Event Notification Report for March 3, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
03/02/1999 - 03/03/1999
** EVENT NUMBERS **
35384 35427 35428 35429 35430 35431 35432 35433 35434
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|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: 03/02/1999|
| 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. |
| |
| |
| * * * UPDATE ON 3/2/99 @ 2215 BY CONICELLA TO GOULD * * * EVENT RETRACTION |
| |
| THE LICENSEE HAS REVIEWED THIS EVENT AND HAS DETERMINED THAT THE SELF |
| INDUCED UNDERVOLTAGE CONDITION ON THE BUS DID NOT ACTUATE THE ESF EQUIPMENT |
| (DIESEL GENERATOR) SINCE IT WAS REMOVED FROM SERVICE. THEREFORE, THIS |
| EVENT WAS NOT REPORTABLE AND IS BEING RETRACTED. |
| |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED. |
| |
| THE REG 1 RDO (MODES) WAS NOTIFIED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35427 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 03/02/1999|
| UNIT: [] [2] [] STATE: GA |NOTIFICATION TIME: 04:32[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/02/1999|
+------------------------------------------------+EVENT TIME: 02:06[EST]|
| NRC NOTIFIED BY: LEE MANSFIELD |LAST UPDATE DATE: 03/02/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ROBERT HAAG 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 M/R Y 100 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - MANUAL Rx TRIP FROM 100% DUE TO CLOSURE OF LOOP 3 MAIN FEEDWATER ISOLATION |
| VALVE - |
| |
| WHILE IN THE PROCESS OF HANGING AN OUTAGE CLEARANCE TAG ON UNIT 1 EQUIPMENT |
| (SEE EVENT #35421), PLANT TECHNICIANS ERRONEOUSLY PULLED THE FUSES TO THE |
| UNIT 2 LOOP 3 MAIN FEEDWATER ISOLATION VALVE (#2HV-5229) TO #3 STEAM |
| GENERATOR CAUSING THE VALVE TO CLOSE. CONTROL ROOM OPERATORS OBSERVED THE |
| LOW WATER LEVEL IN #3 STEAM GENERATOR AND THE STEAM FLOW/FEED FLOW MISMATCH |
| ANNUNCIATORS. |
| |
| AT 0206 ON 03/02/99, CONTROL ROOM OPERATORS MANUALLY TRIPPED THE REACTOR |
| FROM 100% POWER. ALL CONTROL RODS INSERTED COMPLETELY. THE AUXILIARY |
| FEEDWATER SYSTEM ACTUATED, AS EXPECTED. STEAM IS BEING DUMPED TO THE MAIN |
| CONDENSER. |
| |
| DURING THE TRIP, AN ELECTRO-HYDRAULIC CONTROL (EHC) SYSTEM POWER SUPPLY |
| FAILED CAUSING ERRONEOUS INDICATIONS OF MAIN CONDENSER VACUUM AND EHC |
| PRESSURE. |
| |
| UNIT 2 IS STABLE IN MODE 3 (HOT STANDBY). |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35428 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 03/02/1999|
| UNIT: [1] [2] [] STATE: MI |NOTIFICATION TIME: 13:14[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/02/1999|
+------------------------------------------------+EVENT TIME: 09:20[EST]|
| NRC NOTIFIED BY: KOSLOFF |LAST UPDATE DATE: 03/02/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: |JAMES CREED R3 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
|2 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| ICE CONDENSER DESIGN BASIS BYPASS FLOW COULD BE EXCEEDED FOLLOWING A STEAM |
| LINE RUPTURE AND STRUCTURAL FAILURE IN THE STEAM GENERATOR COMPARTMENT. |
| |
| "This is Don Kosloff at American Electric Power, DC Cook Plant, calling with |
| a notification under 10CFR50.72 (b)(2)(i), a condition which was found while |
| the reactor was shutdown, which if it had been found while the reactor was |
| operating, would have resulted in the nuclear power plant being in an |
| unanalyzed condition, outside the design basis. |
| |
| "The Cook units are pressurized water reactors with ice condenser |
| containments. The ice condenser containment requires that the steam and air |
| flowing from the lower containment compartment in the event of an accident |
| be routed to the upper containment compartment through the ice condenser ice |
| bed. To accomplish this, a structural barrier, called the divider barrier, |
| separates the lower and upper containment compartments. The divider barrier |
| includes the walls of the ice compartment, the upper deck, the gates |
| separating the reactor cavity from the refueling canal, portions of the |
| walls of the refueling canal, and the compartments enclosing the upper |
| portion of the steam generators and pressurizer. |
| |
| "The design basis limits bypass flow around the ice bed to no more than 5 |
| square feet. For Unit 1, the installed bypass through the refueling cavity |
| drains is equivalent to 2.2 square feet plus approximately 0.36 square feet |
| bypass via the backdraft damper of the air return fans, totaling 2.56 square |
| feet of bypass area. The construction of Unit 2 is similar. On August 12, |
| 1998, it was determined that the cumulative bypass area for unit 1, had been |
| equivalent to 5.71 square feet. This condition was reported on September |
| 11,1998 in LER 50-315/98-037. During a recent review of existing structural |
| design calculations, AEP personnel determined that there was a potential for |
| a steam line break to overstress the associated steam generator compartment. |
| Such a steam line break inside a steam generator compartment could cause an |
| additional bypass opening through the reinforced concrete walls of the |
| compartment. Such an opening would increase the cumulative effective bypass |
| opening. The size of such an opening has not been determined. Therefore, the |
| safety significance of this potential condition cannot yet be determined. |
| Additional calculations are planned." |
| |
| The resident inspector has been informed. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35429 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 03/02/1999|
| UNIT: [1] [2] [] STATE: MI |NOTIFICATION TIME: 14:17[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/02/1999|
+------------------------------------------------+EVENT TIME: 13:52[EST]|
| NRC NOTIFIED BY: KOSLOFF |LAST UPDATE DATE: 03/02/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES CREED 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 N 0 Cold Shutdown |0 Cold Shutdown |
|2 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| Plant reported a loss of emergency response capability. |
| |
| The Emergency Operations Facility requires three shifts of personnel. Each |
| shift requires 7 communicators. All 21 communicators participated in EP |
| drills. However, only 5 of the 21 have completed qualification |
| documentation. Should an event occur that requires use of the EOF, the EP |
| supervisor will mentor the unqualified communicators. An additional |
| corrective action will be reinstatement of individuals previously qualified. |
| Both Units are currently in Mode 5. |
| |
| |
| The Resident Inspector was informed. |
| |
| |
| *** UPDATE ON 3/2/99 @ 2240 BY DEPUYDT TO GOULD *** |
| |
| THIS UPDATE IS TO CLARIFY THE INITIAL INFORMATION PROVIDED. |
| |
| EACH EOF "TEAM" HAS 12 CRITICAL POSITIONS. OF THESE 12 POSITIONS, 7 ARE |
| COMMUNICATOR POSITIONS. FOR THE 3 EOF TEAMS THAT COOK HAS, A TOTAL OF 21 |
| QUALIFIED COMMUNICATORS ARE REQUIRED. |
| |
| CURRENTLY, THEY HAVE ONLY 5 FULLY QUALIFIED COMMUNICATORS OUT OF THE |
| REQUIRED 21, AND OF THOSE 5, FOUR ARE ALL QUALIFIED FOR THE SAME POSITION. |
| |
| |
| THEREFORE, DUE TO THE SHORTAGE OF QUALIFIED COMMUNICATORS TO MAN THE |
| REQUIRED CRITICAL POSITIONS, THE EOF CANNOT BE MANNED WITH A FULL TEAM OF |
| QUALIFIED INDIVIDUALS. AS AN INTERIM ACTION, SHOULD AN EVENT OCCUR THAT |
| REQUIRES THE ACTIVATION OF THE EOF, THE INDIVIDUALS CURRENTLY ON THE CALL |
| OUT LIST FOR THOSE COMMUNICATOR POSITIONS WOULD BE CALLED OUT AND THE |
| EMERGENCY PLANNING SUPERVISOR WOULD MENTOR THOSE UNQUALIFIED INDIVIDUALS IN |
| THEIR DUTIES. |
| |
| WITHIN THE NEXT 24 HOURS, CORRECTIVE ACTION WILL BE IMPLEMENTED BY |
| REQUALIFICATION AND REINSTATEMENT OF THE INDIVIDUALS WHO WERE PREVIOUSLY |
| QUALIFIED FOR THE COMMUNICATOR POSITIONS. |
| |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED. |
| |
| THE REG 3 RDO(CREED) WAS NOTIFIED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 35430 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: STATE OF FLORIDA BUREAU OF RAD. CTL |NOTIFICATION DATE: 03/02/1999|
|LICENSEE: FLORIDA DEPT OF TRANSPORTATION |NOTIFICATION TIME: 15:10[EST]|
| CITY: DELAND REGION: 2 |EVENT DATE: 03/02/1999|
| COUNTY: STATE: FL |EVENT TIME: 14:15[EST]|
|LICENSE#: 0109-1 AGREEMENT: Y |LAST UPDATE DATE: 03/02/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |CAUDLE JULIAN R2 |
| |FRED COMBS NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: ADAMS | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| A SOIL MOISTURE DENSITY GAUGE INVOLVED IN A MAJOR VEHICLE ACCIDENT. |
| |
| A TROXLER GAUGE MODEL # 3440 (SERIAL #21764 CONTAINING 8 mCi OF Cs-137 AND |
| 40 mCi OF |
| Am-241:Be) WAS TRANSPORTED IN A VEHICLE THAT WAS INVOLVED IN A MAJOR TRAFFIC |
| ACCIDENT INVOLVING 3 FATALITIES. THERE WAS NO APPARENT DAMAGE TO THE GAUGE |
| AND ITS CASE. THE GAUGE WILL BE LEAK TESTED AND RESULTS WILL BE FORWARDED |
| TO THE STATE RADIATION CONTROL OFFICE. THERE MAY BE MEDIA INTEREST. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 35431 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: ARKANSAS DEPT OF HEALTH RAD CONTROL |NOTIFICATION DATE: 03/02/1999|
|LICENSEE: |NOTIFICATION TIME: 17:23[EST]|
| CITY: WEST MEMPHIS REGION: 4 |EVENT DATE: 03/02/1999|
| COUNTY: STATE: AR |EVENT TIME: [CST]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 03/02/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |BILL JONES R4 |
| |CAUDLE JULIAN R2 |
+------------------------------------------------+WAYNE HODGES NMSS |
| NRC NOTIFIED BY: SNELLINGS |DON COOL NMSS |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TROXLER GAUGE FOUND IN SHOPPING MALL IN WEST MEMPHIS ARKANSAS |
| |
| A PRIVATE CITIZEN FOUND A TROXLER GAUGE MODEL 3411B AT A SHOPPING MALL IN |
| WEST MEMPHIS, ARKANSAS. THE CITIZEN REPORTED IT TO THE POLICE AND THE WEST |
| MEMPHIS FIRE DEPT HAZMAT TEAM RESPONDED TO THE MALL. THE GAUGE, WHICH |
| BELONGED TO A TENNESSEE LICENSEE, WAS TURNED INTO THE ARKANSAS DIVISION OF |
| RADIATION CONTROL. THE STATE OF TENNESSEE DEPARTMENT OF RADIOLOGICAL HEALTH |
| HAS BEEN NOTIFIED BY THE DIVISION OF RADIATION CONTROL OF THE ARKANSAS |
| DEPARTMENT OF HEALTH. TENNESSEE WILL HAVE THEIR LICENSEE RETRIEVE THE GAUGE |
| FROM THE ARKANSAS DIVISION OF RADIATION CONTROL. THERE APPEARED TO BE NO |
| DAMAGE TO THE GAUGE OR ITS CASE AND NO ABNORMAL RADIATION LEVELS WERE |
| MEASURED. THERE WILL BE MEDIA INTEREST. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35432 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HADDAM NECK REGION: 1 |NOTIFICATION DATE: 03/02/1999|
| UNIT: [1] [] [] STATE: CT |NOTIFICATION TIME: 17:24[EST]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 03/02/1999|
+------------------------------------------------+EVENT TIME: 17:17[EST]|
| NRC NOTIFIED BY: PIONTKOWSKI |LAST UPDATE DATE: 03/02/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MICHAEL MODES R1 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Decommissioned |0 Decommissioned |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| A POTENTIAL ERROR WITH THE DOSE TO CONTROL ROOM PERSONNEL WAS IDENTIFIED |
| |
| CR-99-0127 IDENTIFIES A POTENTIAL ERROR WITH THE DOSE TO CONTROL ROOM |
| PERSONNEL DURING A POSTULATED RESIN FIRE ACCIDENT AS DESCRIBED IN THE |
| LICENSEE'S UPDATED FINAL SAFETY ANALYSIS REPORT (UFSAR). THE MAXIMUM ORGAN |
| DOSE REPORTED IN THE UFSAR (SECTION 6.4.4.1) IS 3.83 REM FOR BONE. USING |
| THE SAME CONSERVATIVE SOURCE-TERM ASSUMPTIONS GIVEN IN THE UFSAR AND THE |
| DOSE CONVERSION FACTORS FROM FEDERAL GUIDANCE REPORT 11, THE PRELIMINARY |
| RECALCULATED DOSE IS 54 REM CDE (BONE) AND 3.2 REM CEDE. THE 54 REM BONE |
| DOSE EXCEEDS THE 50 REM LIMIT PRESCRIBED IN 10CFR50 APPENDIX A, GENERAL |
| DESIGN CRITERION (GDC) 19, "CONTROL ROOM." |
| |
| THIS ERROR IS SPECIFIC TO THE CALCULATED CONTROL ROOM DOSE FROM THE RESIN |
| FIRE ACCIDENT SCENARIO. A SIMILAR ANALYSIS WAS PERFORMED FOR THE RESIN FIRE |
| ACCIDENT SCENARIO TO CALCULATE THE OFFSITE DOSE TO MEMBERS OF THE PUBLIC. |
| THIS CALCULATION USED A DIFFERENT METHODOLOGY THAN THE CONTROL ROOM DOSE |
| ANALYSIS AND HAS BEEN VERIFIED. |
| |
| IF THE PLANT OPERATED AS PRESENTLY ALLOWED, THE POTENTIAL EXPOSURE TO |
| CONTROL ROOM OPERATORS COULD EXCEED THE DESIGN BASIS OF GDC 19 FOR THE |
| LIMITING RADIOLOGICAL |
| EVENT, A SPENT RESIN FIRE. IN ACTUAL PRACTICE, THE REQUIRED RADIOACTIVE |
| CONTENT OF RESIN DOES NOT EXIST AT ANY ONE PLACE ON SITE, THEREFORE, AN |
| ACTUAL EVENT EXCEEDING THE GDC 19 CRITERIA IS NOT CURRENTLY POSSIBLE. |
| |
| THE RESIDENT INSPECTOR WILL BE INFORMED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 35433 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: INTERNATIONAL PAPER CO. |NOTIFICATION DATE: 03/02/1999|
|LICENSEE: INTERNATIONAL PAPER CO |NOTIFICATION TIME: 17:52[EST]|
| CITY: LOCK HAVEN REGION: 1 |EVENT DATE: 03/02/1999|
| COUNTY: STATE: PA |EVENT TIME: 15:00[EST]|
|LICENSE#: GL1933-70 AGREEMENT: N |LAST UPDATE DATE: 03/02/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MICHAEL MODES R1 |
| |WAYNE HODGES NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: LAIRD | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NINF INFORMATION ONLY | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THE LICENSEE IS MISSING A CONSISTENCY GAUGE FOR A PAPER MACHINE |
| |
| THE GAUGE, NDC SYSTEMS MODEL # 104, CONTAINS 80 MILLICURIES OF AM-241 AND IS |
| USUALLY MOUNTED TO THE PAPER MACHINE. IT WAS LAST INVENTORIED 6 MONTHS AGO |
| WHEN IT WAS LOCATED IN A BOX IN ONE OF THEIR OFFICES. THEY MAY BE ABLE TO |
| LOCATE IT WHEN THEY CAN CONTACT AN EMPLOYEE WHO MAY KNOW WHERE IT IS. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35434 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 03/02/1999|
| UNIT: [] [2] [] STATE: WI |NOTIFICATION TIME: 18:21[EST]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 03/02/1999|
+------------------------------------------------+EVENT TIME: 16:45[CST]|
| NRC NOTIFIED BY: SHORT |LAST UPDATE DATE: 03/02/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES CREED R3 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 1 Startup |1 Startup |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUXILIARY FEEDWATER LEAKING BACK INTO MAIN FEEDWATER SYSTEM |
| |
| THE LICENSEE DISCOVERED THAT THE AUXILIARY FEEDWATER SYSTEM WAS LEAKING BACK |
| INTO THE MAIN FEED SYSTEM ("B" FEED LINE) PAST TWO IN-SERIES CHECK VALVES. |
| THESE CHECK VALVES ARE CONSIDERED CONTAINMENT ISOLATION VALVES. LEAKAGE IS |
| IN EXCESS OF THEIR ALLOWABLE LIMITS. AUXILIARY FEEDWATER IS CURRENTLY |
| FEEDING THE STEAM GENERATORS. THE LEAKAGE HAS BEEN ISOLATED USING MANUAL |
| VALVES. THE UNIT WAS IN STARTUP FOLLOWING A REFUELING OUTAGE WHEN THE |
| CONDITION WAS FOUND. |
| |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED. |
+------------------------------------------------------------------------------+
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