IR 05000456/2014008: Difference between revisions
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====b. Findings==== | ====b. Findings==== | ||
No findings of significance were identified. | No findings of significance were identified. | ||
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==4OA6 Meetings== | ==4OA6 Meetings== | ||
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===.2 Interim Exit Meeting=== | ===.2 Interim Exit Meeting=== | ||
On February 20, 2014, the inspectors presented the inspection results to Mr. J. Bashor and other members of the licensee staff. | On February 20, 2014, the inspectors presented the inspection results to Mr. J. Bashor and other members of the licensee staff. | ||
===.3 Interim Exit Meeting=== | ===.3 Interim Exit Meeting=== | ||
Revision as of 10:54, 20 December 2019
| ML14087A444 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 03/27/2014 |
| From: | Robert Daley Engineering Branch 3 |
| To: | Pacilio M Exelon Generation Co, Exelon Nuclear |
| Dariusz Szwarc | |
| References | |
| IR-14-008 | |
| Download: ML14087A444 (16) | |
Text
UNITED STATES rch 27, 2014
SUBJECT:
BRAIDWOOD STATION, UNITS 1 AND 2 EVALUATIONS OF CHANGES, TESTS, AND EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000456/2014008; 05000457/2014008
Dear:
Mr. Pacillio:
On March 27, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed an Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications inspection at your Braidwood Station, Units 1 and 2. The enclosed inspection report documents the inspection results which were discussed on March 27, 2014, with Mr. P. Raush and other 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.
In accordance with Title 10, Code of Federal Regulations (CFR), Section 2.390 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 NRC Public Document Room or from the Publicly Available Records System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
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 05000456/2014008; 05000457/2014008 w/Attachment: Supplemental Information
REGION III==
Docket No: 50-456; 50-457 License No: NPF-72; NPF-77 Report No: 05000456/2014008; 05000457/2014008 Licensee: Exelon Generating Company, LLC Facility: Braidwood Station, Units 1 and 2 Location: Braceville, IL Dates: January 21 through March 27, 2014 Inspectors: D. Szwarc, Senior Reactor Inspector N. Féliz Adorno, Reactor Inspector I. Hafeez, Reactor Inspector Approved by: Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety
SUMMARY OF FINDINGS
IR 05000456/2014008, 05000457/2014008; 01/21/2014 - 03/27/2014; Braidwood Station, Units and 2; Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications.
This report covers a two-week announced baseline inspection on evaluations of changes, tests, and experiments and permanent plant modifications. The inspection was conducted by Region III based engineering inspectors. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process,
Revision 4, dated December 2006.
NRC-Identified
and Self-Revealed Findings
Cornerstone: Initiating Events
No findings of significance were identified.
Licensee-Identified Violations
No violations of significance were identified.
REPORT DETAILS
REACTOR SAFETY
Cornerstone: Initiating Events, Mitigating Systems, and Barrier Integrity
1R17 Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications
.1 Evaluation of Changes, Tests, and Experiments
a. Inspection Scope
The inspectors reviewed seven safety evaluations performed pursuant to Title 10, Code of Federal Regulations (CFR) 50.59 to determine if the evaluations were adequate and that prior NRC approval was obtained as appropriate. The inspectors also reviewed 13 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 and 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 (NEI) 96-07, Guidelines for 10 CFR 50.59 Implementation, Revision 1, to determine acceptability of the completed evaluations, and screenings. The NEI 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 constituted seven samples of evaluations and 13 samples of screenings as defined in IP 71111.17-04.
b. Findings
No findings of significance were idenfied.
.2 Permanent Plant Modifications
a. Inspection Scope
The inspectors reviewed seven permanent plant modifications that had been installed in the plant during the last three years. This review included in-plant walkdowns for portions of the modified diesel generator governor booster; backup power supplies for the steam generator power operated relief valves; isolation valves in the safety injection system; temporary scaffolds; and electrical circuits related to high energy line break (HELB) in the diesel generator rooms, miscellaneous electric rooms, and engineered safety features switchgear rooms. The modifications were selected based upon risk significance, safety significance, and complexity. The inspectors reviewed the modifications selected to determine if:
- the supporting design and licensing basis documentation was updated;
- the changes were in accordance with the specified design requirements;
- the procedures and training plans affected by the modification have been adequately updated;
- the test documentation as required by the applicable test programs has been updated; and
- post-modification testing adequately verified system operability and/or functionality.
The inspectors also used applicable industry standards to evaluate acceptability of the modifications. The list of modifications and other documents reviewed by the inspectors is included as an attachment to this report.
This inspection constituted seven permanent plant modification samples as defined in IP 71111.17-04.
b. Findings
No findings of significance were identified.
OTHER ACTIVITIES (OA)
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 permanent plant modifications. The inspectors reviewed these documents to evaluate the effectiveness of corrective actions related to permanent plant modifications and evaluations of changes, tests, or 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 of significance were identified.
4OA6 Meetings
.1 Exit Meeting Summary
On March 27, 2014, the inspectors presented the inspection results to Mr. P. Raush and other members of the licensee staff. The licensee personnel acknowledged the inspection results presented.
.2 Interim Exit Meeting
On February 20, 2014, the inspectors presented the inspection results to Mr. J. Bashor and other members of the licensee staff.
.3 Interim Exit Meeting
On February 7, 2014, the inspectors presented the inspection results to Mr. M. Kanavos, and other members of the licensee staff. The inspectors confirmed that all proprietary material reviewed during the inspection was returned to the licensee staff.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee
- M. Kanavos, Plant Manager
- M. Marchionda, Plant Manager
- J. Bashor, Engineering Director
- A. Ferko, Operations Manager
- R. Belair, Mechanical Design Engineering Manager
- P. Raush, Regulatory Assurance Manager
- D. Riedinger, Engineering Training
- G. Wilhelmsen, Design Engineering Manager
- M. Abbas, NRC coordinator
Nuclear Regulatory Commission
- J. Benjamin, Senior Resident Inspector
- R. Daley, Chief, Reactor Safety, Engineering Branch 3
- E. Duncan, Chief, Reactor Projects, Branch 3
LIST OF ITEMS
OPENED, CLOSED AND DISCUSSED
Opened, Closed, and Discussed
None Attachment