ML17347A383

RBS Ope Audit Report

ML17347A383
Person / Time
Site:	River Bend
Issue date:	01/08/2018
From:	Sayoc E NRC/NRR/DMLR/MRPB
To:	Maguire W Entergy Operations
Emmanuel Sayoc, NRR/DMLR/MRPB, 287-3716
References
CAC MF9757
Download: ML17347A383 (40)

Text

January 8, 2018 Mr. William F. Maguire Site Vice President River Bend Station, Unit 1 Entergy Operations, Inc.

5485 U.S. Highway 61 N St. Francisville, LA 70775

SUBJECT:

OPERATING EXPERIENCE AUDIT REPORT REGARDING RIVER BEND STATION, UNIT 1 LICENSE RENEWAL APPLICATION REVIEW (CAC NO.

MF9757)

Dear Mr. Maguire:

By letter dated May 25, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17153A282), Entergy Operations, Inc. (the applicant) submitted an application to the U.S. Nuclear Regulatory Commission (NRC) pursuant to Title 10 of the Code of Federal Regulations Part 54, Requirements for Renewal of Operating Licenses for Nuclear Power Plants, to renew the operating license NPF-47 for River Bend Station, Unit 1. On October 13, 2017, the NRC staff completed an Operating Experience Audit. The audit report is enclosed If you have any questions, please contact me by telephone at 301-415-4084 or via e-mail at Emmanuel.Sayoc@nrc.gov.

Sincerely,

/RA/

Emmanuel Sayoc, Project Manager License Renewal Project Branch Division of Materials and License Renewal Office of Nuclear Reactor Regulation Docket No. 50-458

Enclosure:

Audit Report cc w/encl: Distribution via Listserv

SUBJECT:

AGING MANAGEMENT PROGRAMS AUDIT REPORT REGARDING RIVER BEND STATION, UNIT 1 LICENSE RENEWAL APPLICATION REVIEW (CAC NO. MF9757) DATED DISTRIBUTION:

E-MAIL:

PUBLIC RidsNrrDmlr Resource RidsNrrDmlrMrpb Resource RidsNrrDmlrMenb Resource RidsNrrDmlrMphb Resource RidsNrrDmlrMccb Resource RidsNrrDmlrMvib Resource RidsNrrPMRiverBend Resource RidsRgn4MailCenter ESayoc, NRR AWong, NRR EOesterle, NRR SBloom, NRR DAlley, NRR SRuffin, NRR BWittick, NRR TMartinezNavedo, NRR SBailey, NRR LRegner, NRR TSherwin, OGC DMcIntyre, OPA SBurnell, OPA AMoreno, OCA JSowa, RIV BParks, RIV GPick, RIV JKozal, RIV CYoung, RIV GWerner, RIV VDricks, RIV tbrous1@entergy.com DLach@entergy.com TSCHENK@entergy.com alacey@entergy.com ADAMS Accession Number: ML17347A383

• Concurred via e-mail OFFICE PM:MRPB:DMLR LA:MRPB:DMLR PM:MCCB:DMLR BC:MRPB:DMLR PM:MRPB:DMLR NAME ESayoc YEdmonds (SLent for) BRogers EOesterle w/comments ESayoc DATE 12/26/17 12/22/17 12/28/17 1/3/18 1/8/18 OFFICIAL RECORD

Enclosure River Bend Station, Unit 1, License Renewal Operating Experience Audit Report I.

Introduction On October 2 through 13, 2017, the U.S. Nuclear Regulatory Commission (NRC) Division of Materials and License Renewal (DMLR) performed an audit of Entergy Louisiana, LLC and Entergy Operations, Inc. (EOI) (the applicant), River Bend Station, Unit 1 (RBS), as part of the NRC staffs review of the RBS license renewal application (LRA) at a facility located in Rockville, Maryland. The purpose of the audit was for the NRC staff to perform an independent review of plant specific operating experience (OE) to identify examples of age related degradation, as documented in the applicants corrective action program database. The regulatory bases for the audit was Title 10 of the Code of Federal Regulations, Part 54 (10 CFR Part 54), Requirements for Renewal of Operating Licenses for Nuclear Power Plants,. The staff also considered the guidance contained in NUREG-1800, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants, Revision 2 (SRP-LR) and NUREG-1801, Rev. 2, Generic Aging Lessons Learned (GALL) Report, dated December 2010.

II.

Background

The NRC staff performed the review to identify pertinent examples of OE, concerning age related degradation, as documented in the applicants corrective action program database. The identified OE examples will be evaluated during the staffs subsequent technical review and auditing of aging management programs (AMPs), time limited aging analyses (TLAAs) and aging management review (AMR) line items. The staffs identification and evaluation of pertinent OE and additional related documentation, provides a basis for the staffs conclusions on the ability of the applicants proposed AMPs and TLAAs to manage the effects of aging in the period of extended operation.

III.

Audit Activities The following sections discuss the areas reviewed by the staff and identified examples of pertinent OE.

LRA AMP B.1.1, Aboveground Metallic Tanks Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: corros, flaw, leak, tank, and through wall.

No significant plant-specific operating experience associated with the Aboveground Metallic Tanks program was noted by the staff during its review.

LRA AMP B.1.2, Bolting Integrity Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: bolt, preload, torque, loose, crack, leak, cap screw, corrosion, stress corrosion cracking, SCC, molybdenum, disulfide, and MoS2.

The table below lists the documents that were reviewed by the staff and were found relevant to the Bolting Integrity Program. These documents were identified in the staffs search of the

applicants operating experience database. The results of the review of relevant operating experience is documented in the AMP Audit Report (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17346A732).

Relevant Documents Reviewed Document Description Revision / Date Condition Report (CR)-RBS-2004 02144 Corrosion on underwater service water pump bolts 07/29/2004 CR-RBS-2009-01468 Corrosion on service water cooling motor operated valve bolt head 03/26/2009 CR-RBS-2009-06148 Inadequate torque of bolting in diesel generator 12/01/2009 CR-RBS-2009-02748 Oil leak and loose bolt on EGS-EG1BA 06/17/2009 WO#198581 Oil leak and loose bolt on EGS-EG1BA 06/17/2009 CR-RBS-2015-02393 Normal service water leaks from different bolts 03/26/2015 CR-RBS-2011-07429 Corrosion in bolts of fire water isolation valves 10/14/2011 WO#293656 Corrosion in bolts of fire water isolation valves 06/28/2012 CR-RBS-2015-06533 FitzPatrick operating experience on corrosion of cap screws applicable to River Bend Station 09/08/2015 LRA AMP B.1.3, Boraflex Monitoring Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: Boraflex, BADGER, Racklife, and neutron absorber.

The table below lists the documents that were reviewed by the staff and were found relevant to the Boraflex Monitoring Program. These documents were identified in the staffs search of the applicants operating experience database. The results of the review of relevant operating experience is documented in the AMP Audit Report (ADAMS Accession No. ML17346A732).

Relevant Documents Reviewed Document Description Revision / Date CR-RBS-2003-00053 Racklife Results 01/10/2003 CR-RBS-2011-06932 Boraflex Surveillance Program Document (BISCO) Missing 09/21/2011 CR-RBS-2012-02166 BISCO Document Found 03/27/2012 CR-RBS-2012-02995 Racklife Boron Loss Assumption Exceeded 05/02/2012 CR-RBS-2013-07478 Removal of Long-Term Surveillance Coupon 12/09/2013 LRA AMP B.1.4, Buried and Underground Piping and Tanks Inspection Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: buried, coat, corrosion, concrete, crack, wrap, wall loss, vault, underground, through wall, piping, min wall, microbiologic, loss of material, holiday, flaw, excavat, and leak.

The table below lists the documents that were reviewed by the staff and were found relevant to the Buried and Underground Piping and Tanks Inspection program. These documents were provided by the applicant or were identified in the staffs search of the applicants operating experience database. The results of the review of relevant operating experience is documented in the AMP Audit Report (ADAMS Accession No. ML17346A732).

Relevant Documents Reviewed Document Description Revision / Date CR-RBS-2013-00122 Visual Inspection of Buried Pipe Line CNS-750-497-004 01/08/2013 CR-RBS-2012-07706 Visual Inspection of Buried Pipe Lines CNS-006-251, LWS-004-586, and IAS-001-165 12/17/2012 CR-RBS-2012-07163 Visual Inspection of Buried Pipe Line CSH-016-054 11/19/2012 CR-RBS-2013-06354 UT Examination Readings Taken on Buried Pipe Line Number CWS-020-035-4 10/02/2013 CR-RBS-2010-04298 Cathodic Protection Test Station That Had Less Than The Acceptance Criteria of -0.850 Volts 08/31/2010

Document Description Revision / Date CR-RBS-2014-03095 Equipment Deficiencies on the Cathodic Protection System 06/26/2014 LRA AMP B.1.5, BWR Control Rod Drive (CRD) Return Line Nozzle Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: control rod drive, return line nozzle, crack, and weld.

No significant plant-specific operating experience associated with the BWR CRD Return Line Nozzle Program was noted by the staff during its review.

LRA AMP B.1.6, BWR Feedwater Nozzle Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: feedwater nozzle, crack, fatigue, and weld.

No significant plant-specific operating experience associated with the BWR Feedwater Nozzle Program was noted by the staff during its review.

LRA AMP B.1.7, BWR Penetrations Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: penetration, nozzle, safe-end, and cracking.

The table below lists the documents that were reviewed by the staff and were found relevant to the audit. These documents were provided by the applicant or were identified in the staffs search of the applicants operating experience database.

Relevant Documents Reviewed Document Description Revision / Date RBS B.1.7 Program Basis Document, License Renewal Program Book - BWR Penetrations Rev. 0 EN-FAP-LR-007 Evaluation of Aging Management Programs Rev. 6 CR-RBS-2002-01401 Enhanced VT-2 on weld, and accessibility issues 03/27/2003 CR-RBS-2017-06676 Inspection of nozzle to vessel weld cannot be confirmed 09/13/2017 LRA AMP B1.8, BWR Stress Corrosion Cracking Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: SCC, IGSCC, stress corrosion, crack, weld, and safe end.

The table below lists the document that was reviewed by the staff and was found relevant to the BWR Stress Corrosion Cracking Program. This document was identified in the staffs search of the applicants operating experience database. The results of the review of relevant operating experience are documented in the AMP Audit Report (ADAMS Accession No. ML17346A732).

Relevant Documents Reviewed Document Description Revision / Date CR-RBS-2010-05935 To achieve the goal of not performing inservice inspections behind the biological shield wall in Refueling Outage (RF) 17, it is necessary to include additional inservice inspection examination in the RF-16 scope in order to meet the percentage requirements of BWRVIP-75-A for welds susceptible to intergranular stress corrosion cracking.

11/15/2010 LRA AMP B.1.9, BWR Vessel ID Attachment Welds Program Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: BWRVIP, integral attachment, ID attachment, attachment weld, inservice, and inspection.

The table below lists the documents that were reviewed by the staff and were found relevant to the audit. These documents were provided by the applicant or were identified by the staff during its search of the applicants operating experience database or its review of CRs that were appropriately referenced and summarized in the operating history section of the applicants program evaluation report for LRA AMP B.1.9, BWR Vessel ID Attachment Welds. The results of the review of relevant operating experience is documented in the In-Office Audit Report.

Relevant Documents Reviewed Document Description Revision / Date RBS License Renewal Application, Section B.1.9 BWR Vessel ID Attachment Welds Revision 0 NUREG-1801, Chapter XI, Section (AMP)

XI.M9 Generic Aging Lessons Learned (GALL)

Report, AMP XI.M9, BWR Vessel ID Attachment Welds Revision 2 RBS License Renewal Application, Section 3.1 (Including LRA AMR Tables 3.1.1 and 3.1.2-1 in the Section 3.1)

Reactor Vessel Internals, and Reactor Coolant System Revision 0 RBS License Renewal Application, Appendix A, Updated Safety Analysis Report (USAR), Section A.1, Subsection A.1.9 BWR Vessel ID Attachment Welds Revision 0 RBS-EP 00006, Section 4.5 RBS License Renewal Project, Aging Management Program Evaluation Report, Class 1 Mechanical, BWR Vessel ID Attachment Welds Revision 0 RBS-ME-15-00001 RBS License Renewal Project, Aging Management Review of the Reactor Pressure Vessel Revision 0 EN-FAP-LR-007 Evaluation of Aging Management Programs Revision 6, 02/18/2015 EN-FAP-LR-004 Mechanical System Screening and Aging Management Reviews Revision 8, 08/24/2016 USAR, Chapter 3 Design of Structures, Components, Equipment, and Systems Revision 24 USAR Chapter 4 Reactor Revision 24 USAR Chapter 5 Reactor Coolant System and Connected Systems Revision 24

Document Description Revision / Date BWRVIP-48-A (EPRI TR No.

1009948)

BWR Vessel and Internals Project, Vessel ID Attachment Weld Inspection and Evaluation Guidelines 2004 Entergy Letter No.

RRB-47362 Request for Alternative in Accordance with 10 CFR 50.55a(a)(3)(i), Use of Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines in Lieu of Specific American Society of Mechanical Engineers (ASME) Code Requirements, River Bend Station (ADAMS Accession No. ML13141A257) 05/16/2013 NRC Relief Request and Safety Evaluation River Bend Station, Unit 1 - Request for Relief No. RBS-ISI-019, Alternative to Use Boiling Water Reactor Vessel and Internals Project Guidelines in Lieu of ASME Code,Section XI Requirements for the Fourth 10-Year Inservice Inspection Interval (ADAMS Accession No. ML14127A327) 05/30/2014 Condition Report Nos.

CR-RBS-2014-00253 and CR-RBS-2014-00016 Inspections per GE SIL 658 for Feedwater Sparger End Brackets 2014 RBS-EP-13-00004 RBS RF-17 Reactor Vessel Internals Management Program Post-Outage Report 05/13/2013 RBS-EP-15-00014 RBS RF-18 In-Vessel Visual Inspection (IVVI)

Final Report Rev. 0 LRA AMP B.1.10, BWR Vessel Internals Program Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: cracking, stress corrosion, embrittlement, wear, loss of preload, pitting, reactor internal, X-750, CASS, and fracture toughness.

The table below lists the documents that were reviewed by the staff and were found relevant to the audit. These documents were provided by the applicant or were identified by the staff during its search of the applicants operating experience database or its review of contractors reports (CRs) that were referenced and summarized in the operating history section of the applicants program evaluation report for LRA AMP B.1.10, BWR Vessel Internals Program.

The results of the review of relevant operating experience is documented in the AMP Audit Report (ADAMS Accession No. ML17346A732).

Relevant Documents Reviewed Document Description Revision /

Date CR-RBS-2013-04927 Condition Report for the Core Shroud Assembly (See summary on page 46 of RBS-EP-15-00003) 2013 CR-RBS-2015-01976 Condition Report for the Core Shroud H8 Horizontal Weld (See summary on page 50 of RBS-EP 00003) 2015 CR-RBS-2013-05645 Condition Report for the Low Pressure Coolant Injection (LPCI) Couplings and Their Welds (See summary on page 47 of RBS-EP-15-00003) 2013 CR-RBS-2013-04094 Condition Report for the Top Guide Assembly (See summary on page 45 of RBS-EP-15-00003) 2013 CR-RBS-2000-00686 Condition Report for the Steam Dryer Support Ring Indications - Year 2000 Inspections (See summary on page 43 of RBS-EP-15-00003) 2000 CR-RBS-2006-01770 Condition Report for Steam Dryer Support Ring Indications - Year 2006 Inspections (See summary on pages 43 and 44 of RBS-EP-15-00003) 2006 CR-RBS-2008-00809 and CR-RBS-2008-00971 Condition Report for New Steam Dryer Bank Vertical Weld Indications - Year 2008 Inspections (See summary on page 44 of RBS-EP-15-00003) 2008 LRA AMP B.1.11, Coating Integrity Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: blister, block, clog, coat, delam, flak, foul, holiday, lined, lining, peel, spall, and wear.

No significant plant-specific operating experience associated with the Coating Integrity program was noted by the staff during its review.

LRA AMP B.1.12, Compressed Air Monitoring Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: instrument air, air, and leak.

No significant plant specific operating experience associated with the Compressed Air Monitoring program was noted by the staff during its review.

LRA AMP B.1.13, Containment Inservice Inspection - IWE Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: bellows, blister, bolt, containment corros, coat, degrad, drywell, IWE, loss of material, pit, and suppression.

No significant plant-specific operating experience associated with the Containment Inservice Inspection - IWE Program was noted by the staff during its review.

LRA AMP B.1.14, Containment Leak Rate Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: LLRT [local leak rate test], ILRT [integrated leak rate test], valve, Secondary Bypass Leakage, and Airlock.

The table below lists the documents that were reviewed by the staff and were found relevant to the Containment Leak Rate program. These documents identified in the staffs search of the applicants operating experience database. The results of the review of relevant operating experience is documented in the AMP Audit Report (ADAMS Accession No. ML17346A732).

Relevant Documents Reviewed Document Description Revision / Date CR-RBS-2008-01906 Leakage Path from the Reactor Pressure Vessel (RPV) to the Drywell Sumps was observed during the ILRT:

03/01/2008 CR-RBS-2008-01924 Identifies RVP leakage. Identifies valve V107 as the valve expending water 02/26/2008 CR-RBS-2008-02009 Identifies leak path (through one or more scram inlet valves) 02/27/2008 CR-RBS-2016-00401 Performance of personnel airlocks 10 CFR Part 50 Appendix J testing.

01/16/2016 CR-RBS-2014-04151 No process mechanism providing running LLRT summation. Since 1999 summation has not been kept as noted in NEI 94-01 and NRC Inspection Procedure 61720.

08/21/2014

Document Description Revision / Date CR-RBS-2016-00401 Conflict between procedure SEP-APJ-004 and TS (Drywell Isolation Valves). SR 3.6.5.3.3 states that the frequency of verifying each drywell isolation manual valve and blind flange is required to be closed during accident conditions, is closed; frequency of testing to be prior entering MODE 2 or 3 from MODE 4, if not performed in the previous 92 days. SEP-APJ-004 Note 25 limits testing to 20 months.

01/16/2016 LRA AMP B.1.15, Diesel Fuel Monitoring Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: biological, fuel oil, block and tank.

The table below lists the documents that were reviewed by the staff and were found relevant to the diesel fuel monitoring program. These documents were identified in the staffs search of the applicants operating experience database. The results of the review of relevant operating experience is documented in the AMP Audit Report (ADAMS Accession No. ML17346A732).

Relevant Documents Reviewed Document Description Revision / Date CR-RBS-2015-05171 Strainer blockage 07/20/2015 CR-RBS-2016-03266 Fuel Sampling after draining 6 Gallons 04/28/2016 LRA AMP B.1.16, Environmental Qualification (EQ) of Electrical Components Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: environmental qualification equipment, environmental qualification component, and environmental qualification - aged related degradation.

The table below lists the documents that were reviewed by the staff and were found relevant to the Environmental Qualification of Electrical Components. These documents were identified during the staffs search of the applicants operating experience database. The results of the review of relevant operating experience is documented in the In-Office Audit Report Document.

Relevant Documents Reviewed Document Description Revision/ Date CR-RBS-2009-01231/35 NRC Inspection Report (IR) 08-06 for Component Design Basis Inspection (CDBI) identified the following Non-Cited Violation (NCV). The IR states With the 12/31/09

exception of those molded-case circuit breakers associated with containment isolation circuits (Technical Requirements Manual Section TR 3.8.11 and TR 3.8.12); molded-case circuit breakers were not under periodic test and preventive maintenance (PM) program that assessed age-related degradation of electrical components in the breakers.

CR 09-RBS-1231/35 was initiated to ensure the NRCs concerns were adequately addressed regarding the molded-case circuit breakers.

LRA AMP B.1.17, External Surfaces Monitoring Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: corros, leak, loss of material, piping, and rust.

The table below lists the documents that were identified during the staffs search of the applicants operating experience database and were found relevant to the External Surfaces Monitoring program. The results of the review of relevant operating experience is documented in the AMP Audit Report (ADAMS Accession No. ML17346A732).

Relevant Documents Reviewed Document Description Revision / Date CR-RBS-2014-03098 Service Water Primary 20 inch return header has pipe weld degradation, around entire diameter up to 1/4 inch deep. This degradation appears to be due to continuous rain water runoff from various components above the weld. The SWP piping is severely rusted, pitted and brittle in two areas of the weld, directly on top and bottom of the pipe.

06/26/2014 CR-RBS-2014-03643 General coating degradation on Standby Service Water piping and associated components in the plant area when the F-Tunnel and G-Tunnel connect. General surface coating degradation is present on the exterior of the Service Water Piping at this location.

07/24/2014

Document Description Revision / Date CR-RBS-2015-03429 Leak from SWC-006-059. The coating around the valve, pipe, and tube steel support has degraded and the underlying metal is corroded. This leak is also causing ponding at the base of pipe supports SWP-PSR8252A4 and SWP-PSR8232A4 which has caused corrosion of the tube steel connection to the embed plate in the slab.

05/08/2015 CR-RBS-2016-02355 NRC Resident Observations: 10) SWP Corrosion control. Located in various tunnels. Numerous signs of corrosion were observed. How is corrosion being managed in these areas? What is effect on SWP? Is everything in spec? What is monitoring corrosion of equipment? What is threshold for action?

03/22/2016 LRA AMP B1.18, Fatigue Monitoring Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: fatigue, cycle, crack, usage factor, and CUF.

The table below lists the documents that were reviewed by the staff and were found relevant to the Fatigue Monitoring Program. This documents were identified in the staffs search of the applicants operating experience database. The results of the review of relevant operating experience are documented in the AMP Audit Report (ADAMS Accession No. ML17346A732).

Relevant Documents Reviewed Document Description Revision / Date CR-RBS-2016-00656 The FatiguePro software uses the COLLECT program to retrieve cycle and fatigue related data from the ERIS computer. During the retrieval of Cycle 18 data, it was noticed that the COLLECT program unexpectedly stopped automatically recording data from November 2012 to September 2013.

1/22/2016 CR-RBS-2017-05964 The procedure for fatigue management (EDP-MP-05) has outdated information, calculations and other technical issues. These should be resolved as part of the license renewal enhancements for the Fatigue Management Program.

8/10/2017

LRA AMP B.1.19, Fire Protection Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: Halon 1301, fire suppression agent, fire barriers, fire wraps, fire damming material, fire penetration seals, shrinkage, and fire doors.

The table below lists the documents that were reviewed by the staff and were found relevant to the fire protection program. These documents were identified in the staffs search of the applicants operating experience database. The results of the review of relevant operating experience is documented in the AMP Audit Report (ADAMS Accession No. ML17346A732).

Relevant Documents Reviewed Document Description Revision / Date CR-RBS-2008-04282 During the performance of FPP-0101 Inspection H-5 Halon System, normal switch gear, CAS below floor, system switch is in on the reserved bottle. H-5 Reserve is out-of-service due to low pressure, but not empty. H-5 main bottle is full and is ready for service.

Switch needs to be on the main bottle.

07/08/2008 CR-RBS-2008-05747 Control Building operators found three normally closed fire doors slightly open and unlatched.

09/30/2008 CR-RBS-2012-00578 Thermo-Lag wrap on conduits ICX152 RE and ICX152 RF is deteriorating.

01/24/2012 CR-RBS-2012-06706 The Fukushima Flooring Walk-down identified two cracks in concrete that exceeded 0.04 width.

10/25/2012 CR-RBS-2013-00857 NS-123-11 fire door leading from T-Tunnel 123 to hot machine shop stairwell will not close and latch shut on its own.

02/13/2013 CR-RBS-2014-00514 While performing the Maintenance Rule Structural Inspection of the Control Building Division II, two deficiencies were noted: (1) an 1/8 cracking on the fire proof coating on the overhead girders supporting the 116 elevation, and (2) one column of the west side of the room showed longitudinal cracks on the cement-like fireproofing.

02/04/2015 CR-RBS-2015-01868 SRV RV41D and SRV RV47D have damaged on missing divisional separation fire wrap.

03/10/2015

LRA AMP B.1.20, Fire Water System Program Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: biofoul, block, clog, coat, corros, flaw, foul, leak, microbiologic, MIC, pit, recur, rupture, sprinkler, tank, and through-wall.

The table below lists the documents that were reviewed by the staff and were found relevant to the Fire Water System program. These documents were identified in the staffs search of the applicants operating experience database. The results of the review of relevant operating experience is documented in the AMP Audit Report (ADAMS Accession No. ML17346A732).

Relevant Documents Reviewed Document Description Revision/ Date CR-RBS-2007-4985 Leaking sprinkler head in the turbine building.

11/09/2007 CR-RBS-2008-0600 Crack detected on both sides of the 90 elbow on the water gong alarm line for valve FPW-98.

10/15/2008 CR-RBS-2009-0694 FPW-V164 juncture and piping is greatly corroded. The piping downstream of where the valve joins the pipe is visibly pitted by the corrosion. The floor underneath the valve is rust stained.

02/09/2009 CR-RBS-2009-2516 During execution of WO 183858 it was noted that both runs of vertical piping had extensive corrosion where the pipe nipples were screwed into the valves. On close examination, the piping is leaking because the threads are deteriorated from the inside.

02/09/2009 CR-RBS-2010-0160 During inspection of FPW-STR6A the inlet piping at the strainer has a large amount of rust build up on the pipe. There are rust corrosion spots inside pipe, about the size of a silver dollar. The pipe has a restriction of flow but it is not totally plugged.

0/12/2010 CR-RBS-2010-1240 A corrosion spot was detected the on piping tee to FPW-P2. A pre-inspection walk down of the area identified a small amount of water seepage at the corrosion spot.

03/18/2010 CR-RBS-2010-6444 The tee upstream of FPW-V151 has a small through-wall leak that has water seeping out of it.

12/09/2010

CR-RBS-2011-6297 Mud was found in the SWC-FN1E riser pipes.

Mud has accumulated in the dead end of the riser pipes.

08/23/2011 CR-RBS-2012-1511 This CR recommends pro-active replacement of all pipe and fittings comprising the fire protection water jockey pump (FPW-P3) discharge piping.

The identified condition does not currently cause fire protection equipment to be inoperable or unavailable. The discharge piping of FPW-P3 has excessive corrosion and leakage.

02/27/2012 CR-RBS-2012-4629 While performing a monthly walk down of the degraded suction tee (FPW-010-073) to the electric driven fire pump (FPW-P2), a step change in degradation was noticed. Based on visual inspection of the component and reinforced by the two visible areas on the tee, water is seeping out.

07/16/2012 CR-RBS-2013-3371 There is a pin hole size leak in the pipe elbow of FPW-P3, fire water jockey pump, discharge into FPW-P2, electric fire pump, header. The hole is leaking about 25 drops per minute (dpm).

04/29/2013 CR-RBS-2014-1059 Corrective Action #14 was issued to document the repair of a through-wall leak on line FPW-014-070 that was identified under CR-RBS-2005-03787.

03/04/2014 CR-RBS-2014-4979 During the removal of a tagout on FPW-P2 (motor driven fire pump), the pump and both diesel fire pumps (FPW-P1A and FPW-P1B) started automatically. Upon investigation, operators concluded that the sensing line to FPW-PS107, the pressure switch for the motor driven fire pump, must have become clogged.

10/08/2014 CR-RBS-2014-5761 There is a pin-hole leak in FPW-P3 (jockey pump) discharge line in the electric motor driven fire pump room above the eyewash station. It is dripping approximately 4-8 dpm.

11/11/2014 CR-RBS-2015-6244 During rounds it was noted by the outside operator that there was a noticeable amount of water on the floor by the jockey fire pump. Upon further investigation, a small drip on the pipe was found in between FPW-V112 and FPW-V117.

08/27/2015

The operator wiped it down and noticed a small pin-hole leak in this section of piping.

CR-RBS-2016-4235 The chemistry of the fire protection water in the storage tanks is monitored each quarter. During sampling, about 200 milliliters of rusty water drained out. Over the last few times that these samples have been collected, the sample flow has been decreasing.

06/07/2016 CR-RBS-2016-4759 The main control room received a report that there was a rupture on the main fire header in the main admin building/warehouse and that the leak is spraying on safety-related standby motors, which have their associated space heaters energized 06/07/2016 CR-RBS-2016-8164 A 60 dpm leak was identified coming from a joint in the fire water jockey pump discharge line to the B diesel fire pump. The leak is in the section of the pipe that is in the B diesel fire pump room, at the pipe support that is supporting this discharge line.

12/04/2016 CR-RBS-2016-8305 The three quarter inch piping between FPW-V195, the discharge header drain valve for FPW-P1B, diesel driven fire pump, is degraded and has a pinhole leak where it ties into piping.

12/11/2016 LRA AMP B.1.21, Flow-Accelerated Corrosion Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: cavit, FAC, flow accelerated corrosion, min wall, and piping.

The table below lists the documents that were identified during the staffs search of the applicants operating experience database and were found relevant to the Flow accelerated corrosion program. The results of the review of relevant operating experience is documented in the AMP Audit Report (ADAMS Accession No. ML17346A732).

Relevant Documents Reviewed Document Description Revision / Date CR-RBS-2009-04977 FAC #410 (FWS009035RL1) located on line FWS-012-035 has required min wall thickness of 0.736. Current measured wall thickness is 0.744. Component is acceptable based on a 14-month cycle 16.

10/03/2009 CR-RBS-2010-00610 2009 EPRI [Electric Power Research Institute] reported bug in CHECWORKS software that affects all versions. Bug only affects modeled pipe where partial replacements have occurred.

02/04/2010 CR-RBS-2010-03404 Evaluating OE30018, unit shutdown due to cavitation induced leak in core spray piping.

All RBS ECCS min flow piping downstream of an orifice was analyzed. OE is applicable where high velocities (>20 feet per second (fps)) exist. Five have >20 (20.9fps) and five have near 20 (18.88fps).

07/27/2010 CR-RBS-2011-01709 FAC #412 Class 1 Feedwater elbow reading is 1.325. Tcrit = 1.461 Tnom = 1.788 (low reading appears to be counterbore on the elbow side of weld but pipe clamp prevents further readings to be taken.

02/02/2011 CR-RBS-2013-01348 FAC item 219 (CNM027076EL1) expanding elbow on line CNM-030-085 not acceptable.

A very localized area (1 inch by 1 inch) contains a low reading of 0.350 inches at the toe of the weld in the downstream attached piping. Additional engineering analysis should be performed to accept the component or repair degraded area.

02/22/2013 CR-RBS-2015-05024 Ran with MSR out of service for 2 weeks due to a steam leak on manway Increased potential for FAC and erosion due to extended operation of normally isolated lines.

Recommends inspections of specific components.

07/14/2015

Document Description Revision / Date CR-RBS-2015-08248 Potential valve leak: Perform FAC inspection on downstream piping DTM-00 4-151 during RF19 or next plant shutdown. Perform FAC inspection on condenser connection 29 during RF19.

11/17/2015 LRA AMP B.1.22, Inservice Inspection Audit Activities. The staff conducted an independent search of the applicants operating experience database using the keywords: cracking, leak, wear, loss of material, failure, degradation, flaw, inspection, repair, and weld.

The table below lists the documents that were reviewed by the staff and were found relevant to the audit. These documents were provided by the applicant or were identified in the staffs search of the applicants operating experience database.

Relevant Documents Reviewed Document Description Revision / Date RBS B.1.22 Program Basis Document, License Renewal Program Book - Inservice Inspection Rev. 0 EN-FAP-LR-007 Evaluation of Aging Management Programs Rev. 6 CR-RBS-2002-01401 Enhanced VT-2 on weld, and accessibility issues 03/27/2003 CR-RBS-2002-00255 Indications detected in weld in RCIC during mag particle examinations 02/12/2002 CR-RBS-2007-05190 Class 2 weld under-counted by 354 welds 11/20/2007 CR-RBS-2013-05645 Missed inspection on Internals Weld 6-1a 08/28/2013 CR-RBS-2013-06927 Miss-identified weld resulted erroneous OAR-1 submitted 11/04/2013 CR-RBS-2014-02350 Reactor Vessel Head Flange leakoff line not inspected. Potential Code non-compliance 05/13/2014 CR-RBS-2015-03160 Incorrect database resulted miss-counted Class 3 Cat D-A welds. Resulted fewer welds being VT examined during Intervals 1 and 2. Code Compliance issue.

04/28/2015 CR-RBS-2015-0577 Incorrect database resulted miss-counted support attachments. Resulted fewer supports being VT examined during Intervals 1 and 2. Code Compliance issue 07/15/2015 RBG-47100 Inservice Inspection Plan for the Third 10-year Interval 01/17/2011 RBG-47729 Resubmittal of Owners Activity Report 01/09/2017 ML010430333 NRC Inspection Report 05000458/2008002 05/09/2008 LO-RLO-2011-00108 Containment Inservice Inspection focused assessment 12/03/2011 LO-RLO-2011-00039 Performance Snapshot Assessment -

Inservice Inspection activities 02/23/2016

LRA AMP B.1.23, Inservice Inspection - IWF Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: IWF, hanger, support, pipe support, ASME, corrosion, and bolt.

The table below lists the documents that were reviewed by the staff and were found relevant to the Inservice Inspection - IWF program. These documents were either provided by the applicant or were identified in the staffs search of the applicants operating experience database. The results of the review of relevant operating experience is documented in the AMP Audit Report (ADAMS Accession No. ML17346A732).

Relevant Documents Reviewed Document Title Revision / Date CR-RBS-2015-05077 Pipe rupture restraints not included in the inservice inspection program (ISI) program database 07/15/2015 CR-RBS-2015-03160 Fewer visual examinations selected and performed than required by the ASME Code for ISI Intervals 04/28/2015 CR-RBS-2016-04848 Failure to perform a successive inspection per ASME IWF-2420 06/28/2016 CR-RBS-2005-04099 VT-3 inspection of spring can found the field set dimension off scale and lock nut loose 12/6/2005 CR-RBS-2005-03856 Documentation of the First Interval ASME Section XI examination for certain components was not clearly documented 11/09/2005 CR-RBS-2011-01793 Conditional release of a snubber transferred from Grand Gulf Nuclear Station, Unit 1 due to supporting documentation not available for procurement engineering (like for like) 02/03/2011 CR-RBS-2014-05427 Review of ISI database indicated that some snubber support locations were missing. All snubbers were determined to be correctly documented in the separate snubber program database.

10/27/2014 CR-RBS-2016-03928 Discrepancy in equipment database. Pipe support incorrectly listed as non-safety-related. Corrected to list support as ASME Code Class 3 Safety-Related 05/24/2016

LRA AMP B.1.24, Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: crane, inspection, NUREG 0612, and ASME B30.2.

The table below lists the documents that were reviewed by the staff and were found relevant to the B.1.24 Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems. These documents were provided by the applicant/identified in the staffs search of the applicants operating experience database. The results of the review of relevant operating experience is documented in the AMP Audit Report (ADAMS Accession No. ML17346A732).

Relevant Documents Reviewed Document Description Revision / Date WO-RBS-52457855 Perform Annual Crane Inspection (Fuel Building Bridge Crane) 12/04/2013 WO-RBS-52514220 Perform Annual Crane Inspection (Radwaste Building Crane) 08/26/2014 WO-RBS-52530812 Perform Annual Crane inspection (Fuel Building Crane) 12/032014 WO-RBS-52585623 Perform Annual Crane inspection (Radwaste Building Crane) 08/27/2015 CR-RBS-2007-05557 Polar Crane: Gaps in Heavy Load Lifting (maintenance and lifting procedures for RPV and drywell heads, NUREG 0612 sling and rigging requirements - resolved (3CAs),

procedures revised) 12/14/2007 CR-RBS-2009-0561 Fuel Building Bridge Crane: Modified crane by welding a drip panel to assembly of the 15 ton hook. No design documentation for alteration found. Concerns for existing welds resolved (5CAs) by testing the 15 ton hook to ASME B30.2 requirements (WO 19071).

02/01/2009 LRA AMP B.1.25, Internal Surfaces in Miscellaneous Piping and Ducting Components Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: biofoul, crack, corrosion, wall loss, through wall, piping, foul, leak, and loss of material.

No significant plant-specific operating experience associated with the Internal Surfaces in Miscellaneous Piping and Ducting Components program was noted by the staff during its review.

LRA AMP B.1.26, Masonry Wall Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: CMU, concrete, crack, mortar, masonry, and spall.

No significant plant-specific operating experience associated with the Masonry Wall Program was noted by the staff during its review.

LRA AMP B.1.27, Non-EQ Electrical Cable Connections Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: cable connection - increased resistance, cable connection - discoloration, cable connection - contamination, and cable connection - ohmic heating.

No significant plant-specific operating experience associated with the Non-EQ Electrical Cable Connections was noted by the staff during its review.

LRA AMP B.1.28, Non-EQ Inaccessible Power Cables (>400V)

Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: cable, manhole, submergence, insulation, sump, sump pump, tan delta, degraded cable, and vault.

The table below lists the documents that were reviewed by the staff and were found relevant to the Non-EQ Inaccessible Power Cables (>400V) program. These documents were identified during the staffs search of the applicants operating experience database. The results of the review of relevant operating experience is documented in the AMP Audit Report (ADAMS Accession No. ML17346A732).

Relevant Documents Reviewed Document Description Revision / Date CR-RBS-2012-01591 Cable failed Tan Delta test acceptance criteria per W.O.52389658 02/29/2012 CR-RBS-2014-03068`

During inspection, manhole EMH610 was found with 94 of water and in contact with cables (W.O.52561529-01) 06/25/2014 CR-RBS-2014-02825 During inspection, manhole EMH602 was found with 106 of water and in contact with cables (W.O.52561532-01) 06/10/2014 CR-RBS-2015-01765 Outside operator noticed water flowing into electrical manhole. NRC informed 03/07/2015 CR-RBS-2011-01311 Tan Delta test results showed cable in degraded condition. Consult with subject matter expert and EPRI determined replacement not needed 2011 CR-RBS-2012-03590 Cable INPSANJ304 failed Tan Delta test.

Water found in cable when cable was cut 05/27/2012 CR-RBS-2013-03834 Manhole EMH36 has been in quarterly trend report due to water intrusion. Issue identified during corrective action QA audit (QA-3-2013-RBS-01) 05/23/2013 CR-RBS-2015-08068 Cable ICWSANK001 phase C failed insulation resistance acceptance criteria (5 meg Ohm vs. 317 meg. Ohm). A new W.R.378544 was generated to repair or replace.

11/09/2015 LRA AMP B.1.29, Non-EQ Insulated Cables and Connections Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: cable discoloration, cable contamination cable -

insulation aging degradation, cable - melting, and cable - embrittlement.

No significant plant-specific operating experience associated with the Non-EQ Insulated Cable and Connections was noted by the staff during its review.

LRA AMP B.1.30, Non-EQ Sensitive Instrumentation Circuits Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: Intermediate range monitor, Power range monitor, Source range monitor, Instrumentation circuits, replace cable, and electrical insulation.

The table below lists the documents that were reviewed by the staff and were found relevant to the Non-Environmental Qualification Sensitive Instrumentation Circuits. These documents were identified by the staff in the staffs search of the applicants operating experience database. The results of the review of relevant operating experience is documented in the AMP Audit Report (ADAMS Accession No. ML17346A732).

Relevant Documents Reviewed Document Description Revision / Date CR-RBS-2010-02318 INPO issued SEE-IN Topical Report (TR)

TR10 Cable Aging and Monitoring on May 11, 2010. This TR analyzes power and instrument and control cable failures and events from 2005 - 2009 reported via Nuclear Network. Twelve cable failures have occurred during this five-year period, most because of adverse conditions.

05/20/2010 LRA AMP B.1.31, Oil Analysis Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: oil analysis, wear, and loss of material.

No significant plant specific operating experience associated with the Oil Analysis program was noted by the staff during its review.

LRA AMP B.1.32, One-Time Inspection Audit Activities. The staff noted that this is a new program, therefore no plant specific operating experience have been established No significant plant specific operating experience associated with the One-Time Inspection program was noted by the staff during its review.

LRA AMP B.1.33, One-Time Inspection - Small-Bore Piping Audit Activities. The staff conducted an independent search of the applicants operating experience database using the keywords: weld, cracking, crack, failure, socket, sockolet, weldolet, butt weld, thermal, fatigue, and leakage.

The table below lists the documents that were reviewed by the staff and were found relevant to the audit. These documents were provided by the applicant or were identified in the staffs search of the applicants operating experience database.

Relevant Documents Reviewed Document Description Revision / Date RBS B.1.33 Program Basis Document, License Renewal Program Book - One-Time Inspection - Small-Bore Piping Rev. 0 EN-FAP-LR-007 Evaluation of Aging Management Programs Rev. 6 CR-RBS-1993-434 Historical record 07/241993 CR-RBS-2001-483 Pin-hole leak at welded plus in leak-off line connection 04/10/2001 CR-RBS-1999-1199 Steam leak on drain line socket weld 07/20/1999 CR-RBS-2010-1844 Leak found in tie-in line 04/22/2010 LER-458-1997-002 through-wall crack in weld on RRS Reactor Recirculation System Vent Valve 10/27/1997 LRA AMP B.1.34, Periodic Surveillance and Preventive Maintenance Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: clog, MIC, microbiolig, min wall, and throughwall.

The table below lists the document that was reviewed by the staff and was found relevant to the Periodic Surveillance and Preventive Maintenance program. The document was identified in the staffs search of the applicants operating experience database. The results of the review of relevant operating experience is documented in the AMP Audit Report (ADAMS Accession No. ML17346A732).

Relevant Documents Reviewed Document Description Revision / Date CR-RBS-2009-5426 This CR documents an adverse trend. Performance of an STP is becoming progressively more difficult to accomplish due to system degradation in the carbon steel sections of the plant drain piping. The vast majority of the evolution is spent conducting sump and check valve inspections due to extensive carbon steel corrosion in the drain lines.

Additionally, several full days of drain line clearing and troubleshooting were performed.

10/14/2009

LRA AMP B.1.35, Protective Coating Monitoring and Maintenance Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: Service Level I, coatings, containment, and drywell.

The table below lists the documents that were reviewed by the staff and were found relevant to the Protective Coating Monitoring and Maintenance Program. These documents were identified in the staffs search of the applicants operating experience database. The results of the review of relevant operating experience is documented in the AMP Audit Report (ADAMS Accession No. ML17346A732).

Relevant Documents Reviewed Document Description Revision / Date CR-RBS-2012-07038 Acceptability and Acceptance Criteria for Galvanized Coatings 11/12/2012 CR-RBS-2017-01513 Four Areas of Degraded Coatings in Drywell 02/15/2017 CR-RBS-2016-07893 RF-17 Drywell Coatings Inspection 11/21/2016 CR-RBS-2015-01390 RF-18 Drywell Coatings Inspection 02/27/2015 CR-2000-00904 Potential Impact of Coating Degradation on ECCS Strainers 04/04/2000 0035141 Technical Evaluation for CR-2000-00904 (Attachment to CA-2) 04/04/2000 LRA AMP B.1.36 Reactor Head Closure Studs Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: bolt, bolting, closure stud, stress corrosion cracking, wear, and cracking.

The table below lists the documents that were reviewed by the staff and were found relevant to the audit. These documents were provided by the applicant or were identified in the staffs search of the applicants operating experience database.

Relevant Documents Reviewed Document Description Revision / Date RBS B.1.36 Program Basis Document, License Renewal Program Book - Reactor Head Closure Studs Rev. 0 EN-FAP-LR-007 Evaluation of Aging Management Programs Rev. 6 3RBG-47100 Inservice Inspection Plan for the Third 10-year Interval 01/17/2011 CR-RBS-2001-1349 Two depressions detected on vessel flange 10/07/2001 LRA AMP B.1.37, Reactor Vessel Surveillance Program Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: Part 50, Appendix H, integrated surveillance, ISP, capsule, and BWRVIP-86.

The table below lists the documents that were reviewed by the staff and were found relevant to the audit. These documents were provided by the applicant or were identified by the staff during its search of the applicants operating experience database or the staffs review of the LRA, current licensing basis, and current design basis, as well as the staffs review of the applicants program evaluation report for LRA AMP B.1.32, Reactor Vessel Surveillance. This includes the staffs review of the operating history section in the program evaluation report for the AMP. The results of the review of relevant operating experience is documented in the AMP Audit Report (ADAMS Accession No. ML17346A732).

Relevant Documents Reviewed Document Description Revision / Date LRA Appendix B, Section B.1.37 Reactor Vessel Material Surveillance Revision 0 LRA Section 4.2.3 Pressure-Temperature Limits Revision 0 RBS-15-00006 RBS License Renewal Project, Aging Management Program Evaluation Report - Class 1 Mechanical, Reactor Vessel Surveillance Revision 0 EPRI Report No. 1003346 BWRVIP-86-A: BWR Vessel and Internals Project Updated BWR Integrated Surveillance Program (ISP) Implementation Plan (Non-Public Proprietary Report, ADAMS Accession No. ML023190491)

Revision 0 (A version)

Document Description Revision / Date NRC Safety Evaluation Safety Evaluation Regarding EPRI Proprietary Reports "BWR Vessel and Internals Project, BWR Integrated Surveillance Program Plan (BWRVIP-78)" and BWRVIP "BWR Vessel and Internals Project, BWR Integrated Surveillance Program Implementation Plan." (Publicly available Evaluation in ADAMS Accession No. ML020380691) 02/01/2002 EPRI Report No. 1025144 BWRVIP-86, Revision 1-A: BWR Vessel and Internals Project Updated BWR Integrated Surveillance Program (ISP) Implementation Plan (Proprietary Report, ADAMS Accession Nos. ML13176A098, ML13176A099, ML13176A100, respectively)1 Revision 1-A NRC Safety Evaluation Final Safety Evaluation Regarding EPRI Technical Report 1016575, BWRVIP-86, Revision 1. (ADAMS Accession Nos. ML112780497 and ML112780503, respectively) 10/20/2011 EPRI Report No. 1024452 BWRVIP-94NP, Revision 2: BWR Vessel and Internals Project Program Implementation Guide Revision 2-NP USAR Section 5.3 Reactor Vessel Rev. 24 Facility License Amendment 136 to Docket No. 50-458 River Bend Station, Unit 1 - Issuance of Amendment, RE: Reactor Vessel Material Surveillance Program (ADAMS Accession No. ML032050454) 07/24/2003 EPRI Non-Proprietary Report No.

1021553 BWRVIP-87NP, Revision 1: BWR Vessel and Internals Project, Testing and Evaluation of BWR Supplemental Surveillance Program Capsules D, G, and H (ADAMS Accession No. ML102420110) 08/26/2010 EPRI Non-Proprietary Report No.

1021555 BWRVIP-113: BWR Vessel and Internals Project, River Bend 183 Degree Surveillance Capsule Report (ADAMS Accession No. ML102580248) 09/13/2010

Document Description Revision / Date EPRI Non-Proprietary Report No.

1021556 BWRVIP-169: BWR Vessel and Internals Project, Testing and Evaluation of BWR Supplemental Surveillance Program (SSP) Capsules A, B, and C (ADAMS Accession No. ML102590092) 09/14/2010 EPRI Non-Proprietary Report No.

1021554 BWRVIP-111, Revision 1: BWR Vessel and Internals Project, Testing and Evaluation of BWR Supplemental Surveillance Program Capsules E, F, and I (ADAMS Accession No. ML102720220) 09/24/2010 CR-RBS-2017-04807 Discrepancy found between SAR and TRM and BWRVIP ISP on capsule pull schedule.

June 19, 2017

1.

Publically available, non-proprietary version of the BWRVIP-86, Revision 1-A report is given in ADAMS Accession No. ML13176A097.

LRA AMP B.1.38, RG 1.127 Inspection of Water Control Structures Associated with Nuclear Power Plants Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: steel, concrete, crack, corrosion, loosing bolt, and spall.

No significant plant-specific operating experience associated with the RG 1.127 Inspection of Water Control Structures Associated with Nuclear Power Plants was noted by the staff during its review.

Relevant Documents Reviewed Document Description Revision / Date CR-RBS-2016-04092 Hairline Cracking on Exterior Concrete Wall 5/31/16 CR-RBS-2014-00516 General steel corrosion on supplementary steel support 2/04/14

LRA AMP B.1.39, Selective Leaching Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: dealloy, degraph, dezinc, leach, zinc, dealum dezinc, graphiti, and cast iron.

No significant plant-specific operating experience associated with the Selective Leaching program was noted by the staff during its review.

LRA AMP B.1.40, Service Water Integrity Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: 89-13, biological, coat, corros, leak, loss of material, piping, and redu. The table below lists the documents that were identified during the staffs search of the applicants operating experience database and were found relevant to the Service Water Integrity program. The results of the review of relevant operating experience is documented in the AMP Audit Report (ADAMS Accession No. ML17346A732).

Relevant Documents Reviewed Document Description Revision / Date CR-RBS-2007-05223 Stroking SWP-MOV55A standby cooling tower inlet under flow conditions resulted in approximately 1.2gpm leakby. Subsequent operation of SWP-MOV55A under no flow conditions resulted in essentially 0 leakage 11/23/2007 CR-RBS-2008-01431 SWM-MOV77B supply to Div III EDG is leaking by the passive failure assumptions in USAR Table 9.2.16 in being able to isolate a HPCS EDG jacket cooler are not valid. Post DBA the inventory requirements issue.

02/10/2008 CR-RBS-2008-05043 Sys 103 (Circ Water) Collector pots were filled with broken pieces of cooling tower fill material.

08/22/2008 CR-RBS-2009-04345 CR documents findings of the Stand By Cooling Tower Inspection (SWP-TWR1) for Div 2 performed on 9/23/2009. The overall condition was found to be very good. No structural, mechanical or otherwise functional defect were found. However, the following areas require further action:

09/24/2009

Document Description Revision / Date CR-RBS-2009-04830 This CR is to document the findings of the Stand By Cooling Tower Inspection (SWP-TWR1) for Div 1 performed on 9/30/2009. The inspected areas were below the fans, above the fans, and the area above the fill including the spray header and all associated piping and hardware. The overall condition of the Div 1 side of the tower was found to be very good. No structural, mechanical or otherwise functional defects that could have a negative impact on the operability of the tower were found. However, the following areas require further action:

10/01/2009 CR-RBS-2010-06697 Inaccessible Standby Service Water piping has not been regularly inspected. Portions of the return/riser piping are submerged in the standby cooling tower basin, which significantly increases susceptibility to OD corrosion. Being inaccessible, the GL 89-13 recommendation (Item III) was not recognized as being applicable to this piping.

12/20/2010 CR-RBS-2011-07654 Nonconservative methodology for Standby Cooling Tower Performance and evaporation losses without Drywell Unit Coolers. (From CDBI inspection in 2011) 10/28/2017 CR-RBS-2012-06609 Coating inspection of submerged Standby Cooling Tower piping performed. Minor coating degradation and light rust on some of the inspected piping due to aging. Need to repair or replace the coating to ensure the long-term integrity of the piping.

10/22/2012 CR-RBS-2015-01252 UT exam on pipe SWP-030-028-3 to support installation of 30-inch valves for the Fukushima Project. Min wall for these line is. UT shows 2 places below min wall of 0.164 inch that will require buttering for fit up purposes. (Ref P&ID-09-10E (M-7))

02/25/2015 CR-RBS-2017-02777 Water was observed falling from one location of the tile fill on the east air inlet of the standby cooling tower. Water falling from the tile fill indicates leak by from either the SWP-MOV55A or B valve seats.

03/23/2017

LRA AMP B.1.41, Structures Monitoring Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: concrete, steel, crack, corrosion, leak, SCC, ASR, settlement, rust, coating, spall, groundwater, and leach.

The table below lists the documents that were reviewed by the staff and were found relevant to the Structures Monitoring Program. These documents were identified in the staffs search of the applicants operating experience database. The results of the review of relevant operating experience is documented in the AMP Audit Report (ADAMS Accession No. ML17346A732).

Relevant Documents Reviewed Document Description Revision / Date CR-RBS-2008-00581 Structural Conditions Observed in the Turbine Building 01/19/2008 CR-RBS-2009-01005 Deficiencies identified in the G Tunnel 02/20/2009 CR-RBS-2012-01939 Review of NRC IN 2001-20, Concrete Degradation by Alkali-Silica Reaction 03/16/2012 CR-RBS-2014-00516 General steel corrosion identified on supplementary steel support in Control building 02/04/2014 CR-RBS-2014-01367 Grouting at the pedestal of the main plant stack supports 03/20/2014 CR-RBS-2009-06118 Turbine Building Foundation Crack Identified 11/30/2009 CR-RBS-2010-02033 Anchor Bolt not installed per specification requirements 05/05/2010 CR-RBS-2016-04092 Hairline Crack on the exterior concrete wall of the west and south walls of the main control room 05/31/2016 LRA AMP B.1.42, Water Chemistry Control - BWR Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: oxygen, hydrogen water chemistry, dissolved oxygen, and cracking.

No significant plant specific operating experience associated with the Water Chemistry Control -

BWR program was noted by the staff during its review.

LRA AMP B.1.43 Water Chemistry Control - Closed Treated Water Systems Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: clog, cooler, corros, leak, loss of material, piping, and rust.

The table below lists the documents that were identified during the staffs search of the applicants operating experience database and were found relevant to the Water Chemistry Control - Closed Treated Water Systems program. The results of the review of relevant operating experience is documented in the AMP Audit Report (ADAMS Accession No. ML17346A732).

Relevant Documents Reviewed Document Description Revision / Date CR-RBS-2008-00520 SWC Cooling tower cell B currently is experiencing a low flow condition due to leakage of the cell inlet isolation valve. The deposits may be adding additional weight and blocking the tight flow channels of the new fill.

Visual observation of the past week has shown increase fouling buildup along the fill material.

01/18/2008 CR-RBS-2011-00993 5 of the 6 drains for drywell unit coolers are clogged.

01/23/2011 CR-RBS-2011-01110 SWP-V262 was cut out. Pipe was found to be clogged.

01/25/2011 CR-RBS-2011-02746 The Component Cooling Primary system chemistry has been out of specification since end of RF-16. Chemistry department unsuccessful at restoring parameters using installed demineralizer and feed and bleeds.

Contamination of the system is due to its ability to be cross tied with Service Water Primary.

03/08/2011 CR-RBS-2011-03700 SWP-SRT1H (ref P&ID 09-10H) had high dP.

Performed blowdown on strainer. Went from 10psid to 9psid.

04/23/2011 CR-RBS-2012-01217 During WO-296978, excessive debris was found in SWP-STR1H (Normal SW Supply to SWP/SWC heat exchanger 1H strainer.) WO was most recent performance of PMID-00010545-01. Frequency of PM is As Required SWP-STR1H had not been cleaned since 2000. The PM frequency needs to be updated to prevent excessive clogging. Debris found appears to be mostly rust particles.

02/15/2012

Document Description Revision / Date CR-RBS-2013-02302 The normal SWP system is in service with SWP-P7A & C running and pressure at 129#.

The CCP system is in service with CCP-P1A &

C running and pressure at 101#. SWP continues to leak into the CCP sys.

03/12/2013 CR-RBS-2013-03728 There is an identified leak from service water into CCP via SWP-MOV504B, RPCCW Loop B System Return (reference CR-2011-6584, WO289456) 05/18/2013 CR-RBS-2013-07048 Valve SWP-V509 EGT-E1B (jacket water

/service water cooler) inlet drain valve being clogged.

11/11/2013 CR-RBS-2014-03820 Valve SWP-V3160 drain line upstream is clogged (Ref P&ID-09-10D (B-21))

08/05/2014 CR-RBS-2015-00105 Valve SWP-V871 is clogged, found during testing of SWP-MOV96B (ref P&ID-09-10B (F-20))

01/07/2015 CR-RBS-2015-00871 Valve SWP-V3297 is clogged. (Associated with SWP-MOV501A) (Ref P&ID-09-10D (N-3))

02/11/2015 CR-RBS-2015-01501 Flushing Valve SWP-V3166 is partially clogged (upstream of check valve SWP-V144).

03/02/2015 CR-RBS-2015-03607 Abnormal trend on CCP Component Cooing Primary system indicates makeup occurring twice a day since 5.13.15. Totalizer readings for 3 consecutive days indicate approx. 145 gal, 290 gal, and 440 gal per day respectively.

05/16/2015 CR-RBS-2016-04222 While replacing SWP-RV91B, the inlet piping was discovered to be extremely degraded and corroded. Due to its current condition recommend analyzing for replacement due to the potential of reduced flow. (Ref P&ID-09-10B (J-14))

06/06/2016 CR-RBS-2017-03551 Per SOP-0018 section 5.6, multiple strainer backflushes were performed on SWP-STR1H, SWP-STR1G, and SWP-STR1F with no successful decrease in strainer differential pressure. These strainers are located on the normal service water inlet piping to the Service Water Cooling Heat Exchangers.

04/26/2017

LRA TLLA Section 4.1, Identification of Time-Limited Aging Analyses Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: fatigue, corrosion, flaw growth, stability, pool, liner, allowance, cycles, 40 year, CUF, usage factor, and analysis.

No significant plant-specific operating experience associated with the TLAA Section 4.1, Identification of Time-Limited Aging Analyses, was noted by the staff during its review.

LRA TLAA Section 4.2.2, Adjusted Reference Temperature Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: capsule, neutron, flux, surveillance, fluence, and embrittle.

The table below lists the documents that were reviewed by the staff and were found relevant to the TLAA Section 4.2.2. These documents were identified in the staffs search of the applicants operating experience database. The results of the review of relevant operating experience is documented in the AMP Audit Report (ADAMS Accession No. ML17346A732).

Relevant Documents Reviewed Document Description Revision / Date CR-RBS-2017-06674 General Electric Hitachi (GEH) identified an error in the neutron fluence model used to calculate RBS license renewal fluence projections.

09/18/2017 CR-RBS-2003-02874 An error was found in tables of a report associated with the reactor vessel fluence analysis.

08/07/2003 LRA TLAA Section 4.2.3, Pressure-Temperature Limits Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: capsule, neutron, flux, surveillance, fluence, and embrittle.

The table below lists the documents that were reviewed by the staff and were found relevant to the TLAA Section 4.2.3. These documents were identified in the staffs search of the applicants operating experience database. The results of the review of relevant operating experience is documented in the AMP Audit Report (ADAMS Accession No. ML17346A732).

Relevant Documents Reviewed Document Description Revision / Date CR-RBS-2017-06674 GEH identified an error in the neutron fluence model used to calculate RBS license renewal fluence projections.

09/18/2017 CR-RBS-2003-02874 An error was found in tables of a report associated with the reactor vessel fluence analysis.

08/07/2003 CR-RBS-2009-04143 GE issued a draft letter on impact to PT Curves due to change in methodology used to evaluate the water level instrumentation nozzle.

09/18/2009 CR-RBS-2017-04807 RBS found outdated information in the SAR and program documents in regards to the reactor vessel surveillance program.

06/17/2017 CR-RBS-2017-07277 This CR a question from the resident inspector on a discrepancy between a plant procedure and the technical specifications 10/12/2017 LRA TLAA Section 4.2.4, Upper Shelf Energy Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: capsule, neutron, flux, surveillance, fluence, and embrittle.

The table below lists the documents that were reviewed by the staff and were found relevant to the TLAA Section 4.2.4. These documents were identified in the staffs search of the applicants operating experience database. The results of the review of relevant operating experience is documented in the AMP Audit Report (ADAMS Accession No. ML17346A732).

Relevant Documents Reviewed Document Description Revision / Date CR-RBS-2017-06674 GEH identified an error in the neutron fluence model used to calculate RBS license renewal fluence projections.

09/18/2017 CR-RBS-2003-02874 An error was found in tables of a report associated with the reactor vessel fluence analysis.

08/07/2003

LRA TLLA Section 4.7.1, Erosion of Main Steam Line Flow Restrictors Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: erosion, analysis, main steam, and flow restrictor.

No significant plant-specific operating experience associated with the TLAA Section 4.7.1, Erosion of Main Steam Line Flow Restrictors, was noted by the staff during its review.

LRA TLLA Section 4.7.2, Postulation of HELB Locations Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: HELB, high energy, line break, break, fatigue, CUF, usage factor, and analysis.

No significant plant-specific operating experience associated with the TLAA Section 4.7.2, Postulation of HELB Locations, was noted by the staff during its review.

LRA TLLA Section 4.7.3, Fluence Effects for Reactor Vessel Internals Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: fluence, vessel internals, RVI, core support, and analysis.

No significant plant-specific operating experience associated with the TLAA Section 4.7.3, Fluence Effects for Reactor Vessel Internals, was noted by the staff during its review.

LRA TLAA Section 4.7.4, Crane Load Cycles Analysis Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: crane, fatigue cycle, and vibration.

No significant plant-specific operating experience associated with the TLAA Section 4.7.4, Crane Load Cycles Analysis was noted by the staff during its review.

IV.

Final Briefing A final briefing was held with the applicant on October 27, 2017, to discuss the results of the scoping and screening methodology audit. The audit team identified preliminary areas where additional information would be required to support completion of the staffs LRA review.

VI.

NRC Staff Albert Wong NRR/DMLR/MRPB Bill Rogers NRR/DMLR/MRPB Angie Buford NRR/DE/ESEB Brian Allik NRR/DMLR/MCCB Alexander Chereskin NRR/DMLR/MCCB Samuel Cuadrado NRR/DMLR/MCCB Bart Fu NRR/DMLR/MPHB William Gardner NRR/DMLR/MCCB

James Gavula NRR/DMLR/MCCB Dan Hoang NRR/DE/ESEB William Holston NRR/DMLR/MRPB Alan Huynh NRR/DMLR/MCCB Bryce Lehman NRR/DE/ESEB Juan Lopez NRR/DMLR/MRPB James Medoff NRR/DMLR/MVIB Seung Minh NRR/DMLR/

Arron Mink NRR/DMLR/

Duc Nguyen NRR/DE/EENB Ngola Otto NRR/DE/EENB Andrew Prinaris NRR/DE/ESEB Mohamad Sadollah NRR/DE/EENB George Thomas NRR/DE/ESEB Albert Wong NRR/DMLR/

Mark Yoo NRR/DMLR/

VII. Applicant Personnel Contacted During Audit David Lach Entergy License Renewal Team Herbert Rideout Entergy License Renewal Team Mark Sandusky Entergy License Renewal Team