IR 05000327/2014502: Difference between revisions

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IR 05000327/2014502; 05000328/2014502; on 11/17-2014 - 11/21//2014; Sequoyah Nuclear Plant, Unit 1 and 2; Baseline Inspection
ML14353A361
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 12/19/2014
From: Brian Bonser
NRC/RGN-II/DRS/PSB1
To: James Shea
Tennessee Valley Authority
Linda K. Gruhler 404-997-4633
References
IR 2014502
Download: ML14353A361 (11)


Text

December 19, 2014

SUBJECT:

SEQUOYAH NUCLEAR PLANT - U.S. NUCLEAR REGULATORY COMMISSION EMERGENCY PREPAREDNESS INSPECTION REPORT 05000327/2014502 05000328/2014502

Dear Mr. Shea:

On November 21, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Sequoyah Nuclear Plant. The enclosed inspection report (IR) documents the inspection results that were discussed on November 21, 2014, with Mr. Carlin and members of the plant 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.

Based on the results of this inspection, no findings were identified.

In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 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 Documents Access and Management System (ADAMS); accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/

Brian Bonser, Chief

Plant Support Branch 1

Division of Reactor Safety

Docket Nos. 50-327 and 50-328 License Nos. DPR-77 and DPR-79

Enclosure:

IR 05000327 and 328/2014502 w/Attachment: Supplementary Information

REGION II==

Docket Nos:

05000327 and 05000328

License Nos:

DPR-77 and DPR-79

Report Nos:

05000327/2014502 and 05000328/2014502

Licensee:

Tennessee Valley Authority

Facility:

Sequoyah Nuclear Plant, Units 1 and 2

Location:

Soddy Daisy, TN

Dates:

November 17 - 21, 2014

Inspectors:

S. Sanchez, Senior Emergency Preparedness Inspector

M. Speck, Senior Emergency Preparedness Inspector C. Fontana, Emergency Preparedness Inspector J. Graham, Acting Senior Physical Security Inspector

W. Loo, Senior Health Physicist B. Cecere, Emergency Preparedness Specialist

Approved by:

Brian Bonser, Chief Plant Support Branch 1 Division of Reactor Safety

SUMMARY

Inspection Report (IR) 05000327/2014502; 05000328/2014502; 11/17-2014 - 11/21//2014;

Sequoyah Nuclear Plant, Unit 1 and 2; Baseline Inspection

The report covered an announced inspection by three emergency preparedness inspectors, one emergency preparedness specialist, one physical security inspector, and one health physicist.

No findings of significance were identified. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process.

REPORT DETAILS

REACTOR SAFETY

Cornerstone: Emergency Preparedness

1EP4 Emergency Action Level and Emergency Plan Changes

a. Inspection Scope

Since the last NRC inspection of this program area, Revisions 102 and 103 were made to the Radiological Emergency Plan. The licensee determined that, in accordance with 10 CFR 50.54(q), the Plan continued to meet the requirements of 10 CFR 50.47(b) and Appendix E to 10 CFR Part 50. The inspectors reviewed the changes and sampled implementing procedure changes made between October 2013 and November 2014 to evaluate for potential reductions in the effectiveness of the Plan. As this review was not documented in a Safety Evaluation Report (SER), 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 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 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 (EAL) and emergency plan changes on an annual basis.

b. Findings

No findings were identified.

1EP7 Exercise Evaluation - Hostile Action Event

a. Inspection Scope

Title 10 CFR 50, Appendix E, Section IV.F.2.j, requires in part that nuclear power reactor licensees, in each 8-calendar-year exercise cycle, provide the opportunity for their emergency response organization (ERO) to demonstrate proficiency in the key skills necessary to respond to a hostile action (HA) directed at the plant site. The licensee designed the November 19, 2014, exercise to satisfy that requirement, and the NRC inspected the HA event exercise to assess the licensees ability to effectively implement their emergency plan during a HA event, and adequately protect public health and safety.

The exercise evaluation consisted of the following reviews and assessments:

  • The adequacy of the licensees performance in the biennial exercise, conducted on November 19, 2014, was reviewed and assessed regarding the implementation of the Risk-Significant Planning Standards (RSPS) 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 (ERF) with regard to NUREG-0696, Functional Criteria for Emergency Response Facilities, and Emergency Plan commitments. The facilities assessed were the Control Room Simulator, Central Alarm Station (CAS), Incident Command Post (ICP), the Alternate Facility, and the Emergency Operations Facility (EOF), which the licensee refers to as the Central Emergency Control Center (CECC).
  • A review of other performance areas, such as the ERO recognition of abnormal plant conditions; command and control, including interactions with site security staff, intra-and inter-facility communications; prioritization of mitigation activities; utilization of repair and field monitoring teams; interface with offsite agencies, including local law enforcement agencies; staffing and procedure adequacy; and the overall implementation of the emergency plan and its implementing procedures.
  • The adequacy of the licensees post-exercise critiques, to evaluate licensee self-assessment of its ERO performance during the November 19, 2014, exercise to ensure compliance with 10 CFR 50, Appendix E, Subsection IV.F.2.g.

The inspectors reviewed various documents, which are listed in the Attachment. This inspection activity satisfied one inspection sample for the exercise evaluation on a biennial basis.

b. Findings

No findings were identified.

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 valuation 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 July 1, 2013, through September 30, 2014. To verify the accuracy of the PI data reported during that period, PI definitions and guidance contained in Nuclear Energy Institute (NEI) 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 7, was used to confirm the reporting basis for each data element.

Emergency Preparedness Cornerstone

  • Emergency Response Organization Drill/Exercise Performance (DEP)
  • Emergency Response Organization Readiness (ERO)
  • Alert and Notification System Reliability (ANS)

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, Including Exit

On November 21, 2014, the lead inspector presented the inspection results to Mr. Carlin and other members of the plant staff. The inspectors confirmed that no proprietary information was provided during the inspection.

ATTACHMENT:

SUPPLEMENTARY INFORMATION

KEY POINTS OF CONTACT

Licensee personnel

J. Addison, Manager of Emergency Preparedness Drills and Exercises
M. Baker-Lindsay, Sr. Program Manager, Quality Assurance
J. Carlin, Site Vice President
J. Cross, Emergency Preparedness Manager
A. Day, Chemistry Manager
P. Gain, EP Specialist
J. Graves, Security Coordinator
M. Halter, Radiation Protection Manager
E. Henderson, Licensing Manager
W. Lee, Corporate EP Director
A. Little, Manager Nuclear Site Security
M. McBrearty, Corporate Licensing
T. Nixon, Security Coordinator
T. Noe, Director, Plant Support
J. Parshall, Corporate EP Manager
W. Peggram, EP Specialist
J. Perrel, Corporate EP Procedures
W. Pierce, Engineering Director
T. Reiger, Operations Superintendent
S. Schiel, Corporate EP Simulations
P. Simmons, Plant Manager
C. Sneed, Security Coordinator
R. Travis, Licensing Engineer

ITEMS OPENED, CLOSED, DISCUSSED, AND UPDATED

None

LIST OF DOCUMENTS REVIEWED