Event Notification Report for February 25, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
02/24/1999 - 02/25/1999
** EVENT NUMBERS **
35397 35398 35399 35400 35401
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35397 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 02/24/1999|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 15:01[EST]|
| RXTYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 02/24/1999|
+------------------------------------------------+EVENT TIME: 13:57[EST]|
| NRC NOTIFIED BY: FRANK SIENCZAK |LAST UPDATE DATE: 02/24/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |RICHARD BARKLEY R1 |
|10 CFR SECTION: | |
|ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |95 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| BOTH TRAINS OF HPCI DECLARED INOPERABLE |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "During the performance of a routine surveillance test for high pressure |
| coolant injection (HPCI) operability, feedwater booster pump 12 was secured |
| and observed to be rotating backwards. The discharge check valve failed |
| open causing reverse flow through the pump [which] resulted in both HPCI |
| trains [being declared] inoperable. When both HPCI systems are declared |
| INOP, Tech Spec 3.1.8.c requires an initiation of a shutdown within 1 hr and |
| reactor coolant pressure and temperature [to] be reduced to less [than] 110 |
| psig and saturation temp with 24 hrs." |
| |
| The initial problem was noted at 1357 EST, the determination of |
| inoperability was made at 1420 EST, and actual power reduction was started |
| at 1447 EST. The licensee is investigating the event and plans to isolate |
| the line containing the failed check valve, which will allow the HPCI system |
| to be returned to operable condition and allow maintenance on the check |
| valve. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35398 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 02/24/1999|
| UNIT: [1] [2] [] STATE: TX |NOTIFICATION TIME: 17:45[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/24/1999|
+------------------------------------------------+EVENT TIME: 16:30[CST]|
| NRC NOTIFIED BY: ALLAN GLASS |LAST UPDATE DATE: 02/24/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ELMO COLLINS R4 |
|10 CFR SECTION: | |
|AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PARTIAL LOSS OF PLANT EMERGENCY ASSESSMENT CAPABILITY |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "On 02/22/99 at 2040 [CST], the plant computer's [safety display systems] in |
| the [emergency operations facility (EOF)] and [emergency response data |
| system] datalink to the NRC stopped communicating with the plant computer. |
| These components were unavailable for use if required due to an activation |
| of the EOF as per the Emergency Plan. Investigation found that the bridge |
| which is used to link the EOF components with the plant computer had 'locked |
| up.' There was no apparent cause for the bridge to be 'locked up.' " |
| |
| Technicians had performed an outage on 02/21/99, which lasted about 5 |
| minutes. The components were working properly after the outage. The bridge |
| has been reset as of 1323 CST on 02/24/99 and is functioning properly. |
| |
| The licensee informed the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35399 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 02/24/1999|
| UNIT: [1] [] [] STATE: AZ |NOTIFICATION TIME: 19:12[EST]|
| RXTYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 02/09/1999|
+------------------------------------------------+EVENT TIME: 10:45[MST]|
| NRC NOTIFIED BY: DAN MARKS |LAST UPDATE DATE: 02/24/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ELMO COLLINS R4 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| DISCOVERY OF MISPOSITIONED OUTLET VALVES ON THE UNIT 1 ESSENTIAL CHILLERS |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "On February 9, 1999, at 0510 MST, Unit 1 essential chillers 1MECAEO1 and |
| 1MECBEO1 were started in support of maintenance work in-progress on other |
| equipment. At approximately 1045 [MST], the temperatures of the essential |
| chiller oil reservoirs were found to be reading 193�F/190�F, respectively. |
| Within the next 15 minutes, the temperatures increased to 200�F/195�F, |
| respectively. Inspections revealed that oil cooler outlet valves ECAV321 |
| and ECAV421 were required to be adjusted to bring the oil cooler |
| temperatures within the normal band of 140 - 150�F. Preliminary evaluations |
| indicate that craft personnel may have mispositioned the valves during the |
| recent installation of insulation on adjacent chiller lines. At |
| approximately 1045 MST on February 9, 1999, the valves were adjusted, and |
| the oil temperatures were returned within acceptable limits. Reasonable |
| operator actions corrected the temperature problem; however, an apparent |
| human error (valve mispositioning) did occur that could have prevented the |
| fulfillment of a safety function were it not corrected. The Unit 2 and Unit |
| 3 lube oil cooler outlet valves were inspected and found to be in the |
| correct position. |
| |
| "Engineering personnel have since evaluated the impact of the mispositioned |
| outlet valves on the essential chiller and determined that the mispositioned |
| valves could have caused the chillers to trip in approximately 6-1/2 hours. |
| Therefore, in the event of a loss of coolant accident concurrent with a loss |
| of power, the essential chillers could not have performed their intended |
| design basis function, and this event is reportable in accordance with |
| 10CFR50.72(b)(2)(iii). Reportability was determined at approximately 1445 |
| MST on February 24, 1999." |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35400 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 02/24/1999|
| UNIT: [1] [] [] STATE: VT |NOTIFICATION TIME: 19:19[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 02/24/1999|
+------------------------------------------------+EVENT TIME: 19:07[EST]|
| NRC NOTIFIED BY: JIM BROOKS |LAST UPDATE DATE: 02/24/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |RICHARD BARKLEY R1 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TORUS WATER LEVEL DETERMINED TO BE OUTSIDE DESIGN BASIS DUE TO INSTRUMENT |
| ERROR |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "During the design installation of a more accurate narrow range torus level |
| instrument, as part of our [basis for maintaining operations] process, it |
| was identified that the current level indication was 1.5 inches lower than |
| actual level. Under these conditions we had the potential to be slightly |
| outside the acceptable torus operating level band high. At this time, we |
| are within the Tech Spec limit but outside our administrative limit. With |
| the 1.5-inch discrepancy, it is likely that in the past we have unknowingly |
| operated outside the Tech Spec limit for more than 24 hours. |
| |
| "We don't feel that this is of a significant safety concern since even with |
| the 1.5-inch error, the torus level would only have been approximately 1/2 |
| inch outside the Tech Spec limit. This would still be greater than three |
| feet below a level where emergency depressurization would be required by the |
| emergency operating procedures. |
| |
| "The new indication installed by the design process has been declared |
| operable, and the instrument in error |
| has been declared inoperable. The plant has entered a 24-hour shutdown |
| [limiting condition for operation (LCO)] for being outside our |
| administrative limit as required by plant procedures. Plans are in place to |
| lower torus water level to within administrative limits and exit the 24-hour |
| LCO." |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35401 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 02/24/1999|
| UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 19:20[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 02/24/1999|
+------------------------------------------------+EVENT TIME: 16:18[EST]|
| NRC NOTIFIED BY: HARLAN HANSON |LAST UPDATE DATE: 02/24/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |RICHARD BARKLEY R1 |
|10 CFR SECTION: | |
|AMED 50.72(b)(2)(v) OFFSITE MEDICAL | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TRANSPORTED POTENTIALLY CONTAMINATED INJURED PERSON |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "At 1607 hrs on 02/24/99, a diver qualified maintenance contractor was |
| injured and transported to Salem Memorial Hospital offsite as a potentially |
| contaminated individual. The diver was performing maintenance activities on |
| plant equipment located underwater and inside the plant suppression pool. |
| While setting up a high torque machine, the diver severed his right index |
| finger. The diver was surveyed and found to be clean except for a small |
| portion of his right hand, which could not be surveyed due to the extent of |
| the injury. Radiation Protection personnel accompanied the diver to the |
| hospital, surveyed the diver upon arrival, and determined that the diver was |
| not contaminated. The severed finger tip was subsequently located, |
| determined to be contaminated, and transported to the Salem Hospital. [ ... |
| After an evaluation by hospital medical personnel, the severed finger was |
| returned to the station. ... ] The diver is currently in stable condition |
| and being monitored by hospital personnel. Diving operations and associated |
| maintenance have been suspended pending further investigation." |
| |
| The licensee notified NRC Resident Inspector and the local township |
| officials. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021