Event Notification Report for July 23, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
07/22/1999 - 07/23/1999
** EVENT NUMBERS **
35944 35945 35946 35947
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|Other Nuclear Material |Event Number: 35944 |
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| REP ORG: IDAHO NAT ENGR & ENVIRONMENTAL LAB |NOTIFICATION DATE: 07/21/1999|
|LICENSEE: IDAHO NAT ENGR & ENVIRONMENTAL LAB |NOTIFICATION TIME: 22:17[EDT]|
| CITY: Idaho Falls REGION: 4 |EVENT DATE: 07/21/1999|
| COUNTY: STATE: ID |EVENT TIME: 19:55[MDT]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 07/22/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |ELMO COLLINS R4 |
| |LARRY CAMPER NMSS |
+------------------------------------------------+FRANK CONGEL IRO |
| NRC NOTIFIED BY: JOE GARCIA |CHARLIE BAGWELL FEMA |
| HQ OPS OFFICER: DOUG WEAVER |BILL BEECHER PAO |
+------------------------------------------------+DOE (fax) |
|EMERGENCY CLASS: | |
|10 CFR SECTION: | |
|NINF INFORMATION ONLY | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| DOE ALERT DECLARED DUE TO A BRUSH FIRE ON SITE PROPERTY |
| |
| The licensee declared a DOE ALERT due to a brush fire that has burned onto |
| the Idaho National Engineering and Environmental Laboratory (INEEL) site |
| property. No radioactive material is currently threatened by the fire. The |
| use of some communications towers has been interrupted because the fire |
| burned a telephone pole connecting the towers to the facility. |
| |
| The licensee notified the state of Idaho and local county officials, DOE and |
| the Fort Hall Indian Reservation. |
| |
| * * * UPDATE AT 0047 ON 07/22/99 FROM ED BROWN TO JOLLIFFE * * * |
| |
| The brush fire has burned to within 11 miles of the nearest site building. |
| The wind is presently blowing from 320� (Southeast, away from site |
| buildings) at 4 MPH. The outside temperature is 65�F. The fire is being |
| fought by the Bureau of Land Management. There is no threat to site |
| facilities. |
| |
| * * * UPDATE AT 0137 ON 07/22/99 FROM ED BROWN TO JOLLIFFE * * * |
| |
| The wind is now blowing from 224� (Northeast, away from site buildings). |
| |
| * * * UPDATE AT 0211 ON 07/22/99 FROM ED BROWN TO JOLLIFFE * * * |
| |
| At 2347 MDT on 07/21/99, the licensee terminated the DOE ALERT. The fire is |
| now under control and there is now no ongoing fire on INEEL site property. |
| |
| The licensee notified the state of Idaho and local county officials, DOE and |
| the Fort Hall Indian Reservation of the termination of the DOE ALERT. |
| |
| The NRC Operations Officer notified R4DO Collins, NMSS EO Camper, IRO |
| Congel, FEMA Bagwell, PAO Beecher, DOE (fax), USDA (fax), HHS (fax) and EPA |
| (NRC) (fax) of the termination of the DOE ALERT. |
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|General Information or Other |Event Number: 35945 |
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| REP ORG: TX DEPT OF HEALTH BUR OF RAD CONTRL |NOTIFICATION DATE: 07/22/1999|
|LICENSEE: GENERAL INSPECTION SERVICES, INC |NOTIFICATION TIME: 14:20[EDT]|
| CITY: AUSTIN REGION: 4 |EVENT DATE: 07/22/1999|
| COUNTY: STATE: TX |EVENT TIME: 10:00[CDT]|
|LICENSE#: 02319 AGREEMENT: Y |LAST UPDATE DATE: 07/22/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |ELMO COLLINS R4 |
| |LARRY CAMPER NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JIM OGDEN (FAX) | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
|BAE1 20.2202(b)(1) PERS OVEREXPOSURE | |
| | |
| | |
| | |
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EVENT TEXT
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| RADIATION EXPOSURE TO AN INDUSTRIAL RADIOGRAPHER |
| |
| A WHOLE BODY DOSE OF 6.965 REM WAS RECEIVED BY A GENERAL INSPECTION |
| SERVICES, INC INDUSTRIAL RADIOGRAPHER ACCORDING TO HIS APRIL BADGE READING. |
| HE HAS BEEN REMOVED FROM WORK EXPOSING HIM TO IONIZING RADIATION UNTIL |
| 01/01/00. THIS IS TX INCIDENT #7481. |
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|Power Reactor |Event Number: 35946 |
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| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 07/22/1999|
| UNIT: [] [3] [] STATE: NY |NOTIFICATION TIME: 15:24[EDT]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 07/22/1999|
+------------------------------------------------+EVENT TIME: 14:30[EDT]|
| NRC NOTIFIED BY: CHARLES KOCSIS |LAST UPDATE DATE: 07/22/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES NOGGLE 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|3 N Y 100 Power Operation |100 Power Operation |
| | |
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EVENT TEXT
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| OUTSIDE DESIGN BASIS ISSUE |
| |
| In a conversation with Westinghouse on 07/22/99, the Licensee was advised of |
| the preliminary results of a reanalysis of main steam line break (MSLB) at |
| 70% and 102% power to address a non-conservative assumption made with regard |
| to feedwater addition. The original assumption was 800 cubic feet of |
| unisolable volume which has been determined to be 3,783 cubic feet. This |
| represents the volume from the main boiler feed pump discharge isolation |
| valves to the steam generator (the feedwater isolation valve on the faulted |
| generator is assumed to fail). Westinghouse advised that the preliminary |
| calculation showed that the containment design pressure would be exceeded |
| unless there were changes to the design input assumptions that are part of |
| the Indian Point Unit 3 licensing basis. Based upon this, the Licensee |
| considers Unit 3 to be outside the design basis. |
| |
| The Licensee evaluated plant operability based upon the telecon with |
| Westinghouse. Westinghouse advised that the MSLB peak pressure would not |
| exceed the current calculated pressure of 42.4 psig for the MSLB assuming a |
| 2.6% shutdown margin with credit for 2300 ppm boron in the emergency core |
| cooling injection line. This analysis changes assumptions in UFSAR Section |
| 14.2.5 of 1.3% shutdown margin (this is the required margin per Technical |
| Specification 3.10.1.1) and unborated water in ECCS lines from the refueling |
| water storage tank. Unit 3 currently meets the changed assumptions. The |
| Licensee considers Unit 3 to be operable based on the Westinghouse |
| preliminary calculation and additional conservatism in this calculation |
| (e.g. feedwater addition for 120 seconds when the valve shuts in about 70 |
| seconds, no credit for restriction of feedwater as the valve shuts). |
| |
| Administrative controls will have to be put into place to maintain the plant |
| shutdown margin and the boron concentration. The Westinghouse reanalysis |
| was initiated by the Licensee following industry information (Ginna, in LER |
| 50/244/99-01, identified the non-conservative assumption of 800 cubic feet |
| in WCAP-8822). |
| |
| The Licensee plans to notify the NRC Resident Inspector. |
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|Power Reactor |Event Number: 35947 |
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| FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 07/22/1999|
| UNIT: [3] [] [] STATE: FL |NOTIFICATION TIME: 15:05[EDT]|
| RXTYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 07/22/1999|
+------------------------------------------------+EVENT TIME: 09:25[EDT]|
| NRC NOTIFIED BY: B. STAMP |LAST UPDATE DATE: 07/22/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |EDWARD MCALPINE R2 |
|10 CFR SECTION: |TAD MARSH NRR |
|HFIT 26.73 FITNESS FOR DUTY | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
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EVENT TEXT
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| UNSATISFACTORY RESULTS FROM A DRUG TESTING LABORATORY |
| |
| ON 07/21/99, THE LICENSEE SUBMITTED A BLIND SPECIMEN WHICH HAD BEEN SPIKED |
| WITH 1839 NG/ML OF AMPHETAMINE AND 1860 NG/ML OF METHAMPHETAMINE TO A DRUG |
| TESTING LABORATORY IN LEESBURG, FL TO BE ANALYZED. THE RESULTS WERE |
| RECEIVED BY THE LICENSEE AT 0925 ON 07/22/99 AND THEY WERE REPORTED AS |
| NEGATIVE. THE LICENSEE IS CONDUCTING AN INVESTIGATION. |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
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