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Event Notification Report for October 20, 2010

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
10/19/2010 - 10/20/2010

** EVENT NUMBERS **


46332 46333 46345 46346 46347

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General Information or Other Event Number: 46332
Rep Org: OHIO BUREAU OF RADIATION PROTECTION
Licensee: LEE TESTING & ENGINEERING, INC
Region: 3
City: HILLIARD State: OH
County:
License #: OH31210250011
Agreement: Y
Docket:
NRC Notified By: STEPHEN JAMES
HQ OPS Officer: HOWIE CROUCH
Notification Date: 10/14/2010
Notification Time: 13:43 [ET]
Event Date: 08/30/2010
Event Time: [EDT]
Last Update Date: 10/14/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MONTE PHILLIPS (R3DO)
ANGELA MCINTOSH (FSME)

Event Text

OHIO AGREEMENT STATE REPORT - ABANDONED MOISTURE DENSITY GAUGES

The following information was obtained from the State of Ohio via email:

"On August 11, 2010, the licensee submitted a request to [the State of Ohio to] terminate their portable gauge license. On September 9, 2010, the Ohio Department of Health (ODH) was notified by a third party that Lee Testing had vacated the premises at 3530 Parkway Lane and had left behind a total of seven (7) devices containing radioactive materials. Upon contacting the building owner, it was determined that the licensee had moved out of the building sometime during the prior week, and that the keys to the building and its contents were relinquished to the building owner.

"On September 13, 2010, representatives from ODH and a licensed service provider visited the 3530 Parkway Lane location and removed the seven devices present at that location. This removal was determined to be necessary as authorized under rule 3701:1-38-06(E) of the Ohio Administrative Code (OAC). The seven devices are currently in a safe and secure storage location pending a decision on final disposition.

"ODH is conducting an ongoing investigation.

"The NRC Registry of Radioactive Sealed Sources and Devices indicates that [three Troxler Model] 3411-B gauges contain a Cs-137 source with a maximum activity of 0.33 GBq (9 mCi) and an Am-Be source with a maximum activity of 1.63 GBq (44 mCi). The Registry indicates that [Troxler Model] 3241-C gauge contains an Am-Be source with a maximum activity of 11.1 GBq (300 mCi). The Registry also indicates that the [three Humboldt Scientific Model] 5001 gauges contain a Cs-137 source with a maximum activity of 0.41 GBq (11 mCi) and an Am-Be source with a maximum activity of 1.63 GBq (44 mCi)."

Ohio Report Number: OH100494

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General Information or Other Event Number: 46333
Rep Org: OHIO BUREAU OF RADIATION PROTECTION
Licensee: RIVERSIDE METHODIST HOSPITAL
Region: 3
City: COLUMBUS State: OH
County:
License #: 02120250070
Agreement: Y
Docket:
NRC Notified By: STEPHEN JAMES
HQ OPS Officer: HOWIE CROUCH
Notification Date: 10/14/2010
Notification Time: 13:43 [ET]
Event Date: 04/06/2010
Event Time: [EDT]
Last Update Date: 10/14/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MONTE PHILLIPS (R3DO)
ANGELA MCINTOSH (FSME)

Event Text

OHIO AGREEMENT STATE REPORT - D90 DOSE LESS THAN PRESCRIBED DOSE

The following information was obtained from the State of Ohio via email:

"Note: This information is reported as a result of a special inspection performed [by the State of Ohio] on July 28 and 29, 2010, limited to the licensee's prostate implant program.

"The licensee performed a prostate seed implant on April 6, 2010. The patient was prescribed a dose of 100 Gy using Iodine-125 seeds. The D90 post implant dosimetry performed on May 12, 2010, indicated a D90 of 62.5 Gy was given. This is a difference of 37.5% from the prescribed dose. The post plan dosimetry was performed by a radiation therapist on May 12, 2010, and the results were reviewed by a medical physicist on May 18, 2010. This qualifies as a Medical Event per rule 3701:1-58-101(A)(1)(a) of the Ohio Administrative Code (OAC).

"The licensee failed to notify by telephone the Ohio Department of Health no later than the next calendar day after the discovery of the medical event, and submit a written report within fifteen days after discovery of the medical [event]. This is a violation of ODH requirements as referenced in rule 3701:1-58-101 (c) and (D)."

Ohio Report Number: OH100025

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Power Reactor Event Number: 46345
Facility: SUMMER
Region: 2 State: SC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: GEORGE ROBERTSON
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 10/19/2010
Notification Time: 17:45 [ET]
Event Date: 10/19/2010
Event Time: 08:42 [EDT]
Last Update Date: 10/19/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
RANDY MUSSER (R2DO)

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

FITNESS FOR DUTY - POSITIVE TEST FOR ALCOHOL OF CONTRACT SUPERVISOR.

"A non-licensed contract employee supervisor had a confirmed positive for alcohol during a random fitness-for-duty test. The employee's access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details."

The NRC Resident Inspector has been notified.

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Power Reactor Event Number: 46346
Facility: SAN ONOFRE
Region: 4 State: CA
Unit: [ ] [ ] [3]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: MIKE WONG
HQ OPS Officer: JOE O'HARA
Notification Date: 10/19/2010
Notification Time: 20:09 [ET]
Event Date: 10/19/2010
Event Time: 15:15 [PDT]
Last Update Date: 10/19/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
VIVIAN CAMPBELL (R4DO)

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

Event Text

VALID SPECIFIED SYSTEM ACTUATION

"On October 19, 2010, at about 1515 PDT, SONGS Unit 3 RPS channels 'B' and 'D' were tested for maintenance. During this testing, both channels were powered off, which brought in LPD/DNBR [local power density/departure from nucleate boiling] trips on both channels. There are no applicable Technical Specifications required for these RPS channels in Mode 5.

"Southern California Edison(SCE) is reporting this occurrence as a valid actuation of RPS in accordance with 10 CFR 50.72(b)(3)(iv)(a).

"SCE has taken actions to restore both channels 'B' and 'D' of RPS and cleared the RPS trip signal. At the time of this occurrence, Unit 2 was at approximately 100% power and Unit 3 was in a Steam Generator Replacement Outage, Mode 5, shutdown and cooldown with the RCS open, proceeding to Mode 6."

The NRC Resident Inspector has been notified.

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Power Reactor Event Number: 46347
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: RYAN HAMILTON
HQ OPS Officer: JOE O'HARA
Notification Date: 10/19/2010
Notification Time: 21:14 [ET]
Event Date: 10/19/2010
Event Time: 21:08 [EDT]
Last Update Date: 10/19/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
MARIE MILLER (R1DO)

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

FAILURE OF PLANT PROCESS COMPUTER DISPLAYS AND SPDS TO UPDATE

"This 8-hour non-emergency report is being made based upon requirements of 10 CFR 50.72(b)(3)(xiii) which states that the licensee shall notify the NRC as soon as practical and in all cases within eight hours of the occurrence of: 'Any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability (e.g., significant portion of control room indication, Emergency Notification System, or offsite notification system).'

"At 1308 EDT on Tuesday, October 19, 2010, the Nine Mile Point Unit 1 Control Room received the annunciator for Process Computer Trouble. At the same time, all Process Computer displays stopped updating, including the Safety Parameter Display System (SPDS).

"All Control Room panel indicators and annunciators continue to respond properly providing operators with non-computer based emergency assessment capability. An additional Plant Operator has reported to shift in accordance with Technical Specification 6.2.2.a for minimum shift complement with the process computer out of service.

"An update to this notification will be made after repairs are completed and the SPDS is returned to service."

The licensee informed the NRC Resident Inspector.

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Thursday, March 29, 2012