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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  

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|Power Reactor                                    |Event Number:   35397       |
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| 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  |
|                                                   |                          |
|                                                   |                          |
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                                   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 193F/190F, respectively.   |
| Within the next 15 minutes, the temperatures increased to 200F/195F,       |
| 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 - 150F.  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.                                                                   |
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