IR 05000456/2006004

Errata to IR 05000456-06-004, 05000457-06-004, on 07/01/2006 - 09/30/2006, Braidwood, Units 1 & 2; Fire Protection

ML063210198
Person / Time
Site:	Braidwood
Issue date:	11/16/2006
From:	Richard Skokowski Reactor Projects Branch 3
To:	Crane C Exelon Generation Co, Exelon Nuclear
References
IR-06-004
Download: ML063210198 (5)

Text

ber 16, 2006

SUBJECT:

ERRATA TO BRAIDWOOD STATION, UNITS 1 AND 2 NRC INTEGRATED INSPECTION REPORT 05000456/2006004; 05000457/2006004

Dear Mr. Crane On November 8, 2006, the U. S. Nuclear Regulatory Commission (NRC) issued integrated Inspection Report 05000456/2006004; 05000457/2006004 (ML063120601)

for your Braidwood Station, Units 1 and 2. The Summary of Findings had incorrectly specified the inspection report period.

The enclosed Summary of Findings contains the corrected page 1 (marked revised).

Please insert the enclosed page 1 to replace the current page 1 in Inspection Report 05000456/2006004; 05000457/2006004. Please remove and dispose of the original page 1.

We apologize for any inconvenience to you and your staff.

Sincerely,

/RA by Desiree R. Smith for/

Richard A. Skokowski, Chief Projects Branch 3 Division of Reactor Projects Docket Nos. 50-456; 50-457 License Nos. NPF-72; NPF-77 Enclosure: Revised Summary of Findings to Inspection Report No. 05000456/2006004; 05000457/2006004 DISTRIBUTION:

See next page

C. Crane -2-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 Director Licensing Manager Licensing - Braidwood and Byron Senior Counsel, Nuclear, Mid-West Regional Operating Group Document Control Desk - Licensing Assistant Attorney General Illinois Emergency Management Agency State Liaison Officer Chairman, Illinois Commerce Commission

SUBJECT:

ERRATA TO BRAIDWOOD STATION, UNITS 1 AND 2 NRC INTEGRATED INSPECTION REPORT 05000456/2006004; 05000457/2006004

Dear Mr. Crane On November 8, 2006, the U. S. Nuclear Regulatory Commission (NRC) issued integrated Inspection Report 05000456/2006004; 05000457/2006004 (ML063120601)

for your Braidwood Station, Units 1 and 2. The Summary of Findings had incorrectly specified the inspection report period.

The enclosed Summary of Findings contains the corrected page 1 (marked revised).

Please insert the enclosed page 1 to replace the current page 1 in Inspection Report 05000456/2006004; 05000457/2006004. Please remove and dispose of the original page 1.

We apologize for any inconvenience to you and your staff.

Sincerely, Richard A. Skokowski, Chief Projects Branch 3 Division of Reactor Projects Docket Nos. 50-456; 50-457 License Nos. NPF-72; NPF-77 Enclosure: Revised Summary of Findings to Inspection Report No. 05000456/2006004; 05000457/2006004 DISTRIBUTION:

See next page DOCUMENT NAME:C:\FileNet\ML063210198.wpd G Publicly Available G Non-Publicly Available G Sensitive G 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 RIII NAME DSmith:dtp RSkokowski

• DRS for DATE 11/16/06 11/16/06 OFFICIAL RECORD COPY

SUMMARY OF FINDINGS IR 05000456/2006004, 05000457/2006004; 07/01/2006 - 09/30/2006; Braidwood Station, Units 1 & 2; Fire Protection.

This report covers a 3-month period of inspection by resident inspectors and announced baseline inspections by regional inspectors in Temporary Instruction (TI) 2515/169, Mitigating Systems Performance Index Verification. One Green finding, which was a non-cited violation was identified. The significance of most findings is indicated by their color (Green, White, Yellow, Red) using Inspection Manual Chapter (IMC) 0609, Significance Determination Process (SDP). Findings for which the SDP does not apply may be Green or be assigned a severity level after NRC management review. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 3, dated July 2000.

A. Inspector-Identified and Self-Revealed Findings Cornerstone: Mitigating Systems Green. The inspectors identified a non-cited violation of Braidwood Facility Operating License Nos. NPF-72 and NPF-77, Condition 2.E, for failing to maintain electrical supervision for fire doors between the diesel generator rooms and their associated ventilation shaft rooms as required by the approved Fire Protection Report. The diesel generator rooms were protected by automatic total flooding gas suppression systems for which NRC fire protection regulations require electrical supervision or that a justification for an exception be given in the Fire Protection Report. The licensee had taken no exception for those doors. The licensee entered the issue into its corrective action program for resolution, and evaluated the condition as being acceptable in the interim due to frequent surveillance of the doors and the infrequency of their use.

This finding was more than minor because it affected the Mitigating Systems Cornerstone objective to ensure that external factors (i.e., fire, flood, etc) do not impact the availability, reliability, and capability of systems that respond to initiating events. The finding was of very low safety significance because the issue only affected suppression, not detection or ignition, and a review of the history of the doors indicated that finding them open during the daily surveillances was extremely rare. In addition, failure of the gaseous suppression system to extinguish a diesel room fire due to one of the doors being open, would not lead to the fire spreading to other areas except for the ventilation shaft, which was in the same fire zone. (Section 1R05)

B. Licensee-Identified Violations A violation of very low safety significance, which was identified by the licensee has been reviewed by the inspectors. Corrective actions taken or planned by the licensee have been entered into the licensees corrective action program. This violation and corrective actions are listed in Section 4OA7 of this report.

1 - Revised Enclosure