Event Notification Report for October 13, 2011

FIRE RELATED UNANALYZED CONDITION THAT COULD IMPACT EQUIPMENT CREDITED IN SAFE SHUTDOWN ANALYSIS

"In preparation for converting from 10 CFR 50, Appendix R, to NFPA (National Fire Protection Association) 805, a review of the Brunswick Steam Electric Plant (BSEP) Safe Shutdown Analysis identified conditions that may not ensure a protected train of equipment remains available under certain postulated fire scenarios. The analysis determined that a postulated fire in specific fire areas could cause spurious actuation of critical components, potentially resulting in loss of equipment required for Safe Shutdown. A fire in one of the specified fire areas could potentially adversely affect the following; Suppression Pool level instrument 2-CAC-LT-2602, Residual Heat Removal net positive suction head (i.e., Drywell Containment Overpressure), Reactor Core Isolation Cooling (RCIC), Emergency bus E-1, and Emergency bus E-3.

"The initial safety significance of this event is minimal. Fire watches have been established for the affected portions of fire areas RB2-01, RB1-01, TB1, CB-02, and CB-23E. Additionally, fire detection and suppression equipment in the affected areas is fully functional.

"Fire watches have been established for the affected portions of fire areas RB2-01, RB1-01, TB1, CB-02, and CB-23E. This condition has been entered Into the Corrective Action Program (i.e., CR 493784).

"This is reportable as an unanalyzed condition that significantly degrades plant safety in accordance with 10 CFR 50.72(b)(3)(ii)(B). Compensatory measures have been established to provide an hourly fire watch for the affected fire areas."

The licensee has notified the NRC Resident Inspector.

EMERGENCY RESPONSE DATA SYSTEM INOPERABLE

"The Unit 3 Emergency Response Data System (ERDS) communications link failed its engineering performance test. Troubleshooting [of the problem] is to commence on 10/14/11 during normal business hours."

The license has compensatory measures in place should ERDS be needed by Unit 3 prior to completion of repairs.

The NRC Resident Inspector has been notified.

AGREEMENT STATE REPORT - BROKEN HANDLE ON BERTHOLD NUCLEAR GAUGE

The following was received from the state via e-mail:

"On October 13, 2011, the Agency [Texas Department of State Health Services] was notified by the licensee that while exercising the shutter handle on a Berthold nuclear gauge containing 20 milliCuries of cesium - 137 the handle broke off flush with the gauge housing. The gauge shutter is in the open position, which is the normal operating position of the shutter. No individual will receive any additional exposure due to the failure. The manufacture has been contacted to repair the gauge. The licensee stated that no entry to the vessel will be allowed until the gauge has been repaired. The cause for the failure is unknown at this time. Additional information will be supplied as it is received in accordance with SA-300."

Texas Incident Number: I-8895

AGREEMENT STATE REPORT - DOSE MISADMINISTRATION

The following information was received by facsimile:

"NYS Incident 935 - On 10/31/2011 a NY radioactive materials licensee reported a diagnostic misadministration which occurred on 10/13/2011 and discovered on 10/28/2011. A patient undergoing diagnostic imaging of the thyroid using Iodine-123 was administered 4.21 mCi instead of the intended 400 uCi. The estimated dose to the patient's thyroid is 58 rem.

"This is a preliminary 24 hour notification report.

"The facility is performing an investigation and root cause analysis.

"Telephone communications with the facility [and the State of New York] are ongoing.

"The facility is required to submit a written report within 15 days."

New York Event: NY-11-25

A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.

FISHER CONTROLS PART 21 NOTIFICATION INTERIM REPORT - POSSIBLE DISC PIN ISSUE ON A TYPE A11 BUTTERFLY VALVE

The following information was received by facsimile:

"Pursuant to 10 CFR 21.21(a)(2), Fisher Controls International, LLC (Fisher) is providing the required written interim notification of a possible deviation or failure to comply. On October 13, 2011, Fisher became aware of a possible issue with the disc pin engagement of a 20" type A11 butterfly Valve, serial number 19102243. The affected valve was returned to Fisher for evaluation and correction and, upon correction, was returned to the customer [Clinton Power Station] on November 21, 2011.

"Fisher expects to complete its evaluation by January 31, 2012. At that time, if the evaluation reveals that a potential issue exists with the disc pin engagement, Fisher will issue a notification per the requirements of 10 CFR 21.21(b)."

* * * UPDATE AT 1539 EST ON 01/23/121 FROM GEORGE BAITINGER TO S. SANDIN * * *

This report is retracted based on the following:

"Pursuant to 10 CFR 21.21(a)(2), Fisher Controls International LLC (Fisher) is providing the required written final notification of a possible deviation or failure to comply.

"On December 13, 2011, Fisher provided an interim notification of a possible deviation or failure to comply concerning a possible issue with the disc pin engagement of a 20 inch Type A 11 butterfly valve, serial number 19102243. The affected valve was returned to Fisher for evaluation and correction and, upon correction, was returned to the customer on November 21, 2011.

"Fisher has completed the review of the valve design and has determined that this potential issue would not have negatively affected the subject valve or its performance. Therefore, Fisher will not be issuing a notification per the requirements of 10 CFR 21 21.21(b)."

Notified R3DO (Kozak) and Part 21 Group via email.