Event Notification Report for February 1, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
01/29/1999 - 02/01/1999
** EVENT NUMBERS **
35323 35324 35325 35326 35327 35328 35329 35330 35331 35332 35333 35334
35335
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 35323 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: MD RADIOLOGICAL HEALTH DEPT |NOTIFICATION DATE: 01/29/1999|
|LICENSEE: SYNCOR INTERNATIONAL CORP |NOTIFICATION TIME: 09:35[EST]|
| CITY: TIMONIUM REGION: 1 |EVENT DATE: 01/27/1999|
| COUNTY: STATE: MD |EVENT TIME: 12:00[EST]|
|LICENSE#: MD-05-058-01 AGREEMENT: Y |LAST UPDATE DATE: 01/29/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |DAVID SILK R1 |
| | |
+------------------------------------------------+ |
| NRC NOTIFIED BY: DONNA GAINES | |
| HQ OPS OFFICER: DICK JOLLIFFE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - Moly Generator shipping box apparently contaminated at Syncor - |
| |
| On 01/28/99, a Moly Generator shipped by FedEx from Dupont received at |
| Syncor International Corporation in Timonium, MD, was found to have external |
| contamination but no internal contamination. The wipes from outside of the |
| generator shipping box read 224,590 cpm (244,385 dpm). The generator was |
| taken out of the shipping box and used since there was no internal |
| contamination. The shipping box was isolated and rewiped later in the |
| afternoon, and no contamination was detected. |
| |
| The shipping box was labeled RADIII Mo-99 287.59 GBq with a TI of 4.1. |
| |
| The FedEx driver and his delivery truck were surveyed and no contamination |
| above background was found. |
| |
| Based on the above events, it appears that the shipping box was contaminated |
| once in the restricted area at Syncor. The person conducting the survey |
| could have touched something contaminated and subsequently contaminated the |
| shipping box. |
| |
| Syncor's package receipt procedures were reviewed by a MD inspector with |
| emphasis on their protocol for contaminated packages. |
| |
| Syncor is conducting an investigation and plans to submit a written report |
| of this incident and follow-up action taken to MD within 30 days. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35324 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 01/29/1999|
| UNIT: [3] [] [] STATE: LA |NOTIFICATION TIME: 09:48[EST]|
| RXTYPE: [3] CE |EVENT DATE: 01/29/1999|
+------------------------------------------------+EVENT TIME: 07:57[CST]|
| NRC NOTIFIED BY: VICTOR COLLINS |LAST UPDATE DATE: 01/29/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHARLES MARSCHALL R4 |
|10 CFR SECTION: | |
|DDDD 73.71 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3 N Y 94 Power Operation |94 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SECURITY REPORT - |
| |
| UNACCOUNTED FOR PERSONNEL DOOR LOCK PULLER. COMPENSATORY MEASURES |
| IMMEDIATELY TAKEN UPON DISCOVERY. THE LICENSEE NOTIFIED THE NRC RESIDENT |
| INSPECTOR. REFER TO THE HOO LOG FOR ADDITIONAL DETAILS. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Hospital |Event Number: 35325 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: DETROIT MACOMB HOSPITAL |NOTIFICATION DATE: 01/29/1999|
|LICENSEE: DETROIT MACOMB HOSPITAL |NOTIFICATION TIME: 11:28[EST]|
| CITY: DETROIT REGION: 3 |EVENT DATE: 01/28/1999|
| COUNTY: STATE: MI |EVENT TIME: 16:10[EST]|
|LICENSE#: 21-01190-05 AGREEMENT: N |LAST UPDATE DATE: 01/29/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |TONY VEGEL R3 |
| |DONALD COOL NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: ARTHUR EWALD | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|LADM 35.33(a) MED MISADMINISTRATION | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MEDICAL MISADMINISTRATION DUE TO PATIENT INTERVENTION |
| |
| During brachytherapy treatment of a patient's endobronchial area, the |
| patient dislodged the catheter approximately 25 cm, causing the treatment |
| site to receive only 3.8% of the prescribed dose. Additionally, the |
| patient's nasal area received approximately 13 rads (13 cGy) due to the |
| displacement. The licensee estimates that the catheter was dislodged for |
| approximately 10 minutes before being discovered. |
| |
| The patient's referring physician has been informed of this event. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Hospital |Event Number: 35326 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: SAINT MARY'S HOSPITAL |NOTIFICATION DATE: 01/29/1999|
|LICENSEE: SAINT MARY'S HOSPITAL |NOTIFICATION TIME: 11:49[EST]|
| CITY: RICHMOND REGION: 2 |EVENT DATE: 01/08/1998|
| COUNTY: STATE: VA |EVENT TIME: 11:50[EST]|
|LICENSE#: 451136702 AGREEMENT: N |LAST UPDATE DATE: 01/29/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |BRIAN BONSER R2 |
| |DON COOL NMSS EO |
+------------------------------------------------+ |
| NRC NOTIFIED BY: ANTHONY | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|LADM 35.33(a) MED MISADMINISTRATION | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MEDICAL MISADMINISTRATION |
| |
| SAINT MARY'S HOSPITAL IN RICHMOND, VIRGINIA DISCOVERED, ON 1/28/99 @ 1150 |
| DURING AN ANNUAL REVIEW OF THEIR QUALITY MANAGEMENT PROGRAM, THEY HAD |
| ADMINISTERED THE WRONG DOSAGE DURING TREATMENT OF A PATIENT WITH GRAVES |
| DISEASE. THE PRESCRIBED DOSAGE WAS 8 MILLICURIES OF I-131, BUT THE |
| ADMINISTERED DOSAGE WAS 9.8 MILLICURIES OF |
| I-131. THE PATIENT'S PHYSICIAN WAS NOTIFIED, BUT SHE DID NOT THINK IT WAS |
| NECESSARY TO NOTIFY THE PATIENT. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35327 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 01/29/1999|
| UNIT: [1] [] [] STATE: MA |NOTIFICATION TIME: 13:57[EST]|
| RXTYPE: [1] GE-3 |EVENT DATE: 01/29/1999|
+------------------------------------------------+EVENT TIME: 12:03[EST]|
| NRC NOTIFIED BY: FIELDER |LAST UPDATE DATE: 01/29/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DAVID SILK R1 |
|10 CFR SECTION: | |
|AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | |
|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 ENTERED A 14 DAY LCO DUE TO HPCI BEING DECLARED INOPERABLE. |
| |
| THE HPCI SYSTEM WAS ISOLATED AND DECLARED INOPERABLE DUE TO A SUSPECTED |
| PROBLEM WITH STEAMLINE FLOW SWITCH TRIP SETPOINT. IT WAS DETERMINED THERE |
| WAS A POSSIBILITY THAT THE SETSCREW INTERNAL TO THE BARTON DIFFERENTIAL |
| PRESSURE SWITCH HAD NOT BEEN TIGHTEN AFTER PERFORMANCE OF THE LAST |
| CALIBRATION. THIS CONDITION COULD CAUSE EXCESSIVE DRIFT. |
| |
| A SECOND CONCERN IS THE SWITCH'S RESPONSE DURING A SEISMIC EVENT MAY BE |
| AFFECTED WITH A LOOSE SCREW. HPCI WAS ISOLATED TO MAINTAIN PRIMARY |
| CONTAINMENT INTEGRITY AND A MAINTENANCE REQUEST HAS BEEN SUBMITTED. THIS |
| CONCERN MAY ALSO BE APPLICABLE TO OTHER SAFETY RELATED SYSTEMS AND THEY WILL |
| BE CHECKED TO ENSURE THE SETSCREW IS APPROPRIATELY TIGHTENED. RCIC IS |
| OPERABLE. |
| |
| THE RESIDENT INSPECTOR WAS NOTIFIED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35328 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 01/29/1999|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 15:31[EST]|
| RXTYPE: [1] GE-6 |EVENT DATE: 01/29/1999|
+------------------------------------------------+EVENT TIME: 13:59[CST]|
| NRC NOTIFIED BY: LANDIN |LAST UPDATE DATE: 01/29/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |TONY VEGEL R3 |
|10 CFR SECTION: | |
|AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP | |
|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 N 0 Cold Shutdown |0 Cold Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THE PLANT DECLARED DIVISION 1 AND 2 SERVICE WATER INOPERABLE. |
| |
| THE DIV 1 AND DIV 2 SERVICE WATER PUMPS(SX) BEARINGS WERE DETERMINED TO BE |
| DEGRADED AND THIS CONDITION REPRESENTED A REASONABLE DOUBT THAT THE SX PUMPS |
| WOULD BE UNABLE TO PERFORM THEIR DESIGN FUNCTION FOR AN EXTENDED 30 DAY TIME |
| PERIOD. THESE PUMPS ARE REQUIRED TO SUPPORT ACCIDENT MITIGATION, SAFE |
| SHUTDOWN AND RESIDUAL HEAT REMOVAL. THIS CONDITION PUT THE PLANT IN A LCO |
| FOR THE SUPPORTED SYSTEMS TO SUSPEND ALL FUEL MOVEMENT AND OPERATIONS WHICH |
| HAVE THE POTENTIAL FOR DRAINING THE VESSEL. |
| |
| THIS CONDITION WAS DISCOVERED 1/9/99 AND CORRECTIVE ACTIONS WERE INITIATED |
| THE SAME DAY ON BOTH DIVISIONS AND COMPLETED WITHIN THE LAST SEVERAL DAYS. |
| DIV 1 IS REPAIRED AND DECLARED OPERABLE AND DIV 2 IS REPAIRED AND WILL BE |
| DECLARED OPERABLE UPON COMPLETION OF POST-REPAIR DOCUMENTATION REVIEW. |
| |
| THE LICENSEE DID NOT DETERMINE THIS EVENT REPORTABLE UNTIL 1/29/99 @ 1359. |
| |
| THE RESIDENT INSPECTOR WAS NOTIFIED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 35329 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: SWAGELOK COMPANY |NOTIFICATION DATE: 01/29/1999|
|LICENSEE: SWAGELOK COMPANY |NOTIFICATION TIME: 16:04[EST]|
| CITY: SOLON REGION: 3 |EVENT DATE: 01/28/1999|
| COUNTY: STATE: OH |EVENT TIME: [EST]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 01/29/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |DAVID SILK R1 |
| |BRIAN BONSER R2 |
+------------------------------------------------+VERN HODGE NRR |
| NRC NOTIFIED BY: BRUCE FLUSCHE (FAX) | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THE SWAGELOK COMPANY IS SUBMITTING A POSSIBLE 10CFR PART 21 NOTIFICATION |
| BECAUSE OF A POSSIBLE MATERIAL DEFECT IN A SWAGELOK PIPE FITTING TEE, PART # |
| SS-6-T. THE DEFECT IS A CRACK IN THE CENTER OF THE FORGING. THEY ARE |
| CONTINUING THEIR ANALYSIS OF THE PART. |
| THIS PART WAS SUPPLIED TO PUBLIC SERVICE ELECTRIC & GAS(20 PCS.) IN HANCOCKS |
| BRIDGE N.J. AND SOUTH CAROLINA ELECTRIC & GAS CO., VC SUMMER STATION(3 PCS.) |
| THE PRODUCT ID IS R27GE0123B. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35330 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 01/29/1999|
| UNIT: [1] [2] [] STATE: IL |NOTIFICATION TIME: 17:03[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/29/1999|
+------------------------------------------------+EVENT TIME: 13:45[CST]|
| NRC NOTIFIED BY: BAKER |LAST UPDATE DATE: 01/29/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |TONY VEGEL R3 |
|10 CFR SECTION: | |
|HFIT 26.73 FITNESS FOR DUTY | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| ALCOHOL FOUND IN THE VITAL AREA (AUXILIARY BUILDING). |
| |
| THE LICENSEE FOUND A 200ML JACK DANIELS BOTTLE, CONTAINING APPROXIMATELY ONE |
| TEASPOON OF LIQUID, IN A VITAL AREA COMMON TO BOTH UNITS. THE BOTTLE WAS |
| FOUND INSIDE OF A TUBE STEEL STRUCTURAL SUPPORT DURING A ROUTINE RADIATION |
| PROTECTION HOUSE CLEANING AND WALKDOWN. THEY TOOK POSSESSION OF THE BOTTLE |
| AND CONTINUED THE INSPECTION. A SECURITY INVESTIGATION WILL FOLLOW. |
| |
| THE RESIDENT INSPECTOR WAS NOTIFIED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 35331 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: ALABAMA RADIATION CONTROL |NOTIFICATION DATE: 01/29/1999|
|LICENSEE: TUSCALOOSA STEEL |NOTIFICATION TIME: 17:11[EST]|
| CITY: TUSCALOOSA REGION: 2 |EVENT DATE: 01/29/1999|
| COUNTY: STATE: AL |EVENT TIME: 15:10[CST]|
|LICENSE#: 1190 AGREEMENT: Y |LAST UPDATE DATE: 01/29/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |BRIAN BONSER R2 |
| |DAVID SILK R1 |
+------------------------------------------------+LARRY CAMPER NMSS |
| NRC NOTIFIED BY: DAVID WALTER |STUART RUBIN IRD |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THE ALABAMA RADIATION CONTROL OFFICE WAS NOTIFIED BY TUSCALOOSA STEEL OF AN |
| UNAUTHORIZED TRANSFER OF RADIOACTIVE MATERIAL. |
| |
| TUSCALOOSA STEEL REPORTED THAT A TRANSFER OF A DEVICE (RONAN MODEL SA-15, |
| S/N GG390), CONTAINING A 100 MILLICURIE CESIUM-137 SOURCE, TO THE GLADWIN |
| COMPANY IN PITTSBURGH, PA FOR REPAIR HAD OCCURRED. THE MOLD CASTER, WHICH |
| IS THE SOURCE HOLDER, WAS SENT FOR REPAIR INADVERTENTLY WITH THE SOURCE |
| STILL INSIDE. IT IS NOT BELIEVED, HOWEVER, THAT THE SOURCE HOLDER'S SHUTTER |
| WAS OPEN, SINCE NO RADIATION MONITORS WENT OFF WHEN THE MOLD CASTER WAS |
| LEAVING THE PLANT. TUSCALOOSA STEEL CONTACTED THE GLADWIN COMPANY TO HAVE |
| THEM MOVE THE MOLD CASTER TO A REMOTE AREA OF THEIR PLANT AND WAIT FOR RONAN |
| ENGINEERS TO ARRIVE SO THEY CAN REMOVE THE SOURCE AND RETURN IT TO |
| TUSCALOOSA STEEL. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 35332 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: OKLAHOMA DEPT OF ENVIR. PROTECTION. |NOTIFICATION DATE: 01/29/1999|
|LICENSEE: N/A |NOTIFICATION TIME: 18:17[EST]|
| CITY: OKLAHOMA CITY REGION: 4 |EVENT DATE: 01/29/1999|
| COUNTY: STATE: OK |EVENT TIME: 15:30[CST]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 01/29/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |CHARLES MARSCHALL R4 |
| |LARRY CAMPER NMSS |
+------------------------------------------------+STUART RUBIN IRD |
| NRC NOTIFIED BY: BRODERICK | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NINF INFORMATION ONLY | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THE OKLAHOMA CITY FIRE DEPARTMENT NOTIFIED THE OKLAHOMA DEPARTMENT OF |
| ENVIRONMENTAL PROTECTION THAT AN INDIVIDUAL HAD A 10 LB. DEPLETED URANIUM |
| SOURCE (POSSIBLY AN AIRCRAFT COUNTER WEIGHT) MEASURING 1.8 MILLIREM/HR AT |
| HIS HOUSE. THE INDIVIDUAL PURCHASED THE SOURCE AT A SURPLUS STORE. THE |
| INDIVIDUAL WAS INFORMED TO KEEP THE SOURCE ISOLATED UNTIL IT IS REMOVED FROM |
| HIS HOUSE. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|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: 01/29/1999|
| 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. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35334 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 01/29/1999|
| UNIT: [] [2] [] STATE: PA |NOTIFICATION TIME: 18:55[EST]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 01/29/1999|
+------------------------------------------------+EVENT TIME: 18:00[EST]|
| NRC NOTIFIED BY: COTTER |LAST UPDATE DATE: 01/29/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DAVID SILK 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AN ERRONEOUS ASSUMPTION WAS MADE IN THE FIRE PROTECTION SAFE SHUTDOWN |
| REPORT. |
| |
| A REVIEW ASSOCIATED WITH AN ENGINEERING FIRE PROTECTION SELF-ASSESSMENT HAS |
| IDENTIFIED AN ERRONEOUS ASSUMPTION REGARDING AN OPERATOR ACTION CREDITED IN |
| THE FIRE PROTECTION SAFE SHUTDOWN REPORT. POTENTIAL FIRE-INDUCED SPURIOUS |
| OPERATION OF THE REACTOR COOLANT SYSTEM (RCS) LOOP DRAIN VALVES 2RCS-MOV557A |
| , B, OR C, IN CONJUNCTION WITH SPURIOUS OPERATION OF THE DOWNSTREAM VALVES, |
| RCS EXCESS LETDOWN VALVES 2CHS-HCV137 AND 2CHS-MOV201 WAS NOT ADEQUATELY |
| CONSIDERED. THE UNIT 2 FIRE PROTECTION SAFE SHUTDOWN REPORT STATES THAT IN |
| THE EVENT OF A FIRE-INDUCED SPURIOUS OPERATION OF 2RCS-MOV557A, B, OR C, THE |
| OPERATOR COULD MANUALLY CLOSE EITHER 2CHS-MOV201 OR 2CHS-HCV137 TO ISOLATE |
| THE RESULTING EXCESS LETDOWN FLOW. OPERATION OF THESE VALVES FROM THE |
| CONTROL ROOM DOES NOT SATISFY THE REQUIREMENT SINCE THE FIRE MAY HAVE |
| DAMAGED THE CONTROL AND/OR POWER CIRCUITS. LOCAL MANUAL OPERATION OF THESE |
| VALVES WOULD NOT BE FEASIBLE WITHIN THE REQUIREMENTS OF THE SAFE SHUTDOWN |
| ANALYSIS BECAUSE OF INACCESSIBILITY IN CONTAINMENT. |
| |
| AT 1806 POWER WAS REMOVED FROM THE RCS LOOP DRAIN VALVES TO ISOLATE THIS |
| POTENTIAL FLOW PATH AND THUS RESTORE COMPLIANCE WITH THEIR POST-FIRE SAFE |
| SHUTDOWN ANALYSIS. |
| |
| THE RESIDENT INSPECTOR WAS NOTIFIED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35335 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 01/29/1999|
| UNIT: [2] [] [] STATE: PA |NOTIFICATION TIME: 19:12[EST]|
| RXTYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 01/29/1999|
+------------------------------------------------+EVENT TIME: 18:30[EST]|
| NRC NOTIFIED BY: PAUTLER |LAST UPDATE DATE: 01/29/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DAVID SILK 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| CONDITION THAT WOULD RESULT IN A NON-CONSERVATIVE INPUT TO THE ROD BLOCK |
| MONITORING SYSTEM. |
| |
| DURING A UNIT 2 MINOR MAINTENANCE INVESTIGATION ON A LOCAL POWER RANGE |
| MONITOR (LPRM) BYPASS LIGHT, TROUBLESHOOTING PERSONNEL FOUND A WIRING |
| CONCERN INVOLVING LPRM INPUTS TO THE UNIT 2 ROD BLOCK MONITORING (RBM) |
| SYSTEM. TWO LPRM LOCATIONS WERE FOUND SWAPPED WITHIN THE RBM SYSTEM. THIS |
| CONDITION WOULD CAUSE A NON-CONSERVATIVE INPUT TO THE RBM SYSTEM DURING |
| CONTROL ROD MOVEMENT, THEREFORE ALLOWING UNIT 2 TO POTENTIALLY OPERATE |
| OUTSIDE ITS DESIGN BASIS. PER PROCEDURE, BOTH LPRMS WERE BYPASSED TO RETURN |
| BOTH CHANNELS BACK TO OPERABLE STATUS. |
| |
| THE RESIDENT INSPECTOR WAS NOTIFIED. |
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Page Last Reviewed/Updated Thursday, March 25, 2021