Event Notification Report for May 06, 2011
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/05/2011 - 05/06/2011
Power Reactor
Event Number: 46827
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: CHRISTINE JONES
HQ OPS Officer: PETE SNYDER
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: CHRISTINE JONES
HQ OPS Officer: PETE SNYDER
Notification Date: 05/06/2011
Notification Time: 16:46 [ET]
Event Date: 05/06/2011
Event Time: 13:00 [EDT]
Last Update Date: 05/06/2011
Notification Time: 16:46 [ET]
Event Date: 05/06/2011
Event Time: 13:00 [EDT]
Last Update Date: 05/06/2011
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):
HAROLD GRAY (R1DO)
HAROLD GRAY (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
CHANGES IN FUEL VENDOR CALCULATION METHODOLOGY TO COMPLY WITH THE ECCS PERFORMANCE REQUIREMENTS OF 10 CFR 50.46(b)
"Nine Mile Point Nuclear Station Unit 1 has been informed of a change in its fuel vendor's (General Electric Hitachi) Calculation of the Peak Cladding Temperature (PCT) and Maximum Local Oxidation (MLO). This change was required to address four individual errors and model changes identified by the fuel vendor for the previous calculation of record. Based on 10 CFR 50.46 Appendix K inputs and assumptions, correction of one of the identified errors resulted in a calculated 60 degrees F increase in PCT and a calculated 4 percent increase in MLO, which results in exceeding the PCT and MLO acceptance criteria specified in 10 CFR 50.46 (b). In addition, corrections for two of the other identified items resulted in calculated MLO values that also exceeded the MLO acceptance criterion. However, the cumulative effect of all four of the identified errors/changes was determined to result in calculated PCT and MLO values that remain within the 10 CFR 50.46(b) acceptance criteria.
"To ensure compliance with the 10 CFR 50.46 requirements, adjusted Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) limits have been implemented to maintain the PCT and MLO values within the 10 CFR 50,46(b) acceptance criteria and restore design margins. These changes were made prior to the Nine Mile Point Unit 1 startup from the recent spring 2011 refueling outage 21 through a plant monitoring system update. The updated MAPLHGR limits have also been included in the NMP1 Core Operating Limits Report (COLR) for the current operating cycle (Cycle 20), which commenced following the 2011 refueling outage. As such, Nine Mile Point Unit 1 Cycle 20 is in full compliance with the 10 CFR 50.46 requirements.
"This notification is being made in accordance with the 10 CFR 50.46(a)(3)(ii) requirement to report this issue in accordance with 10 CFR 50.72 and 10 CFR 50.73.
"Based on current core thermal power level and existing margin to limits on power operation, there is sufficient margin for analyzed accident scenarios requiring Emergency Core Cooling System (ECCS) operation, including appropriate MAPLHGR compensation, to maintain the calculated PCT and the MLO within the 10 CFR 50.46 acceptance criteria; therefore, there is no impact on safe operation of the plant. The current LOCA analysis of record remains applicable and therefore, the calculated radiological consequences are still bounded by our current safety analysis. Therefore, this event is not significant with respect to the health and safety of the public.
"The licensee has notified the NRC Resident Inspector."
"Nine Mile Point Nuclear Station Unit 1 has been informed of a change in its fuel vendor's (General Electric Hitachi) Calculation of the Peak Cladding Temperature (PCT) and Maximum Local Oxidation (MLO). This change was required to address four individual errors and model changes identified by the fuel vendor for the previous calculation of record. Based on 10 CFR 50.46 Appendix K inputs and assumptions, correction of one of the identified errors resulted in a calculated 60 degrees F increase in PCT and a calculated 4 percent increase in MLO, which results in exceeding the PCT and MLO acceptance criteria specified in 10 CFR 50.46 (b). In addition, corrections for two of the other identified items resulted in calculated MLO values that also exceeded the MLO acceptance criterion. However, the cumulative effect of all four of the identified errors/changes was determined to result in calculated PCT and MLO values that remain within the 10 CFR 50.46(b) acceptance criteria.
"To ensure compliance with the 10 CFR 50.46 requirements, adjusted Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) limits have been implemented to maintain the PCT and MLO values within the 10 CFR 50,46(b) acceptance criteria and restore design margins. These changes were made prior to the Nine Mile Point Unit 1 startup from the recent spring 2011 refueling outage 21 through a plant monitoring system update. The updated MAPLHGR limits have also been included in the NMP1 Core Operating Limits Report (COLR) for the current operating cycle (Cycle 20), which commenced following the 2011 refueling outage. As such, Nine Mile Point Unit 1 Cycle 20 is in full compliance with the 10 CFR 50.46 requirements.
"This notification is being made in accordance with the 10 CFR 50.46(a)(3)(ii) requirement to report this issue in accordance with 10 CFR 50.72 and 10 CFR 50.73.
"Based on current core thermal power level and existing margin to limits on power operation, there is sufficient margin for analyzed accident scenarios requiring Emergency Core Cooling System (ECCS) operation, including appropriate MAPLHGR compensation, to maintain the calculated PCT and the MLO within the 10 CFR 50.46 acceptance criteria; therefore, there is no impact on safe operation of the plant. The current LOCA analysis of record remains applicable and therefore, the calculated radiological consequences are still bounded by our current safety analysis. Therefore, this event is not significant with respect to the health and safety of the public.
"The licensee has notified the NRC Resident Inspector."
Power Reactor
Event Number: 46824
Facility: WATERFORD
Region: 4 State: LA
Unit: [3] [] []
RX Type: [3] CE
NRC Notified By: MICHAEL SHUMATE
HQ OPS Officer: HOWIE CROUCH
Region: 4 State: LA
Unit: [3] [] []
RX Type: [3] CE
NRC Notified By: MICHAEL SHUMATE
HQ OPS Officer: HOWIE CROUCH
Notification Date: 05/06/2011
Notification Time: 04:07 [ET]
Event Date: 05/06/2011
Event Time: 02:09 [CDT]
Last Update Date: 05/06/2011
Notification Time: 04:07 [ET]
Event Date: 05/06/2011
Event Time: 02:09 [CDT]
Last Update Date: 05/06/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
DAVID PROULX (R4DO)
BRIAN HOLIAN (NRR)
JANE MARSHALL (IRD)
DAVID PROULX (R4DO)
BRIAN HOLIAN (NRR)
JANE MARSHALL (IRD)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
DISCOVERY OF AN AFTER-THE-FACT UNUSUAL EVENT
Operators were making preparations to fill the Containment Spray System riser to support outage activities. At 0204 CDT, when Containment Spray Riser Isolation Valve CS-125A was opened, pressurizer level began to lower. The licensee suspects leak by of a valve in the Shutdown Cooling System. At 0214 CDT, the leak was stopped. Pressurizer level was lowered by 2.6%.
After reviewing the event, the licensee determined that the leak rate was greater than 25 gpm which would have resulted in a declaration of an Unusual Event under EAL CU1. Since the event had concluded, no declaration was made.
The licensee notified the NRC Resident Inspector.
Operators were making preparations to fill the Containment Spray System riser to support outage activities. At 0204 CDT, when Containment Spray Riser Isolation Valve CS-125A was opened, pressurizer level began to lower. The licensee suspects leak by of a valve in the Shutdown Cooling System. At 0214 CDT, the leak was stopped. Pressurizer level was lowered by 2.6%.
After reviewing the event, the licensee determined that the leak rate was greater than 25 gpm which would have resulted in a declaration of an Unusual Event under EAL CU1. Since the event had concluded, no declaration was made.
The licensee notified the NRC Resident Inspector.
Agreement State
Event Number: 51362
Rep Org: TENNESSEE DIV OF RAD HEALTH
Licensee: LETICA-MAUI CUP DIVISION
Region: 1
City: CLARKSVILLE State: TN
County:
License #: GL 910
Agreement: Y
Docket:
NRC Notified By: BETH SHELTON
HQ OPS Officer: MARK ABRAMOVITZ
Licensee: LETICA-MAUI CUP DIVISION
Region: 1
City: CLARKSVILLE State: TN
County:
License #: GL 910
Agreement: Y
Docket:
NRC Notified By: BETH SHELTON
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 09/02/2015
Notification Time: 15:17 [ET]
Event Date: 05/06/2011
Event Time: 00:00 [EDT]
Last Update Date: 09/02/2015
Notification Time: 15:17 [ET]
Event Date: 05/06/2011
Event Time: 00:00 [EDT]
Last Update Date: 09/02/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
JOHNATHAN LILLIENDAH (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)
JOHNATHAN LILLIENDAH (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)
AGREEMENT STATE REPORT - GAUGE SHUTTER BROKEN AND TAPED SHUT
"On September 2, 2015, inspectors from the Nashville Field Office [Tennessee Division of Radiological Health] went to Letica-Maui Cup Division in Clarksville, Tennessee to inspect their generally licensed devices. It was discovered during the inspection that one of their gauges was broken. On May 6, 2011, the shutter on the NDC model 102X (serial number 12571) broke off. The shutter was taped back into the closed position at that time and the gauge was removed from the manufacturing line. No notification was made to the Division. The gauge contains an 80 mCi Americium 241 source."
Tennessee Event: TN-15-129
"On September 2, 2015, inspectors from the Nashville Field Office [Tennessee Division of Radiological Health] went to Letica-Maui Cup Division in Clarksville, Tennessee to inspect their generally licensed devices. It was discovered during the inspection that one of their gauges was broken. On May 6, 2011, the shutter on the NDC model 102X (serial number 12571) broke off. The shutter was taped back into the closed position at that time and the gauge was removed from the manufacturing line. No notification was made to the Division. The gauge contains an 80 mCi Americium 241 source."
Tennessee Event: TN-15-129