Event Notification Report for August 9, 2001
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 08/08/2001 - 08/09/2001 ** EVENT NUMBERS ** 38189 38190 38191 38192 +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38189 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 08/07/2001| | UNIT: [1] [] [] STATE: MS |NOTIFICATION TIME: 23:11[EDT]| | RXTYPE: [1] GE-6 |EVENT DATE: 08/07/2001| +------------------------------------------------+EVENT TIME: 20:15[CDT]| | NRC NOTIFIED BY: BRIAN BLANCHE |LAST UPDATE DATE: 08/08/2001| | HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |CHARLES MARSCHALL R4 | |10 CFR SECTION: | | |ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| | |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 A/R Y 100 Power Operation |0 Hot Shutdown | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 1 EXPERIENCED AN AUTOMATIC REACTOR SCRAM FOR REASONS UNKNOWN | | | | "At 2015, Grand Gulf Unit 1 had an automatic RPS actuation. This is a | | 4-hour notification per 10 CFR 50.72 (b)(2)(iv)(B). All systems performed | | as expected, except that Feedwater/Condensate were not available due to | | hotwell level problems. RCIC was manually started for level control. At | | the time of the scram, a local generating station was experiencing | | switchyard problems (Baxter Wilson Electric Station). Also at the time, | | significant lightning strikes were noticed in the area. Scram initiation | | event analysis is in progress." | | | | All rods fully inserted. The licensee is in the process of restoring the | | condensate system. Offsite power is stable and available. All safety | | equipment is available. The main condenser is available for decay heat | | removal. | | | | The licensee informed the NRC resident inspector. | | | | * * * UPDATE 1756EDT ON 8/8/01 FROM WALTER CADE TO S. SANDIN * * * | | | | "This is supplemental to event number 38189 reported on 8/7/01. | | | | " During Post Trip analysis of Reactor Scram, it was determined that the | | EOC-RPT circuits required by GGNS Technical Specifications did not function | | as expected. There were no consequences to the failure as a non-tech spec | | vendor supplied load reject circuit operated properly. This is being | | reported per 10 CFR 50.72 (b)(3)(v)(A). Details will be available in the | | LER to follow. This circuit [is] not required below 40% Reactor Power." | | | | The unit is currently in mode 3 making preparations for restart. Corrective | | actions will be determined following completion of a fuels analysis. This | | issue and a possible TS change request has been discussed with NRR. The | | licensee informed the NRC resident inspector. Notified R4DO(Marschall). | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38190 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 08/08/2001| | UNIT: [1] [2] [] STATE: PA |NOTIFICATION TIME: 11:37[EDT]| | RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 08/07/2001| +------------------------------------------------+EVENT TIME: 18:10[EDT]| | NRC NOTIFIED BY: ROBINSON |LAST UPDATE DATE: 08/08/2001| | HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |DANIEL HOLODY R1 | |10 CFR SECTION: | | |NONR OTHER UNSPEC REQMNT | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 100 Power Operation |99.8 Power Operation | |2 N Y 100 Power Operation |99.8 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL OPERATION OUTSIDE OF LICENSE LIMITS | | | | On 8/7/2001, with Unit 1 and Unit 2 operating in Mode 1 at 100% power, | | during a review of the Core Thermal Power calculation, Engineering | | discovered that a constant for the Moisture Fraction input into the | | calculation was non-conservative. Due to the identified non-conservatism in | | the constant, actual core thermal power could have been as much as 6 MWth | | higher than indicated (~0.2% of Rated Thermal Power). This condition | | resulted in both Units having potentially operated above their Maximum Power | | Level License Limits (Reference NPF-14, 2.C(1) and NPF-22, 2.C(1)). | | | | Both Units have been administratively de-rated 7 MWth until this issue is | | resolved. | | | | There is a potential that this condition has existed since the startup of | | both Units. | | | | This event meets the License Conditions requiring a 24 Hour report in | | accordance with 10CFR50.72. | | | | | | The NRC Resident Inspector was notified. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Fuel Cycle Facility |Event Number: 38191 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 08/08/2001| | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 21:20[EDT]| | COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 08/08/2001| | 6903 ROCKLEDGE DRIVE |EVENT TIME: 09:15[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 08/08/2001| | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION | |LICENSE#: GDP-1 AGREEMENT: Y |ANNE MARIE STONE R3 | | DOCKET: 0707001 |SUSAN FRANT NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: K. A. BEASLEY | | | HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24-HOUR NRC BULLETIN 91-01 REPORT INVOLVING VIOLATION OF CRITICALITY | | CONTROLS | | | | "At 0915, on 8-8-01, the Plant Shift Superintendent (PSS) was notified of an | | NCSA violation that had occurred in the C-335 building. While a Waste | | Management operator was transporting a potentially fissile 5.5 gallon waste | | drum on the ground floor of C-335, the operator momentarily set down the | | drum being transported closer than 2 feet from another potentially fissile | | drum in violation of the spacing requirements in NCSA GEN-15. The operator | | them continued the task, and transported the container to its desired | | location. The requirement states that a minimum 2 foot edge-to edge spacing | | is required between fissile/potentially fissile waste containers. This | | requirement is used as an interaction control. | | | | "Since one leg of double contingency was lost this is being reported to the | | NRC as a 24-hr. Event report. | | | | "The NRC Acting Senior Resident has been notified of this event. | | | | "SAFETY SIGNIFICANCE OF EVENTS: | | | | "While a control was violated, concurrent violations of the same control | | would have to occur for a criticality to be possible. NCSA GEN-15 limits the | | movement of fissile/potentially fissile waste to one container at a time, | | limiting the possibility of concurrent violations of the spacing control. | | | | "POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO(S) OF HOW | | CRITICALITY COULD OCCUR: | | | | "In order for a criticality to be possible, additional concurrent spacing | | violations would have to occur. | | | | "CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.): | | | | "Double contingency for this scenario is established by Implementing a | | control for geometry and a control for interaction. | | | | "ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS | | LIMIT AND %WORST CASE CRITICAL MASS): | | | | "Less than 240 grams U-235 | | . | | "NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION | | OF THE FAILURES OR DEFICIENCIES | | | | "Double contingency for this scenario is established by implementing a | | control for geometry and a control for interaction. | | | | "The first leg of double contingency is based on geometry. Specific | | dimensions for the 5.5 gallon waste drums are used in the calculation | | analysis. The drum used was an AQ-NCS approved container. This control was | | not violated. | | | | "The second leg of double contingency is based on interaction. NCSA GEN-15 | | requires fissile/potentially fissile waste container be maintained a minimum | | of 2 foot edge-to edge from other fissile/potentially fissile material. By | | placing the drum less than 2 feet from another fissile/potentially fissile | | waste container, the control was violated and the process condition limit | | was exceeded. | | | | "Since the interaction process condition limit was exceeded, double | | contingency was not maintained. | | | | "CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEMS AN WHEN EACH WAS IMPLEMENTED: | | | | "The drum was placed in a safe configuration immediately following the | | incident." | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38192 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 08/08/2001| | UNIT: [] [4] [] STATE: FL |NOTIFICATION TIME: 22:42[EDT]| | RXTYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 08/08/2001| +------------------------------------------------+EVENT TIME: 19:00[EDT]| | NRC NOTIFIED BY: ROBERT GOODIN |LAST UPDATE DATE: 08/08/2001| | HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |CAUDLE JULIAN R2 | |10 CFR SECTION: | | |NONR OTHER UNSPEC REQMNT | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | |4 N Y 100 Power Operation |100 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | STARTUP TRANSFORMER (SUT) AND 4A EMERGENCY DIESEL GENERATOR (EDG) BOTH | | INOPERABLE | | | | Unit 4 Startup Transformer (SUT) and 4A EDG were both inoperable for 3 | | hours, 40 minutes on 08/08/01. This was discovered after the fact at 1900 | | hours on 08/08/01 while investigating a failure of the 4A EDG ventilation | | system. The 4A EDG was restored to operable status at 1920 hours on | | 08/08/01. The Unit 4 SUT was taken out of service at 0800 0n 08/08/01 for | | planned maintenance. The SUT on Unit 4 was returned to operable status at | | 1140 hours on 08/08/01. | | | | | | The NRC Resident Inspector was notified of this event by the licensee. | +------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021