U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/15/97 - 04/16/97 ** EVENT NUMBERS ** 32150 32151 32152 32153 32154 32155 32156 32157 32158 32159 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32150 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 04/15/97 | |UNIT: [ ] [2] [ ] STATE: TX |NOTIFICATION TIME: 02:12 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/15/97 | +------------------------------------------------+EVENT TIME: 00:37[CDT]| |NRC NOTIFIED BY: COTTON |LAST UPDATE DATE: 04/15/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BILL JONES RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | TURBINE DRIVEN AUXILIARY FEEDWATER PUMP STARTED DUE TO VALVE FAILURE | | | | TURBINE DRIVEN AUXILIARY FEEDWATER (TDAFW) STEAM SUPPLY VALVE #2-HV-2452-2 | | FAILED OPEN, STARTING TDAFW PUMP #2-01. THE PUMP INJECTED WATER TO ALL | | FOUR STEAM GENERATORS FOR APPROXIMATELY 30-40 SECONDS UNTIL AFW FLOW | | CONTROL VALVES WERE MANUALLY CLOSED. THE MAIN FEEDWATER LEVEL CONTROL | | SYSTEM COMPENSATED FOR THE AFW FLOW AND STEAM GENERATOR LEVELS REMAINED | | ESSENTIALLY UNCHANGED. | | | | THE LICENSEE'S INITIAL INVESTIGATION INDICATES THAT THE VALVE FAILURE WAS | | DUE TO A RUPTURED DIAPHRAGM. OPERATORS SECURED THE PUMP BY CLOSING MANUAL | | ISOLATION VALVES IN LINE WITH THE FAILED STEAM SUPPLY VALVE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32151 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 04/15/97 | |UNIT: [ ] [ ] [3] STATE: AL |NOTIFICATION TIME: 07:13 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 04/15/97 | +------------------------------------------------+EVENT TIME: 02:30[CDT]| |NRC NOTIFIED BY: TIM GOLDEN |LAST UPDATE DATE: 04/15/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER 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 +------------------------------------------------------------------------------+ | PRIMARY CONTAINMENT ISOLATION VALVES FOR THE HYDROGEN WATER ANALYZER | | ISOLATED DURING A SCHEDULED SURVEILLANCE INSTRUCTION. | | | | WHILE PERFORMING A SCHEDULED SURVEILLANCE INSTRUCTION ON CONTAINMENT HIGH | | RANGE RADIATION MONITORING [3-SI-4.2.F-19(B)], THE DRYWELL/SUPPRESSION | | CHAMBER 3B H2O2 ANALYZER SAMPLE PUMP TRIPPED OFF AND THE ASSOCIATED GROUP 6 | | PRIMARY CONTAINMENT ISOLATION SYSTEM VALVES, 3-FSV-76-59, 3-FSV-76-60, | | 3-FSV-76-67 AND 3-FSV-76-68 CLOSED. THE SPECIFIED VALVES CLOSED WHEN THEY | | DEENERGIZED DUE TO THE ASSOCIATED RELAYS ON PANEL 3-9-55 BEING JARRED BY | | INSTRUMENT MAINTENANCE PERSONNEL WHILE REMOVING THE CONTAINMENT HIGH RANGE | | RADIATION MONITORING DRAWER (3-RM-90-273A) FROM THE PANEL. THIS RESULTED IN | | AN INVALID CLOSURE OF THE GROUP 6 VALVES AND THUS IS AN INVALID ESF IN | | ACCORDANCE WITH SITE STANDARD PRACTICE 4.5. IN ACCORDANCE WITH SITE | | STANDARD PRACTICE 4.5 APPENDIX "D", INVALID ESFs OF THIS TYPE ARE | | REPORTABLE AS A FOUR HOUR NON-EMERGENCY REPORT. AN LER WILL ALSO BE | | SUBMITTED WITHIN 30 DAYS OF THIS EVENT. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32152 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HADDAM NECK REGION: 1 |NOTIFICATION DATE: 04/15/97 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 09:20 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 04/15/97 | +------------------------------------------------+EVENT TIME: 09:10[EDT]| |NRC NOTIFIED BY: WILLIS |LAST UPDATE DATE: 04/15/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN KINNEMAN RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL FOR LOSS OF NPSH TO SPENT FUEL POOL COOLING PUMP. | | | | DURING ONGOING EVALUATIONS IN SUPPORT OF DECOMMISSIONING, THE LICENSEE | | DETERMINED THAT, PRIOR TO 1975, A POTENTIAL EXISTED FOR THE SPENT FUEL POOL | | COOLING PUMP TO LOSE NPSH IF THE POOL TEMPERATURE EXCEEDED 150ųF. THE | | LICENSEE STATED THAT IN 1975 AN ADDITIONAL SPENT FUEL POOL COOLING PUMP WAS | | INSTALLED, ELIMINATING THIS CONCERN. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32153 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 04/15/97 | |UNIT: [1] [2] [ ] STATE: MI |NOTIFICATION TIME: 13:36 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/15/97 | +------------------------------------------------+EVENT TIME: 12:42[EDT]| |NRC NOTIFIED BY: PTACEK |LAST UPDATE DATE: 04/15/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE BURGESS RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CERTAIN RADIATION MONITORS HAD INCORRECT CALIBRATION CONSTANTS SINCE 1990. | | | | THE USE OF AN INCORRECT CALIBRATION CONSTANT RESULTS IN THE MONITOR | | INDICATING LOWER THAN ACTUAL VALUES AND SETPOINTS THAT DO NOT CORRESPOND TO | | ACTUAL REQUIRED VALUES. THE FOLLOWING MONITORS ARE AFFECTED: | | | | UNIT 1: | | ERS-1301 CONTAINMENT LOWER COMPARTMENT TRAIN A | | ERS-1401 CONTAINMENT LOWER COMPARTMENT TRAIN B | | VRS-1501 AUXILIARY BUILDING EFFLUENT PARTICULATE RADIATION MONITOR(FSAR) | | | | UNIT 2: | | ERS-2301 CONTAINMENT LOWER COMPARTMENT TRAIN A | | ERS-2401 CONTAINMENT LOWER COMPARTMENT TRAIN B | | VRS-2501 AUXILIARY BUILDING EFFLUENT PARTICULATE RADIATION MONITOR(FSAR) | | | | ERS-1301/2301 AND 1401/2401 ARE USED TO ISOLATE PURGE AND REACTOR COOLANT | | LEAK DETECTION. VSR-1501/2501 ARE USED TO INDICATE VENT STACK PARTICULATE | | ACTIVITY. CURRENTLY THEY HAVE ENTERED THE APPROPRIATE ACTION STATEMENTS | | AND ARE RESETTING THE CALIBRATION CONSTANTS. (COMPLETED ON UNIT 2) | | | | THE CALIBRATION CONSTANT ERROR RESULTED FROM AN EQUATION ERROR, IN THE | | DETERMINATION OF THE CALIBRATION CONSTANT. CALCULATION OF THE TOTAL | | RADIOACTIVITY RELEASES FROM THE COOK PLANT AS REPORTED IN THEIR ANNUAL | | EFFLUENT RELEASE REPORTS, ARE CALCULATED BY INDEPENDENT MEANS AND ARE | | CURRENT. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32154 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 04/15/97 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 13:48 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 04/15/97 | +------------------------------------------------+EVENT TIME: 13:20[EDT]| |NRC NOTIFIED BY: BONNER |LAST UPDATE DATE: 04/15/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN KINNEMAN RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | GENERIC LETTER 96-06 EVENT | | | | IN RESPONSE TO NRC GENERIC LETTER 96-06, A LICENSEE REVIEW OF THE | | CONTAINMENT AIR RECIRCULATION COOLERS CONCLUDED THAT THE COOLERS MAY NOT BE | | ABLE TO PERFORM THEIR REQUIRED SAFETY FUNCTION DURING ACCIDENT CONDITIONS. | | | | THE POTENTIAL EXISTS FOR A WATER HAMMER TO OCCUR AFTER REACTOR BUILDING | | CLOSED COOLING WATER PUMP RESTART FROM A LOSS OF POWER, DUE TO COLLAPSE OF | | A STEAM VOID UPON REINTRODUCTION OF COOLING WATER. | | | | WATER HAMMER CONCERNS WILL BE ADDRESSED PRIOR TO RESTART FROM THE CURRENT | | OUTAGE. | | | | THE LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS AND THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32155 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 04/15/97 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 13:48 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 04/15/97 | +------------------------------------------------+EVENT TIME: 13:20[EDT]| |NRC NOTIFIED BY: BONNER |LAST UPDATE DATE: 04/15/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN KINNEMAN 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 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR BUILDING CLOSED COOLING WATER FLOW TO THE HIGH PRESSURE SAFETY | | INJECTION PUMP SEAL COOLERS MAY BE INADEQUATE. | | | | A LICENSEE ENGINEERING REVIEW HAS CONCLUDED THAT REACTOR BUILDING CLOSED | | COOLING WATER FLOW TO THE HIGH PRESSURE SAFETY INJECTION PUMP SEAL COOLERS | | MAY BE INADEQUATE. ANALYSIS INDICATES THAT THE PUMP SEALS COULD FAIL, | | RESULTING IN A DILUTION OF THE PUMP OIL RESERVOIR AND FAILURE OF THE PUMP. | | | | COOLING WATER FLOW CONCERNS WILL BE CORRECTED PRIOR TO RESTART FROM THE | | CURRENT OUTAGE. | | | | THE LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS AND THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 32156 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: US ARMY ROCK ISLAND ARSENAL |NOTIFICATION DATE: 04/15/97 | | CITY: FORT RILEY REGION: 4 |NOTIFICATION TIME: 18:34 [ET]| | COUNTY: STATE: KS |EVENT DATE: 04/14/97 | |LICENSE#: 12-00722-13 AGREEMENT: Y |EVENT TIME: 10:00[CDT]| | DOCKET: |LAST UPDATE DATE: 04/15/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |BILL JONES, R4 RDO | | |CHARLEY HAUGHNEY EO | +------------------------------------------------+FRANK CONGEL IRD | |NRC NOTIFIED BY: MOHS, ROCK ISLAND ARSENAL |BRUCE BURGESS, R3 RDO | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | |IBAC 30.50(b)(1)(i) ACCESS DENIED >24 HRS | | |NAGR AGREEMENT STATE | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE US ARMY ROCK ISLAND ARSENAL REPORTED THAT TWO INDIVIDUALS POTENTIALLY | | MAY HAVE BEEN EXPOSED TO AN AMERICIUM SOURCE. | | | | THESE INDIVIDUALS WERE WORKING WITH A "M43A1" CHEMICAL AGENT DETECTOR | | CONTAINING 250 ęCi OF AMERICIUM-241 IN BUILDING 8380 AT FORT RILEY, KANSAS. | | AMERICIUM WHITE POWDER WAS OBSERVED ON THE BOTTOM OF THE DETECTOR CASE AND | | WHEN IT WAS WIPED, AMERICIUM POWDER WAS KNOCKED OUT OF THE TOP OF THE CASE. | | THE SOURCE HAS BEEN PLACED IN A CONTROLLED AREA IN A STORAGE CABINET AND | | HAS BEEN ISOLATED. WIPES OF THE AREA HAVE BEEN TAKEN. ONE WIPE EVALUATED | | WITH AN "ANPDR-77" METER READ 300-400 CPM WHICH EQUATES TO APPROXIMATELY | | 2000 DPM. THIS VALUE (0.0009 ęCi) IS LESS THAN 5 TIMES THE ANNUAL-LIMIT- | | OF-INTAKE LIMIT WHICH HAS A VALUE OF 0.03 ęCi. NO BIOASSAY WAS MADE OF THE | | INDIVIDUALS. THE LICENSEE IS CONTINUING TO INVESTIGATE THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 32157 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: US ARMY ROCK ISLAND ARSENAL |NOTIFICATION DATE: 04/15/97 | | CITY: ABERDEEN REGION: 1 |NOTIFICATION TIME: 18:34 [ET]| | COUNTY: STATE: MD |EVENT DATE: 04/14/97 | |LICENSE#: 12-00722-06 AGREEMENT: Y |EVENT TIME: 15:00[EDT]| | DOCKET: |LAST UPDATE DATE: 04/15/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JOHN KINNEMAN, R1 RDO | | |CHARLEY HAUGHNEY EO | +------------------------------------------------+FRANK CONGEL IRD | |NRC NOTIFIED BY: MOHS, ROCK ISLAND ARSENAL |BRUCE BURGESS, R3 RDO | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | |IBAC 30.50(b)(1)(i) ACCESS DENIED >24 HRS | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE US ARMY ROCK ISLAND ARSENAL REPORTED THAT AN INSTRUCTOR MAY HAVE BEEN | | CONTAMINATED WHILE HANDLING AN "M-187" MOUNT TELESCOPE. | | | | THE "M-187" MOUNT TELESCOPE CONTAINS TWO TRITIUM SOURCES MEASURING | | 0.81 Ci EACH. THE INSTRUCTOR WAS REMOVING THE SOURCES SO THAT STUDENTS | | WOULD NOT HAVE TO HANDLE THEM. WHILE ATTEMPTING TO REMOVE THE SOURCES WITH | | A SCREW DRIVER, IT SLIPPED AND PUNCTURED AT LEAST ONE OF THE TWO SOURCES. | | THE "M-187" WAS ISOLATED AND BAGGED WITH THE PIECES. WIPES WERE TAKEN | | IN VARIOUS AREAS OF THE CLASSROOM AND THE HIGHEST AREA OF CONTAMINATION | | WAS THE FLOOR MEASURING 2700 DPM. THE DOOR KNOB MEASURED AT 220 DPM. SHOES | | AND CLOTHING WERE NOT ABOVE BACKGROUND. THE 5 TIMES ANNUAL-LIMIT- | | OF-INTAKE LIMIT OF 20E+3 ęCi WAS EXCEEDED BY THE ACTUAL VALUE OF | | 8.1E+5 ęCi. THE AREA IS ISOLATED UNTIL CLEANUP. A BIOASSAY WILL BE | | PERFORMED ON THE INSTRUCTOR. THE LICENSEE IS CONTINUING TO INVESTIGATE | | THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32158 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 04/15/97 | |UNIT: [3] [ ] [ ] STATE: LA |NOTIFICATION TIME: 19:03 [ET]| |RX TYPE: [3] CE |EVENT DATE: 04/15/97 | +------------------------------------------------+EVENT TIME: 14:00[CDT]| |NRC NOTIFIED BY: LITOLFF |LAST UPDATE DATE: 04/15/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BILL JONES RDO | |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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A CONDITION WHERE THE CONTAINMENT SPRAY SYSTEM MAY NOT HAVE BEEN OPERABLE | | | | TECHNICAL SPECIFICATION 4.6.2.1.a REQUIRES THAT EACH CONTAINMENT SPRAY (CS) | | SYSTEM BE DEMONSTRATED OPERABLE BY VERIFYING THAT THE WATER LEVEL IN THE | | CONTAINMENT SPRAY RISER HEADER IS GREATER THAN 149 FEET MAIN STEAM LEVEL | | (MSL) ELEVATION. IN THE PAST, THIS SURVEILLANCE HAS BEEN ACCOMPLISHED BY | | VERIFYING THAT THE LEVEL INSTRUMENTS LOCATED APPROXIMATELY 31 FEET BELOW | | MSL READ 181 FEET. THE LICENSEE DISCOVERED, USING WORST CASE INSTRUMENT | | UNCERTAINTIES, THAT ACTUAL WATER LEVEL IN THE CONTAINMENT SPRAY RISER | | HEADER COULD BE AS LOW AS 139 FEET-7 INCHES WHEN THE LEVEL INSTRUMENTS READ | | 181 FEET. | | | | WHEN DETERMINING THE SAFETY SIGNIFICANCE OF THIS CONDITION, THE LICENSEE | | RERAN THE LIMITING PEAK CONTAINMENT PRESSURE EVENT (MAIN | | STEAM LINE BREAK FROM 75% POWER) WITH THE FOLLOWING ADDITIONAL ASSUMPTIONS: | | (1) WORST CASE FAILURE (e.g., THE FAILURE OF ONE MAIN STEAM ISOLATION | | VALVE TO CLOSE), (2) ONE CONTAINMENT FAN COOLER (CFC) PER TRAIN OPERABLE, | | (3) A COMPONENT COOLING WATER (CCW) FLOW RATE OF 1100 GPM TO EACH CFC, | | (4) BOTH CS SYSTEMS OPERABLE, AND (5) A CCW FLOW RATE OF 2250 GPM TO EACH | | SHUTDOWN COOLING HEAT EXCHANGER. THE ANALYSIS RESULTED IN A CONTAINMENT | | PEAK PRESSURE OF 44.05 PSIG, WHICH IS SLIGHTLY (0.05 PSIG) ABOVE THE | | CONTAINMENT DESIGN PRESSURE OF 44.0 PSIG. THE LICENSEE BELIEVES THAT THE | | ANALYSIS HAS SUFFICIENT CONSERVATISM TO ACCOMMODATE THE 0.05 PSIG EXCESS. | | HOWEVER, THIS CONDITION IS BEING CONSERVATIVELY REPORTED AS A CONDITION | | ALONE THAT COULD HAVE PREVENTED THE FULFILLMENT OF A SAFETY FUNCTION. | | | | THIS IS A PAST OPERABILITY ISSUE ONLY. CURRENT PLANT PROCEDURES REQUIRE | | THAT TWO CONTAINMENT FAN COOLERS PER TRAIN BE OPERABLE AND THE CONTAINMENT | | SPRAY RISER LEVEL IS BEING MAINTAINED AT A HEIGHT TO ACCOUNT FOR INSTRUMENT | | UNCERTAINTIES. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32159 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 04/15/97 | |UNIT: [1] [ ] [ ] STATE: MN |NOTIFICATION TIME: 20:17 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 04/15/97 | +------------------------------------------------+EVENT TIME: 18:40[CDT]| |NRC NOTIFIED BY: WITSCHEN |LAST UPDATE DATE: 04/15/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE BURGESS 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 +------------------------------------------------------------------------------+ | THE LICENSEE HAS DETERMINED THAT THE NET POSITIVE SUCTION HEAD (NPSH) | | AVAILABLE TO CORE SPRAY PUMPS MAY NOT MEET THE REQUIRED NPSH UNDER ALL | | ACCIDENT CONDITIONS. | | | | DURING A REVIEW OF ECCS PUMP NPSH REQUIREMENTS, A NEW HIGHER HEAD LOSS WAS | | CALCULATED FOR ECCS SUCTION STRAINERS. ANALYSIS INDICATES THAT THE NPSH | | AVAILABLE TO CORE SPRAY PUMPS MAY NOT MEET REQUIRED NPSH UNDER ALL ACCIDENT | | CONDITIONS. THE SPECIFIC CONDITION OF CONCERN INVOLVES A FAILURE OF LPCI | | TO SELECT THE INTACT REACTOR RECIRCULATION LOOP. THIS CONDITION MINIMIZES | | PRIMARY CONTAINMENT PRESSURE WHILE MAXIMIZING SUCTION STRAINER FLOW LOSES. | | PROMPT OPERABILITY EVALUATIONS HAVE DETERMINED THAT UNDER THIS CONDITION | | CORE SPRAY WILL BE ABLE TO MEET FLOW REQUIREMENTS DURING THE PERIOD OF THE | | TIME REQUIRED BY PLANT ANALYSIS AND EOPs. THE LICENSEE IS CONTINUING TO | | EVALUATE THIS CONDITION. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+