U.S. Nuclear Regulatory Commission Operations Center Event Reports For 09/08/97 - 09/09/97 ** EVENT NUMBERS ** 32879 32884 32885 32886 32887 32888 32889 32890 32891 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32879 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 09/05/97 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 19:33 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 09/05/97 | +------------------------------------------------+EVENT TIME: 17:24[EDT]| |NRC NOTIFIED BY: TOBY TORBITT |LAST UPDATE DATE: 09/08/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE DOERFLEIN 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | RADWASTE BUILDING VENTILATION ISOLATION | | | | WHILE PERFORMING A CALIBRATION OF THE 'B' RADWASTE BUILDING VENTILATION | | RADIATION MONITOR (17RM-458B), THE RADWASTE BUILDING VENTILATION SYSTEM | | ISOLATED. THE RADIATION MONITOR HAD NOT BEEN PROPERLY REMOVED FROM SERVICE, | | AND THE ISOLATION OCCURRED WHEN THE CHECK SOURCE WAS INSERTED INTO THE | | DETECTOR. THE LICENSEE COMPLETED THE TEST PROCEDURE AND HAS RESET THE | | VENTILATION ISOLATION. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | | | | * * * UPDATE 1058 9/8/97 FROM ZAREMBA TAKEN BY STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS NOTIFICATION. AFTER REVIEWING THE | | CIRCUMSTANCES OF THIS EVENT, THE LICENSEE HAS DETERMINED THAT IT DOES NOT | | MEET THE REQUIREMENTS FOR REPORTABILITY. THE NRC RESIDENT INSPECTOR HAS | | BEEN INFORMED BY THE LICENSEE. NOTIFIED R1DO (DOERFLEIN). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32884 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 09/08/97 | |UNIT: [ ] [2] [ ] STATE: AZ |NOTIFICATION TIME: 02:21 [ET]| |RX TYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 09/07/97 | +------------------------------------------------+EVENT TIME: 19:23[MST]| |NRC NOTIFIED BY: DAN MARKS |LAST UPDATE DATE: 09/08/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GENE BATES 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INADVERTENT ENGINEERED SAFETY FEATURE (ESF) ACTUATION DUE TO AN INCORRECTLY | | PERFORMED STEP DURING THE PERFORMANCE OF SURVEILLANCE TESTING | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "[AN] INADVERTENT ESF ACTUATION RESULTED FROM AN INCORRECTLY PERFORMED STEP | | DURING THE PERFORMANCE OF [AN] INTEGRATED SAFEGUARDS SURVEILLANCE TEST ON | | THE 'B' SAFETY EQUIPMENT." | | | | "THE SUB-SECTION OF THE TEST BEING PERFORMED IS A LOSS OF POWER (LOP) TO | | TRAIN 'B' INITIATED BY OPENING THE NORMAL SUPPLY BREAKER TO E-NBN-X04. THE | | INTENT IS TO DEMONSTRATE PROPER RESPONSE OF THE ESF EQUIPMENT. THE | | [EMERGENCY DIESEL GENERATOR (EDG)] IS INITIALLY PLACED IN AN 'OVERRIDE' | | CONDITION PRIOR TO THE 'LOP' INITIATION TO DEMONSTRATE THAT UPON THE | | RESULTING 'LOAD SHED' SIGNAL, THE EDG WILL BE REMOVED FROM 'OVERRIDE' AND | | WILL START IN THE 'EMERGENCY' MODE. ONE OF THE PRE-TEST CONDITIONS IS TO | | PLACE THE CLASS BUS ALTERNATE SUPPLY BREAKER IN THE 'TEST' POSITION AND | | CLOSED LOCALLY. DUE TO AN INCORRECTLY PERFORMED STEP, THE ALTERNATE SUPPLY | | BREAKER WAS CLOSED FROM THE CONTROL ROOM. THE SYNCHRONIZING SWITCH | | INTERLOCK LOGIC AUTOMATICALLY OPENED THE NORMAL SUPPLY BREAKER RESULTING IN | | A 'LOP' ON THE CLASS BUS. THE DIESEL GENERATOR STARTED AND RESTORED BUS | | VOLTAGE. ALL EQUIPMENT OPERATED AS REQUIRED. THERE WERE NO OTHER | | ACTUATIONS, AND NONE WERE REQUIRED." | | | | "THE EVENT DID NOT RESULT IN ANY CHALLENGES TO THE FISSION PRODUCT BARRIER | | OR RESULT IN ANY RELEASES OF RADIOACTIVE MATERIALS. THERE WERE NO ADVERSE | | CONSEQUENCES OR IMPLICATIONS AS A RESULT OF THIS EVENT. THIS EVENT DID NOT | | ADVERSELY AFFECT THE SAFE OPERATION OF THE PLANT OR HEALTH AND SAFETY OF | | THE PUBLIC." | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 32885 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ILLINOIS POWER |NOTIFICATION DATE: 09/08/97 | | CITY: HAVANA REGION: 3 |NOTIFICATION TIME: 08:17 [ET]| | COUNTY: STATE: IL |EVENT DATE: 09/08/97 | |LICENSE#: IL-01523-01 AGREEMENT: Y |EVENT TIME: 00:00[CDT]| | DOCKET: |LAST UPDATE DATE: 09/08/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |MARK RING RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: BRUCE SANZA (STATE OF IL) | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE ILLINOIS DEPARTMENT OF NUCLEAR SAFETY REPORTED THAT A COAL FIRE DAMAGED | | A FIXED NUCLEAR GAUGE AT ILLINOIS POWER'S HAVANA STATION. | | | | THE FOLLOWING TEXT IS A PORTION OF AN ELECTRONICALLY MAILED MEMORANDUM FROM | | THE ILLINOIS DEPARTMENT OF NUCLEAR SAFETY REGARDING A REPORTABLE INCIDENT: | | | | NOTE: THE EVENT DATE AND TIME ARE UNKNOWN. | | | | "CALLER [JOE KOCH, R. M. WESTER & ASSOCIATES] ARRANGED FOR A FOUR-WAY CALL | | REGARDING A COAL FIRE THAT DAMAGED A FIXED NUCLEAR GAUGE AT [ILLINOIS | | POWER]'S HAVANA STATION. OTHERS ON THE LINE WERE: FRANK ROSENBERGER, | | HAVANA PLANT [RADIATION SAFETY OFFICER (RSO)]; AND TED LINDENBUSH, | | CORPORATE RSO. THE CALL WAS MADE TO NOTIFY THE DEPARTMENT THAT THE CONTENTS | | OF A COAL SILO UNDERWENT SPONTANEOUS COMBUSTION AND CAUSED THE LEAD | | SHIELDING IN A TN-5219 GAUGE (CONTAINING 50 mCi OF [CESIUM]-137) TO MELT." | | | | "MR. ROSENBERGER REPORTED SURFACE DOSE RATES ON THE GAUGE SOURCE HOLDER OF | | 600 TO 700 MREM/HR AND READINGS AT 1.5 FEET TO BE 5 MREM/HR. THE FIRE WAS | | EXTINGUISHED, AND THE AREA AROUND THE GAUGE HAS BEEN ROPED OFF, BUT SOME | | MOLTEN LEAD WAS OBSERVED. R. M. WESTER & ASSOCIATES WAS TO BE CONTACTING | | TN TECHNOLOGIES IN ROUND ROCK, TEXAS, TO ARRANGE FOR A REPLACEMENT DEVICE | | TO BE SENT OVER THE WEEKEND." | | | | "AFTER BEING INFORMED BY MR. LINDENBUSH THAT THE DEVICE WAS UNDER [ILLINOIS | | POWER]'S SPECIFIC LICENSE, [BRUCE SANZA] INFORMED THE PARTIES IN THE CALL | | THAT THIS EVENT WOULD FALL UNDER SECTION 340.1220(c)(4) SINCE THE FIRE | | DAMAGE AFFECTED THE INTEGRITY OF THE SOURCE HOLDER. [BRUCE SANZA] ALSO | | REMINDED THEM THAT A 30-DAY REPORT IS REQUIRED UNDER SECTION 340.1230 AS | | WELL. MR. KOCH AGREED TO ASSIST [ILLINOIS POWER] WITH THE REPORT IF THEY | | REQUESTED. ROOT CAUSE AND CORRECTIVE ACTION, IF ANY, WILL BE ADDRESSED IN | | THE WRITTEN REPORT." | | | | (REFER TO THE HOO LOG FOR CONTACT TELEPHONE NUMBERS.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32886 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 09/08/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 11:38 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 09/08/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 00:10[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 09/08/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |MARK RING RDO | | DOCKET: 0707002 |FRED COMBS, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: HALCOMB | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NCFR NON CFR REPORT REQMNT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOCLAVE STEAM SUPPLY ISOLATION DUE TO HIGH CONDENSATE ALARM | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE CERTIFICATE HOLDER: | | "ON 9/8/97 AT 0010 HOURS, OPERATIONS PERSONNEL RECEIVED A STEAM SHUTDOWN | | ALARM ON AUTOCLAVE #3 IN THE X-343 FACILITY. THE STEAM SHUTDOWN WAS CAUSED | | BY AN ACTUATION OF THE HIGH CONDENSATE ALARM (BOTH 'A' AND 'B' PROBES). | | INVESTIGATION OF THE ALARMS REVEALED THAT THE AUTOCLAVE #3 HIGH CONDENSATE | | ALARM WAS CAUSED BY AN ACTUAL HIGH CONDENSATE CONDITION. THE AUTOCLAVE | | CONDENSATE IS A 'Q' SAFETY SYSTEM IN THE X-343 FACILITY. THE ACTUATION OF | | THE AUTOCLAVE HIGH CONDENSATE SYSTEM ALARM OCCURRED WHILE THE AUTOCLAVE WAS | | IN OPERATIONAL MODE II (HEATING). THIS EVENT IS REPORTABLE TO THE NRC PER | | EVENT REPORTING PROCEDURE UE2-RA-RE1030, APPENDIX D, SECTION J, PARAGRAPH | | #2 (24 HOUR REPORT). THE X-343 AUTOCLAVE #3 WAS IMMEDIATELY SHUT DOWN AND | | DECLARED INOPERABLE BY THE PLANT SHIFT SUPERINTENDENT. THERE WAS NO RELEASE | | OF HAZARDOUS MATERIALS OR RADIOACTIVE CONTAMINATION EXPOSURES ASSOCIATED | | WITH THIS 'Q' SYSTEM ALARM ACTUATION. THE NRC RESIDENT INSPECTOR HAS BEEN | | NOTIFIED OF THIS EVENT." | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 32887 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: U OF WI-MADISON RAD THERAPY CLINIC |NOTIFICATION DATE: 09/08/97 | | CITY: MADISON REGION: 3 |NOTIFICATION TIME: 14:32 [ET]| | COUNTY: STATE: WI |EVENT DATE: 09/08/97 | |LICENSE#: 48-0984318 AGREEMENT: N |EVENT TIME: 08:30[CDT]| | DOCKET: |LAST UPDATE DATE: 09/08/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |MARK RING RDO | | |JOSE PICCONE, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: RON BRESELL | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |LADM 35.33(a) MED MISADMINISTRATION | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - MEDICAL MISADMINISTRATION - RADIATION OVERDOSE TO CANCER PATIENT - | | | | A FEMALE PATIENT WAS GIVEN FIVE PLANNED RADIATION TREATMENTS FOR CERVICAL | | CANCER AT THE UNIVERSITY OF WISCONSIN - MADISON RADIATION THERAPY CLINIC. A | | 10 Ci Ir-192 SOURCE WAS PASSED THROUGH A CATHETER AT A PRESCRIBED RATE OF | | TRAVEL. THE FIRST THREE PRESCRIBED DOSES WERE 6 GRAYS EACH AND THE | | LAST TWO PRESCRIBED DOSES WERE 4.5 GRAYS EACH. HOWEVER, THE FIFTH DOSE | | GIVEN TO THE PATIENT WAS 6 GRAYS INSTEAD OF THE PRESCRIBED 4.5 GRAYS. | | THIS REPRESENTS A 33% FRACTIONATED MEDICAL OVERDOSE (5.5% TOTAL MEDICAL | | OVERDOSE) CAUSED BY PERSONNEL ERROR. THIS MEDICAL OVERDOSE HAS NO ADVERSE | | MEDICAL EFFECTS ON THE PATIENT. FUTURE TREATMENTS WILL BE ADJUSTED | | ACCORDINGLY. THE PATIENT WAS NOTIFIED AND THE PATIENT'S REFERRING | | PHYSICIAN WILL ALSO BE NOTIFIED OF THE OVERDOSE. | | | | CLINIC PERSONNEL ARE INVESTIGATING THE SITUATION, PLAN TO NOTIFY NRC REGION | | 3, AND SUBMIT A WRITTEN REPORT TO NRC REGION 3 WITHIN 15 DAYS. | | | | REFER TO THE HOO LOG FOR CALL BACK TELEPHONE NUMBERS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32888 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 09/08/97 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 16:32 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 09/08/97 | +------------------------------------------------+EVENT TIME: 15:25[EDT]| |NRC NOTIFIED BY: ARCHIE FAULKNER |LAST UPDATE DATE: 09/08/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN ROGGE 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 Y 76 POWER OPERATION | 76 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -HOPE CREEK & SALEM EMERGENCY OFFSITE SIRENS AUTO ACTIVATED FOR 3 MINUTES- | | | | AT 1525 ON 09/08/97, THE EMERGENCY OFFSITE SIRENS IN SALEM COUNTY | | INADVERTENTLY ACTUATED AND SOUNDED FOR APPROXIMATELY 3 MINUTES AND THEN | | RETURNED TO NORMAL STANDBY MODE. THE REASON FOR THE ACTUATION IS UNKNOWN | | AT THIS TIME AND IS BEING INVESTIGATED. | | | | SALEM COUNTY EMERGENCY MANAGEMENT PERSONNEL NOTIFIED NEW JERSEY STATE | | POLICE WHO ISSUED A PRESS RELEASE NOTIFYING THE NEWS MEDIA OF THE FALSE | | ACTIVATION. | | | | THIS EVENT APPLIES TO BOTH HOPE CREEK AND SALEM GENERATING STATIONS. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND WILL NOTIFY LOCAL | | OFFICIALS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32889 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 09/08/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 16:38 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/08/97 | +------------------------------------------------+EVENT TIME: 14:00[CDT]| |NRC NOTIFIED BY: GLENN KAHT |LAST UPDATE DATE: 09/08/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK RING RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | |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 REFUELING | 0 REFUELING | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - S/G PRESSURE TRANSMITTERS INOPERABLE DUE TO INADEQUATE CABLE ROUTING - | | | | ON 04/23/97, THE LICENSEE REPORTED TO THE NRC THAT UNIT 1 AND 2 STEAM | | GENERATOR (S/G) PRESSURE TRANSMITTERS WOULD NOT OPERATE PROPERLY DURING A | | STEAM LINE BREAK OUTSIDE OF CONTAINMENT DUE TO LOW INSTRUMENTATION CABLE | | INSULATION RESISTANCE CAUSED BY ELEVATED TEMPERATURES IN THE VALVE ROOMS | | AND STEAM TUNNELS (SEE RELATED EVENT REPORT #32205). | | | | AT 1040 (CDT) ON 09/08/97, DURING A REVIEW OF SAFETY EVALUATION #97-472 | | (FOR EXEMPT CHANGE #F22-2-97-251B) AND UFSAR, APPENDIX 3A, "ANALYSIS OF THE | | EFFECTS OF A MAIN STEAM OR FEEDWATER PIPE BREAK OUTSIDE THE CONTAINMENT," | | THE LICENSEE IDENTIFIED AN APPARENT DISCREPANCY BETWEEN THE ASSUMPTIONS | | MADE IN THE UFSAR ANALYSIS AND THE AS-BUILT PLANT CONDITIONS. | | | | THE UFSAR ANALYSIS STATES, IN PART, (1) "ALL ELECTRICAL CABLING ASSOCIATED | | WITH THE NUCLEAR SAFETY-RELATED (AUTOCLOSE) OPERATION OF THE MAIN STEAM | | ISOLATION VALVES (MSIVs) IS ROUTED OUTSIDE OF THE MAIN STEAM PIPE TUNNEL | | THROUGH AREAS OF THE STATION WHICH WOULD NOT EXPOSE THEM TO THE ENVIRONMENT | | RESULTING FROM A RUPTURE OF THE MAIN STEAM LINES. ...THEREFORE, FROM AN | | ELECTRICAL EQUIPMENT AND CABLING VIEWPOINT, THE ENVIRONMENT RESULTING FROM | | THE POSTULATED MAIN STEAM LINE RUPTURE WOULD HAVE NO DELETERIOUS EFFECT ON | | NUCLEAR SAFETY-RELATED SYSTEMS REQUIRED TO PLACE AND MAINTAIN THE REACTOR | | IN A SAFE SHUTDOWN CONDITION", AND (2) "THE ABILITY TO BRING THE AFFECTED | | UNIT TO A SAFE SHUTDOWN WILL NOT BE IMPAIRED BECAUSE THERE IS NO | | SAFETY-RELATED EQUIPMENT LOCATED IN THE PIPE TUNNEL. IN ADDITION, ALL | | ELECTRICAL CABLES REQUIRED FOR SAFE SHUTDOWN, INCLUDING THE MAIN STEAM | | ISOLATION VALVE CABLES, ARE NOT ROUTED DOWN THE PIPE TUNNEL." | | | | AN APPARENT CONTRADICTION WITH THESE STATEMENTS IS THAT THE CABLES FOR | | UNIT 1 AND 2 STEAM GENERATOR PRESSURE TRANSMITTERS #PT-514, 515, 516, 524, | | 525, 526, 534, 535, 536, 544, 545, AND 546 ARE ROUTED THROUGH THE STEAM | | PIPE TUNNEL. THESE TRANSMITTERS PROVIDE AN INPUT SIGNAL TO THE FOLLOWING | | SAFETY INJECTION SYSTEM ACTUATIONS: STEAM LINE HIGH DIFFERENTIAL PRESSURE, | | AND HIGH STEAM FLOW COINCIDENT WITH LOW STEAM LINE PRESSURE OR LOW-LOW Tave | | (THIS ACTUATION PROVIDES AN AUTO CLOSE SIGNAL FOR THE MSIVs). | | | | THE LICENSEE IS DETERMINING CORRECTIVE ACTIONS WHICH WILL BE COMPLETED | | PRIOR TO STARTUP OF EITHER UNIT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32890 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 09/08/97 | |UNIT: [1] [2] [ ] STATE: MI |NOTIFICATION TIME: 20:57 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/08/97 | +------------------------------------------------+EVENT TIME: 20:00[EDT]| |NRC NOTIFIED BY: SAM PARTIN/MARY DePUYDT |LAST UPDATE DATE: 09/08/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |MARK RING RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |CECIL THOMAS, NRR EO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS |SULLIVAN FEMA | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS |RICHARD BARRETT IRD | |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 | 57 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 85 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - UE DECLARED & TS REQD S/D ON BOTH UNITS DUE TO INOPERABLE CONTAINMENTS - | | | | AS A RESULT OF ISSUES RAISED DURING THE ONGOING ARCHITECT/ENGINEER DESIGN | | INSPECTION, THE LICENSEE WAS REVIEWING THE DESIGN ASPECTS OF THE | | CONTAINMENTS (BOTH UNITS HAVE SIMILAR CONTAINMENTS). AFTER CONSULTING WITH | | THE NUCLEAR STEAM SUPPLY SYSTEM SUPPLIER (WESTINGHOUSE) THE LICENSEE | | DETERMINED THAT CONCERNS EXISTED ABOUT WHETHER ADEQUATE COMMUNICATION | | (FLOWPATHS) EXISTS BETWEEN THE ACTIVE AND INACTIVE PORTIONS OF THE | | CONTAINMENT SUMP. | | | | DURING CERTAIN SCENARIOS, THE VOLUME OF WATER FLOW BACK TO THE CONTAINMENT | | RECIRCULATION SUMP MAY NOT BE ADEQUATE TO SUPPORT LONG TERM EMERGENCY CORE | | COOLING (ECC) SYSTEMS (RHR SYSTEM, SAFETY INJECTION SYSTEM, CHARGING | | SYSTEM) OR CONTAINMENT SPRAY PUMP OPERATION DURING THE RECIRCULATION PHASE | | OF A LARGE OR SMALL BREAK LOCA. THE CONTAINMENT DRAINAGE SYSTEM IS | | DESIGNED TO ENSURE THAT WATER ENTERING THE CONTAINMENT FROM THE BREACH IN | | THE REACTOR COOLANT SYSTEM, ECC SYSTEMS INJECTION, AND ICE CONDENSER MELT | | FLOWS BACK INTO THE CONTAINMENT RECIRCULATION SUMP VIA DRAINS. LICENSEE | | ANALYSIS WAS UNABLE TO CONFIRM THAT SUFFICIENT COMMUNICATION EXISTED | | BETWEEN INACTIVE AND ACTIVE VOLUMES OF THE CONTAINMENT TO ENSURE ADEQUATE | | DRAINAGE TO THE RECIRCULATION SUMP. WITHOUT ADEQUATE DRAINAGE INTO THE | | SUMP, A LOW SUMP LEVEL WILL RESULT, WHICH JEOPARDIZES LONG TERM OPERATION | | OF THE ECC SYSTEMS AND CONTAINMENT SPRAY PUMPS DUE TO VORTEXING AND AIR | | ENTRAINMENT. | | | | AS A CONSERVATIVE MEASURE BECAUSE OF THESE CONCERNS, THE LICENSEE DECLARED | | BOTH TRAINS OF THE ECC SYSTEMS AND THE CONTAINMENT SPRAY SYSTEM INOPERABLE | | FOR BOTH UNITS AND ENTERED TECH SPEC LCO A/S 3.0.3 TO SHUT DOWN BOTH UNITS. | | THE LICENSEE COMMENCED SHUTTING UNIT 1 DOWN FROM 100% POWER AT 1655 AND | | UNIT 2 DOWN FROM 100% POWER AT 1728. | | | | AT 2000, THE LICENSEE DECLARED AN UNUSUAL EVENT ON BOTH UNITS DUE TO THE | | POTENTIAL LOSS OF CONTAINMENT BARRIER ON BOTH UNITS. | | | | THE LICENSEE PLANS TO PERFORM FURTHER ANALYSIS TO DETERMINE THE EXTENT OF | | THE EXISTING COMMUNICATION BETWEEN THE PORTIONS OF THE SUMPS AND WHETHER | | PLANT MODIFICATIONS WILL BE NECESSARY. | | | | THE LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS AND THE NRC RESIDENT | | INSPECTOR OF THE DECLARATION OF THE UNUSUAL EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32891 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 09/08/97 | |UNIT: [ ] [2] [ ] STATE: NC |NOTIFICATION TIME: 22:50 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 09/08/97 | +------------------------------------------------+EVENT TIME: 19:30[EDT]| |NRC NOTIFIED BY: DAN HARDIN |LAST UPDATE DATE: 09/08/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM RANKIN 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 +------------------------------------------------------------------------------+ | - HPCI SYSTEM INOPERABLE DUE TO NON-SEISMICALLY MOUNTED PIPING OVERHEAD - | | | | ON 09/05/97, THE LICENSEE INSTALLED TEMPORARY AIR PIPING OVER THE TOP | | OF THE 250 VDC MOTOR CONTROL CENTER (MCC) IN THE REACTOR BUILDING IN | | PREPARATION FOR THE UPCOMING REFUELING OUTAGE. THIS MCC SUPPLIES POWER | | TO THE HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM | | | | AT 1930 ON 09/08/97, LICENSEE ENGINEERING DEPARTMENT PERSONNEL DETERMINED | | THAT THE TEMPORARY AIR PIPING WAS NOT SEISMICALLY QUALIFIED (MOUNTED) AND | | THEREFORE, THE CONTROL ROOM OPERATORS DECLARED THE HPCI SYSTEM INOPERABLE, | | EVEN THOUGH THE SYSTEM WAS FUNCTIONAL. | | | | AT 2000 ON 09/08/97, THE LICENSEE REMOVED THE TEMPORARY AIR PIPING FROM | | OVER THE TOP OF THE MCC AND DECLARED THE HPCI SYSTEM OPERABLE. | | | | THE EMERGENCY CORE COOLING SYSTEMS AND THE RCIC SYSTEM WERE OPERABLE DURING | | THIS 30 MINUTE PERIOD. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+