U.S. Nuclear Regulatory Commission Operations Center Event Reports For 03/07/97 - 03/10/97 ** EVENT NUMBERS ** 31905 31907 31908 31909 31910 31911 31912 31913 31914 31915 31916 31917 31918 31919 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31905 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 03/06/97 | |UNIT: [1] [2] [ ] STATE: NJ |NOTIFICATION TIME: 13:25 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/06/97 | +------------------------------------------------+EVENT TIME: 10:15[EST]| |NRC NOTIFIED BY: ROBERTSON |LAST UPDATE DATE: 03/07/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DANIEL HOLODY RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE WILL NOTIFY THE STATES OF NEW JERSEY AND DELAWARE THAT A | | LICENSEE EMPLOYEE CAME TO WORK AND SET OFF THE CONTAMINATION MONITOR ALARM. | | | | THE EMPLOYEE ENTERED THE SECURITY CENTER ON HIS WAY TO WORK AND SET OFF A | | CONTAMINATION MONITOR ALARM, MEASURING APPROXIMATELY 100 COUNTS ABOVE | | BACKGROUND. THE INDIVIDUAL WAS NOT ALLOWED INTO THE FACILITY, BUT HE WAS | | ESCORTED TO THE PROCESSING CENTER FOR AN EVALUATION AND FOLLOW-UP SURVEY. | | AT THIS POINT AND TIME, WHETHER OR NOT THE RADIOACTIVE CONTAMINATION IS | | NATURAL OCCURRING OR FROM ANOTHER SOURCE, HAS NOT BEEN DETERMINED. THE | | INDIVIDUAL HAS NOT BEEN IN THE RADIOLOGICALLY CONTROLLED AREA SINCE 2/7/97. | | THE INDIVIDUAL WAS AT WORK THE PREVIOUS DAY AND HAD NO PROBLEMS ENTERING OR | | EXITING THE FACILITY. HIS WORK AREAS HAVE BEEN SURVEYED AND THERE IS NO | | DETECTABLE CONTAMINATION. THE RESIDENT INSPECTOR HAS BEEN INFORMED AND | | LOWER ALLOWAYS CREEK TOWNSHIP WILL BE NOTIFIED. | | | | ***UPDATE ON 3/7/97 @ 1753 BY ARMANDO TO GOULD*** CONTAMINATION SURVEYS | | PERFORMED AT THE EMPLOYEE'S HOME CONCLUDED THAT THE RADIOISOTOPES DETECTED | | ON THE INDIVIDUAL WERE NATURALLY OCCURRING RADON DAUGHTER PRODUCTS. UPON | | FURTHER INVESTIGATION OF THE EMPLOYEE'S HOME, A RADON MITIGATION SYSTEM, | | WHICH WAS REQUIRED BY TOWNSHIP BUILDING CODE, HAD NOT BEEN COMPLETELY | | INSTALLED AND WAS NOT OPERATING AS DESIGNED. CONTAMINATION LEVELS IN THE | | HOME RANGED FROM 500 TO 700 COUNTS ABOVE BACKGROUND ON A TV SCREEN, TO | | APPROXIMATELY 1,500 COUNTS ABOVE BACKGROUND ON THE HOME HEATING SYSTEM | | FILTER. THE EMPLOYEE CONTACTED THE BUILDING CONTRACTOR AND IS IN THE | | PROCESS OF RETURNING THE RADON MITIGATION SYSTEM TO OPERATION. THE | | EMPLOYEE RETURNED TO WORK WITHOUT INCIDENT. | | | | THE RESIDENT INSPECTOR AND LAC TOWNSHIP WILL BE NOTIFIED. | | | | REGION 1 RDO(HOLODY) WAS NOTIFIED | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31907 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATTS BAR REGION: 2 |NOTIFICATION DATE: 03/06/97 | |UNIT: [1] [ ] [ ] STATE: TN |NOTIFICATION TIME: 18:34 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/06/97 | +------------------------------------------------+EVENT TIME: 17:43[EST]| |NRC NOTIFIED BY: WALLACE |LAST UPDATE DATE: 03/07/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS PEEBLES RDO | |ACCS 50.72(b)(1)(iv) ECCS INJECTION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 HOT STANDBY | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT REPORTED THAT THEY HAD AN ECCS INJECTION WHILE COOLING DOWN FROM | | MODE 3 TO MODE 4. | | | | DURING PLANT COOLDOWN TO MODE 4 FROM MODE 3, THEY EXPERIENCED A SAFETY | | INJECTION SIGNAL DUE TO LOW STEAM LINE PRESSURE(<675 PSIG). THE INITIATION | | SIGNAL OCCURRED BEFORE THEY COULD BLOCK IT. ECCS DID INJECT TO THE RCS | | THROUGH THE HIGH HEAD INJECTION PATH, BUT THE VOLUME OF WATER INJECTED IS | | UNKNOWN AT THIS TIME. THE SAFETY INJECTION SIGNAL WAS TERMINATED WITHIN | | ELEVEN MINUTES. ALL OTHER ESF EQUIPMENT ACTUATED, FUNCTIONED AS DESIGNED, | | AND WAS SECURED WITHIN ELEVEN MINUTES. THE PLANT WILL CONTINUE TO COOLDOWN | | TO MODE 5 AFTER ESF EQUIPMENT IS REALIGNED. THE RESIDENT INSPECTOR WILL BE | | NOTIFIED. | | | | * * * UPDATE ON 3/6/97 @ 2338 BY EARLES TO GOULD * * * | | | | WHILE RECOVERING FROM THE INITIAL EVENT, THE SAFETY INJECTION (SI) FUNCTION | | WAS BLOCKED IN ACCORDANCE WITH PLANT PROCEDURES. HOWEVER, AT APPROXIMATELY | | 2022, AN INVALID 'B' TRAIN SI SIGNAL WAS INITIATED. DUE TO THIS SIGNAL ECCS | | INJECTION INCREASED RCS PRESSURE ABOVE 1970 PSIG, RESETTING THE SI BLOCK | | FUNCTION. CONCURRENT WITH THIS, STEAM GENERATOR PRESSURE HAD DROPPED BELOW | | 675 PSIG DUE TO PLANT COOLDOWN. THIS GENERATED A SIGNAL WHICH INITIATED AN | | 'A' TRAIN SI. TROUBLESHOOTING OF THE SOLID STATE PROTECTION SYSTEM HAS | | BEGUN TO IDENTIFY THE SOURCE OF THE INVALID SIGNAL. CURRENT PLANT | | CONDITIONS ARE SUCH THAT AUTOMATIC INITIATION ON AN SI HAS BEEN REINSTATED | | AND THE PLANT WILL BE MAINTAINED IN ITS PRESENT CONDITION UNTIL THE SOURCE | | OF THE INVALID SIGNAL IS IDENTIFIED. | | | | THE RESIDENT INSPECTOR AND REG 2 RDO (PEEBLES) WERE NOTIFIED. | | | | * * * UPDATE 0530 3/7/97 FROM BUSHNELL TAKEN BY STRANSKY * * * | | | | AT 0419, WHILE TROUBLESHOOTING THE SSPS TO DETERMINE THE CAUSE OF THE | | SECOND SI MENTIONED ABOVE, AN 'A' TRAIN SI OCCURRED. AT THE TIME OF THE | | EVENT, THE 'B' TRAIN OF SI WAS OUT OF SERVICE FOR THE TEST, AND THE 'A' | | TRAIN LOGIC WAS BLOCKED. THE LICENSEE STATED THAT SOME QUANTITY OF WATER | | WAS INJECTED TO THE RCS, BUT DID NOT KNOW HOW MUCH. TROUBLESHOOTING | | ACTIVITIES ARE CONTINUING. THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY | | THE LICENSEE. NOTIFIED R2DO (PEEBLES). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31908 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 03/07/97 | |UNIT: [1] [2] [ ] STATE: WI |NOTIFICATION TIME: 02:04 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 03/07/97 | +------------------------------------------------+EVENT TIME: 00:58[CST]| |NRC NOTIFIED BY: SOKOL |LAST UPDATE DATE: 03/07/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |McCORMICK-BARGER 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 HOT STANDBY | 0 HOT STANDBY | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNITS IN DEGRADED CONDITION WHILE TESTING EMERGENCY DIESEL GENERATORS | | | | THE LICENSEE HAS CONSERVATIVELY ENTERED TECHNICAL SPECIFICATION 15.3.0.b | | WHILE PERFORMING SURVEILLANCE TESTS ON THE G01 AND G02 EMERGENCY DIESEL | | GENERATORS (EDGs). EDG G04 HAS BEEN OUT OF SERVICE DUE TO A BEARING FAILURE | | IN THE GENERATOR. EDG G03 HAD BEEN PROVIDING STANDBY EMERGENCY POWER FOR | | BOTH UNITS. ON 2/28/97, THE EDG VENDOR INFORMED THE LICENSEE THAT THE | | BEARING FAILURE HAD BEEN CAUSED BY CIRCULATING CURRENTS IN THE GENERATOR | | SHAFT, AND THAT EDG G03 WAS SUSCEPTIBLE TO A SIMILAR FAILURE. (EDGs G01 AND | | G02 ARE NOT SUSCEPTIBLE TO THIS FAILURE MODE.) THE LICENSEE DECLARED EDG | | G03 INOPERABLE, AND PLANT TECHNICAL SPECIFICATIONS REQUIRE TESTING OF THE | | OPERABLE EDGs ON AN INCREASED FREQUENCY (EVERY 72 HOURS). | | | | SINCE EDGs G01 AND G02 ARE ASSOCIATED WITH THE 'A' TRAIN OF ESF EQUIPMENT | | ON THEIR RESPECTIVE UNITS, WHENEVER ONE OF THE EDGs IS BEING TESTED, NO | | STANDBY EMERGENCY POWER IS AVAILABLE TO THAT UNIT. THE NRC RESIDENT | | INSPECTOR HAS BEEN INFORMED OF THIS NOTIFICATION BY THE LICENSEE. | | | | SEE EVENT # 31847 (03/01/97) & 31913 (03/07/97). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31909 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 03/07/97 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 10:45 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 03/06/97 | +------------------------------------------------+EVENT TIME: 12:30[EST]| |NRC NOTIFIED BY: JOHN BASS |LAST UPDATE DATE: 03/07/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |McCORMICK-BARGER RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | EECW SYSTEM MAY NOT ALIGN PROPERLY FOR USE FROM REMOTE SHUTDOWN PANEL. | | | | DURING AN ENGINEERING REVIEW, THE LICENSEE DISCOVERED THAT THE EMERGENCY | | EQUIPMENT COOLING WATER (EECW) SYSTEM MAY NOT PROPERLY ALIGN FOR OPERATION | | FROM THE REMOTE SHUTDOWN PANEL, AS SPECIFIED IN THE DEDICATED SHUTDOWN | | PROCEDURE FOR A SERIOUS CONTROL ROOM FIRE. SPECIFICALLY, THE EECW MAKEUP | | VALVE FROM THE EECW MAKEUP TANK MAY NOT OPEN DUE TO AN ELECTRICAL INTERLOCK | | WITH THE REACTOR BUILDING CLOSED COOLING WATER (RBCCW) TO EECW ISOLATION | | VALVES, UNLESS THE ISOLATION VALVES ARE FULLY CLOSED. THERE ARE NO LOCAL | | TRANSFER SWITCHES TO OVERRIDE THE INTERLOCK. THIS INTERLOCK COULD PREVENT | | THE EECW SYSTEM FROM BEING ALIGNED TO THE EECW MAKEUP TANK TO SUPPORT | | OPERATION OF THE SYSTEM FROM THE REMOTE SHUTDOWN PANEL. HOWEVER, THE EECW | | SYSTEM MAKEUP VALVE IS LOCATED ADJACENT TO THE DEDICATED SHUTDOWN PANEL, | | AND IS ACCESSIBLE FOR MANUAL OPERATION. | | | | THIS CONDITION IS NOT IN COMPLIANCE WITH TECHNICAL SPECIFICATION 3.7.11.d, | | WHICH CONCERNS 10 CFR PART 50, APPENDIX R ALTERNATE SHUTDOWN CONTROL | | CIRCUITS. UFSAR TABLE 9A.6.9-1 LISTS THE EECW MAKEUP VALVE AS A CONTROL | | CIRCUIT NECESSARY TO SUPPORT THE TECHNICAL SPECIFICATION. THIS TECHNICAL | | SPECIFICATION IS ONLY APPLICABLE IN OPERATING MODES 1, 2 AND 3. THE PLANT | | IS CURRENTLY IN MODE 4. | | | | THE LICENSEE STATED THAT THIS CONDITION REQUIRES A 24-HOUR REPORT DUE TO | | THE VIOLATION OF OPERATING LICENSE CONDITION 2.C(9) AS A CONDITION THAT | | ADVERSELY AFFECTS THE ABILITY OF THE PLANT TO REACH AND MAINTAIN SAFE | | SHUTDOWN IN THE EVENT OF A FIRE. THE NRC RESIDENT INSPECTOR WILL BE | | INFORMED OF THIS NOTIFICATION BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31910 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 03/07/97 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 13:57 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 03/07/97 | +------------------------------------------------+EVENT TIME: 13:45[EST]| |NRC NOTIFIED BY: QUINN |LAST UPDATE DATE: 03/07/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DANIEL HOLODY RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE HAS DECLARED THE EMERGENCY SERVICE WATER SYSTEM INOPERABLE ON | | MILLSTONE 1. | | | | IT WAS DISCOVERED THAT THERE COULD BE A POTENTIAL FOR FAILURE OF A | | NON-QUALIFIED PRESSURE REGULATOR ON THE AIR SYSTEM WHICH SUPPLIES AIR TO | | THE SOLENOID OPERATED VALVES THAT ACTUATE THE BLOWDOWN VALVE FOR THE | | EMERGENCY SERVICE WATER STRAINER. THE FAILURE OF THIS REGULATOR COULD ALLOW | | THE SOLENOIDS, WHICH ARE RATED AT 85LBS, TO SEE FULL SYSTEM AIR | | PRESSURE(100LBS), AND POSSIBLY FAIL. THE FAILURE OF THE SOLENOID VALVES | | COULD PREVENT THE EMERGENCY SERVICE WATER STRAINERS BLOWDOWN VALVES FROM | | OPENING WHICH WOULD PREVENT FULFILLMENT OF THE SAFETY FUNCTION OF THE ESW | | SYSTEM. BOTH TRAINS OF THE ESW SYSTEM ARE AFFECTED SINCE THE REGULATOR | | PROVIDES A COMMON AIR SUPPLY TO BOTH SOLENOID OPERATED VALVES. THEY ARE | | ALSO LOOKING AT OTHER SOLENOID VALVES IN THE PLANT TO DETERMINE IF THEY | | HAVE THE SAME PROBLEM. THE RESIDENT INSPECTOR WAS INFORMED AND THE STATE | | AND LOCAL GOVERNMENTS WERE NOTIFIED BY THE LICENSEE'S PAGING SYSTEM. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 31911 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: LUIS VASQUEZ OUTPATIENT SVC. CLINIC |NOTIFICATION DATE: 03/07/97 | | CITY: MAYAGUEZ REGION: 2 |NOTIFICATION TIME: 15:03 [ET]| | COUNTY: STATE: PR |EVENT DATE: 12/31/93 | |LICENSE#: 52-16660-03 AGREEMENT: N |EVENT TIME: 00:00[AT ]| | DOCKET: |LAST UPDATE DATE: 03/07/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |THOMAS PEEBLES RDO | | |DONALD COOL EO | +------------------------------------------------+FRANK CONGEL IRD | |NRC NOTIFIED BY: BERMUDEZ(REG 2) | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |LADM 35.33(a) MED MISADMINISTRATION | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LUIS VASQUEZ OUTPATIENT SERVICES CLINIC IN MAYAGUEZ PR WAS FOUND TO | | HAVE ADMINISTERED A TOTAL OF 581 MEDICAL MISADMINISTRATIONS INVOLVING 493 | | PATIENTS FROM 1990-1993. OF THE TOTAL NUMBER OF THESE MISADMINISTRATIONS, | | 533 WERE UNDERDOSES BETWEEN 25% AND 32%. THE REMAINING 48 | | MISADMINISTRATIONS WERE OVERDOSES BY 71%. LUIS VASQUEZ DIED IN AUGUST | | 1993, BETWEEN HIS DEATH AND THE END OF DECEMBER 1993 A STRONTIUM-90 EYE | | APPLICATOR WAS USED 5 TIMES WITHOUT A LICENSE. | | | | | | HOO NOTE: THIS CASE IS A SPIN OFF OF THE DR. FERNANDEZ CASE. SEE EVENT # | | 30840 WHICH WAS REPORTED ON AUGUST 7, 1996 TO THE OPERATION CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31912 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 03/07/97 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 16:16 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 03/07/97 | +------------------------------------------------+EVENT TIME: 14:49[EST]| |NRC NOTIFIED BY: TREPANIER |LAST UPDATE DATE: 03/07/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DANIEL HOLODY RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION |FREDERICK HEBDON EO | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | PARTIAL LOSS OF OFFSITE POWER, CAUSING AN AUTO START OF THE 'B' EDG AND | | REACTOR BUILDING AND PARTIAL PCIS GROUP 2 ISOLATIONS. | | | | THE PLANT IS DEFUELED WITH ALL FUEL IN THE SPENT FUEL POOL. AT 1449, WHILE | | PLANT OFFSITE ELECTRICAL POWER WAS BEING SUPPLIED TO THE AUXILIARY | | TRANSFORMER THROUGH THE MAIN TRANSFORMER, THERE WAS A FAULT ON THE MAIN | | TRANSFORMER WHICH RESULTED IN THE "B" EDG AUTO STARTING AND LOADING | | EMERGENCY BUS 'A6'. THE SHUTDOWN TRANSFORMER AUTOMATICALLY RE-ENERGIZED | | EMERGENCY BUS 'A5' DUE TO THE 'A' EDG BEING OUT OF SERVICE FOR PLANNED | | MAINTENANCE. THE MAIN TRANSFORMER LIGHTNING ARRESTER DISENGAGED AND FELL | | FROM THE TRANSFORMER, CAUSING A PHASE 1 DIFFERENTIAL OVERCURRENT FAULT. | | APPROXIMATELY 600 GALS OF OIL LEAKED FROM THE MAIN TRANSFORMER DUE TO AN | | INTERNAL FAULT. THE ELECTRICAL FAULT IS BEING INVESTIGATED. THE OIL FROM | | THE MAIN TRANSFORMER WAS CONTAINED WITHIN THE BERM SURROUNDING THE MAIN | | TRANSFORMER. ADDITIONAL OIL FROM THE SUDDEN PRESSURE INCREASE OF THE MAIN | | TRANSFORMER TRAVELED THROUGH THE DUCTWORK INTO THE TURBINE BUILDING. THIS | | OIL HAS ALSO BEEN CONTAINED. THERE WAS NO FIRE OR EXPLOSION DUE TO THE MAIN | | TRANSFORMER OIL LEAK. | | | | THE STARTUP TRANSFORMER IS CURRENTLY OUT OF SERVICE FOR SCHEDULED | | MAINTENANCE, BUT SHOULD BE RETURNED TO SERVICE IN LESS THAN 12 HOURS. THE | | SHUTDOWN TRANSFORMER IS AVAILABLE AS A BACKUP SOURCE OF ELECTRICAL POWER TO | | BUS 'A6' AND IS CURRENTLY FEEDING ELECTRICAL POWER TO BUS 'A5'. THE ONSITE | | BLACKOUT DIESEL (NON-CLASS 1E POWER SUPPLY) IS ALSO AVAILABLE AS A BACKUP | | POWER SUPPLY IF NEEDED. THE CURRENT PROTECTED ELECTRICAL LOOP FOR SHUTDOWN | | SAFETY IS THE "B" LOOP, WHICH CAN USE EITHER THE SHUTDOWN TRANSFORMER, THE | | 'B' EDG, OR THE BLACKOUT DIESEL. | | | | WHEN OFFSITE POWER WAS LOST, AUGMENTED SPENT FUEL POOL COOLING (USING RHR | | PUMPS) WAS LOST FOR 56 MINUTES. ELECTRICAL POWER TO THE AUGMENTED SPENT | | FUEL COOLING WAS RESTORED FROM EMERGENCY BUS 'A6'. DURING THE LOSS OF | | AUGMENTED SPENT FUEL POOL COOLING, THE SPENT FUEL POOL TEMPERATURE | | INCREASED FROM 86øF TO 88øF. THE PARTIAL LOSS OF OFFSITE POWER ALSO CAUSED | | A REACTOR BUILDING ISOLATION AND A PARTIAL GROUP 2 ISOLATION. THE | | ISOLATIONS HAVE NOT BEEN RESET. THE LICENSEE DOES NOT KNOW AT THIS TIME | | WHEN THE MAIN TRANSFORMER WILL BE RETURNED TO SERVICE. THE STATE OF | | MASSACHUSETTS WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE. THE NRC | | RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31913 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 03/07/97 | |UNIT: [1] [2] [ ] STATE: WI |NOTIFICATION TIME: 16:51 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 03/07/97 | +------------------------------------------------+EVENT TIME: 16:00[CST]| |NRC NOTIFIED BY: KING |LAST UPDATE DATE: 03/07/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM MCCORMICKBARGER RDO | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 HOT STANDBY | 0 HOT STANDBY | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT IS IN A 7 DAY LCO WHICH EXPIRES AT 1600 ON 3/7/97 AT WHICH TIME | | THEY HAVE TO BE IN HOT S/D WITHIN 6 HRS AND COLD S/D WITHIN 36 HRS. | | | | EMERGENCY DIESEL GENERATOR (EDG) "G-04"(B TRAIN) HAS BEEN OUT OF SERVICE | | DUE TO A GENERATOR BEARING FAILURE. WITH G-04 OUT OF SERVICE, EDG G-03(B | | TRAIN) HAD BEEN PROVIDING STANDBY EMERGENCY POWER FOR BOTH UNITS' B TRAIN | | BUSES. ON 2/28/97 AT 1600 HRS, THE DIESEL MANUFACTURER REPORTED THAT THE | | G-04 BEARING FAILURE WAS DUE TO CIRCULATING CURRENTS IN THE SHAFT AND WAS A | | POTENTIAL COMMON MODE FAILURE FOR THE SIMILAR DIESEL GENERATOR, G-03. EDG | | G-03 WAS DECLARED OUT OF SERVICE AT 1600HRS ON 2/28/97. | | | | WHEN THE 7-DAY LCO EXPIRES, BOTH UNITS HAVE TO BE IN HOT S/D WITHIN 6 HRS | | AND COLD S/D IN 36 HRS. POST-MAINTENANCE TESTING OF EDG G-03 IS CURRENTLY | | IN PROGRESS. ESTIMATED RETURN OF THE EDG G-03 TO SERVICE IS APPROXIMATELY | | 1900 HRS ON 3/7/97. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED. | | | | SEE EVENTS # 31908 (03/07/97) & 31874 (03/01/97). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31914 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 03/07/97 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 17:48 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 03/07/97 | +------------------------------------------------+EVENT TIME: 15:30[EST]| |NRC NOTIFIED BY: BANDHAUER |LAST UPDATE DATE: 03/07/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS PEEBLES 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 +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED A CONDITION WHERE THE HIGH PRESSURE INJECTION (HPI) | | PUMP MAY FAIL. | | | | THE LICENSEE DISCOVERED THAT FOR CERTAIN SMALL BREAK LOSS OF COOLANT | | ACCIDENTS, THE HPI PUMP FLOW RATES MAY BE SUFFICIENTLY LOW THAT | | RECIRCULATION IS REQUIRED. IF THE LOW PRESSURE INJECTION PUMP IS IN | | SERVICE TO PROVIDE NET POSITIVE SUCTION HEAD (NPSH) TO THE HPI PUMP, THEN A | | FLOW PATH COULD BE ESTABLISHED FROM THE REACTOR BUILDING SUMP TO OUTSIDE | | CONTAINMENT VIA A RELIEF VALVE IN THE HPI RECIRCULATION FLOW PATH. THIS | | FLOW PATH WOULD BE CREATED IF A MAKEUP TANK RELIEF VALVE LIFTED AND THUS | | CONTAINMENT SUMP INVENTORY WOULD ENTER THE AUXILIARY BUILDING SUMP VIA THE | | MAKEUP TANK RELIEF VALVE. | | | | AN ADDITIONAL CONCERN IS IF ONE OF THE TWO RECIRCULATION ISOLATION VALVES | | IN THE RECIRCULATION LINE FAILS TO OPEN, AND THE HPI PUMP FLOW RATE IS | | SUFFICIENTLY LOWER THAN THE HPI PUMP MAY NOT HAVE ENOUGH FLOW FOR CONTINUED | | OPERATION. | | | | THEY HAVE A NUMBER OF CORRECTIVE ACTIONS WHICH COULD BE IMPLEMENTED, BUT | | ONE UNDER CONSIDERATION IS A MODIFICATION THAT WOULD CONNECT THEIR HPI PUMP | | DISCHARGE LINE TO THE REACTOR BUILDING SPRAY LINE. THIS WOULD PROVIDE A | | FLOW PATH THAT WOULD RETURN THE RECIRCULATION FLOW BACK INTO THE REACTOR | | BUILDING. | | | | THE RESIDENT INSPECTOR WILL BE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31915 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 03/07/97 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 20:44 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 03/07/97 | +------------------------------------------------+EVENT TIME: 20:20[EST]| |NRC NOTIFIED BY: MAY |LAST UPDATE DATE: 03/07/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DANIEL HOLODY 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 DURING A MAIN STEAM HIGH ENERGY LINE BREAK, A | | CONDITION COULD EVOLVE THAT WOULD PUT THE PLANT OUTSIDE THE DESIGN BASIS. | | | | IT WAS DISCOVERED DURING A HIGH ENERGY MAIN STEAM LINE BREAK ANALYSIS, THAT | | THE TURBINE BUILDING COULD BE PRESSURIZED UP TO 1.4LBS. THE TURBINE | | BUILDING PRESSURE INCREASE DUE TO THE HIGH ENERGY MAIN STEAM LINE BREAK | | WOULD KNOCK DOWN THE WALL THAT SEPARATES THE TURBINE BUILDING FROM THE HVAC | | SYSTEMS. WITH THIS WALL DOWN, THE HVAC ROOM, WHICH IS CONSIDERED RIGHT NOW | | TO BE A MILD ENVIRONMENT DURING A HIGH ENERGY MAIN STEAM LINE BREAK EVENT, | | WOULD NOW TURN INTO A HARSH ENVIRONMENT. THE LICENSEE ALSO EXPECTS THE | | CONTROL ROOM HVAC SYSTEM WOULD FAIL DUE TO THE HARSH ENVIRONMENT IN THE | | HVAC ROOM, PLACING THE PLANT IN A CONDITION OUTSIDE ITS DESIGN BASIS. | | | | CURRENTLY THE LICENSEE HAS ENGINEERING CONTRACTORS WORKING ON A BASIS FOR | | MAINTAINING OPERABILITY. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED ALONG WITH VERMONT DEPARTMENT | | OF PUBLIC SERVICE OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 31916 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: DEPARTMENT OF ENERGY |NOTIFICATION DATE: 03/08/97 | | CITY: AIKEN REGION: 2 |NOTIFICATION TIME: 14:12 [ET]| | COUNTY: AIKEN STATE: SC |EVENT DATE: 03/08/97 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 10:30[EST]| | DOCKET: |LAST UPDATE DATE: 03/08/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |THOMAS PEEBLES RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: HUDSPETH(NAT. RES. CTR.) | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE NATIONAL RESPONSE CENTER NOTIFIED THE NUCLEAR REGULATORY COMMISSION | | THAT THE DEPARTMENT OF ENERGY HAD CALLED IN AN INCIDENT WHICH OCCURRED AT | | THE SAVANNAH RIVER SITE. A SPILL OF APPROXIMATELY 20 GALS. OF WASTE WATER | | OCCURRED WHILE THEY WERE CLOSING HIGH LEVEL WASTE WATER TANK #29. WHILE | | SEALING THE TANK CLOSURE WITH GROUT, THE WATER OVERFLOWED AND RAN ONTO THE | | GROUND. THE DOE RESPONSE TEAM IS ON SITE TO CONTAIN THE WATER. THE TOTAL | | PLUTONIUM-238 AND CURIUM-243 CURIE CONTENT IN THE WASTE WATER WAS 0.0108. | | | | THE NATIONAL RESPONSE CENTER WILL NOTIFY REG IV EPA, GEORGIA EMERGENCY | | MANAGEMENT AGENCY, NOAA REGION IV, AND THE SOUTH CAROLINA DEPARTMENT OF | | ENVIRONMENTAL CONTROL. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31917 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 03/09/97 | |UNIT: [3] [ ] [ ] STATE: LA |NOTIFICATION TIME: 05:36 [ET]| |RX TYPE: [3] CE |EVENT DATE: 03/09/97 | +------------------------------------------------+EVENT TIME: 00:45[CST]| |NRC NOTIFIED BY: TIM TULLOS |LAST UPDATE DATE: 03/09/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |IAN BARNES 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ERROR DISCOVERED IN CALIBRATION OF THE REFUELING WATER STORAGE POOL (RWSP) | | LEVEL INSTRUMENTATION. | | | | AS A RESULT OF THE METHOD IN WHICH THE LICENSEE CALIBRATES THE RWSP LEVEL | | INSTRUMENTATION, THE RECIRCULATION ACTUATION SIGNAL (RAS) TO THE PLANT | | PROTECTION SYSTEM (PPS) IS AFFECTED. | | | | DURING THE CONDITION OF TWO CONTROLLED VENTILATION AREA SYSTEM (CVAS) | | TRAINS OPERATING IN THE ACCIDENT MODE, RAS SIGNAL WOULD INITIATE AT A | | SETPOINT BELOW TECHNICAL SPECIFICATION ALLOWABLE LIMIT OF 9.08%. THE | | SUCTION FOR THE CVAS IS LOCATED IN THE SAME ROOM AS THE RWSP LEVEL | | INSTRUMENT TAPS. WHEN BOTH TRAINS OF CVAS ARE OPERATING RWSP LEVEL | | INCREASES. THIS CONDITION DOES NOT EXIST WITH ONLY ONE TRAIN OF THE CVAS IN | | OPERATION. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31918 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 03/09/97 | |UNIT: [ ] [3] [ ] STATE: PA |NOTIFICATION TIME: 09:38 [ET]| |RX TYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 03/09/97 | +------------------------------------------------+EVENT TIME: 06:00[EST]| |NRC NOTIFIED BY: C. J. CAMPBELL |LAST UPDATE DATE: 03/09/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAN HOLODY RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | M/R Y 14 STARTUP | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR MANUALLY SCRAMMED AFTER THE ONLY OPERATING RECIRCULATION PUMP | | TRIPPED AFTER THE MAIN TURBINE HAD BEEN TRIPPED FOR A PREPLANNED DRYWELL | | ENTRY. | | | | ON THE MORNING OF MARCH 8, A LOW OIL LEVEL ALARM WAS RECEIVED ON | | RECIRCULATION PUMP "3A" AT WHICH TIME IT WAS SECURED. REACTOR POWER WAS | | BEING LOWERED THIS MORNING SO A PLANNED ENTRY COULD BE MADE INTO THE | | DRYWELL TO CHECK THE OIL LEVEL OF RECIRCULATION PUMP "3A". AT 0559 EST A | | PLANNED MAIN TURBINE TRIP AND GENERATOR LOCKOUT WAS INITIATED. WHEN THE | | GENERATOR LOCKED OUT THE # 4 13KV FEEDER BREAKER TO THE 13KV AUXILIARY BUS, | | THE "B" SWITCH FAILED TO INDICATE THE OPEN STATUS (THE BREAKER WAS OPEN) OF | | THE # 4 AUXILIARY BUS FEEDER BREAKER. RECIRCULATION PUMP "3B" AUTOMATICALLY | | TRIPPED DUE TO THE # 4 FEEDER BREAKER FAILING TO INDICATE THAT IT WAS OPEN | | CONCURRENT WITH A GENERATOR LOCKOUT. AT 0600 EST THE REACTOR WAS MANUALLY | | SCRAMMED FROM APPROXIMATELY 14% POWER LEVEL. THE REGION OF INSTABILITY WAS | | NOT ENTERED. ALL RODS FULLY INSERTED INTO THE CORE. THE TURBINE BYPASS | | VALVES ARE OPERATING PROPERLY AND DUMPING STEAM TO THE MAIN CONDENSER. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31919 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BYRON REGION: 3 |NOTIFICATION DATE: 03/09/97 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 14:03 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/09/97 | +------------------------------------------------+EVENT TIME: 04:47[CST]| |NRC NOTIFIED BY: STIMAC |LAST UPDATE DATE: 03/09/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |McCORMICK-BARGER RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | PARTIAL LOSS OF PROCESS COMPUTER | | | | AT 0447 CST, THE UNIT 2 PROCESS COMPUTER EXPERIENCED A PARTIAL FAILURE, | | RESULTING IN THE LOSS OF THE COMPUTER POINT HISTORY. THE LICENSEE CONSIDERS | | THIS CONDITION TO REPRESENT A REDUCTION IN EMERGENCY ASSESSMENT CAPABILITY. | | THE LICENSEE STATED THAT PLANT PROCEDURES GRANT EIGHT HOURS FOLLOWING | | DISCOVERY TO CORRECT THE PROBLEM, FOLLOWED BY ONE HOUR TO REPORT THE | | CONDITION TO THE NRC IF THE PROBLEM CANNOT BE CORRECTED. THE NRC RESIDENT | | INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+