IR 05000424/2014007: Difference between revisions
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{{#Wiki_filter:UNITED STATES | {{#Wiki_filter:UNITED STATES uly 22, 2014 | ||
==SUBJECT:== | |||
VOGTLE ELECTRIC GENERATING PLANT - NRC EVALUATION OF CHANGES, TESTS, AND EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS INSPECTION REPORT 05000424/2014007 AND 05000425/2014007 | |||
==Dear Mr. Tynan:== | ==Dear Mr. Tynan:== | ||
| Line 33: | Line 28: | ||
The NRC inspectors did not identify any findings or violations of more than minor significance. | The NRC inspectors did not identify any findings or violations of more than minor significance. | ||
In accordance with Title 10 of the Code of Federal Regulations 2.390, | In accordance with Title 10 of the Code of Federal Regulations 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 NRC Public Document Room or from the Publicly Available Records (PARS) component of 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, | Sincerely, | ||
/RA: Shakur A. Walker for/ | /RA: Shakur A. Walker for/ | ||
Rebecca L. Nease, Chief Engineering Branch 1 Division of Reactor Safety | Rebecca L. Nease, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos.: 05000424, 05000425 License Nos.: NPF-68 and NPF-81 | ||
Docket Nos.: 05000424, 05000425 | |||
License Nos.: NPF-68 and NPF-81 | |||
===Enclosure:=== | ===Enclosure:=== | ||
Inspection Report 05000424/2014007 and 05000425/2014007 w/Attachment: Supplementary Information | Inspection Report 05000424/2014007 and 05000425/2014007 w/Attachment: Supplementary Information | ||
REGION II== | REGION II== | ||
Docket Nos.: 50-424, 50-425 | Docket Nos.: 50-424, 50-425 License Nos.: NPF-68, NPF-81 Report Nos.: 05000424/2014007, 05000425/2014007 Licensee: Southern Nuclear Operating Company, Inc. (SNC) | ||
Facility: Vogtle Electric Generating Plant, Units 1 and 2 Location: Waynesboro, GA 30830 Dates: June 9, 2014 - June 27, 2014 Inspectors: A. Alen, Reactor Inspector (Team Leader) | |||
License Nos.: NPF-68, NPF-81 | S. Walker, Senior Reactor Inspector A. Wilson, Construction Projects Inspector Approved by: Rebecca L. Nease, Chief Engineering Branch 1 Division of Reactor Safety Enclosure | ||
Report Nos.: 05000424/2014007, 05000425/2014007 | |||
Licensee: Southern Nuclear Operating Company, Inc. (SNC) | |||
Facility: Vogtle Electric Generating Plant, Units 1 and 2 | |||
Location: Waynesboro, GA 30830 | |||
Dates: June 9, 2014 - June 27, 2014 | |||
Inspectors: A. Alen, Reactor Inspector (Team Leader) S. Walker, Senior Reactor Inspector A. Wilson, Construction Projects Inspector | |||
Approved by: Rebecca L. Nease, Chief Engineering Branch 1 Division of Reactor Safety | |||
=SUMMARY= | =SUMMARY= | ||
Inspection Report (IR) 05000424/2014007, 05000425/2014007; 06/09/2014-06/27/2014; Vogtle | Inspection Report (IR) 05000424/2014007, 05000425/2014007; 06/09/2014-06/27/2014; Vogtle | ||
Electric Generating Plant, Units 1 and 2; NRC Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications. | Electric Generating Plant, Units 1 and 2; NRC Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications. | ||
This report covers a two-week, on-site inspection by three regional inspectors. No findings or violations were identified. The Nuclear Regulatory | This report covers a two-week, on-site inspection by three regional inspectors. No findings or violations were identified. The Nuclear Regulatory Commissions (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. | ||
=REPORT DETAILS= | =REPORT DETAILS= | ||
==REACTOR SAFETY== | ==REACTOR SAFETY== | ||
Cornerstones: | Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity | ||
{{a|1R17}} | {{a|1R17}} | ||
==1R17 Evaluations of Changes, Tests, Experiments and Permanent Plant Modifications== | ==1R17 Evaluations of Changes, Tests, Experiments and Permanent Plant Modifications== | ||
{{IP sample|IP=IP 71111.17T}} | |||
====a. Inspection Scope==== | ====a. Inspection Scope==== | ||
Evaluations of Changes, Tests, and Experiments | Evaluations of Changes, Tests, and Experiments: The team reviewed six safety evaluations performed pursuant to Title 10, Code of Federal Regulations (CFR) 50.59, Changes, tests, and experiments, to determine if the evaluations were adequate and that prior NRC approval was obtained as appropriate. The team also reviewed 19 screenings where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary. The team reviewed these documents to determine if: | ||
: | |||
* the changes, tests, or 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, or 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 issues requiring the changes, tests or experiments were resolved; | * the safety issues requiring the changes, tests or experiments were resolved; | ||
| Line 90: | Line 64: | ||
* the design and licensing basis documentation used to support the change was updated to reflect the change. | * the design and licensing basis documentation used to support the change was updated to reflect the change. | ||
The team used, in part, Nuclear Energy Institute (NEI) 96-07, | The team 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. | ||
This inspection constituted six samples of evaluations and 19 samples of screenings as defined in Inspection Procedure (IP) 71111.17-04. | This inspection constituted six samples of evaluations and 19 samples of screenings as defined in Inspection Procedure (IP) 71111.17-04. | ||
Permanent Plant Modifications: | Permanent Plant Modifications: The team reviewed 10 permanent plant modifications that had been installed in the plant during the last three years. The modifications reviewed are listed below: | ||
* Design Change Package (DCP) 1060336501, 480-Volt (V) Breakers and 4160/480V Transformer Replacement, Ver. 4.0 | * Design Change Package (DCP) 1060336501, 480-Volt (V) Breakers and 4160/480V Transformer Replacement, Ver. 4.0 | ||
* DCP 1081089101, Replacement/Modification of Motor Operators | * DCP 1081089101, Replacement/Modification of Motor Operators HV8811A/B, Ver. 6.0 | ||
* DCP 1102491801, Penetration through Auxiliary Building Roof, Ver. 2.0 | * DCP 1102491801, Penetration through Auxiliary Building Roof, Ver. 2.0 | ||
* DCP SNC466754, High Efficiency Purge Unit, Ver. 1.0 | * DCP SNC466754, High Efficiency Purge Unit, Ver. 1.0 | ||
* DCP 1039002501, Digital Feedwater Control System, Ver. 5.0 | * DCP 1039002501, Digital Feedwater Control System, Ver. 5.0 | ||
* Equivalency Determination (ED) SNC366192, Replace G700 Main Steam Isolation Valve (MSIV) packing with Argo 524, Ver. 1.0 | * Equivalency Determination (ED) SNC366192, Replace G700 Main Steam Isolation Valve (MSIV) packing with Argo 524, Ver. 1.0 | ||
* ED SNC438360, Westinghouse 2D82820G02 5-V Direct Current Power | * ED SNC438360, Westinghouse 2D82820G02 5-V Direct Current Power Supply, Ver. 2.0 | ||
* ED SNC447263, MSIV Stem Material Change to SA638 Gr 660, Ver. 2.0 | * ED SNC447263, MSIV Stem Material Change to SA638 Gr 660, Ver. 2.0 | ||
* ED SNC491984, Emergency Diesel Generator Jacket Water Gasket Binder Change from Nitrile Butadiene Rubber (NBR) to Styrol Butadiene Rubber (SBR), Ver. 1.0 | * ED SNC491984, Emergency Diesel Generator Jacket Water Gasket Binder Change from Nitrile Butadiene Rubber (NBR) to Styrol Butadiene Rubber (SBR), Ver. 1.0 | ||
* ED SNC128991, Reserve Auxiliary | * ED SNC128991, Reserve Auxiliary Transformer and Generator Step-up Transformer Lighting Arresters, Ver. 1.0 The modifications were selected based upon risk significance, safety significance, and complexity. The team reviewed the modifications selected to determine if: | ||
The modifications were selected based upon risk significance, safety significance, and complexity. The team reviewed the modifications selected to determine if: | |||
* the supporting design and licensing basis documentation was updated; | * the supporting design and licensing basis documentation was updated; | ||
* the changes were in accordance with the specified design requirements; | * the changes were in accordance with the specified design requirements; | ||
| Line 113: | Line 85: | ||
* post-modification testing adequately verified system operability and/or functionality. | * post-modification testing adequately verified system operability and/or functionality. | ||
The team also used applicable industry | The team also used applicable industry standards to evaluate acceptability of the modifications and performed walkdowns of accessible portions of the modifications. | ||
Documents reviewed are listed in the Attachment. | |||
71111.17-04. | This inspection constituted 10 permanent plant modification samples as defined in IP 71111.17-04. | ||
====b. Findings==== | ====b. Findings==== | ||
| Line 125: | Line 97: | ||
==4OA6 Meetings, Including Exit== | ==4OA6 Meetings, Including Exit== | ||
On June 27, 2014, the team presented inspection results to Mr. J. Thomas and other members of the | On June 27, 2014, the team presented inspection results to Mr. J. Thomas and other members of the licensees staff. The team verified that no proprietary information was retained by the inspectors or documented in this report. | ||
ATTACHMENT: | ATTACHMENT: | ||
=SUPPLEMENTARY INFORMATION= | =SUPPLEMENTARY INFORMATION= | ||
| Line 134: | Line 106: | ||
===Licensee personnel=== | ===Licensee personnel=== | ||
: [[contact::L. Mansfield]], Fleet Design Director | : [[contact::L. Mansfield]], Fleet Design Director | ||
: [[contact::G. Gunn]], Licensing Supervisor | : [[contact::G. Gunn]], Licensing Supervisor | ||
: [[contact::K. Walden]], Licensing Engineer | : [[contact::K. Walden]], Licensing Engineer | ||
: [[contact::H. Jones]], Lead Engineer | : [[contact::H. Jones]], Lead Engineer | ||
: [[contact::J. Wade]], Site Design Manager | : [[contact::J. Wade]], Site Design Manager | ||
===NRC personnel=== | ===NRC personnel=== | ||
: [[contact::M. Cain]], Senior Resident Inspector, Vogtle | : [[contact::M. Cain]], Senior Resident Inspector, Vogtle | ||
: [[contact::W. Pursley]], Resident Inspector (Acting), Vogtle | : [[contact::W. Pursley]], Resident Inspector (Acting), Vogtle | ||
==LIST OF ITEMS OPENED, CLOSED, DISCUSSED, AND UPDATED== | ==LIST OF ITEMS OPENED, CLOSED, DISCUSSED, AND UPDATED== | ||
===Opened=== | ===Opened=== | ||
None | |||
None | |||
===Closed=== | ===Closed=== | ||
None | |||
None | |||
===Discussed=== | ===Discussed=== | ||
None | None Updated None | ||
None | |||
==LIST OF DOCUMENTS REVIEWED== | ==LIST OF DOCUMENTS REVIEWED== | ||
}} | }} | ||
Revision as of 02:11, 4 November 2019
| ML14205A176 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 07/22/2014 |
| From: | Nease R NRC/RGN-II/DRS/EB1 |
| To: | Tynan T Southern Nuclear Operating Co |
| References | |
| IR-14-007 | |
| Download: ML14205A176 (14) | |
Text
UNITED STATES uly 22, 2014
SUBJECT:
VOGTLE ELECTRIC GENERATING PLANT - NRC EVALUATION OF CHANGES, TESTS, AND EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS INSPECTION REPORT 05000424/2014007 AND 05000425/2014007
Dear Mr. Tynan:
On June 27, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Vogtle Electric Generating Plant, Units 1 and 2, and discussed the results of this inspection with Mr. J. Thomas and other members of your staff. Inspectors documented the results of this inspection in the enclosed inspection report.
The NRC inspectors did not identify any findings or violations of more than minor significance.
In accordance with Title 10 of the Code of Federal Regulations 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 NRC Public Document Room or from the Publicly Available Records (PARS) component of 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: Shakur A. Walker for/
Rebecca L. Nease, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos.: 05000424, 05000425 License Nos.: NPF-68 and NPF-81
Enclosure:
Inspection Report 05000424/2014007 and 05000425/2014007 w/Attachment: Supplementary Information
REGION II==
Docket Nos.: 50-424, 50-425 License Nos.: NPF-68, NPF-81 Report Nos.: 05000424/2014007, 05000425/2014007 Licensee: Southern Nuclear Operating Company, Inc. (SNC)
Facility: Vogtle Electric Generating Plant, Units 1 and 2 Location: Waynesboro, GA 30830 Dates: June 9, 2014 - June 27, 2014 Inspectors: A. Alen, Reactor Inspector (Team Leader)
S. Walker, Senior Reactor Inspector A. Wilson, Construction Projects Inspector Approved by: Rebecca L. Nease, Chief Engineering Branch 1 Division of Reactor Safety Enclosure
SUMMARY
Inspection Report (IR) 05000424/2014007, 05000425/2014007; 06/09/2014-06/27/2014; Vogtle
Electric Generating Plant, Units 1 and 2; NRC Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications.
This report covers a two-week, on-site inspection by three regional inspectors. No findings or violations were identified. The Nuclear Regulatory Commissions (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.
REPORT DETAILS
REACTOR SAFETY
Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity
1R17 Evaluations of Changes, Tests, Experiments and Permanent Plant Modifications
a. Inspection Scope
Evaluations of Changes, Tests, and Experiments: The team reviewed six safety evaluations performed pursuant to Title 10, Code of Federal Regulations (CFR) 50.59, Changes, tests, and experiments, to determine if the evaluations were adequate and that prior NRC approval was obtained as appropriate. The team also reviewed 19 screenings where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary. The team reviewed these documents to determine if:
- the changes, tests, or 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 issues requiring the changes, tests or experiments were resolved;
- the licensee conclusions for evaluations of changes, tests, or experiments were correct and consistent with 10 CFR 50.59; and
- the design and licensing basis documentation used to support the change was updated to reflect the change.
The team 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.
This inspection constituted six samples of evaluations and 19 samples of screenings as defined in Inspection Procedure (IP) 71111.17-04.
Permanent Plant Modifications: The team reviewed 10 permanent plant modifications that had been installed in the plant during the last three years. The modifications reviewed are listed below:
- Design Change Package (DCP) 1060336501, 480-Volt (V) Breakers and 4160/480V Transformer Replacement, Ver. 4.0
- DCP 1081089101, Replacement/Modification of Motor Operators HV8811A/B, Ver. 6.0
- DCP 1102491801, Penetration through Auxiliary Building Roof, Ver. 2.0
- DCP SNC466754, High Efficiency Purge Unit, Ver. 1.0
- Equivalency Determination (ED) SNC366192, Replace G700 Main Steam Isolation Valve (MSIV) packing with Argo 524, Ver. 1.0
- ED SNC438360, Westinghouse 2D82820G02 5-V Direct Current Power Supply, Ver. 2.0
- ED SNC491984, Emergency Diesel Generator Jacket Water Gasket Binder Change from Nitrile Butadiene Rubber (NBR) to Styrol Butadiene Rubber (SBR), Ver. 1.0
- ED SNC128991, Reserve Auxiliary Transformer and Generator Step-up Transformer Lighting Arresters, Ver. 1.0 The modifications were selected based upon risk significance, safety significance, and complexity. The team 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 had been adequately updated;
- the test documentation as required by the applicable test programs had been updated; and
- post-modification testing adequately verified system operability and/or functionality.
The team also used applicable industry standards to evaluate acceptability of the modifications and performed walkdowns of accessible portions of the modifications.
Documents reviewed are listed in the Attachment.
This inspection constituted 10 permanent plant modification samples as defined in IP 71111.17-04.
b. Findings
No findings were identified.
4OA6 Meetings, Including Exit
On June 27, 2014, the team presented inspection results to Mr. J. Thomas and other members of the licensees staff. The team verified that no proprietary information was retained by the inspectors or documented in this report.
ATTACHMENT:
SUPPLEMENTARY INFORMATION
KEY POINTS OF CONTACT
Licensee personnel
- L. Mansfield, Fleet Design Director
- G. Gunn, Licensing Supervisor
- K. Walden, Licensing Engineer
- J. Wade, Site Design Manager
NRC personnel
- M. Cain, Senior Resident Inspector, Vogtle
- W. Pursley, Resident Inspector (Acting), Vogtle
LIST OF ITEMS OPENED, CLOSED, DISCUSSED, AND UPDATED
Opened
None
Closed
None
Discussed
None Updated None