Event Notification Report for March 01, 2002
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/28/2002 - 03/01/2002
EVENT NUMBERS
38743387413874538804
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 38743
Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: R. Kimbrough
HQ OPS Officer: GERRY WAIG
Region: 2 State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: R. Kimbrough
HQ OPS Officer: GERRY WAIG
Notification Date: 03/01/2002
Notification Time: 10:20 [ET]
Event Date: 03/01/2002
Event Time: 02:59 [EST]
Last Update Date: 03/20/2002
Notification Time: 10:20 [ET]
Event Date: 03/01/2002
Event Time: 02:59 [EST]
Last Update Date: 03/20/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
CAUDLE JULIAN (R2)
CAUDLE JULIAN (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
UNIT EXPERIENCED MOMENTARY LOSS OF RHR COOLING
"At approximately 0259 on March 1, 2002, with the Watts Bar Unit 1 reactor in Mode 6 with RCS temperature at approximately 100 degrees, during a refueling outage, operators isolated the common flowpath to the residual heat removal (RHR) pumps on two occasions over a 2 minute span. At the time of the event, operators were performing full flow testing of ECCS lines in conjunction with reactor cavity fill for refueling activities.
The circumstances of the event are currently under investigation by the Site staff."
No observable RCS heatup occurred during the period that RHR was isolated.
The NRC resident inspector was notified.
* * * RETRACTED ON 3/20/02 AT 1503 FROM PAUL PACE TO GERRY WAIG * * *
"On March 1, 2002. TVA's Watts Bar Nuclear Plant reported the following event to the NRC Operations Center under 10 CFR 50.72 (b)(3)(v)(B). (Event Number 38743):
"At approximately 0259 on March 1, 2002, with the Watts Bar unit 1 reactor in Mode 6 with RCS temperature at approximately 100 degrees, during a refueling outage, operators isolated the common fiowpath to the residual heat removal (RHR) pumps on two occasions over a 2 minute span At the time of the event, operators were performing full flow testing of ECCS lines in conjunction with reactor cavity fill for refueling activities...
"A subsequent detailed review of the event described above and the guidance of NUREG 1022 has determined that there was no 'reasonable expectation of preventing fulfillment of the safety function' to remove residual heat. Therefore the event is not considered reportable under 10CFR 50.72 and is withdrawn."
The licensee notified the NRC Resident Inspector.
The R2DO (J. Henson) notified.
"At approximately 0259 on March 1, 2002, with the Watts Bar Unit 1 reactor in Mode 6 with RCS temperature at approximately 100 degrees, during a refueling outage, operators isolated the common flowpath to the residual heat removal (RHR) pumps on two occasions over a 2 minute span. At the time of the event, operators were performing full flow testing of ECCS lines in conjunction with reactor cavity fill for refueling activities.
The circumstances of the event are currently under investigation by the Site staff."
No observable RCS heatup occurred during the period that RHR was isolated.
The NRC resident inspector was notified.
* * * RETRACTED ON 3/20/02 AT 1503 FROM PAUL PACE TO GERRY WAIG * * *
"On March 1, 2002. TVA's Watts Bar Nuclear Plant reported the following event to the NRC Operations Center under 10 CFR 50.72 (b)(3)(v)(B). (Event Number 38743):
"At approximately 0259 on March 1, 2002, with the Watts Bar unit 1 reactor in Mode 6 with RCS temperature at approximately 100 degrees, during a refueling outage, operators isolated the common fiowpath to the residual heat removal (RHR) pumps on two occasions over a 2 minute span At the time of the event, operators were performing full flow testing of ECCS lines in conjunction with reactor cavity fill for refueling activities...
"A subsequent detailed review of the event described above and the guidance of NUREG 1022 has determined that there was no 'reasonable expectation of preventing fulfillment of the safety function' to remove residual heat. Therefore the event is not considered reportable under 10CFR 50.72 and is withdrawn."
The licensee notified the NRC Resident Inspector.
The R2DO (J. Henson) notified.
Power Reactor
Event Number: 38741
Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: PHILIP CHASE
HQ OPS Officer: STEVE SANDIN
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: PHILIP CHASE
HQ OPS Officer: STEVE SANDIN
Notification Date: 03/01/2002
Notification Time: 02:29 [ET]
Event Date: 03/01/2002
Event Time: 02:16 [EST]
Last Update Date: 03/01/2002
Notification Time: 02:29 [ET]
Event Date: 03/01/2002
Event Time: 02:16 [EST]
Last Update Date: 03/01/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
Person (Organization):
JAMES LINVILLE (R1)
JAMES LINVILLE (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 87 | Power Operation | 87 | Power Operation |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
SECURITY REPORT
Unescorted access granted inappropriately to contract employee. Immediate compensatory measures taken upon discovery. The licensee will inform the NRC resident inspector. Contact the Headquarters Operations Officer for additional details.
Unescorted access granted inappropriately to contract employee. Immediate compensatory measures taken upon discovery. The licensee will inform the NRC resident inspector. Contact the Headquarters Operations Officer for additional details.
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 38745
Facility: HARRIS
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: MARK ELLINGTON
HQ OPS Officer: FANGIE JONES
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: MARK ELLINGTON
HQ OPS Officer: FANGIE JONES
Notification Date: 03/01/2002
Notification Time: 18:14 [ET]
Event Date: 03/01/2002
Event Time: 00:00 [EST]
Last Update Date: 03/27/2002
Notification Time: 18:14 [ET]
Event Date: 03/01/2002
Event Time: 00:00 [EST]
Last Update Date: 03/27/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
CAUDLE JULIAN (R2)
CAUDLE JULIAN (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 |
UNANALYZED CONDITION DUE TO FIRE BARRIERS NOT INSTALLED PER DESIGN
"On March 1, 2002, Harris Nuclear Plant personnel determined that an unanalyzed condition existed due to a required three-hour fire barrier not installed per design. The applicable fire barrier was designed to provide required separation between redundant train cables supplying A-SA Emergency Diesel Generator and B-SB Emergency Diesel Generator. Harris Nuclear Plant has initiated a continuous fire watch as a compensatory measure until the affected barrier could be restored to the design configuration. This issue is being reported in accordance with 10 CFR 50.72 as an unanalyzed condition."
The licensee notified the NRC Resident Inspector.
* * * RETRACTED ON 03/27/02 AT 1500 BY JOHN CAVES TO GERRY WAIG * * *
"Reference Event Notification (EN) # 38745. On March 1, 2002 at 1814, Harris Nuclear Plant (HNP) submitted an eight hour report per 10 CFR 50.72 (b)(3)(ii)(B) for an unanalyzed condition related to a three-hour fire barrier. HNP subsequently determined that the as-found condition is consistent with the HNP Licensing Basis. Therefore, Harris Nuclear Plant is withdrawing the report EN # 38745."
The licensee notified the NRC Resident Inspector.
R2DO (Carolyn Evans) was notified.
"On March 1, 2002, Harris Nuclear Plant personnel determined that an unanalyzed condition existed due to a required three-hour fire barrier not installed per design. The applicable fire barrier was designed to provide required separation between redundant train cables supplying A-SA Emergency Diesel Generator and B-SB Emergency Diesel Generator. Harris Nuclear Plant has initiated a continuous fire watch as a compensatory measure until the affected barrier could be restored to the design configuration. This issue is being reported in accordance with 10 CFR 50.72 as an unanalyzed condition."
The licensee notified the NRC Resident Inspector.
* * * RETRACTED ON 03/27/02 AT 1500 BY JOHN CAVES TO GERRY WAIG * * *
"Reference Event Notification (EN) # 38745. On March 1, 2002 at 1814, Harris Nuclear Plant (HNP) submitted an eight hour report per 10 CFR 50.72 (b)(3)(ii)(B) for an unanalyzed condition related to a three-hour fire barrier. HNP subsequently determined that the as-found condition is consistent with the HNP Licensing Basis. Therefore, Harris Nuclear Plant is withdrawing the report EN # 38745."
The licensee notified the NRC Resident Inspector.
R2DO (Carolyn Evans) was notified.
Hospital
Event Number: 38804
Rep Org: LEHIGH VALLEY HOSPITAL
Licensee: LEHIGH VALLEY HOSPTIAL
Region: 1
City: ALLENTOWN State: PA
County:
License #: 37-01548-01
Agreement: N
Docket:
NRC Notified By: CYNTHIA GOODMAN-MUNNA
HQ OPS Officer: MIKE NORRIS
Licensee: LEHIGH VALLEY HOSPTIAL
Region: 1
City: ALLENTOWN State: PA
County:
License #: 37-01548-01
Agreement: N
Docket:
NRC Notified By: CYNTHIA GOODMAN-MUNNA
HQ OPS Officer: MIKE NORRIS
Notification Date: 03/27/2002
Notification Time: 08:27 [ET]
Event Date: 03/01/2002
Event Time: 00:00 [EST]
Last Update Date: 03/27/2002
Notification Time: 08:27 [ET]
Event Date: 03/01/2002
Event Time: 00:00 [EST]
Last Update Date: 03/27/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
Person (Organization):
WILLIAM RULAND (R1)
FRED BROWN (NMSS)
WILLIAM RULAND (R1)
FRED BROWN (NMSS)
LOST LICENSED NUCLEAR MATERIAL >10 TIMES APPENDIX C QUANTITIES
Licensee reports that on 3/1/02, I-125 medical seeds ordered, arrived from a shipper in Texas. After the Licensee conducted their inventory, it concluded that 95 of the 96 seeds ordered had arrived. The Licensee conducted 2 searches at the hospital, with negative results, and notified the shipper of the inventory shortage. The shipper conducted inventory and searches at it's facility, also with negative results, and believes that the materials were shipped. The seeds were nominal .305 to .33 millicuries of I-125, which has a half-life of approximately 60 days. Each seed reads 450 mrem/hr on contact and 500 micro Rem/hr at 30 centimeters. The Licensee will be informing the carrier(believed to be Fed Ex at the time of report) of this lost of material.
Licensee reports that on 3/1/02, I-125 medical seeds ordered, arrived from a shipper in Texas. After the Licensee conducted their inventory, it concluded that 95 of the 96 seeds ordered had arrived. The Licensee conducted 2 searches at the hospital, with negative results, and notified the shipper of the inventory shortage. The shipper conducted inventory and searches at it's facility, also with negative results, and believes that the materials were shipped. The seeds were nominal .305 to .33 millicuries of I-125, which has a half-life of approximately 60 days. Each seed reads 450 mrem/hr on contact and 500 micro Rem/hr at 30 centimeters. The Licensee will be informing the carrier(believed to be Fed Ex at the time of report) of this lost of material.