The U.S. Nuclear Regulatory Commission is in the process of rescinding or revising guidance and policies posted on this webpage in accordance with Executive Order 14151 Ending Radical and Wasteful Government DEI Programs and Preferencing, and Executive Order 14168 Defending Women From Gender Ideology Extremism and Restoring Biological Truth to the Federal Government. In the interim, any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

Event Notification Report for September 27, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           09/26/2000 - 09/27/2000

                              ** EVENT NUMBERS **

37378  37379  37380  37381  37382  37383  37384  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37378       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SEQUOYAH                 REGION:  2  |NOTIFICATION DATE: 09/26/2000|
|    UNIT:  [1] [] []                 STATE:  TN |NOTIFICATION TIME: 01:23[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        09/26/2000|
+------------------------------------------------+EVENT TIME:        00:43[EDT]|
| NRC NOTIFIED BY:  THOMAS MARSHALL              |LAST UPDATE DATE:  09/26/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          UNU                   |THOMAS DECKER        R2      |
|10 CFR SECTION:                                 |BILL BATEMAN         NRR     |
|AAEC                                            |JOSEPH GIITTER       IRO     |
|                                                |CANUPP               FEMA    |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Hot Shutdown     |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNIT 1 MET THE CONDITIONS FOR AN UNUSUAL EVENT BASED ON RCS LEAKAGE > 25 GPM |
| WHILE IN MODE 4.                                                             |
|                                                                              |
| "While placing the '1A'  RHR Pump in service for shutdown cooling, the Unit  |
| experienced an RCS leak of approximately 45 gpm.  It is believed that the    |
| cause of the leak is a relief valve that lifted and failed to reseat.  The   |
| leak was isolated from the RCS when the RHR suction valves from the RCS      |
| (1-FCV-74-1 and 1-FCV-74-2) were closed.  The leak lasted approximately 10   |
| minutes.                                                                     |
|                                                                              |
| "According to the Plant's Radiological Emergency Plan, the conditions for a  |
| Notification of Unusual Event (NOUE) were met, but before it could be        |
| declared the leak was isolated, so an NOUE was not declared but will be      |
| reported."                                                                   |
|                                                                              |
| The RCS which leak occurred at 0002EDT was terminated at 0012EDT (10         |
| minutes).  Operators estimated the leakage at 45 gpm based on the change in  |
| PRT (pressurizer relief tank) level.  The two relief valves involved are     |
| 1-VLV-63-626 and 1-VLV-63-627 with setpoints of approximately 600 psig.  RCS |
| pressure was 345 psig when the RHR suction valves were opened.  The RHR      |
| pumps develop approximately 180 psig which combined with the 345 psig RCS    |
| pressure (inlet) indicated about 525 psig RHR discharge pressure in the      |
| control room.  Both trains of RHR have been declared inoperable pending      |
| identification and correction of the problem.  Decay heat is current being   |
| removed by the main condenser through the steam dumps using both             |
| motor-driven auxiliary feedwater pumps.  The licensee has no plans for a     |
| press release at this time and did inform the NRC resident inspector.        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37379       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAN ONOFRE               REGION:  4  |NOTIFICATION DATE: 09/26/2000|
|    UNIT:  [] [2] [3]                STATE:  CA |NOTIFICATION TIME: 16:35[EDT]|
|   RXTYPE: [1] W-3-LP,[2] CE,[3] CE             |EVENT DATE:        09/26/2000|
+------------------------------------------------+EVENT TIME:        13:00[PDT]|
| NRC NOTIFIED BY:  CLAY WILLIAMS                |LAST UPDATE DATE:  09/26/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHUCK CAIN           R4      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(vi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|3     N          Y       100      Power Operation  |100      Power Operation  |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION MADE TO THE CALIFORNIA DEPARTMENT OF ENVIRONMENTAL      |
| HEALTH AND THE OFFICE OF EMERGENCY SERVICES FOR A SODIUM HYPOCHLORIDE TANK   |
| LEAK.                                                                        |
|                                                                              |
| On September 26, 2000, at about 0816 PDT, control room personnel were        |
| notified of a small leak from Unit 2 sodium hypochloride tank.  The leak was |
| in the tank discharge line upstream of the outlet isolation valve.  At about |
| 1020 PDT, site personnel completed installation of a soft patch to terminate |
| the leak (SCE is planning to implement  a more permanent repair after the    |
| tank contents have been offloaded).  All of the estimated 300 gallons that   |
| leaked from the tank was contained within a tank sump and was not released   |
| to the environment.                                                          |
|                                                                              |
| The NRC Resident Inspector has been informed of this event by the licensee.  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37380       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  CALIFORNIA RADIATION CONTROL PRGM    |NOTIFICATION DATE: 09/26/2000|
|LICENSEE:  LAW ENGR. ENVIRONMENTAL SERVICE, KY  |NOTIFICATION TIME: 18:10[EDT]|
|    CITY:  SACARAMENTO              REGION:  4  |EVENT DATE:        09/26/2000|
|  COUNTY:                            STATE:  CA |EVENT TIME:        06:00[PDT]|
|LICENSE#:  KY 201257-51          AGREEMENT:  Y  |LAST UPDATE DATE:  09/26/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |CHUCK CAIN           R4      |
|                                                |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  BOB FUNDERBURG               |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TROXLER MOISTURE DENSITY GAUGE STOLEN FROM THE BACK OF A PICKUP TRUCK.       |
|                                                                              |
| An employee of Law Engineering Environmental Service of Kentucky had         |
| reciprocity with the state of Nevada.  After the employee had completed his  |
| work in Las Vegas, NV he decided to take the long way home.  He spent the    |
| night at the Holiday Inn in downtown Sacramento, CA.  In the morning the     |
| person discovered that the chain had been cut to the Troxler Moisture        |
| Density gauge, Model #3411-B  S/N 12599.   The Sacramento Police Department  |
| was notified of the theft of the gauge.   An ad will be placed in the        |
| Sacramento Bee newspaper with a $1,000 reward for the return of the gauge.   |
| The Radiation Safety Officer for Law  Engineering Environmental Service was  |
| notified of this incident.                                                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   37381       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  PHILLIP  MORRIS, USA                 |NOTIFICATION DATE: 09/26/2000|
|LICENSEE:  PHILLIP MORRIS, USA                  |NOTIFICATION TIME: 18:28[EDT]|
|    CITY:  RICHMOND                 REGION:  2  |EVENT DATE:        09/25/2000|
|  COUNTY:                            STATE:  VA |EVENT TIME:        17:00[EDT]|
|LICENSE#:  45-00385-06           AGREEMENT:  N  |LAST UPDATE DATE:  09/26/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |CHARLES R. OGLE      R2      |
|                                                |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  CHUCK STIFF                  |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|IBBF 30.50(b)(2)(ii)     EQUIP DISABLED/FAILS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| ACCURAY MICRO 10 GAUGE LEAD FUSIBLE LINK MELTED AND CAUSED THE SHUTTER OF    |
| THE GAUGE TO REMAIN OPEN.                                                    |
|                                                                              |
| 24 HOUR NOTIFICATION                                                         |
|                                                                              |
| An Accuray Micro 10 gauge, containing a 25 millicurie Sr-90 sealed source,   |
| fusible lead link melted, preventing the gauge shutter from closing.  A      |
| warning light associated with Accuray Micro 10 gauge warned plant personnel  |
| that the shutter to the gauge was still open.  Nobody was exposed.  The      |
| Accuray Micro 10 gauge registration number is NR-109-D-125-B.  The shutter   |
| of the gauge was closed, placed in a lead pig and stored in a lead safe.     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37382       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH                    REGION:  2  |NOTIFICATION DATE: 09/26/2000|
|    UNIT:  [1] [] []                 STATE:  GA |NOTIFICATION TIME: 18:45[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        09/26/2000|
+------------------------------------------------+EVENT TIME:        16:20[EDT]|
| NRC NOTIFIED BY:  ED BURKETT                   |LAST UPDATE DATE:  09/26/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHARLES R. OGLE      R2      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       95       Power Operation  |95       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| EXCESS FLOW CHECK VALVE  FOR  "A" RECIRCULATION PUMP # 2 SEAL PRESSURE       |
| SIGNAL FAILED TO SEAT OFF WHEN TESTED.                                       |
|                                                                              |
| Excess flow check valve 1B31F003A failed to check (seat off) when tested per |
| S7SV-SUV-004-1S.  This excess flow check valve provides isolation for the    |
| "A" Recirculation Pump # 2 seal pressure  signal.  The excess flow check     |
| valve will be isolated per Technical Specification 3.6.1.3.C (Primary        |
| Containment Isolation Valve).  Technical Specification 3.6.1.3.C states that |
| ,if the valve cannot be isolated, the plant must be in Mode 3 (Hot Shutdown) |
| within 12 hours.  The licensee stated that the valve will be isolated before |
| the TS time limit runs out.                                                  |
|                                                                              |
| The NRC Resident Inspector will be notified by the licensee of this event.   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   37383       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 09/26/2000|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 20:40[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        09/26/2000|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        17:30[EDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  09/26/2000|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |BRENT CLAYTON        R3      |
|  DOCKET:  0707002                              |JOHN HICKEY          NMSS    |
+------------------------------------------------+FRANK CONGEL         IRO     |
| NRC NOTIFIED BY:  JIM McCLEERY                 |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 4-HOUR NRC BULLETIN 91-01 REPORT INVOLVING THE X-705, DECON FACILITY,        |
| COMPLEXING HANDTABLE DUCTWORK                                                |
|                                                                              |
| At 1730 during a review of Nuclear Criticality Safety Approval (NCSA)        |
| Corrective Action Plan (CAP) with NCS it was noted that the X-705 Complexing |
| Handtable was not covered by an active NCSA.  NCSA 705_014A00 had been       |
| cancelled and the PORC approved 705_014A01 was not activated.  Based on      |
| security sweep data completed by Applied Nuclear Technology (ANT) personnel  |
| it can be conservatively estimated that greater than 15 grams of U-235 exist |
| in the duct work associated with the handtable.  TSR 3.11.2 Requires a NCSA  |
| when operations involve uranium enriched to 1.0% or higher U-235 and 15      |
| grams or more U-235.                                                         |
|                                                                              |
| The complexing handtable has not been in operation since NRC transition on   |
| 03/03/97 and remains out of service.  Upon notification of this issue the    |
| Plant Staff Superintendent office directed the facility management to enter  |
| an anomalous condition.  This is reportable under UE2-RA-RE1030 (Event       |
| Report Criteria) 3.C.1 as a 4 hour NRC Bulletin 91-01 event.                 |
|                                                                              |
| SAFETY SIGNIFICANCE OF EVENT:                                                |
|                                                                              |
| The safety significance of this event is very low.  No operation had taken   |
| place on the complexing handtable since transition on 03/03/97.  The small   |
| amount of hold up may be greater than 15 grams of U-235, however, the        |
| available data for the remainder of the handtable operation shows reading at |
| or near background levels.                                                   |
|                                                                              |
| POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO OF HOW CRITICALITY , |
| ETC.):                                                                       |
|                                                                              |
| Since the handtable and associated piping are favorable geometry for any     |
| enrichment, material would have to accumulate in the ductwork or pile up to  |
| achieve a critical configuration.  The operation is not currently being      |
| performed and the ductwork is not connected to any system, therefore, a      |
| criticality does not appear credible.                                        |
|                                                                              |
| CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.):     |
|                                                                              |
| The controlled parameter is geometry.  The approved, but not implemented     |
| NCSA establishes two controls based on geometry.                             |
|                                                                              |
| ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS     |
| LIMIT AND % WORST CASE OF CRITICAL MASS):                                    |
|                                                                              |
| The amount of U-235 is not more than 25 grams.  Enrichment is not known, but |
| could be as high as 100%.  The form of material is either uranyl fluoride or |
| uranyl nitrate.                                                              |
|                                                                              |
| NUCLEAR CRITICALITY SAFETY CONTROL OR CONTROL SYSTEMS AND DESCRIPTION OF THE |
| FAILURES OR DEFICIENCIES                                                     |
|                                                                              |
| The only deficiency is that the ductwork for the handtable potentially       |
| contains more than 15 grams U-235 without an active NCSA to establish the    |
| necessary controls to ensure double contingency.                             |
|                                                                              |
| CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN EACH WAS IMPLEMENTED:   |
|                                                                              |
| Anomalous condition remains in effect until evaluations and testing are      |
| completed.                                                                   |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the certificate     |
| holder.                                                                      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37384       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT          REGION:  1  |NOTIFICATION DATE: 09/27/2000|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 03:15[EDT]|
|   RXTYPE: [1] GE-2,[2] GE-5                    |EVENT DATE:        09/27/2000|
+------------------------------------------------+EVENT TIME:        01:23[EDT]|
| NRC NOTIFIED BY:  ERIC KELSEY                  |LAST UPDATE DATE:  09/27/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN KINNEMAN        R1      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     A          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR SCRAM SIGNAL WITH ALL CONTROL RODS ALREADY INSERTED        |
|                                                                              |
| "While in Cold Shutdown conditions, Nine Mile Point Unit 1 experienced a     |
| Reactor Scram initiated by Low water level. All rods were fully inserted at  |
| the time of the initiation and all required safety functions operated as     |
| required. The cause of the low water level condition was due to a level      |
| transient experienced while placing the Reactor Water Cleanup System in      |
| service. The lowest indicated water level was 133 inches above top of active |
| fuel. Emergency Operating Procedures and Special Operating Procedures were   |
| implemented and reactor water level was returned to the normal cold shutdown |
| level of 149 inches above top of active fuel. There were no adverse effects  |
| on Reactor Plant Systems."                                                   |
|                                                                              |
| The NRC resident inspector will be informed of this event by the licensee.   |
+------------------------------------------------------------------------------+


Page Last Reviewed/Updated Wednesday, March 24, 2021