U.S. Nuclear Regulatory Commission Operations Center Event Reports For 07/24/97 - 07/25/97 ** EVENT NUMBERS ** 32167 32558 32577 32669 32670 32671 32672 32673 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!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 WILL 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 0302EDT ON 7/25/97 FROM STEVE VERCELLI TO S.SANDIN * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT BASED ON THE FOLLOWING: | | | | "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 TIME." | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. NOTIFIED | | R3DO(GAVULA). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32558 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 06/28/97 | |UNIT: [ ] [ ] [3] STATE: AZ |NOTIFICATION TIME: 18:29 [ET]| |RX TYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 06/28/97 | +------------------------------------------------+EVENT TIME: 14:27[MST]| |NRC NOTIFIED BY: LARRY ESAU |LAST UPDATE DATE: 07/24/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SANBORN RDO | |AFIR 50.72(b)(1)(vi) FIRE (ONSITE) | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - ONSITE TRASH DUMPSTER FIRE INSIDE PLANT PROTECTED AREA - LASTED 6 MINUTES | | | | AT 1427 MST, A FIRE OCCURRED IN A TRASH DUMPSTER LOCATED OUTSIDE AN | | ADMINISTRATIVE BUILDING INSIDE THE PLANT PROTECTED AREA. THE ONSITE | | FIRE BRIGADE EXTINGUISHED THE FIRE WITHIN 6 MINUTES. THE OFFSITE FIRE | | DEPARTMENT WAS NOT NOTIFIED. THERE WERE NO PERSONNEL INJURIES, AND NO | | EQUIPMENT WAS DAMAGED. THE ORIGIN OF THE FIRE IS UNKNOWN AND IS BEING | | INVESTIGATED. | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | | | | * * * 1412 JULY 24, 1997, UPDATE FROM STROUD RECEIVED BY GOULD * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION BASED UPON SUBSEQUENT | | INVESTIGATION WHICH REVEALED THAT THE FIRE WAS MOST LIKELY THE RESULT OF | | EITHER CARELESSNESS IN THE DISPOSAL OF SMOKING MATERIALS OR THE SPONTANEOUS | | COMBUSTION OF ORGANIC MATERIAL CONTAINED WITHIN THE TRASH DUMPSTER. THE | | INITIAL NOTIFICATION WAS BASED UPON LIMITED INFORMATION AVAILABLE AT THE | | TIME OF THE EVENT. SUBSEQUENT INVESTIGATION OF THE EVENT REVEALED THAT | | THERE WAS NO EVIDENCE TO SUGGEST THAT THE FIRE WAS OF A SUSPICIOUS NATURE, | | AND THERE WAS NO SIGNIFICANT DAMAGE TO THE FACILITY AS A RESULT OF THE | | FIRE. THE FIRE DID NOT THREATEN THE POWER PLANT, AND PLANT PERSONNEL WERE | | NOT SIGNIFICANTLY HAMPERED IN THE PERFORMANCE OF DUTIES NECESSARY FOR THE | | OPERATION OF THE FACILITY. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. THE NRC | | OPERATIONS CENTER NOTIFIED THE R4DO (MURRAY) | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32577 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 07/02/97 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 14:29 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 07/02/97 | +------------------------------------------------+EVENT TIME: 13:00[EDT]| |NRC NOTIFIED BY: FREGEAU |LAST UPDATE DATE: 07/24/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |SHANBAKY 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 +------------------------------------------------------------------------------+ | THE HIGH PRESSURE CORE SPRAY (HPCS) SYSTEM WAS DECLARED INOPERABLE. | | | | DURING SURVEILLANCE TESTING, THE HPCS SUCTION CHECK VALVE FROM THE | | SUPPRESSION POOL FAILED THE REVERSE FLOW PORTION OF THE TEST. HPCS WAS | | DECLARED INOPERABLE BY THE LICENSEE. HPCS IS A SINGLE-TRAIN EMERGENCY CORE | | COOLING SYSTEM. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | | | | * * * 1523 JULY 24, 1997, UPDATE FROM GREEN RECEIVED BY TROCINE * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION BASED UPON THE RESULTS | | OF AN APPLICABILITY REVIEW OF THE REVERSE FLOW FAILURE OF THE SUCTION CHECK | | VALVE. THE LICENSEE'S REVIEW DETERMINED THAT THE CHECK VALVE SERVES NO | | SAFETY-RELATED FUNCTION IN THE REVERSE FLOW DIRECTION, AND TESTING OF THE | | REVERSE FLOW FUNCTION OF THIS VALVE HAS BEEN REMOVED FROM THE LICENSEE'S | | IN-SERVICE INSPECTION PROGRAM. IN ADDITION, THE LICENSEE DOES NOT BELIEVE | | THAT IT WAS NECESSARY TO DECLARE HPCS INOPERABLE WHEN THE VALVE FAILED THE | | REVERSE FLOW PORTION OF THE SURVEILLANCE TEST. | | | | 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: 07/24/97 | |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. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32670 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 07/24/97 | |UNIT: [1] [2] [ ] STATE: NC |NOTIFICATION TIME: 17:52 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 07/24/97 | +------------------------------------------------+EVENT TIME: 15:23[EDT]| |NRC NOTIFIED BY: HAL WALL |LAST UPDATE DATE: 07/24/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KERRY LANDIS RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ACTUATION OF THE CONTROL BUILDING EMERGENCY AIR FILTRATION (CBEAF) SYSTEM | | DUE TO A FLANGE LEAK ON THE #2 CHLORINATOR FOLLOWING MAINTENANCE | | | | AT 1523, THE CBEAF SYSTEM ACTUATED WHILE THE LICENSEE WAS PLACING THE | | CHLORINATION SYSTEM IN SERVICE FOLLOWING MAINTENANCE. THE SYSTEM ALIGNED | | TO THE CHLORINATION PROTECTION MODE AND FUNCTIONED AS DESIGNED. THE | | INITIATING EVENT WAS DETERMINED TO BE A FLANGE LEAK ON THE #2 CHLORINATOR. | | | | WHEN THE CBEAF SYSTEM ALIGNED TO THE CHLORINE PROTECTION MODE, THE CBEAF | | HIGH RADIATION AND SMOKE/FIRE PROTECTION MODES BECOME INOPERABLE. WITH | | BOTH OF THESE MODES OF OPERATION INOPERABLE, THE UNITS ENTERED A 12-HOUR | | LIMITING CONDITION FOR OPERATION. THIS LIMITING CONDITION FOR OPERATION | | WAS EXITED AT 1542 WHEN THE CBEAF SYSTEM WAS RESTORED TO ITS NORMAL LINEUP. | | THE UNITS ALSO ENTERED ABNORMAL OPERATING PROCEDURE AOP-34, CHLORINE | | EMERGENCIES, AND PERSONNEL WERE EVACUATED FROM THE AFFECTED AREAS. THE | | CHLORINE TANK CAR WAS ISOLATED, AND SURVEYS WERE PERFORMED. SURVEYS | | PERFORMED AT 1531 SHOWED CHLORINE CONCENTRATION LEVELS AT ZERO. ABNORMAL | | OPERATING PROCEDURE AOP-34 WAS EXITED AT 1548. IN ADDITION, CONTROL | | BUILDING VENTILATION HAS BEEN RESTORED TO THE NORMAL LINEUP. THE LICENSEE | | PLANS TO REPAIR THE #2 CHLORINATOR UNDER WORK REQUEST/JOB ORDER 97-AEMX1. | | THE LICENSEE ALSO PLANS TO PERFORM ADDITIONAL INVESTIGATION AND RESOLUTION | | IN ACCORDANCE WITH THE PLANT CORRECTIVE ACTION PROGRAM. | | | | THE LICENSEE DETERMINED THE SAFETY SIGNIFICANCE OF THIS EVENT TO BE MINIMAL | | BECAUSE THE CBEAF SYSTEM FUNCTIONED AS DESIGNED. THERE WERE NO PERSONNEL | | INJURIES ASSOCIATED WITH THIS EVENT. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32671 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 07/24/97 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 20:01 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 07/24/97 | +------------------------------------------------+EVENT TIME: 17:00[EDT]| |NRC NOTIFIED BY: MELISA STREIBER |LAST UPDATE DATE: 07/24/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GLENN MEYER RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 89 POWER OPERATION | 89 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION OF A ONE-OUNCE OIL SPILL LOCATED NEAR A STORM DRAIN ON | | A ROADWAY OUTSIDE THE PROTECTED AREA | | | | THE LICENSEE NOTIFIED THE NEW YORK DEPARTMENT OF ENVIRONMENTAL CONTROL AND | | THE WESTCHESTER DEPARTMENT OF HEALTH OF A ONE-OUNCE OIL SPILL THAT REACHED | | A STORM DRAIN LOCATED OUTSIDE THE PROTECTED AREA. THE LICENSEE DOES NOT | | BELIEVE THAT THE OIL REACHED ANY WATERWAYS. | | | | IT HAS BEEN RAINING AT THE SITE, AND AN OIL SHEEN WAS NOTICED NEAR A STORM | | DRAIN. THE LICENSEE SUBSEQUENTLY SENT INDIVIDUALS TO THE LOCATION OF THE | | SHEEN IN ORDER TO IDENTIFY THE SOURCE OF THE OIL AND TO CLEAN UP THE OIL. | | AT THIS TIME, THE LICENSEE DOES NOT KNOW WHERE THE OIL CAME FROM. THE | | SHEEN WAS LOCATED IN THE ROADWAY OUTSIDE THE PROTECTED AREA, AND IT IS | | CURRENTLY BELIEVED TO HAVE COME FROM A VEHICLE. AT THE TIME OF THIS | | NOTIFICATION, THE OIL HAD BEEN CLEANED UP. | | | | THE EVENT OCCURRED AT 1700. THE CONTROL ROOM WAS NOTIFIED OF THE OIL SPILL | | AT 1800, AND THE CONTROL ROOM WAS NOTIFIED OF THE OFFSITE NOTIFICATIONS AT | | 1901. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32672 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 07/24/97 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 20:04 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 07/24/97 | +------------------------------------------------+EVENT TIME: 19:15[EDT]| |NRC NOTIFIED BY: CHRISTOPHER HYNES |LAST UPDATE DATE: 07/24/97 | |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 THAT UNIT 1 DIESEL GENERATOR BUILDING CO2 DISCHARGE PRESSURE | | SWITCHES DO NOT MEET THE REQUIRED QUALITY LEVEL CATEGORIZATION FOR THEIR | | INSTALLATION | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "ON JULY 24, 1997, IT WAS DISCOVERED THAT UNIT 1 DIESEL GENERATOR BUILDING | | CO2 DISCHARGE PRESSURE SWITCHES DO NOT MEET THE REQUIRED QUALITY LEVEL | | CATEGORIZATION FOR THEIR INSTALLATION. IF THESE SWITCHE[S] WERE TO FAIL | | OPEN, THE DIESEL GENERATOR BUILDING VENTILATION WOULD BE SHUT DOWN. THIS | | WOULD NOT PREVENT THE DIESEL GENERATOR(S) FROM STARTING, BUT WITHOUT | | VENTILATION, THE DIESEL GENERATOR ROOM WOULD CONTINUE TO HEAT UP AND | | DEGRADE DIESEL GENERATOR(S) PERFORMANCE UNTIL THE DIESEL GENERATOR(S) WOULD | | NO LONGER BE ABLE TO PERFORM THEIR INTENDED FUNCTION." | | | | "UNIT 1 DIESEL GENERATOR BUILDING CO2 DISCHARGE PRESSURE SWITCHES | | PS-FP-CDL1A AND PS-FP-CDL1B ARE QA CATEGORY F AND WERE PURCHASED AS PART OF | | THE FIRE PROTECTION SYSTEM. THEY ARE CONNECTED IN THE CONTROL CIRCUIT FOR | | DIESEL GENERATOR BUILDING EXHAUST FANS VS-F-22A AND -22B, WHICH ARE SAFETY | | RELATED. THE SWITCHES ARE NORMALLY CLOSED AND OPEN ON DISCHARGE OF THE CO2 | | FIRE PROTECTION SYSTEM TO SHUT DOWN THE VENTILATION FANS AND CLOSE THE | | OUTSIDE AIR DAMPERS. SPURIOUS OPENING OF THE SWITCHES WOULD SHUTOFF THE | | VENTILATION." | | | | "THE PRESSURE SWITCHES WERE EVALUATED UNDER SQUG [A SAFETY QUALITY GROUP] | | AND WERE DETERMINED TO BE 'CHATTER ACCEPTABLE,' THAT IS, IF THE SWITCH | | CONTACTS WOULD MOMENTARILY CHATTER DUE TO SEISMIC VIBRATION, IT WOULD NOT | | ADVERSELY AFFECT SAFE SHUTDOWN. HOWEVER, THERE IS STILL A PROBLEM WITH THE | | USE OF QA CATEGORY F EQUIPMENT IN A CATEGORY 1 CIRCUIT. THE SWITCHES | | PERFORMED THE SAFETY-RELATED FUNCTION OF MAINTAINING CIRCUIT CONTINUITY FOR | | OPERATION OF THE FANS AND DAMPERS, THEREFORE[, THEY] SHOULD BE CATEGORY 1." | | | | "THE ROOT CAUSE FOR THIS CONDITION IS UNKNOWN AT THIS TIME. A CONDITION | | REPORT HAS BEEN WRITTEN TO DOCUMENT THIS CONDITION [AND TO] DETERMINE THE | | ROOT CAUSE AND CORRECTIVE ACTIONS. CURRENTLY, THE CO2 SYSTEM FOR THE UNIT | | 1 DIESEL GENERATORS IS ISOLATED FOR A SEPARATE CONCERN, AND COMPENSATORY | | ACTIONS ARE IN PLACE FOR THE DISABLED FIRE PROTECTION SYSTEM." | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | HOO NOTE: SEE RELATED EVENT #32592 | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32673 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 07/24/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 20:35 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 07/24/97 | +------------------------------------------------+EVENT TIME: 17:09[CDT]| |NRC NOTIFIED BY: CURTIS BASNER |LAST UPDATE DATE: 07/24/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM GAVULA RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ENGINEERED SAFETY FEATURE ACTUATIONS DUE TO PERSONNEL ERROR DURING THE | | PERFORMANCE OF AN EMERGENCY DIESEL GENERATOR (EDG) SURVEILLANCE | | | | DURING THE PERFORMANCE OF A TECHNICAL SPECIFICATION SURVEILLANCE TEST ON | | THE '1A' EDG TO VERIFY OPERABILITY OF THE EDG DURING STATION BLACKOUT | | CONDITIONS, A TEST SWITCH WAS CLOSED OUT OF SEQUENCE (PRIOR TO THE BUS | | BEING DE-ENERGIZED). AS A RESULT, VARIOUS EQUIPMENT ACTUATED INCLUDING ALL | | FIVE REACTOR CONTAINMENT FAN COOLERS AND TWO SERVICE WATER ISOLATION VALVES | | TO THE TURBINE BUILDING. ALL OF THE EQUIPMENT THAT ACTUATED DURING THIS | | EVENT WOULD HAVE ACTUATED AT ANOTHER TIME DURING THE PERFORMANCE OF THE | | SURVEILLANCE TEST; HOWEVER, THE EQUIPMENT ACTUATED OUT OF SEQUENCE. THE | | LICENSEE HAS ATTRIBUTED THIS EVENT TO POTENTIAL PERSONNEL ERROR DUE TO | | INADEQUATE COMMUNICATIONS. | | | | AT THIS TIME, THE '1A' EDG IS CONSIDERED TO BE OPERABLE. HOWEVER, IT WILL | | BECOME INOPERABLE (BUT STILL AVAILABLE) AT 2359 CDT TODAY BECAUSE THE | | REFERENCED SURVEILLANCE WAS NOT PERFORMED SATISFACTORILY. THE LICENSEE | | CURRENTLY PLANS TO RECOMMENCE THIS SURVEILLANCE TEST TOMORROW MORNING. THE | | '1B' EDG IS CURRENTLY OUT OF SERVICE FOR MAINTENANCE, AND THE COMMON '0' | | EDG IS OPERABLE. THE UNIT IS DEFUELED. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+