U.S. Nuclear Regulatory Commission Operations Center Event Reports For 09/06/94 - 09/07/94 ** EVENT NUMBERS ** 27750 27751 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27750 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUMMER REGION: 2 |NOTIFICATION DATE: 09/06/94 | |UNIT: [1] [ ] [ ] STATE: SC |NOTIFICATION TIME: 17:02 [ET]| |RX TYPE: [1] W-3-LP |EVENT DATE: 09/06/94 | +------------------------------------------------+EVENT TIME: 15:10[EDT]| |NRC NOTIFIED BY: MIKE FOWLKES |LAST UPDATE DATE: 09/06/94 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM CLINE 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 80 POWER OPERATION | 80 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFF-SITE NOTIFICATION TO THE OCCUPATIONAL SAFETY AND HEALTH ADMINISTRATION | | (OSHA) REGARDING A FATALITY ON SITE. | | | | OSHA WAS NOTIFIED THAT AN INDIVIDUAL IN TRAINING WAS DISCOVERED DEAD IN HIS | | AUTOMOBILE IN THE PARKING LOT OUTSIDE THE CRAFT TRAINING CENTER. DEATH IS | | THOUGHT TO BE FROM NATURAL CAUSES, NOT RELATED TO INDUSTRIAL OR NUCLEAR | | SAFETY. AN INVESTIGATION IS ONGOING. THE LICENSEE WILL INFORM THE NRC | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27751 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 09/06/94 | |UNIT: [1] [ ] [ ] STATE: AZ |NOTIFICATION TIME: 18:09 [ET]| |RX TYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 09/06/94 | +------------------------------------------------+EVENT TIME: 13:00[MST]| |NRC NOTIFIED BY: KATHLEEN ROBERSON |LAST UPDATE DATE: 09/06/94 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ART HOWELL 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE HAS IDENTIFIED THE POSSIBILITY FOR EXCEEDING FUEL DESIGN | | LIMITS IF AN INADVERTENT CRITICALITY OCCURS DURING CONTROL ROD TESTING | | WHILE SHUT DOWN. | | | | AN EXTREMELY UNLIKELY POTENTIAL TO VIOLATE THE SAFETY ANALYSIS ASSUMPTIONS | | FOR SUBCRITICAL CONTROL ELEMENT ASSEMBLY (CEA) WITHDRAWAL, AS DESCRIBED IN | | UFSAR CHAPTER 15.4.1 ACCIDENT ANALYSIS, EXISTS. THE CEA EXERCISE PROCESS | | AS CURRENTLY PERFORMED DURING SHUTDOWN (MODE 3 OR LOWER) DOES NOT PREVENT | | REACTOR CRITICALITY ON THE INADVERTENT WITHDRAWAL OF A SHUTDOWN CEA BANK | | "A" OR "B". THE CONDITION COULD OCCUR ONLY DURING SHUTDOWN. THE | | POSTULATED SHUTDOWN GROUP WITHDRAWAL COULD OCCUR VIA CONTROL SYSTEM FAILURE | | OR OPERATOR ERROR. THERE EXISTS A VERY LOW PROBABILITY FOR A VIOLATION OF | | THE LICENSEE'S SPECIFIED ACCEPTABLE FUEL DESIGN LIMIT. THERE ARE NO | | IMMEDIATE CONCERNS (ALL THREE UNIT ARE AT POWER). ADMINISTRATIVE | | RESTRICTIONS HAVE BEEN IMPOSED ON CEA EXERCISING WHEN A UNIT IS SHUTDOWN. | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+