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Event Notification Report for June 22, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           06/21/2000 - 06/22/2000

                              ** EVENT NUMBERS **

37051  37060  37098  37099  37100  37101  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   37051       |
+------------------------------------------------------------------------------+
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| FACILITY: NINE MILE POINT          REGION:  1  |NOTIFICATION DATE: 06/02/2000|
|    UNIT:  [] [2] []                 STATE:  NY |NOTIFICATION TIME: 19:24[EDT]|
|   RXTYPE: [1] GE-2,[2] GE-5                    |EVENT DATE:        06/02/2000|
+------------------------------------------------+EVENT TIME:        17:21[EDT]|
| NRC NOTIFIED BY:  TOM CHWALEK                  |LAST UPDATE DATE:  06/21/2000|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |RICHARD BARKLEY      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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| REACTOR CORE ISOLATION COOLING SYSTEM INOPERABLE DUE TO A FAULTY LEVEL       |
| SWITCH -                                                                     |
|                                                                              |
| At 1721 on 06/02/00, Nine Mile Point Unit 2 received a Reactor Core          |
| Isolation Cooling (RCIC) System high point vent low level annunciator alarm. |
| This alarm came in and cleared repeatedly.  The licensee declared the RCIC   |
| System inoperable but functional and entered Technical Specification 3.7.4   |
| which requires the RCIC System to be restored to operable status within 14   |
| days.  The licensee closed the RCIC System turbine trip throttle valve,      |
| #2ICS*MOV150 in accordance with the annunciator response procedure.  The     |
| licensee then performed the RCIC System fill and vent procedure              |
| #N2-OSP-ICS-M001 satisfactorily with a solid stream of water being vented    |
| and no evidence of air in the system.  The high point vent low level         |
| annunciator alarm remained in solid following the fill and vent procedure.   |
| The licensee suspects that a  faulty high point vent level switch is the     |
| problem and prepared a Problem Identification to repair the switch.  The     |
| licensee has returned the RCIC System to available status (but still         |
| inoperable) and is reviewing compensatory actions for the faulty level       |
| switch to support the return of the RCIC System to operable status.          |
|                                                                              |
| This event has no effect on Unit 1 which is at 100% power.                   |
|                                                                              |
| The licensee plans to notify the NRC Resident Inspector.                     |
|                                                                              |
| * * * RETRACTED AT 1446 EDT ON 6/21/00 BY MATT WALDECKER TO FANGIE JONES * * |
| *                                                                            |
|                                                                              |
| "On June 2, 2000 at 1721 hours, the reactor core isolation cooling system    |
| was declared inoperable when a high point vent level low annunciator alarmed |
| and cleared repeatedly. The reactor core isolation cooling trip throttle     |
| valve was closed in accordance with the annunciator response procedure.      |
|                                                                              |
| "Subsequent review has determined that the high point vent level low         |
| annunciator alarming and clearing repeatedly was due to a failed level       |
| switch. Correct high point vent water level was verified utilizing an        |
| approved operating procedure. 50.72(b)(2)(iii) and 50.73(a)(2)(v) reporting  |
| criteria covers an event or condition where structures, components, or       |
| trains of a safety system could have failed to perform their safety function |
| because of equipment failures. The failure of the high point level switch    |
| does not constitute an event or condition which rendered the Reactor Core    |
| Isolation Cooling System incapable of performing its safety function. In     |
| addition, the level switch is only used to warn the operators of decreasing  |
| water inventory in the reactor core isolation cooling discharge line. No     |
| credit is taken for the level switch in any safety analyses and does not     |
| directly control the removal of residual heat (the safety function) from the |
| Reactor Vessel. Therefore, this event is not reportable.                     |
|                                                                              |
| "The operator action to close the reactor core isolation cooling trip        |
| throttle valve in accordance with the annunciator response procedure does    |
| not constitute an event or condition as discussed in the NUREG-1022.         |
| Therefore, notification of this event is being retracted."                   |
|                                                                              |
| The licensee notified the NRC Resident Inspector.  The R1DO (Robert Summers) |
| was notified.                                                                |
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!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37060       |
+------------------------------------------------------------------------------+
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| FACILITY: DUANE ARNOLD             REGION:  3  |NOTIFICATION DATE: 06/06/2000|
|    UNIT:  [1] [] []                 STATE:  IA |NOTIFICATION TIME: 06:02[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        06/06/2000|
+------------------------------------------------+EVENT TIME:        02:36[CDT]|
| NRC NOTIFIED BY:  JOHN VAN SICKEL              |LAST UPDATE DATE:  06/21/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:                                |JOHN JACOBSON        R3      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SECONDARY CONTAINMENT DECLARED INOPERABLE DUE TO LOSS OF WATER SEAL CAUSED   |
| BY PIPE CORROSION                                                            |
|                                                                              |
| "A 4 inch diameter floor drain outlet pipe inside the Standby Gas Treatment  |
| Sump was identified by Operating personnel to be corroded through near the   |
| wall of the sump. This piping is designed to act as a Secondary Containment  |
| boundary which is used to form a loop seal between the Reactor Building and  |
| the SBGT room. Normally, the piping would come out from the wall and make a  |
| 90 degree turn to near the bottom of the sump, and open under water.         |
| However, with the erosion occurring near the wall of the sump, a breech of   |
| secondary containment exists. Due to the amount of corrosion, the opening    |
| was estimated to be 12.57 square inches. Additionally, damaged seals on two  |
| other doors (#225 and #128) located on airlocks associated with Secondary    |
| Containment accounted for another 7 square inches, for a total of 19.57      |
| square inches. Openings in excess of 12.7 square inches in this              |
| configuration have not been tested/evaluated. Therefore, Secondary           |
| Containment was considered inoperable. Operations entered Technical          |
| Specification LCO 3.6.4.1, condition A, for Secondary Containment inoperable |
| in Mode 1 at 0236[CDT]. Required action A.1 is to restore Secondary          |
| Containment to operable status in 4 hours.                                   |
|                                                                              |
| "Operations took actions to prohibit access through the two seal damaged     |
| doors/airlocks by posting them to prevent access. Once administrative        |
| control of the doors was established, the known opening in secondary         |
| containment was reduced to the corroded pipe in the SBGT sump, or 12.57      |
| square inches. This is less than the 12.7 square inches allowed. Technical   |
| Specification LCO 3.6.4.1, condition A, was exited at 0258[CDT]."            |
| The licensee informed the NRC Resident Inspector.                            |
|                                                                              |
| * * * UPDATE AT 0903 ON 06/21/00 BY BOB NURRELL TO JOLLIFFE * * *            |
|                                                                              |
| Upon further engineering review, the licensee has determined that during     |
| this event, secondary containment was operable based on the actual measured  |
| opening size (2.25 square inches).  Therefore, since secondary containment   |
| was not inoperable, this event is not reportable under the specified         |
| criterion and no other criteria apply and thus, the licensee desires to      |
| retract this event.  The licensee notified the NRC Resident Inspector.       |
| The NRC Operations Officer notified the R3DO Roger Lanksbury.                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37098       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: ROBINSON                 REGION:  2  |NOTIFICATION DATE: 06/21/2000|
|    UNIT:  [2] [] []                 STATE:  SC |NOTIFICATION TIME: 05:08[EDT]|
|   RXTYPE: [2] W-3-LP                           |EVENT DATE:        06/21/2000|
+------------------------------------------------+EVENT TIME:        02:57[EDT]|
| NRC NOTIFIED BY:  AL GARROU                    |LAST UPDATE DATE:  06/21/2000|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |KERRY LANDIS         R2      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     M/R        Y       68       Power Operation  |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - MANUAL REACTOR TRIP FROM 68% POWER DUE TO UNISOLABLE EHC SYSTEM OIL LEAK   |
| -                                                                            |
|                                                                              |
| At 0257 on 06/21/00, control room operators manually tripped the plant from  |
| 68% power due to an unisolable electrohydraulic control (EHC) system oil     |
| leak which caused main turbine control valve oscillations.  Two control rod  |
| bottom lights, shutdown bank 'A' and control bank 'C' did not illuminate;    |
| however, the control rod position indications showed that all control rods   |
| were fully inserted into the core.   The auxiliary feedwater system          |
| actuated, as expected.  Steam is being dumped to the main condenser.  The    |
| plant is stable in Mode 3 (Hot Standby).                                     |
|                                                                              |
| The licensee is repairing the oil leak and investigating the problem with    |
| the control rod bottom lights.                                               |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37099       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  NC DIVISION OF RADIATION PROTECTION  |NOTIFICATION DATE: 06/21/2000|
|LICENSEE:  APA CONSTRUCTION COMPANY             |NOTIFICATION TIME: 10:28[EDT]|
|    CITY:  SILER CITY               REGION:  2  |EVENT DATE:        06/20/2000|
|  COUNTY:                            STATE:  NC |EVENT TIME:        15:10[EDT]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  06/21/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |KERRY LANDIS         R2      |
|                                                |BOB AYRES            NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  LEE COX, NC DRP              |                             |
|  HQ OPS OFFICER:  DICK JOLLIFFE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|NDAM                     DAMAGED GAUGE/DEVICE   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - TROXLER MOISTURE DENSITY GAUGE RUN OVER BY A TRUCK -                       |
|                                                                              |
| A truck owned by APA Construction Company backed over a Troxler Moisture     |
| Density Gauge, Model #4640, Serial #1717, at State Road 1554, Siler City,    |
| NC.  The gauge sources, 8 millicuries Cs-137 and 40 millicuries Am-241-Be,   |
| were not damaged and are in their shielded position.  The gauge appeared to  |
| be functioning properly.  The licensee plans to send the gauge to Troxler    |
| for inspection/repair.                                                       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   37100       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  DNX TRANSGENIC SCIENCES              |NOTIFICATION DATE: 06/21/2000|
|LICENSEE:  DNX TRANSGENIC SCIENCES              |NOTIFICATION TIME: 10:35[EDT]|
|    CITY:  CRANBURY                 REGION:  1  |EVENT DATE:        06/07/2000|
|  COUNTY:                            STATE:  NJ |EVENT TIME:        11:00[EDT]|
|LICENSE#:  29-30350-01           AGREEMENT:  N  |LAST UPDATE DATE:  06/21/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |ROBERT SUMMERS       R1      |
|                                                |BOB AYRES            NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JOE D'IPPOLITO, RSO          |                             |
|  HQ OPS OFFICER:  DICK JOLLIFFE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB2 20.2201(a)(1)(ii)   LOST/STOLEN LNM>10X    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - LOSS OF LICENSED MATERIAL -                                                |
|                                                                              |
| On 06/02/00, one vial of 500 ÁCi of [alpha-32] deoxycytidine 5'-Triphosphate |
| (dCTP) was received at DNX Transgenic Sciences, Cranbury, NJ.  The           |
| concentration of the material was 10 ÁCi/Ál.  Upon arrival, this vial was    |
| designated as vial #153.  At 1130 on 06/07/00, Roland Felkner, a DNX         |
| Transgenic Sciences research associate, was planning to remove 50 ÁCi of     |
| material from this vial to do a DNA labeling experiment.  However, he        |
| discovered that there was no material in the vial.  According to the isotope |
| inventory log of vial #153, there should have been 150 ÁCi of the 500 ÁCi    |
| still available in the vial.  Upon investigation, it was determined that 200 |
| ÁCi, rather than 150 ÁCi, was actually missing.  This error is attributed to |
| a computational mistake made in the log by another research associate.       |
|                                                                              |
| Joe D'Ippolito, DNX Transgenic Sciences Radiation Safety Officer (RSO),      |
| interviewed lab personnel, conducted a survey of the lab area and performed  |
| an internal investigation to locate the missing material.  There was no      |
| indication of radiation exposure to lab personnel.  Based on the results of  |
| the investigation, the RSO and members of the DNX Transgenic Sciences        |
| Radiation Safety Committee believe that less material had been sent in vial  |
| #153 by their supplier, NEN Life Science Product, than was reported on the   |
| vial label.                                                                  |
|                                                                              |
| The RSO is continuing his investigation and will determine corrective        |
| actions.                                                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37101       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  FLORIDA BUREAU OF RADIATION CONTROL  |NOTIFICATION DATE: 06/21/2000|
|LICENSEE:  PROFESSIONAL ENGINEERING & INSPECTION|NOTIFICATION TIME: 11:01[EDT]|
|    CITY:  PLANTATION               REGION:  2  |EVENT DATE:        06/21/2000|
|  COUNTY:                            STATE:  FL |EVENT TIME:        06:30[EDT]|
|LICENSE#:  2113-1                AGREEMENT:  Y  |LAST UPDATE DATE:  06/21/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |KERRY LANDIS         R2      |
|                                                |BOB AYRES            NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  CHARLEY ADAMS                |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT INVOLVING A STOLEN TROXLER GAUGE OWNED BY             |
| PROFESSIONAL ENGINEERING & INSPECTION COMPANY, INC. (PEICO) LOCATED IN       |
| PLANTATION, FLORIDA                                                          |
|                                                                              |
| The following text is a portion of a facsimile received from the Florida     |
| Bureau of Radiation Control about the theft of a Troxler Soil/Moisture       |
| Density Gauge, Model #3440, Serial #13201, Isotope(s):  Cs-137 (8.0 mCi);    |
| Am-241:Be (40 mCi):                                                          |
|                                                                              |
| "Licensee:  Professional Engineering & Inspection Company, Inc. (PEICO)      |
|                                                                              |
| "Incident Location:  1385 S.W. 19th St., Miami, Florida 33145                |
|                                                                              |
| "Incident Description:  Licensee reported that a gauge was stolen from a     |
| technician's home at approximately 6:30 am.. The technician had come to work |
| and noted that his first job was later in the morning, so he returned home   |
| for breakfast. When he came out of his home he noticed that the container,   |
| gauge and the securing cable and lock were missing. The keys were not        |
| stolen. The Miami Police Department and the Florida Bureau of Radiation      |
| Control are investigating.                                                   |
|                                                                              |
| "Miami PD case #173-1159Z                                                    |
|                                                                              |
| "Office:  Environmental Radiation Control                                    |
|                                                                              |
| "Date: Time Investigated:  21-June-00; 0930"                                 |
|                                                                              |
| Call the NRC operations officer for contact information.                     |
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