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
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|Power Reactor |Event Number: 38694 |
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| 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 |
| | |
| | |
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EVENT TEXT
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| 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. |
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|Other Nuclear Material |Event Number: 38695 |
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| 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 | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| 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.) |
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|Other Nuclear Material |Event Number: 38696 |
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| 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 | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| 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.) |
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|Power Reactor |Event Number: 38697 |
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| 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 |
| | |
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EVENT TEXT
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| 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.) |
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|Power Reactor |Event Number: 38698 |
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| 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 |
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+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 98 Power Operation |98 Power Operation |
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EVENT TEXT
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| 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. |
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