ML19142A369
| ML19142A369 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 06/06/2019 |
| From: | Bennett Brady NRC/NRR/DMLR/MRPB |
| To: | Gallagher M Exelon Generation Co |
| Brady B, NRR-DMLR 415-2981 | |
| References | |
| EPID L-2018-RNW-0012 | |
| Download: ML19142A369 (49) | |
Text
June 6, 2019 Mr. Michael Gallagher Vice President, License Renewal and Decommissioning Exelon Generation Company, LLC 200 Exelon Way Kennett Square, PA 19348
SUBJECT:
PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 - REVISED REPORT FOR THE OPERATING EXPERIENCE REVIEW AUDIT REGARDING THE SUBSEQUENT LICENSE RENEWAL APPLICATION REVIEW (EPID NO. L-2018-RNW-0012)
Dear Mr. Gallagher:
By letter dated July 10, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18193A689), the Exelon Generation Company, LLC, (Exelon) submitted to the U.S. Nuclear Regulatory Commission (NRC or staff) an application to renew the Renewed Facility Operating License Nos. DPR-44 and DPR-56 for the Peach Bottom Atomic Power Station, Units 2 and 3 (Peach Bottom), respectively. Exelon submitted the application pursuant to Title 10 of the Code of Federal Regulations Part 54, Requirements for Renewal of Operating Licenses for Nuclear Power Plants, for subsequent license renewal. The NRC staff completed its operating experience review audit at the Excel Services Corporation offices in Rockville, Maryland, from September 17 through September 27, 2018, in accordance with the operating experience review audit plan (ADAMS Accession No. ML18249A280). The audit report is enclosed.
If you have any questions, please contact me by telephone at 301-415-2981 or by e-mail at Bennett.Brady@nrc.gov Sincerely,
/RA/
Bennett Brady, Senior Project Manager License Renewal Projects Branch Division of Materials and License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-277 and 50-278
Enclosure:
Audit Report cc w/encl: Listserv
ML19142A369 *concurred by email OFFICE PM:MRPB:DMLR LA:MRPB:DMLR PM:MRPB:DMLR BC:MRPB:DMLR*
NAME BBrady YEdmonds BRogers EOesterle DATE 05/22/19 05/23/19 06/6/19 06/6/19 OFFICE PM:MRPB:DMLR NAME BBrady DATE 06/6/19
Audit Report Operating Experience Review Audit Regarding the Peach Bottom Atomic Power Station Units 2 and 3, Subsequent License Renewal Application September 17-27, 2018 Division of Materials and License Renewal Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Enclosure
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION, DIVISION OF MATERIALS AND LICENSE RENEWAL Docket Nos: 50-277 and 50-278 License No: DPR-44 and DPR-56 Licensee: Exelon Generation Company, LLC Facility: Peach Bottom Atomic Power Station, Units 2 and 3 Location: Rockville, Maryland Dates: September 17 through 27, 2018 Reviewers: B. Allik, Materials Engineer, Division of Materials and License Renewal (DMLR)
A. Buford, Structural Engineer, Division of Engineering (DE)
A. Chereskin, Chemical Engineer, DMLR G. Cheruvenki, Materials Engineer, DMLR S. Cuadrado de Jesus, Structural Engineer, DE R. Fitzpatrick, Electrical Engineer, DE B. Fu, Materials Engineer, DMLR W. Gardner, Physical Scientist, DMLR J. Gavula, Mechanical Engineer, DMLR D. Hoang, Structural Engineer, DE K. Hoffman, Materials Engineer, DMLR W. Holston, Senior Mechanical Engineer, DMLR A. Hovanec, Materials Engineer, DMLR A. Huynh, Materials Engineer, DMLR J. Jenkins, Materials Engineer, DMLR A. Johnson, Materials Engineer, DMLR S. Jones, Sr. Reactor Systems Engineer, Division of Safety Systems N. Khan Electrical Engineer, DE B. Lehman, Structural Engineer, DE J. Lopez, Structural Engineer, DE S. Min, Materials Engineer, DMLR D. Nguyen, Electrical Engineer, DE A. Prinaris, Structural Engineer, DE A. Rezai, Materials Engineer, DMLR M. Sadollah, Electrical Engineer, DE G. Thomas, Senior Structural Engineer, DE
Approved By: David Alley, Chief Vessels & Internals Branch Division of Materials and License Renewal Steve Bloom, Chief Chemical, Corrosion, & Steam Generator Branch Division of Materials and License Renewal Eric Oesterle, Chief License Renewal Projects Branch Division of Materials and License Renewal Stephen Cumblidge, Acting Chief Piping & Head Penetration Branch Division of Materials and License Renewal Tania Martinez-Navedo, Chief Electrical Engineering, New Reactors, & License Renewal Branch Division of Engineering Brian Wittick, Chief Structural Engineering Branch Division of Engineering
Report for the Operating Experience Review Audit Peach Bottom Atomic Power Station, Units 2 and 3 Subsequent License Renewal Application
- 1. Introduction The U.S. Nuclear Regulatory Commission (NRC or the staff) conducted an audit of Exelon Generation Company, LLC (Exelon) Peach Bottom Atomic Power Station (PBAPS) Units 2 and 3 (PB or the applicants) plant-specific operating experience (OpE), as part of the staffs review of the Peach Bottom subsequent license renewal application (SLRA) at the EXCEL Services Corporation located in Rockville, Maryland, from September 17 through 27, 2018. The purpose of the audit was for the NRC staff to perform an independent review of plant specific OpE 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, Requirements for Renewal of Operating Licenses for Nuclear Power Plants, (10 CFR Part 54). The staff also considered the guidance contained in NUREG-2192, Rev. 0, Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants (SRP-SLR), dated July 2017, and NUREG-2191, Rev. 0, Generic Aging Lessons Learned for Subsequent License Renewal (GALL-SLR) Report, dated July 2017.
The identified OpE examples will be further 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 OpE 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 subsequent period of extended operation.
- 2. Audit Activities The following sections discuss the areas reviewed by the staff and identified examples of pertinent OpE.1 SLRA AMP B.2.1.1, ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: flaw, age, crack, brittle, weld, bolt, buried, corrosion, damage, fracture, leak, scc, piping, rupture, nickel-alloy, min wall, rust, pwscc, mechanical wear, indication, qualification, thread, through wall, transgra, vessel, vessel internals, wall loss, wall thin, wastage, wear, and pit.
The table below lists the documents that were reviewed by the staff and were found relevant to the ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD Program. These documents were identified in the staffs search of the applicants operating experience database. The staff will document its review of relevant operating experience in the (Safety Evaluation Report (SER).
1 Not all AMPs at Peach Bottom are discussed in this report as technical revierwer for some AMPs had not been assigned at the time of the audit.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date AR-02546998 ASME percentage limitations not met 08/27/2015 AR-04003429 ISI database discrepancies (reactor head stud bolting) 04/27/2017 AR-02564068 P3R20 ISI expanded scope requirements 10/01/2015 AR-01554519 PBAPS UNIT 3 RPV head weld flaw documentation 09/05/2013 AR-02704854 HPSW leak from pipe 08/16/2016 AR-00823513 P2R17 ISI indications in weld 9/28/2008 AR-01118530 P2R18 flaw indication on RPV head to flange weld 09/27/2010 AR-00919813 EOC piping examination for ESW root cause 05/14/2009 AR-01587735 U3 LR CIA need tracking for commitment 11/20/2013 AR-01568638 Rejectable weld flaw FW-DD-25 10/07/2013 AR-00811174 P2R17 3 ISI weld examinations not scheduled 08/26/2008 SLRA AMP B.2.1.2, Water Chemistry Audit Activities. The staff conducted an independent search of applicants operating experience database using keywords: chloride, conductivity, crack, dissolved oxygen, fluoride, HWC
[hydrogen water chemistry], hydrogen water, iron, noble, organic, oxygen, PWSCC
[pressurized-water stress corrosion cracking], SCC [stress corrosion cracking], stress, sulfate, and zinc.
The table below lists the documents that were reviewed by the staff and were found relevant to the Water Chemistry program. These documents were identified in the staffs search of applicants operating experience database. The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date Electrochemical corrosion potential exceeded 230 millivolts for Unit AR-01410743 09/10/2012 2 due to the Unit 2 refueling outage 19 shutdown Relation between Unit 3 reactor water clean-up system and iron AR-01468207 01/29/2013 injection on chloride concentration AR-01136659 Chemistry deep dive results and recommended actions 11/06/2010
Document Title Revision / Date AR-01697416 Chemistry department rated chronic yellow by nuclear oversight 08/28/2014 AR-01691387 Unit 3 total organic carbon (TOC) above limit 08/11/2014 AR-01601996 Adverse trend - torus TOC 12/30/2013 AR-01601661 Unit 2 TOC above limit 12/29/2013 SLRA AMP B.2.1.3, Reactor Head Closure Stud Bolting Audit Activities. During its audit, the staff had discussions with the applicants staff and reviewed onsite documentation provided by the applicant. The table below lists Exelon documents that were reviewed by the staff and were found relevant to the audit.
The table below lists the documents that were reviewed by the staff and were found relevant to the Reactor Head Closure Stud Bolting program. These documents were identified in the staffs search of applicants operating experience database. The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date PI-AA-115-1003 Processing OE evaluations REV. 4 M-004-400 Reactor pressure vessel reassembly REV. 43 M-004-400 Reactor pressure vessel disassembly REV. 38 P2R18-168976-In-service inspection report for Peach Bottom Power Station 10/2010 HE2-ISI P3R18-3Q11-In-Service inspection report for Peach Bottom Power Station 09/2011 NDE-2LO14H-ISI REV. 0 H5814 Reactor head spare stud CMTR 11/08/1971 Peach Bottom Units 2 And 3, materials properties and test REV. 0 AR-003N9506 results for closure studs, nuts, washers and bushing 12/2016 AR-00834915 Stuck stud #80, lessons learned for refuel floor 09/15/2008 SLRA AMP B.2.1.4, Vessel ID Attachment Welds Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: Crack, SCC, Vessels, and Weld.
No significant plant-specific operating experience associated with AMP B.2.1.4, BWR Vessel ID Welds was noted by the staff during its review.
SLRA AMP B.2.1.5, BWR Stress Corrosion Cracking Audit Activities. The SLRA states that AMP B.2.1.5, BWR Stress Corrosion Cracking, is an existing program that is consistent with the program elements in GALL-SLR Report AMP XI.M7, BWR Stress Corrosion Cracking.
To verify this claim of consistency, the staff audited the SLRA AMP, staff conducted an independent search of Exelons operating experience database and interviewed the licenses staff and the onsite documentation provided by the licensee.
The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED DURING THE AUDIT Document Title Revision / Date P3R20 ISI: RWCU Weld 12-I-1C Limited Coverage the licensee AR-04014529 identified that an inspection coverage of 84.2% of the area was 06/13/2017 obtained in lieu of the required amount of 90%
ISI scope IGSCC weld RWCU in PBAPS,Unit 2. During a focused area self-assessment (fasa) of ISI program it was AR-02582071 identified as a total of 5 IGSCC Category D welds in the RWCU 11/9/2015 systems were erronesly not scheduled for re-examinations set at every 6 year interval PBAPS Unit 2, had determined not to mitigate previously AR-01479610 06/14/2013 selected 15 IGSCC category D welds for MSIP treatment 3R21 RPV instrumentation nozzle examinations; a leakage was discovered during a leakage test in one of the water level AR-04047787 09/30/2017 instrumentation nozzles located on the top-of-active fuel at one of the BWR Units in the fleet During the ISI inspections (P3R21) at PBAPS, Unit 3, two AR-04068795 09/25/2018 indications were identified in RWCU Weld 12-13-12 SLRA AMP B.2.1.6, BWR Penetrations Audit Activities. The staff conducted an independent search of Exelons operating experience database.
No significant plant-specific operating experience associated with the BWR Penetrations was noted by the staff during its review.
SLRA AMP B.2.1.7, BWR Vessel Internals Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: crack, SCC, vessels, and weld.
The table below lists the documents that were reviewed by the staff and were found relevant to the BWR Reactor Water Vessel Internals. 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 In-Office Audit Report.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date P2R16 jet pump 17 in outage P2R21, the licensee reevaluated AR-2738604 indications in weld DF-2 that were first identified in P2R16. 11/08/2016 There was a reduction in limiting flaw length acceptance criterion 2R21 IVVI replacement steam dryer the licensee identified cracked welds in the replacement steam dryer hold down rods.
This condition report is referenced in the report titled results of AR-2734507 10/30/2016 visual inspection of Unit 2 replacement steam dryer dated December 7, 2016 (ADAMS No. ML16342b621) which was required by Operating License Condition 2.c(15)(g) 3R20 Core Shroud UT Exam the licensee found atypical AR-2570717 indications identified as possible IGSCC during the UT exam of 10/14/2015 Weld H4; further evaluation proposed by licensee P3R18 core spray sparger bracket the licensee identified AR-1265631 unreportable indications of length about 1 inch during IVVI 09/20/2011 examinations P2R18 Reexam UT Indication, the licensee identified 2 possible IGSCC indications during the reexam of the tee box weld; total AR-1117134 09/23/2010 indication length was about 7.5 inches but there had been no growth since initial discovery P2R18 IVVI Core Spray Piping the licensee identified two AR-1114823 possible IGSCC indications in the reexam of weld P3B1; total 09/18/2010 indication length was about 3.4 inches; one indication appeared slightly longer than when previously evaluated Jet Pump 9_10 Weld the licensee identified a crack of unknown cause during the reexam of weld RS-1; total indication length AR-970611 09/25/2009 was about 2.4 inches but there had been no growth since the previous exam Jet Pump Main Wedge Wear the licensee identified new wear AR-968920 during the exam of main wedges on jet pumps 3 and 9; 09/23/2009 BWRVIP-41 R1 requires scope expansion P2R17 Core Spray Piping the licensee identified possible AR-821459 09/23/2008 IGSCC indications in the exam of weld P3B1 P2R17 Steam Seperator Gusset the licensee identified possible IGSCC indications during the IVVI exam of several gussets; new indications were found on 4 gussets and change or AR-820446 growth of indications were found on 5 gussets; the licensee 09/21/2008 identified that this is a non-safety related component not required to be inspected by BWRVIP or ASME; examinations were performed to provide industry OpE
Document Title Revision / Date Deviation From BWRVIP the licensee identified a deviation from BWRVIP-76 when the examination frequency for Weld H1 AR-798768 07/21/2008 was extended from 6 to 10 years; the licensee resolved the deviation by performing a plant specific evaluation 2R21 Exam Of Steam Dryer Support the licensee identified AR-2735052 10/31/2016 new wear during the reexam of steam dryer support brackets 2012 INPO BWRVIP Review the licensee identified that HWC AR-1392477 (hydrogen water chemistry) availability was good, but 07/24/2012 recommended modifications to improve availability Jet Pump 9 Aux Wedge Overtravel the licensee identified significant wear in the vessel side auxiliary wedge. the licensee AR-4067342 10/26/2017 recommended removal to prevent further damage to the jet pump 2R21 Exam Of Jet Pumps 13 and 18 the licensee identified AR-2737278 minor wear during the exam of aux wedges JP13VS and 11/04/2016 JP18SS; the licensee determined the condition to be acceptable 2R21 Indications Of Shroud the licensee identified fillet weld breaks and potential for loose parts during IVVI of the jet pumps.
AR-2736160 11/02/2016 the licensee stated this damage was most likely caused during inspection and recommended removal of broken brackets 2R21 Scope Adds And Descopes the licensee identified AR-2735819 several jet pump welds to be added or removed from inspection 11/02/2016 scope based on updated guidance from BWRVIP-41 R3 2016 BWRVIP FASA Deficiency 1 the licensee identified that several hidden welds were not in accordance with BWRVIP-41 AR-2667801 for leakage evaluation; the licensee recommended that core 05/10/2016 spray and jet pump flaw evaluations be revised to assume leakage from inaccessible welds 3R20 Jet Pump 09 Auxilliary Wedge the licensee identified AR-2565404 new wear on the vessel side aux wedge that would require a 10/04/2015 scope expansion to the main wedge 2R21 Jet Pump A Loop Adapt the licensee identified several indications in backing rings during the IVVI of the AD-1 welds.
AR-2737370 11/04/2016 The licensee stated that there was no evidence that the structural weld was degraded 2R21 Expanded Scope On RS-1 this condition report was AR-2736876 written in conjunction with Condition Report 02736616 (see 11/03/2016 below) and clarifies the expanded scope to meet BWRVIP-41.
2R21 Jet Pump 11-12 RS-1 the licensee identified an indication during IVVI of weld RS-1; the licensee recommended AR-2736616 that a determination be made if scope expansion was warranted. 11/03/2016 Another Condition Report (AT-2736876) discussed scope expansion
Document Title Revision / Date 2R21 Re-exam Of Core Spray Piping P3B1 the licensee identified no apparent changes in the indications that were AR-2734940 10/31/2016 identified in previous outages; (Condition Report AR-1265631 documents these indications during previous outage P3R18) 2R21 Jet Pump Adapter Backing Ring the licensee identified several indications in backing rings during the IVVI of the AD-1 AR-2734935 10/31/2016 welds; the licensee stated that there was no evidence that the structural weld was degraded SLRA AMP Section B.2.1.8, Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS)
Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: cast, thermal aging, CF8, pump casing, N-481, flaw, and flaw tolerance.
The table below lists the document that was reviewed by the staff and was found relevant to the Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS) Program. This document was provided by Exelon. The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date AR-2455499 P2R21 ISI Scope - PIMS AR for ISI inspection of Pump B 02/18/2015 SLRA AMP B.2.1.9, Flow-Accelerated Corrosion Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: cavitat, CHECWORK, erosi, FAC, flow-accelerated, and min wall.
The table below lists the documents that were reviewed by the staff and were found relevant to the Flow-Accelerated Corrosion program. These documents were provided by Exelon or were identified in the staffs search of the applicants operating experience database. The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date AR-04079500 Historical maintenance rule failure 11/30/2017 FAC [flow-accelerated corrosion] scope selection of P3R21 UT piping AR-02656237 04/15/2016 inspections AR-02615405 HPCI turbine inlet drain HI level alarm received 01/21/2016
Document Title Revision / Date AR-02568865 Steady stream leak from 3C RHR heat exchanger 10/10/2015 AR-02561767 Erosion in piping and components inspection below t minimum 09/28/2015 AR-02573389 OE review of IER L3-15-31, Unexpected Flow-Accelerated Corrosion 10/19/2015 AR-02392700 FAC FASA DEF No. 2 checworks unexpected output pH value 10/08/2014 AR-01646140 Erosion in piping and component program change management 04/11/2014 AR-01621291 Flow element/flow orifice FAC inspections 02/14/2014 AR-01386703 Benchmarking of FAC Chug meeting June 07/09/2012 AR-00984517 Piping material differs from expected 10/26/2009 SLRA AMP B.2.1.10, Bolting Integrity Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: leak, cap screw, SCC, stress corrosion cracking, crack, torque, preload, bolt, moly, and corro.
The table below lists the documents that were reviewed by the staff and were found relevant to the Bolting Integrity Program. These documents were provided by Exelon or were identified in the staffs search of the applicants operating experience database. The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date AR-00877922 Large packing leak on ECW pump discharge valve 02/08/2009 AR-03972629 Small packing leak from HV-3-19-ISC 02/10/2017 AR-02418492 Packing leak HPSW in the 2D RHR room 11/29/2014 AR-01510178 Verify torque on PSD-3-23-007 flanges 05/03/2013 AR-04033375 Flange leak on MO-3-48-3804B 07/19/2017 AR-00915882 MO-502A Bonnet Bolts Potentially under-torqued 05/05/2009 AR-00820405 P2R17 ISI loose bolts on Unit 2 HPCI suction strainer 09/21/2018 AR-01086963 Torus Dewatering Tank (TDT) drain valve found degraded 07/01/2010
Document Title Revision / Date WO C023395 Replace existing valve with new 08/05/2010 SLRA AMP B.2.1.11, Open-Cycle Cooling Water System Audit Activities. The staff conducted an independent search of Exelons operating experience database using keywords: emergency service water (ESW), high pressure service water (HPSW), emergency cooling water (ECW), GL 89-13, crack, biofoul, heat transfer, and corrosion.
The table below lists the documents that were reviewed by the staff and were found relevant to the Open-Cycle Cooling Water System Aging Management Program. These documents were identified in the staffs search of Exelons operating experience database. The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date As part of initiative to centralize engineering programs, Generic AR-04097435 Letter (GL) 89-13 implementation moved from site engineering 01/26/2018 programs role to fleet engineering, systems engineering Peach Bottom raw water/GL 89-13 programs credit raw water program NDE work requests towards meeting annual GL 89-13 piping integrity monitoring expectations per ER-AA-340. Raw AR-04056936 09/28/2017 water program engineer identified inspections previously planned for completion have not been executed during year(s) credited by GL 89-13 Stem/disc connection failure on valve HV-V-3-33-503 in April 2013 has prevented flow of service water into ESW. Biocide AR-01534045 added to service water is cited in GL 89-13 response as method 07/10/2013 for complying with Action 1 of GL 89-13. Unit 3 ESW has gone without biocide since early April.
Leak was identified in A ESW supply piping during engineering AR-01444838 walkdown. Engineering selected locations to evaluate areas of 11/27/2012 similar risk in ESW piping Gl 89-13 had two consecutive yellow quarters (3rd/4th 2007).
Completing check-in assessment by 11/14/2008 will meet ER-AR-00721798 03/14/2008 AA-1100 requirement to check-in by one year after first yellow quarter 2C core spray room cooler heat transfer test performed was AR-00871970 evaluated to be unsatisfactory. Recommended action to clean 01/26/2009 and perform retest Chemistry has not optimized raw water strategy to efficiently monitor and control corrosion in service water systems (e.g.,
AR-01039055 since April 2009, an increase in chlorination with intent to control 03/05/2010 microbiological growth led to increased corrosion on brass components due to overchlorination)
Document Title Revision / Date Copper corrosion rate in goal since April 2010 for Unit 3 and since May 2010 for Unit 2. Chlorine concentration typically within AR-1039055-35 12/30/2010 goal, but sometimes exceeds upper limit and will likely continue until online chlorine monitoring system is installed 2016 WANO Raw Water AFI cites ineffective chlorination in raw AR-1039055-39 water. some of the raw water piping is not provided chemical 09/01/2016 treatment Circulating water chemistry data indicates that target free AR-00759277 residual chlorine concentration was achieved 36% of the time in 04/04/2008 March 2008 AR-01020991 2B RHR room cooler evaluated to be unsatisfactory 01/25/2010 ESW mild steel corrosion inhibitor NALCO 3DT124 becoming obsolete. Vendor offered similar alternative NALCO 3DT424.
AR-03987883 03/21/2017 Chemistry reviewed technical literature and active ingredients are the same, but the polymer is changing.
Peach Bottom raw water chemical treatment does not sufficiently AR-01232297 protect against corrosion in HPSW system. Implementing 06/23/2011 biocide/corrosion inhibitor will increase asset protection SLRA AMP B.2.1.12, Closed Treated Water Systems Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: bacteria, clog, cooler, corros, foul, heat exch, leak, MIC, and 89-13.
The table below lists the documents that were reviewed by the staff and were found relevant to the Closed Treated Water Systems program. These documents were provided by Exelon or were identified in the staffs search of the applicants operating experience database. The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date AR-02725547 E2 Diesel Generator Jacket Cooling Water Leak Suspected 10/07/2016 AR-01691632 Unit 2 RBCCW Chemistry Trending Down Due to Suspect Leak 08/12/2014 AR-01440635 Leak on Piping Above TBCCW Expansion Tank 11/15/2012 SLRA AMP B.2.1.13, Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems Audit Activities. The staff conducted an independent search of Exelons operating experience database using keywords: crane, corro, defor, deflect, bolt, crack, fatigue, and cycle.
The table below lists the documents that were reviewed by the staff and were found relevant to the Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems. These documents were provided by Exelon or were identified in the staffs search of Exelons operating experience database. The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date AR-02527289 00H016 Gantry Crane Deficiencies 07/13/2015 AR-01361743 License renewal inspections for reactor building cranes 05/02/2012 PROCEDURE Periodic inspection of reactor building cranes 01/11/2013 M-017-001 AR-00901692 Perform inspections per NER-09-11-R 04/01/2009 AR-01653234 Defect identified on E4 EDG overhead crane 04/29/2014 AR-01253042 Deficiencies noted on turbine crane 0BH009 08/18/2011 SLRA AMP B.2.1.14, Compressed Air Monitoring Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: air, aging, moist, chlorine, and instrument.
No significant plant-specific operating experience associated with the Compressed Air Monitoring program was noted by the staff during its review.
SLRA AMP B.2.1.15, BWR Reactor Water Cleanup System Audit Activities. The staff conducted an independent search of Exelons operating experience database.
The table below lists the documents that were reviewed by the staff and were found relevant to BWR Reactor Water Cleanup System. These documents were provided by Exelon or were identified in the staffs search of Exelons operating experience database. The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date Program Basis Document - BWR Reactor Water Cleanup PB-PBD-AMP-XI.M25 Revision 2 System
Document Title Revision / Date NRC letter dated September 15, 1995, Reactor Water Cleanup (RWCU) System Weld Inspections at Peach ML090930466 09/15/1995 Bottom Atomic Power Station, Units 2 and 3 (TAC Nos.
M92442 and M92443)
Plant OE - XI.M25 BWR reactor water cleanup system Plant OE - XI.M25 12/2017 aging management program Implementing Implementing Documents - XI.M25 BWR reactor water 08/2014 Documents - XI.M25 cleanup system aging management program Plant Operating Water chemistry - plant operating experience - XI.M2 05/2016 Experience - X1.M2 Water Chemistry Program SLRA AMP B.2.1.16, Fire Protection Audit Activities. The staff conducted an independent search of Exelons operating experience database using keywords: penetration seal, fire door, fire damper, insulation, combustible, carbon dioxide, CO2, wall, ceiling, and floor.
The table below lists the documents that were reviewed by the staff and were found relevant to the Fire Protection Aging Management Program. These documents were identified in the staffs search of the applicants operating experience database. The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date Random walkdown of seismic gap penetration seals was performed; the seals did not meet acceptance criteria in DWG-3010, Revision 1 (no voids greater than a depth of 1 inch in AR-00848237 11/21/2008 surface of seal, shrinkage of foam away from pipes, tray, or barrier less than 1/8 inches); the seals were evaluated for repair, compensatory actions, and extent of condition NRC resident identified a link seal in penetration protruding from the wall about 1-2 inches, along with one bolt that was AR-04056797 missing; the foam seal on other side is sufficient for fire 09/28/2017 containment; the link seal was recommended to be repaired or replaced Door #R31 was found to be leaking and letting excessive air AR-04072454 flow through; immediately notified Supervisor and 11/08/2017 recommended repair or replacement of door seals
Document Title Revision / Date AR-04059540 AR-03949290 AR-01643697 AR-01625690 AR-01381458 Latch on door #388 sticking and intermittently preventing door AR-01162732 from latching; immediately notified Supervisor and recommended investigation and repair AR-00998614 AR-00996858 AR-00965783 AR-00945934 AR-00848118 Door #307 in fan room 165 foot elevation sticks when attempting to close due to malfunctioning door handle.
AR-03994441 04/05/2017 Recommend fixing door; immediately posted sign and generated IR Door so rusted that door started to cave in; door will have to be replaced (01/28/2007).
Door replacement scheduled for 2012; work was not performed AR-03801968 01/28/2007 (09/28/2012)
Door replacement was not completed in 2012 due to lack of engineering support (10/26/2012).
AR-02734298 Door would not unlatch when carding out. 10/29/2016 Door #149 will not latch; took immediate compensatory AR-02565724 measures in accordance with SY-PB-101-102; recommended 10/05/2015 investigation and repair.
One cinder block detached from mortar, creating a void around the block. The wall is not an Appendix R fire barrier required AR-02696748 for safe shutdown, but it does separate plant computer rooms; 07/26/2016 evaluated condition such that there is reasonable assurance that the wall will perform intended function.
Two deficiencies in fire barrier wall TB2-150-302-S; (1) upper west end corner has 30-40 pound chunk of concrete hanging in place; additional concrete lying below (2) penetration seal 3015 AR-01422732 10/05/2012 and 3015A-N exhibiting mild inward deterioration; recommend evaluation/inspection of loose concrete and deteriorating penetration material to determine appropriate action Five of seven fire extinguishers available for operations to use AR-01342499 03/19/2012 as replacements were identified as no good
Document Title Revision / Date Appearance of leakage near roof along DDFP exhaust header back down in to DDFP room. Recommend scheduling roof AR-02619638 inspection to verify insulation and flashing intact in order to 01/31/2016 avoid risk of roof fire as previously experienced on one of EDGS Fire insulation material was knocked off a steel column.
Recommendations made to reapply the fire insulation material AR-01259015 09/02/2011 to the steel column and inspect the area to identify/fix any other steel that may be missing insulation RB3-091-040-2510 fire barrier penetration failed inspection per AR-00888533 03/04/2009 its installation detail E-2 EDG room ceiling louver failed and fell out of the ceiling.
The resulting opening is a 36 x 4 hole in ceiling. In addition to AR-00842348 11/08/2008 repair, recommendations made to check all louvers for extent of condition.
NRC resident identified caulk was missing or partially missing AR-01188313 from the gap around the concrete covers above manholes 16, 03/16/2011 17, 18, 40. Caulk is a required part of fire barrier seal Enhancement to E-1400, Sh. 9. E-1400 Sh. 9 describes requirements for cable fire proofing, but does not specify AR-03947643 whether cables are to be wrapped as a bundle or as a single 11/30/2016 cable. Recommend revision to include individual wrapping requirements up to penetration seal.
Several cable trays in overhead have black tape/wrapping with AR-01020308 01/23/2010 fire proofing material that is peeling and coming off.
Approximately 24 feet of fire system piping in each unit AR-00878889 02/10/2009 circulation pump bay requires insulation to prevent freezing.
Maintenance instructions in the field need to include guidance to assess and replace oil contaminated insulation. Enhance AR-01194716 03/30/2011 procedures and training on risk associated with insulation contaminated with oil.
SLRA AMP B.2.1.17, Fire Water System Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: biofoul, biological, block, break, clog, damage, deposits, drainage, fail, flow restrict, foul, hole, indication, lined, lining, masonry, mortar, recur, rupture, sediment, silt, and sprinkler.
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 staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date A sprinkler head is leaking in the operations managers office at a AR-791182 06/7/2008 rate of one drop every 2 - 3 minutes.
A sprinkler head is leaking in the third floor northeast corner of the AR-812251 08/29/2008 site management building.
The diesel-driven fire pump (DDFP) y-strainer cooling water inlet AR-815694 09/9/2008 is clogged with dirt and debris.
A one gallon per minute leak was detected in the fire water piping AR-850043 11/26/2008 near the Unit 2 condensate pump pit.
A break in the fire water system sprayed water on the 2C AR-868307 circulating water pump motor exciter cabinet; causing a Unit 2 01/18/2009 transient.
A sprinkler is leaking in the administrative building at a rate of one AR-915059 05/2/2009 drop per second.
AR-935435 A through-wall leak was detected on the DDFP cooling piping. 06/25/2009 A small leak was detected in an elbow for the sprinkler piping near AR-936777 06/29/2009 turbine bearing number 5.
Two piping leaks were detected in the 1-1/2-inch piping AR-937457 06/30/2009 associated with the DDFP.
There is a one drop per minute pinhole leak on the flange weld AR-946274 07/27/2009 associated with hand valve, HV-0-57C-12444.
A partially blocked main drain was detected during main drain AR-1031495 02/17/2010 testing.
A sprinkler head is leaking in the high bay warehouse at a rate of AR-1074273 05/27/2010 15 - 20 drops per minute.
AR-1087814 A pinhole leak was detected at hand valve, HV-037D-12300. 07/5/2010 A leak in the fire water header was detected as evidenced by AR-01094142 07/25/2010 water spraying in the vicinity of 3A moisture separator area.
Corrosion was noted on a sprinkler in the moisture separator AR-1114191 09/17/2010 area.
A leak in the discharge piping of the motor-driven fire pump AR-1135415 11/3/2010 (MDFP) resulted in piping replacement.
A pinhole leak was detected downstream of BS-0421 [basket AR-1140078 11/14/2010 strainer]; spraying 16 milliliters/minute.
Four pinhole leaks were detected downstream of AR-1175779 02/15/2011 HV-037D-12300.
Document Title Revision / Date AR-1201388 The DDFP has nine small leaks from a downstream elbow. 04/12/2011 A fire water system leak was detected in the Unit 3 Turbine AR-1277329 10/17/2011 Building-135, north end.
One sprinkler head is leaking in a rebuild area at a rate of 32 AR-1343009 03/20/2012 drops per minute.
One nozzle had very low flow during a deluge system test, AR-1349054 04/2/2012 RT-O-37B-356-2.
One sprinkler head is leaking on the third floor of the AR-1357329 04/23/2012 administration building at a rate of less than one drop per minute AR-1387581 DDFP cooling line y-strainer clogging 07/11/2012 AR-1397594 DDFP cooling line y-strainer clogging 08/5/2012 A pinhole leak associated with the relief valve for the MDFP was AR-1446739 11/30/2012 detected, which is leaking at a rate of 30 drops per minute Two sprinkler heads are leaking in the vice presidents office, AR-1489948 03/19/2013 which are leaking at a rate of 1 drop per minute A sprinkle head is leaking in the Unit 2 main turbine lube oil room AR-1663767 05/23/2014 at a rate of 3 drops per minute Point defects were detected in the internal mortar lining of the fire AR-2382429 water system main; there was no evidence of piping damage or 09/17/2014 corrosion The main drain test procedure, RT-O-37B-2, does not record AR-2412210 11/13/2014 static and dynamic pressure AR-2458840 A sprinkler head is leaking in the administrative building. 02/25/2015 The DDFP cooling water inlet pressure indicator, PI-0281, is AR-2488219 04/19/2015 trending downwards A sprinkler head in the instrument and controls managers office is AR-2500757 05/14/2015 dripping at a rate of one drop per minute A pinhole leak was detected downstream of hand valve, AR-2612224 01/14/2016 HV-037D-12300 associated with the DDFP Two sprinkler heads in a managers office were leaking at a rate AR-2669950 05/16/2016 of 10 to 15 drops per minute AR-2692153 The DDFP sensing line continues to clog 07/13/2016 PI-0281, associated with the DDFP cooling water supply, AR-2724449 10/5/2016 continues to trend downward.
Document Title Revision / Date A small pinhole leak was detected downstream of AR-4005626 05/2/2017 HV-037D-12300; associated with the DDFP.
One deluge nozzle was clogged for the Unit 2 startup and AR-4010971 emergency auxiliary transformer; there was no impact on the fire 05/15/2017 water protection function for the transformer.
There have been frequent instances of pinhole leaks occurring in AR-4026398 06/27/2017 the relief valve piping for the MDFP.
Several fire hydrants failed the flush test criteria due to failure to AR-4044061 08/21/2017 drain.
AR-4055356 Two sprinkler heads are dripping water 09/24/2017 Fire system piping was leaking in the location of the turbine T9 AR-4071934 11/2/2017 bearing. Five feet of pipe was replaced.
A deluge nozzle failed testing because water was trickling from AR-4071773 the head instead of spraying for the C main turbine deluge 11/7/2017 system.
One sprinkler head failed on the Unit 3 main turbine operating AR-4077706 11/24/2017 floor SLRA AMP B.2.1.18, Outdoor and Large Atmospheric Metallic Storage Tanks Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: crack, through-wall, pinhole, leak, tank, blister, delamination, coatings, rust, holiday, corrosion, insulation, refueling water storage tank (RWST/RST), and condensate storage tank (CST).
The table below lists the documents that were reviewed by the staff and were found relevant to the Outdoor and Large Atmospheric Metallic Storage Tanks Aging Management Program.
These documents were identified in the staffs search of the applicants operating experience database. The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date Lessons learned from tank inspection include using more appropriate lighting, qualifying other coatings at the site, qualifying other contractrs AR-01523775 to perform inspections and repairs, qualifying tank cleaning service, and 06/11/2013 identifying responsible parties for tank inspections in a more timely manner Weeds were found growing in the joints of Unit 3 CST moat. Indication AR-02561237 09/27/2015 of lack of complete integrity of secondary containment.
AR-02524605 Please generate Pims AR for Unit 2 CST internal recoating. 07/07/2015
Document Title Revision / Date During RFO 20, volumetric floor inspection of U2 CST (20T010) was attempted using Magnetic Flux Leakage (MFL). MFL tooling popped AR-02416582 11/24/2014 blisters as rolled across the floor; popping blisters expected, water behind blisters was not.
Unit 2 CST floor should be scheduled for proactive repair due to AR-04022739 06/16/2017 indications found during RFO 21. Repair Iaw Tank Code API653 During RFO 21, 12 indications identified as below screening wall AR-03965638 01/23/2017 thickness and would need to be evaluated Water absorbed into Unit 2 moat floor; moat floor is sealed and should AR-00792787 07/02/2008 not absorb water Water leak at heating steam pipe connection to Unit 2 CST. Water is AR-01003942 leaking from insulation where heating steam condensate return line 12/10/2009 exits the tank.
An inspection of moat integrity was performed as an EOC review.
Inspection of CST/RST moat identified that the sealant in a vertical AR-01282227 10/27/2011 seam where the moat wall meets the Unit 2 reactor building railroad airlock shows minor degradation.
20T010 CST tank very rusty at bottom of tank; it appears water AR-00761933 04/11/2008 accumulates in moat in this area.
Identified coating either peeling or rusting away in small areas around AR-02586319 the tank (RST) heating steam and condensate return connections at 11/12/2015 horizontal welds Actions recommended to proactively verify RST tank bottom integrity AR-01455775 12/26/2012 during next RST PM Sealing activities for Unit 3 CST and TDT moat will not take place in AR-00844188 2008. 20T010 Unit 2 CST/RST moat was completed, but all remaining 11/12/2008 moats will be re-sealed in 2009 Tritium found in hatch groundwater; actions recommended to verify Peach Bottom RST tank bottom integrity during next RST; RST is AR-01455775 12/26/2012 coated carbon steel on mildly corrosive ground; cathodic protection in proximity insufficient SLRA AMP B.2.1.19, Fuel Oil Chemistry Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: biofuel, biological, MIC, bacteria, sample, fuel oil, and diesel.
The table below lists the documents that were reviewed by the staff and were found relevant to the Fuel Oil Chemistry program. These documents were identified in the staffs search of the applicants operating experience database. The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date AR-00842578 E1 main fuel contains small amount of water 11/09/2008 AR-00856075 E1 FO tank water/sediment found in tank 12/14/2008 AR-00856080 E4 FO tank water/sediment found in tank 12/14/2008 AR-00926496 E4 EDG main fuel oil STOR TK has high bacteria 06/01/2009 AR-01206734 Water found in E3 fuel oil sample 04/23/2011 AR-01306107 ODT038 E4 EDG fuel oil tank sediments 12/22/2011 AR-01418484 E2 DG main FO storage tank upward trend in particulate 09/26/2012 AR-01479030 E3 EDG fuel oil storage tank bacteria 02/22/2013 AR-01510201 EDG fuel oil tank long term health plan 05/03/2013 AR-01681817 Buried E1 diesel piping guide wave 2014 07/14/2014 AR-02691462 Sludge and biological growth found in DDFP day tank 07/11/2016 SLRA AMP B.2.1.21, One-Time Inspection Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: blister, break, clam, coat, corro, crack, damage, delamin, fail, flaw, hole, holiday, rust, and scal.
The table below lists the documents that were reviewed by the staff and were found relevant to the One-Time Inspection Program. These documents were identified in the staffs search of the applicants operating experience database. The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date AR-00921199 Torus item 05/18/2009 AR-04024041 Torus coating inspection frequency 06/21/2017 AR-2571658 3R20 containment coating inspection results 10/16/2015 Coating defects and pinpoint rust in torus belly band AR-02413128 11/17/2014 area
Document Title Revision / Date AR-01603399 P2R20 - torus coating inspection 01/03/2014 AR-02407173 Pit with depth of 126 mils 11/05/2014 A boiler tube leak creating waste water disposal AR-01206713 04/23/2011 expense AR-01542130 Raw water inspection program process improvements 08/01/2013 SLRA AMP B.2.1.22, Selective Leaching Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: bronze, graphiti, dealloy, degraph, zinc, leach, dealum, and cast.
The table below lists the documents that were reviewed by the staff and were found relevant to the Selective Leaching program. These documents were identified in the staffs search of the applicants operating experience database. The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date AR-01257959 License renewal fire system testing for selective leaching 08/30/2011 SLRA AMP B.2.1.23, ASME Code Class 1 Small-Bore Piping Audit Activities. The staff conducted an independent search of Exelons operating experience database.
The table below lists documents that were reviewed by the staff and were found relevant to the audit. These documents were provided by Exelon or were identified in the staffs search of Exelons operating experience database. The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date XI.M35 References Basis for weld counts, second license renewal project Rev. 0 Part 1 AR-04065691 Steam leak at weld 10/23/2017 AR-04067473 EOC review for failed weld 10/26/2017 AR-00856352 Inspection of RI-ISI piping socket welds 12/15/2008 AR-04078978 Maintenance rule system 04 recommendation 11/29/2017
Document Title Revision / Date Maintenance rule system 04-1-1 performance criteria AR-4079492 11/30/2017 exceeded AR-2732668 Main steam D flow instrument lines small-bore piping 10/25/2016 SLRA AMP B.2.1.24, External Surfaces Monitoring of Mechanical Components Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: corros, drip, drop, leak, rust, and wall thin.
The table below lists the documents that were reviewed by the staff and were found relevant to the External Surfaces Monitoring of Mechanical Components program. These documents were provided by the applicant or were identified in the staffs search of the applicants operating experience database. The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date Air intake is 90% clogged with dust and lint; review preventive AR-02634061 maintenance work orders to determine if changes are needed 03/01/2016 to ensure screens are cleaned AR-02573369 Degraded RBCCW piping to recirc motor oil coolers 10/19/2015 AR-01635636 Walkdown of HPSW piping in Unit 3 RHR room 03/19/2014 SLRA AMP B.2.1.25, Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: aging, biofoul, block, corro, piping, leak, microbiologic, and loss of.
No significant plant-specific operating experience associated with the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components progam was noted by the staff during its review.
SLRA AMP B.2.1.26, Lubricating Oil Analysis Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: lube, oil, lubricating, wear, sample, water, and intrusion.
No significant plant-specific operating experience associated with the Lubricating Oil Analysis program was noted by the staff during its review.
SLRA AMP B.2.1.27, Monitoring of Neutron-Absorbing Materials Other than Boraflex Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: blister, Boral, NETCO, neutron absorb, and neutron.
The table below lists the documents that were reviewed by the staff and were found relevant to the Monitoring of Neutron-Absorbing Materials Other than Boraflex program. These documents were identified in the staffs search of the applicants operating experience database. The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date AR-01542109 Fuel rack insert design documents not updated correctly. 08/01/2013 NETCO inserts could not be installed in two Unit 2 spent fuel AR-01605678 01/08/2014 pool (SFP) locations.
AR-02734159 SFP cell location DD-19 not useable during core shuffle 1B 10/29/2016 AR-04047328 Incorrect tolerance value in SFP criticality analyses. 08/30/2017 SLRA AMP B.2.1.28, Buried and Underground Piping and Tanks Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: aging, buried, coat, corro, wrap, vault, underground, piping, microbiologic, loss of, holiday, flaw, excavat, galvanic, chloride, 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 program. These documents were identified in the staffs search of the applicants operating experience database. The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date AR-02382429 PBAPS buried fire protection pipe internal conditions 09/17/2014 External coating damage on buried emergency service water (ESW)
AR-01279994 10/22/2011 piping AR-04056450 PBAPS buried piping corrosion results 09/27/2017 Subsequent License Renewal (SLR) buried condensate storage pipe AR-04055916 09/26/2017 requires coating for slr AR-01137854 Pin hole leak identified on a ESW supply in excavation #2 11/09/2010
Operating Experience (OPEX) program action for buried fire protection AR-01561817 09/20/2013 corrosion AR-01255154 Coating degradation/external corrosion on buried pipe site #7 08/24/2011 AR-02513031 PBAPS buried pipe coating conditions near FLEX building 06/10/2015 SLRA AMP B.2.1.29, Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: blister, coat, block, delamin, flak, flaw, holiday, leak, lined, lining, peel, and spall.
The table below lists the documents that were reviewed by the staff and were found relevant to the Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks program. These documents were identified in the staffs search of the applicants operating experience database. The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date SLR Residual Heat Removal (RHR) heat exchanger water box AR-04049466 09/06/2017 coating not present AR-02524605 AR required to do condensate storage tank (CST) internal recoat 07/06/2015 AR-02414144 CST coating blisters popped while inspecting floor 11/16/2014 SLRA AMP B.2.1.30, ASME Section XI, Subsection IWE Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: bellows, blister, bolt, coat, containment, corro, crack, degrad, downcomer, drywell, rust, shell, torus, scal, moisture barrier, pit, and loss of material. vent, header.
The table below lists the documents that were reviewed by the staff and were found relevant to the LRA AMP B.2.1.30, ASME Section XI, Subsection IWE. These documents were provided by the applicant or were identified in the staffs search of the applicants operating experience database. The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date AR-01098438 Nos ID containment inspection issues not entered into cap 08/05/2010 AR-01113597, Inadequate thread engagement on bolts for Unit 2 N-110E, N-09/15/2010 (ALL) 01113593, 01113594 110A, N110-AC, Hatch
Document Title Revision / Date AR-02571658 P3R20 Containment Coating Inspection results - Unit 3 10/15/2015 AR-02417863 P2R20 Containment Coating Inspection results - Unit 2 11/25/2014 Pit with depth of 126 mils metal loss, Unit 2 torus underwater AR-02407173 11/5/2014 IWE inspection AR-02569613 P3R21 CISI repair - repair floor coating 10/9/2015 AR-01562169 Coating damage on inside diameter of drywell head Unit 3 09/19/2013 AR-02400490 P2R20 CNF-007 - coating damage on floor and wall of drywell 10/22/2014 AR-00820200 P2R17 CISI - peeling of moisture barrier 09/20/2008 AR-01563175 FME: containment general visual results P3R19 - downcomers 09/24/2013 AR-00970529 P3R17 VT-3 inspection of downcomers submerged surfaces 09/25/2009 AR-00974909 P3R17 CISI documentation of condition of downcomers 10/5/2009 P2R20 torus downcomers - perform asbestos abatement and AR-01391214 07/20/2012 recoat WO C0236452 P3R19 torus lining project (AR-1696762) 11/13/2013 WO C0240807 P2R19 torus lining project (AR-1753580) 12/5/2012 SLRA AMP B.2.1.31, ASME Section XI, Subsection IWF Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: bolt, degrad, crack, corro, struct, rust, SCC, hanger, support and IWF.
The table below lists the documents that were reviewed by the staff and were found relevant to the ASME Section XI, Subsection IWF program. These documents were provided by the applicant or were identified in the staffs search of the applicants operating experience database. The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date AR-4030738 Online ISI - inadequate thread engagement on 23HB-H23 07/11/2017 AR-04013046 MS clamp missing bolting 05/20/2017 AR-0257497 Broken hanger found on MSL drain line 10/23/2015
Document Title Revision / Date Project PEA-21158 Failure analysis of stud from a main steam line drain line 12/11/2015 AR-02737268 P2R21 ISI CNF-015 - spring can out of tolerance 11/04/2016 WO 04768628 23-DBN-H51; P2R22 - spring cans out of tolerance 04/06/2018 WO C0259988 23-DBN-H51 exam 11/14/2016 AR-02735294 Dual spring can, size, load scale, bolting 11/01/2016 AR-02648629 ISI inspection of 10HB-S10 (RHR support) 03/31/2016 AR-01421162 P2R19 ISI scope - PIMS AR for additional ISI inspections 10/02/2012 AR-02733492 ISI scope change - RHR hangers 10/27/2016 WO C0263353 NDE 10HB-H25 10HB-25(IA) 11/16/2016 AR-02401934 P2R20 ISI CNF-015 - 12DCN-H150 hanger out of tolerance 10/27/2014 AR-02733492 ISI scope change - RHR hangers 10/27/2016 AR-02402207 P2R20 ISI expanded scope for 12DCN-H150 10/28/2014 AR-02402431 P2R20 ISI expanded scope correction 10/28/2014 AR-01475216 P2R20 ISI scope - PIMS AR for ISI inspection of 12DCN-H150 02/14/2013 Nuclear safety related specification for fabrication installation Rev 4 M-00618 and inspection of critical pipe supports, hangers and restraints at Peach Bottom Atomic Power Station Units 2 and 3 01/23/15 SLRA AMP B.2.1.32, 10 CFR Part 50 Appendix J Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: LLRT, ILRT, and Pressure-Boundary.
The table below lists the documents that were reviewed by the staff and were found relevant to the 10 CFR Part 50, Appendix J Program. These documents were identified in the staffs search of Applicants operating experience database. The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date AR-01632412 Through wall HPSW leak identified during ST-O-032-635-3 03/12/2014
Document Title Revision / Date AR-01638733* Unit 2 ILRT activities 03/26/2014 AR-01639839 Low wall reading on former Unit 3 a HPSW ILRT line 03/28/2014 AR-01646381 Unit 3 A HPSW piping, ILRT extent of condition 04/11/2014 AR-02418132 Packing leak on RTV-2-14-036D 11/27/2014 AR-02418238 RTV-2-07B-2503B packing leaks 11/28/2014 AR-02418617 As found ILRT UNSAT for ST-J-07A-600-2 11/30/2014 AR-02720162 Nos programs assessment roll up for lessons learned 09/26/2016 AR-02718721 Nos id: U2 ilrt critique comments not dispositioned 09/22/2016 AR-02463849 LLRT results exceed normal leakage values 03/05/2015 AR-02530466 SV-2-07D-2671D failed off scale during LLRT 07/20/2015 AR-02684409 SV-3-07D-3671G exceed admin limit during LLRT 06/22/2016 AR-02667246 SV-2-07D2978G exceed admin limit during LLRT 05/09/2016 AR-02667062 SV-3-07D-3978C exceed admin limit 05/09/2016 AR-02659549 Exceeded SVLC for SV-3-07D-3671E during ST/LLRT 30.07D.05 04/22/2016 AR-02649404 A low level trend in inaccurate classification of IRS by SOC 04/01/2016 AR-02640532 SV-3-07D-3671A thru valve leakage, failed ST/LLRT30.07.01 03/15/2016 AR-02571383 Elevated leakage on AO-3-20-0833 10/15/2015 AR-02561375 Main steam line drain LLRT results 09/28/2015 AR-02561049 A inboard MSIV did not pass LLRT 09/26/2015 AR-02558419 AO-3-20-83 LLRT failure 09/21/2015 AR-00827484 CRD hatch failed LLRT 10/07/2008 AR-00826622 Assess P2R17 LLRT results 10/04/2008 AR-00826137 AO-2-20-083 failed off-scale as-left LRRT 10/03/2008 AR-00824880 ST/LLRT 20.20B.01 revealed leakage past valves 10/01/2008 AR-00824871 ST/LLRT 20.20B.01 revealed leakage past valves 10/01/2008 AR-00823017 MO-2-10-26A failed high leakage during LLRT 09/26/2008 AR-00818517 C MSIV line high leakage during LLRT 09/16/2008
Document Title Revision / Date AR-01112867 AO-20-7B-2502B failed LLRT ST/LLRT 20.07b.05 off scale high 09/14/2010 AR-04070394 Nos QV ID: indication on fitting 11/03/2017 DW penetration N-3 not IAW ASME XI exam, exemption AR-00742879 02/29/2008 requirements SLRA AMP B.2.1.33, Masonry Walls Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: block, masonry, crack, concrete, spall, mortar, wall, and steel.
The table below lists the documents that were reviewed by the staff and were found relevant to the Masonry Walls program. These documents were identified in the staffs search of the applicants operating experience database. The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date AR-01645153 Hairline crack in concrete block wall Unit 2 CPS pump room 04/09/2014 AR-02390129 Void found in block wall 09/30/2014 AR-02657801 Large cracks in masonry wall TB3 135 elevation 04/18/2016 SLRA AMP B.2.1.34, Structures Monitoring Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: rebar, degrad, crack, corro, struct, manhole, concrete, rust, SCC, tank, underground, leak, efflor, leach, and excav.
The table below lists the documents that were reviewed by the staff and were found relevant to the Structures Monitoring Program. These documents were provided by the applicant or were identified in the staffs search of the applicants operating experience database. The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date Maintenance rule walkdowns datasheet (site structures ROOM 1 - ROOM X26 1997-LATEST monitoring program walkdowns database)
Additional scope for HPSW east exterior wall repair (circulating AR-4114053 03/12/2018 water pump structure parapet)
AR-2561844 Moisture barrier degradation (drywell) 09/28/2015
Document Title Revision / Date Cracked concrete at 3a RHR north wall requires repair -
AR-2448766 02/16/2015 evaluated per AR-243612312-03 AR-4047174 Effloresce build-up on concrete wall - water intrusion 08/30/2017 AR-2482098 Reactor building concrete wall spalling 04/08/2015 AR-0745523 Multiple bolting IRS identified at Peach Bottom 03/06/2008 AR-4066929 SLR: clarify cathodic protection in UFSAR for structural piles 10/25/2017 AR-4033732 Broken grout under switch yard supports 07/20/2017 AR-2482098 Reactor building concrete wall spalling 04/08/2015 AR-0864007 Groundwater intrusion deficiency identified during walkdowns 01/08/2009 AR-1332710 Spalled concrete 02/27/2012 Peach Bottom water samples (second license renewal AR-3965485 05/15/2017 samples) for AR-3965485 SLRA AMP B.2.1.35, 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, coroson, loosing bolt, and
- spall, The table below lists the documents that were reviewed by the staff and were found relevant to the Inspection of Water Control Structures Associated with Nuclear Power Plants. These documents were provided by the applicant or were identified in the staffs search of the applicants operating experience database. The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date AR-04032918 Excessive cracking & spalling on exterior pump structure 07/14/2014 AR-02702731 The wall/ceiling is chipping off in 2B CCW room 08/10/2016 AR-01668542 Concrete degrading at door C16 inner screen building 06/06/2014 AR-0656538 Manhole 77 has damaged concrete 05/06/2014 AR-3014280 Crack on emergency cooling tower and reservoir wall 06/03/1997 AR-3894011 Degradation from replacement of 2A circulating screen 03/10/2017
Document Title Revision / Date AR-3406097 HV-2-30-23427A, 2A sluice gate deficiencies 06/11/2012 AR-3406099 HV-3-30-33427B-3B sluice gate deficiencies 06/11/2012 SLRA AMP B.2.1.36, Protective Coating Monitoring and Maintenance Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: blister, coat, delamin, lined, lining, peel, and perforat.
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 staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date AR-04047208 Coating Check-In and Re-Baseline. 08/30/2017 AR-04024041 Update torus inspection frequency for Subsequent License Renewal. 06/21/2017 AR-03952615 Drywell coatings not captured in unqualified coatings logs. 12/13/2016 AR-02571658 Unit 3 refueling outage 20 containment coating inspection results. 10/16/2015 AR-02417863 Unit 2 refueling outage 20 containment coating inspection results. 11/26/2014 AR-02413128 Coating defects and pinpoint rust in torus belly band area. 11/17/2014 AR-02399188 Duane Arnold torus coating delamination operating experience review. 10/22/2014 AR-02176881 Part 21 - coating failure to meet specified irradiation during test. 09/10/2014 AR-01570061 Unit 3 torus coating application non-compliance. 10/09/2013 AR-01567612 Unit 3 torus surface preparation non-compliance. 10/04/2013 AR-01691387 Unit 3 torus TOC above limit. 08/11/2014 AR-01601996 Adverse trend in torus TOCs. 12/30/2013 AR-01601661 Unit 2 torus water above limit for TOC. 12/29/2013 AR-1420875 Containment visible on blasted surface. 10/01/2012 Main steam safety relief valve discharge piping temperature is greater AR-01192421 03/25/2011 than the torus coating qualified temperature.
AR-01431174 Torus relining project increased unqualified coatings. 10/25/2012
Document Title Revision / Date AR-01423337 Coating application non-conformance reports. 10/06/2012 SLRA AMP B.2.1.37, Electrical Insulation for Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Audit Activities. The staff conducted an independent search of the applicants operating experience database using the keywords: cable, embrittlement, cracking, discoloration, melting, swelling, surface contamination, insulation, and adverse localized, and searching by system numbers.
The table below lists the documents that were reviewed by the staff and were found relevant to the Electrical Insulation for Electrical Cables and Connections Not Subject to 10 CFR Section 50.49 Environmental Qualification Requirements. These documents were identified in the staffs search of the applicants operating experience database. The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date E/S-7139-1 power cord outer jacket is bad due to dry rot.
AR-03955141 Conductors fine. Tape applied to cable jacket. No further action 12/20/2016 noted.
Cable inside starter cabinet 2A for the drywell chillers showing heat degradation. Heat source: control power transformer.
AR-02627247 Transformer relocated. Cable deemed to not need repair. [AR 02/17/2016 also references same conditions found on 3C drywell chiller and the A control room chiller.]
Cable inside starter cabinet 3C for the drywell chillers showing heat degradation. Heat source: control power transformer.
AR-02620248 Suggested course of action: repair cable and move transformer. 02/01/2016 Status: transformer not relocated and cable repair in next work window. Per the ar, cable repair on hold.
480V A24 bus and B24 bus ageing issues. The secondary contact connection separations in both switchgear are brittle AR-01502003 and breaking. Suggested course of action: look at repairing or 04/15/2013 replacing if the cooling towers will be required after the study.
No further details. AR closed.
Potential degradation of 480V MCC 4R4-R-B feeder cable.
Discovered as part of investigation of faulted 480V MCC 3R4-AR-01570557 10/09/2013 R-B feeder cable due to close proximity to main steam lines in moisture separator area.
Documentation of 3SU cable repair/replacement plan. Subject AR-01516504 cable is part of the aging monitoring process but the AR 05/21/2013 provides detailed insight into the actual plan followed.
SLRA AMP B.2.1.38, Electrical Insulation for Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements used in 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 circuit, neutron flux, radiation monitor, thermal transient, moisture intrusion, electrical insulation, sensitive circuit, high voltage circuit, low-level current signal, calibration, and surveillance test.
The table below lists the documents that were reviewed by the staff and were found relevant to the Electrical Insulation for Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements used in Instrumentation Circuits. These documents were identified in the staffs search of the applicants operating experience database. The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date During performance of the source calibration, the 2D main steam line radiation monitor failed downscale. Maintenance I&C found scaffolding erected for the calibration was removed and AR-01118854 10/28/2010 the cables running to the C & D radiation elements were not as uniform as the A & B. the cause of the failure was due to failed connectors and cable disturbance.
During calibration check on PS-3-02-071L there were 11 cables AR-01557269 found to be bad. Cable and connector will need to be replaced. 10/12/2013 PS-3-02-071L will need to be retested.
The 2D MSL rad monitor drifted from 11 mr/hr to downscale over an approximately 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> period. The 2 A/B/C rad monitors AR-02410383 remained constant at 11-12 mr/hr during this time. The detector 12/11/2014 drifted downscale due to the nature and energy levels of gamma radiation.
SLRA AMP B.2.1.39, Electrical Insulation for Inaccessible Medium-Voltage Power Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: cable, manhole, submerge, insulation, 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 Electrical Insulation for Inaccessible Medium-Voltage Power Cable Not Subject to 10 CFR 50.49 EQ Requirements. These documents were provided by the applicant or were identified in the staffs search of the applicants operating experience database. The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date 2B Condensate pump cables were tan delta tested in 2004.
Cable 2H0206A phase C tested further study required (IR AR-2537689 08/04/2015 2412081). This is 2 years after the last test, which would satisfy the requirement of an increased frequency testing.
Water level in MH-069 was found 7.1 below water level sensor.
AR-4087039 The threshold was 11 below the water level sensor. Applicant 12/23/2017 initiated a CR to pump out water.
2C condensate pump cable were tan delta tested in 2014.
Cable 2H0207A phase C tested further study required AR-2537706 08/04/2015 (IR2412089). This is 2 years after the last test, which would satisfy the requirement of an increased test frequency.
This issue is written to create an AR-to perform work required by Rev.1 of OP evaluation 10-002. The power cable feeding AR-1093787 07/23/2010 0CX026 shall be tan delta tested, removed and sent to a lab for analysis. A new cable shall be installed in its place.
Per mysmart cover website MH-106 has a high level advisory.
AR-4094210 An applicant staff notified shift supervisor and water was 01/16/2018 pumped out.
SLRA AMP B.2.1.40, Electrical Insulation for Inaccessible Instrument and Control Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: cable, manhole, submerge, insulation, sump pump, degraded cable, and vault.
The table below lists the documents that were reviewed by the staff and were found relevant to the Electrical Insulation for Inaccessible Instrument and Control Cables Not Subject to 10 CFR 50.49 EQ Requirements. These documents were provided by the applicant or were identified in the staffs search of the applicants operating experience database. The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date Water level in MH-042 was found 25.8 below the water level AR-4087254 sensor. The threshold was 26.0 below the water level sensor. 12/25/2017 Applicant initiated a CR to pump out water.
Water level in MH-069 was found 7.1 below water level sensor.
AR-4087039 The threshold was 11 below the water level sensor. Applicant 12/23/2017 initiated a CR to pump out water.
Per mysmart cover website, MH-106 has a high level advisory.
AR-4094210 An applicant staff notified a shift supervisor. Water was 01/16/2018 pumped out.
Document Title Revision / Date Water level in MH-042 was found 20.4 below water level AR-4095189 01/10/2018 sensor. Applicant pumped water out.
Water level in MH-062 was found 13 below the water level AR-4087163 sensor. The threshold was 24 below the water level sensor. 12/25/2017 Applicant initiated a CR to pump out water.
SLRA AMP B.2.1.41, Electrical Insulation for Inaccessible Low-Voltage Power Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: cable, manhole, submerge, insulation, 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 Electrical Insulation for Inaccessible Low-Voltage Power Cables Not Subject to 10 CFR 50.49 EQ Requirements. These documents were provided by the applicant or were identified in the staffs search of the applicants operating experience database. The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date Water level in MH-042 was found 25.8 below the water level AR-4087254 sensor. The threshold was 26.0 below the water level sensor. 12/25/2017 Applicant initiated a CR to pump out water.
Water level in MH-069 was found 7.1 below water level sensor.
AR-4087039 The threshold was 11 below the water level sensor. Applicant 12/23/2017 initiated a CR to pump out water.
Per mysmart cover website, MH-106 has a high level advisory.
AR-4094210 An applicant staff notified his shift supervisor. Water was 01/16/2018 pumped out.
This issue is written to create an AR to perform work required by Rev.1 of OP evaluation 10-002. The power cable feeding AR-1093787 07/23/2010 OCX026 shall be tan delta tested, removed and sent to a lab for analysis. A new cable shall be installed in its place.
Water level in MH-062 was found 13 below the water level AR-4087163 sensor. The threshold was 24 below the water level sensor. 12/25/2017 Applicant initiated a CR to pump out water.
SLRA AMP B.2.1.42, Metal Enclosed Bus Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: enclosed bus, electrical bus, connections, elastomers, gaskets, MEB, cable bus, and metal enclosed bus.
The table below lists the document that was reviewed by the staff and was found relevant to the Metal Enclosed Bus program. This document was provided by the applicant or was identified in the staffs search of the applicants operating experience database. The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date 3B transformer to isophase bus transition piece and flex links AR-00871272 were found degraded. Parts were replaced as needed and an 02/23/2009 extent of condition IR-873040 was created.
SLRA AMP B.2.1.43, Electrical Cable Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: cable connection, increased resistance, loose connection, discoloration, thermal cycling, thermography, ohmic heating, chemical contamination, corrosion, vibration, and oxidation.
The table below lists the documents that were reviewed by the staff and were found relevant to the Electrical Cable Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements program. These documents were provided by the applicant or were identified in the staffs search of the applicants operating experience database. The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date Thermography on turbine building crane identified anomalies.
AR-00813174 10/02/2018 Connections were tightened and monitoring was increased.
Motor control center (MCC) load side connection showed a delta temperature (T) of 22 degrees. Per MA-AA-716-230-AR-01513403 06/12/2013 1003, delta T of 14 to 50 is blue action level. Connections were tightened and rescanned.
Discovered overheating of circulating water pump 3A.
AR-01129217 Developed a list of other motors that may have similar field 10/20/2010 connections.
Checked cables and connectors of 2D main steam line AR-01118854 10/28/2010 radiation monitor and replaced connector.
Found a burnt motor connection insulation. Cause found to be one-bolt connection instead of two. Also dielectric grease was AR-01112568 01/26/2011 not used. Installed belleville washers and two bolts. Also affects other motors in core spray, EDG, service water systems.
SLRA AMP B 3.1.1, Fatigue Monitoring Program Audit Activities. The staff conducted an independent search of applicants operating experience database using keywords: "Fatigue Monitoring," "FatiguePro," cycles, fatigue usage, cumulative usage and usage factor.
The table below lists the documents that were reviewed by the staff and were found relevant to the Fatigue Monitoring Program. These documents were provided by applicant or identified in the staffs search of applicants operating experience database. The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date AR-00915984 Update of PB fatigue monitoring program 04/28/2012 AR-01555998 RPV fatigue monitoring program documentation 05/25/2019 AR-04021824 SLR: improper close out of FLR FMP commitment 01/09/2018 AR-03952475 Fatigue & transient monitoring program deficiencies 03/28/2017 AR-04067104 Fatigue monitoring program recommendations 07/28/2018 SLRA AMP B.3.1.3, Environmental Qualification of Electric Equipment Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: EQ, 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 Electric Equipment. These documents were provided by the applicant or were identified in the staffs search of the applicants operating experience database. The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date It was recommended that the static O-ring pressure switch, model N-AA3, be replaced as soon as reasonable possible and AR-4095189 not to approach the maximum EQ adjusted qualified life. 01/19/2018 Because no EQ preventive maintenance existed for replacement due to extensive EQ period.
Document Title Revision / Date Applicant has identified that the bendix connectors associated with 3AC872 and 3BC872 (drywell/torus CAC/CAD analog PNL. A/B) have not been replaced within the EQ qualified life of 14.86 years per EQ binder PB-037A. Work order history AR-4021418 indicated the bendix connectors were last replaced in 1994. 06/12/2017 Applicant created an assignment to EQ engineer to determine from the temperature data if there was a basis for providing an extended qualified life and replaced all eight bendix connectors as soon as possible.
As described in IR 4005664, PS-9087F did not have an EQ maintenance task to replace the subject pressure switch before AR-4025572 06/26/2017 the end of 45 year EQ life. Applicant wrote an IR and created work order to replace the pressure switch.
Applicant identified during plant extension per IR 3997737 03, pressure switches must be replaced per EQ requirements.
AR-4095177 01/19/2018 Applicant would create an IR for each PS-2(3)10-120A/B/C/E/F/G/H switch for EQ replacement.
As the result of recent revision to EQ life calculation, the qualified life of 8 relays have been reduced from 25 years to 19.31 years. Initial investigation has determined that these components were last replaced under their respective PMS in AR-2480628 04/06/2015 1989. Based on the new EQ life calculations, these relays were due for replacement in June of 2008. Design engineering to determine actual EQ life of these components and provide due dates for replacement.
SLRA TLAA 4.2.1, Reactor Vessel and Internals Neutron Fluence Analyses Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: Crack, SCC, Vessels, and Weld.
No significant plant-specific operating experience associated with TLAA 4.2.1, Neutron Fluence Analyses, was noted by the staff during its review.
SLRA TLAA 4.2.3, Reactor Vessel Adjusted Reference Temperature (ART) Analyses Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: Crack, SCC, Vessels, and Weld.
No significant plant-specific operating experience associated with TLAA 4.2.3, Reactor Vessel Adjusted Reference Temperature (ART) Analyses. was noted by the staff during its review.
SLRA TLAA 4.2.4, Reactor Vessel Pressure-Temperature (P-T) Limits Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: pressure-temperature, P-T, and PTLR.
No significant plant-specific operating experience associated with TLAA 4.2.4, Reactor Vessel Pressure-Temperature (P-T) Limits, was noted by the staff during its review.
SLRA TLAA 4.2.5, Reactor Vessel Circumferential Weld Failure Probability Analyses Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: circumferential weld, shell weld, 14R-51.
No significant plant-specific operating experience associated with TLAA 4.2.5, Reactor Vessel Circumferential Weld Failure Probability Analyses, was noted by the staff during its review.
SLRA TLAA 4.2.6, Reactor Vessel Axial Weld Failure Probability Analyses Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: axial weld, shell weld, 14R-51.
The table below lists the documents that were reviewed by the staff and were found relevant to TLAA 4.2.6, Reactor Vessel Axial Weld Failure Probability Analyses. These documents were identified in the staffs search of the applicants operating experience database. The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date AR-02458945 P3R20 scope add - RPV Shell welds 03/27/2015 AR-02510740 P2R21 IVVI executive challenge action items 12/30/2015 AR-02570753 3R20 ISI - UT exam results of RPV shell welds 11/21/2015 SLRA TLAA 4.2.7, Reactor Vessel Reflood Thermal Shock Analysis Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: Crack, SCC, Vessels, and Weld.
No significant plant-specific operating experience associated with TLAA 4.2.7, Reactor Vessel Reflood Thermal Shock Analysis, was noted by the staff during its review.
SLRA TLAA 4.2.8, Core Shroud Reflood Thermal Shock Analysis Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: Crack, SCC, Vessels, and Weld.
No significant plant-specific operating experience associated with TLAA 4.2.8, Core Shroud Reflood Thermal Shock Analysis, was noted by the staff during its review.
SLRA TLAA 4.2.13, Replacement Core Plate Plug Extended Life Irradiation - Enhanced Stress Relaxation Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: core plate, mandrel spring, plugs.
No significant plant-specific operating experience associated with TLAA 4.2.13, Replacement Core Plate Plug Extended Life Irradiation - Enhanced Stress Relaxation, was noted by the staff during its review.
SLRA TLAA 4.2.14, First License Renewal Application Core Shroud IASCC and Embrittlement Analysis Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: core shroud, IASCC, embrittlement.
The table below lists the document that was reviewed by the staff and was found relevant to TLAA 4.2.14, First License Renewal Application Core Shroud IASCC and Embrittlement Analysis. This document was identified in the staffs search of the applicants operating experience database. The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date AR-00798768 Deviation from BWRVIP needed guidance 08/22/2008 SLRA TLAA 4.2.15, Unit 3 Core Spray Replacement Piping Bolting Loss Of Preload Evaluation Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: Crack, SCC, Vessels, and Weld.
No significant plant-specific operating experience associated with TLAA 4.2.15, Unit 3 Core Spray Replacement Piping Bolting Loss of Preload Evaluation, was noted by the staff during its review.
SLRA TLAA 4.3.1, Transient Cycle And Cumulative Usage Projections For 80 Years Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: design cycles, CUF, EAF and fatigue cracking.
No significant plant-specific operating experience associated with the TLAAs Section 4.3.1 Metal Fatigue of Class 1 Components, 4.3.2 Metal Fatigue of Piping Components, and 4.3.3 Environmentally Assisted Fatigue, was noted by the staff during its review.
SLRA TLAA 4.3.5, Environmental Fatigue Analyses For RPV And Class 1 Piping Audit Activities. The staff conducted an independent search of the applicants operating experience database and reviewed the relevant documents listed in the table below.
No significant plant-specific operating experience associated with TLAA 4.3.5, Environmental Fatigue Analyses For RPV And Class 1 Piping, was noted by the staff during its review.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date PB-TLAABD, Part 1 Time-Limited Aging Analysis (TLAA) Basis Document - Part 1 - Revision 0 TLAA Identification PB-TLAABD, Part 2 Time-Limited Aging Analysis (TLAA) Basis Document - Part 2 - Revision 0 TLAA Evaluation, Section 4.3.5, Environmental Fatigue analysis for RPV and Class 1 Piping SIR-99-091 Report on System Review and Recommendations or a Transient Revision 0 and Fatigue Monitoring System at Peach Bottom Atomic Power Station 602-S-VC-23 Fatigue Analysis for Limiting Piping Components Revision 0 1400630.301 60 and 80 Year Fatigue Projections Revision 1 1400630.302 Peach Bottom Fatigue Usage Assessment Revision 0 1400630.303 Peach Bottom Environmentally-Assisted Fatigue Screening Revision 0 ER-AA-470 Fatigue and Transient Monitoring Program Revision 7 ST-J-080-940-2 Reactor Pressure Vessel Fatigue Monitoring Record Revision 9 SIR-99-122 Cycle Counting and Cycle-based Fatigue Report for the Revision 6 Transient and Fatigue Monitoring System for Peach Bottom Atomic Power Station Units 2 and 3 SLRA TLAA 4.3.6.1, Generic BWR Fatigue Analyses for Various Reactor Vessel Internal Components Audit Activities. The staff conducted an independent search of the applicants operating experience database and reviewed the relevant documents listed in the table below.
No significant plant-specific operating experience associated with TLAA 4.3.6.1, Generic BWR Fatigue Analyses for Various Reactor Vessel Internal Components, was noted by the staff during its review.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date PB-TLAABD, Part 1 Time-Limited Aging Analysis (TLAA) Basis Document - Part 1 - Revision 0 TLAA Identification
Document Title Revision / Date PB-TLAABD, Part 2 Time-Limited Aging Analysis (TLAA) Basis Document - Part 2 - Revision 0 TLAA Evaluation, Section 4.3.6.1, Generic BWR Fatigue Analyses for Various Reactor Vessel Internal Components NEDC-33566P GE Hitachi Nuclear Energy Safety Analysis Report for Exelon Revision 0 Peach Bottom Atomic Power Station Units 2 and 3 Constant Pressure Power Uprate NEDC-33873P GE Hitachi Nuclear Energy Safety Analysis Report for Peach Revision 0 Bottom Atomic Power Station Units 2 and 3 Thermal Power Optimization SLRA TLAA 4.3.6.2, Generic BWR Fatigue Analyses for the Core Shroud Audit Activities. The staff conducted an independent search of the applicants operating experience database and reviewed the relevant documents listed in the table below.
No significant plant-specific operating experience associated with TLAA 4.3.6.2, Generic BWR Fatigue Analyses for the Core Shroud, was noted by the staff during its review.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date PB-TLAABD, Part 1 Time-Limited Aging Analysis (TLAA) Basis Document - Part 1 - Revision 0 TLAA Identification PB-TLAABD, Part 2 Time-Limited Aging Analysis (TLAA) Basis Document - Part 2 - Revision 0 TLAA Evaluation, Section 4.3.6.2, Generic BWR Fatigue Analyses for the Core Shroud NEDC-33566P GE Hitachi Safety Analysis Report for Exelon Peach Bottom Revision 0 Atomic Power Station Units 2 and 3 Constant Pressure Power Uprate NEDC-33873P GE Hitachi Safety Analysis Report for Peach Bottom Atomic Revision 0 Power Station Units 2 and 3 Thermal Power Optimization 004N2968 GE Hitachi Report on Peach Bottom Atomic Power Station Revision 1 Units 2 and 3 Shroud Fatigue Information SLRA TLAA 4.3.6.3, Core Shroud Support Fatigue Analysis Reevaluation Audit Activities. The staff conducted an independent search of the applicants operating experience database and reviewed the relevant documents listed in the table below.
No significant plant-specific operating experience associated with TLAA 4.3.6.3, Core Shroud Support Fatigue Analysis Reevaluation, was noted by the staff during its review.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date PB-TLAABD, Part 1 Time-Limited Aging Analysis (TLAA) Basis Document - Part 1 - Revision 0 TLAA Identification PB-TLAABD, Part 2 Time-Limited Aging Analysis (TLAA) Basis Document - Part 2 - Revision 0 TLAA Evaluation, Section 4.3.6.3, Core Shroud Support Fatigue Analysis Reevaluation SIR-98-030 Thermal Events at Peach Bottom Atomic Power Station 4/3/1998 NEDC-33566P GE Hitachi Safety Analysis Report for Exelon Peach Bottom Revision 0 Atomic Power Station Units 2 and 3 Constant Pressure Power Uprate NEDC-33873P GE Hitachi Safety Analysis Report for Peach Bottom Atomic Revision 0 Power Station Units 2 and 3 Thermal Power Optimization 1400630.303 Peach Bottom Environmentally-Assisted Fatigue Screening Revision 0 SLRA TLAA 4.3.6.4, Jet Pump Diffuser/Core Shroud Support Plate Fatigue Analysis Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: Fatigue and Stress.
No significant plant-specific operating experience associated with the TLAA 4.3.6.4, Jet Pump Diffuser/Core Shroud Support Plate Fatigue Analysis, was noted by the staff during its review.
SLRA TLAA 4.3.6.5, Replacement Steam Dryer Stress Report and Fatigue Evaluation Audit Activities. The staff conducted an independent search the applicants operating experience database.
During its audit, the staff reviewed onsite documentation provided by the applicant. The table below lists the documents that were reviewed by the staff and were found relevant to TLAA 4.3.6.5, Replacement Steam Dryer Stress Report and Fatigue Evaluation. The staff will document its review of relevant operating experience in the SER RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date Revision 0 / September PB-TLAABD, PART 1 TLAA basis document - Part 1 - TLAA identification 2017 TLAA basis document - Part 2 - TLAA evaluation, Section PB-TLAABD, PART 2 4.3.6.5, replacement steam dryer stress report and fatigue Revision 0 evaluation PACKAGE ADAMS License amendment request (LAR) - extended power uprate ACCESSION NO. 09/28/2012 (EPU) for Peach Bottom, Units 2 and 3 ML122860201
Document Title Revision / Date EPRI REPORT NO. BWRVIP-139, Revision 1-A: BWR vessel and internals 11/2017 3002010541 project, steam dryer inspection and flaw evaluation guidelines SLRA TLAA 4.6, Primary Containment Fatigue Analyses; 4.6.1 Primary Containment Structures, Penetrations, and Associated Components with Fatigue Analyses; 4.6.2 Containment Process Line Penetration Bellows Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: Fatigue, Torus, Penetration, and Bellows.
The table below lists the documents that were reviewed by the staff and were found relevant to the TLAA 4.6, Primary Containment Fatigue Analyses. These documents were identified in the staffs search of the applicants operating experience database. The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date AR-04031330 Rain water intrusion sealing suggestion 07/13/2017 AR-01086963 Torus dewatering drain valve found degraded 07/01/2010 AR-01398861 3C RHR HPSW return pipe penetration seal degraded 08/09/2012 AR-00742879 DW penetration N-3 not iaw ASME xi exam, exemption requirements 02/29/2008 AR-04067104 Fatigue monitoring program recommendation 10/26/2017 AR-01290273 GEH Part 21 SC 11-10: interruption/delay in RHR drywell SPR 11/14/2011 AR-04047489 3K srv bellows leak alarm 08/30/2017 AR-01175843 Penetration seal is being pushed out 02/16/2011 SLRA TLAA 4.7.1, Cranes Cyclic Loading Analyses Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: crane, crack, fatigue, cycle, defor, and deflect.
No significant plant-specific operating experience associated with the TLAA 4.7.1, Crane Cyclic Loading Analyses, was noted by the staff during its review.
SLRA TLAA 4.7.4, Fracture Mechanics Analysis of ISI Reportable Indications for Group I Piping: As-Forged Laminar Tear in a Unit 3 Main Steam Elbow Near Weld 1-B-3BC-LDO Discovered During Preservice UT Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: Stress and cracking.
No significant plant-specific operating experience associated with TLAA 4.7.4, Fracture Mechanics Analysis of ISI Reportable Indications for Group I Piping: As-Forged Laminar Tear in a Unit 3 Main Steam Elbow Near Weld 1-B-3BC-LDO Discovered During Preservice UT, was noted by the staff during its review.
SLRA TLAA 4.7.5, Unit 3 Core Spray Replacement Piping Fatigue and Leakage Assessment Audit Activities. The staff conducted an independent search of Exelons operating experience database.
The table below lists the documents that were reviewed by the staff and were found relevant to the TLAA 4.7.5, Unit 3 Core Spray Replacement Piping Fatigue and Leakage Assessment.
This document was provided by Exelon or was identified in the staffs search of Exelons operating experience database. The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date Peach Bottom Atomic Power Station Unit 3 piping replacement Revision 0, GEH-004N3501 design life extension evaluation August 2017 AMR Item OE Input Not Associated with an AMP Audit Activities. The staff conducted an independent search of the applicants operating experience database using keywords: concrete, froz, freeze, thaw, elevated temperature, crack, expan, pattern, leach, settle.
The table below lists the document that was reviewed by the staff and was found relevant to the concrete and inaccessible areas. This document was provided by the applicant or were identified in the staffs search of the applicants operating experience database. The staff will document its review of relevant operating experience in the SER.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date AR-01341413 ECT has calcium like deposits leaching out of building 03/15/2012
- 3. Applicant Personnel Contacted During Audit PARTICIPANTS ORGANIZATION John Hilditch Exelon Paul Weyhmuller Exelon
John Hufnagel Exelon Michael Baker Exelon Brian Placido Exelon James Annett Exelon Leah Ritz Exelon Mary Kowalski Exelon Debora Spamer Exelon Scott Kauffman Exelon Peter Tamburro Exelon
- 4. Exit Meeting An exit meeting was held with the applicant on September 27, 2018, to discuss the results of the operating experience audit. The staff may issue requests for additional information to support completion of the staffs SLRA review.