U.S. Nuclear Regulatory Commission Operations Center Event Reports For 07/01/96 - 07/02/96 ** EVENT NUMBERS ** 30680 30697 30698 30699 30700 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30680 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 06/26/96 | |UNIT: [ ] [2] [ ] STATE: NC |NOTIFICATION TIME: 14:42 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/12/96 | +------------------------------------------------+EVENT TIME: 00:00[EDT]| |NRC NOTIFIED BY: JAMES SNYDER |LAST UPDATE DATE: 07/01/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KERRY LANDIS RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - FAILURE OF A REACTOR TRIP BYPASS BREAKER DURING A SURVEILLANCE TEST - | | | | DURING A SURVEILLANCE OF THE UNIT 2 REACTOR TRIP BYPASS BREAKER "2A", THE | | BYPASS BREAKER DID NOT TRIP AS REQUIRED WHILE IN THE TEST POSITION. THE | | REACTOR TRIP SYSTEM REMAINED FULLY FUNCTIONAL; HOWEVER, SURVEILLANCE | | TESTING COULD NOT BE PERFORMED DUE TO THE FAILURE OF THE BYPASS BREAKER | | TRIP. SITE NRC PERSONNEL WERE NOTIFIED ON 06/13/96. THIS NOTIFICATION | | (SPECIAL REPORT) IS MADE PER THE REPORTING REQUIREMENTS OF MCGUIRE UNIT 2 | | FACILITY OPERATING LICENSE NPF-17, AMENDMENT 2, DATED 05/27/83. ONSITE | | FAILURE INVESTIGATION IS PROCEEDING. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * 1124 JULY 1, 1996, UPDATE FROM CRANE RECEIVED BY TROCINE * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT BECAUSE THE LICENSE CONDITION TO | | REPORT ANY FAILURES ASSOCIATED WITH REACTOR TRIP BYPASS BREAKERS IS NO | | LONGER PART OF THE LICENSEE'S LICENSE OR TECHNICAL SPECIFICATIONS. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND PLANS TO SUBMIT A | | RETRACTION OF A WRITTEN FOLLOWUP NOTIFICATION (AN ABSTRACT OF A SPECIAL | | REPORT) THAT WAS SUBMITTED TO THE REGIONAL OFFICE. THE NRC OPERATIONS | | CENTER NOTIFIED THE R2DO (LANDIS). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30697 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 06/30/96 | |UNIT: [ ] [2] [ ] STATE: NC |NOTIFICATION TIME: 05:18 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/30/96 | +------------------------------------------------+EVENT TIME: 05:07[EDT]| |NRC NOTIFIED BY: JIM PHILLIPS |LAST UPDATE DATE: 07/01/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KERRY LANDIS RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 HOT STANDBY | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BRIEF LOSS OF CONTAINMENT INTEGRITY AND TECHNICAL SPECIFICATION 3.0.3 ENTRY | | DUE TO FAILURE OF SEALS ON THE REACTOR SIDE CONTAINMENT AIR LOCK DOOR | | | | WHEN TWO INDIVIDUALS ENTERED THE CONTAINMENT AIR LOCK AT 0445 FOLLOWING THE | | PERFORMANCE OF WORK IN THE LOWER CONTAINMENT, THE REACTOR SIDE AIR LOCK | | DOOR CLOSED, BUT THE SEALS STAYED DEFLATED. THE AUXILIARY SIDE DOOR WILL | | NOT OPEN UNLESS THE REACTOR SIDE AIR LOCK DOOR SEALS ARE INFLATED. AS A | | RESULT, THE AUXILIARY SIDE DOOR WAS PLACED IN BYPASS AND OPENED AT 0507 TO | | ALLOW THE INDIVIDUALS TO EXIT THE AIRLOCK. THE AUXILIARY SIDE DOOR | | RECLOSED AND RESEALED AT 0509. DURING THIS 2-MINUTE PERIOD, THE LICENSEE | | ENTERED TECHNICAL SPECIFICATION 3.0.3 BECAUSE CONTAINMENT INTEGRITY WAS | | LOST WHEN BOTH AIR LOCK DOORS WERE TECHNICALLY OPEN AT THE SAME TIME. | | | | (NOTE: EVEN THOUGH THE REACTOR SIDE AIR LOCK DOOR SEALS WOULD NOT INFLATE, | | THE DOOR ITSELF COULD HAVE BEEN OPENED TO ALLOW THE INDIVIDUALS TO GO BACK | | INTO CONTAINMENT. THE INDIVIDUALS COULD THEN HAVE EXITED CONTAINMENT | | THROUGH THE UPPER CONTAINMENT OR THE ICE CONDENSER. THE LICENSEE ELECTED | | TO OPEN THE AUXILIARY AIR LOCK DOOR INSTEAD BECAUSE THE INDIVIDUALS WERE | | HOT, TIRED, AND STRESSED. THERE WERE NO INJURIES ASSOCIATED WITH THIS | | EVENT.) | | | | (NOTE: TECHNICAL SPECIFICATION 3.0.3 WAS ENTERED BECAUSE TECHNICAL | | SPECIFICATION 3.6.1.3 FOR THE AIR LOCK DOORS HAS THE SAME ACTION STATEMENTS | | AS TECHNICAL SPECIFICATION 3.0.3. THE LICENSEE WILL NEED TO RE-ENTER | | TECHNICAL SPECIFICATION 3.0.3 IN ORDER TO ALLOW INDIVIDUALS INTO THE AIR | | LOCK TO REPAIR THE FAILED SEALS.) | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE 1437 EDT ON 07/01/96, FROM JAMES SANDER TO S. SANDIN * * * | | | | THE LICENSEE IS RETRACTING THIS REPORT AFTER REVIEWING AN ANALYSIS AT 1230 | | EDT WHICH CONCLUDED THAT THE ENTRY INTO TECHNICAL SPECIFICATION 3.0.3 WAS | | INAPPROPRIATE AND OVERLY CONSERVATIVE. IN FACT, TECHNICAL SPECIFICATION | | 3.6.1.3.a.3 APPLIED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R2DO (LANDIS). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30698 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 07/01/96 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 10:49 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 07/01/96 | +------------------------------------------------+EVENT TIME: 09:30[CDT]| |NRC NOTIFIED BY: TERRY L. RATZLAFF |LAST UPDATE DATE: 07/01/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES CAIN RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | STATE NOTIFICATION OF HIGH CIRCULATING WATER DISCHARGE TEMPERATURE | | | | AT 0930 CDT ON JULY 1, 1996, THE LICENSEE NOTIFIED THE STATE OF NEBRASKA | | DEPARTMENT OF ENVIRONMENTAL QUALITY (NDEQ) THAT NATIONAL POLLUTION | | DISCHARGE ELIMINATION SYSTEM (NPDES) REQUIREMENTS WERE EXCEEDED WHEN | | CIRCULATION WATER DISCHARGE TEMPERATURE EXCEEDED 103øF FOR APPROXIMATELY 24 | | MINUTES (FROM 0324 CDT TO 0348 CDT ON JULY 1, 1996). THE MAXIMUM | | TEMPERATURE REACHED WAS 104.9øF. THIS EVENT OCCURRED DURING ROUTINE | | BACKWASHING OF THE MAIN CONDENSER. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND THE STATE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 30699 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: US ARMY |NOTIFICATION DATE: 07/01/96 | | CITY: FT. SILL REGION: 4 |NOTIFICATION TIME: 17:00 [ET]| | COUNTY: STATE: OK |EVENT DATE: 06/28/96 | |LICENSE#: AGREEMENT: N |EVENT TIME: 14:45[CDT]| | DOCKET: |LAST UPDATE DATE: 07/01/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |CHARLES CAIN RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: JEFF ILES | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TWO EXIT SIGNS, EACH CONTAINING 5 SOURCES OF 5 Ci TRITIUM OR 25 Ci TOTAL, | | WERE REPORTED DAMAGED ON JUNE 28, 1996, AT 1445 CDT. THE TWO EXITS SIGNS | | WERE LOCATED IN A BUILDING AT FORT SILL, OK, SCHEDULED FOR DEMOLITION. | | REGION IV OFFICE (RADCLIFFE) INFORMED. | | | | SEE HOO LOG FOR CALLER'S TELEPHONE NUMBER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30700 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BYRON REGION: 3 |NOTIFICATION DATE: 07/02/96 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 04:56 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 07/02/96 | +------------------------------------------------+EVENT TIME: 03:16[CDT]| |NRC NOTIFIED BY: MIKE WINTER |LAST UPDATE DATE: 07/02/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON RDO | |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 | M/R Y 15 STARTUP | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR TRIP FROM 15% POWER (WITH THE UNIT OFF LINE) DUE TO THE | | CLOSURE OF A STEAM GENERATOR FEEDWATER ISOLATION VALVE WHICH RESULTED FROM | | A BROKEN INSTRUMENT AIR SUPPLY LINE | | | | AT APPROXIMATELY 0312 CDT, THE '1B' STEAM GENERATOR FEEDWATER ISOLATION | | VALVE (1FW039B) FAILED CLOSED DUE TO A BROKEN INSTRUMENT AIR SUPPLY LINE. | | THIS VALVE FAILURE RESULTED IN INADEQUATE FEEDWATER FLOW TO THE '1B' STEAM | | GENERATOR. AS A RESULT, THE UNIT 1 REACTOR WAS MANUALLY TRIPPED AT 0316 | | CDT PRIOR STEAM GENERATOR LEVEL REACHING THE AUTOMATIC TRIP SETPOINT OF | | LOW-2 STEAM GENERATOR LEVEL. LEVEL DECREASED TO THE LOW-2 STEAM GENERATOR | | LEVEL SETPOINT FOLLOWING THE MANUAL REACTOR TRIP RESULTING IN AUTOMATIC | | INITIATION OF AUXILIARY FEEDWATER. A FEEDWATER ISOLATION WAS ALSO | | RECEIVED. ALL RODS FULLY INSERTED FOLLOWING THE TRIP, AND ALL EQUIPMENT | | RESPONDED AND OPERATED AS EXPECTED. | | | | THE UNIT IS CURRENTLY STABLE IN HOT STANDBY. IN ORDER TO SECURE AUXILIARY | | FEEDWATER, THE LICENSEE IS IN THE PROCESS OF RESTORING NORMAL FEEDWATER TO | | THE STEAM GENERATORS. THE CONDENSER IS ALSO AVAILABLE AS A HEAT SINK. IN | | ADDITION, NORMAL CHARGING AND MAKEUP, PRESSURIZER HEATERS AND SPRAYS, AND | | THE REACTOR COOLANT PUMPS ARE BEING UTILIZED FOR PRIMARY SYSTEM INVENTORY, | | PRESSURE, AND TRANSPORT CONTROL. THE LICENSEE PLANS TO REPAIR THE BROKEN | | INSTRUMENT AIR SUPPLY LINE, AND UNIT RESTART IS CURRENTLY SCHEDULED FOR | | LATER TODAY. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+