U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/07/94 - 04/08/94 ** EVENT NUMBERS ** 26843 26932 27052 27053 27054 27055 27056 27057 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 26843 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 02/24/94 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 19:18 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 02/24/94 | +------------------------------------------------+EVENT TIME: 17:55[EST]| |NRC NOTIFIED BY: COLOMB |LAST UPDATE DATE: 04/07/94 | |HQ OPS OFFICER: GREG SCARFO +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROBERT BORES 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 +------------------------------------------------------------------------------+ | IT WAS DETERMINED THAT THE CONTROL ROOM (CR) EMERGENCY VENTILATION SYSTEM | | WOULD NOT MAINTAIN THE HABITABILITY OF THE CR DURING AN ACCIDENT WHERE A | | RADIOLOGICAL RELEASE OCCURS. | | | | A REVIEW OF THE CR EMERGENCY VENTILATION SYSTEM DETERMINED THAT THE | | RADIOLOGICAL HABITABILITY OF THE CR WOULD NOT BE MAINTAINED DURING AN | | ACCIDENT WHERE A RADIOLOGICAL RELEASE OCCURS (OUTSIDE OF SECONDARY | | CONTAINMENT) IF THE SYSTEM IS IN ITS NORMAL (UNISOLATED) MODE. THE DESIGN | | BASIS CALCULATIONS ASSUME A FACTOR OF 99% TRAIN FILTER EFFICIENCY FOR | | NORMAL-MODE OPERATIONS. THIS ASSUMPTION IS INCORRECT IF THE RELATIVE | | HUMIDITY DECREASES BELOW 70%. THE CR EMERGENCY VENTILATION SYSTEM DOES NOT | | CONTROL HUMIDITY IN NORMAL MODE, THEREFORE, SUCH AN ASSUMPTION IS | | QUESTIONABLE (90% EFFICIENCY SHOULD'VE BEEN USED). | | | | THE CR EMERGENCY VENTILATION SYSTEM HAS BEEN ISOLATED AND IS OPERABLE. IT | | WILL REMAIN ISOLATED UNTIL CORRECTIVE ACTIONS HAVE BEEN TAKEN. CORRECTIVE | | ACTIONS MUST STILL BE DETERMINED. THE LICENSEE WILL INFORM THE NRC | | RESIDENT INSPECTOR. | | | | *** UPDATE DATE/TIME:4/7/94 ***FROM LICENSEE:ZARENBA BY:McGINTY *** | | THE LICENSEE IS RETRACTING THIS EVENT BECAUSE AFTER FURTHER REVIEW BY | | ENGINEERING, THIS CONDITION DID NOT, IN FACT, EXIST AND IS NOT A REPORTABLE | | CONDITION. | | | | A 1974 CALCULATION HAD BEEN IDENTIFIED WHICH HAD DETERMINED THAT A 99% CREV | | FILTER EFFICIENCY WAS REQUIRED DURING A PARTICULAR POSTULATED ACCIDENT | | INVOLVING THE FAILURE OF A MAIN STEAM ISOLATION VALVE (MSIV) TO CLOSE. THE | | 1974 CALCULATION HAD BEEN PERFORMED TO SUPPORT A PROPOSED MAIN STEAM | | LEAKAGE COLLECTION SYSTEM (MSLCS) DESIGN WHICH APPARENTLY DID NOT HAVE | | REDUNDANT LINES AND DID NOT COLLECT LEAKAGE DOWNSTREAM OF THE OUTBOARD | | MSIVs. SINCE THE CREV SYSTEM CURRENTLY DOES NOT HAVE HUMIDITY CONTROL | | GUARANTEEING LESS THAN 70% HUMIDITY, ONLY 90% FILTER EFFICIENCY COULD BE | | ASSUMED (PER REG. GUIDE 1.52). | | | | THE MSLCS ACTUALLY INSTALLED (AFTER THE 1974 CALCULATION WAS ISSUED) IS | | DESIGNED TO COLLECT AND PROCESS ALL POSTULATED MSIV LEAKAGE AND HAS | | REDUNDANT COMPONENTS. THE RADIOLOGICAL EFFECTS REMAIN UNCHANGED FROM THOSE | | PRESENTED IN THE FSAR. THE PRESENT CREV SYSTEM, WITH 90% FILTER EFFICIENCY | | WITHOUT HUMIDITY CONTROL, IS CAPABLE OF MAINTAINING LONG TERM CONTROL ROOM | | HABITABILITY. | | | | THE LICENSEE INFORMED THE RESIDENT INSPECTOR. HOO NOTIFIED THE R1DO | | (PASCIAK). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 26932 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 03/12/94 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 22:17 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/12/94 | +------------------------------------------------+EVENT TIME: 20:20[EST]| |NRC NOTIFIED BY: JOE MONAGHAN |LAST UPDATE DATE: 04/07/94 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 30 POWER OPERATION | 30 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM DECLARED INOPERABLE DUE TO | | HIGH MOISTURE CONTENT IN THE OIL USED IN THE SYSTEM. | | | | THE LICENSEE HAD REPLACED THE HPCI OIL DURING THE LAST OUTAGE AND HAD | | FILLED THE OIL RESERVOIR PAST THE HI LEVEL ALARM SETPOINT. (THE OIL IS | | USED FOR LUBRICATION AND IS ALSO USED IN THE CONTROL SYSTEM.) THE | | LICENSEE WAS DRAINING SOME OF THE OIL FROM THE RESERVOIR WHEN PERSONNEL | | NOTICED SOME MOISTURE IN THE SYSTEM. A SAMPLE OF THE OIL WAS TAKEN AND | | ANALYZED. THE ADMINISTRATIVE LIMIT FOR THE MOISTURE CONTENT IS 0.9 % WATER. | | THE SAMPLE RESULTS WERE 1.09% WATER CONTENT. | | | | THE LICENSEE HAS ENTERED A 14 DAY LIMITING CONDITION FOR OPERATION DUE TO | | HPCI BEING DECLARED INOPERABLE. ALL OTHER ECCS SYSTEMS ARE OPERABLE AS | | WELL AS THE RCIC SYSTEM. THE LICENSEE IS CHANGING OUT THE OIL IN THE HPCI | | SYSTEM AND IS INVESTIGATING THE CAUSE OF THE PROBLEM. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR. | | | | *** UPDATE DATE/TIME:4/7/94 @ 0801 EDT ***FROM LICENSEE:NEFF BY:McGINTY *** | | THE LICENSEE RETRACTED THIS EVENT BASED ON THE FOLLOWING: | | FURTHER EVALUATION OF THE MOISTURE CONTENT AND THE EFFECT OF THIS MOISTURE | | WAS PERFORMED AND IT HAS BEEN CONCLUDED THAT THE HPCI SYSTEM WAS OPERABLE. | | THIS CONCLUSION IS BASED ON: | | | | 1. A LOW MOISTURE CONTENT (1.09% BEING SLIGHTLY OVER THE LIMIT WHICH | | WAS SET AT 0.9%) | | | | 2. SUCCESSFUL STARTUP TESTING PERFORMED WITH THIS MOISTURE CONTENT A | | FEW DAYS BEFORE THE DISCOVERY | | | | 3. THE OIL USED AT LIMERICK IS MOBILRAD 797, WHICH IS A SUPERIOR GRADE | | OIL, LESS LIKELY TO EXPERIENCE DEGRADATION | | | | 4. THE MOISTURE WAS IN THE OIL FOR A SHORT PERIOD OF TIME (LESS THAN 7 | | DAYS) | | | | 5. THE OIL WAS NOT EXPOSED TO ELEVATED TEMPERATURES FOR A LONG PERIOD | | OF TIME (WHICH WILL HELP PROLONG OIL LIFE) | | | | THE OIL WAS CLEANED AS A PLANNED MAINTENANCE ACTIVITY WITHIN THE TECH SPEC | | ACTION LIMITS, AND THEREFORE THIS EVENT IS NOT REPORTABLE. SEE NUREG 1022 | | SUPPLEMENT 1, 7.10 & 7.11. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR. HOO NOTIFIED THE R1DO | | (PASCIAK). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27052 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 04/07/94 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 10:38 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/07/94 | +------------------------------------------------+EVENT TIME: 08:00[CDT]| |NRC NOTIFIED BY: ROBERT YURKOVICH |LAST UPDATE DATE: 04/07/94 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE BURGESS 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 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DURING STEAM GENERATOR TUBE INSPECTION MORE THAN 1% OF THE STEAM GENERATORS | | TUBES FOR STEAM GENERATORS "A", "C", & "D" WERE CLASSIFIED DEFECTIVE TUBES. | | | | THE FOLLOWING TEXT IS FROM A FACSIMILE. | | "ON MARCH 21, 1994 A STEAM GENERATOR (SG) TUBE INSERVICE INSPECTION WAS | | INITIATED ON BRAIDWOOD UNIT 1 IN ACCORDANCE WITH TECHNICAL SPECIFICATION | | SURVEILLANCE REQUIREMENT (TSSR) 4.4.5.0. | | THE INITIAL SAMPLE SIZE OF 100% OF ALL AVAILABLE TUBES WAS SELECTED. | | TSSR 4.4.5.2.c REQUIRES THAT THE RESULTS OF EACH SAMPLE INSPECTION BE | | CLASSIFIED INTO ONE OF THREE CATEGORIES. A SG WILL BE CLASSIFIED IN | | CATEGORY C-3 IF MORE THAN 10% OF THE TOTAL TUBES INSPECTED ARE DEGRADED OR | | MORE THAN 1% OF THE INSPECTED TUBES ARE DEFECTIVE. A SG TUBE IS CONSIDERED | | DEGRADED IF IT HAS AN IMPERFECTION OF GREATER THAN OR EQUAL TO 20% NOMINAL | | TUBE WALL THICKNESS. A SG TUBE IS CONSIDERED DEFECTIVE IF IT HAS AN | | IMPERFECTION OF GREATER THAN OR EQUAL TO 40% NOMINAL TUBE WALL THICKNESS. | | ON APRIL 7, 1994, AT 0800 HOURS, THE RESULTS OF THE INITIAL SAMPLE | | INSPECTION RESULTED IN SGs 1A, 1C, AND 1D BEING CLASSIFIED INTO CATEGORY | | C-3 BASED ON THE FOLLOWING NUMBER OF DEFECTIVE TUBES: | | FOR SG 1A, 86 OUT OF 4521 TUBES INSPECTED (1.90%); SG 1C 140 OUT OF 4352 | | TUBES INSPECTED (3.22%) (AN ADDITIONAL 117 DEFECTIVE TUBES WERE PLUGGED | | DURING BRAIDWOOD UNIT 1 FORCED OUTAGE 26 (OCTOBER 24 THROUGH NOVEMBER 11, | | 1993); AND SG 1D 73 OUT OF 4529 TUBES INSPECTED (1.61%). | | TECHNICAL SPECIFICATION TABLE 4.4-2 REQUIRES NRC NOTIFICATIONS PURSUANT TO | | 10 CFR 50.72 (b) (2) (i) FOR ANY SG CLASSIFIED IN CATEGORY C-3. | | PREVIOUSLY, ON MARCH 28, 1994, AS A RESULT OF THE EXTREMELY LARGE NUMBER OF | | INDICATIONS BEING FOUND DURING THE SG TUBE INSERVICE INSPECTION, BRAIDWOOD | | INITIATED A CONTINUING DIALOG WITH THE OFFICE OF NUCLEAR REACTOR REGULATING | | REGARDING THE POSSIBILITY OF PURSUING AN EMERGENCY TECHNICAL SPECIFICATION | | AMENDMENT TO IMPLEMENT A SG TUBE INTERIM PLUGGING CRITERIA." | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27053 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 04/07/94 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 11:31 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/07/94 | +------------------------------------------------+EVENT TIME: 10:47[EDT]| |NRC NOTIFIED BY: HEDMON |LAST UPDATE DATE: 04/08/94 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: ALERT +-----------------------------+ |10 CFR SECTION: |WALTER PASCIAK RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |GRIMES EO | | |SIMMERS FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 75 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD A REACTOR TRIP FROM 25% POWER ON POWER LOW RANGE/HIGH FLUX | | SIGNAL AND A SAFETY INJECTION INITIATION ON LOW-LOW TAVG COINCIDENT WITH | | HIGH STEAM FLOW. | | | | THE LICENSEE WAS LOWERING REACTOR POWER BECAUSE OF THE LOSS OF SOME | | CIRCULATING WATER PUMPS AT THE TIME OF THE TRIP. POWER WAS LOWERED TO LESS | | THAN 10%, THUS AUTOMATICALLY INSTATING THE LOW POWER TRIP SET POINT OF 25%. | | THE LICENSEE HAS SPECULATED THAT OPERATORS BEGAN WITHDRAWING CONTROL RODS | | TO RESTORE A LOWER THAN NORMAL TAVG. POWER INCREASED TO 25%, AND A REACTOR | | TRIP WAS RECEIVED, ALL RODS FULLY INSERTED. | | | | A SAFETY INJECTION SIGNAL WAS RECEIVED BECAUSE OF A LOW LOW TAVG IN | | CONJUNCTION WITH HIGH STEAM FLOW SIGNAL. AT LEAST TWO MAIN STEAM ISOLATION | | VALVES AND TWO FEED WATER ISOLATION VALVES FAILED TO CLOSE AS REQUIRED, IN | | ADDITION, THE MAIN FEED PUMPS FAILED TO TRIP. THE SUBSEQUENT COOLDOWN OF | | THE REACTOR COOLANT SYSTEM CAUSED PRESSURIZER PRESSURE AND LEVEL TO DROP. A | | SECOND SAFETY INJECTION SIGNAL WAS RECEIVED ON LOW PRESSURIZER PRESSURE. | | | | THE PLANT WAS TAKEN SOLID BY THE HIGH HEAD SAFETY INJECTION PUMPS. THE | | POWER OPERATED RELIEF VALVES (PORVs) ON THE PRESSURIZER OPENED AND RELIEVED | | TO THE PRESSURIZER RELIEF TANK (PRT). THE BLOW OUT DISC ON THE PRT BLEW | | OUT TO PREVENT OVER PRESSURIZATION OF THE TANK. THE PRT RELIEVES TO THE | | CONTAINMENT. | | | | ***UPDATE AT 11:55 4/7/94 FROM HEDMON TO GOULD*** AT 11:26 THE "11" STEAM | | GENERATOR SAFETY VALVE LIFTED AND FULLY RESEATED. THE COOLDOWN RESULTED IN | | A DECREASE IN RCS PRESSURE. THIS WORKED IN CONJUNCTION WITH THE OVER | | FEEDING TO CAUSE THE SECOND SI SIGNAL. | | | | * * * UPDATE @ 13:53 4/7/94 FROM HEDMON TO MCGINTY * * * | | LICENSEE DECLARED A PRECAUTIONARY ALERT AT 13:16 4/7/94 TO HELP STAFF THE | | TSC IN RESPONSE TO THE ABOVE EVENT. | | | | * * * UPDATE AT 1602 EDT BY KARSCH * * * COMMISSIONER'S ASSISTANTS BRIEFING | | BRIEFER (WENSINGER) RGN 1, ATTENDEES AEOD (JORDAN & HOLAHAN), IRB | | (BROCKMAN), PA (BEECHER), SP (LOHAUS), EDO (TATUM), NRR EO (DENNIG), SECY | | (BATES), CA (MADDEN), ROGERS' (SORENSEN), SELIN'S (BAKER), REMICK'S | | (GOODMAN), DePLANQUE'S (RULAND), OTHERS NRR (DENBECK), NRR/RSB (COLLINS). | | | | THE LICENSEE HAS DRAWN A BUBBLE IN THE PRESSURIZER AND INTENDS TO LOWER | | PRESSURIZER LEVEL TO 50% AND BEGIN A NORMAL COOLDOWN TO COLD SHUTDOWN. | | | | | | ***UPDATE AT 20:31 BY GIGGETTS/OTT TO GOULD*** THE LICENSEE TERMINATED THE | | ALERT AND NOUE AT 20:20ET BASED ON PLANT COOLDOWN BEING IN PROGRESS. THEY | | ARE IN HOT STANDBY(483F AND 1500PSI). THE COOLDOWN RATE IS 25-30F/HR. THEY | | EXPECT TO BE IN MODE 4 BY MIDNIGHT. RI WAS NOTIFIED. | | | | THE FOLLOWING AGENCIES WERE NOTIFIED OF THE ALERT AND ITS TERMINATION: | | 1. DOE(VISNOSKY) | | 2. USDA(COOPER/GRAHAM) | | 3. HHS(BURGER) | | 4. FEMA(SIMMERS/CARR) | | 5. EPA(LYMON/CONKLIN) | | | | *** UPDATE DATE/TIME:4/8/94 @ 0410 BY:McGINTY *** | | AS OF 0410 EST ON 4/8/94, THE PLANT IS IN MODE 4 AT 370 psig AND 350F. | | PREPARATIONS ARE BEING MADE TO PLACE RHR ON SERVICE. THE LICENSEE | | ANTICIPATES REACHING COLD SHUTDOWN AT ABOUT NOON, TODAY. THE LICENSEE HAD | | NO NEW INFORMATION TO REPORT REGARDING THE EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27054 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 04/07/94 | |UNIT: [ ] [4] [ ] STATE: FL |NOTIFICATION TIME: 14:29 [ET]| |RX TYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 04/07/94 | +------------------------------------------------+EVENT TIME: 03:55[EDT]| |NRC NOTIFIED BY: ARTHUR SINGER |LAST UPDATE DATE: 04/07/94 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KERRY LANDIS RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 4 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE IS MAKING A 24 HOUR REPORT DUE TO PLANNED MAINTENANCE ON THE | | STANDBY STEAM GENERATOR FEEDWATER SYSTEM. | | | | THE STANDBY STEAM GENERATOR FEEDWATER SYSTEM CONSISTS OF 2 MOTOR DRIVEN | | PUMPS AND IS A BACKUP TO THE 3 TURBINE DRIVEN AUXILIARY FEEDWATER PUMPS. | | BOTH THE STANDBY STEAM GENERATOR FEEDWATER SYSTEM AND THE AUXILIARY | | FEEDWATER SYSTEM ARE SHARED BETWEEN THE NUCLEAR UNITS AT TURKEY POINT | | (UNITS 3 AND 4). UNIT 3 IS CURRENTLY IN MODE 5 IN A REFUELING OUTAGE. | | | | THE LICENSEE IS REQUIRED BY TECH SPEC 3.7.1.6 TO INFORM THE NRC WITHIN 24 | | HOURS ANYTIME BOTH STANDBY STEAM GENERATOR FEEDWATER PUMPS ARE TAKEN OUT OF | | SERVICE. AT 03:55 EDT 4/7/94 THE LICENSEE REMOVED BOTH STANDBY STEAM | | GENERATOR FEEDWATER PUMPS FROM SERVICE TO PERFORM WORK ON A COMMON | | DISCHARGE VALVE TO UNIT 3 (DWDS-3-012). THE LICENSEE PERFORMED THE | | MAINTENANCE ON THIS VALVE AND RETURNED THE 'B' STANDBY STEAM GENERATOR | | FEEDWATER PUMP TO SERVICE AT 14:00 EDT 4/7/94. THE 'A' STANDBY STEAM | | GENERATOR FEEDWATER PUMP REMAINS INOPERABLE DUE TO ONGOING PLANNED | | MAINTENANCE ON IT. | | | | THE LICENSEE WILL ISSUE A FOLLOWUP WRITTEN REPORT TO THE NRC AND THE | | LICENSEE HAS INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27055 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 04/07/94 | |UNIT: [1] [2] [ ] STATE: TX |NOTIFICATION TIME: 17:08 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/07/94 | +------------------------------------------------+EVENT TIME: 14:00[CDT]| |NRC NOTIFIED BY: TOM RUCKER |LAST UPDATE DATE: 04/07/94 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |IAN BARNES 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 73 POWER OPERATION | 73 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFF-SITE NOTIFICATION TO THE TEXAS NATURAL RESOURCES CONSERVATION | | COMMISSION REGARDING THE LEAKAGE OF APPROXIMATELY TEN GALLONS OF HYDRAULIC | | OIL INTO LAKE GRANBURY. | | | | WHILE PERFORMING MAINTENANCE ON THE MAKE-UP WATER TRANSFER PUMPS AT LAKE | | GRANBURY, A HYDRAULIC LINE WAS ACCIDENTLY BROKEN. HYDRAULIC OIL SPRAYED | | WITHIN THE PUMP STRUCTURE. IN THE PROCESS OF ISOLATING THE HYDRAULIC LEAK | | AN INSTRUMENT LINE FOR ONE OF THE OPERATING PUMPS BROKE, WHICH DESPITE THE | | LICENSEE'S BEST EFFORTS, WASHED APPROXIMATELY TEN GALLONS OF HYDRAULIC OIL | | OUT OF THE STRUCTURE INTO LAKE GRANBURY VIA FLOOR DRAINS. | | | | THE LICENSEE REPORTED THE LEAK TO THE TEXAS NATURAL RESOURCES CONSERVATION | | COMMISSION, AND IS ATTEMPTING TO CONTAIN AND CLEAN UP THE OIL. THE | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27056 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 04/07/94 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 17:57 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 04/07/94 | +------------------------------------------------+EVENT TIME: 17:30[EDT]| |NRC NOTIFIED BY: HOSKINS |LAST UPDATE DATE: 04/07/94 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE BURGESS RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | THE LICENSEE ISSUED A PRESS RELEASE CONCERNING CURRENT STATUS ON THREE | | ITEMS. | | | | THE FIRST WAS THE INVESTIGATION INTO THE ROOT CAUSE OF THE 12/25/93 MAIN | | TURBINE FAILURE. DURING AN INVESTIGATION FOCUSING ON THE 8TH STAGE OF THE | | #3 LOW PRESSURE TURBINE, THEY DISCOVERED ADDITIONAL CRACKS IN THE ROOT OF | | 12 SEVENTH STAGE BLADES OF LOW PRESSURE TURBINES 2 & 3. PRELIMINARY TESTS | | INDICATE THAT THESE CRACKS MAY HAVE EXISTED BEFORE THE 12/25/93 EVENT. THE | | FINDING OF THESE ADDITIONAL BLADE CRACKS HAS PROMPTED THE LICENSEE TO | | CONSIDER WHETHER TO REPLACE PART OR ALL OF THE TURBINE. MINOR DISTORTIONS | | HAVE ALSO BEEN FOUND IN ALL 3 LOW PRESSURE TURBINE ROTORS. | | | | THE SECOND ITEM WAS THAT THE LICENSEE PLANS TO RELEASE THE REMAINING | | 500,000 GALS OF EXCESS WATER WHICH ACCUMULATED AFTER THE ACCIDENT. THE | | QUALITY OF THE WATER MEETS ALL STATE AND FEDERAL ENVIRONMENTAL STANDARDS | | FOR DISCHARGE. | | | | THE THIRD ITEM IS THAT THE LICENSEE IS MOVING AHEAD WITH ARRANGEMENTS TO | | REFUEL THE REACTOR. THE RI WILL BE INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27057 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 04/07/94 | |UNIT: [1] [2] [ ] STATE: NC |NOTIFICATION TIME: 23:20 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/07/94 | +------------------------------------------------+EVENT TIME: 23:20[EDT]| |NRC NOTIFIED BY: VELLERS |LAST UPDATE DATE: 04/07/94 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |KERRY LANDIS RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |JOHN ZWOLINSKI EO | | |EARL FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED THAT THEY EVACUATED PERSONNEL FROM A PROTECTED AREA | | DUE TO THE RELEASE OF EXCESSIVE TOXIC VAPORS. | | | | THIS OCCURRED WHILE WORKERS WERE USING METHYL-ETHYL-KETONE TO CLEAN OFF THE | | INSULATION ON THE CHILLER IN THE AUX BUILDING. THEY EVIDENTLY USED TOO MUCH | | SOLVENT WHERE THEY WERE BEGINNING TO TASTE IT IN THEIR MOUTH FROM THE | | VAPORS. WHEN THEY CALLED THE SAFETY DEPARTMENT, IT WAS RECOMMENDED THAT THE | | AREA BE EVACUATED(APPROX 15:40). WHEN READINGS WERE FINALLY TAKEN OF THE | | VAPOR CONCENTRATION, SOME TIME HAD ELAPSED, AND THE CONCENTRATION RETURNED | | WITHIN ACCEPTABLE LIMITS FOR PERSONS TO WORK IN THAT AREA. THE WORKERS | | RETURNED TO THE AREA WITHIN 2 HOURS AFTER BEING EVACUATED. VENTILATION IN | | THE AREA WAS INCREASED. THE NOUE WAS TERMINATED AT 23:20. NO WORKERS | | REQUIRED ANY MEDICAL ATTENTION. THE RI WAS INFORMED AND STATE AND LOCAL | | AGENCIES WERE NOTIFIED. | +------------------------------------------------------------------------------+