Event Notification Report for October 7, 2002
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
10/04/2002 - 10/07/2002
** EVENT NUMBERS **
39237 39246 39247 39248 39249 39250 39251
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|General Information or Other |Event Number: 39237 |
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| REP ORG: CALIFORNIA RADIATION CONTROL PRGM |NOTIFICATION DATE: 10/02/2002|
|LICENSEE: CONSTRUCTION TESTING & ENG., INC. |NOTIFICATION TIME: 10:19[EDT]|
| CITY: ESCONDIDO REGION: 4 |EVENT DATE: 09/24/2002|
| COUNTY: STATE: CA |EVENT TIME: 06:00[PDT]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 10/02/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |KRISS KENNEDY R4 |
| |FRED BROWN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: PEGGY L. MCKARNAN | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| STOLEN AND RECOVERED CPN MOISTURE DENSITY GAUGE |
| |
| "The user stated, he picked up gauge from the temporary storage location at |
| approximately 4:30am. He blocked, braced and locked the case to the bed of |
| his truck and drove back to his residence to make some phone calls. When he |
| came out to the truck between 7:30 and 8am the chain had been cut and the |
| gauge was gone. He contacted the police and the ARSO and also talked to |
| neighbors to see if anyone had seen anything suspicious. The ARSO contacted |
| the RHB at approximately 10:15am to report the theft. At 11 am the ARSO |
| contacted us to let us know that the gauge had been recovered. The gauge |
| was found in a park approximately 2 blocks from where the gauge was stolen. |
| The gauge was still in the case and the gauge handle was still locked. The |
| gauge was returned to the office where a leak test was performed." |
| |
| Gauge stolen and recovered was a CPN Model # 501 gauge which contains 10 |
| millicuries of Cesium-137 and 50 millicuries of AM241:Be. Leak test result |
| (in microcuries) was less than 0.005. |
| |
| State of California incident number for this event is XCA 251. |
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|Power Reactor |Event Number: 39246 |
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| FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 10/04/2002|
| UNIT: [1] [] [] STATE: KS |NOTIFICATION TIME: 12:26[EDT]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 10/04/2002|
+------------------------------------------------+EVENT TIME: 10:45[CDT]|
| NRC NOTIFIED BY: DAVE DEES |LAST UPDATE DATE: 10/04/2002|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |KRISS KENNEDY R4 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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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| OFFSITE NOTIFICATION DUE TO SMALL FIRE IN TURBINE BUILDING |
| |
| "Press release issued to local media at 0145 CDT 10/4/2002. Press release |
| described response to an electrical component fire that occurred at 0650 CDT |
| 10/4/2002. The fire occurred in a cathodic protection transformer located |
| in the turbine building. The plant fire brigade responded to the scene. |
| Power to the component was secured which extinguished the fire. Plant |
| operation was not affected. The fire was declared out at 0700 CDT |
| 10/4/2002." |
| |
| The press release was issued to the local paper - Coffey County Republican |
| and local radio KSNP. The New Strawn Fire Department was called, however, |
| the fire was extinguished before they arrived. The licensee informed |
| state/local agencies and the NRC resident inspector. |
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|General Information or Other |Event Number: 39247 |
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| REP ORG: GENERAL ELECTRIC COMPANY |NOTIFICATION DATE: 10/04/2002|
|LICENSEE: GENERAL ELECTRIC COMPANY |NOTIFICATION TIME: 12:35[EDT]|
| CITY: SAN JOSE REGION: 4 |EVENT DATE: 10/04/2002|
| COUNTY: STATE: CA |EVENT TIME: [PDT]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 10/04/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |KRISS KENNEDY R4 |
| |SONIA BURGESS R3 |
+------------------------------------------------+VERN HODGE (via fax) NRR |
| NRC NOTIFIED BY: JASON S. POST (via fax) | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| FUEL SUPPORT SIDE ENTRY ORIFICE LOSS COEFFICIENT IN CORE MONITORING SYSTEM |
| DATABANK |
| |
| "This letter provides notification of a Reportable Condition under 10CFR |
| 21.21(d) for Clinton and Perry 1. The basis for this conclusion is the data |
| used for the fuel support side entry orifice (SEO) loss coefficient in the |
| core monitoring system supplied by GE Nuclear Energy (GE)/Global Nuclear |
| Fuel (GNF). Other plants that have a similar geometry, but for which GE/GNF |
| did not provide the core monitoring system (Grand Gulf and River Bend) have |
| also been informed of this issue. |
| |
| "The core support structure in a BWR/6 affects the fuel support casting SEO |
| loss coefficient. Bundles may be adjacent to zero, one, or two core support |
| beams depending upon their location as illustrated in Figure 1. The SEO loss |
| coefficient depends upon the number of adjacent core support beams. |
| |
| "The core monitoring system in the affected plants uses an average SEO loss |
| coefficient for all of the central bundles, and a separate average value for |
| all of the peripheral bundles. This was previously evaluated for GE/GNF 8x8 |
| fuel designs and found to be acceptable. Recent calculations have shown that |
| the Critical Power Ratio (CPR) response for newer GE/GNF fuel designs are |
| more sensitive to the reduced flow in bundles that are adjacent to two core |
| support beams (which have the highest loss coefficient). Thus, the core |
| monitoring system over predicts CPR for these bundles, and thereby, may |
| under predict the margin to the Operating Limit Minimum CPR (OLMCPR). The |
| CPR over prediction is approximately 0.01 in CPR, which reaches the |
| threshold for a reportable condition on a Technical Specification Safety |
| Limit. In actual practice, plants maintain significantly more than 0.01 CPR |
| margin to the OLMCPR, so MCPR Safety Limit protection is not threatened." |
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|Power Reactor |Event Number: 39248 |
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| FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 10/05/2002|
| UNIT: [1] [] [] STATE: AR |NOTIFICATION TIME: 00:30[EDT]|
| RXTYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 10/04/2002|
+------------------------------------------------+EVENT TIME: 22:14[CDT]|
| NRC NOTIFIED BY: WAYNE AHO |LAST UPDATE DATE: 10/05/2002|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |WILLIAM JONES R4 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 A/R Y 42 Power Operation |0 Hot Standby |
| | |
| | |
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EVENT TEXT
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| TURBINE TRIP CAUSED REACTOR TRIP DURING SHUTDOWN IN PREPARATION FOR |
| REFUELING OUTAGE |
| |
| "A power reduction was in progress for entry into refueling outage 1R17. A |
| main turbine overspeed trip test was being conducted which resulted in a |
| turbine trip which then caused a reactor trip on RPS". |
| |
| All rods were automatically inserted into the core with no problems. The |
| trip occurred from 42% reactor power. No safety systems were actuated and |
| all plant systems functioned as designed. |
| |
| The Resident Inspector was notified. |
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|Power Reactor |Event Number: 39249 |
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| FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 10/05/2002|
| UNIT: [1] [2] [] STATE: VA |NOTIFICATION TIME: 14:16[EDT]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 10/05/2002|
+------------------------------------------------+EVENT TIME: 11:25[EDT]|
| NRC NOTIFIED BY: BRAD BROWN |LAST UPDATE DATE: 10/05/2002|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |JAY HENSON R2 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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 N 0 Refueling |0 Refueling |
| | |
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EVENT TEXT
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| OFFSITE NOTIFICATION DUE TO A FREON RELEASE IN THE TURBINE BUILDING |
| |
| "At 0210 today, 10/5/02, we had a failure of a seal on our mechanical |
| refrigeration unit. This resulted in 5,250 lbs of freon, R-12, being |
| released to the environment. This required reporting to Federal, State and |
| Local agencies that a release of greater than 5,000 lbs had occurred in less |
| than 24 hours. The release ended at 0454 today due to the contents had |
| completely blown down. |
| |
| - The National Response Center was notified at 1125 today |
| - The Virginia Emergency Services Operations Center was notified at 1130 |
| today |
| - The Virginia State Dept. of Environmental Quality and the Local Emergency |
| Planning Coordinator will be notified by the Virginia Emergency Services |
| Operations Center. |
| |
| "Due to these offsite notifications we are making this 4 hour report." |
| |
| The licensee informed the NRC resident inspector. |
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|Power Reactor |Event Number: 39250 |
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| FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 10/06/2002|
| UNIT: [1] [] [] STATE: VT |NOTIFICATION TIME: 18:00[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 10/06/2002|
+------------------------------------------------+EVENT TIME: 11:30[EDT]|
| NRC NOTIFIED BY: MITCH McCLUSKIE |LAST UPDATE DATE: 10/06/2002|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |PETE ESELGROTH R1 |
|10 CFR SECTION: | |
|AIND 50.72(b)(3)(v)(D) ACCIDENT MITIGATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
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EVENT TEXT
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| RCIC SYSTEM DECLARED INOPERABLE |
| |
| Following reactor core isolation cooling system injection check valve |
| surveillance, the check valve apparently did not fully close. This resulted |
| in high pump suction pressure trip which would have prevented further system |
| operation. The licensee conservatively declared the RCIC system inoperable |
| and entered Tech Spec LCO 3.5.G.2, a 14 day action statement. Shortly |
| afterwards the plant pressure was dropped to less than 150 psig as part of |
| normal plant shutdown to refueling, this takes the plant out of the Tech |
| Spec action statement as it no longer applies. The licensee is conducting |
| an investigation of the problem with RCIC injection check valve. Repairs |
| will be completed prior to plant restart. |
| |
| The licensee notified the NRC Resident Inspector and the State of Vermont. |
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|Power Reactor |Event Number: 39251 |
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| FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 10/06/2002|
| UNIT: [1] [] [] STATE: TX |NOTIFICATION TIME: 18:45[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/06/2002|
+------------------------------------------------+EVENT TIME: 16:50[CDT]|
| NRC NOTIFIED BY: MARK VERBECK |LAST UPDATE DATE: 10/06/2002|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |WILLIAM JONES R4 |
|10 CFR SECTION: | |
|NONR OTHER UNSPEC REQMNT | |
|ADEG 50.72(b)(3)(ii)(A) DEGRADED CONDITION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
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EVENT TEXT
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| 4-HOUR REPORT PURSUANT TO 10 CFR 50.72(b)(2) PER LICENSEE ADMINISTRATIVE |
| REQUIREMENTS |
| |
| "Results of the steam generator eddy current testing of the hot leg top of |
| the tube sheet rotating plus point coil program indicated that greater than |
| 1% of the tubes are defective in Steam Generator #2. |
| |
| "Technical Specification category C-3. 5.6.10." |
| |
| The licensee informed the NRC resident inspector. |
| |
| * * * UPDATE 2326EDT ON 10/6/02 FROM DENNIS REDINGER TO S.SANDIN * * * |
| |
| The licensee is updating this report to include the following additional SG |
| inspection findings for Steam Generators #3 and #4: |
| |
| "Results of the steam generator eddy current testing of the hot leg top of |
| the tube sheet rotating pancake plus point coil indicates that greater than |
| 1% of the tubes are defective in CPSES Unit 1 Steam Generators # 3 and Steam |
| Generators # 4. |
| |
| "CPSES Technical Specification states that, '[R]esults of steam generator |
| tube inspections which fall into Category C-3 shall be reported to the |
| Commission pursuant to 10 CFR 50.72(b)(2) within four hours of initial |
| discovery, and in a report within 30 days and prior to resumption of plant |
| operation.' |
| |
| "Note: |
| |
| "We understand that CPSES Technical Specification is conservative with |
| respect to timing of reporting this condition; and that the current 10 CFR |
| 50.72 requirements are eight hour notification. However, until the license |
| amendment (which is in process) is issued, CPSES will continue to report |
| this condition within four hours." |
| |
| The licensee informed the NRC resident inspector. Notified R4DO(Jones). |
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Page Last Reviewed/Updated Thursday, March 25, 2021