IR 05000324/2015005

Mid-Cycle Assessment Letter for Brunswick Steam Electric Plant, Units 1 and 2 - NRC Inspection Report 05000325/2015005 and 05000324/2015005

ML15244B073
Person / Time
Site:	Brunswick
Issue date:	09/01/2015
From:	Hopper G NRC/RGN-II/DRP/RPB4
To:	William Gideon Duke Energy Progress
References
IR 2015005
Download: ML15244B073 (6)

Text

UNITED STATES September 1, 2015

SUBJECT:

MID-CYCLE ASSESSMENT LETTER FOR BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 - NRC INSPECTION REPORT 05000325/2015005 AND 05000324/2015005

Dear Mr. Gideon:

On August 12, 2015, the Nuclear Regulatory Commission (NRC) completed its mid-cycle performance review of Brunswick Steam Electric Plant, Units 1 and 2. The NRC reviewed the most recent quarterly performance indicators (PIs) in addition to inspection results and enforcement actions from July 1, 2014, through June 30, 2015. This letter informs you of the NRCs assessment of your facility during this period and its plans for future inspections at your facility. This performance review and enclosed inspection plan do not include security information.

The NRC determined that overall, Brunswick Steam Electric Plant, Units 1 and 2 operated in a manner that preserved public health and safety and met all cornerstone objectives. The NRC determined the performance at Brunswick Steam Electric Plant, Units 1 and 2, 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 enclosed inspection plan lists the inspections scheduled through June 30, 2017. Routine inspections performed by resident inspectors are not included in the inspection plan. The inspections listed during the second half 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.

We also plan on conducting the following infrequently performed inspection: Operator Licensing Initial Exams. 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. This Order 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. This Order 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. The audit was completed for the Brunswick Steam Electric Plant, and the information gathered will aid staff in development of the ultimate Safety Evaluation for the site. After the NRC staff receives the Final Compliance letter for the site, the Final Safety Evaluation will be issued. Then, the NRC staff will confirm through inspections, the full implementation of the orders mentioned above performing TI 191, Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans.

In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 of the NRCs Agency Rules of Practice and Procedure, a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs Agencywide Document Access and Management System (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Please contact George Hopper at (404) 997-4645 with any questions you may have regarding this letter.

Sincerely,

/RA/

George T. Hopper, Chief Reactor Projects Branch 4 Division of Reactor Projects Docket Nos.: 50-325, 50-324 License Nos.: DPR-71, DPR-62 Enclosure:

Brunswick Inspection/Activity Plan (09/01/2015 - 06/30/2017)

cc: Distribution via ListServ

_________________________ SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII:DRP RII:DRP RII:DRP SIGNATURE DXW4 JSD GTH NAME DJackson JDodson GHopper DATE 8/28/2015 8/21/2015 8/31/2015 E-MAIL COPY? YES NO YES NO YES NO Letter to William from George T. Hopper dated September 1, 2015.

SUBJECT: MID-CYCLE ASSESSMENT LETTER FOR BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 - NRC INSPECTION REPORT 05000325/2015005 AND 05000324/2015005 DISTRIBUTION:

D. Gamberoni, RII L. Gibson, RII OE Mail RIDSNRRDIRS PUBLIC RidsNrrPMBrunswick Resource ROP Assessment ROP Reports Institute of Nuclear Power Operations (INPO)

Page 1 of 2 Brunswick 09/01/2015 10:16:57 Inspection / Activity Plan Report 22 09/01/2015 - 06/30/2017 Unit Planned Dates No. of Staff Number Start End Inspection Activity Title on Site OL EXAM - INITIAL LICENSE EXAM PREP 3 1 11/02/2015 11/06/2015 V23431 BRUNSWICK/NOVEMBER 2015 INITIAL EXAM AT POWER FACILITIES OL EXAM - INITIAL LICENSE EXAM 3 1 11/30/2015 12/11/2015 V23431 BRUNSWICK/NOVEMBER 2015 INITIAL EXAM AT POWER FACILITIES ISI - UNIT 1 IN-SERVICE INSPECTION 1 1 03/07/2016 03/11/2016 IP 7111108G Inservice Inspection Activities - BWR RP - RAD HAZARDS AND TRANSPORTATION 2 1, 2 03/07/2016 03/11/2016 IP 71124.01 Radiological Hazard Assessment and Exposure Controls 1, 2 03/07/2016 03/11/2016 IP 71124.08 Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation RP - RP PUBLIC RAD SAFETY BASELINE 2 1, 2 05/23/2016 05/27/2016 IP 71124.06 Radioactive Gaseous and Liquid Effluent Treatment 1, 2 05/23/2016 05/27/2016 IP 71124.07 Radiological Environmental Monitoring Program 1, 2 05/23/2016 05/27/2016 IP 71151 Performance Indicator Verification EP - EP EXERCISE INSPECTION 6 1, 2 07/25/2016 07/29/2016 IP 7111401 Exercise Evaluation 1, 2 07/25/2016 07/29/2016 IP 7111404 Emergency Action Level and Emergency Plan Changes 1, 2 07/25/2016 07/29/2016 IP 7111408 Exercise Evaluation - Scenario Review 1, 2 07/25/2016 07/29/2016 IP 71151 Performance Indicator Verification OL RQ - REQUAL INSP 2 1, 2 10/17/2016 10/21/2016 IP 7111111B Licensed Operator Requalification Program CDBI - COMPONENT DESIGN BASES INSPECTION 7 1, 2 10/17/2016 10/21/2016 IP 7111121 Component Design Bases Inspection 1, 2 11/14/2016 11/18/2016 IP 7111121 Component Design Bases Inspection 1, 2 11/28/2016 12/02/2016 IP 7111121 Component Design Bases Inspection 1, 2 12/12/2016 12/16/2016 IP 7111121 Component Design Bases Inspection TFPI - TRIENNIEL FIRE PROTECTION INSPECTION 4 1, 2 01/23/2017 01/27/2017 IP 7111105T Fire Protection [Triennial]

1, 2 02/06/2017 02/10/2017 IP 7111105T Fire Protection [Triennial]

ISI - UNIT 2 IN-SERVICE INSPECTION 1 2 03/13/2017 03/17/2017 IP 7111108G Inservice Inspection Activities - BWR RP - RAD HAZARDS AND PIV 1 1, 2 03/20/2017 03/24/2017 IP 71124.01 Radiological Hazard Assessment and Exposure Controls 1, 2 03/20/2017 03/24/2017 IP 71151 Performance Indicator Verification This report does not include INPO and OUTAGE activities.

This report shows only on-site and announced inspection procedures.

Enclosure

Page 2 of 2 Brunswick 09/01/2015 10:16:57 Inspection / Activity Plan Report 22 09/01/2015 - 06/30/2017 Unit Planned Dates No. of Staff Number Start End Inspection Activity Title on Site PI&R - PROBLEM IDENTIFICATION AND RESOLUTION 5 1, 2 05/08/2017 05/12/2017 IP 71152B Problem Identification and Resolution 1, 2 05/22/2017 05/26/2017 IP 60851 Design Control Of ISFSI Components This report does not include INPO and OUTAGE activities. Enclosure This report shows only on-site and announced inspection procedures.