IR 05000456/2017007
| ML17093A954 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 03/30/2017 |
| From: | Robert Daley Engineering Branch 3 |
| To: | Bryan Hanson Exelon Generation Co, Exelon Nuclear |
| References | |
| IR 2017007 | |
| Download: ML17093A954 (9) | |
Text
March 30, 2017
SUBJECT:
BRAIDWOOD NUCLEAR GENERATING STATION: EVALUATIONS OF CHANGES, TESTS, AND EXPERIMENTS BASELINE INSPECTION REPORT 05000456/2017007; 05000457/2017007
Dear Mr. Hanson:
On February 17, 2017, the U.S. Nuclear Regulatory Commission (NRC) completed an Evaluations of Changes, Tests, and Experiments inspection at your Braidwood Nuclear Generating Station. The enclosed inspection report documents the inspection results, which were discussed on February 17, 2017, with members of your staff. The inspection examined activities conducted under your license as they relate to safety and , and with the conditions of your license. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. The NRC inspectors did not identify any findings or violations 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
Sincerely,
/RA/ Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50456; 50457 License Nos. NPF72; NPF77 Enclosure: Inspection Report 050004562017007; 05000457/2017007 cc: Distribution via LISTSERV
SUMMARY
Inspection Report 050004562017007; 05000457/2017007; 02/13/2017 02/17/2017; Braidwood Nuclear Generating Station; Evaluations of Changes, Tests, and Experiments. This report covers a 2-week announced baseline inspection on evaluations of changes, tests, and experiments. The inspection was conducted by Region III based engineering inspectors. The U.S Nuclear Regulatory Commissioncommercial nuclear power reactors is described in NUREG-r Revision 6, dated July 2016.
NRC-Identified
and Self-Revealed Findings No findings were identified.
Licensee-Identified Violations
No violations were identified.
3
REPORT DETAILS
REACTOR SAFETY
Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity
1R17 Evaluations of Changes, Tests, and Experiments
.1 Evaluation of Changes, Tests, and Experiments
a. Inspection Scope
The inspectors reviewed 9 safety evaluations performed pursuant to Title 10, Code of Federal Regulations (CFR), Part 50.59 to determine if the evaluation was adequate and that prior U.S. Nuclear Regulatory Commission (NRC) approval was obtained as appropriate. The inspectors also reviewed 17 screenings where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary. The inspectors reviewed these documents to determine if: the changes, tests, and experiments performed were evaluated in accordance with 10 CFR 50.59, and that sufficient documentation existed to confirm that a license amendment was not required; the safety issue requiring the change, tests or experiment was resolved; the licensee conclusions for evaluations of changes, tests, and experiments were correct and consistent with 10 CFR 50.59; and the design and licensing basis documentation was updated to reflect the change. The inspectors used, in part, Nuclear Energy Institute 96-10 CFR ability of the completed evaluations, and screenings. The Nuclear Energy Institute document was endorsed by CFR 50.59, tors also consulted Part CFR Guidance for 10 CFR This inspection sample constituted 26 evaluations and screenings as defined in Inspection Procedure 71111.17T.
b. Findings
No findings were identified.
OTHER ACTIVITIES
4OA2 Problem Identification and Resolution
.1 Routine Review of Condition Reports
a. Inspection Scope
The inspectors reviewed several corrective action process documents that identified or were related to 10 CFR 50.59 evaluations and screenings. The inspectors reviewed these documents to evaluate the effectiveness of corrective actions related to screenings and evaluations of changes, tests, and experiments. In addition, corrective action documents written on issues identified during the inspection were reviewed to verify adequate problem identification, and incorporation of the problems into the corrective action system. The specific corrective action documents that were sampled and reviewed by the inspectors are listed in the Attachment to this report.
b. Findings
No findings were identified.
4OA6 Management Meetings
.1 Exit Meeting Summary
The inspectors presented the inspection results to Mrs. M. Marchionda-Palmer and other members of the licensee staff on February 17, 2017. The licensee personnel acknowledged the inspection results presented, and did not identify any proprietary content. ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee
- M. Marchionda-Palmer, Site Vice President
- A. Ferko, Plant Manager
- S. Reynolds, Regulatory Assurance Manager
- F. Piriano, Design Engineering Manager
- R. Schliessmann, Regulatory Assurance
- C. Kulbida Design Engineering J. Morales, Design Engineering
- G. Holt, Design Engineering
- U.S. Nuclear Regulatory Commission D. Kimble, Senior Resident Inspector
- D. Betancourt, Resident Inspector
LIST OF ITEMS
OPENED, CLOSED AND DISCUSSED
Opened, Closed, and Discussed
None LIST OF ACRONYMS USED CFR Code of Federal Regulations
LIST OF DOCUMENTS REVIEWED
The following is a list of documents reviewed during the inspection.
- Inclusion on this list does not imply that the NRC inspectors reviewed the documents in their entirety, but rather, that selected sections of portions of the documents were evaluated as part of the overall inspection effort.
- Inclusion of a document on this list does not imply NRC acceptance of the document or any part of it, unless this is stated in the body of the inspection report. 10
- CFR 50.59 EVALUATIONS Number Description or Title Revision 2015-055 UFSAR Revision for Reactor Head Lift
- Polar Crane Single Failure Proof Equivalency Per
- NEI 08-05 0 2015-92 Westinghouse Ovation Digital Upgrade for Rod Control Logic Cabinet 0 and 1 2015-064 Fukushima FLEX Piping Connections for Auxiliary Feedwater 0 2015-110
- RC-RCP Seal Replace/Upgrade A2R18 /
- RC-RCP Seal Replace/Upgrade A1R19 0 2016-20 Replace RCP Underfrequency KF Relays with Circuit Shield Type 81 Frequency Relays to Address ABB Part 21 Notification of Potential Defect for KF Relay ZPA 0 and1 2016-31 20 DT/TA Loop
- Two THOT RTD Operation
- Cycle 19 0 2014-120 Incorporation of PAD Code Version 4.0 for Byron BWD Fuel Rod Design 0 2016-14 Remove AF Diesel Air Intake Elbow And Blank Off TB Air Intake 0 2016-71 Modification of Combustion Air Intakes for AF Diesel Engines 1AF01PB and 2AF01PB 0 2014-032 Steam Generator Main Steam Safety Valve (MSSV Vent Pipe Removal) 0 2014-101
- GL 08-01: Add ECCS Vents in Support of Online Maintenance 0 2014-121 Retention of Temporary Scaffold Installed Beyond 90 Days in Support of Maintenance 0 2015-096 Storage of Reactor Head Stand, Bioshield Wall Extension and Shielded Door Assembly in Containment After A2R18 0 2015-153 Installation of New Pipe Support 2SX08117X for
- GL 96-06 Load 0 2014-60 New Design Universal Logic Board and Safeguards Driver Board 48 VDC Input 0 2014-89 UFSAR Update to Address Tornado Missile Protection Considerations for Essential Service Water Discharge Extension Lines 0 2015-35 As Left Condition for Unit 1 DRPI MS (IRD43R) AS Coil Open 0 2014-92 Technical Specification (TS) Bases B 3.8.1 Revision for Surveillance Requirement (SR) 3.8.1.14 0 2014-109 Exciter Trip Gen Trip, Generator Field Forcing 0 2014-139 UFSAR Revision for Section 8.3.1 and Table 8.1-1
- BOP-DG-11
- Diesel Generator Startup 0 2015-6 Main XFRMR 1E/1W/2E/2W Oil Temperature High 0 2014-106 U2 MSSV Vent Line Modification 0 2014-150 Revision to 1/2BwOSR 0.1-1,2,3 and 1/2BwOSR 01-4 to Incorporate a Revised UHS Temperature Value 0 2015-14 Reduced Elongation Range for the U1 Reactor Vessel Main Closure Studs
- 0 2016-53 Add Insulation to 2WE171A- 0 2016-74 Revise Fuel Center Line Melt Temperature Limit Per MUR Analyses 0