IR 05000336/2013001

2013 Annual Assessment Letter for Millstone Power Station Units 2 and 3 (Report 05000336/2013001 and 05000423/2013001)(w/Inspection Plan)

ML14059A046
Person / Time
Site:	Millstone
Issue date:	03/04/2014
From:	Raymond McKinley NRC/RGN-I/DRP/PB5
To:	Heacock D Dominion Resources
McKinley R R
References
IR-13-001
Download: ML14059A046 (5)

Text

March 4, 2014

Mr. David Heacock President and Chief Nuclear Officer Dominion Resources, Inc.

5000 Dominion Boulevard Glen Allen, VA 23060-6711

SUBJECT: ANNUAL ASSESSMENT LETTER FOR MILLSTONE POWER STATION UNITS 2 AND 3 (REPORT 05000336/2013001 AND 05000423/2013001)

Dear Mr. Heacock:

On February 13, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed its end-of-cycle performance review of Millstone Power Station Units 2 and 3. The NRC reviewed the most recent quarterly performance indicators in addition to inspection results and enforcement actions from January 1, 2013, through December 31, 2013. This letter informs you of the NRC's assessment of your facility during this period and its plans for future inspections at your facility. The NRC determined that overall, Millstone Power Station Units 2 and 3 operated in a manner that preserved public health and safety and met all cornerstone objectives. The NRC determined the performance at Millstone Power Station Units 2 and 3 during the most recent quarter was within the Licensee Response Column of the NRC's Reactor Oversight Process Action Matrix because all inspection findings had very low (i.e., green) safety significance, and all performance indicators demonstrated that your performance was within the nominal, expected range (i.e, green). Therefore, the NRC plans to conduct Reactor Oversight Process baseline inspections at your facility.

As a result of the Safety Culture Common Language Initiative, the terminology and coding of cross-cutting aspects were revised. All cross-cutting aspects identified during inspections conducted in calendar year (CY) 2014 will reflect this revision to Inspection Manual Chapter (IMC) 0310. The CY 2013 end-of-cycle assessments were conducted using the IMC 0310 guidance in effect in CY 2013 (dated October 28, 2011). Cross-cutting aspects identified in 2013 using the 2013 terminology will be converted to the latest revision in accordance with the cross-reference in IMC 0310 during the mid-cycle assessment review and evaluated for cross-cutting themes and potential substantive cross-cutting issues in accordance with IMC 0305.

The enclosed inspection plan lists the inspections scheduled through June 30, 2015. Routine inspections performed by resident inspectors are not included in the inspection plan. The inspections listed during the last nine months of the inspection plan are tentative and may be revised at the mid-cycle performance review. In addition to baseline inspections, the NRC will perform Inspection Procedure (IP) 71003, "Post-Approval Site Inspection for License Renewal," IP 60855.1, "Operation of an Independent Spent Fuel Storage Installation at Operating Plants,"

and Temporary Instruction 2515/182, "Review of the Implementation of the Industry Initiative to Control Degradation of Underground Piping and Tanks." The NRC provides the inspection plan to allow for the resolution of any scheduling conflicts and personnel availability issues. The NRC will contact you as soon as possible to discuss changes to the inspection plan should circumstances warrant any changes. This inspection plan does not include security-related inspections, which will be sent via separate, non-publicly available correspondence. Additionally, an NRC audit of licensee efforts towards compliance with Order EA-12-049, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events," is ongoing. This audit includes an onsite component in order for the NRC to evaluate mitigating strategies as described in licensee submittals, and to receive and review information relative to associated open items. This onsite activity will occur in the months prior to a declaration of compliance for the first unit at each site, and will aid staff in development of an ultimate Safety Evaluation for the site. The onsite component has been scheduled for the week of June 23, 2014. A site-specific audit plan for the visit will be provided in advance to allow sufficient time for preparations.

In accordance with Title 10 of the Code of Federal Regulations 2.390, "Public Inspections, Exemptions, Requests for Withholding," of the NRC's "Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records component of the NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). Please contact me at (610)337-5150 with any questions you have regarding this letter.

Sincerely,/RA/ Raymond R. McKinley, Chief Reactor Projects Branch 5 Division Reactor Projects Docket Nos: 50-336 and 50-423 License Nos: DPR-65 and NPF-49

Enclosure:

Inspection Plan cc w/encl: Distribution via ListServ