Event Notification Report for April 12, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
04/09/1999 - 04/12/1999
** EVENT NUMBERS **
35562 35563 35564 35565 35566 35567 35568 35569 35570 35571 35572 35573
35574 35575
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35562 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 04/09/1999|
| UNIT: [] [] [3] STATE: AL |NOTIFICATION TIME: 00:51[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 04/08/1999|
+------------------------------------------------+EVENT TIME: 20:45[CDT]|
| NRC NOTIFIED BY: TIM GOLDEN |LAST UPDATE DATE: 04/09/1999|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |WALTER RODGERS R2 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
| | |
|3 N Y 100 Power Operation |100 Power Operation |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| HPCI TEMPORARILY INOPERABLE |
| |
| System Affected: During the performance of a regularly scheduled |
| Instrumentation surveillance on the Unit 3 HPCI Steam Line Space High |
| Temperature switches (in accordance with plant procedure 3-SR-3.3.6.1(3D)) |
| personnel noticed that a relay not tested by procedure was chattering. The |
| affected relay 3-RLY-073-23A-K16 was adjacent to a relay 3-RLY-073-23A-K8 |
| which was being tested by the surveillance. While troubleshooting the cause |
| of the chattering relay, a loose wire was found in the power supply pathway |
| for the HPCI logic circuit. This loose wire had the potential to prevent |
| adequate voltage being supplied to the initiation and isolation logic for |
| the Unit 3 HPCI system. |
| |
| Actions: The loose wire was retightened. |
| |
| Reportability: The potential for inadequate voltage being available for the |
| HPCI logic circuit resulted in a conservative decision to declare the HPCI |
| system inoperable. In accordance with plant procedure SPP 3.5, code of |
| Federal Regulations 10CFR50.72/73 and NUREG 1022 Rev 1 this is reportable as |
| a 4 Hour Non-Emergency report due to any event or condition that alone could |
| have prevented the Fulfillment of the safety function of structures or |
| systems that are needed to (d) Mitigate the consequences of an accident. |
| This criteria is specified in 10CFR50.72.b.2.iii as a 4 hour report and in |
| 10CFR50.73.a.2.v as a 30 day written report. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 35563 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 04/09/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 02:50[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 04/08/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 23:00[EDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 04/09/1999|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |BRUCE BURGESS R3 |
| DOCKET: 0707002 |ROSEMARY HOGAN IRO |
+------------------------------------------------+SUSAN SHANKMAN NMSS |
| NRC NOTIFIED BY: KEITH VANDERPOOL | |
| HQ OPS OFFICER: DOUG WEAVER | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| BULLETIN 91-01 REPORT - VIOLATION OF NCSA |
| |
| "ON 4/8/99, AT 2300 IT WAS DISCOVERED THAT REQUIREMENT #14 OF NCSA-0333_ |
| 015.E03 WAS NOT BEING MAINTAINED ON CELL 33-3-8 WITHIN THE X-333 PROCESS |
| BUILDING. REQUIREMENT #14 STATES IN PART 'IF THE MOTORS ARE OFF, EITHER |
| THE RCW CONTROL VALVE OR THE RCW SUPPLY BLOCK VALVE SHALL BE CLOSED WITHIN 4 |
| HOURS.' THE MOTORS WERE IN FACT OFF AND THE RCW CONTROL VALVE FAILED IN |
| THE OPEN POSITION AND THE RCW SUPPLY VALVE WAS NOT CLOSED WITHIN 4 HOURS, |
| THUS VIOLATING REQUIREMENT #14. VIOLATION OF THIS REQUIREMENT CONSTITUTES |
| A LOSS OF CONTROL "B" (MODERATION) IN THE DOUBLE CONTINGENCY MATRIX FOR |
| CONTINGENCY EVENT B.6.b.1. CONTROL 'A' WHICH IS THE PASSIVE BARRIER |
| PROVIDED BY THE |
| CONDENSER AND COOLER TUBES REMAINED IN PLACE THROUGHOUT THIS EVENT. |
| CONTROL WAS NOT ESTABLISHED WITHIN THE 4 HOUR SPECIFIED TIME FRAME THUS |
| MAKING THIS A 4 HOUR NRC EVENT. CONTROL HAS BEEN ESTABLISHED AND CELL |
| 33-3-8 IS NOW ONSTREAM. (MOTORS ON)" |
| |
| THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35564 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 04/09/1999|
| UNIT: [1] [2] [] STATE: SC |NOTIFICATION TIME: 05:15[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/09/1999|
+------------------------------------------------+EVENT TIME: 04:28[EDT]|
| NRC NOTIFIED BY: HOLLAND |LAST UPDATE DATE: 04/09/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |WALTER RODGERS R2 |
|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 |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PLANT ENTERED 3.0.3 DUE TO BOTH TRAINS OF CONTROL ROOM VENTILATION BEING |
| INOPERABLE. |
| |
| A SPURIOUS SIGNAL ON THE CHLORINE DETECTOR ON UNIT 1 "B" TRAIN CONTROL ROOM |
| VENTILATION INTAKE WAS RECEIVED WHILE UNIT 2 VENTILATION INTAKE WAS CLOSED. |
| UNIT 2 CONTROL ROOM INTAKE HAD PREVIOUSLY CLOSED ON A SPURIOUS SIGNAL( SEE |
| EVENT 35561) AND IT WAS STILL CLOSED FOR TROUBLESHOOTING. BOTH UNITS |
| CONTROL ROOM VENT SYSTEMS BEING CLOSED RESULTS IN THE INOPERABILITY OF BOTH |
| TRAINS OF CONTROL ROOM VENTILATION, PLACING BOTH UNITS IN TS 3.0.3. |
| |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED. |
| |
| *** UPDATE AT 0530 BY HOLLAND TO GOULD *** |
| |
| THEY EXITED 3.0.3 AT 0526 WHEN THE "B" TRAIN WAS RESTORED TO OPERABLE |
| CONDITION. |
| |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35565 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 04/09/1999|
| UNIT: [1] [2] [] STATE: PA |NOTIFICATION TIME: 09:14[EDT]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 04/09/1999|
+------------------------------------------------+EVENT TIME: 08:37[EDT]|
| NRC NOTIFIED BY: DANIEL MURRAY |LAST UPDATE DATE: 04/09/1999|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN KINNEMAN R1 |
|10 CFR SECTION: | |
|AENS 50.72(b)(1)(v) ENS INOPERABLE | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Hot Standby |0 Hot Standby |
|2 N Y 98 Power Operation |98 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| EMERGENCY SIRENS INOPERABLE |
| |
| At 0837, the control room received a report from the Beaver County Emergency |
| Management Agency (BCEMA 911 center) that the emergency notification |
| sirens for Beaver County were inoperable. The computer that activates the |
| sirens was damaged by a lightning strike. This constitutes a major loss of |
| emergency communications capability as listed in 10CFR50.72.(b)1.v. Crews |
| are working to repair the main (damaged) computer and are also working to |
| place the backup computer in service. They expect to have the emergency |
| sirens returned to service within 1 hour. |
| |
| The licensee notified the NRC resident inspector. |
| |
| *** UPDATE ON 4/9/99 @ 1431 BY SHIPE TO GOULD *** |
| |
| ALL SIRENS WERE RETURNED TO SERVICE AT 1401. |
| |
| THE RESIDENT INSPECTOR WILL BE INFORMED. R1DO (KINNEMAN) WAS NOTIFIED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 35566 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: MATERIALS TESTING CONSULTANTS |NOTIFICATION DATE: 04/09/1999|
|LICENSEE: MATERIALS TESTING CONSULTANTS |NOTIFICATION TIME: 12:14[EDT]|
| CITY: GRAND RAPIDS REGION: 3 |EVENT DATE: 04/09/1999|
| COUNTY: STATE: MI |EVENT TIME: 09:00[EDT]|
|LICENSE#: 21-15281-02 AGREEMENT: N |LAST UPDATE DATE: 04/09/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |BRUCE BURGESS R3 |
| |SCOTT MOORE NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: PETE GASEWICZ | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOST TROXLER MOISTURE/DENSITY GAUGE |
| |
| A technician, en route to a project site, encountered problems with his |
| pickup truck approximately one mile from the company offices. The |
| technician was transporting a Troxler model 3430 gauge, containing one 8 mCi |
| Cs-137 source and one 40 mCi Am-241/Be source. A second truck was sent to |
| retrieve the technician and his equipment. However, when the gauge was |
| moved to the second truck, it was not properly secured to the bed of the |
| truck, nor was the tailgate raised. Upon arrival at the office, the |
| technician discovered that the gauge had fallen from the truck. The |
| technician immediately retraced the route of travel, but did not find the |
| gauge. The licensee believes that a passing motorist may have picked it up. |
| The gauge was locked inside of its storage case at the time of the loss. |
| The local police department has been contacted by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 35567 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: ROCHESTER GAS AND ELECTRIC CORP |NOTIFICATION DATE: 04/09/1999|
|LICENSEE: COLTEC INDUSTRIES |NOTIFICATION TIME: 13:50[EDT]|
| CITY: ROCHESTER REGION: 1 |EVENT DATE: 04/09/1999|
| COUNTY: STATE: NY |EVENT TIME: [EDT]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 04/09/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JOHN KINNEMAN R1 |
| |VERN HODGE (FAX) NRR |
+------------------------------------------------+ |
| NRC NOTIFIED BY: WIDAY (FAX) | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THE LICENSEE REPORTED A PART 21 DEFECT ON A REPLACEMENT TURBOCHARGER |
| SUPPLIED BY COLTEC INDUSTRIES. |
| |
| THE LICENSEE REPLACED A TURBOCHARGER(MODEL 730), SUPPLIED BY COLTEC |
| INDUSTRIES, ON THEIR "B" EMERGENCY DIESEL GENERATOR (ALCO MODEL 16-251F) AT |
| GINNA STATION. IT WAS DETERMINED THAT THERE WAS A MANUFACTURING DEFICIENCY |
| IN THE REPLACEMENT TURBOCHARGER WHICH CONSISTED OF A MISSING DRAIN PORT IN |
| THE INTERMEDIATE CASING ON THE TURBINE END WHICH WOULD PREVENT ENGINE |
| LUBRICATING OIL FROM BEING ABLE TO DRAIN BACK TO THE ENGINE SUMP FROM THE |
| TURBOCHARGER SHAFT AND BEARINGS. THIS DEFICIENCY CREATED A CONDITION WHERE |
| ENGINE LUBE OIL WAS BEING DIRECTED INTO THE CYLINDERS THROUGH THE EXHAUST |
| MANIFOLD PIPING, WHICH COULD HAVE RESULTED IN SERIOUS ENGINE DAMAGE. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 35568 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 04/09/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 18:07[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 04/08/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 18:55[EDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 04/09/1999|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |BRUCE BURGESS R3 |
| DOCKET: 0707002 |SUSAN SHANKMAN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: RICK LARSON | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 24-HOUR NRC BULLETIN 91-01 REPORT |
| |
| "At 1855 on 4/8/99, a Nuclear Criticality Safety Analysis (NCSA) |
| PLANT033.A01 control was lost. This loss was of one control (concentration), |
| which is one contingency of a double contingency design of this NCSA. |
| Moderation was maintained. The concentration control was lost when a surge |
| of UF6 material at less than 1% U-235 sublimed from a cell being returned to |
| service, causing the pressure in an intermediate drum (a type of surge drum) |
| to exceed the NCSA limit of 17 psia. The highest pressure reached was 19.6 |
| psia in the drum. Actions were immediately taken to reduce the drum pressure |
| and it was returned to allowable limits within 45 minutes. The drum |
| temperature was maintained above 220�F during this excursion. |
| |
| "This is reportable under NRC Bulletin 91-01 24-hour criticality control. |
| There was no loss of hazardous/radioactive material or |
| radioactive/radiological exposure as a result of this event." |
| |
| The NRC resident inspector has been informed of this notification. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 35569 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: SYNCOR INTERNATIONAL CORPORATION |NOTIFICATION DATE: 04/09/1999|
|LICENSEE: SYNCOR INTERNATIONAL CORPORATION |NOTIFICATION TIME: 18:31[EDT]|
| CITY: COLUMBUS REGION: 3 |EVENT DATE: 04/08/1999|
| COUNTY: STATE: OH |EVENT TIME: 03:30[EDT]|
|LICENSE#: 04-26507-01MD AGREEMENT: N |LAST UPDATE DATE: 04/09/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |BRUCE BURGESS R3 |
| |SUSAN SHANKMAN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: SCOTT LANGFORD | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAE2 20.2202(b)(2) EXCESSIVE RELEASE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOSS OF 185 mCi OF Tc-99m |
| |
| The licensee reported that 185 mCi of Tc-99m (5 unit doses) was lost from |
| the Syncor radiopharmacy facility in Columbus, OH. The missing unit doses |
| were contained in an ammo can which was one of eight cans in this particular |
| shipment. The driver for the shipment stated that only seven cans were |
| located on the shelf when he arrived to pick them up; however, another |
| driver who had picked his shipment up several minutes before stated that |
| there were eight cans located on the shelf when he left the area. |
| |
| This is an access controlled facility, and the licensee believes that the |
| can was either misplaced within the facility, inadvertently delivered to the |
| wrong customer, or disposed of as an undeliverable shipment. The licensee |
| will submit a written report to the NRC regarding this event. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35570 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 04/09/1999|
| UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 18:46[EDT]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 04/09/1999|
+------------------------------------------------+EVENT TIME: 18:38[EDT]|
| NRC NOTIFIED BY: DANIEL MURRAY |LAST UPDATE DATE: 04/09/1999|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN KINNEMAN R1 |
|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 98 Power Operation |98 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| DISCREPANCIES DISCOVERED IN APPENDIX R PROCEDURES |
| |
| "A review associated with an Engineering fire protection self-assessment has |
| identified discrepancies in manual actions specified in select Unit 1 |
| post-fire safe shutdown procedures. Steps in these procedures require |
| certain manual actions to be taken that have been determined to be |
| inappropriate. Performing these actions could place Unit 1 in a condition |
| which is outside the design basis of the Fire Protection Program involving |
| Appendix R Safe Shutdown capability. These actions involve manually |
| de-energizing non-essential class 1E power circuits. The intent of these |
| actions is to turn off circuits that are not required for safe shutdown in |
| order to eliminate the potential for circuit faults due to a postulated fire |
| that could trip out an entire AC distribution panel. However, performing |
| these actions would result in de-energizing the power to the diesel building |
| exhaust dampers. It has been determined that the dampers revert to the |
| closed position when their power supply is de-energized. This could have |
| resulted in the emergency diesel generator operating with insufficient |
| ventilation for diesel room cooling. This condition could have prevented the |
| fulfillment of the safety function of the emergency diesel generators needed |
| to satisfy the Appendix R Safe Shutdown requirements. As a result of these |
| procedural deficiencies, the ability to mitigate the consequences of a fire |
| event and to place the plant in a safe shutdown condition cannot be |
| assured. |
| |
| "A condition report has been written to document these procedural |
| discrepancies. The root cause and corrective actions are being addressed |
| through the corrective action program." |
| |
| The licensee will inform the NRC resident inspector of this notification. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35571 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: YANKEE ROWE REGION: 1 |NOTIFICATION DATE: 04/09/1999|
| UNIT: [1] [] [] STATE: MA |NOTIFICATION TIME: 19:13[EDT]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 04/09/1999|
+------------------------------------------------+EVENT TIME: 18:50[EDT]|
| NRC NOTIFIED BY: MARK GILMORE |LAST UPDATE DATE: 04/09/1999|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN KINNEMAN R1 |
|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 N 0 Decommissioned |0 Decommissioned |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| NUCLEAR ALERT TELEPHONE SYSTEM INOPERABLE |
| |
| The licensee reported that the Nuclear Alert telephone, which links the |
| plant to local police departments, is inoperable. FTS2000 and commercial |
| telephone service is unaffected. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35572 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 04/10/1999|
| UNIT: [1] [] [] STATE: LA |NOTIFICATION TIME: 07:46[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 04/10/1999|
+------------------------------------------------+EVENT TIME: 03:10[CDT]|
| NRC NOTIFIED BY: HUSTON |LAST UPDATE DATE: 04/10/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |LAWRENCE YANDELL R4 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| ESF SIGNAL INITIATED CAUSING SOME CONTAINMENT ISOLATION VALVES TO CLOSE |
| |
| "While performing preparations for an ENS-SWG1A bus outage the alternate |
| supply breaker ENS-ACB04 tripped. The bus was being supplied by this source |
| and the resultant loss of power and invalid actuation signal caused several |
| containment isolation AOVs to close. The containment purge system was in |
| operation and isolated as designed. Two drain system valves (DFR-AOV102 and |
| DER AOV127) and one sample system valve (B33-FO20) also isolated." |
| |
| The trip took place during a clearance procedure when an individual, in the |
| field, opened a fuse cabinet. The incident is being investigated. A |
| limited restoration of systems has been done. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35573 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WATTS BAR REGION: 2 |NOTIFICATION DATE: 04/11/1999|
| UNIT: [1] [] [] STATE: TN |NOTIFICATION TIME: 02:46[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/11/1999|
+------------------------------------------------+EVENT TIME: 00:42[EDT]|
| NRC NOTIFIED BY: RICK O'REAR |LAST UPDATE DATE: 04/11/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |WALTER RODGERS 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 M/R N 0 Hot Standby |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MANUAL REACTOR TRIP DUE TO CONTROL ROD DRIVE MALFUNCTION |
| |
| "Watts Bar Unit 1 experienced a Manual Reactor Trip during Control Rod |
| Testing while in Mode 3 (with Reactor shutdown for Refueling Outage). At |
| 0042 on 04/11/1999, the Main Control Room Crew manually opened the |
| Reactor Trip Breakers when the Control Rod Drive system continued to |
| withdraw Shutdown Bank A following a Manual withdrawal to 10 steps. The |
| rods should have stopped at 10 steps withdrawn. This was the first in a |
| sequence of rod withdrawals per Surveillance instruction 1-S I-85-2. |
| |
| "All other rods were fully inserted at the time of testing Shutdown Bank A |
| with RCS Boron concentration at 2184 PPM. When Shutdown Bank A continued to |
| withdraw, the SRO directed the Reactor Trip breakers to be |
| opened and verified all rods fully inserted. All systems responded as |
| expected. The Unit remains stable in Mode 3. |
| |
| "In addition, this generated a Main Feedwater Isolation Signal. At the time |
| of the event, all feedwater lines were isolated for outage work. |
| |
| "At present, an investigation is in progress to determine cause of event and |
| Control Rod Testing has been suspended pending outcome of that |
| investigation." |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35574 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 04/11/1999|
| UNIT: [] [2] [] STATE: NJ |NOTIFICATION TIME: 17:52[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/11/1999|
+------------------------------------------------+EVENT TIME: 15:54[EDT]|
| NRC NOTIFIED BY: PETE JONES |LAST UPDATE DATE: 04/11/1999|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN KINNEMAN R1 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N N 0 Refueling |0 Refueling |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| CONTAINMENT VENTILATION ISOLATION |
| |
| During the process of lifting the reactor vessel head, the containment noble |
| gas monitor (2R12A) alarmed, causing a containment ventilation isolation. |
| The containment purge isolation valves closed as a result of the isolation. |
| Nonessential personnel were immediately evacuated from containment, and all |
| remaining personnel (except the crane operator) were evacuated after the |
| reactor vessel head was placed onto its stand. The crane operator is |
| required to be on station in accordance with station procedures. The |
| licensee is analyzing samples taken from the containment atmosphere. The |
| NRC resident inspector will be informed of this notification by the |
| licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35575 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 04/11/1999|
| UNIT: [1] [2] [] STATE: SC |NOTIFICATION TIME: 21:13[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/11/1999|
+------------------------------------------------+EVENT TIME: 20:21[EDT]|
| NRC NOTIFIED BY: GARY HAMILTON |LAST UPDATE DATE: 04/11/1999|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |WALTER RODGERS R2 |
|10 CFR SECTION: | |
|ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | |
|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 |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| CONTROL ROOM CHILLERS DECLARED INOPERABLE |
| |
| Both control room ventilation chillers were declared inoperable due to high |
| temperature in the Standby Nuclear Service Water pond. The system had been |
| operating in an "operable but degraded" condition due to fouling of tubes in |
| the chiller condensers. The engineering analysis in support of continued |
| system operation specified a maximum Standby Nuclear Service Water pond |
| temperature of 70�F (the normal temperature limit for the pond is 91.5�F). |
| The licensee is currently attempting to cool the pond, but stated that |
| preparations are also being made to commence a dual unit shutdown. The NRC |
| resident inspector will be informed of this notification by the licensee. |
| |
| * * * UPDATE 2148 4/11/1999 FROM HAMILTON TAKEN BY STRANSKY * * * |
| |
| The licensee commenced shutdowns of both units at 2120. At 2133, the "B" |
| control room chiller was restored to operable, and the shutdowns were |
| terminated. Reactor power had been decreased to 98%, and is being returned |
| to rated. The NRC resident inspector will be informed of this notification |
| by the licensee. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021