U.S. Nuclear Regulatory Commission Operations Center Event Reports For 08/14/98 - 08/17/98 ** EVENT NUMBERS ** 34581 34641 34642 34643 +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 34581 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: GUARDIAN AUTOMOTIVE |NOTIFICATION DATE: 07/28/98 | | CITY: EVANSVILLE REGION: 3 |NOTIFICATION TIME: 14:53 [ET]| | COUNTY: STATE: IN |EVENT DATE: 07/06/98 | |LICENSE#: AGREEMENT: N |EVENT TIME: 00:00[EDT]| | DOCKET: |LAST UPDATE DATE: 08/14/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |MELVYN LEACH RDO | | |LARRY CAMPER EO | +------------------------------------------------+ | |NRC NOTIFIED BY: WILLIAM PETERS | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOST STATIC ELIMINATOR | | | | THE CALLER REPORTED THAT AN NRD MODEL P-2051 DESTAT GUN (SERIAL #92607) HAS | | BEEN LOST AND MAY HAVE BEEN DISCARDED IN THE TRASH. THE DEVICE CONTAINS A | | 10 mCi Po-210 SOURCE. THE DEVICE WAS FIRST DISCOVERED TO BE MISSING ON | | 7/6/98, AND EXTENSIVE SEARCHES OF THE FACILITY HAVE NOT BEEN SUCCESSFUL. | | NRC REGION 3 HAS BEEN INFORMED OF THIS EVENT. | | | | ***UPDATE BY WILLIAM PETERS ON 08/14/98 @ 0940 ET TAKEN BY MACKINNON*** | | | | THE CALLER REPORTED THAT THEY ARE MISSING ANOTHER NRD MODEL P-2051 DESTAT | | GUN (SERIAL #94961). THE DEVICE CONTAINS A 10 mCi Po-210 SOURCE. THE DEVICE | | WAS DISCOVERED TO BE MISSING A COUPLE OF DAYS AGO AND EXTENSIVE SEARCHES OF | | THE FACILITY HAVE NOT BEEN SUCCESSFUL. R3DO (MARK RING) & NMSS EO (FRED | | COMBS) NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34641 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 08/14/98 | |UNIT: [1] [2] [ ] STATE: MI |NOTIFICATION TIME: 14:07 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/14/98 | +------------------------------------------------+EVENT TIME: 10:15[EDT]| |NRC NOTIFIED BY: MARY BETH DEPUYDT |LAST UPDATE DATE: 08/14/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK RING RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE DISCOVERED DURING AN EOP REVIEW A CONDITION WHICH COULD HAVE | | RESULTED IN THE ISOLATION OF THE RWST FOLLOWING A POSTULATED SINGLE FAILURE | | DURING AN ACCIDENT. | | | | "ON AUGUST 14, 1998 AT 1015EDT, DURING REVIEW OF THE EMERGENCY OPERATING | | PROCEDURES (EOP), IT WAS DISCOVERED THAT AN EOP REVISION ESTABLISHED | | CONDITIONS SUCH THAT A SINGLE FAILURE, FOR EXAMPLE A HOT 'SMART' SHORT OR | | AN OPERATOR ERROR, COULD HAVE RESULTED IN ISOLATION OF THE EMERGENCY CORE | | COOLING SYSTEM (ECCS) SUCTION FLOW PATH FOLLOWING ENTRY INTO THE EOPs. | | | | "ONE SUCTION ISOLATION VALVE FROM THE REFUELING WATER STORAGE TANK (RWST) | | SUPPLIES BOTH TRAINS OF THE RESIDUAL HEAT REMOVAL (RHR) SYSTEM, AND ANOTHER | | SINGLE ISOLATION VALVE FROM THE RWST SUPPLIES BOTH SAFETY INJECTION (SI) | | PUMPS. TO ENSURE THAT THE VALVES REMAIN OPEN TO SUPPLY RWST WATER TO THE | | ECCS PUMPS, CONTROL POWER IS REMOVED FROM THE ISOLATION VALVES. THE | | SUCTION SUPPLIES ARE TRANSFERRED TO THE RECIRCULATION MODE OF OPERATION | | WHEN RWST LEVEL DROPS TO A PRESET LEVEL, AT WHICH TIME CONTROL POWER IS | | RESTORED TO THE RWST ISOLATION VALVES, AND THE VALVES ARE THEN CLOSED. | | | | "THE EOP REVISION RESTORED CONTROL POWER TO THE RWST SUCTION ISOLATION | | VALVES EARLIER THAN WHEN NECESSARY TO CLOSE THE VALVES. THIS RESTORATION | | OF CONTROL POWER ESTABLISHED A CONDITION THAT WOULD ALLOW A SINGLE FAILURE | | IN THE CIRCUIT TO CLOSE THE RWST SUCTION ISOLATION VALVES. INADVERTENT | | CLOSURE OF THE RWST SUCTION VALVES WOULD CAUSE THE ECCS PUMPS TO RUN WITH | | NO SUCTION SUPPLY, DAMAGING THE PUMPS AND PREVENTING INJECTION TO THE | | REACTOR COOLANT SYSTEM. | | | | "THE EOP REVISION THAT ESTABLISHED THE ABOVE CONDITION OCCURRED DECEMBER | | 31, 1996. THE PROCEDURE WAS SUBSEQUENTLY CORRECTED ON JANUARY 6, 1997." | | | | THIS DISCREPANCY WAS IDENTIFIED BY THE OPERATIONS DEPARTMENT DURING AN EOP | | REVIEW AND IS HISTORICAL IN NATURE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34642 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 08/14/98 | |UNIT: [1] [ ] [ ] STATE: KS |NOTIFICATION TIME: 14:43 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 08/14/98 | +------------------------------------------------+EVENT TIME: 13:10[CDT]| |NRC NOTIFIED BY: PATRCIK GUEVEL |LAST UPDATE DATE: 08/14/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SANBORN 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 +------------------------------------------------------------------------------+ | LICENSEE IDENTIFIED DISCREPANCY BETWEEN ADMINISTRATIVE PROCEDURES AND HEAVY | | LOAD ANALYSIS FOR POLAR CRANE USE IN MODES 5 AND 6. | | | | "IT WAS DISCOVERED THAT ADMINISTRATIVE PROCEDURES DO NOT COMPLY WITH THE | | WCNOC [WOLF CREEK NUCLEAR OPERATING CORPORATION] ANALYSIS ON HEAVY LOADS, | | WCNOC 4, 'REPORT ON THE CONTROL OF HEAVY LOADS.' THE ANALYSIS IN WCNOC 4 | | IS BASED ON TWO TRAINS OF RHR BEING OPERABLE WHEN MOVING HEAVY LOADS IN | | MODES 5 AND 6. THE GOVERNING ADMINISTRATIVE PROCEDURE HAS ALLOWED HEAVY | | LOADS TO BE LIFTED IN MODES 5 AND 6 WITH ONE TRAIN OF RHR OPERABLE. THIS | | PROCEDURE HAS BEEN USED IN PAST REFUELING OUTAGES. THIS PRACTICE IS | | CONTRARY TO OUR HEAVY LOADS ANALYSIS." | | | | THE ABOVE ANALYSIS PERTAINS TO USE OF THE POLAR CRANE WHILE IN MODES 5 AND | | 6. THE ABOVE DEFICIENCY WAS DISCOVERED DURING AN ENGINEERING REVIEW OF A | | LOAD PATH PROCEDURE CHANGE. THE LICENSEE WILL CHANGE THE APPLICABLE | | PROCEDURES TO COMPLY WITH THE ANALYSIS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34643 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 08/15/98 | |UNIT: [1] [2] [ ] STATE: NC |NOTIFICATION TIME: 16:16 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 08/15/98 | +------------------------------------------------+EVENT TIME: 12:37[EDT]| |NRC NOTIFIED BY: JOHN REINSBURROW |LAST UPDATE DATE: 08/15/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |EDWARD MCALPINE RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BOTH UNITS EXPERIENCED A GROUP 6 ENGINEERED SAFEGUARDS FEATURE (ESF) | | ACTUATION IN RESPONSE TO A HIGH-HIGH MAIN STACK RADIATION SIGNAL FOR | | REASONS UNKNOWN. | | | | "ON AUGUST 15, 1998 AT 1237EDT A PRIMARY CONTAINMENT GROUP 6 ISOLATION | | (CONTAINMENT ATMOSPHERE CONTROL SYSTEM VALVES AND POST ACCIDENT SAMPLING | | VALVES), SECONDARY CONTAINMENT ISOLATION AND STANDBY GAS TREATMENT SYSTEM | | ACTUATION OCCURRED DUE TO A HIGH-HIGH MAIN STACK RADIATION SIGNAL [SETPOINT | | 1.03E-2 ęCi/cc]. ALL REQUIRED ISOLATIONS AND ACTUATIONS OCCURRED AS A | | RESULT OF THE HIGH-HIGH MAIN STACK RADIATION INITIATION SIGNAL. HOWEVER, IT | | IS NOT KNOWN WHY THE HIGH-HIGH MAIN STACK RADIATION SIGNAL WAS RECEIVED. | | SEVERAL HIGH-HIGH MAIN STACK RADIATION SPIKES WERE RECEIVED OVER THE | | FOLLOWING TWENTY-ONE MINUTE PERIOD. THERE ARE NO APPARENT REASONS FOR THE | | MAIN STACK RADIATION TO HAVE BEEN ELEVATED. NO OTHER INDICATIONS OF | | ELEVATED RADIATION CONDITIONS WERE OBSERVED. I&C IS CURRENTLY | | INVESTIGATING. | | | | "THE MAIN STACK RADIATION MONITOR HAS BEEN DECLARED INOPERABLE AND THE | | APPROPRIATE LIMITING CONDITION FOR OPERATION, TECHNICAL REQUIREMENTS MANUAL | | SPECIFICATION, AND OFFSITE DOSE CALCULATION MANUAL SPECIFICATION ACTIONS | | HAVE BEEN TAKEN. THESE ACTIONS INCLUDE TAKING A MAIN STACK GRAB SAMPLE | | ONCE PER 12 HOURS AND ANALYZING THE SAMPLE WITHIN 24 HOURS AFTER THE SAMPLE | | IS DRAWN, AND RESTORE THE MAIN STACK CHANNEL TO OPERABLE STATUS WITHIN 7 | | DAYS. BOTH UNITS RESTORED REACTOR BUILDING HVAC AND SHUTDOWN STANDBY GAS | | TREATMENT. INVESTIGATION IS CONTINUING TO DETERMINE THE ROOT CAUSE OF THE | | EVENT." | | | | THE LICENSEE HAS EVALUATED THE INITIAL SAFETY SIGNIFICANCE AS MINIMAL AND | | INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+