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Event Notification Report for May 6, 2008

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
05/05/2008 - 05/06/2008

** EVENT NUMBERS **


44138 44180 44184 44187 44188

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 44138
Facility: FT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: ERICK MATZKE
HQ OPS Officer: JOE O'HARA
Notification Date: 04/14/2008
Notification Time: 16:05 [ET]
Event Date: 04/14/2008
Event Time: 12:45 [CDT]
Last Update Date: 05/05/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
JEFFREY CLARK (R4)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation

Event Text

HIGH ENERGY LINE BREAK ANALYSIS REVEALED POTENTIAL ACCIDENT MITIGATION DEFICIENCY

"During review of a High Energy Line Break (HELB) analysis a condition was discovered where a break in the auxiliary steam system could result in a loss of all the containment fans and coolers, which are required to be maintained operable due to procedural restrictions to mitigate a design basis accident.

"The plant entered Technical Specification (T.S.) 2.0.1 at 1245 CDT. This specification requires a plant shutdown within 6 hours. Operations personnel isolated auxiliary steam to the affected areas of the Auxiliary Building at 1305 CDT. With auxiliary steam isolated to the Auxiliary Building, containment fans and associated coolers were restored to an operable status. Plant exited T.S. 2.0.1 at 1305 CDT."

The licensee notified the NRC Resident Inspector.

* * * RETRACTION AT 1224 EDT ON 5/5/08 FROM MATZKE TO HUFFMAN * * *

"An exhaustive review of the high energy line break licensing and design basis for the auxiliary steam system as it impacts the safety functions or the containment coolers has determined that the required safety functions are met for the licensed and designed basis of the plant. Therefore the previous notification (EN 44138) of April 14 is being withdrawn."

The licensee notified the NRC Resident Inspector. R4DO (Pick) notified.

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General Information or Other Event Number: 44180
Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: WUESTHOFF HEALTH CENTER
Region: 1
City: ROCKLEDGE State: FL
County:
License #: 0833-1
Agreement: Y
Docket:
NRC Notified By: STEVE FURNACE
HQ OPS Officer: JOE O'HARA
Notification Date: 04/30/2008
Notification Time: 16:35 [ET]
Event Date: 04/30/2008
Event Time: [EDT]
Last Update Date: 04/30/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MARIE MILLER (R1)
RICHARD TURTIL (FSME)
ILTAB VIA EMAIL ()

This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

EIGHT LOST PALLADIUM - 103 SEEDS

The State provided the following information via facsimile:

"[Florida Bureau of Radiation Control was] informed at 1600 hours that (8) Pd-103 seeds and (8) I-125 seeds, all in one box are lost. Box was labeled for a delivery to North American Scientific. Box was left in restricted area over night and was found missing the next day. Housekeeping was suspected of throwing box in the trash. Surveys were performed, dumpster was checked, and North American Scientific was contacted. No further action will be taken on this incident."

Activity of Pd-103 seeds 1.2 milliCuries per seed, I-125 seeds 0.381 microCuries per seed. Licensee is retraining staff on proper disposal procedures.

FL Incident Number: FL08-066

THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL

Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks.

This source is not amongst those sources or devices identified by the IAEA Code of Conduct for the Safety & Security of Radioactive Sources to be of concern from a radiological standpoint. Therefore is it being categorized as a less than Category 3 source

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General Information or Other Event Number: 44184
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: UNIVERSITY OF CALIFORNIA BERKELEY
Region: 4
City: BERKELEY State: CA
County:
License #: 0377-01
Agreement: Y
Docket:
NRC Notified By: KENT PRENDERGAST
HQ OPS Officer: JOE O'HARA
Notification Date: 05/01/2008
Notification Time: 18:59 [ET]
Event Date: 04/30/2008
Event Time: 11:40 [PDT]
Last Update Date: 05/01/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
GREG PICK (R4)
RICHARD TURTIL (FSME)

Event Text

AGREEMENT STATE REPORT - TWO ABANDONED ELECTRON CAPTURE DETECTORS

The State provided the following information via facsimile:

"On April 19, 2008, Urban Ore picked up a load of material from 2151 Berkeley Way, which included a gas chromatograph with an ECD [Electron Capture Detector] containing 300 mCi of Tritium. Prior to this, 2151 Berkeley Way had been sold to the University of California at Berkeley (UCB). On April 26, 2008, Urban Ore returned the gas chromatograph to the loading dock of 2151 Berkeley Way.

"On April 28, 2008, the Richmond Regional Office of RHB [Radiological Health Branch] was notified. On April 28, 2008, at 1330 the UCB RSO, and other representatives from UCB met at 2151 Berkeley Way and identified a Largus Applied Technologies gas chromatograph, with an Electron Capture Detector (ECD), Model 200 within the loading dock containing approximately 150 mCi of Tritium. Smears were taken of this ECD and no contamination was found. The group inspected the parking garage inside the building and found another ECD unit, Valco containing approximately 500 mCi of Tritium and a 0.9 uCi Radium-226 button source. Smears of this ECD identified approximately 8000 dpm of contamination at the open end of small bore exhaust tubing. The ECD reportedly came from room 100C. The Largus unit was moved from the loading to the inside of the building and labeled 'do not remove.' At 1600 on April 28, 2008, the RSO asked that all recycling work be stopped in 2151 Berkeley Way.

"The RHB was informed of the events of April 28, 2008, at about 1140 on April 29, 2008, which was followed by an email to RHB detailing the above at 1830 on April 29, 2008. On April 30, 2008, RHB has taken custody of the 2 ECDs, and met with the RSOs of UCB and DOL [Department of Labor] and other representatives of CDPH [California Department of Public Health]. A strategy for resolving this incident was worked out, and RHB offered full assistance to DOL."

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Power Reactor Event Number: 44187
Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [ ] [ ] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: NACOSTE
HQ OPS Officer: BILL HUFFMAN
Notification Date: 05/05/2008
Notification Time: 12:02 [ET]
Event Date: 05/05/2008
Event Time: 03:32 [CDT]
Last Update Date: 05/05/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
CAROLYN EVANS (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
3 N N 0 Refueling 0 Refueling

Event Text

LOSS OF POWER TO ESF BUSES DURING TRANSFER OF OFFSITE POWER SOURCE

"With Unit 3 in a refueling outage and in mode 5, as part of outage activities 4160V unit board transfers were in progress to return Unit 3 to 500KV offsite source, the 3B 4160V Unit Board failed to transfer. The loss of 3B 4160V Unit Board resulted in loss of power to 3EC and 3ED 4160V shutdown boards, 3B 480V shutdown board, 480V SBGT board, and 3B RPS. 3EC and 3ED diesel generators started and tied to the 4160V shutdown boards as required for loss of power.

"Unit 3 groups 3 and 6 isolations were received as expected. An unexpected full scram was received. An invalid A IRM actuation occurred (A channel half scram) while RPS 3B bus de-energized resulting in a full scram signal. Previous to this event all control rods were already inserted.

"This non-emergency event is reportable under 50.72(b)(3)(iv)(A)(h) - Any event or condition that results in valid actuation of emergency ac electrical power systems.

"UNIT 3 remains in Mode 5, flooded up with fuel pool gates removed and all rods are fully inserted. 3A, 3B and 3C 4160V Unit Boards and all four shutdown boards are energized.

"Units 1 and 2 were operating at 100% power and were not affected by the incident except for the common refuel zone isolation and temporary loss of control bay ventilation."

The EDGs have been restored to standby and the electrical configuration has been returned to normal.

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 44188
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [ ] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: GLENN BURGE
HQ OPS Officer: BILL HUFFMAN
Notification Date: 05/05/2008
Notification Time: 17:03 [ET]
Event Date: 05/05/2008
Event Time: 12:37 [EDT]
Last Update Date: 05/05/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
CAROLYN EVANS (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
4 N N 0 Hot Standby 0 Hot Standby

Event Text

HIGH HEAD SAFETY INJECTION MANUAL VALVE TO COLD LEG FOUND MISPOSITIONED DURING HEATUP

"This is all eight-hour non-emergency reportable event to the NRCOC in accordance with 10 CFR 50.72 (b)(3)(v)(D) for a condition that could have prevented the fulfillment of a safety function.

"High Head Safety Injection (HHSI) pump discharge to cold leg injection isolation valve 4-867 was discovered out of position while in a refueling outage (4-24.) The valve was discovered out of position on 5/5/08 at 12:37 and placed in its correct position, locked open and back-seated, at 13:07. Valve 4-867 is required to be locked open and back-seated when the reactor coolant system (RCS) temperature is greater than 380 degrees F, per Technical Specification 3.5.2. Unit 4 was in Technical Specification 3.0.3 (no OPERABLE cold leg injection flowpath for all HHSI pumps to Unit 4) for 30 minutes from time of discovery at 12:37 until correction at 13:07. Valve 4-867 was out of its required position for 5 hours and 26 minutes when the RCS was above 380 degrees F at 07:41 until it was correctly repositioned at 13:07."

The licensee notified the NRC Resident Inspector.

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Thursday, March 29, 2012