U.S. Nuclear Regulatory Commission Operations Center Event Reports For 03/13/96 - 03/14/96 ** EVENT NUMBERS ** 30101 30102 30103 30104 30105 30106 30107 30108 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30101 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 03/13/96 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 01:54 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 03/13/96 | +------------------------------------------------+EVENT TIME: 00:41[EST]| |NRC NOTIFIED BY: WILLIAM SPAHN |LAST UPDATE DATE: 03/13/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD BARKLEY RDO | |DSAF 73.71(b)(1) SECURITY DEGRADATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SAFEGUARD SYSTEM DEGRADATION RELATED TO THE POWER SUPPLY FUNCTION. | | IMMEDIATE COMPENSATORY ACTIONS TAKEN. THE LICENSEE NOTIFIED THE NRC | | INSPECTOR. SEE HOO LOG FOR DETAILS. | | | | * * * UPDATE AT 0403 BY SPAHN TAKEN BY WEAVER * * * | | THE POWER SUPPLY FUNCTION HAS BEEN RESTORED. THE LICENSEE INFORMED THE NRC | | RESIDENT INSPECTOR. HOO NOTIFIED THE RDO (BARKLEY). | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30102 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 03/13/96 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 07:37 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 03/13/96 | +------------------------------------------------+EVENT TIME: 07:30[EST]| |NRC NOTIFIED BY: BAKER |LAST UPDATE DATE: 03/13/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BARKLEY RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | CONDENSER HIGH-LEVEL AUTOMATIC TRIP CIRCUITS FOR CIRCULATING WATER PUMPS | | INOPERABLE. | | | | THE LICENSEE DISCOVERED THAT LEVEL SWITCHES IN THE CONDENSER HOTWELL WERE | | NOT WIRED CORRECTLY. THESE LEVEL SWITCHES PROVIDE A TRIP SIGNAL TO THE | | CIRCULATING WATER PUMPS UPON A HIGH LEVEL CONDITION IN THE CONDENSER PIT | | SUMP. WITH THE SWITCHES INOPERABLE, THE CIRCULATING WATER PUMPS WOULD NOT | | HAVE TRIPPED IF A HIGH LEVEL CONDITION HAD OCCURRED. THE LICENSEE STATED | | THAT THIS FAILURE COULD AFFECT THE OPERABILITY OF THE AUXILIARY FEEDWATER | | SYSTEM. THE LICENSEE HAS CORRECTED THE WIRING DISCREPANCY. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30103 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 03/13/96 | |UNIT: [ ] [2] [ ] STATE: AL |NOTIFICATION TIME: 12:09 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 03/13/96 | +------------------------------------------------+EVENT TIME: 10:30[CST]| |NRC NOTIFIED BY: RANDY KNIGHT |LAST UPDATE DATE: 03/13/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM PEEBLES RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |ACNC 50.72(b)(1)(ii)(C) COND OUTSIDE EOPS | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 83 POWER OPERATION | 83 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ONGOING REVIEW OF THE SAFE SHUTDOWN (APPENDIX R) PROGRAM IDENTIFIED THAT A | | HIGH PRESSURE COOLANT INJECTION (HPCI) STEAM SUPPLY VALVE MAY BECOME | | INOPERABLE IF A FIRE OCCURRED IN FIRE ZONE 11. | | | | DURING AN ONGOING EVALUATION OF UNIT 2 SAFE SHUTDOWN (APPENDIX R) PROGRAM | | TO ESTABLISH A CONSISTENT MULTI-UNIT BASELINE, INFORMATION WAS RECEIVED | | FROM NUCLEAR ENGINEERING THAT HPCI STEAM SUPPLY VALVE (2-FCV-73-16) POWER | | CABLES WERE ROUTED THROUGH FIRE ZONE 11. HPCI IS SUPPOSED TO BE CONSIDERED | | AVAILABLE IF A FIRE OCCURS IN FIRE ZONE 11. THE HPCI STEAM SUPPLY VALVE IS | | A "NORMALLY CLOSED" VALVE AND RELIABLE OPERATION COULD NOT BE ASSURED FOR A | | FIRE IN FIRE ZONE 11. | | A COMPENSATORY FIRE WATCH HAS BEEN ESTABLISHED IN FIRE ZONE 11, AND WILL | | REMAIN IN PLACE UNTIL A LONG TERM CORRECTIVE ACTION IS DEVELOPED. LICENSEE | | WILL ENTER THEIR 8th REFUELING OUTAGE 03/23/96. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30104 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 03/13/96 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 13:06 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 03/13/96 | +------------------------------------------------+EVENT TIME: 12:25[EST]| |NRC NOTIFIED BY: ANDY WISNIEWSKI |LAST UPDATE DATE: 03/13/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD BARKLEY 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 +------------------------------------------------------------------------------+ | 23 OF 26 FIRE DAMPERS FOUND NOT TO BE PROPERLY INSTALLED. | | | | ON 03/04/96 IT WAS DETERMINED THAT 23 OF 26 FIRE DAMPERS HAD NOT BEEN | | PROPERLY INSTALLED. FURTHER ENGINEERING ANALYSIS IDENTIFIED THAT 11 OF | | THESE DAMPERS WERE INSTALLED SUCH THAT IT COULD NOT BE ASSURED THAT THEY | | WOULD PREVENT A FIRE FROM PROPAGATING FROM ONE AREA TO ANOTHER AS REQUIRED | | BY THE FIRE SYSTEM DESIGN BASIS (FSAR SECTION 10.11.2). THE REMAINING 12 | | DAMPERS ARE EITHER NOT REQUIRED OR ACCEPTABLE IN THEIR CURRENT | | CONFIGURATION. LICENSEE IS PRESENTLY MODIFYING THE DAMPERS AND TESTING THEM | | TO SEE IF THEY OPERATE PROPERLY. LICENSEE DID NOT KNOW WHEN THE DAMPERS | | WERE IMPROPERLY INSTALLED. THE CONTROL ROOM WAS INFORMED OF THIS CONDITION | | AT 1225. | | LICENSEE WILL NOTIFY THE STATE OF VERMONT OF THIS EVENT. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30105 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 03/13/96 | |UNIT: [1] [ ] [ ] STATE: MN |NOTIFICATION TIME: 14:20 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 03/13/96 | +------------------------------------------------+EVENT TIME: 11:20[CST]| |NRC NOTIFIED BY: R PEARSON |LAST UPDATE DATE: 03/13/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WAYNE KROPP 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | STEAM GENERATOR #12 WELDED SLEEVE JOINT WAS FOUND NOT TO MEET THE DESIGN | | BASIS REQUIREMENTS FOR LEAK TIGHTNESS AND MINIMUM AVERAGE WELD HEIGHT. | | | | DURING INSPECTION OF #12 STEAM GENERATOR TUBES IN FEBRUARY, 1996, A STEAM | | GENERATOR TUBE WELDED SLEEVE WAS REMOVED FROM ROW 7 COLUMN 63 FOR | | METALLURGICAL EXAMINATION DUE TO POTENTIAL LEAKAGE AND EDDY CURRENT | | INDICATIONS. THE METALLURGICAL EXAMINATION OF THE TUBE-TO-SLEEVE UPPER | | JOINT FOUND THAT THE WELDED SLEEVE JOINT DID NOT MEET THE DESIGN BASIS | | REQUIREMENTS FOR LEAK TIGHTNESS AND MINIMUM AVERAGE WELD HEIGHT. THE | | DEFECTS FOUND IN THE WELDED JOINT IS DEGRADED IN THAT A LACK OF WELD FUSION | | RESULTED IN A LEAK PATH FROM THE PRIMARY TO SECONDARY SIDE. THIS SLEEVE WAS | | IN SERVICE FROM JANUARY, 1993 UNTIL JANUARY, 1996. PRELIMINARY EVALUATION | | INDICATED THAT TUBE #R7C63 WOULD HAVE MET THE STRUCTURAL AND LEAKAGE | | REQUIREMENTS OF DRAFT REGULATORY GUIDE 1.121, "BASES FOR PLUGGING DEGRADED | | PRESSURIZED WATER REACTOR STEAM GENERATOR TUBES". THE OTHER UNIT 1 STEAM | | GENERATOR DOES NOT HAVE ANY SLEEVES IN IT. THE UNIT 2 STEAM GENERATORS DO | | NOT HAVE ANY SLEEVES IN THEM. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30106 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 03/13/96 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 16:30 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 03/13/96 | +------------------------------------------------+EVENT TIME: 16:30[EST]| |NRC NOTIFIED BY: D CORNAX |LAST UPDATE DATE: 03/13/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICH BARKLEY RDO | |AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | THE LICENSEE HAS DETERMINED THAT UNDER CERTAIN CONDITIONS THE PLANT MAY | | HAVE OPERATED OUTSIDE ITS DESIGN BASIS. | | | | PLANT OPERATING PROCEDURES PERMIT TRANSFER OF NITROGEN OR WATER THROUGH | | COMMON FILL LINES. THIS COULD ALLOW CROSS-CONNECTING OF ACCUMULATOR GAS | | AND/OR LIQUID SPACE. IN THE EVENT OF A LARGE BREAK LOSS OF COOLANT ACCIDENT | | DURING THE PERIOD OF POTENTIAL CROSS-CONNECTION, NITROGEN PRESSURE IS | | POSTULATED TO BLEED OFF THROUGH ONE ACCUMULATOR THROUGH THE FAULTED LOOP TO | | CONTAINMENT. THIS MAY OCCUR BEFORE THE ACCUMULATOR FILL VALVES CLOSE TO | | ISOLATE THE ACCUMULATORS FROM THE GAS FILL LINE. | | AS A RESULT, UNDER THE ABOVE CONDITIONS, THE NITROGEN PRESSURE IN THE | | CROSS-CONNECTED ACCUMULATORS MAY BE LESS THAN THAT ASSUMED IN THE ACCIDENT | | ANALYSIS WHEN THE ACCUMULATORS ARE CALLED UPON TO OPERATE. | | STANDARD OPERATING PROCEDURE 10.1.1 WAS REVISED TO PROHIBIT | | CROSS-CONNECTION OF ACCUMULATOR GAS OR LIQUID SPACES WHEN RCS TEMPERATURE | | IS GREATER THAN 350 F. WESTINGHOUSE WAS NOTIFIED OF THE POTENTIAL | | CONDITION. | | | | RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | | | | SEE INDIAN POINT UNIT 3 EVENT #30087 ON 03/08/96 FOR A SIMILAR EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30107 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 03/13/96 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 16:36 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 03/13/96 | +------------------------------------------------+EVENT TIME: 16:26[EST]| |NRC NOTIFIED BY: RUTTAR |LAST UPDATE DATE: 03/13/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICH BARKLEY RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNSUPPORTED BEAMS LOCATED ABOVE THE CONTAINMENT RECIRCULATION SPRAY SYSTEM | | (RSS) HEAT EXCHANGERS DURING A SEISMIC EVENT COULD HAVE RESULTED IN THE | | LOSS OF 1 OF THE HEAT EXCHANGERS IN EACH OF THE 2 TRAINS OF RSS. | | | | AN ENGINEERING REVIEW INDICATED THAT UNSUPPORTED BEAMS ABOVE RSS HEAT | | EXCHANGERS (BOTH TRAINS) DURING A SEISMIC EVENT COULD HAVE RESULTED IN THE | | LOSS OF 1 OR 2 HEAT EXCHANGERS IN EACH OF THE TWO TRAINS OF RSS. THIS | | CONDITION NO LONGER EXISTS, BUT WAS A CONDITION THAT COULD HAVE RESULTED IN | | THE LOSS OF SAFETY FUNCTION OF THE RSS, AND POTENTIALLY A BREACH OF | | CONTAINMENT SINCE RSS SUCTION VALVES ARE NORMALLY OPEN TO THE CONTAINMENT | | SUMP. THIS CONDITION WOULD THUS, ALSO INVOLVE A CONDITION OUTSIDE THE | | DESIGN BASIS, SINCE THE SINGLE SEISMIC EVENT COULD HAVE RESULTED IN THE | | PLANT HAVING MULTIPLE TRAINS INCAPABLE OF PERFORMING THEIR DESIGN BASIS | | FUNCTION. THE BEAMS WERE REMOVED AT 2030 ET ON 03/12/96. | | LICENSEE WILL NOTIFY STATE AND LOCAL OFFICIALS OF THIS EVENT. | | | | RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30108 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATTS BAR REGION: 2 |NOTIFICATION DATE: 03/13/96 | |UNIT: [1] [ ] [ ] STATE: TN |NOTIFICATION TIME: 23:25 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/13/96 | +------------------------------------------------+EVENT TIME: 20:07[EST]| |NRC NOTIFIED BY: JAMES BAKER |LAST UPDATE DATE: 03/13/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM PEEBLES RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | M/R Y 49 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR MANUALLY TRIPPED FROM 1.5% POWER AFTER REDUCING POWER FROM 49% DUE | | TO MAIN CONDENSER BACK PRESSURE. | | | | REACTOR WAS OPERATING AT 49% POWER WHEN PROBLEMS WERE EXPERIENCED WITH MAIN | | CONDENSER BACK PRESSURE. LICENSEE ENTERED ABNORMAL OPERATING INSTRUCTION | | #11 (LOSS OF CONDENSER VACUUM). AFTER REDUCING LOAD IN AN ATTEMPT TO | | MITIGATE THE PROBLEM, OPERATORS MANUALLY TRIPPED THE MAIN TURBINE AT 1946 | | IN ACCORDANCE WITH ABNORMAL OPERATING INSTRUCTION #11 (TURBINE TRIP). | | OPERATORS SUBSEQUENTLY TRIPPED THE "A" MAIN FEED WATER PUMP DUE TO | | INDICATED HIGH VIBRATION AND STARTED THE STANDBY MAIN FEED WATER PUMP. THE | | STANDBY MAIN FEED WATER PUMP CAN HANDLE REACTOR POWER BETWEEN 10 AND 15% | | POWER. AFTER OBSERVING INADEQUATE FLOW FROM THE STANDBY MAIN FEED WATER | | PUMP, OPERATORS MANUALLY TRIPPED THE REACTOR AT 2007 FROM 1.5% POWER. ALL | | RODS FULLY INSERTED INTO THE CORE. BOTH MOTOR DRIVEN AND TURBINE DRIVEN | | AUXILIARY FEED WATER PUMPS AUTOMATICALLY STARTED ON THE FEED WATER | | ISOLATION SIGNAL WHICH WAS CAUSED BY THE REACTOR TRIP COINCIDENCE WITH LOW | | Tave. STEAM GENERATOR ATMOSPHERIC VALVES OPENED AND CLOSED JUST BEFORE THE | | REACTOR WAS MANUALLY TRIPPED AT 1950. THE PLANT RESPONDED AS EXPECTED | | DURING THE POST TRIP. THE TURBINE DRIVEN AUXILIARY FEED WATER PUMP WAS | | SECURED AND THE STEAM GENERATORS ARE BEING FED BY THE MOTOR DRIVEN | | AUXILIARY FEED WATER PUMPS. AT THE PRESENT TIME THE PLANT IS STABLE, AT | | NORMAL OPERATING TEMPERATURE AND PRESSURE. STEAM DUMP SYSTEM OPERATED | | PROPERLY. LICENSEE IS INVESTIGATING THE MAIN CONDENSER PROBLEM, "A" MAIN | | FEED WATER PUMP VIBRATION PROBLEM, AND THE STANDBY MAIN FEED WATER PUMP LOW | | FLOW PROBLEM. LICENSEE SAID THAT ONE OF THE HEATER STRINGS FOR THE STANDBY | | MAIN FEED WATER PUMP ISOLATED AND THIS MAY HAVE CAUSED INADEQUATE FLOW TO | | THE STANDBY MAIN FEED WATER PUMP. | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+