IR 05000346/2017010: Difference between revisions
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{{#Wiki_filter:UNITED STATES | {{#Wiki_filter:UNITED STATES ber 11, 2017 | ||
==SUBJECT:== | |||
DAVIS-BESSE NUCLEAR POWER STATION EVALUATIONS OF CHANGES, TESTS, AND EXPERIMENTS BASELINE INSPECTION REPORT 05000346/2017010 | |||
==Dear Mr. Bezilla:== | ==Dear Mr. Bezilla:== | ||
On September 22, 2017 the U.S. Nuclear Regulatory Commission (NRC) completed an Evaluations of Changes, Tests, and Experiments inspection at your Davis-Besse Nuclear Power Station. The enclosed inspection report documents the inspection results which were discussed on September 22, 2017, with you and other members of your staff | On September 22, 2017 the U.S. Nuclear Regulatory Commission (NRC) completed an Evaluations of Changes, Tests, and Experiments inspection at your Davis-Besse Nuclear Power Station. The enclosed inspection report documents the inspection results which were discussed on September 22, 2017, with you and other members of your staff. | ||
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, | 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, | Sincerely, | ||
/RA/ | /RA/ | ||
Robert C. Daley, Chief Engineering Branch 3 | Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket No. 50-346 License No. NPF-3 | ||
Division of Reactor Safety Docket No. 50-346 License No. NPF-3 | |||
===Enclosure:=== | ===Enclosure:=== | ||
IR 05000346/2017010 | IR 05000346/2017010 | ||
REGION III Docket No: 50-346 License No: NPF-3 Report No: 05000346/2017010 Licensee: FirstEnergy Nuclear Operating Company Facility: Davis-Besse Nuclear Power Station Location: Oak Harbor, OH Dates: September 18-22, 2017 Inspectors: J. Bozga, Senior Reactor Inspector (Lead) J. Benjamin, Senior Reactor Inspector J. Gilliam, Reactor Inspector | REGION III== | ||
Docket No: 50-346 License No: NPF-3 Report No: 05000346/2017010 Licensee: FirstEnergy Nuclear Operating Company Facility: Davis-Besse Nuclear Power Station Location: Oak Harbor, OH Dates: September 18-22, 2017 Inspectors: J. Bozga, Senior Reactor Inspector (Lead) | |||
J. Benjamin, Senior Reactor Inspector J. Gilliam, Reactor Inspector N. Khan, Electrical Engineer (Observer) | |||
Approved by: Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Enclosure | |||
=SUMMARY= | |||
Inspection Report 05000346/2017010; 09/18/2017-09/22/2017; Davis-Besse Nuclear Power | |||
Station; Evaluations of Changes, Tests, and Experiments. | |||
This report covers a 1-week announced evaluations of changes, tests, and experiments baseline inspection. 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 6, dated July 201 | |||
The | |||
===NRC-Identified=== | ===NRC-Identified=== | ||
and Self-Revealed Findings No findings were identified. | and Self-Revealed Findings No findings were identified. | ||
=== | ===Licensee-Identified Violations=== | ||
No violations were identified. | No violations were identified. | ||
=REPORT DETAILS= | =REPORT DETAILS= | ||
| Line 63: | Line 66: | ||
==REACTOR SAFETY== | ==REACTOR SAFETY== | ||
===Cornerstone: | ===Cornerstone: Initiating Events, Mitigating Systems, and Barrier Integrity=== | ||
{{a|1R17}} | {{a|1R17}} | ||
==1R17 Evaluations of Changes, Tests, and Experiments== | ==1R17 Evaluations of Changes, Tests, and Experiments== | ||
| Line 70: | Line 73: | ||
====a. Inspection Scope==== | ====a. Inspection Scope==== | ||
The inspectors reviewed 4 evaluations performed pursuant to Title 10, Code of Federal | The inspectors reviewed 4 evaluations performed pursuant to Title 10, Code of Federal Regulations (CFR), Part 50, Section 59, to determine if the evaluations were adequate and that prior NRC approval was obtained as appropriate. The inspectors also reviewed screenings and applicability determinations where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary. The inspectors reviewed these documents to determine if: | ||
Regulations (CFR), Part 50, Section 59, to determine if the evaluations were adequate and that prior NRC approval was obtained as appropriate. The inspectors also reviewed screenings and applicability determinations 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 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 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 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, | * 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 U.S. Nuclear Regulatory Commission 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 U.S. Nuclear Regulatory Commission Inspection Manual, 10 CFR Guidance for 10 CFR 50.59, Changes, Tests, and Experiments. | |||
This inspection constituted 30 samples of evaluations, screenings, and/or applicability determinations as defined in Inspection Procedure 71111.17-05. | |||
====b. Findings==== | ====b. Findings==== | ||
| Line 92: | Line 97: | ||
====b. Findings==== | ====b. Findings==== | ||
No findings of significance were identified. | No findings of significance were identified. | ||
{{a|4OA6}} | {{a|4OA6}} | ||
==4OA6 Management Meetings== | ==4OA6 Management Meetings== | ||
===.1 Exit Meeting Summary=== | ===.1 Exit Meeting Summary=== | ||
On September 22, 2017, the inspectors presented the inspection results to Mr. M. Bezilla, Site Vice President, and other members of the licensee staff. The licensee personnel acknowledged the inspection results presented and did not identify any proprietary content. The inspectors confirmed that all proprietary material reviewed during the inspection was returned to the licensee staff. ATTACHMENT: | |||
On September 22, 2017, the inspectors presented the inspection results to Mr. M. Bezilla, Site Vice President, and other members of the licensee staff. The licensee personnel acknowledged the inspection results presented and did not identify any proprietary content. The inspectors confirmed that all proprietary material reviewed during the inspection was returned to the licensee staff. | |||
ATTACHMENT: | |||
=SUPPLEMENTAL INFORMATION= | =SUPPLEMENTAL INFORMATION= | ||
| Line 102: | Line 110: | ||
==KEY POINTS OF CONTACT== | ==KEY POINTS OF CONTACT== | ||
Licensee | Licensee | ||
: [[contact::M. Bezilla]], Site Vice President | : [[contact::M. Bezilla]], Site Vice President | ||
: [[contact::G. Wolf]], Regulatory Compliance Supervisor | : [[contact::G. Wolf]], Regulatory Compliance Supervisor | ||
: [[contact::D. Blakely]], Engineering Analysis Supervisor | : [[contact::D. Blakely]], Engineering Analysis Supervisor | ||
: [[contact::J. Sturdavant]], Regulatory Compliance Specialist | : [[contact::J. Sturdavant]], Regulatory Compliance Specialist | ||
==LIST OF ITEMS== | ==LIST OF ITEMS== | ||
OPENED, CLOSED AND DISCUSSED Opened, Closed and | |||
===OPENED, CLOSED AND DISCUSSED=== | |||
Opened, Closed and | |||
===Discussed=== | ===Discussed=== | ||
None LIST OF ACRONYMS USED CFR Code of Federal Regulations | None LIST OF ACRONYMS USED CFR Code of Federal Regulations | ||
==LIST OF DOCUMENTS REVIEWED== | ==LIST OF DOCUMENTS REVIEWED== | ||
}} | }} | ||
Latest revision as of 10:01, 19 December 2019
| ML17286B124 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 10/11/2017 |
| From: | Robert Daley Engineering Branch 3 |
| To: | Bezilla M FirstEnergy Nuclear Operating Co |
| References | |
| IR 2017010 | |
| Download: ML17286B124 (13) | |
Text
UNITED STATES ber 11, 2017
SUBJECT:
DAVIS-BESSE NUCLEAR POWER STATION EVALUATIONS OF CHANGES, TESTS, AND EXPERIMENTS BASELINE INSPECTION REPORT 05000346/2017010
Dear Mr. Bezilla:
On September 22, 2017 the U.S. Nuclear Regulatory Commission (NRC) completed an Evaluations of Changes, Tests, and Experiments inspection at your Davis-Besse Nuclear Power Station. The enclosed inspection report documents the inspection results which were discussed on September 22, 2017, with you 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.
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 No. 50-346 License No. NPF-3
Enclosure:
REGION III==
Docket No: 50-346 License No: NPF-3 Report No: 05000346/2017010 Licensee: FirstEnergy Nuclear Operating Company Facility: Davis-Besse Nuclear Power Station Location: Oak Harbor, OH Dates: September 18-22, 2017 Inspectors: J. Bozga, Senior Reactor Inspector (Lead)
J. Benjamin, Senior Reactor Inspector J. Gilliam, Reactor Inspector N. Khan, Electrical Engineer (Observer)
Approved by: Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Enclosure
SUMMARY
Inspection Report 05000346/2017010; 09/18/2017-09/22/2017; Davis-Besse Nuclear Power
Station; Evaluations of Changes, Tests, and Experiments.
This report covers a 1-week announced evaluations of changes, tests, and experiments baseline inspection. 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 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
Cornerstone: 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 4 evaluations performed pursuant to Title 10, Code of Federal Regulations (CFR), Part 50, Section 59, to determine if the evaluations were adequate and that prior NRC approval was obtained as appropriate. The inspectors also reviewed screenings and applicability determinations 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 U.S. Nuclear Regulatory Commission 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 U.S. Nuclear Regulatory Commission Inspection Manual, 10 CFR Guidance for 10 CFR 50.59, Changes, Tests, and Experiments.
This inspection constituted 30 samples of evaluations, screenings, and/or applicability determinations as defined in Inspection Procedure 71111.17-05.
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. The inspectors reviewed these documents to evaluate the effectiveness of corrective actions related to 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 of significance were identified.
4OA6 Management Meetings
.1 Exit Meeting Summary
On September 22, 2017, the inspectors presented the inspection results to Mr. M. Bezilla, Site Vice President, and other members of the licensee staff. The licensee personnel acknowledged the inspection results presented and did not identify any proprietary content. 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. Bezilla, Site Vice President
- G. Wolf, Regulatory Compliance Supervisor
- D. Blakely, Engineering Analysis Supervisor
- J. Sturdavant, Regulatory Compliance Specialist
LIST OF ITEMS
OPENED, CLOSED AND DISCUSSED
Opened, Closed and
Discussed
None LIST OF ACRONYMS USED CFR Code of Federal Regulations