U.S. Nuclear Regulatory Commission Operations Center Event Reports For 02/07/95 - 02/08/95 ** EVENT NUMBERS ** 28347 28348 28349 28350 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28347 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 02/07/95 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 11:53 [ET]| |RX TYPE: [1] W-3-LP |EVENT DATE: 02/07/95 | +------------------------------------------------+EVENT TIME: 10:55[EST]| |NRC NOTIFIED BY: KEN PACE |LAST UPDATE DATE: 02/07/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILT SHYMLOCK RDO | |AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP | | |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 +------------------------------------------------------------------------------+ | THE LICENSEE HAS DECLARED BOTH TRAINS OF THEIR SOLID STATE PROTECTION | | SYSTEM (SSPS) INOPERABLE AND ENTERED TECH SPEC 3.0.3. | | | | PLANT NUCLEAR SAFETY COMMITTEE MET AFTER READING NUCLEAR REGULATORY | | COMMISSION INFORMATION NOTICE 95-10 (POTENTIAL FOR LOSS OF AUTOMATIC | | ENGINEERED SAFETY FEATURES ACTUATION). THEY DETERMINED THAT THEIR SSPS | | SYSTEM IS SUSCEPTIBLE TO THE SAME FAILURES AS DESCRIBED IN THE INFORMATION | | NOTICE. AT 1140 EST LICENSEE COMPLETED A REQUEST FOR DISCRETIONARY | | ENFORCEMENT. LICENSEE ENTERED TECH SPEC 3.0.3 AT 1055 EST AND THEY HAVE TO | | BE IN A HOT STANDBY CONDITION BY 1655 EST IF THEY ARE NOT GRANTED A NOTICE | | OF ENFORCEMENT DISCRETION (NOED). LICENSEE WILL COMMENCE A REACTOR SHUTDOWN | | AT 1330 EST IF THEY HAVE NOT RECEIVED A NOED. ALL THEIR ECCS SYSTEMS, & | | EDGs ARE FULLY OPERABLE IF NEEDED. | | | | SEE SIMILAR EVENTS # 28318 (DIABLO CANYON), 28331 (NORTH ANNA), & 28346 | | (FARLEY). | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28348 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 02/07/95 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 17:54 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 02/07/95 | +------------------------------------------------+EVENT TIME: 17:25[EST]| |NRC NOTIFIED BY: DENNIS MAY |LAST UPDATE DATE: 02/07/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICH KEIMIG RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | REACTOR BUILDING "A" CORNER ROOM COOLERS DIFFERENTIAL PRESSURE (dP) ABOVE | | MAXIMUM ALLOWABLE LIMIT. ENTERED TECH SPEC 3.5.C.3 (SHUTDOWN WITHIN 24 | | HOURS). | | | | REACTOR BUILDING "A" CORNER ROOM WHICH HOUSES "A" CORE SPRAY PUMP, TWO | | RESIDUAL HEAT REMOVAL SERVICE WATER PUMPS (RHR SW), AND RESIDUAL HEAT | | REMOVAL PUMPS (RHR) "A" & "B", ROOM COOLERS (REACTOR BUILDING | | RECIRCULATION UNITS) dP WERE GREATER THAN MAXIMUM ALLOWABLE LIMIT OF | | 15psid. THE GREATER THE dP ACROSS THE SERVICE WATER SIDE OF THE ROOM | | COOLERS THE LESS FLOW THROUGH THE COOLERS. THIS MEANS THE ROOM COOLERS FOR | | "A" CORNER ROOM CANNOT MEET THEIR HEAT REMOVAL CAPABILITY DURING A DESIGN | | BASIS ACCIDENT. LICENSEE ENTERED TECH SPEC 3.5.C.3 WHICH REQUIRES THAT BOTH | | TRAINS OF CORE SPRAY BE OPERABLE OR TO BE SHUTDOWN WITHIN 24 HOURS. "A" | | CORNER ROOM COOLER # 7 IS LARGER THAN THE OTHER ROOM COOLER (# 5). | | DIFFERENTIAL PRESSURE ACROSS ROOM COOLER # 7 WAS 15.2psid AND THE | | DIFFERENTIAL PRESSURE ACROSS ROOM COOLER # 5 WAS 15.82psid. ROOM COOLER # | | 7 IS LARGE ENOUGH TO SUPPORT "A" CORNER ROOM HEAT LOADS DURING A DESIGN | | BASIS ACCIDENT IF ITS DIFFERENTIAL PRESSURE IS LESS THAN 15.0psid. | | LICENSEE WILL EITHER BACKFLUSH THE "A" CORNER ROOM COOLERS (WHICH WOULD | | TAKE A FEW HOURS TO PERFORM OR MAKE A PROCEDURAL CHANGE. 15psid | | DIFFERENTIAL PRESSURE READING WAS BASED ON LESS ACCURATE GAGES THAT USED TO | | BE INSTALLED ON THE ROOM COOLERS. THESE GAGES WERE REPLACED WITH MORE | | ACCURATE GAGES. LICENSEES PROCEDURAL CHANGE (MENTIONED ABOVE) WOULD REQUIRE | | PLANT ENGINEERING TO REDUCE THE UNCERTAINTY OF THE GAGE ERROR BY USING THE | | MORE ACCURATE GAGE READING AND CHANGING THE 15psid MAXIMUM LIMIT IN THE | | PROCEDURE TO REFLECT THE MORE ACCURATE GAGES THAT THEY NOW HAVE INSTALLED | | ON THE ROOM COOLERS. | | LICENSEE HAS NOT PERFORMED THE DIFFERENTIAL PRESSURE TEST ON THE "B" CORNER | | ROOM COOLERS. LICENSEE WILL PERFORM THIS TEST ON 02/08/95. "B" CORNER ROOM | | HAS "B" CORE SPRAY PUMP, TWO RHR SW PUMPS AND RHR PUMPS "B" & "D". | | LICENSE WILL INFORM VERMONT PUBLIC SERVICE OF THIS EVENT. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | | | | ****UPDATE @ 2246EST 02/07/95 BY DENNIS MAY TAKEN BY MACKINNON**** | | | | LICENSEE EXITED TECH SPEC REQUIRED SHUTDOWN AT 2245EST. LICENSEE CHANGED | | THEIR SURVEILLANCE TEST PROCEDURE (OP4181 - SERVICE WATER/ALTERNATE COOLING | | SURVEILLANCE) BY INCREASING THE MAXIMUM dP VALUE ACROSS THE ROOM COOLER | | SERVICE WATER SIDE FROM 15.0psid TO 15.5psid TO REFLECT HAVING MORE | | ACCURATE GAGES ON THE ROOM COOLERS. BY INCREASING THE MAXIMUM dP TO | | 15.5psid ROOM COOLER # 7 IS CONSIDERED FULLY OPERABLE SINCE ITS MEASURED dP | | WAS 15.2psid. ROOM COOLER # 7, BY ITSELF, CAN HANDLE ALL OF "A" CORNER ROOM | | HEAT LOADS DURING A DESIGN BASIS ACCIDENT. LICENSEE WILL CLEAN THE ROOM | | COOLERS WITHIN THE EIGHT DAYS. R1DO (KEIMIG) NOTIFIED. | | | | RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28349 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 02/07/95 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 18:37 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 02/07/95 | +------------------------------------------------+EVENT TIME: 16:15[CST]| |NRC NOTIFIED BY: HASTY/DORWICK |LAST UPDATE DATE: 02/07/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BOB DEFAYETTE RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | |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 +------------------------------------------------------------------------------+ | REACTOR CORE ISOLATION COOLING (RCIC) DECLARED INOPERABLE. ALL OTHER | | EMERGENCY CORE COOLING SYSTEMS ARE FULLY OPERABLE. | | | | LICENSEE WAS PERFORMING PREPLANNED MAINTENANCE TO REPACK RCIC STEAM SUPPLY | | DRAIN POT VALVE PACKING WHEN THEY DISCOVERED THAT THEY WERE UNABLE TO | | DEPRESSURIZED RCIC PIPING TO REPACK THE VALVE. LICENSEE HAD ISOLATED RCIC | | PIPING BY CLOSING BOTH OF ITS INBOARD ISOLATION VALVES (CONTAINMENT | | ISOLATION VALVES) SO THEY COULD DEPRESSURIZE THE PIPE AND THEN REPACK THE | | VALVE. LICENSEE ENTERED TECH SPEC 3.7.3 (14 DAYS TO GET RCIC OPERABLE OR | | SHUTDOWN) AND TECH SPEC 3.6.3 (PRIMARY CONTAINMENT ISOLATION - 4 HOURS TO | | ISOLATE OR SHUTDOWN). LICENSEE MET TECH SPEC 3.6.3 BY SHUTTING RCIC | | OUTBOARD ISOLATION VALVE AND THEN DEENERGIZING THE VALVE ACTUATOR. ALL | | OTHER ECCS SYSTEMS ARE FULLY OPERABLE IF NEEDED. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28350 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 02/07/95 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 19:42 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 02/07/95 | +------------------------------------------------+EVENT TIME: 16:54[EST]| |NRC NOTIFIED BY: SWEENEY |LAST UPDATE DATE: 02/07/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |FLOYD CANTRELL RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | LICENSEE LOST ENGINEERED SAFEGUARD BUS "A" (ES BUS "A") DURING UNDERVOLTAGE | | RELAY TESTING OF THE ENGINEERED SAFEGUARD BUS. | | | | SURVEILLANCE TEST WAS BEING PERFORMED TO TEST THE UNDERVOLTAGE RELAY ON ES | | BUS "A". ES BUS "A" ASSOCIATED EMERGENCY DIESEL GENERATOR (EDG "1A") WAS | | TAGGED OUT OF SERVICE FOR THE PERFORMANCE OF THIS SURVEILLANCE TEST. AN | | ELECTRICIAN MISSED A PROCEDURAL STEP AND DID NOT PLACE A CERTAIN SWITCH | | (LICENSEE DID NOT KNOW WHICH SWITCH) TO ITS CORRECT POSITION. WHEN THE | | UNDERVOLTAGE SIGNAL WAS SIMULATED ALL SUPPLY BREAKERS TO ES BUS "A" OPENED | | (UNEXPECTED) AND STRIPPED THE BUS. ES BUS "A" EDG "1A" DID NOT | | AUTOMATICALLY START BECAUSE IT WAS TAGGED OUT OF SERVICE FOR THE TEST. ALL | | POWER TO EQUIPMENT ASSOCIATED WITH ES BUS "A" WAS LOST. POWER WAS RESTORED | | TO ES BUS "A" WITHIN NINE MINUTES. DURING THE TIME POWER WAS LOST TO ES BUS | | "A" LICENSEES' ONLY OPERATING MAKEUP PUMP "B" (THE OTHER TWO MAKEUP PUMPS | | ARE POWERED FROM ES BUS "B" AND THEY WERE NOT OPERATING) WAS DEENERGIZED. | | PRESSURIZER LEVEL DECREASED FROM 220" TO 200" BEFORE MAKEUP PUMP "B" WAS | | RESTORED TO SERVICE. | | ES BUS "B" AND ITS ASSOCIATED EDG "1B" (IN STANDBY ) WERE FULLY OPERABLE | | DURING THE TIME PERIOD THAT ES BUS "A" WAS DEENERGIZED. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+