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Event Notification Report for January 8, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           01/05/2001 - 01/08/2001

                              ** EVENT NUMBERS **

37637  37646  37647  37648  37649  37650  37651  37652  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37637       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOPER                   REGION:  4  |NOTIFICATION DATE: 12/28/2000|
|    UNIT:  [1] [] []                 STATE:  NE |NOTIFICATION TIME: 12:21[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        12/28/2000|
+------------------------------------------------+EVENT TIME:        07:41[CST]|
| NRC NOTIFIED BY:  STEVE WHEELER                |LAST UPDATE DATE:  01/05/2001|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHARLES MARSCHALL    R4      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| CONTROL BUILDING VENTILATION ISOLATION                                       |
|                                                                              |
| "At 0741 CST the Control Building Emergency Filtration System automatically  |
| initiated on a Control Building Intake Gas High Activity alarm. The cause of |
| the Gas High Activity alarm is under investigation."                         |
|                                                                              |
| The NRC resident inspector has been informed of this event by the licensee.  |
|                                                                              |
| * * * UPDATE ON 12/29/00, 0024 ET BY MYERS TAKEN BY MACKINNON * * *          |
|                                                                              |
| During the day, trouble shooting was performed to determine the source of    |
| the actuation at 0741 CST today. Surveillance Procedure 6.PRM.317, CONTROL   |
| ROOM AIR SAMPLING SYSTEM ELECTRONIC CALIBRATION, was performed, and all      |
| indications were within specification.  A source check of the gaseous        |
| channel was also performed per Instrument Operating Procedure 4.17, and the  |
| response of the monitor was normal.  Air sampling was conducted, and no      |
| indications of abnormal radiation were identified.  The Control Room         |
| Emergency Filtration System was returned to the standby lineup.              |
|                                                                              |
| At 1933, the Control Room Emergency Filtration System again initiated on a   |
| high gaseous activity signal.  All equipment functioned as required.  The    |
| Control Building Ventilation Radiation Monitor has been declared inoperable, |
| and the Control Room Emergency Filtration System remains in service, aligned |
| in the accident mode.                                                        |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
|                                                                              |
| Note: The Control Building Ventilation Radiation Monitor consists of three   |
| channels, with two required to be operable.  The Iodine channel is also      |
| presently inoperable.  The actuation logic requires only one channel of the  |
| three to initiate Control Room Isolation and start the Emergency Booster     |
| (pressurization) fan.                                                        |
|                                                                              |
| Noble gas sample was taken at 2142 CST.  All readings were normal.   NRC     |
| R4DO (C. Marschall) notified.                                                |
|                                                                              |
| * * * UPDATE ON 1/5/01 @ 1113 BY  VAN DER KAMP  TO GOULD * * *  RETRACTION   |
|                                                                              |
| Event Number 37637 reported a condition at Cooper Nuclear Station (CNS)      |
| where the Control Room Emergency Filtration System (CREPS) automatically     |
| initiated on a Control Building Intake Gas High Activity alarm. Surveillance |
| testing found no abnormalities with the system and air sampling found no     |
| indications of abnormal radiation levels.  A subsequent identical event      |
| occurred later the same day and was reported to the NRC Operations Center in |
| an update.                                                                   |
|                                                                              |
| Subsequent troubleshooting has found a solder connection, that connects gas  |
| monitor components to ground, had come apart.  Discussions with the          |
| manufacturer of the monitor confirm that the loss of ground can cause        |
| spiking in the displayed background reading.                                 |
|                                                                              |
| CNS investigation has found that the initiation of the CREPS was due to an   |
| invalid signal, i.e., not due to an actual elevated radioactive              |
| concentration.  Per 10CFR50.72(b)(2)(ii), invalid actuations of CREFS are    |
| not required to be reported and EN 37637 is retracted.                       |
|                                                                              |
| The NRC Resident Inspector will be notified of this event by the licensee.   |
|                                                                              |
| The Reg 4 RDO(Johnson) was notified.                                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37646       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  HOLTEC INTERNATIONAL                 |NOTIFICATION DATE: 01/04/2001|
|LICENSEE:  HOLTEC INTERNATIONAL                 |NOTIFICATION TIME: 15:59[EST]|
|    CITY:  MARLTON                  REGION:  1  |EVENT DATE:        10/18/2000|
|  COUNTY:                            STATE:  NJ |EVENT TIME:        12:00[EST]|
|LICENSE#:                        AGREEMENT:  N  |LAST UPDATE DATE:  01/05/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |MELVYN LEACH         R3      |
|                                                |VERN HODGE, FAX      NRR     |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  BRIAN GUTHERMAN              |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 10 CFR PART 21 NOTIFICATION FOR DISCREPANT WEIGHT OF SPENT FUEL RACKS        |
|                                                                              |
| Spent fuel racks removed from Byron Nuclear Power Plant were discovered to   |
| have as-found weights ranging from approximately 8,200 to 10,500 lbs more    |
| than the weights used in the analyses supporting the original design and     |
| licensing of these racks and in the design of the lifting equipment used to  |
| lift the racks. The analyses related to seismic loadings, bearing pad        |
| design, spent fuel pool liner fatigue, and possibly others used to design    |
| and license these racks may no longer be conservative when the additional    |
| weight is considered.  The actual impact on these analyses has not, to our   |
| knowledge, been evaluated.  The impact on the design of the lifting          |
| equipment is that the design safety factors for the lifting equipment, while |
| still above 1.0, may not meet the minimum safety factors in NUREG-0612 and   |
| associated reference documents.                                              |
|                                                                              |
| Braidwood Nuclear Station has four similarly designed racks provided by the  |
| same supplier.                                                               |
|                                                                              |
|                                                                              |
| * * * UPDATE ON 1/5/01 @ 0946 BY GUTHERMAN TO GOULD * * *                    |
|                                                                              |
| The manufacturer of the spent fuel racks reported in the initial reports was |
| Joseph Oat Co of Camden, NJ.                                                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37647       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: THREE MILE ISLAND        REGION:  1  |NOTIFICATION DATE: 01/05/2001|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 06:38[EST]|
|   RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP            |EVENT DATE:        01/05/2001|
+------------------------------------------------+EVENT TIME:        06:20[EST]|
| NRC NOTIFIED BY:  SCHORK                       |LAST UPDATE DATE:  01/05/2001|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JAMES NOGGLE         R1      |
|10 CFR SECTION:                                 |                             |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| THE MOTOR FOR MS-V-1C HAS BEEN DECLARED INOPERABLE                           |
|                                                                              |
| TMI identified a condition that is outside the design basis of the facility  |
| at 0620 hours on January 5, 2001. The condition is that MS-V-1C may not be   |
| capable of being closed within 120 seconds as described in the bases for     |
| Technical Specification 4.8.2 and FSAR Section 10.3.  The bases for TS 4.8.2 |
| and FSAR Section 10.3 both state that the valve is capable of being remotely |
| closed within 120 seconds from the Control Room.  With the motor inoperable, |
| the valve cannot be remotely closed within 120 seconds. The condition was    |
| found during routine surveillance testing and subsequent evaluation.  During |
| the surveillance testing the valve is stroke closed 10% and then returned to |
| its normal operation position of full open.  The valve stroke closed to the  |
| 10% closed position without incident.  During the return of the valve to the |
| full open position sparks were observed and a burning odor was present.      |
| However, the sparking ceased and the motor successfully traveled to the fail |
| open position (verified by visual observation of the valve stern position).  |
| Subsequent visual inspection of the valve and motor, interviews with the     |
| technicians, the system engineer and the Electrical Foreman resulted in the  |
| declaration of the inoperability of the motor for MS-V-1C.                   |
|                                                                              |
| This deficient condition has been documented in the TMI Corrective Action    |
| program.  Troubleshooting of the motor for MS-V-1C is in progress.  Interim  |
| action has been taken to provide for the expeditious manual closure of the   |
| valve and those actions are contained in an approved plant procedure.        |
|                                                                              |
| The Resident Inspector will be informed.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37648       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  COLORADO DEPARTMENT OF HEALTH        |NOTIFICATION DATE: 01/05/2001|
|LICENSEE:  SAN LUIS VALLEY REGIONAL MED CENTER  |NOTIFICATION TIME: 10:02[EST]|
|    CITY:  ALAMOSA                  REGION:  4  |EVENT DATE:        01/05/2001|
|  COUNTY:                            STATE:  CO |EVENT TIME:        08:00[MST]|
|LICENSE#:  14202                 AGREEMENT:  Y  |LAST UPDATE DATE:  01/05/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |WILLIAM JOHNSON      R4      |
|                                                |BRIAN SMITH          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  PENTECOST                    |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT - MOLYBDENUM-99/TECHNETIUM-99m GENERATOR LOST WHILE   |
| IN SHIPMENT                                                                  |
|                                                                              |
| DUPONT PHARMACEUTICALS SHIPPED A 750 MILLICURIE MOLYBDENUM/TECHNETIUM        |
| GENERATOR VIA FEDEX TO THE SAN LUIS VALLEY REGIONAL MEDICAL CENTER IN        |
| ALAMOSA, CO ON 12/28/00.  AS OF THIS DATE THE SHIPMENT HAS NOT BEEN          |
| RECEIVED.  THERE WAS NO FEDEX TRACKING NUMBER  AND DUPONT COULD NOT GIVE THE |
| STATE ANY INFORMATION BECAUSE THEIR COMPUTERS WERE DOWN.                     |
|                                                                              |
| * * * UPDATE ON 1/5/01 @ 1037 BY PENTECOST TO GOULD * * *                    |
|                                                                              |
| THE GENERATOR WAS LOCATED @ 0830MST AT THE FEDEX DENVER FACILITY AND IT IS   |
| IN TRANSIT TO THE MEDICAL FACILITY.                                          |
|                                                                              |
| NOTIFIED REG 4 RDO(JOHNSON) AND NMSS(SMITH) WERE NOTIFIED                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37649       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  CALIFORNIA RADIATION CONTROL PRGM    |NOTIFICATION DATE: 01/05/2001|
|LICENSEE:  PACIFIC SOILS ENGINEERING            |NOTIFICATION TIME: 11:22[EST]|
|    CITY:  OCEANSIDE                REGION:  4  |EVENT DATE:        01/02/2001|
|  COUNTY:                            STATE:  CA |EVENT TIME:             [PST]|
|LICENSE#:  3142                  AGREEMENT:  Y  |LAST UPDATE DATE:  01/05/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |WILLIAM JOHNSON      R4      |
|                                                |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  GREGER                       |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| STOLEN NUCLEAR  MOISTURE DENSITY GAUGE                                       |
|                                                                              |
| The licensee reported that a Campbell Pacific Nuclear moisture density gauge |
| was stolen from a storage unit in Oceanside, Ca between 1530 on 12/29/00 and |
| noon on 12/30/00.  Model # of the gauge was MC-3 and its serial # is         |
| M380504284.  The gauge contained approximately 8 millicuries of cesium-137   |
| and 40 millicuries of americium/beryllium.  The licensee will offer a        |
| reward.                                                                      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37650       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: ARKANSAS NUCLEAR         REGION:  4  |NOTIFICATION DATE: 01/05/2001|
|    UNIT:  [1] [] []                 STATE:  AR |NOTIFICATION TIME: 12:25[EST]|
|   RXTYPE: [1] B&W-L-LP,[2] CE                  |EVENT DATE:        01/05/2001|
+------------------------------------------------+EVENT TIME:        08:48[CST]|
| NRC NOTIFIED BY:  JAMES PORTER                 |LAST UPDATE DATE:  01/05/2001|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |WILLIAM JOHNSON      R4      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|APRE 50.72(b)(2)(vi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     M/R        Y       100      Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| REACTOR MANUALLY TRIPPED FROM 80% POWER LEVEL DUE TO EXCESSIVE MAIN TURBINE  |
| GENERATOR  HYDROGEN LEAK.                                                    |
|                                                                              |
| "At 0848 CT on 01/05/01 ANO Unit 1 reactor was manually tripped due to       |
| excessive hydrogen leakage on the main turbine generator.  Reactor power was |
| reduced from 100% to 80% prior to the manual reactor trip. No ESF actuations |
| occurred following the trip.  The unit is currently stable at Hot Shutdown   |
| conditions."                                                                 |
|                                                                              |
| Hydrogen leak on the main turbine generator was first noticed around 2100    |
| hours CT on 01/04/01.  Normal hydrogen pressure in the main turbine          |
| generator is 70 psi.  The licensee stated that they were losing              |
| approximately 3 psi per hour.  The licensee evacuated the Turbine Building   |
| as a precaution.  After reactor power had been reduced to 80% power the      |
| hydrogen leak increased at which point the licensee manually tripped the     |
| reactor.  All rods fully inserted into the core.  Once Through Steam         |
| Generator atmospheric valves operated properly.  The licensee stated that    |
| they have a 0.17 gallon per day primary leak to secondary system leak.  All  |
| Emergency Core Cooling Systems and the Emergency Generators are fully        |
| operable if needed.  Once Through Steam Generator water levels are being     |
| maintained using main feedwater, one main feedwater pump operating.  At the  |
| time of the notification the licensee had not located the source of the      |
| hydrogen leak.                                                               |
|                                                                              |
| The licensee notified Arkansas Department of Health.                         |
|                                                                              |
| The NRC Resident Inspector was notified of this event  by the licensee.      |
|                                                                              |
| * * * UPDATE ON 01/05/01 AT 1734 ET BY REX KNIGHT TAKEN BY MACKINNON * * *   |
|                                                                              |
| When the reactor was tripped, discharge canal temperature dropped from 52    |
| degrees F to 37 degrees F. This caused a large number of Thread Fin Shad to  |
| die.  A member of the public called the Arkansas Game and Fish (AG&F)        |
| Commission about the Shad.  ANO has contacted the AG&F Commission and        |
| explained the situation.  A Press Release is not planned at this time.  NRC  |
| R4DO (Bill Johnson) notified.                                                |
|                                                                              |
| The NRC Resident Inspector was notified of the event update by the licensee. |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37651       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PRAIRIE ISLAND           REGION:  3  |NOTIFICATION DATE: 01/06/2001|
|    UNIT:  [1] [] []                 STATE:  MN |NOTIFICATION TIME: 20:50[EST]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        01/06/2001|
+------------------------------------------------+EVENT TIME:        18:30[CST]|
| NRC NOTIFIED BY:  LES ANDERSON                 |LAST UPDATE DATE:  01/06/2001|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:                                |MELVYN LEACH         R3      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(vi)     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  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| COURTESY CALL TO THE NATIONAL RESPONSE CENTER (NRC) MADE AFTER SPILLING      |
| APPROXIMATELY 25 GALLONS OF SULFURIC ACID.                                   |
|                                                                              |
| A courtesy call was made to the National Response Center that was made to    |
| report a sulfuric acid spill at the  plant water treatment area.  The        |
| Corporate Environmental and Regulatory Affairs Department, which the         |
| licensee calls ERAD,  was notified.  ERAD, in turn, notified the Minnesota   |
| State Pollution Control Agency.  The Minnesota State Pollution Control       |
| Agency suggested a courtesy call to the National Response Center.            |
|                                                                              |
| Approximately 25 gallons of sulfuric acid was spilled (reportable quantity   |
| is 65 gallons of greater). A small amount, less than 10 gallons, of acid     |
| drained to their Turbine Building Sump of which a very small amount may have |
| been released.                                                               |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37652       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE                REGION:  1  |NOTIFICATION DATE: 01/07/2001|
|    UNIT:  [] [2] [3]                STATE:  CT |NOTIFICATION TIME: 09:50[EST]|
|   RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP           |EVENT DATE:        01/07/2001|
+------------------------------------------------+EVENT TIME:        06:00[EST]|
| NRC NOTIFIED BY:  ROBERT SMITH                 |LAST UPDATE DATE:  01/07/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JAMES NOGGLE         R1      |
|10 CFR SECTION:                                 |                             |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|3     N          Y       90       Power Operation  |90       Power Operation  |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SECURITY REPORT                                                              |
|                                                                              |
| Safeguard system degradation related to area boundary.  Immediate            |
| compensatory measures taken upon discovery.  The licensee notified the NRC   |
| Resident Inspector.                                                          |
|                                                                              |
| Refer to HOO Log for additional details.                                     |
+------------------------------------------------------------------------------+