Event Notification Report for October 5, 2001
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
10/04/2001 - 10/05/2001
** EVENT NUMBERS **
38346 38347 38348 38349 38350 38351 38352
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|General Information or Other |Event Number: 38346 |
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| REP ORG: NV DIV OF RAD HEALTH |NOTIFICATION DATE: 10/04/2001|
|LICENSEE: LAS VALLEY WATER DISTRICT |NOTIFICATION TIME: 14:11[EDT]|
| CITY: LAS VEGAS REGION: 4 |EVENT DATE: 10/04/2001|
| COUNTY: STATE: NV |EVENT TIME: [PDT]|
|LICENSE#: 00-11-0196-01 AGREEMENT: Y |LAST UPDATE DATE: 10/04/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |CLAUDE JOHNSON R4 |
| |FRED BROWN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: STAN MARSHALL | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| AGREEMENT STATE REPORT - DAMAGED GAUGE |
| |
| 1. Event Report ID No.: NV-01-006 |
| |
| 2. License No.: 00-11-0196-01 |
| |
| 3. Licensee: Las Valley Water District |
| |
| 4. Event time, date, location: Las Vegas, NV, October 1, 2001 |
| |
| 5. Event type (e.g. misadministration, lost source, overexposure, etc.): |
| Slightly damaged portable gauge. Cause of the incident was lack of attention |
| to detail. |
| |
| 6. Any notifications i.e. other agencies, patient, press release, FBI, etc.: |
| N/A |
| |
| 7. Event description: release, isotope, activity, exposure(s), dose, |
| contamination level, equipment malfunction model, serial No., etc.: A |
| portable gauge fell off the bed of a slow moving transporting pickup and was |
| slightly damaged. The gauge was not carried in it's shipping container at |
| the time of the incident, The source was in the safe, shielded position at |
| the time of the incident. The gauge has been surveyed and leak tested and |
| has been shipped to the manufacturer for repair. The gauge was a Troxler |
| Model 3440, s/n 22284 containing 10 mCi of Cs-137 and 40 mCi of Am-241 :Be. |
| |
| 8. Transport vehicle description, if known: Company pickup. |
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|Power Reactor |Event Number: 38347 |
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| FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 10/04/2001|
| UNIT: [] [2] [] STATE: PA |NOTIFICATION TIME: 14:23[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 10/03/2001|
+------------------------------------------------+EVENT TIME: 23:28[EDT]|
| NRC NOTIFIED BY: PETER ORPHANOS |LAST UPDATE DATE: 10/04/2001|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |RICHARD CONTE R1 |
|10 CFR SECTION: | |
|NONR OTHER UNSPEC REQMNT | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
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EVENT TEXT
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| 24-HOUR REPORT IN ACCORDANCE WITH OPERATING LICENSE DUE TO POTENTIAL MAXIMUM |
| POWER LEVEL VIOLATION |
| |
| "This report is being made in accordance with Limerick Generating Station |
| Unit 2 Operating License Condition 2.E. as a potential violation of License |
| Condition 2.C(1), Maximum Power Level |
| |
| "GE Report titled 'Impact of Steam Carryover Fraction on Process Computer |
| Heat Balance Calculations', September 2001, documents a non-conservative |
| assumption for the moisture carryover fraction used in the calculation of |
| core thermal power. The assumed carryover fraction of 0.1% was discovered to |
| be potentially closer to zero and therefore non-conservative in later model |
| GE BWRs. |
| |
| "A review of Limerick Unit 2 moisture carryover data from an ASME PTC 6 test |
| performed in October of 1999 found a moisture carryover value of 0.0277%, |
| inducing an estimated bias of approximately 2.8 MWth. Similar testing on |
| Limerick Unit 1 found a value of greater than 0.1%. Based on this data |
| Limerick Unit 1 is not considered affected at this time. |
| |
| "Based on this potential non-conservatism on Unit 2, indicated Maximum Power |
| Level shift average is being administratively controlled 3 MWth below the |
| licensed power level of 3458 MWth. |
| |
| "Exelon staff is continuing to evaluate the effect of the moisture carryover |
| term in the heat balance calculation." |
| |
| The NRC resident has been notified. |
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|Power Reactor |Event Number: 38348 |
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| FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 10/04/2001|
| UNIT: [3] [] [] STATE: FL |NOTIFICATION TIME: 15:59[EDT]|
| RXTYPE: [3] B&W-L-LP |EVENT DATE: 10/04/2001|
+------------------------------------------------+EVENT TIME: [EDT]|
| NRC NOTIFIED BY: RICKY RAWLS |LAST UPDATE DATE: 10/04/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |CHARLES CASTO R2DO |
|10 CFR SECTION: | |
|ADEG 50.72(b)(3)(ii)(A) DEGRADED CONDITION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3 N N 0 Refueling |0 Refueling |
| | |
| | |
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EVENT TEXT
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| SMALL PRESSURE BOUNDARY LEAK IDENTIFIED WHILE SHUTDOWN |
| |
| "At 0809 on October 4, 2001, Crystal River Unit 3 (CR-3) was in MODE 6 |
| shutdown for refueling operation. CR-3 has identified a small defect in the |
| reactor coolant system (RCS) pressure boundary. An RCS leak was suspected |
| due to elevated radioactivity levels detected in the nuclear services closed |
| cycle cooling water (SW) system since June 2001. Testing was conducted |
| on-line in MODE 1 and could not determine the source of the leakage. |
| Additional testing in MODE 6 has identified the seal area heat exchanger on |
| the 1B reactor coolant pump (RCP-1B) as the most likely source of the |
| leakage. The defect allowed a small amount of leakage to occur from the RCS |
| to the SW system during the previous operating cycle. A definitive leak |
| location could not be identified due to the extremely small size of the |
| leak. However, since all components in the RCP heat exchanger are included |
| as part of the class 1 RCS pressure boundary, this defect is reportable |
| under 10 CFR 50.72(b)(3)(ii)(A). CR-3 was shutdown in MODE 6 at the time of |
| the discovery. The RCP heat exchanger will be repaired prior to returning to |
| power operation." |
| |
| The leak rate has been determined to be 0.02 gpm which exceeds the Technical |
| Specification limit of 'No Pressure Boundary Leakage' and it appears to be a |
| long term development. |
| |
| The licensee notified the NRC Resident Inspector. |
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|Power Reactor |Event Number: 38349 |
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| FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 10/04/2001|
| UNIT: [1] [] [] STATE: LA |NOTIFICATION TIME: 16:10[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 10/04/2001|
+------------------------------------------------+EVENT TIME: 09:13[CDT]|
| NRC NOTIFIED BY: DANNY WILLIAMSON |LAST UPDATE DATE: 10/04/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |CLAUDE JOHNSON R4 |
|10 CFR SECTION: | |
|NONR OTHER UNSPEC REQMNT | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
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EVENT TEXT
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| OPERATING LICENSE CONDITION VIOLATION (POTENTIAL MAXIMUM POWER LEVEL |
| VIOLATION) |
| |
| "This report is being made as required by River Bend Station license |
| condition 2.E. River Bend is reporting a potential violation of the maximum |
| power level as authorized in license condition 2.C.1. |
| |
| "This event is similar to event numbers 38337 and 38340 reported by two |
| other BWR plants Based on the General Electric (GE) report titled, 'Impact |
| of Steam Generator Carryover Fraction on Process Computer Heat Balance |
| Calculations, September 2001.' It is possible that River Bend may have |
| exceeded the maximum power level on some occasions in the past by |
| approximately three megawatts thermal. |
| |
| "River Bend Station is currently in a refueling outage, so no immediate |
| actions are necessary. This condition has been entered into the station's |
| corrective action program to further evaluate the applicability of this |
| condition and to develop an appropriate response before returning to power |
| operations. |
| |
| "The licensee notified the NRC resident inspector." |
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|Hospital |Event Number: 38350 |
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| REP ORG: RAPID CITY REGIONAL HOSPITAL |NOTIFICATION DATE: 10/04/2001|
|LICENSEE: RAPID CITY REGIONAL HOSPITAL |NOTIFICATION TIME: 16:58[EDT]|
| CITY: RAPID CITY REGION: 4 |EVENT DATE: 10/04/2001|
| COUNTY: STATE: SD |EVENT TIME: [MDT]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 10/04/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |CLAUDE JOHNSON R4 |
| |PATRICIA HOLAHAN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: ERIC HENDEE | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|LADM 35.33(a) MED MISADMINISTRATION | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| MEDICAL MISADMINISTRATION - UNDERDOSE |
| |
| Today, 10/4/01, when the dose for a second treatment was being prepared, it |
| was discovered that the first dose was not as large as prescribed. The |
| first dose administered on 9/27/01 should have been 750 centigray and was |
| only 400 to 500 centigray. The attending physician has been notified and |
| the patient will be notified. A correcting dose, an additional fraction, |
| will be given to correct the underdose. No adverse affects are expected by |
| this misadministration. |
| |
| The dosage is administered with a high dose rate machine, Nucletron |
| Microselectron. |
| |
| The Radiation Safety Officer contacted NRC Region 4 (Richard Leonardi). |
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|Other Nuclear Material |Event Number: 38351 |
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| REP ORG: US AIR FORCE |NOTIFICATION DATE: 10/04/2001|
|LICENSEE: US AIR FORCE |NOTIFICATION TIME: 18:09[EDT]|
| CITY: CANNON AFB REGION: 4 |EVENT DATE: 10/04/2001|
| COUNTY: STATE: NM |EVENT TIME: [MDT]|
|LICENSE#: 42-23539-01AF AGREEMENT: Y |LAST UPDATE DATE: 10/04/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |CLAUDE JOHNSON R4 |
| |PATRICIA HOLAHAN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: CRAIG REFOSCO | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| REPORT OF 2 MISSING EXIT SIGNS CONTAINING TRITIUM AT CANNON AFB |
| |
| Two exit signs containing 20 curies of tritium each were discovered missing |
| from building 1258 at Cannon Air Force Base, New Mexico. The signs were in |
| place on 9/26/01 during a previous inspection. The signs are manufactured |
| by SRB Technologies and the serial numbers are 192167 and 192168. There |
| will be a formal investigation conducted. |
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|Power Reactor |Event Number: 38352 |
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| FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 10/05/2001|
| UNIT: [] [2] [] STATE: PA |NOTIFICATION TIME: 04:30[EDT]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 10/05/2001|
+------------------------------------------------+EVENT TIME: 00:26[EDT]|
| NRC NOTIFIED BY: J. A. WITTER |LAST UPDATE DATE: 10/05/2001|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |RICHARD CONTE R1 |
|10 CFR SECTION: | |
|AINB 50.72(b)(3)(v)(B) POT RHR INOP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
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| UNIT 2 ENTERED TECH SPEC 3.0.3 DUE TO TWO TRAINS OF SERVICE WATER DECLARED |
| INOPERABLE |
| |
| "At 0026 hrs on October 5, 2001, Beaver Valley Power Station Unit 2 |
| experienced a trip of the 'A' Train Service Water (SWS) Pump. 2SWS-P21 C was |
| operating on the 'A' SWS header when the pump tripped on Motor Ground Over |
| Current. Both A and B Train Emergency Service Water Pumps (SWE) auto started |
| as designed and Service Water header pressure returned to normal values. Due |
| to a piping class break, safety/non-safety, between the SWS and SWE systems, |
| the unit entered Technical Specification 3.0.3 due to two trains of Service |
| Water being Inoperable. The unit entered and completed the Abnormal |
| Operating Procedure for Loss of Service Water, and the Bravo Train of |
| Service Water was restored Operable when 2SWE-P21 B was secured and isolated |
| from the 'B' SWS header. 25W5-P21 B continued to operate normally during |
| this event. Technical Specification 3.0.3 was exited at 0037 hrs. The plant |
| is currently stable and operating at 100% power. Technical Specification |
| 3.7.4.1 for Service Water (72-hour action) is applicable, as the only |
| operating pump on the 'A' SWS header is 2SWE-P21A. The Alpha Service Water |
| Pump, 2SWS-P21 A is unavailable due to Intake Structure Bay cleaning. |
| Currently efforts are under way to recover the Intake Bay and restore |
| 2SWS-P21A Operable. It is expected that both trains of Service Water will be |
| Operable within 12 hours. The Non Safety Related Chiller units tripped due |
| to the SWS low pressure conditions, and were recovered shortly there after. |
| No additional failures or equipment challenges occurred as a result of this |
| event." |
| |
| The licensee informed the NRC resident inspector. |
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