Event Notification Report for May 17, 2013

UNANALYZED CONDITION FOR REACTOR COOLANT SYSTEM TEMPERATURE BELOW REQUIRED VALUE

"On May 17, 2013 at 0439 EDT, with the unit in Mode 3, operators identified RCS temperature decreased below 551 deg. F with the reactor trip breakers closed. The condition existed for approximately one hour after which operators identified this was below the procedurally required value identified to support power range nuclear instrumentation trip operability. The condition was then immediately corrected.

"The plant remains stable in Mode 3.

"This condition is reportable pursuant to 10 CFR 50.72(b)(3)(ii)(B) for an unanalyzed condition. The NRC Senior Resident Inspector has been notified."

The reactor trip breakers were closed to support rod testing at the time this event occurred. RCS temperature was decreasing due to Terry turbine testing which was being performed at the same time. The reactor trip breakers were opened when the operators identified RCS temperature below 551 degrees. The RCS temperature was returned to above 551 degrees. This temperature limit is specified in Millstone 3 FSAR section 15.4.1, "Uncontrolled rod cluster control assembly bank withdrawal from a subcritical or low power startup condition".

The licensee notified state and local authorities.


* * * RETRACTION FROM WILLIAM BARTRON TO DONALD NORWOOD AT 1053 EDT ON 5/23/2013 * * *

"The purpose of this call is to retract the report made on May 17, 2013, Event Number 49047.

"Upon further review, the condition in which Reactor Coolant System (RCS) temperature decreased below a procedural limit while in Mode 3 did not result in an unanalyzed condition. Engineers verified that RCS boron concentration was sufficiently high that criticality could not have occurred during any inadvertent control rod withdrawal. The details of the engineering review have been provided to the NRC Senior Resident Inspector."

Notified R1DO (Gray).

PLANT PROCESS COMPUTER REMOVED FROM SERVICE FOR MAINTENANCE AND UPGRADES

"This is a non-emergency 8-hour notification for a planned loss of emergency assessment capability. This event is reportable in accordance with 10CFR50.72(b)(3)(xiii) because the work activities affects the functionality of the Plant Process Computer System. Monticello Nuclear Generating Plant will remove the Plant Process Computer System (PPCS) from service on 5/17/13 at 1527 [CDT] to perform system upgrades and planned maintenance. The PPCS system is planned to be non-functional for less than 4 hours. While the system is out of service, the Emergency Plan can still be implemented as assessment capabilities are available under alternate means and communication of the assessment results using communication equipment. ERDS will be out of service during this period. Compensatory measures for the loss will be implemented. The NRC Resident Inspector has been notified."

MASSACHUSETTS AGREEMENT STATE REPORT - MEDICAL EVENT CONCERNING GAMMA KNIFE THERAPY

A patient was undergoing a second gamma knife treatment when the treatment was delivered to the wrong side of the brain. The patient and the prescribing physician were informed. The patient received 75 Gy to the brain. No serious effects are expected.

The Commonwealth of Massachusetts will be providing an update to this event.

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.

* * * UPDATE FROM MICHAEL WHALEN TO JOHN SHOEMAKER AT 1350 EDT ON 5/20/13 * * *

The following report was received via email.

"Event Occurred on 5/17/2013 at approximately 1000 [EDT].

"With a Gamma Knife
Manufacturer: Leksell Gamma System
Model: Model 24001 Type C

"Sealed Sources information:
Manufacturer: Elekta
Model number: 43685

"Prescribed treatment was for one fraction [the daily dose] of 75 Grays to be delivered to the left side of brain. However, the right side of the brain received the treatment."

Notified R1DO (Gray) and FSME EVENTS RESOURCE via email.

EMBEDMENT DEPTH FOR SEISMIC ANCHORS INADEQUATE

"It has been determined that some instrument racks in the Containment and Auxiliary buildings do not meet their design basis capacity due to inadequate embedment depth of the seismic anchors. Assumptions made about embedment depth for a previous event were determined to be incorrect; therefore, the design basis capacity cannot be assured. This report is being made under 10 CFR 50.72(b)(3)(ii)(B), 'Unanalyzed condition'."

The licensee has notified the NRC Resident Inspector.

* * * RETRACTION ON 6/10/2013 AT 1630 EDT FROM DAVID ORTIZ TO MARK ABRAMOVITZ * * *

"Additional evaluation has determined that the instrument racks are adequately anchored. Therefore, this event is not reportable."

The licensee notified the NRC Resident Inspector.

Notified the R4DO (Gepford).

NOTIFICATION OF VALVE BODY LEAKAGE

Subject: 10CFR21 Notification on Potential Valve Body Leakage - 20 Valve Assemblies.

Crane Nuclear, Inc. has been advised by one customer about leakage on the body of an installed 2" valve assembly. The valve body identified as leaking or weeping was cast from alloy SB 148 UNS 95200.

While it was the customer that identified the valve body leakage to Crane Nuclear, a notification letter with their purchase order history was sent to Dominion / Millstone today in accordance with their purchase order notification requirements.