IR 05000327/2008501: Difference between revisions

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No findings of significance were identified.
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1EP4 Emergency Action Level and Emergency Plan Changes
1EP4 Emergency Action Level and Emergency Plan Changes


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====b. Findings====
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No findings of significance were identified.
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==4OA5 Other Activities==
==4OA5 Other Activities==



Latest revision as of 01:47, 22 December 2019

IR 05000327-08-501 & 05000328-08-501; Tennessee Valley Authority; on 10/13/2008 - 10/17/2008; Sequoyah Nuclear Plant Units 1 and 2, NRC Emergency Preparedness Inspection Report
ML083260004
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 11/21/2008
From: Brian Bonser
NRC/RGN-II/DRS/PSB1
To: Campbell W
Tennessee Valley Authority
References
IR-08-501
Download: ML083260004 (13)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION November 21, 2008

SUBJECT:

SEQUOYAH NUCLEAR PLANT - NRC EMERGENCY PREPAREDNESS INSPECTION REPORT 05000327/2008501 AND 05000328/2008501

Dear Mr. Campbell,

Jr.:

On October 17, 2008, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Sequoyah Nuclear Plant, Units 1 and 2. The enclosed inspection report documents the inspection results, which were discussed on October 16, 2008, with Mr. T. Cleary and other members of his 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 of significance were identified.

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 document system (ADAMS). ADAMS is accessible from the NRC Website 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 No.: 50-327, 50-328 License No.: DPR-77, DPR-79

Enclosure:

Inspection Report 05000327/2008501 and 05000328/2008501 w/Attachment:

Supplemental Information (

REGION II==

Docket Nos.: 05000327, 05000328 License Nos.: DPR-77, DPR-79 Report No.: 05000327/2008501 and 05000328/2008501 Licensee: Tennessee Valley Authority Facility: Sequoyah Nuclear Plant, Units 1 and 2 Location: Soddy-Daisy, TN Dates: October 13, 2008 through October 17, 2008 Inspectors: Lee Miller, Senior Emergency Preparedness Inspector Bob Holbrook, Emergency Preparedness Inspector Rick Baldwin, Senior Operations Engineer Approved by: Brian Bonser, Chief Plant Support Branch 1 Division of Reactor Safety Attachment

SUMMARY OF FINDINGS

IR 05000327/2008-501 and 05000328/2008-501; 10/13/2008 - 10/17/2008; Sequoyah Nuclear

Plant, Units 1 and 2; Emergency Preparedness Baseline Inspection The report covered an announced inspection by two regional emergency preparedness inspectors and an operations engineer. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, AReactor Oversight Process,@ Revision 3, dated July 2000.

NRC-Identified and Self-Revealing Findings

No findings of significance were identified.

Licensee-Identified Violations

.

None.

Attachment

REPORT DETAILS

REACTOR SAFETY

Cornerstone: Emergency Preparedness

1EP1 Exercise Evaluation

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 to determine if the exercise would test major elements of the emergency plan as required by 10 CFR 50.47(b)(14).

This inspection activity represents one sample on a biennial cycle.

The onsite inspection consisted of the following review and assessment:

  • The adequacy of the licensees performance in the biennial exercise conducted on October 15, 2008, was reviewed and assessed regarding the implementation of the Risk Significant Planning Standards (RSPSs) 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 (TSC), Operations Support Center (OSC) and Central Emergency Control Center (CECC).
  • Other performance areas besides the RSPS, 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 16, 2008, to evaluate the licensees self-assessment of its ERO performance during the exercise and to ensure compliance with 10 CFR 50 Appendix E.IV.F.2.g.

The inspectors reviewed various documents which are listed in the Attachment to this report.

b. Findings

No findings of significance were identified.

1EP4 Emergency Action Level and Emergency Plan Changes

a. Inspection Scope

Since the last NRC inspection of this program area, Revisions 87 and 88 of Tennessee Valley Authority Nuclear Radiological Emergency Plan were implemented based on the licensees determination, in accordance with 10 CFR 50.54(q), that the changes resulted in no decrease in the effectiveness of the Plan, and that the revised Plan continued to meet the requirements of 10 CFR 50.47(b) and Appendix E to 10 CFR Part 50. The inspectors conducted a sampling review of the Plan changes and implementing procedure changes made between June 1, 2007 and September 30, 2008 to evaluate for potential decreases in effectiveness of the Plan. However, this review was not documented in a Safety Evaluation Report and does not constitute formal NRC approval of the changes. Therefore, these changes remain subject to future NRC inspection in their entirety.

The inspection was conducted in accordance with NRC Inspection Procedure 71114, 04, AEmergency Action Level and Emergency Plan Changes.@ The applicable planning standard (PS), 10 CFR 50.47(b)

(4) and its related 10 CFR 50, Appendix E requirements 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

No findings of significance were identified.

OTHER ACTIVITIES

4OA1 Performance Indicator Verification

a. Inspection Scope

Cornerstone: Emergency Preparedness

The inspectors sampled licensee submittals for three Performance Indicators (PI) listed below. For each of the submittals reviewed, the inspectors reviewed the period from April 1, 2007 through June 30, 2008. To verify the accuracy of the PI data reported during that period, PI definitions and guidance contained in Nuclear Energy Institute (NEI) 99-02, ARegulatory Assessment Indicator Guideline,@ Revision 5, were used to verify the basis in reporting for each data element.

$ Emergency Response Organization Drill/Exercise Performance (DEP)

$ Emergency Response Organization Readiness (ERO)

$ Alert and Notification System Reliability (ANS)

The inspectors reviewed portions of the raw PI data developed from monthly performance indicator reports and discussed the methods for compiling and reporting the PIs with cognizant emergency preparedness personnel. The inspectors also independently screened drill and exercise opportunity evaluations, drill participation reports, and drill evaluations. Selected reported values were calculated to verify their accuracy. The inspectors compared graphical representations from the most recent PI report to the raw data to verify that the data was correctly reflected in the report.

Reviewed documents are listed in the Attachment to this report.

b. Findings

No findings of significance were identified.

4OA5 Other Activities

.1 (Closed) NRC Temporary Instruction (TI) 2525/175, Emergency Response Organization,

Drill/Exercise Performance Indicator, Program Review The inspectors completed Temporary Instruction TI 2515/175, Emergency Response Organization, Drill/Exercise Performance Indicator, Program Review. Appropriate documentation of the results was provided to NRC, HQ, as required by the TI. This completes the Region II inspection requirements for this TI for Sequoyah Nuclear Power Plant.

4OA6 Meetings, including Exit

On October 16, 2008, the lead inspector presented the inspection results to Mr. T.

Cleary and other members of your staff. The inspectors confirmed that proprietary information was not provided during the inspection.

ATTACHMENT:

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee personnel

T. Cleary, Site Vice President
C. Church, Plant Manager
B. Marks, Corporate Emergency Preparedness Manager
R. Thompson, Emergency Preparedness Manager
R. Proffitt, Licensing Engineer

LIST OF DOCUMENTS REVIEWED