Event Notification Report for July 2, 2001
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
06/29/2001 - 07/02/2001
** EVENT NUMBERS **
38104 38105 38106 38107 38108 38109 38110 38111
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|General Information or Other |Event Number: 38104 |
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| REP ORG: GE NUCLEAR ENERGY |NOTIFICATION DATE: 06/29/2001|
|LICENSEE: GE NUCLEAR ENERGY |NOTIFICATION TIME: 13:31[EDT]|
| CITY: SAN JOSE REGION: 4 |EVENT DATE: 06/29/2001|
| COUNTY: STATE: CA |EVENT TIME: [PDT]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 06/29/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |GREG PICK R4 |
| |RICHARD BARKLEY R1 |
+------------------------------------------------+THOMAS DECKER R2 |
| NRC NOTIFIED BY: JASON POST |GEOFFREY WRIGHT R3 |
| HQ OPS OFFICER: FANGIE JONES |VERN HODGE (FAX) NRR |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| 10 CFR 21 REPORT: STABILITY RELOAD LICENSING CALCULATIONS MAY BE |
| NON-CONSERVATIVE |
| |
| "This letter provides information concerning the potential for |
| non-conservative reload licensing calculations for plants which have |
| implemented stability detect and suppress trip systems. The non-conservatism |
| could result in (1) Option III stability trip system setpoints which do not |
| provide Minimum Critical Power Ration (MCPR) Safety Limit protection, and |
| (2) inadequate MCPR safety limit protection from the flow-biased Average |
| Power Range Monitor (APRM) flux trip for plants which have implemented |
| Option I-D or Option 11. This notification is provided under 10 CFR Part |
| 21(d) as a reportable condition for Hatch Units 1 and 2, and as an interim |
| report per �21.21(a)(2) for the other plants listed in Attachment 1: the |
| full impact of this deviation cannot be completed within 60 days from the |
| date of discovery. Therefore, this notification describes the deviation that |
| is being evaluated by GE Nuclear Energy (GE-NE) for associated safety |
| related reload licensing calculations supplied to licensees by GE-NE and |
| states when the evaluation will be completed. |
| |
| "In addition, GE-NE does not have the capability to perform the evaluation |
| to determine if a defect exists for plants at which GE-NE is not responsible |
| for stability reload licensing calculations. GE-NE has transferred |
| information pursuant to �21.21(b) to those licensees which are known to be |
| potentially affected. |
| |
| "GE-NE has informed all BWR utilities of this issue through the BWROG |
| Potential Issues Response Team (PIRT). All potentially affected utilities |
| have been notified. Compensatory action has been taken at the plants which |
| have been determined to be reportable. Additional information is included in |
| this notification and has been provided to the potentially affected |
| licensees so that they can determine if the concern impacts their stability |
| detect and suppress reload licensing calculations." |
| |
| All GE BWR plants are potentially affected. |
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|General Information or Other |Event Number: 38105 |
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| REP ORG: KANSAS DEPT OF HEALTH & ENVIRONMENT |NOTIFICATION DATE: 06/29/2001|
|LICENSEE: CHEMSYN SCIENCE LABORATORIES |NOTIFICATION TIME: 14:13[EDT]|
| CITY: LENEXA REGION: 4 |EVENT DATE: 06/28/2001|
| COUNTY: STATE: KS |EVENT TIME: 13:30[CDT]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 06/29/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |GREG PICK R4 |
| |PATRICIA HOLAHAN NMSS |
+------------------------------------------------+THOMAS DECKER R2 |
| NRC NOTIFIED BY: JAMES JOHNSON | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| AGREEMENT STATE REPORT: MISSING SHIPMENT OF RADIONUCLIDE |
| |
| Kansas Department of Health (KDHE) was notified that a shipment to Inveresk |
| Research in Scotland was reported missing from the Federal Express at their |
| Memphis, TN hub terminal . The shipment from Chemsyn Science Laboratories |
| of Lenexa, Kansas was 3.5 mCi of radiolabeled (inidazol-2-14C) NED 2000-1 |
| dibenzenesulfonate. The shipment was sent on 6/19/2001 and the search was |
| started on 6/26/2001 when Inveresk contacted Chemsyn about not receiving |
| shipment. |
| |
| Federal Express found the overpack, a dry ice chest (16" x 16" x 23") which |
| originally contained 54 pounds of dry ice and the small Type A Package. The |
| small Type A Package has not been located. |
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|Power Reactor |Event Number: 38106 |
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| FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 06/29/2001|
| UNIT: [] [2] [] STATE: NY |NOTIFICATION TIME: 19:19[EDT]|
| RXTYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 06/29/2001|
+------------------------------------------------+EVENT TIME: 17:15[EDT]|
| NRC NOTIFIED BY: ANTHONY PETRELLI |LAST UPDATE DATE: 06/29/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |RICHARD BARKLEY R1 |
|10 CFR SECTION: | |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
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EVENT TEXT
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| NON-CONSERVATIVE ANALYSIS FOR OPRM SCRAM SETPOINTS |
| |
| "On June 29, 2001, General Electric informed Niagara Mohawk Power |
| Corporation of a non-conservative analysis that supports Operation Power |
| Range Monitor (OPRM) scram setpoints. The non-conservative analysis is |
| generic and has the potential to affect all stability option III and I-D |
| plants. |
| |
| "The consequences of the non-conservative analysis are that the associated |
| OPRM Reactor Protection System (RPS) scram setpoints are also |
| non-conservative. The non-conservative RPS setpoints may result in violating |
| the Minimum Critical Power Ratio (MCPR) safety limit during a |
| thermal-hydraulic instability. |
| |
| "All OPRM channels have been declared inoperable. Technical Specification |
| 3.3.1.1 Action F requires an alternate method of detecting and suppressing |
| thermal-hydraulic instabilities to be implemented within 12 hours. Alternate |
| methods are already established in procedures N2-SOP-29 and N2-RESP-12. |
| Therefore, the Technical Specification required action is satisfied. These |
| alternate methods are the same methods used prior to implementation of the |
| OPRM scram function. |
| |
| "Nine Mile Point Unit 2 has 120 days to restore the OPRMs to an operable |
| condition. If the 120 day allowed outage time is exceeded, the Unit must be |
| in at least STARTUP within the following six hours. |
| |
| "This report is being made as required by 10CFR50.72 (B) (3) (V) (A) as |
| condition that could have prevented the fulfillment of the safety function |
| of a system needed to shutdown the reactor." |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| See EN #38104, GE Nuclear Energy 10 CFR 21 report. |
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|Power Reactor |Event Number: 38107 |
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| FACILITY: WATTS BAR REGION: 2 |NOTIFICATION DATE: 06/29/2001|
| UNIT: [1] [] [] STATE: TN |NOTIFICATION TIME: 21:12[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/29/2001|
+------------------------------------------------+EVENT TIME: 17:28[EDT]|
| NRC NOTIFIED BY: WILLIAM RUSSELL |LAST UPDATE DATE: 06/29/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |THOMAS DECKER R2 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
|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 M/R Y 100 Power Operation |0 Hot Standby |
| | |
| | |
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EVENT TEXT
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| MANUAL REACTOR TRIP PER PROCEDURE DUE TO INCREASING CONDENSER PRESSURE |
| |
| "Watts Bar Unit 1 was manually tripped when the main condenser backpressure |
| reached limits required by procedure. The rise in the backpressure was |
| caused by a reduced condenser circulating water (CCW) flow which resulted |
| from cooling tower fill material obstructing suction screens to the CCW |
| pumps. All safety systems responded as required during the event. Auxiliary |
| Feedwater initiated due to reactor trip with low Tavg, as required. All |
| control rods inserted properly. Inspections are under way to determine the |
| extent of the debris in the system." |
| |
| The licensee notified the NRC Resident Inspector. They will be notifying |
| the State and Local authorities due to noise from the use of steam generator |
| atmospheric reliefs for excess heat removal while the condenser is not |
| available. |
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|General Information or Other |Event Number: 38108 |
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| REP ORG: JACA & SIERRA TESTING LABS |NOTIFICATION DATE: 06/30/2001|
|LICENSEE: JACA & SIERRA TESTING LABS |NOTIFICATION TIME: 15:00[EDT]|
| CITY: TRUJILLO ALTO REGION: 2 |EVENT DATE: 06/30/2001|
| COUNTY: STATE: PR |EVENT TIME: [EDT]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 06/30/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |THOMAS DECKER R2 |
| |PATRICIA HOLAHAN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: MARCOS AROCHO | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|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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| STOLEN MOISTURE DENSITY GAUGE |
| |
| A pickup truck with a stored and locked Troxler moisture density gauge |
| (serial # M1A03A16A) was stolen sometime this morning (6/30/01) in San Juan, |
| Puerto Rico. The gauge contains sealed sources of Cs-137 (10 mCi) and |
| Am-241/Be (50 mCi). The local police and the Puerto Rico Civil Defense have |
| been notified. There has been a press release and their will be television |
| announcements. |
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|Power Reactor |Event Number: 38109 |
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| FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 07/01/2001|
| UNIT: [2] [] [] STATE: PA |NOTIFICATION TIME: 04:35[EDT]|
| RXTYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 07/01/2001|
+------------------------------------------------+EVENT TIME: 02:10[EDT]|
| NRC NOTIFIED BY: ALAN DAY |LAST UPDATE DATE: 07/01/2001|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |RICHARD BARKLEY R1 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 A/R Y 100 Power Operation |0 Hot Shutdown |
| | |
| | |
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EVENT TEXT
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| AUTOMATIC TURBINE TRIP/REACTOR SCRAM DURING TROUBLESHOOTING |
| |
| "During troubleshooting of Peach Bottom Unit 2 electrohydraulic control |
| (EHC) system, the main turbine control valves fast closed, resulting in an |
| automatic turbine trip, reactor protection system (RPS) trip and reactor |
| scram. |
| |
| "Additionally, as a normal result of the reactor scram, reactor water level |
| lowered below 1 inch, causing a valid automatic group II/III primary |
| containment isolation signal (PCIS) in multiple trains. |
| |
| "The plant responded normally, RPS and PCIS signals were reset and unit 2 is |
| continuing to a cooled-down depressurized condition. No radiological |
| release" |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
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|Power Reactor |Event Number: 38110 |
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| FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 07/01/2001|
| UNIT: [1] [2] [] STATE: FL |NOTIFICATION TIME: 15:07[EDT]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 07/01/2001|
+------------------------------------------------+EVENT TIME: 14:10[EDT]|
| NRC NOTIFIED BY: SCOT OEHRLE |LAST UPDATE DATE: 07/01/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |THOMAS DECKER 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 90 Power Operation |90 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
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EVENT TEXT
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| OFFSITE NOTIFICATION DUE TO INJURED LOGGERHEAD SEA TURTLE |
| |
| The licensee notified the State of Florida Fish and Wildlife Commission |
| about the discovery of an injured loggerhead sea turtle from the intake bay. |
| The turtle is being transported to rehabilitation. |
| |
| The licensee notified the NRC Resident Inspector. |
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|Power Reactor |Event Number: 38111 |
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| FACILITY: PALISADES REGION: 3 |NOTIFICATION DATE: 07/01/2001|
| UNIT: [1] [] [] STATE: MI |NOTIFICATION TIME: 17:20[EDT]|
| RXTYPE: [1] CE |EVENT DATE: 07/01/2001|
+------------------------------------------------+EVENT TIME: 13:30[EDT]|
| NRC NOTIFIED BY: DANIEL MALONE |LAST UPDATE DATE: 07/01/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |GEOFFREY WRIGHT R3 |
|10 CFR SECTION: |GENE IMBRO NRR |
|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 Cold Shutdown |0 Cold Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| NON-DESTRUCTIVE EXAMINATION OF CRDM PRESSURE HOUSING FOUND CRACK INDICATION |
| |
| "During non-destructive examination (NDE) of welds on control rod drive |
| mechanism (CRDM) pressure housings, an indication was discovered on CRDM-40. |
| The method being utilized was ultrasonic testing (UT). The indication is |
| axial, approximately 0.7 inches long, located-on the inner surface of the |
| pressure housing. The depth of the indication is approximately 50% |
| through-wall. The indication is located in the top side heat affected zone |
| of an 8 inch butt weld which joins the pressure housing's tubular section to |
| an eccentric reducer. The material of the pressure housing is type 347 |
| stainless steel. |
| |
| "The weld examinations were being conducted as part of an extent of |
| condition evaluation resulting from an earlier discovery, on June 21, 2001, |
| of a through-wall axial indication on CRDM-21. The CRDM-40 indication |
| location corresponds to the location of the earlier discovered indication in |
| CRDM-21(EN #38083) and CRDM-25 (EN #38103). Cause evaluation is ongoing." |
| |
| The licensee notified the NRC Resident Inspector. |
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