ML14245A124
| ML14245A124 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 09/02/2014 |
| From: | Jamnes Cameron Reactor Projects Region 3 Branch 4 |
| To: | Pacilio M Exelon Generation Co, Exelon Nuclear |
| References | |
| Download: ML14245A124 (5) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE RD. SUITE 210 LISLE, IL 60532-4352 September 2, 2014 Mr. Michael J. Pacilio Senior VP, Exelon Generation Co., LLC President and CNO, Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
MID-CYCLE ASSESSMENT LETTER FOR DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3
Dear Mr. Pacilio:
On August 6, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed its mid-cycle performance review of Dresden Nuclear Power Station, Units 2 and 3. The NRC reviewed the most recent quarterly performance indicators (PIs) in addition to inspection results and enforcement actions from July 1, 2013, through June 30, 2014. This letter informs you of the NRCs assessment of your facility during this period and its plans for future inspections at your facility.
The NRC determined that overall, Dresden Nuclear Power Station, Units 2 and 3 was operated in a manner that preserved public health and safety and met all cornerstone objectives The NRC determined the performance at Dresden Nuclear Power Station, Units 2 and 3 during the most recent quarter was within the Licensee Response Column of the NRCs Reactor Oversight Process (ROP) Action Matrix because all inspection findings had very low (i.e., green) safety significance, and all PIs indicated that your performance was within the nominal, expected range (i.e., green). Therefore, the NRC plans to conduct ROP baseline inspections at your facility.
The NRC determined the performance at Dresden Nuclear Power Station, Units 2 and 3, during the fourth quarter of 2013 was within the Regulatory Response Column of the NRCs ROP Action Matrix because of one White finding associated with a deficiency in your external flood response procedure in addressing makeup to the reactor vessel during a potential flooding event. The finding was identified in the first quarter of 2013 and was applicable to both Units 2 and 3, in the Mitigating Systems Cornerstone. Additionally, the NRC advised you the finding would remain open until you notified us that you were ready for the NRC to conduct a supplemental inspection using Inspection Procedure 95001, Inspection for One or Two White Inputs in Strategic Performance Area, and the inspection was successfully completed.
On November 25, 2013, your staff notified the NRC of your readiness for a supplemental inspection, using Inspection Procedure 95001, to review the actions taken to address the performance issues associated with the deficiency in the flood response procedure. On December 20, 2013, the NRC completed the supplemental inspection using NRC Inspection Procedure 95001 and in NRC Inspection Report 05000237/2013010; 05000249/2013010 (ADAMS Ascension Number ML14023A004), dated January 22, 2014,
M. Pacilio documented that completed or planned corrective actions were sufficient to address the performance that led to the White finding. Therefore, you were advised that the performance issue would not be considered as an Action Matrix input after the end of the fourth quarter of 2013. As a result, the NRC determined the performance at Dresden Nuclear Power Station, Units 2 and 3, to be in the Licensee Response Column of the ROP Action Matrix as of January 1, 2014.
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.
The inspections listed during the last 9-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.
The enclosed plan does include a triennial Evaluations of Changes, Tests and Experiments and Permanent Plant Modifications inspection per procedure 71111.17T and triennial Heat Sink inspection per procedure 71111.07T.
In response to the accident at Fukushima, the Commission issued Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, which requires licensees to develop, implement, and maintain guidance and strategies to maintain or restore core cooling, containment, and spent fuel pool cooling capabilities following a beyond-design-basis external event. Additionally, the Commission issued Order EA-12-051, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation, which requires licensees to have a reliable means of remotely monitoring wide-range Spent Fuel Pool levels to support effective prioritization of event mitigation and recovery actions in the event of a beyond-design-basis external event. The NRC is conducting audits of licensee efforts towards compliance with these Orders. This audit includes an onsite component in order for the NRC to evaluate licensee plans for complying with the Orders, as described in site-specific 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 date for the onsite component at your site is being coordinated with your staff. A site-specific audit plan for the visit will be provided in advance to allow sufficient time for preparations.
M. Pacilio 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, 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 System (PARS) component of 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 630-829-9833 with any questions you have regarding this letter.
Sincerely,
/RA/
Jamnes L. Cameron, Chief Branch 4 Division of Reactor Projects Docket Nos. 50-237; 50-249 License Nos. DPR-19; DPR-25
Enclosure:
Dresden Nuclear Power Station Inspection/Activity Plan cc w/encl: Distribution via LISTSERV
M. Pacilio 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, 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 System (PARS) component of 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 630-829-9833 with any questions you have regarding this letter.
Sincerely,
/RA/
Jamnes L. Cameron, Chief Branch 4 Division of Reactor Projects Docket Nos. 50-237; 50-249 License Nos. DPR-19; DPR-25
Enclosure:
Dresden Nuclear Power Station Inspection/Activity Plan cc w/encl: Distribution via LISTSERV DISTRIBUTION w/encl:
Anthony Bowers RidsNrrDorlLpl3-2 Resource RidsNrrPMDresden Resource RidsNrrDirsIrib Resource Cynthia Pederson Darrell Roberts Steven Orth Allan Barker Carole Ariano Linda Linn DRPIII DRSIII Patricia Buckley Carmen Olteanu ROPassessment.Resource@nrc.gov DOCUMENT NAME: Dresden 2014 Mid-Cycle Assessment Letter Publicly Available Non-Publicly Available Sensitive Non-Sensitive To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy OFFICE RIII NAME BBartlett for JRutkowski:mt JCameron DATE 08/21/14 08/25/14 OFFICIAL RECORD COPY
Page 1 of 1 08/22/2014 09:36:37 Report 22 Unit Number Planned Dates Start End Inspection Activity Title No. of Staff on Site Dresden Inspection / Activity Plan 09/01/2014 - 12/31/2015 BI ISI
- INSERVICE INSPECTION UNIT 3 1
2 IP Inservice Inspection Activities - BWR 7111108G 10/27/2014 11/15/2014 BI RP
- RADIATION INSPECTION 1
2 IP Radiological Hazard Assessment and Exposure Controls 71124.01 11/03/2014 11/07/2014 2
IP Occupational ALARA Planning and Controls 71124.02 11/03/2014 11/07/2014 BI HS
- TRIENNIAL HEAT SINK INSPECTION 2
2, 3 IP Heat Sink Performance 7111107T 12/01/2014 12/05/2014 BI RP
- RADIATION PROTECTION BASELINE INSPECTION 1
2 IP Radioactive Gaseous and Liquid Effluent Treatment 71124.06 01/26/2015 01/30/2015 OL PREP
- INIT EXAM/MARCH 2015 3
2 OL - INITIAL EXAM - 2015 MAR-APR - DRESDEN W90328 03/02/2015 03/06/2015 OL EXAM
- INIT EXAM/MARCH 2015 3
2 OL - INITIAL EXAM - 2015 MAR-APR - DRESDEN W90328 04/06/2015 04/17/2015 BL EPX
- EP EXECISE INSPECTION / PI VERIFICATION 2
2, 3 IP Exercise Evaluation 7111401 05/04/2015 05/08/2015 2, 3 IP Exercise Evaluation - Scenario Review 7111408 05/04/2015 05/08/2015 2
IP Performance Indicator Verification 71151 05/04/2015 05/08/2015 BI MODS
- MODIFICATIONS / 50.59 INSPECTION 3
2, 3 IP Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications 7111117T 05/11/2015 05/29/2015 BI RP
- RADIATION PROTECTION BASELINE INSPECTION 1
2 IP Radiological Environmental Monitoring Program 71124.07 05/18/2015 05/22/2015 2
IP 71151-PR01 05/18/2015 05/22/2015 BI RP
- RADIATION PROTECTION BASELINE INSPECTION 1
2 IP Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation 71124.08 07/13/2015 07/17/2015 2
IP 71151-BI01 07/13/2015 07/17/2015 BI RP
- RADIATION PROTECTION BASELINE INSPECTION 1
2 IP Radiological Hazard Assessment and Exposure Controls 71124.01 11/02/2015 11/06/2015 2
IP Occupational ALARA Planning and Controls 71124.02 11/02/2015 11/06/2015 2
IP 71151-OR01 11/02/2015 11/06/2015 This report does not include INPO and OUTAGE activities.
This report shows only on-site and announced inspection procedures.