Event Notification Report for August 01, 2000
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
07/31/2000 - 08/01/2000
EVENT NUMBERS
37201372023720337350
Power Reactor
Event Number: 37201
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [4] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: PAUL REIMERS
HQ OPS Officer: DICK JOLLIFFE
Region: 2 State: FL
Unit: [3] [4] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: PAUL REIMERS
HQ OPS Officer: DICK JOLLIFFE
Notification Date: 08/01/2000
Notification Time: 10:44 [ET]
Event Date: 08/01/2000
Event Time: 10:20 [EDT]
Last Update Date: 08/01/2000
Notification Time: 10:44 [ET]
Event Date: 08/01/2000
Event Time: 10:20 [EDT]
Last Update Date: 08/01/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(1)(ii)(B) - OUTSIDE DESIGN BASIS
10 CFR Section:
50.72(b)(1)(ii)(B) - OUTSIDE DESIGN BASIS
Person (Organization):
STEPHEN CAHILL (R2)
STEPHEN CAHILL (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
| 4 | N | Y | 100 | Power Operation | 100 | Power Operation |
- CARM ISOLATION VALVES LABELS IN CONTROL ROOM DIFFERENT THAN UFSAR DESCRIPTION -
Tables 7.5-1 and 7.5-2 of the Turkey Point UFSAR indicate that "Open/Close" position indication is provided in the control room for the containment atmosphere radiation monitor (CARM) isolation valves #SV-*-2911, #SV-*-2912 and #SV-*-2913 (containment isolation valves) in compliance with commitments related to NRC Reg Guide 1.97 (Revision 3). Contrary to this, the stated containment isolation valves are provided with "Open/Not Open" position indication in the control room.
Tech Spec LCO 3.3.3.3, Action 39 requires the licensee to restore the valves to operable status within 72 hours or isolate the related containment penetrations within 4 hours in accordance with Tech Spec 3.6.4.
Since the installed configuration does not meet the plant design as described in the UFSAR, the condition is considered to be reportable under the requirement of 10 CFR 50.72(b)(1)(ii)(B) as a condition that is outside the plant design basis.
The licensee is determining corrective actions.
The licensee notified the NRC Resident Inspector.
Tables 7.5-1 and 7.5-2 of the Turkey Point UFSAR indicate that "Open/Close" position indication is provided in the control room for the containment atmosphere radiation monitor (CARM) isolation valves #SV-*-2911, #SV-*-2912 and #SV-*-2913 (containment isolation valves) in compliance with commitments related to NRC Reg Guide 1.97 (Revision 3). Contrary to this, the stated containment isolation valves are provided with "Open/Not Open" position indication in the control room.
Tech Spec LCO 3.3.3.3, Action 39 requires the licensee to restore the valves to operable status within 72 hours or isolate the related containment penetrations within 4 hours in accordance with Tech Spec 3.6.4.
Since the installed configuration does not meet the plant design as described in the UFSAR, the condition is considered to be reportable under the requirement of 10 CFR 50.72(b)(1)(ii)(B) as a condition that is outside the plant design basis.
The licensee is determining corrective actions.
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 37202
Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [3] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: BREIDENBAUGH
HQ OPS Officer: DOUG WEAVER
Region: 1 State: PA
Unit: [2] [3] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: BREIDENBAUGH
HQ OPS Officer: DOUG WEAVER
Notification Date: 08/01/2000
Notification Time: 19:06 [ET]
Event Date: 08/01/2000
Event Time: 18:47 [EDT]
Last Update Date: 08/01/2000
Notification Time: 19:06 [ET]
Event Date: 08/01/2000
Event Time: 18:47 [EDT]
Last Update Date: 08/01/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(1)(ii)(B) - OUTSIDE DESIGN BASIS
10 CFR Section:
50.72(b)(1)(ii)(B) - OUTSIDE DESIGN BASIS
Person (Organization):
JACK MCFADDEN (R1)
JACK MCFADDEN (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 93 | Power Operation | 93 | Power Operation |
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
OUTSIDE DESIGN BASIS - EDG COOLING WATER
This report is being made pursuant to 10CFR50.72(b)(1)(ii) due to the plant being in a condition outside the design basis. During initial analysis of data acquired from the Emergency Diesel Generator (EDG) GL 89-13 testing, it has been determined that cross flow exists between the jacket water and air cooler loops on the EDGs. As a result, the air cooler heat exchanger capacity may be exceeded during a LOCA / LOOP condition when heat sink temperature is greater than approximately 80°F. Previous hot weather conditions during the summer of 1999 and early 2000 resulted in heat sink temperatures being greater than 80°F for several days. Currently, heat sink temperatures are below 80°F. The EDGs are currently operable, further analysis is being conducted to increase margin, and compensatory actions are being developed to reduce cross flow between heat exchangers.
The NRC resident has been notified.
This report is being made pursuant to 10CFR50.72(b)(1)(ii) due to the plant being in a condition outside the design basis. During initial analysis of data acquired from the Emergency Diesel Generator (EDG) GL 89-13 testing, it has been determined that cross flow exists between the jacket water and air cooler loops on the EDGs. As a result, the air cooler heat exchanger capacity may be exceeded during a LOCA / LOOP condition when heat sink temperature is greater than approximately 80°F. Previous hot weather conditions during the summer of 1999 and early 2000 resulted in heat sink temperatures being greater than 80°F for several days. Currently, heat sink temperatures are below 80°F. The EDGs are currently operable, further analysis is being conducted to increase margin, and compensatory actions are being developed to reduce cross flow between heat exchangers.
The NRC resident has been notified.
Power Reactor
Event Number: 37203
Facility: HATCH
Region: 2 State: GA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: ANDY DISMUKE
HQ OPS Officer: FANGIE JONES
Region: 2 State: GA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: ANDY DISMUKE
HQ OPS Officer: FANGIE JONES
Notification Date: 08/02/2000
Notification Time: 10:19 [ET]
Event Date: 08/01/2000
Event Time: 13:30 [EDT]
Last Update Date: 08/02/2000
Notification Time: 10:19 [ET]
Event Date: 08/01/2000
Event Time: 13:30 [EDT]
Last Update Date: 08/02/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
GEORGE BELISLE (R2)
GEORGE BELISLE (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 |
24 HOUR FITNESS FOR DUTY REPORT
Package containing small quantity of a controlled substance discovered in protected area. The licensee notified the NRC Resident Inspector.
Package containing small quantity of a controlled substance discovered in protected area. The licensee notified the NRC Resident Inspector.
General Information or Other
Event Number: 37350
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: TOLUNAY WONG ENGINEERS, INC.
Region: 4
City: HOUSTON State: TX
County:
License #: L04848-001
Agreement: Y
Docket:
NRC Notified By: JAMES OGDEN (FAX)
HQ OPS Officer: BOB STRANSKY
Licensee: TOLUNAY WONG ENGINEERS, INC.
Region: 4
City: HOUSTON State: TX
County:
License #: L04848-001
Agreement: Y
Docket:
NRC Notified By: JAMES OGDEN (FAX)
HQ OPS Officer: BOB STRANSKY
Notification Date: 09/19/2000
Notification Time: 15:32 [ET]
Event Date: 08/01/2000
Event Time: 00:00 [CDT]
Last Update Date: 09/19/2000
Notification Time: 15:32 [ET]
Event Date: 08/01/2000
Event Time: 00:00 [CDT]
Last Update Date: 09/19/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
JEFF SHACKELFORD (R4)
JOHN GREEVES (NMSS)
JEFF SHACKELFORD (R4)
JOHN GREEVES (NMSS)
AGREEMENT STATE REPORT - STOLEN TROXLER GAUGE
"Troxler Model 3430: Serial No. 26131, with the following sources: 8 millicuries Cs-137; Serial No. 75-9150 and 40 millicuries Am-241/Be; Serial No. 47-22513. Stolen from an unauthorized storage location - 16545 Loch Katrine Land, Houston, Texas (residence of the driver/operator) on July 31-August 1, 2000. A police report was made with the Houston Police Department. Texas Licensee is Tolunay Wong Engineers, Inc. (L04848-001) of Houston, Texas. Steel cables securing the gauge in the truck were cut. The gauge was stolen during the hours of darkness. The gauge has not been recovered."
"Troxler Model 3430: Serial No. 26131, with the following sources: 8 millicuries Cs-137; Serial No. 75-9150 and 40 millicuries Am-241/Be; Serial No. 47-22513. Stolen from an unauthorized storage location - 16545 Loch Katrine Land, Houston, Texas (residence of the driver/operator) on July 31-August 1, 2000. A police report was made with the Houston Police Department. Texas Licensee is Tolunay Wong Engineers, Inc. (L04848-001) of Houston, Texas. Steel cables securing the gauge in the truck were cut. The gauge was stolen during the hours of darkness. The gauge has not been recovered."