ML050620309

Annual Assessment Letter - Braidwood Units 1 and 2

ML050620309
Person / Time
Site:	Braidwood
Issue date:	03/02/2005
From:	Passehl D NRC/RGN-III/DRP/RPB3
To:	Crane C Exelon Generation Co, Exelon Nuclear
References
IR-05-001
Download: ML050620309 (7)

Text

March 2, 2005 Mr. Christopher M. Crane President and Chief Nuclear Officer Exelon Nuclear Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

ANNUAL ASSESSMENT LETTER - BRAIDWOOD STATION UNITS 1 AND 2 (REPORT 05000456/200501; 05000457/200501)

Dear Mr. Crane:

On February 9, 2005, the NRC staff completed its end-of-cycle plant performance assessment of Braidwood Station Units 1 and 2. The end-of-cycle review for Braidwood Station involved the participation of the reactor technical divisions in evaluating performance indicators (PIs) for the most recent quarter and inspection results for the period from January 1 through December 31, 2004. 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 so that you will have an opportunity to prepare for these inspections and to inform us of any planned inspections that may conflict with your plant activities.

This performance review and enclosed inspection plan do not include physical protection information. A separate letter designated and marked as Exempt from Public Disclosure in accordance with 10 CFR 2.390 will include the physical protection review and resultant inspection plan.

Overall, Braidwood Station Units 1 and 2 operated in a manner that preserved public health and safety and fully met all cornerstone objectives. Plant performance for the most recent quarter 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 only baseline inspections at your facility through September 30, 2006.

While performance of both Units during the most recent quarter was within the licensee response column of the Action Matrix, there was a safety significant PI during the first quarter of the assessment cycle for Unit 1. The Mitigating Systems Unavailability, Heat Removal Systems (Auxiliary Feedwater - AFW) PI for Unit 1 was White during the first quarter of the assessment cycle. NRC Supplemental Inspection Procedure 95001, "Inspection for One or Two White Inputs in a Strategic Performance Area," was completed in May 2004 and documented in NRC Inspection Report 50-456/04-05. There were no findings identified and this PI returned to Green for the remaining three quarters of the assessment cycle.

C. Crane The enclosed inspection plan details the inspections, less those related to physical protection scheduled through September 30, 2006. The following infrequently performed inspections are planned to commence during the months shown: Modifications and 10 CFR 50.59 inspection in March 2005, Safety System Design and Performance Capability inspection in August 2005, Problem Identification and Resolution inspection in October 2005, Temporary Instruction (TI) 2515/150, Reactor Pressure Vessel Head and Vessel Head Penetration Nozzles (Unit 1) in April 2006, and Triennial Fire Protection inspection in July 2006. The inspection plan is provided to minimize the resource impact on your staff and to allow for scheduling conflicts and personnel availability to be resolved 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 meeting.

In accordance with 10 CFR 2.390 of the NRCs Rules 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 me at (630) 829-9872 with any questions you may have regarding this letter or the inspection plan.

Sincerely,

/RA/

Dave Passehl, Acting Chief Reactor Projects Branch 3 Division of Reactor Projects Docket Nos. 50-456, 50-457 License Nos. NPF-72, NPF-77

Enclosure:

Braidwood Station Units 1 and 2 Inspection/Activity Plan See Attached Distribution

C. Crane The enclosed inspection plan details the inspections, less those related to physical protection scheduled through September 30, 2006. The following infrequently performed inspections are planned to commence during the months shown: Modifications and 10 CFR 50.59 inspection in March 2005, Safety System Design and Performance Capability inspection in August 2005, Problem Identification and Resolution inspection in October 2005, Temporary Instruction (TI) 2515/150, Reactor Pressure Vessel Head and Vessel Head Penetration Nozzles (Unit 1) in April 2006, and Triennial Fire Protection inspection in July 2006. The inspection plan is provided to minimize the resource impact on your staff and to allow for scheduling conflicts and personnel availability to be resolved 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 meeting.

In accordance with 10 CFR 2.390 of the NRCs Rules 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 me at (630) 829-9872 with any questions you may have regarding this letter or the inspection plan.

Sincerely,

/RA/

Dave Passehl, Acting Chief Reactor Projects Branch 3 Division of Reactor Projects Docket Nos. 50-456, 50-457 License Nos. NPF-72, NPF-77

Enclosure:

Braidwood Station Units 1 and 2 Inspection/Activity Plan See Attached Distribution DOCUMENT NAME: G:\Branch TSS\EOC Ltrs\eoc 030205\Braidwood.wpd To receive a copy of this document, indicate in the box "C" = Copy w ithout att achment/enclosure "E" = Copy w ith attachment/enclosure "N "

= No copy OFFICE RIII NAME DPassehl:co DATE 03/02/05 OFFICIAL RECORD COPY

C. Crane cc w/encl: Site Vice President - Braidwood Station Plant Manager - Braidwood Station Regulatory Assurance Manager - Braidwood Station Chief Operating Officer Senior Vice President - Nuclear Services Vice President - Operations Support Vice President - Licensing and Regulatory Affairs Director Licensing Manager Licensing - Braidwood and Byron Senior Counsel, Nuclear, Mid-West Regional Operating Group Document Control Desk - Licensing Assistant Attorney General Illinois Department of Nuclear Safety State Liaison Officer Chairman, Illinois Commerce Commission

C. Crane ADAMS Distribution:

AJM GFD RidsNrrDipmIipb GEG KGO SPR CAA1 DRPIII DRSIII PLB1 JRK1 ROPreports@nrc.gov (inspection reports, final SDP letters, any letter with an IR number)

Institute of Nuclear Power Operations (INPO)

Page 1 of 2 Braidwood 02/28/2005 08:10:21 Inspection / Activity Plan Report 22 03/01/2005 - 09/30/2006 Unit No. of Staff Planned Dates Inspection Number Inspection Activity Title on Site Start End Type MOD/5059 - MODIFICATIONS/50.59 INSPECTION 5 1, 2 IP 7111102 Evaluation of Changes, Tests, or Experiments 03/14/2005 03/18/2005 Baseline Inspections 1, 2 IP 7111117B Permanent Plant Modifications 03/14/2005 03/18/2005 Baseline Inspections OUTAGE - ACCESS CONTROL, ALARA 1 1, 2 IP 7112101 Access Control to Radiologically Significant Areas 04/18/2005 04/29/2005 Baseline Inspections 1, 2 IP 7112102 ALARA Planning and Controls 04/18/2005 04/29/2005 Baseline Inspections 71122.01 - EFFLUENTS AND ACCESS CONTROL 1 1, 2 IP 7112101 Access Control to Radiologically Significant Areas 07/11/2005 07/15/2005 Baseline Inspections 1, 2 IP 7112103 Radiation Monitoring Instrumentation and Protective Equipment 07/11/2005 07/15/2005 Baseline Inspections 1, 2 IP 7112201 Radioactive Gaseous and Liquid Effluent Treatment and Monitoring Systems 07/11/2005 07/15/2005 Baseline Inspections MAINT - BIENNIAL MAINTENANCE RULE INSPECTION 1 1, 2 IP 7111112B Maintenance Effectiveness 08/08/2005 08/12/2005 Baseline Inspections SSDPC - SAFETY SYSTEM DESIGN & PERFORMANCE 6 1, 2 IP 7111121 Safety System Design and Performance Capability 08/15/2005 09/02/2005 Baseline Inspections 71114 - BASELINE EP INSPECTION 1 1, 2 IP 7111402 Alert and Notification System Testing 08/08/2005 08/12/2005 Baseline Inspections 1, 2 IP 7111403 Emergency Response Organization Augmentation Testing 08/08/2005 08/12/2005 Baseline Inspections 1, 2 IP 7111405 Correction of Emergency Preparedness Weaknesses and Deficiencies 08/08/2005 08/12/2005 Baseline Inspections 1, 2 IP 71151 Performance Indicator Verification 08/08/2005 08/12/2005 Baseline Inspections 71122.03 - REMP, PI VERIFICATION 1 1, 2 IP 7112203 Radiological Environmental Monitoring Program 08/22/2005 08/26/2005 Baseline Inspections 1, 2 IP 71151 Performance Indicator Verification 08/22/2005 08/26/2005 Baseline Inspections 71111.11 - LIC OPERATOR REQUAL PROGRAM EVALUATION 2 1, 2 IP 7111111B Licensed Operator Requalification Program 09/12/2005 09/16/2005 Baseline Inspections PI&R - PROBLEM IDENTIFICATION AND RESOLUTION 3 1, 2 IP 71152B Identification and Resolution of Problems 10/16/2005 11/04/2005 Baseline Inspections ISI - BRAIDWOOD UNIT 1 ISI & TI-150 INSPECTION 2 1 IP 2515/150 Reactor Pressure Vessel Head and Vessel Head Penetration Nozzles (NRC Bulletin 2002-02 04/10/2006 04/27/2006 Safety Issues 1 IP 7111108P Inservice Inspection Activities - PWR 04/10/2006 04/27/2006 Baseline Inspections OUTAGE - ALARA, ACCESS CONTROL 1 1, 2 IP 7112101 Access Control to Radiologically Significant Areas 04/10/2006 04/21/2006 Baseline Inspections 1, 2 IP 7112102 ALARA Planning and Controls 04/10/2006 04/21/2006 Baseline Inspections FPI - TRIENNIAL FIRE PROTECTION INSPECTION 3 1, 2 IP 7111105T Fire Protection 07/24/2006 08/11/2006 Baseline Inspections This report does not include INPO and OUTAGE activities.

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

Page 2 of 2 Braidwood 02/28/2005 08:10:21 Inspection / Activity Plan Report 22 03/01/2005 - 09/30/2006 Unit No. of Staff Planned Dates Inspection Number Inspection Activity Title on Site Start End Type IP 71114 - EP EXERCISE BASELINE 2 1, 2 IP 7111401 Exercise Evaluation 08/07/2006 08/11/2006 Baseline Inspections 1, 2 IP 71151 Performance Indicator Verification 08/07/2006 08/11/2006 Baseline Inspections ROUTINE - INSTRUMENTATION, ACCESS CONTROL 1 1, 2 IP 7112101 Access Control to Radiologically Significant Areas 08/07/2006 08/11/2006 Baseline Inspections 1, 2 IP 7112103 Radiation Monitoring Instrumentation and Protective Equipment 08/07/2006 08/11/2006 Baseline Inspections This report does not include INPO and OUTAGE activities.

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