Event Notification Report for June 30, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
06/29/2000 - 06/30/2000
** EVENT NUMBERS **
37075 37130 37131 37132 37133 37134 37135 37136 37137
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 37075 |
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| FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 06/09/2000|
| UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 20:00[EDT]|
| RXTYPE: [1] GE-2 |EVENT DATE: 06/09/2000|
+------------------------------------------------+EVENT TIME: 18:30[EDT]|
| NRC NOTIFIED BY: FRANK CIGANIK |LAST UPDATE DATE: 06/29/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |THOMAS MOSLAK R1 |
|10 CFR SECTION: | |
|NLTR LICENSEE 24 HR REPORT | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| LICENSEE MAY HAVE EXCEEDED LICENSED THERMAL POWER LIMIT |
| |
| While reviewing the plants thermal performance, Oyster Creek discovered that |
| the plant was potentially operating above the Technical Specification |
| licensed thermal limit. Based on a comparison of the various inputs to the |
| plant's thermal heat balance, it appears that the total feedwater flow |
| venturi is reading non-conservatively (lower than actual) in comparison to |
| the summation of the individual feedwater strings flows. As a result of |
| this disparity, the plant's Engineering Staff has tentatively concluded that |
| the heat balance is non-conservatively calculating 5 MWth less than actual |
| based on the lower flow reading. |
| |
| The plant's Technical Specification steady-state thermal power limit is 1930 |
| MWth. Oyster Creek has administratively limited thermal power to 1920 MWth |
| until this situation can be fully analyzed. The plant's Engineering Staff is |
| presently developing a plan to confirm this information and initiate the |
| appropriate corrective actions to resolve this disparity. |
| |
| This condition has been determined reportable under the plant's Technical |
| Specifications Section 2.E (24 Hour Notification) which requires |
| notification of the NRC for all Technical Specification violations. The |
| plant's Technical Specifications require maintaining core thermal power less |
| than 1930 MWth under steady-state conditions and the plant might have been |
| operated for prolonged periods at as high as 1935 MWth. The safety |
| significance of this discrepancy is minimal because the plant's licensing |
| bases includes a 2% error margin which was never challenged. |
| |
| * * * RETRACTION 1623 6/29/2000 FROM FULLER TAKEN BY STRANSKY * * * |
| |
| "After further review, it has been determined that Oyster Creek Nuclear |
| Generating Station did not operate above the licensed limit of 1930 MWt, and |
| we are retracting the notification made on 6/9/00. We determined that the |
| mismatch between the computer generated heat balance and the manual heat |
| balance was due to a feedwater heater leak, and not due to degradation of |
| the final feedwater venturi. The feedwater heater leak will be repaired at |
| the earliest opportunity during the upcoming scheduled refueling outage. As |
| a result, Oyster Creek Nuclear Generating Station has removed the |
| administrative thermal power limit of 1915 MWt, and has returned to full |
| power." |
| |
| The NRC resident inspector will be informed of this retraction. Notified |
| R1DO (Rogge). |
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|Fuel Cycle Facility |Event Number: 37130 |
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| FACILITY: SIEMENS POWER CORPORATION |NOTIFICATION DATE: 06/29/2000|
| RXTYPE: URANIUM FUEL FABRICATION |NOTIFICATION TIME: 00:55[EDT]|
| COMMENTS: LEU CONVERSION (UF6 to UO2) |EVENT DATE: 06/28/2000|
| FABRICATION & SCRAP RECOVERY |EVENT TIME: 21:15[PDT]|
| COMMERICAL LWR FUEL |LAST UPDATE DATE: 06/29/2000|
| CITY: RICHLAND REGION: 4 +-----------------------------+
| COUNTY: BENTON STATE: WA |PERSON ORGANIZATION |
|LICENSE#: SNM-1227 AGREEMENT: Y |GAIL GOOD R4 |
| DOCKET: 07001257 |JOHN HICKEY NMSS |
+------------------------------------------------+CHARLES MILLER IRO |
| NRC NOTIFIED BY: LOREN MAAS |PETER PRESCOTT RCT |
| HQ OPS OFFICER: DOUG WEAVER |GABRINI DOE |
+------------------------------------------------+TURMAN NRC |
|EMERGENCY CLASS: ALE | |
|10 CFR SECTION: | |
|AAEC EMERGENCY DECLARED | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| ALERT DECLARED - OFFSITE FIRE |
| |
| RANGE FIRE ON AND ADJACENT TO THE HANFORD NUCLEAR RESERVATION HAS PROMPTED |
| BENTON COUNTY EMERGENCY MANAGEMENT, IN CONJUNCTION WITH LOCAL LAW |
| ENFORCEMENT, TO REQUIRE A PRECAUTIONARY EVACUATION OF THE HORN RAPIDS |
| TRIANGLE INDUSTRIAL AREA IN WHICH THE SIEMENS FUEL FABRICATION PLANT IS |
| LOCATED. THE PLANT PRODUCTION HAS BEEN SHUT DOWN. ESSENTIAL PLANT |
| PERSONNEL ARE ONSITE. BASED ON DISTANCE AND CURRENT WIND DIRECTION, THE |
| PLANT IS NOT THREATENED. |
| |
| * * * UPDATE AT 0451 ON 6/29/00 BY PROBASCO, RECEIVED BY WEAVER * * * |
| |
| THE ALERT WAS TERMINATED AT 0150 PDT BECAUSE THE FIRE HAS MOVED FURTHER AWAY |
| FROM THE SITE AND IS CONTINUING TO MOVE IN THAT DIRECTION. |
| |
| NRC NOTIFIED RDO (GOOD); EO (HICKEY); IRO (MILLER); FEMA (STEINDURF); DOE |
| (STAMBAUGH); NRC (TURMAN) |
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|Fuel Cycle Facility |Event Number: 37131 |
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| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 06/29/2000|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 09:05[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 06/28/2000|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 08:32[CDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 06/29/2000|
| CITY: PADUCAH REGION: 3 +-----------------------------+
| COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION |
|LICENSE#: GDP-1 AGREEMENT: Y |MELVYN LEACH R3 |
| DOCKET: 0707001 |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: TONY HUDSON | |
| HQ OPS OFFICER: DOUG WEAVER | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| BULLETIN 91-01 24 HOUR REPORT |
| |
| Loss of one of two criticality controls was lost in Drum Room of the C-331 |
| building. The controlled parameter is moderation. The temperature control |
| was lost when the door to the room was left open, this allowed the room |
| temperature to drop below the NCSA specified limit of 105 F (the lowest |
| temperature reached was 103 F). The other controlled parameter, pressure, |
| was maintained throughout this event. |
| |
| The cause of the door being left open is under investigation. The plant |
| notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37132 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WNP-2 REGION: 4 |NOTIFICATION DATE: 06/29/2000|
| UNIT: [2] [] [] STATE: WA |NOTIFICATION TIME: 09:50[EDT]|
| RXTYPE: [2] GE-5 |EVENT DATE: 06/29/2000|
+------------------------------------------------+EVENT TIME: 06:22[PDT]|
| NRC NOTIFIED BY: MIKE KELLER |LAST UPDATE DATE: 06/29/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GAIL GOOD R4 |
|10 CFR SECTION: | |
|NINF INFORMATION ONLY | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| COURTESY CALL RELATED TO BRUSH FIRE |
| |
| This is a courtesy call regarding a brush fire located in the vicinity of |
| the Columbia Generating Station located within the Department of Energy |
| (DOE) Hanford Area in South Eastern portion Washington State. Columbia |
| Generating Station is monitoring a brush fire (30,000 to 40,000 acres) |
| located 2 to 4 miles west of the station. Currently the local Benton County |
| Emergency Operations Center (EOC) and the DOE EOC are coordinating fire |
| fighting efforts. |
| |
| Current weather forecast anticipate winds climbing to 30 knots with |
| continued hot & dry weather. At present the access roads to the station |
| remain open with the DOE restricting access to essential personnel only. |
| The DOE has indicated that later this morning a substantial increase in |
| federal fire fighting assets will be available to fight the fire. |
| |
| The licensee notified the NRC resident inspector. |
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|Power Reactor |Event Number: 37133 |
+------------------------------------------------------------------------------+
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| FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 06/29/2000|
| UNIT: [] [2] [] STATE: TX |NOTIFICATION TIME: 12:14[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/28/2000|
+------------------------------------------------+EVENT TIME: 16:53[CDT]|
| NRC NOTIFIED BY: JIM MORRIS |LAST UPDATE DATE: 06/29/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GAIL GOOD R4 |
|10 CFR SECTION: | |
|NLTR LICENSEE 24 HR REPORT | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PLANT FOUND TO BE IN A CONDITION OUTSIDE OF TECHNICAL SPECIFICATIONS |
| |
| "On June 28, 2000, at 1653 hours, it was determined that Containment |
| Penetration M-85 was not properly isolated in accordance with Technical |
| Specification 3.6.3. |
| |
| "On December 25, 1999, the 2A RCS Hot Leg Primary Sampling system Inside |
| Containment Isolation Valve FV-4454 was declared inoperable and was |
| deenergized in the closed position to comply with Technical Specification |
| 3.6.3 Action b. |
| |
| "In order to perform a stroke test on valve FV-4454, on June 12, 2000, at |
| 1246 hours, the associated Outside |
| Containment Isolation Valve FV-4456 was deenergized in the closed position |
| to comply with Technical |
| Specification 3.6.3 Action b, and subsequently on June 13, 2000, at 1012 |
| hours, the equipment clearance order for FV-4454 was lifted and the valve |
| was energized. However, the associated Post Accident Sampling System Outside |
| Containment Isolation Valve FV-2455/2455A for Penetration M-85 was not |
| deactivated in the closed position as required. |
| |
| "This condition was discovered on June 28, 2000, at 1653 hours, during |
| testing and valve line-up verification on the Post Accident Sampling System. |
| Although not deenergized, valve FV-2455/2455A is a normally closed valve and |
| flow through the penetration has occurred briefly during Post Accident |
| Sampling System testing. |
| |
| "On June 28, 2000, at 1700 hours, Inside Containment Isolation Valve FV-4454 |
| was deenergized in the closed |
| position in order to restore compliance with Technical Specification 3.6.3 |
| Action b. |
| |
| "This notification is being made pursuant to Operating License NPF-80 |
| Condition 2.G for operation or condition |
| prohibited by Technical Specifications." |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 37134 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: METOREX, INC. |NOTIFICATION DATE: 06/29/2000|
|LICENSEE: METOREX, INC |NOTIFICATION TIME: 12:15[EDT]|
| CITY: EWING REGION: 1 |EVENT DATE: 06/28/2000|
| COUNTY: STATE: NJ |EVENT TIME: [EDT]|
|LICENSE#: 29-30342-01 AGREEMENT: N |LAST UPDATE DATE: 06/29/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JOHN ROGGE R1 |
| | |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JAKE COPLAND | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAAA 20.1906(d) SURFACE CONT/ EXT RAD | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SOURCE RECEIVED WITH SURFACE CONTAMINATION |
| |
| The licensee reported that a gauge containing a 40 mCi Fe-55 source (S/N |
| 6674LG) was received with surface contamination (based upon wipe samples) |
| calculated to be 1.37 �Ci. The licensee reported that no contamination was |
| detected on the outside of the shipping package. The source had been shipped |
| to the licensee from AK Steel in Ashland, KY. The licensee has contacted the |
| shipper. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 37135 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: TEXAS DEPARTMENT OF HEALTH |NOTIFICATION DATE: 06/29/2000|
|LICENSEE: RADIOGRAPHIC SPECIALISTS, INC. |NOTIFICATION TIME: 16:51[EDT]|
| CITY: HOUSTON REGION: 4 |EVENT DATE: 06/27/2000|
| COUNTY: STATE: TX |EVENT TIME: [CDT]|
|LICENSE#: L02742 AGREEMENT: Y |LAST UPDATE DATE: 06/29/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |GAIL GOOD R4 |
| |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: HELEN WATKINS (FACSIMILE) | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| AGREEMENT STATE REPORT |
| |
| The film badge of a radiographer for Radiographic Specialists, Houston, TX, |
| received an exposure of 5.755R during the period from 5/10/00-6/9/00. The |
| licensee reported that the individual may have left the film badge clipped |
| to his shirt in a high radiation area. The State of Texas is investigating |
| the incident. |
+------------------------------------------------------------------------------+
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|Power Reactor |Event Number: 37136 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: THREE MILE ISLAND REGION: 1 |NOTIFICATION DATE: 06/29/2000|
| UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 17:06[EDT]|
| RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP |EVENT DATE: 06/29/2000|
+------------------------------------------------+EVENT TIME: 16:44[EDT]|
| NRC NOTIFIED BY: GOODLAVAGE |LAST UPDATE DATE: 06/29/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN ROGGE R1 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNIT OUTSIDE DESIGN BASIS DUE TO 10 CFR PART 50 APPENDIX R ISSUE |
| |
| "10 CFR 50, Appendix R, Section (III)(L)(5) requires that alternate and |
| dedicated shutdown facilities have the means to achieve and maintain cold |
| shutdown condition within 72 hours. TMI committed to this requirement. |
| |
| "Review of current analysis has determined that the commitment to achieve |
| cold shutdown within 72 hours cannot be met. At 1644 on 6/29/00, this |
| condition has been determined to be reportable under 10 CFR 50.72 |
| (b)(1)(ii)(B), which says 'any event or condition during operation that |
| results in the condition of the nuclear power plant, including its principal |
| safety barriers, being seriously degraded or results in the nuclear power |
| plant being in a condition that is outside of the design basis of the |
| plant.' It has been determined that the equipment is operable, but in a |
| nonconforming condition since the 10 CFR 50 Appendix R requirement to |
| achieve cold shutdown within 72 hours cannot be achieved." |
| |
| The NRC resident inspector has been informed of this report by the licensee. |
+------------------------------------------------------------------------------+
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|Power Reactor |Event Number: 37137 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 06/30/2000|
| UNIT: [1] [2] [] STATE: NC |NOTIFICATION TIME: 00:28[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 06/29/2000|
+------------------------------------------------+EVENT TIME: 21:12[EDT]|
| NRC NOTIFIED BY: REINSBURROW |LAST UPDATE DATE: 06/30/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CAUDLE JULIAN R2 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 92 Power Operation |92 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION - FAILURE OF A WARNING SIREN |
| |
| During normal plant operations, a spurious and sustained actuation of siren |
| #7 of the Off Site Emergency Warning System occurred. The actuation was not |
| as a result of personnel actions. Local government agencies were notified. |
| The affected siren actuated at 2112 and was deactivated at 2201. The area |
| covered by the siren has been placed on backup route alerting. |
| |
| The licensee will inform the NRC resident inspector. |
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