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Event Notification Report for January 4, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           12/31/1998 - 01/04/1999

                              ** EVENT NUMBERS **

35207  35208  35209  35210  35211  35212  35213  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35207       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 12/31/1998|
|    UNIT:  [] [3] []                 STATE:  NY |NOTIFICATION TIME: 11:43[EST]|
|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        12/31/1998|
+------------------------------------------------+EVENT TIME:        10:45[EST]|
| NRC NOTIFIED BY:  ED FIRTH                     |LAST UPDATE DATE:  12/31/1998|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JACK DURR            R1      |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|3     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| CONTROL ROOM VENTILATION OUTSIDE DESIGN BASIS CALCULATION                    |
|                                                                              |
| The Licensee made the following voluntary notification:  "On December 31,    |
| 1998, while the plant was in operation, it was determined that based upon a  |
| review of a previous Nuclear Safety Evaluation (NSE-98-3-015), # 33 Safety   |
| Injection (SI) pump seal leakage placed the Control Room Ventilation System  |
| outside its system design basis calculation assumption for external          |
| recirculation system leakage (approximately 0.7 gph).  The Control Room      |
| Ventilation System continues to remain operable as per an existing           |
| Operability Determination (#98-16).  The New York Power Authority is         |
| currently evaluating repair options for this SI pump seal."                  |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35208       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WOLF CREEK               REGION:  4  |NOTIFICATION DATE: 12/31/1998|
|    UNIT:  [1] [] []                 STATE:  KS |NOTIFICATION TIME: 13:22[EST]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        12/31/1998|
+------------------------------------------------+EVENT TIME:        11:25[CST]|
| NRC NOTIFIED BY:  RICHARD HUBBARD              |LAST UPDATE DATE:  12/31/1998|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHARLES MARSCHALL    R4      |
|10 CFR SECTION:                                 |                             |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| INOPERABLE ATMOSPHERIC RELIEF VALVES                                         |
|                                                                              |
| The Licensee made the following notification:                                |
|                                                                              |
| "On December 31, I998, WCNOC concluded that due to inoperable local control  |
| of Atmospheric Relief Valve (ARV), AB PV-2, LCO 3.7.1.6 was not met  during  |
| certain periods of time.  WCNOC Technical Specifications states that at      |
| least three ARVs shall be operable and with more than one inoperable,        |
| restore to operable within 24 hours.  In addition to Technical Specification |
| requirements, the USAR requires four ARVs to be operable to meet design      |
| basis cooldown requirements.  To ensure the USAR requirements are met, WCNOC |
| has implemented Operations Special Order #17 which is more restrictive than  |
| T.S. 3.7.1.6 by one additional ARV for all cases.  This variance will be     |
| corrected when Improved Technical Specifications are implemented.  During    |
| the period when the local control was not available for AB PV-2 other ARVs   |
| have been removed from service for longer than the 24 hour LCO time.         |
| Therefore, design bases requirements for safe shut down could not have been  |
| met in the event of a fire.                                                  |
|                                                                              |
| "A local control modification was installed for two ARV to satisfy fire      |
| protection criteria in response to Generic Letter 92-08.  During maintenance |
| in June 1998, it appears that tubing, was re-installed incorrectly on the    |
| local control for AB PV-2.  This condition was discovered during normally    |
| scheduled surveillance testing on December 30/31, 1998.  Therefore, the      |
| potential operability for exceeding the LCO, was from June through December  |
| 1998.  Engineering and Maintenance are continuing to evaluate this           |
| condition.                                                                   |
|                                                                              |
| "Maintenance activities are ongoing at this time to correct the tubing       |
| installation on AB PV-2.  This work activity is expected to be completed by  |
| end of the day.  Until that time, WCGS has entered the appropriate LCO."     |
|                                                                              |
| The Licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35209       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OCONEE                   REGION:  2  |NOTIFICATION DATE: 12/31/1998|
|    UNIT:  [] [] [3]                 STATE:  SC |NOTIFICATION TIME: 15:57[EST]|
|   RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-L|EVENT DATE:        12/31/1998|
+------------------------------------------------+EVENT TIME:        14:35[EST]|
| NRC NOTIFIED BY:  REGIS REPKO                  |LAST UPDATE DATE:  12/31/1998|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |PIERCE SKINNER       R2      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|                                                   |                          |
|3     A/R        Y       100      Power Operation  |0        Hot Shutdown     |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| REACTOR TRIP DURING CONTROL ROD DRIVE BREAKER TESTING                        |
|                                                                              |
| At 1435 hours on December 31, 1998, Oconee Unit 3 reactor tripped from 100%  |
| steady state operation.  Control Rod Drive breaker testing was in progress   |
| at the time of the reactor trip.  The 3A Reactor Protective System (RPS)     |
| channel was in bypass for the breaker testing.  When the associated CRD      |
| breaker was tripped from the 3A RPS cabinet, the remaining three RPS         |
| channels actuated causing the reactor trip.  All rods fully inserted and the |
| plant responded properly to the reactor trip.  The Unit is presently stable  |
| at hot shutdown in forced circulation cooling, main feedwater supplying the  |
| steam generators, and heat is being removed through the turbine bypass       |
| valves to the main condenser.  The cause of the trip is unknown at this time |
| and under investigation.                                                     |
|                                                                              |
| The Licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35210       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM                  REGION:  1  |NOTIFICATION DATE: 12/31/1998|
|    UNIT:  [1] [] []                 STATE:  MA |NOTIFICATION TIME: 16:02[EST]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        12/31/1998|
+------------------------------------------------+EVENT TIME:        15:15[EST]|
| NRC NOTIFIED BY:  TOM McELHINNEY               |LAST UPDATE DATE:  12/31/1998|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JACK DURR            R1      |
|10 CFR SECTION:                                 |                             |
|ADEG 50.72(b)(1)(ii)     DEGRAD COND DURING OP  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| SAFETY RELATED PUMP ROOM TEMPERATURE LESS THAN DESIGN                        |
|                                                                              |
| FSAR Table 10.9-1 specifies that intake structure design temperature is  60  |
| -105F with  an outdoor temperature of 21F.  The Licensee determined that   |
| the intake structure temperature was below 60F.  Specifically, in safety    |
| related pump rooms (Salt Service Water) the temperatures were:               |
|                                                                              |
| Pump rooms A &B - 57F                                                       |
| Pump rooms D & E- 56F                                                       |
| Pump room C - 52F                                                           |
|                                                                              |
| Engineering has done a preliminary review of design requirements for         |
| safety-related equipment and has thus far shown that the equipment can       |
| perform its design function down to 32F.                                    |
|                                                                              |
| Actions are underway to install temporary heaters and align ventilation to   |
| raise temperatures above 60F.                                               |
|                                                                              |
| The Licensee intends to notify the NRC Resident Inspector.                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35211       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALO VERDE               REGION:  4  |NOTIFICATION DATE: 01/01/1999|
|    UNIT:  [1] [2] [3]               STATE:  AZ |NOTIFICATION TIME: 18:29[EST]|
|   RXTYPE: [1] CE,[2] CE,[3] CE                 |EVENT DATE:        01/01/1999|
+------------------------------------------------+EVENT TIME:        15:45[MST]|
| NRC NOTIFIED BY:  ALAN BRIESE                  |LAST UPDATE DATE:  01/01/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHARLES MARSCHALL    R4      |
|10 CFR SECTION:                                 |                             |
|AESS 50.72(b)(1)(v)      EMERGENCY SIREN 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  |
|3     N          Y       100      Power Operation  |100      Power Operation  |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SIRENS FOUND INOPERABLE IN THE EMERGENCY PLANNING ZONE                       |
|                                                                              |
| At 1545 MST on 1/1/99, PVNGS Unit 1 was informed by the Maricopa County      |
| Sheriff's Department that a routine Siren Interrogation Test failed for all  |
| (39) offsite sirens in the emergency planning zone.  Appropriate personnel   |
| have been dispatched to troubleshoot and repair.  Although the cause is      |
| currently unknown, there are no adverse weather conditions in the vicinity.  |
| Contingency procedures are in place to compensate for a failure of the       |
| offsite siren system.                                                        |
|                                                                              |
| The licensee intends to inform the NRC Resident Inspector.                   |
|                                                                              |
| Note similar events numbers 35174 and  35166 in December 1998.               |
|                                                                              |
| * * * UPDATE AT 1949 EST ON 01/01/99 BY ALAN BRIESE TO FANGIE JONES * * *    |
|                                                                              |
| At 1722 MST all offsite sirens have been returned to operation.  The         |
| licensee intends to inform the NRC Resident Inspector.                       |
|                                                                              |
| The NRC Operations Officer notified the R4DO (Charles Marschall)             |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35212       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CLINTON                  REGION:  3  |NOTIFICATION DATE: 01/02/1999|
|    UNIT:  [1] [] []                 STATE:  IL |NOTIFICATION TIME: 08:51[EST]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        01/02/1999|
+------------------------------------------------+EVENT TIME:        07:45[CST]|
| NRC NOTIFIED BY:  MARSHALL FUNKHOUSER          |LAST UPDATE DATE:  01/02/1999|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MONTE PHILLIPS       R3      |
|10 CFR SECTION:                                 |JOHN HANNON          NRR     |
|AARC 50.72(b)(1)(v)      OTHER ASMT/COMM INOP   |ROSEMARY HOGAN       IRD     |
|                                                |JOSEPH HIMES         RCT     |
|                                                |CHARLES MILLER       NRR     |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LICENSEE CONCLUDED THAT THE EMERGENCY RESPONSE ORGANIZATION COULD NOT MEET   |
| THE STAFFING TIME REQUIREMENT DUE TO ADVERSE WEATHER CONDITIONS.             |
|                                                                              |
| "10CFR50.72(b)(v) REQUIRES THE FACILITY TO NOTIFY THE NRC OPERATIONS CENTER  |
| DURING ANY EVENT THAT RESULTS IN THE MAJOR LOSS OF EMERGENCY OFFSITE         |
| RESPONSE CAPABILITY.                                                         |
|                                                                              |
| "WEATHER CONDITIONS HAVE DETERIORATED DRIVING CONDITIONS PREVENTING MULTIPLE |
| PERSONNEL FROM REACHING THE PLANT.  BASED ON THESE RESULTS AND PRESENT       |
| WEATHER CONDITIONS, IT IS DOUBTFUL THAT THE EMERGENCY RESPONSE ORGANIZATION  |
| WOULD BE FILLED WITHIN THE REQUIRED TIME.  THUS, THIS NOTIFICATION [IS]      |
| BEING MADE."                                                                 |
|                                                                              |
| THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR.                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35213       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COMANCHE PEAK            REGION:  4  |NOTIFICATION DATE: 01/03/1999|
|    UNIT:  [] [2] []                 STATE:  TX |NOTIFICATION TIME: 13:54[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        01/03/1999|
+------------------------------------------------+EVENT TIME:        11:15[CST]|
| NRC NOTIFIED BY:  STEVEN SEWELL                |LAST UPDATE DATE:  01/03/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHARLES MARSCHALL    R4      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     M/R        Y       100      Power Operation  |0        Hot Standby      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MANUAL REACTOR TRIP DUE TO TURBINE CONTROL SYSTEM MALFUNCTION                |
|                                                                              |
| The licensee reported that the turbine control system instantaneously        |
| reduced turbine load from 1161 MWe to about 200 MWe for an unknown reason.   |
| Multiple steam generator alarms were received, control rods began inserting, |
| and the steam dumps opened in response to the turbine load decrease.         |
| Pressurizer relief valve PCV-455A opened momentarily due to the pressure     |
| transient.  The reactor was manually tripped, all rods fully inserted, and   |
| the auxiliary feedwater pumps, both motor and steam turbine driven, started  |
| and restored steam generator level in all steam generators.  The unit is     |
| stable in Mode 3, Hot Standby.  All safety systems responded as expected and |
| restart will be evaluated after further investigation of the cause of the    |
| event.                                                                       |
|                                                                              |
| The licensee notified the resident inspector.                                |
+------------------------------------------------------------------------------+