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 |
| -105�F with an outdoor temperature of 21�F. The Licensee determined that |
| the intake structure temperature was below 60�F. Specifically, in safety |
| related pump rooms (Salt Service Water) the temperatures were: |
| |
| Pump rooms A &B - 57�F |
| Pump rooms D & E- 56�F |
| Pump room C - 52�F |
| |
| 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 32�F. |
| |
| Actions are underway to install temporary heaters and align ventilation to |
| raise temperatures above 60�F. |
| |
| 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. |
+------------------------------------------------------------------------------+
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