N25-0048 ANTI-VIBRATION BAR (AVB) WEAR Page 2 of 4 Salem Unit 2 - 2R27, SG 22 AVB Wear Indications 20 %TW Row Col

%TW Support Volts Row Col

%TW Support Volts 59 61 20 AV5 0.47 81 65 22 AV3 0.57 62 62 20 AV5 0.47 82 56 22 AV5 0.56 64 64 20 AV2 0.47 95 57 22 AV5 0.57 65 67 20 AV5 0.48 60 58 23 AV3 0.58 68 60 20 AV3 0.46 61 61 23 AV5 0.59 69 63 20 AV2 0.47 62 62 23 AV4 0.58 70 64 20 AV3 0.47 67 61 23 AV3 0.61 71 63 20 AV3 0.47 89 61 23 AV3 0.58 73 65 20 AV4 0.48 91 59 23 AV5 0.60 76 54 20 AV3 0.46 66 60 24 AV4 0.65 82 56 20 AV4 0.48 70 64 24 AV2 0.65 89 53 20 AV4 0.46 71 65 24 AV4 0.64 89 59 20 AV3 0.46 77 63 24 AV4 0.64 93 59 20 AV4 0.48 97 57 24 AV4 0.64 95 57 20 AV4 0.46 98 58 24 AV3 0.66 98 52 20 AV2 0.49 98 58 24 AV4 0.63 61 61 21 AV3 0.49 77 63 25 AV3 0.67 62 60 21 AV3 0.49 89 59 25 AV2 0.70 71 63 21 AV4 0.52 81 69 26 AV3 0.76 72 68 21 AV3 0.50 65 67 27 AV4 0.79 72 68 21 AV4 0.52 66 60 27 AV3 0.81 81 65 21 AV4 0.49 93 65 27 AV5 0.79 93 57 21 AV4 0.51 92 50 28 AV3 0.89 64 64 22 AV5 0.56 92 50 28 AV4 0.89 67 61 22 AV5 0.53 62 52 29 AV5 0.94 76 54 22 AV4 0.56 92 54 29 AV4 0.92 79 59 22 AV5 0.53 62 52 31 AV4 1.13 81 57 22 AV3 0.54 92 54 31 AV5 1.13 81 57 22 AV4 0.56 95 55 32 AV3 1.26

LR-N25-0048 ANTI-VIBRATION BAR (AVB) WEAR Page 3 of 4 Salem Unit 2 - 2R27, SG 23 AVB Wear Indications 20 %TW Row Col

%TW Support Volts 92 56 20 AV5 0.48 67 61 21 AV4 0.53 75 73 21 AV5 0.52 91 73 21 AV2 0.53 92 56 21 AV4 0.53 67 61 22 AV3 0.57 73 75 24 AV4 0.63 77 73 25 AV4 0.70 83 67 27 AV5 0.83 95 51 27 AV5 0.81 91 63 31 AV5 1.12

LR-N25-0048 ANTI-VIBRATION BAR (AVB) WEAR Page 4 of 4 Salem Unit 2 - 2R27, SG 24 AVB Wear Indications 20 %TW Row Col

%TW Support Volts 70 76 20 AV2 0.47 76 62 20 AV5 0.46 82 64 20 AV3 0.45 82 64 20 AV5 0.47 96 64 20 AV4 0.48 59 73 21 AV5 0.50 81 67 21 AV2 0.53 81 67 21 AV4 0.51 81 67 21 AV5 0.53 53 53 22 AV5 0.56 59 73 22 AV4 0.55 80 60 22 AV5 0.57 92 76 22 AV2 0.57 100 76 22 AV2 0.56 70 68 23 AV3 0.58 76 62 23 AV3 0.58 73 61 24 AV3 0.62 76 62 24 AV4 0.66 79 65 24 AV4 0.64 100 58 24 AV4 0.67 101 53 24 AV5 0.65 53 53 25 AV4 0.71 70 68 25 AV4 0.70 98 52 25 AV2 0.69 102 70 29 AV2 0.94

LR-N25-0048 TUBE SUPPORT PLATE (TSP) WEAR

LR-N25-0048 Page 1 of 1 SALEM UNIT 2 - 2R27, ALL TSP WEAR INDICATIONS SG Row Col

%TW Support Volts SG Row Col

%TW Support Volts 21 80 24 9

05H 0.11 23 1

103 11 04C 0.14 21 80 24 9

06H 0.11 23 3

75 11 05C 0.13 21 2

64 10 05C 0.1 23 97 87 11 08C 0.09 21 14 96 10 07H 0.11 23 1

87 12 05C 0.16 21 100 80 11 05H 0.13 21 1

61 13 06C 0.14 24 84 62 7

06H 0.08 24 11 53 8

05C 0.09 22 3

111 7

06C 0.09 24 98 82 9

07H 0.11 22 85 91 8

05H 0.10 24 100 78 9

07C 0.10 22 45 73 10 04C 0.15 24 1

39 10 04C 0.12 22 72 108 10 06H 0.10 24 1

65 10 06C 0.12 22 90 94 10 06C 0.09 24 2

44 10 06C 0.12 22 103 67 10 06C 0.10 24 2

44 10 07C 0.11 22 2

60 12 04C 0.13 24 5

49 10 04C 0.12 24 1

65 11 06C 0.13 23 1

97 9

05C 0.11 24 104 66 11 06C 0.12 23 53 51 9

06H 0.09 24 1

67 12 06C 0.14 23 1

23 10 04C 0.12 24 1

83 12 06C 0.15 23 15 125 10 05H 0.10 24 2

16 12 04C 0.15 23 56 116 10 05H 0.09 24 61 91 12 06H 0.16 23 97 43 10 04H 0.09 24 69 29 12 03H 0.14 23 1

9 11 05C 0.13 24 103 73 12 07H 0.14 23 1

97 11 04C 0.13 24 1

65 13 05C 0.16

LR-N25-0048 ALL SGS %TW WEAR INDICATION DEPTH DISTRIBUTION

LR-N25-0048 Page 1 of 1 Salem Unit 2 - 2R27, All SGs %TW Wear Indication Depth Distribution 421 -

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LR-N25-0048 2R27 TUBES PLUGGED FOR EACH DEGRADATION MECHANISM

LR-N25-0048 Page 1 of 1 Salem Unit 2 - 2R27 Plugged Tubes SG Row Col Reason for Plugging 21 72 64 PTP @ AV3 (27%TW) 21 84 58 PTP @ AV5 (27%TW) 21 89 57 PTP @ AV4 (28%TW) 22 62 52 PTP @ AV4 (31%TW) 22 66 60 PTP @ AV3 (27%TW) 22 81 69 PTP @ AV3 (26%TW) 22 92 50 PTP @ AV4 (28%TW) 22 92 54 PTP @ AV5 (31%TW) 22 95 55 PTP @ AV3 (32%TW) 23 91 63 PTP @ AV5 (31%TW)