Event Notification Report for October 3, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
10/02/2000 - 10/03/2000
** EVENT NUMBERS **
37396 37397 37398 37399 37400 37401
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|Power Reactor |Event Number: 37396 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 10/02/2000|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 07:42[EDT]|
| RXTYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 10/02/2000|
+------------------------------------------------+EVENT TIME: 06:25[EDT]|
| NRC NOTIFIED BY: MICHAUD |LAST UPDATE DATE: 10/02/2000|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNU |JOHN KINNEMAN R1 |
|10 CFR SECTION: |ED GOODWIN EO |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION |CHARLIE MILLER IRO |
|AESF 50.72(b)(2)(ii) ESF ACTUATION |STEINDURF FEMA |
|NLCO TECH SPEC LCO A/S | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 M/R Y 1 Startup |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| REACTOR WAS MANUALLY SCRAMMED FROM <1% DUE TO INDICATIONS OF THE |
| ELECTROMATIC RELIEF VALVE(ERV) BEING OPEN. |
| |
| The manual scram was inserted due to indications of main steam ERV 111 being |
| stuck open. All rods fully inserted, no ECCS initiations, no relief valves |
| lifted and all systems functioned as expected. They also had isolation of |
| the main steam isolation valves due to the mode switch being in the shutdown |
| position, condenser vacuum less than LoLoLo and reactor pressure less than |
| 600 psig. |
| |
| Following the reactor scram they declared an Unusual Event (@0712) due to |
| unidentified drywell internal leakage greater than 10 gpm (they have not yet |
| determined the maximum leakage rate). Initial indication of this problem is |
| the #11 main steam line ERV 111 is stuck open. The cause of the Drywell |
| leakage is suspected to be a failure of one of the ERV line vacuum breakers |
| to close resulting in leakage from Torus back to the Drywell. |
| |
| The unit also entered TS S/D LCO 3.2.5.a(1&2), Reactor Coolant System |
| Leakage, which requires the plant to be in cold shutdown within 24 hours. |
| They plan to depressurize and cool down the reactor using shutdown cooling |
| to reach cold shutdown. |
| |
| The NRC Resident Inspector, State and Local Agencies were notified. |
| |
| There will be a press release issued by the licensee. |
| |
| * * * UPDATE 0912 10/2/00 FROM MICHAUD TAKEN BY STRANSKY * * * |
| |
| The Unusual Event was terminated at 0905 EDT. Total unidentified leakage is |
| approximately 0.5 gpm. The unit is in cold shutdown, and is continuing to |
| cool down. The NRC resident inspector has been informed of this update by |
| the licensee. Notified R1DO (Linville), EO (Goodwin), IRO(Congel), and FEMA |
| (Steindurf). |
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+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37397 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 10/02/2000|
| UNIT: [1] [] [] STATE: VT |NOTIFICATION TIME: 13:23[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 10/02/2000|
+------------------------------------------------+EVENT TIME: 13:10[EDT]|
| NRC NOTIFIED BY: MITCHELL McCLUSKIE |LAST UPDATE DATE: 10/02/2000|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES LINVILLE R1 |
|10 CFR SECTION: |BRIAN SMITH NMSS |
|BAAA 20.1906(d) SURFACE CONT/ EXT RAD |FRANK CONGEL IRO |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION |THOMAS YATES DOE |
| |RATHBUN (via NRC) DOT |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| RECEIPT OF A PACKAGE WITH EXTERIOR RADIATION LEVELS GREATER THAT THE LIMIT |
| |
| A package containing radioactive tools was received onsite, and the bottom |
| side of one of the packages had a dose rate of 550 mR/hour on contact. (The |
| limit is 200 mR/hour on contact.) The package came from a Chem Nuclear |
| facility on a flat bed truck, and the radioactive tools were going to be |
| used for a spent fuel pool cleanup effort. |
| |
| The box in question is still located on the truck. Radiation Protection |
| Department personnel have posted the area and roped it off as a Radiation |
| Area in order to control access. The licensee plans to unload the box and |
| perform an investigation to find out what is in the box and why the event |
| happened. The licensee also plans to continue controlling access to the |
| area until the investigation is complete. |
| |
| The licensee reported this event as a 1-hour report in accordance with 10 |
| CFR 20.1906(d)(2). |
| |
| Radiation Protection Department personnel notified Chem Nuclear. The |
| licensee plans to notified the NRC resident inspector and the Vermont |
| Department of Public Service. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37398 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 10/02/2000|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 14:02[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 10/02/2000|
+------------------------------------------------+EVENT TIME: 12:20[EDT]|
| NRC NOTIFIED BY: GEORGE TASICK |LAST UPDATE DATE: 10/02/2000|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES LINVILLE R1 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 99 Power Operation |99 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| DISCOVERY THAT A HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM STEAM |
| ADMISSION VALVE MAY NOT CLOSE AGAINST DESIGN BASIS DIFFERENTIAL PRESSURE |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "Engineering review has determined that the steam admission valve (inboard |
| primary containment isolation valve) for the HPCI system may not close |
| against design basis differential pressure (dP). Engineering review has |
| determined that the valve position limit switch may not indicate true stem |
| and disc position and, therefore, under design basis dP conditions, may stop |
| closure before hard seat contact. Evaluation of operability is continuing. |
| A review of 1995 test data is underway which may determine that this valve |
| is in fact operable. In the event this review determines that this valve is |
| operable, this notification will be retracted." |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 37399 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: SCHNABEL ENGINEERING ASSOCIATES |NOTIFICATION DATE: 10/02/2000|
|LICENSEE: SCHNABEL ENGINEERING ASSOCIATES |NOTIFICATION TIME: 17:11[EDT]|
| CITY: RICHMOND REGION: 2 |EVENT DATE: 10/02/2000|
| COUNTY: CITY OF RICHMOND STATE: VA |EVENT TIME: 10:00[EDT]|
|LICENSE#: 45-19703-01 AGREEMENT: N |LAST UPDATE DATE: 10/02/2000|
| DOCKET: 03019126 |+----------------------------+
| |PERSON ORGANIZATION |
| |CHARLES R. OGLE R2 |
| |JOHN HICKEY NMSS |
+------------------------------------------------+FRANK CONGEL IRO |
| NRC NOTIFIED BY: BOB HILL | |
| HQ OPS OFFICER: LEIGH TROCINE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SCHNABEL ENGINEERING ASSOCIATES REPORT OF A VEHICLE CONTAINING A LOCKED |
| TROXLER NUCLEAR DENSITY GAUGE THAT WAS STOLEN FROM AN EMPLOYEE'S RESIDENCE |
| IN RICHMOND, VIRGINIA |
| |
| Schnabel Engineering Associates reported that an employee worked over the |
| weekend and locked a Troxler nuclear density gauge in the back of his 1988 |
| Chevy Blazer located in the parking lot at his residence (an apartment |
| building or townhouse complex in Richmond, Virginia). At approximately 0700 |
| on 10/02/00, the employee discovered that his Chevy Blazer had been stolen |
| from the parking lot at his residence. Bob Hill (the licensee's Radiation |
| Safety Officer for the Richmond, Hampden, Charlottesville, Leesburg Office) |
| was notified at approximately 1000 on 10/02/00, and several attempts were |
| made to located the vehicle. The licensee notified the Police of the stolen |
| vehicle and that a locked nuclear density gauge was in the back of the |
| stolen vehicle. So far, there has been no record of the truck being found. |
| The licensee also checked with local towing companies, and there is also no |
| record of the vehicle being towed. |
| |
| The missing nuclear density gauge (model #3430, serial #29171) had a sealed |
| source containing 40 mCi of Americium-241/beryllium and 8 mCi of cesium-137. |
| The gauge also had two locks on it (one on the trigger and one on the box), |
| and the box was locked inside the back of the enclosed vehicle. The vehicle |
| was also locked. |
| |
| The licensee notified the NRC Region 2 office (Wade Loo) via telephone at |
| approximately 1130 on 10/02/00. The licensee also reported to the NRC |
| Operations Center that the NRC Region 2 office planned to notify the |
| Virginia Bureau of Radiological Health and planned to issue a Preliminary |
| Notification. The licensee also plans to submit a 30-day written report. |
| |
| (Call the NRC operations officer for licensee contact telephone numbers, a |
| licensee address, the employee's name, and the employee's address.) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37400 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 10/02/2000|
| UNIT: [1] [2] [] STATE: WI |NOTIFICATION TIME: 19:00[EDT]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 10/02/2000|
+------------------------------------------------+EVENT TIME: 17:10[CDT]|
| NRC NOTIFIED BY: RICK ROBBINS |LAST UPDATE DATE: 10/02/2000|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN MADERA R3 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| DISCOVERY OF A DISCREPANCY BETWEEN A PROCEDURE, THE PLANT CONFIGURATION TO |
| ESTABLISH PORTABLE SHIELDING, AND THE FINAL SAFETY ANALYSIS REPORT (FSAR) |
| ANALYSIS FOR CONTROL ROOM DOSE |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "During a engineering review for placing a table adjacent to an exterior |
| Control Room wall, it was noticed that the calculation for placing portable |
| shielding in front of the Control Room window and South access door assumes |
| the shielding [is] in place from the on set of the event. A discrepancy |
| exists between the procedure and the plant configuration to establish the |
| portable shielding to limit the whole body dose to Control Room operators |
| and the FSAR analysis for Control Room dose (FSAR 14.3.5). The analysis |
| (FSAR 14.3.5-1 of 14, last paragraph, Calculation 97-0115) assumes that the |
| portable shielding is in place at initiation of event; however, the |
| procedure necessary to implement the portable shielding (EOP-1, step 18) |
| provides instructions to set up the portable shielding some time after the |
| initiating event." |
| |
| "At this time, portable shielding is being installed until further |
| engineering reviews of this calculation and its assumptions can be made." |
| |
| The licensee plans to notify the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 37401 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 10/02/2000|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 22:52[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 10/02/2000|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 15:41[EDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 10/02/2000|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |JOHN MADERA R3 |
| DOCKET: 0707002 |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: ERIC SPAETH | |
| HQ OPS OFFICER: LEIGH TROCINE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NCFR NON CFR REPORT REQMNT | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| HISTORICAL INFORMATION REGARDING A FAILURE TO COMPLETE X-333 LOW ASSAY |
| WITHDRAWAL (LAW) COMPRESSOR PYROTRONIC SMOKE DETECTION SYSTEM ENGINEERING |
| MODIFICATIONS AS DESIGNED (24-hour report) |
| |
| The following text is a portion of a facsimile received from Portsmouth |
| personnel: |
| |
| "The engineering modifications to the X-333 LAW compressor Pyrotronic smoke |
| detection system were not completed as designed. The modifications were |
| intended to cause the safety system to alarm with only one smoke head firing |
| instead of requiring two smoke heads to activate the alarm. The |
| investigation into this matter was completed 10/02/00 at 1541 [hours]. The |
| investigation identified that on one occasion, a LAW station compressor was |
| in an applicable operating mode where the Pyrotronic smoke detection safety |
| system was required to be operable and one of the heads was in fact |
| inoperable making the system inoperable. Operations personnel did post an |
| immediate smoke watch to maintain [Technical Safety Requirement (TSR)] |
| compliance." |
| |
| "This finding is reportable to the NRC as a 24-hour event due to the fact |
| the equipment was required by the TSR to be available and operable and |
| should have been operating, and no redundant equipment was available to |
| provide the required safety function." |
| |
| "Note: The engineering modifications were completed 10/01/00, and |
| applicable [post-maintenance tests were completed satisfactorily]." |
| |
| It was reported that the inoperable head that was identified to be |
| inoperable on 10/01/99, but this issue was not identified until the |
| investigation was completed today (10/02/00) at 1541 hours. It was also |
| reported that there was nothing unusual or misunderstood and that all |
| systems functioned as required. |
| |
| NOTE: The X-333 building LAW station was reported to be a UF6 withdrawal |
| station. |
| |
| Portsmouth personnel have notified the NRC resident inspector and plan to |
| notify the Department of Energy site representative. |
+------------------------------------------------------------------------------+
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