RA-19-0391, Refuel 23 (C2R23) Inservice Inspection (ISI) and Steam Generator Inspection (SG-ISI) Report

Refuel 23 (C2R23) Inservice Inspection (ISI) and Steam Generator Inspection (SG-ISI) Report

ML19353A416
Person / Time
Site:	Catawba
Issue date:	12/19/2019
From:	Hare M Duke Energy Corp
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RA-19-0391
Download: ML19353A416 (36)

Text

{/.~ DUKE

~ ENERGY.

December 19, 2019 Serial: RA-19-0391 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Catawba Nuclear Station, Unit No. 2 Docket No. 50-414 / Renewed License No. NPF-52 Mandy Hare Nuclear Support Services Manager Catawba Nuclear Station Duke Energy CN03CH I 4800 Concord Rd Yori<, SC 29745 803.701.2218 Mandy.Hare@duke-energy com

Subject:

Catawba Unit 2, Refuel 23 (C2R23) lnservice Inspection (ISi) and Steam Generator Inspection (SG-ISI) Report Ladies and Gentlemen:

In accordance with Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Duke Energy is providing its lnservice Inspection (ISi) Summary Report for Catawba Nuclear Station, Unit No. 2, Refuel 23 (C2R23). Also included is the Steam Generator lnservice Inspection (SG-ISI) Summary Report for Catawba Nuclear Station, Unit No.

2, Refuel 23 (C2R23). contains the C2R23 Owner's Activity Summary Report. contains the SG-ISI tube inspection report for C2R23.

This submittal contains no regulatory commitments. Should you have any questions concerning this letter, or require additional information, please contact Art Zaremba, Manager - Nuclear Fleet Licensing, at 980-373-2062.

Sincerely, Mandy Hare Nuclear Support Services Manager, Catawba Nuclear Station

U.S. Nuclear Regulatory Commission Serial: RA-19-0391 Enclosure(s):

1. Owner's Activity Summary Report For Refueling Outage 23

2. Steam Generator lnservice Inspection Report For Refueling Outage 23 NOE cc:

(w/ all enclosures)

M. Mahoney, NRC Project Manager, NRR cc:

(without SG data)

L. Dudes, NRC Regional Administrator, Region II J.D. Austin, NRC Senior Resident Inspector, Catawba Nuclear Station Page 2 RA-19-0391 Owner's Activity Summary Report for Refueling Outage 23

DUKE ENERGY INSERVICE INSPECTION

SUMMARY

REPORT UNIT 2 CATAWBA FALL 2019 REFUELING OUTAGE Originated By:

Checked By:

Approved By:

C2R23 (Outage 3)

Location: 4800 Concord Road, York, SC, 29745 NRC Docket No. 50-414 Commercial Service Date: August 19, 1986 Owner: Duke Energy 526 South Church St.

Charlotte, NC 28201-1006 Revision 0

~~{?~

Austin C. Keller

~

enniferSmith

. Pyne Date Date Date I~ Lil l°t 1 I 12--\\i' ].;l)\\1

z/4}49 7

CASE N-532-5 FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number ________

O_w_ne_r_*s_A_ct_iv_it_y_R_e~p~o_rt_fo_r_R_e_f_ue_l_in~g~O_u_ta~g~e_C_2_R_2_3 ______ _

Plant Unit No.

Catawba Nuclear Station, 4800 Concord Road, York, SC 29745 2

Commercial service date August 19, 1986 Refueling outage no. _;;;;.C~2R2'-=3=-----

(ff applicable)

Current inspection interval Fourth Inspection Interval (ISi), Third Inspection Interval (Containment ISi)

(1st 2nd. 3rd, 41h, other)

Current inspection period Second Inspection Period (ISi and Containment ISi)

(1,t, 2nd. 3rd)

Edition and Addenda of Section XI applicable to the inspection plans ASME Section XI 2007 Edition through 2008 Addenda Date and revision of inspection plans See Attachment - Page 2 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans Same as above Code Cases used for inspection and evaluation:

The following Code Cases are permitted by the ISi Plan and Addenda:

4th Interval: N-513-3, N-532-5, N-586-1, N-600, N-613-1, N-639, N-643-2, N-648-1, N-651, N-705, N-706-1, N-712, N-716-1, N-722-1, N-729-4, N-731, N-735, N-747, N-751, N-765, N-770-2, N-771, N-776, N-786-1, N-798, N-800, N-805, N-823, N-825, & N-845

(~ applicable)

CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests meet the Inspection Plan as required by the ASME Code,Section XI; and (c) the repair/replacement activities and evaluations supporting the completion of C2R23 conform to the requirements of Section XI.

(refueling outage number)

Signed~

Austin C. Keller, ISi Program Owner Date -'--=2.=4/'--'4c..,1,-/_1.... 1 __

CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of South Carolina and employed by OneCIS Insurance Company Lynn MA have inspected the items described in this Owner's Activity Report, and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

...,.--4-::;;...:.___....;;;;;;;;!~!iil--:::=--c::::_..,;;;;:=--=---=D=--=u=-=s-=tin:..:...:.:.M:..::a:.::.lle:....:t:___ ___ commissions 15196 Al.IS, I, N, R lnspedrr'sSgmre N!llitra Ebro. Sae. Al:Mrce, a.:l6d.iga1ets Date 12/05/2019 Page 1 of 4

CASE N-532-5 Attachment Catawba Unit 2 Refueling Outage 23, lnservice Inspection Report Date and Revision of lnservice Inspection Plans:

I.

Fourth Interval lnservice Inspection Plans

1. The following documents comprise the Catawba Nuclear Station 4th Interval lnservice Inspection Plan for Unit 2 (Class 1, 2, and 3 Components):

a. Catawba Nuclear Station Unit 1 and Unit 2 - Fourth Interval lnservice Inspection Plan, Document#CISl-1462.10-0040-ISI PLAN, Rev. 4, dated 01/14/2019.

b. Fourth Interval lnservice Inspection Outage Schedule Catawba Nuclear Station Unit 2, Document #CISl-1462.10-0040-UNIT 2, Rev. 1, dated 03/14/2019.

2. The following documents comprise the Catawba Nuclear Station 4th Interval lnservice Inspection Pressure Test Plan for Unit 2:

a. Catawba Nuclear Station Units 1 and 2 Fourth Inspection Interval lnservice Inspection Pressure Test Plan, Document #CISl-1462.20.0040-PTPlan, Rev. 1, dated 07/13/2017, including the following addenda:

i. CISl-1462.20-0040-C2-PT-003 II.

Fourth Interval Augmented lnservice Inspection Plan

1. The following document comprises the Catawba Nuclear Station 4th Interval Augmented lnservice Inspection Plan and Schedule for Unit 2:

a.

Catawba Nuclear Station Units 1 and 2 - Fourth Interval Augmented lnservice Inspection Plan and Schedule, Document #CISl-1462.10.0030-AUGISI-U1&U2, Rev. 6, dated 10/21/2019.

Ill.

Third Interval Containment lnservice Inspection Plan

1.

The following document comprises the Catawba Nuclear Station 3rd Interval Containment lnservice Inspection Plan for Unit 2 (Class MC):

a. Catawba Nuclear Station Units 1 and 2 - Third Interval Containment lnservice Inspection Plan, Document#CN-ISIC3-1042-0001, Rev. 9, dated 10/21/2019.

Page 2 of 4

CASE N-532-5 TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Category and Item Description Evaluation Description Item Number Blended cut marks on CRDMs 63 and

74. This area was evaluated by N/A Reactor Vessel Head CRDMs 63 and 7 4 Engineering and found to be acceptable. Reference NCR

1. 02293548-03.

Boric acid residue found during ISi Pressure Areas identified in NCR #02295850 8-P / 815.10 were evaluated by Engineering and Test Zone, 2NC-001 L-A found to be acceptable.

Boric acid residue found on mechanical joint Areas identified in NCR #02293967 C-H / C7.10 2ND-50 MJ-1 were evaluated by Engineering and (Class B Bolted Connection - IWA-5241 (f))

found to be acceptable.

Boric acid residue found on mechanical joint Areas identified in NCR #02293637 2ND-21 MJ-1 and the bolted connection of 28 C-H / C7.10 ND Heat Exchanger were evaluated by Engineering and (Class B Bolted Connections - IWA-5241(f))

found to be acceptable.

Boric acid residue found on mechanical joints Areas identified in NCR #02293254 2ND-14 MJ-1, 2ND-14 MJ-2, 2ND-28 MJ-2, C-H / C7.10 2ND-47 MJ-1, and 2ND-51 MJ-1 were evaluated by Engineering and (Class B Bolted Connections - IWA-5241 (f))

found to be acceptable.

Boric acid residue found during ISi Pressure Areas identified in NCR #02291854 C-H / C7.10 were evaluated by Engineering and Test Zone, 2ND-001 L-8 found to be acceptable.

Boric acid residue found during ISi Pressure Areas identified in NCR #02253112 C-H / C7.10 were evaluated by Engineering and Test Zone, 2NS-001 L-8 found to be acceptable.

Boric acid residue found during ISi Pressure Area identified in NCR #02295853 was C-H / C7.10 evaluated by Engineering and found to Test Zone, 2NV-001 L-8 be acceptable.

Areas identified in NCRs #02278933, C-H / C7.10 Boric acid residue found during ISi Pressure

1. 02208956, and #02239422 were Test Zone, 2NV-006L-B evaluated by Engineering and found to be acceptable.

Boric acid residue found on bolted connection Area identified in NCR #02289318 was D-8 / D2.10 of valve 2KF-21 evaluated by Engineering and found to (Class C Bolted Connection - IWA-5241(f))

be acceptable.

Page 3 of 4

CASE N-532-5 TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Repair/

Class Item Description Description of Work Date Completed Replacement Plan Number 1

Reactor Vessel Head Weld repair cut marks 9/28/2019 20355145 CROM 67 on CROM 67 Page 4 of 4 RA-19-0391 Steam Generator lnservice Inspection Report for Refueling Outage 23

Steam Generator In-service Inspection Summary Report Catawba Nuclear Station Unit 2 EOC-23 September 2019 Location: 4800 Concord Road, York South Carolina 29745 NRC Docket No. 50-414 National Board No. 173 Commercial Service Date: August 19, 1986 Owner: Duke Energy Corporation 526 South Church St.

Charlotte, N.C. 28201-1006 Revision 0 Prepared By: Dan Mayes \\JB~.ee Date: 11/25/2019 Reviewed By: Chuck Cauthen Cf!:JL::..r.u1!J~ Date:

11/25/2019 Approved By: Etienne Fonteneau ~

Date:

11/25/2019

FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number ____

O.c.,_w_n.... e_r'""'"s_A_c_t_iv_it,._y_R_e_.p_o_rt-'--fo_r_S_t....

e"""a_m_G_e_n_e_ra_t_o_r_ln_s_.p_e_c_f_10_n_O_ut_a..,,9'"'e_E_O __ C_-_2_3 __ _

Catawba Nuclear Station, 4800 Concord Road, York, SC 29745 Plant Unit No.

2 Commercial service date 08/19/1986 Refueling outage no.

EOC-23 (ff applicable)

Current inspection interval _F_o_urt_h_ln_t_e_rv_a_l ______

...,<,.,...1*.,.t. 2=-n..,.d,-=-3,.,.d,"""

41,,..h,""'oo,,,..e""'r> ___________

Current inspection period

_S_e_co_n_d_P_e_ri_od ________

..,.,<1...,

51,..,,2-nd'"""', 3,...,d,,...) -------------

Edition and Addenda of Section XI applicable to the inspection plans 2007 Edition through 2008 Addendum Date and revision of inspection plans August 19, 2015, Revision O (Document #C-ISIG-0169.030.0040)

Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans Same as Plan Code Cases used:

N-532-5 (ff applicable)

CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests meet the Inspection Plan as required by the ASME Code,Section XI; and (c) the repair/replacement activities and evaluations supporting the completion of EOC-23 conform to the requirements of Section XI.

(refueling outage number)

Signed Date 1112s12019 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of South Carolina and employed by OneCIS Insurance Company of Lynn. MA have inspected the items described in this Owner's Activity Report, and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with th~

ection.

L-~

_.....,,......,,=====~...:::==----,;;)...... __

-!D:::.:u~s::!!ti::..!n..:.:M~a~ll'.:::e:!...t ___ Commissions 15196; Al, IS, I, N, R specto(s Signalln National Board, State, Province, and Endorsements Date 12/03/2019

Catawba Nuclear Unit 2 Form OAR-1 Owner's Activity Report Table 1 Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service Examination Category and Item Description Evaluation Description Item Number No ASME Section XI Category B-Q Steam Generator Tubing in U-Tube Design Acceptance Requirement B16.20 Exceeded (Reference Attached Inspection Report)

Catawba Nuclear Unit 2 Form OAR-1 Owner's Activity Report Table 2 Abstract of Repair/Replacement Activities Required for Continued Service Code Item Description Description of Work Date Completed Repair/ Replacement Class Plan Number Steam Generator 2A Plugged and stabilized 3 tubes 1

(2 NC HXA) via rolled plug and wire rope 10/01/2019 20291454-07 stabilizer Steam Generator 2B Plugged and stabilized 3 tubes 1

(2 NC HX B) via rolled plug and wire rope 10/01/2019 20291453-07 stabilizer Steam Generator 20 Plugged and stabilized 11 1

(2 NC HX D) tubes via rolled plug and wire 10/01/2019 20291451-07 rope stabilizer

Catawba 2 EOC23 Steam Generator Tube Inspection Report (reference Catawba technical Specification 5.6.8)

Summary of inspections and inspection results:

a) The scope of inspections performed on each SG The inspection scope for all four steam generators was as follows:

Bobbin Inspection 100%/ull length (except Row 1-5 U-bend region)

Row 1-5 hot leg straight section Row 1-5 cold leg straight section Tubes surrounding plugged tubes full length Array Inspection 100% TTS hot leg (l'EH to TSH +3'J TTS hot leg two tubes deep periphery, including the T-slot and open lane (l'EH to 0lH or 02H for the baffle cutout)

TTS cold leg two tubes deep periphery, including the T-slot and open lane (l'EC to 18C+3'J 50% Row 1-5 U-bends (includes any tubes not examined in EOC-19 or EOC-21) 0BH to 09C 20% Row 10 U-bends-0BH to 09C All tubes (12) screened as high stress (Seabrook) full length Expanded baffles at TSP 17C and lBC with extent of+/- 3" at each support plate (20% sample of expanded baffles not examined in EOC EOC-20) 50% of dents greater than or equal to 5 volts in the HL and u bend All tubes with existing tube end cracks Array Special Interest All tube locations with indication calls that required Array sizing from EOC-21 Tubes with PLP calls as well as a bounding inspection of one tube deep. For PLP indications with tube degradation bounding inspection of two tube deep Bounding inspection 2 tubes deep surrounding known foreign object locations New wear indications All bobbin I-codes New DNT calls Visual Inspection Previously installed plugs Bowl cladding inspection Foreign object search and retrieval (FOSAR) of the tubesheet in all 4 steam generators.

Photogrammetry of the area of missing stainless steel clad in SG2D hot leg

b.

Degradation mechanisms found

Degradationfound included wear at support structures; wear from foreign objects, crack like indication at and above the tube support plates and crack-like indications near the tube ends.

c.

Non-destructive examination techniques utilized for each degradation mechanism The bobbin probe was utilized for the detection of wear at support structures, frees pan locations and crack like indication at and above the tube support plates and to size wear at support structures. The array probe was used for detection of indications within the tubesheet, U-bend regions, and the 2 sigma high stress tubes. The array probe was used to size the foreign object wear. The plus point probe was used to size crack like indication at and above the tube support plates

d.

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

The complete listing for service induced indications is attached.

Tubes with anti-vibration bar wear indications SG 2A - 84 tubes/ 158 indications SG 2B - 24 tubes/36 indications SG 2C-50 tubes/75 indications SG 2D - 78 tubes/ I 13 indications Total - 236 tubes/382 indications Tubes with tube support plate wear indications SG 2A - 4 tubes/4 indications SG 2B - IO tubes/ IO indications SG 2C -3 tubes/3 indications SG 2D - I tubes/ I indications Total-18 tubes/ I 8 indications 16 broached TSP wear-2 baffle plate wear Tubes with tube presumed foreign obiect wear indications SG 2A - 9 tubes/9 indications SG 2B - 19 tubes/21 indications SG 2C-4 tubes/4 indications SG 2D - 6 tubes/6 indications Total-38 tubes/40 indications Crack like indications at and above the tube support plates SG 2A - 1 tube/I indication SG 2B - I tube/2 indications SG 2C - 0 tubes/0 indications SG 2D - 0 tubes/0 indications Total - 2 tubes/3 indications

Tubes with crack like indications within the tubesheet at the tube end SG 2A-18 tubes/19 indications SG 2B - 213 tubes/219 indications SG 2C-24 tubes/24 indications SG 2D-42 tubes/47 indications Total-297 tubes/309 indications

e.

Number of tubes plugged during the inspection outage for each degradation mechanism Steam Generator 2A:

There were three (3) tubes plugged. Two (2) tubes were plugged due to a wear with a foreign object present. One (1) tube was plugged/or crack like indication at the 3H tube support plate. The tubes plugged were as follows:

SG2A Count Row Tube Reason 1

1 8

FOwearat4H 2

32 32 FOwearat 3H 3

31 33 Crack like at 3H Steam Generator 2B:

There were three (3) tubes plugged. One (]) was for a high stress tube or two sigma tube.

One(]) tube was plugged due to a wear with a foreign object present. One(]) tube was plugged for crack like indication at the 5H tube support plate. The tubes plugged were as follows:

SG2B Count Row Tube Reason 1

22 92 High Stress Tube 2

20 68 FOwearat 3H 3

26 28 Crack like at 5H Steam Generator 2C:

There were no tubes to plug.

Steam Generator 2D:

There were eleven (11) tubes plugged. All were high stress tubes or two sigma tubes.

The tubes plugged were as follows:

SG2D Count Row Tube Reason 1

11 14 HiJ!h Stress Tube 2

11 59 HiJ!h Stress Tube 3

15 47 HiJ!h Stress Tube 4

16 25 HiJ!h Stress Tube 5

17 24 HiJ!h Stress Tube 6

17 15 HiJ!h Stress Tube 7

18 4

High Stress Tube

8 20 107 Hif!h Stress Tube 9

21 19 Hif!h Stress Tube JO 21 7

Hif!h Stress Tube 11 21 8

Hif!h Stress Tube

f.

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

Steam Generator' 2A 2B 2C 2D Total Prior to EOC-23 85 131 77 97 390 EOC-23 3

3 0

))

17 Total 88 133 77 108 407

%Plugged 1.92 2.91 1.68 2.36 2.22 1= There are 4578 tubes per steam generator

g.

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

The cumulative EFPYfor EOC-20 was 24.24, EOC-21 was 25.67 and EOC-22 was 27.10 and EOC-23 was 28.50.

Condition monitoring was met for all degradation. All structural performance criteria were met for wear with more than adequate margin. Axial outside diameter crack like indications were demonstrated to meet condition monitoring by the length of the flaws being less than the structural length for a limiting through-wall crack. For the two axial outside diameter crack like indications at the same location, the flaws were combined by applying a conservative depth to the intact ligament between the flaws. This combined flaw also met condition monitoring based on a burst pressure calculation. All axial outside diameter crack like indications met condition monitoring for leakage because the voltages were less than the threshold voltage for leakage Foreign Object Search and Retrieval (FOSAR) was performed in areas of known foreign object accumulation or where indicated by eddy current examination. FOSAR was performed at the top of tube sheet and the waterbox/preheater section. All historical foreign objects that were not removed have a technical evaluation demonstrating that tube integrity will be met through the next scheduled inspection of this region at EOC-25.

An upper bundle visual inspection was performed in the steam generator 2A, no degradation was detected.

No degradation was detected in the plug visual.

Bowl cladding inspections at EOC-21 did identify an area of missing stainless-steel cladding in the Catawba Unit 2 SG D hot leg channel head. The area of missing stainless-steel cladding was inspected at EOC-23 no changes were noted.

There was no degradation detected in any of the other bowl cladding inspections.

No in-situ tests or tube pulls were performed.

h.

For Unit 2, the primary to secondary LEAKAGE rate observed in each SG (if it is not practical to assign 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.

There was no primary to secondary leakage above detection limits during the preceding cycle 23 operation.

i.

For Unit 2, the calculated leakage rate from the portion of the tubes below 14.01 inches from the top of the tubesheet for the most limiting accident in the most limiting SG. In addition, if the calculated accident leakage rate from the most limiting accident is less than 3.27 times the maximum primary to secondary LEAKAGE rate, the report shall describe how it was determined.

There was no calculated leakage from the portion of the tubes more than 14.01 inches from the top of the tubesheet, for the most limiting accident in the most limiting SG.

j.

For Unit 2, 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 indications of slippage were detected.

List of Service Induced Indications Catawba 2, EOC-23

The complete listings of service induced indications are on the following pages. The codes and their descriptions used in the inspection data base are provided here to assist in review of these lists.

Indication Code MAI MCI PCT SAi SCI SVI WAR Description Multiple Axial Indication Multiple Circumferential Indication Percent Indication Single Axial Indication Single Circumferential Indication Single Volumetric Indication Wear

SG - 2A - Service Induced Degradation Catawba Nuclear Station 2 2EOC23 DDP 20190901 11/21/2019 11:11:12

+----+----+---------+----+----+----+-----+----+---------+---------+---------+---------+-------+----+-------+----+----+----- -+----- -+------+--+-----+

I ROW COL VOLTS DEG IND PER CHN LOCN INCHl INCH2 UTILl UTIL2 CRLEN CEG CRWID BEGT ENDT PDIA PTYPE CAL L

IDXI

+----+----+---------+----+----+----+-----+----+---------+---------+---------+---------+-------+----+-------+----+----+------+------+------+--+-----+

1 8

1.07 121 PCT 29 122 04H

.58

.83

.25 58

.38 04H TEH

.610 ZYAXP 46 H

2991 1

8 1.07 121 SVI 122 04H

.72 04H TEH

.610 ZYAXP 46 H

2991 I

32 12

.30 51 PCT 12 P4 AV3

.08 WAR TEC TEH

.610 ZBAUC 26 H

1401 I

30 13

.51 126 PCT 12 P4 AV3

.10 WAR TEC TEH

.610 ZBAUC 31 H

1241 I

32 15

.21 52 PCT 7

P4 AV2

.00 WAR TEC TEH

.610 ZBAUC 25 H

1651 I

33 15

.24 164 PCT 8

P4 AV3

.00 WAR TEC TEH

.610 ZBAUC 25 H

168 32 16

.24 157 PCT 8

P4 AV2

.00 WAR TEC TEH

.610 ZBAUC 25 H

166 35 16

.38 74 PCT 12 P4 AV2

.00 WAR TEC TEH

.610 ZBAUC 25 H

161 35 16 1.02 129 PCT 22 P4 AV3

.00 WAR TEC TEH

.610 ZBAUC 25 H

161 36 17

.21 166 PCT 9

P4 AVl

.00 WAR TEC TEH

.610 ZBAUC 26 H

129 36 17

.39 99 PCT 14 P4 AV2

.00 WAR TEC TEH

.610 ZBAUC 26 H

129 36 17

.55 20 PCT 18 P4 AV3

.00 WAR TEC TEH

.610 ZBAUC 26 H

129 37 17

.20 121 PCT 9

P4 AV2

-.10 WAR TEC TEH

.610 ZBAUC 26 H

132 37 17

.65 79 PCT 20 P4 AV3

.03 WAR TEC TEH

.610 ZBAUC 26 H

132 I

38 17

.44 85 PCT 16 P4 AVl

-. 05 WAR TEC TEH

.610 ZBAUC 26 H

1341 38 17

.84 79 PCT 23 P4 AV3

.00 WAR TEC TEH

.610 ZBAUC 26 H

1341 38 17

.38 35 PCT 14 P4 AV4

.00 WAR TEC TEH

.610 ZBAUC 26 H

1341 I

36 18

.23 147 PCT 8

P4 AV3

.00 WAR TEC TEH

.610 ZBAUC 25 H

1451 I

40 18

.30 34 PCT 10 P4 AVl

.00 WAR TEC TEH

.610 ZBAUC 25 H

1541 40 18

.28 123 PCT 9

P4 AV2

.00 WAR TEC TEH

.610 ZBAUC 25 H

1541 40 1B

1. 51 105 PCT 27 P4 AV3

.00 WAR TEC TEH

.610 ZBAUC 25 H

1541 I

38 19

.32 141 PCT 10 P4 AVl

.00 WAR TEC TEH

.610 ZBAUC 25 H

1501 I

37 21

.28 159 PCT 9

P4 AV3

.00 WAR TEC TEH

.610 ZBAUC 25 H

1491 I

38 21

.68 69 PCT 20 P4 AV2

-. 03 WAR TEC TEH

.610 ZBAUC 26 H

1311 38 21

.22 109 PCT 9

P4 AV4

.10 WAR TEC TEH

.610 ZBAUC 26 H

1311 I

39 21

.52 144 PCT 17 P4 AVl

.00 WAR TEC TEH

.610 ZBAUC 26 H

1331 39 21

.53 131 PCT 18 P4 AV2

.00 WAR TEC TEH

.610 ZBAUC 26 H

1331 39 21

.29 132 PCT 11 P4 AV3

.03 WAR TEC TEH

.610 ZBAUC 26 H

1331 I

38 22

.57 86 PCT 18 P4 AV2

-.12 WAR TEC TEH

.610 ZBAUC 26 H

1081 38 22

.44 52 PCT 16 P4 AV3

.00 WAR TEC TEH

.610 ZBAUC 26 H

1081 I

30 23

.40 0

PCT 11 P4 AV2

.03 WAR TEC TEH

.610 ZBAUC 34 H

611 I

+----+----+---------+----+----+----+-----+----+---------+---------+---------+---------+-------+----+-------+----+----+------+------+------+--+-----+

I ROW COL VOLTS DEG IND PER CHN LOCN INCHl INCH2 UTILl UTIL2 CRLEN CEG CRWID BEGT ENDT PDIA PTYPE CAL L

IDXI

+----+----+-------- -+----+----+----+-----+----+---------+---------+---- - ----+---------+-------+----+-------+----+----+------+------+------+--+-----+

1 ST Max

SG - 2A - Service Induced Degradation Catawba Nuclear Station 2 2EOC23 DDP 20190901 11/21/2019 11:11 :12

+----+----+---------+- - --+----+----+-----+----+---------+---------+---------+---------+-------+- - --+-------+ - ---+----+------+------+------+--+-----+

I ROW COL VOLTS DEG IND PER CHN LOCN INCHl INCH2 UTILl UTIL2 CRLEN CEG CRWID BEGT ENDT PDIA PTYPE CAL L

IDXI

+----+----+------- - -+----+----+----+-----+----+---------+---------+---------+---------+-------+----+-------+----+----+------+----- - +------+--+-----+

33 23

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116 33 23

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116 38 23

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97 43 23

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1111 I

17 26

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61 I

45 26

.68 141 PCT 14 P4 AV2

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15

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INCH2 UTILl UTIL2 CRLEN CEG CRWID BEGT ENDT PDIA PTYPE CAL L

IDXI

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2 ST Max

SG - 2A - Service Induced Degradation Catawba Nuclear Station 2 2EOC23 DDP 20190901 11/21/2019 11:11:12

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IDXI

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149

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I ROW COL VOLTS DEG IND PER CHN LOCN INCHl INCH2 UTILl UTIL2 CRLEN CEG CRWID BEGT ENDT PDIA PTYPE CAL L

IDXI

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3 ST Max

SG - 2A - Service Induced Degradation Catawba Nuclear Station 2 2EOC23 DDP 20190901 11/21/2019 11:11:12

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I ROW COL VOLTS DEG IND PER CHN LOCN INCHl INCH2 UTILl UTIL2 CRLEN CEG CRWID BEGT ENDT PDIA PTYPE CAL L

IDXI

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49 83

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H 341 I

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42 90

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1851 I

44 90

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H 1751 I

38 91

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I ROW COL VOLTS DEG IND PER CHN LOCN INCHl INCH2 UTILl UTIL2 CRLEN CEG CRWID BEGT ENDT PDIA PTYPE CAL L

IDXI

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4 ST Max

SG - 2A - Service Induced Degradation Catawba Nuclear Station 2 2EOC23 DDP 20190901 11/21/2019 11:11 :12

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I ROW COL VOLTS DEG IND PER CHN LOCN INCH!

INCH2 UTILl UTIL2 CRLEN CEG CRWID BEGT ENDT PDIA PTYPE CAL L

IDXI

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H 7

44 92

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H 7

33 93

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232 i

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1641 I

38 93

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184 38 94

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183 41 94

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.49 65 PCT 11 P4 AV3

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177 38 96

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I ROW COL VOLTS DEG IND PER CHN LOCN INCHl INCH2 UTILl UTIL2 CRLEN CEG CRWID BEGT ENDT PDIA PTYPE CAL L

IDXI

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5 ST Max

SG - 2A - Service Induced Degradation Catawba Nuclear Station 2 2EOC23 DDP 20190901 11/21/2019 11 :11 :12

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I ROW COL VOLTS DEG IND PER CHN LOCN INCH!

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IDXI

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33 98

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H 11

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6 Tubes : 98 Records: 176 ST Max

SG - 2B - Service Induced Degradation Catawba Nuclear Station 2 2EOC23 DDP 20190901 11/21/2019 10:57:25

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IDXI

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45 1. 26 95 PCT 32 74 05H

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6 5

55

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P3 04H

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7

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I ROW COL VOLTS DEG IND PER CHN LOCN INCHl INCH2 UTILl UTIL2 CRLEN CEG CRWID BEGT ENDT PDIA PTYPE CAL L

IDXI

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1 ST Max

SG - 28 - Service Induced Degradation Catawba Nuclear Station 2 2EOC23 DDP 20190901 11/21/2019 10:57:25

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IDXI

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241 I

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71 I

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701 I

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561 I

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911 I

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05H

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541 I

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I ROW COL VOLTS DEG IND PER CHN LOCN INCH!

INCH2 UTILl UTIL2 CRLEN CEG CRWID BEGT ENDT PDIA PTYPE CAL L

IDXI

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2 ST Max

SG - 2B - Service Induced Degradation Catawba Nuclear Station 2 2EOC23 DDP 20190901 11/21/2019 10 :57:25

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I ROW COL VOLTS DEG IND PER CHN LOCN INCHl INCH2 UTILl UTIL2 CRLEN CEG CRWID BEGT ENDT PDIA PTYPE CAL L

IDXI

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141 I

36 98

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521 I

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701 I

36 99

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102

.24 105 PCT 13 158 05H

1. 21

1. 50 17902.3 12X

.29 70

.46 05H 05H

.610 ZYAXP 46 H

19 32 102

.20 165 PCT 6

P4 AVl

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.610 ZBAUL 63 H

57 32 103

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.610 ZBAUL 63 H

62 32 103

.39 47 PCT 10 P4 AV3

.03 WAR TEC TEH

.610 ZBAUL 63 H

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113

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12

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I ROW COL VOLTS DEG IND PER CHN LOCN INCH!

INCH2 UTILl UTIL2 CRLEN CEG CRWID BEGT ENDT PDIA PTYPE CAL L

IDXI

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3 Tubes : 54 Records : 72 ST Max

SG - 2C - Service Induced Degradation Catawba Nuclear Station 2 2EOC23 DDP 20190901 11/21/2019 10:57:25

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I ROW COL VOLTS DEG IND PER CHN LOCN INCHl INCH2 UTILl UTIL2 CRLEN CEG CRWID BEGT ENDT PDIA PTYPE CAL L

IDXI

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30 15

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31 15

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.24 149 PCT 7

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P4 AV2

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35 21

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I ROW COL VOLTS DEG IND PER CHN LOCN INCHl INCH2 UTILl UTIL2 CRLEN CEG CRWID BEGT ENDT PDIA PTYPE CAL L

IDXI

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1 ST Max

SG - 2C - Service Induced Degradation Catawba Nuclear Station 2 2EOC23 DDP 20190901 11/21/2019 10:57:25

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I ROW COL VOLTS DEG IND PER CHN LOCN INCHl INCH2 UTILl UTIL2 CRLEN CEG CRWID BEGT ENDT PDIA PTYPE CAL L

IDXI

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.54 17902.3

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13 36 25

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79 2

26

.71 49 PCT 9

P3 llC

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6 31 27

.66 135 PCT 15 P4 AVl

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.610 ZBAUL 57 H

1441 I

39 27

.29 167 PCT 8

P4 AV2

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541 I

40 27

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36 33

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38 34

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1. 79 17902.1

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IDXI

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2 ST Max

SG - 2C - Service Induced Degradation Catawba Nuclear Station 2 2EOC23 DDP 20190901 11/21/2019 10:57:25

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I ROW COL VOLTS DEG IND PER CHN LOCN INCH!

INCH2 UTILl UTIL2 CRLEN CEG CRWID BEGT ENDT PDIA PTYPE CAL L

IDXI

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P4 AV4

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P4 AV4

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33 42 91

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.62 17902.3

.14 46

.30 18C TEC

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C 161 44 92

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P4 AV3

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P4 AV4

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P4 AV2

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H 9

33 101

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P4 AV3

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H 9

33 101

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P4 AV4

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H 9

33 102

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P4 AV2

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H 10 28 103

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P4 AV3

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H 10 28 105

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PCT 17 P4 AV3

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P4 AV3

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104

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I ROW COL VOLTS DEG IND PER CHN LOCN INCH!

INCH2 UTILl UTIL2 CRLEN CEG CRWID BEGT ENDT PDIA PTYPE CAL L

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3 Tubes: 59 Records : 84 ST Max

SG - 2D - Service Induced Degradation Catawba Nuclear Station 2 2EOC23 DDP 20190901 11/21/2019 10:57 :25

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I ROW COL VOLTS DEG IND PER CHN LOCN INCHl INCH2 UTILl UTIL2 CRLEN CEG CRWID BEGT ENDT PDIA PTYPE CAL L

IDXI

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28 10

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58 32 12

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H 21 33 13

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H 21 33 13

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P4 AV4

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49 35 14

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49 33 15

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.64 126 PCT 14 P4 AV3

.00 WAR TEC TEH

.610 ZBAHS 2

H 28 36 16

.33 29 PCT 8

P4 AV4

.03 WAR TEC TEH

.610 ZBAHS 2

H 281 I

37 17

. 72 135 PCT 15 P4 AV2

-. 05 WAR TEC TEH

.610 ZBAHS 2

H 311 37 17

.73 126 PCT 15 P4 AV4

.00 WAR TEC TEH

.610 ZBAHS 2

H 311 I

38 18 1.11 125 PCT 21 P4 AV2

.00 WAR TEC TEH

.610 ZBAHS 2

H 341 38 18

.82 82 PCT 17 P4 AV4

.10 WAR TEC TEH

.610 ZBAHS 2

H 34 38 19

.30 135 PCT 8

P4 AV2

-.16 WAR TEC TEH

.610 ZBAHS 2

H 35 38 20

.58 123 PCT 13 P4 AV2

-. 03 WAR TEC TEH

.610 ZBAHS 10 H

106 38 20

.32 25 PCT 8

P4 AV4

.10 WAR TEC TEH

.610 ZBAHS 10 H

106 41 20

.34 161 PCT 8

P4 AV4

.00 WAR TEC TEH

.610 ZBAHS 2

H 40 38 21

. 34 38 PCT 8

P4 AV2

.08 WAR TEC TEH

.610 Z8AHS 1

H 33 43 22

.31 151 PCT 8

P4 AVl

.00 WAR TEC TEH

.610 ZBAHS 2

H 79 43 22

.47 108 PCT 11 P4 AV2

.00 WAR TEC TEH

.610 ZBAHS 2

H 79 43 22 1.68 128 PCT 26 P4 AV3

.00 WAR TEC TEH

.610 ZBAHS 2

H 79 43 22

.94 112 PCT 19 P4 AV4

.00 WAR TEC TEH

.610 ZBAHS 2

H 79 42 23 1.05 139 PCT 19 P4 AV2

-.08 WAR TEC TEH

.610 ZBAHS 1

H 28 42 23

.31 114 PCT 8

P4 AV4

.10 WAR TEC TEH

.610 ZBAHS 1

H 281 I

44 24

.39 77 PCT 9

P4 AV3

.08 WAR TEC TEH

.610 ZBAHS 1

H 831 I

38 26

.32 125 PCT 8

P4 AV2

.03 WAR TEC TEH

.610 ZBAHS 1

H 711 I

33 28

.22 132 PCT 6

P4 AV2

.08 WAR TEC TEH

.610 ZBAHS 1

H 571

+- - - -+- - - -+- - - - - - - - -+- - - -+- - - -+- - - -+- - - - -+- - - -+- - - - - - - - -+- - - - - - - - -+- - - - - - - - -+- - - - - - - - -+- - - - - - -+- - - -+- - - - - - -+- - - -+- - - -+- - - - - -+- - - - - -+- - - - - -+- -+- - - - -+

I ROW COL VOLTS DEG IND PER CHN LOCN INCH!

INCH2 UTILl UTIL2 CRLEN CEG CRWID 8EGT ENDT PDIA PTYPE CAL L

IDXI

+----+----+---------+----+----+----+-----+----+---------+---------+---------+---------+-------+----+-------+----+----+------+------+----- - +--+-----+

1 ST Max

SG - 2D - Service Induced Degradation Catawba Nuclear Station 2 2EOC23 DDP 20190901 11/21/2019 10 :57:25

+----+----+---------+----+----+----+-----+----+---------+---------+---------+----- - ---+-------+----+-------+----+----+------+------+------+--+-----+

I ROW COL VOLTS DEG IND PER CHN LOCN INCHl INCH2 UTILl UTIL2 CRLEN CEG CRWID BEGT ENDT PDIA PTYPE CAL L

IDXI

+----+----+---------+----+----+----+-----+----+---------+---------+---------+---------+-------+----+--- - ---+----+----+------+------+------+--+-----+

I 43 29

.36 97 PCT 9

P4 AV2

.05 WAR TEC TEH

.610 ZBAHS 2

H 941 I

42 30

.50 143 PCT 14 P4 AV2

-. 05 WAR TEC TEH

.610 ZBAHS 9

H 1171 I

42 32

.53 128 PCT 12 P4 AV2

-.08 WAR TEC TEH

.610 ZBAHS 2

H 931 I

44 34

.25 146 PCT 6

P4 AV2

-.10 WAR TEC TEH

.610 ZBAHS 4

H 131 I

49 37

.23 149 PCT 5

P4 AVl

. 00 WAR TEC TEH

.610 ZBAHS 4

H 241 I

29 40

.50 110 PCT 19 122 05H

.98 1.20

.21 58

.38 09C TEH

.610 ZYAXP 49 H

24 44 46 1.34 110 PCT 22 P4 AV3

. 00 WAR TEC TEH

.610 ZBAHS 4

H 96 17 55

.69 94 PCT 23 26 01H

-.13

.06 17902.3 18%

.19 46

.30 01H TEH

.610 ZYAXP 39 H

70 46 56

.36 70 PCT 8

P4 AV4

.48 WAR TEC TEH

.610 ZBAHS 4

H 172 48 61 2.96 115 PCT 30 P3 13C

.00 WAR TEH TEC

.610 ZBAUC 11 C

6 38 64

.94 120 PCT 19 P4 AV2

.00 WAR TEC TEH

.610 ZBAHS 20 H

153 36 65

.89 69 PCT 19 P4 AV3

.74 WAR TEC TEH

.610 ZBAHS 20 H

123 45 65

.43 106 PCT 9

P4 AV2

.05 WAR TEC TEH

.610 ZBAHS 22 H

20 49 66

.39 147 PCT 11 P4 AV4

.03 WAR TEC TEH

.610 ZBAHS 21 H

541 I

28 69 1.08 89 PCT 30 134 10C

-1.16

-. 91 17902.3 28%

.25 58

.38 10C TEC

.610 ZYAXP 23 C

391 I

21 70

.82 89 PCT 18 18 06H 1.36 1.68 17902.1

.33 46

.30 07H TEH

.610 ZYAXP 70 H

241 I

12 72

.80 75 PCT 25 74 01H

.34

.52 17902.3 23%

.18 46

.30 01H TEH

.610 ZYAXP 55 H

381 I

48 72

.78 118 PCT 25 74 18C 1.02 1.23 17902.3 28%

.21 58

.38 17C TEC

.610 ZYAXP 18 C

1051 I

49 74

.22 129 PCT 6

P4 AV4

-.10 WAR TEC TEH

.610 ZBAHS 19 H

1081 I

41 77

.90 112 PCT 18 P4 AV2

.13 WAR TEC TEH

.610 ZBAHS 19 H

1181 41 77

.38 139 PCT 9

P4 AV3

-.08 WAR TEC TEH

.610 ZBAHS 19 H

1181 I

38 78

.22 104 PCT 6

P4 AV2

.18 WAR TEC TEH

.610 ZBAHS 20 H

451 38 78 1.46 95 PCT 25 P4 AV3

.15 WAR TEC TEH

.610 ZBAHS 20 H

451 I

43 78 2.12 112 PCT 30 P4 AV2

. 00 WAR TEC TEH

.610 ZBAHS 20 H

1001 43 78 3.96 118 PCT 38 P4 AV3

.00 WAR TEC TEH

.610 ZBAHS 20 H

1001 I

33 79

.30 147 PCT 7

P4 AVl

.08 WAR TEC TEH

.610 ZBAHS 18 H

1381

+----+----+---------+----+----+----+-----+----+---------+---------+---------+---------+-------+----+-------+----+----+------+------+- - ----+- - +---- - +

I ROW COL VOLTS DEG IND PER CHN LOCN INCHl INCH2 UTILl UTIL2 CRLEN CEG CRWID BEGT ENDT PDIA PTYPE CAL L

IDXI

+----+----+---------+----+----+----+-----+----+-------- -+---------+---------+---------+-------+----+-------+----+----+------+------+------+--+-----+

2 ST Max

SG - 2D - Service Induced Degradation Catawba Nuclear Station 2 2EOC23 DDP 20190901 11/21/2019 10:57:25

+----+----+---------+----+----+----+-----+----+---------+---------+---------+---------+-------+----+-------+----+----+------+------+------+--+-----+

I ROW COL VOLTS DEG IND PER CHN LOCN INCHl INCH2 UTILl UTIL2 CRLEN CEG CRWID BEGT ENDT PDIA PTYPE CAL L

IDXI

+----+----+---------+----+----+----+-----+----+---------+------- - -+---------+---------+-------+----+-------+----+----+------+------+------+--+-----+

33 79

.51 119 PCT 11 P4 AV2

-.28 WAR TEC TEH

.610 ZBAHS 18 H

1381 I

36 79

.29 38 PCT 7

P4 AVl

.10 WAR TEC TEH

.610 ZBAHS 18 H

1451 36 79

.50 33 PCT 11 P4 AV3

-. 03 WAR TEC TEH

.610 ZBAHS 18 H

1451 I

33 81

.29 83 PCT 6

P4 AV2

.00 WAR TEC TEH

.610 ZBAHS 17 H

1511 I

39 81

.37 123 PCT 9

P4 AV2

.15 WAR TEC TEH

.610 ZBAHS 19 H

71 I

48 82

.36 141 PCT 8

P4 AVl

-.12 WAR TEC TEH

.610 ZBAHS 18 H 961 I

49 82

.63 159 PCT 13 P4 AVl

-.10 WAR TEC TEH

.610 ZBAHS 18 H 98 48 83

.46 136 PCT 10 P4 AVl

-. 26 WAR TEC TEH

.610 ZBAHS 18 H

97 49 84

.36 160 PCT 7

P4 AVl

-.18 WAR TEC TEH

.610 ZBAHS 17 H

107 42 85

.81 135 PCT 14 P4 AV2

.00 WAR TEC TEH

.610 ZBAHS 17 H

110 42 85

.40 49 PCT 8

P4 AV3

.08 WAR TEC TEH

.610 ZBAHS 17 H

110 33 87

.38 143 PCT 8

P4 AV2

.05 WAR TEC TEH

.610 ZBAHS 18 H

127 46 87

.35 139 PCT 8

P4 AVl

. 00 WAR TEC TEH

.610 ZBAHS 18 H 93 47 87

.30 45 PCT 7

P4 AV4

.13 WAR TEC TEH

.610 ZBAHS 18 H

95 46 89

.36 172 PCT 7

P4 AVl

-. 08 WAR TEC TEH

.610 ZBAHS 17 H

99 46 89

.22 161 PCT 5

P4 AV2

.00 WAR TEC TEH

.610 ZBAHS 17 H

99 38 90

.48 113 PCT 10 P4 AV2

. 00 WAR TEC TEH

.610 ZBAHS 18 H

78 39 90

.89 148 PCT 17 P4 AV2

-.13 WAR TEC TEH

.610 ZBAHS 18 H 81 44 90

.37 148 PCT 8

P4 AVl

. 00 WAR TEC TEH

.610 ZBAHS 18 H

87 44 91

.52 117 PCT 11 P4 AV2

.05 WAR TEC TEH

.610 ZBAHS 18 H 90 44 91

.54 164 PCT 11 P4 AV3

.08 WAR TEC TEH

.610 ZBAHS 18 H 90 44 91

.41 163 PCT 9

P4 AV4

-.15 WAR TEC TEH

.610 ZBAHS 18 H 90 45 91

.62 165 PCT 13 P4 AV2

.08 WAR TEC TEH

.610 ZBAHS 18 H 91 45 91

.62 137 PCT 13 P4 AV4

-.10 WAR TEC TEH

.610 ZBAHS 18 H 91 42 92

.35 107 PCT 8

P4 AV4

-. 03 WAR TEC TEH

.610 ZBAHS 18 H

39 36 93 1.18 120 PCT 18 P4 AV2

.03 WAR TEC TEH

.610 ZBAHS 18 H

62 36 93

.39 120 PCT 7

P4 AV3

.00 WAR TEC TEH

.610 ZBAHS 18 H

621 I

38 93 1.34 133 PCT 21 P4 AV2

. 00 WAR TEC TEH

.610 ZBAHS 17 H

811 38 93

.43 132 PCT 9

P4 AV3

. 00 WAR TEC TEH

.610 ZBAHS 17 H

811

+----+----+---------+----+----+----+-----+----+---------+---------+---------+---------+-------+----+-------+----+----+------+------+------+--+-----+

I ROW COL VOLTS DEG IND PER CHN LOCN INCH!

INCH2 UTILl UTIL2 CRLEN CEG CRWID BEGT ENDT PDIA PTYPE CAL L

IDXI

+----+----+---------+----+----+----+-----+----+---------+---------+---------+---------+-------+----+-------+----+----+------+------+------+--+-----+

3 ST Max

SG - 2D - Service Induced Degradation Catawba Nuclear Station 2 2EOC23 DDP 20190901 11/21/2019 10 :57 :25

+- ---+----+------- --+----+----+----+-----+----+---------+---------+---------+--- ------+-- ---- -+----+- ---- --+----+----+------+------+------+--+---- -+

I ROW COL VOL TS DEG IND PER CHN LOCN INCH!

INCH2 UTILl UTIL2 CRLEN CEG CRWID BEGT ENDT PDIA PTYPE CAL L

IDXI

+-- --+----+---------+----+----+--- -+-- ---+----+---------+---------+---------+---------+-------+----+-------+----+----+------+------+------+--+-----+

I 40 93

.30 127 PCT 6

P4 AV!

-.05 WAR TEC TEH

.610 ZBAHS 18 H 791 40 93

.58 92 PCT 12 P4 AV2

-. 03 WAR TEC TEH

.610 ZBAHS 18 H 791 I

36 94

.38 91 PCT 8

P4 AV!

-.28 WAR TEC TEH

.610 ZBAHS 17 H

611 36 94

.48 146 PCT 9

P4 AV2

. 00 WAR TEC TEH

.610 ZBAHS 17 H

611 I

38 94

.40 154 PCT 8

P4 AV3

.00 WAR TEC TEH

.610 ZBAHS 17 H

431 I

40 94

.21 161 PCT 5

P4 AV!

-. 31 WAR TEC TEH

.610 ZBAHS 17 H

481 40 94

.95 145 PCT 16 P4 AV2

.00 WAR TEC TEH

.610 ZBAHS 17 H

481 40 94 1.01 148 PCT 17 P4 AV3

.00 WAR TEC TEH

.610 ZBAHS 17 H

481 I

32 96

.50 159 PCT 9

P4 AV2

.23 WAR TEC TEH

.610 ZBAHS 18 H

521 I

35 96

.19 51 PCT 5

P4 AV2

.00 WAR TEC TEH

.610 ZBAHS 18 H

591 I

36 96 1.12 130 PCT 17 P4 AV2

-.10 WAR TEC TEH

.610 ZBAHS 18 H

611 36 96

.49 128 PCT 9

P4 AV3

.10 WAR TEC TEH

.610 ZBAHS 18 H 611 I

39 96

.95 116 PCT 17 P4 AV3

.10 WAR TEC TEH

.610 ZBAHS 18 H 461 I

40 96

.49 59 PCT 9

P4 AV!

.05 WAR TEC TEH

.610 ZBAHS 18 H 481 I

36 97

.90 112 PCT 16 P4 AV2

. 00 WAR TEC TEH

.610 ZBAHS 17 H

34 34 98 1.55 126 PCT 21 P4 AV2

-.20 WAR TEC TEH

.610 ZBAHS 18 H

55 36 98

. 77 115 PCT 14 P4 AV3

.00 WAR TEC TEH

.610 ZBAHS 17 H

45 39 98

.36 158 PCT 8

P4 AV!

.10 WAR TEC TEH

.610 ZBAHS 18 H 42 29 99

.30 98 PCT 8

P4 AV3

.00 WAR TEC TEH

.610 ZBAHS 16 H

147 34 99

.71 142 PCT 13 P4 AV2

.00 WAR TEC TEH

.610 ZBAHS 17 H

30 34 100

.68 148 PCT 13 P4 AV3

. 00 WAR TEC TEH

.610 ZBAHS 17 H

31 36 100 1.50 112 PCT 23 P4 AV3

-. 74 WAR TEC TEH

.610 ZBAHS 17 H

35 36 100 4.20 85 PCT 38 P4 AV3

-. 28 WAR TEC TEH

.610 ZBAHS 17 H

351 36 100

.91 29 PCT 16 P4 AV3

.44 WAR TEC TEH

.610 ZBAHS 17 H

351 I

32 101

.58 142 PCT 12 P4 AV3

.08 WAR TEC TEH

.610 ZBAHS 18 H 301 I

30 102 1.02 131 PCT 18 P4 AV3

-. 03 WAR TEC TEH

.610 ZBAHS 15 H

1641 I

27 104

.39 101 PCT 10 P4 AV2

-.08 WAR TEC TEH

.610 ZBAHS 16 H

1541 I

29 104

.63 135 PCT 15 P4 AV2

.00 WAR TEC TEH

.610 ZBAHS 16 H

1601

+----+----+---------+----+- ---+--- -+-----+----+---------+---------+---------+-------- -+------ -+- ---+-------+----+----+------+------+------+--+-----+

I ROW COL VOLTS DEG IND PER CHN LOCN INCHl INCH2 UTill UTIL2 CRLEN CEG CRWID BEGT ENDT PDIA PTYPE CAL L

IDXI

+----+----+- --------+----+- ---+--- -+-----+--- -+----- -- --+--- -- ----+---------+---- ---- -+-------+--- -+- --- -- -+- -- -+- -- -+---- --+---- --+- -----+--+---- -+

4 ST Max

SG - 20 - Service Induced Degradation Catawba Nuclear Station 2 2EOC23 DDP 20190901 11/21/2019 10 :57:25

+----+----+---------+----+----+----+-----+----+---------+---------+---------+---------+-------+----+-------+-- --+----+-- ----+------+------+--+-----+

I ROW COL VOLTS DEG IND PER CHN LOCN INCH!

INCH2 UTILl UTIL2 CRLEN CEG CRWID BEGT ENDT PDIA PTYPE CAL L

IDXI

+----+----+---------+----+----+----+-----+----+---------+---------+---------+---------+-------+--- -+-------+-- --+----+------+------+------+--+-----+

I 28 105 1.29 139 PCT 24 P4 AV2

.10 WAR TEC TEH

.610 ZBAHS 16 H

1581 28 105

.65 136 PCT 15 P4 AV3

.05 WAR TEC TEH

.610 ZBAHS 16 H

1581 I

25 107 1.26 127 PCT 18 P4 AV2

-.10 WAR TEC TEH

.610 ZBAHS 18 H 281 25 107

.68 96 PCT 11 P4 AV3

.28 WAR TEC TEH

.610 ZBAHS 18 H 281 I

27 107 1.22 149 PCT 23 P4 AV2

.13 WAR TEC TEH

.610 ZBAHS 16 H

1551

+----+----+---------+----+----+----+-----+----+---------+---------+---------+---------+-------+----+-------+----+----+------+- -----+------+--+---- -+

I ROW COL VOLTS DEG IND PER CHN LOCN INCH!

INCH2 UTILl UTIL2 CRLEN CEG CRWID BEGT ENDT PDIA PTYPE CAL L

IDXI

+----+----+---------+----+----+----+-----+----+---------+---------+---------+---------+-------+----+-------+----+----+------+------+------+--+-----+

5 Tubes : 85 Records : 120 ST Max