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Event Notification Report for December 18, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           12/15/2000 - 12/18/2000

                              ** EVENT NUMBERS **

37599  37600  37601  37602  37603  37604  37605  37606  37607  37608  37609  37610 
37611  37612  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37599       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WNP-2                    REGION:  4  |NOTIFICATION DATE: 12/15/2000|
|    UNIT:  [2] [] []                 STATE:  WA |NOTIFICATION TIME: 03:53[EST]|
|   RXTYPE: [2] GE-5                             |EVENT DATE:        12/14/2000|
+------------------------------------------------+EVENT TIME:        21:30[PST]|
| NRC NOTIFIED BY:  ARTHUR J. MOORE              |LAST UPDATE DATE:  12/15/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHUCK CAIN           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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| ISOLATION OF A CONTAINMENT INSTRUMENT AIR HEADER FROM ITS NORMAL SUPPLY AND  |
| ACTUATION OF THE ASSOCIATED BACKUP NITROGEN BOTTLE BANK PROGRAMMER           |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "At 2130 PST, the plant experienced an isolation of the 'B' Containment      |
| Instrument Air (CIA) header from its normal supply and actuation of the      |
| associated backup nitrogen bottle bank programmer.  The isolation and        |
| actuation were due to an actual system low pressure caused by performance of |
| a maintenance procedure in conjunction with a failed heater in the           |
| non-safety related normal Containment Nitrogen (CN) system."                 |
|                                                                              |
| "The CIA system supplies nitrogen to provide motive force for safety-related |
| valves inside the primary containment.  The valves are reactor pressure      |
| vessel Safety Relief Valves (SRVs) and inboard Main Steam Isolation Valves   |
| (MSIVs)."                                                                    |
|                                                                              |
| "Evaluation of computer information indicates that pressure on the 'A' CIA   |
| header may have been below the administrative allowable value for the        |
| associated pressure switch.  Investigation continues as to why the isolation |
| and [actuation] involved only the 'B' train."                                |
|                                                                              |
| "The plant is stable, and there were no other abnormal occurrences in        |
| conjunction with this event."                                                |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   37600       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  U.S. ARMY                            |NOTIFICATION DATE: 12/15/2000|
|LICENSEE:  U.S. ARMY                            |NOTIFICATION TIME: 09:59[EST]|
|    CITY:  ROCK ISLAND              REGION:  3  |EVENT DATE:        11/16/2000|
|  COUNTY:                            STATE:  IL |EVENT TIME:             [CST]|
|LICENSE#:  12-00722-06           AGREEMENT:  Y  |LAST UPDATE DATE:  12/15/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |BRUCE BURGESS        R3      |
|                                                |CHUCK CAIN           R4      |
+------------------------------------------------+BRIAN SMITH          NMSS    |
| NRC NOTIFIED BY:  JEFF HAVENNER                |                             |
|  HQ OPS OFFICER:  LEIGH TROCINE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB2 20.2201(a)(1)(ii)   LOST/STOLEN LNM>10X    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DISCOVERY THAT A LEVEL VIAL CONTAINING 75 MILLICURIES OF TRITIUM WAS MISSING |
| FROM AN M-18 GUNNERS QUADRANT AT FORT POLK, LOUISIANA                        |
|                                                                              |
| During an audit at Fort Polk (near Alexandria, Louisiana) on 11/16/00, the   |
| licensee discovered that a level vial was missing from an M-18 gunners       |
| quadrant.  Fort Polk reported this event to Rock Island, Illinois, on        |
| 12/05/00.                                                                    |
|                                                                              |
| The licensee stated that the missing level vial contained both 75            |
| millicuries of tritium and some amount of alcohol.  Apparently, the alcohol  |
| portion of the level vial can be broken without breaking the tritium source. |
| In addition, the vial did not have a serial number, and there is no way to   |
| specifically identify it.                                                    |
|                                                                              |
| The licensee currently believes that the Army still has possession of the    |
| missing source, and it is not believed that the source is in the public      |
| domain.  The licensee also believes that this event represents an            |
| undocumented transfer from one gun to another.  It was hypothesized that the |
| alcohol portion of a level vial may have been broken, the broken level vial  |
| may have been replaced with an intact level vial from another M-18 gunners   |
| quadrant, and the broken vial may have been placed in radioactive waste.     |
|                                                                              |
| The gun crew was interviewed and stated that they were out doing drills on   |
| one day.  They went out again the next day, and the level vial was missing.  |
| The guns had not been moved out of the motor pool, and therefore, the vial   |
| did not disappear along the road anywhere.                                   |
|                                                                              |
| The licensee stated that this was a 30-day report to the NRC.  In addition   |
| to this notification, the licensee plans to submit a written report to the   |
| NRC Region 3 office.                                                         |
|                                                                              |
| (Call the NRC operations officer for a licensee contact telephone number.)   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   37601       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  U.S. AIR FORCE                       |NOTIFICATION DATE: 12/15/2000|
|LICENSEE:  U.S. AIR FORCE                       |NOTIFICATION TIME: 11:05[EST]|
|    CITY:  WASHINGTON               REGION:  1  |EVENT DATE:        12/14/2000|
|  COUNTY:                            STATE:  DC |EVENT TIME:             [EST]|
|LICENSE#:  42-23539-01AF         AGREEMENT:  N  |LAST UPDATE DATE:  12/15/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |CHUCK CAIN           R4      |
|                                                |ROBERT HAAG          R2      |
+------------------------------------------------+BRIAN SMITH          NMSS    |
| NRC NOTIFIED BY:  CAPT. DAVID PUGH, USAF       |                             |
|  HQ OPS OFFICER:  LEIGH TROCINE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB2 20.2201(a)(1)(ii)   LOST/STOLEN LNM>10X    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DISCOVERY OF RADIOACTIVE MATERIAL AT A SCRAP YARD IN ORLANDO, FLORIDA, THAT  |
| COULD POSSIBLY BE TIED TO THE U.S. AIR FORCE                                 |
|                                                                              |
| At 0950 on 12/15/00, Patrick Air Force Base (AFB) in Florida notified        |
| Bolling AFB in Washington D.C. of the discovery of radioactive material that |
| may be tied to the U.S. Air Force at a scrap yard (E&H Car Crushing) in      |
| Orlando, Florida.  Patrick AFB received the report late in the afternoon on  |
| 12/14/00.                                                                    |
|                                                                              |
| It was determined that the material involved a rocket body from a titan      |
| rocket that belonged to a memorabilia collector who apparently obtained the  |
| rocket body from the U.S. Air Force approximately 10 years ago.  (The        |
| memorabilia collector died, and his estate either transferred or sold the    |
| rocket body to the scrap yard.)  Other radioactive materials were also       |
| discovered in the same vicinity (a 55-gallon drum containing scrap metal, a  |
| metal bale, and a titan nose cone), but there is no proof that this other    |
| material belonged to either the memorabilia collector or the U.S. Air        |
| Force.                                                                       |
|                                                                              |
| It was reported that the rocket body contain a magnesium/thorium alloy.      |
| However, the activity and percent weight is not know at this time in order   |
| to identify whether or not the material meets the unimportant quantity       |
| requirements in 10 CFR 40.13, paragraph 4.                                   |
|                                                                              |
| The U.S. Air Force plans to contact its Occupational Health Team in San      |
| Antonio, Texas, in order to have them survey the material next week.  They   |
| also plan to dispose of the rocket body (at a minimum) and to possibly       |
| dispose of the other questionable material as well.                          |
|                                                                              |
| It was reported that a law firm surveyed the material and got readings of 2  |
| mR/hour on contact and less than 200 ÁR/hour at a distance of 5 feet.  The   |
| type of equipment used to perform these surveys and the qualifications of    |
| the individuals taking the surveys for the law firm were not known a the     |
| time of this notification.                                                   |
|                                                                              |
| The licensee plans to notify their lawyer as well as the NRC Region 4 office |
| (Chuck Cain).  The NRC Region 2 office plans to notify the State of Florida. |
| (Call the NRC operations officer for a contact telephone number.)            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37602       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 12/15/2000|
|    UNIT:  [] [3] []                 STATE:  NY |NOTIFICATION TIME: 12:39[EST]|
|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        12/14/2000|
+------------------------------------------------+EVENT TIME:        14:00[EST]|
| NRC NOTIFIED BY:  STEPHON PRUSSMAN             |LAST UPDATE DATE:  12/15/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN WHITE           R1      |
|10 CFR SECTION:                                 |VERN HODGE           NRR     |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|3     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PART 21 REPORT CONCERNING POSSIBLE INOPERABILITY OF A SAFETY RELATED STATIC  |
| INVERTER                                                                     |
|                                                                              |
| "On December 14, 2000, Entergy determined that a potential defect existed in |
| the Indian Point 3 safety related 34 static inverter supplied by             |
| Westinghouse. Six (6) aluminum electrolytic capacitors manufactured by       |
| Mallory Inc. (part number CGS432T200X4C) were purchased from Westinghouse    |
| (part number 454A8391110) as commercial grade components. The capacitors     |
| were identified as replacement parts in the Westinghouse instruction manual  |
| for the 34 static inverter. The capacitors were subsequently dedicated for   |
| use in the Indian Point 3 safety related static inverter 34. The dedication  |
| program did not identify a mounting restriction since this is not typically  |
| a critical characteristic for replacement parts. The Westinghouse            |
| instruction manual, used for procurement, did not specify any restriction on |
| mounting orientation. Indian Point 3 (IP3) considers this a deviation. IP3   |
| was notified, by Westinghouse letter dated September 5, 2000, that an        |
| internal design change to the capacitor had been made by Mallory that        |
| imposed the mounting restriction. Mounting of the capacitors in a horizontal |
| direction could result in catastrophic failure of the component (i.e., short |
| circuit) and render the 34 static inverter and associated instrument bus     |
| inoperable. IP3 considers this a potential substantial safety hazard because |
| IP3 is not designed for a postulated design basis accident with a single     |
| failure (e.g., failure of another inverter) and the failure of the 34 static |
| inverter. On October 26, 2000 the plant was shutdown and corrective action   |
| was completed to replace the inverter capacitors prior to their failure. An  |
| operating experience event report is being prepared for distribution to the  |
| industry. Westinghouse has discontinued use of this model Mallory capacitor. |
| The Indian Point 3 staff has not ascertained other potential users or uses   |
| of the capacitors."                                                          |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37603       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  WA DIVISION OF RADIATION PROTECTION  |NOTIFICATION DATE: 12/15/2000|
|LICENSEE:  MDS PHARMA SERVICES, INC.            |NOTIFICATION TIME: 15:37[EST]|
|    CITY:  BOTHELL                  REGION:  4  |EVENT DATE:        10/14/2000|
|  COUNTY:                            STATE:  WA |EVENT TIME:             [PST]|
|LICENSE#:  WN-L0106-1            AGREEMENT:  Y  |LAST UPDATE DATE:  12/15/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |CHUCK CAIN           R4      |
|                                                |JOHN GREEVES         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  TERRY FRAZEE                 |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT                                                       |
|                                                                              |
| The following is taken from an e-mail report:                                |
|                                                                              |
| This is notification of an event in Washington state as identified by the WA |
| Department of Health, Division of Radiation Protection during a routine      |
| license inspection.                                                          |
|                                                                              |
| STATUS: new/closed                                                           |
|                                                                              |
| Licensee: MDS Pharma Services, Inc.                                          |
| City and state: Bothell, WA                                                  |
| License number: WN-L0106-1                                                   |
| Type of license: Research lab                                                |
|                                                                              |
| Date of event: October 14, 1999                                              |
| Location of Event: Bothell, WA                                               |
| ABSTRACT: (where, when, how, why; cause, contributing factors, corrective    |
| actions, consequences, DOH onsite investigation; media attention) On October |
| 14, 1999, a Yellow II packaged from Amersham Corporation, Arlington Heights, |
| IL, was delivered by Federal Express to the licensee.  The package contained |
| 5 millicuries of H-3 and 10 microcuries of I-125 in sealed vials. Laboratory |
| personnel measured 10 mR/hr on the package surface with nothing detectable   |
| at a meter thus verifying the Yellow II label.  The package appeared in good |
| shape and personnel unpacked the contents and determined that the exterior   |
| of the vials and inner packaging were free of contamination.  However, upon  |
| surveying the empty packaging, the outside corner of the outer package was   |
| determined to be contaminated.  12,000 counts per minute of removable        |
| contamination were noted using a sodium iodide detector.  No reading was     |
| detected on the wipe using a pancake probe leading the licensee to conclude  |
| the source of the activity was most likely I-125.  The licensee immediately  |
| called ChemTrec which in turn notified shipper.  Amersham called the         |
| licensee and informed the RSO that Amersham would take care of any           |
| additional notifications including the carrier.  The licensee documented the |
| event and instituted additional handling procedures for all future           |
| receipts.                                                                    |
|                                                                              |
| On December 5, 2000, during a routine license inspection by the WA           |
| Department of Health, the inspectors noted the incident report and that the  |
| licensee had failed to notify the department as required (the department     |
| estimated the removable contamination to be 120,000 DPM and thus required to |
| be reported).  The licensee was cited for failing to notify the department.  |
| This report is being made to complete the record.                            |
|                                                                              |
| What is the notification or reporting criteria involved? WAC 246-221-160     |
| Procedures for picking up, receiving, and opening packages.                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37604       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  CALIFORNIA RADIATION CONTROL PRGM    |NOTIFICATION DATE: 12/15/2000|
|LICENSEE:  HAZARD MANAGEMENT SERVICES           |NOTIFICATION TIME: 18:59[EST]|
|    CITY:  FRESNO                   REGION:  4  |EVENT DATE:        12/14/2000|
|  COUNTY:                            STATE:  CA |EVENT TIME:        16:30[PST]|
|LICENSE#:  CA-6508               AGREEMENT:  Y  |LAST UPDATE DATE:  12/15/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |CHUCK CAIN           R4      |
|                                                |JOHN GREEVES         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  ROBERT GREGER                |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| STOLEN LEAD ANALYZER CONTAINING 6 mCi CADMIUM-109                            |
|                                                                              |
| This report is made under 10 CFR 20.2201(1)(a)(1).  A lead analyzer          |
| containing 6 mCi of Cd-109, used for checking for lead in paint, was stolen  |
| while momentarily unattended in the hall of the Edison Middle School.  The   |
| school authorities and police have been notified.  A reward of $500 has been |
| posted.  There is little threat to the public as readings on contact are     |
| only 100 - 200 ÁR/hr when source is exposed.                                 |
|                                                                              |
| NMED # CA000035                                                              |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37605       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  WA DIVISION OF RADIATION PROTECTION  |NOTIFICATION DATE: 12/15/2000|
|LICENSEE:  NORTHWEST INSPECTION, INC.           |NOTIFICATION TIME: 19:25[EST]|
|    CITY:  PASCO                    REGION:  4  |EVENT DATE:        12/15/2000|
|  COUNTY:                            STATE:  WA |EVENT TIME:             [PST]|
|LICENSE#:  WN-IR065-1            AGREEMENT:  Y  |LAST UPDATE DATE:  12/15/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |CHUCK CAIN           R4      |
|                                                |JOHN GREEVES         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  TERRY FRAZEE                 |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT                                                       |
|                                                                              |
| The following is taken from an e-mail report:                                |
|                                                                              |
| This is notification of an event in Washington state as investigated by the  |
| WA Department of Health, Division of Radiation Protection.                   |
|                                                                              |
| STATUS: new/closed                                                           |
|                                                                              |
| Licensee: NorthWest Inspection, Inc.                                         |
| City and state: Richland, WA                                                 |
| License number: WN-IR065-1                                                   |
| Type of license: Industrial Radiography                                      |
|                                                                              |
| Date of event: December 15, 2000                                             |
| Location of Event: Pasco, WA                                                 |
| ABSTRACT: (where, when, how, why; cause, contributing factors, corrective    |
| actions, consequences, DOH on-site investigation; media attention) The       |
| building where the licensee stores its radiography equipment suffered a      |
| major fire in the early morning of December 15, 2000.   The building,        |
| constructed of concrete block walls with a wood/plywood type roof, is        |
| primarily occupied by the local Pipe Fitters Union which has offices,        |
| classrooms and a welding test area in the portion of the building that       |
| burned.  The licensee's industrial radiography camera and a source changer   |
| were locked in a 3/8 inch steel, lead-lined, cabinet next to the concrete    |
| block wall.  Because of the licensee's inability to take immediate           |
| protective actions necessary to avoid exposure to sources of radiation or    |
| releases of radioactive material that could exceed regulatory limits, the    |
| licensee immediately notified the department.  For several hours the         |
| licensee was not permitted to enter the area to determine whether damage had |
| occurred to his equipment which contains depleted uranium for shielding and  |
| one 35 curie Iridium-192 source.  The licensee was not able to retrieve the  |
| equipment until the debris from the burned out roof was cleared that         |
| afternoon.  Staff from the department was on-scene to survey the             |
| radiography                                                                  |
| camera and source changer and take appropriate smears to check for           |
| contamination.  No contamination was noted.  The licensee secured the        |
| equipment in his truck (normal mode of transportation for these items)       |
| pending license amendment for a new storage location.                        |
|                                                                              |
| What is the notification or reporting criteria involved? WAC 246-221-250     |
| Notification of incidents (Immediate notification)                           |
|                                                                              |
| Activity and Isotope(s) involved:  35 curies Ir-192; depleted uranium.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   37606       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 12/15/2000|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 21:27[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        12/15/2000|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        17:30[CST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  12/15/2000|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |RONALD GARDNER       R3      |
|  DOCKET:  0707001                              |JOHN GREEVES         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  K BEASLEY                    |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NLTR                     LICENSEE 24 HR REPORT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 24 HOUR REPORT - SAFETY SYSTEM ACTUATION                                     |
|                                                                              |
| "At 1730 on 12/15/00, the PSS office was notified that a primary condensate  |
| alarm was received on the C-337A position 3 East autoclave Water Inventory   |
| Control System (WICS). The WICS system is required to be operable while      |
| heating in mode 5 according to TSR 2.2.4.2. The autoclave was checked        |
| according to the alarm response procedure, removed from service and the      |
| Water Inventory Control System was declared inoperable by the Plant Shift    |
| Superintendent.                                                              |
|                                                                              |
| "This safety system actuation is reportable to the NRC as required by Safety |
| Analysis Report, section 6.9, table 1, criteria J.2, Safety System actuation |
| due to a valid signal as a 24-hour event notification.                       |
|                                                                              |
| "The NRC Senior Resident inspector has been notified of this event."         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37607       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRAIDWOOD                REGION:  3  |NOTIFICATION DATE: 12/16/2000|
|    UNIT:  [1] [2] []                STATE:  IL |NOTIFICATION TIME: 13:42[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        12/16/2000|
+------------------------------------------------+EVENT TIME:        12:03[CST]|
| NRC NOTIFIED BY:  DENNIS HIGINBOTHAM           |LAST UPDATE DATE:  12/16/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |RONALD GARDNER       R3      |
|10 CFR SECTION:                                 |                             |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| SECURITY REPORT                                                              |
|                                                                              |
| Safeguard system degradation related to area doors and monitoring.           |
| Immediate compensatory measures taken upon discovery.  The licensee notified |
| the NRC Resident Inspector.                                                  |
|                                                                              |
| Refer to HOO Log for additional details.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37608       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SOUTH TEXAS              REGION:  4  |NOTIFICATION DATE: 12/17/2000|
|    UNIT:  [1] [] []                 STATE:  TX |NOTIFICATION TIME: 00:57[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        12/16/2000|
+------------------------------------------------+EVENT TIME:        23:00[CST]|
| NRC NOTIFIED BY:  JAMES MERTINK                |LAST UPDATE DATE:  12/17/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHUCK CAIN           R4      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|ACCS 50.72(b)(1)(iv)     ECCS INJECTION         |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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 DUE TO CLOSURE OF TURBINE GOVERNOR VALVES                |
|                                                                              |
| "Unit 1 manually tripped the reactor at 2300 on 12/16/00. The unit was in    |
| the process of performing main turbine valve operability testing when all    |
| four Governor Valves went closed. The crew manually tripped the reactor and  |
| entered emergency operating procedures. Primary pressure continued to lower  |
| to the Safety Injection actuation setpoint. All ESF equipment actuated and   |
| performed as expected with the exception of one Source Range Nuclear         |
| Instrument. The cause of the Safety Injection actuation is not fully         |
| understood at this time."                                                    |
|                                                                              |
| The NRC resident inspector has been informed of this event by the licensee.  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37609       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DRESDEN                  REGION:  3  |NOTIFICATION DATE: 12/17/2000|
|    UNIT:  [] [2] []                 STATE:  IL |NOTIFICATION TIME: 06:18[EST]|
|   RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3           |EVENT DATE:        12/17/2000|
+------------------------------------------------+EVENT TIME:        03:12[CST]|
| NRC NOTIFIED BY:  D. THRONE                    |LAST UPDATE DATE:  12/17/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |RONALD GARDNER       R3      |
|10 CFR SECTION:                                 |                             |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP           |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       85       Power Operation  |85       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| RHR INOPERABLE DUE TO LOGIC FAILURE                                          |
|                                                                              |
| "Logic for shutdown cooling would have prevented placing the shutdown        |
| cooling system in service. System not currently required. A component in the |
| logic system experienced high resistance which simulated a high temperature  |
| condition."                                                                  |
|                                                                              |
| The licensee has declared the shutdown cooling system inoperable. The NRC    |
| resident inspector will be informed of this event by the licensee.           |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37610       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PEACH BOTTOM             REGION:  1  |NOTIFICATION DATE: 12/17/2000|
|    UNIT:  [] [3] []                 STATE:  PA |NOTIFICATION TIME: 06:35[EST]|
|   RXTYPE: [2] GE-4,[3] GE-4                    |EVENT DATE:        12/17/2000|
+------------------------------------------------+EVENT TIME:        05:45[EST]|
| NRC NOTIFIED BY:  TODD STRAYER                 |LAST UPDATE DATE:  12/17/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN WHITE           R1      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|3     N          Y       18       Power Operation  |18       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PRIMARY CONTAINMENT ISOLATION DUE TO LIGHTNING STRIKE                        |
|                                                                              |
| "During the performance of Primary Containment venting for a planned Primary |
| Containment (Drywell) entry, an invalid ESF actuation occurred. A lightning  |
| strike at the Main Offgas Stack caused the  B  Main Stack Radiation Monitor  |
| to lose communications and initiate a Primary Containment Isolation Signal   |
| to all Outboard Primary Containment ventilation valves 6"  and greater. The  |
| Primary Containment Isolation Valves open at the time of Primary Containment |
| venting were the 18"  Torus vent valves. The Outboard 18"  Torus vent valve  |
| was the only ESF actuation. Since the ESF signal was invalid, but caused an  |
| actuation of an ESF, this event is reportable under 10CFR50.72(b)(2)(ii)."   |
|                                                                              |
| The NRC resident inspector has been informed of this notification by the     |
| licensee.                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37611       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: RIVER BEND               REGION:  4  |NOTIFICATION DATE: 12/17/2000|
|    UNIT:  [1] [] []                 STATE:  LA |NOTIFICATION TIME: 13:01[EST]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        12/17/2000|
+------------------------------------------------+EVENT TIME:        08:23[CST]|
| NRC NOTIFIED BY:  DAVID YOUNG                  |LAST UPDATE DATE:  12/17/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHUCK CAIN           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                                   
+------------------------------------------------------------------------------+
| AUTOMATIC ESF ACTUATION - SUPPRESSION POOL CLEANUP ISOLATION                 |
|                                                                              |
| "Received isolation of Suppression Pool Cleanup (SPC) System while           |
| performing I&C surveillance testing.                                         |
|                                                                              |
| "A Division 1 RHR/RCIC area temperature isolation signal was input for the   |
| test. The actual isolation is normally bypassed during the surveillance.     |
| Upon receiving the isolation, the surveillance was secured.                  |
|                                                                              |
| "Upon investigation, the screws connecting the terminal block of the         |
| isolation bypass switch were found to have backed out such that with the     |
| keylock switch taken to the bypass position the contacts of the switch did   |
| not change status.                                                           |
|                                                                              |
| "All isolations took place as designed The Division I SPC suction valve      |
| (RHS-A0V63) and discharge valve (RHS-A0V64) closed. All RHR valves which     |
| receive an isolation on this signal are normally closed valves. The Division |
| I RCIC isolation did not take place due to the isolation signal being        |
| removed prior to a time delay relay timing out.                              |
|                                                                              |
| "The suppression pool cleanup system was secured."                           |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37612       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SALEM                    REGION:  1  |NOTIFICATION DATE: 12/17/2000|
|    UNIT:  [1] [2] []                STATE:  NJ |NOTIFICATION TIME: 17:43[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        12/17/2000|
+------------------------------------------------+EVENT TIME:        16:15[EST]|
| NRC NOTIFIED BY:  JOHN KONOVALCHICK            |LAST UPDATE DATE:  12/17/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN WHITE           R1      |
|10 CFR SECTION:                                 |                             |
|AARC 50.72(b)(1)(v)      OTHER ASMT/COMM 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  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOSS OF OFFSITE COMMUNICATIONS CAPABILITY                                    |
|                                                                              |
| The licensee determined that the Emergency Response Data  System (ERDS) was  |
| unavailable as of 1615 EST on 12/17/00.  The Salem TSC lost normal power at  |
| 0954 EST and the diesel generator started as designed and supplied power as  |
| designed.  On loss of normal power to the TSC, the phone line to transmit    |
| date from the ERDS system is supplied by a backup battery system with an     |
| expected life of 8 hours.  At 1615 EST the batteries were down powered and   |
| the capability to transmit ERDS to the NRC was loss.  Troubleshooting and    |
| repairs are proceeding, but the time for restoration is unknown at this      |
| time.                                                                        |
|                                                                              |
| The licensee intends to notify the NRC Resident Inspector.                   |
+------------------------------------------------------------------------------+