IR 05000244/2019011

R. E. Ginna Nuclear Power Plant: Post-Approval Site Inspection for License Renewal: Phase 4 Inspection Report 05000244/2019011

ML19126A012
Person / Time
Site:	Ginna
Issue date:	05/03/2019
From:	Mel Gray NRC Region 1
To:	Bryan Hanson Exelon Generation Co, Exelon Nuclear
References
IR 2019011
Download: ML19126A012 (7)

Text

SUBJECT:

R. E. GINNA NUCLEAR POWER PLANT - POST-APPROVAL SITE INSPECTION FOR LICENSE RENEWAL - PHASE 4 INSPECTION REPORT 05000244/2019011

Dear Mr. Hanson:

On March 22, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed a Post-Approval Site Inspection for License Renewal - Phase 4 inspection at your R. E. Ginna Nuclear Power Plant and discussed the results of this inspection with Paul Swift, Plant Manager and other members of your staff. The results of this inspection are documented in the enclosed report.

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 at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Mel Gray, Branch Chief Engineering Branch 1 Division of Reactor Safety Docket No.: 50-244 License No.: DPR-18

Enclosure:

Inspection Report 05000244/2019011

Inspection Report

Docket Number: 05000244 License Number: DPR-18 Report Number: 05000244/2019011 Enterprise Identifier: I-2019-011-0021 Licensee: R. E. Ginna Nuclear Power Plant, LLC Facility: R. E. Ginna Nuclear Power Plant Location: Ontario, New York Inspection Dates: March 17, 2019 to March 23, 2019 Inspectors: K. Mangan, Senior Reactor Inspector (Team Lead)

M. Orr, Reactor Inspector S. Pindale, Senior Reactor Inspector Approved By: Mel Gray, Branch Chief Engineering Branch 1 Division of Reactor Safety

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a Post-Approval Site Inspection for License Renewal - Phase 4 inspection at R. E. Ginna Nuclear Power Plant 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. Findings and violations being considered in the NRCs assessment are summarized in the table below.

List of Findings and Violations No findings were identified.

Additional Tracking Items None.

INSPECTION SCOPES

Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs 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 IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2516, Policy and Guidance for the License Renewal Inspection Program. The inspectors 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.

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL

===71003 - Post-Approval Site Inspection for License Renewal The team selected for evaluation six aging management programs. The team selection of programs was based on 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 IP 71003, Phase IV. For the aging management programs selected, the team reviewed records, interviewed plant staff, and conducted plant walk downs to evaluate whether aging management program elements were being implemented in accordance with NRC requirements. The team evaluated the following elements of the aging management 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 aging management programs were evaluated by the team:

Post-Approval Site Inspection for License Renewal ===

(1) Flow-Accelerated Corrosion

(2) Buried Piping and Tanks Inspection

(3) Inaccessible Medium-Voltage Cables not Subject to 10 CFR 50.49 Equipment Qualification Requirements

(4) Periodic Surveillance and Preventative Maintenance

(5) ASME Section XI, Subsection IWE & IWL Inservice Inspection

(6) Structures Monitoring

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

• On March 22, 2019, the team conducted an exit meeting and presented the inspection results to Mr. Paul Swift, Plant Manager and other members of the licensee staff.

DOCUMENTS REVIEWED

Completed Tests

M-15.10, 1A or 1B EDG Underground Fuel Oil Storage Tank Leak Tightness Testing, performed

5/24/18 and 7/27/18

M-15.1P, A or B Diesel Generator Fuel Oil System Inspection and Maintenance, performed

10/5/10 and 11/12/10

Corrective Action Documents

01701480 02530472 04197672 2011-001543

01929169 02576330 04214674 2011-001544

01947095 02617311 04218210 2011-002037

2327025 02631315 04228497 2011-002932

2331893 02634324 2007-004949 2011-003069

2333633 04003135 2009-007043

2441684 04035603 2011-000463

2530386 04164593 2011-001542

Drawings

33013-2112, Plant Arrangement Turbine Building Plan - Basement Floor, Revision 0

33013-2539, AC System Plant Load Distribution One Line Wiring Diagram, Revision 30

Miscellaneous

Buried Pipe Cathodic Protection Performance Indicators, Annual Report, January 2019

ECP-15-000715, Technical Evaluation, dated 1/7/16

FAC Program Performance Indicators, Annual Report, January 2019

GA-N1059-501, Final Report for Ginna Nuclear Power Plant 2010 Containment Building Tendon

Surveillance, Revision 0

GNP010-C-1, Reactor Building Slab Analysis, Revision 1

ISR NL-2007-000081-017, Cast Iron - Raw Water Drainage, Revision 0

ISR NL-2007-000081-020, Carbon Low Alloy Steel - Raw Water, Revision 0

ISR NL-2007-000081-021, Carbon Low Alloy Steel - Treated Water Other, Revision 0

ISR NL-2007-00081-019, Carbon Low Alloy Steel - Air and Gas >140F & <140F (Wetted),

Revision 0

LRAM-ELECTPAS, License Renewal Aging Management Review Report for Electrical/I&C

Components, Revision 0

RE Ginna Updated Final Safety Analysis Report Chapter 18 - Supplement for License Renewal,

Revision 19

Reactor Cavity Leakage Walkdown Notes, 5/3/11

REP-1125-510, Suburban Laboratories, Inc. Analyses of Unit 1 Tendon Grease Samples

dated 5/27/16

Work Orders

C20705037 C92099897 C93217152 C93620777

C20805914 C92099962 C93225184 C93624469

C90672977 C92507446 C93243561 C93634366

C90679533 C92594624 C93266300 C93635952

C91467532 C92784945 C93411926

C91468358 C92846392 C93619409

C92072823 C92999194 C93619722

Procedures

EP-2-P-0169, Structural Assessment and Monitoring Program, Revision 19

EP-VT-113, Visual Examination of Class CC Concrete Components (IWL), Revision 00101

ER-AA-310, Implementation of the Maintenance Rule, Revision 12

ER-AA-335-018, Visual Examination of ASME IWE Class MC and Metallic Liners of IWL

Class CC Components, Revision 13

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-450, Structures Monitoring, Revision 7

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

Guide, Revision 11

LR-BTNK-PROGPLAN, Ginna Station License Renewal Project Buried Piping and Tanks

Inspection Program, Revision 5

LR-FAC-PROGPLAN, Ginna Station License Renewal Project Flow Accelerated Corrosion

Program, Revision 3

LR-IMVC-PROGPLAN, Inaccessible Medium Voltage Cables Not Subject to 10 CFR 50.49

Environmental Qualification Requirements [XI.E3], Revision 3

LR-IWEL-PROGPLAN, ASME Section XI, Subsections IWE & IWL Inservice Inspection,

Revision 5

LR-OTI-PROGPLAN, One-Time Inspection Program, Revision 6

LR-PSPM-PROGPLAN, Periodic Surveillance and Preventive Maintenance Program, Revision 7

LR-STRM-PROGPLAN, Structures Monitoring Program, Revision 7

LR-SYSN-PROGRAM, Systems Monitoring Program, Revision 5

STP-O-22.1, Local Leak Rate Testing of Equipment Hatch Door Seal, Revision 00202

STP-O-27.2, Tendon Surveillance Program, Revision 00400