IR 05000280/2017009
| ML17137A194 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 05/17/2017 |
| From: | Philip Mckenna Reactor Projects Branch 7 |
| To: | Stoddard D Virginia Electric & Power Co (VEPCO) |
| References | |
| IR 2017009 | |
| Download: ML17137A194 (13) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION May 17, 2017
SUBJECT:
ERRATA - SURRY POWER STATION - NRC TEAM INSPECTION REPORT 05000280/2017009 AND 05000281/2017009
Dear Mr. Stoddard:
The U.S. Nuclear Regulatory Commission (NRC) identified two administrative errors on the cover letter for NRC Inspection Report 05000280/2017009 and 05000281/2017009, dated April 11, 2017 (ADAMS Accession No. ML17101A808). First, the addressee should have been Mr. Daniel G. Stoddard. Second, there were extraneous words in the second paragraph. Specifically, the last sentence should have stated: Within these areas, the inspection involved examination of selected procedures and records, observation of activities, and interviews with station personnel. As a result, the NRC has reissued the report in its entirety to correct these errors.
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/
Philip J. McKenna, Acting Chief Reactor Projects Branch 7 Division of Reactor Projects Docket Nos.: 50-280, 50-281 License Nos.: NPF-32, NPF-37
Enclosure:
IR 05000280/2017009 and 05000281/2017009 w/Attachment: Supplemental Information
REGION II==
Docket No.: 50-280, 50-281 License No.: DPR-32, DPR-37 Report No.: 05000280/2017009, 05000281/2017009 Licensee: Virginia Electric and Power Company (VEPCO)
Facility: Surry Power Station, Units 1 and 2 Location: 5850 Hog Island Road Surry, VA 23883 Dates: March 13 - 16, 2017 Inspectors: S. Freeman, Senior Reactor Analyst, RII (Team Leader)
G. MacDonald, Senior Reactor Analyst, RII C. Jones, Resident Inspector, Surry Approved by: Philip J. McKenna, Acting Chief Reactor Projects Branch 7 Division of Reactor Projects Enclosure
SUMMARY
IR 05000280/2017009, 05000281/2017009; 03/13/2017 - 03/16/2017; Surry Power Station
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 two senior reactor analysts and one resident inspector. No NRC-identified or self-revealing findings were identified. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 5.
NRC-Identified and Self-Revealing Findings
None
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 licensees Final Integrated Plan, which was described in letters dated January 25, 2016, (ADAMS Accession No. ML16033A353) and July 20, 2015, (ADAMS Accession No. ML15205A342) and the NRCs plant safety evaluation (ADAMS Accession No. ML16158A432) 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 the NRCs 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 walk downs to verify that the strategies could be implemented as stated in the licensees 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 teams inspection activities are described in the following sections.
1. Mitigation Strategies for Beyond-Design Basis External Events
a. Inspection Scope
The team examined the licensees 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 walkdowns 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 assure 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 noncompliances with the current licensing requirements, and other issues identified during the inspection, were entered into the licensees corrective action program.
c. Findings
No findings were identified.
2. Spent Fuel Pool Instrumentation
a. Inspection Scope
The team examined the licensees 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 were 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 ensure 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 noncompliances with the current licensing requirements, and other issues identified during the inspection, were entered into the licensees corrective action program.
c. Findings
No findings were 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 licensees 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 licensees site-specific dose assessment software and approach as described in the licensees multi-unit dose assessment submittal. Documents reviewed are listed in the attachment.
b. Assessment The inspectors reviewed information provided in the licensees multi-unit dose submittal and in response to the NRCS 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 resulted 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 changes to support an ELAP scenario.
- Implemented dose assessment capabilities (including releases from spent fuel pools) using the licensees site-specific dose assessment software and approach.
The inspectors verified that noncompliances 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 were identified.
4OA6 Exit
Exit Meeting Summary
On March 16, 2017, the inspectors presented the inspection results to Mr. R. Simmons and other members of the site staff. The inspectors confirmed that proprietary information was not provided or examined during the inspection.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee personnel
- F. Mladen, Site Vice President
- R. Simmons, Plant Manager
- R. Johnson, Operations Manager
- T. Shell, Assistant Operations Manager
- H. Johnson, Superintendent of Shift Operations
- J. Rosenberger, Site Engineering Director
- J. Henderson, Manager of Design Engineering
- J. Holloway, Engineering Supervisor
- E. Turko, Engineering Supervisor
- D. Lawrence, Director of Nuclear Safety and Licensing
- L. Baker, Manager of Nuclear Training
- B. Garber, Licensing Manager
- L. Helstosky, Licensing Engineer
- D. Aitken, Licensing Engineer
- K. Rowland, General Project Manager
NRC personnel
- E. Andrews, Acting Senior Resident Inspector
LIST OF REPORT ITEMS
Opened and Closed
None
Discussed
None