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Event Notification Report for April 26, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           04/25/2000 - 04/26/2000

                              ** EVENT NUMBERS **

36927  36928  36929  36930  

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|Power Reactor                                    |Event Number:   36927       |
+------------------------------------------------------------------------------+
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| FACILITY: NINE MILE POINT          REGION:  1  |NOTIFICATION DATE: 04/25/2000|
|    UNIT:  [] [2] []                 STATE:  NY |NOTIFICATION TIME: 13:59[EDT]|
|   RXTYPE: [1] GE-2,[2] GE-5                    |EVENT DATE:        04/25/2000|
+------------------------------------------------+EVENT TIME:        11:02[EDT]|
| NRC NOTIFIED BY:  M. JAQUIN                    |LAST UPDATE DATE:  04/25/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JAMES NOGGLE         R1      |
|10 CFR SECTION:                                 |                             |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP           |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| REACTOR CORE ISOLATION COOLING (RCIC) STEAM FLOW INSTRUMENTS DECLARED        |
| INOPERABLE                                                                   |
|                                                                              |
| RCIC steam flow instruments for both Division 1 & 2 became inoperable.       |
| Inoperability of these trip units were based upon erratic indications on the |
| trip units.  RCIC was subsequently declared inoperable as a result of the    |
| required Technical Specification 3.3.2 action for the inoperability of the   |
| steam flow instrument which required the isolation of RCIC steam supply      |
| line.  A 7 day Limiting Condition of Operation for RCIC was entered per      |
| Technical Specification 3.7.3 when RCIC steam supply line was isolated.      |
| Actions are being taken to correct RCIC steam flow instrument erratic        |
| indications.   All Emergency Core Cooling Systems and the Emergency Diesel   |
| Generators are fully operable if needed.                                     |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36928       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: TURKEY POINT             REGION:  2  |NOTIFICATION DATE: 04/25/2000|
|    UNIT:  [3] [4] []                STATE:  FL |NOTIFICATION TIME: 15:22[EDT]|
|   RXTYPE: [3] W-3-LP,[4] W-3-LP                |EVENT DATE:        04/25/2000|
+------------------------------------------------+EVENT TIME:        15:00[EDT]|
| NRC NOTIFIED BY:  C.  MOWREY                   |LAST UPDATE DATE:  04/25/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |PAUL FREDRICKSON     R2      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(vi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION MADE TO THE STATE OF FLORIDA CONCERNING LOW LEVEL FIXED |
| SURFACE CONTAMINATION FOUND ON SCAFFOLDING EQUIPMENT RECEIVED FROM A         |
| VENDOR.                                                                      |
|                                                                              |
| While performing a routine survey, Turkey Point Health Physics personnel     |
| discovered low levels of radioactivity on several pieces of scaffolding      |
| knuckles and elbows received from a vendor.  The knuckles never entered the  |
| site's radiologically controlled area.  These items were counted in a Small  |
| Article Monitor (SAM) and indicated low level contamination was present.  In |
| total 12 out of approximately 3,000 items surveyed indicated the presence of |
| low level fixed activity.  The highest level measured was 15,833             |
| disintegration's per minute (DPM) when counted on the SAM and 125 net (above |
| background) counts per minute using a standard HP-210 probe. Isotopic        |
| analysis indicates Cobalt-60 and Cesium-137.  No loose surface contamination |
| was found.  The items identified with low level fixed contamination are now  |
| being held inside the Turkey Point radiologically controlled area.           |
|                                                                              |
| The NRC Resident Inspector was notified of this event notification by the    |
| licensee.                                                                    |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36929       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM                  REGION:  1  |NOTIFICATION DATE: 04/25/2000|
|    UNIT:  [1] [] []                 STATE:  MA |NOTIFICATION TIME: 16:21[EDT]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        04/25/2000|
+------------------------------------------------+EVENT TIME:        15:45[EDT]|
| NRC NOTIFIED BY:  W. FIEDLER                   |LAST UPDATE DATE:  04/25/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JAMES NOGGLE         R1      |
|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                                   
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION (HPCI) DECLARED INOPERABLE.                  |
|                                                                              |
| HPCI inverter failure alarm was received at 1545ET.  An operator checked the |
| power breakers to the inverter and found them closed.  The inverter reset    |
| itself at 1551 ET.  HPCI was declared inoperable and a 14 day limiting       |
| condition of operation was entered per Technical Specification 3.5.          |
| Licensee investigating HPCI inverter problem. All other Emergency Core       |
| Cooling Systems and the Emergency Diesel Generators are fully operable.      |
|                                                                              |
|                                                                              |
| The NRC Resident Inspector was notified of the event by the licensee.        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36930       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BROWNS FERRY             REGION:  2  |NOTIFICATION DATE: 04/26/2000|
|    UNIT:  [] [] [3]                 STATE:  AL |NOTIFICATION TIME: 03:23[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4,[3] GE-4           |EVENT DATE:        04/25/2000|
+------------------------------------------------+EVENT TIME:        23:42[CDT]|
| NRC NOTIFIED BY:  RODNEY NACOSTE               |LAST UPDATE DATE:  04/26/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |PAUL FREDRICKSON     R2      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|                                                   |                          |
|3     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| VARIOUS ESF ACTUATIONS DUE TO RPS BUS 3B DE-ENERGIZING AS A RESULT OF A      |
| FAILED RELAY                                                                 |
|                                                                              |
| "At 23:42 [CDT] the RPS bus 3B de-energized causing PCIS Group 2 and Group 6 |
| isolation valves to automatically close. A burnt relay was the initiating    |
| condition. Group 2 outboard drywell equipment drain valve and drywell floor  |
| drain valve closed. Group 6 drywell radiation monitor isolation valves       |
| closed. All other expected group isolations occurred along with the          |
| automatic starts of SBGTS and CREVS.                                         |
|                                                                              |
| "Unit 3 is in Mode 5 with primary containment integrity not required.        |
|                                                                              |
| "This event is reportable under criteria 50.72.b.2.ii :  Any event or        |
| condition that results in manual or automatic actuation of any engineered    |
| safety feature (ESF), including the reactor protection system (RPS)."        |
|                                                                              |
| RPS bus 3B was re-energized from its alternate power supply.  Electricians   |
| are currently troubleshooting the cause of the failed relay.  There was no   |
| electrical maintenance or testing ongoing at the time of the relay failure.  |
|                                                                              |
| The licensee informed the NRC Resident Inspector.                            |
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