| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
01/21/2010 - 01/22/2010 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 45571 | Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: JEFF SCHAEFER
HQ OPS Officer: JOHN KNOKE | Notification Date: 12/15/2009
Notification Time: 18:37 [ET]
Event Date: 12/15/2009
Event Time: 14:30 [CST]
Last Update Date: 01/21/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
JACK WHITTEN (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text HELB CONFIGURATION CALCULATIONS NOT CONSISTENT WITH PREVIOUS HELB ANALYSIS
"During a review of a High-Energy Line Break (HELB) calculation, valve FBV0146 on a 3" Auxiliary Steam line, FB-093-HBD-3", was found to be kept normally open. This is not consistent with HELB analysis, which assumes flow in line FB-093-HBD-3" is restricted by an orifice plate or isolated by FBV0146. This HELB analysis classified FB-093-HBD-3" as a moderate-energy line downstream of FBV0146 as a result of line isolation.
"No orifice plate was installed, and line FB-093-HBD-3" downstream of the FBV0146 is considered a high-energy line if FBV0146 is open. A room containing line FB-093-HBD-3" downstream from FBV0146 includes several components, the most critical of which are two RCS [Reactor Coolant System] pressure transmitters in one train which are used to provide indications during post-accident conditions. This configuration is therefore outside of current HELB analysis and potentially represents a condition that significantly degrades plant safety.
"Valve FBV0146 was closed at 1522. The NRC resident inspectors have been notified."
* * * RETRACTION FROM KEITH CRIBLEZ TO VINCE KLCO ON 1/21/2010 AT 1739 * * *
"On 12/15/2009, EN #45571 provided notification that valve FBV0146 on Auxiliary Steam line FB-093-HBD-3 was found to be kept normally open. This configuration was not consistent with High Energy Line Break (HELB) analysis which assumes flow beyond this valve to be restricted or isolated.
"An engineering evaluation was subsequently performed for the rooms containing this line downstream of FBV0146. This evaluation has determined that all safety-related components in the affected rooms would be able to perform their safety functions in the event of a line break. Pipe whip, jet impingement, compartment over pressurization, flooding, and internal missiles resulting from a postulated line break would not prevent any
safety-related equipment from performing its design function.
"As supported by this evaluation, this condition does not meet the criteria for an unanalyzed condition that significantly degrades plant safety as stated in 10CFR 50.72(b)(3)(ii)(B). Therefore, the notification made on 12/15/2009 is hereby retracted.
"The [NRC] Resident Inspectors have been notified."
Notified the R4DO (Werner). |
| Power Reactor | Event Number: 45634 | Facility: SAN ONOFRE
Region: 4 State: CA
Unit: [ ] [2] [3]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: GEOFF COOK
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 01/18/2010
Notification Time: 23:43 [ET]
Event Date: 01/18/2010
Event Time: 19:50 [PST]
Last Update Date: 01/21/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
LINDA HOWELL (R4DO)
ROBERT KAHLER (NSIR)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Refueling | 0 | Refueling | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text EMERGENCY OPERATIONS FACILITY INACCESSIBLE DUE TO ROAD FLOODING
"On January 18, 2010, at about 1950 PST, the access road to the SONGS MESA facilities became flooded after a day of rain. The San Onofre Emergency Operations Facility (EOF) is located at the MESA and because of the flooding, is inaccessible to passenger vehicles. While the EOF itself is operable, in the event of an emergency at San Onofre, SCE [Southern California Edison] would direct EOF emergency responders to the alternate EOF located in Irvine, California. SCE is reporting this occurrence to the NRC in accordance with 10CFR50.72(b)(3)(xiii).
"At the time of this occurrence, Unit 2 was shutdown for a Steam Generator Replacement outage and Unit 3 was operating at about 100% power. SCE will notify the NRC Resident Inspectors about this occurrence and will provide them with a copy of this report."
* * * UPDATE FROM GEOFF COOK TO DONG PARK @ 1208 EST ON 01/19/10 * * *
"On January 18, 2010 at about 2101 PST, the MESA road flooding had dissipated sufficiently for car traffic to be passable. In the event of an emergency at San Onofre, there is no longer a need to redirect emergency responders to the alternate EOF located in Irvine, California. This report is to advise the NRC of this change in EOF access status. Also note that it is expected that rain will continue in the SONGS area during the week of January 17, 2010 and this status is subject to change.
"At the time of this occurrence, Unit 2 was shutdown for a Steam Generator Replacement Outage and Unit 3 was operating at about 100% power. SCE will notify the NRC Resident Inspectors about this occurrence and will provide them with a copy of this report."
Notified R4DO (Werner) and NSIR (Kahler).
* * * UPDATE FROM GEOFF COOK TO PETE SNYDER @ 1232 EST ON 01/21/10 * * *
"On January 20, 2009, at about 2107 PST, the access road to the SONGS MESA facilities again became flooded after a day of rain (reference NRC Operations Log Number 45634). The San Onofre Emergency Operations Facility (EOF) is located at the MESA and because of the flooding, is inaccessible to passenger vehicles. While the EOF itself is operable, in the event of an Emergency at San Onofre, SCE would direct EOF emergency responders to the alternate EOF located in Irvine California. SCE is reporting this occurrence to the NRC in accordance with 10CFR50.72(b)(3)(xiii).
"At the time of this occurrence, Unit 2 was in a Steam Generator Replacement Outage and Unit 3 was operating at about 100% power. SCE will notify the NRC resident inspectors about this occurrence and will provide them with a copy of this report."
Notified R4DO (Werner) and NSIR/EP. |
| General Information or Other | Event Number: 45637 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: HUNTSMAN CORPORATION
Region: 4
City: PORT NECHES State: TX
County:
License #: L-06107
Agreement: Y
Docket:
NRC Notified By: ANNIE BACKHAUS
HQ OPS Officer: DONG HWA PARK | Notification Date: 01/19/2010
Notification Time: 16:00 [ET]
Event Date: 01/18/2010
Event Time: 10:30 [CST]
Last Update Date: 01/19/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
GREG WERNER (R4DO)
LARRY CAMPER (FSME)
| Event Text AGREEMENT STATE REPORT - FIXED GAUGE SHUTTER STUCK IN OPEN POSITION
The shutter for a fixed nuclear gauge located 30 feet off the ground was attempted to be closed. The handle sheared off and the shutter remained stuck in the open position. The repair facility has been contacted and repairs are expected to be made in 5-7 days. No exposures resulted from this incident.
The gauge was from Ohmart/VEGA Corporation containing a 375 milliCurie Cesium (Cs) - 137 source.
Texas Incident: I-8702 |
| Power Reactor | Event Number: 45647 | Facility: SALEM
Region: 1 State: NJ
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN KONOVALCHICK
HQ OPS Officer: VINCE KLCO | Notification Date: 01/21/2010
Notification Time: 21:36 [ET]
Event Date: 01/21/2010
Event Time: 18:20 [EST]
Last Update Date: 01/21/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
RONALD BELLAMY (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | A/R | Y | 70 | Power Operation | 0 | Hot Standby | Event Text AUTOMATIC REACTOR TRIP DUE TO LOW STEAM GENERATOR WATER LEVEL
"On January 21, 2010, at 1820 hours, Salem Unit 2 had an Automatic Reactor Trip due to low steam generator (SG) water level in the 22 SG. Prior to the reactor trip, the 21 SG feedwater pump tripped due to low oil pressure. A turbine runback was in progress and SG levels failed to recover. [Also at the time of the reactor trip], the 22 SG feedwater pump tripped on overspeed.
"All rods fully inserted on the trip and all systems responded as designed with decay heat being removed via the Steam Dump system, with condenser vacuum maintained. All three AFW Pumps auto started due to low Steam Generator level. Following the trip, the 22 Reactor Coolant Pump (RCP) flange vibration level spiked to approximately 9 mils and returned to a normal value of 2.6 mils. 22 RCP remained in service following the trip. The 21RS12 low pressure turbine intercept valve failed to indicate closed following the turbine trip but was locally verified closed.
"Salem Unit 2 is currently in mode 3. The Reactor Coolant System temperature is 547 degrees F with pressure at 2235 psig (NOT and NOP). All ECCS and ESF Systems are available and no ECCS systems actuated during the event. No personnel injuries occurred as a result of the trip."
There is no primary to secondary leakage. The electrical shutdown configuration is normal. There was no impact on Unit-1.
The licensee notified the NRC Resident Inspector. | |