U.S. Nuclear Regulatory Commission Operations Center Event Reports For 07/21/97 - 07/22/97 ** EVENT NUMBERS ** 31766 32658 32659 32660 32661 32662 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31766 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 02/11/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 16:45 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 02/11/97 | +------------------------------------------------+EVENT TIME: 15:12[CST]| |NRC NOTIFIED BY: R POWERS |LAST UPDATE DATE: 07/21/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARC DAPAS 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 N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY OF CONTAINMENT PENETRATIONS THAT ARE SUSCEPTIBLE TO THERMALLY | | INDUCED OVERPRESSURIZATION FOLLOWING A LOCA (GENERIC LETTER 96-06 ISSUE) | | | | DURING GENERIC LETTER 96-06 REVIEW, THE LICENSEE IDENTIFIED 21 CONTAINMENT | | PENETRATIONS AS BEING POTENTIALLY SUSCEPTIBLE TO THERMALLY INDUCED | | OVERPRESSURIZATION FOLLOWING A LOSS OF COOLANT ACCIDENT. WHILE PERFORMING | | SUBSEQUENT ENGINEERING EVALUATIONS IN RESPONSE TO NRC GENERIC LETTER 96-06, | | IT WAS DETERMINED THAT 17 OF THE 21 CONTAINMENT PENETRATIONS ARE | | SUSCEPTIBLE TO THERMALLY INDUCED OVERPRESSURIZATION DURING A DESIGN BASIS | | LOSS OF COOLANT ACCIDENT SUCH THAT CODE ALLOWABLE STRESS LIMITS COULD BE | | EXCEEDED. THESE INCLUDED THE FOLLOWING PENETRATIONS: | | | | 1MC-046 CC CC SUPPLY | | 1MC-047 CC CC RETURN | | 1MC-050 MC MC MAKEUP CONDENSATE (MC) | | 1MC-052 FC FUEL POOL COOLING AND CLEANUP | | 1MC-053 FC FUEL POOL COOLING AND CLEANUP | | 1MC-056 FP FIRE PROTECTION | | 1MC-065 WX RADWASTE REPRO. AND DISPOSAL | | 1MC-069 RE CNMT. EQUIPMENT DRAINS RE | | 1MC-070 RF CNMT. FLOOR DRAINS RF | | 1MC-081 FP FIRE PROTECTION | | 1MC-082 FP FIRE PROTECTION | | 1MC-085 CY CYCLE CONDENSATE | | 1MC-088 CC CCW RETURN | | 1MC-103 WO WO CHILLER WATER SUPP. | | 1MC-104 WO WO CHILLER WATER RETURN | | 1MC-116 SC STANDBY LIQUID CONTROL | | | | THE LICENSEE PLANS TO FIX THESE PENETRATIONS BY EITHER DRILLING HOLES IN | | THE DISC OF THE VALVES, INSTALLING RELIEF VALVES, INSTALLING RUPTURE DISKS, | | OR ADDING EXPANSION TANKS. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | | | *** UPDATE BY ROBERT POWERS ON 07/21/97 @ 1550 EDT TAKEN BY MACKINNON *** | | | | DURING A SECOND GENERIC LETTER 96-06 REVIEW, THE LICENSEE IDENTIFIED 2 | | CONTAINMENT PENETRATIONS THAT WEREN'T LISTED IN THE ABOVE EVENT | | NOTIFICATION AS BEING SUSCEPTIBLE TO THERMALLY INDUCED OVERPRESSURIZATION | | FOLLOWING A LOSS OF COOLANT ACCIDENT. WHILE PERFORMING THE ENGINEERING | | EVALUATION IN RESPONSE TO GENERIC LETTER 96-06, IT WAS DETERMINED THAT 2 | | ADDITIONAL CONTAINMENT PENETRATIONS ARE SUSCEPTIBLE TO THERMALLY INDUCED | | OVERPRESSURIZATION DURING A DESIGN BASIS LOSS OF COOLANT ACCIDENT SUCH THAT | | CODE ALLOWABLE STRESS LIMITS COULD BE EXCEEDED. THESE PENETRATIONS ARE AS | | FOLLOWS: | | | | # 1MC-078, SYSTEM IS "CC" (COMPONENT COOLING WATER SUPPLY); & # 1MC-086, | | SYSTEM "RT" (REACTOR WATER CLEAN-UP TO CONDENSER). | | | | THE LICENSEE WILL CORRECT THESE BEFORE STARTUP. R3DO (JIM GAVULA) NOTIFIED. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED BY THE LICENSEE OF THIS EVENT. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32658 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 07/21/97 | |UNIT: [1] [2] [3] STATE: SC |NOTIFICATION TIME: 09:55 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 07/21/97 | +------------------------------------------------+EVENT TIME: 09:00[EDT]| |NRC NOTIFIED BY: PAUL BRANDT |LAST UPDATE DATE: 07/21/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN POTTER RDO | |AESS 50.72(b)(1)(v) EMERGENCY SIREN INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 73 POWER OPERATION | 73 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | EMERGENCY NOTIFICATION SIRENS INOPERABLE | | | | AT 0900, THE LICENSEE DISCOVERED THAT ALL EMERGENCY SIRENS WERE INOPERABLE | | AS A RESULT OF THE INOPERABILITY OF THE MASTER TRANSMITTER. THE LICENSEE | | ACTIVATED THE BACKUP TRANSMITTER, AND THE SIRENS WERE RESTORED AT 0915. THE | | LICENSEE REPORTED THAT THE SIRENS HAD LAST BEEN TESTED ON 7/18/97. THE NRC | | RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32659 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 07/21/97 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 10:59 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 07/01/97 | +------------------------------------------------+EVENT TIME: 00:00[EDT]| |NRC NOTIFIED BY: W. BANHAUER |LAST UPDATE DATE: 07/21/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |POTTER 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 +------------------------------------------------------------------------------+ | POTENTIAL FOR INADEQUATE CORE COOLING DURING A LOSS OF COOLANT ACCIDENT | | | | DURING A DESIGN BASIS LOCA CONCURRENT WITH A LOSS OF OFFSITE POWER AND A | | SINGLE FAILURE OF THE 'A' BATTERY BUS, THE 'B' ENGINEERED SAFEGUARDS (ES) | | SYSTEM CANNOT BE BYPASSED. THE INABILITY TO BYPASS THE 'B' ES ACTUATION | | CAUSES THE FOLLOWING PROBLEMS: (1) CONTROL COMPLEX CHILLERS CANNOT BE | | RESTORED, (2) 'B' SIDE HIGH PRESSURE INJECTION (HPI) VALVES MUV-25 AND | | MUV-26 WILL REMAIN OPEN AND CANNOT BE CLOSED REMOTELY IF NEEDED WHEN THE | | LOCA BREAK IS ON ONE OF THE HPI LINES, RESULTING IN A POTENTIAL FOR | | INADEQUATE CORE COOLING, AND (3) EMERGENCY OPERATING PROCEDURES (EOPs) DO | | NOT CONTAIN ADEQUATE GUIDANCE FOR OVERCOMING THIS PROBLEM. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32660 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 07/21/97 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 17:28 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 07/21/97 | +------------------------------------------------+EVENT TIME: 15:37[CDT]| |NRC NOTIFIED BY: BART CROW |LAST UPDATE DATE: 07/21/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAINE MURRAY 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 +------------------------------------------------------------------------------+ | POTENTIAL FOR LOSS OF STANDBY GAS TREATMENT (SGT) SYSTEM. | | | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "DURING THE PERFORMANCE OF 6.SUMP.101 SURVEILLANCE PROCEDURE FOR Z-SUMP | | (ERP SUMP) OPERABILITY, THE Z-SUMP PUMP FAILED TO START AFTER APPROXIMATELY | | 30 MINUTES OF FILLING. AOG [AUGMENTED OFFGAS] WAS THEN ISOLATED AND Z-SUMP | | PUMPED APPROXIMATELY 1000 GALLONS OF WATER TO RADWASTE. | | | | "THE POWER SUPPLY TO THE Z-SUMPS IS SUPPLIED BY MCC-N, WHICH IS LOAD SHED | | ON A LOSS OF OFF-SITE POWER. IF A LOSS OF OFF-SITE POWER WOULD HAVE | | OCCURRED AT THIS TIME THE 1000 GALLONS OF WATER WOULD HAVE CAUSED THE LEVEL | | IN THE Z-SUMP TO RISE ABOVE THE SGT DISCHARGE LINES RENDERING BOTH TRAINS | | OF SGT INOPERABLE. | | | | "SINCE A LOSS OF OFF-SITE POWER DID NOT OCCUR THE Z-SUMP LEVEL WAS | | CONTROLLED BY THE SUMP PUMPS AND SGT WOULD HAVE OPERATED AS DESIGNED. | | | | "THIS EVENT WAS DETERMINED TO BE REPORTABLE AT 1537 AS A CONDITION BEYOND | | DESIGN BASIS." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN NOTIFIED BY THE LICENSEE. HOO NOTE: SEE | | EN #32618 & #32636 FOR RELATED NOTIFICATIONS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32661 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 07/21/97 | |UNIT: [1] [2] [ ] STATE: TX |NOTIFICATION TIME: 18:50 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 07/21/97 | +------------------------------------------------+EVENT TIME: 16:55[CDT]| |NRC NOTIFIED BY: CLIFF BUEDE |LAST UPDATE DATE: 07/21/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAINE MURRAY RDO | |DSAF 73.71(b)(1) SECURITY DEGRADATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | SECURITY SYSTEM DEGRADATION DUE TO A LOSS OF AC POWER TO THE SECURITY | | COMPUTER. IMMEDIATE COMPENSATORY MEASURES TAKEN UPON DISCOVERY. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | SEE HOO LOG BOOK FOR FURTHER DETAILS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32662 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 07/21/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 22:18 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 07/21/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 19:00[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 07/21/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |JIM GAVULA RDO | | DOCKET: 0707002 |JOHN HICKEY (NMSS) EO | +------------------------------------------------+ | |NRC NOTIFIED BY: RON CRABTREEE | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NCFR NON CFR REPORT REQMNT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A VALID HIGH CONDENSATE ALARM WAS RECEIVED ON AUTOCLAVE # 3. | | | | OPERATIONS PERSONNEL RECEIVED A STEAM SHUTDOWN ALARM ON AUTOCLAVE #3 IN THE | | X-344A FACILITY (TOLL ENRICHMENT SERVICES FACILITY). THE STEAM SHUTDOWN WAS | | CAUSED BY THE ACTUATION OF A HIGH CONDENSATE ALARM (BOTH "A" & "B" | | CONDENSATE PROBES ACTUATED A REDUNDANT ALARM SYSTEM). INVESTIGATION OF THE | | ALARM REVEALED THAT AUTOCLAVE #3 HIGH CONDENSATE ALARM WAS CAUSED BY AN | | ACTUAL HIGH CONDENSATE CONDITION. THE AUTOCLAVE ALARM IS A "Q" SAFETY | | SYSTEM IN THE FACILITY. ACTUATION OF THE ALARM HIGH CONDENSATE SYSTEM | | OCCURRED WHILE THE AUTOCLAVE WAS IN OPERATIONAL MODE 2 (HEATING MODE). THE | | "Q" SAFETY SYSTEM IS CONSIDERED OPERABLE WHEN THE AUTOCLAVE IS IN MODE 2. | | | | THE AUTOCLAVE WAS IMMEDIATELY SHUTDOWN AND DECLARED INOPERABLE BY THE PLANT | | SHIFT SUPERINTENDENT. THERE WAS NO RELEASE OF HAZARDOUS MATERIAL OR | | RADIOLOGICAL CONTAMINATION ASSOCIATED WITH THE "Q" SAFETY SYSTEM ALARM | | ACTUATION. | | | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+