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Event Notification Report for October 11, 2007

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
10/10/2007 - 10/11/2007

** EVENT NUMBERS **


43614 43700 43704 43705 43706 43707 43708 43709 43710 43711

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Power Reactor Event Number: 43614
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: EDWARD NIELSEN
HQ OPS Officer: BILL HUFFMAN
Notification Date: 09/05/2007
Notification Time: 12:46 [ET]
Event Date: 09/05/2007
Event Time: 11:17 [EDT]
Last Update Date: 10/10/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
MIKE ERNSTES (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
3 N N 0 Cold Shutdown 0 Cold Shutdown
4 N Y 100 Power Operation 100 Power Operation

Event Text

MODIFICATION TO PROCESS COMPUTER THAT IMPACT ERDS AND SPDS

"The Plant Process Computer System (Emergency Response and Data Acquisition System, 'ERDADS') will be taken out of service for an approximate 4 week period (on Unit 3) to implement a planned modification. The current ERDADS is being replaced on Unit 3 and a computer outage is required for the installation of the new ERDADS. During this time period ERDS and SPDS functions will not be available for Unit 3. Unit 4 will function normally after a modification (expected duration 6 hours) to the existing computer operating system software is implemented. Also, Unit 3 Regulatory Guide 1.97 category 2D containment temperature and power system indicators for motor control centers, batteries, and inverters will not be available in the Control Room, although other instrumentation is available to monitor these parameters.

"This is an 8-hour reportable event per 10 CFR 50.72(b)(3)(xiii) Major Loss of Assessment Capability. The operation of plant systems will not be affected due to this planned action. ERDS and SPDS parameters will be monitored by control board indications. Compensatory actions have been developed.

"Follow up notification to NRC will be given once Unit 4 ERDS and SPDS are returned to service."

The licensee notified the NRC Resident Inspector.

* * * UPDATE PROVIDED BY JIM SPEICHER TO JEFF ROTTON AT 1031 EDT ON 09/10/07 * * *

"The Plant Process Computer System (Emergency Response and Data Acquisition System, 'ERDADS') was taken out of service on both Unit 3 and Unit 4 in order to implement a planned modification on Unit 3. The current ERDADS system is being replaced on Unit 3 during the current Unit 3 refueling outage. In order to perform this replacement, ERDS and SPDS functions had to be temporarily removed from Unit 4.

"ERDADS and SPDS functions have been returned to service on Unit 4 and have been verified to operate correctly. The ERDS link for Unit 4 was satisfactorily tested on 9/7/07.

"The ERDADS replacement on Unit 3 will continue with an estimated completion on September 24, 2007."

The licensee notified the NRC Resident Inspector. Notified R2DO (S. Shaeffer)

* * * UPDATE FROM NIELSEN TO HUFFMAN AT 1642 EDT ON 10/10/07 * * *

"The Plant Process Computer System (Emergency Response and Data Acquisition System. 'ERDADS') was taken out of service in order to implement a planned modification on Unit 3. Replacement of the ERDADS system on Unit 3 is complete. The ERDS link for Unit 3 was satisfactorily tested on 10/10/07."

The licensee notified the NRC Resident Inspector. Notified R2DO (Desai).

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General Information or Other Event Number: 43700
Rep Org: IOWA DEPARTMENT OF PUBLIC HEALTH
Licensee: PHARMACY SERVICES OF THE QUAD CITIES
Region: 3
City: DAVENPORT State: IA
County:
License #: 0207-1-82-NP
Agreement: Y
Docket:
NRC Notified By: NANCY FARMINGTON
HQ OPS Officer: JOE O'HARA
Notification Date: 10/08/2007
Notification Time: 09:53 [ET]
Event Date: 10/04/2007
Event Time: [CDT]
Last Update Date: 10/08/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
LAURA KOZAK (R3)
NADER MAMISH (FSME)

Event Text

AGREEMENT STATE REPORT - MOLYBDENUM 99 CONCENTRATION TOO HIGH ON ELUTION ON MOLYBDENUM 99/TECHNETIUM- 99M GENERATOR

The State provided the following information via email:

"Event Cause: MOLYBDENUM 99 CONCENTRATION TOO HIGH ON ELUTION ON MOLYBDENUM 99/TECHNETIUM- 99M GENERATOR

"Event Date: 10/04/2007 Report Date: 10/05/2007

"Licensee/Reporting Party Information:

"Name: PHARMACY SERVICES OF THE QUAD CITIES, License Number: 0207-1-82-NP, DAVENPORT, IA 52807

"IDPH received a call from the Pharmacy Services of Quad Cities RSO on Friday, October 5, 2007, concerning a Bristol-Myers Squibb (BMS) Mo99/Tc99M generator that they had received on Wednesday, October 3, 2007. The licensee first eluted the generator on Thursday, October 4, 2007, and discovered an elevated Mo99 concentration in the elution. Subsequent elutions also had elevated Mo99 concentrations. The licensee contacted the manufacturer (BMS) and was asked to ship the generator back to the manufacturer. The licensee contacted IDPH concerning the shipping container. An Information Notice that was issued in 1997 talks to this issue, and IDPH told the licensee to hold the generator 10 1/2 lives or a special salvage container would be needed to ship the generator back to BMS."

The State reported that elutions greater than .15 micro Curies per milli Curie Tc-99m are unacceptable and exceed establish limits. See Information Notice No. 84-85: 'Molybdenum Breakthrough From Technetium-99m Generators' Also a state representative said that the lot number of this generator was "M275711D," the size was 15 curies, the calibration date is 10/2 and the expiration date is 10/6.

"As of Monday October 8, 2007, the generator is being held at the pharmacy.

"Corrective Actions: Action Number: 1 MANUFACTURER WILL NOTIFY CUSTOMERS OF DEFECT

"Keywords: ELEVATED MO99 CONCENTRATION FROM GENERATOR ELUTION

"Source of Radiation: Source Number: 1 Form of Radioactive: ELEVATED MO99 CONCENTRATION

"Radionuclide or Voltage (kVp/MeV): MO-99

"Source Use: RADIOPHARMACEUTICAL

"Manufacturer: BRISTOL-MEYERS SQUIB

"Device/Associated Equipment: Device Number: 1

"Device Name: RADIOPHARMACEUTICAL GENERATOR

"Manufacturer: BRISTOL-MEYERS SQUIB

"Problem with Equipment: ELEVATED MO99

"Reporting Requirements: 30.50(b)(2)(ii) - The 24 hour report of an event where required equipment is disabled or fails to function as designed when the equipment is required to be available and operable when it is disabled or fails to function.

"Iowa Event # IA070004"

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Research Reactor Event Number: 43704
Facility: PENNSYLVANIA STATE UNIVERSITY
RX Type: 1000 KW TRIGA MARK III
Comments:
Region: 1
City: UNIVERSITY PARK State: PA
County: CENTRE
License #: R-2
Agreement: N
Docket: 05000005
NRC Notified By: MARK TRUMP
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 10/09/2007
Notification Time: 16:45 [ET]
Event Date: 10/09/2007
Event Time: 16:00 [EDT]
Last Update Date: 10/10/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
INFORMATION ONLY
Person (Organization):
WILLIAM COOK (R1)
MARVIN MENDONCA (NRR)
ALEXANDER ADAMS (NRR)
SCOTT FLANDERS (FSME)
MARK CUNNINGHAM (NRR)

Event Text

POSSIBLE LEAK AT PENN STATE RESEARCH REACTOR

Pennsylvania State University Operations personnel noticed increased makeup at the Breazeale (Triga) reactor, an open pool reactor. At 1600, the leak rate was measured at approximately ten gallons per hour. The Pennsylvania Department of Environmental Health was notified of the probable leak to the environment (possibly to the ground around the containment pool). The licensee has not reached any required reporting criteria.

Water activity:
Gross Alpha: less than minimum detectable
Gross Beta: approx. 3.8 picoCuries/liter
Chromium Gamma: approx. 103 picoCuries/liter


* * * UPDATE FROM MARVIN MENDONCA VIA E-MAIL TO JOE O'HARA AT 0606 ON 10/10/07 * * *

Mark A. Trump, Associate Director of Operations, Breazeale Nuclear Reactor Radiation Science and Engineering Center Pennsylvania State University, University Park, PA 16801 provided the following information to Marvin Mendonca via e-mail at 0536 on 10/10/07.

"At approximately 1600 hrs on 10/9/07 review of water inventory data on the reactor pool indicates a probable leak of approximately 10 gallons per hour from the approximately 71,000 gallon pool. A walk down of reactor systems does not show any signs of leakage into any interfacing systems leading to a probable conclusion that the leak is through the concrete pool wall into the biological shielding (earthen wall). This leakage amount is well within normal makeup system capacity and is at the low threshold of our ability to determine the leakage due to variables such as evaporation rates.

"The reactor is in a safe condition, all reactor pool water chemistry is normal but notification is being done to the PA Department of Environmental Protection (as required).

"Notification of the NRC operational department is also being made concurrently. Notification number 43704."

Notified R1DO(Cook), NRR(Mendonca), NRR(Adams), FSME(Flanders), and NRR(Cunningham).

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Power Reactor Event Number: 43705
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [ ] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: EDDIE NEVILLE
HQ OPS Officer: JASON KOZAL
Notification Date: 10/10/2007
Notification Time: 05:35 [ET]
Event Date: 10/10/2007
Event Time: 00:00 [EDT]
Last Update Date: 10/10/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
BEINOY DESAI (R2)

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

Event Text

LOSS OF ERDADS AND ERDS LINK

"The Emergency Response and Data Acquisition System (ERDADS) was out of service at 0000 EST on 10/10/2007. This resulted in a loss of the ERDS link of plant data to the NRC. This is an 8-hour reportable event pursuant to 10CFR50.72(b)(3)(xiii) Major Loss of Assessment Capability. The cause of the loss appears to be a computer malfunction, there is no evidence of tampering. Follow-up notification to the NRC will be given once Unit 4 ERDS is returned to service."

As of 0515 ERDADS was available in the licensee control room, but the ERDS link was not available with the NRC.

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 43706
Facility: CRYSTAL RIVER
Region: 2 State: FL
Unit: [3] [ ] [ ]
RX Type: [3] B&W-L-LP
NRC Notified By: RICK RAWLS
HQ OPS Officer: BILL HUFFMAN
Notification Date: 10/10/2007
Notification Time: 14:09 [ET]
Event Date: 10/10/2007
Event Time: 13:12 [EDT]
Last Update Date: 10/10/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
INFORMATION ONLY
OTHER UNSPEC REQMNT
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
BEINOY DESAI (R2)
MARY JANE ROSS-LEE (NRR)
TOM BLOUNT (IRD)

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

Event Text

PRESSURIZER PORV OPENED MOMENTARILY WITH RCS DISCHARGE OF APPROXIMATELY 10 GALLONS

"On 10/10/2007 at 1312, Crystal River Unit 3 was performing maintenance on its Pressurizer Pilot Operated Relief Valve (PORV). The I&C technicians were replacing a circuit board card in the circuitry for the PORV. The PORV had been selected to close during the replacement of the card. When the PORV was selected to its auto position, the PORV opened and was immediately closed by the reactor operator. It was estimated that the PORV was opened for 2 second with a total flow of 10 gallons. This rate is in excess of the 25 gpm as found in the EAL. The event was quickly terminated with the closing of the PORV and PORV block valve. The plant remains stable with the PORV and PORV block valve closed. CR3 briefly met the conditions of an Unusual Event, however declaration was not required."

The licensee is still trouble-shooting the cause of the event. The reactor is stable at full power and the technical specification action statement requirement for an inoperable PORV valve (TS 3.4.10) have been satisfied. The licensee reported this event for information based on the guidance of NUREG 1022 concerning reporting an event that was rapidly terminated that may have met the criteria of an emergency based on an after the fact review.

The licensee notified the State and local authorities and the NRC Resident Inspector.

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Other Nuclear Material Event Number: 43707
Rep Org: ECS MID-ATLANTIC
Licensee: ECS MID-ATLANTIC
Region: 1
City: MIDLOTHIAN State: VA
County:
License #: 45-25239-01
Agreement: N
Docket:
NRC Notified By: DON LONGEST
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 10/10/2007
Notification Time: 14:22 [ET]
Event Date: 10/08/2007
Event Time: 16:30 [EDT]
Last Update Date: 10/10/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
WILLIAM COOK (R1)
GREG MORELL (FSME)

Event Text

TROXLER MOISTURE DENSITY GAUGE DAMAGED

A Troxler moisture density gauge was damaged by construction equipment in Midlothian, VA (NW corner of Midlothian Turnpike and Route 288). The plastic shell was damaged, but there was no damage to the rod or housing. The licensee conducted a leak test and is awaiting results. No abnormal radiation levels were detected on the outside of the housing. The licensee is in possession of the gauge and is planning to ship the gauge back to the manufacturer for repair.

Troxler Model 3430
S/N: 26757
Sources: 40 milliCurie Am/Be & 8 milliCurie Cs-137
Source S/N: 47-22173 & 75-8778 (licensee uncertain which S/N is paired with each source)

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Fuel Cycle Facility Event Number: 43708
Facility: PADUCAH GASEOUS DIFFUSION PLANT
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
                   6903 ROCKLEDGE DRIVE
                   BETHESDA, MD 20817 (301)564-3200
Region: 2
City: PADUCAH State: KY
County: McCRACKEN
License #: GDP-1
Agreement: Y
Docket: 0707001
NRC Notified By: MIKE UNDERWOOD
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 10/10/2007
Notification Time: 16:16 [ET]
Event Date: 10/09/2007
Event Time: 17:00 [CDT]
Last Update Date: 10/10/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
76.120(c)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
BEINOY DESAI (R2)
SCOTT FLANDERS (FSME)

Event Text

SAFETY SYSTEM VALVE DID NOT OPERATE AS EXPECTED

"At 1700 CDT, on 10-09-07 the Plant Shift Superintendent (PSS) was notified that the C-333 Unit 4 Cell 3 freezer/sublimer computer indicated that the 'B' valve failed to unknown status. Investigation by an operator determined that the 'B' valve would not operate electrically and was in the open position. The freezer/sublimer automatically transitioned to the Hot Standby Mode (FS4) and the electrically failed 'B' valve was closed manually by an operator. The freezer/sublimer was being operated in mode FS1, the freeze mode, at the time of the failure. TSR 2.4.3.1 requires the high-high weight trip system and its associated 'B' valve to be operable in mode FS1. It was determined that the system would not have been able to perform its intended safety function with the 'B' valve disabled. This event is reportable as a 24 hour event in accordance with 10 CFR 76.120(c)(2)(i). This is an event in which equipment is disabled or fails to function as designed when: a.) the equipment is required by a TSR to prevent releases, prevent exposures to radiation and radioactive materials exceeding specified limits, mitigate the consequences of an accident, or restore this facility to a pre-established safe condition after an accident; b.) the equipment is required by a TSR to be available and operable and either should have been operating or should have operated on demand, and c.) no redundant equipment is available and operable to perform the required safety function.

"The NRC Resident Inspector has been notified of this event.

"PGDP Assessment and Tracking Report No. ATR-07-2675; PGDP Event Report No. PAD-2007-16"

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Fuel Cycle Facility Event Number: 43709
Facility: WESTINGHOUSE ELECTRIC CORPORATION
RX Type: URANIUM FUEL FABRICATION
Comments: LEU CONVERSION (UF6 to UO2)
                   COMMERCIAL LWR FUEL
Region: 2
City: COLUMBIA State: SC
County: RICHLAND
License #: SNM-1107
Agreement: Y
Docket: 07001151
NRC Notified By: DAVE PRECHT
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 10/10/2007
Notification Time: 20:20 [ET]
Event Date: 10/10/2007
Event Time: 21:00 [EDT]
Last Update Date: 10/10/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
INFORMATION ONLY
Person (Organization):
BEINOY DESAI (R2)
SCOTT FLANDERS (FSME)

Event Text

PLANNED SHUTDOWN DUE TO WATER MAIN BREAK

The licensee initiated a planned shutdown of the fuel fabrication processes, following notification from the City of Columbia (SC) of a water main break offsite from the facility. The City of Columbia will shut off the water supply from the facility at 2100 EDT to conduct repairs on the water main. This water outage is anticipated to last a few hours. The licensee can remain in this condition indefinitely. The licensee has verified that fire fighting and cooling water tanks are at capacity.

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Power Reactor Event Number: 43710
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [2] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: QUENTIN HICKS
HQ OPS Officer: JASON KOZAL
Notification Date: 10/11/2007
Notification Time: 04:25 [ET]
Event Date: 10/11/2007
Event Time: 01:00 [EDT]
Last Update Date: 10/11/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
WILLIAM COOK (R1)

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

Event Text

TONE ALERT RADIO SYSTEM OUT OF SERVICE FOR MAINTENANCE

"The tone alert radio system for Nine Mile point was taken out of service for planned maintenance. Per Site Emergency Planning procedures this constitutes a partial loss of the Public Prompt Notification System (Loss of Communication) and thus is reportable under 10 CFR 50.72 (3)(b)(xiii).

"The tone alert radio system is installed in Oswego County residences and businesses who can not hear the siren system when activated. The tone alert radio system notifies Oswego County resident of emergency situations. The tone alert radio system is maintained and operated by the National Weather Service (NWS).

"NWS estimates that the system will be out of service for approximately 6 hours. The county alert sirens, which also function as part of the public prompt Notification System, are operable."

The licensee notified the State and local governments. The licensee will notify the NRC Resident Inspector.

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Power Reactor Event Number: 43711
Facility: BRUNSWICK
Region: 2 State: NC
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: TOM HACKLER
HQ OPS Officer: JOE O'HARA
Notification Date: 10/11/2007
Notification Time: 05:20 [ET]
Event Date: 10/10/2007
Event Time: 22:45 [EDT]
Last Update Date: 10/11/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
BEINOY DESAI (R2)

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

Event Text

UNIT 2 HPCI PUMP SEAL FAILURE

"On 10/10/2007 a 2245, the Unit 2 High Pressure Coolant Injection (HPCI) Pump developed a leak of approximately 5 gpm due to a suspected pump seal failure.

"HPCI was in service for a scheduled surveillance test per plant procedure OPT-09.2, HPCI System Operability Test.

"When the leak was identified, operators secured HPCI. The leak was isolated by securing the pump, closing the pump suction isolation valves, isolating the keep fill supply valves. Operators declared the Unit 2 HPCI System inoperable when the keep fill system was isolated.

"No automatic system isolation or actuation set points were reached.

"Safety significance is minimal due to the operability and availability of redundant systems. If a Loss of Coolant Accident (LOCA) were to occur the Reactor Core Isolation Cooling (RCIC) System would automatically inject and if necessary the Automatic Depressurization System (ADS) would depressurize the reactor pressure vessel allowing low pressure Emergency Core Cooling Systems (ECCS) to inject. All low pressure ECCS are operable.

"Plant risk has been evaluated and remains 'Green'.

"The Unit 2 HPCI system has been removed from service. The pump suction isolation valves have been closed. Injection piping keep fill connections have been isolated. These actions were taken to stop the leakage of system water out of the failed pump seal.

"Actions have been taken to protect redundant safety systems, including the RCIC System and ADS.

"In accordance with Technical Specification 3.5.1 Required Actions: RCIC has been verified to be operable, and HPCI must be restored to operable status within 14 days.

"HPCI pump seal replacement is being planned in accordance with the site's Work Management process. This event has been entered into the sites Corrective Action Program and an investigation into the cause of the seal failure will be performed."

The licensee notified the NRC Resident Inspector.

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Thursday, March 29, 2012