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. |
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+------------------------------------------------------------------------------+
|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
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| 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. |
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+------------------------------------------------------------------------------+
|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
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| 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. |
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+------------------------------------------------------------------------------+
|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. |
+------------------------------------------------------------------------------+
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|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
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| 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. |
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