ML050620309
| 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)
Braidwood Inspection / Activity Plan 03/01/2005 - 09/30/2006 Inspection Type Inspection Activity Planned Dates Start End No. of Staff on Site Title Unit Number Page 1 of 2 02/28/2005 08:10:21 Report 22 5
MOD/5059
- MODIFICATIONS/50.59 INSPECTION Baseline Inspections 03/14/2005 03/18/2005 Evaluation of Changes, Tests, or Experiments IP 7111102 1, 2 Baseline Inspections 03/14/2005 03/18/2005 Permanent Plant Modifications IP 7111117B 1, 2 1
OUTAGE
- ACCESS CONTROL, ALARA Baseline Inspections 04/18/2005 04/29/2005 Access Control to Radiologically Significant Areas IP 7112101 1, 2 Baseline Inspections 04/18/2005 04/29/2005 ALARA Planning and Controls IP 7112102 1, 2 1
- EFFLUENTS AND ACCESS CONTROL Baseline Inspections 07/11/2005 07/15/2005 Access Control to Radiologically Significant Areas IP 7112101 1, 2 Baseline Inspections 07/11/2005 07/15/2005 Radiation Monitoring Instrumentation and Protective Equipment IP 7112103 1, 2 Baseline Inspections 07/11/2005 07/15/2005 Radioactive Gaseous and Liquid Effluent Treatment and Monitoring Systems IP 7112201 1, 2 1
MAINT
- BIENNIAL MAINTENANCE RULE INSPECTION Baseline Inspections 08/08/2005 08/12/2005 Maintenance Effectiveness IP 7111112B 1, 2 6
SSDPC
- SAFETY SYSTEM DESIGN & PERFORMANCE Baseline Inspections 08/15/2005 09/02/2005 Safety System Design and Performance Capability IP 7111121 1, 2 1
71114
- BASELINE EP INSPECTION Baseline Inspections 08/08/2005 08/12/2005 Alert and Notification System Testing IP 7111402 1, 2 Baseline Inspections 08/08/2005 08/12/2005 Emergency Response Organization Augmentation Testing IP 7111403 1, 2 Baseline Inspections 08/08/2005 08/12/2005 Correction of Emergency Preparedness Weaknesses and Deficiencies IP 7111405 1, 2 Baseline Inspections 08/08/2005 08/12/2005 Performance Indicator Verification IP 71151 1, 2 1
- REMP, PI VERIFICATION Baseline Inspections 08/22/2005 08/26/2005 Radiological Environmental Monitoring Program IP 7112203 1, 2 Baseline Inspections 08/22/2005 08/26/2005 Performance Indicator Verification IP 71151 1, 2 2
- LIC OPERATOR REQUAL PROGRAM EVALUATION Baseline Inspections 09/12/2005 09/16/2005 Licensed Operator Requalification Program IP 7111111B 1, 2 3
- PROBLEM IDENTIFICATION AND RESOLUTION Baseline Inspections 10/16/2005 11/04/2005 Identification and Resolution of Problems IP 71152B 1, 2 2
- BRAIDWOOD UNIT 1 ISI & TI-150 INSPECTION Safety Issues 04/10/2006 04/27/2006 Reactor Pressure Vessel Head and Vessel Head Penetration Nozzles (NRC Bulletin 2002-02 IP 2515/150 1
Baseline Inspections 04/10/2006 04/27/2006 Inservice Inspection Activities - PWR IP 7111108P 1
1 OUTAGE
- ALARA, ACCESS CONTROL Baseline Inspections 04/10/2006 04/21/2006 Access Control to Radiologically Significant Areas IP 7112101 1, 2 Baseline Inspections 04/10/2006 04/21/2006 ALARA Planning and Controls IP 7112102 1, 2 3
FPI
- TRIENNIAL FIRE PROTECTION INSPECTION Baseline Inspections 07/24/2006 08/11/2006 Fire Protection IP 7111105T 1, 2 This report does not include INPO and OUTAGE activities.
This report shows only on-site and announced inspection procedures.
Braidwood Inspection / Activity Plan 03/01/2005 - 09/30/2006 Inspection Type Inspection Activity Planned Dates Start End No. of Staff on Site Title Unit Number Page 2 of 2 02/28/2005 08:10:21 Report 22 2
- EP EXERCISE BASELINE Baseline Inspections 08/07/2006 08/11/2006 Exercise Evaluation IP 7111401 1, 2 Baseline Inspections 08/07/2006 08/11/2006 Performance Indicator Verification IP 71151 1, 2 1
ROUTINE
- INSTRUMENTATION, ACCESS CONTROL Baseline Inspections 08/07/2006 08/11/2006 Access Control to Radiologically Significant Areas IP 7112101 1, 2 Baseline Inspections 08/07/2006 08/11/2006 Radiation Monitoring Instrumentation and Protective Equipment IP 7112103 1, 2 This report does not include INPO and OUTAGE activities.
This report shows only on-site and announced inspection procedures.