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Event Notification Report for July 2, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           06/29/2001 - 07/02/2001

                              ** EVENT NUMBERS **

38104  38105  38106  38107  38108  38109  38110  38111  

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|General Information or Other                     |Event Number:   38104       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  GE NUCLEAR ENERGY                    |NOTIFICATION DATE: 06/29/2001|
|LICENSEE:  GE NUCLEAR ENERGY                    |NOTIFICATION TIME: 13:31[EDT]|
|    CITY:  SAN JOSE                 REGION:  4  |EVENT DATE:        06/29/2001|
|  COUNTY:                            STATE:  CA |EVENT TIME:             [PDT]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  06/29/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |GREG PICK            R4      |
|                                                |RICHARD BARKLEY      R1      |
+------------------------------------------------+THOMAS DECKER        R2      |
| NRC NOTIFIED BY:  JASON POST                   |GEOFFREY WRIGHT      R3      |
|  HQ OPS OFFICER:  FANGIE JONES                 |VERN HODGE (FAX)     NRR     |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 10 CFR 21 REPORT:  STABILITY RELOAD LICENSING CALCULATIONS MAY BE            |
| NON-CONSERVATIVE                                                             |
|                                                                              |
| "This letter provides information concerning the potential for               |
| non-conservative reload licensing calculations for plants which have         |
| implemented stability detect and suppress trip systems. The non-conservatism |
| could result in (1) Option III stability trip system setpoints which do not  |
| provide Minimum Critical Power Ration (MCPR) Safety Limit protection, and    |
| (2) inadequate MCPR safety limit protection from the flow-biased Average     |
| Power Range Monitor (APRM) flux trip for plants which have implemented       |
| Option I-D or Option 11. This notification is provided under 10 CFR Part     |
| 21(d) as a reportable condition for Hatch Units 1 and 2, and as an interim   |
| report per 21.21(a)(2) for the other plants listed in Attachment 1: the     |
| full impact of this deviation cannot be completed within 60 days from the    |
| date of discovery. Therefore, this notification describes the deviation that |
| is being evaluated by GE Nuclear Energy (GE-NE) for associated safety        |
| related reload licensing calculations supplied to licensees by GE-NE and     |
| states when the evaluation will be completed.                                |
|                                                                              |
| "In addition, GE-NE does not have the capability to perform the evaluation   |
| to determine if a defect exists for plants at which GE-NE is not responsible |
| for stability reload licensing calculations. GE-NE has transferred           |
| information pursuant to 21.21(b) to those licensees which are known to be   |
| potentially affected.                                                        |
|                                                                              |
| "GE-NE has informed all BWR utilities of this issue through the BWROG        |
| Potential Issues Response Team (PIRT). All potentially affected utilities    |
| have been notified. Compensatory action has been taken at the plants which   |
| have been determined to be reportable. Additional information is included in |
| this notification and has been provided to the potentially affected          |
| licensees so that they can determine if the concern impacts their stability  |
| detect and suppress reload licensing calculations."                          |
|                                                                              |
| All GE BWR plants are potentially affected.                                  |
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|General Information or Other                     |Event Number:   38105       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  KANSAS DEPT OF HEALTH & ENVIRONMENT  |NOTIFICATION DATE: 06/29/2001|
|LICENSEE:  CHEMSYN SCIENCE LABORATORIES         |NOTIFICATION TIME: 14:13[EDT]|
|    CITY:  LENEXA                   REGION:  4  |EVENT DATE:        06/28/2001|
|  COUNTY:                            STATE:  KS |EVENT TIME:        13:30[CDT]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  06/29/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |GREG PICK            R4      |
|                                                |PATRICIA HOLAHAN     NMSS    |
+------------------------------------------------+THOMAS DECKER        R2      |
| NRC NOTIFIED BY:  JAMES JOHNSON                |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT:  MISSING SHIPMENT OF RADIONUCLIDE                    |
|                                                                              |
| Kansas Department of Health (KDHE) was notified that a shipment to Inveresk  |
| Research in Scotland was reported missing from the Federal Express at their  |
| Memphis, TN hub terminal .  The shipment from Chemsyn Science Laboratories   |
| of Lenexa, Kansas was 3.5 mCi of radiolabeled (inidazol-2-14C) NED 2000-1    |
| dibenzenesulfonate.  The shipment was sent on 6/19/2001 and the search was   |
| started on 6/26/2001 when Inveresk contacted Chemsyn about not receiving     |
| shipment.                                                                    |
|                                                                              |
| Federal Express found the overpack, a dry ice chest (16" x 16" x 23") which  |
| originally contained 54 pounds of dry ice and the small Type A Package.  The |
| small Type A Package has not been located.                                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38106       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT          REGION:  1  |NOTIFICATION DATE: 06/29/2001|
|    UNIT:  [] [2] []                 STATE:  NY |NOTIFICATION TIME: 19:19[EDT]|
|   RXTYPE: [1] GE-2,[2] GE-5                    |EVENT DATE:        06/29/2001|
+------------------------------------------------+EVENT TIME:        17:15[EDT]|
| NRC NOTIFIED BY:  ANTHONY PETRELLI             |LAST UPDATE DATE:  06/29/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |RICHARD BARKLEY      R1      |
|10 CFR SECTION:                                 |                             |
|AINA 50.72(b)(3)(v)(A)   POT UNABLE TO SAFE SD  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| NON-CONSERVATIVE ANALYSIS FOR OPRM SCRAM SETPOINTS                           |
|                                                                              |
| "On June 29, 2001, General Electric informed Niagara Mohawk Power            |
| Corporation of a non-conservative analysis that supports Operation Power     |
| Range Monitor (OPRM) scram setpoints. The non-conservative analysis is       |
| generic and has the potential to affect all stability option III and I-D     |
| plants.                                                                      |
|                                                                              |
| "The consequences of the non-conservative analysis are that the associated   |
| OPRM Reactor Protection System (RPS) scram setpoints are also                |
| non-conservative. The non-conservative RPS setpoints may result in violating |
| the Minimum Critical Power Ratio (MCPR) safety limit during a                |
| thermal-hydraulic instability.                                               |
|                                                                              |
| "All OPRM channels have been declared inoperable. Technical Specification    |
| 3.3.1.1 Action F requires an alternate method of detecting and suppressing   |
| thermal-hydraulic instabilities to be implemented within 12 hours. Alternate |
| methods are already established in procedures N2-SOP-29 and N2-RESP-12.      |
| Therefore, the Technical Specification required action is satisfied. These   |
| alternate methods are the same methods used prior to implementation of the   |
| OPRM scram function.                                                         |
|                                                                              |
| "Nine Mile Point Unit 2 has 120 days to restore the OPRMs to an operable     |
| condition. If the 120 day allowed outage time is exceeded, the Unit must be  |
| in at least STARTUP within the following six hours.                          |
|                                                                              |
| "This report is being made as required by 10CFR50.72 (B) (3) (V) (A) as      |
| condition that could have prevented the fulfillment of the safety function   |
| of a system needed to shutdown the reactor."                                 |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
|                                                                              |
| See EN #38104, GE Nuclear Energy 10 CFR 21 report.                           |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38107       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WATTS BAR                REGION:  2  |NOTIFICATION DATE: 06/29/2001|
|    UNIT:  [1] [] []                 STATE:  TN |NOTIFICATION TIME: 21:12[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        06/29/2001|
+------------------------------------------------+EVENT TIME:        17:28[EDT]|
| NRC NOTIFIED BY:  WILLIAM RUSSELL              |LAST UPDATE DATE:  06/29/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |THOMAS DECKER        R2      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |
|AESF 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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     M/R        Y       100      Power Operation  |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MANUAL REACTOR TRIP PER PROCEDURE DUE TO INCREASING CONDENSER PRESSURE       |
|                                                                              |
| "Watts Bar Unit 1 was manually tripped when the main condenser backpressure  |
| reached limits required by procedure. The rise in the backpressure was       |
| caused by a reduced condenser circulating water (CCW) flow which resulted    |
| from cooling tower fill material obstructing suction screens to the CCW      |
| pumps. All safety systems responded as required during the event. Auxiliary  |
| Feedwater initiated due to reactor trip with low Tavg, as required. All      |
| control rods inserted properly. Inspections are under way to determine the   |
| extent of the debris in the system."                                         |
|                                                                              |
| The licensee notified the NRC Resident Inspector.  They will be notifying    |
| the State and Local authorities due to noise from the use of steam generator |
| atmospheric reliefs for excess heat removal while the condenser is not       |
| available.                                                                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   38108       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  JACA & SIERRA TESTING LABS           |NOTIFICATION DATE: 06/30/2001|
|LICENSEE:  JACA & SIERRA TESTING LABS           |NOTIFICATION TIME: 15:00[EDT]|
|    CITY:  TRUJILLO ALTO            REGION:  2  |EVENT DATE:        06/30/2001|
|  COUNTY:                            STATE:  PR |EVENT TIME:             [EDT]|
|LICENSE#:                        AGREEMENT:  N  |LAST UPDATE DATE:  06/30/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |THOMAS DECKER        R2      |
|                                                |PATRICIA HOLAHAN     NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  MARCOS AROCHO                |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| STOLEN MOISTURE DENSITY GAUGE                                                |
|                                                                              |
| A pickup truck with a stored and locked Troxler moisture density gauge       |
| (serial # M1A03A16A) was stolen sometime this morning (6/30/01) in San Juan, |
| Puerto Rico.  The gauge contains sealed sources of Cs-137 (10 mCi) and       |
| Am-241/Be (50 mCi).  The local police and the Puerto Rico Civil Defense have |
| been notified.  There has been a press release and their will be television  |
| announcements.                                                               |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38109       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PEACH BOTTOM             REGION:  1  |NOTIFICATION DATE: 07/01/2001|
|    UNIT:  [2] [] []                 STATE:  PA |NOTIFICATION TIME: 04:35[EDT]|
|   RXTYPE: [2] GE-4,[3] GE-4                    |EVENT DATE:        07/01/2001|
+------------------------------------------------+EVENT TIME:        02:10[EDT]|
| NRC NOTIFIED BY:  ALAN DAY                     |LAST UPDATE DATE:  07/01/2001|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |RICHARD BARKLEY      R1      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |
|AESF 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     A/R        Y       100      Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC TURBINE TRIP/REACTOR SCRAM DURING TROUBLESHOOTING                  |
|                                                                              |
| "During troubleshooting of Peach Bottom Unit 2 electrohydraulic control      |
| (EHC) system, the main turbine control valves fast closed, resulting in an   |
| automatic turbine trip, reactor protection system (RPS) trip and reactor     |
| scram.                                                                       |
|                                                                              |
| "Additionally, as a normal result of the reactor scram, reactor water level  |
| lowered below 1 inch, causing a valid automatic group II/III primary         |
| containment isolation signal (PCIS) in multiple trains.                      |
|                                                                              |
| "The plant responded normally, RPS and PCIS signals were reset and unit 2 is |
| continuing to a cooled-down depressurized condition.  No radiological        |
| release"                                                                     |
|                                                                              |
| The NRC resident inspector has been informed of this event by the licensee.  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38110       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE              REGION:  2  |NOTIFICATION DATE: 07/01/2001|
|    UNIT:  [1] [2] []                STATE:  FL |NOTIFICATION TIME: 15:07[EDT]|
|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        07/01/2001|
+------------------------------------------------+EVENT TIME:        14:10[EDT]|
| NRC NOTIFIED BY:  SCOT OEHRLE                  |LAST UPDATE DATE:  07/01/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |THOMAS DECKER        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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       90       Power Operation  |90       Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION DUE TO INJURED LOGGERHEAD SEA TURTLE                    |
|                                                                              |
| The licensee notified the State of Florida Fish and Wildlife Commission      |
| about the discovery of an injured loggerhead sea turtle from the intake bay. |
| The turtle is being transported to rehabilitation.                           |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38111       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALISADES                REGION:  3  |NOTIFICATION DATE: 07/01/2001|
|    UNIT:  [1] [] []                 STATE:  MI |NOTIFICATION TIME: 17:20[EDT]|
|   RXTYPE: [1] CE                               |EVENT DATE:        07/01/2001|
+------------------------------------------------+EVENT TIME:        13:30[EDT]|
| NRC NOTIFIED BY:  DANIEL MALONE                |LAST UPDATE DATE:  07/01/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |GEOFFREY WRIGHT      R3      |
|10 CFR SECTION:                                 |GENE IMBRO           NRR     |
|ADEG 50.72(b)(3)(ii)(A)  DEGRADED CONDITION     |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| NON-DESTRUCTIVE EXAMINATION OF CRDM PRESSURE HOUSING FOUND CRACK INDICATION  |
|                                                                              |
| "During non-destructive examination (NDE) of welds on control rod drive      |
| mechanism (CRDM) pressure housings, an indication was discovered on CRDM-40. |
| The method being utilized was ultrasonic testing (UT). The indication is     |
| axial, approximately 0.7 inches long, located-on the inner surface of the    |
| pressure housing. The depth of the indication is approximately 50%           |
| through-wall. The indication is located in the top side heat affected zone   |
| of an 8 inch butt weld which joins the pressure housing's tubular section to |
| an eccentric reducer. The material of the pressure housing is type 347       |
| stainless steel.                                                             |
|                                                                              |
| "The weld examinations were being conducted as part of an extent of          |
| condition evaluation resulting from an earlier discovery, on June 21, 2001,  |
| of a through-wall axial indication on CRDM-21. The CRDM-40 indication        |
| location corresponds to the location of the earlier discovered indication in |
| CRDM-21(EN #38083) and CRDM-25 (EN #38103). Cause evaluation is ongoing."    |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+