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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  

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|Power Reactor                                    |Event Number:   37378       |
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| 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.   |
+------------------------------------------------------------------------------+