RNP-RA/17-0051, Submittal of Nine Day Inservice Inspection Summary Report
| ML17180A352 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 06/29/2017 |
| From: | Kapopoulos E Duke Energy Progress |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RNP-RA/17-0051 | |
| Download: ML17180A352 (11) | |
Text
Serial: RNP-RA/17-0051 JUN 2 9 2017 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 H. 8. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/RENEWED LICENSE NO. DPR-23 Ernest J. Kapopou/os, Jr.
H B Robinson Steam Electric Plant Umt 2 Site Vice PreStdent Duke Energy 3581 West Entrance Road Hartsville, SC 29550 0 843 857 1701 F 843 857 1319 Ernie.Kapopou/o.r;@,1/uke*energy.com 10 CFR 50.55a SUBMITTAL OF NINETY DAY INSERVICE INSPECTION
SUMMARY
REPORT Ladies and Gentlemen:
In accordance with the requirements of 10 CFR 50.55a "Codes and Standards," Duke Energy Progress, LLC is providing as an enclosure to this letter, the lnservice Inspection Summary Report for Class 1 and Class 2 pressure retaining components and their supports. This report has been prepared in accordance with the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME),Section XI, 2007 Edition, 2008 Addenda, and is subject to the limitations and modifications of 10 CFR 50.55a(b)(2), with the exception of design and access provisions and preservice examination requirements. This report is further prepared in accordance with the requirements of ASME Code Case N-532-5 and covers inspection activities during Cycle 30 and Refueling Outage 30 (R230). It is noted, R230 is the first of two outages of the second period in the fifth inspection interval and includes the repair/replacement activities from August 8, 2015 to June 12, 2017.
There are no regulatory commitments made in this submittal. If you have any questions regarding this submittal, please contact Mr. Tony Pilo, Manager - Nuclear Regulatory Affairs, at (843) 857-1409.
I declare under penalty of perjury that the foregoing is true and correct.
Executed On: 2-<t 5°utJf, Zd.7 Sincerely, w~
Ernest J. Kapopoulos, Jr.
Site Vice President
United States Nuclear Regulatory Commission Serial: RNP-RA/17-0051 Page 2 of 2 EJK/am
Enclosure:
Ninety Day lnservice Inspection Summary Report For Refueling Outage 30 cc:
NRC Regional Administrator, NRC, Region II D. Galvin, NRC Project Manager, NRR (w/o Enclosures)
NRC Resident Inspector, HBRSEP Unit No. 2
United States Nuclear Regulatory Commission Enclosure to Serial: RNP-RA/17-0051 9 Pages (including cover page)
H.B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 NINETY DAY INSERVICE INSPECTION
SUMMARY
REPORT FOR REFUELING OUTAGE 30
Form OAR-1 OWNER'S ACTIVITY REPORT Summary The H. 8. Robinson Nuclear Power Plant, Unit 2, Fifth Ten-Year Interval Inservice Inspection Plan was developed and prepared to meet the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, 2007 Edition with 2008 Addenda, and is subject to the limitations and modifications of 10 CFR 50.55a(b )(2), with the exception of design and access provisions and preservice examination requirements. This summary report is submitted pursuant to the reporting requirements of ASME Section XI as amended by ASME Code Case N-532-5, "Repair/Replacement Activity Documentation Requirements and Inservice Summary Report Preparation and Submission Section XI, Division 1." Contained within this summary report are the Owner's Activity Report, Form OAR-1, and Tables 1 and 2 of Code Case N-532-5 for H. 8. Robinson Nuclear Power Plant during Cycle 30 and Refueling Outage 30 (R230). R230 is the first of two outages of the second period in the fifth inspection interval and includes the Repair/Replacement activities from August 8, 2015, to June 12, 2017.
Form OAR-1 OWNER'S ACTIVITY REPORT Plant: -------"H
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Unit No.: ------- Commercial Service Date: __
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~3~0-2 Current Inspection Interval: IWB. IWC.IWD. IWF: Fifth Interval IWE/IWL: Second Interval Current Inspection Period:
IWB. IWC.IWD. IWF: Second Period of the Fifth Interval IWE/IWL: Second Period of the Second Interval Edition and Addenda of Section XI applicable to the Inspection plans:
ISi: 2007 Edition Thru 2008 Addenda. IWEllWL: 2001 Edition Thru 2003 Addenda Date and Revision of Inspection Plans:
ISi: RNP-PM-009. Revision 5, 12/19/2016 IWEllWL: RNP-PM-007. Revision 5, 612512014 Edition and Addenda of Section XI applicable to Repair/Replacement activities, if different than the Inspection Plans:..J:flA Code Cases used: N-639, N-731. N-722-1. N-770-1. N-586-1, N-532-5. N-600. N648-1 CERTIFICATE OF CONFORMANCE I certlfy that (a) the statements made In this report are correct, (b) the exam:naUons 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 or _.._.R..,230..._ _____
(Roluolng0...thml>ofl conform to the requirements of Section XI.
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Owner or Owner's Oeslgnee, TiUe CERTIFICATE OF INSERVICE INSPECTION I, lhe undersigned, holding a vatid commission Issued by lhe National Board of Boller and Pressure Vessel lnspeclors and the Stale or Province ol South Garolina and employed by HSB Global St.andards of Hartford CT have Inspected the Items described In this Owner's Activily Report, and stale that, to lhe besl of my knowledge and betief, the Owner has perfonned all activities represented by this report In accordance with the requirements of Section XI.
By signing !his certificate neither the Inspector nor hls employer makes any warranty, expressed or lmpHed, concerning the repair/replacement activities and evaluallon described In lhls 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 comected with \\his lnspecUon.
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Examination Category and Item Number F-A, Fl.40 Form OAR-1 OWNER'S ACTIVITY REPORT Table I ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Item Descripdon Evaluation Description Inservice inspection Program Identified issues:
I. One of the CRDM Bumpt.'T screws docs not fully engage the boss welded to the CRDM seismic support platform.
- 2. Several CROM Bumper screws arc missing the cotter pins shown on Westinghouse drawings.
These locations arc secured with wire thnt is intact nnd bent to prevent it becoming dislodged. The wire is not brittle or degraded.
- 3. Two locations hnvc been identified on the Seismic Support Platform surface thnt contain what nppcar to be nrc strikes.
From Westinghouse onnlysis #L TR-CHE-17-057, Rev. 0:
"Westinghouse has dett.Tmined that the CRDM bumper screw shown in Figures I nnd 2 is ncccptnble to use-ns-is nnd recommends thnt the plant confirms the wire shown in Figures 5 ond 6 docs not come loose and become FME. If the plnnt feels these locations moy come loose, 1010/CRDM Westinghouse recommends that these locations be replaced with o cotter pin or lock wire thot can SSS be confirmed to not come loose nnd become FME. Westinghouse recommends utilizing n cotter pin CROM or lock wire nt locations where nvailoble. Westinghouse also recommends thnt arc strike locations Seismic be blended, NDE inspected to confirm no cracks ore present, and then touched-up using paint approved for use inside of containment to prevent future corrosion nnd protect the component. The Support A WS code requires thnt arc strike locations be repaired ns n.-commended by Westinghouse. The Structure areas appear to be minor nnd therefore Westinghouse recommends that the plant repair areas deemed to be arc strikes as detcnnined by a qualified weld inspector, this outage or next outnge."
Inspection Nolt."S:
I. The jam nut on the affected bumper has been validated to be snug.
- 2. All wires have been validated by the inspectors to be intact, not loose nnd firmly bent sons to preclude being dislodged.
- 3. Work Order #20153937 hns been generated to remove the nrc strikes during R23 l. The work order also contains a task for performance of visual and liquid pcnctrant examinations following removal to validate no detrimental conditions exist.
- 4. Engineering Change #407963 has been completed to evaluate the conditions noled and the Westinghouse analysis. The EC has accepted the Westinghouse analysis and recommendations.
RE: NCR #02109120, Evaluation EV-17-002. WO #20153937
Form OAR-1 OWNER'S ACTIVITY REPORT Examination Item Category and Description Evaluation Description Item Number During examination of Component Support CPL-123-CC, it was identified that the pipe clamp bolting on the bottom side of the pipe had inadequate thread engagement. The bolt was not fully engaged into the nut by approximately one thread. The nut was not found to be loose, or have any apparent causes to have become loose during service, to cause the inadequate thread engagement.
Evaluation EV-17-001 states the following:
3-CH-14 is the Charging Pump discharge to the Regenerative Heat Exchanger and is therefore part of the CVCS System. Per the system DBD, DBD/R87038/SD21, the CVCS safety function is making the core subcritical under hot standby or hot operating conditions and credible accident conditions, with appropriate margins for contingencies, nnd limiting any subsequent return to power such that there will be no undue risk to the
- 12JiCC, health and safety of the public and providing RCP seal injection. However, a review of F-A, Fl.10 Rod Hanger Chapter 15 of the UFSAR (15.4, 15.5, and 15.6) did not find any accident where operation of the charging pumps are credited in preventing or mitigating the consequences of an accident. It's therefore reasonable to conclude that the Chemical and Volume Control System does not perfonn a safety function as defined in the DBD and a mission time is not applicable.
The hanger of concern (CPL-123-CC) is a dead weight rod hanger and is not credited for upset or emergency conditions of the charging line 3-CH-14 (Cale CH-13-7513B). Since the accident loads envelope deadweight loads, and the hanger remains in a functioning condition (i.e., bolt, nut and clamp are not failed), having one thread less than full thread engagement does not affect operability.
SM Signature N. Roh 317117 @ 1046 RE: NCR# 02105770, Evaluation EV-17-001
Examination Category and Item Number B-Q, B16.20 Item Description 105NECT-B, Steam Generator "B" Tubes I 058/ECT -C, Steam Generator "C" Tubes form OAR-1 OWNER'S ACTIVITY REPORT Evaluation Description Number of tubes plugged during the Inspection outage for each active degradation mechanism:
No tubes were plugged in 1he A SG, one (I) tube was plugged in 1he B SG end five (5) tubes were plugged in the C SG. ll1e tube in B SG was plugged for wear at a tube support plate. Two (2) tubes in C SG were plugged for wear from a foreign object. Three (3) tubes in C SG were plugged preventively to bound a foreign object.
ASG BSG CSG Row I Colum11 Row I Colunr11 Row Column None 37 I
73 37 22 30 13 31 13 29 13 29 12 The total number and percentage of tubes plugged to date arc:
Steam Generator*
ASG BSG CSG Total Pl11f!s oresenl orior 10 ROJO 9
23 17 49 Plul!s added in R030 0
I 5
6 Total Plul!s 9
24 23 55
% Plmu!ed 0.3 0.8 0.7 0.6
- There are 3214 wbes per generator.
The results of condition monitoring, Including the results of tube pulls and In-situ pressure testing are as follows:
The cumulative SG EFPY for R027 was 21.82, R028 was 23.27, R029 was 24.67, and R030 was 26.26.
As of R030, the Robinson steam generators had operated 25.39 EFPY since the first in-service inspt.-ction after replacement. In total, the Robinson steam generators had operated 26.26 EFPY since replacement.
Condition Monitoring structural and accident induced leakage integrity was demonstrated for A VB, TSP, FOB and FO wear.
An NOE mnximum depth call of 49.5%TW or less for AVB wear is sufficient to demonstrate a minimum degraded tube burst pressure of 3~P. 4350 psi, at 0.95 probability with 50°a confidence.
TI1e worst case depth call for A VB wear observed during the inspection was an NOE depth of 31%TW.
An NOE maximum depth call of 54.5%TW or less for TSP wear is sufficient to demonstrate a minimum degraded tube burst pressure of J~P. 4350 psi, et 0.95 probability with 50°0 confidence.
The worst case depth call for TSP wear observed during the inspection was an NOE depth of 40%TW.
An NOE maximum depth call of57.0%TW or less for FOB wear is sufficient to demonstrate a minimum degraded tube burst pressure of J~P, 4350 psi, et 0.95 probabilily with 50° o confidence.
The worst case depth call for TSP wear observed during the inspection was an NOE depth of 13%TW.
An NOE maximum depth call of57.0%TW or less for FO wear is sufficient to demonstrate a minimum degraded tube burst pressure of J~P. 4350 psi, at 0.95 probebilhy with 50°a confidence.
The worst case depth call for FO wear observed during the inspection was an NOE depth of 42%TW.
No degradation was detected in the plug visual or bowl clodding inspections.
No in-situ tests or tube pulls were pcrfonned.
RE:NCR#2107342, WO #20016375, 20016428
Form OAR-1 OWNER'S ACTIVITY REPORT Examination Item Category and Description Evaluation Description Item Number Pressure Test Program B-P,B 15.10 EST-083-1, Approximately 114 teaspoons of dry white boric acid at tee titting. No active leakage. Disassembled
\\Bollt'f.! conneclion PS-953A fittings, cleaned and inspected in accordance with AD-EG-PWR-1611, reassembled fittings.
c:tamin3Jion)
Reference:
WR 20063109 WO 20150358 NCR 2106135.
B-P,BlS.10 EST-083-1, Approximately 1/4 teaspoons of dry while boric acid at tee fitting at top of bellows. No active (Bollt'l.I COllllL'Cliun LX-511AA leakage. Cleaned and inspected in accordance with AD-EG-PWR-1611.
Reference:
WR 20063111 c:tnmin:uion)
W020150361 NCR2106135 B-P.815.10 EST-083-1, Approximately 1/4 Teaspoons of dry white boric acid at flange mating surface. Not in contact with (Bolt~'l.I corut~'Clion body to bonnet studs. No active leakage. Cleaned and inspected in accordance with AD-EG-PWR-cJ1a01inationl RC-536 1611.
Reference:
WR 200631 12 WO 20150362 NCR 2106135 B-P.BIS.IO EST-083-1, Ariproximntely 112 tsp of dry white-blueish boric acid at the packing area. No active leakage.
(Bolled COllllL"Clion C caned and inspected in accordance with AD-EG-PWR-1611.
Reference:
WR20063I15 WO examination)
PCV-455A 20150363 NCR2106135 B-P,B 15.10 EST-083-1, 2TBSP, DRY WHITE BORIC ACIDATTHE PACKING AREA. NO ACTIVE LEAKAGE.
(BoltL-<l connection Cleaned and inspected in accordance with AD-EG-PWR-1611.
Reference:
WR 20063121 WO cxamin;ition)
RHR-750 20150364 NCR2106135 C-H,C7. IO EST-078.
Dry white boric acid at packing 1-112 tsp. No Active Leakage. Cleaned and inspected in Sl-898C accordance with AD-EG-PWR-161 I.
Reference:
WR 20029555 C-H.C7.IO EST-078, Dry white boric acid at packing 2 tsp. No Active Leakage. Cleaned and inspected in accordance Sl-898J with AD-EG-PWR-1611.
Reference:
WR 20029556 C-H.C7.IO EST-078, Dry white boric acid at packing l
- 112 tsp. No Active Leakage. Cleaned and inspected in Sl-888L accordance with AD-EG-PWR-1611.
Reference:
WR 20029557 5.4 ml/min lenk observed at pump casing flange. Middle section of the casing on east-side, looking C-H,C7. IO EST-078, south. No leakage observed when the pump was secured. B-51-Pump is Normally Out of Service Sl-PUMP-B equipment "Swing Pump".
Reference:
WO 20028658/WO 20035437, NCR 1966533 Attribute 3A OPER/FUNC and Ass!!n 02. Reference EC 82347Rl(EC 282347RI).
C-H,C7.10 EST-078, Dry white boric acid on the valve packing. Less than I tsp on packing. No other components Sl-898G affected. Clean and inspect in accordance with AD-EG-PWR-1611.
Reference:
WR 20029559 C-H,C7.IO EST-078, Dry white boric acid on the valve packing. Less than I tsp on packing. No other compont."flts SI-898H affected. Clean and inspect in accordance with AD-EG-PWR-1611.
Reference:
WR 20029561 C-H.C7.10 EST-078, Dry white boric acid on the valve packing. Less than I tsp on packing. No other components SI-895P affected. Clean and inspect in accordance with AD-EG-PWR-1611.Refcrence: WR 20029562 D-B, 02.10 EST-084, VT-I exam ofremoved stud due to boric acid in contact with stud at body to body connection. VT*
SFPC-742 I stud exam was satisfactory. Reference WO 13379359 Task 01, 03 and NCR 682334.
C-H,C7.10 EST-078, Dry white boric acid on the valve packing. Less than I tsp on packing. No other components SI-895A affected. Clean and inspect in accordance with AD-EG-PWR-1611.Refcrcnce: WR 20029563 EST-091, LT-969; Approximately I tsp. Dry white boric acid observed at the fitting region. No active leakage C-H,C7.10 LT-969 or degradation reported. Clean and inspect in accordance with the boric acid program, attachment 3, AD-EG-PWR-I 611.
Reference:
WR 20004481 D-B, 02.10 EST-084, VT-I exam of removed stud due to boric acid in contact with stud at body to body conm.-ction. VT-SFPC-742 I stud exam was satisfactory. Reference WO 13379359 Task 0 I, 03 and NCR 682334.
C-H,C7. IO EST-078, Dry white boric acid on the valve packing. Less thnn I tsp on packing. No other components SI-895A affected. Clean nnd inspect in accordance with AD-EG-PWR-1611.
Reference:
WR 20029563 EST-091, Sl-838D: Approximately 1 tsp. Dry white boric acid observed at the bonnet. No active leakage or C-H.C7. IO SI-8380 degradation reported. Non-bolted connection. Clean and inspect in accordance with the Boric Acid Program, Attachment 3. AD*EG-PWR-1611.
Reference:
WR 20004482 EST-091, Sl-838H: Approximately 1 L~p. Dry white boric acid observed at the fitting region. No active C-H,C7.IO SI-838H leakage or degradation reported. Clean and inspect in accordance with the Boric Acid Program,, AD-EG-PWR-1611.
Reference:
WR 20004483 EST-091, Sl-892G: Approximately I tsp. Dry white boric acid observed at the packing region. No active C-H,C7.10 SI-892G leakage or degradation reported. Clean and inspect in accordance with the Boric Acid Program,, AD-EG-PWR-1611.
Reference:
Form OAR-1 OWNER'S ACTIVITY REPORT Examination Item Category and Description Evaluation Description Item Number EST-091, Sl-871: Approximately I tsp. Dry white boric acid observed at the bonnet region. No active leakage C-H, C7.10 SI-87I or degradation reported. Bonnet bolting not affected. Cleon and inspect in accordance with the Boric Acid Proirram, Atlachment 3, AD-EG-PWR-1611. WR 20004486 EST-127, EST* 127 item. Inactive dry, white boric acid approx 114 tsp at packing. Cleon and inspect in C-H, C7.10 CVC-304C accordance with AD*EG-PWR-161 I BACCP.
Reference:
WR 20061707 WO 2014 7572 NCR 2100362 EST-127, EST-127 item. Inactive dry, white boric acid approx. 118 tsp nt packing. Clean and inspect in C-H,C7. IO CVC-3040 accordance with AD*EG-PWR-1611 BACCP.
Reference:
WR 20061708 WO 2014 7571 NCR 2100362 EST-I27, EST-127 ilcm. Inactive dry, white boric acid approx. 1/2 tsp nt packing. Clean and inspect in C-H,C7.10 CVC-304L accordance with AD*EG-PWR-1611 BACCP.
Reference:
WR 20061709 WO 2014 7404 NCR 2100362 EST-I29, EST-129 item. Inactive dry, white boric acid approx. 3/4 tsp nt packing. Clean and inspect in C-H, C7.10 SI-87SJ accordance with AD-EG-PWR-1611 BACCP.
Reference:
WR 20061710 WO 20147394 NCR 2100369.
EST-129, EST-129 item. Inactive dry, white boric acid approx. 3/4 tsp nt packing. Clean and inspect in C-H, C7.10 SI-86SB accordance with AD-EG-PWR-1611 BACCP.
Reference:
WR 20061711WO20147381 NCR 2100369.
EST-129, EST-129 item. Inactive dry, white boric acid approx. I tbsp at packing. Clean and inspect in C-H,C7.IO Sl-8SIA accordance with AD-EG-PWR-1611 BACCP.
Reference:
WR 20061713 WO 20147407 NCR 2100369.
PS-956G: EST-083-2 item. Wetted boric acid droplets collected at the tubing to fitting connection of PS-956G. Residue is localized at the tubing. Clean and inspect per AD-EG-PWR-1611. During repair of PS-956C (NCR 2113939) it was determined the leak indications present on PS-9568/PS-EST-083-2, 956G was n result of spray from PS-956C. Following repair of PS-956C, PS-9568/PS-956G were B-P, 815.10 PS-956G/C also retested with no leakage identified.
PS-956C: during the perfonnnnce of OST-909 step 7.2.5 a leak of approitimately one gallon per minute was discovered on PS-956C on the union between the pipe and the valve. Located leaking fitting. Tightened Swagelok nut approx. I full tum.
Reference:
WO 20157817/WO 20157797(PS-956C). NCR 2114167 /NCR 2113955 Attribute 3A OPER/FUNC and NCR 2113939 (PS-956C).
PS-9568: EST-083-2 item. Wetted boric acid droplets collected nt the tubing to titting connection EST-083-2, of PS-9568. Residue is localized at the tubing. Clean and inspect per AD-EG-PWR-1611. During repair of PS-956C (NCR 2113939) it was determined the leak indications present on PS-9568/PS-B-P, BIS.IO PS-9S6B 956G was n result of spray from PS-956C. Following repair of PS-956C, PS-9568 PS-956G were also retested with no leakage identified. WO 20157814 NCR 2114167 I NCR 2113954 Attribute 3A OPER/FUNC and NCR 2113939 (PS-956C)
EST-083-2, EST-083-2 item. Detector was identified to have I teaspoon buildup of dry boric acid nt detector B-P, BIS.to Seal Table Det.
fitting assembly. No active leak reported. Perform clean and inspection in accordance with AD-EG*
H-13 PWR-1611ATI.3.
Reference:
WO 20157829 NCR 2114167.
EST-083-2, EST-083-2 item. 112 teaspoon dry white boric acid at packing gland. No active leak observed.
B-P, BIS.IO SI-86SB Perfonn cleaning and inspection task in accordance with AD-EG-PWR-1611 ATT. 3. WO 20157826 NCR 2114167.
EST-083-2, A I /4 tsp of dry boric acid on the outlet flange of RC-575 not in contact with the bolts. Clean and B-P, BIS.IO RC-S75 inspect in accordance with AD-EG-PWR-1611 BACCP ATT. 3 is required. WO 20157812 NCR 2114167 EST-083-2, A leak of approximately 50 drops per minute was discovered ot tubing adaplor to rc-591 fitting B*P, BIS.IO RC-S9 I Fitting during the EST-083-2 walkdown. Tightened fitting to stop leak. WO 20157800NCR2t14167 and NCR 2113953.
The nbove Engineering Surveillance Tests and nil exceptions were addressed by the normal work request process, corrective action program and retained as pennanent r1.-cords, ns required, which may be obtained through Duke Energy Progress, Inc., Document Control Services.
Form OAR-1 OWNER'S ACTIVITY REPORT TABLE2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Class Item Description Description of Work Date Repair/Replacement Completed Plan Number l
RC-S51A Replace Valve Disc and Nozzle 3/6/2017 20015491 -0 l I
RPV Closure Head Replace Closure Head Nut 3/23/2017 20015540-0 l Nut l
Steam Generator Install Plug in One Steam 3/14/2017 20016428-09 "B"
Generator Tube 1
Steam Generator Install Plug in Five Steam 3/14/2017 20016375-09 "C"
Generator Tubes RC-3-2404 Repair Welded Support I
RC-3-2405 8/30/2016 2054449-01 RC-3-2406 Attachments 2
RHR-PUMP-B Replace Casting I Stuffing Box 8/2412015 13329230-01 Extension 2
CH-13-5000 Replace Failed Bolt 11124/2015 13388608-0 I 2
BA-TNK-A-HTR-B Replace Flange Bolting 9/13/2016 13542966-01 2
RHR-782 Replace Valve Disc 3/12/2017 20016577-01 3
CVC-336 Replace Valve Bonnet 3/8/2017 13346958-0 l Note: Table 2 repair replacement activities required for continued service include all activities from 08tl8/2015up to llild including 06/ 12/2017. Any repair replacement documentation closed after 6/12/2017 will be documented in the next OAR-I Owner's Activity Report.