U.S. Nuclear Regulatory Commission Operations Center Event Reports For 12/16/94 - 12/19/94 ** EVENT NUMBERS ** 28152 28153 28154 28155 28156 28157 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28152 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 12/16/94 | |UNIT: [1] [2] [ ] STATE: MI |NOTIFICATION TIME: 12:28 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/16/94 | +------------------------------------------------+EVENT TIME: 11:30[EST]| |NRC NOTIFIED BY: PTACEK |LAST UPDATE DATE: 12/16/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM MCCORMICKBARGER 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 | | 2 | N Y 48 POWER OPERATION | 48 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | APPENDIX R EXEMPTION REQUEST FROM A PREVIOUS YEAR CONTAINED INCORRECT | | INFORMATION. | | | | INCORRECT INFORMATION WAS PROVIDED TO THE NRC FOR AN EXEMPTION TO APPENDIX | | R SECTION 3.G.2 FOR PLANT FIRE ZONE 29G (THE SCREENHOUSE AUXILIARY MOTOR | | CONTROL CENTER ROOM). THE EXEMPTION REQUEST STATED THAT "BOTH THE EAST AND | | WEST TRAINS OF ESW (FOR BOTH UNITS 1 & 2) WILL BE PROTECTED FROM THE | | EFFECTS OF FIRES IN FIRE ZONE 29G". CONTRARY TO THIS STATEMENT, EACH ESW | | TRAIN WOULD BE AFFECTED BY A FIRE IN THAT THE CABLE ASSOCIATED WITH THE | | POWER SUPPLY TO EACH ESW PUMP DISCHARGE VALVE WOULD BE LOST (THERE IS A SIX | | INCH CABLE RUN BETWEEN AREAS THAT WOULD ALLOW A FIRE TO PROPAGATE FROM ONE | | AREA TO ANOTHER). THIS WOULD RESULT IN THE VALVES FAILING IN THE PRE-FIRE | | POSITION. | | | | COOK NORMALLY RUNS TWO ESW PUMPS (ONE PER UNIT), AND WITH THE VALVES | | FAILING IN THE PRE-FIRE CONDITION (OPEN), ESW FLOW WOULD CONTINUE TO BE | | PROVIDED. CURRENTLY COMPENSATORY MEASURES ARE IN PLACE (ROVING FIRE | | WATCHES ARE IN PLACE IN THE APPROPRIATE AREAS). AREA 29G HAS HAD A FIRE | | WATCH PLACED SINCE JUNE OF 1992 DUE TO A TSI (THERMOLAG TYPE) MATERIAL | | CONCERN. A PLANT STANDING ORDER HAS EXPANDED THAT COMPENSATORY ACTION TO | | AREAS 20A THROUGH 29G. | | | | THE LICENSEE IS IN THE PROCESS OF A RECONSTITUTION OF IT'S RESPONSE TO | | APPENDIX R AND HAS INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28153 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 12/16/94 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 18:32 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/16/94 | +------------------------------------------------+EVENT TIME: 17:00[EST]| |NRC NOTIFIED BY: SAUER |LAST UPDATE DATE: 12/16/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LARRY NICHOLSON 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE STICKING OF A TEST PUSH-BUTTON ON A SAFEGUARDS EMERGENCY CONTROL | | CABINET WOULD HAVE RESULTED IN SALEM 1 EXCEEDING THE TECHNICAL | | SPECIFICATION TIME RESPONSE LIMIT FOR CONTAINMENT SPRAY PUMP START IN | | RESPONSE TO A LOCA ALONG WITH A LOSS OF 2 OUT OF 3 VITAL BUSES. | | | | AS A RESULT OF AN EVALUATION PROMPTED BY A PROBLEM WITH AN SEC (SAFEGUARDS | | EMERGENCY CONTROL) CABINET ON 12/9/94 (SEE RELATED EVENT #28127), AN | | ADDITIONAL PROBLEM WAS DISCOVERED. THE SEC PROVIDES CONTROL SIGNALS SUCH | | AS ECCS PUMP STARTS FOR ACCIDENTS AND LOAD SEQUENCING FOR BLACKOUTS. | | CONTINUED INVESTIGATION DISCOVERED THAT AS A RESULT OF THE STUCK | | PUSH-BUTTON, SALEM WOULD HAVE EXCEEDED THE TIME RESPONSE LIMIT IN TS 3.3.2, | | TABLE 3.3-5. | | | | FURTHER RESEARCH INTO THE PLANT DESIGN BASIS REVEALED THAT THE UNIT WOULD | | HAVE EXCEEDED THE TIME LIMIT TO INITIATE CONTAINMENT SPRAY FOR A LOCA WITH | | A CONCURRENT LOSS OF OFFSITE POWER (LOOP) BY OVER SIX SECONDS. THE STUCK | | PUSH-BUTTON WOULD HAVE INHIBITED THE INITIAL CONTAINMENT SPRAY PUMP (CSP) | | START (9 SECONDS INTO THE LOADING SEQUENCE FOR THE DIESEL), BUT WOULD HAVE | | PROVIDED A SUCCESSFUL CSP START WHEN RETRIED UPON COMPLETION OF THE | | SEQUENCE (AT ABOUT 26 SECONDS). THE ENGINEERING EVALUATION WAS REVIEWED FOR | | THE CORRECT TIMES WHEN MAKING THIS DETERMINATION. | | | | THE NUCLEAR FUELS GROUP WAS CONSULTED, AND USING ENGINEERING JUDGMENT, | | CONCLUDED THAT DURING THE TIME THAT THIS PUSH-BUTTON IS ASSUMED TO HAVE | | BEEN STUCK (11/23/94 TO 12/9/94), IF A LOCA WITH A LOOP HAD OCCURRED, THE | | UNIT WOULD NOT HAVE EXCEEDED DESIGN MAXIMUM CONTAINMENT PRESSURE BASED ON | | ACTUAL RIVER WATER TEMPERATURES AND STATUS OF CONTAINMENT COOLING | | CAPABILITIES DURING THAT PERIOD. HOWEVER, HAD THE SAME EVENTS OCCURRED | | DURING A SUMMER HEAT WAVE, SALEM 1 COULD HAVE EXCEEDED THE CONTAINMENT | | PRESSURE DESIGN BASIS. | | | | THE LICENSEE WILL NOTIFY THE RESIDENT INSPECTOR AND LAC TOWNSHIP. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28154 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 12/17/94 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 13:20 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 12/17/94 | +------------------------------------------------+EVENT TIME: 09:33[EST]| |NRC NOTIFIED BY: RAY |LAST UPDATE DATE: 12/17/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM MCCORMICKBARGER 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 N 0 STARTUP | 0 STARTUP | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTROL CENTER VENTILATION SWAPPED TO THE RECIRC MODE DUE TO AN INVALID | | SIGNAL. | | | | FERMI HAD AN AUTOMATIC SWAP OF CONTROL CENTER (CC) HVAC FROM THE NORMAL | | MODE TO THE RECIRC MODE DUE TO AN UPSCALE TRIP SIGNAL FROM THE CONTROL | | CENTER MAKEUP AIR VENTILATION RADIATION MONITOR. THE CONTROL CENTER MAKEUP | | AIR VENTILATION UPSCALE ALARM ALSO CAME IN AT THIS TIME AS DID THE RHR | | SERVICE WATER RAD MONITOR UPSCALE ALARM AND THE RHR SERVICE WATER UPSCALE | | TRIP ALARM. THESE RAD MONITORS SHARE A COMMON POWER SUPPLY. | | | | INITIAL INVESTIGATION SHOWS THAT THESE SIGNALS ARE INVALID, AND UPON | | CONFIRMATION OF THE INITIAL INVESTIGATION, THIS NOTIFICATION WILL BE | | RETRACTED. THE LICENSEE HAS RESET THE RAD MONITORS AND WILL BE | | RE-ESTABLISHING A NORMAL CONTROL CENTER VENTILATION LINEUP UPON VERIFYING | | THE SIGNALS ARE INVALID. THE LICENSEE WILL BE INVESTIGATING THE COMMON | | POWER SUPPLY FOR PROBLEMS. FERMI 2 IS IN STARTUP, BUT HAS NOT BEGUN TO | | PULL RODS YET PENDING THE COMPLETION OF A FEW OUTSTANDING ITEMS. THE | | LICENSEE INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28155 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 12/17/94 | |UNIT: [ ] [2] [ ] STATE: NJ |NOTIFICATION TIME: 15:20 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/17/94 | +------------------------------------------------+EVENT TIME: 11:39[EST]| |NRC NOTIFIED BY: SAUER |LAST UPDATE DATE: 12/17/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LARRY NICHOLSON RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | A N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR TRIP SIGNALS GENERATED DURING SAFETY INJECTION SYSTEM LOGIC TESTING | | DUE TO PROCEDURAL PROBLEMS. | | | | A REACTOR TRIP SIGNAL WAS GENERATED DURING MANUAL SAFETY INJECTION (SI) | | SYSTEM LOGIC TESTING AS A RESULT OF SWITCH MANIPULATIONS IN THE SOLID STATE | | PROTECTION SYSTEM (SSPS). THIS RESULTED IN A "GENERAL WARNING" REACTOR | | TRIP (DESCRIBED AS "TWO SEPARATE PROBLEMATIC CONDITIONS IN THE SSPS"). THE | | REACTOR TRIP BREAKERS, WHICH HAD BEEN CLOSED IN TO SUPPORT THE TESTING, | | WERE NOT PROCEDURALLY ANTICIPATED TO OPEN. THE ROD CONTROL SYSTEM WAS OUT | | OF SERVICE AT THE TIME, AND THEREFORE NO CONTROL ROD MOVEMENT OCCURRED. | | | | THE SAME ACTUATION HAD OCCURRED ON THE PREVIOUS DAY (WHILE PERFORMING THE | | SAME TEST FOR THE OTHER SI TRAIN), BUT IT WAS NOT RECOGNIZED AT THE TIME AS | | BEING REPORTABLE. THE CAUSE OF THE TRIP IS ATTRIBUTED TO PROCEDURAL | | INADEQUACY. THE PROCEDURE WAS APPARENTLY REVISED IN OCTOBER, AND THIS | | PROCEDURE IS ONLY PERFORMED DURING REFUELING OUTAGES. THE LICENSEE WILL BE | | FULLY INVESTIGATING THE CAUSE OF THE TRIPS DURING THE TESTS, AND WILL BE | | SUBMITTING A LICENSEE EVENT REPORT. THE LICENSEE INFORMED THE RESIDENT | | INSPECTOR AND LAC TOWNSHIP. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28156 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 12/17/94 | |UNIT: [1] [2] [ ] STATE: TN |NOTIFICATION TIME: 20:41 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/17/94 | +------------------------------------------------+EVENT TIME: 09:00[EST]| |NRC NOTIFIED BY: HAMILTON |LAST UPDATE DATE: 12/17/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM RANKIN RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | A NON-LICENSED SUPERVISORY EMPLOYEE TESTED POSITIVE DURING A "FOR CAUSE" | | TEST FOR ALCOHOL. THE EMPLOYEE'S ACCESS TO THE PLANT HAS BEEN TERMINATED. | | SEE HOO LOG FOR ADDITIONAL DETAILS. LICENSEE WILL INFORM THE RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28157 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 12/18/94 | |UNIT: [ ] [2] [ ] STATE: AL |NOTIFICATION TIME: 06:31 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 12/18/94 | +------------------------------------------------+EVENT TIME: 03:52[CST]| |NRC NOTIFIED BY: JOEL POWELL |LAST UPDATE DATE: 12/18/94 | |HQ OPS OFFICER: WILLIAM HUFFMAN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM RANKIN RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR TRIP FROM FULL POWER FOLLOWING CLOSURE OF TURBINE GOVERNOR VALVE. | | | | A REACTOR TRIP FROM 100% POWER OCCURRED WHEN THE #3 MAIN TURBINE GOVERNOR | | VALVE WENT FULLY CLOSED. THE CLOSURE OF THE VALVE RESULTED IN LEVEL | | SHRINKAGE IN ALL THREE STEAM GENERATOR. ACCORDING TO THE FIRST OUT | | ANNUNCIATOR, THE REACTOR TRIP WAS GENERATED BY "2C" STEAM GENERATOR LOW-LOW | | LEVEL (17%). | | | | ALL RODS FULLY INSERTED. THE REACTOR IS STABLE AT NO LOAD T-AVE OF 547øF | | AND A PRESSURE OF 2235 PSIG. DECAY HEAT IS BEING DISCHARGED TO THE MAIN | | CONDENSER VIA THE STEAM DUMPS AND AUXILIARY FEEDWATER IS BEING SUPPLIED TO | | THE STEAM GENERATORS. NO PRIMARY OR SECONDARY CODE SAFETY VALVES LIFTED. | | THERE WERE NO COMPLICATIONS DURING THE TRANSIENT AND ALL SYSTEMS FUNCTIONED | | AS REQUIRED. | | | | THE LICENSEE WILL REMAIN IN MODE 3 WHILE INVESTIGATING THE CAUSE OF THE | | MAIN TURBINE GOVERNOR VALVE MALFUNCTION. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+