IR 05000456/2015003

IR 05000456/2015003; 05000457/2015003, on 07/01/2015 -09/30/2015, Braidwood Station, Units 1 & 2; Routine Integrated Inspection Report

ML15299A380
Person / Time
Site:	Braidwood
Issue date:	10/26/2015
From:	Eric Duncan Region 3 Branch 3
To:	Bryan Hanson Exelon Generation Co, Exelon Nuclear
References
IR 2015003
Download: ML15299A380 (42)

Text

UNITED STATES ber 26, 2015

SUBJECT:

BRAIDWOOD STATION, UNITS 1 AND 2 - NRC INTEGRATED INSPECTION REPORT 05000456/2015003; 05000457/2015003

Dear Mr. Hanson:

On September 30, 2015, the U.S. Nuclear Regulatory Commission (NRC) completed an integrated inspection at your Braidwood Station, Units 1 and 2. On October 7, 2015, the NRC inspectors discussed the results of this inspection with Mr. M. Kanavos, and other members of your staff. The inspectors documented the results of this inspection in the enclosed inspection 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.

The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.

No NRC-identified or self-revealing findings were identified during this inspection. However, the inspectors documented two license-identified violations which were determined to be of very low safety significance. The NRC is treating these violations as Non-Cited Violations (NCVs)

consistent with Section 2.3.2 of the NRCs Enforcement Policy.

If you contest the violations or significance of these NCVs, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001, with copies to the Regional Administrator, U.S. Nuclear Regulatory Commission, Region III; the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspector at the Braidwood Station. In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding, of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS)

component of the NRC's 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/

Eric R. Duncan, Chief Branch 3 Division of Reactor Projects Docket Nos. 50-456; 50-457 License Nos. NPF-72; NPF-77

Enclosure:

IR 05000456/2015003; 05000457/2015003 w/Attachment: Supplemental Information

REGION III==

Docket Nos: 50-456; 50-457 License Nos: NPF-72; NPF-77 Report No: 05000456/2015003; 05000457/2015003 Licensee: Exelon Generation Company, LLC Facility: Braidwood Station, Units 1 and 2 Location: Braceville, IL Dates: July 1 through September 30, 2015 Inspectors: J. Benjamin, Senior Resident Inspector D. Betancourt, Resident Inspector T. Go, Health Physics M. Jones, Reactor Inspector J. McGhee, Senior Resident Inspector, Byron D. McNeil, Senior Operations Engineer D. Reeser, Operations Engineer L. Rodriguez, Reactor Inspector A. Schwab, Project Engineer Approved by: E. Duncan, Chief Branch 3 Division of Reactor Projects Enclosure

SUMMARY

................................................................................................................................ 2

REPORT DETAILS

.................................................................................................................... 3

REACTOR SAFETY

..................................................................................................... 3

1R01 Adverse Weather Protection

........................................................... 3

1R04 Equipment Alignment

...................................................................... 4

1R05 Fire Protection

................................................................................ 5

1R07 Annual Heat Sink Performance

....................................................... 6

1R11 Licensed Operator Requalification Program

................................... 8

1R12 Maintenance Effectiveness

............................................................12

1R13 Maintenance Risk Assessments and Emergent Work Control

.......12

1R15 Operability Determinations and Functional Assessments

..............13

1R18 Plant Modifications

........................................................................14

1R19 Post-Maintenance Testing

.............................................................14

RADIATION SAFETY

..................................................................................................17

2RS1 Radiological Hazard Assessment and Exposure Controls

.............17

2RS2 Occupational As-Low-As-Reasonably-Achievable Planning and Controls

.......................................................................................................17

other activities .............................................................................................................18

4OA1 Performance Indicator Verification

......................................................18

4OA2 Identification and Resolution of Problems

...........................................21

4OA3 Follow-Up of Events and Notices of Enforcement Discretion

..............23

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee

M. Kanavos, Site Vice President

M. Marchionda, Plant Manager

J. Bashor, Engineering Manager

J. Cady, Radiation Protection Manager

J. Coughlin, Radiation Protection Supervisor

R. Cameron, Operations Training Manager

K. Dovas, Training Director

A. Ferko, Operations Manager

B. Finlay, Site Security Manager

C. Ingold, Maintenance Manager

J. Overstreet, Training Support Manager

P. Raush, Regulatory Assurance Manager

S. Reynolds, Nuclear Oversight Manager

D. Riedinger, Senior Manager Design Engineering

J. Taff, LORT Lead

A. Trespalacios, Maintenance Planning Manager

U.S. Nuclear Regulatory Commission

E. Duncan, Chief, Reactor Projects Branch 3

LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED

Closed

05000456/2015-002-00 LER Indication in Control Rod Drive Mechanism Nozzle Weld Due to Embedded Flaws Opening Up from Thermal and Pressure Stresses During Operation (Section 4OA3.1)

05000457/2015-003-00 LER Degraded Valve Causes Loss of Diesel Fuel Oil System Volume for One Train of the Diesel Generator System Resulting in Inoperability Longer than Allowed by Technical Specifications (Section 4OA3.2)

Discussed

None