U.S. Nuclear Regulatory Commission Operations Center Event Reports For 08/19/97 - 08/20/97 ** EVENT NUMBERS ** 32698 32780 32785 32786 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32698 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 07/29/97 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 17:02 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 07/24/97 | +------------------------------------------------+EVENT TIME: 21:00[EDT]| |NRC NOTIFIED BY: BILL WILSON |LAST UPDATE DATE: 08/19/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -EDG COULD BE OVERLOADED DUE TO THE BUS LOADING SEQUENCE FOLLOWING A LOOP- | | | | DURING THE PRESENT MAINTENANCE OUTAGE, THE TWO EMERGENCY DIESEL GENERATORS | | (EDGs) AT CRYSTAL RIVER UNIT 3 ARE BEING PHYSICALLY UPGRADED. | | | | AT 2100 ON 07/24/97, WHILE EVALUATING PLANT EMERGENCY OPERATING PROCEDURES | | (EOPs), THE LICENSEE DETERMINED THAT FOLLOWING A LOSS OF OFFSITE POWER | | (LOOP), EOP #AP-770 DIRECTS OPERATORS TO RESTORE PLANT CONDITIONS TO | | NORMAL. IF AN AUTOMATIC OR MANUAL EMERGENCY SAFEGUARDS (ES) (HIGH PRESSURE | | INJECTION) ACTUATION OCCURS DURING THE TIME THAT EDG #1A IS SUPPLYING POWER | | TO THE ES BUS, EDG #1A HAS THE POTENTIAL TO EXCEED ITS MAXIMUM RATING DUE | | TO THE STARTING CURRENT OF THE #1A 700 HP MAKEUP PUMP MOTOR. | | | | THE EDG #1A LOADING EVALUATION CALCULATION/ANALYSIS SPECIFIES A PARTICULAR | | AUTOMATIC BUS LOADING SEQUENCE TO PREVENT OVERLOADING THE EDG DUE TO | | EXCESSIVE MOTOR STARTING CURRENTS. HOWEVER, IF THE PLANT LOADS ARE | | MANUALLY SEQUENCED ONTO THE BUS IN AN ORDER DIFFERENT THAN THAT ASSUMED | | IN THE CALCULATIONS/ANALYSES, EDG #1A COULD BE OVERLOADED. | | | | THE DESIGN BASIS ACCIDENT ANALYSIS REQUIRES EDG #1A TO SUPPORT A LOSS OF | | COOLANT ACCIDENT (LOCA) COINCIDENT WITH A LOOP. HOWEVER, THE PLANT DESIGN | | CRITERIA COVERS ONLY A SINGLE FAILURE SCENARIO (LOCA OR LOOP) AND DOES NOT | | ASSUME A SECOND FAILURE SCENARIO (LOOP OR LOCA). | | | | AT 1610 ON 07/29/97, THE LICENSEE DETERMINED THAT THIS CONDITION WAS | | REPORTABLE TO THE NRC AS AN UNANALYZED CONDITION. | | | | EDG #1A IS OPERABLE, AND IN THE PRESENT PLANT OPERATING MODE (MODE 5 - COLD | | SHUTDOWN), THE ES ACTUATION SIGNAL IS BYPASSED. | | | | THE LICENSEE IS EVALUATING THIS ISSUE AND PLANS TO DEVELOP A WORST-CASE | | MODEL FOR EDG BUS LOADING TO SUPPORT THE EDG UPGRADE MODIFICATION. THE | | LICENSEE ALSO PLANS TO INCLUDE THE DETAILS IN THE EDG UPGRADE PLANT | | MODIFICATION DOCUMENTATION. IN ADDITION, THIS ISSUE WILL BE INCLUDED IN | | PLANT RESTART ITEM #D-14. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1048 ON 08/19/97 BY PAT PETERSON ENTERED BY JOLLIFFE * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION. | | | | EDG #1A IS DESIGNED FOR THE WORST CASE SCENARIO WHICH IS AN EMERGENCY | | SAFEGUARDS ACTUATION DUE TO AN INTERMEDIATE BREAK LOCA COINCIDENT WITH A | | LOOP AND A FAILURE OF EDG #1B. THE LICENSING BASIS FOR ACCIDENT ANALYSIS | | IS SUCH THAT ONLY LOOP EVENTS COINCIDENT WITH CERTAIN ACCIDENT SCENARIOS | | (e.g. LOCA OR LOSS OF EMERGENCY FEEDWATER PUMP #1) ARE REQUIRED. THE LOCA | | ANALYSIS OF RECORD DID NOT CONSIDER THE EFFECT OF A LOOP SUBSEQUENT TO AN | | INITIATING EVENT NOR AN INITIATING EVENT SUBSEQUENT TO A LOOP BECAUSE THE | | REGULATIONS DO NOT REQUIRE SUCH SCENARIOS TO BE ANALYZED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | THE OPERATIONS OFFICER NOTIFIED THE R2DO TOM DECKER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32780 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 08/17/97 | |UNIT: [ ] [2] [ ] STATE: SC |NOTIFICATION TIME: 02:50 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/17/97 | +------------------------------------------------+EVENT TIME: 01:30[EDT]| |NRC NOTIFIED BY: C. W. SENN |LAST UPDATE DATE: 08/19/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KERRY LANDIS RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | M/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - MANUAL REACTOR TRIP FROM 100% POWER DUE TO FAILED CLOSED MSIV - | | | | AT 0130 ON 08/17/97, THE #2D STEAM GENERATOR MAIN STEAM ISOLATION VALVE | | (MSIV) #2FM1 FAILED CLOSED FOR UNKNOWN REASONS. NO TESTING OR MAINTENANCE | | ACTIVITIES WERE BEING CONDUCTED AND NO EXTREME WEATHER WAS PRESENT AT THE | | TIME. | | | | CONTROL ROOM OPERATORS MANUALLY TRIPPED UNIT 2 FROM 100% POWER. ALL | | CONTROL RODS INSERTED COMPLETELY. STEAM IS BEING DUMPED TO THE MAIN | | CONDENSER. THE AUXILIARY FEEDWATER SYSTEM AUTO ACTIVATED, AS EXPECTED. | | NO SAFETY OR RELIEF VALVES LIFTED. | | | | UNIT 2 IS STABLE IN MODE 3 (HOT STANDBY). | | | | THE LICENSEE IS INVESTIGATING THE CAUSE OF THE FAILED MSIV. THIS EVENT | | HAD NO EFFECT ON UNIT 1. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 0345 ON 08/19/97 BY JIM REECE ENTERED BY JOLLIFFE * * * | | | | THE ABOVE VALVE NUMBER SHOULD BE #2SM1 INSTEAD OF #2FM1. THE CAUSE OF THE | | MSIV FAILURE IS A FAILED OPTICAL ISOLATOR IN THE TRAIN 'B' VALVE CONTROL | | CIRCUITRY. THE CAUSE OF #2SM1 MSIV FAILURE ON 07/26/97 (EVENT #32684) | | IS A FAILED OPTICAL ISOLATOR IN THE TRAIN 'A' VALVE CONTROL CIRCUITRY. | | ON 08/17/97 AND 08/18/97, THE LICENSEE REPLACED A TOTAL OF SIX OPTICAL | | ISOLATORS ON FOUR UNIT 2 MSIVs FROM THE SAME BATCH DATED AUG 95 OR NOV 95. | | THE LICENSEE IS INVESTIGATING A POSSIBLE SIMILAR CONDITION ON UNIT 1. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32785 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 08/19/97 | |UNIT: [ ] [2] [ ] STATE: NJ |NOTIFICATION TIME: 00:35 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/19/97 | +------------------------------------------------+EVENT TIME: 00:05[EDT]| |NRC NOTIFIED BY: JOHN KONOVALCHICK |LAST UPDATE DATE: 08/19/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BILL RULAND RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 1 STARTUP | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -TECH SPEC REQD PLANT S/D DUE TO 2 CONTROL ROD INDICATORS OUT OF POSITION- | | | | DURING THE PERFORMANCE OF REACTOR PHYSICS TESTING FOR CONTROL ROD SWAPS, | | CONTROL BANK 'D' HAD TWO ANALOG ROD POSITION INDICATORS GREATER THAN | | +/-12 STEPS FROM THE GROUP DEMAND COUNTERS FOR CONTROL RODS #1D4 AND #2D4. | | | | AT 0005 ON 08/19/97, CONTROL ROOM OPERATORS INSERTED ALL CONTROL RODS TO | | COMPLY WITH TECH SPEC LCO A/S 3.1.3.2.1.a, ACTION b. UNIT 2 IS STABLE IN | | MODE 3 (HOT STANDBY). | | | | THE LICENSEE IS DETERMINING CORRECTIVE ACTIONS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32786 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 08/19/97 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 07:32 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 08/19/97 | +------------------------------------------------+EVENT TIME: 03:57[EDT]| |NRC NOTIFIED BY: BRIAN STETSON |LAST UPDATE DATE: 08/19/97 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE BURGESS 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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AN OPERATOR ERROR DURING MAINTENANCE CAUSED THE LOSS OF A 5KV EMERGENCY BUS | | | | AN OPERATOR INADVERTENTLY DEENERGIZED THE EH11 5KV EMERGENCY BUS BY PULLING | | THE WRONG FUSE WHILE HANGING A TAGOUT. THE ASSOCIATED EMERGENCY DIESEL | | GENERATOR WAS IN PULL TO LOCK IN PREPARATION FOR THE MAINTENANCE WORK. THE | | LOSS OF THE BUS CAUSED THE CLOSURE OF CONTAINMENT ISOLATION VALVES WHICH | | SUPPORT RADIATION MONITORING. | | | | THE EH11 BUS IS CURRENTLY DEENERGIZED, BUT ACTIONS ARE IN PROGRESS TO | | RESTORE POWER TO THE BUS. THE MOST LIMITING LCO IS A 4 HOUR LCO TO RESTORE | | THE CONTAINMENT RADIATION MONITORING FUNCTION. THIS LCO EXPIRES AT 0757 AT | | WHICH TIME THE LICENSEE HAS AN ADDITIONAL 12 HOURS TO BE IN HOT STANDBY. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+