Event Notification Report for February 10, 1999
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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|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. |
+------------------------------------------------------------------------------+
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