U.S. Nuclear Regulatory Commission Operations Center Event Reports For 08/21/97 - 08/22/97 ** EVENT NUMBERS ** 32792 32793 32794 32795 32796 32797 32798 32799 32800 +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32792 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 08/21/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 14:10 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 08/21/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 13:20[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 08/21/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |BRUCE BURGESS RDO | | DOCKET: 0707002 |FRED COMBS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: KURT SISLER | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NCFR NON CFR REPORT REQMNT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NON CFR REPORT REQUIREMENT - POSSIBLE COMPROMISE OF CONFIDENTIAL/RESTRICTED | | DATA. | | | | ON 08/21/97 AT 1320 HOURS, IT WAS CONFIRMED BY THE SITE SECURITY DEPARTMENT | | AND THE SITE CLASSIFICATION OFFICER THAT A POSSIBLE COMPROMISE TO | | CONFIDENTIAL/RESTRICTED DATA OCCURRED. THIS POSSIBLE COMPROMISE WAS THE | | RESULT OF CLASSIFIED DOCUMENTS BEING STORED IN A UNLOCKED METAL FILE | | CABINET IN THE X-7721 MAINTENANCE, STORES AND TRAINING BUILDING. SECURITY | | INVESTIGATION IS ONGOING. | | | | THIS EVENT IS REPORTABLE PER PROCEDURE, UE2-RA-RE1030 REVISION 2, APPENDIX | | D, L(5) CRITERIA: ANY INFRACTIONS, LOSSES, COMPROMISES, OR POSSIBLE | | COMPROMISE OF NATIONAL SECURITY INFORMATION AND/OR RESTRICTED DATA OR | | CLASSIFIED DOCUMENTS NOT FALLING WITHIN 10 CFR 95.57(a). | | | | THE LICENSEE NOTIFIED THE NRC REGION 3 REGIONAL ADMINISTRATOR'S OFFICE OF | | THIS EVENT PER 10 CFR 95.57 REPORTING REQUIREMENTS. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32793 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 08/21/97 | |UNIT: [ ] [2] [3] STATE: CA |NOTIFICATION TIME: 14:12 [ET]| |RX TYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 08/20/97 | +------------------------------------------------+EVENT TIME: 13:30[PDT]| |NRC NOTIFIED BY: DAN QUINN |LAST UPDATE DATE: 08/21/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BILL JOHNSON RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INCORRECT LOCKING DEVICE USED | | | | THE FOLLOWING INFORMATION IS TAKEN FROM A FACSIMILE SUBMITED BY THE | | LICENSEE: | | | | "THIS NOTIFICATION IS FOR SAN ONOFRE UNITS 2 AND 3 AND IS BEING MADE IN | | ACCORDANCE WITH CONDITION 2.G OF THE FACILITY OPERATING LICENSES FOR UNITS | | 2 AND 3, WHICH REQUIRES EDISON TO REPORT VIOLATIONS OF LICENSE CONDITION | | 2.E WITHIN 24 HOURS. CONDITION 2.E STATES, IN PART: "SCE SHALL FULLY | | IMPLEMENT AND MAINTAIN IN EFFECT ALL PROVISIONS OF THE COMMISSION-APPROVED | | ... SAFEGUARDS CONTINGENCY PLAN (SCP)." | | | | "SECTION 3.4.5 OF THE SAN ONOFRE SCP REQUIRES AN EXPLICIT LOCKING DEVICE BE | | USED AT SPECIFIED LOCATIONS (NOTE: THE DETAILS OF THIS ARE SAFEGUARDS | | INFORMATION). | | | | "ON AUGUST 20, 1997, AT ABOUT 1330 PDT, EDISON CONCLUDED THAT DURING | | CHANGEOUT OF LOCKING DEVICES, AN EQUIVALENT DEVICE OF A DIFFERENT TYPE WAS | | SUBSTITUTED ON FEBRUARY 10, 1997, AT CERTAIN LOCATIONS. NOTWITHSTANDING THE | | LOCKING DEVICE PROVIDED EQUIVALENT PROTECTION, AND IN SOME RESPECTS | | PROVIDES A HIGHER LEVEL OF PROTECTION, EDISON CONCLUDED THIS DID NOT COMPLY | | FULLY WITH THE SCP AND WAS REPORTABLE. THE LOCKS WERE IMMEDIATELY REPLACED | | WITH THE SPECIFIC LOCK SPECIFIED IN THE SCP. | | | | "EDISON BELIEVES THIS CONDITION WAS OF NO SAFETY SIGNIFICANCE. | | | | "AT THE TIME OF THIS REPORT, BOTH UNITS 2 AND 3 WERE AT ABOUT 100% POWER. | | | | "EDISON WILL PROVIDE A 14-DAY FOLLOW-UP REPORT BY SEPTEMBER 3, 1997. | | | | "BY FACSIMILE COPY OF THIS MEMORANDUM, EDISON IS PROVIDING NOTIFICATION TO | | THE NRC REGIONAL ADMINISTRATOR, REGION IV, AS REQUIRED BY LICENSE CONDITION | | 2.G, AND ALSO TO THE DIRECTOR, WALNUT CREEK FIELD OFFICE, NRC REGION IV. | | THIS REPORT WILL BE DISCUSSED WITH THE NRC RESIDENT INSPECTORS." | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32794 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 08/21/97 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 15:31 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 08/21/97 | +------------------------------------------------+EVENT TIME: 11:45[EDT]| |NRC NOTIFIED BY: FAULKNER |LAST UPDATE DATE: 08/21/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |NIEL DELLA GRECA RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 82 POWER OPERATION | 82 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ROUTINE MONTHLY SAMPLE RESULTS OF THE STANDBY LIQUID CONTROL STORAGE TANK | | CONCENTRATION AND SODIUM PENTABORATE WEIGHT CAME BACK OUT OF SPECIFICATION. | | | | | | AT 1145 EDT ON 08/21/97, ROUTINE MONTHLY SAMPLE RESULTS OF THE STANDBY | | LIQUID CONTROL STORAGE TANK CONCENTRATION AND SODIUM PENTABORATE WEIGHT | | CAME BACK OUT OF SPECIFICATION LOW AT 13.42% CONCENTRATION. THE MINIMUM | | CONCENTRATION ALLOWED BY TECHNICAL SPECIFICATION 3.1.5 IS 13.6%. A SECOND | | SET OF SAMPLES TAKEN FROM THE STANDBY LIQUID CONTROL TANK VALIDATED THE | | CONDITION AT 1415 EDT. TECHNICAL SPECIFICATION 3.1.5 WAS ENTERED AT 1145 | | EDT. IN ACCORDANCE WITH TECHNICAL SPECIFICATION 3.1.5, THE LICENSEE HAS 8 | | HOURS TO CORRECT THE SODIUM PENTABORATE CONCENTRATION PROBLEM. IF THE | | PROBLEM CANNOT BE CORRECTED WITHIN 8 HOURS, THEN IN THE NEXT 12 HOURS THE | | PLANT HAS TO BE IN A HOT SHUTDOWN CONDITION. IT IS NOT KNOWN AT THIS TIME | | WHY THE CONCENTRATION CHANGED. THE CURRENT PLAN IS TO ADD SODIUM | | PENTABORATE TO RESTORE THE CONCENTRATION IN THE STANDBY LIQUID CONTROL | | STORAGE TANK TO ITS NORMAL LEVEL. THIS SHOULD BE COMPLETED BY 2100 EDT. | | | | ALL EMERGENCY CORE COOLING SYSTEMS AND THE EMERGENCY DIESEL GENERATORS ARE | | FULLY OPERABLE IF NEEDED. THE ELECTRICAL GRID IS ALSO STABLE. | | | | THE NRC RESIDENT INSPECTOR AND THE LOWER ALLOWAYS CREEK TOWNSHIP WILL BE | | NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32795 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 08/21/97 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 16:09 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 08/21/97 | +------------------------------------------------+EVENT TIME: 15:20[EDT]| |NRC NOTIFIED BY: PHIL SANTINI |LAST UPDATE DATE: 08/21/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |NIEL DELLA GRECA RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 100 POWER OPERATION | 82 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TWO ENERGIZED RELAYS IDENTIFIED WHICH WOULD BLOCK MAIN BOILER FEED PUMP | | TRIP WHEN THE MAIN BOILER FEED PUMP DISCHARGE MOTOR OPERATED STOP VALVES | | ARE OFF THEIR SEAT. | | | | AT 1520 EDT ON 08/21/97, INDIAN POINT UNIT #2 WAS OPERATING AT 100% POWER | | WITH THE MAIN FEEDWATER REGULATING VALVE AND LOW FLOW FEED REGULATING VALVE | | MOTOR OPERATED STOP VALVES CONTROL SWITCHES IN THE OPEN POSITION. THIS WAS | | REQUIRED DUE TO AN EARLIER IDENTIFIED CONDITION WHERE THE VALVES WOULD | | CLOSE WITH THE CONTROL SWITCHES IN AUTOMATIC. DURING TROUBLESHOOTING OF | | THIS PROBLEM, TWO RELAYS (3RSBFP1 AND 3RSBFP2) WERE IDENTIFIED AS BEING | | ENERGIZED. THIS CONDITION WOULD BLOCK MAIN BOILER FEED PUMP (MBFP) TRIP | | WHEN THE MBFP DISCHARGE MOTOR OPERATED STOP VALVES ARE OFF THEIR OPEN SEAT. | | THIS IS PART OF THE FEED WATER ISOLATION SEQUENCE ON SAFETY INJECTION OR | | HIGH STEAM GENERATOR WATER LEVEL. THIS RESULTED IN AN ENTRY INTO TECHNICAL | | SPECIFICATION 3.0.1 AND A PLANT SHUT DOWN TO HOT SHUTDOWN IS IN PROGRESS. | | ALL OTHER ESF TRIP FEATURES ARE OPERABLE. THE PLANT HAS TO BE IN A HOT | | SHUTDOWN CONDITION BY 2220 EDT IF THE RELAY PROBLEM CANNOT BE CORRECTED. | | ALL EMERGENCY CORE COOLING SYSTEMS AND THE EMERGENCY DIESEL GENERATORS ARE | | FULLY OPERABLE IF NEEDED. | | | | THE LICENSEE IS TROUBLESHOOTING THIS PROBLEM PER WORK ORDERS 097-94004 AND | | 93941. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | * * * UPDATE BY M. SAVINO AT 2123 EDT ON 08/21/97 TAKEN BY MACKINNON * * * | | | | AT 1905 EDT TECHNICAL SPECIFICATION 3.0.1 WAS EXITED WHEN THE MAIN BOILER | | FEED PUMP TRIP CIRCUITRY WAS REESTABLISHED. CURRENT REACTOR POWER LEVEL IS | | 58%. LOWEST REACTOR POWER LEVEL REACHED WHILE IN TECHNICAL SPECIFICATION | | 3.0.1 WAS 48%. THE LICENSEE WILL INCREASE REACTOR POWER LEVEL TO 70% TO | | PERFORM FOLLOW-UP TESTING. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32796 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 08/21/97 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 16:38 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 08/21/97 | +------------------------------------------------+EVENT TIME: 16:22[EDT]| |NRC NOTIFIED BY: TOM COTTER |LAST UPDATE DATE: 08/21/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |NIEL DELLA GRECA RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THIS IS A FOLLOW-UP TO THE ENS NOTIFICATION FOR BEAVER VALLEY POWER STATION | | (BVPS) UNIT 1 AT 1810 HOURS ON 07/26/97 (EVENT # 32683). | | | | THE 07/26/97 ENS REPORT IDENTIFIED THAT CERTAIN UNIT 1 NON-SEISMICALLY | | QUALIFIED CONTROL CIRCUIT CONTACTORS (RELAYS AND HEAT AFFECTED DEVICES OR | | HADs) IN THE FIRE PROTECTION SYSTEM FOR THE SUPPLEMENTARY LEAK COLLECTION | | AND RELEASE SYSTEM (SLCRS) HAD THE POTENTIAL TO ACTUATE THE FIRE PROTECTION | | (FP) SYSTEM DURING A SEISMIC EVENT. SUCH ACTUATION COULD ADVERSELY AFFECT | | THE ABILITY OF THE CHARCOAL FILTERS, DUE TO WATER DELUGE OF CHARCOAL, | | PREVENTING AIR PASSAGE. | | | | A FOLLOWUP EXTENT OF CONDITION EVALUATION HAS IDENTIFIED THAT THE UNIT 2 | | SLCRS FP SYSTEM HAS A MANUAL CONTROL CIRCUIT WITH A SEAL-IN RELAY FOR A | | PUSH BUTTON SWITCH THAT IS NOT SEISMICALLY QUALIFIED AND UNDER SEISMIC | | MOTION COULD ACTUATE THE FIRE PROTECTION SYSTEM WITH A SIMILAR IMPACT ON | | THE OPERABILITY OF THE UNIT 2 SLCRS CHARCOAL FILTERS. | | | | BVPS UNIT 2 WILL INSTITUTE MANUAL CONTROL OF THE FP DELUGE SYSTEM FOR THE | | SLCRS CHARCOAL FILTERS. 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 TOUR OF THE FILTER HOUSING | | AREA. THIS FIRE TOUR IS IN EFFECT. | | | | AN ENGINEERING REVIEW TO ASSESS THE POTENTIAL IMPACT ON SAFETY-RELATED | | EQUIPMENT OF THE AUTOMATICALLY ACTUATED FP SYSTEMS HAS BEEN COMPLETED AND A | | REVIEW OF THE MANUAL FP SYSTEMS IS ONGOING. | | | | THE RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32797 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 08/21/97 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 18:39 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 08/21/97 | +------------------------------------------------+EVENT TIME: 17:50[EDT]| |NRC NOTIFIED BY: PAUL MALZAHN |LAST UPDATE DATE: 08/21/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |NIEL DELLA GRECA RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 LICENSEE NOTIFIED THE STATE OF CONNECTICUT DEPARTMENT OF ENVIRONMENTAL | | PROTECTION THAT THEY MAY HAVE VIOLATED THEIR NPDES PERMIT TIME INTERVAL | | BETWEEN SAMPLES AT A FLOW DISCHARGE POINT. | | | | A REVIEW OF THE SAMPLING PRACTICES AT DISCHARGE SERIAL NUMBER (DSN) 006 AND | | THE REGULATIONS OF CONNECTICUT STATE AGENCIES (RGSA) SECTION | | 22a-430-3(a)93) HAS BEEN COMPLETED AND IT IS THE DETERMINATION OF | | ENVIRONMENTAL SERVICES-NUCLEAR THAT THIS EVENT IS REPORTABLE UNDER THE | | CONNECTICUT DEPARTMENT OF ENVIRONMENTAL PROTECTION REPORTING REQUIREMENTS. | | | | DSN 006 IS A CONTINUOUS FLOW DISCHARGE POINT. THE FLOW AT DSN 006 IS ALSO | | VARIABLE. THE AUTOMATIC SAMPLER AT DSN 006 IS PROGRAMMED TO SAMPLE THE | | DISCHARGE PATH ONCE EVERY 3000 GALLONS. IF THE DISCHARGE FLOW RATE DROPS | | BELOW 50 GALLONS PER MINUTE FOR AN EXTENDED PERIOD, A PERIOD OF GREATER | | THAN SIXTY MINUTES WILL LAPSE BETWEEN SAMPLES. THE ABOVE REFERENCED RGSAs | | INDICATE THAT THE MAXIMUM TIME INTERVAL ALLOWED BETWEEN SAMPLES IS SIXTY | | MINUTES WITHOUT PRIOR APPROVAL OF THE DEP COMMISSIONER. THIS IS CONFIRMED | | IN DEP DOCUMENT "HOW TO MAINTAIN COMPLIANCE WITH YOUR PERMIT". A REVIEW OF | | THE PAST SIX MONTHS OF SAMPLES DATA AT DSN 006 INDICATES THAT THE TIME | | INTERVAL BETWEEN SAMPLES MAY HAVE EXCEEDED SIXTY MINUTES AND THEREFORE, | | THIS EVENT IS REPORTABLE TO THE CONNECTICUT DEPARTMENT OF ENVIRONMENTAL | | PROTECTION. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 32798 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: UINTAH ENGINEERING INC. |NOTIFICATION DATE: 08/21/97 | | CITY: VERNAL REGION: 4 |NOTIFICATION TIME: 19:54 [ET]| | COUNTY: RICH STATE: UT |EVENT DATE: 08/21/97 | |LICENSE#: UT2400046 AGREEMENT: Y |EVENT TIME: 17:54[MDT]| | DOCKET: |LAST UPDATE DATE: 08/21/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |BILL JOHNSON RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: JULIE FELICE | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TROXLER MOISTURE DENSITY GAUGE MISSING | | | | THE STATE OF UTAH DIVISION OF RADIATION CONTROL PERFORMED AN INSPECTION OF | | UINTAH ENGINEERING INC., LOCATED AT P.O. BOX 1758, VERNAL, UTAH. A TROXLER | | MOISTURE GAUGE WAS FOUND MISSING. THE LICENSEE SAID THAT THEY HAD THE GAUGE | | DURING THE LAST THE TIME THEY WERE INSPECTED BY THE UTAH DIVISION OF | | RADIATION CONTROL IN APRIL OF 1993. THE STATE OF UTAH DIVISION OF RADIATION | | CONTROL ISSUED THEM A NOTICE OF VIOLATION FOR NOT HAVING THE GAUGE IN LATE | | APRIL OF THIS YEAR. UINTAH ENGINEERING INC. SAID THAT THEY HAD GIVEN THE | | GAUGE TO NUCLEAR TESTING SERVICES TO DESTROY THE GAUGE. UPON INVESTIGATION, | | THE UTAH DIVISION OF RADIATION CONTROL FOUND THAT NO RECORDS EXISTED AT | | NUCLEAR TESTING SERVICES OR WITH TROXLER SHOWING THAT THE GAUGE HAD BEEN | | GIVEN TO EITHER ONE THEM BY UINTAH ENGINEERING INC. THE UTAH DIVISION OF | | RADIATION CONTROL IS SENDING AN ORDER TO UINTAH ENGINEERING INC. REQUESTING | | THEM TO FIND THE GAUGE OR REPORT THE GAUGE MISSING TO THE POLICE. THE MODEL | | NUMBER OF THE MISSING GAUGE IS 2401 AND THE SOURCE SERIAL NUMBER IS | | 64-4500. THE GAUGE CONTAINED 7.4 mCi OF Cs-137 AND 50mCi OF Am-241/Be. THE | | STATE OF UTAH HAS NOT ASSIGNED AN ORIGINAL ITEM NUMBER TO THIS EVENT. | | | | SEE HOO LOG BOOK FOR PHONE NUMBERS AND NAMES. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32799 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 08/21/97 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 22:35 [ET]| |RX TYPE: [1] CE |EVENT DATE: 08/21/97 | +------------------------------------------------+EVENT TIME: 20:38[CDT]| |NRC NOTIFIED BY: JEFF BROWN |LAST UPDATE DATE: 08/21/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BILL JOHNSON RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DURING THE COURSE OF SURVEILLANCE TESTING BOTH SPRAY HEADER ISOLATION | | VALVES WERE PLACED IN OVERRIDE WHICH RENDERED BOTH SPRAY HEADERS INSIDE | | CONTAINMENT INOPERABLE. | | | | AT 2038 CDT, WHILE RESTORING FROM A QUARTERLY TEST OF THE SAFETY INJECTION | | AND CONTAINMENT SPRAY PUMP INSERVICE AND VALVE EXERCISE TEST, IT WAS | | DISCOVERED THAT THE CONTROL SWITCHES FOR THE TWO CONTAINMENT SPRAY HEADER | | ISOLATION VALVES, HCV-344 AND HCV-345, WERE IN THE "OVERRIDE" POSITION, NOT | | THE "AUTO" POSITION AS REQUIRED. THIS RENDERED THESE VALVES INOPERABLE FOR | | MORE THAN ELEVEN HOURS. WITH THE CONTROL SWITCHES IN THIS POSITION, THE | | VALVES WOULD NOT HAVE OPENED AUTOMATICALLY IF REQUIRED DURING A DESIGN | | BASIS ACCIDENT. HOWEVER, THEY COULD HAVE BEEN OPENED BY OPERATORS IN THE | | CONTROL ROOM. PLANT PROCEDURES REQUIRE THE OPERATORS TO VERIFY FLOW THROUGH | | THE SPRAY HEADERS DURING ACCIDENTS REQUIRING CONTAINMENT SPRAY AND TO OPEN | | THESE SPRAY HEADER ISOLATION VALVES IF REQUIRED. | | | | INITIAL INVESTIGATION INDICATES THAT THE CONTROL SWITCH WAS PLACED IN THE | | "OVERRIDE" POSITION AT APPROXIMATELY 0900 CDT WHILE COMPLETING THE INITIAL | | LINEUP FOR THE SURVEILLANCE TEST PROCEDURE. THE TECHNICAL SPECIFICATION | | LIMITING CONDITION FOR OPERATION FOR THESE VALVES DOES NOT ALLOW BOTH OF | | THEM TO BE INOPERABLE AT THE SAME TIME. UPON DISCOVERY OF THIS CONDITION, | | THE SWITCHES WERE IMMEDIATELY PLACED IN THE CORRECT POSITION. THE CONTROL | | SWITCHES FOR THESE VALVES HAVE THREE POSITIONS "OPEN," "AUTO," AND | | "OVERRIDE." INITIAL INVESTIGATION INDICATED THAT THIS CONDITION IS OUTSIDE | | THE DESIGN BASIS FOR THE PLANT, AND WOULD HAVE PREVENTED THE AUTOMATIC | | FULFILLMENT OF A SAFETY FUNCTION REQUIRED TO MITIGATE THE CONSEQUENCES OF | | AN ACCIDENT. IT APPEARS THAT THE OPERATOR MISUNDERSTOOD THE DIRECTION OF | | THE PROCEDURE. THE PROCEDURES REQUIRES THE VALVE TO BE CLOSED USING THE | | HAND CONTROLLER, NOT THE "OVERRIDE" POSITION OF THE CONTROL SWITCH. | | | | THE LICENSEE HAS PAGED THE NRC RESIDENT INSPECTOR TO INFORM HIM OF THIS | | EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32800 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 08/22/97 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 03:51 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 08/22/97 | +------------------------------------------------+EVENT TIME: 00:26[CDT]| |NRC NOTIFIED BY: JIM BOYLE |LAST UPDATE DATE: 08/22/97 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM JOHNSON 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 93 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | GENERATOR TRIP - REACTOR SCRAM | | | | THE MAIN GENERATOR TRIPPED AT 0026 FOR UNKNOWN REASONS CAUSING A REACTOR | | SCRAM. ALL CONTROL RODS FULLY INSERTED. NO ELECTRICAL BUSES WERE LOST AND | | THE PLANT IS STABLE IN MODE THREE. REACTOR WATER LEVEL IS BEING MAINTAINED | | BY THE MAIN FEED SYSTEM AND STEAM IS BEING DUMPED TO THE MAIN CONDENSER AS | | NECESSARY TO REMOVE DECAY HEAT. | | | | DURING THE INITIAL TRANSIENT THE SUPPRESSION POOL CLEANUP SYSTEM ISOLATED | | AT REACTOR WATER LEVEL THREE. | | | | THE PLANT WILL REMAIN IN MODE THREE WHILE THE CAUSE OF THE GENERATOR TRIP | | IS INVESTIGATED. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+