IR 05000244/2017007

LLC - Design Bases Assurance (Environmental Qualification Program) Inspection Report 05000244/2017007

ML17258A696
Person / Time
Site:	Ginna
Issue date:	09/15/2017
From:	Glenn Dentel Engineering Region 1 Branch 2
To:	Bryan Hanson Exelon Generation Co, Exelon Nuclear
References
IR 2017007
Download: ML17258A696 (15)

Text

ber 15, 2017

SUBJECT:

R.E. GINNA NUCLEAR POWER PLANT, LLC - DESIGN BASES ASSURANCE (ENVIRONMENTAL QUALIFICATION PROGRAM) INSPECTION REPORT 05000244/2017007

Dear Mr. Hanson:

On August 24, 2017, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at R.E. Ginna Nuclear Power Plant, LLC (Ginna). The enclosed inspection report documents the inspection results, which were discussed with Mr. William Carsky, Site Vice President, and other members of the Ginna staff.

NRC inspectors 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 Exelons implementation of the electrical equipment environmental qualification program required by Title 10, Code of Federal Regulations (10 CFR) 50.49 for maintaining the qualified status of equipment during the life of the plant. The inspection involved field walkdowns, examination of selected procedures, calculations and records, and interviews with station personnel.

No NRC-identified or self-revealing findings were identified during this inspection.

In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC Public Docket Room or from the Publicly Available Records component of NRCs document system, Agencywide Documents Access and Management System (ADAMS).

ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/

Glenn Dentel, Chief Engineering Branch 2 Division of Reactor Safety Docket No. 50-244 License No. DPR-18

Enclosure:

Inspection Report 05000244/2017007 w/Attachment: Supplementary Information

REGION I==

Docket No. 50-244 License No. DPR-18 Report No. 05000244/2017007 Licensee: Exelon Generation Company, LLC (Exelon)

Facility: R.E. Ginna Nuclear Power Plant, LLC (Ginna)

Location: Ontario, New York Inspection Period: August 7 through August 24, 2017 Inspectors: D. Kern, Senior Reactor Inspector, Division of Reactor Safety (DRS),

Team Leader J. Schoppy, Senior Reactor Inspector, DRS J. Rady, Reactor Inspector, DRS Approved By: Glenn Dentel, Chief Engineering Branch 2 Division of Reactor Safety Enclosure

SUMMARY

IR 05000244/2017007; 8/7/2017 - 8/24//2017; Ginna; Design Bases Assurance

Inspection (Programs).

The report covers the Design Bases Assurance Inspection - Programs conducted by a team of three NRC region-based reactor inspectors. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649,

Reactor Oversight Process, Revision 6, dated July 2016.

No findings were identified.

REPORT DETAILS

REACTOR SAFETY

Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity

1R21 Design Bases Assurance Inspection (Programs) (IP 71111.21N - 10 samples)

.1 Inspection Sample Selection Process

The inspection team assessed the implementation of Exelons Environmental Qualification (EQ) program, established to meet the requirements of Title 10 of the Code of Federal Regulations (10 CFR) 50.49, Environmental Qualification of Electrical Equipment Important to Safety for Nuclear Power Plants. The inspection team performed an inspection as outlined in NRC Inspection Procedure (IP) 71111.21N, Attachment 1, Environmental Qualification under 10 CFR 50.49 Programs, Processes, and Procedures. The team reviewed components that were either safety-related equipment relied upon to remain functional during and following design basis events, non-safety-related components whose failure could prevent safety-related equipment from performing design functions, and certain post-accident monitoring equipment.

The team then determined which components environment would be adversely affected by postulated post-accident environmental conditions (temperature, pressure, humidity, chemical spray, radiation level, or flood level) and reviewed information contained in the Ginna Probabilistic Risk Assessment (PRA) and the U.S. NRCs Standardized Plant Analysis Risk (SPAR) model for Ginna to determine risk significant components that were also required to meet EQ requirements. Additionally, the team interviewed plant staff, reviewed design records, and discussed the EQ program with the resident inspectors to assist in the selection of components. Finally, the team ensured that different types of components were selected included pump motors, motor-operated valves, solenoid valves, electrical breakers, containment penetrations, and flow/pressure transmitters located both inside and outside of primary containment. Based on these reviews, the team selected ten EQ components and associated sub-components (seals, cables, connectors, and lubricants) for inspection.

.2 Results of Detailed Reviews

a. Inspection Scope

The inspection was conducted as outlined in NRC IP 71111.21N. The team assessed Exelons implementation of the EQ program required by 10 CFR 50.49. The team reviewed EQ program-related procedures, component EQ files, EQ test records, equipment maintenance and operating history, maintenance and operating procedures, vendor documents, design documents, previously identified deficiencies, and design calculations. The team also interviewed plant staff knowledgeable of the design, maintenance, and operation of the selected components. The review and associated interviews were performed to evaluate whether Exelons staff properly maintained the equipment qualifications for electrical equipment important to safety through plant life (repair, replacement, modification, and plant life extension); established and maintained required EQ documentation records; and implemented an effective corrective action program to identify and correct EQ-related deficiencies and evaluate EQ-related industry operating experience. The team also performed walkdowns (where accessible) of selected components to:

(1) verify that equipment was installed as described in Ginna environmental qualification component documentation files;

(2) ensure that the environmental conditions were consistent with those assumed in the evaluations;

(3) determine whether equipment surrounding EQ component could fail in a manner that would prevent the components safety function from being performed; and

(4) to ensure that the components were installed in their tested configuration. The component and associated subcomponents inspected included:

MO-515, Pressurizer Power Operated Relief Valve Block Valve Motor Operator MO-857C, Residual Heat Removal Heat Exchanger A&B Outlet Cross-Tie to Safety Injection and Containment Spray Pump Suction Valve Motor Operator MO/CF1C, C Containment Recirculation Fan Motor and Damper Control Valve 5874 Solenoid Operated Valves (14113S, 14114S)52/CHP1B, B Charging Pump Breaker MO/SIP1A, Replacement Safety Injection Pump Motor CVPBE02, New Containment Penetration AOV-4269, A Main Feed Water Flow Control Valve, associated SOVs (4269S1 and 4269S2)

AOV-3516, B Main Steam Isolation Valve and associated SOVs (air supply 3516S1, 3516S2 and vent 3516S3, 3516S4)

PT-420, Reactor Coolant System Hot Leg Pressure Transmitter FT-689, Residual Heat Removal Injection Flow Transmitter In addition to the inspection of the selected components, the team performed general plant walkdowns to determine whether components located in areas susceptible to a high-energy line break were properly evaluated for operation in a harsh environment. The team also reviewed procurement records and inspected a sample of replacement parts stored in the warehouse to verify EQ parts approved for installation in the plant were properly identified and controlled; and that storage time and environmental conditions did not adversely affect the components qualified life or service life. Finally, the team reviewed a sample of components that had been removed from the EQ program to determine if Exelon had correctly determined that the components no longer were required to meet 10 CFR 50.49. Documents reviewed for this inspection are listed in the

.

b. Findings

No findings were identified.

4OA2 Identification and Resolution of Problems (IP 71152)

a. Inspection Scope

The team reviewed a sample of problems that Exelon had previously identified and entered into the corrective action program. The team reviewed a sample of these issues to verify an appropriate threshold for identifying issues and to evaluate the effectiveness of corrective actions. Additionally, the team evaluated whether deficiencies identified during the inspection were properly documented and evaluated in the corrective action program.

b. Findings

No findings were identified.

4OA6 Meetings, including Exit

On August 24, 2017, the team presented the inspection results to Mr. William Carsky, Site Vice President, and other members of the Ginna staff. The inspectors verified that no proprietary information was retained by the inspectors or documented in this report.

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Exelon Personnel

W. Carsky, Site Vice President

P. Swift, Plant Manager

J. Bement, Manager, Radiation Engineering

D. Blankenship, Director, Operations

J. Brown, Director, Site Training

D. Dettman, Senior Reactor Operator

T. Edwards, Manager, Site Chemistry, Environmental and RadWaste

W. Foigherait, Chemist

K. Garnish, Manager, Regulatory Assurance

R. Hellems, Systems Engineer

M. Kubisa, System Engineer

C. Johnson, Electrical Design Engineer

G. Jones, Chemist

J. Knowles, Senior Reactor Operator

J. List, Manager, On-Line Work Management

D. Markowski, Senior Manager, Design Engineering

D. Pascuzzi, Branch Manager, Systems Engineering

B. Raczkiewicz, Environmental Qualification Program Owner

S. Rafaniello, System Engineer

C. Siverd, Senior Regulatory Assurance Engineer

A. Smith, Nine Mile Point Environmental Qualification Program Owner

J. Sperr, Manager, Electrical Systems Engineering

J. Stanger, System Engineer

G. Verdin, Operations Shift Supervisor

C. Walsh, Civil Engineer

R. Westerbeck, Chemistry Technician

D. Wilson, Director, Engineering

M. Zweigle, Senior Staff Engineer, Design Engineering

NRC Personnel

N. Perry, Senior Resident Inspector

J. Schussler, Resident Inspector

LIST OF ITEMS OPENED, CLOSED, DISCUSSED, AND UPDATED

Opened/Closed

None