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
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|Power Reactor |Event Number: 38189 |
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| 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
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| 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). |
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|Power Reactor |Event Number: 38190 |
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+------------------------------------------------------------------------------+
| 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 |
+------------------------------------------------------------------------------+
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| 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
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| 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
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| 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. |
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