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=Text=
=Text=
{{#Wiki_filter:une 21, 2013
{{#Wiki_filter:UNITED STATES une 21, 2013


==SUBJECT:==
==SUBJECT:==
EDWIN I. HATCH NUCLEAR PLANT  
EDWIN I. HATCH NUCLEAR PLANT - NRC EVALUATION OF CHANGES, TESTS, AND EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000321/2013010 AND 05000366/2013010
- NRC EVALUATION OF CHANGES, TESTS, AND EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000321/20 1 3 0 10 AND 05000366/20 1 3 0 1 0


Dear Mr. Madison
==Dear Mr. Madison:==
:
On May 23, 2013, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your E. I. Hatch Units 1 and 2. The enclosed inspection report documents the inspection results which were discussed on May 23, 2013, with you and other members of your staff.
On Ma y 23, 2013, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your E. I. Hatch Units 1 and The enclosed inspection report documents the inspection results which were discussed on May 23, 2013 , with you and other members of your staf The inspection examined activities conducted under your license s as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license The team reviewed selected procedures and records, observed activities, and interviewed personne No findings were identified during this inspectio In accordance with 10 CFR 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 (PARS) component of NRC's Agency-wide Document Access and Management System (ADAMS).


D. Madison 2 ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
The inspection examined activities conducted under your licenses as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your licenses. The team reviewed selected procedures and records, observed activities, and interviewed personnel.


Sincerely, RA Rebecca L. Nease, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos.:
No findings were identified during this inspection.
50-321, 50-366 License Nos.:
DPR-57 and NPF-5 Enclosure:
Inspection Report 05000321/20130 10, 05000366/20130 1 0 w/attachment: Supplemental Information


Enclosure U. S. NUCLEAR REGULATORY COMMISSION
In accordance with 10 CFR 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 (PARS) component of NRC's Agency-wide Document 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 Rebecca L. Nease, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos.: 50-321, 50-366 License Nos.: DPR-57 and NPF-5 Enclosure:
Inspection Report 05000321/2013010, 05000366/2013010 w/attachment: Supplemental Information
 
U. S. NUCLEAR REGULATORY COMMISSION


==REGION II==
==REGION II==
Docket Nos.:
Docket Nos.: 50-321, 50-366 License Nos.: DPR-57 and NPF-5 Report Nos.: 05000321/2013010 and 05000366/2013010 Licensee: Southern Nuclear Operating Company, Inc.
50-321, 50-366 License Nos.:
DPR-57 and NPF-5 Report Nos.:
05000321/20 1 3 0 1 0 and 05000366/20 1 3 0 1 0 Licensee: Southern Nuclear Operating Company, In Facility: Edwin I. Hatch Nuclear Plant


Location: Baxley, Georgia 31513 Dates: May 6 - Ma y 2 3 , 2013 Inspectors:
Facility: Edwin I. Hatch Nuclear Plant Location: Baxley, Georgia 31513 Dates: May 6 - May 23, 2013 Inspectors: E. Stamm, Senior Reactor Inspector (Team Leader)
E. Stamm, Senior Re ac t or Inspector (Team Leader)
A. Butcavage, Reactor Inspector M. Schwieg, Resident Inspector (Brunswick)
A. Butcavage, Reactor Inspector M. Schwieg, Resident Inspector (Brunswick)
Approved by:
Approved by: Rebecca L. Nease, Chief Engineering Branch 1 Division of Reactor Safety Enclosure
Rebecca L. Nease, Chief Engineering Branch 1 Division of Reactor Safety Enclosure  


=SUMMARY OF FINDINGS=
=SUMMARY OF FINDINGS=
IR 05000321/20 1 3 0 10, 05000366/20 1 3 0 1 0; 0 5/0 6/20 1 3-0 5/2 3/20 1 3; Edwin I. Hatch Nuclear Plant, Units 1 and 2
IR 05000321/2013010, 05000366/2013010; 05/06/2013-05/23/2013; Edwin I. Hatch Nuclear
; Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications Th is report cover s a two-week on-site inspection by one senior reactor inspector, one reactor inspector, and one resident inspector. No findings were identified. The NRC's program for overseeing the safe operations of commercial nuclear power reactors is described in NUREG
 
-1649, "Reactor Oversight Process
Plant, Units 1 and 2; Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications This report covers a two-week on-site inspection by one senior reactor inspector, one reactor inspector, and one resident inspector. No findings were identified. The NRCs program for overseeing the safe operations of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 4.
," Revision 4.


No findings were identified during this inspection
No findings were identified during this inspection.
.


=REPORT DETAILS=
=REPORT DETAILS=


==REACTOR SAFETY==
==REACTOR SAFETY==
Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity 1R1 7  Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications (71111.1 7T)
Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity
 
{{a|1R17}}
==1R17 Evaluations of Changes, Tests, and Experiments and Permanent Plant==
 
Modifications (71111.17T)


====a. Inspection Scope====
====a. Inspection Scope====
Evaluations of Changes, Tests, and Experiments
Evaluations of Changes, Tests, and Experiments: From May 6, 2013, through May 23, 2013, the team reviewed eight 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 team also reviewed 13 screenings where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary. The team reviewed these documents to determine if:
: From May 6, 2013, through May 23 , 2013, the team reviewed eight 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 team also reviewed 13 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 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 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
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. The team also consulted Part 9900 of the NRC Inspection Manual, 10 CFR Guidance for 10 CFR 50.59, Changes, Tests, and Experiments, dated March 2001.
-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 team also consulted Part 9900 of the NRC Inspection Manual, "10 CFR Guidance for 10 CFR 50.59, Changes, Tests, and Experiments
," dated March 2001.


This inspection constituted eight samples of evaluations and 13 samples of screenings as defined in Inspection Procedure (IP) 71111.17-04.
This inspection constituted eight samples of evaluations and 13 samples of screenings as defined in Inspection Procedure (IP) 71111.17-04.


Permanent Plant Modifications
Permanent Plant Modifications: From May 6, 2013, through May 23, 2013, the team reviewed six permanent plant modifications that had been installed in the plant during the last three years. The six modifications reviewed are listed below:
: From May 6, 2013, through May 23, 2013, the team reviewed six permanent plant modifications that had been installed in the plant during the last three years. The six modifications reviewed are listed below:
* Design Change Package (DCP) 1071694001, Modification to Isolate Unit 1 Protected Service Water from Turbine Building, Rev. 0
Design Change Package (DCP) 1071694001
* DCP 1072721101, Reroute Cables out of Fire Area 0014, Ver. 3.0
, Modification to Isolate Unit 1 Protected Service Water from Turbine Building, Rev. 0 DCP 1072721101
* DCP 1081976501, Replacement of Upper Shroud Support Assemblies and Tie Rod Nuts, Ver. 2.0
, Reroute Cables out of Fire Area 0014, Ver. 3.0 DCP 1081976501
* DCP 1092321101, Coordination Enhancement for 250 VDC Motor Control Center 1R24-S022 Cubicles 4A, 6A, and 9C, Ver. 2.0
, Replacement of Upper Shroud Support Assemblies and Tie Rod Nuts, Ver. 2.0 DCP 1092321101
* DCP 1101786501, Replace Fission Product Monitor Inboard Isolation Valve 1D11-F050, Ver. 1.0
, Coordination Enhancement for 250 VDC Motor Control Center 1R24-S022 Cubicles 4A, 6A, and 9C, Ver. 2.
* DCP 2039000201, 4.16kV Breaker Replacement, Ver. 1.1 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;
DCP 1101786501
* the changes were in accordance with the specified design requirements;
, Replace Fission Product Monitor Inboard Isolation Valve 1D11-F050, Ver. 1.0 DCP 2039000201
* the procedures and training plans affected by the modification had been adequately updated;
, 4.16kV Breaker Replacement, Ver. 1.1 The modifications were selected based upon risk significance, safety significance, and complexity.
* 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 reviewed the modifications selected to determine if:
The team also used applicable industry standards to evaluate acceptability of the modifications and performed walk downs of accessible portions of the modifications.
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 ha d been adequately updated; the test documentation as required by the applicable test programs ha d 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 walk downs of accessible portions of the modifications. Documents reviewed are listed in the Attachment.
Documents reviewed are listed in the Attachment.


This inspection constituted six permanent plant modification samples as defined in IP 71111.17-04.
This inspection constituted six permanent plant modification samples as defined in IP 71111.17-04.


====b. Findings====
====b. Findings====
No findings were identified
No findings were identified.
.


{{a|4OA6}}
{{a|4OA6}}
==4OA6 Meetings, Including Exit==
==4OA6 Meetings, Including Exit==


On May 23, 2013, the team presented the inspection results to Mr. Dennis Madison and other members of the licensee's staff. The team verified that no proprietary information was retained by the inspectors or documented in this report.
On May 23, 2013, the team presented the inspection results to Mr. Dennis Madison 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:  


=SUPPLEMENTAL INFORMATION=
=SUPPLEMENTAL INFORMATION=
Line 114: Line 111:
: [[contact::E. DelRosario]], Site Design Engineer
: [[contact::E. DelRosario]], Site Design Engineer
: [[contact::D. Hines]], Site Design Supervisor
: [[contact::D. Hines]], Site Design Supervisor
: [[contact::B. Hulett]], Site Design Manager  
: [[contact::B. Hulett]], Site Design Manager
: [[contact::C. Lane]], Engineering Director
: [[contact::C. Lane]], Engineering Director
: [[contact::K. Long]], Operations Director
: [[contact::K. Long]], Operations Director
Line 122: Line 119:
: [[contact::C. Robinson]], ASD Engineer
: [[contact::C. Robinson]], ASD Engineer
: [[contact::R. Seiter]], Engineering Supervisor
: [[contact::R. Seiter]], Engineering Supervisor
: [[contact::B. Shuman]], Engineering Programs Manager  
: [[contact::B. Shuman]], Engineering Programs Manager
: [[contact::S. Tipps]], Licensing Supervisor
: [[contact::S. Tipps]], Licensing Supervisor
: [[contact::D. Vineyard]], Plant Manager
: [[contact::D. Vineyard]], Plant Manager
Line 128: Line 125:
: [[contact::E. Wonn]], Senior Designer
: [[contact::E. Wonn]], Senior Designer
: [[contact::F. Zayas]], Site Design Supervisor
: [[contact::F. Zayas]], Site Design Supervisor
===NRC personnel===
===NRC personnel===
: [[contact::E. Morris]], Senior Resident Inspector, Hatch
: [[contact::E. Morris]], Senior Resident Inspector, Hatch
Line 136: Line 132:
OPENED AND CLOSED
OPENED AND CLOSED


===Opened and
===Opened and Closed===
Closed===
 
None      
None


==LIST OF DOCUMENTS REVIEWED==
==LIST OF DOCUMENTS REVIEWED==


}}
}}

Revision as of 16:45, 4 November 2019

IR 05000321-13-010, 05000366-13-010, 05/06/2013-05/23/2013, Edwin I. Hatch Nuclear Plant, Units 1 and 2; Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications
ML13172A142
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 06/21/2013
From: Nease R
NRC/RGN-II/DRS/EB1
To: Madison D
Southern Nuclear Operating Co
References
IR-13-010
Download: ML13172A142 (12)
v • d • e


Text

UNITED STATES une 21, 2013

SUBJECT:

EDWIN I. HATCH NUCLEAR PLANT - NRC EVALUATION OF CHANGES, TESTS, AND EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000321/2013010 AND 05000366/2013010

Dear Mr. Madison:

On May 23, 2013, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your E. I. Hatch Units 1 and 2. The enclosed inspection report documents the inspection results which were discussed on May 23, 2013, with you and other members of your staff.

The inspection examined activities conducted under your licenses as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your licenses. The team reviewed selected procedures and records, observed activities, and interviewed personnel.

No findings were identified during this inspection.

In accordance with 10 CFR 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 (PARS) component of NRC's Agency-wide Document 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 Rebecca L. Nease, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos.: 50-321, 50-366 License Nos.: DPR-57 and NPF-5 Enclosure:

Inspection Report 05000321/2013010, 05000366/2013010 w/attachment: Supplemental Information

U. S. NUCLEAR REGULATORY COMMISSION

REGION II

Docket Nos.: 50-321, 50-366 License Nos.: DPR-57 and NPF-5 Report Nos.: 05000321/2013010 and 05000366/2013010 Licensee: Southern Nuclear Operating Company, Inc.

Facility: Edwin I. Hatch Nuclear Plant Location: Baxley, Georgia 31513 Dates: May 6 - May 23, 2013 Inspectors: E. Stamm, Senior Reactor Inspector (Team Leader)

A. Butcavage, Reactor Inspector M. Schwieg, Resident Inspector (Brunswick)

Approved by: Rebecca L. Nease, Chief Engineering Branch 1 Division of Reactor Safety Enclosure

SUMMARY OF FINDINGS

IR 05000321/2013010, 05000366/2013010; 05/06/2013-05/23/2013; Edwin I. Hatch Nuclear

Plant, Units 1 and 2; Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications This report covers a two-week on-site inspection by one senior reactor inspector, one reactor inspector, and one resident inspector. No findings were identified. The NRCs program for overseeing the safe operations of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 4.

No findings were identified during this inspection.

REPORT DETAILS

REACTOR SAFETY

Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity

1R17 Evaluations of Changes, Tests, and Experiments and Permanent Plant

Modifications (71111.17T)

a. Inspection Scope

Evaluations of Changes, Tests, and Experiments: From May 6, 2013, through May 23, 2013, the team reviewed eight 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 team also reviewed 13 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. The team also consulted Part 9900 of the NRC Inspection Manual, 10 CFR Guidance for 10 CFR 50.59, Changes, Tests, and Experiments, dated March 2001.

This inspection constituted eight samples of evaluations and 13 samples of screenings as defined in Inspection Procedure (IP) 71111.17-04.

Permanent Plant Modifications: From May 6, 2013, through May 23, 2013, the team reviewed six permanent plant modifications that had been installed in the plant during the last three years. The six modifications reviewed are listed below:

  • Design Change Package (DCP) 1071694001, Modification to Isolate Unit 1 Protected Service Water from Turbine Building, Rev. 0
  • DCP 1072721101, Reroute Cables out of Fire Area 0014, Ver. 3.0
  • DCP 1081976501, Replacement of Upper Shroud Support Assemblies and Tie Rod Nuts, Ver. 2.0
  • DCP 1092321101, Coordination Enhancement for 250 VDC Motor Control Center 1R24-S022 Cubicles 4A, 6A, and 9C, Ver. 2.0
  • DCP 1101786501, Replace Fission Product Monitor Inboard Isolation Valve 1D11-F050, Ver. 1.0
  • DCP 2039000201, 4.16kV Breaker Replacement, Ver. 1.1 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 walk downs of accessible portions of the modifications.

Documents reviewed are listed in the Attachment.

This inspection constituted six permanent plant modification samples as defined in IP 71111.17-04.

b. Findings

No findings were identified.

4OA6 Meetings, Including Exit

On May 23, 2013, the team presented the inspection results to Mr. Dennis Madison 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:

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee personnel

B. Anderson, Health Physics Manager
S. Beverly, Licensing Engineer
T. Crowell, Site Design Engineer
E. DelRosario, Site Design Engineer
D. Hines, Site Design Supervisor
B. Hulett, Site Design Manager
C. Lane, Engineering Director
K. Long, Operations Director
D. Madison, Vice President
C. McCall, Project Engineer
M. Peacock, Designer
C. Robinson, ASD Engineer
R. Seiter, Engineering Supervisor
B. Shuman, Engineering Programs Manager
S. Tipps, Licensing Supervisor
D. Vineyard, Plant Manager
T. Wells, Principal Engineer
E. Wonn, Senior Designer
F. Zayas, Site Design Supervisor

NRC personnel

E. Morris, Senior Resident Inspector, Hatch
D. Hardage, Resident Inspector, Hatch

LIST OF ITEMS

OPENED AND CLOSED

Opened and Closed

None

LIST OF DOCUMENTS REVIEWED

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