U.S. Nuclear Regulatory Commission Operations Center Event Reports For 02/09/1999 - 02/10/1999 ** EVENT NUMBERS ** 35333 35356 35357 35358 35359 35360 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35333 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 01/29/1999| | UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 18:20[EST]| | RXTYPE: [1] GE-4 |EVENT DATE: 01/29/1999| +------------------------------------------------+EVENT TIME: 14:50[CST]| | NRC NOTIFIED BY: GREEN |LAST UPDATE DATE: 02/09/1999| | HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |LAWRENCE YANDELL R4 | |10 CFR SECTION: | | |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 +------------------------------------------------------------------------------+ | THE PLANT DECLARED RCIC INOPERABLE DUE TO LOW TURBINE OIL LEVEL. | | | | THE RCIC OUTBOARD TURBINE BEARING OIL LEVEL WAS SLIGHTLY BELOW THE LOW LEVEL | | MARK AND THE RCIC SYSTEM WAS THEREFORE DECLARED INOPERABLE AT 1450. HPCI | | HAS BEEN VERIFIED TO BE OPERABLE. THIS CONDITION CAUSED ENTRY INTO A 14 DAY | | LCO DUE TO RCIC BEING INOPERABLE. AN INSPECTION OF THE OIL SYSTEM DID NOT | | INDICATE ANY LEAKAGE AND OIL LEVEL HAD ONLY LOWERED SLIGHTLY FROM THE | | PREVIOUS DAY. MAINTENANCE PERSONNEL HAVE BEEN CALLED IN TO ADD OIL TO THE | | BEARING. THE RESIDENT INSPECTOR WAS NOTIFIED. | | | | * * * UPDATE ON 1/29/99 @ 2135 BY WHEELER TO GOULD * * * | | | | RCIC RETURNED TO OPERABLE CONDITION AT 1848 WHEN THE OIL LEVEL ON THE | | OUTBOARD TURBINE BEARING WAS RESTORED TO ITS PROPER LEVEL. THE RESIDENT | | INSPECTOR WAS NOTIFIED. | | | | THE REG 4 RDO (YANDELL) WAS INFORMED. | | | | * * * UPDATE AT 1446 ON 02/09/99 BY BILL GREEN TO JOLLIFFE * * * | | | | UPON FURTHER REVIEW OF THIS EVENT, THE LICENSEE DETERMINED THAT THE RCIC | | SYSTEM TURBINE HAD BEEN OPERABLE DURING THIS EVENT BECAUSE OF THE FOLLOWING | | REASONS: | | 1) THE SHAFT DRIVEN OIL PUMP PROVIDES PRIMARY LUBRICATION TO THE TURBINE | | AND OIL LEVEL BEING BELOW THE LOW LEVEL MARK WILL NOT PREVENT THE PUMP FROM | | PROVIDING ADEQUATE LUBRICATION, AND 2) THE OIL SLINGER RING WAS STILL | | SUBMERGED BY APPROXIMATELY 1/4 INCH. | | THUS, THE RCIC SYSTEM WAS CAPABLE OF OPERATING THROUGHOUT THIS EVENT AND | | THEREFORE, THE LICENSEE DESIRES TO RETRACT THIS EVENT. THE LICENSEE | | INFORMED THE NRC RESIDENT INSPECTOR. | | | | THE NRC OPERATIONS OFFICER NOTIFIED THE R4DO JOHN PELLET. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35356 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 02/09/1999| | UNIT: [1] [2] [] STATE: FL |NOTIFICATION TIME: 13:09[EST]| | RXTYPE: [1] CE,[2] CE |EVENT DATE: 02/07/1999| +------------------------------------------------+EVENT TIME: 17:00[EST]| | NRC NOTIFIED BY: CALVIN WARD |LAST UPDATE DATE: 02/09/1999| | HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |THOMAS DECKER R2 | |10 CFR SECTION: | | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | - STATE NOTIFIED OF A SMALL DEAD GREEN TURTLE FOUND IN A NET IN THE PLANT | | INTAKE CANAL - | | | | THE LICENSEE FOUND A DEAD 7.5 POUND GREEN TURTLE IN A CAPTURE NET IN THE | | PLANT INTAKE CANAL. THE LICENSEE NOTIFIED THE FLORIDA DEPARTMENT OF | | ENVIRONMENTAL PROTECTION (DEP) AND PLANS TO SEND THE TURTLE TO A FLORIDA DEP | | LAB FOR NECROPSY. THE LICENSEE IS DETERMINING CORRECTIVE ACTIONS AND PLANS | | TO SUBMIT A WRITTEN REPORT TO THE NRC WITHIN 30 DAYS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Fuel Cycle Facility |Event Number: 35357 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 02/09/1999| | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 15:45[EST]| | COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 02/08/1999| | 6903 ROCKLEDGE DRIVE |EVENT TIME: 22:00[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 02/09/1999| | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION | |LICENSE#: GDP-2 AGREEMENT: N |GARY SHEAR R3 | | DOCKET: 0707002 |JOHN GREEVES NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: ERIC SPAETH | | | HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24-HOUR NRC BULLETIN 91-01 REPORT | | | | On February 8, 1999, at 2220 hours, Cascade operations personnel discovered | | that two Nuclear Criticality Safety Approval (NCSA) requirements were not | | being maintained within the X-326 process building. A plastic bag of | | soiled, oily 3M absorbent pads was discovered in the Area 4 Seal Exhaust | | Station with the top open and without holes. NCSA-PLANT_018.A02 | | requirements #9 and #11 state in part: "Dry active waste (DAW) bags and | | containers shall be closed or covered with a rigid lid when unattended, and | | have holes in the bottom to allow for solution drainage. | | | | The Non-Compliance of requirements #9 and #11 constitute a loss of one (1) | | control, (control "B") in the double contingency matrix for contingency | | event A/B 1.1. Control "A" (mass and moderation) was maintained throughout | | this event. The deficiency (loss of control "B") was corrected at 2256 | | hours per the direction of the Portsmouth Nuclear Criticality Staff. | | | | Safety significance of events: A bag of absorbent waste was not closed and | | did not have holes in the bag. If a leak occurred in the area and the bag | | was in the path of the leak, there could be a potential for a criticality. | | | | Potential criticality pathways involved (brief scenarios) of how criticality | | could occur: A leak of uranium bearing oil would have to occur, such that | | the DAW bag collected the uranium-bearing oil. (The oil that was absorbed In | | the cloth was essentially new oil). | | | | Controlled parameters (mass, moderation, geometry, concentration, etc.): | | The controlled parameters were mass and moderation. In addition, a leak | | would have to occur in the area to be a concern. | | | | Estimated amount, enrichment, form of licensed material (include process | | limit and % worst case of critical mass): Approximately 10% U-235. | | | | Nuclear criticality safety control(s) or control system(s) and description | | of the failures or deficiencies: NCS controls limit mass and moderation. | | In addition, a leak would have to occur in the area before a criticality was | | possible. Two requirements were violated that controlled material addition | | to the waste bag. Other controls on mass remained in place. | | | | Corrective actions to restore safety system and when each was implemented: | | The bag in question was closed and placed into a DAW barrel at 2256 hours. | | | | There was no loss of hazardous or radioactive material nor radioactive or | | radiological contamination exposure as a result of this event. | | | | The licensee informed the NRC Resident Inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35358 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 02/09/1999| | UNIT: [1] [] [] STATE: IA |NOTIFICATION TIME: 17:52[EST]| | RXTYPE: [1] GE-4 |EVENT DATE: 02/09/1999| +------------------------------------------------+EVENT TIME: 16:00[CST]| | NRC NOTIFIED BY: DICK FOWLER |LAST UPDATE DATE: 02/09/1999| | HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |GARY SHEAR R3 | |10 CFR SECTION: |JOSE CALVO, EO NRR | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 100 Power Operation |100 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION REQUIRED PLANT SHUTDOWN DUE TO INOPERABLE CONTROL | | BUILDING VENTILATION SYSTEM | | | | WITH THE TRAIN 'A' CONTROL BUILDING VENTILATION (CBV) SYSTEM STANDBY FILTER | | UNIT (SFU) INOPERABLE FOR PLANNED MAINTENANCE ACTIVITIES, THE LICENSEE | | DISCOVERED THAT THE PHOTOCELL FOR THE 'B' TRAIN DIFFERENTIAL PRESSURE SWITCH | | (DPS) (#7304B) WAS NOT ILLUMINATED. THIS CONDITION PREVENTS THE DPS FROM | | PERFORMING ITS FUNCTION TO CONTROL THE TRAIN 'B' SFU HEATERS, RENDERING THE | | TRAIN 'B' CBV SYSTEM SFU INOPERABLE. | | | | WITH BOTH TRAINS OF THE CBV SYSTEM SFUs INOPERABLE, THE LICENSEE ENTERED | | TECH SPEC LCO A/S 3.0.3 WHICH REQUIRES THE LICENSEE TO BEGIN SHUTTING THE | | PLANT DOWN WITHIN ONE HOUR AND TO PLACE THE PLANT IN AT LEAST CONDITION 2 | | (STARTUP) WITHIN NINE HOURS. | | | | THE LICENSEE PLANS TO REPLACE THE FAILED DIFFERENTIAL PRESSURE SWITCH WITHIN | | EIGHT HOURS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35359 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 02/09/1999| | UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 18:37[EST]| | RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 02/09/1999| +------------------------------------------------+EVENT TIME: 18:20[EST]| | NRC NOTIFIED BY: JEFF SHIPE |LAST UPDATE DATE: 02/09/1999| | HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |LAURIE PELUSO R1 | |10 CFR SECTION: | | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 98 Power Operation |98 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - Non-conservative dose calculation methodology is a condition outside the | | design basis of the plant - | | | | As a result of LER 2-97-008 corrective actions, non-conservative inputs have | | been identified that is associated with the Beaver Valley Power Station | | (BVPS) methodology in calculating radiation doses for accidents which must | | analyze for a concurrent iodine spike as part of their radiological | | analyses. The identified non-conservative factors during past operation, | | could have resulted in the calculated control room personnel dose values | | exceeding 10CFR50 Appendix A, Criterion 19 thyroid limits. Since BVPS no | | longer has reasonable assurance that acceptance criteria for control room | | personnel dose limits per Criterion 19 would have been met during past | | operation, the identified non-conservative dose calculation methodology was | | a condition which was outside the design basis of the plant per | | 10CFR50.72(b)(1)(ii). This condition is also being evaluated for the | | criteria in 10CFR Part 21. | | | | For BVPS, the only Design Basis Accidents (DBAs) which involve a concurrent | | iodine spike analysis are Main Steam Line Break, Small Line Breaks (e.g., | | letdown line break outside containment), and Steam Generator Tube Rupture. | | The most significant of the non-conservative issues is purification (i.e., | | letdown) flow, which was given as 60 gpm. This is the lower limit of the | | plant design flow rate range of 60-120 gpm. Analysis using 60 gpm results | | in a significant underestimation of the concurrent iodine spike source term | | as compared to operation at the upper design limit of 120 gpm. Of lesser | | importance were underestimated demineralizer decontamination factor, | | overestimated reactor coolant system (RCS) mass and inadequate use of RCS | | leakage as an iodine removal mechanism. It has been determined that | | correcting the above identified non-conservative factor would raise | | calculated control room personnel dose values of those events analyzed for | | concurrent iodine spikes by at least 40% and potentially as high as 140%. | | | | Until the BVPS dose calculations can be formally revised to address the | | identified non-conservative factors, the station has placed administrative | | controls on the extent of steady state letdown flow to ensure that plant | | operation remains within past analyzed limits. The influence of the other | | identified non-conservative factors have also been reviewed and determined | | not to be an operability concern at this time. | | | | The licensee plans to notify the NRC Resident Inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35360 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 02/09/1999| | UNIT: [3] [4] [] STATE: FL |NOTIFICATION TIME: 21:50[EST]| | RXTYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 02/09/1999| +------------------------------------------------+EVENT TIME: 21:00[EST]| | NRC NOTIFIED BY: ANDRE DALL'AU |LAST UPDATE DATE: 02/09/1999| | HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |THOMAS DECKER R2 | |10 CFR SECTION: | | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |3 N Y 100 Power Operation |100 Power Operation | |4 N Y 100 Power Operation |100 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - BOTH UNIT ERDS LOST DUE TO ERDADS COMPUTER FAILURE - | | | | AT 2100 ON 02/09/99, THE COMMON EMERGENCY RESPONSE DATA ACQUISITION AND | | DISPLAY SYSTEM (ERDADS) COMPUTER FAILED CAUSING A LOSS OF THE EMERGENCY | | RESPONSE DATA SYSTEM (ERDS) FOR BOTH UNITS. THE LICENSEE IS INVESTIGATING | | THE CAUSE OF THE LOSS. AT 2110, THE LICENSEE RESTORED THE UNIT 3 ERDS TO | | OPERABLE STATUS AND IS RESTORING THE UNIT 4 ERDS. | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+