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Event Notification Report for January 30, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           01/29/2001 - 01/30/2001

                              ** EVENT NUMBERS **

37697  37698  37699  37700  37701  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   37697       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 01/28/2001|
|    UNIT:  [2] [] []                 STATE:  NY |NOTIFICATION TIME: 23:38[EST]|
|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        01/28/2001|
+------------------------------------------------+EVENT TIME:        22:28[EST]|
| NRC NOTIFIED BY:  SANTINI                      |LAST UPDATE DATE:  01/29/2001|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |STEVEN DENNIS        R1      |
|10 CFR SECTION:                                 |                             |
|*ESF 50.72(b)(3)(iv)(A)  VALID SPECIF SYS ACTUAT|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| STEAM GENERATOR BLOWDOWN ISOLATED FOLLOWING ALARM RECEIVED ON RAD MONITOR    |
| R-49                                                                         |
|                                                                              |
| An alarm was received for rad monitor R-49, Steam Generator radiation        |
| monitor, due to a spike.  This resulted in automatic closure of the Steam    |
| Generator Blowdown isolation valves which is an ESF actuation.  All other    |
| primary to secondary leakage parameters were normal.  At the time of the     |
| spike, the Nuclear NPO was adjusting 24 S/G sample flow to obtain the        |
| required flow (as found: 35gph, required: 38-40gph).   AOI 1.2(Steam         |
| Generator Tube Leak Procedure) was entered and supplemental monitoring was   |
| initiated.  There are no indications of primary to secondary steam generator |
| tube leakage.                                                                |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
|                                                                              |
| * * * UPDATED AT 1350 ON 1/29/01 BY GOETHCHIUS, RECEIVED BY WEAVER * * *     |
|                                                                              |
| Upon further review, the closure of these isolation valves is not reportable |
| per 10 CFR 50.72.   These containment isolation valves are limited to a      |
| single system and therefore, no reporting is required.  Investigation of the |
| issue will be in accordance with our corrective action process.  This event  |
| is retracted   The licensee notified the NRC resident inspector.             |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37698       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WATERFORD                REGION:  4  |NOTIFICATION DATE: 01/29/2001|
|    UNIT:  [3] [] []                 STATE:  LA |NOTIFICATION TIME: 05:36[EST]|
|   RXTYPE: [3] CE                               |EVENT DATE:        01/28/2001|
+------------------------------------------------+EVENT TIME:        22:45[CST]|
| NRC NOTIFIED BY:  PELLEGRIN                    |LAST UPDATE DATE:  01/29/2001|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DALE POWERS          R4      |
|10 CFR SECTION:                                 |                             |
|AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PRESSURIZER STEAM SPACE SAMPLE ISOLATION VALVES FAILED TO CLOSE              |
|                                                                              |
| At 2245 on 1/28/01 it was discovered that PSL-303 and PSL-304, Pressurizer   |
| Steam Space Sample Inside and Outside Containment Isolation Valves would not |
| close when their respective control switches at OP-8 in the Control Room     |
| were taken to the "Close" position.  The valves had been open since 1455     |
| that same day to perform degas of the Pressurizer.  The Nuclear Plant        |
| Operator first took the switch for PSL-304 to the "Close" position and       |
| observed that the valve continued to indicate "Open".  He then took the      |
| Switch for PSL-303 to the "Close" position, and observed that valve continue |
| to indicate "Open".  Technical Specification 3.6.3 was entered and a Nuclear |
| Auxiliary Operator was dispatched to verify the position of PSL-304 locally. |
| PSL-304 was found to be in the open position and the on-shift chemistry      |
| technician confirmed that there were still indications of flow through the   |
| sample line.   Another attempt to close PSL-304 was made using the switch on |
| CP-8 in the control room.  The Nuclear Auxiliary Operator observed that the  |
| valve moved approximately one quarter-inch in the closed direction.   At     |
| 2257 PSL-304 was closed using the manual gagging device.   At 2310 PSL-304   |
| was de-energized to comply with the action requirements of Technical         |
| Specification 3.6.3.b.   At 0007 on 1/29/01, another attempt was made to     |
| close PSL-303 using the control switch at OP-8. This attempt was successful. |
| The affected containment penetration is a one-half-inch line and is          |
| currently isolated.  They are investigating the cause.                       |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37699       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HADDAM NECK              REGION:  1  |NOTIFICATION DATE: 01/29/2001|
|    UNIT:  [1] [] []                 STATE:  CT |NOTIFICATION TIME: 16:31[EST]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        01/29/2001|
+------------------------------------------------+EVENT TIME:        16:20[EST]|
| NRC NOTIFIED BY:  CHARLES REID                 |LAST UPDATE DATE:  01/29/2001|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DANIEL HOLODY        R1      |
|10 CFR SECTION:                                 |                             |
|*PRE 50.72(b)(2)(xi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Decommissioned   |0        Decommissioned   |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION                                                         |
|                                                                              |
| The licensee reported a spill of mercury greater than one pound mass to the  |
| State of Connecticut Department of Environmental Protection.  The spill was  |
| just over one pound mass and occurred in the primary auxiliary building.     |
| The spill has been contained and a contractor has been contacted to clean up |
| the spill.                                                                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37700       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CLINTON                  REGION:  3  |NOTIFICATION DATE: 01/29/2001|
|    UNIT:  [1] [] []                 STATE:  IL |NOTIFICATION TIME: 19:38[EST]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        01/29/2001|
+------------------------------------------------+EVENT TIME:        18:10[CST]|
| NRC NOTIFIED BY:  JEFF NADEN                   |LAST UPDATE DATE:  01/29/2001|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DAVID HILLS          R3      |
|10 CFR SECTION:                                 |                             |
|NONR                     OTHER UNSPEC REQMNT    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| FISH KILL                                                                    |
|                                                                              |
| Clinton Power Station personnel have been investigating the cause of a fish  |
| kill on Clinton Lake that was first discovered on January 24, 2001.   After  |
| reviewing environmental data, CPS has sufficient evidence to conclude that   |
| the plant trip on December 18, 2000, following a Group 1 isolation was the   |
| cause of the fish kill.   During this event, the main steam isolation valves |
| closed and all decay heat was removed through the suppression pool instead   |
| of the main condenser and discharge flume to the lake.  With the sudden loss |
| of heat, input into the discharge flume and the lake in the vicinity of the  |
| flume discharge, a rapid drop in lake temperature shocked the fish in this   |
| area causing a kill of an estimated 7000 fish. The majority of these fish    |
| were carp and buffalo head. CPS has provided pertinent plant data to the     |
| Illinois Department of Natural Resources and the Illinois Environmental      |
| Protection Agency.                                                           |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37701       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO               REGION:  3  |NOTIFICATION DATE: 01/30/2001|
|    UNIT:  [1] [] []                 STATE:  MN |NOTIFICATION TIME: 01:34[EST]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        01/30/2001|
+------------------------------------------------+EVENT TIME:        00:15[CST]|
| NRC NOTIFIED BY:  TEMPOE                       |LAST UPDATE DATE:  01/30/2001|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DAVID HILLS          R3      |
|10 CFR SECTION:                                 |                             |
|ASHU 50.72(b)(1)(i)(A)   PLANT S/D REQD BY TS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |99       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SAFETY RELIEF VALVES WERE DECLARED INOPERABLE                                |
|                                                                              |
| A Technical Specification shutdown was initiated as required by T.S. 3.6.E.2 |
| following the discovery that not all of Section XI requirements were met     |
| with respect to the safety relief valves.  The safety relief valves were     |
| declared inoperable @ 1830 on 1/29/01.  The reactor conditions shall be as   |
| follows within 24 hrs:  reactor pressure <110 psig and reactor temperature   |
| <345F.                                                                      |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
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