IR 05000336/2014006: Difference between revisions

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| number = ML14241A020
| number = ML14241A020
| issue date = 09/02/2014
| issue date = 09/02/2014
| title = Mid-Cycle Assessment Letter and Inspection Plan 2014 (ROP-15) - Millstone Power Station Units 2 and 3 (Report 05000336/2014006 and 05000423/2014006)
| title = Mid-Cycle Assessment Letter and Inspection Plan 2014 (Rop-15) - Millstone Power Station Units 2 and 3 (Report 05000336/2014006 and 05000423/2014006)
| author name = McKinley R R
| author name = McKinley R R
| author affiliation = NRC/RGN-I/DRP/PB5
| author affiliation = NRC/RGN-I/DRP/PB5

Revision as of 02:38, 13 February 2018

Mid-Cycle Assessment Letter and Inspection Plan 2014 (Rop-15) - Millstone Power Station Units 2 and 3 (Report 05000336/2014006 and 05000423/2014006)
ML14241A020
Person / Time
Site: Millstone  Dominion icon.png
Issue date: 09/02/2014
From: Raymond McKinley
NRC/RGN-I/DRP/PB5
To: Heacock D
Dominion Resources
McKinley R R
References
IR-2014-006
Download: ML14241A020 (6)


Text

September 2, 2014

Mr. David Heacock President and Chief Nuclear Officer Dominion Resources 5000 Dominion Boulevard Glen Allen, VA 23060-6711

SUBJECT: MID-CYCLE ASSESSMENT LETTER FOR MILLSTONE POWER STATION UNITS 2 AND 3 (REPORT 05000336/2014006 AND 05000423/2014006)

Dear Mr Heacock:

On August 12, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed its mid-cycle performance review of Millstone Power Station, Units 2 and 3 (Millstone). The NRC reviewed the most recent quarterly performance indicators in addition to inspection results and enforcement actions from July 1, 2013 through June 30, 2014. 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, Dominion operated Millstone in a manner that preserved public health and safety and met all cornerstone objectives. The NRC determined the performance at Millstone during the most recent quarter was within the Licensee Response Column of the NRC's Reactor Oversight Process (ROP) 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 ROP baseline inspections at your facility. Although plant performance was within the Licensee Response Column, the NRC has not yet finalized the significance of a preliminary White finding (NCV 05000423/2014008-001, Failure to Maintain Adequate Maintenance Instructions for the Turbine Driven Auxiliary Feedwater Pump Governor Control Valve Linkage) documented in NRC inspection report 05000423/2014008. The final safety significance determination may affect the NRC's assessment of plant performance and the enclosed inspection plan.

Additionally, the NRC has not finalized the severity of a preliminary Severity Level III traditional enforcement apparent violation (AV 05000336 & 05000423/2014011-01, Failure to Complete a 10 CFR 50.59 Evaluation for Removal of the Severe Line Outage Detection System) documented in NRC inspection report 05000336/2014011 and 05000423/2014011.

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 2014 reflect this revision to Inspection Manual Chapter (IMC) 0310. Cross-cutting aspects identified in 2013 using the 2013 terminology were 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 December 31, 2015.

Routine inspections performed by resident inspectors are not included in the inspection plan.

In addition to baseline inspections, the NRC will perform Inspection Procedure (IP) 71003,

"Post-Approval Site Inspection for License Renewal," IP 60855, "Operation of an Independent Spent Fuel Storage Installation (ISFSI)," and IP 60855.1, "Operation of an ISFSI at Operating Plant." The inspections listed during the last nine months of the inspection plan are tentative and may be revised at the end-of-cycle performance review. 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, during this assessment period, the NRC issued an inspection report dated June 24, 2014 (ADAMS Accession No. ML14175A464), which documented a Green violation related to Dominion's failure on two previous occasions to identify the issue. As a result, the NRC plans to conduct IP 92702, "Follow-up on Corrective Actions for Violations and Deviations," to follow-up on your actions related to the Notice of Violation. The NRC tentatively plans to perform IP 92702 in May of 2015.

In accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 2.390 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 of Reactor Projects Docket Nos. 50-336 and 50-423 License Nos. DPR-65 and NPF-49

Enclosure:

Millstone Inspection/Activity Plan cc w/encl: Distribution via ListServ