| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
06/26/2007 - 06/27/2007 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 43369 | Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: MATTHEW MINNICK
HQ OPS Officer: GERRY WAIG | Notification Date: 05/17/2007
Notification Time: 20:23 [ET]
Event Date: 05/17/2007
Event Time: 12:30 [EDT]
Last Update Date: 06/26/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
| Person (Organization):
NEIL PERRY (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text DEGRADED CONDITION - DEGRADATION OF PRINCIPAL SAFETY BARRIER
"Under 10CFR50.72 (b)(3)(ii)(A), the following event has been determined to be reportable. This section concerns the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded. This criteria was determined to apply to material problems that cause abnormal degradation of or stress upon a principal safety barrier (in this case, Reactor Coolant System).
"On 5/17/07, a Nine Mile Point Unit 1 shutdown was in progress for forced outage inspection and repairs of the Turbine Lube Oil system. Prior to the shutdown, a discrepancy was being experienced between Reactor level readings from channel 11 and 12 Reactor Level columns. A step change increase of 2 inches of Reactor level had occurred on May 6th, 2007 on Reactor Level column 12. This change was coincident with an increase of 18 [degrees] F of the reference leg and 2 [degrees] F decrease of the variable leg. The level difference was then 5 inches with a Technical Specification limit of 6 inches based on current Drywell temperature. The condition was documented in the Corrective Action Program, compensatory actions were taken, and an Integrated Response Team was formed to investigate and determine the cause. Calculations by engineering determined a leak of 4 drops per minute could explain the observed indications.
"During the initial drywell entry a visual examination was performed on the reference leg instrumentation line associated with Reactor Level Column 12. The piping was visually examined for any evidence of leakage. The exam was performed from the bottom of the condensing pot piping to the drywell shell penetration. The examination revealed a wet area at the bottom of a 1.0 inch 90 degree pipe elbow at an associated socket weld. The weld had one drop approximately 1.0 inch from the toe of the welds on the bottom of the pipe. The drop was wiped away with a leather gloved hand, which did show evidence of leakage. After waiting approx. 15 minutes, no additional leakage was observed. Reactor pressure had been lowered to approximately 400 psig at the time of the inspection due to the Reactor shutdown in progress. The piping, welds and Reactor level column above were closely examined and no other wetness or evidence of leakage was found. Also an exam was performed below pipe weld 012 (surrounding areas) and again no evidence of leakage could be found. No staining or other discoloration could be seen. The observations were documented in the Corrective Action Program."
The licensee also provided the following information:
Location of the Leak: 12 Yarway Reactor Level Reference Leg
Leak Rate: 1 drop per minute
T.S. Limits: 5 gallons per minute
Sudden or Long-term Development: Sudden
Leak Start Date: 5-06-2007
Time: 08:10 a.m. EDT
Coolant Activity: 2.02 E-3 microcuries/ml
Secondary: N/A
List of Safety Related Equipment Not Operational: None
The licensee has notified the NRC Resident Inspector.
* * * UPDATE AT 1705 EDT ON 06/26/07 FROM BRIAN FINCH TO J. ROTTON * * *
The licensee is retracting this report based on the following:
"Following plant shutdown the piping segment from the 12 Yarway Reactor Water Level Reference Leg initially believed to be leaking was removed from the station for examination and testing. The piping segment was subjected to a 1600 psig nitrogen pressure test for approximately one half hour with no indications of leakage. Additional nondestructive examinations were performed which also did not show evidence of through-wall indications. Based on the exploratory nondestructive examination and leak testing completed in the field and on the removed piping segment, it was determined that there was no actual leakage in the drywell associated with the 12 Yarway Reactor Water Level Reference Leg piping. Further leak testing identified a 5 to 6 drop-per-minute leak from the drain valves associated with the 12 Yarway Reactor Water Level Reference Leg. Based on engineering analysis, this amount of leakage through the drain valve assemblies accounted for the level instrumentation differences noted between channel 11 and 12 Reactor Water Level columns.
"Following maintenance and repair activities, in-situ leak checks were performed on the reference leg piping in the drywell and the associated instrument rooms outside the drywell during plant startup on 5/22/2007 at approximately 900 psi with no leakage identified.
"Due to the leakage being identified in the valve assemblies for the level instrumentation and not in the piping inside the drywell, this issue does not represent a reportable condition under 10CFR50.72 and therefore is being retracted."
The drain valve has been repaired. The licensee informed the NRC Resident Inspector. Notified R1DO(Powell). |
| General Information or Other | Event Number: 43434 | Rep Org: OR DEPT OF HEALTH RAD PROTECTION
Licensee: OREGON HEALTH SCIENCE UNIVERSITY
Region: 4
City: PORTLAND State: OR
County:
License #: ORE-90013
Agreement: Y
Docket:
NRC Notified By: TERRY LINDSEY
HQ OPS Officer: JEFF ROTTON | Notification Date: 06/20/2007
Notification Time: 18:54 [ET]
Event Date: 06/18/2007
Event Time: 16:00 [PDT]
Last Update Date: 06/20/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
BLAIR SPITZBERG (R4)
JACK DAVIS (FSME)
| Event Text OREGON AGREEMENT STATE REPORT - POTENTIAL UNDERDOSE TREATMENT TO LIVER
"Written order was requested for a therapy dose of 2.45 GBq (66.2 milliCuries) of Y-90 TheraSphere for treatment to the patient's liver. 1.74 GBq (47 milliCuries) was received from MDS Nordion and used for treatment. Calculation error may have contributed to under treatment with approximately 80 Gray delivered to the liver with an intended dose of 100-110 Gray. Concern to not exceed lung dose of 15 Gray achieved with treatment dose at low end of optimal range. Physician notified and will consult with patient to decide whether to conduct additional treatment."
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. |
| Other Nuclear Material | Event Number: 43446 | Rep Org: WATTS CONSTRUCTORS, LLC
Licensee: WATTS CONSTRUCTORS, LLC
Region: 4
City: HONOLULU State: HI
County: HONOLULU
License #: 53-27792-01
Agreement: N
Docket:
NRC Notified By: RYAN TERAYAMA
HQ OPS Officer: STEVE SANDIN | Notification Date: 06/26/2007
Notification Time: 20:45 [ET]
Event Date: 06/26/2007
Event Time: 13:00 [HST]
Last Update Date: 06/26/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
| Person (Organization):
GREG PICK (R4)
EDWIN HACKETT (FSME)
ILTAB (via email) ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text NUCLEAR MOISTURE DENSITY GAUGE STOLEN FROM CONSTRUCTION SITE
At approximately 1300 HST on 6/2607, the licensee discovered that their Nuclear Moisture Density Gauge, a CPN Model MC-3 Serial Number M3409007585, had been stolen from a storage shed at the construction site. The outer storage shed lock and the lock on the gauge's storage container were cut. In addition to the gauge some propane equipment was also taken. The Honolulu PD is on-site conducting an investigation.
The construction site is located on Ford Island (federal property portion) in Pearl Harbor near Building 184. The project is for NOAA with contract administration provided by Department of the Navy. The last known use of this particular gauge by the licensee was on 6/8/07. The licensee is evaluating whether to offer a reward for the return of the stolen gauge.
The licensee's RSO was informed of the theft by staff at the construction site. Notified the State of Hawaii Rad Health.
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 | |