Event Notification Report for May 11, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
05/10/1999 - 05/11/1999
** EVENT NUMBERS **
35696 35697 35698 35699
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|General Information or Other |Event Number: 35696 |
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| REP ORG: NEW YORK CITY DEPART OF HEALTH |NOTIFICATION DATE: 05/10/1999|
|LICENSEE: BROWNING FERRIS INDUSTRIES |NOTIFICATION TIME: 11:47[EDT]|
| CITY: NEW YORK REGION: 1 |EVENT DATE: 05/07/1999|
| COUNTY: STATE: NY |EVENT TIME: 08:00[EDT]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 05/10/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |CURTIS COWGILL R1 |
| |FRED COMBS NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: BORRI (NYC DPT OF HEALTH) | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| LANDFILL REJECTED HOSPITAL SOLID WASTE CONTAINING 300 MILLICURIES OF |
| TECHNETIUM-99m |
| |
| BROWNING FERRIS INDUSTRIES (BFI) RECEIVED A LOAD OF SOLID WASTE FROM CITY |
| HOSPITAL CENTER AT ELMHURST IN NEW YORK CITY AND TOOK IT TO THEIR TRANSFER |
| STATION IN BROOKLYN, NY. THE WASTE WAS THEN MOVED TO A LANDFILL IN |
| COMSTOCK, PA WHERE IT WAS REJECTED AND RETURNED TO THE BFI FACILITY IN |
| BROOKLYN ON 05/07/99. THE WASTE CONTAINED APPROXIMATELY 300 MILLICURIES OF |
| TECHNETIUM-99m. THE WASTE IS BEING RETURNED TO THE HOSPITAL. THE CITY IS |
| INVESTIGATING THIS INCIDENT. |
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|Power Reactor |Event Number: 35697 |
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| FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 05/10/1999|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 15:18[EDT]|
| RXTYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 05/10/1999|
+------------------------------------------------+EVENT TIME: 13:00[EDT]|
| NRC NOTIFIED BY: BELDEN |LAST UPDATE DATE: 05/10/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CURTIS COWGILL R1 |
|10 CFR SECTION: | |
|ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
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EVENT TEXT
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| UNIT 1 VALVES FAILED THEIR LOCAL LEAK RATE TEST. |
| |
| UNDER THE APPENDIX J PROGRAM PLAN (#NMP1-APPJ-001) SECTION III/1.8 OUTAGE |
| TESTING REQUIREMENTS INCLUDE MAINTAINING A COMBINED TOTAL TYPE 'B' AND 'C' |
| AS-FOUND MINIMUM PATHWAY LEAKAGE. IN ACCORDANCE WITH TECH SPEC 6.16.4, THE |
| COMBINED LOCAL LEAK RATE TEST (TYPE 'B' & 'C' TESTS INCLUDING AIRLOCKS) |
| ACCEPTANCE CRITERIA IS LESS THAN 0.6 La, CALCULATED IN THE MINIMUM PATHWAY |
| BASIS, AT ALL TIMES WHEN CONTAINMENT INTEGRITY IS REQUIRED. THE VALUE OF |
| 0.6 La FOR UNIT 1 WAS CALCULATED TO BE 388.44 SCFH. THE RESULTS OF THE TEST |
| MEASURED 388.756 SCFH, WHICH EXCEED THE CALCULATED VALUE FOR THE COMBINED |
| AS-FOUND TYPE 'B' AND 'C' LOCAL LEAK RATE TESTS. THIS CONDITION WOULD HAVE |
| BEEN A TECH SPEC VIOLATION IF IDENTIFIED DURING POWER OPERATION. |
| |
| THIS CONDITION WILL BE CORRECTED PRIOR TO PLANT RESTART. |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
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|Power Reactor |Event Number: 35698 |
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| FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 05/10/1999|
| UNIT: [2] [3] [] STATE: PA |NOTIFICATION TIME: 19:51[EDT]|
| RXTYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 05/10/1999|
+------------------------------------------------+EVENT TIME: 09:30[EDT]|
| NRC NOTIFIED BY: KOVALCHICK |LAST UPDATE DATE: 05/10/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CURTIS COWGILL R1 |
|10 CFR SECTION: | |
|HFIT 26.73 FITNESS FOR DUTY | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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 |
| | |
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EVENT TEXT
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| TRACES OF A CONTROLLED SUBSTANCE FOUND IN A BATHROOM INSIDE THE PROTECTED |
| AREA |
| |
| ON 04/15/99, THREE SUSPECTED ITEMS WERE FOUND IN A BATHROOM INSIDE THE PLANT |
| PROTECTED AREA AND WERE TURNED OVER TO PECO ENERGY CORPORATE SECURITY. AT |
| 0930 ON 05/10/99, THE LICENSEE RECEIVED A REPORT FROM AN INDEPENDENT |
| LABORATORY THAT INDICATED THAT, ALTHOUGH THERE WAS NO VISIBLE RESIDUE |
| PRESENT, A GAS CHROMATOGRAPHY/MASS SPECTROMETRY DETECTED AND CONFIRMED THE |
| PRESENCE OF A CONTROLLED SUBSTANCE. AT THE PRESENT TIME, THE SUSPECTED |
| ITEMS HAVE NOT BEEN ASSOCIATED WITH ANY SPECIFIC INDIVIDUAL. THE LICENSEE |
| IS CONTINUING TO INVESTIGATE THIS SITUATION. |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
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|Power Reactor |Event Number: 35699 |
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| FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 05/10/1999|
| UNIT: [1] [] [] STATE: LA |NOTIFICATION TIME: 21:34[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 05/10/1999|
+------------------------------------------------+EVENT TIME: 16:58[CDT]|
| NRC NOTIFIED BY: CARLSON |LAST UPDATE DATE: 05/10/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHARLES CAIN R4 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
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EVENT TEXT
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| DIV 1 EDG INITIATION AND RHR LPCI "A" & LPCS INJECTION INTO THE RPV DUE TO |
| AN INVALID SIGNAL |
| |
| WITH THE PLANT IN OPERATIONAL CONDITION 5 IN A REFUELING OUTAGE, THE START |
| OF THE DIVISION 1 EMERGENCY DIESEL GENERATOR (EDG) AND INJECTION INTO THE |
| REACTOR PRESSURE VESSEL (RPV) VIA THE RESIDUAL HEAT REMOVAL (RHR) LOW |
| PRESSURE COOLANT INJECTION (LPCI) "A" AND LOW PRESSURE CORE SPRAY (LPCS) |
| SYSTEMS OCCURRED DUE TO AN INVALID EMERGENCY CORE COOLING SYSTEM INITIATION |
| SIGNAL. |
| |
| THE CAUSE OF THE INITIATION SIGNAL WAS A FAILED ROSEMONT TRIP UNIT |
| (#B21-N671A), WHICH WAS NEWLY INSTALLED AND PLACED INTO SERVICE DURING THE |
| PRESENT REFUELING OUTAGE IN |
| RESPONSE TO THE SAFETY/RELIEF VALVE LOGIC SMART FIRE ISSUE. WHEN THE TRIP |
| UNIT FAILED, IT AFFECTED POWER TO THE DIVISION 1 INSTRUMENT RACK RESULTING |
| IN THE GENERATION OF AN INVALID RPV LEVEL 1 INITIATION SIGNAL CAUSING THE |
| ESF ACTUATIONS. PLANT OPERATORS VERIFIED THE REACTOR CAVITY LEVEL AND |
| IMMEDIATELY OVERRODE THE OPEN INJECTION VALVE SIGNAL TO STOP THE INJECTION. |
| APPROXIMATELY TWO INCHES OF WATER HAD BEEN ADDED TO THE REACTOR CAVITY LEVEL |
| FROM THE SUPPRESSION POOL. THE EDG DID NOT LOAD AND WAS SECURED AFTER |
| APPROXIMATELY TWO HOURS. |
| |
| WHEN THE OPEN LPCS INJECTION VALVE SIGNAL WAS OVERRIDDEN, THE SYSTEM MINIMUM |
| FLOW VALVE DID NOT REOPEN AND CONTROL ROOM OPERATORS OPENED THE MINIMUM FLOW |
| VALVE TO PROVIDE LPCS PUMP PROTECTION. ALSO, THE RHR "A" INJECTION CHECK |
| VALVE WAS STILL INDICATING OPEN (UNCLEAR IF THIS IS AN INDICATION PROBLEM OR |
| A STUCK OPEN VALVE PROBLEM) AFTER THE INJECTION VALVE HAD BEEN SHUT. THE |
| LICENSEE IS INVESTIGATING BOTH OF THESE CONDITIONS. |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
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