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| number = ML17318A497
| number = ML17318A497
| issue date = 11/09/2017
| issue date = 11/09/2017
| title = Edwin I. Hatch Nuclear Plant - U.S. Nuclear Regulatory Commission Emergency Preparedness Inspection Report 05000321/2017502 and 05000366/2017502
| title = U.S. Nuclear Regulatory Commission Emergency Preparedness Inspection Report 05000321/2017502 and 05000366/2017502
| author name = Guthrie E F
| author name = Guthrie E
| author affiliation = NRC/RGN-II/DRS/EB2
| author affiliation = NRC/RGN-II/DRS/EB2
| addressee name = Vineyard D R
| addressee name = Vineyard D
| addressee affiliation = Southern Nuclear Operating Co, Inc
| addressee affiliation = Southern Nuclear Operating Co, Inc
| docket = 05000321, 05000366
| docket = 05000321, 05000366
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 November 9, 2017  
{{#Wiki_filter:UNITED STATES November 9, 2017


Mr. David Vice President
==SUBJECT:==
 
EDWIN I. HATCH NUCLEAR PLANT - U.S. NUCLEAR REGULATORY COMMISSION EMERGENCY PREPAREDNESS INSPECTION REPORT 05000321/2017502 AND 05000366/2017502
Southern Nuclear Operating Company, Inc.
 
Edwin I. Hatch Nuclear Plant 11028 Hatch Parkway North Baxley, GA 31513
 
SUBJECT: EDWIN I. HATCH NUCLEAR PLANT - U.S. NUCLEAR REGULATORY COMMISSION EMERGENCY PREPAREDNESS INSPECTION REPORT 05000321/2017502 AND 05000366/2017502


==Dear Mr. Vineyard:==
==Dear Mr. Vineyard:==
On October 20, 2017, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Hatch Nuclear Plant. On October 19, 2017, the NRC inspectors discussed the results of this inspection with members of your staff. The results of this inspection are documented in the enclosed report.
On October 20, 2017, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Hatch Nuclear Plant. On October 19, 2017, the NRC inspectors discussed the results of this inspection with members of your staff. The results of this inspection are documented in the enclosed report.


No NRC-identified or self-revealing findings were identified during this inspection. However, inspectors documented a licensee-identified violation which was determined to be of Severity Level IV in this report. The NRC is treating this violation as non-cited violation (NCV) consistent with Section 2.3.2.a of the Enforcement Policy.
No NRC-identified or self-revealing findings were identified during this inspection. However, inspectors documented a licensee-identified violation which was determined to be of Severity Level IV in this report. The NRC is treating this violation as non-cited violation (NCV)
consistent with Section 2.3.2.a of the Enforcement Policy.


This letter, its enclosure, and your response (if any) will be made available for public inspection  
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.


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/
Sincerely,/RA/ Eugene F. Guthrie, Chief Operator Licensing Branch 2 Division of Reactor Safety  
Eugene F. Guthrie, Chief Operator Licensing Branch 2 Division of Reactor Safety Docket Nos. 50-321 and 50-366 License Nos. DPR-57 and NPF-5
 
Docket Nos. 50-321 and 50-366 License Nos. DPR-57 and NPF-5  


===Enclosure:===
===Enclosure:===
NRC IR 05000321, 366/2017502  
NRC IR 05000321, 366/2017502 w/Attachment: Supplemental Information
 
===w/Attachment:===
Supplemental Information  
 
cc: Distribution via Listserve
 
SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII:DRS RII:DRS RII:DRS RII:DRS RII:DRP RII:DRP RII:DRS SIGNATURE SPS JDH9 CAF2 EFG FOR JRP1AMR4 AJB3 EFG* NAME S. SANCHEZ J. HICKMAN C. FONTANA J. PANFEL A. RUH A. BLAMEY E. GUTHRIE DATE 11/8 /2017 11/ 8 /2017 11/8 /2017 11/ 9 /2017 11/ 8 /2017 11/ 9 /2017 *11/9/2017 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION II Docket Nos: 50-321, 50-366
 
License No: DPR-57, NPF-5
 
Report No: 05000321/2017502 and 05000366/2017502


Licensee: Southern Nuclear Operating Company, Inc.
REGION II==
Docket Nos: 50-321, 50-366 License No: DPR-57, NPF-5 Report No: 05000321/2017502 and 05000366/2017502 Licensee: Southern Nuclear Operating Company, Inc.


Facility: Edwin I. Hatch Nuclear Plant  
Facility: Edwin I. Hatch Nuclear Plant Location: Baxley, GA Dates: October 16 - 20, 2017 Inspectors: Steven P. Sanchez, Senior Emergency Preparedness Inspector Christopher A. Fontana, Emergency Preparedness Inspector John D. Hickman, Emergency Preparedness Inspector Adam Ruh, Acting Senior Resident Inspector Jacob Panfel, Health Physicist Approved by: Eugene F. Guthrie, Chief Operator Licensing Branch 2 Division of Reactor Safety Enclosure
 
Location: Baxley, GA  
 
Dates: October 16 - 20, 2017  
 
Inspectors: Steven P. Sanchez, Senior Emergency Preparedness Inspector Christopher A. Fontana, Emergency Preparedness Inspector John D. Hickman, Emergency Preparedness Inspector Adam Ruh, Acting Senior Resident Inspector Jacob Panfel, Health Physicist  
 
Approved by: Eugene F. Guthrie, Chief Operator Licensing Branch 2  
 
Division of Reactor Safety  


=SUMMARY=
=SUMMARY=
Inspection Report (IR) 05000321/2017502 and 05000366/2017502; 10/16/2017 - 10/20/2017;  
Inspection Report (IR) 05000321/2017502 and 05000366/2017502; 10/16/2017 - 10/20/2017;
 
Edwin I. Hatch, Units 1 and 2; Exercise and Baseline Inspection 


This report covers an announced inspection by three emergency preparedness inspectors, one senior resident inspector, and one health physicist. The significance of inspection findings are indicated by their color (i.e., greater than Green, or Green, White, Yellow, Red) and determined using Inspection Manual Chapter (IMC) 0609, "Significance Determination Process," dated April 29, 2015. The U.S. Nuclear Regulatory Commission's (NRC) program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 6.
Edwin I. Hatch, Units 1 and 2; Exercise and Baseline Inspection This report covers an announced inspection by three emergency preparedness inspectors, one senior resident inspector, and one health physicist. The significance of inspection findings are indicated by their color (i.e., greater than Green, or Green, White, Yellow, Red) and determined using Inspection Manual Chapter (IMC) 0609, Significance Determination Process, dated April 29, 2015. The U.S. Nuclear Regulatory Commissions (NRC) program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 6.


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.


One violation of Severity Level IV that was identified by the licensee has been reviewed by the NRC. Corrective action taken or planned by the licensee has been entered into the licensee's corrective action program (CAP). This violation and corrective action tracking number is listed in Section 4OA7 of this report.
One violation of Severity Level IV that was identified by the licensee has been reviewed by the NRC. Corrective action taken or planned by the licensee has been entered into the licensees corrective action program (CAP). This violation and corrective action tracking number is listed in Section 4OA7 of this report.


=REPORT DETAILS=
=REPORT DETAILS=
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==REACTOR SAFETY==
==REACTOR SAFETY==


===Cornerstone:===
===Cornerstone: Emergency Preparedness===
Emergency Preparedness


1EP1 Exercise Evaluation
1EP1 Exercise Evaluation
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====a. Inspection Scope====
====a. Inspection Scope====
The onsite inspection consisted of the following review and assessment:
The onsite inspection consisted of the following review and assessment:
* The adequacy of the licensee's performance in the biennial exercise, conducted on October 17, 2017, was reviewed and assessed regarding the implementation of the Risk Significant Planning Standards in 10 CFR 50.47(b)(4), (5), (9), and (10); which address emergency classification, offsite notification, radiological assessment, and protective action recommendations, respectively.
* The adequacy of the licensees performance in the biennial exercise, conducted on October 17, 2017, was reviewed and assessed regarding the implementation of the Risk Significant Planning Standards in 10 CFR 50.47(b)(4), (5), (9), and (10); which address emergency classification, offsite notification, radiological assessment, and protective action recommendations, respectively.
* The overall adequacy of the licensee's emergency response facilities with regard to NUREG-0696, "Functional Criteria for Emergency Response Facilities," and Emergency Plan commitments. The facilities assessed were the Control Room Simulator, Technical Support Center, Operations Support Center, and the corporate Emergency Operations Facility.
* The overall adequacy of the licensees emergency response facilities with regard to NUREG-0696, Functional Criteria for Emergency Response Facilities, and Emergency Plan commitments. The facilities assessed were the Control Room Simulator, Technical Support Center, Operations Support Center, and the corporate Emergency Operations Facility.
* Other performance areas, such as the emergency response organization's (ERO) recognition of abnormal plant conditions; command and control, intra- and inter- facility communications; prioritization of mitigation activities; utilization of repair and field monitoring teams; interface with offsite agencies; and the overall implementation of the emergency plan and its implementing procedures.
* Other performance areas, such as the emergency response organizations (ERO)recognition of abnormal plant conditions; command and control, intra- and inter-facility communications; prioritization of mitigation activities; utilization of repair and field monitoring teams; interface with offsite agencies; and the overall implementation of the emergency plan and its implementing procedures.
* Past performance issues from NRC inspection reports and Federal Emergency Management Agency (FEMA)/Department of Homeland Security (DHS) exercise reports to determine the effectiveness of corrective actions as demonstrated during this exercise to ensure compliance with 10 CFR 50.47(b)(14).
* Past performance issues from NRC inspection reports and Federal Emergency Management Agency (FEMA)/Department of Homeland Security (DHS) exercise reports to determine the effectiveness of corrective actions as demonstrated during this exercise to ensure compliance with 10 CFR 50.47(b)(14).
* The post-exercise critique process and the presentation to the licensee's senior management conducted on October 19, 2017, to evaluate the licensee's self-assessment of its ERO performance during the exercise, and to ensure compliance with 10 CFR Part 50, Appendix E, Subsection IV.F.2.g.
* The post-exercise critique process and the presentation to the licensee's senior management conducted on October 19, 2017, to evaluate the licensees self-assessment of its ERO performance during the exercise, and to ensure compliance with 10 CFR Part 50, Appendix E, Subsection IV.F.2.g.


The inspectors reviewed various documents, which are listed in the Attachment. The inspectors also attended the FEMA-sponsored public meeting on October 20, 2017.
The inspectors reviewed various documents, which are listed in the Attachment. The inspectors also attended the FEMA-sponsored public meeting on October 20, 2017.
Line 103: Line 74:
====b. Findings====
====b. Findings====
No findings were identified.
No findings were identified.
1EP4 Emergency Action Level and Emergency Plan Changes
1EP4 Emergency Action Level and Emergency Plan Changes


====a. Inspection Scope====
====a. Inspection Scope====
Since the last NRC inspection of this program area, one revision to the emergency plan, one revision to the emergency action levels, and several revisions to emergency plan implementing procedures had been made. The licensee determined that, in accordance with 10 CFR 50.54(q), the emergency plan continued to meet the requirements of 10 CFR 50.47(b), and Appendix E to 10 CFR Part 50. The inspectors reviewed the revisions, and sampled implementing procedure changes to evaluate potential reductions in the effectiveness of the Plan. As this review was not documented in a Safety Evaluation Report, and does not constitute formal NRC approval of the changes, these changes remain subject to futu re NRC inspection in their entirety.
Since the last NRC inspection of this program area, one revision to the emergency plan, one revision to the emergency action levels, and several revisions to emergency plan implementing procedures had been made. The licensee determined that, in accordance with 10 CFR 50.54(q), the emergency plan continued to meet the requirements of 10 CFR 50.47(b), and Appendix E to 10 CFR Part 50. The inspectors reviewed the revisions, and sampled implementing procedure changes to evaluate potential reductions in the effectiveness of the Plan. As this review was not documented in a Safety Evaluation Report, and does not constitute formal NRC approval of the changes, these changes remain subject to future NRC inspection in their entirety.


The inspection was conducted in accordanc e with NRC Inspection Procedure (IP) 71114, Attachment 04, Emergency Action Level and Emergency Plan Changes. The applicable planning standards of 10 CFR 50.47(b), and its related requirements in 10 CFR Part 50, Appendix E, were used as reference criteria. The inspectors reviewed various documents, which are listed in the Attachment to this report. This inspection activity satisfied one inspection sample for the emergency action level and emergency plan changes on an annual basis.
The inspection was conducted in accordance with NRC Inspection Procedure (IP)71114, Attachment 04, Emergency Action Level and Emergency Plan Changes. The applicable planning standards of 10 CFR 50.47(b), and its related requirements in 10 CFR Part 50, Appendix E, were used as reference criteria. The inspectors reviewed various documents, which are listed in the Attachment to this report. This inspection activity satisfied one inspection sample for the emergency action level and emergency plan changes on an annual basis.


====b. Findings====
====b. Findings====
A licensee-identified violation (LIV) is documented in Section 4OA7.
A licensee-identified violation (LIV) is documented in Section 4OA7.
1EP8 Exercise Evaluation - Scenario Review
1EP8 Exercise Evaluation - Scenario Review


====a. Inspection Scope====
====a. Inspection Scope====
Prior to the inspection activity, the inspectors conducted an in-office review of the exercise objectives and scenario submitted to the NRC using IP 71114.08, "Exercise  
Prior to the inspection activity, the inspectors conducted an in-office review of the exercise objectives and scenario submitted to the NRC using IP 71114.08, Exercise Evaluation - Scenario Review, to determine if the exercise would test major elements of the emergency plan as required by 10 CFR 50.47(b)(14). The inspectors reviewed various documents, which are listed in the Attachment to this report. This inspection activity satisfied one inspection sample for the exercise evaluation on a biennial basis.
 
Evaluation - Scenario Review," to determine if the exercise would test major elements of the emergency plan as required by 10 CFR 50.47(b)(14). The inspectors reviewed various documents, which are listed in the Attachment to this report. This inspection activity satisfied one inspection sample for the exercise evaluation on a biennial basis.


====b. Findings====
====b. Findings====
Line 129: Line 96:


====a. Inspection Scope====
====a. Inspection Scope====
The inspectors sampled licensee submittals relative to the performance indicators (PIs) listed below for the period October 1, 2016, through June 30, 2017. To verify the accuracy of the PI data reported during that period, PI definitions and guidance contained in Nuclear Energy Institute 99-02, "Regulatory Assessment Performance Indicator Guideline," Revision 7, was used to confirm the reporting basis for each data element.
The inspectors sampled licensee submittals relative to the performance indicators (PIs)listed below for the period October 1, 2016, through June 30, 2017. To verify the accuracy of the PI data reported during that period, PI definitions and guidance contained in Nuclear Energy Institute 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 7, was used to confirm the reporting basis for each data element.


Emergency Preparedness Cornerstone
Emergency Preparedness Cornerstone
* Drill/Exercise Performance (DEP)
* Drill/Exercise Performance (DEP)
* Emergency Response Organization (ERO) Readiness
* Emergency Response Organization (ERO) Readiness
* Alert and Notification System (ANS) Reliability For the specified review period, the inspectors examined data reported to the NRC, procedural guidance for reporting PI information, and records used by the licensee to identify potential PI occurrences. The inspectors verified the accuracy of the PIs for ERO and DEP through review of a sample of drill and event records. The inspectors reviewed selected training records to verify the accuracy of the PI for ERO drill participation for personnel assigned to key positions in the ERO. The inspectors verified the accuracy of the PI for ANS reliability through review of a sample of the licensee's records of periodic system tests. The inspectors also interviewed the licensee personnel who were responsible for collecting and evaluating the PI data. Licensee procedures, records, and other documents reviewed within this inspection area, are listed in the  
* Alert and Notification System (ANS) Reliability For the specified review period, the inspectors examined data reported to the NRC, procedural guidance for reporting PI information, and records used by the licensee to identify potential PI occurrences. The inspectors verified the accuracy of the PIs for ERO and DEP through review of a sample of drill and event records. The inspectors reviewed selected training records to verify the accuracy of the PI for ERO drill participation for personnel assigned to key positions in the ERO. The inspectors verified the accuracy of the PI for ANS reliability through review of a sample of the licensees records of periodic system tests. The inspectors also interviewed the licensee personnel who were responsible for collecting and evaluating the PI data. Licensee procedures, records, and other documents reviewed within this inspection area, are listed in the
. This inspection satisfied three inspection samples for PI verification on an annual basis.
. This inspection satisfied three inspection samples for PI verification on an annual basis.


====b. Findings====
====b. Findings====
No findings were identified.
No findings were identified.
 
{{a|4OA6}}
{{a|4OA6}}
==4OA6 Meetings==
==4OA6 Meetings==


Line 148: Line 114:
==4OA7 Licensee-Identified Violations==
==4OA7 Licensee-Identified Violations==


The following licensee-identified violation of NRC requirements was determined to be of very low safety significance or Severity Level IV and meet the NRC Enforcement Policy criteria for being dispositioned as a Non-Cited Violation. Because it had the potential for impacting the NRC's ability to perform its regulatory function, traditional enforcement is applicable in accordance with Inspection Manual Chapter 0612, Appendix B. This finding was also determined to be a Severity Level IV violation in accordance with Section 6.6.d.1 of the Enforcement Policy because it involved the licensee's ability to meet or implement a regulatory requirement not related to assessment or notification such that the effectiveness of the emergency plan was reduced. Title 10 of the Code of Federal Regulations, Part 50.54(q) states, in part, that a licensee may make changes to emergency plans without prior NRC approval only if the changes do not reduce the effectiveness of the plans and the plans, as changed, continue to meet the standards of 50.47(b) and the requirements of Appendix E. Proposed changes that reduce the effectiveness of the approved emergency plans may not be implemented without application to and approval by the NRC. Contrary to the above, on multiple occasions between 2008 and 2014, the licensee implemented changes to their Radiological Emergency Plan and Emergency Action Levels (EALs) which reduced the effectiveness of the Plan. Specifically, the licensee deleted and/or changed EAL threshold values, all of which would have resulted in a change that reduced the effectiveness of the approved Emergency Plan and was implemented without application to and approval by the NRC. Because the violation was entered into the licensee's corrective action program as Condition Report 10421212, it is being treated as a Green non-cited licensee-identified SL IV violation consistent with Section 2.3.2 of the Enforcement Policy.
The following licensee-identified violation of NRC requirements was determined to be of very low safety significance or Severity Level IV and meet the NRC Enforcement Policy criteria for being dispositioned as a Non-Cited Violation. Because it had the potential for impacting the NRCs ability to perform its regulatory function, traditional enforcement is applicable in accordance with Inspection Manual Chapter 0612, Appendix B. This finding was also determined to be a Severity Level IV violation in accordance with Section 6.6.d.1 of the Enforcement Policy because it involved the licensees ability to meet or implement a regulatory requirement not related to assessment or notification such that the effectiveness of the emergency plan was reduced. Title 10 of the Code of Federal Regulations, Part 50.54(q) states, in part, that a licensee may make changes to emergency plans without prior NRC approval only if the changes do not reduce the effectiveness of the plans and the plans, as changed, continue to meet the standards of 50.47(b) and the requirements of Appendix E. Proposed changes that reduce the effectiveness of the approved emergency plans may not be implemented without application to and approval by the NRC. Contrary to the above, on multiple occasions between 2008 and 2014, the licensee implemented changes to their Radiological Emergency Plan and Emergency Action Levels (EALs) which reduced the effectiveness of the Plan. Specifically, the licensee deleted and/or changed EAL threshold values, all of which would have resulted in a change that reduced the effectiveness of the approved Emergency Plan and was implemented without application to and approval by the NRC.


ATTACHMENT:
Because the violation was entered into the licensees corrective action program as Condition Report 10421212, it is being treated as a Green non-cited licensee-identified SL IV violation consistent with Section 2.3.2 of the Enforcement Policy.
 
ATTACHMENT:  


=SUPPLEMENTAL INFORMATION=
=SUPPLEMENTAL INFORMATION=
Line 157: Line 125:


===Licensee personnel===
===Licensee personnel===
: [[contact::H. Betsill]], Emergency Preparedness Specialist  
: [[contact::H. Betsill]], Emergency Preparedness Specialist
: [[contact::G. Brinson]], Maintenance Director  
: [[contact::G. Brinson]], Maintenance Director
: [[contact::J. Calhoun]], Fleet Drill & Exercise Coordinator  
: [[contact::J. Calhoun]], Fleet Drill & Exercise Coordinator
: [[contact::R. Collings]], Fleet Emergency Preparedness  
: [[contact::R. Collings]], Fleet Emergency Preparedness
: [[contact::C. Collins]], Licensing Supervisor  
: [[contact::C. Collins]], Licensing Supervisor
: [[contact::C. Cornelius]], Emergency Preparedness Specialist  
: [[contact::C. Cornelius]], Emergency Preparedness Specialist
: [[contact::J. Henry]], Operations Director  
: [[contact::J. Henry]], Operations Director
: [[contact::B. Hulett]], Engineering Director  
: [[contact::B. Hulett]], Engineering Director
: [[contact::G. Johnson]], Regulatory Affairs Director  
: [[contact::G. Johnson]], Regulatory Affairs Director
: [[contact::R. Johnson]], Work Management Director  
: [[contact::R. Johnson]], Work Management Director
: [[contact::S. Lee]], Radiation Protection Support Supervisor  
: [[contact::S. Lee]], Radiation Protection Support Supervisor
: [[contact::K. Long]], Site Projects Manager  
: [[contact::K. Long]], Site Projects Manager
: [[contact::L. Mansfield]], Fleet Emergency Preparedness Director  
: [[contact::L. Mansfield]], Fleet Emergency Preparedness Director
: [[contact::J. Merritt]], Security Manager  
: [[contact::J. Merritt]], Security Manager
: [[contact::D. Moore]], Emergency Preparedness Specialist  
: [[contact::D. Moore]], Emergency Preparedness Specialist
: [[contact::A. Morgan]], Chemistry Manager  
: [[contact::A. Morgan]], Chemistry Manager
: [[contact::R. Reddick]], Emergency Preparedness Supervisor  
: [[contact::R. Reddick]], Emergency Preparedness Supervisor
: [[contact::R. Spring]], Plant Manager  
: [[contact::R. Spring]], Plant Manager
: [[contact::C. Edmond]], Acting Nuclear Oversight Manager  
: [[contact::C. Edmond]], Acting Nuclear Oversight Manager
: [[contact::C. Vonier]], Engineering Plant Support Manager K, Wainwright, Operations Training Manager  
: [[contact::C. Vonier]], Engineering Plant Support Manager
: [[contact::J. Willis]], Assistant Plant Manager  
K, Wainwright, Operations Training Manager
: [[contact::J. Willis]], Assistant Plant Manager


==LIST OF DOCUMENTS REVIEWED==
==LIST OF DOCUMENTS REVIEWED==
1EP1 Exercise Evaluation 
===Procedures===
: NMP-EP-140, Accident Assessment, Ver. 1.0
: NMP-EP-140-002-F01, Hatch Core Damage Assessment, Ver. 1.1
: NMP-EP-141, Event Classification, Ver. 1.0
: NMP-EP-141-002, Hatch Emergency Action Levels & Basis (NEI 99-01 Rev.6), Ver. 2.0
: NMP-EP-141-F01, Emergency Classification Determination, Ver. 1.0
: NMP-EP-141-002-F02, Cold Initiating Conditions Evaluation, Ver. 1.0
: NMP-EP-142, Emergency Notification, Ver. 1.0
: NMP-EP-142-F01, Emergency Notification Form (ENF), Ver. 1.0
: NMP-EP-142-F02, Emergency Notification Instructions, Ver. 1.0
: NMP-EP-142-F04, Plant Hatch Emergency Notification Agency Listing, Ver. 1.0
: NMP-EP-143, Facility Activation, Ver. 1.0
: NMP-EP-144, Protective Action Recommendations, Ver. 1.0
: NMP-EP-145, Termination and Recovery, Ver. 1.0
: NMP-EP-146, Emergency Response Organization, Ver. 1.0
: NMP-EP-146-F10 EOF ENN Communicator, Ver. 1.0, p.1
: NMP-EP-146-F12, EOF ERF Communicator, Ver. 1.0, p. 1
: NMP-EP-146-F13, EOF Field Team Communicator, Ver. 1.0, p. 1
: NMP-EP-146-F14, EOF Field Team Coordinator, Ver. 1.0, p.p. 1-2
: NMP-EP-146-F24, EOF Technical Supervisor, Ver. 1.0, pp. 1-2
: NMP-EP-147, Offsite Dose Assessment, Ver. 2.0
: NMP-EP-147-001, SNC Field Monitoring Teams Radiological Surveys and Sampling, Ver. 1.0
: NMP-EP-147-001, GL02, SNC Field Monito ring Teams operation of FMT communication devices, Ver. 1.0
: NMP-EP-147-003, Hatch Units 1 and 2 MI
: DAS-NU Dose Projections, Ver. 1.0
: NMP-EP-147-F05, Offsite Dose Assessment Hatch Safety Parameter Display System (SPDS),    data entry records, Ver. 1.0
: NMP-EP-147-F08, Offsite Dose Assessment Alternate Meteorology Data Services, Ver. 1.0
: NMP-EP-303, Drill and Exercise Standards, Ver. 17.0
: NMP-GM-002-001, Corrective Action Program Instructions, Ver. 36.0 Southern Nuclear Operating Company (SNC) Standard Emergency Plan (SEP), Ver. 1.0 SNC Standard Emergency Plan Annex for Hatch Nuclear Plant (HNP) Units 1 & 2, Ver. 1.0
: Records and Data Plant Hatch Emergency Preparedness, 2017 Evaluated Exercise, 10/17/2017, Exercise 
: Controller Book Simulator Control Room, Technical Support Center, Operations Support Center, and the Emergency Operations Facility Documentation packages (logs, event notification forms, Protective Action Recommendations, Media releases, and Radiological Dose Assessments)
: Corrective Action Program Documents (Condition Reports)
: CR 10348137, TSC Low Differential Pressure Alarms
: CR 10387634, Toombs County ENN Inoperable
: CR 10402509, Loss of NRC phone line in the Control Room
: CR 10420563, Offsite Dose assessment issues
: CR 10420844, HPN Exercise PAR accuracy failure
: CR 10420845, HNP Exercise Alert notification was not timely
: CR 10421255, HNP Exercise ENS Notification to NRC was not timely
==1EP4 Emergency Action Level and Emergency Plan Changes==
===Procedures===
: Edwin I. Hatch Nuclear Plant Unit 1 & 2 Emergency Plan, Ver. 39
: NMP-EP-141-002, Hatch Emergency Action Levels & Basis (NEI 99-01 Rev.6), Ver. 2.0
: NMP-EP-142, Emergency Notification, Ver. 1.0
: NMP-EP-143, Facility Activation, Ver. 1.0
: NMP-EP-144, Protective Action Recommendations, Ver. 1.0
: NMP-EP-147, Offsite Dose Assessment, Ver. 2.0
: NMP-EP-312, Development of Emergency Preparedness Technical Products, Ver. 1.0
: Southern Nuclear Operating Company (SNC) Standard Emergency Plan (SEP), Ver. 1.0
: SNC Standard Emergency Plan Annex for Hatch Nuclear Plant (HNP) Units 1 & 2, Ver. 1.0
: Change Packages
: FLT-17-005-01, 10
: CFR 50.54(q) Screening/Evaluation for
: NMP-EP-142, Emergency Notifications, Ver. 1.0, dated 6/27/17
: FLT-17-006-01, 10
: CFR 50.54(q) Screening/Evaluation for
: NMP-EP-143, Facility Activations, Ver. 1.0, dated 6/27/17
: FLT-17-007-01, 10
: CFR 50.54(q) Screening/Evaluation for
: NMP-EP-144, Protective Actions,
: Ver. 1.0, dated 6/27/17
: FLT-17-017-01, 10
: CFR 50.54(q) Screening/Evaluation for
: NMP-EP-147, Offsite Dose
: Assessment, Ver. 2.0, dated 7/14/17
: HNP-15-003-02, 10
: CFR 50.54(q) Screening/Evaluation for SNC SEP, HNP Unit 1 & 2 Annex, &
: HNP Unit 1 & 2 Justification Matrix, Ver. 1.0, dated 8/17/15
: HNP-17-005-01, 10
: CFR 50.54(q) Screening/Evaluation for
: NMP-EP-141-002, Hatch Emergency Action Levels & Basis Ver. 2.0, date 10/04/17
: Corrective Action Program Documents
: CR 10340703, Hatch EAL review
: CR 10355799,
: NMP-EP-104, Ver. 9.0 procedural guidance is inadequate
: CR 10403331, Change Request to
: NMP-EP-144-F01 PAR Worksheet
: CR 10421212, 10
: CFR 50.54(q) Evaluations for EAL did not identify a reduction in effectiveness
==1EP8 Exercise Evaluation==
===Procedures===
: NMP-EP-303, Drill and Exercise Standards, Ver. 17.0
: Southern Nuclear Operating Company (SNC) Standard Emergency Plan (SEP), Ver. 1.0
: SNC Standard Emergency Plan Annex for Hatch Nuclear Plant (HNP) Units 1 & 2, Ver. 1.0
: Records and Data FEMA Final After Action Report, Edwin I. Hatch Nuclear Plant Radiological Emergency Preparedness Exercise, Exercise Date: December 9, 2015, dated 5/23/16
: Hatch Emergency Preparedness Drill Report 16EX01, dated 6/29/16
: Hatch Emergency Preparedness Drill Report 16EX02, dated 11/6/16 Hatch Emergency Preparedness Drill Report 17EX01, dated 4/27/17 Hatch Emergency Preparedness Drill Report 17EX02, dated 5/24/17
: Hatch 8 Year Tracking Matrix, dated 5/23/17
: Plant Hatch Emergency Preparedness, 2017 Evaluated Exercise, 10/17/2017, Exercise 
: Controller Book 2016 Plant Hatch Post Accident Sampling System Drill Report, dated 12/12/16 2016 Plant Hatch Medical Drill Report, dated 12/12/16
: Corrective Action Program Documents
: CR 10285811, Emergency Drill 16EX02- 3 OSC phones inoperable
: CR 10287377, 16EX02 Drill Objective Failure
: CR 10287380, 16EX02 OSC Drill Objective Failure
: CR 10387634, Toombs County ENN inoperable
==4OA1 Performance Indicator Verification==


===Procedures===
: NMP-EP-311, SNC Emergency Preparedness Tier 4 Performance Indicators, Ver. 3.0 Southern Nuclear Operating Company (SNC) Standard Emergency Plan (SEP), Ver. 1.0
: SNC Standard Emergency Plan Annex for Hatch Nuclear Plant (HNP) Units 1 & 2, Ver. 1.0
: Records and Data DEP opportunities documentation for Fourth quarter 2016; and First and Second quarters 2017
: Siren test data for Fourth quarter 2016; and First and Second quarters 2017
: Drill and exercise participation records of ERO personnel for Fourth quarter 2016; and First and Second quarters 2017 
: Corrective Action Program Documents
: CR 10321516, Appling Siren Station storm damage
: CR 10343233, Siren 77 has a partial activation
: CR 10351351, DEP Failure per
: NMP-TR-100
: CR 10351773, Siren 2 has a communication failure
: CR 10365343, ERO pager did not receive weekly meeting reminder
: CR 10366339, EP PI data for March was entered incorrectly
: CR 10367198, Potential issue with new ERO qualification effective July 1
: CR 10380685, ERO key position change status notification
: CR 10382654, Need to consider modifying requirement to be at weekly ERO muster meeting
: CR 10401708, DEP failure not coded for crew clock reset
==LIST OF ACRONYMS==
: [[USED]] [[]]
: [[ANS]] [[Alert and Notification System]]
: [[DEP]] [[Drill and Exercise Performance]]
: [[DHS]] [[Department of Homeland Security]]
: [[EAL]] [[Emergency Action Level]]
: [[EOF]] [[Emergency Operations Facility]]
: [[EP]] [[Emergency Preparedness E-Plan  Emergency Plan]]
: [[ERO]] [[Emergency Response Organization]]
: [[FEMA]] [[Federal Emergency Management Agency]]
: [[IP]] [[Inspection Procedure]]
: [[NEI]] [[Nuclear Energy Institute]]
: [[OSC]] [[Operations Support Center]]
: [[PI]] [[Performance Indicators]]
: [[TSC]] [[Technical Support Center]]
}}
}}

Latest revision as of 07:52, 19 December 2019

U.S. Nuclear Regulatory Commission Emergency Preparedness Inspection Report 05000321/2017502 and 05000366/2017502
ML17318A497
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 11/09/2017
From: Eugene Guthrie
NRC/RGN-II/DRS/EB2
To: Vineyard D
Southern Nuclear Operating Co
References
IR 2017502
Download: ML17318A497 (15)
v • d • e


Text

UNITED STATES November 9, 2017

SUBJECT:

EDWIN I. HATCH NUCLEAR PLANT - U.S. NUCLEAR REGULATORY COMMISSION EMERGENCY PREPAREDNESS INSPECTION REPORT 05000321/2017502 AND 05000366/2017502

Dear Mr. Vineyard:

On October 20, 2017, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Hatch Nuclear Plant. On October 19, 2017, the NRC inspectors discussed the results of this inspection with members of your staff. The results of this inspection are documented in the enclosed report.

No NRC-identified or self-revealing findings were identified during this inspection. However, inspectors documented a licensee-identified violation which was determined to be of Severity Level IV in this report. The NRC is treating this violation as non-cited violation (NCV)

consistent with Section 2.3.2.a of the Enforcement Policy.

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/

Eugene F. Guthrie, Chief Operator Licensing Branch 2 Division of Reactor Safety Docket Nos. 50-321 and 50-366 License Nos. DPR-57 and NPF-5

Enclosure:

NRC IR 05000321, 366/2017502 w/Attachment: Supplemental Information

REGION II==

Docket Nos: 50-321, 50-366 License No: DPR-57, NPF-5 Report No: 05000321/2017502 and 05000366/2017502 Licensee: Southern Nuclear Operating Company, Inc.

Facility: Edwin I. Hatch Nuclear Plant Location: Baxley, GA Dates: October 16 - 20, 2017 Inspectors: Steven P. Sanchez, Senior Emergency Preparedness Inspector Christopher A. Fontana, Emergency Preparedness Inspector John D. Hickman, Emergency Preparedness Inspector Adam Ruh, Acting Senior Resident Inspector Jacob Panfel, Health Physicist Approved by: Eugene F. Guthrie, Chief Operator Licensing Branch 2 Division of Reactor Safety Enclosure

SUMMARY

Inspection Report (IR) 05000321/2017502 and 05000366/2017502; 10/16/2017 - 10/20/2017;

Edwin I. Hatch, Units 1 and 2; Exercise and Baseline Inspection This report covers an announced inspection by three emergency preparedness inspectors, one senior resident inspector, and one health physicist. The significance of inspection findings are indicated by their color (i.e., greater than Green, or Green, White, Yellow, Red) and determined using Inspection Manual Chapter (IMC) 0609, Significance Determination Process, dated April 29, 2015. The U.S. Nuclear Regulatory Commissions (NRC) program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 6.

The NRC inspectors did not identify any findings or violations of more than minor significance.

One violation of Severity Level IV that was identified by the licensee has been reviewed by the NRC. Corrective action taken or planned by the licensee has been entered into the licensees corrective action program (CAP). This violation and corrective action tracking number is listed in Section 4OA7 of this report.

REPORT DETAILS

REACTOR SAFETY

Cornerstone: Emergency Preparedness

1EP1 Exercise Evaluation

a. Inspection Scope

The onsite inspection consisted of the following review and assessment:

  • The adequacy of the licensees performance in the biennial exercise, conducted on October 17, 2017, was reviewed and assessed regarding the implementation of the Risk Significant Planning Standards in 10 CFR 50.47(b)(4), (5), (9), and (10); which address emergency classification, offsite notification, radiological assessment, and protective action recommendations, respectively.
  • The overall adequacy of the licensees emergency response facilities with regard to NUREG-0696, Functional Criteria for Emergency Response Facilities, and Emergency Plan commitments. The facilities assessed were the Control Room Simulator, Technical Support Center, Operations Support Center, and the corporate Emergency Operations Facility.
  • Other performance areas, such as the emergency response organizations (ERO)recognition of abnormal plant conditions; command and control, intra- and inter-facility communications; prioritization of mitigation activities; utilization of repair and field monitoring teams; interface with offsite agencies; and the overall implementation of the emergency plan and its implementing procedures.
  • The post-exercise critique process and the presentation to the licensee's senior management conducted on October 19, 2017, to evaluate the licensees self-assessment of its ERO performance during the exercise, and to ensure compliance with 10 CFR Part 50, Appendix E, Subsection IV.F.2.g.

The inspectors reviewed various documents, which are listed in the Attachment. The inspectors also attended the FEMA-sponsored public meeting on October 20, 2017.

This inspection activity satisfied one inspection sample for the exercise evaluation on a biennial basis.

b. Findings

No findings were identified.

1EP4 Emergency Action Level and Emergency Plan Changes

a. Inspection Scope

Since the last NRC inspection of this program area, one revision to the emergency plan, one revision to the emergency action levels, and several revisions to emergency plan implementing procedures had been made. The licensee determined that, in accordance with 10 CFR 50.54(q), the emergency plan continued to meet the requirements of 10 CFR 50.47(b), and Appendix E to 10 CFR Part 50. The inspectors reviewed the revisions, and sampled implementing procedure changes to evaluate potential reductions in the effectiveness of the Plan. As this review was not documented in a Safety Evaluation Report, and does not constitute formal NRC approval of the changes, these changes remain subject to future NRC inspection in their entirety.

The inspection was conducted in accordance with NRC Inspection Procedure (IP)71114, Attachment 04, Emergency Action Level and Emergency Plan Changes. The applicable planning standards of 10 CFR 50.47(b), and its related requirements in 10 CFR Part 50, Appendix E, were used as reference criteria. The inspectors reviewed various documents, which are listed in the Attachment to this report. This inspection activity satisfied one inspection sample for the emergency action level and emergency plan changes on an annual basis.

b. Findings

A licensee-identified violation (LIV) is documented in Section 4OA7.

1EP8 Exercise Evaluation - Scenario Review

a. Inspection Scope

Prior to the inspection activity, the inspectors conducted an in-office review of the exercise objectives and scenario submitted to the NRC using IP 71114.08, Exercise Evaluation - Scenario Review, to determine if the exercise would test major elements of the emergency plan as required by 10 CFR 50.47(b)(14). The inspectors reviewed various documents, which are listed in the Attachment to this report. This inspection activity satisfied one inspection sample for the exercise evaluation on a biennial basis.

b. Findings

No findings were identified.

OTHER ACTIVITIES

4OA1 Performance Indicator Verification

a. Inspection Scope

The inspectors sampled licensee submittals relative to the performance indicators (PIs)listed below for the period October 1, 2016, through June 30, 2017. To verify the accuracy of the PI data reported during that period, PI definitions and guidance contained in Nuclear Energy Institute 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 7, was used to confirm the reporting basis for each data element.

Emergency Preparedness Cornerstone

  • Drill/Exercise Performance (DEP)
  • Emergency Response Organization (ERO) Readiness
  • Alert and Notification System (ANS) Reliability For the specified review period, the inspectors examined data reported to the NRC, procedural guidance for reporting PI information, and records used by the licensee to identify potential PI occurrences. The inspectors verified the accuracy of the PIs for ERO and DEP through review of a sample of drill and event records. The inspectors reviewed selected training records to verify the accuracy of the PI for ERO drill participation for personnel assigned to key positions in the ERO. The inspectors verified the accuracy of the PI for ANS reliability through review of a sample of the licensees records of periodic system tests. The inspectors also interviewed the licensee personnel who were responsible for collecting and evaluating the PI data. Licensee procedures, records, and other documents reviewed within this inspection area, are listed in the

. This inspection satisfied three inspection samples for PI verification on an annual basis.

b. Findings

No findings were identified.

4OA6 Meetings

On October 19, 2017, the inspection team presented the inspection results to Mr. T. Spring and other members of the plant staff. The inspectors confirmed that no proprietary information was provided during the inspection.

4OA7 Licensee-Identified Violations

The following licensee-identified violation of NRC requirements was determined to be of very low safety significance or Severity Level IV and meet the NRC Enforcement Policy criteria for being dispositioned as a Non-Cited Violation. Because it had the potential for impacting the NRCs ability to perform its regulatory function, traditional enforcement is applicable in accordance with Inspection Manual Chapter 0612, Appendix B. This finding was also determined to be a Severity Level IV violation in accordance with Section 6.6.d.1 of the Enforcement Policy because it involved the licensees ability to meet or implement a regulatory requirement not related to assessment or notification such that the effectiveness of the emergency plan was reduced. Title 10 of the Code of Federal Regulations, Part 50.54(q) states, in part, that a licensee may make changes to emergency plans without prior NRC approval only if the changes do not reduce the effectiveness of the plans and the plans, as changed, continue to meet the standards of 50.47(b) and the requirements of Appendix E. Proposed changes that reduce the effectiveness of the approved emergency plans may not be implemented without application to and approval by the NRC. Contrary to the above, on multiple occasions between 2008 and 2014, the licensee implemented changes to their Radiological Emergency Plan and Emergency Action Levels (EALs) which reduced the effectiveness of the Plan. Specifically, the licensee deleted and/or changed EAL threshold values, all of which would have resulted in a change that reduced the effectiveness of the approved Emergency Plan and was implemented without application to and approval by the NRC.

Because the violation was entered into the licensees corrective action program as Condition Report 10421212, it is being treated as a Green non-cited licensee-identified SL IV violation consistent with Section 2.3.2 of the Enforcement Policy.

ATTACHMENT:

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee personnel

H. Betsill, Emergency Preparedness Specialist
G. Brinson, Maintenance Director
J. Calhoun, Fleet Drill & Exercise Coordinator
R. Collings, Fleet Emergency Preparedness
C. Collins, Licensing Supervisor
C. Cornelius, Emergency Preparedness Specialist
J. Henry, Operations Director
B. Hulett, Engineering Director
G. Johnson, Regulatory Affairs Director
R. Johnson, Work Management Director
S. Lee, Radiation Protection Support Supervisor
K. Long, Site Projects Manager
L. Mansfield, Fleet Emergency Preparedness Director
J. Merritt, Security Manager
D. Moore, Emergency Preparedness Specialist
A. Morgan, Chemistry Manager
R. Reddick, Emergency Preparedness Supervisor
R. Spring, Plant Manager
C. Edmond, Acting Nuclear Oversight Manager
C. Vonier, Engineering Plant Support Manager

K, Wainwright, Operations Training Manager

J. Willis, Assistant Plant Manager

LIST OF DOCUMENTS REVIEWED

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