IR 05000277/2018011

Post-Approval Site Inspection for License Renewal - Phase 4 Inspection Report 05000277/2018011 and 05000278/2018011

ML18355A401
Person / Time
Site:	Peach Bottom
Issue date:	12/20/2018
From:	Mel Gray Engineering Region 1 Branch 1
To:	Bryan Hanson Exelon Generation Co, Exelon Nuclear
Gray M
References
IR 2018011
Download: ML18355A401 (9)

Text

ber 20, 2018

SUBJECT:

PEACH BOTTOM ATOMIC POWER STATION - POST-APPROVAL SITE INSPECTION FOR LICENSE RENEWAL - PHASE 4 INSPECTION REPORT 05000277/2018011 AND 05000278/2018011

Dear Mr. Hanson:

On November 30, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at the Peach Bottom Atomic Power Station, Units 2 and 3 and discussed the results of this inspection with Mr. Matthew Herr, Plant Manager, and other members of your staff. The results of this inspection are documented in the enclosed report.

The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.

In conducting the inspection, the team examined a sample of your Aging Management Programs to verify the effects of aging were being managed to ensure structures, systems, and components in the scope of these programs maintained the ability to perform their intended functions. The inspection involved review of your implementing procedures, evaluations, and corrective actions associated with your monitoring activities. The inspection also involved plant equipment walkdowns and interviews with station personnel.

The NRC inspectors did not identify any finding or violation of more than minor significance. This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Mel Gray, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos. 50-277 and 50-278 License Nos. DPR-44 and DPR-56

Enclosure:

Inspection Report 05000277/2018011 and 05000278/2018011

Inspection Report

Docket Numbers: 50-277 and 50-278 License Numbers: DPR-44 and DPR-56 Report Numbers: 05000277/2018011 and 05000278/2018011 Enterprise Identifier: I-2018-011-0052 Licensee: Exelon Generation Company, LLC (Exelon)

Facility: Peach Bottom Atomic Power Station, Units 2 and 3 Location: Delta, Pennsylvania Inspection Period: November 26 - 30, 2018 Inspectors: K. Mangan, Senior Reactor Inspector, Division of Reactor Safety (DRS),

Team Leader M. Modes, Senior Reactor Inspector, DRS N. Floyd, Senior Reactor Inspector, DRS Approved By: Mel Gray, Chief Engineering Branch 1 Division of Reactor Safety Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring Exelons performance at

Peach Bottom Atomic Power Station, Units 2 and 3 by conducting a Post-Approval Site Inspection for License Renewal - Phase 4 in accordance with the Reactor Oversight Process.

The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.

No findings or more-than-minor violations were identified.

INSPECTION SCOPES

This inspection was conducted using the appropriate portions of the inspection procedure in effect at the beginning of the inspection unless otherwise noted. Currently approved inspection procedures with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html.

Samples were declared complete when the inspection procedure requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter 2515, Light-Water Reactor Inspection Program - Operations Phase. The team reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

REACTOR SAFETY

71003 - Post-Approval Site Inspection for License Renewal - Phase 4

The team selected for evaluation six aging management programs considering risk insights and programs that were enhanced or new under the renewed operating license. The team also considered for selection those programs with monitoring results that were performed for the first time or identified examination or test results not experienced in the past. The inspection performed by the team was conducted as outlined in NRC Inspection Procedure 71003. For the age management programs selected, the team reviewed records, interviewed plant staff, and conducted plant walk downs to evaluate whether age management program elements were being implemented Involving program scope, preventive actions, parameters monitored or inspected, detection of aging effects, monitoring and trending, acceptance criteria, corrective actions, confirmation process, administrative controls, and operating experience.

The following age management programs were evaluated by the team:

Q 1.1, Flow Accelerated Corrosion Program Q 1.16, Maintenance Rule Structural Monitoring Program Q 2.3, Ventilation System Inspection and Testing Activities Q 2.5, Outdoor, Buried and Submerged Component Inspection Activities Q 2.9, Fire Protection Activities Q 3.5, In-accessible Medium Voltage Cables not subject to 10 CFR 50.49 Environmental Qualification Requirements

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

On November 30, 2018, the inspectors presented the teams inspection results to Mr. Matthew Herr, Plant Manager, and other members of the licensee staff.

DOCUMENTS REVIEWED

Corrective Action Condition Reports

257959 02741249 04106712 04166806

01381435 01656419 04115606 04198726

01445365 03965606 04133867 04198906

01509144 04022739 04150564 04198912

01509209 04024134 04163257 04198906

01656419 04087238 04166806

2701330 04090201 04190107

Design and Licensing Basis Documents

PBAPS Updated Final Safety Analysis Report, Appendix Q - License Renewal Aging

Management UFSAR Supplement, Revision 26

UFSAR Change 2018-0013, Removing CST Statement from Q.2.5, dated 4/12/18

Drawings

280-E-1, Sh. 1, Single Line Diagram Station, Revision 58

LR-M-384, Shts. 2 and 3, License Renewal Drawing Control Room HVAC, Revision 0

LR-M-309, Sh. 1, License Renewal Drawing Condensate & Refueling Water Storage and

Transfer Systems, Revision 0

LR-M-309, Sh. 2, License Renewal Drawing Condensate & Refueling Water Storage and

Transfer Systems, Revision 0

LR-M-318, Sh. 1, License Renewal Drawing Fire Protection System, Revision 0

LR-M-318, Sh. 2, License Renewal Drawing Fire Protection System, Revision 0

Engineering Calculations and Evaluations

200.00-02, Peach Bottom Atomic Power Station Unit 2 FAC Susceptibility Non-Modeled

Evaluation (SNM), 2/3/2012

200.100-04, Peach Bottom Power Station Unit 3 FAC Susceptibility Non-Modeled Evaluation

(SNM), 2/3/2012

EP-2016-0079-01-TR, Exelon - Peach Bottom Atomic Power Station Unit 2 Erosion

Susceptibility Evaluation (ESE) Technical Report Revision 0

EP-2016-0079-02-TR, Exelon - Peach Bottom Atomic Power Station Unit 3 Erosion

Susceptibility Evaluation (ESE) Technical Report, Revision 0

PEA-05738, Failure Analysis of Fire Protection Piping, dated 11/1/18

PEA-71643, Selective Leaching Evaluation of One Fire Valve and One Piping Tee, dated

5/26/17

PEA-71646, Selective Leaching Evaluation of Fire Valves, dated 5/26/17

Miscellaneous

AMP Effectiveness Review for Fire Protection Activities, dated 6/25/18

AMP Effectiveness Review for Outdoor, Buried, and Submerged Component Inspection

Activities

Book 3.5, Peach Bottom Atomic Power Station Inaccessible Medium-Voltage Cables not subject

to 10 CFR 50.49 Environmental Qualification Requirements Aging Management

Program Result Binder, Revision 0

BOP-UT-18-032, UT Data Report for Unit 2 Refueling Water Storage Tank, dated 6/28/18

MFL Inspection Report for Unit 2 Condensate Storage Tank, dated 10/29/16

MM-AA-723-500, Inspection of Non EQ Cables and Connections for Managing Averse

Localized Environments, Revision 11

MO2, Aging Management Review Technical Report - Ventilation, Revision 3

NSAC-202L-R4, Recommendations for an Effective Flow-Accelerated Corrosion Program,

Revision 4

Vendor Field Service Report for Diesel Driven Fire Pump, dated 9/28/18

Procedures

ER-AA-300-150, Cable Condition Monitoring Program, Revision 5

ER-AA-3003, Cable Condition Monitoring Program, Revision 2

ER-AA-430, Conduct of Flow Accelerated Corrosion Activities, Revision 7

ER-AA-430-1001, Guidelines for Flow Accelerated Corrosion Activities, Revision 11

ER-AA-430-1002, Feedwater Heater Shell Inspection for Detection of Flow Accelerated

Corrosion, Revision 6

ER-AA-430-1003, Flow Accelerated Corrosion Program Performance Indicators, Revision 4

ER-AA-430-1004, Erosion in Piping and Components, Revision 1

ER-AA-5400, Underground (Buried) Piping and Raw Water Integrity Management Programs

Guide, Revision 10

ER-AA-5400-1002, Underground Piping and Tanks Examination Guide, Revision 9

ER-AA-700, License Renewal Implementation Program, Revision 7

ER-AA-700-1003, Screening and Evaluation of Potential Aging Issues, Revision 4

ER-AA-700-401, Selective Leaching Aging Management, Revision 1

ER-AA-700-403, Inspection of Internal Surfaces in Miscellaneous Piping and Duct Components

Aging Management Program, Revision 1

ER-AA-450, Structures Monitoring, Revision 7

ER-PB-450-1006, Peach Bottom Structures Monitoring Instructions, Revision 5

RT-O-100-911-2, Inspection of Aboveground Storage Tanks, Revision 12

SA-AA-117, Excavation, Trenching, and Shoring, Revision 21

ST-M-37D-380-2, Diesel Driven Fire Pump Inspection, Revision 3

Surveillance Tests

2-PEB-ISO-2-12-2-V01 D/S, Engineering Evaluation of UT Inspected Component, performed

10/28/2018

2-PEB-ISO-2-14-6-F01, Engineering Evaluation of UT Inspected Component, performed

10/23/2018

2-PEB-M-295-S77-E05, Engineering Evaluation of UT Inspected Component, performed

11/2/2016

3-PEB-FSK-M-3013-S13-E03, Engineering Evaluation of UT Inspected Component, performed

10/26/2017

3-PEB-FSK-M-3013-S13-E04, Engineering Evaluation of UT Inspected Component, performed

10/26/2017

3-PEB-HISO-656-R04, Engineering Evaluation of UT Inspected Component, performed

11/1/2017

3-PEB-ISO-3-02-15-V03 U/S, Engineering Evaluation of UT Inspected Component, performed

10/2/2015

3-PEB-iso-3-12-101-V01 D/S, Engineering Evaluation of UT Inspected Component, performed

10/2/2015

3-PEB-ISO-3-12-15-R02, Engineering Evaluation of UT Inspected Component, performed

10/7/2015

3-PEB-ISO3-12-15-R02, Engineering Evaluation of UT Inspected Component, performed

10/7/2015

ST-M-40D-601-2, Control Room Emergency Ventilation Filter Train B Test, performed 1/13/16

ST-M-40D-905-2, Control Room Emergency Ventilation Filter Train A Test, performed 6/6/16

Maintenance Rule Walkdown Datasheet, Room 414, Completed 12/16/1997, 1/29/2002,

2/8/2007, 12/4/2012, and 11/1/2016

Maintenance Rule Walkdown Datasheet, Room 457, Completed 6/17/1998, 4/2/2002,

6/22/2007, 12/26/2012, 8/14/2017

Work Orders

R1265418 C0234463 C0243177 04261297

262165 04275013 04587766 04625728

04718861