Event Notification Report for February 15, 2002
*** NOT FOR PUBLIC DISTRIBUTION *** U.S. Nuclear Regulatory Commission Operations Center Event Reports For 02/14/2002 - 02/15/2002 ** EVENT NUMBERS ** 38694 38695 38696 38697 38698 +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38694 | +------------------------------------------------------------------------------+ *** NOT FOR PUBLIC DISTRIBUTION *** +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: COLUMBIA GENERATING STATIREGION: 4 |NOTIFICATION DATE: 02/14/2002| | UNIT: [2] [] [] STATE: WA |NOTIFICATION TIME: 04:18[EST]| | RXTYPE: [2] GE-5 |EVENT DATE: 02/14/2002| +------------------------------------------------+EVENT TIME: 01:03[PST]| | NRC NOTIFIED BY: BRIAN ADAMI |LAST UPDATE DATE: 02/14/2002| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |LINDA SMITH R4 | |10 CFR SECTION: | | |ASHU 50.72(b)(2)(i) PLANT S/D REQD BY TS | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |2 N Y 100 Power Operation |97 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN | | | | "This ENS notification is made to report initiation of a plant shutdown | | required by the Columbia Generating Station Technical Specifications | | pursuant to 10 CFR 50.72(b)(2)(i). This plant shutdown is initiated due to | | the expected inability to restore the Division II Emergency Diesel Generator | | (DG) to Operable status prior to exceeding the expiration of the Completion | | Time of Tech Spec LCO 3.8 1 Required Action B.4. The expected inability to | | restore the DG to operable status is due to a mechanical problem in the DG | | output breaker. The breaker is capable of closing and connecting the DG to | | its safety bus however, Mechanically Operated Contacts that are actuated by | | the breaker have failed to actuate, Although the Completion time of | | Technical Specification LCO 3 8.1 Required Acton B.4 expires at 0315, | | February 14, 2002, plant shutdown will commence prior to that time in order | | to fully evaluate the breaker anomaly." | | | | The NRC resident inspector has been informed of this notification by the | | licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Other Nuclear Material |Event Number: 38695 | +------------------------------------------------------------------------------+ *** NOT FOR PUBLIC DISTRIBUTION *** +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: ENG. RESEARCH & DEVELOPMENT CENTER |NOTIFICATION DATE: 02/14/2002| |LICENSEE: ENG. RESEARCH & DEVELOPMENT CENTER |NOTIFICATION TIME: 13:52[EST]| | CITY: HANOVER REGION: 1 |EVENT DATE: 02/14/2002| | COUNTY: GRAFTON STATE: NH |EVENT TIME: [EST]| |LICENSE#: 28-07946-06 AGREEMENT: Y |LAST UPDATE DATE: 02/14/2002| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |JAMES TRAPP R1 | | |DON COOL NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: ALAN GREATOREX | | | HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |BAE1 20.2202(b)(1) PERS OVEREXPOSURE/TEDE | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL OVEREXPOSURE AT ENGINEER RESEARCH & DEVELOPMENT CENTER IN HANOVER, | | NEW HAMPSHIRE | | | | On 02/04/02, the licensee received a telephone notification that an | | individual's badge had an exposure of 16 Rem during a 3-month period. After | | further investigation on 02/05/02, the licensee determined that the | | individual had lost the badge while packing a moisture density gauge for | | storage. Approximately 4 weeks later, the badge was discovered when the | | device was being prepared to be sent for recalibration. | | | | On 02/08/02, the licensee received a telex identifying what the exposures | | were in writing. The licensee notified the NRC Region 1 office (Betsy | | Ullrich) on 02/14/02. | | | | The licensee currently believes that the 16-Rem exposure was an exposure to | | the badge and not to the individual. | | | | NOTE: The licensee stated that Engineer Research & Development Center is a | | research portion of the Core of | | Engineers and that it was previously know as the U.S. Army Cold Regions | | Research & Engineering | | Laboratory. | | | | (Call the NRC operations officer for a licensee contact telephone number.) | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Other Nuclear Material |Event Number: 38696 | +------------------------------------------------------------------------------+ *** NOT FOR PUBLIC DISTRIBUTION *** +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: POWER RESOURCES |NOTIFICATION DATE: 02/14/2002| |LICENSEE: POWER RESOURCES |NOTIFICATION TIME: 18:19[EST]| | CITY: DOUGLAS REGION: 4 |EVENT DATE: 02/14/2002| | COUNTY: CONVERSE STATE: WY |EVENT TIME: 13:30[MST]| |LICENSE#: 15-SUA-1511 AGREEMENT: N |LAST UPDATE DATE: 02/14/2002| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |MYRON FLIEGEL/MINING NMSS | | |MIKE LAYTON/MINING NMSS | +------------------------------------------------+LINDA SMITH R4 | | NRC NOTIFIED BY: WILLIAM KEARNEY |SUSAN FRANT NMSS | | HQ OPS OFFICER: LEIGH TROCINE |DWIGHT CHAMBERLAIN R4 | +------------------------------------------------+(via NRC) BROWN EPA | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NMIN MINING EVENT | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POWER RESOURCES HIGHLAND URANIUM PROJECT (AN IN-SITU URANIUM MINE LOCATED IN | | A RURAL AREA APPROXIMATELY 30 MILES NORTH OF DOUGLAS, WYOMING) REPORTED A | | MINOR RELEASE OF RADIOACTIVE MATERIAL. | | | | At 1330 MST, while personnel were moving a trailer-mounted 1,000-gallon tank | | full of water from a well, they forgot to close a valve, and approximately | | 20 to 25 gallons of water containing uranium drained onto a county road. | | The spill was cleaned up by approximately 1530 MST. Original contamination | | levels were between 1,000 and 5,000 cpm, however, alpha scans of the area | | currently meet the NRC unrestricted release standard of 1,000 cpm. A sample | | of the water from the trailer is being analyzed to determine the actual | | activity levels. There were no personnel contaminations or injuries | | associated with this event. | | | | The licensee notified the Department of Transportation and plans to notify | | the local sheriff's office. The NRC Region 4 office plans to notify the | | State of Wyoming. | | | | The NRC mining experts assessed this event and stated that no adverse impact | | is anticipated and no response is required. | | | | (Call the NRC operations officer for licensee contact telephone numbers.) | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38697 | +------------------------------------------------------------------------------+ *** NOT FOR PUBLIC DISTRIBUTION *** +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 02/14/2002| | UNIT: [1] [2] [] STATE: CA |NOTIFICATION TIME: 20:30[EST]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/14/2002| +------------------------------------------------+EVENT TIME: 16:20[PST]| | NRC NOTIFIED BY: DOUGLAS DYE |LAST UPDATE DATE: 02/14/2002| | HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |LINDA SMITH R4 | |10 CFR SECTION: |JAMES TRAPP R1 | |ASHU 50.72(b)(2)(i) PLANT S/D REQD BY TS | | |AINA 50.72(b)(3)(v)(A) POT UNABLE TO SAFE SD | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 100 Power Operation |90 Power Operation | |2 N Y 100 Power Operation |89 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN OF BOTH UNITS BECAUSE STEAM | | GENERATOR WATER LEVEL INSTRUMENT CHANNELS ARE INOPERABLE DUE TO A | | NON-CONSERVATIVE WATER LEVEL-LOW LOW SETPOINT | | | | The following text is a portion of a facsimile received from the licensee: | | | | "During the investigation into the Unit 2 manual reactor trip on February 9, | | 2002 (Event Number 38687), PG&E discovered a potentially unanalyzed | | condition. The narrow range (NR) steam generator (SG) water level | | instrumentation did not respond as expected to initiate an automatic reactor | | trip and auxiliary feedwater actuation on SG water level-low low." | | | | "The SG NR water level-low low setpoint is 7.2 percent. This | | instrumentation is part of the Reactor Trip System (Technical Specification | | (TS) Table 3.3.1-1 Function 14.a), and Engineered Safety Feature Actuation | | System (ESFAS) (TS Table 3.3.2-1 Function 6.d), Auxiliary Feedwater (AFW)." | | | | "On February 9, 2002, main feedwater regulating valve (MFRV) FW-2-FCV-540 | | failed closed, resulting in a rapid decrease in SG 2-4 water level. | | Indicated NR water level fell to approximately 7.5 percent and leveled out. | | Operators tripped the reactor within approximately one minute of the MFRV | | closing. Based on investigations and conversations with Westinghouse today, | | PG&E believes the actual SG 2-4 NR water level fell below the 7.2 percent | | setpoint before the reactor was tripped. Westinghouse attributes this water | | level discrepancy to a previously unaccounted for differential pressure (dP) | | created by steam flow past the mid-deck plate (MDP) in the moisture | | separator section of the SG. This dP phenomena will cause the SG NR to read | | higher than actual at high steam flows (>60% power). Thus, the SG NR water | | level-low low setpoint is believed to be non-conservative during certain | | transients." | | | | "In response, operators declared all SG NR water level-low low channels | | inoperable and entered TS Action 3.0.3. At 1700 [PST], both units began | | reducing power to approximately 60 percent, where Westinghouse indicates | | this condition will no longer result in a non-conservative setpoint." | | | | "In accordance with 10 CFR 50.72(b)(2)(i), PG&E is reporting this as the | | initiation of a TS required shutdown. It is also being reported under 10 | | CFR 50.72(b)(3)(v)(A) as condition that at the time of discovery could have | | prevented the fulfillment of the safety function of structures or systems | | that are needed to shutdown the reactor and maintain it in a safe shutdown | | condition." | | | | The licensee notified the Salem facility and the NRC resident inspector. | | The licensee also plans to notify the local Advisory of the County. | | | | (Refer to event #38687 for additional information.) | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38698 | +------------------------------------------------------------------------------+ *** NOT FOR PUBLIC DISTRIBUTION *** +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 02/15/2002| | UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 05:36[EST]| | RXTYPE: [1] CE |EVENT DATE: 02/15/2002| +------------------------------------------------+EVENT TIME: 03:53[CST]| | NRC NOTIFIED BY: RANDY CADE |LAST UPDATE DATE: 02/15/2002| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: UNUSUAL EVENT |LINDA SMITH R4 | |10 CFR SECTION: |JOSE CALVO NRR | |AAEC 50.72(a) (1) (i) EMERGENCY DECLARED |STEINDURF FEMA | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 98 Power Operation |98 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCRETIONARY DECLARATION OF UNUSUAL EVENT DUE TO "INCREASED PLANT | | AWARENESS" | | | | During a dewatering evolution of the Spent Resin Storage Tank, some spent | | resin entered the tank vent header. This caused an elevated reading of 263 | | mrem on a single area radiation monitor (RM-081). The licensee declared an | | Unusual Event in accordance with EAL 11.4, "Increased Plant Awareness." | | Additional personnel are being called in to the site to assist in devising a | | plan to flush the resin from the affected piping. The licensee estimates | | that it will take two to three hours to complete this evolution. The NRC | | resident inspector and state and local government agencies have been | | informed of this event by the licensee. | +------------------------------------------------------------------------------+
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021