Event Notification Report for February 14, 2002
*** NOT FOR PUBLIC DISTRIBUTION ***
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
02/13/2002 - 02/14/2002
** EVENT NUMBERS **
38690 38691 38692 38693 38694
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|Power Reactor |Event Number: 38690 |
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| FACILITY: CALLAWAY REGION: 4 |NOTIFICATION DATE: 02/13/2002|
| UNIT: [1] [] [] STATE: MO |NOTIFICATION TIME: 13:11[EST]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 02/13/2002|
+------------------------------------------------+EVENT TIME: 04:34[CST]|
| NRC NOTIFIED BY: E. HENSON |LAST UPDATE DATE: 02/13/2002|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |ANTHONY GODY R4 |
|10 CFR SECTION: | |
|AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
| | |
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EVENT TEXT
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| VALID REACTOR PROTECTION SYSTEM ACTUATION. |
| |
| At 0434, 2/13/02, Callaway Plant experienced a valid Reactor Protection |
| System (RPS) actuation. The plant was in Mode 4 with the primary system at |
| 330 degrees F and 395 PSIG. The Reactor Trip breakers were closed to |
| facilitate Main Turbine shell and chest warming. Secondary plant |
| manipulations, which included securing Steam Generator Blowdown and |
| conducting Auxiliary Feedwater flow testing, caused a reduction in |
| condensate flow through feedwater preheaters. This reduction in flow through |
| the preheaters caused steam pressure inside the Main Turbine to increase |
| above a permissive (P13) setpoint normally activated at 10 % reactor power. |
| This P13 permissive in turn enabled a Reactor Trip permissive (P7) for a low |
| Pressurizer pressure reactor trip which has a setpoint of 1885 PSIG. Since |
| primary pressure was below the 1885 PSIG setpoint, a Reactor Protection |
| System signal was generated and caused the Reactor Trip breakers to open. |
| Although pressure measured within the Main Turbine increased, primary system |
| temperature and pressure never increased above the limits for Mode 4. All |
| systems actuated as expected. Main Turbine warming was secured and an Event |
| Review Team was assembled to determine the cause of the event. Operating |
| instructions are being modified to address this situation and prevent future |
| actuations related to these conditions. |
| |
| The NRC Resident Inspector was notified. |
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|Other Nuclear Material |Event Number: 38691 |
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| REP ORG: THOMAS G. FARIA CO. |NOTIFICATION DATE: 02/13/2002|
|LICENSEE: THOMAS G. FARIA CO. |NOTIFICATION TIME: 14:56[EST]|
| CITY: Uncasville REGION: 1 |EVENT DATE: 02/13/2002|
| COUNTY: STATE: CT |EVENT TIME: 14:56[EST]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 02/13/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JAMES TRAPP R1 |
| |FRED BROWN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: DONALD SAWYER | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
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| | |
| | |
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EVENT TEXT
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| STATIC ELIMINATOR MISSING SINCE 1992 |
| |
| Thomas G. Faria Co., located in Uncasville, CT, received an invoice from |
| the state of CT requesting a $100 fee for a static eliminator. Nobody in |
| the company knew anything about the static eliminator. Research by company |
| officials found that they did have a static eliminator at one time. The |
| static eliminator was made NRD LLC located in Grand Island, NY. NRD records |
| indicated that they had sent a static eliminator to Thomas G. Faria Co. on |
| 12/13/91. The static eliminator contained 20 millicuries of Po-210 and the |
| Model # of the static eliminator was P-2031. Serial number of the static |
| eliminator was 46218. Everybody associated with the static eliminator |
| retired several years ago. Thomas G. Faria Co. no longer uses a static |
| eliminator. The halflife of Po-210 is 138.4 days. |
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|Other Nuclear Material |Event Number: 38692 |
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| REP ORG: C.F.MARTIN & CO. INC. |NOTIFICATION DATE: 02/13/2002|
|LICENSEE: C.F.MARTIN & CO. INC. |NOTIFICATION TIME: 16:28[EST]|
| CITY: NAZARETH REGION: 1 |EVENT DATE: 02/13/2002|
| COUNTY: STATE: PA |EVENT TIME: 16:28[EST]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 02/13/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JAMES TRAPP R1 |
| |SUSAN FRANT NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: BILL WHALEN | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
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EVENT TEXT
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| MISSING STATIC ELIMINATOR GUN |
| |
| Mr. Whalen of C.F.Martin & Co. Inc. reported that they are missing a static |
| eliminator gun. The static eliminator gun model number is P2021 which |
| originally contained 10 millicuries of Po-210. The static eliminator gun was |
| made by NRD LLC, located in Grand Island N.Y., on August 16, 2000. The |
| licensee thinks that they have misplaced the static eliminator gun. Serial |
| number of the gun is A2AC914. |
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|Power Reactor |Event Number: 38693 |
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| FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 02/13/2002|
| UNIT: [1] [] [] STATE: NH |NOTIFICATION TIME: 22:17[EST]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 02/13/2002|
+------------------------------------------------+EVENT TIME: 21:08[EST]|
| NRC NOTIFIED BY: H. HAWKINS |LAST UPDATE DATE: 02/13/2002|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |JAMES TRAPP R1 |
|10 CFR SECTION: | |
|ACOM 50.72(b)(3)(xiii) LOSS COMM/ASMT/RESPONSE| |
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| | |
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+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
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EVENT TEXT
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| LOSS OF EMERGENCY SIREN EQUIPMENT GREATER THAN ONE HOUR |
| |
| "We have a simultaneous inoperability of the Massachusetts Emergency |
| Management Agency (MEMA) Framingham and the MEMA Area 1 siren activation |
| equipment for greater than one hour. This condition was discovered during |
| the performance of a routine silent activation test that is conducted |
| approximately every two weeks. We verified the state has implemented their |
| contingency plan to be able to activate the sirens locally if needed. |
| Twenty-seven sirens are affected by the problem. The sirens for the state |
| of New Hampshire were verified to be working correctly." |
| |
| The NRC Resident Inspector was notified of this event by the license. |
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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 | |
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+-----+----------+-------+--------+-----------------+--------+-----------------+
|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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Page Last Reviewed/Updated Wednesday, March 24, 2021