U.S. Nuclear Regulatory Commission Operations Center Event Reports For 07/25/97 - 07/28/97 ** EVENT NUMBERS ** 32167 32460 32554 32669 32674 32675 32676 32677 32678 32679 32680 32681 32682 32683 32684 32685 32686 32687 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32167 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 04/16/97 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 21:49 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 04/16/97 | +------------------------------------------------+EVENT TIME: 19:45[CDT]| |NRC NOTIFIED BY: MATTSON |LAST UPDATE DATE: 07/25/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DETERMINED THAT SEVERAL WELDS ON A CONTAINMENT PENETRATION | | ANCHOR FRAME WERE OUTSIDE OF UFSAR STRESS LIMITS. | | | | INITIAL LICENSEE EVALUATION INDICATED THAT THE STRESSES ON SEVERAL WELDS | | ON A CONTAINMENT PENETRATION ANCHOR FRAME EXCEEDED OPERABILITY LIMITS | | SPECIFIED IN THE UFSAR. THE ANCHOR FRAME PROVIDES SUPPORT FOR THE | | CONTAINMENT PENETRATION AND THE UNIT 2 "B" LOW PRESSURE COOLANT INJECTION | | LINE. THIS FRAME IS USED TO MAINTAIN CONTAINMENT INTEGRITY AND THE | | INTEGRITY OF THE LOW PRESSURE COOLANT INJECTION PIPING. | | | | THE LICENSEE PLANS TO REPAIR THE ANCHOR FRAME PRIOR TO RESTARTING UNIT 2. | | | | THE LICENSEE IS EVALUATING THE CORRESPONDING UNIT 3 ANCHOR FRAMES. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE 0302 EDT ON 7/25/97, FROM STEVE VERCELLI TO S. SANDIN * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION BASED ON THE FOLLOWING | | TEXT RECEIVED FROM THE LICENSEE: | | | | "THIS CALL IS BEING MADE TO RETRACT THE ENS CALL MADE ON APRIL 16, 1997, | | FOLLOWING NOTIFICATION THAT A NUMBER OF WELDS ON UNIT 2 CONTAINMENT | | PENETRATION (X-116B DIV 2 LPCI) APPEARED TO BE OUTSIDE THE UFSAR STRESS | | LIMITS AND, THEREFORE, NOT OPERABLE." | | | | "IT WAS SUBSEQUENTLY DETERMINED BY SARGENT AND LUNDY CALCULATION #8188-RP-S | | THAT PENETRATION X-116B WAS OPERABLE AT ALL TIMES." | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. THE NRC | | OPERATIONS CENTER NOTIFIED THE R3DO (GAVULA). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32460 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 06/11/97 | |UNIT: [ ] [ ] [3] STATE: IL |NOTIFICATION TIME: 02:22 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 06/10/97 | +------------------------------------------------+EVENT TIME: 23:50[CDT]| |NRC NOTIFIED BY: PETE KARABA |LAST UPDATE DATE: 07/25/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES CREED RDO | |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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INVALID ESF SIGNAL DURING SURVEILLANCE TESTING | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "WHILE LIFTING LEADS TO DEFEAT AN ISOLATION SIGNAL TO THE HIGH PRESSURE | | COOLANT INJECTION (HPCI) SYSTEM TO FACILITATE VALVE CYCLING FOR OPERATING | | SURVEILLANCES, A HPCI SUCTION AUTO-TRANSFER OCCURRED. THE APPARENT CAUSE | | OF THE EVENT WAS THAT A DAISY CHAIN IN THE HPCI CONTROL LOGIC WAS BROKEN | | RESULTING IN AN INVALID CST LO-LO LEVEL SIGNAL. UNIT 3 IS IN MODE 4 AND | | HPCI WAS NOT REQUIRED TO BE OPERABLE." | | | | THE LICENSEE IS BACKING OUT OF THE SURVEILLANCE. CORRECTIVE ACTIONS | | INCLUDE REVISING THE PROCEDURE TO BE MORE SPECIFIC IN IDENTIFYING THAT THE | | "FIELD" SIDE OF THE TERMINAL BOARD LEADS SHOULD BE LIFTED ("INCOMING" SIDE | | LEADS WERE LIFTED IN THIS INSTANCE). UPON COMPLETION OF THE INVESTIGATION | | AND CORRECTIVE ACTIONS, THE LICENSEE WILL REPEAT THIS SURVEILLANCE. | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | | | | * * * 2058 JULY 25, 1997, UPDATE FROM PETE KARABA RECEIVED BY TROCINE * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION AFTER DETERMINING THAT | | THE SYSTEM WAS ADEQUATELY REMOVED FROM SERVICE. IN ADDITION, THE GUIDANCE | | OF NUREG-1022, REVISION 1, DRAFT 2, INDICATES THAT ACTUATION OF SINGLE | | COMPONENTS DUE TO AN INVALID SIGNAL IS NOT REPORTABLE IN ACCORDANCE WITH 10 | | CFR 50.72 AND 10 CFR 50.73. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R3DO (GAVULA). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32554 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 06/27/97 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 17:21 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 06/27/97 | +------------------------------------------------+EVENT TIME: 13:45[EDT]| |NRC NOTIFIED BY: BRIAN WEAVER |LAST UPDATE DATE: 07/25/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |FRANK COSTELLO 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 95 POWER OPERATION | 95 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - DRYWELL H2 AND O2 MONITORS INOPERABLE DUE TO FAULTY RUBBER GASKETS - | | | | AT 1345 ON 06/27/97, THE LICENSEE DECLARED BOTH DIVISION I AND II OF THE | | DRYWELL HYDROGEN AND OXYGEN CONCENTRATION MONITORS INOPERABLE DUE TO A | | COMMON DISCREPANCY IN BOTH DIVISIONS. THE RUBBER MATTING ATTACHED TO | | COVER PLATES IN THE 2CMS*PNL73A AND B CABINETS IS NOT MAKING CONTACT WITH | | ELECTRONIC CARDS IN THE CABINETS WHICH COULD ALLOW THESE CARDS TO BECOME | | LOOSE AND SAG DURING A SEISMIC EVENT. THIS SITUATION HAS THE POTENTIAL TO | | PREVENT THESE MONITORS FROM FULFILLING THEIR DESIGN FUNCTION. | | | | TECH SPEC 3.3.7.5-1, ACTION 80.b, REQUIRES THE LICENSEE TO RESTORE THE | | INOPERABLE CHANNELS TO OPERABLE STATUS WITHIN 7 DAYS OR TO PLACE UNIT 2 | | IN AT LEAST HOT SHUTDOWN CONDITION WITHIN THE NEXT 12 HOURS. | | | | THE LICENSEE IS REPAIRING THE MONITORS. | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | | | | * * * 2207 JULY 25, 1997, UPDATE FROM WEAVER RECEIVED BY TROCINE * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION BECAUSE THE EQUIPMENT | | VENDOR OPERATIONS MANAGER HAS INFORMED THE LICENSEE THAT IT IS NOT A DESIGN | | REQUIREMENT TO HAVE THE BACK PLATES PRESS ON THE MODULES TO HOLD THEM IN | | THE SOCKETS. THESE BACK PLATES ARE INSTALLED ONLY FOR PHYSICAL PROTECTION, | | AND ALL REQUIRED ELECTRONIC CARD SUPPORT FOR EACH MODULE IS PROVIDED BY THE | | SOCKET. THE AIR GAP IS NOT A DESIGN DEFICIENCY ACCORDING TO THE ORIGINAL | | DESIGN AND EQUIPMENT QUALIFICATION. | | | | SINCE THE AIR GAP WAS NOT A DESIGN DEFICIENCY AND THE DIVISION II PANEL HAD | | NO MODULES LOOSE WHEN IT WAS INSPECTED ON THE NIGHT OF THE INCIDENT, THE | | DIVISION II PANEL WOULD HAVE PERFORMED ITS DESIGN FUNCTION. THEREFORE, THE | | DIVISION II PANEL DID NOT NEED TO BE DECLARED INOPERABLE. AS SUCH, THE | | LICENSEE BELIEVES THAT THIS EVENT IS NOT REPORTABLE UNDER 10 CFR 50.72 OR | | 10 CFR 50.73 AND THAT A LICENSEE EVENT REPORT IS NOT REQUIRED. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. THE NRC | | OPERATIONS CENTER NOTIFIED THE R1DO (MEYER). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32669 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 07/24/97 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 10:24 [ET]| |RX TYPE: [1] W-3-LP |EVENT DATE: 07/24/97 | +------------------------------------------------+EVENT TIME: 09:11[EDT]| |NRC NOTIFIED BY: JOE DAVIS |LAST UPDATE DATE: 07/25/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KERRY LANDIS 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 N 0 HOT STANDBY | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF EMERGENCY SIREN CAPABILITY DUE TO ADVERSE WEATHER CONDITIONS | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "AT 0911 [EDT] ON 7/24/97[,] THE LOAD DISPATCHER DETERMINED THAT THERE WAS | | A[N] INSUFFICIENT NUMBER OF EMERGENCY WARNING SIRENS. I WAS MADE AWARE OF | | THE SIREN STATUS AT 1000 [EDT] ON 7/24/97. [THE] CONDITIONS AT THE TIME OF | | THE SIREN LOSS [WERE] HEAVY RAIN IN THE AREA. [THE] BEST ESTIMATE FOR | | RETURN OF [THE] SIRENS [TO SERVICE] WILL BE TODAY, 7/24/97." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * 1211 7/25/97, UPDATE FROM MIKE VERRILLI TAKEN BY MACKINNON * * * | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "THIS IS A FOLLOWUP NOTIFICATION REGARDING THE LOSS OF OFF-SITE EMERGENCY | | NOTIFICATION SIRENS AT HNP ON 7/24/97. FOLLOWING OUR INITIAL NOTIFICATION | | AT 1024 ON 7/24/97 INDICATING A LOSS OF GREATER THAN 20% OF OFF-SITE | | SIRENS, A FINAL TOTAL OF SIRENS WITHOUT ELECTRICAL POWER WAS DETERMINED TO | | BE 22 OF 81. AS OF 1258 ON 7/24/97, POWER HAD BEEN RESTORED TO 10 OF THE | | ORIGINAL 22 SIRENS OUT OF SERVICE. AT THE PRESENT TIME, POWER HAS BEEN | | RESTORED TO ALL 81 SIRENS." THE SIRENS WERE MADE INOPERABLE DUE TO THE | | INCLEMENT WEATHER GENERATED BY TROPICAL STORM DANNY. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND THE STATE AND LOCAL | | OFFICIALS OF THIS EVENT UPDATE. THE NRC OPERATIONS CENTER NOTIFIED THE | | R2DO (LANDIS). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 32674 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: BOWSER MORNER, INC |NOTIFICATION DATE: 07/25/97 | | CITY: TOLEDO REGION: 3 |NOTIFICATION TIME: 09:35 [ET]| | COUNTY: LUCAS STATE: OH |EVENT DATE: 07/25/97 | |LICENSE#: 34-17390-01 AGREEMENT: N |EVENT TIME: 06:30[EDT]| | DOCKET: |LAST UPDATE DATE: 07/25/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JIM GAVULA RDO | | |FRED COMBS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: ROBERT WHITE | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | STOLEN TROXLER MOISTURE DENSITY GAUGE | | | | SOMETIME BETWEEN 1800 EDT ON 7/24/97 AND 0630 EDT ON 7/25/97, A TROXLER | | MOISTURE DENSITY GAUGE (MODEL #3401 S/N 5031) WAS STOLEN FROM THE BACK OF A | | LOCKED PICKUP TRUCK PARKED AT AN EMPLOYEE'S RESIDENCE. THE TRUCK CAP DOOR | | WAS FORCED OPEN, AND THE CHAIN SECURING THE DEVICE WAS CUT. THE GAUGE | | CONTAINED AN 8.9 mCi CESIUM-137/40 mCi AMERICIUM-241 SOURCE (S/N 402073). | | THE LICENSEE NOTIFIED THE TOLEDO POLICE DEPARTMENT AND NRC REGION 3 | | (CAMERON). | | | | (REFER TO THE HOO LOG FOR CONTACT TELEPHONE NUMBERS AND ADDRESSES.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32675 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: YANKEE ROWE REGION: 1 |NOTIFICATION DATE: 07/25/97 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 12:09 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 07/25/97 | +------------------------------------------------+EVENT TIME: 11:30[EDT]| |NRC NOTIFIED BY: RAY JODOIN |LAST UPDATE DATE: 07/25/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GLENN MEYER RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 DECOMMISSIONED | 0 DECOMMISSIONED | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY OF THE POTENTIAL COMPROMISE OF SAFEGUARDS INFORMATION | | | | AT 1130 ON JULY 25, 1997, THE CONTROL ROOM WAS REQUESTED TO MAKE THIS | | ONE-HOUR NOTIFICATION IN ACCORDANCE WITH 10 CFR 73.71, APPENDIX G, | | PARAGRAPH I, SUBPARAGRAPH A. THIS EVENT INVOLVED THE DISCOVERY OF THE | | POTENTIAL COMPROMISE OF SAFEGUARDS INFORMATION AT THE LICENSEE'S CORPORATE | | OFFICE LOCATED IN BOLTON, MASSACHUSETTS, ON JULY 24, 1997. COMPENSATORY | | MEASURES WERE PROPERLY TAKEN UPON DISCOVERY. (REFER TO THE HOO LOG FOR | | ADDITIONAL INFORMATION.) | | | | THE LICENSEE LEFT A MESSAGE FOR THE NRC RESIDENT INSPECTOR AT THE VERMONT | | YANKEE SITE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32676 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: THREE MILE ISLAND REGION: 1 |NOTIFICATION DATE: 07/25/97 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 14:07 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP |EVENT DATE: 07/25/97 | +------------------------------------------------+EVENT TIME: 13:30[EDT]| |NRC NOTIFIED BY: MAX NELSON/C. HARTMAN |LAST UPDATE DATE: 07/25/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GLENN MEYER RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |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 +------------------------------------------------------------------------------+ | DISCOVERY OF A PROBLEM WITH THE CAPABILITY TO TRANSFER EMERGENCY CORE | | COOLING SYSTEM SUCTION FROM THE BORATED WATER STORAGE TANK TO THE REACTOR | | BUILDING SUMP DURING A SPECIFIC ACCIDENT SCENARIO | | | | THE LICENSEE DISCOVERED THIS ISSUE AS A RESULT OF FOLLOWUP ON A RELATED | | EVENT AT CRYSTAL RIVER INVOLVING THE DESIGN OF THE ENGINEERED SAFEGUARDS | | ACTUATION SYSTEM. [REFER TO EN 32659 FOR ADDITIONAL INFORMATION.] SIMILAR | | TO CRYSTAL RIVER, THREE MILE ISLAND UNIT 1 HAS A THREE-CHANNEL SYSTEM. TWO | | OF THE CHANNELS ARE AFFECTED BY THE 'A' TRAIN OF DC, AND THE THIRD CHANNEL | | IS AFFECTED BY THE 'B' TRAIN OF DC. | | | | FOR A SPECIFIC SCENARIO (LOSS OF THE 'A' TRAIN OF DC FOLLOWED BY A LOSS OF | | OFFSITE POWER CONCURRENT WITH A LARGE BREAK LOSS OF COOLANT ACCIDENT), THE | | SAFETY SYSTEM ACTUATION AND CORE COOLING FUNCTION WOULD OCCUR AS EXPECTED. | | HOWEVER, AFTER APPROXIMATELY 40 MINUTES (WHEN IT IS NECESSARY TO TRANSFER | | FROM THE BORATED WATER STORAGE TANK TO THE REACTOR BUILDING SUMP), | | OPERATORS WOULD HAVE TO RESTORE POWER TO AN ELECTRICAL BUS IN ORDER TO BE | | ABLE TO TRANSFER THE VALVES. OPERATORS NORMALLY BYPASS THE ENGINEERED | | SAFEGUARDS SYSTEM IN ORDER TO CONTROL THE VALVES; HOWEVER, THE LOSS OF THE | | 'A' TRAIN OF DC PREVENTS THE BYPASS OF THE 'B' TRAIN. THERE ARE OTHER | | ACTIONS THAT THE OPERATORS COULD TAKE; HOWEVER, THE LICENSEE DOES NOT | | BELIEVE THAT IT IS REASONABLE FOR THE OPERATORS TO DIAGNOSE THIS PROBLEM | | AND TAKE THE APPROPRIATE CORRECTIVE ACTIONS WITHIN THE 40-MINUTE TIME | | FRAME. THE LICENSEE IS IN THE PROCESS OF PROCEDURALIZING THE APPROPRIATE | | ACTIONS. (THERE IS NOT A SIMILAR FAILURE OF THE 'A' TRAIN WHEN THE 'B' | | TRAIN OF DC IS LOST BECAUSE THE 'B' TRAIN AFFECTS ONLY ONE OF THE THREE | | EMERGENCY SAFEGUARDS CHANNELS.) | | | | AS A RESULT OF THIS ISSUE, THE LICENSEE HAS DECLARED THE 'B' TRAIN OF LOW | | PRESSURE INJECTION AND BUILDING SPRAY INOPERABLE BECAUSE THESE SYSTEMS ARE | | AFFECTED BY THE TRANSFER FROM THE BORATED WATER STORAGE TANK TO THE REACTOR | | BUILDING SUMP. THIS PLACES THE UNIT IN A 72-HOUR TECHNICAL SPECIFICATION | | LIMITING CONDITION FOR OPERATION. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 32677 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: U.S. ARMY RESEARCH LABORATORY |NOTIFICATION DATE: 07/25/97 | | CITY: ADELPHI REGION: 1 |NOTIFICATION TIME: 15:58 [ET]| | COUNTY: MONTGOMERY/PG STATE: MD |EVENT DATE: 07/25/97 | |LICENSE#: 19-17250-05 AGREEMENT: Y |EVENT TIME: 07:30[EDT]| | DOCKET: 03012840 |LAST UPDATE DATE: 07/25/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JIM GAVULA (REG 3) RDO | | |JOHN HICKEY/NMSS EO | +------------------------------------------------+RICHARD BARRETT/AEOD IRD | |NRC NOTIFIED BY: DAVID CONRAD |GLENN MEYER (REG 1) RDO | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |MAAD 36.83(a)(4) FAILED CABLE/DRIVE | | |MAAJ 36.83(a)(10) POOL COND HIGH | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY OF THE POTENTIAL FOR FAILURE OF THE CABLE OR DRIVE MECHANISM USED | | TO MOVE THE SOURCE RACKS AND FOR HIGH POOL WATER CONDUCTIVITY DUE TO WATER | | ENTRY INTO THE PNEUMATIC CONTROL SYSTEMS AT AN IRRADIATOR FACILITY | | | | THE LICENSEE DISCOVERED THAT WATER ENTERED THE PNEUMATIC CONTROL SYSTEMS | | FOR THE FACILITY AT THE COMPRESSOR (ANOTHER PART OF THE BUILDING). WATER | | IN THE PNEUMATIC CONTROL SYSTEMS COULD CAUSE THE CONGEALING OF THE | | LUBRICATING OIL THAT WAS ADDED TO AVOID RUST AND LUBRICATE THE SEALS, AND | | CONGEALED OIL IN TURN COULD CAUSE THE FOUR-WAY VALVE IN THE ELEVATOR SYSTEM | | TO STICK MIDWAY. THERE IS NO REDUNDANT VALVE IN THIS SYSTEM. (NEWER | | FACILITIES HAVE A DUAL SYSTEM THAT IS FAIL SAFE.) AS AN EXTRA PRECAUTION | | TO PREVENT FAILURE OF THIS VALVE, THE LICENSEE HAS BEEN REPLACING THIS | | VALVE EVERY SIX MONTHS DURING MAINTENANCE INSPECTIONS. THE FOUR-WAY VALVE | | IN THE ELEVATOR SYSTEM WAS LAST REPLACED ON JULY 8, 1997. | | | | THE POOL WATER LEVEL INDICATOR COULD ALSO BE AFFECTED BY WATER IN THE | | PNEUMATIC CONTROL SYSTEMS. CONGEALED OIL COULD POTENTIALLY CAUSE FLOW | | INDICATORS AND NEEDLE VALVES IN THIS SYSTEM TO STICK, AND THIS IN TURN | | COULD CAUSE THE INDICATOR TO FAIL. IF THIS WERE TO OCCUR, THE SYSTEM WOULD | | GO INTO ALARM AND MIMIC A LOW WATER LEVEL SCENARIO. THE NRC HAS APPROVED | | THE USE OF A MANUAL VALVE ON THIS SYSTEM IN LIEU OF THE AUTOMATIC MODE FOR | | POOL FLOODING; SO POOL FLOODING WOULD NOT BE A PROBLEM. HOWEVER, THE | | CIRCULATING PUMPS WOULD STOP ON INDICATED LOW LEVEL. THIS IN TURN COULD | | ALLOW POOL CONDUCTIVITY TO INCREASE TO A POINT WHERE CORROSION OF THE | | SOURCE PENCILS COULD POTENTIALLY OCCUR. | | | | NOTE: EACH COBALT-60 SOURCE IS DOUBLE ENCAPSULATED IN A STAINLESS STEEL | | PENCIL, AND THERE IS CURRENTLY A TOTAL ACTIVITY OF APPROXIMATELY | | 10,000 CURIES. THERE ARE THREE SOURCE PACKAGES. THE ELEVATOR | | SOURCE PACKAGE IS COMPRISED OF 8 OF THESE PENCILS, AND THIS | | COMPRISES THE MAJORITY OF THE 10,000 CURIES. AS OF JUNE 1, 1996, | | THE 8 ELEVATOR SOURCE PACKAGE PENCILS HAD A TOTAL ACTIVITY OF | | 9,927 CURIES; THE 8 'B' SOURCE PACKAGE PENCILS HAD A TOTAL ACTIVITY | | OF 132 CURIES; AND THE 24 'A' SOURCE PACKAGE PENCILS HAD A TOTAL | | ACTIVITY OF 1,984 CURIES. | | | | NOTE: THIS FACILITY IS A PANORAMIC TYPE IRRADIATOR WITH WET STORAGE AND | | DRY IRRADIATION. THE SOURCES ARE NOT CURRENTLY IN THE ELEVATOR, THE | | ELEVATOR HAS BEEN TAGGED OUT OF SERVICE FOR OTHER REASONS, AND THERE | | IS NO INTENDED FUTURE USE BECAUSE THE FACILITY IS CURRENTLY IN THE | | PROCESS OF ENTERING A DECOMMISSIONING PHASE. | | | | THERE WERE NO PERSONNEL RADIATION EXPOSURE ISSUES OR INJURIES ASSOCIATED | | WITH THIS DISCOVERY. IN ORDER TO PREVENT THESE POTENTIAL SITUATIONS FROM | | RECURRING, THE LICENSEE INSTALLED AN AUTOMATIC DRYER. (REFER TO THE HOO | | LOG FOR SITE CONTACT TELEPHONE NUMBERS AND A STREET ADDRESS.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32678 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 07/25/97 | |UNIT: [1] [2] [ ] STATE: AL |NOTIFICATION TIME: 16:29 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 07/25/97 | +------------------------------------------------+EVENT TIME: 14:44[CDT]| |NRC NOTIFIED BY: JIM HUNTER |LAST UPDATE DATE: 07/25/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KERRY LANDIS RDO | |AESS 50.72(b)(1)(v) EMERGENCY SIREN INOP | | |ANLI 50.72(b)(1)(iii) LIGHTNING | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | PUBLIC PROMPT NOTIFICATION SYSTEM PROBLEM DUE TO A LIGHTNING STRIKE IN | | HOUSTON COUNTY (EMERGENCY SIREN CONTROL PANEL OR REPEATER AT HOUSTON | | COUNTY COURT HOUSE INOPERABLE FOR GREATER THAN 15 MINUTES) | | | | UNDER NORMAL CONDITIONS, THE HOUSTON COUNTY EMERGENCY MANAGEMENT | | ASSOCIATION HAS THE CAPABILITY TO REMOTELY ACTUATE THE TONE ALERT RADIO | | SYSTEM AND THE EMERGENCY SIRENS FOR THREE OF THE LOCAL TOWNS (COLUMBIA, | | ASHFORD, AND GORDON). THESE SYSTEMS CAN TYPICALLY BE ACTUATED FROM THE | | HOUSTON COUNTY COURT HOUSE. HOWEVER, A LIGHTNING STRIKE EARLIER TODAY | | DISABLED THE COUNTY'S CONSOLES/CONTROL PANELS. AS A RESULT, THE COUNTY NO | | LONGER HAS THE CAPABILITY TO REMOTELY ACTUATE THE TONE ALERT RADIO SYSTEM | | AND EMERGENCY SIRENS. IN ADDITION, THE COUNTY'S EMERGENCY NOTIFICATION | | NETWORK IS NO LONGER AVAILABLE. | | | | AT THE TIME OF THIS NOTIFICATION, THE LICENSEE DID HAVE THE CAPABILITY OF | | ACTUATING THE TONE ALERT RADIO FROM THE SITE. THE LICENSEE ALSO BELIEVES | | THAT THE SIREN CONTROL PANEL CAN BE ACTUATED LOCALLY AT EACH EMERGENCY | | SIREN. (THERE ARE A TOTAL OF THREE; ONE FOR EACH TOWN.) THE LICENSEE IS | | CURRENTLY IN THE PROCESS OF VERIFYING THIS CAPABILITY. REPAIR TEAMS ARE IN | | ROUTE. | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR AND PLANS TO NOTIFY | | THE STATE OF ALABAMA VIA THE EMERGENCY NOTIFICATION NETWORK. (COMMERCIAL | | TELEPHONE LINES ARE AVAILABLE IF THE DEDICATED EMERGENCY NOTIFICATION | | NETWORK LINE TO THE STATE DOES NOT WORK.) | | | | * * * 2151 JULY 25, 1997, UPDATE FROM FOREST LERO RECEIVED BY TROCINE * * * | | | | THE SYSTEM WAS RETURNED TO SERVICE AT 2050 CDT. THE LICENSEE IS CURRENTLY | | RELYING ON THE BACKUP SYSTEM (TELEPHONE LINE COMMUNICATIONS FROM THE | | COUNTY) FOR OPERABILITY, AND THE LICENSEE PLANS TO WORK ON THE PRIMARY | | SYSTEM NEXT WEEK. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. THE NRC | | OPERATIONS CENTER NOTIFIED THE RD20 (LANDIS). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32679 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 07/25/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 16:36 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 07/25/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 13:05[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 07/26/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |JIM GAVULA RDO | | DOCKET: 0707001 |JOHN HICKEY/NMSS EO | +------------------------------------------------+RICHARD BARRETT/AEOD IRD | |NRC NOTIFIED BY: W. G. HALICKS | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NCFR NON CFR REPORT REQMNT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION OF A 50-GALLON OIL SPILL IN THE C-537 SWITCHYARD, THE | | DISCOVERY OF OIL IN A PLANT OUTFALL, AND A FISH KILL (4-HOUR REPORT) | | | | AT 1305 CDT ON JULY 25, 1997, AN OIL SPILL OCCURRED FROM A TRANSFORMER | | FILLED WITH OIL CONTAINING 9.8 PPM POLYCHLORINATED BIPHENYLS (PCB). | | ELECTRICIANS WERE REMOVING THE OIL CIRCULATION PUMP WHEN THE LOWER FLAPPER | | VALVE OPERATING ROD HANDLE FAILED. THIS ALLOWED THE VALVE TO OPEN TO THE | | ATMOSPHERE. THE ELECTRICIANS QUICKLY BOLTED THE PUMP BACK INTO POSITION | | AND STOPPED THE LEAK. APPROXIMATELY 50 GALLONS OF OIL SPILLED ONTO THE | | GROUND BENEATH THE TRANSFORMER. THE TRANSFORMER HOLDS 13,000 GALLONS OF | | OIL, AND PADUCAH BELIEVES THAT THE ACTIONS BY THE ELECTRICIANS PREVENTED A | | MUCH LARGER SPILL. | | | | THE REPORTABLE QUANTITY OF OIL FOR THE KENTUCKY DEPARTMENT FOR | | ENVIRONMENTAL PROTECTION (KDEP) IS 25 GALLONS, AND THIS WAS EXCEEDED. AS A | | RESULT, PADUCAH NOTIFIED THE KDEP OF THE SPILL AT 1320 CDT, AND A SPILL | | NUMBER OF B5197 WAS ASSIGNED. (THE REPORTABLE QUANTITY FOR PCBs IS ONE | | POUND. HOWEVER, THE ESTIMATE AMOUNT OF PCBs INVOLVED IN THE SPILL WAS | | 0.004 POUNDS.) | | | | THE PADUCAH EVENT REPORTING CRITERIA REQUIRES NRC NOTIFICATION WITHIN FOUR | | HOURS FOR ANY EVENT OR SITUATION (RELATED TO THE HEALTH AND SAFETY OF THE | | PUBLIC OR ONSITE PERSONNEL OR RELATED TO THE PROTECTION OF THE ENVIRONMENT) | | FOR WHICH A NEWS RELEASE IS PLANNED OR FOR WHICH NOTIFICATION TO OTHER | | GOVERNMENT AGENCIES HAS BEEN MADE. THIS FOUR-HOUR EVENT NOTIFICATION WAS | | MADE BASED UPON THIS CRITERIA. | | | | PADUCAH ALSO NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | * * * 1938 JULY 26, 1997, UPDATE FROM HALICKS RECEIVED BY TROCINE * * * | | | | IT WAS INITIALLY REPORTED THAT APPROXIMATELY 50 GALLONS OF OIL CONTAINING | | 9.8 PPM PCBs LEAKED FROM A TRANSFORMER IN THE C-537 SWITCHYARD DURING | | MAINTENANCE ACTIVITIES. CLEANUP WAS INITIATED, AND IT WAS THOUGHT THAT THE | | OIL SPILL WAS CONTAINED AT THE SITE. TODAY, JULY 26, 1997, OIL WAS | | DISCOVERED IN PLANT OUTFALL #001 LOCATED WEST OF THE PLANT. DEAD FISH WERE | | ALSO FOUND AT THIS LOCATION. THIS OIL IS SIMILAR TO THE TRANSFORMER OIL, | | AND IT IS ASSUMED THAT IT CAME FROM THE SPILL. THE DRAINAGE SYSTEM FROM | | THE C-537 SWITCHYARD FEEDS OUTFALL 001. | | | | AT 1850 CDT, THE KDEP WAS NOTIFIED OF THE DISCOVERY OF THE OIL IN THE | | OUTFALL AND OF THE FISH KILL. THE KDEP HAS REQUESTED THE PLANT TO SAMPLE | | FOR PCBs, OIL, GREASE, AND DISSOLVED OXYGEN. ABSORBENT BOOMS WERE PLACED | | IN THE OUTFALL, AND THE OIL APPEARS TO BE CONTAINED ON THE PLANT SIDE OF AN | | INVERTED PIPE DAM (CONSIDERED TO BE THE PLANT BOUNDARY). ABSORBENT PADS | | AND AN OIL SKIMMER ARE BEING EMPLOYED TO REMOVE THE OIL FROM THE SURFACE OF | | THE WATER. PADUCAH BELIEVES THAT ADDITIONAL CLEANUP AND FURTHER | | COMMUNICATION WITH THE KDEP WILL BE NECESSARY TO CLOSE THIS ISSUE. | | | | PADUCAH NOTIFIED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS CENTER | | NOTIFIED THE R3DO (GAVULA), NMSS EO (HICKEY), AND AEOD IRD (GIITTER). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32680 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 07/26/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 01:35 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 07/25/97 | +------------------------------------------------+EVENT TIME: 23:59[CDT]| |NRC NOTIFIED BY: RAASCH |LAST UPDATE DATE: 07/26/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM GAVULA RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | |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 REFUELING | 0 REFUELING | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ALL EMERGENCY DIESEL GENERATORS ASSOCIATED WITH UNIT 1 HAVE BEEN DECLARED | | INOPERABLE. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "DUE TO THE FAILURE TO MEET THE 18-MONTH SURVEILLANCE REQUIREMENTS FOR | | UNDERVOLTAGE AND SAFE SHUTDOWN TIMERS ON [THE] 1A AND 0 EMERGENCY DIESEL | | GENERATORS PER TECHNICAL SPECIFICATION 4.15.1.B IN COMBINATION WITH [THE] | | 1B EMERGENCY DIESEL GENERATOR (EDG) BEING [OUT OF SERVICE], ALL EDGs | | ASSOCIATED WITH UNIT 1 HAVE BEEN DECLARED INOPERABLE. [THE] 1A EDG | | EXCEEDED ITS CRITICAL DATE FOR SURVEILLANCE TSS 3.8.1.10 AT 2359 [ON] | | 7/24/97, AND [IT] WAS DECLARED INOPERABLE. SUBSEQUENTLY, DURING THE | | PERFORMANCE OF THE TSS, AFTER ONE DIVISION WAS SUCCESSFULLY TESTED, THE | | SECOND DIVISION FAILED DUE TO THE FAILURE OF THE SAFE SHUTDOWN TIMER. AT | | 2359 [ON] 7/25/97, [THE] '0' EDG EXCEEDED ITS CRITICAL DATE FOR | | SURVEILLANCE TSS 3.8.1.10 RENDERING IT INOPERABLE." | | | | "BECAUSE OF UNIT 1 EDGs ALL BEING INOPERABLE, ALL SERVICE WATER PUMPS | | ASSOCIATED WITH UNIT 1 ARE CONSIDERED TO BE INOPERABLE. THIS MAKES THE | | SERVICE WATER SYSTEM INOPERABLE. ZION STATION IS OUTSIDE ITS DESIGN BASIS | | DUE TO POTENTIAL FAILURE TO MEET SINGLE PASSIVE FAILURE CRITERIA WITH EACH | | UNIT'S SERVICE WATER CROSS-TIED, AND ALL SERVICE WATER PUMPS FOR ONE UNIT | | INOPERABLE." | | | | "THIS IN TURN MAKES THE COMPONENT COOLING SYSTEM INOPERABLE AS SERVICE | | WATER IS ITS SUPPORT SYSTEM. [THE UNIT] 2 [RESIDUAL HEAT REMOVAL (RHR)] | | SYSTEM ALSO IS TO BE CONSIDERED INOPERABLE, AS COMPONENT COOLING IS ITS | | SUPPORT SYSTEM." | | | | "WITH THE EXCEPTION OF [THE] 1B EDG, ALL COMPONENTS DISCUSSED ARE | | CONSIDERED TO BE AVAILABLE." | | | | "FOR UNIT 2: | | - [THE] 2A, 2B, AND 0 EDGs ARE OPERABLE. | | - [THE] 2A, 2B, AND 2C SERVICE WATER PUMPS ARE AVAILABLE. | | - [THE] 0A AND 0B COMPONENT COOLING PUMPS ARE AVAILABLE. | | - [THE] 2A AND 2B RHR PUMPS ARE AVAILABLE." | | | | THE LICENSEE PLANS TO TEST THE 0 EDG TIMER ON 7/26/97. | | | | THE LICENSEE ALSO PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32681 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 07/26/97 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 11:00 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 07/26/97 | +------------------------------------------------+EVENT TIME: 09:06[EDT]| |NRC NOTIFIED BY: SANTINI |LAST UPDATE DATE: 07/26/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GLENN MEYER RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION |BRUCE BOGER/NRR EO | |AESF 50.72(b)(2)(ii) ESF ACTUATION |RICHARD BARRETT/AEOD IRD | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | A/R Y 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC REACTOR TRIP FROM 100% POWER DUE TO A TURBINE TRIP | | | | THE TURBINE TRIP OCCURRED WHEN A PROBLEM ON 345-KV TRANSFORMER TA5 CLEARED | | BREAKERS F7, 7, AND 11 ON THE RING BUS. DURING THE TRIP, THE 6.9-KV BUSES | | DID NOT TRANSFER TO OFFSITE POWER. THE CAUSE IS UNKNOWN AND BEING | | INVESTIGATED. AS A CONSEQUENCE, ALL REACTOR COOLANT PUMPS (RCP) TRIPPED, | | AND NATURAL CIRCULATION WAS ESTABLISHED. IN ADDITION, SINCE 480-V BUSES 5A | | AND 6A REMAINED ENERGIZED, THE EMERGENCY DIESEL GENERATORS, WHICH HAD | | AUTOMATICALLY STARTED, DID NOT CLOSE ONTO THE 480-V BUSES SINCE NO BLACKOUT | | SIGNAL WAS PRESENT. AS A RESULT, THE 21 AUXILIARY BOILER FEED PUMP DID NOT | | AUTOMATICALLY START WHEN ALL 4 STEAM GENERATORS WENT OFF SCALE LOW ON THE | | NARROW RANGE SINCE BUS 3A REMAINED DE-ENERGIZED. THE 6.9-KV BUSES WERE | | MANUALLY TRANSFERRED TO OFFSITE POWER WITHIN 3 MINUTES. BUS 3A WAS | | ENERGIZED FROM ITS NORMAL SOURCE (6.9-KV BUS 3), AND THE 21 AUXILIARY | | BOILER FEED PUMP WAS MANUALLY STARTED AT 0913. ALL OTHER AUTOMATIC ACTIONS | | OCCURRED AS REQUIRED. ALL RODS FULLY INSERTED, NO SAFETY INJECTION | | OCCURRED, AND NO PRIMARY OR SECONDARY SAFETY RELIEF VALVES LIFTED. AT | | 0945, THE 24 RCP WAS STARTED, AND THE STEAM GENERATORS ARE THE HEAT SINK | | WITH THE ATMOSPHERIC DUMPS OPENING AT SOME POINT FOLLOWING THE CLOSURE OF | | THE M/S 1's FOR ISOLATION OF THE S/G's FROM THE SECONDARY PLANT. THEY HAVE | | NO HISTORY OF STEAM GENERATOR TUBE LEAKAGE. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32682 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 07/26/97 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 13:33 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 07/26/97 | +------------------------------------------------+EVENT TIME: 10:18[EDT]| |NRC NOTIFIED BY: RON MONACO |LAST UPDATE DATE: 07/26/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GLENN MEYER RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC CLOSURE OF THE DRYWELL CHILLED WATER SYSTEM PRIMARY CONTAINMENT | | ISOLATION VALVES DUE TO A BLOWN FUSE DURING SURVEILLANCE TESTING OF THE D21 | | DIESEL GENERATOR GOVERNOR | | | | THE DRYWELL CHILLED WATER SYSTEM PRIMARY CONTAINMENT ISOLATION VALVES | | AUTOMATICALLY CLOSED WHEN A POWER SUPPLY FUSE TO THE VALVE CLOSING LOGIC | | BLEW. THE PRIMARY CONTAINMENT ISOLATION VALVES ISOLATED ONE OF TWO LOOPS | | OF DRYWELL CHILLED WATER GOING TO CONTAINMENT. COOLING LOADS INSIDE | | CONTAINMENT WERE SWAPPED TO THE PARALLEL LOOP OF DRYWELL CHILLED WATER IN | | ORDER TO MAINTAIN PROPER COOLING. | | | | THE FUSE BLEW DURING THE PERFORMANCE OF A D21 DIESEL GENERATOR GOVERNOR | | TEST. DURING THIS TEST, A HIGHER THAN NORMAL BUS VOLTAGE WAS EXPERIENCED, | | AND THE LICENSEE CURRENTLY BELIEVES THAT THIS WAS THE LIKELY CAUSE OF THE | | FUSE FAILURE. THE LICENSEE'S INVESTIGATION IS ONGOING. THE DRYWELL | | CHILLED WATER ISOLATION VALVES REMAIN CLOSED AT THIS TIME. | | | | ALL SYSTEMS FUNCTIONED AS REQUIRED, AND NOTHING WAS UNUSUAL OR NOT | | UNDERSTOOD. THE UNIT IS NOT CURRENTLY IN A TECHNICAL SPECIFICATION | | LIMITING CONDITION FOR OPERATION AS A RESULT OF THIS EVENT. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32683 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 07/26/97 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 20:25 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 07/26/97 | +------------------------------------------------+EVENT TIME: 18:10[EDT]| |NRC NOTIFIED BY: CHRISTOPHER P. HYNES |LAST UPDATE DATE: 07/26/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GLENN MEYER 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 +------------------------------------------------------------------------------+ | DISCOVERY OF THE POTENTIAL FOR INADVERTENT WATER DELUGE OF THE | | SUPPLEMENTARY LEAK COLLECTION AND RELEASE SYSTEM CHARCOAL FILTERS DUE TO | | SEISMIC MOTION | | | | SECTION 9.10 OF THE BEAVER VALLEY UPDATED FINAL SAFETY ANALYSIS REPORT | | STATES THAT THE FIRE PROTECTION SYSTEM IS DESIGNED ON THE BASIS THAT | | RUPTURE OR INADVERTENT OPERATION WILL NOT SIGNIFICANTLY IMPAIR THE SAFETY | | CAPABILITY OF STRUCTURES, SYSTEMS, OR COMPONENTS IMPORTANT TO SAFETY OR | | DESIGNED TO SEISMIC CATEGORY 1 REQUIREMENTS. | | | | IT HAS BEEN DETERMINED THAT INADVERTENT OPERATION OF THE FIRE PROTECTION | | SYSTEM FOR THE SUPPLEMENTARY LEAK COLLECTION AND RELEASE SYSTEM CHARCOAL | | FILTERS (VS-FL-5 AND 8) DUE TO SEISMIC MOTION COULD ADVERSELY AFFECT THEIR | | ABILITY TO FUNCTION DUE TO WATER DELUGE OF THE CHARCOAL PREVENTING AIR | | PASSAGE. CHATTERING OF CONTROL CIRCUIT CONTACTORS (RELAYS AND HEAT | | ACTUATING DEVICES) THAT LACK SEISMIC QUALIFICATION COULD ACTUATE THE | | SYSTEM. SEISMIC ACTUATION COULD OCCUR SIMULTANEOUSLY FOR BOTH | | SUPPLEMENTARY LEAK COLLECTION AND RELEASE SYSTEM TRAINS. | | | | THE DELUGE SYSTEM FOR EACH CHARCOAL FILTER HAS BEEN ISOLATED TO PREVENT | | INADVERTENT WATER SPRAY OF THE FILTER. THE REMOTE FIRE DETECTION SENSORS | | FOR AN ACTUAL FIRE REMAIN OPERABLE TO PROVIDE ALARM CAPABILITY IN THE | | CONTROL ROOM. THE FIRE PROTECTION PROGRAM REQUIRES A ONCE-PER-HOUR FIRE | | TOUR OF THE FILTER HOUSING AREA, AND THIS FIRE TOUR IS CURRENTLY IN EFFECT. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32684 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 07/27/97 | |UNIT: [ ] [2] [ ] STATE: SC |NOTIFICATION TIME: 00:53 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 07/26/97 | +------------------------------------------------+EVENT TIME: 22:22[EDT]| |NRC NOTIFIED BY: BEAVER |LAST UPDATE DATE: 07/27/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KERRY LANDIS 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 +------------------------------------------------------------------------------+ | THE REACTOR WAS MANUALLY TRIPPED FROM 100% POWER. | | | | THIS MANUAL REACTOR TRIP OCCURRED AFTER MAIN STEAM ISOLATION VALVE "2SM1" | | ON THE "D" STEAM GENERATOR WENT CLOSED. THE CAUSE IS UNKNOWN AND IS BEING | | INVESTIGATED. THE OPERATOR INITIATED THE MANUAL TRIP PRIOR TO RECEIVING AN | | AUTOMATIC TRIP SIGNAL. THE TURBINE TRIPPED DUE TO THE REACTOR TRIP, AND | | THE AUXILIARY FEEDWATER AUTOMATIC START RESULTED FROM THE TRIP OF BOTH MAIN | | FEEDWATER PUMPS. IN ADDITION, FEEDWATER ISOLATION OCCURRED DUE TO THE | | REACTOR TRIP WITH LOW Tave. ALL RODS FULLY INSERTED, AND NO EMERGENCY CORE | | COOLING SYSTEM INJECTIONS OCCURRED. THE SECONDARY SAFETY RELIEF VALVES | | LIFTED ON THE "D" STEAM GENERATOR (NO S/G TUBE LEAK HISTORY), AND THEY | | FULLY RESEATED AFTER A FEW SECONDS. THE HEAT SINK IS THE CONDENSER. ALL | | OTHER SYSTEMS AND PLANT PARAMETERS ARE NORMAL. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 32685 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ST MARYS HOSPITAL |NOTIFICATION DATE: 07/27/97 | | CITY: RICHMOND REGION: 2 |NOTIFICATION TIME: 04:32 [ET]| | COUNTY: STATE: VA |EVENT DATE: 07/27/97 | |LICENSE#: SNM1375 AGREEMENT: N |EVENT TIME: 03:20[EDT]| | DOCKET: |LAST UPDATE DATE: 07/27/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |KERRY LANDIS RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: LINDSEY | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NCAR CARDIAC PACEMAKER | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ST. MARYS HOSPITAL LOCATED IN RICHMOND, VIRGINIA, REPORTED THAT A PATIENT | | WITH A MEDITRONIC PACEMAKER DIED AT THE HENRICO DOCTORS HOSPITAL. | | | | ST. MARYS HOSPITAL REPORTED THAT A PATIENT WITH A MEDITRONIC PACEMAKER | | (MODEL #9000) DIED AT THE HENRICO DOCTORS HOSPITAL. THE PATIENT WILL BE | | TRANSPORTED TO ST. MARYS HOSPITAL FOR REMOVAL OF THE PACEMAKER. THE CAUSE | | OF DEATH IS UNKNOWN, AND IT IS NOT KNOWN IF THERE WAS ANY MALFUNCTION OF | | THE PACEMAKER. THE PACEMAKER WILL BE STORED IN SECURE STORAGE AT THE | | HOSPITAL WHEN IT IS REMOVED FROM THE PATIENT. THE PACEMAKER WILL BE | | REMOVED TODAY AT 0700. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32686 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 07/28/97 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 05:33 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 07/28/97 | +------------------------------------------------+EVENT TIME: 01:39[CDT]| |NRC NOTIFIED BY: GADBOIS |LAST UPDATE DATE: 07/28/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |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 87 POWER OPERATION | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE REACTOR WAS MANUALLY SCRAMMED FROM 87% POWER FOLLOWING A REACTOR FEED | | PUMP TRIP. | | | | THIS OCCURRED WHILE THE REACTOR FEED PUMPS WERE BEING SWAPPED TO TAKE THE | | MINIMUM FLOW VALVE FOR THE "B" REACTOR FEED PUMP OUT OF SERVICE. THE | | MINIMUM FLOW VALVE WAS BEING REMOVED FROM SERVICE BECAUSE IT HAD FAILED | | OPEN ON THE PREVIOUS SHIFT. DURING THE PUMP SWAP, REACTOR LEVEL STARTED TO | | INCREASE AND THE OPERATOR TOOK MANUAL CONTROL OF THE FEED WATER SYSTEM. | | THEN REACTOR WATER LEVEL DECREASED TO THE LOW ALARM SETPOINT (25") AND THE | | "C" REACTOR FEED PUMP TRIPPED. AT THAT POINT, THE OPERATOR WAS DIRECTED TO | | MANUALLY SCRAM THE REACTOR. ALL RODS FULLY INSERTED, NO SAFETY RELIEF | | VALVES LIFTED AND NO ECCS INJECTION OCCURRED. GROUP 2 & 3 ISOLATIONS | | OCCURRED AS EXPECTED. THE REACTOR IS CURRENTLY COOLING DOWN NORMALLY WITH | | THE RWCU SYSTEM AND AUXILIARY STEAM LOADS. THE CAUSE OF REACTOR WATER | | LEVEL FLUCTUATIONS IS UNKNOWN AND BEING INVESTIGATED. | | | | THE RESIDENT INSPECTOR WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32687 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 07/28/97 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 05:42 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 07/28/97 | +------------------------------------------------+EVENT TIME: 03:29[EDT]| |NRC NOTIFIED BY: MCKEE |LAST UPDATE DATE: 07/28/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD CONTAINMENT VENTILATION ISOLATION ON A HIGH RADIATION MONITOR | | ALARM. | | | | DURING FUEL HANDLING ACTIVITIES (CORE RELOAD), THE CONTAINMENT VENTILATION | | SYSTEM ACTUATED RESULTING IN A CONTAINMENT VENTILATION ISOLATION. THE | | INITIATING SIGNAL WAS A HIGH RADIATION ALARM SPIKE ON THE "R-14" PLANT | | VENTILATION RADIOGAS MONITOR. THIS WAS CAUSED BY DIRECT "RADIATION SHINE" | | FROM A NEUTRON SOURCE IN THE FUEL ASSEMBLY BEING MOVED. THE ISOLATION WAS | | RESET WITHIN 17 MINUTES. | | | | THE RESIDENT INSPECTOR WILL BE NOTIFIED. | +------------------------------------------------------------------------------+