Event Notification Report for May 24, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
05/21/1999 - 05/24/1999
** EVENT NUMBERS **
35644 35744 35746 35749 35750 35751 35752 35753 35754 35755 35756 35757
35758
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35644 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 04/27/1999|
| UNIT: [1] [2] [] STATE: CA |NOTIFICATION TIME: 22:14[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/27/1999|
+------------------------------------------------+EVENT TIME: 18:45[PDT]|
| NRC NOTIFIED BY: RODERTO ARROYO |LAST UPDATE DATE: 05/21/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DAVID GRAVES R4 |
|10 CFR SECTION: | |
|DDDD 73.71 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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 50 Power Operation |50 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| DISCOVERY OF A SAFEGUARDS SYSTEM DEGRADATION RELATED TO A VITAL AREA |
| BARRIER |
| |
| Security personnel discovered a safeguard system degradation related to the |
| vital area barrier. Immediate compensatory actions were taken upon |
| discovery. (Contact the NRC Operations Officer for additional details and |
| for a licensee contact telephone number.) |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| * * * UPDATE AT 1746 ON 05/26/99 BY JOHN HUBBLE TO JOLLIFFE * * * |
| |
| The licensee is retracting this event since adequate compensatory measures |
| were already in place when this degradation was discovered. (Contact the |
| NRC Operations Officer for additional details.) |
| |
| The licensee plans to notify the NRC Resident Inspector. |
| |
| The NRC Operations Officer notified the R4DO Gary Sanborn. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35744 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 05/20/1999|
| UNIT: [] [] [3] STATE: CT |NOTIFICATION TIME: 10:23[EDT]|
| RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 05/20/1999|
+------------------------------------------------+EVENT TIME: 10:14[EDT]|
| NRC NOTIFIED BY: BRADSKY |LAST UPDATE DATE: 05/21/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |PETER ESELGROTH R1 |
|10 CFR SECTION: | |
|ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
| | |
|3 N N 0 Refueling |0 Refueling |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - FAILURE OF BOTH SAFETY RELATED CONTAINMENT CUBICAL SUMP AIR DRIVEN PUMPS |
| - |
| |
| ON 5/16/99 DURING THE 18 MONTH SURVEILLANCE FOR THE SAFETY RELATED |
| CONTAINMENT RECIRCULATION CUBICAL SUMP AIR DRIVEN PUMPS, BOTH PUMPS FAILED |
| TO DISCHARGE WATER FROM THE SUMPS TO OUTSIDE THE ENGINEERING SAFETY FEATURES |
| BUILDING. A REVISION TO THE SURVEILLANCE TO INCREASE THE AIR PRESSURE TO |
| THE PUMPS WAS APPROVED ON 5/19/99. ON 5/19/99, BOTH AIR DRIVEN PUMPS WERE |
| DECLARED INOPERABLE WHEN PUMP DAS*P15A FAILED TO DISCHARGE WATER FROM THE |
| SUMPS TO OUTSIDE THE ENGINEERING SAFETY FEATURES BUILDING WITH THE INCREASED |
| AIR PRESSURE. |
| |
| THE SAFETY RELATED CONTAINMENT RECIRCULATION CUBICAL SUMP AIR DRIVEN PUMPS |
| ARE REQUIRED FOLLOWING A LOCA WHEN THE ENGINEERING SAFETY FEATURES BUILDING |
| IS INACCESSIBLE DUE TO HIGH DOSE RATES IN THE BUILDING. THE PLANT IS |
| CURRENTLY IN A REFUELING OUTAGE AND THE NON-SAFETY RELATED CONTAINMENT |
| RECIRCULATION CUBICAL SUMP PUMPS ARE FUNCTIONAL. |
| |
| THE CAUSE OF THE EVENT IS CURRENTLY UNDER INVESTIGATION. AT THIS TIME, IT |
| IS HYPOTHESIZED THAT THE AIR CHAMBER OF THE PUMPS ARE FLOODED WITH |
| LUBRICATING OIL WHICH REDUCES THEIR CAPABILITIES TO PUMP WATER. |
| |
| THE RESIDENT INSPECTOR WAS INFORMED. |
| |
| *** UPDATE ON 5/21/99 @ 0838 BY MARTIN TO GOULD *** |
| |
| THE DATE BOTH AIR DRIVEN PUMPS WERE DECLARED INOPERABLE WAS 5/20/99 INSTEAD |
| OF 5/19/99 AS REPORTED IN THE INITIAL REPORT. |
| |
| THE RESIDENT INSPECTOR WAS NOTIFIED. REG 1 RDO (ESELGROTH) WAS INFORMED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35746 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 05/20/1999|
| UNIT: [] [3] [] STATE: NY |NOTIFICATION TIME: 14:23[EDT]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 12/01/1975|
+------------------------------------------------+EVENT TIME: 12:00[EDT]|
| NRC NOTIFIED BY: TOM McKEE |LAST UPDATE DATE: 05/21/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |PETER ESELGROTH 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|3 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - COMPONENT COOLING WATER PIPING IS RUN INSIDE A CRANE WALL (NOT MISSILE |
| PROTECTED) - |
| |
| During a 10CFR50.54(f) review of the UFSAR, the licensee discovered a |
| certain component cooling water (CCW) piping run inside a crane wall (i.e., |
| not missile protected from LOCA generated missiles by the crane wall) [DER |
| 99-0840]. After searching plant records, the licensee has not located any |
| initial engineering documentation justifying the running of piping inside |
| the crane wall. Based on this review, the licensee has concluded that the |
| CCW piping may have been outside the system design basis stated in the UFSAR |
| since original operation of the plant in December 1975. The licensee |
| believes that the design requirement (i.e., protected from LOCA generated |
| missiles) for the system was restored in March 1986 based on the NRC Safety |
| Evaluation for Generic Safety Issue A-2. The Safety Evaluation Report (SER) |
| states, in part, that "dynamic effects associated with postulated pipe |
| breaks in the primary coolant system of this facility need not be a design |
| basis." |
| |
| The licensee has declared the CCW piping operable based on the 1986 SER and |
| is continuing to reconcile the design basis of this issue using the |
| 10CFR50.59 process. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 35749 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: L.A. COUNTY DEPT OF HEALTH SERVICES |NOTIFICATION DATE: 05/21/1999|
|LICENSEE: KAISER PERMANENTE MED CARE PROGRAM |NOTIFICATION TIME: 11:15[EDT]|
| CITY: LOS ANGELES REGION: 4 |EVENT DATE: 04/23/1999|
| COUNTY: STATE: CA |EVENT TIME: 12:00[PDT]|
|LICENSE#: 0372-19 AGREEMENT: Y |LAST UPDATE DATE: 05/21/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |GARY SANBORN R4 |
| |LARRY CAMPER NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: STEPHEN DOERFLER | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THERAPEUTIC MEDICAL MISADMINISTRATION AT KAISER PERMANENTE MEDICAL CARE |
| PROGRAM OF SOUTHERN CALIFORNIA. |
| |
| A PATIENT WAS SCHEDULED FOR THREE THERAPEUTIC TREATMENTS FOR CANCER OF THE |
| CERVIX USING THE HIGH DOSE RATE AFTERLOADER. PRIOR TO THE INITIATION OF THE |
| FIRST TREATMENT ON 04/23/99, THE AUTHORIZED USER MADE A "LAST MINUTE" CHANGE |
| IN THE TREATMENT PLAN WITH RESPECT TO THE SOURCE TRAVEL DISTANCE. AFTER THE |
| CHANGE WAS MADE, THE SETUP CALLED FOR THE SOURCE TO BEGIN AT 989 |
| MILLIMETERS. THE PHYSICIST, HOWEVER, SET UP THE UNIT SO THAT THE SOURCE |
| BEGAN ITS TRAVEL AT 889 MILLIMETERS. PRIOR TO INITIATION OF THE TREATMENT, |
| THE AUTHORIZED USER, PHYSICIST, AND TECHNOLOGIST SIGNED OFF ON THIS |
| TREATMENT PLAN. THE PATIENT WAS THEN TREATED. THE SOURCE TRAVEL DISTANCE |
| WAS 100 MILLIMETERS SHORTER THAN THE TREATMENT PLAN REQUIRED, AND DIFFERENT |
| FROM THAT INTENDED. IT WAS NOT NOTED DURING OR AFTER COMPLETION OF THIS |
| TREATMENT. |
| |
| THE SECOND TREATMENT OCCURRED ON 04/30/99. A SECOND PHYSICIST, WITHOUT |
| VERIFYING THE ACCURACY OF THE FIRST TREATMENT, SET UP THE SECOND TREATMENT |
| USING THE SAME PARAMETERS, A TRAVEL DISTANCE OF 894 MILLIMETERS. THE |
| AUTHORIZED USER, PHYSICIST, AND TECHNOLOGIST SIGNED OFF ON THE SECOND |
| TREATMENT PLAN. THE TREATMENT WAS ADMINISTERED TO A DIFFERENT LOCATION THAN |
| INTENDED. THE ERROR WAS NOT NOTED PRIOR TO, DURING, OR AFTER THIS |
| TREATMENT. |
| |
| THE THIRD TREATMENT PERFORMED ON 05/07/99 BY A THIRD PHYSICIST WHO SET UP |
| THE PARAMETERS CORRECTLY, AS PLANNED (TRAVEL DISTANCE OF 994 MILLIMETERS) |
| WAS COMPLETED WITHOUT INCIDENT. |
| |
| THE THIRD PHYSICIST PERFORMED A CHART REVIEW ON 05/11/99 AND FOUND THE ERROR |
| IN THE 04/23/99 AND 04/30/99 TREATMENTS AND NOTIFIED THE RADIATION THERAPY |
| ADMINISTRATOR AND CHIEF OF SERVICE. |
| |
| THE REGIONAL RADIATION SAFETY OFFICER (RSO) WAS NOTIFIED ON 05/17/99 BY THE |
| SITE RSO IN VIOLATION OF THE REQUIRED 4 HOUR NOTIFICATION TIME. |
| |
| THE PATIENT AND HIS REFERRING PHYSICIAN WERE NOTIFIED OF THIS INCIDENT ON |
| 05/18/99. |
| |
| A COMPLETE INVESTIGATION OF THESE INCIDENTS, INCLUDING A DOSE ASSESSMENT, |
| AND THE DEVELOPMENT OF AN ACTION PLAN TO PREVENT FURTHER OCCURRENCES WILL BE |
| MADE. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35750 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 05/21/1999|
| UNIT: [] [2] [] STATE: AR |NOTIFICATION TIME: 13:38[EDT]|
| RXTYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 05/21/1999|
+------------------------------------------------+EVENT TIME: 09:39[CDT]|
| NRC NOTIFIED BY: WAYNE AHO |LAST UPDATE DATE: 05/21/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GARY SANBORN 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| CONTROL ROOM ISOLATION & EMERGENCY VENTILATION/FILTRATION SYSTEM (CREVS) |
| ACTUATION |
| |
| A Health Physics Technician was transporting a spent fuel pool purification |
| filter in the vicinity of the radiation detectors for the CREVS system. The |
| filter had a contact reading of 131 mrem/hour, and 45.4 mrem/hour at 30 cm. |
| The actuated radiation detector, #2RITS-8750-1B, has a setpoint of 140 |
| counts per minute., This filter was placed near the detector, causing the |
| actuation. |
| |
| This is not the normal transport path for contaminated filters. The filter |
| was triple-bagged, but developed a leak during transport. The Health |
| Physics Technician decided to place the filter in a barrel that is normally |
| used for torn protective clothing, to prevent the spread of contamination. |
| This barrel is in the vicinity of the control room ventilation radiation |
| detectors. |
| |
| At 1035 CDT, the control room ventilation system was returned to normal. |
| |
| Unit 1 was unaffected by this event. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35751 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 05/21/1999|
| UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 13:53[EDT]|
| RXTYPE: [1] W-3-LP |EVENT DATE: 05/21/1999|
+------------------------------------------------+EVENT TIME: 10:16[EDT]|
| NRC NOTIFIED BY: MARK ELLINGTON |LAST UPDATE DATE: 05/21/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ANN BOLAND R2 |
|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 Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| INADVERTENT START OF THE 'B' CONTAINMENT SPRAY PUMP DUE TO AN INVALID START |
| SIGNAL |
| |
| While performing the test of the Sequencer Block Circuit and Containment Fan |
| Cooler, Train 'B' (#OST- 1095) with the plant at 100% power, a maintenance |
| technician placed multimeter leads on the wrong terminal points. These |
| terminal points were adjacent to the desired points. This caused an |
| inadvertent start of the 'B' Containment Spray Pump. This invalid actuation |
| was the result of an invalid signal generated by the maintenance technician. |
| Investigation indicates that no other components actuated. |
| |
| The pump was aligned in standby and no flow was admitted to containment. |
| The pump operated for approximately two minutes with adequate recirculation |
| flow before it was secured. No equipment damage occurred and the 'B' |
| Containment Spray system is currently operable. The licensee has |
| conservatively determined that the pump start constitutes an ESF actuation. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35752 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 05/21/1999|
| UNIT: [2] [] [] STATE: MI |NOTIFICATION TIME: 15:02[EDT]|
| RXTYPE: [2] GE-4 |EVENT DATE: 05/21/1999|
+------------------------------------------------+EVENT TIME: 10:14[EDT]|
| NRC NOTIFIED BY: STEVE MAREK |LAST UPDATE DATE: 05/21/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BRENT CLAYTON R3 |
|10 CFR SECTION: | |
|NLTR LICENSEE 24 HR REPORT | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 N Y 15 Power Operation |15 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 24 hour License Condition 2.C.(9) report concerning non-compliance with the |
| approved fire protection program. |
| |
| During a design calculation review, plant engineering department personnel |
| discovered that cable routing for safety/relief valve (SRV) 'G' is not in |
| compliance with Appendix R design assumptions for cable separation. The SRV |
| is used in the dedicated shutdown procedure to control reactor pressure and |
| to depressurize the plant so that a cold shutdown condition can be achieved |
| within 10 hours after plant shutdown (UFSAR commitment). An hourly fire |
| watch has been established in the affected zone, pending an evaluation by |
| engineering department personnel. |
| |
| The NRC Resident Inspector has been notified of this event notification by |
| the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35753 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 05/21/1999|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 22:40[EDT]|
| RXTYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 05/21/1999|
+------------------------------------------------+EVENT TIME: 20:46[CDT]|
| NRC NOTIFIED BY: RON RUSTICK |LAST UPDATE DATE: 05/22/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BRENT CLAYTON R3 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 A/R Y 100 Power Operation |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - UNIT 1 SCRAMMED FROM 100% POWER DUE TO A SCRAM DISCHARGE VOLUME HIGH LEVEL |
| SIGNAL - |
| |
| AT 2046 CDT ON 05/21/99, UNIT 1 RECEIVED A 'B' HALF SCRAM SIGNAL DUE TO A |
| SCRAM DISCHARGE VOLUME HIGH LEVEL SIGNAL. APPROXIMATELY 45 SECONDS LATER, |
| UNIT 1 RECEIVED A FULL SCRAM SIGNAL DUE TO A SCRAM DISCHARGE VOLUME HIGH |
| LEVEL SIGNAL. THE REACTOR SCRAMMED FROM 100% POWER DUE TO A VALID SCRAM |
| DISCHARGE VOLUME HIGH LEVEL SIGNAL POSSIBLY DUE TO A LEAKING VALVE ON A |
| SCRAM DISCHARGE VOLUME HYDRAULIC CONTROL UNIT. |
| |
| ALL CONTROL RODS INSERTED COMPLETELY. NO SAFETY/RELIEF VALVES LIFTED. |
| DECAY HEAT IS BEING DISSIPATED VIA THE STEAM JET AIR EJECTORS AND AUXILIARY |
| LOADS. UNIT 1 PRIMARY CONTAINMENT ISOLATION SYSTEM GROUP 2 (STANDBY GAS |
| TREATMENT SYSTEM) AND GROUP 3 (REACTOR WATER CLEANUP SYSTEM) ACTUATED. UNIT |
| 1 IS STABLE IN OPERATIONAL CONDITION 3 (HOT SHUTDOWN). THE LICENSEE IS |
| INVESTIGATING THE CAUSE OF THE SCRAM DISCHARGE VOLUME HIGH LEVEL SIGNALS. |
| |
| THIS EVENT HAD NO EFFECT ON UNIT 2 WHICH IS OPERATING AT 100% POWER. |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
| |
| * * * UPDATE AT 0800 EDT ON 5/22/99 BY RON RUSTICK TO FANGIE JONES * * * |
| |
| In review of the event it was noted that the Unit 1 diesel generator |
| auto-started on the transfer of auxiliary power, an ESF actuation. |
| |
| It is also believed that a reactor water cleanup system relief valve lifted, |
| pressurizing the reactor building drain tank and forcing backflow to fill up |
| the scram discharge volume causing the reactor scram. |
| |
| The licensee informed the NRC Resident Inspector. The Headquarters |
| Operations Officer informed the R3DO (Brent Clayton). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35754 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 05/22/1999|
| UNIT: [2] [3] [] STATE: PA |NOTIFICATION TIME: 01:56[EDT]|
| RXTYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 05/21/1999|
+------------------------------------------------+EVENT TIME: 22:20[EDT]|
| NRC NOTIFIED BY: JIM KOVALCHICK |LAST UPDATE DATE: 05/22/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |PETER ESELGROTH 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 Y 100 Power Operation |100 Power Operation |
|3 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PRIMARY CONTAINMENT ISOLATION SYSTEM ACTUATION DUE TO UNEXPECTED POWER LOSS |
| |
| "At 2220 [EDT] on 5/21/99 two of four 4 kVolt emergency electrical buses on |
| Unit 2 and Unit 3 fast transferred to the alternate offsite feed when the |
| normal offsite feed unexpectedly deenergized during switching operations. |
| The momentary power loss that occurred during the fast transfer unexpectedly |
| deenergized control logics that resulted in the following invalid Primary |
| Containment Isolation System Isolation actuations: |
| |
| Unit 2 |
| a) Outboard isolation of Drywell Instrument Nitrogen System |
| b) Outboard isolation of Reactor Water Cleanup System |
| c) Outboard isolation of Drywell Sump System |
| |
| Unit 3 |
| a) Inboard isolation of Drywell Instrument Nitrogen System |
| b) Inboard isolation of Drywell Sump System |
| c) Full Reactor Water Cleanup System isolation |
| d) Inboard isolation Containment Atmosphere Sampling System |
| |
| "The cause of the loss of feed is under investigation. Both units remain at |
| 100 % power." Power has been restored to the normal offsite feed, but the |
| busses are not being transferred back until the cause of the loss of power |
| is determined. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35755 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 05/22/1999|
| UNIT: [1] [2] [] STATE: IL |NOTIFICATION TIME: 05:10[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/22/1999|
+------------------------------------------------+EVENT TIME: 03:15[CDT]|
| NRC NOTIFIED BY: DENNIS HIGINBOLHAM |LAST UPDATE DATE: 05/22/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BRENT CLAYTON R3 |
|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 60 Power Operation |60 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PROCESS COMPUTER OUT-OF-SERVICE FOR PLANNED MAINTENANCE |
| |
| The Plant Process Computer was placed out-of-service for modification to a |
| inverter power supply and temporary power was not available. This also |
| placed the Safety Parameter Display System (SPDS) and the ability to link to |
| the Emergency Response Data System (ERDS) out-of-service. |
| |
| Preparations for full restoration is in progress and it is expected to be |
| complete by 0600 CDT. |
| |
| The licensee plans to notify the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35756 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 05/22/1999|
| UNIT: [] [2] [] STATE: TX |NOTIFICATION TIME: 09:40[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/22/1999|
+------------------------------------------------+EVENT TIME: 07:15[CDT]|
| NRC NOTIFIED BY: GREGORY BRYAN |LAST UPDATE DATE: 05/22/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GARY SANBORN 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THE 'A' SAFEGUARDS BUS DEENERGIZED CAUSING THE DIESEL GENERATOR TO START AND |
| REENERGIZE IT |
| |
| The Train 'A' Safeguards 6.9 kV electrical bus experienced a lockout relay |
| actuation (due to a neutral ground overcurrent). The diesel generator |
| (2-01) started and energized the bus. The Blackout Sequencer actuated and |
| restored the safeguards equipment on the affected bus. The ESF equipment |
| that actuated included the 'A' Train Control Room HVAC, motor driven |
| Auxiliary Feedwater Pump, turbine driven Auxiliary Feedwater Pump ( 'A' |
| Train only), and the Blackout Sequencer. |
| |
| The unit entered the abnormal procedure to respond to the loss of the normal |
| power supply to the Train 'A' Bus and restore from the Blackout Sequencer. |
| |
| |
| The cause of the relay actuation is under investigation and the diesel |
| generator will continue to power the bus until it is determined what caused |
| the actuation. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 35757 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: MEAD PAPER CORPORATION |NOTIFICATION DATE: 05/22/1999|
|LICENSEE: MEAD PAPER CORPORATION |NOTIFICATION TIME: 12:01[EDT]|
| CITY: CHILLICOTHE REGION: 3 |EVENT DATE: 05/22/1999|
| COUNTY: STATE: OH |EVENT TIME: 07:10[EDT]|
|LICENSE#: 34-06188-09 AGREEMENT: N |LAST UPDATE DATE: 05/22/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |BRENT CLAYTON R3 |
| |CHARLEY HAUGHNEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JIM SEGELHORST, RSO | |
| HQ OPS OFFICER: DICK JOLLIFFE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NINF INFORMATION ONLY | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - OHMART DENSITY GAUGE (20 MILLICURIES Cs-137 SOURCE) IN A FIRE AT A PAPER |
| PLANT - |
| |
| AT 0710 ON 05/22/99, A FIRE OCCURRED IN A WOOD CHIP CONVEYOR, POSSIBLY DUE |
| TO A SEIZED BEARING, AT THE MEAD PAPER CORPORATION FACILITY IN CHILLICOTHE, |
| OH. THE LOCAL FIRE DEPARTMENT WAS CALLED AND RESPONDED TO THE FIRE, WHICH |
| WAS EXTINGUISHED WITHIN APPROXIMATELY 15 MINUTES. A OHMART DENSITY |
| GAUGE(MODEL #SH1-00PS), WHICH IS INSTALLED IN THE AREA OF THE FIRE, HAD ITS |
| OUTER CASE CHARRED AND SLIGHTLY DAMAGED. THE GAUGE, WHICH CONTAINS A 20 |
| MILLICURIE CESIUM-137 RADIATION SOURCE, APPEARS NOT TO BE DAMAGED. |
| |
| JIM SEGELHORST, MEAD PAPER CORPORATION RADIATION SAFETY OFFICER (RSO) |
| MEASURED THE SOURCE AND OBTAINED NORMAL READINGS AT A DISTANCE OF |
| APPROXIMATELY ONE FOOT. THE RSO BARRICADED THE AREA AROUND THE GAUGE TO |
| ISOLATE IT FROM PERSONNEL. A OHMART REPRESENTATIVE IS ON HIS WAY TO THE |
| SITE AND PLANS TO TAKE POSSESSION OF THE GAUGE AROUND 1500 AND SHIP IT BACK |
| TO THE MANUFACTURER. NO PERSONNEL WERE EXPOSED TO RADIATION. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35758 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 05/23/1999|
| UNIT: [2] [] [] STATE: PA |NOTIFICATION TIME: 09:30[EDT]|
| RXTYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 05/23/1999|
+------------------------------------------------+EVENT TIME: 08:53[EDT]|
| NRC NOTIFIED BY: CAMERON CAMPBELL |LAST UPDATE DATE: 05/23/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |PETER ESELGROTH 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SAFETY PARAMETER DISPLAY SYSTEM OUT OF SERVICE DUE TO PLANNED MAINTENANCE |
| |
| The safety parameter display system (SPDS) was placed out of service due to |
| planned computer maintenance. Outage on the plant monitoring system |
| computer will disable SPDS for up to 24 hours. Operators are taking |
| compensatory measures for monitoring parameters. |
| |
| The licensee has notified the NRC resident inspector. |
| |
| ******************** UPDATE AT 2049 ON 05/23/99 FROM SCOTT PABIS TO LEIGH |
| TROCINE ******************** |
| |
| The planned computer maintenance outage has been completed, and SPDS was |
| returned to service at 2026. |
| |
| The licensee plans to notify the NRC resident inspector of this update. The |
| NRC operations officer notified the R1DO (Eselgroth). |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021