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 �R/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 �R/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. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021