IR 05000327/2017010
| ML17108A583 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/18/2017 |
| From: | McKenna P J Reactor Projects Branch 7 |
| To: | Shea J W Tennessee Valley Authority |
| References | |
| IR 2017010 | |
| Download: ML17108A583 (13) | |
Text
April 18, 2017
Mr. Joseph Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 3R-C Chattanooga, TN 37402-2801
SUBJECT: SEQUOYAH NUCLEAR PLANT - NRC TEAM INSPECTION REPORT 05000327/2017010 AND 05000328/2017010
Dear Mr. Shea:
On March 9, 2017, the U. S. Nuclear Regulatory Commission (NRC) completed an inspection at your Sequoyah Nuclear Power Plant Units 1 and 2. The enclosed report documents the inspection results, which were discussed on March 9, 2017, with Mr. G. Boerschig and other members of your staff. A re-exit was conducted with Mr. Z. Kitts via telephone on April 12, 2017, to discuss the final results of the inspection. The results of this inspection are documented in the enclosed report.
The inspection examined activities conducted under your license as they relate to the implementation of mitigation strategies and spent fuel pool instrumentation orders (EA-12-049 and EA-12-051) and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans, your compliance with the Commission's rules and regulations, and with the conditions of your operating license. Within these areas, the inspection involved examination of selected procedures and records, observation of activities, and interviews with station personnel.
No NRC-identified or self-revealing 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 and its enclosure will be available electronically for public inspection in the NRC's Public Document Room or from the Publicly Available Records (PARS) component of the NRC's document 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/
Philip J. McKenna, Acting Chief Reactor Projects Branch 7 Division of Reactor Projects Docket Nos. 05000327, 05000328 License Nos. DPR-77, DPR-79
Enclosure:
IR 05000327/2017010 and 05000328/2017010
w/Attachment:
Supplemental Information
cc Distribution via ListServ
ML17108A583 OFFICE RII:DRP RII:DRP RII:DRP RII:DRP RII:DRP NAME RRodriguez RTaylor WDeschaine ABlamey PMcKenna DATE 4/14/2017 4/14/2017 4/13/2017 4/17/2017 4/17/2017 Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION II Docket No.: 50-327, 50-328 License No.: DPR-77, DPR-79 Report No.: 05000327/2017010, 05000328/2017010 Licensee: Tennessee Valley Authority (TVA)
Facility: Sequoyah Nuclear Plant, Units 1 and 2 Location: Sequoyah Access Road Soddy-Daisy, TN 37379 Dates: March 6 - 9, 2017 Inspectors: R. Rodriguez, Senior Project Engineer (Team Leader)
W. Deschaine, Resident Inspector, Sequoyah R. Taylor, Senior Project Inspector Approved by: Philip McKenna, Acting Chief Reactor Projects Branch 7 Division of Reactor Projects
SUMMARY
IR 05000327/2017010, 05000328/2017010; 3/6/2017 - 3/9/2017; Sequoyah Nuclear Power Plant Units 1 and 2; Temporary Instruction 2515/191, Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency
Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans issued December 23, 2015.
The inspection covered a one-week inspection by one senior project engineer, one senior project inspector, and one resident inspector. No NRC-identified or self-revealing findings were identified. The Nuclear Regulatory Commission's (NRC's) program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 5.
A. NRC-Identified and Self-Revealing Findings
None
B. Licensee-Identified Violations
None
REPORT DETAILS
4. Other Activities
4OA5 Other Activities (TI 2515/191)
The objective of Temporary Instruction (TI) 2015/191, "Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans," is to verify that licensees have adequately implemented the mitigation strategies as described in the licensee's Final Integrated Plan, dated August 8, 2016, and the Nuclear Regulatory Commission's (NRC's) plant safety evaluation (ADAMS Accession No. ML16270A517) and to verify that the licensees installed reliable water-level measurement instrumentation in their spent fuel pools. The purpose of this TI is also to verify the licensees have implemented Emergency Preparedness (EP) enhancements as described in their site-specific submittals and NRC safety assessments, including multi-unit dose assessment capability and enhancements to ensure that staffing is sufficient and communications can be maintained during such an event.
The inspection verifies that plans for complying with NRC Orders EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (ADAMS Accession No. ML12054A736) and EA-12-051, Order Modifying Licenses With Regard to Reliable Spent Fuel Pool Instrumentation (ADAMS Accession No. ML12054A679) are in place and are being implemented by the licensee. Additionally, the inspection verifies implementation of staffing and communications information provided in response to the March 12, 2012, request for information letter and multiunit dose assessment information provided per COMSECY-13-0010, Schedule and Plans for Tier 2 Order on Emergency Preparedness for Japan Lessons Learned, dated March 27, 2013, (ADAMS Accession No.
ML12339A262). The team discussed the plans and strategies with plant staff, reviewed documentation, and where appropriate, performed plant walkdowns to verify that the strategies could be implemented as stated in the licensee's submittals and the NRC staff prepared safety evaluation. For most strategies, this included verification that the strategy was feasible, procedures and/or guidance had been developed, training had been provided to plant staff, and required equipment had been identified and staged. Specific details of the team's inspection activities are described in the following sections.
1. Mitigation Strategies for Beyond-Design Basis External Events
a. Inspection Scope
The team examined the licensee's established guidelines and implementing procedures for the beyond-design basis mitigation strategies. The team assessed how the licensee coordinated and documented the interface/transition between existing off-normal and emergency operating procedures with the newly developed mitigation strategies. The team selected a number of mitigation strategies and conducted plant walk downs with licensed operators and responsible plant staff to assess: The adequacy and completeness of the procedures; familiarity of operators with the procedure objectives and specific guidance; staging and compatibility of equipment; and the practicality of the operator actions prescribed by the procedures, consistent with the postulated scenarios. The team verified that a preventive maintenance program had been established for the Diverse and Flexible Coping Strategies (FLEX) portable equipment and that periodic equipment inventories were in place and being conducted. Additionally, the team examined the introductory and planned periodic/refresher training provided to the Operations and Security staff most likely to be tasked with implementation of the FLEX mitigation strategies. The team also reviewed the introductory and planned periodic training provided to the Emergency Response Organization personnel. Documents reviewed are listed in the attachment. b. Assessment Based on samples selected for review, the inspectors verified that the licensee satisfactorily implemented appropriate elements of the FLEX strategy as described in the plant-specific submittals and the associated safety evaluation and determined that the licensee was generally in compliance with NRC Order EA-12-049. The inspectors verified that the licensee satisfactorily:
- developed and issued FLEX Support Guidelines (FSG) to implement the FLEX strategies for postulated external events.
- integrated the FSGs into existing plant procedures such that entry into and departure from the FSGs were clear when using existing plant procedures.
- protected FLEX equipment from site-specific hazards.
- developed and implemented adequate testing and maintenance of FLEX equipment to ensure its availability and capability.
- trained the staff to ensure personnel proficiency in the mitigation of beyond-design- basis events.
- developed means to ensure that the necessary off-site FLEX equipment would be available from off-site locations.
The inspectors verified that noncompliance with the current licensing requirements, and other issues identified during the inspection, were entered into the licensee's corrective action program.
c. Findings
No findings identified.
2. Spent Fuel Pool Instrumentation
a. Inspection Scope
The team examined the licensee's newly installed spent fuel pool instrumentation.
Specifically, the inspectors verified the sensors were installed as described in the plant-specific submittals and the associated safety evaluation and that the cabling for the power supplies and the indications for each channel are physically and electrically separated. Additionally, environmental conditions and accessibility of the instruments were evaluated. Documents reviewed are listed in the attachment.
b. Assessment Based on samples selected for review, the inspectors determined that the licensee satisfactorily installed and established control of the spent fuel pool (SFP) instrumentation as described in the plant-specific submittals and the associated safety evaluation and determined that the licensee is generally in compliance with NRC Order EA-12-051. The inspectors verified that the licensee satisfactorily:
- installed the SFP instrumentation sensors, cabling and power supplies to provide physical and electrical separation as described in the plant-specific submittals and safety evaluation.
- installed the SFP instrumentation display in the location, environmental conditions and accessibility as described in the plant-specific submittals.
- trained their staff to assure personnel proficiency with the maintenance, testing, and use of the SFP instrumentation.
- developed and issued procedures for maintenance, testing, and use of the reliable SFP instrumentation.
The inspectors verified that noncompliance with the current licensing requirements, and other issues identified during the inspection, were entered into the licensee's corrective action program.
c. Findings
No findings identified. 3. Staffing and Communication Request for Information
a. Inspection Scope
Through discussions with plant staff, review of documentation and plant walkdowns, the team verified that the licensee had implemented required changes to staffing, communications equipment and facilities to support a multi-unit extended loss of offsite power scenario as described in the licensee's staffing assessment and the NRC safety assessment. The team also verified that the licensee had implemented dose assessment (including releases from spent fuel pools) capability using the licensee's site-specific dose assessment software and approach as described in the licensee's multi-unit dose assessment submittal. Documents reviewed are listed in the attachment. b. Assessment The inspectors reviewed information provided in the licensee's multi-unit dose submittal and in response to the NRC's March 12, 2012, request for information letter and verified that the licensee satisfactorily implemented enhancements pertaining to Near-Term Task Force Recommendation 9.3 response to a large scale natural emergency event that results in an extended loss of all alternating current power (ELAP) to the site and impedes access to the site. The inspectors verified the following:
- Licensee satisfactorily implemented required staffing change(s) to support an ELAP scenario.
- Implemented dose assessment capabilities (including releases from spent fuel pools) using the licensee's site-specific dose assessment software and approach.
The inspectors verified that noncompliance with the current licensing requirements, and other issues identified during the inspection, were entered into the licensee's corrective action program.
c. Findings
No findings identified.
4OA6 Exit
Exit Meeting Summary
On March 9, 2017, the inspectors presented the inspection results to Mr. G. Boerschig and other members of the site staff. A re-exit was conducted with Mr. Z. Kitts via telephone on April 12, 2017, to discuss the final results of the inspection. The inspectors confirmed that proprietary information was not provided or examined during the inspection. ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee personnel
- G. Boerschig, Site Vice President
- B. Lacey, Corporate Engineering Programs
- R. Thompson, Corporate Licensing
- P. Pareshask, Operations
- W. Lee, Corporate Emergency Preparedness Director
- M. Hayes, Engineering Programs
- Z. Kitts, Licensing
NRC personnel
- None
LIST OF REPORT ITEMS
Opened and Closed
None
Discussed
None
LIST OF DOCUMENTS REVIEWED
Procedures
- ECA-0.0, Loss of All AC Power, Rev. 29
- EA-250-1, Load Shed of Vital Loads after Station Blackout, Rev. 18
- EA-201-1, 480V Board Room Breaker Alignments, Rev. 2
- 0-TI-DXX-000-922.3, Diverse and Flexible Coping Strategies (FLEX) Program Basis, Rev. 1
- EA-78-1, Refilling the Spent Fuel Pit, Rev. 6
- FSI-5.03, 6.9KV & 480V Shutdown Board Initial FLEX Alignment, Rev. 0
- FSI-5.01, Initial Assessment and FLEX Equipment Deployment, Rev. 1
- FSI-11, Alternate SFP Makeup and Cooling, Rev. 0
- NPG-SPP-07.2.11, Shutdown Risk Management, Rev. 11
- EPIP-13, Dose Assessment Rev. 17 CECC
- EPIP-8, Dose Assessment Staff Activities during Nuclear Plant Radiological Emergencies, Rev. 44 0-MI-FMI-360-001.0, Align Submersible High Pressure, Rev. 1
- 0-MI-FMI-360-003.0, Align Submersible Spare High Pressure FLEX Pump, Rev. 1
- 0-MI-FMI-360-005.0, Align Submersible High Pressure Pump from Boric Acid Tanks Wye Connection to RCS, Rev. 1 0-MI-FMI-360-017.0, FLEX - Spent Fuel Pool Makeup from Elev. 734 ERCW, Rev. 2 0-MI-FMI-360-018.0, FLEX - Spent Fuel Pool Makeup from Elev. 714 ERCW, Rev. 1
- 0-MI-FMI-360-020.0, FLEX - Water Transfer Pump Makeup to Condensate Storage Tanks, Rev. 0
- 0-MI-FMI-360-022.1, Staging of Low Pressure Diesel Driven Triton Pump (Floating Booster Pump) and 5000 GPM Dominator Pump (FLEX ERCW Pump), Rev. 1 0-MI-FMI-360-022.2, FLEX - Transporting and Staging of Water Transfer Pumps, Rev. 1 0-MI-FMI-360-023.0, FLEX - Portable Diesel Equipment Refueling, Rev. 2
- 0-MI-FMI-360-026.0, FLEX - Align Elevation 714 Intermediate Pressure Pumps from ERCW to SG Makeup, Rev. 1 0-MI-FMI-360-027.0, FLEX - Align Elevation 669 Intermediate Pressure Pump from ERCW to SG Makeup, Rev. 1 0-MI-FMI-360-029.0, FLEX - Hose Deployment for Essential Raw Cooling Water System, Rev. 3
Drawings
- 2-45n2418-2, Lightning Floor
- EL 734.0 Plan and Details Sheet 2, Rev. 1 1,2-55w300-8, Communications Harris Cabinet #6 Connection Diagram, Rev. 0
- 1,2-45N749-3, Wiring Diagrams 480V Shutdown Board 1B1-B Single Line, Rev. 53
- 1,2-45N706-3, Wiring Diagram 120AC Vital Instrument Power Boards 1-III and 2-III Connection Diagram Sheet 3, Rev. 52 1,2-45N706-1, Wiring Diagram 120AC Vital Instrument Power Boards 1-I and 2-I Connection Diagram Sheet 1, Rev. 53 0-55w300-1, Communications Harris Cabinet #5 Connection Diagram, Rev. 0
- 55W2792, Communications VHF Radios In-Plant Repeaters Arraignment and Details, Modifications
- CDN 23096-A, SQN Nextel Replacement Project
- DCN 23376, CST Missile Barrier Modification, Rev. A
Calculations
Condition Reports
- Reviewed
- 1164886,
- 1164895,
- 1164898,
- 1164902,
- 1164886,
- 1164903,
- 1164904,
- 1263523
Condition Reports
- Generated as part of the Inspection
- 1270809, PMs and tests of FLEX Tritons and Dominators do not contain acceptance criteria for flow and pressure
- 1270790, FLEX Hose Deployment for Essential Raw Cooling Water System procedure providing misleading instructions
- 1269775, FLEX- Remove lockable door knobs and replace with unlockable door knobs
- 270155, Drawing discrepancy on 45N706-2
- 1270328, NRC
- TI 191- NRC identified equipment discrepancy during Maintenance Procedure walkdown
- 1270322, NRC FLEX Inspection- Observation on inventory
- Surveillances
- EPIP-12, Emergency Equipment and Supplies, Appendix C, Dated 11/18/16
- EPIP-12, Emergency Equipment and Supplies, Appendix A, Dated 11/17/16
- EPIP-12, Emergency Equipment and Supplies, Appendix I, Dated 2/8/17
- EPIP-12, Emergency Equipment and Supplies, Appendix C, Dated 2/8/17
- EPIP-12, Emergency Equipment and Supplies, Appendix A, Dated 2/8/17
- EPIP-12, Emergency Equipment and Supplies, Appendix I, Dated 1/3/17
- 0-PI-REM-244-002.Q, Quarterly Testing of Emergency Response Facility Communications Equipment Rev. 1, Dated 11/2/16 0-PI-REM-244-002.Q, Quarterly Testing of Emergency Response Facility Communications Equipment Rev. 1, Dated 2/1/17
- Other Sequoyah Nuclear Plant, Units 1 and 2 - Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders
- EA-12-049 and
- B85161215005, FLEX Final Integrated Plan, Rev. 1
- EPM-7-1, EOI Administrative Controls, Validation Scenario Sheet, Rev. 16
- PR
- SL-E-0389, Elect Cable 8000g Diesel Fuel Tank D22929, Rev. 0
- SQN-ENG-SSA-17-014, Self-Assessment for Flex Inspection
- EA-12-049 and
- EA-12-051 (ML16270A517), October 12, 2016
- B85161215005 - FLEX Final Integrated Plan, Rev. 1
- SQN-DC-V-48.0, Flex Response System, Rev. 8
- NPG-SQN-200103, Licensed Operator Cycle 15-2 Continuing Training Curriculum
- NPG-SQN-200105, Non Licensed Operator Cycle 15-2 Continuing Training Curriculum Fire Ops Flex Training
- B85161215005, Flex Final Integrated Plan, Rev. 1
- CDQ0003602014000172, Qualification of FLEX Equipment Storage Building, Rev. 1