U.S. Nuclear Regulatory Commission Operations Center Event Reports For 02/12/97 - 02/13/97 ** EVENT NUMBERS ** 31622 31772 31773 31774 31775 31776 31777 31778 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31622 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 01/20/97 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 16:49 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 01/20/97 | +------------------------------------------------+EVENT TIME: 16:25[EST]| |NRC NOTIFIED BY: BRENT HURSEY/D. VAIL |LAST UPDATE DATE: 02/12/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN WHITE RDO | |ADEG 50.72(b)(1)(ii) DEGRAD COND DURING OP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FAILURE TO MEET ELECTRICAL SEPARATION CRITERIA | | | | AMENDMENT NO. 16 OF MILLSTONE UNIT 1 PROVISIONAL LICENSE ISSUED IN 1969 | | STATED THAT THE S1 POWER SUPPLY (POWER FROM THE GAS TURBINE) AND THE S2 | | POWER SUPPLY (POWER FROM THE EMERGENCY DIESEL GENERATORS) FOR THE SERVICE | | WATER SYSTEM AND THE TURBINE BUILDING SECONDARY CLOSED COOLING WATER | | SYSTEMS MUST BE SEPARATED. THE LICENSEE DETERMINED THAT THE POWER SUPPLY | | CABLE FROM THE S2 SERVICE WATER TRAIN HAD BEEN RUN INTO AND OUT OF THE S1 | | SERVICE WATER TRAIN WITHOUT MEETING AMENDMENT NO. 16 CRITERIA. AMENDMENT | | NO. 16 STATES THAT THE REDUNDANT POWER SUPPLIES (S1 AND S2) MUST EITHER BE | | SEPARATED FROM EACH OTHER BY THREE FEET OR HAVE A BARRIER BETWEEN THE TWO | | CABLES. THE S1 AND S2 POWER SUPPLY CABLES FOR THE SERVICE WATER PUMPS ARE | | WITHIN ONE FOOT OF EACH OTHER WITHOUT A BARRIER BETWEEN THE CABLES. THIS | | PROBLEM WILL BE CORRECTED. THE LICENSEE WROTE ADVERSE CONDITION REPORT NO. | | 6476 ON THIS PROBLEM IN NOVEMBER OF 1995. THE TURBINE BUILDING SECONDARY | | CLOSED COOLING WATER SYSTEM PUMP'S REDUNDANT CONTROL POWER SUPPLY CABLES | | WERE FOUND TO BE WITHIN THE SAME ISOLATION BOX. THIS PROBLEM WAS CORRECTED | | IN NOVEMBER OF 1995. THE LICENSEE WROTE ADVERSE CONDITION REPORT NO. 3113 | | ON THIS PROBLEM IN JUNE OF 1995. THE LICENSEE IS LOOKING INTO THE | | ELECTRICAL SEPARATION ISSUES AT MILLSTONE. | | | | THE STATE AND LOCAL OFFICIALS WERE NOTIFIED OF THIS EVENT BY THE LICENSEE. | | THE NRC RESIDENT INSPECTOR WAS ALSO NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | ***UPDATE ON 02/12/97, @ 1846 EST FROM CLEARY TAKEN BY MACKINNON*** | | | | TWO MORE CABLE SEPARATION PROBLEMS WERE DISCOVERED. TWO CABLE TRAYS | | (24C-198 S1 AND 24C-212 S2) IN THE CABLE VAULT ROOM ARE LESS THAN THREE | | FEET APART. THE CABLE TRAYS ARE APPROXIMATELY ONE FOOT FOUR INCHES APART | | INSTEAD. | | | | RELAY 27-5 HAS A NOMINAL 120-VOLT AC BUS POTENTIAL SIGNAL ON TERMINAL NO. 1 | | (NORMALLY OPEN) FROM S1 BUS 14E. TERMINAL NO. 3 (A NORMALLY CLOSED | | CONTACT) HAS A NOMINAL 120-VOLT AC BUS POTENTIAL SIGNAL FROM S2 BUS 14F. | | TERMINALS 1, 3, AND 7 CONSTITUTE A FORM-C CONTACT SET. THE PRESENCE OF S1 | | AND S2 WIRING (i.e., WIRING FROM TWO REDUNDANT DIVISIONS) ON A SINGLE | | CONTACT SET DOES NOT MEET THE DIVISIONAL SEPARATION CRITERIA SPECIFIED IN | | AMENDMENT NO. 16 (1969) OF THE APPLICATION FOR AN OPERATING LICENSE. IN | | ADDITION, THE POTENTIALS ON TERMINALS 1 AND 3 MAY BE OUT OF PHASE WITH ONE | | ANOTHER SO THAT THE DIFFERENCE IN POTENTIAL ACROSS THE CONTACTS COULD | | APPROACH 350 VOLTS (PEAK). THIS MAY OR MAY NOT BE WITHIN THE RELAY'S | | RATINGS. A POSTULATED SINGLE FAILURE AT THIS RELAY CAN POTENTIALLY AFFECT | | BOTH REDUNDANT SAFEGUARDS DIVISIONS. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED BY THE LICENSEE OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31772 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 02/12/97 | |UNIT: [1] [ ] [ ] STATE: NH |NOTIFICATION TIME: 08:40 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 02/12/97 | +------------------------------------------------+EVENT TIME: 07:55[EST]| |NRC NOTIFIED BY: STEVE MORRISSEY |LAST UPDATE DATE: 02/12/97 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD BELLAMY RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | A RING OF KEYS, SOME OF WHICH ARE FOR VITAL AREA DOORS, WAS REPORTED TO BE | | MISSING. THE LICENSEE IS SEARCHING FOR THE KEYS. VITAL AREA DOOR ALARMS | | ARE OPERABLE AND WOULD ALARM IF A DOOR IS OPENED USING A KEY. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31773 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DAVIS BESSE REGION: 3 |NOTIFICATION DATE: 02/12/97 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 11:40 [ET]| |RX TYPE: [1] B&W-R-LP |EVENT DATE: 02/12/97 | +------------------------------------------------+EVENT TIME: 11:20[EST]| |NRC NOTIFIED BY: McGEE |LAST UPDATE DATE: 02/12/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARC DAPAS 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION 3.0.3 ENTRY DUE TO THE DISCOVERY THAT A VACUUM LEAK | | TEST HAD NOT BEEN PERFORMED ON THE DECAY HEAT PIT INSPECTION COVER AFTER IT | | WAS OPENED | | | | IT HAS BEEN DETERMINED BY THE LICENSEE THAT THE DECAY HEAT PIT INSPECTION | | OPENING WAS OPENED SUBSEQUENT TO PERFORMING THE VACUUM LEAKAGE TEST PER | | TECHNICAL SPECIFICATION 4.5.2.f.2. THIS SURVEILLANCE REQUIREMENT REQUIRES | | PERFORMANCE OF VACUUM LEAKAGE TEST AFTER EACH OPENING. THE STATION WAS | | PREVIOUSLY CONSIDERED TO BE IN COMPLIANCE WITH THE SURVEILLANCE REQUIREMENT | | VIA A SAFETY EVALUATION WHICH DID NOT REQUIRE THE PERFORMANCE OF THE VACUUM | | LEAKAGE TEST AFTER EACH OPENING OF THE INSPECTION COVER (WHICH DOES NOT | | APPEAR TO BE IN LITERAL COMPLIANCE WITH TECHNICAL SPECIFICATION | | SURVEILLANCE REQUIREMENT 4.5.2.f.2). THIS HAS RESULTED IN BOTH TRAINS OF | | THE EMERGENCY CORE COOLING SYSTEMS BEING DECLARED INOPERABLE AND ENTRY INTO | | TECHNICAL SPECIFICATION 3.0.3 WHICH REQUIRES THE LICENSEE TO CORRECT THE | | PROBLEM WITHIN 1 HOUR OR TO PLACE THE UNIT IN A HOT SHUTDOWN CONDITION | | WITHIN 6 HOURS. THE 24-HOUR DELAY ALLOWED BY SURVEILLANCE REQUIREMENT | | 4.0.3 IS BEING INVOKED WHILE EFFORTS ARE MADE TO PERFORM THIS SURVEILLANCE. | | THE INSPECTION OPENING IS CURRENTLY CLOSED, AND THE EMERGENCY CORE COOLING | | SYSTEMS ARE CONSIDERED OPERABLE. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED BY THE LICENSEE. | | | | *** UPDATE FROM McGEE ON 02/12/97, @ 1529 EST TAKEN BY MACKINNON *** | | | | AT 1435 EST, IT WAS DETERMINED THAT SURVEILLANCE REQUIREMENT 4.5.2.f.2 | | CANNOT BE PERFORMED WHILE THE UNIT IS IN MODE 1. THEREFORE, THE 24-HOUR | | DELAY ALLOWED BY SURVEILLANCE REQUIREMENT 4.0.3 NO LONGER APPLIES. PLANT | | SHUTDOWN WAS COMMENCED AT 1521 EST, AND THE PLANT IS REQUIRED TO BE IN MODE | | 3 (HOT SHUTDOWN) BY 2135 EST PER TECHNICAL SPECIFICATION 3.0.3. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS UPDATE BY THE LICENSEE. | | THE NRC OPERATIONS CENTER NOTIFIED THE R3DO (MARC DAPAS). | | | | *** UPDATE FROM IMLAY ON 02/12/97, @ 2115 EST TAKEN BY MACKINNON *** | | | | AT 2005 EST, AN ORAL NOTIFICATION OF ENFORCEMENT DISCRETION WAS GRANTED | | FROM THE NRC'S OFFICE OF NUCLEAR REACTOR REGULATION FOR CONTINUED | | OPERATIONS, AND TECHNICAL SPECIFICATION 3.0.3 WAS EXITED. REACTOR POWER | | LEVEL IS CURRENTLY AT 10%. THE LICENSEE PLANS TO PLACE THE MAIN TURBINE | | BACK ON LINE AND TO INCREASE REACTOR POWER TO 100%. THE LICENSEE ALSO | | PLANS TO PERFORM THE SURVEILLANCE VACUUM LEAK TEST THE NEXT TIME THE PLANT | | IS SHUTDOWN. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS UPDATE BY THE LICENSEE, AND | | THE R3DO (MARC DAPAS) WAS NOTIFIED BY THE NRC OPERATIONS CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31774 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HADDAM NECK REGION: 1 |NOTIFICATION DATE: 02/12/97 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 13:35 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 02/12/97 | +------------------------------------------------+EVENT TIME: 13:20[EST]| |NRC NOTIFIED BY: D McCRACKEN |LAST UPDATE DATE: 02/12/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RON BELLAMY 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 N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE "B" RESIDUAL HEAT REMOVAL (RHR) PUMP MAY NOT HAVE BEEN ABLE TO PERFORM | | LONG-TERM RECIRCULATION. | | | | THIS NOTIFICATION INVOLVES A HISTORICAL EVENT. AT THE PRESENT TIME, THE | | REACTOR IS DEFUELED, AND THE PLANT WILL BE DECOMMISSIONED. | | | | WHEN THE LICENSEE TRIED TO START THE "B" RHR PUMP IN SEPTEMBER OF 1996, THE | | PUMP WOULD NOT START. DURING THE INVESTIGATION OF THE PUMP'S FAILURE TO | | START, THE PUMP WAS FOUND TO BE SEIZED UP. THE INVESTIGATION TEAM ALSO | | CONCLUDED THAT THE "B" RHR PUMP PROBABLY SEIZED UP WHEN IT WAS SECURED THE | | LAST TIME IT OPERATED, WHICH WAS IN AUGUST OF 1996. THE LICENSEE SUBMITTED | | A LICENSEE EVENT REPORT TO THE NRC TO DOCUMENT THIS PUMP SEIZURE. | | | | THE LAST TIME THE RHR PUMP HAD BEEN OVERHAULED WAS IN 1987. A ROOT CAUSE | | TEAM DISCOVERED THAT THE "B" RHR PUMP HAD INHERENT MANUFACTURING DEFECTS | | AND MARGINAL DESIGN (PARTS ON RHR PUMP "B" OUT OF TOLERANCE) TO THE EXTENT | | THAT THE PUMP WAS INCAPABLE OF PERFORMING ITS DESIGN FUNCTION. THE | | MANUFACTURING DEFECTS HAD PROBABLY EXISTED SINCE THE PUMP WAS LAST | | OVERHAULED IN 1987. IT IS CURRENTLY QUESTIONABLE IF RHR PUMP "B" WOULD | | HAVE REMAINED OPERATIONAL DURING LONG-TERM CORE COOLING (LONG-TERM | | RECIRCULATION). | | | | THE NRC RESIDENT INSPECTOR AND APPLICABLE STATE AND LOCAL OFFICIALS HAVE | | BEEN NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31775 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 02/12/97 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 17:28 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 02/12/97 | +------------------------------------------------+EVENT TIME: 17:15[EST]| |NRC NOTIFIED BY: CLEARY |LAST UPDATE DATE: 02/12/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RON BELLAMY 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION SETPOINT FOR THE YARWAY LOW-LOW REACTOR VESSEL | | WATER LEVEL IS SUPPOSED TO BE 79 (+4/-0) INCHES ABOVE THE TOP OF THE ACTIVE | | FUEL, AND CALCULATIONS ON THE LOW-LOW REACTOR VESSEL WATER LEVEL FOR THE | | YARWAYS SHOWS AN ERROR OF APPROXIMATELY 7 (+3/-4.3) INCHES. | | | | LOW-LOW REACTOR VESSEL WATER LEVEL CALCULATIONS DETERMINED THAT THE YARWAYS | | HAVE APPROXIMATELY 7 INCHES OF ERROR (+3.0/-4.3 INCHES). HOWEVER, | | TECHNICAL SPECIFICATION 3.2, TABLE 3.2.2, REQUIRES THE YARWAYS TO BE SET 79 | | INCHES ABOVE THE TOP OF THE ACTIVE FUEL (+4.0/-0). THE CALCULATION ALSO | | STATES, "THERE IS A POSSIBILITY THAT THE UPPER TECHNICAL SPECIFICATION | | LIMIT OF 83 INCHES COULD BE EXCEEDED." A REVIEW OF THE ACTUAL SETPOINT | | REVEALED THAT THE EXISTING SETPOINT MAY BE SET BELOW THE ACTUAL TECHNICAL | | SPECIFICATION VALUE. | | | | THERE ARE TWO YARWAYS ON EACH SIDE OF THE REACTOR VESSEL WHICH MEASURE | | REACTOR VESSEL WATER LEVEL. THE YARWAYS SEND REACTOR VESSEL WATER LEVEL | | SIGNALS TO CHANNELS "A" AND "B" OF THE REACTOR PROTECTION SYSTEM. IF | | REACTOR VESSEL WATER LEVEL DECREASES TO THE LOW-LOW REACTOR VESSEL WATER | | LEVEL SETPOINT, ALL THE EMERGENCY CORE COOLING SYSTEMS ACTUATE (FEEDWATER | | COOLANT INJECTION, LOW PRESSURE COOLANT INJECTION, AND CORE SPRAY). IN | | ADDITION, THE EMERGENCY DIESEL GENERATORS START, AND THE ISOLATION | | CONDENSER INITIATES. AT MILLSTONE UNIT 1, THE LOW-LOW REACTOR VESSEL WATER | | LEVEL SETPOINT IS SET AT 81 INCHES ABOVE THE TOP OF THE ACTIVE FUEL. THE | | CALCULATED YARWAY ERROR IS (+3/-4.3); THEREFORE, ACTUATION OF THE EMERGENCY | | SYSTEMS COULD START AT A HIGHER REACTOR VESSEL WATER LEVEL THAN THEY SHOULD | | START AT (81 INCHES + 3 INCHES = 84 INCHES) OR AT A LOWER REACTOR VESSEL | | WATER LEVEL (81 INCHES - 4.3 INCHES = 76.7 INCHES). THE TECHNICAL | | SPECIFICATION REQUIREMENT SETPOINT IS BETWEEN 83 INCHES AND 76 INCHES. | | | | THE LICENSEE PLANS TO EITHER CHANGE OUT THE INSTRUMENTATION, REQUEST A | | TECHNICAL SPECIFICATION CHANGE, OR PERFORM ANOTHER CALCULATION. | | | | THE NRC RESIDENT INSPECTOR, STATE OFFICIALS, AND LOCAL OFFICIALS WERE | | NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31776 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 02/12/97 | |UNIT: [1] [2] [ ] STATE: AL |NOTIFICATION TIME: 18:46 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 02/12/97 | +------------------------------------------------+EVENT TIME: 17:00[CST]| |NRC NOTIFIED BY: GRISSETTE |LAST UPDATE DATE: 02/12/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |POTTER RDO | |ADEG 50.72(b)(1)(ii) DEGRAD COND DURING OP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | TWO ISSUES THAT APPLY TO THE PIPING PENETRATION ROOM FILTRATION SYSTEM | | | | FIRST, THERE ARE NO PROCEDURAL STEPS IN EXISTING EMERGENCY PROCEDURES TO | | REQUIRE THAT THE PENETRATION ROOM FILTRATION BE PLACED IN OPERATION DURING | | THE RECIRCULATION PHASE OF EMERGENCY CORE COOLING SYSTEM INJECTION FOR LOSS | | OF COOLANT ACCIDENT CONDITIONS THAT DO NOT RESULT IN REACHING PHASE 'B' | | (CONTAINMENT HIGH-HIGH PRESSURE >27 psig). THE PROCEDURES ARE BEING | | REVISED, AND OPERATIONS PERSONNEL ARE BEING BRIEFED ON THESE ISSUES. | | | | SECOND, INCREASED AIR IN-LEAKAGE DISCOVERED DURING RECENT PENETRATION ROOM | | FILTRATION TESTING SHOWS THAT THE PENETRATION ROOM FILTRATION SYSTEM COULD | | NOT MAINTAIN NEGATIVE 0.5 INCHES ON THE WATER COLUMN WHILE IN THE FULL | | RECIRCULATION MODE OF PENETRATION ROOM FILTRATION OPERATION. THE FINAL | | SAFETY ANALYSIS REPORT (FSAR) DESCRIBES PENETRATION ROOM FILTRATION SYSTEM | | PERFORMANCE PARAMETERS, AND NOT ALL PARAMETERS COULD BE ACHIEVED DURING | | TESTING. HOWEVER, SYSTEM DESIGN BASIS FUNCTIONS WERE MET. THE PENETRATION | | ROOM FILTRATION RECIRCULATION MODE IS NOT CREDITED IN THE FARLEY NUCLEAR | | POWER PLANT DESIGN BASIS, BUT IT IS DESCRIBED IN THE FSAR. REPAIRS ARE | | BEING PERFORMED TO ALLOW THE SYSTEM TO ACHIEVE FSAR PERFORMANCE PARAMETERS. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31777 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 02/12/97 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 19:19 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 02/12/97 | +------------------------------------------------+EVENT TIME: 18:35[EST]| |NRC NOTIFIED BY: J FREEMAN |LAST UPDATE DATE: 02/12/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RON BELLAMY 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 99 POWER OPERATION | 86 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION SHUTDOWN DUE TO LESS THAN 4 OPERATING RECIRCULATION | | PUMPS. | | | | ON 02/11/97, THE 'E' RECIRCULATION PUMP MOTOR-GENERATOR SET WAS TAKEN OUT | | OF SERVICE DUE TO A CABLE FAILURE. TODAY (02/12/97) AT 1835 EST, THE 'C' | | RECIRCULATION PUMP MOTOR-GENERATOR SET TRIPPED WHILE REACTOR POWER LEVEL | | WAS BEING INCREASED FROM 96% TO 100%. THE 'C' MOTOR-GENERATOR SET HAD A | | VOLTAGE REGULATOR PROBLEM. TECHNICAL SPECIFICATION 3.3.F.3 WAS ENTERED DUE | | TO HAVING LESS THAN 4 OF THE 5 RECIRCULATION PUMPS IN OPERATION DURING | | POWER OPERATIONS. | | | | THE LICENSEE HAS 12 HOURS (FROM 1835 HOURS) TO PLACE THE REACTOR MODE | | SWITCH IN THE SHUTDOWN POSITION. IF THE 'C' MOTOR-GENERATOR SET VOLTAGE | | REGULATOR LOOKS OKAY, THE LICENSEE PLANS TO RESTART THE 'C' RECIRCULATION | | PUMP AND INCREASE REACTOR POWER. IF THE VOLTAGE REGULATOR HAS TO BE | | REPLACED, THEN THE REACTOR WILL BE SHUTDOWN WITHIN THE NEXT 10 HOURS. THE | | EMERGENCY DIESEL GENERATORS AND THE EMERGENCY CORE COOLING SYSTEMS ARE | | FULLY OPERABLE IF NEEDED. THE ELECTRICAL GRID IS ALSO STABLE. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | *** UPDATE FROM FREEMAN ON 02/12/97, @ 2145 EST TAKEN BY MACKINNON *** | | | | RECIRCULATION PUMP 'C' WAS RETURNED TO SERVICE AT 2145 EST, AND TECHNICAL | | SPECIFICATION 3.3.F.3 WAS EXITED AT THE SAME TIME. REACTOR POWER LEVEL WAS | | AT 71% POWER. THE PROCEDURE FOR OPERATING THE MOTOR-GENERATOR SET REQUIRED | | AN INCREASED CURRENT TO THE MOTOR-GENERATOR SET, AND THE LICENSEE BELIEVED | | THAT THIS INCREASED CURRENT CAUSED THE VOLTAGE REGULATOR TO TRIP. THE | | CURRENT TO THE MOTOR-GENERATOR HAS BEEN REDUCED BACK TO ITS FORMER VALUE TO | | PREVENT THE VOLTAGE REGULATOR FROM TRIPPING, AND THE LICENSEE PLANS TO | | INCREASE REACTOR POWER TO 96%. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS UPDATE BY THE LICENSEE. | | THE R1DO (RON BELLAMY) WAS NOTIFIED BY THE NRC OPERATIONS CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31778 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 02/13/97 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 01:44 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 02/12/97 | +------------------------------------------------+EVENT TIME: 22:05[EST]| |NRC NOTIFIED BY: MIKE WILLIAMS |LAST UPDATE DATE: 02/13/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN POTTER RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 95 POWER OPERATION | 95 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FAILURE OF A HIGH PRESSURE COOLANT INJECTION SYSTEM MINIMUM FLOW BYPASS | | VALVE TO MEET ITS REQUIRED STROKE TIME DURING TESTING | | | | WHILE PERFORMING A HIGH PRESSURE COOLANT INJECTION SYSTEM OPERABILITY TEST, | | THE MINIMUM FLOW BYPASS VALVE TO THE SUPPRESSION POOL EXCEEDED ITS REQUIRED | | OPENING STROKE TIME OF 10 SECONDS. THE ACTUAL STROKE TIME WAS 10.04 | | SECONDS. AS A RESULT, THE HIGH PRESSURE COOLANT INJECTION SYSTEM WAS | | DECLARED TO BE INOPERABLE, AND A 7-DAY TECHNICAL SPECIFICATION LIMITING | | CONDITION FOR OPERATION WAS ENTERED AT 2205 ON FEBRUARY 12, 1997. | | | | THE LICENSEE DETERMINED THAT THE INITIAL SAFETY SIGNIFICANCE WAS MINIMAL | | BECAUSE THE AUTOMATIC DEPRESSURIZATION, LOW PRESSURE COOLANT INJECTION, | | CORE SPRAY, AND REACTOR CORE ISOLATION COOLING SYSTEMS WERE ALL OPERABLE. | | THE LICENSEE PLANS TO INSPECT AND REPAIR THE MINIMUM FLOW VALVE TO OBTAIN | | THE REQUIRED STROKE TIME. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+