U.S. Nuclear Regulatory Commission Operations Center Event Reports For 06/01/95 - 06/02/95 ** EVENT NUMBERS ** 28079 28869 28873 28874 28875 28876 28877 28878 +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 28079 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: DOW CORNING CORPORATION |NOTIFICATION DATE: 11/28/94 | | CITY: MIDLAND REGION: 3 |NOTIFICATION TIME: 17:26 [ET]| | COUNTY: STATE: MI |EVENT DATE: 11/28/94 | |LICENSE#: AGREEMENT: N |EVENT TIME: 12:00[EST]| | DOCKET: |LAST UPDATE DATE: 06/01/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | | | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: FACSIMILE | | |HQ OPS OFFICER: WILLIAM HUFFMAN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PROBLEM WITH DOW CORNING SUPPLIED SILICONE ELASTOMERS. | | | | DOW CORNING OF MIDLAND, MICHIGAN, NOTIFIED THEIR CUSTOMERS (SUPPLIERS TO | | NUCLEAR UTILITIES) OF A PROBLEM WITH CERTAIN SILICONE ELASTOMERS. THE | | ELASTOMERS HAVE EXPERIENCED DEVIATIONS IN THE SPECIFIED CURE RATES. IT IS | | NOT YET KNOWN IF THE DEVIATIONS AFFECT THE CURED PROPERTIES OF THESE | | MATERIALS OR COULD CREATE A SAFETY HAZARD FOR THEIR NUCLEAR APPLICATIONS. | | | | THE PRECISE USAGE OF THESE ELASTOMERS WITHIN THE NUCLEAR INDUSTRY WAS NOT | | PROVIDED, BUT APPLICATIONS APPARENTLY INCLUDE FIRE PROTECTION FUNCTIONS. | | THE ELASTOMERS INVOLVED ARE IN THE SYLGARD 170 PRODUCT LINE. A RECENT PART | | 21 REPORT ON DOW RTV ADHESIVE DEVIATIONS APPEARS TO BE RELATED TO THIS | | PROBLEM (SEE EVENTS #28042 & 28161). | | | | A COPY OF THIS REPORT HAS BEEN SENT TO NRR/TQMB (HAASS). | | | | ***UPDATE AT 1205 ON 01/24/95 BY ROBERT M. SCHROEDER TAKEN BY MACKINNON*** | | | | PROGRESS SINCE LAST COMMUNICATION ON SILICONE ELASTOMERS ISSUE. | | | | THE FOLLOWING TEXT IS FROM A FACSIMILE RECEIVED FROM DOW CORNING CORP., | | MIDLAND, MI. | | | | "DOW CORNING 96-081 RTV ADHESIVE/SEALANT DOW CORNING HAS COMPLETED TRIAL | | RUNS OF DOW CORNING 96-081 RTV ADHESIVE/SEALANT INCORPORATING THE HIGHER | | PURITY GRADE PIGMENT. LOT ACCEPTANCE TESTING CONFIRMED THAT THE MATERIAL | | PRODUCED WITH THE HIGHER PURITY GRADE PIGMENT MEETS ALL OF OUR SALES | | SPECIFICATIONS. THEREFORE, WE ARE ONCE AGAIN CAPABLE OF SUPPLYING DOW | | CORNING 96-081 RTV ADHESIVE/SEALANT WHICH MEETS ALL OF OUR SALES | | SPECIFICATIONS. MATERIALS SHOULD BE AVAILABLE NO LATER THAN THE END OF | | FEBRUARY. | | | | UNDERWRITERS LABORATORIES DOW CORNING HAS MET WITH UNDERWRITERS | | LABORATORIES AND IDENTIFIED APPROPRIATE FIRE PERFORMANCE TESTS TO EVALUATE | | THE SYLGARD 170 SILICONE ELASTOMER, SYLGARD 170 SILICONE FAST CURE | | ELASTOMER, AND DOW CORNING 96-081 RTV ADHESIVE/SEALANT IN QUESTION. TESTING | | WILL BE COMPLETE IN MID MAY. A FINAL REPORT DOCUMENTING THE TEST RESULTS | | WILL BE ISSUED BY THE END OF MAY. | | | | OUR NEXT UPDATE WILL OCCUR NO LATER THAN APRIL 7, 1995 TO PROVIDE A | | PROGRESS REPORT ON TESTING. IF YOU HAVE QUESTIONS, PLEASE CONTACT ME ON OUR | | INFORMATION LINE FOR THIS MATTER." | | | | A COPY OF THIS PART 21 UPDATE HAS BEEN FAXED TO WALTER HAASS OF NRR/TQMB. | | | | ***UPDATE 6/1/95 @ 14:55 FROM SCHROEDER TAKEN BY SEBROSKY *** | | THE COMPANY FORWARDED A LETTER SAYING THAT THE FINAL REPORT ON THE SYLGARD | | 170 SILICONE FAST CURE ELASTOMER, AND DOW CORNING 96081 RTV | | ADHESIVE/SEALANT WILL BE DELAYED. THE TESTING HAS BEEN COMPLETED AT | | UNDERWRITERS LABORATORIES AND A FINAL REPORT WILL BE ISSUED BY JUNE 9, | | 1995. A REPORT SUMMARIZING THE TEST RESULTS WILL BE FORWARDED TO THE NRC | | ON JUNE 12, 1995. IN GENERAL, TESTING DID NOT REVEAL ANY PERFORMANCE | | DIFFERENCES BETWEEN MATERIALS THAT DEVIATED FROM DOW CORNING'S SALES | | SPECIFICATION AND MATERIALS THAT MET THE COMPANY'S SALES SPECIFICATIONS. | | | | A COPY OF THIS LETTER HAS BEEN SENT TO VERN HODGE NRR. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28869 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 05/30/95 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 22:16 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/30/95 | +------------------------------------------------+EVENT TIME: 21:55[EDT]| |NRC NOTIFIED BY: MARVIN JOHNSON |LAST UPDATE DATE: 06/01/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DOUGLAS COLLINS 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -LESS THAN 15% OF UNIT 1 CONTROL ROOM ANNUNCIATORS LOST FOR UNKNOWN REASONS | | | | UNIT 1 LOST LESS THAN 15% OF THE CONTROL ROOM ANNUNCIATOR CAPABILITY FOR | | UNKNOWN REASONS. LOST ARE THE ANNUNCIATORS FOR THE STANDBY (REMOTE) | | SHUTDOWN FACILITY, THE FIRE PROTECTION PANELS, THE INSTRUMENT AIR | | COMPRESSORS, THE HVAC BOARDS, AND THE OPERATOR AID COMPUTER PANEL. | | | | PLANT PERSONNEL ARE MONITORING LOCAL PANELS AND OPERATING EQUIPMENT LOCALLY | | UNTIL THE PROBLEM IS CORRECTED. | | | | INSTRUMENT AND CONTROL TECHNICIANS ARE INVESTIGATING THE CAUSE AND | | DETERMINING CORRECTIVE ACTIONS. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | **UPDATE DATE\TIME: 5/31/95 @ 0415 EDT *FROM LICENSEE: SMALL BY:McGINTY** | | | | THE LICENSEE REPLACED A BAD ANNUNCIATOR CARD THAT FED THE "1-AD-13, A-2, | | AND A-3" ANNUNCIATORS. THE CARD WAS CAUSING THE FUSES TO BLOW THAT FEED | | THE POWER SUPPLY FOR THOSE CABINETS. THE ANNUNCIATORS ARE NOW WORKING | | CORRECTLY AND THE WORK ORDER HAS BEEN CLOSED OUT. THE LICENSEE WILL INFORM | | THE NRC RESIDENT INSPECTOR. HOO NOTIFIED R2DO COLLINS. | | | | ** UPDATE @ 1115 EDT ON 6/1/95 ***FROM LICENSEE: BUSHNELL BY:McGINTY ** | | THE LICENSEE IS RETRACTING THIS EVENT BASED ON NOT BEING A SIGNIFICANT LOSS | | OF CONTROL ROOM INDICATION. THE LICENSEE DETERMINED THAT THE LOSS OF | | ALARMS ASSOCIATED WITH THESE TWO PANELS ARE NOT SAFETY RELATED AND THEIR | | LOSS WOULD IN NO WAY CONSTITUTE A LOSS OF CAPABILITY BY OPS CONTROL ROOM | | PERSONNEL TO TAKE ACTIONS NECESSARY TO MITIGATE AN ACCIDENT. REDUNDANT | | MONITORING CAPABILITY EXISTS AND WAS AVAILABLE IF NEEDED FOR THE EQUIPMENT | | PARAMETERS ASSOCIATED WITH THE ALARMS ON THESE PANELS. THE LICENSEE WILL | | INFORM THE RESIDENT INSPECTOR. HOO NOTIFIED THE R2DO (COLLINS). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28873 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 06/01/95 | |UNIT: [ ] [2] [ ] STATE: AL |NOTIFICATION TIME: 02:26 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 06/01/95 | +------------------------------------------------+EVENT TIME: 00:58[CDT]| |NRC NOTIFIED BY: VAUDY HOLLY JR. |LAST UPDATE DATE: 06/01/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DOUGLAS COLLINS 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 | M/R Y 15 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE RUPTURE OF AN ELECTRO-HYDRAULIC CONTROL (EHC) LINE RESULTED IN A MANUAL | | TURBINE TRIP AND MANUAL REACTOR TRIP. | | | | A RUPTURE OF A 1/2-INCH TO 3/4-INCH DIAMETER EHC LINE OCCURRED WHILE THE | | UNIT WAS OPERATING AT APPROXIMATELY 30% POWER. (EHC FLUID IS USED IN THE | | CONTROL SYSTEMS FOR THE TURBINE AND THE STEAM GENERATOR FEEDWATER PUMPS.) | | THE EHC LINE SHEARED OFF AT A WELD WHERE THE LINE GOES INTO THE SUPPLY | | BLOCK FOR THE LOW PRESSURE GOVERNOR VALVE ON THE 'A' FEEDWATER PUMP (WHICH | | WAS SUPPLYING THE UNIT AT THE TIME OF THE EVENT). THE RUPTURED EHC LINE | | CAUSED A DROP IN EHC PRESSURE AND CAUSED OSCILLATIONS OF THE 'A' MAIN | | FEEDWATER PUMP. AS A RESULT, THE LICENSEE BEGAN DECREASING REACTOR POWER, | | STARTED THE THE MOTOR-DRIVEN AND TURBINE DRIVEN AUXILIARY FEEDWATER PUMPS, | | INITIATED A MANUAL TURBINE TRIP, AND INITIATED A MANUAL REACTOR TRIP WHEN | | THE UNIT WAS AT APPROXIMATELY 15% REACTOR POWER. | | | | THE LICENSEE DETERMINED THAT THERE MAY HAVE BEEN A FAULT IN THE FIRST OUT | | ANNUNCIATOR FOR A MANUAL REACTOR TRIP AND IS STILL INVESTIGATING WHETHER OR | | NOT AN AUTOMATIC REACTOR TRIP ON LOW-LOW STEAM GENERATOR WATER LEVEL MAY | | HAVE OCCURRED SIMULTANEOUSLY. (THE AUTOMATIC REACTOR TRIP ON A TURBINE | | TRIP OCCURS WHEN REACTOR POWER IS GREATER THAN OR EQUAL TO 35%.) FIRST OUT | | ANNUNCIATORS WERE NOT RECEIVED FOR EITHER A MANUAL REACTOR TRIP OR LOW-LOW | | STEAM GENERATOR LEVEL TRIP. THE FIRST OUT ANNUNCIATOR WAS A POWER RANGE | | NEGATIVE RATE TRIP WHEN THE CONTROL RODS WENT IN. THE LICENSEE BELIEVES | | THAT A MANUAL REACTOR TRIP OCCURRED FIRST BUT IS CURRENTLY VERIFYING THIS | | WITH COMPUTER LOGS. | | | | ALL CONTROL RODS FULLY INSERTED, AND ALL EMERGENCY CORE COOLING SYSTEMS AND | | ALL EMERGENCY DIESEL GENERATORS WERE OPERABLE AT THE TIME OF THE EVENT. | | CONDENSER VACUUM WAS ALSO MAINTAINED AT ALL TIMES. IN ADDITION, THERE WERE | | NO PROBLEMS WITH THE TRANSFERS OF POWER, AND NO POWER OPERATED RELIEF | | VALVES LIFTED. ALL SYSTEMS FUNCTIONED AS REQUIRED. | | | | FOLLOWING THE EVENT, THE LICENSEE RETURNED ALL SYSTEMS TO A STABLE | | CONDITION. THE LICENSEE'S POST-TRIP REVIEW IS CURRENTLY IN PROGRESS. | | | | THE LICENSEE WILL NOTIFY THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28874 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 06/01/95 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 10:27 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 06/01/95 | +------------------------------------------------+EVENT TIME: 08:45[EDT]| |NRC NOTIFIED BY: ZAREMBA |LAST UPDATE DATE: 06/01/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOCAL LEAK RATE TEST OF THE "B" RECIRCULATION LOOP SAMPLE LINE PENETRATION | | WAS DETERMINED TO EXCEED THE ALLOWABLE LIMITS. | | | | DURING THE PERFORMANCE OF ST-39B-X41 (LEAK TEST OF THE "B" RECIRCULATION | | LOOPS SAMPLE LINE PENETRATION) ON 5/31/95, IT WAS DETERMINED THAT VALVE | | "02-AOV-39" (THE INBOARD SAMPLE ISOLATION VALVE) HAD AN UNACCEPTABLE LEAK | | RATE. THE OUTBOARD SAMPLE ISOLATION VALVE "02-AOV-40" HAD PREVIOUSLY BEEN | | DECLARED INOPERABLE DUE TO FAILING STROKE TIME REQUIREMENTS. | | | | THE FAILURE OF THE INBOARD VALVE RESULTED IN TOTAL LEAKAGE THROUGH THE | | PENETRATION TO BE IN EXCESS OF ACCEPTABLE LIMITS (.6La). THE LICENSEE USED | | A MEDIUM RANGE TEST PANEL FOR THE INITIAL LEAK RATE TESTING, WHICH ONLY | | ALLOWED THE LEAKAGE TO BE MEASURED UP TO A MAXIMUM OF 1000 STANDARD CUBIC | | FEET PER DAY (SCFD). ALTHOUGH 1000 SCFD IS BELOW THE .6La REQUIREMENTS, | | THE LICENSEE WAS UNABLE TO QUANTIFY THE LEAKAGE DUE TO THE USE OF THE | | MID-RANGE TEST PANEL. THUS THE LICENSEE IS MAKING THE CONSERVATIVE | | ASSUMPTION THAT THE LEAKAGE EXCEEDED THE .6La LIMIT. | | | | SUBSEQUENTLY THE PENETRATION LINE WAS PURGED WITH AIR, AND THE INBOARD | | VALVE WAS RETESTED SATISFACTORILY. SINCE THE OUTBOARD VALVE REMAINS | | INOPERABLE DUE TO THE STROKE TIME PROBLEM, THE LICENSEE HAS CLOSED AND | | PULLED THE FUSES FOR THE INBOARD ISOLATION VALVE TO MEET TECH SPEC | | REQUIREMENTS FOR CONTAINMENT ISOLATION. THE LICENSEE IS PREPARING FOR A | | PLANT STARTUP. THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28875 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 06/01/95 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 15:47 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 06/01/95 | +------------------------------------------------+EVENT TIME: 14:00[EDT]| |NRC NOTIFIED BY: GORDON FIDLER |LAST UPDATE DATE: 06/01/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY RDO | |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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | GROUP III ISOLATION OCCURRED DURING REFERENCE LEG BACKFILL. | | | | DURING PERFORMANCE OF PROCEDURE 3M2-12.4 (REFERENCE LEG BACKFILL) THE | | LICENSEE RECEIVED A GROUP III ISOLATION ON REACTOR PRESSURE GREATER THAN 70 | | PSIG. THE CAUSE OF THE PROBLEM WAS TOO HIGH OF A PRESSURE ON THE WATER | | SOURCE FOR THE REFERENCE LEG BACKFILL. THE RHR SYSTEM WAS SECURED AT THE | | TIME, HOWEVER, THE SHUTDOWN COOLING VALVES IN THE SYSTEM WERE IN THE OPEN | | POSITION. UPON RECEIPT OF THE GROUP III ISOLATION SIGNAL THESE VALVES | | CLOSED (MO1001-47, MO1001-50, AND MO1001-29B). THE ISOLATION SIGNAL HAS | | BEEN RESET AND THESE VALVES HAVE BEEN REOPENED. | | | | THE PRESSURE TRANSMITTER THAT CAUSED THE ISOLATION IS IN THE SAME LINE AS | | THE REFERENCE LEG THAT WAS BEING BACKFILLED AT THE TIME. PRIOR TO THE | | EVOLUTION THERE HAD BEEN SOME DISCUSSION ABOUT A POSSIBLE SPIKE IN PRESSURE | | AND THE LICENSEE HAD CLOSED THE MSIVS, AND THE MAIN STEAM DRAIN LINE VALVES | | TO PREVENT THEM FROM REPOSITIONING IN CASE THERE WAS A PRESSURE SPIKE. THE | | SHUTDOWN COOLING VALVES, HOWEVER, WERE NOT REPOSITIONED PRIOR TO THE | | EVOLUTION. | | | | THE LICENSEE WILL INFORM THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28876 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 06/02/95 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 03:34 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 06/01/95 | +------------------------------------------------+EVENT TIME: 23:10[CDT]| |NRC NOTIFIED BY: RATZLAFF |LAST UPDATE DATE: 06/02/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFF-GAS FILTER DRAIN VALVE WAS FOUND TO OPEN WHEN THE CONTROL SWITCH WAS | | PLACED IN THE "CLOSED" POSITION. | | | | WHILE IN THE PROCESS OF FLUSHING THE OFF-GAS FILTERS (OG-F-A&B), IT WAS | | DISCOVERED THAT OFF-GAS FILTER DRAIN VALVE TO THE "Z" SUMP (OG-AOV-13AV) | | WAS CLOSED (NORMALLY OPEN). SUBSEQUENTLY, THE VALVE OPENED WHEN ITS | | CONTROL SWITCH WAS PLACED TO "CLOSED". THIS VALVE IS REQUIRED BY TECH | | SPECS (TABLE 3.2.D, ACTION A) AND THE USAR (SECTION 7.12.2) TO ISOLATE | | OFF-GAS WITHIN 15 MINUTES AFTER A STEAM JET AIR EJECTOR CONTINUOUS HIGH RAD | | CONDITION WHICH EXCEEDS ONE Ci/SEC. | | | | THE VALVE HAS BEEN DISABLED IN THE ISOLATED CONDITION, AS IT CANNOT BE | | ASSURED THAT THE VALVE WOULD REMAIN CLOSED ON AN ISOLATION SIGNAL. THE | | LICENSEE WILL BE INVESTIGATING THE CAUSE. THE LICENSEE WILL BE UTILIZING | | ADMINISTRATIVE CONTROLS TO CYCLE THE VALVE PERIODICALLY (ABOUT EVERY SIX | | HOURS) TO ENSURE THE FILTERS REMAIN DRAINED. | | | | THE LICENSEE WILL INFORM THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28877 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 06/02/95 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 04:27 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 06/02/95 | +------------------------------------------------+EVENT TIME: 03:13[EDT]| |NRC NOTIFIED BY: STEPHENSON |LAST UPDATE DATE: 06/02/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |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 +------------------------------------------------------------------------------+ | CONTROL ROOM EMERGENCY VENTILATION SYSTEM ACTUATION DUE TO A BRIEF RELEASE | | OF SULFUR DIOXIDE GAS DURING THE TRANSFER TO A STORAGE TANK AT THE ADJACENT | | FOSSIL UNITS. | | | | DURING THE TRANSFER OF SULFUR DIOXIDE (SO2) GAS AT CRYSTAL RIVER FOSSIL | | UNITS 1 & 2, A SMALL AMOUNT OF SO2 WAS RELEASED WHILE CONNECTING A HOSE. | | THIS RELEASE ACTUATED A GAS DETECTOR LOCATED NEAR THE TANK, WHICH ACTUATED | | THE CONTROL ROOM EMERGENCY VENTILATION SYSTEM. THE RELEASE CLEARED WITHIN | | A FEW MOMENTS. OPERATORS IMPLEMENTED THE APPLICABLE ABNORMAL PROCEDURE, | | SUBSEQUENTLY CONTACTED THE FOSSIL UNITS AND WERE NOTIFIED THAT THE RELEASE | | WAS ONLY MOMENTARY. | | | | THE FOSSIL UNITS USE SO2 GAS IN THEIR PRECIPITATORS. A TRUCK WAS | | TRANSFERRING THE GAS TO THE STORAGE TANK ON-SITE, AND A BRIEF RELEASE | | OCCURRED WHILE CONNECTING UP THE TRANSFER HOSE. THE GAS DETECTOR FUNCTIONS | | TO DETECT A TANK FAILURE AND INITIATE AN ISOLATION OF THE CONTROL ROOM | | VENTILATION SYSTEM. THE LICENSEE HAS RESTORED THE CONTROL ROOM VENTILATION | | SYSTEM LINE-UP. | | | | THE LICENSEE MENTIONED THAT WHEN THE HOSE IS DISCONNECTED IN A COUPLE OF | | HOURS, A SIMILAR ACTUATION MAY OCCUR AGAIN, ALTHOUGH IT IS NOT EXPECTED. | | SO2 GAS AT ELEVATED LEVELS IS A PERSONNEL HAZARD, BUT THERE WERE NOT ANY | | SIGNIFICANT EXPOSURES TO PERSONNEL DUE TO THIS EVENT. | | | | THE LICENSEE INFORMED THE RESIDENT INSPECTOR. | | | | ** UPDATE @ 0611 ON 6/2/95 ***FROM LICENSEE:STEPHENSON BY:McGINTY** | | THE LICENSEE NOTIFIED THE OPERATIONS CENTER THAT ANOTHER CONTROL ROOM | | VENTILATION ACTUATION OCCURRED WHEN A SMALL AMOUNT OF SO2 GAS WAS RELEASED | | DURING THE DISCONNECTION OF THE HOSE AT 0534 EDT. THE LICENSEE IMPLEMENTED | | THE SAME ACTIONS AS DISCUSSED PREVIOUSLY, AND HAS RESET THE VENTILATION | | SYSTEM. THE LICENSEE INFORMED THE RESIDENT INSPECTOR. HOO NOTIFIED THE | | R2DO (). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28878 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 06/02/95 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 04:41 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 06/02/95 | +------------------------------------------------+EVENT TIME: 04:25[EDT]| |NRC NOTIFIED BY: ENOCH |LAST UPDATE DATE: 06/02/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED | | | |WRIGHT FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 HOT STANDBY | 0 HOT STANDBY | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UE DECLARED AND TERMINATED DUE TO THE OCCURRENCE OF A FIRE IN CONTAINMENT | | ON THE PREVIOUS DAY. | | | | THE LICENSEE HAS IDENTIFIED THE OCCURRENCE OF AN UNUSUAL EVENT AT ABOUT | | NOON ON 6/1/95. THE LICENSEE DECLARED AND TERMINATED THE UNUSUAL EVENT AT | | 0425 EDT ON 6/2/95 DUE TO THE INDICATION THAT A FIRE HAD OCCURRED IN | | CONTAINMENT THE PREVIOUS DAY. THE FIRE WAS ON THE INSULATION OF RCS PIPING | | (THE CROSS-UNDER PIPE FOR THE "A" RCS LOOP). | | | | AT 1147 EDT ON 6/1/95, A FIRE DETECTION ALARM OCCURRED IN CONTAINMENT. UPON | | INVESTIGATION, THE LICENSEE HAS FOUND EVIDENCE OF SOME SMOLDERING AND SMOKE | | IN CONTAINMENT. THE LICENSEE IS IN THE PROCESS OF A HEATUP, AND SPECULATED | | THAT OIL ON THE INSULATION OF THE RCS PIPING MAY HAVE BEEN THE CAUSE. THE | | TOTAL DURATION OF THE FIRE IS UNKNOWN. THE FIRE SELF-EXTINGUISHED. THE | | FIRE DETECTOR ALARM LASTED FOR 15 MINUTES. THE EMERGENCY PLAN SPECIFIES | | THE DECLARATION OF AN UNUSUAL EVENT FOR A FIRE LASTING LONGER THAN 10 | | MINUTES IN THIS LOCATION. | | | | THE LICENSEE MADE AN INITIAL CONTAINMENT ENTRY ON 6/1/95 AFTER RECEIVING | | THE ALARM. CONTAINMENT ATMOSPHERIC CONDITIONS ASSOCIATED WITH THE HEAT-UP | | MADE IT DIFFICULT TO ASCERTAIN IF A FIRE HAD OCCURRED, AND NO SPECIFIC | | EVIDENCE OF A FIRE WAS FOUND DURING THAT ENTRY. ANOTHER CONTAINMENT ENTRY | | THIS MORNING (6/2/95) FOUND THE EVIDENCE OF SMOKE AND SMOLDERING ON THE RCS | | PIPING INSULATION. THE LICENSEE IS EVALUATING INSULATION DAMAGE AND IF | | THERE IS ANY POTENTIAL PIPING DAMAGE. THE LICENSEE HAS INFORMED STATE AND | | LOCAL AUTHORITIES, AND WILL NOTIFY THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+