U.S. Nuclear Regulatory Commission Operations Center Event Reports For 11/06/95 - 11/07/95 ** EVENT NUMBERS ** 29563 29564 29565 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29563 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 11/06/95 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 13:08 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 11/06/95 | +------------------------------------------------+EVENT TIME: 12:55[EST]| |NRC NOTIFIED BY: DONOVAN |LAST UPDATE DATE: 11/06/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN KINNEMAN RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - SBGT SYSTEM FLOW ASSUMPTIONS IN DESIGN CALCULATIONS ARE NONCONSERVATIVE - | | | | PLANT DESIGN CALCULATIONS CONTAIN AN ASSUMPTION THAT A MAXIMUM OF 20% OF | | THE TOTAL STANDBY GAS TREATMENT (SBGT) SYSTEM FLOW COMES FROM THE SPENT | | FUEL POOL FLOOR. HOWEVER, FLOW MEASUREMENTS OF REACTOR BUILDING HVAC | | DUCTING TAKEN ON 11/01/95, INDICATE THAT THE ACTUAL FLOW WAS APPROXIMATELY | | 30% OF THE TOTAL SBGT SYSTEM FLOW. THIS ACTUAL FLOW DISTRIBUTION RESULTS | | IN A HIGHER INLET TEMPERATURE TO THE SBGT SYSTEM FOLLOWING A DROPPED SPENT | | FUEL ROD ACCIDENT. PLANT CALCULATIONS INDICATE THAT FOR SPENT FUEL POOL | | TEMPERATURES UP TO 125øF, OPERABILITY OF THE SBGT SYSTEM IS UNAFFECTED. FOR | | HIGHER TEMPERATURES, SUCH AS THOSE WHICH COULD OCCUR WITH A FULL CORE | | OFFLOAD, THE 5-KW HEATER WOULD TRIP AT ITS PRESENT SETPOINT OF 130øF WHICH | | WOULD RESULT IN THE INABILITY TO REDUCE THE HUMIDITY OF THE INCOMING | | PROCESS GAS TO 70% AS REQUIRED BY THE PRESENT DESIGN SPECIFICATIONS. | | | | THE LICENSEE IS PROCESSING A PLANT MODIFICATION TO RAISE THE 5-KW HEATER | | TRIP SETPOINT FROM 130øF TO 187øF TO ELIMINATE THIS VULNERABILITY. THE | | LICENSEE ALSO PLANS NO FUEL MOVEMENT DURING THIS PRESENT REFUELING OUTAGE | | UNTIL THIS PLANT MODIFICATION IS IMPLEMENTED. | | | | SINCE FULL CORE OFFLOADS HAVE BEEN CONDUCTED IN THE PAST, THE SBGT SYSTEM | | MAY NOT HAVE BEEN ABLE TO PERFORM ITS DESIGN FUNCTION FOLLOWING A DROPPED | | SPENT FUEL ROD ACCIDENT. THUS, THIS CONDITION IS REPORTABLE TO THE NRC | | AS ANY CONDITION THAT ALONE COULD HAVE PREVENTED THE FULFILLMENT OF THE | | SAFETY FUNCTION OF SYSTEMS THAT ARE NEEDED TO CONTROL THE RELEASE OF | | RADIOACTIVE MATERIAL. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29564 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 11/06/95 | |UNIT: [1] [2] [ ] STATE: MD |NOTIFICATION TIME: 14:25 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 11/06/95 | +------------------------------------------------+EVENT TIME: 13:40[EST]| |NRC NOTIFIED BY: GECKLE |LAST UPDATE DATE: 11/06/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN KINNEMAN RDO | |AENS 50.72(b)(1)(v) ENS INOPERABLE | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | ST MARY'S COUNTY OFFICIALS NOTIFIED THE LICENSEE THAT 17 OF 17 CALVERT | | CLIFFS' OFFSITE EMERGENCY SIRENS (#11 - 14 AND #39 - 51) FAILED THE ANNUAL | | FULL CYCLE TEST. | | | | COUNTY OFFICIALS ARE REPAIRING THE SIRENS AND WILL RETEST THEM. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29565 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 11/06/95 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 19:08 [ET]| |RX TYPE: [1] W-3-LP |EVENT DATE: 11/06/95 | +------------------------------------------------+EVENT TIME: 15:09[EST]| |NRC NOTIFIED BY: HOBBS |LAST UPDATE DATE: 11/06/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES CASTO RDO | |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 HOT STANDBY | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - AFW SYSTEM FLOW CONTROL VALVES OPENED UNEXPECTEDLY DURING A TEST - | | | | DURING THE QUARTERLY SURVEILLANCE TEST OF THE SOLID STATE PROTECTION | | SYSTEM TEST CIRCUIT SLAVE RELAYS, THE AUXILIARY FEEDWATER (AFW) SYSTEM FLOW | | CONTROL VALVES OPENED FULLY FROM THEIR ORIGINALLY THROTTLED POSITIONS. | | WHILE THESE RELAYS OPENED AS DESIGNED, THE OPENINGS WERE NOT MENTIONED IN | | THE TEST PROCEDURE. IN THE CURRENT MODE 3 (HOT STANDBY) CONDITION, THE AFW | | SYSTEM FLOW CONTROL VALVES ARE THROTTLED TO CONTROL STEAM GENERATOR LEVEL. | | CONTROL ROOM OPERATORS RE-ESTABLISHED STEAM GENERATOR LEVEL CONTROL PRIOR | | TO LEVEL EXCEEDING THE NORMAL OPERATING BAND. THE LICENSEE WILL REVISE THE | | TEST PROCEDURE. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+