U.S. Nuclear Regulatory Commission Operations Center Event Reports For 08/06/98 - 08/07/98 ** EVENT NUMBERS ** 34609 34610 34611 34612 34613 +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34609 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 08/06/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 03:00 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 08/05/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 15:45[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 08/06/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |BRUCE BURGESS RDO | | DOCKET: 0707002 |FREDERICK COMBS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: KURT SISLER | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24-HOUR NRC BULLETIN 91-01 REPORT | | | | A NUCLEAR CRITICALITY SAFETY APPROVAL (NCSA) REQUIREMENT WAS NOT BEING | | MAINTAINED WITHIN THE X-343 VAPORIZATION AND SAMPLING FACILITY. NUCLEAR | | CRITICALITY SAFETY (NCS) PERSONNEL FOUND THE HEPA FILTER UNIT ON THE ALWAYS | | SAFE PORTABLE SMALL UF6 GULPER SPACED SIXTEEN INCHES FROM A DRY ACTIVE | | WASTE (DAW) CONTAINER. NCSA-PLANT049.0C1 REQUIREMENT #4 REQUIRES A 24 INCH | | EDGE-TO-EDGE SPACING FROM THE GULPER'S TRAP AND HEPA FILTER ASSEMBLY TO ANY | | OTHER URANIUM BEARING MATERIALS OR EQUIPMENT. THIS CONDITION CONSTITUTES A | | LOSS OF CONTROL "A" (SPACING) FOR CONTINGENCY EVENT A/B.7.1, ALTHOUGH | | CONTROL "B" (MASS/GEOMETRY) WAS MAINTAINED. NCS PERSONNEL REESTABLISHED | | CONTROL "A" BY MOVING THE HEPA FILTER ASSEMBLY AWAY FROM THE DAW CONTAINER. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34610 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COMBUSTION ENGINEERING INC. |NOTIFICATION DATE: 08/06/98 | | RXTYPE: URANIUM FUEL FABRICATION |NOTIFICATION TIME: 14:55 [ET]| |COMMENTS: LEU CONVERSION (UF6 to UO2) |EVENT DATE: 08/05/98 | | COMMERCIAL LWR FUEL |EVENT TIME: 14:00[CDT]| | |LAST UPDATE DATE: 08/06/98 | | CITY: HEMATITE REGION: 3 +-----------------------------+ | COUNTY: JEFFERSON STATE: MO |PERSON ORGANIZATION| |LICENSE#: SNM-33 AGREEMENT: N |BRUCE BURGESS RDO | | DOCKET: 07000036 |FRED COMBS, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: BOB SHARKEY | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24 HOUR NRC BULLETIN 91-01 REPORT, U-235 ACCUMULATION IN TRASH INCINERATOR- | | | | WHILE PERFORMING MAINTENANCE ON THE PLANT TRASH INCINERATOR, PLANT | | PERSONNEL DISCOVERED THAT A GREATER-THAN-EXPECTED AMOUNT OF URANIUM | | HAD ACCUMULATED IN THE HEAT EXCHANGER. BEST ESTIMATES CONSERVATIVELY | | PLACE THE AMOUNT OF URANIUM AT LESS THAN 300 GRAMS OF U-235. THE | | CONTROLLED PARAMETERS FOR THE INCINERATOR SYSTEM ARE MASS AND MODERATOR. | | A SECOND MODERATOR BARRIER HAS BEEN ADDED TO THE HEAT EXCHANGER PORTION. | | TESTS OF THE MATERIAL INDICATE A MOISTURE LEVEL OF 0.02 WEIGHT % MOISTURE. | | | | THIS REPORT IS BEING MADE BECAUSE THE EXACT DISTRIBUTION AND DENSITY | | OF MATERIAL IN INACCESSIBLE PORTIONS OF THE HEAT EXCHANGER ARE UNKNOWN, | | LEADING TO SOME UNCERTAINTY IN THE MASS ESTIMATE. HOWEVER, GAMMA | | MEASUREMENT OF THE HEAT EXCHANGER DUCTWORK INDICATES THAT THE ACCUMULATION | | IS NO MORE SEVERE THAN THE VISIBLE PORTION UPON WHICH THE MASS ESTIMATE | | WAS BASED. BOUNDING ESTIMATES OF THE AMOUNT OF MATERIAL INDICATE THAT | | THE WORST CASE ACCUMULATION IS SAFE, EVEN IF MODERATED. THE INCINERATOR | | IS SHUTDOWN AND NO SPECIAL NUCLEAR MATERIAL IS PRESENT IN THE REMAINDER | | OF THE SYSTEM. BASED ON THE BEST ESTIMATE OF CONTAINED MASS, MASS CONTROL | | HAS BEEN REESTABLISHED BELOW THE PROCEDURALLY REQUIRED LEVEL. BASED ON | | BOUNDING CALCULATIONS, MASS CONTROL HAS BEEN REESTABLISHED AT LESS THAN | | THE MINIMUM CRITICAL MASS, REDUCED BY A FACTOR OF 1.3. | | | | THE LICENSEE IS INVESTIGATING THIS EVENT IN ACCORDANCE WITH THEIR ABNORMAL | | EVENT OCCURRENCE PROCESS AND DETERMINING CORRECTIVE ACTIONS. | | | | THE LICENSEE INFORMED JACK DAVIS, NRC REGION 3 INSPECTOR, WHO IS PRESENTLY | | ONSITE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34611 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 08/06/98 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 16:09 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 08/06/98 | +------------------------------------------------+EVENT TIME: 07:19[CDT]| |NRC NOTIFIED BY: STEVE WHEELER |LAST UPDATE DATE: 08/06/98 | |HQ OPS OFFICER: HENRY BAILEY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM JOHNSON RDO | |NONR OTHER UNSPEC REQMNT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | NRC IE BULLETIN 80-14 NOTIFICATION | | | | AT 0719 CDT ON 08/06/98, THE SOUTH SCRAM DISCHARGE VOLUME (SDV) OUTBOARD | | AIR OPERATED VENT VALVE WAS DECLARED INOPERABLE AS A PRIMARY CONTAINMENT | | VALVE FOR PLANNED MAINTENANCE. THE ASSOCIATED INBOARD VALVE WAS MANUALLY | | CLOSED TO PROVIDE FOR ISOLATION OF THE SCRAM DISCHARGE VOLUME VENT LINE. | | | | THE MAINTENANCE WAS PERFORMED AND THE VALVE WAS TESTED SATISFACTORILY. | | THE OUTBOARD VENT VALVE WAS DECLARED OPERABLE FOLLOWING TESTING AND THE | | SDV VALVES WERE RESTORED TO THEIR NORMALLY OPEN CONFIGURATION AT 1234 CDT | | ON 08/06/98. | | | | NRC NOTIFICATION IS REQUIRED BY COOPER NUCLEAR STATION PROCEDURES DUE TO | | A COMMITMENT MADE IN RESPONSE TO NRC IE BULLETIN 80-14. THIS COMMITMENT | | REQUIRES PROMPT NOTIFICATION OF THE NRC WITHIN 24 HOURS IF ANY SCRAM | | DISCHARGE VOLUME VENT OR DRAIN VALVE IS DECLARED INOPERABLE OR IS CLOSED | | FOR MORE THAN ONE HOUR IN ANY 24 HOUR PERIOD. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34612 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 08/06/98 | |UNIT: [1] [2] [ ] STATE: TX |NOTIFICATION TIME: 19:05 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/06/98 | +------------------------------------------------+EVENT TIME: 17:15[CDT]| |NRC NOTIFIED BY: SCOTT HEAD |LAST UPDATE DATE: 08/06/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM JOHNSON RDO | |NCFR NON CFR REPORT REQMNT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | SI ACCUMULATOR PRESSURE ALARM MAY NOT ACTUATE DUE TO INSTRUMENT UNCERTAINTY | | | | AS PART OF THE SOUTH TEXAS SETPOINT IMPROVEMENT PROGRAM, THE LICENSEE | | DETERMINED THAT THERE IS AN INSTRUMENT UNCERTAINTY OF +/- 22.7 PSIG | | ASSOCIATED WITH THE SAFETY INJECTION (SI) ACCUMULATOR PRESSURE MONITORING | | INSTRUMENTATION LOOPS. THESE INSTRUMENT LOOPS ARE USED TO SATISFY | | TECHNICAL SPECIFICATION (TS) SURVEILLANCE 4.5.1.1. | | | | TS 3.5.1 REQUIRES THAT SI ACCUMULATOR PRESSURE BE MAINTAINED BETWEEN | | 590 AND 670 PSIG. TS SURVEILLANCE 4.5.1.1 REQUIRES THAT THE ACCUMULATOR | | PRESSURE BE VERIFIED WITHIN TS LIMITS BY THE ABSENCE OF ALARMS. | | | | THEREFORE, THE ALARM SHOULD BE CALIBRATED SUCH THAT IT ACTUATES AT OR | | BEFORE THE TS LIMIT ACCOUNTING FOR APPROPRIATE INSTRUMENT UNCERTAINTIES. | | THE CURRENT BISTABLE SETTING FOR THE ACCUMULATOR LOW PRESSURE ALARM IS | | 603 PSIG, 13 PSIG ABOVE THE LOWER TS LIMIT. BECAUSE THE LOOP UNCERTAINTY | | IS +/- 22.7 PSIG, IT IS POSSIBLE THAT THE LOW PRESSURE ALARM MAY NOT | | ACTUATE UNTIL ACCUMULATOR PRESSURE IS BELOW THE LOWER TS LIMIT. (THIS SAME | | REASONING APPLIES TO THE HIGH PRESSURE SETPOINT - THE HIGH PRESSURE ALARM | | MAY NOT ACTUATE UNTIL ACCUMULATOR PRESSURE IS ABOVE THE UPPER TS LIMIT.) | | | | THEREFORE, THE LICENSEE HAS CONCLUDED THAT THIS INADEQUACY PREVENTS | | SOUTH TEXAS FROM STRICTLY COMPLYING WITH TS SURVEILLANCE 4.5.1.1 | | AND CONSIDERS THAT THIS CONDITION IS REPORTABLE IN ACCORDANCE WITH | | 10CFR50.73(a)(2)(i)(B). THIS NOTIFICATION IS BEING MADE IN ACCORDANCE | | WITH SOUTH TEXAS LICENSE CONDITION 2.g. | | | | THE LICENSEE ESTABLISHED TEMPORARY LOGS IN BOTH CONTROL ROOMS ON 07/30/98. | | THESE TEMPORARY LOGS REQUIRE VERIFICATION THAT ACCUMULATOR PRESSURE | | (AS READ ON THE EMERGENCY RESPONSE FACILITY DATA ACQUISITION AND DISPLAY | | SYSTEM) IS MAINTAINED BETWEEN 618 AND 642 PSIG. THIS BAND ACCOUNTS FOR | | THE CALCULATED INSTRUMENT UNCERTAINTIES AND ENSURES THAT THE ACCUMULATORS | | ARE PRESSURIZED WITHIN TS LIMITS. | | | | A SIMILAR REPORTABLE CONDITION ALSO EXISTS WITH REGARD TO ACCUMULATOR | | VOLUME AS DETERMINED BY LEVEL INSTRUMENT LOOPS. COMPENSATORY ACTIONS | | SIMILAR TO THOSE NOTED ABOVE HAVE ALSO BEEN PUT IN PLACE. | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34613 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 08/07/98 | |UNIT: [ ] [2] [ ] STATE: MD |NOTIFICATION TIME: 05:52 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 08/07/98 | +------------------------------------------------+EVENT TIME: 03:20[EDT]| |NRC NOTIFIED BY: DOUGLAS BAUDER |LAST UPDATE DATE: 08/07/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM MOSLAK 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 HOT STANDBY | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THREE MAIN STEAM SAFETY VALVES DISCOVERED TO HAVE EXCESSIVE INITIAL LIFT | | SETPOINTS | | | | WHILE PERFORMING MAIN STEAM SAFETY VALVE TESTING, THREE OF SIXTEEN MAIN | | STEAM SAFETY VALVES TESTED HAD INITIAL LIFT PRESSURES IN EXCESS OF THE | | LIMIT ALLOWED BY PLANT TECHNICAL SPECIFICATIONS. THE PRESSURE LIMIT OF | | TECHNICAL SPECIFICATION 3.7.1.1 IS 995 PSIG. THE VALVES AND AS-FOUND | | INITIAL LIFT PRESSURES ARE AS FOLLOWS: | | | | VALVE LIFT PRESSURE | | 2-RV-4001 1007 PSIG | | 2-RV-4000 1015 PSIG | | 2-RV-3992 1001 PSIG | | | | THESE VALVES WERE READJUSTED AND RETESTED TWICE SATISFACTORILY. THE NRC | | RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | | | | | | | +------------------------------------------------------------------------------+