Event Notification Report for February 22, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
02/19/1999 - 02/22/1999
** EVENT NUMBERS **
35359 35378 35384 35385 35386 35387 35388 35389 35390 35391
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35359 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 02/09/1999|
| UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 18:37[EST]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 02/09/1999|
+------------------------------------------------+EVENT TIME: 18:20[EST]|
| NRC NOTIFIED BY: JEFF SHIPE |LAST UPDATE DATE: 02/19/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |LAURIE PELUSO R1 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| - Non-conservative dose calculation methodology is a condition outside the |
| design basis of Unit 1 - |
| |
| As a result of LER 2-97-008 corrective actions, non-conservative inputs have |
| been identified that is associated with the Beaver Valley Power Station |
| (BVPS) methodology in calculating radiation doses for accidents which must |
| analyze for a concurrent iodine spike as part of their radiological |
| analyses. The identified non-conservative factors during past operation, |
| could have resulted in the calculated control room personnel dose values |
| exceeding 10CFR50 Appendix A, Criterion 19 thyroid limits. Since BVPS no |
| longer has reasonable assurance that acceptance criteria for control room |
| personnel dose limits per Criterion 19 would have been met during past |
| operation, the identified non-conservative dose calculation methodology was |
| a condition which was outside the design basis of the plant per |
| 10CFR50.72(b)(1)(ii). This condition is also being evaluated for the |
| criteria in 10CFR Part 21. |
| |
| For BVPS, the only Design Basis Accidents (DBAs) which involve a concurrent |
| iodine spike analysis are Main Steam Line Break, Small Line Breaks (e.g., |
| letdown line break outside containment), and Steam Generator Tube Rupture. |
| The most significant of the non-conservative issues is purification (i.e., |
| letdown) flow, which was given as 60 gpm. This is the lower limit of the |
| plant design flow rate range of 60-120 gpm. Analysis using 60 gpm results |
| in a significant underestimation of the concurrent iodine spike source term |
| as compared to operation at the upper design limit of 120 gpm. Of lesser |
| importance were underestimated demineralizer decontamination factor, |
| overestimated reactor coolant system (RCS) mass and inadequate use of RCS |
| leakage as an iodine removal mechanism. It has been determined that |
| correcting the above identified non-conservative factor would raise |
| calculated control room personnel dose values of those events analyzed for |
| concurrent iodine spikes by at least 40% and potentially as high as 140%. |
| |
| Until the BVPS dose calculations can be formally revised to address the |
| identified non-conservative factors, the station has placed administrative |
| controls on the extent of steady state letdown flow to ensure that plant |
| operation remains within past analyzed limits. The influence of the other |
| identified non-conservative factors have also been reviewed and determined |
| not to be an operability concern at this time. |
| |
| The licensee plans to notify the NRC Resident Inspector. |
| |
| * * * UPDATE AT 1110 ON 02/19/99 FROM JIM DAUGHERTY TO JOLLIFFE * * * |
| |
| The licensee is evaluating the above described issue and at 1600 on |
| 02/18/99, they determined that it also meets the reportability criteria |
| pursuant to l0CFR Part 21 specifically for Beaver Valley Unit 1. The generic |
| issue (Westinghouse issue) is applicable to both Beaver Valley Units I and |
| 2. A written report will be supplied pursuant to 10CFR Part 21 and |
| I0CFR50.73 in a supplement to LER 2-97-008. |
| |
| Until the Beaver Valley dose calculations can be formally revised to address |
| the identified non-conservative factors, BVPS has implemented administrative |
| controls to ensure that plant operation remains within past analyzed |
| limits. |
| |
| The licensee is continuing to evaluate this issue. |
| |
| The licensee plans to notify the NRC Resident Inspector. |
| |
| The NRC Operations Officer notified the R1DO Jim Trapp and NRR Vern Hodge. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35378 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 02/17/1999|
| UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 13:05[EST]|
| RXTYPE: [1] W-3-LP |EVENT DATE: 02/17/1999|
+------------------------------------------------+EVENT TIME: 12:19[EST]|
| NRC NOTIFIED BY: MARK PALMER |LAST UPDATE DATE: 02/19/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ANN BOLAND R2 |
|10 CFR SECTION: | |
|ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | |
|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 |7 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TECHNICAL SPECIFICATION REQUIRED PLANT SHUTDOWN DUE TO FAILURE OF THE 'A' |
| REACTOR TRIP BREAKER TO CLOSE RELIABLY DURING TESTING |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "During [technical specification] surveillance testing [with the unit] at |
| 100% power, a testing failure occurred on the train 'A' reactor trip |
| breaker. The test in progress was MST-I001, Train 'A' Solid State |
| Protection System Actuation Logic and Master Relay Test. During this test, |
| the 'A' reactor trip breaker failed to close with the test pushbutton. The |
| following timeline occurred:" |
| |
| "0821- [The] train 'A' reactor trip bypass breaker [was racked in and |
| closed]. This began a 2-hour time |
| limit allowed for surveillance testing. |
| 0916 - Reactor trip breaker 'A' failed to close with the test pushbutton. |
| At this point, the 2-hour limit for |
| surveillance testing ended, and [Technical Specification] 3.3.1, action 8, |
| was entered. This action |
| required the plant to be in Mode 3 within 6 hours. The time to enter Mode 3 |
| is 1516. |
| 1026 - NRC Region II representative, George MacDonald, [was] notified of |
| [limiting condition for operation] |
| and necessity to be in Mode 3 by 1516. Mr. MacDonald was notified because |
| [the] Harris resident |
| inspectors are out of town. |
| 1219 - [A generator] load reduction for plant shutdown [was commenced]. |
| Maintenance and engineering |
| personnel are investigating the problem." |
| |
| The licensee emphasized that the train 'A' reactor trip breaker did not fail |
| to open, which is its safety function. The breaker only failed to re-close. |
| It has since been opened and re-closed several times during ongoing |
| troubleshooting activities. The licensee currently believes that the |
| failure of the breaker to re-close reliably may be the result of a possible |
| problem with the test circuitry allowing the test signal to stay in. |
| |
| Although all of the emergency diesel generators and emergency core cooling |
| systems are operable and available if needed, the licensee stated that the |
| emergency response data system is not available due to a Y2K problem. (The |
| Y2K problem is not related to the breaker problem.) |
| |
| |
| *** UPDATE ON 2/19/99 @ 1356 BY FLEMING TO GOULD *** |
| |
| THE PLANT EXITED TS 3.3.1 ACTION 8 AT 1452 ON 2/17/99 WHILE AT 7% POWER. |
| THE UNIT DID NOT DROP FROM THE GRID OR ENTER MODE 3 PRIOR TO DECLARING THE |
| "A" REACTOR TRIP BREAKER OPERABLE AND IN-SERVICE WITH ITS BYPASS BREAKER |
| OPEN. AFTER EXITING THE LCO, POWER LEVEL WAS INCREASED AND THE REACTOR IS |
| CURRENTLY AT 100% POWER. |
| |
| THE ORIGINAL REPORT STATED THAT "ERDS NOT AVAILABLE DUE TO Y2K PROBLEM." A |
| SUBSEQUENT INVESTIGATION HAS REVEALED THAT ERDS REMAINED AVAILABLE |
| IMMEDIATELY PRIOR TO AND DURING THE REPORTED EVENT. CONTROL ROOM STAFF WAS |
| UNDER A MISTAKEN IMPRESSION THAT THE ERDS LINK WAS UNAVAILABLE DUE TO Y2K |
| TESTING BY THE NRC. A SERIES OF INCOMPLETE COMMUNICATIONS LED THEM TO THAT |
| CONCLUSION. |
| |
| THE RESIDENT INSPECTOR WAS NOTIFIED. |
| |
| REG2 RDO(BOLAND) WAS INFORMED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35384 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 02/19/1999|
| UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 13:33[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 02/19/1999|
+------------------------------------------------+EVENT TIME: 09:51[EST]|
| NRC NOTIFIED BY: BREADY |LAST UPDATE DATE: 02/19/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JIM TRAPP 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SEVERAL ESF ACTUATIONS OCCURRED DUE TO THE UNEXPECTED DE-ENERGIZATION OF THE |
| "D" 4.16KV VITAL BUS. |
| |
| DURING THE CONDUCT OF AN 18 MONTH DEGRADED VOLTAGE TEST OF THE "D" 4.16KV |
| VITAL BUS INFEED BREAKER, THE BUS WAS INADVERTENTLY DE-ENERGIZED RESULTING |
| IN A BUS UNDERVOLTAGE CONDITION. THE RELAY TECHNICIAN CONDUCTING THE TEST |
| STATED THAT THE NORMAL INFEED BREAKER TRIPPED OPEN AS HE WITHDREW HIS |
| VOLTMETER LEADS UPON COMPLETING THE DEGRADED VOLTAGE RELAY STATUS CHECK. |
| THE CAUSE OF THIS BREAKER TRIP IS UNKNOWN AND BEING INVESTIGATED. THE |
| ALTERNATE FEED BREAKER DID NOT CLOSE WHEN THE NORMAL INFEED TRIPPED, AND THE |
| "D" VITAL BUS WAS DE-ENERGIZED AS A RESULT. AT THE TIME OF THE EVENT, THE |
| PLANT WAS IN OPERATIONAL CONDITION 5 WITH CORE OFF LOAD IN PROGRESS. "A" |
| AND "C" CHANNELS OF ELECTRICAL POWER AND SAFETY RELATED EQUIPMENT WERE |
| PROTECTED AND AVAILABLE. THE "D" EMERGENCY DIESEL GENERATOR HAD BEEN |
| CLEARED AND TAGGED FOR SCHEDULED MAINTENANCE, AND THE "DD447" 125 VDC |
| BATTERY WAS ALSO CLEARED AND TAGGED FOR SCHEDULED MAINTENANCE. THE LOSS OF |
| THE 4.16 KV BUS DE-ENERGIZED THE ASSOCIATED "D" CHANNEL 480 VAC UNIT |
| SUBSTATION, MOTOR CONTROL CENTERS, AND UNINTERRUPTIBLE POWER SUPPLIES. THE |
| LOSS OF THIS ASSOCIATED EQUIPMENT CAUSED A LOSS OF THE CONTROL ROD POSITION |
| INDICATION, REACTOR BUILDING VENTILATION, AND REACTOR WATER CLEANUP PUMPS. |
| THE "A" RHR PUMP REMAINED IN SHUTDOWN COOLING AND WAS NOT AFFECTED BY THE |
| LOSS OF THE "D" BUS. THE FRVS SYSTEM WAS PLACED IN SERVICE TO RESTORE THE |
| REACTOR BUILDING TO A NEGATIVE PRESSURE. ONE OF TWO COMMON SHUTDOWN COOLING |
| SUCTION ISOLATION VALVES WAS DE-ENERGIZED IN THE OPEN POSITION, AS WELL AS |
| THE "A" SHUTDOWN COOLING RETURN TO THE REACTOR VESSEL. CORE ALTERATIONS |
| WERE TERMINATED AT THE TIME OF THE EVENT, AND THERE WAS NO IMPACT TO PLANT |
| SAFETY. BUS RESTORATION AND ROOT CAUSE INVESTIGATION IS IN PROGRESS. |
| |
| THE RESIDENT INSPECTOR WAS NOTIFIED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 35385 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: COGEMA MINING INC. |NOTIFICATION DATE: 02/19/1999|
|LICENSEE: COGEMA MINING INC. |NOTIFICATION TIME: 17:07[EST]|
| CITY: LINCH REGION: 4 |EVENT DATE: 02/17/1999|
| COUNTY: CAMPBELL STATE: WY |EVENT TIME: 12:00[MST]|
|LICENSE#: SUA-1341 AGREEMENT: N |LAST UPDATE DATE: 02/19/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |LAWRENCE YANDELL R4 |
| |CHARLEY HAUGHNEY NMSS |
+------------------------------------------------+JOE HOLONICH NMSS |
| NRC NOTIFIED BY: VASELIN (RSO) | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NLTR LICENSEE 24 HR REPORT | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MONITOR WELL PLACED ON EXCURSION STATUS |
| |
| A ROUTINE BI-WEEKLY WATER SAMPLE COLLECTED ON 02/17/99 FROM MONITOR WELL |
| "6MW40", EXCEEDED ALL 3 OF ITS UPPER CONTROL LIMITS UCLs. A CONFIRMATION |
| SAMPLE WAS COLLECTED 2/19/99, WHICH ALSO EXCEEDED ALL 3 UCLs. MONITOR WELL |
| "6MW40" WAS THEN PLACED ON EXCURSION STATUS AS PER LICENSE SECTION 11.2 AND |
| ITS SAMPLING FREQUENCY INCREASED TO WEEKLY. "6MW40" IS A PERIMETER ORE ZONE |
| MONITOR WELL LOCATED APPROXIMATELY 180 FEET (MAX. CAN BE 300 FT) EAST OF THE |
| MINE UNIT 6 BOUNDARY AT THE CHRISTENSEN MINE, CAMPBELL COUNTY, WYOMING. THE |
| NEAREST COMMUNITY IS LINCH, WYOMING, APPROXIMATELY 15 MILES TO THE |
| SOUTHEAST. |
| |
| |
| ANALYSIS DATA: |
| |
| DATE CHLORIDE mg/l CONDUCTIVITY �mhos/cm� ALKALINITY |
| mg/l URANIUM mg/l U3O8 |
| SAMPLED UCL 20.0 UCL 1576 |
| UCL 95.2 NO UCL |
| ---------------------------------------------------------------------------- |
| ------------------------------------------------------------------------ |
| 2/17/99 39.2 1861 |
| 386.2 <0.4 |
| |
| 2/19/99 25.9 1660 |
| 260.8 <0.4 |
| |
| THERE ARE NO HEALTH OR ENVIRONMENTAL HAZARDS FROM THE RESULTS OF THIS |
| EXCURSION. |
| |
| CORRECTIVE ACTION: OVER-RECOVERY PUMPING OF 50 GPM HAS BEGUN IN THE |
| WELLFIELD AREA NEAREST MONITOR WELL "6MW40". |
| |
| A WRITTEN NOTIFICATION WILL BE SUBMITTED TO NRC URANIUM RECOVERY BRANCH |
| WITHIN 7 DAYS. |
| |
| HOO NOTE: SEE EVENT #35190 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35386 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 02/20/1999|
| UNIT: [] [] [3] STATE: IL |NOTIFICATION TIME: 06:02[EST]|
| RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 02/20/1999|
+------------------------------------------------+EVENT TIME: 04:14[CST]|
| NRC NOTIFIED BY: SALGADO |LAST UPDATE DATE: 02/20/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MIKE JORDAN 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
| | |
|3 A N 0 Cold Shutdown |0 Cold Shutdown |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| A FULL REACTOR SCRAM OCCURRED DURING RESTORATION LINEUP AFTER A HYDROSTATIC |
| TEST |
| |
| Unit 3 experienced a full reactor scram (no rod motion), group 2 (Reactor |
| Water Cleanup, drywell atmosphere) isolation and group 3 (shutdown cooling) |
| isolation while in mode 4 (cold shutdown). Actual reactor vessel water |
| level was plus 32 inches (scram/isolation setpoint is approximately plus 15 |
| inches). This event occurred during the restoration from the hydrostatic |
| test lineup (probably a pressure spike on a instrument line during the |
| restoration lineup caused this event). Shutdown cooling was lost for |
| approximately 10 minutes. There was no discernable rise in reactor vessel |
| water temperature during the time period shutdown cooling was inoperable. |
| The licensee is investigating the cause of the reactor scram and the group |
| isolations. |
| |
| The NRC resident inspector will be informed of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 35387 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 02/20/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 08:44[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 02/19/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 10:05[CST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 02/20/1999|
| CITY: PADUCAH REGION: 3 +-----------------------------+
| COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION |
|LICENSE#: GDP-1 AGREEMENT: Y |MIKE JORDAN R3 |
| DOCKET: 0707001 |CHARLEY HAUGHNEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: K. A. BEASLEY | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NCFR NON CFR REPORT REQMNT | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| WATER INVENTORY CONTROL SYSTEM ACTIVATION |
| |
| A water inventory control system (WICS) activation occurred on C-360 |
| position 4 autoclave on February 19, 1999 at 1005 CST. A high level drain |
| primary alarm was received during a cylinder sampling heat cycle. The |
| safety system did operate as required (shuts off steam to the autoclave |
| which reduces the amount of condensation in the autoclave). The purpose of |
| the WICS is to limit the amount of condensate in the autoclave. The cause of |
| this actuation is being investigated. The certificate holder thinks that |
| this event might have been caused by an invalid signal and if it is |
| determined that this event was caused by an invalid signal this event |
| notification will be retracted at a later time. |
| |
| The safety system actuation is reportable per Safety Analysis Report, |
| section 6.9 Table 1, criteria J.2, Safety System actuation due to a valid |
| signal as a 24-hour event notification. |
| |
| |
| The NRC resident inspector was notified of this event. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35388 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 02/20/1999|
| UNIT: [1] [2] [3] STATE: AZ |NOTIFICATION TIME: 10:30[EST]|
| RXTYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 02/20/1999|
+------------------------------------------------+EVENT TIME: 06:48[MST]|
| NRC NOTIFIED BY: DANN R. DAILEY |LAST UPDATE DATE: 02/22/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |LAWRENCE YANDELL R4 |
|10 CFR SECTION: | |
|AESS 50.72(b)(1)(v) EMERGENCY SIREN INOP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
|3 N Y 100 Power Operation |100 Power Operation |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THE OFFSITE EMERGENCY SIREN SYSTEM SILENT AND BACKUP TEST FAILED. |
| |
| On 02/20/99 at approximately 0648 MST, Palo Verde was notified by the |
| Maricopa County Sheriff's Office (MCSO) of a failure of the Offsite Siren |
| System in the Emergency Planning Zone. The discovery was during a scheduled |
| silent test of the sirens by MCSO personnel. At approximately 0720 MST, the |
| Department of Public Safety performed a back-up test of the Offsite Siren |
| System that also failed. Emergency Planning personnel have been notified |
| and are responding to correct the problem. Investigation of the above |
| problem is in progress. |
| |
| The NRC resident inspector was notified of this event by the licensee. |
| |
| |
| ***Update by Dann R. Dailey on 02/20/99 at 1034 EST taken by MacKinnon*** |
| |
| The Offsite Siren System was successfully tested and returned to service at |
| 0820 MST. R4DO (Larry Yandell) notified. |
| |
| The NRC resident inspector will be notified of this update by the licensee. |
| |
| |
| **** UPDATE ON 2/20/99 @ 1428 BY MARKS TO GOULD *** |
| |
| ALL 39 SIRENS WERE RETURNED TO SERVICE AT 0820 MST. CAUSE OF FAILURE WAS |
| DUE TO PERSONNEL ERROR. A TEST TONE WAS INADVERTENTLY LEFT ON THE PHONE |
| LINE AND IT INTERFERED WITH THE ABILITY TO ACTIVATE THE OFF-SITE SIRENS. |
| |
| THE RESIDENT INSPECTOR WAS NOTIFIED. THE REG 4 RDO(YANDELL) WAS INFORMED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 35389 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 02/20/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 21:38[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 02/19/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 23:00[EST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 02/20/1999|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |MIKE JORDAN R3 |
| DOCKET: 0707002 |CHARLEY HAUGHNEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: SPAETH | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NCFR NON CFR REPORT REQMNT | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| CRITICALITY ACCIDENT ALARM SYSTEM (CAAS) "SLAVE" SYSTEM DECLARED |
| INOPERABLE. |
| |
| AT 2300 ON 2/19/99, AN INSTRUMENT MAINTENANCE WORK CREW DISCOVERED THE |
| NITROGEN BOTTLE VALVED OFF WHILE RESPONDING TO A TROUBLESHOOT AND REPAIR |
| WORK PACKAGE FOR THE X-700 CAAS "SLAVE" SYSTEM. THE REQUIRED ACTIONS FOR |
| THIS LCO WERE NOT IMPLEMENTED UNTIL THE CAAS "SLAVE" SYSTEM WAS DECLARED |
| INOPERABLE AT 2234 |
| |
| THIS DISCOVERY RESULTED IN A NONCOMPLIANCE WITH TECHNICAL SAFETY REQUIREMENT |
| (TSR) 2.8.3.1b LIMITING CONDITION OF OPERATION (LCO), WHICH STATES THE |
| CRITICALITY ACCIDENT ALARM SHALL BE OPERABLE (AUDIBLE). |
| |
| THE X-700 BUILDING IS PROVIDED WITH BOTH A CAAS CLUSTER WITH ITS ASSOCIATED |
| NITROGEN BOTTLE AND A "SLAVE" NITROGEN-DRIVEN HORN SYSTEM (INCLUDES 3 HORNS) |
| TO PROVIDE ADEQUATE AUDIBILITY WITHIN THE BUILDING IN THE UNLIKELY EVENT OF |
| A NUCLEAR CRITICALITY. |
| |
| THE CAAS CLUSTER AND ITS ASSOCIATED NITROGEN HORN REMAINED OPERABLE |
| THROUGHOUT THIS EVENT, THEREFORE, TSR COMPLIANCE WITH THE LCO. CRITICALITY |
| ACCIDENT DETECTION WAS MAINTAINED. |
| |
| THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIAL OR |
| RADIOACTIVE/RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT. |
| |
| THE NRC RESIDENT INSPECTOR WAS INFORMED AND THE DOE REPRESENTATIVE WILL BE |
| NOTIFIED |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35390 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 02/21/1999|
| UNIT: [1] [] [] STATE: NH |NOTIFICATION TIME: 11:28[EST]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 02/20/1999|
+------------------------------------------------+EVENT TIME: 21:00[EST]|
| NRC NOTIFIED BY: STEVE MORRISSEY |LAST UPDATE DATE: 02/21/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JIM TRAPP R1 |
|10 CFR SECTION: | |
|NLTR LICENSEE 24 HR REPORT | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| ELEVEN DEAD SEA DUCKS FOUND IN CIRCULATING WATER SCREEN WASH DEBRIS |
| |
| Eleven dead sea ducks were observed in Seabrook station's circulating water |
| screen wash debris on February 20, 1999 at approximately 2100 hours. It is |
| not known at this time whether the ducks were alive or dead upon entering |
| the offshore intake structure. Sea ducks are diving birds which feed |
| underwater. This is a 24 hour notification in accordance with section 4.1 |
| of the environmental protection plan, appendix B of the operating license. |
| |
| The NRC resident inspector was notified of this event report by the |
| licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35391 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 02/21/1999|
| UNIT: [1] [] [] STATE: MS |NOTIFICATION TIME: 22:25[EST]|
| RXTYPE: [1] GE-6 |EVENT DATE: 02/21/1999|
+------------------------------------------------+EVENT TIME: 20:50[CST]|
| NRC NOTIFIED BY: HANKS |LAST UPDATE DATE: 02/21/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |LAWRENCE YANDELL R4 |
|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 Y 100 Power Operation |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| REACTOR WAS MANUALLY SCRAMMED FROM 100% POWER DUE TO LOSS OF CONDENSER |
| VACUUM. |
| |
| THE "A" MAIN CONDENSER HAD A SEAL FAILURE ON THE EXPANSION JOINT WHICH |
| RESULTED IN A DECREASE AND LOSS OF CONDENSER VACUUM. DUE TO THIS |
| CONDITION, A MANUAL SCRAM WAS INITIATED FOLLOWED BY A MAIN TURBINE TRIP. |
| THE CONTROLLED SHUTDOWN HAD NO IMMEDIATE PROBLEMS. ALL RODS FULLY INSERTED. |
| NO ECCS ACTUATIONS OCCURRED. THE LICENSEE ANTICIPATES THAT REACTOR VESSEL |
| PRESSURE MAY BE LATER CONTROLLED VIA THE RELIEF VALVES DEPENDING ON THE |
| COOLDOWN RATE (REACTOR VESSEL PRESSURE IS CURRENTLY 550 LBS). THE CURRENT |
| HEAT SINK IS THE MAIN CONDENSER, BUT THE LICENSEE IS PREPARING TO SHUT THE |
| MSIVs AND SHIFT THE HEAT SINK TO THE SUPPRESSION POOL. |
| |
| THE RESIDENT INSPECTOR WAS NOTIFIED. |
+------------------------------------------------------------------------------+
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