Event Notification Report for July 24, 2001
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
07/23/2001 - 07/24/2001
** EVENT NUMBERS **
38161 38162 38163 38164
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|Fuel Cycle Facility |Event Number: 38161 |
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| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 07/23/2001|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 17:27[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 07/23/2001|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 12:55[CDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 07/23/2001|
| CITY: PADUCAH REGION: 3 +-----------------------------+
| COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION |
|LICENSE#: GDP-1 AGREEMENT: Y |MONTE PHILLIPS R3 |
| DOCKET: 0707001 |C.W. (BILL) REAMER NMSS |
+------------------------------------------------+NADER MAMISH IRO |
| NRC NOTIFIED BY: TOM WHITE | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| 4-HOUR NRC BULLETIN 91-01 REPORT |
| |
| The following text is a portion of a facsimile received from Paducah |
| personnel: |
| |
| "At 1255, on 7-23-01, the Plant Shift Superintendent (PSS) was notified that |
| checks required to meet the requirements of NCSA CAS-011 were not performed |
| during replacement of the C-337 Unit 5 Cell 10 RCW [recirculating cooling |
| water] spool piece. NCSA CAS-011 requires a line clarity check on the peak |
| reading pressure gauges prior to connecting the spool piece. This check was |
| not performed. The purpose of this requirement is to ensure the RCW pressure |
| in the condenser does not exceed 35.5 PSIA. |
| |
| "The NRC Acting Senior Resident has been notified of this event. |
| |
| "SAFETY SIGNIFICANCE OF EVENTS: |
| "While a control was violated, insufficient time existed for moisture from |
| the RCW system to enter the process gas system. |
| |
| "POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO(S) OF HOW |
| CRITICALITY COULD OCCUR): |
| "In order for a criticality to be possible, the following conditions must |
| exist. With the condenser RCW supply and return valves closed, the supply or |
| return valve must be leaking to allow the condenser pressure to exceed the |
| minimum coolant pressure of 35.5 PSIA. The process gas equipment must |
| contain a UO2F2 deposit greater than a critical mass. The condenser must |
| have a leak of sufficient rate and duration to allow enough water to |
| overcome the down corner allowing liquid water to enter the cooler. The |
| cooler must also have a simultaneous leak which would allow wet coolant to |
| leak into the process gas side of the equipment at a location which would |
| allow a moderation of the deposit. |
| |
| "CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC): |
| "Two controls on moderation. |
| |
| "ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS |
| LIMIT AND % WORST CASE CRITICAL MASS): |
| "No known deposits of concern at this time.. |
| |
| "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 two |
| controls on moderation. |
| |
| "The first leg of double contingency is based on preventing moderation of a |
| deposit by maintaining the RCW pressure in a condenser below 35.5 PSIA. |
| Pressure gauges are installed and checked for clarity whenever the RCW |
| return valve is closed on a cell without a fluorinating environment. Since |
| clarity of the pressure reading instrument was not verified, the |
| functionality of the pressure reading instrument cannot be assured, |
| violating the control. |
| |
| "The second leg of double contingency is based upon independent verification |
| that the RCW pressure gauges are reading correctly. Since clarity of the |
| pressure reading instrument was not independently verified, this control was |
| violated. |
| |
| "CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEMS AND WHEN EACH WAS |
| IMPLEMENTED: |
| "Upon discovery of the failure to perform the requirement, the coolant |
| system was sampled for moisture and verified to be dry." |
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|Power Reactor |Event Number: 38162 |
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| FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 07/23/2001|
| UNIT: [1] [] [] STATE: NH |NOTIFICATION TIME: 18:34[EDT]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 07/23/2001|
+------------------------------------------------+EVENT TIME: 17:45[EDT]|
| NRC NOTIFIED BY: HUGH HAWKINS |LAST UPDATE DATE: 07/23/2001|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |JOHN WHITE R1 |
|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 |
| | |
| | |
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EVENT TEXT
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| SECURITY REPORT |
| |
| Unescorted access granted inappropriately. Immediate compensatory measures |
| taken upon discovery. The NRC resident inspector will be informed. Contact |
| the NRC Operations Center for additional details. |
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|Power Reactor |Event Number: 38163 |
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| FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 07/23/2001|
| UNIT: [1] [2] [] STATE: GA |NOTIFICATION TIME: 22:19[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 07/23/2001|
+------------------------------------------------+EVENT TIME: 21:36[EDT]|
| NRC NOTIFIED BY: STEVE HOWARD |LAST UPDATE DATE: 07/23/2001|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNUSUAL EVENT |JAY HENSON R2 |
|10 CFR SECTION: |WILLIAM DEAN NRR |
|AAEC 50.72(a) (1) (i) EMERGENCY DECLARED |MR. EACHES FEMA |
| |NADER MAMISH IRO |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |85 Power Operation |
|2 N Y 100 Power Operation |90 Power Operation |
| | |
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EVENT TEXT
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| UNUSUAL EVENT DECLARED DUE TO LOW SERVICE WATER INTAKE LEVEL |
| |
| At 2136, the licensee declared an Unusual Event due to service water intake |
| pump well level less than 60.7' MSL (mean sea level). The licensee |
| determined that one of the intake traveling water screens had become clogged |
| with debris, cleared the screen, and terminated the UE at 2137 when normal |
| pump well level was restored. Reactor power of both units was reduced as a |
| result of the event. |
| |
| The licensee's preliminary investigation indicates that the upstream |
| traveling water screen did not automatically enter a backwash cycle as |
| designed in response to increased differential pressure. The downstream |
| screen was tagged out of service for a planned design modification. The NRC |
| resident inspector has been informed of this event by the licensee. |
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|Power Reactor |Event Number: 38164 |
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| FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 07/24/2001|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 05:59[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 07/24/2001|
+------------------------------------------------+EVENT TIME: 02:51[CDT]|
| NRC NOTIFIED BY: LARRY WESTEROOK |LAST UPDATE DATE: 07/24/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MONTE PHILLIPS R3 |
|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 100 Power Operation |0 Hot Shutdown |
| | |
| | |
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EVENT TEXT
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| AUTOMATIC REACTOR SCRAM ON HIGH REACTOR VESSEL LEVEL |
| |
| The reactor scrammed at 0251 CDT on 7/24/20001 on a level 8 signal, a high |
| reactor vessel level. All rods fully inserted and all systems functioned |
| properly. At the time of the scram there was a surveillance being performed |
| on a level transmitter that feeds the feedwater level control system. |
| Exactly what happened is not known at this time, but an investigation is on |
| going. |
| |
| The plant is stable using the bypass valves to the condenser and level is |
| being maintained with motor driven feedwater pump. |
| |
| The licensee notified the NRC Resident Inspector. |
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