U.S. Nuclear Regulatory Commission Operations Center Event Reports For 01/15/98 - 01/16/98 ** EVENT NUMBERS ** 33540 33541 33542 33543 33544 33545 33546 33547 33548 33549 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33540 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 01/15/98 | |UNIT: [1] [2] [ ] STATE: MI |NOTIFICATION TIME: 10:01 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/15/98 | +------------------------------------------------+EVENT TIME: 08:30[EST]| |NRC NOTIFIED BY: RANDY PTACEK |LAST UPDATE DATE: 01/15/98 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SHEAR RDO | |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 +------------------------------------------------------------------------------+ | SOLID STATE PROTECTION SYSTEM RELAYS FOUND IN A DEGRADED CONDITION | | | | ON 1/8/98, WHILE PERFORMING SOLID STATE PROTECTION SYSTEM (SSPS) | | SURVEILLANCE TESTING, IT WAS IDENTIFIED THAT UNIT 1'S TRAIN B SSPS MASTER | | RELAY COVERS WERE DEGRADED. THE RETAINING RELAY COVER EARS LOCATED ON THE | | BASE OF THE RELAY HAD WORN TO THE POINT WHERE THE RELAY COVER COULD NO | | LONGER BE PROPERLY RETAINED. ON 1/11/98, A SEISMIC QUALIFICATION PULL TEST | | WAS PERFORMED TO DETERMINE THE SEISMIC ACCEPTABILITY OF THE AS-FOUND SSPS | | TRAINS. THE FOLLOWING RESULTS WERE OBTAINED FROM THE SSPS SEISMIC | | QUALIFICATION PULL TEST: 15 OF 46 UNIT 1 SSPS MASTER RELAYS WERE FOUND IN | | AN UNACCEPTABLE CONDITION AND 23 OF 46 UNIT 2 SSPS MASTER RELAYS WERE FOUND | | IN AN UNACCEPTABLE CONDITION. THE SUBJECT SSPS MASTER RELAYS HAVE ALWAYS | | ELECTRONICALLY PASSED THEIR MONTHLY AND REFUELING OUTAGE SURVEILLANCE TEST | | REQUIREMENTS. | | | | THE CAUSE OF THIS EVENT HAS BEEN ATTRIBUTED TO THE PAST PRACTICE OF | | REMOVING THE SSPS MASTER RELAY COVERS TO PERFORM TESTING. THE REMOVING OF | | THE RELAY COVER RESULTED IN THE COVER RETAINING EARS FOUND ON THE BASE OF | | THE RELAY TO WEAR TO THE POINT WHERE THE COVER COULD NO LONGER BE PROPERLY | | RETAINED. THIS PRACTICE IS NO LONGER IN EFFECT. | | | | ALL SSPS MASTER RELAY WITH UNACCEPTABLE COVERS ARE BEING REPLACED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33541 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 01/15/98 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 10:36 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 01/15/98 | +------------------------------------------------+EVENT TIME: 07:45[CST]| |NRC NOTIFIED BY: BILL BARTLETT |LAST UPDATE DATE: 01/15/98 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SHEAR RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FITNESS FOR DUTY - CONTRACT SUPERVISOR TESTED FOR CAUSE | | | | A CONTRACT SUPERVISOR WAS TESTED FOR CAUSE BASED ON THE ODOR OF ALCOHOL. | | THE SUPERVISOR WAS CONFIRMED POSITIVE FOR ALCOHOL AND HE WAS ESCORTED | | OFFSITE AND HIS SITE ACCESS HAS BEEN SUSPENDED. | | | | A REVIEW OF THE WORK PERFORMED BY THE INDIVIDUAL IS IN PROGRESS. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 33542 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: WESTINGHOUSE ELECTRIC COMPANY |NOTIFICATION DATE: 01/15/98 | | CITY: PITTSBURGH REGION: 1 |NOTIFICATION TIME: 14:07 [ET]| | COUNTY: STATE: PA |EVENT DATE: 01/15/98 | |LICENSE#: AGREEMENT: N |EVENT TIME: 00:00[EST]| | DOCKET: |LAST UPDATE DATE: 01/15/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | | | | | | +------------------------------------------------+VERN HODGE NRR | |NRC NOTIFIED BY: JOHN GALEMBUSH | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 10 CFR PART 21 REPORT REGARDING TESTING OF SOLID STATE PROTECTION SYSTEM | | LOGIC | | | | WESTINGHOUSE WAS RECENTLY NOTIFIED OF SOLID STATE PROTECTION SYSTEM (SSPS) | | CIRCUITS THAT WERE NOT FULLY TESTED DURING SEMI-AUTOMATIC TESTING OF THE | | SYSTEM. THE CIRCUITS NOT FULLY TESTED ARE THE FEEDWATER ISOLATION MEMORY | | CIRCUIT AND THE P-10 SOURCE RANGE BLOCK MEMORY CIRCUIT. THESE CIRCUITS RELY | | ON PARALLELING EACH INPUT TO PROVIDE AN OUTPUT WITHOUT UTILIZING THE | | RETENTIVE MEMORY. THE ORIGINAL TESTING ARRANGEMENT DID NOT VERIFY THAT BOTH | | OF THE PARALLEL INPUTS ARE OPERATIONAL BECAUSE THE SIGNAL (E.G., P-4 FOR | | FEEDWATER ISOLATION) THAT INITIATES THE RETENTIVE MEMORY WAS PRESENT AT THE | | LOGIC GATE INPUT DURING TESTING. AN OPEN LOGIC INPUT ISOLATION DIODE MAY | | PREVENT THE DESIRED OUTPUT FROM THE LOGIC GATE. | | | | FOR ALL PLANTS THAT UTILIZE THE SSPS, THIS LOGIC GATE INITIATES FEEDWATER | | ISOLATION ON A SAFETY INJECTION SIGNAL OR A HI-HI STEAM GENERATOR WATER | | LEVEL SIGNAL. SAFETY INJECTION INITIATES A REACTOR TRIP AND, FOR MOST | | PLANTS, THE HI-HI STEAM GENERATOR WATER LEVEL INITIATES A TURBINE TRIP | | THROUGH SEPARATE LOGIC WHICH LEADS TO A REACTOR TRIP. THESE FUNCTIONS | | PROVIDE A P-4 (REACTOR TRIP) SIGNAL SO FEEDWATER ISOLATION IS INITIATED | | WITH ONLY A SLIGHT DELAY (MILLISECONDS). FOR SEQUOYAH UNITS 1 AND 2 AND | | WATTS BAR THE TURBINE TRIP SIGNAL FROM HI-HI STEAM GENERATOR WATER LEVEL IS | | NOT INITIATED SEPARATELY AND DEPENDS ON THE PROPER FUNCTIONING OF THE LOGIC | | GATE WITH PARALLEL INPUTS, AS DOES FEEDWATER ISOLATION. THE LACK OF | | FEEDWATER ISOLATION COULD LEAD TO WATER CARRYOVER INTO THE STEAM LINES FOR | | THESE PLANTS. | | | | THE SAME TYPE OF CIRCUIT IS USED FOR THE P-10 SOURCE RANGE BLOCK FUNCTION. | | THIS IS A BACK-UP FUNCTION TO P-6 AND IF BOTH OF THESE MALFUNCTIONED IT | | WOULD BE DETECTABLE BY OBSERVING THAT THE SOURCE RANGE WAS NOT BLOCKED AS | | POWER INCREASED. | | | | WESTINGHOUSE HAS DETERMINED THAT CIRCUIT MODIFICATIONS ARE NOT REQUIRED TO | | TEST BOTH PARALLEL INPUTS. BY PRESSING THE RESET SWITCH, THE RETENTIVE | | MEMORY SIGNAL (E.G., P-4 FOR FEEDWATER ISOLATION) IS DEFEATED AND THE | | ABILITY TO OBTAIN AN OUTPUT FROM THE LOGIC GATE CONFIRMS THAT BOTH INPUTS | | ARE FUNCTIONING. WESTINGHOUSE HAS COMMUNICATED THIS INFORMATION TO ALL | | PLANTS UTILIZING THE SSPS VIA TECHNICAL BULLETIN ESBU-TB-97-09, DATED | | DECEMBER 17, 1997. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33543 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 01/15/98 | |UNIT: [1] [2] [ ] STATE: CA |NOTIFICATION TIME: 14:24 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/15/98 | +------------------------------------------------+EVENT TIME: 10:30[PST]| |NRC NOTIFIED BY: WELLS |LAST UPDATE DATE: 01/15/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | |KEN BROCKMAN IAT | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SAFEGUARDS SYSTEM DEGRADATION RELATED TO COMPUTER. IMMEDIATE COMPENSATORY | | ACTIONS TAKEN UPON DISCOVERY. THE NRC RESIDENT INSPECTOR WILL BE INFORMED | | BY THE LICENSEE. REFER TO THE HOO LOG FOR ADDITIONAL DETAILS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33544 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 01/15/98 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 14:49 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 01/15/98 | +------------------------------------------------+EVENT TIME: 12:30[CST]| |NRC NOTIFIED BY: TOM OSELAND |LAST UPDATE DATE: 01/15/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SHEAR RDO | |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 +------------------------------------------------------------------------------+ | OUTSIDE DESIGN BASIS BECAUSE OF ISSUE REGARDING OVERHEAD CRANE | | | | THE LICENSEE HAS DETERMINED THAT THE REACTOR BUILDING SUPERSTRUCTURE IS | | OUTSIDE OF ITS DESIGN BASIS DUE TO INCORRECT DESIGN CONSIDERATIONS | | REGARDING THE REACTOR BUILDING OVERHEAD CRANE. THE CURRENT DESIGN BASIS | | CALCULATIONS FOR THE REACTOR BUILDING COLUMNS ARE BASED ON THE ASSUMPTION | | THAT THE OVERHEAD CRANE WILL BE IN ITS PARKED POSITION DURING A SAFE | | SHUTDOWN SEISMIC EVENT. THESE CALCULATIONS DO NOT ADDRESS THE OCCURRENCE OF | | A SEISMIC EVENT WHILE THE CRANE IS IN USE. | | | | THE REACTOR BUILDING SUPERSTRUCTURE IS QUALIFIED FOR SUPPORT OF THE CRANE, | | INCLUDING FULL LIFTED LOAD, AT ANY POSITION ALONG THE CRANE RUNWAY PROVIDED | | THAT SEISMIC LOADS ARE NOT CONSIDERED. THE OVERHEAD IS CURRENTLY IN THE | | PARKED POSITION AND IS BEING CONTROLLED ADMINISTRATIVELY. THE NRC RESIDENT | | INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33545 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 01/15/98 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 16:45 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 01/15/98 | +------------------------------------------------+EVENT TIME: 16:25[EST]| |NRC NOTIFIED BY: BROOKS |LAST UPDATE DATE: 01/15/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HAROLD GRAY RDO | |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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL FOR WATER HAMMER IN HPCI OR RCIC TURBINE EXHAUST LINES DURING | | OPERATION WITH ELEVATED SUPPRESSION POOL PRESSURE | | | | THE LICENSEE HAS DETERMINED THAT ELEVATED PRESSURE (>5 PSIG) WITHIN THE | | SUPPRESSION POOL COULD PERMIT WATER TO BE DRAWN INTO THE HIGH PRESSURE | | COOLANT INJECTION (HPCI) OR REACTOR CORE ISOLATION COOLING (RCIC) EXHAUST | | LINES FOLLOWING SYSTEM OPERATION. FOR EXAMPLE, FOLLOWING A REACTOR SCRAM, | | WITH TURBINE EXHAUST PRESSURE INITIALLY GREATER THAN SUPPRESSION POOL | | PRESSURE, AND SUPPRESSION POOL PRESSURE GREATER THAN REACTOR BUILDING | | PRESSURE, AS EXHAUST LINE PRESSURE DECREASES BELOW SUPPRESSION POOL | | PRESSURE, WATER WILL BE FORCED INTO THE EXHAUST LINE BY SUPPRESSION POOL | | OVERPRESSURE. THE VACUUM RELIEF VALVES TO THE REACTOR BUILDING WILL REMAIN | | CLOSED UNTIL EXHAUST LINE PRESSURE DECREASES BELOW REACTOR BUILDING | | PRESSURE. OPERATION OF EITHER SYSTEM WHILE IN THIS CONDITION COULD LEAD TO | | WATER HAMMER AND POSSIBLE DAMAGE TO COMPONENTS SUCH AS CHECK VALVES AND | | RUPTURE DISKS. SUCH FAILURES COULD CHALLENGE FURTHER HPCI OR RCIC OPERATION | | AND CONTAINMENT INTEGRITY. | | | | IN 1973, VACUUM BREAKERS WERE INSTALLED ONTO THE HPCI AND RCIC TURBINE | | EXHAUST LINES AFTER THE HPCI TURBINE EXHAUST LINE EXPERIENCED SEVERE | | VIBRATION CAUSED BY STEAM CONDENSING IN THE EXHAUST LINE AND DRAWING COLD | | WATER INTO THE HOT PIPING. THE VACUUM BREAKERS WERE INITIALLY INSTALLED ON | | PIPING INSIDE OF THE SUPPRESSION POOL, BUT WERE RELOCATED TO PIPING OUTSIDE | | OF THE SUPPRESSION POOL DUE TO CONCERNS REGARDING CONTAINMENT LEAKAGE | | TESTING. THE RESIDENT INSPECTOR WAS NOTIFIED. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33546 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 01/15/98 | |UNIT: [ ] [2] [ ] STATE: TX |NOTIFICATION TIME: 18:28 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/28/97 | +------------------------------------------------+EVENT TIME: 01:06[CST]| |NRC NOTIFIED BY: JOHN MILLIFF |LAST UPDATE DATE: 01/15/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ELMO COLLINS RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | EVENT NOTIFICATION REQUIRED BY PLANT OPERATING LICENSE | | | | RESULTS OF A FAILURE ANALYSIS RECEIVED ON 1/15/98 INDICATES THAT THE | | VOLTAGE REGULATOR FOR EMERGENCY DIESEL GENERATOR (EDG) #21 HAD DEGRADED | | DURING A SURVEILLANCE TEST CONDUCTED ON 12/27/97, AND WOULD HAVE PREVENTED | | THE EDG FROM PERFORMING ITS INTENDED SAFETY FUNCTION. BASED ON THE RESULTS | | OF THE FAILURE ANALYSIS, THE LICENSEE HAS DETERMINED THAT THE EDG SHOULD | | HAVE BEEN DECLARED INOPERABLE AT 0106 ON 12/28/97, AND THE ACTIONS OF | | TECHNICAL SPECIFICATION 3.8.1.1 SHOULD HAVE BEEN REQUIRED. THE LICENSEE HAS | | DETERMINED THAT THIS CONDITION IS REPORTABLE IN ACCORDANCE WITH SECTION 2G | | OF THE OPERATING LICENSE. | | | | EDG #21 WAS REMOVED FROM SERVICE AT 1947 ON 12/30/97 TO TROUBLESHOOT AND | | REPAIR THE VOLTAGE REGULATOR, AND WAS DECLARED OPERABLE AT 2320 ON 1/1/98. | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33547 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 01/15/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 19:28 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 01/15/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 00:00[CST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 01/16/98 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |GARY SHEAR RDO | | DOCKET: 0707001 |LARRY CAMPER EO | +------------------------------------------------+FRANK CONGEL IRD | |NRC NOTIFIED BY: MIKE UNDERWOOD | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 4-HOUR NRC BULLETIN 91-01 REPORT | | | | UPON FURTHER REVIEW OF NONDESTRUCTIVE ANALYSIS (NDA) DATA REGARDING AN NCSA | | ISSUE WITH THE MAINTENANCE OF ONE OF THE C-335 P&E PUMPS (EN #33539), AN | | ERROR WAS DISCOVERED. AFTER RECALCULATION OF THE MASS OF URANIUM PRESENT | | USING THE CORRECTED VALUE, THE #2 P&E PUMP COOLER WAS DETERMINED TO CONTAIN | | MORE THAN THE SAFE MASS OF URANIUM. | | | | ACCESS TO THE AREA HAS BEEN RESTRICTED, AND A DRY AIR BUFFER HAS BEEN | | APPLIED TO THE SYSTEM. THE NRC RESIDENT INSPECTOR WILL BE INFORMED. | | | | * * * UPDATE AT 0402 ON 1/16/98, BY MAURER TAKEN BY WEAVER * * * | | THIS REPORT WAS BASED ON THE RESULT OF HISTORICAL NON-DESTRUCTIVE ASSAY | | (NDA) MEASUREMENTS WHICH INDICATED THAT MORE THAN A SAFE MASS OF | | FISSIONABLE MATERIAL WAS CONTAINED IN THE C-335 No. 1 AND No. 2 P&E PUMP | | COOLERS. ON 1/15/98 AT 2200, THE RESULTS OF TWO ADDITIONAL INDEPENDENT NDA | | MEASUREMENTS CONDUCTED FROM A MORE ACCURATE OVERHEAD LOCATION INDICATED | | THAT THE No. 2 P&E COOLER CONTAINS LESS THAN THE SAFE MASS OF FISSIONABLE | | MATERIAL, THEREFORE THIS EVENT REPORT IS RETRACTED. THE LICENSEE INFORMED | | THE NRC RESIDENT INSPECTOR THE HOO INFORMED THE R3DO(SHEAR). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33548 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 01/15/98 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 20:09 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 01/15/98 | +------------------------------------------------+EVENT TIME: 20:00[EST]| |NRC NOTIFIED BY: JESSE PIKE |LAST UPDATE DATE: 01/15/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HAROLD GRAY RDO | |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 +------------------------------------------------------------------------------+ | APRM CHANNELS DECLARED INOPERABLE DUE TO NONCONSERVATIVE SETPOINT ERROR | | | | THE LICENSEE HAS DECLARED ALL SIX CHANNELS OF THE AVERAGE POWER RANGE | | MONITOR (APRM) INOPERABLE DUE TO THE DISCOVERY OF A CALCULATIONAL ERROR IN | | THE FLOW BIASING VALUE USED TO DETERMINE THE APRM FLOW BIASED SCRAM | | SETPOINT. AS A RESULT OF THE ERROR, CORE FLOW VALUES USED IN THE APRM FLOW | | BIASING LOGIC ARE APPROXIMATELY 3% GREATER THAN ACTUAL. THIS ERROR MAY | | RESULT IN FLOW BIASED SCRAM SETPOINTS THAT ARE OUTSIDE OF THE RANGE | | SPECIFIED IN THE TECHNICAL SPECIFICATIONS. THE LICENSEE HAS ENTERED | | TECHNICAL SPECIFICATION 3.3.1, WHICH REQUIRES THE INSERTION OF A HALF SCRAM | | SIGNAL AND A SHUTDOWN WITHIN SIX HOURS. | | | | THE LICENSEE REPORTED THAT THE ERROR WAS MADE ON 4/13/96, AND WAS PRESENT | | THROUGHOUT CYCLES 7 AND 8 (THE UNIT IS CURRENTLY 34 DAYS INTO CYCLE 8). I&C | | TECHNICIANS ARE CURRENTLY CORRECTING THE FLOW BIASING VALUE, AND A UNIT | | SHUTDOWN IS NOT EXPECTED. THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY | | THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33549 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 01/15/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 23:02 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 01/15/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 06:20[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 01/15/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |GARY SHEAR RDO | | DOCKET: 0707002 |LARRY CAMPER EO | +------------------------------------------------+ | |NRC NOTIFIED BY: KEITH WILLIAMSON | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24-HOUR NRC BULLETIN 91-01 REPORT | | | | WHILE PERFORMING A BUILDING WALKDOWN OF THE X-334 BUILDING, A FIRST LINE | | MANAGER DISCOVERED AN UPRIGHT, EMPTY BUCKET IN A POSTED CONTAMINATION AREA. | | THE MOP BUCKET DID NOT HAVE THE PASSIVE DESIGN FEATURE OF AT LEAST TWO | | SLOTS CUT INTO PARALLEL SIDES SO THAT THE BOTTOM OF THE SLOTS WOULD BE NO | | MORE THAN 3.6 INCHES FROM THE BOTTOM OF THE INTERIOR SURFACE. THIS PASSIVE | | DESIGN FEATURE ASSURES THAT THE LEVEL (3.6 INCHES FOR 10% U-235, IN THIS | | INSTANCE) IS NOT EXCEEDED. THIS DISCOVERY CONSTITUTES A VIOLATION OF | | NUCLEAR CRITICALITY SAFETY APPROVAL (NCSA) PLANT066.A02, CONTINGENCY EVENT | | B.2.1, CONTROL A, REQUIREMENT #2. THE MOP BUCKET WAS RELOCATED TO AN AREA | | WHERE A STANDARD MOP BUCKET IS PERMITTED. THE NRC RESIDENT INSPECTOR HAS | | BEEN INFORMED. | +------------------------------------------------------------------------------+