U.S. Nuclear Regulatory Commission Operations Center Event Reports For 03/26/97 - 03/27/97 ** EVENT NUMBERS ** 30950 31882 31910 31934 32018 32019 32020 32021 32022 32023 32024 32025 32026 32027 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30950 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BYRON REGION: 3 |NOTIFICATION DATE: 09/03/96 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 12:40 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/03/96 | +------------------------------------------------+EVENT TIME: 11:14[CDT]| |NRC NOTIFIED BY: SCOTT FRUIN |LAST UPDATE DATE: 03/26/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROGER LANKSBURY 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 97 POWER OPERATION | 97 POWER OPERATION | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY OF SPENT FUEL RACK BORAFLEX MATERIAL GAPING GREATER THAN THE | | MAXIMUM ASSUMED GAP | | | | RESULTS OF THE EVALUATION OF SPENT FUEL RACK NEUTRON ATTENUATION TEST DATA | | RECEIVED ON SEPTEMBER 3, 1996, SHOWED BORAFLEX MATERIAL GAPING OF GREATER | | THAN ONE FOOT IN A CELL. THE MAXIMUM GAP ASSUMED IN THE CURRENT CRITICAL | | ANALYSIS IS FOUR INCHES. SINCE THE OBSERVED GAP EXCEEDS THE MAXIMUM | | ASSUMED GAP, THE FUEL RACK IS OUTSIDE OF ITS DESIGN BASIS. CURRENTLY, NO | | FUEL IS STORED IN THIS LOCATION OR IN ANY ADJACENT LOCATION. COMPENSATORY | | MEASURES ARE ALSO IN PLACE TO ENSURE THAT A SUFFICIENT BORON CONCENTRATION | | IS MAINTAINED IN THE POOL TO ACCOUNT FOR DEGRADATION OF THE BORAFLEX | | MATERIAL. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1737 EST ON 03/26/97 FROM M WOLFE TAKEN BY MACKINNON * * * | | | | THE LICENSEE HAS REANALYZED REGION 1 SPENT FUEL POOL RACK MODULES ASSUMING | | NO BORAFLEX PRESENT. AN INTERIM TECHNICAL SPECIFICATION AMENDMENT WAS | | SUBMITTED TO ESTABLISH LIMITS ON SOLUBLE BORON CONCENTRATION. THIS WAS DONE | | TO COMPENSATE FOR BORAFLEX DEGRADATION. IN AN ADDITIONAL ANALYSIS, BORAL | | WAS ASSUMED TO SURROUND ALL REGION 1 LOCATIONS. INVESTIGATION HAS REVEALED | | THAT PERIPHERAL CELL LOCATIONS ARE NOT SURROUNDED BY BORAL. COMPENSATORY | | ACTIONS ARE BEING EVALUATED AT THIS TIME. A TELECONFERENCE HAS BEEN | | SCHEDULED FOR 03/27/97 WITH NRR. R3DO (LANKSBURY) NOTIFIED. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31882 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 03/03/97 | |UNIT: [1] [ ] [ ] STATE: KS |NOTIFICATION TIME: 22:25 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 03/03/97 | +------------------------------------------------+EVENT TIME: 20:44[CST]| |NRC NOTIFIED BY: JAMES GILMORE |LAST UPDATE DATE: 03/26/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |IAN BARNES RDO | |ADEG 50.72(b)(1)(ii) DEGRAD COND DURING OP | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | MORE THAN ONE INOPERABLE MAIN STEAM ISOLATION VALVE DUE TO EXCESSIVE | | HYDRAULIC OIL PRESSURES AND SUBSEQUENT TECHNICAL SPECIFICATION 3.0.3 ENTRY | | | | AT 2044 CST, THE UNIT ENTERED TECHNICAL SPECIFICATION 3.0.3 DUE TO | | EXCESSIVE HYDRAULIC OIL PRESSURES IDENTIFIED ON TWO OF FOUR MAIN STEAM | | ISOLATION VALVES. THE HYDRAULIC OIL PRESSURES ON THE VALVES IN QUESTION | | WERE IDENTIFIED TO BE GREATER THAN THE LIMIT OF 5,400 PSIG. THE PRESSURE | | ON ONE OF THESE VALVES WAS APPROXIMATELY 5,500 PSIG. THE VALVES REMAINED | | OPEN. | | | | THE LICENSEE BELIEVES THAT THE EXCESSIVE HYDRAULIC OIL PRESSURES WERE | | CAUSED BY FLUCTUATIONS IN OUTSIDE AIR TEMPERATURE. THE LICENSEE SETS THESE | | PRESSURES FOR BOTH WINTER MODE AND SUMMER MODE, AND TROUBLE IS EXPERIENCED | | WHEN AIR TEMPERATURES CHANGE. | | | | THE LICENSEE REDUCED THE HYDRAULIC OIL PRESSURE ON ONE OF THE TWO AFFECTED | | MAIN STEAM ISOLATION VALVES, AND TECHNICAL SPECIFICATION 3.0.3 WAS EXITED | | AT 2049 CST. AT THE TIME OF THIS NOTIFICATION, THE PRESSURE IN THE OTHER | | AFFECTED VALVE WAS STILL GREATER THAN THE 5,400 PSIG LIMIT. AS A RESULT, | | THE UNIT IS CURRENTLY IN A 4-HOUR LIMITING CONDITION FOR OPERATION IN | | ACCORDANCE WITH TECHNICAL SPECIFICATION 3.7.1.5. THE LICENSEE EXPECTS TO | | REDUCE THE HYDRAULIC OIL PRESSURE ON THIS VALVE WITHIN 30 TO 40 MINUTES. | | | | THE LICENSEE IS CURRENTLY WORKING ON TECHNICAL SPECIFICATION | | INTERPRETATIONS AND CHANGES TO ALLEVIATE THIS PROBLEM. THE LICENSEE ALSO | | STATED THAT THIS EVENT MAY BE RETRACTED WITHIN THE NEXT FEW DAYS. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE 1554 3/26/97 FROM YUNK TAKEN BY BAILEY * * * | | | | THE LICENSEE IS RETRACTING THIS NOTIFICATION. THE LICENSEE HAS DETERMINED | | THAT THE HYDRAULIC OIL PRESSURE OF 5,400 PSIG IS A PROCEDURAL LIMIT AND | | THIS OIL PRESSURE IS NOT A LIMITING FACTOR FOR OPERABILITY. THEREFORE ENTRY | | INTO TECHNICAL SPECIFICATION 3.0.3 WAS NOT NECESSARY AND NO REPORTABLE | | EVENT OCCURRED. NOTIFIED R4DO (STETKA) | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |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: 03/26/97 | |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. | | | | * * * UPDATE 1059 3/26/97 FROM BECHEM TAKEN BY STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS NOTIFICATION. THE LICENSEE STATED THAT THE | | EMERGENCY BLOWDOWN FEATURE IS NOT REQUIRED, AND THAT THE NRC STAFF HAS | | CONCURRED WITH THIS DETERMINATION. (THE LICENSEE HAS A LETTER FROM THE NRC | | STAFF THAT ADDRESSES THIS ISSUE.) THE NRC RESIDENT INSPECTOR WILL BE | | INFORMED OF THIS RETRACTION. NOTIFIED R1DO (HARRISON). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31934 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 03/11/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 21:38 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 03/11/97 | +------------------------------------------------+EVENT TIME: 19:45[CST]| |NRC NOTIFIED BY: JAY HOUSTON |LAST UPDATE DATE: 03/26/97 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |WAYNE KROPP RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |STUART RICHARDS, NRR EO | | |KNUPP FEMA | | |STU RUBIN, IRD AEOD | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DECLARED AN UNUSUAL EVENT AT 1945 CST WHEN LAKE LEVEL ROSE | | ABOVE THE MAXIMUM ALLOWED FINAL SAFETY ANALYSIS REPORT (FSAR) VALUE. | | | | THE MAXIMUM LAKE LEVEL ALLOWED BY THE LICENSEE'S FSAR IS 701 FEET, AND THE | | LAKE LEVEL IS NOW AT 701.8 FEET. THE LAKE LEVEL BLOWDOWN VALVE IS BROKEN, | | AND RAIN IS FORECAST. THE LICENSEE, THEREFORE, EXPECTS THAT LAKE LEVEL | | MIGHT INCREASE IN THE NEAR FUTURE. THE LICENSEE IS ATTEMPTING TO HAVE | | DIVERS REPAIR THE BLOWDOWN VALVE. IN ADDITION, PERSONNEL ARE MONITORING | | THE LOWER ELEVATIONS IN THE PLANT, AND THE ENGINEERING DEPARTMENT IS | | RE-EVALUATING THE 701-FOOT LEVEL LIMIT. | | | | THE LICENSEE IS ACTIVATING ITS TECHNICAL SUPPORT CENTER AND HAS NOTIFIED | | STATE GOVERNMENT AGENCIES AND THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 2159 ON MARCH 15, 1997, FROM ARGUBRIGHT TO S. SANDIN * * * | | | | THE STATION REMAINS IN AN UNUSUAL EVENT (EAL HU2) DUE TO A HIGH LAKE LEVEL | | (>701 FEET) THAT IS OUTSIDE OF THE PLANT'S DESIGN BASIS. LAKE LEVEL IS | | CURRENTLY 701.5 FEET AND HAS BEEN TRENDING DOWNWARD SINCE BLOWDOWN FLOW WAS | | REESTABLISHED ON THURSDAY, MARCH 13, 1997. | | | | THE STATION ANTICIPATES TERMINATING THE UNUSUAL EVENT NEXT WEEK WHEN LAKE | | LEVEL HAS BEEN RESTORED TO LESS THAN 700.75 FEET (CONFIRMED BY SURVEYOR), | | PROVIDED NO SIGNIFICANT PRECIPITATION IS FORECASTED IN THE SUBSEQUENT 3 | | DAYS. | | | | COMPENSATORY AND CONTINGENCY ACTIONS (FLOOD WATCHES, EMERGENCY BACKUP | | PUMPING EQUIPMENT, SANDBAGS, ETC.) ESTABLISHED AT THE ONSET OF THE UNUSUAL | | EVENT WILL REMAIN IN EFFECT UNTIL THE UNUSUAL EVENT IS TERMINATED. | | | | BASED ON THE CORRECTIVE, MITIGATING, AND COMPENSATORY ACTIONS TAKEN AND THE | | CURRENT DOWNWARD TREND IN LAKE LEVEL, THE TECHNICAL SUPPORT CENTER MANNING | | ESTABLISHED AT THE ONSET OF THE EVENT HAS BEEN SECURED. THE UNIT 1 SHIFT | | MANAGER WILL CONTINUE FULFILLING THE POSITION OF ACTING STATION DIRECTOR. | | THE UNIT 1 PLANT MANAGER HAS BEEN ASSIGNED AS THE ISSUES MANAGER FOR ANY | | NEW AND REMAINING ISSUES. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE HOO NOTIFIED THE | | R3DO (KROPP) AND NRR EO (RICHARDS). | | | | * * * UPDATE 1810 EST ON 03/26/97 BY GRAFF TAKEN BY MACKINNON * * * | | | | UNUSUAL EVENT TERMINATED AT 1705 CST ON 03/26/97 BECAUSE LAKE WATER LEVEL | | HAS DECREASED BELOW 700.75'. THE LAKE LEVEL IS CURRENTLY 700.65' AND | | DECREASING. OUTFLOW FROM THE LAKE IS GREATER THAN 30,000 GALLONS PER MINUTE | | AND THERE IS NO RAIN FORECASTED FOR THE NEXT THREE DAYS. LICENSEE NOTIFIED | | STATE AND LOCAL OFFICIALS OF THE TERMINATION OF THE UNUSUAL EVENT. R3DO | | (ROGER LANKSBURY), NRR EO (MARSH), FEMA (CIBOCH) NOTIFIED. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THE UNUSUAL EVENT TERMINATION BY | | THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32018 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 03/26/97 | |UNIT: [1] [2] [ ] STATE: NJ |NOTIFICATION TIME: 09:00 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/26/97 | +------------------------------------------------+EVENT TIME: 07:02[EST]| |NRC NOTIFIED BY: HAMILTON |LAST UPDATE DATE: 03/26/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HARRISON 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 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE NOTIFIED STATE AND FEDERAL AGENCIES REGARDING SMALL OIL SPILL INTO | | DELAWARE RIVER. | | | | AT 0702, THE UNIT 1 CONTROL ROOM RECEIVED A REPORT OF AN OIL SHEEN ON THE | | DELAWARE RIVER. THE APPARENT SOURCE OF THE SHEEN WAS THE OIL/WATER | | SEPARATOR. THE LICENSEE DISPATCHED PERSONNEL TO PLACE FLOATING BOOMS TO | | CONTAIN THE SPILL, AND TO TERMINATE THE RELEASE FROM THE OIL/WATER | | SEPARATOR. THE RELEASE WAS STOPPED AT 0732 AFTER APPROXIMATELY 4 OUNCES OF | | OIL HAD ENTERED THE RIVER. | | | | THE LICENSEE IS CONTINUING EFFORTS TO CLEAN UP THE SPILL. THE LICENSEE | | CONTACTED THE NEW JERSEY DEPARTMENT OF ENVIRONMENTAL PROTECTION, LOWER | | ALLOWAYS CREEK TOWNSHIP, AND THE USDOT NATIONAL RESPONSE CENTER. THE NRC | | RESIDENT INSPECTOR HAS BEEN INFORMED OF THIS NOTIFICATION. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 32019 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: CT DEPT OF ENVIRONMENTAL PROTECTION |NOTIFICATION DATE: 03/26/97 | | CITY: TORRINGTON REGION: 1 |NOTIFICATION TIME: 09:08 [ET]| | COUNTY: STATE: CT |EVENT DATE: 03/25/97 | |LICENSE#: AGREEMENT: N |EVENT TIME: 00:00[EST]| | DOCKET: |LAST UPDATE DATE: 03/26/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |HARRISON RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: SCHEURITZEL | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | IODINE-131 CONTAMINATION FOUND IN WASTE AT TORRINGTON TRANSFER STATION. | | | | ON 3/25/97, A WASTE TRUCK SET OFF THE SCALE RADIATION ALARM AT THE | | TORRINGTON TRANSFER STATION. THE CONNECTICUT DEPARTMENT OF ENVIRONMENTAL | | PROTECTION RESPONDED, AND DISCOVERED THE SOURCE OF THE ALARM TO BE A | | PLASTIC BUCKET, THE BOTTOM OF WHICH WAS LINED WITH PAPER TOWELS THAT WERE | | STAINED YELLOW. THE MATERIAL WAS IDENTIFIED AS I-131 BY GAMMA SPECTROSCOPY. | | THE STATE REPRESENTATIVE DID NOT ESTIMATE THE TOTAL ACTIVITY, BUT STATED | | THAT THE RADIATION EMITTED WAS ONLY SLIGHTLY ABOVE BACKGROUND. | | | | THE STATE CONTACTED NRC REGION 1 REGARDING THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32020 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 03/26/97 | |UNIT: [ ] [2] [ ] STATE: NC |NOTIFICATION TIME: 09:25 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/26/97 | +------------------------------------------------+EVENT TIME: 08:54[EST]| |NRC NOTIFIED BY: T. REAMES |LAST UPDATE DATE: 03/26/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |VERRELLI RDO | |ADEG 50.72(b)(1)(ii) DEGRAD COND DURING OP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | BOTH TRAINS OF CONTROL ROOM VENTILATION SYSTEM INOPERABLE FOR TWO MINUTES. | | | | THE LICENSEE ENTERED TECHNICAL SPECIFICATION 3.0.3 WHEN BOTH TRAINS OF | | CONTROL ROOM VENTILATION WERE DECLARED INOPERABLE FOR APPROXIMATELY TWO | | MINUTES. AT THE TIME OF THE EVENT, TWO OF THE FOUR INTAKES WERE CLOSED DUE | | TO WORK BEING PERFORMED ON GASEOUS RADIATION MONITOR 1EMF-43B. RADIATION | | MONITOR 1EMF-43A SPIKED, CAUSING A TRIP II (SECOND ALARM LEVEL WHEN A HIGH | | RADIATION SIGNAL IS RECEIVED), AND OPERATORS RESPONDED BY CLOSING THE OTHER | | TWO INTAKES. | | | | RADIATION PROTECTION TECHNICIANS DETERMINED THAT THE SPIKE WAS SPURIOUS, | | AND THE INTAKES WERE REOPENED. THE NRC RESIDENT INSPECTOR WILL BE INFORMED | | BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 32021 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: UNKNOWN |NOTIFICATION DATE: 03/26/97 | | CITY: STEELTON REGION: 1 |NOTIFICATION TIME: 15:00 [ET]| | COUNTY: STATE: PA |EVENT DATE: 03/25/97 | |LICENSE#: AGREEMENT: N |EVENT TIME: 13:30[EST]| | DOCKET: |LAST UPDATE DATE: 03/26/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |LEANNE HARISON (R1) RDO | | |Dr COOL EO | +------------------------------------------------+FINKBEINER (NRC) EPA | |NRC NOTIFIED BY: Dr COOL |ROSEMARY HOGAN (IRD) AEOD | |HQ OPS OFFICER: JOHN MacKINNON |LANKSBURY (REG 3) RDO | +------------------------------------------------+JOHNSON DOE | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A TRUCK LOAD OF CONTAMINATED STEEL SET OFF A RADIATION ALARM AT BETHLEHEM | | STEEL TECHNOLOGIES, STEELTON, PA. RADIATION LEVELS WERE APPROXIMATELY | | 50æR/hr (10 TIMES BACKGROUND). | | | | THIS INFORMATION WAS INITIALLY REPORTED BY DON COOL (NMSS), WITH ADDITIONAL | | INFORMATION PROVIDED BY JIM COPENHAVER, PROGRAM MANAGER FOR RADIATION | | PROTECTION, STATE OF PENNSYLVANIA. | | | | A RADIATION MONITOR AT BETHLEHEM STEEL TECHNOLOGY, LOCATED IN STEELTON, | | PA., WAS ACTUATED ON MARCH 25, 1997, DURING EARLY AFTERNOON BY A TRUCK | | DELIVERING SCRAP STEEL TO THE PLANT. THE PENNSYLVANIA DEPARTMENT OF | | RADIATION PROTECTION WAS PROMPTLY NOTIFIED BY BETHLEHEM STEEL OF THIS | | INCIDENT. THE PENNSYLVANIA DEPARTMENT OF RADIATION PROTECTION MEASURED | | RADIATION LEVELS OF 50æR/hr ON THE SCRAP STEEL LOCATED IN THE TRUCK. THE | | RADIATION SOURCE IS NOT LOCALIZED. THE TRUCK HAD ORIGINALLY CAME FROM TRUE | | TEMPER HARDWARE LOCATED IN CAMP HILL, PA., AND IT PASSED THROUGH L. LEVETON | | STEEL CO. LOCATED IN YORK, PA., BEFORE ARRIVING AT BETHLEHEM STEEL | | TECHNOLOGY. | | | | UPON FURTHER INVESTIGATION IT WAS FOUND THAT TRUE TEMPER HARDWARE MADE | | 33,000 SHOVEL BLADES FROM ROLLS OF STEEL THAT WERE RECEIVED FROM LIBERTY | | STEEL, LOCATED IN NORTH JACKSON, OH (STEEL DISTRIBUTION CENTER). LIBERTY | | STEEL HAD RECEIVED THESE ROLLS FROM WCI STEEL CO. LOCATED IN WARREN, OH. AT | | THIS TIME IT IS BELIEVED THESE STEEL ROLLS WERE MADE AT THE WCI STEEL CO. | | | | TRUE TEMPER HARDWARE HAD TWO ROLLS OF STEEL LEFT OVER WHICH ARE | | CONTAMINATED. THE READING TAKEN INSIDE THE ROLLS WAS BETWEEN (30 - 40)æR/hr | | AND THE SHOVEL BLADES' RADIATION LEVELS WERE (10 - 15)æR/hr. BACKGROUND | | RADIATION LEVEL IS 5æR/hr. TRUE TEMPER HARDWARE RECEIVED THE CONTAMINATED | | STEEL ROLLS BETWEEN MARCH 19-20 AND THE ROLLS WERE STAMPED INTO SHOVEL | | BLANKS ON MARCH 21st. | | | | THE STATE OF PENNSYLVANIA RADIATION PROTECTION BELIEVES THE RADIOACTIVE | | MATERIAL IS THORIUM. | | | | US NRC REGION 1 AND REGION 3 HAD ALREADY BEEN NOTIFIED OF THIS EVENT. | | | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32022 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 03/26/97 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 16:18 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 03/26/97 | +------------------------------------------------+EVENT TIME: 11:35[CST]| |NRC NOTIFIED BY: WILLIAM GREEN |LAST UPDATE DATE: 03/26/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM STETKA RDO | |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 92 POWER OPERATION | 92 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INNER AND OUTER REACTOR BUILDING DOORS WERE INADVERTENTLY OPENED AT THE | | SAME TIME. | | | | TODAY FROM 08:48:40 TO 08:48:56, 10:09:35 TO 10:09:36, AND AGAIN FROM | | 11:35:35 TO 11:42:27 SECONDARY CONTAINMENT APPEARS TO HAVE BEEN BREACHED | | WHEN BOTH THE INNER AND THE OUTER REACTOR BUILDING DOORS WERE INADVERTENTLY | | OPENED AT THE SAME TIME. DURING THE THIRD INSTANCE OF OPENING BOTH DOORS | | THE INTERLOCK LATCH THAT IS INTENDED TO PREVENT BOTH DOORS FROM OPENING WAS | | DAMAGED AND HAD TO BE REPLACED. PER THE DESIGN OF THE DEVICE (MICROSWITCH) | | THE INNER AND THE OUTER DOORS CAN BE OPENED AT THE SAME TIME IF BOTH DOORS | | ARE HIT (ACTUATED) AT THE SAME TIME. | | | | WHILE TRANSPORTING PERSONNEL OUT OF THE REACTOR BUILDING THRU THE ALTERNATE | | SHUTDOWN ROOM, IT APPEARS THAT BOTH THE INNER AND OUTER DOORS OF THE | | ALTERNATE SHUTDOWN ROOM WERE MOMENTARILY OPEN AT THE SAME TIME. THIS | | CONDITION ALSO RESULTED IN A LOSS OF SECONDARY CONTAINMENT. STANDBY GAS | | TREATMENT WAS OPERATED TO CONFIRM ITS ABILITY TO MAINTAIN SECONDARY | | CONTAINMENT AT 0.05 INCHES OF WATER NEGATIVE PRESSURE AS REQUIRED BY | | TECHNICAL SPECIFICATION 4.7.C.d. THE BROKEN DOOR LATCH HAS BEEN REPAIRED AT | | THIS TIME. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32023 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 03/26/97 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 17:47 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 03/26/97 | +------------------------------------------------+EVENT TIME: 15:30[EST]| |NRC NOTIFIED BY: R ORZELL |LAST UPDATE DATE: 03/26/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LEANNE HARRISON 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HIGH PRESSURE CORE SPRAY (HPCS) DECLARED INOPERABLE | | | | UPON REVIEW OF SURVEILLANCE REQUIREMENT 4.3.3.3 (ECCS RESPONSE TIME) AND | | THE TECHNICAL SPECIFICATION DEFINITION FOR "ECCS SYSTEM RESPONSE TIME," IT | | APPEARS THAT THE EXISTING SURVEILLANCE PROCEDURES DO NOT COMPLETELY SATISFY | | THE TECHNICAL SPECIFICATION REQUIREMENTS. THE TECHNICAL SPECIFICATION | | DEFINITION REQUIRES THAT CSH (HPCS SYSTEM) BE RESPONSE TIME TESTED FROM THE | | CHANNELS SENSOR THROUGH THE ACTUATED DEVICE (FOUR CHANNELS FOR HIGH DRYWELL | | PRESSURE AND FOUR CHANNELS FOR REACTOR VESSEL WATER LEVEL 2 HAVE NOT BEEN | | TESTED). CURRENTLY, A PORTION OF THE CSH (HPCS SYSTEM) CIRCUIT WAS NOT | | TESTED. CONSEQUENTLY, HPCS WAS DECLARED INOPERABLE AT 1530 EST. THIS PLACES | | UNIT 2 IN A 14 DAY LCO. ADDITIONALLY, DUE TO TECHNICAL SPECIFICATION | | TERMINOLOGY AND RECENT TECHNICAL SPECIFICATION AMENDMENTS, THE PLANT IS | | ALSO ENTERING A 24 HOUR SHUTDOWN LCO TO ACCOMMODATE THE MISSED | | SURVEILLANCE. THE MISSED SURVEILLANCE TESTING ON HPCS CHANNELS SHOULD BE | | COMPLETED WITHIN THE NEXT 24 HOURS. | | | | ALL OTHER ECCS SYSTEMS, EMERGENCY DIESEL GENERATORS, AND RCIC ARE FULLY | | OPERABLE, IF NEEDED. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32024 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HADDAM NECK REGION: 1 |NOTIFICATION DATE: 03/26/97 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 19:41 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 03/26/97 | +------------------------------------------------+EVENT TIME: 19:05[EST]| |NRC NOTIFIED BY: WILLIS |LAST UPDATE DATE: 03/26/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LEANNE HARRISON 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 +------------------------------------------------------------------------------+ | A FLAW IN THE SPENT FUEL POOL (SFP) HEAT EXCHANGER SERVICE WATER RETURN | | LINE WAS IDENTIFIED. | | | | AN ENGINEERING EVALUATION OF THE SFP HEAT EXCHANGER SERVICE WATER RETURN | | LINE FOUND THAT IT WAS INCAPABLE OF WITHSTANDING DESIGN BASIS LOADING | | (i.e., COMBINATION OF DEAD WEIGHT, PRESSURE, AND SEISMIC LOADS). | | CONSEQUENTLY, THE RETURN LINE WAS DECLARED INOPERABLE, ALTHOUGH THE LINE IS | | INTACT AND IN SERVICE. THE FLAW, i.e., PIPING THICKNESS LESS THAN THE | | MINIMUM WALL REQUIREMENT, WAS IDENTIFIED DURING RADIOGRAPHY. THIS RETURN | | LINE WAS LAST CHECKED ABOUT 6 MONTHS AGO AT WHICH TIME NO FLAWS WERE FOUND. | | THE LICENSEE IS EVALUATING INSTALLING A FIRE HOSE JUMPER IN ORDER TO REPAIR | | THE RETURN LINE. THE SERVICE WATER SUPPLY WAS DECLARED OUT-OF-SERVICE DUE | | TO WATER HAMMER CONCERNS AT 1801 EST ON 3/11/97. THE LICENSEE HAS COMMITTED | | TO COMPLETING REPAIRS TO THE SUPPLY LINE BY 4/14/97 AND IS EVALUATING | | PERFORMING REPAIRS TO THE RETURN LINE CONCURRENTLY. IF SFP COOLING IS LOST, | | THE SFP HEAT UP RATE WOULD BE 1 TO 2øF/HR. CURRENTLY, THE SFP TEMPERATURE | | IS 70øF. THE LICENSEE NOTIFIED THE STATE AND LOCAL COUNTIES OF THIS EVENT. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32025 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 03/26/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 19:41 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 03/26/97 | +------------------------------------------------+EVENT TIME: 14:55[CST]| |NRC NOTIFIED BY: SCHOTTEL |LAST UPDATE DATE: 03/26/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROGER LANKSBURY 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERED THAT THE DEGRADED VOLTAGE DROPOUT 4.16KV UNDERVOLTAGE RELAYS DO | | NOT MEET CURRENT DEFINITION OF OPERABILITY. | | | | DURING THE PREPARATION AND REVIEW OF A LICENSE AMENDMENT TO INCORPORATE THE | | USE OF COMPENSATORY OPERATOR ACTION TO MITIGATE A POSTULATED DEGRADED | | VOLTAGE CONDITION, IT WAS DISCOVERED THAT THE SECOND LEVEL OR DEGRADED | | UNDERVOLTAGE RELAYS DO NOT MEET THE CURRENT DEFINITION OF OPERABILITY (AS | | FOUND IN THE IMPROVED TECHNICAL SPECIFICATIONS). THESE RELAYS (DEGRADED | | VOLTAGE DROPOUT 4.16KV UNDERVOLTAGE RELAYS - 2 SETS OF RELAYS IN EACH | | DIVISION AND THE LICENSEE HAS 3 DIVISIONS) WILL NOT PROVIDE THE DEGRADED | | UNDERVOLTAGE RELAY PROTECTION AUTOMATICALLY AND THEREFORE CANNOT BE | | "OPERABLE" FOR THE PURPOSE OF ASSURING OPERATION OR PREVENTING DAMAGE TO | | CLASS 1E ELECTRICAL LOADS IN THE EVENT OF A DEGRADED VOLTAGE CONDITION. IT | | WAS PREVIOUSLY REALIZED THAT THESE RELAYS WOULD NOT PROVIDE THE REQUIRED | | PROTECTION AUTOMATICALLY AND LER 94-005 WAS SUBMITTED AS A RESULT OF THIS | | DISCOVERY. AT THAT TIME MANUAL COMPENSATORY ACTION WAS INSTITUTED TO | | COMPENSATE FOR THIS LACK OF AUTOMATIC ACTION. THIS CURRENT REVIEW HAS | | REVEALED THAT PER TECHNICAL SPECIFICATION BASES SR 3.0.1 DISCUSSION, THE | | MANUAL COMPENSATORY ACTION CANNOT BE CREDITED TO CONSIDER THE DEGRADED | | VOLTAGE RELAY FUNCTION OPERABLE. THE UNIT HAS DECLARED ALL THREE DIVISIONS | | OF DEGRADED VOLTAGE INSTRUMENTS AND THEIR ASSOCIATED EMERGENCY DIESEL | | GENERATORS INOPERABLE AS A RESULT OF THIS DISCOVERY. LICENSEE IS IN | | TECHNICAL SPECIFICATION 3.8.8.2(b)(1-4). AT THE PRESENT TIME, THE LICENSEE | | CANNOT PERFORM ANY CORE ALTERATIONS, MOVE ANY IRRADIATED FUEL, OR DRAIN ANY | | WATER FROM THE REACTOR VESSEL. ENGINEERING IS WORKING ON RESTORING THE | | SYSTEM TO AN OPERABLE STATUS IMMEDIATELY. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32026 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 03/27/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 00:00 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 03/26/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 11:36[CST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 03/27/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |ROGER LANKSBURY RDO | | DOCKET: 0707001 |JOE HOLONICH EO | +------------------------------------------------+FRANK CONGEL IRD | |NRC NOTIFIED BY: MATT C. MAURER | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE HIGH PRESSURE FIRE WATER SYSTEM IN BUILDING C-331 WAS DECLARED | | INOPERABLE. | | | | THE FOLLOWING WAS RECEIVED VIA FACSIMILE: | | | | "DURING A WALKDOWN OF THE C-331 BUILDING HIGH PRESSURE FIRE WATER (HPFW) | | SPRINKLER SYSTEMS, A BRANCH LINE WAS DISCOVERED MISSING ON HPFW #17 AT | | COLUMN EE-16 THROUGH FF-16 ON THE CELL FLOOR. THE MISSING BRANCH LINE | | PROVIDES FIRE PROTECTION FOR AN OPEN AREA UNDER THE UNIT BYPASS. THE | | MISSING BRANCH LINE SHOULD CONTAIN THREE SPRINKLER HEADS. THIS DEFICIENCY | | WAS IDENTIFIED DURING AN NRC FIRE PROTECTION INSPECTION. THIS SPRINKLER | | SYSTEM WAS DECLARED INOPERABLE AT 1126 HOURS ON 3/26/97 AND AN HOURLY FIRE | | PATROL WAS INITIATED AS REQUIRED BY TSR 2.4.4.5." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | HOO NOTE: SEE EVENTS #31841, 31850, 31972, 31977, 32002 AND 32012 FOR | | OTHER FIRE PROTECTION REPORTS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32027 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 03/27/97 | |UNIT: [ ] [2] [ ] STATE: TX |NOTIFICATION TIME: 01:38 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/26/97 | +------------------------------------------------+EVENT TIME: 21:47[CST]| |NRC NOTIFIED BY: JOHN MILLIFF |LAST UPDATE DATE: 03/27/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM STETKA RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | M/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 2 WAS MANUALLY TRIPPED FROM 100% POWER DURING A FEEDWATER TRANSIENT. | | | | THE FOLLOWING IS A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "MANUAL REACTOR TRIP WAS INITIATED DUE TO A LOW STEAM GENERATOR LEVEL ON | | 'B' STEAM GENERATOR APPROACHING THE AUTOMATIC TRIP SETPOINT OF 33%. ACTUAL | | STEAM GENERATOR LEVEL IN 'B' STEAM GENERATOR WAS INDICATED AT 36% AND | | DECREASING AT THE TIME OF THE MANUAL REACTOR TRIP. CAUSE OF THE MAIN | | FEEDWATER PERTURBATION IS UNDER INVESTIGATION. ALL SAFETY SYSTEMS | | FUNCTIONED PROPERLY WITH NO DISCREPANCIES. ALL CONTROL RODS INSERTED | | FULLY." | | | | THE NORMAL STEAM GENERATOR OPERATING LEVEL AT 100% POWER IS 58.6% OF NARROW | | RANGE. DURING THE FEEDWATER TRANSIENT, OPERATORS UNSUCCESSFULLY ATTEMPTED | | TO RECOVER 'B' STEAM GENERATOR LEVEL USING MANUAL CONTROL OF THE 'B' MAIN | | FEEDWATER REG VALVE ALTHOUGH THE DEMANDED POSITION INDICATED 100%. ALL 3 | | TURBINE DRIVEN MAIN FEEDWATER PUMPS WERE IN SERVICE. FOLLOWING THE TRIP, | | STEAM GENERATOR LEVELS DECREASED TO APPROXIMATELY 40% WIDE RANGE RESULTING | | IN THE ACTUATION OF ALL 3 MOTOR DRIVEN AND THE STEAM DRIVEN AUXILIARY | | FEEDWATER PUMPS AS EXPECTED. MAIN FEEDWATER HAS SINCE BEEN RESTORED TO | | SERVICE AND THE AFW SYSTEM SHUTDOWN AND RETURNED TO STANDBY. NO PRIMARY OR | | SECONDARY RELIEF LIFTED. THE STEAM DUMPS TO THE MAIN CONDENSER ARE IN USE | | TO REMOVE DECAY HEAT. OFFSITE POWER REMAINED AVAILABLE WITH THE UNIT'S | | EMERGENCY DIESEL GENERATORS OPERABLE AND IN STANDBY. UNIT 1 WAS UNAFFECTED | | AND REMAINS AT 100% POWER. | | | | THE LICENSEE ESTIMATES A UNIT 2 RESTART SOMETIME TODAY FOLLOWING COMPLETION | | OF THE POST TRIP REVIEW AND ROOT CAUSE INVESTIGATION. THE LICENSEE DOES NOT | | INTEND TO ISSUE A PRESS RELEASE OR MAKE ANY OFFSITE NOTIFICATIONS. THE NRC | | RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+