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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    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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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