Event Notification Report for January 3, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
12/30/1999 - 01/03/2000
** EVENT NUMBERS **
36396 36487 36539 36544 36548 36549 36550 36551 36552 36553 36554 36555
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Hospital |Event Number: 36396 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: PRINCETON MEDICAL CENTER |NOTIFICATION DATE: 11/04/1999|
|LICENSEE: PRINCETON MEDICAL CENTER |NOTIFICATION TIME: 14:30[EST]|
| CITY: PRINCETON REGION: 1 |EVENT DATE: 11/04/1999|
| COUNTY: STATE: NJ |EVENT TIME: 09:15[EST]|
|LICENSE#: 29-06750-01 AGREEMENT: N |LAST UPDATE DATE: 12/30/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MOHAMED SHANBAKY R1 |
| |JOSIE PICCONE NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: EDWARD BACZA | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|LADM 35.33(a) MED MISADMINISTRATION | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| POTENTIAL MISADMINISTRATION INVOLVING DISLODGED BRACHYTHERAPY SOURCE |
| |
| AT APPROXIMATELY 0915EST AN ELDERLY FEMALE PATIENT NOTIFIED HOSPITAL STAFF |
| THAT A BRACYTHERAPY SOURCE (Cs-137 - 21.8 MILLIGRAM RADIUM EQUIVALENT) HAD |
| BECOME DISLODGED. HOSPITAL STAFF CONTACTED THE PHYSICIAN THAT HAD INSERTED |
| THE SOURCE AND WAS INSTRUCTED TO RELOCATE THE APPLICATOR TO THE FOOT OF THE |
| BED. THE HOSPITAL PHYSICIST ESTIMATES THAT THE SOURCE WAS IN THE VICINITY |
| OF THE PATIENT'S THIGH FOR APPROXIMATELY 15 MINUTES AND AT THE FOOT THE BED |
| FOR ANOTHER 18 MINUTES BEFORE BEING PLACED IN A LEAD PIG. THE ATTENDING |
| PHYSICIAN DOES NOT INTEND ANY ADDITIONAL EXPOSURE SINCE THE SOURCE REMAINED |
| IN PLACE FOR 18.45 OF THE 22.79 HOURS PRESCRIBED. NO ADVERSE HEALTH |
| CONSEQUENCES ARE EXPECTED. |
| |
| |
| * * * UPDATE AT 0900 ON 12/30/99 BY BACZA, TAKEN BY WEAVER * * * |
| |
| THE LICENSEE REQUESTED THIS EVENT BE RETRACTED. REGIONAL INSPECTORS |
| CONDUCTED AN INVESTIGATION OF THIS EVENT AND DETERMINED THAT NO |
| MISADMINISTRATION HAD OCCURRED. |
| HOO NOTIFIED RDO (BELLAMY). |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36487 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 12/04/1999|
| UNIT: [] [2] [] STATE: MN |NOTIFICATION TIME: 01:17[EST]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 12/03/1999|
+------------------------------------------------+EVENT TIME: 22:30[CST]|
| NRC NOTIFIED BY: MICHAEL T. MURPHY |LAST UPDATE DATE: 12/30/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GEOFFREY WRIGHT R3 |
|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
+------------------------------------------------------------------------------+
| ACTUATION OF TWO UNIT 2 AUXILIARY BUILDING NORMAL RADIATION MONITORS DURING |
| PERFORMANCE OF VENTILATION SYSTEM SURVEILLANCE TESTING |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "At 2230 [CST] during normal Unit 1 [and] 2 [reactor coolant system] |
| sampling, a [high] radiation and [emergency safety feature (ESF)] actuation |
| signal was received on [radiation monitors] 2R-30 and 2R-37 ([auxiliary |
| building] normal exhaust monitors). Normal exhaust was off, and [the |
| auxiliary] building special ventilation system was in operation while |
| performing [surveillance procedure] SP-1172, Monthly Ventilation System |
| Operation. Alarm response procedures were completed for high radiation on |
| 2R-30 [and 2R-]37. [The] duty chemist was informed, the sample was secured, |
| and 2R-30 [and 2R-]37 levels [then] returned normal. At 2255 [CST,] the |
| actuating signals were reset, and all equipment returned to normal." |
| |
| The licensee stated that all systems functioned as required in response to |
| the high radiation and ESF actuation signal. The cause of the ESF signal is |
| under investigation. At the time of this event notification, both units |
| were operating at 100% power. |
| |
| The licensee notified the NRC resident inspector. |
| |
| * * * UPDATE AT 1251 ON 12/30/99 BY DALE JOHNSON TO JOLLIFFE * * * |
| |
| The licensee desires to retract this event because the regulation does not |
| require reporting of an actuation of the Auxiliary Building Special |
| Ventilation System if it was started by an invalid start signal. The |
| licensee determined that the actuation in this instance was initiated by an |
| invalid start signal. |
| |
| The licensee plans to notify the NRC Resident Inspector. |
| |
| The NRC Operations Officer notified the R3DO Bruce Burgess. |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36539 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 12/25/1999|
| UNIT: [1] [] [] STATE: MA |NOTIFICATION TIME: 07:45[EST]|
| RXTYPE: [1] GE-3 |EVENT DATE: 12/25/1999|
+------------------------------------------------+EVENT TIME: 07:00[EST]|
| NRC NOTIFIED BY: BRIAN SULLIVAN |LAST UPDATE DATE: 12/30/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |RICHARD CONTE 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
+------------------------------------------------------------------------------+
| LOW SWITCHGEAR ROOM TEMPERATURE DUE TO DEGRADED HEATING, VENTILATION, AND |
| AIR CONDITIONING (HVAC) COMPONENTS IN CONJUNCTION WITH COLD WEATHER |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "[The] 'A' switchgear room temperature [was] outside the [final safety |
| analysis report] design temperature limit of 60�F. [The] temperature |
| decreased to 59�F due to degraded [heating, ventilation, and air |
| conditioning (HVAC)] components. No known operability issues have been |
| identified." |
| |
| The licensee stated that the temperature in the 'A' switchgear room has |
| returned to 60�F but that cold weather is expected again tonight. The |
| licensee is currently in the process of repairing the degraded HVAC |
| components. |
| |
| The licensee notified the NRC resident inspector. |
| |
| * * * UPDATE AT 1045 ON 12/30/99 BY MANTENFEL, TAKEN BY WEAVER * * * |
| |
| An engineering evaluation determined that the equipment remained operable at |
| the as found temperature. The licensee is retracting this event. The NRC |
| resident will be informed. The Operations center notified the RDO |
| (Bellamy). |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36544 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 12/29/1999|
| UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 06:15[EST]|
| RXTYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 12/29/1999|
+------------------------------------------------+EVENT TIME: 04:20[CST]|
| NRC NOTIFIED BY: DARYL NOHR |LAST UPDATE DATE: 12/30/1999|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BRUCE BURGESS R3 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 90 Power Operation |80 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| HPCI INOPERABLE |
| |
| During QCOS 2300-28 'HPCI Turning Gear Logic Functional Test' the HPCI |
| turning gear failed to engage. The test was stopped and HPCI was placed on |
| the turning gear from a normal standby lineup and removed from the turning |
| gear using QCOP 2300-13 'HPCI Turning Gear Operation'. Per analysis the |
| HPCI turbine must be able to be remotely placed on the turning gear. Since |
| HPCI failed to go on gear during the logic test it was declared inoperable |
| at 0420. A 14 day LCO was centered per Tech Spec 3.5.A action 3. |
| |
| The Licensee will notify the NRC resident inspector. |
| |
| * * * UPDATE AT 1839 ON 12/30/99 BY TONY SCOTT TO JOLLIFFE * * * |
| |
| The licensee desires to retract this event due to the test method being used |
| during the test. During the test, the HPCI turning gear would have |
| functioned, as required. |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| The NRC Operations Officer notified the R3DO Bruce Burgess. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36548 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 12/30/1999|
| UNIT: [] [2] [] STATE: GA |NOTIFICATION TIME: 05:53[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/30/1999|
+------------------------------------------------+EVENT TIME: 04:56[EST]|
| NRC NOTIFIED BY: LEE MANSFIELD |LAST UPDATE DATE: 12/30/1999|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHRIS CHRISTENSEN 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 M/R N 0 Startup |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| REACTOR TRIP FROM MODE TWO |
| |
| "Plant Vogtle Unit 2 was in a reactor startup following repair of a |
| Feedwater Heater. During withdrawal of Control Bank B to 85 steps, Control |
| Bank B rod B6 became misaligned from its bank by Digital Rod position |
| indication System (DRPI) indication and the demand step counters. The Rod |
| Control System Malfunction abnormal operating procedure was entered and the |
| reactor was manually tripped at 0456 hours EST due to a misalignment of |
| greater than 12 steps between DRPI and the demand step counters. All rods |
| inserted as expected during the trip and no other anomalies were noted. The |
| reactor is currently stable in Mode 3." |
| |
| The licensee informed the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36549 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 12/30/1999|
| UNIT: [1] [2] [] STATE: MI |NOTIFICATION TIME: 17:42[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/30/1999|
+------------------------------------------------+EVENT TIME: 16:55[EST]|
| NRC NOTIFIED BY: DEAN BRUCK |LAST UPDATE DATE: 12/30/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BRUCE BURGESS R3 |
|10 CFR SECTION: | |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
|2 N N 0 Refueling |0 Refueling |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - Unit 1 and 2 valves have the potential to experience pressure locking |
| under post-LOCA conditions - |
| |
| Motor operated valves ICM-305 and ICM-306, for both units, have been |
| identified as having the potential to experience pressure locking under |
| post-LOCA conditions. These valves are the ECCS suction valves from the |
| recirculation sump that are opened to supply water to the Residual Heat |
| Removal (RHR) pump suction, which in turn supplies flow to the suction of |
| the safety injection and charging pumps. Calculations performed during a |
| review of Generic Letter 95-07 determined that the valve operators are |
| potentially incapable of opening the valves under pressure locking |
| conditions, which result from the post LOCA temperature rise. |
| |
| Additionally, Units 1 and 2 IMO-330 and IMO-331, the RHR to upper |
| containment spray shutoff valves, have been determined to experience the |
| same post-LOCA pressure locking problem. These valves provide isolation of |
| RHR flow to the upper containment spray headers, and are opened during the |
| recirculation phase of an accident if upper spray is needed. |
| |
| Design changes are being developed to modify the valves to eliminate the |
| potential for pressure locking. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36550 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 12/30/1999|
| UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 17:53[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 12/30/1999|
+------------------------------------------------+EVENT TIME: 16:00[CST]|
| NRC NOTIFIED BY: BILL GREEN |LAST UPDATE DATE: 12/30/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GARY SANBORN R4 |
|10 CFR SECTION: |RICHARD WESSMAN NRR |
|ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS |JOSEPH GIITTER IRO |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
|NLCO TECH SPEC LCO A/S | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - TS REQUIRED PLANT SHUTDOWN DUE TO 23 GPD REACTOR EQUIPMENT COOLING SYSTEM |
| LEAK - |
| |
| AT 1600 CST ON 12/30/99, THE LICENSEE DECLARED THE REACTOR EQUIPMENT COOLING |
| (REC) SYSTEM INOPERABLE DUE TO THE REC SYSTEM LEAK RATE BEING APPROXIMATELY |
| 3 INCHES OF SURGE TANK LEVEL PER DAY (APPROXIMATELY 23 GALLONS PER DAY). |
| THIS LEAK RATE DOES NOT ALLOW THE REC SYSTEM TO REMAIN OPERABLE 30 DAYS |
| POST-LOCA AS REQUIRED BY THE UFSAR, SECTION X-6, PAGE X-6-8. TECH SPEC LCO |
| 3.7.3, CONDITION B, REQUIRES THE PLANT TO BE IN MODE 3 IN 12 HOURS AND MODE |
| 4 IN 36 HOURS. |
| |
| ONE OF TWO EDGs (#2 EDG) AND THE 'B' SERVICE WATER BOOSTER PUMP ARE |
| INOPERABLE. |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36551 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 12/30/1999|
| UNIT: [] [2] [] STATE: SC |NOTIFICATION TIME: 20:07[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/30/1999|
+------------------------------------------------+EVENT TIME: 18:21[EST]|
| NRC NOTIFIED BY: BOB WHITE |LAST UPDATE DATE: 01/02/2000|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHRIS CHRISTENSEN R2 |
|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 A/R Y 100 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - AUTO REACTOR TRIP FROM 100% POWER FOR UNKNOWN REASONS - |
| |
| AT 1821 ON 12/30/99, UNIT 2 AUTO TRIPPED FROM 100% POWER FOR UNKNOWN REASONS |
| CAUSING A MAIN TURBINE TRIP. THE MAIN FEEDWATER SYSTEM ISOLATED AND THE |
| AUXILIARY FEEDWATER SYSTEM AUTOSTARTED. ALL CONTROL RODS INSERTED |
| COMPLETELY. STEAM IS BEING DUMPED TO THE MAIN CONDENSER. INTERMEDIATE |
| RANGE MONITOR N-35 APPEARED UNDERCOMPENSATED, REQUIRING A MANUAL RESET OF |
| THE SOURCE RANGES. |
| |
| UNIT 2 IS STABLE IN MODE 3 (HOT STANDBY). |
| |
| THE LICENSEE IS INVESTIGATING THE CAUSE OF THE TRIP. |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
| |
| * * * UPDATE AT 1616 ON 01/02/00 BY GARY HAMILTON TO JOLLIFFE * * * |
| |
| THE CAUSE OF THE REACTOR TRIP WAS A MAIN TURBINE TRIP ABOVE THE P-9 |
| PERMISSIVE INTERLOCK (WITH REACTOR POWER BELOW 50% POWER, THE REACTOR |
| REMAINS AT POWER IF THE MAIN TURBINE TRIPS). THE MAIN TURBINE TRIPPED DUE |
| TO TWO WIRES SHORTING TOGETHER ON AN ELECTRICAL CONNECTOR OF THE ELECTRIC |
| TRIP SOLENOID VALVE IN THE MAIN TURBINE CONTROL CIRCUITRY. |
| |
| THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. |
| |
| THE NRC OPERATIONS OFFICER NOTIFIED THE R2DO CHRIS CHRISTENSEN. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 36552 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 12/30/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 21:45[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 12/30/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 11:30[CST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 12/30/1999|
| CITY: PADUCAH REGION: 3 +-----------------------------+
| COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION |
|LICENSE#: GDP-1 AGREEMENT: Y |BRUCE BURGESS R3 |
| DOCKET: 0707001 |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: ERIC WALKER | |
| HQ OPS OFFICER: DICK JOLLIFFE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|OCBA 76.120(c)(2)(i) ACCID MT EQUIP FAILS | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| NOTE: THIS EVENT IS A CONTINUATION OF EVENT #35790. |
| |
| At 1130 CST on 12/30/99, the Plant Shift Superintendent (PSS) was notified |
| that during walkdowns of the High Pressure Fire Water System in C-337, a |
| total of 13 corroded sprinkler heads were discovered in System B-2. The |
| system was declared inoperable and actions were taken as required by the |
| technical safety requirement. The PSS determined that an update to this |
| event report is required. |
| |
| The NRC Resident Inspector has been notified of this event. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36553 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 12/31/1999|
| UNIT: [] [2] [] STATE: PA |NOTIFICATION TIME: 03:11[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 12/31/1999|
+------------------------------------------------+EVENT TIME: 01:11[EST]|
| NRC NOTIFIED BY: DOUG AMTSFIELD |LAST UPDATE DATE: 12/31/1999|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNU |RANDY BLOUGH R1 |
|10 CFR SECTION: |RICHARD WESSMAN NRR |
|AAEC 50.72 (a) (1) (I) EMERGENCY DECLARED |JOSEPH GIITTER IRO |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION |KEN CYBOCH FEMA |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 100 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNUSUAL EVENT - MAIN TRANSFORMER FAILURE |
| |
| A main transformer insulator failure led to a catastrophic failure of the |
| main transformer. This in turn led to a turbine trip and reactor scram. |
| The plant response to the transient was normal and the plant is now stable |
| in mode 3. Decay heat is being removed by dumping steam to the main |
| condenser. Reactor vessel water level is being maintained by the condensate |
| and feed systems. Offsite power was maintained throughout the event and no |
| safety related equipment has been damaged. The event occurred at 0111 and |
| the Unusual Event was declared at 0255. The Reactor Recirculation Pump |
| EOC-RPT (End of Cycle Recirc Pump Trip) breakers tripped as expected due to |
| the turbine stop valve and turbine control valve closures. |
| |
| The unusual event was declared because of the potential impact of the |
| failure on other plant components in the vicinity of the transformer. The |
| licensee has notified the resident inspector. |
| |
| * * * UPDATE AT 0431 ON 12/31/99 BY AMTSFIELD, RECEIVED BY WEAVER * * * |
| |
| The unusual event was terminated at 0400. Damage was limited to the main |
| transformer phase 'B' insulator with only ancillary damage to surrounding |
| equipment and no damage to safety related equipment. The licensee has |
| notified state and local governments of the event and a press release will |
| be issued. |
| |
| The operations center notified R1 (Blough); IRO (Giitter); EO (Wessman); |
| FEMA (CYBOCH) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36554 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: THREE MILE ISLAND REGION: 1 |NOTIFICATION DATE: 12/31/1999|
| UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 11:09[EST]|
| RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP |EVENT DATE: 12/31/1999|
+------------------------------------------------+EVENT TIME: [EST]|
| NRC NOTIFIED BY: MARK JANES |LAST UPDATE DATE: 12/31/1999|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ROBERT SUMMERS R1 |
|10 CFR SECTION: |JOHN DAVIDSON NMSS |
|NINF INFORMATION ONLY |RICHARD ROSANO NRR |
| |JOHN WHITE R1 |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| NON-CREDIBLE BOMB THREAT. |
| |
| CONTACT THE NRC OPERATIONS CENTER FOR ADDITIONAL DETAILS. |
| |
| LICENSEE WILL NOTIFY THE NRC RESIDENT. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36555 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 12/31/1999|
| UNIT: [1] [] [] STATE: IA |NOTIFICATION TIME: 13:13[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 12/31/1999|
+------------------------------------------------+EVENT TIME: 11:33[CST]|
| NRC NOTIFIED BY: BRUCE ROWLAND |LAST UPDATE DATE: 12/31/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BRUCE BURGESS R3 |
|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 |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PHYSICAL SECURITY EVENT - |
| |
| MINIMUM SECURITY PERSONNEL STAFFING REQUIREMENTS NOT MET FOR 22 MINUTES. |
| COMPENSATORY MEASURES IMMEDIATELY TAKEN UPON DISCOVERY. THE LICENSEE PLANS |
| TO NOTIFY THE NRC RESIDENT INSPECTOR. CONTACT THE NRC OPERATIONS OFFICER |
| FOR ADDITIONAL DETAILS. |
+------------------------------------------------------------------------------+
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