IR 05000454/2008002

IR 05000454-08-002, 05000455-08-002, on 01/01/2008 - 03/31/2008, Byron Station, Units 1 and 2; Access Control to Radiologically Significant Areas, Problem Identification and Resolution

ML081350248
Person / Time
Site:	Byron
Issue date:	05/14/2008
From:	Richard Skokowski Region 3 Branch 3
To:	Pardee C Exelon Generation Co
References
IR-08-002
Download: ML081350248 (7)

Text

UNITED STATES May 14, 2008

SUBJECT:

BYRON STATION, UNITS 1 AND 2 NRC INTEGRATED INSPECTION REPORT 05000454/2008002; 05000455/2008002

Dear Mr. Pardee:

On March 31, 2008, the U.S. Nuclear Regulatory Commission (NRC) completed an integrated inspection at your Byron Station, Units 1 and 2. The enclosed report documents the inspection results, which were discussed on April 11, 2008, with Mr. David Hoots and other members of your staff.

The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.

The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.

Based on the results of this inspection, two NRC-identified findings of very low safety significance were identified. These findings involved violations of NRC requirements. In addition, two licensee-identified violations which were determined to be of very low safety significance are listed in this report. Because of their very low safety significance, and because the issues were entered into your corrective action program, the NRC is treating these issues as Non-Cited Violations in accordance with Section VI. A. 1 of the NRC Enforcement Policy.

If you contest the subject or severity of a Non-Cited Violation, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001, with a copy to the Regional Administrator, U.S. Nuclear Regulatory Commission - Region III, 2443 Warrenville Road, Suite 210, Lisle, IL 60532-4352; the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; and the Resident Inspector Office at the Byron Station. 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 NRCs document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/

Richard A. Skokowski, Chief Branch 3 Division of Reactor Projects Docket Nos. 50-454; 50-455 License Nos. NPF-37; NPF-66 Enclosure: Inspection Report 05000454/2008002; and 05000455/2008002 w/Attachment: Supplemental Information cc w/encl: Site Vice President - Byron Station Plant Manager - Byron Station Regulatory Assurance Manager - Byron Station Chief Operating Officer and Senior Vice President Senior Vice President - Midwest Operations Senior Vice President - Operations Support Vice President - Licensing and Regulatory Affairs Director - Licensing and Regulatory Affairs Manager Licensing - Braidwood, Byron, and LaSalle Associate General Counsel Document Control Desk - Licensing Assistant Attorney General Illinois Emergency Management Agency J. Klinger, State Liaison Officer, State of Illinois P. Schmidt, State Liaison Officer, State of Wisconsin Chairman, Illinois Commerce Commission B. Quigley, Byron Station

SUMMARY OF FINDINGS

...........................................................................................................1

REPORT DETAILS

.......................................................................................................................3 Summary of Plant Status...........................................................................................................3

REACTOR SAFETY

....................................................................................3

1R04 Equipment Alignment

................................................................3

1R05 Fire Protection

...........................................................................4

1R07 Annual Heat Sink Performance

.................................................5

1R11 Licensed Operator Requalification Program

.............................5

1R12 Maintenance Effectiveness

.......................................................6

1R18 Plant Modifications

....................................................................8

1R20 Outage Activities

.......................................................................9

1R22 Surveillance Testing

................................................................10

Radiation Protection ..................................................................................12 2OS1 Access Control to Radiologically Significant Areas (71121.01) .................12 2OS2 As-Low-As-Is-Reasonably-Achievable (ALARA) Planning And Controls (71121.02) .................................................................................................17

4OA1 Performance Indicator Verification

...............................................19

4OA2 Identification and Resolution of Problems

....................................21

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

.....................................................................................................1

LIST OF ITEMS

OPENED, CLOSED AND DISCUSSED .........................................................1

LIST OF DOCUMENTS REVIEWED

.........................................................................................2