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 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.
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 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety
Docket Nos. 50-456; 50-457 License Nos. NPF-72; NPF-77 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 Commissions program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process,
Revision 6, dated July 201
NRC-Identified
and Self-Revealed Findings No findings were identified.
Licensee-Identified Violations
No violations were identified.
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 96-07, Guidelines for 10 CFR 50.59 Implementation, Revision 1, to determine acceptability of the completed evaluations, and screenings. The Nuclear Energy Institute document was endorsed by the NRC in Regulatory Guide 1.187, Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments, dated November 2000. The inspectors also consulted Part 9900 of the NRC Inspection Manual, 10 CFR Guidance for 10 CFR 50.59, Changes, Tests, and Experiments.
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