IR 05000456/2010001

Braidwood Power Plant EOC Annual Assessment Letter (05000456-10-001; 05000457-10-001)

ML100610223
Person / Time
Site:	Braidwood
Issue date:	03/03/2010
From:	Stephanie West Division Reactor Projects III
To:	Pardee C Exelon Generation Co, Exelon Nuclear
References
IR-10-001
Download: ML100610223 (7)

Text

UNITED STATES rch 3, 2010

SUBJECT:

ANNUAL ASSESSMENT LETTER - BRAIDWOOD STATION, UNITS 1 AND 2, (05000456/2010001; 05000457/2010001)

Dear Mr. Pardee:

On February 10, 2010, the NRC staff completed its performance review of Braidwood Station, Units 1 and 2. Our technical staff reviewed performance indicators (PIs) for the most recent quarter and inspection results for the period from January 1 through December 31, 2009. The purpose of this letter is to inform you of our assessment of your safety performance during this period and our plans for future inspections at your facility.

This performance review and enclosed inspection plan do not include security information. A separate letter designated and marked as "Official Use Only - Security Information" will include the Security Cornerstone review and resultant inspection plan.

Overall, Braidwood Station operated in a manner that preserved public health and safety and fully met all cornerstone objectives.

Plant performance for the most recent quarter at Braidwood Station Unit 1 was within the Regulatory Response Cornerstone column of the NRCs Action Matrix, based on one inspection finding being classified as having low-to-moderate safety significance (White) and all PIs indicating performance at a level requiring no additional NRC oversight (Green). The White finding involved the failure of the containment sump suction isolation valve to fully open.

When you notify us of your readiness, we will conduct a supplemental inspection for Braidwood Unit 1 using Inspection Procedure 95001, Inspection for One or Two White Inputs in a Strategic Performance Area. In addition, we plan to conduct reactor oversight program (ROP) baseline inspections at Braidwood Unit 1.

Plant performance for the most recent quarter, as well as the first three quarters of the assessment periods at Braidwood Station Unit 2, was within the Licensee Response column of the NRCs Action Matrix, based on all inspection findings being classified as having very low safety significance (Green) and all PIs indicating performance at a level requiring no additional NRC oversight (Green). Therefore, we plan to conduct reactor oversight program (ROP)

baseline inspections at Braidwood Station Unit 2. The NRC also plans to conduct several special and infrequently performed inspection procedures (IPs), which include inspections related to the pre-operational testing and operation of the Independent Spent Fuel Storage Installation.

In the mid-cycle performance review letter dated September 1, 2009, [ML092440402], we advised you of a substantive cross-cutting issue in the area of human performance. The substantive cross-cutting issue was the result of several findings that involved deficiencies in human performance throughout the station. In response to the identified cross-cutting issues, you had provided us your Human Performance Improvement Plan and specific actions that you planned to take to correct the cross-cutting issue performance deficiencies.

Nevertheless, the staff has continued to have concerns with your human performance. During this assessment period, you have had three of these findings in the human performance area that shared the common cross-cutting aspect of failure to make conservative assumptions and demonstrating the proposed action is safe (H.1(b)). These findings were from more than one cornerstone (Mitigating Systems and Initiating Events). Moreover, your Human Performance Improvement Plan actions have not yet proven effective in substantially mitigating the cross-cutting theme even though a reasonable duration of time has passed. Therefore, this substantive cross-cutting issue remains open until your corrective actions have resulted in a positive sustainable improvement in the area and the number of findings in the theme is reduced or maintained. Please provide a status update of the progress that was made to improve the human performance during the annual end-of-cycle public meeting to be scheduled at a later date. We will also access the human performance related issues as a Problem Identification and Resolution follow-up inspection item in accordance with IP 71152, Identification and Resolution of Problems, Section 03.02, Selected Issue Follow-up Inspection.

The enclosed inspection plan details the inspections, less those related to physical protection, scheduled through June 30, 2011. Please note that we plan on conducting two infrequently performed IPs: IP 60854.1, Preoperational Testing of an Independent Spent Fuel Storage Facility Installation at Operating Plants, and IP 60855.1, Operation of an Independent Spent Fuel Storage Installation at Operating Plants, this year at your Braidwood Station. The inspection plan is provided to allow for the resolution of any scheduling conflicts and personnel availability issues well in advance of inspector arrival onsite. Routine resident inspections are not listed due to their ongoing and continuous nature. The inspections in the last 9 months of the inspection plan are tentative and may be revised at the mid-cycle review.

In accordance with 10 CFR 2.390 of the NRC=s ARules of Practice,@ a copy of this letter and its enclosure will be made available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). If circumstances arise which cause us to change this inspection plan, we will contact you to discuss the change as soon as possible. Please contact Richard A. Skokowski at 630-829-9620 with any questions you may have regarding this letter or the inspection plan.

Sincerely,

/RA/

Steven West, Director Division of Reactor Projects Docket Nos. 50-456, 50-457 License Nos. NPF-72, NPF-77 Enclosure: Braidwood Station Inspection/Activity Plan cc w/encl: Distribution via ListServ

Braidwood Inspection / Activity Plan 03/01/2010 - 06/30/2011 Planned Dates No. of Staff Start End Inspection Activity Title on Site BI ENG - COMPONENT DESIGN BASIS INSPECTION 8

/01/2010 04/02/2010 IP 7111121 Component Design Bases Inspection BI EP - EP EXERCISE INSPECTION / PI VERIFICATION 3

/22/2010 03/26/2010 IP 7111401 Exercise Evaluation

/22/2010 03/26/2010 IP 71151-EP01 Drill/Exercise Performance

/22/2010 03/26/2010 IP 71151-EP02 ERO Drill Participation

/22/2010 03/26/2010 IP 71151-EP03 Alert & Notification System BI RP - RADIATION PROTECTION BASELINE INSPECTI 1

/14/2010 06/18/2010 IP 71124.05 Radiation Monitoring Instrumentation

/14/2010 06/18/2010 IP 71151-BI01 Reactor Coolant System Activity BI RP - RADIATION PROTECTION BASELINE INSPECTI 1

/12/2010 07/16/2010 IP 71124.08 Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation

/12/2010 07/16/2010 IP 71151-PR01 RETS/ODCM Radiological Effluent BI PI&R - BIENNIAL PI&R INSPECTION 4

/30/2010 09/17/2010 IP 71152B Identification and Resolution of Problems BI ENG - ENGINEERING INSERVICE INSPECTION 1

/04/2010 10/29/2010 IP 7111108P Inservice Inspection Activities - PWR BI RP - RADIATION PROTECTION BASELINE INSPECTION 1

/18/2010 10/22/2010 IP 2515/179 Verification of Licensee Responses to NRC Requirement for Inventories of Materials Tracked in NSTS

/18/2010 10/22/2010 IP 71124.01 Radiological Hazard Assessment and Exposure Controls

/18/2010 10/22/2010 IP 71124.02 Occupational ALARA Planning and Controls

/18/2010 10/22/2010 IP 71151-OR01 Occupational Exposure Control Effectiveness BI ENG - POLAR CRANE SINGLE FAILURE PROOF UPGRADE 1

/15/2010 12/03/2010 IP 7111120 Refueling and Other Outage Activities BI EP - EP ROUTINE INSPECTION / PI VERIFICATION 2

/31/2011 02/04/2011 IP 7111402 Radiological Environmental Monitoring Program

/31/2011 02/04/2011 IP 7111403 Emergency Response Organization Augmentation Testing

/31/2011 02/04/2011 IP 7111405 Correction of Emergency Preparedness Weaknesses and Deficiencies

/31/2011 02/04/2011 IP 71151-EP01 Drill/Exercise Performance

/31/2011 02/04/2011 IP 71151-EP02 ERO Drill Participation

/31/2011 02/04/2011 IP 71151-EP03 Alert & Notification System ISFSI - ISFSI INSPECTION. - SCHEDULE DEPENDENT 2

/01/2011 06/30/2011 IP 60854.1 Preoperational Testing of Independent Spent Fuel Storage Facility Installation at Operating Plants

/01/2011 08/31/2011 IP 60855.1 Operation of an Independent Spent Fuel Storage Installation at Operating Plants

Braidwood Inspection / Activity Plan 03/01/2010 - 06/30/2011 Planned Dates No. of Staff Start End Inspection Activity Title on Site BI RP - RADIATION PROTECTION BASELINE INSPECTI 1 03/28/2011 04/01/2011 IP 71124.03 In-Plant Airborne Radioactivity Control and Mitigation 03/28/2011 04/01/2011 IP 71124.04 Occupational Dose Assessment 03/28/2011 04/01/2011 IP 71151-BI01 Reactor Coolant System Activity BI ENG - ENGINEERING INSERVICE INSPECTION - U2 1 04/18/2011 05/05/2011 IP 7111108P Inservice Inspection Activities - PWR BI RP - RADIATION PROTECTION BASELINE INSPECTI 1 05/23/2011 05/27/2011 IP 71124.06 Radioactive Gaseous and Liquid Effluent Treatment 05/23/2011 05/27/2011 IP 71151 Performance Indicator Verification OL PREP - BRAIDWOOD INIT PREP - 05/2011 2 05/30/2011 06/03/2011 W90226 OL - INITIAL EXAM - JUN 2011 - BRAI OL EXAM - BRAIDWOOD INIT EXAM - 06/2011 2 06/20/2011 07/01/2011 W90226 OL - INITIAL EXAM - JUN 2011 - BRAI