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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!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 |
| <345�F. |
| |
| The NRC Resident Inspector was notified. |
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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021