Event Notification Report for July 19, 1999
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
07/18/1999 - 07/19/1999
EVENT NUMBERS
35934359353593235952
Other Nuclear Material
Event Number: 35934
Rep Org: ER SQUIBB & SONS
Licensee: ER SQUIBB & SONS
Region: 1
City: NEW BRUNSWICK State: NJ
County:
License #: 2900139-02
Agreement: N
Docket:
NRC Notified By: MICHAEL VALA
HQ OPS Officer: DOUG WEAVER
Licensee: ER SQUIBB & SONS
Region: 1
City: NEW BRUNSWICK State: NJ
County:
License #: 2900139-02
Agreement: N
Docket:
NRC Notified By: MICHAEL VALA
HQ OPS Officer: DOUG WEAVER
Notification Date: 07/19/1999
Notification Time: 14:42 [ET]
Event Date: 07/19/1999
Event Time: 13:00 [EDT]
Last Update Date: 07/19/1999
Notification Time: 14:42 [ET]
Event Date: 07/19/1999
Event Time: 13:00 [EDT]
Last Update Date: 07/19/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
Person (Organization):
JAMES NOGGLE (R1)
SCOTT MOORE (NMSS)
JAMES NOGGLE (R1)
SCOTT MOORE (NMSS)
LOST PACKAGE CONTAINING 4.9 mCi OF IODINE 131
A package containing 4.9 mCi of I-131 in the form of two NaI solid dosage capsules was inadvertently picked up by the wrong courier from the licensee's facility in New Brunswick, NJ. The courier was supposed to be Delmed, but the package was in fact picked up by E. LBLINK. The licensee continues to investigate this event, but does not yet know why E. LBLINK picked up this package. The event was discovered when the courier from Delmed arrived and requested the package.
The shipment was intended for North Troy University Hospital in Manhasset, NY. The hospital has been contacted and confirmed that the shipment has not yet arrived. It was due at 1:00 p.m. today, 7/19/99. Discussions with the personnel involved revealed the E. LBLINK courier understood the package was to go to New York, even though the package was not intended for his company. The license plate of the truck was recorded and is available in the NRC Operations Center log.
The package was properly prepared and has an transportation index of 0.5.
A package containing 4.9 mCi of I-131 in the form of two NaI solid dosage capsules was inadvertently picked up by the wrong courier from the licensee's facility in New Brunswick, NJ. The courier was supposed to be Delmed, but the package was in fact picked up by E. LBLINK. The licensee continues to investigate this event, but does not yet know why E. LBLINK picked up this package. The event was discovered when the courier from Delmed arrived and requested the package.
The shipment was intended for North Troy University Hospital in Manhasset, NY. The hospital has been contacted and confirmed that the shipment has not yet arrived. It was due at 1:00 p.m. today, 7/19/99. Discussions with the personnel involved revealed the E. LBLINK courier understood the package was to go to New York, even though the package was not intended for his company. The license plate of the truck was recorded and is available in the NRC Operations Center log.
The package was properly prepared and has an transportation index of 0.5.
Power Reactor
Event Number: 35935
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: KEN GRACIA
HQ OPS Officer: DOUG WEAVER
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: KEN GRACIA
HQ OPS Officer: DOUG WEAVER
Notification Date: 07/19/1999
Notification Time: 15:48 [ET]
Event Date: 07/19/1999
Event Time: 15:05 [EDT]
Last Update Date: 07/19/1999
Notification Time: 15:48 [ET]
Event Date: 07/19/1999
Event Time: 15:05 [EDT]
Last Update Date: 07/19/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(1)(v) - OTHER ASMT/COMM INOP
10 CFR Section:
50.72(b)(1)(v) - OTHER ASMT/COMM INOP
Person (Organization):
JAMES NOGGLE (R1)
JAMES NOGGLE (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 |
EMERGENCY SIRENS INOPERABLE
A lightning strike has rendered the prompt alert system (emergency sirens) inoperable. The licensee has notified the Massachusetts Emergency Management Agency as well as the five towns in the Emergency Planning Zone. The system should be restored by tomorrow morning.
The NRC resident inspector has been notified.
A lightning strike has rendered the prompt alert system (emergency sirens) inoperable. The licensee has notified the Massachusetts Emergency Management Agency as well as the five towns in the Emergency Planning Zone. The system should be restored by tomorrow morning.
The NRC resident inspector has been notified.
Power Reactor
Event Number: 35932
Facility: GRAND GULF
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: CHRIS MILLER
HQ OPS Officer: BOB STRANSKY
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: CHRIS MILLER
HQ OPS Officer: BOB STRANSKY
Notification Date: 07/19/1999
Notification Time: 10:32 [ET]
Event Date: 07/19/1999
Event Time: 08:00 [CDT]
Last Update Date: 07/19/1999
Notification Time: 10:32 [ET]
Event Date: 07/19/1999
Event Time: 08:00 [CDT]
Last Update Date: 07/19/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(vi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(vi) - OFFSITE NOTIFICATION
Person (Organization):
ELMO COLLINS (R4)
ANN BOLAND (R2)
ELMO COLLINS (R4)
ANN BOLAND (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
OFFSITE NOTIFICATION REGARDING ANOMALY DURING RADIOGRAPHIC PROCEDURE
At approximately 0500 CDT, following the radiograph of a check valve, the source could not be retracted into its shield using the normal method. However, the radiographer was able to manually retract the source without directly handling the source. The licensee notified the State of Mississippi regarding this anomaly. The NRC resident inspector will be informed of this notification by the licensee.
At approximately 0500 CDT, following the radiograph of a check valve, the source could not be retracted into its shield using the normal method. However, the radiographer was able to manually retract the source without directly handling the source. The licensee notified the State of Mississippi regarding this anomaly. The NRC resident inspector will be informed of this notification by the licensee.
Power Reactor
Event Number: 35952
Facility: NORTH ANNA
Region: 2 State: VA
Unit: [1] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: MIKE WHALEN
HQ OPS Officer: CHAUNCEY GOULD
Region: 2 State: VA
Unit: [1] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: MIKE WHALEN
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 07/23/1999
Notification Time: 13:26 [ET]
Event Date: 07/19/1999
Event Time: 09:45 [EDT]
Last Update Date: 07/23/1999
Notification Time: 13:26 [ET]
Event Date: 07/19/1999
Event Time: 09:45 [EDT]
Last Update Date: 07/23/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
EDWARD MCALPINE (R2)
EDWARD MCALPINE (R2)
| 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 |
A LICENSEE VOLUNTARY 24 HOUR NOTIFICATION IS BEING MADE TO REPORT AN INITIAL LACK OF INDEPENDENT ANALYSIS OF BORON CONCENTRATION SAMPLES.
Dissolved boron concentration of the spent fuel pool and of the water added to the cavity of a sealed source storage cask is required to be within limits specified in ISFSI Technical Specification Section 3.2.1, Table 3-1 within 4 hours prior to commencing loading operations. The boron concentration is determined using chemical analysis of two samples analyzed by different individuals to reduce the risk that a single error could lead to not meeting the LCO.
By procedure, Sample 1 is obtained from the spent fuel pool and from the cask pit by one technician. Sample 2 is then obtained from the spent fuel pool and from the cask pit by a different technician. Sample 1 is to be analyzed by the technician who obtained Sample 2 and vice versa.
On 07/19/99, boron concentration sampling was performed prior to loading a spent fuel cask. Technician 1 obtained both cask pit samples and Technician 2 obtained both spent fuel pool samples. Technician 1 then analyzed both cask pit samples and Technician 2 analyzed both spent fuel pool samples. This is contrary to ISFSI Technical Specification Section 3.2.1. Upon realizing the lack of independence in analyzing the samples, Technician 1 analyzed the samples Technician 2 obtained and vice versa. Results of the analysis indicated acceptable dissolved boron concentrations.
The Licensee informed the NRC Resident Inspector.
Dissolved boron concentration of the spent fuel pool and of the water added to the cavity of a sealed source storage cask is required to be within limits specified in ISFSI Technical Specification Section 3.2.1, Table 3-1 within 4 hours prior to commencing loading operations. The boron concentration is determined using chemical analysis of two samples analyzed by different individuals to reduce the risk that a single error could lead to not meeting the LCO.
By procedure, Sample 1 is obtained from the spent fuel pool and from the cask pit by one technician. Sample 2 is then obtained from the spent fuel pool and from the cask pit by a different technician. Sample 1 is to be analyzed by the technician who obtained Sample 2 and vice versa.
On 07/19/99, boron concentration sampling was performed prior to loading a spent fuel cask. Technician 1 obtained both cask pit samples and Technician 2 obtained both spent fuel pool samples. Technician 1 then analyzed both cask pit samples and Technician 2 analyzed both spent fuel pool samples. This is contrary to ISFSI Technical Specification Section 3.2.1. Upon realizing the lack of independence in analyzing the samples, Technician 1 analyzed the samples Technician 2 obtained and vice versa. Results of the analysis indicated acceptable dissolved boron concentrations.
The Licensee informed the NRC Resident Inspector.