Event Notification Report for June 11, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           06/08/2001 - 06/11/2001

                              ** EVENT NUMBERS **

37902  37920  38058  38059  38060  

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|Power Reactor                                    |Event Number:   37902       |
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| FACILITY: CRYSTAL RIVER            REGION:  2  |NOTIFICATION DATE: 04/09/2001|
|    UNIT:  [3] [] []                 STATE:  FL |NOTIFICATION TIME: 11:08[EDT]|
|   RXTYPE: [3] B&W-L-LP                         |EVENT DATE:        04/09/2001|
+------------------------------------------------+EVENT TIME:        09:54[EDT]|
| NRC NOTIFIED BY:  RICHARD SWEENEY              |LAST UPDATE DATE:  06/10/2001|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |CAUDLE JULIAN        R2      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(xi)     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  |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| OFFSITE NOTIFICATION TO THE NATIONAL MARINE AND FISHERIES SERVICE AS A       |
| RESULT OF THE ENDANGERED SEA TURTLES NON-LETHAL TAKE LIMIT BEING EXCEEDED    |
|                                                                              |
| "On April 09, 2001 at 0940 the 40th non-lethal sea turtle take in the        |
| biennial period occurred.                                                    |
|                                                                              |
| "In accordance with Crystal River Unit #3 Operating License, Appendix B,     |
| Environmental Protection Plan (Non-Radiological),  'Endangered or threatened |
| sea turtles shall be protected in accordance with the Incidental Take        |
| Statement issued by the National Marine and Fisheries Service (NMFS).'  The  |
| NMFS has established numerical limits on live takes, lethal takes causally   |
| related to plant operation, and lethal takes not related to plant            |
| operations.                                                                  |
|                                                                              |
| "The NMFS must be notified within five days whenever:                        |
|                                                                              |
| a.  The 40th non-lethal take occurs in the biennial period, or               |
| b.  The third causally related mortality occurs in the biennial period, or   |
| c.   The sixth non-causally related mortality occurs in the biennial         |
| period.                                                                      |
|                                                                              |
| "The current biennial period for monitoring sea turtle takes began January   |
| 1, 2001.                                                                     |
|                                                                              |
| "Thus, in accordance with Crystal Unit #3 Administrative Instruction 571,    |
| Sea Turtle Rescue and Handling Guidance, the NMFS must be notified within    |
| five days.                                                                   |
|                                                                              |
| "In accordance with Crystal River Unit #3 Compliance Procedure 151, External |
| Reporting Requirements, this 40th non-lethal sea turtle take is Reportable   |
| as a 4-Hour Report under 10 CFR 50.72(b)(2)(xi) as this event is related to  |
| the protection of the environment for which a notification to other          |
| government agencies has been or will be made."                               |
|                                                                              |
| The licensee will inform the NRC resident inspector.                         |
|                                                                              |
| * * * UPDATE 0944EDT ON 4/10/01 FROM R. SWEENEY TO S. SANDIN * * *           |
|                                                                              |
| "On April 10, 2001 at 0859 the 41st non-lethal sea turtle take in the        |
| biennial period occurred."                                                   |
|                                                                              |
| The licensee informed the NRC resident inspector.  Notified R2DO(Julian).    |
|                                                                              |
| ***** UPDATE RECEIVED AT 0911 ON 04/17/01 FROM CHRISTOPHER PELLERIN TO LEIGH |
| TROCINE *****                                                                |
|                                                                              |
| The 42nd, non-lethal, sea turtle take in the biennial period occurred at     |
| 0810 on April 17, 2001.                                                      |
|                                                                              |
| The licensee notified the NRC resident inspector.  The NRC operations        |
| officer notified the R2DO (Ernstes).                                         |
|                                                                              |
| * * * UPDATE 1125 EDT ON 5/1/01 FROM DAVID SCHULKER TO FANGIE JONES * * *    |
|                                                                              |
| "On May 1, 2001 at 0805 a turtle was identified as the 43rd rescued, live    |
| sea turtle in this biennial period.  This sea turtle will be kept for a      |
| short observation period and then safely returned to the environment."       |
|                                                                              |
| The licensee will inform the NRC Resident Inspector and the National         |
| Wildlife and Fisheries Service.  Notified R2DO(Jay Henson).                  |
|                                                                              |
| * * * UPDATE ON 5/29/01 BY FERGUSON TO SANDIN * * *                          |
|                                                                              |
| On May 29, 2001 at 0943 two turtles were identified as the 44th and 45th     |
| rescued, Iive Sea turtles in this biennial period. These healthy sea turtles |
| will be kept for a short observation period and then safely returned to the  |
| environment.                                                                 |
|                                                                              |
|                                                                              |
| This is Reportable as a 4-Hour Report under 10 CFR 50.72 (b) (2) (xi) as     |
| this event is related to the protection of the environment for which a       |
| notification to other government agencies has been or will be made. This is  |
| an update to event 37902.                                                    |
|                                                                              |
| The NRC Resident Inspector was notified.  The REG2 RDO(Barr) was informed.   |
|                                                                              |
| * * * UPDATE 2014 EDT 6/4/2001 FROM RAWLS TAKEN BY STRANSKY * * *            |
|                                                                              |
| On June 4, 2001 at 1815, the 46th non-lethal sea turtle (Kemp's Ridley) take |
| in the biennial period occurred. The license has informed the NRC resident   |
| inspector.  Notified R2DO (Barr).                                            |
|                                                                              |
| * * * UPDATE 1315EDT ON 6/10/01 FROM CHARLES J. MORRIS TO S. SANDIN * * *    |
|                                                                              |
| On June 10, 2001 at 1100, the 47th non-lethal sea turtle take in the         |
| biennial period occurred. The license has informed the NRC resident          |
| inspector.  Notified R2DO (Bonser).                                          |
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!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   37920       |
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| FACILITY: MONTICELLO               REGION:  3  |NOTIFICATION DATE: 04/15/2001|
|    UNIT:  [1] [] []                 STATE:  MN |NOTIFICATION TIME: 17:15[EDT]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        04/15/2001|
+------------------------------------------------+EVENT TIME:        11:50[CDT]|
| NRC NOTIFIED BY:  DUSTIN WRIGHT                |LAST UPDATE DATE:  06/08/2001|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |MICHAEL PARKER       R3      |
|10 CFR SECTION:                                 |                             |
|AINB 50.72(b)(3)(v)(B)   POT RHR INOP           |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| BOTH LOW PRESSURE COOLANT INJECTION (LPCI) PATHS TEMPORARILY INOPERABLE      |
|                                                                              |
| Procedure inadequacies for venting RHR System using Ops Manual B.08.01.03-05 |
| resulted in Tech Spec LCO(s) 3.5.A declaring both LPCI Injection Paths       |
| inoperable (72 Hour LCO) and Tech Spec 3.5.C  for one Division of            |
| Containment Spray and Cooling inoperable (7 Day LCO) NOT entered.   Contrary |
| to Ops Procedure #2145 RHR System Discharge Venting these LCO(s) should be   |
| entered when RHR is vented.  Notifications are being made because a vent     |
| valve was opened which made both LPCI Injection Paths inoperable.  This      |
| condition at the time of discovery could have prevented the fulfillment of   |
| the safety function or system that is needed for Residual Heat Capacity.     |
| The vent valve is closed and verified closed.   The RHR System is Operable   |
| at this time.                                                                |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
|                                                                              |
| * * * UPDATE 1645EDT ON 6/8/01 FROM DUANE SCHMIDT TO S. SANDIN * * *         |
|                                                                              |
| The licensee is retracting this report based on the following:               |
|                                                                              |
| "On April 15, 2001, we reported that the opening of a vent valve made both   |
| LPCI Injection Paths Inoperable causing the loss of the LPCI safety          |
| function. This operation was a planned evolution in accordance with approved |
| procedures, as it was prescribed by the Operations Manual. As such, there    |
| was not a loss of the LPCI safety function and thus this is not reportable   |
| per the guidance in NUREG 1022, page 56."                                    |
|                                                                              |
| The licensee informed the NRC resident inspector.  Notified R3DO(Clayton).   |
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|Power Reactor                                    |Event Number:   38058       |
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| FACILITY: DUANE ARNOLD             REGION:  3  |NOTIFICATION DATE: 06/08/2001|
|    UNIT:  [1] [] []                 STATE:  IA |NOTIFICATION TIME: 00:41[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        06/07/2001|
+------------------------------------------------+EVENT TIME:        21:33[CDT]|
| NRC NOTIFIED BY:  ROBINSON                     |LAST UPDATE DATE:  06/08/2001|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |BRENT CLAYTON        R3      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(3)(v)(D)   ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       47       Power Operation  |47       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HPCI DECLARED INOPERABLE DUE TO A FAULTY FLOW INDICATING SWITCH              |
|                                                                              |
| With DAEC operating in mode 1, at approximately 47% power, HPCI was declared |
| inoperable due to a faulty flow indicating switch which is utilized to       |
| position the minimum flow valve.  A 14-day LCO was entered per Technical     |
| Specification 3.5.1, condition F, at 2133 on 6/7/01.  This condition is      |
| reportable under 50.72(b)(3)(v)(D) and 50.73(a)(2)(v)(D) as a failure of a   |
| single train of equipment required to mitigate the consequences of an        |
| accident.                                                                    |
|                                                                              |
| While an in-plant operator was performing his rounds within the HPCI room,   |
| he discovered that flow indicating switch, FS2310, which should indicate     |
| total HPCI flow, indicated approximately -170 gpm rather than the expected   |
| zero gpm.  The HPCI pump was not in operation.  This flow switch is          |
| interlocked with the HPCI minimum flow valve, allowing it to open with total |
| HPCI flow less than 300 gpm and HPCI discharge pressure greater than 125     |
| psig.  The flow switch would close the minimum flow valve once HPCI total    |
| flow reached 600 gpm.  With the correct operation of the HPCI minimum flow   |
| valve in question, HPCI was declared inoperable.                             |
|                                                                              |
| It is believed that the cause of the faulty indication is air in the         |
| instrument sensing lines feeding the flow switch. Troubleshooting efforts    |
| will begin early tomorrow morning.                                           |
|                                                                              |
| The NRC Resident Inspector was notified                                      |
|                                                                              |
|                                                                              |
| HOO NOTE:  see event #38029                                                  |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38059       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM                  REGION:  1  |NOTIFICATION DATE: 06/08/2001|
|    UNIT:  [1] [] []                 STATE:  MA |NOTIFICATION TIME: 17:12[EDT]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        06/08/2001|
+------------------------------------------------+EVENT TIME:        16:15[EDT]|
| NRC NOTIFIED BY:  ERIC OLSON                   |LAST UPDATE DATE:  06/08/2001|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |MICHELE EVANS        R1      |
|10 CFR SECTION:                                 |M. WAYNE HODGES      NMSS    |
|KSNM 70.52(a)            LOSS OF SNM/CRIT       |TAD MARSH            NRR     |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| SPECIAL NUCLEAR MATERIAL (SNM) REPORT INVOLVING 1 MILLIGRAM U-235            |
|                                                                              |
| "During [the] process of replacing the 'A' Transverse In-Core Probe (TIP)    |
| Detector, the old detector was removed and its serial number recorded.  The  |
| serial number was not the serial number expected.  The expected serial       |
| number was 6553444 and the detector that was removed had serial number       |
| 6608500.  The TIP detector is a fission chamber that utilizes approximately  |
| 1 milligram of enriched uranium and is therefore treated as SNM.             |
|                                                                              |
| "During 1975 to 1986, Pilgrim did not track TIP detectors as SNM due to      |
| being less than one gram of SNM.  It is suspected that during this time      |
| frame this detector was changed out.  In 1987 a records search was made but  |
| did not reveal maintenance performed on this detector.  However, an          |
| intensive records search will be performed as well as corrective actions yet |
| to be determined."                                                           |
|                                                                              |
| The licensee informed the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38060       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH                    REGION:  2  |NOTIFICATION DATE: 06/10/2001|
|    UNIT:  [1] [2] []                STATE:  GA |NOTIFICATION TIME: 11:12[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        06/10/2001|
+------------------------------------------------+EVENT TIME:        07:15[EDT]|
| NRC NOTIFIED BY:  BRUCE BUTLER                 |LAST UPDATE DATE:  06/10/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |BRIAN BONSER         R2      |
|10 CFR SECTION:                                 |TAD MARSH            NRR     |
|ISFS 72.75               SPENT FUEL CASK EVENT  |M. WAYNE HODGES      NMSS    |
|                                                |JOSEPH HOLONICH      IRO     |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| POSSIBLE SPENT FUEL STORAGE CAST DEFECT AND POTENTIAL SIGNIFICANT REDUCTION  |
| IN EFFECTIVENESS OF THE SPENT FUEL STORAGE CASK CONFINEMENT SYSTEM DUE TO    |
| FAILURE OF MULTI-PURPOSE CANISTER (MPC) VENT AND DRAIN CAPS TO FULLY CLOSE   |
| (4-HOUR REPORT)                                                              |
|                                                                              |
| As part of the dry storage project, the licensee has loaded one MPC-68.      |
| (This MPC holds 68 fuel bundles.)  Subsequent to system vacuum drying and    |
| helium backfilling, the vent and drain caps failed to fully close (at 0715). |
| These caps are currently about half closed, and they appear to be stuck in   |
| that position.                                                               |
|                                                                              |
| At this time, the licensee is not aware of the loss of any helium.  Licensee |
| personnel have snooped for helium in the area and near the fittings.         |
| Licensee personnel are also currently in the process of installing pressure  |
| gauges to verify that the proper amount of helium remains in the MPC.  The   |
| licensee plans to place a helium purge on the system if it is determined     |
| that helium is being lost.  The licensee also notified the cask supplier     |
| (Holtec International). The supplier informed the licensee that the presents |
| of helium will keep the system closed.                                       |
|                                                                              |
| The technical specifications that apply to dry storage state that the MPC    |
| shall be dry and helium filled, and a helium backfill density limit is also  |
| specified.  The licensee stated that this technical specification density    |
| requirement was met before the attempt to close the vent and drain caps.     |
| At this time, the licensee believes that this limit is still being met.      |
| However, the licensee is not positive that this limit is being met with the  |
| vent and drain caps in the current position.  Therefore, the applicable      |
| technical specification limiting condition for operation (LCO) was entered.  |
| This LCO requires the licensee to perform an engineering evaluation to       |
| determine the impact of helium differential within 72 hours and to develop   |
| and initiate corrective actions necessary to return the MPC to an analyzed   |
| condition within 14 days.                                                    |
|                                                                              |
| In addition, the applicable technical specifications also specify an MPC     |
| helium leak rate limit.  The LCO for this specification was also entered.    |
| It requires the licensee to perform an engineering evaluation to determine   |
| the impact of increased helium leak rate on heat removal capability and      |
| offsite dose within 24 hours and to develop and initiate corrective actions  |
| necessary to return the MPC to an analyzed condition within 7 days.  (The    |
| supplier is currently performing an engineering evaluation for the licensee, |
| and the results are expected to be available later today.)                   |
|                                                                              |
| The licensee is making this notification as a 4-hour report in accordance    |
| with 10 CFR 72.216(a)(1) and (2) for any instance of a defect in any spent   |
| fuel storage cask structure, system, or component which is important to      |
| safety and for a significant reduction in the effectiveness of any spent     |
| fuel storage cask confinement system during use of the storage cask under a  |
| general license issued under 10 CFR 72.210.                                  |
|                                                                              |
| HOO NOTE:  In accordance with 65 FR 63788 on 10/25/00, the reporting         |
| requirements of 10 CFR 72.216 were revised (effective 01/23/01) to require   |
| that licensees make initial and written reports in accordance with 10 CFR    |
| 72.74 and 72.75.  Therefore, more appropriate reporting requirements for     |
| this 4-hour report are believed to be 10 CFR 72.75(b)(2) and (3).            |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.                     |
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