Event Notification Report for January 4, 2001
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
01/03/2001 - 01/04/2001
** EVENT NUMBERS **
37642 37643 37644
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|Power Reactor |Event Number: 37642 |
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| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 01/02/2001|
| UNIT: [2] [] [] STATE: NY |NOTIFICATION TIME: 22:05[EST]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 01/02/2001|
+------------------------------------------------+EVENT TIME: 15:36[EST]|
| NRC NOTIFIED BY: PHIL SANTINI |LAST UPDATE DATE: 01/03/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES NOGGLE R1 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 N Y 6.5 Power Operation |5 Power Operation |
| | |
| | |
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EVENT TEXT
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| AUXILIARY FEEDWATER PUMP AUTOMATIC START |
| |
| The plant sustained a main turbine trip on steam generator high level, cause |
| under review. The turbine trip caused a main feedwater trip which caused an |
| automatic start of the 21 and 23 auxiliary feedwater pumps, as designed. |
| The licensee review of the event determined, later in the evening, that the |
| pump starts were reportable under 10 CFR 50.72(b)(2)(ii). |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| * * * UPDATED AT 1633 EST ON 01/03/2001 BY ROBERT ALLEN TO FANGIE JONES * * |
| * |
| |
| "The following is an update to NRC event report 37642: ESF Actuations |
| |
| "Indian Point Unit 2 sustained inadvertent ESF component actuations |
| following a main turbine trip on high steam generator level that occurred |
| during preparation for admitting steam to roll the main turbine for plant |
| startup. There was no reactor trip nor was one required. The main turbine |
| was latched with the stop valves open and the control valves closed. Steam |
| Generator level control was in manual as is normal at low reactor power |
| levels. A second condensate pump was started which caused an increase in |
| main feedwater pressure which caused increasing steam generator levels. |
| Operator attempts to reduce flow were unsuccessful and a high steam |
| generator level turbine trip signal caused the main turbine stop valves to |
| close (trip) and caused the main feedwater pump to trip. This high level |
| trip signal also resulted in the closing of the main feedwater pump |
| discharge valves (ESF valves), the closing of the steam generator blow down |
| isolation valves (ESF valves) and the starting of the motor driven Auxiliary |
| Feedwater pumps (ESF) as designed." |
| |
| The licensee intends to notify the NRC Resident Inspector. |
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|Fuel Cycle Facility |Event Number: 37643 |
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| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 01/03/2001|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 15:03[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 01/02/2001|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 17:00[CST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 01/03/2001|
| CITY: PADUCAH REGION: 3 +-----------------------------+
| COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION |
|LICENSE#: GDP-1 AGREEMENT: Y |MELVYN LEACH R3 |
| DOCKET: 0707001 |PATRICIA HOLAHAN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: M.C. PITTMAN | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
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| | |
| | |
| | |
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EVENT TEXT
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| NRC BULLETIN 91-01 24 HOUR REPORT |
| |
| The following is quoted from the written report: |
| |
| At 1700, on 1/2/01 The Plant Shift Superintendent (PSS) was notified that |
| the mass of U-235 was incorrectly copied from a Request for Waste |
| Classification (RWC) onto the Waste Consolidation Container Log Sheet and |
| incorrectly independently verified in violation of NCSA.WMO.004. Independent |
| verification of the consolidation drum mass is used to ensure the total mass |
| dose not exceed the 120 gram U-235 limit. The particular drum in question |
| contains less than 15 grams of U-235. [This event actually occurred on |
| 6/21/2000 and was found during a normal review of records on 01/02/2001] |
| |
| The NRC resident inspector has been notified of this event. |
| |
| PGDP Problem Report No. ATRC-01-0024; PGDP event Report No, PAD-2001-001 |
| Event Worksheet |
| Responsible Division: Production Support |
| |
| SAFETY SIGNIFICANCE OF EVENTS: Even though less than 15 grams of U-235 was |
| involved in this incident, independent verification was not properly |
| performed. This type of administrative control is used throughout the PGDP |
| NCS program. |
| |
| POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO(S) OF HOW |
| CRITICALITY COULD OCCUR: In order for a criticality to be possible, |
| multiple drums would have to be incorrectly consolidated and the resulting |
| mass contained within the drum would need to exceed 1500 grams of U-235 at |
| an enrichment of 5.5%. (This all was generated onsite and has an enrichment |
| of less than 2.1 %.) |
| |
| CONTROLLED PARAMETERS (MASS, MODERATION GEOMETRY CONCENTRATION ETC): Double |
| contingency for this scenario Is established by implementing two independent |
| controls on mass |
| |
| ESTIMATED AMOUNT, ENRICHMENT FORM OF LICENSED MATERIAL (INCLUDE PROCESS |
| LIMIT AND % WORST CASE CRITICAL MASS): Less than 15 grams of U~235 at an |
| enrichment of less than 2.1%. |
| |
| NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION |
| OF THE FAILURES OR DEFICIENCIES: The first leg of double contingency is |
| based on correctly calculating the cumulative U-235 mass in the |
| consolidation drum to ensure the 120 gram limit is not exceeded. The actual |
| mass was incorrectly copied from the RWC onto the consolidation log sheet, |
| making it impossible to correctly calculate the consolidated mass. |
| Therefore, the control was violated and the first leg of double contingency |
| was lost. |
| |
| The second leg of double contingency is an administrative control to |
| independently verify that the mass was copied correctly and the cumulative |
| mass total is correct. The independent verification did not identify that |
| the incorrect mass was copied. This control was violated and this leg of |
| double contingency was not maintained. |
| |
| Since double contingency is based on two controls on mass, double |
| contingency was not maintained. |
| |
| CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEMS AND WHEN EACH WAS IMPLEMENTED: |
| The area was immediately roped off and posted to control access and prevent |
| the movement of fissile/potentially fissile material within the area. The |
| actual mess of U-235 in the consolidation drum was verified to be less than |
| 15 grams which reestablished control. The waste consolidation container log |
| sheet was corrected and independently verified prior to removing the ropes |
| and postings. |
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|Power Reactor |Event Number: 37644 |
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| FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 01/03/2001|
| UNIT: [1] [2] [] STATE: AL |NOTIFICATION TIME: 18:27[EST]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 01/03/2001|
+------------------------------------------------+EVENT TIME: 15:30[CST]|
| NRC NOTIFIED BY: JAMES ODOM |LAST UPDATE DATE: 01/03/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MIKE ERNSTES R2 |
|10 CFR SECTION: | |
|DDDD 73.71 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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 Y 100 Power Operation |100 Power Operation |
| | |
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EVENT TEXT
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| PHYSICAL SECURITY REPORT - 1 HOUR |
| |
| The licensee discovered a potential compromise of classified safeguards |
| information and took immediate compensatory measures. |
| |
| The licensee notified the NRC Resident Inspector. |
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