Event Notification Report for July 31, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
07/28/2000 - 07/31/2000
** EVENT NUMBERS **
35406 37193 37194 37195 37196 37197 37198 37199
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|General Information or Other |Event Number: 35406 |
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| REP ORG: PYCO, INC. |NOTIFICATION DATE: 02/25/1999|
|LICENSEE: PYCO, INC. |NOTIFICATION TIME: 17:03[EST]|
| CITY: PENNDEL REGION: 1 |EVENT DATE: 02/25/1999|
| COUNTY: STATE: PA |EVENT TIME: 17:03[EST]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 07/28/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |ROBERT HAAG R2 |
| |VERN HODGE (via fax) NRR |
+------------------------------------------------+RICHARD BARKLEY R1 |
| NRC NOTIFIED BY: WILLIAM SZARY | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| 10 CFR PART 21 REPORT REGARDING FAULTY RESISTANCE TEMPERATURE DETECTORS |
| (RTD) |
| |
| The following text is a portion of a facsimile received from PYCO, Inc.: |
| |
| "A deviation has been detected in that a limited number of 200 OHM DUPLEX |
| RTD assemblies have been fabricated by PYCO using THIN-FILM RTD sensors |
| instead of the WIRE-WOUND RTD sensors specified for the assembly. RTD |
| assemblies fabricated using wire-wound sensors have been tested and |
| qualified by PYCO for nuclear use under our nuclear qualification test |
| program. RTD assemblies fabricated using thin-film sensors have not been |
| tested by PYCO to IEEE-323 and IEEE-344 requirements." |
| |
| "Externally, thin-film and wire-wound RTDs have the same physical |
| appearance, shape, and electrical characteristics. Both the wire-wound and |
| thin-film sensors meet the requirements of the International Industrial |
| Standard IEC-751, 'Industrial Platinum Resistance Thermometer Sensors'." |
| |
| These RTDs have been sold to Carolina Power and Light and South Carolina |
| Electric and Gas for use at the Robinson, Brunswick, and Summer plants. |
| |
| (Call the NRC Operations Center for a contact telephone number.) |
| |
| * * * UPDATE 1256EDT ON 7/28/00 TO S. SANDIN * * * |
| |
| The following is a summary of the corrective actions completed: |
| |
| "PYCO has completed all corrective action activities for NCR Event# 35406. |
| All affected Power Utilities have completed an 'Operability Evaluation and |
| Determination of Acceptance' for potential thin-film RTD's in-service. |
| |
| "PYCO has completed an x--ray evaluation of all returned in-service or |
| in-stock assemblies and identified those containing the incorrect thin-film |
| sensor. |
| |
| "Assemblies found to have been manufactured with the correct wire-wound |
| sensor were inspected, calibrated and returned to the utilities. Any |
| assemblies found to contain the incorrect thin-film sensor were scrapped, |
| and replacement assemblies containing the correct sensor were manufactured |
| and shipped to the utilities. |
| |
| "As required by 10CFR Part 21, the following information is to provide |
| notification of CORRECTIVE ACTION COMPLETION in connection with certain 200 |
| OHM duplex Resistance Temperature Detectors (RTD's) supplied to Carolina |
| Power & Light - Robinson Plant and Brunswick Plant and South Carolina |
| Electric & Gas - V.C. Summer Station." |
| |
| Notified R1DO(Shanbaky), R2DO(Cahill) and NRR(Hodge via fax). |
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|General Information or Other |Event Number: 37193 |
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| REP ORG: IDAHO NAT ENGR & ENVIRONMENTAL LAB |NOTIFICATION DATE: 07/27/2000|
|LICENSEE: IDAHO NAT ENGR & ENVIRONMENTAL LAB |NOTIFICATION TIME: 19:22[EDT]|
| CITY: IDAHO FALLS REGION: 4 |EVENT DATE: 07/27/2000|
| COUNTY: STATE: ID |EVENT TIME: 15:55[MDT]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 07/29/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |BILL JONES R4 |
| |ELLIS MERSCHOFF RA |
+------------------------------------------------+ELMO COLLINS NMSS |
| NRC NOTIFIED BY: JOE GARCIA |CHARLES MILLER IRO |
| HQ OPS OFFICER: STEVE SANDIN |STEINDURF FEMA |
+------------------------------------------------+DOE, USDA, HHS (fax) |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NINF INFORMATION ONLY | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| COURTESY NOTIFICATION OF A DOE EMERGENCY DECLARATION AT AN INDEPENDENT SPENT |
| FUEL STORAGE INSTALLATION (ISFSI) IN IDAHO |
| |
| At 1555MDT, DOE INEEL declared a Site Area Emergency due to wildland fires |
| on DOE controlled property. The ISFSI containing the TMI spent fuel is not |
| threatened. This notification is a courtesy call only and does not involve |
| the NRC Radiological Emergency Plan. No NRC assistance is requested. |
| |
| DOE INEEL has notified the State of Idaho, all surrounding counties and DOE |
| Headquarters. |
| |
| *** UPDATE AT 0304 EDT ON 07/28/00 FROM JOE GARCIA AND FOREST HOLMS TO LEIGH |
| TROCINE *** |
| |
| This event status update was provided as a courtesy notification. The Site |
| Area Emergency remains in progress. There is a site-wide emergency action |
| level in effect because of a wildland fire. The TMI-2 ISFSI is located at |
| the Idaho National Engineering & Environmental Laboratory (INEEL), but the |
| Site Area Emergency does not impact the TMI-2 ISFSI. However, INEEL has |
| been directed by the Department of Energy (DOE) to notify the NRC when |
| emergency action levels of this nature are in place. The Site Area |
| Emergency will remain in effect until the fire is extinguished. |
| |
| The following text is a portion of a facsimile received from the INEEL: |
| |
| "Description of Incident: Wildland fire on the INEEL. Fire suppression |
| efforts continue. Emergency response centers [are] operational at RWMC, |
| CFA, INTEC, TRA, EOC with reduced staffing. INTEC and TRA [are] continuing |
| to monitor facilities." |
| |
| The NRC operations officer notified the R4DO (Jones), R4RA (Merschoff), NMSS |
| EO (Collins), IRO (Miller), and the Federal Emergency Management Agency |
| (FEMA) (Storer). DOE, U.S. Department of Agriculture (USDA), Department of |
| Health and Human Services (HHS), Environmental Protection Agency (EPA), and |
| Department of Transportation (DOT) (via the National Response Center) were |
| also notified via facsimile. |
| |
| |
| * * * UPDATE 1709EDT 7/29/00 FROM GREG BYBEE TO S. SANDIN * * * |
| |
| The Site Area Emergency was terminated at 1500MST. |
| |
| The NRC operations officer notified the R4DO (Jones), R4RA (Merschoff), NMSS |
| EO (Collins), IRO (Miller), and the Federal Emergency Management Agency |
| (FEMA) (Eaches). DOE, U.S. Department of Agriculture (USDA), Department of |
| Health and Human Services (HHS), Environmental Protection Agency (EPA), and |
| Department of Transportation (DOT) (via the National Response Center) were |
| also notified via facsimile. |
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|General Information or Other |Event Number: 37194 |
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| REP ORG: NOVARTIS PHARMACEUTICAL CORP |NOTIFICATION DATE: 07/28/2000|
|LICENSEE: NOVARTIS PHARMACEUTICAL CORP |NOTIFICATION TIME: 10:07[EDT]|
| CITY: SUMMIT REGION: 1 |EVENT DATE: 06/29/2000|
| COUNTY: STATE: NJ |EVENT TIME: 15:50[EDT]|
|LICENSE#: 2908978-02 AGREEMENT: N |LAST UPDATE DATE: 07/28/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MOHAMED SHANBAKY R1 |
| |JOSIE PICCONE NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: KING | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAE1 20.2202(b)(1) PERS OVEREXPOSURE | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| NOVARTIS PHARMACEUTICAL CORPORATION REPORTED AN OVEREXPOSURE OF ONE OF THEIR |
| EMPLOYEES. |
| |
| An employee was working with carbon-14 in a hood wearing gloves when a drop |
| of the organic compound solution went onto the gloves. He immediately |
| removed the gloves and noticed discoloration to his skin due to the chemical |
| going through the gloves to a certain extent. He then proceeded to |
| decontaminate himself using normal decontaminating procedures. Surveys were |
| made and further decontamination was conducted, and based on their |
| preliminary calculations at this point, the dose at skin depth of .007 cm is |
| approx. 100 rads(includes the step wise decon). They do not believe he |
| exceeded the NRC dose limit until early July. The solution was on the tip |
| of the left index finger where the skin is much thicker(approx. .04 cm) than |
| the NRC depth of skin dose calculation of .007 cm. The dose, if the |
| material is deposited on the surface of the skin, to the live tissue at a |
| skin depth of .04 cm is zero from carbon-14 due to its low energy. |
| Initially they counted 250,000 cpm on 6/29/00 and after various steps of |
| decontamination it was reduced to 6,000 cpm after one week. Daily urine |
| samples were taken and monitoring continued for a week. By 7/19/00 counts |
| per minute were down to 100 cpm. |
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|Power Reactor |Event Number: 37195 |
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| FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 07/28/2000|
| UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 10:25[EDT]|
| RXTYPE: [1] GE-2 |EVENT DATE: 07/28/2000|
+------------------------------------------------+EVENT TIME: 09:41[EDT]|
| NRC NOTIFIED BY: FREEMAN |LAST UPDATE DATE: 07/28/2000|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MOHAMED SHANBAKY 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 64 Power Operation |64 Power Operation |
| | |
| | |
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EVENT TEXT
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| CEILING OF THE "C" BATTERY ROOM DOES NOT MEET FIRE RATING REQUIREMENTS. |
| |
| OYSTER CREEK NUCLEAR GENERATING STATION HAS DETERMINED THAT THE "C" BATTERY |
| ROOM CEILING DOES NOT MEET THE REQUIREMENT OF A 3 HR FIRE RATING. THIS |
| CONDITION WAS DISCOVERED AS PART OF AN EXTENT REVIEW PER LER 2000-04. THIS |
| WAS DETERMINED TO BE REPORTABLE BECAUSE THE CONDITION IS NOT A RECENT |
| DEGRADATION BUT THE RESULT OF A DESIGN DEFICIENCY WHICH PLACES THE "C" |
| BATTERY ROOM OUTSIDE DESIGN BASES. |
| |
| THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. |
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|Power Reactor |Event Number: 37196 |
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| FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 07/28/2000|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 13:07[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 07/28/2000|
+------------------------------------------------+EVENT TIME: 12:30[EDT]|
| NRC NOTIFIED BY: MARK ABRAMSKI |LAST UPDATE DATE: 07/29/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MOHAMED SHANBAKY 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 |
| | |
| | |
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EVENT TEXT
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| UNIT OUTSIDE DESIGN BASIS BASED ON THE POSITION OF THE MECHANICAL STOP ON |
| THE "A" RECIRC PUMP SPEED LIMITER |
| |
| "The mechanical stop for the 'A' Recirc Pump speed limiter was found to have |
| exceeded the value assumed in the calculation for the flow dependent minimum |
| critical power ratio (MCPR) (K-sub f) in the Core Operating Limit Report |
| (COLR). If a Recirc Pump transient (runaway recirc flow) is postulated from |
| a low flow condition, the flow dependent MCPR (K-sub f) may be exceeded. |
| This could result in exceeding the safety limit MCPR under these postulated |
| conditions. This condition is outside the design basis of the plant." |
| |
| This condition was discovered by Engineering and has existed since the last |
| outage in mid-April of this year. Evaluation of the 'B' Recirc Pump is |
| currently in progress. The licensee informed the NRC Resident Inspector. |
| |
| * * * UPDATE AT 1126 ON 07/29/00 BY BERNARD HORNING TO JOLLIFFE * * * |
| |
| At 1105 on 07/29/00, the licensee has determined that the mechanical stop |
| for the 'B' Recirc Pump speed limiter also exceeded the value assumed in the |
| calculation for the flow dependent minimum critical power ratio (MCPR) |
| (K-sub f) in the Core Operating Limit Report (COLR). If a Recirc Pump |
| transient (runaway recirc flow) is postulated from a low flow condition, the |
| flow dependent MCPR (K-sub f) may be exceeded. This could result in |
| exceeding the safety limit MCPR under these postulated conditions. This |
| condition is outside the design basis of the plant. |
| |
| The licensee informed the NRC Resident Inspector. The NRC Operations |
| Officer informed the R1DO Mohamed Shanbaky. |
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|Other Nuclear Material |Event Number: 37197 |
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| REP ORG: NATIONAL INST OF STANDARDS & TECH |NOTIFICATION DATE: 07/28/2000|
|LICENSEE: NATIONAL INST OF STANDARDS & TECH |NOTIFICATION TIME: 14:29[EDT]|
| CITY: GAITHERSBURG REGION: 1 |EVENT DATE: 07/10/2000|
| COUNTY: STATE: MD |EVENT TIME: [EDT]|
|LICENSE#: SNM-362 AGREEMENT: Y |LAST UPDATE DATE: 07/28/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MOHAMED SHANBAKY R1 |
| |SCOTT MOORE NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JIM O'REAR | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NINF INFORMATION ONLY | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| POTENTIALLY LEAKING SOURCE |
| |
| A 5mCi Sr-90 source in the form of a brachytherpy seed used for |
| investigational purposes may be leaking. There is no known personnel |
| exposure or spread of contamination involved. The source was manufactured |
| by Novoste which is located in GA . The evaluation will continue to |
| determine whether the source is actually leaking. |
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|Power Reactor |Event Number: 37198 |
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| FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 07/28/2000|
| UNIT: [1] [] [] STATE: AZ |NOTIFICATION TIME: 15:06[EDT]|
| RXTYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 07/28/2000|
+------------------------------------------------+EVENT TIME: 11:07[MST]|
| NRC NOTIFIED BY: RUSSELL STROUD |LAST UPDATE DATE: 07/28/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BILL JONES R4 |
|10 CFR SECTION: | |
|DDDD 73.71 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
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EVENT TEXT
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| 1 HOUR SECURITY REPORT |
| |
| SAFEGUARDS SAFETY DEGRADATION RELATED TO THE CONTROL OF CLASSIFIED |
| DOCUMENT(S)/SAFEGUARDS INFORMATION. IMMEDIATE COMPENSATORY MEASURES TAKEN |
| UPON DISCOVERY. LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. |
| |
| CONTACT THE HEADQUARTERS OPERATIONS OFFICER FOR ADDITIONAL DETAILS. |
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|Power Reactor |Event Number: 37199 |
+------------------------------------------------------------------------------+
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| FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 07/30/2000|
| UNIT: [] [2] [] STATE: AR |NOTIFICATION TIME: 18:39[EDT]|
| RXTYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 07/30/2000|
+------------------------------------------------+EVENT TIME: 16:35[CDT]|
| NRC NOTIFIED BY: TOM MOSBY |LAST UPDATE DATE: 07/31/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BILL JONES R4 |
|10 CFR SECTION: | |
|ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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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| INDICATION OF REACTOR COOLANT LEAKAGE ON PRESSURIZER HEATER PENETRATIONS |
| |
| "Boron was discovered on the reactor coolant system pressurizer heater power |
| cables. An inspection of the heater sleeves was performed and it appears |
| that two heaters (B2 and D2) are leaking. B2 is on backup heater bank #4 |
| and D2 is on backup heater bank #6. The leakage appears to be the result of |
| primary water stress corrosion cracking (PWSCC) of either the heater sleeve |
| or the J-groove weld between the heater sleeve and the pressurizer cladding. |
| The insulation will need to be removed to positively determine which heater |
| sleeve(s) had been leaking. Currently, Unit 2 is in reduced inventory with |
| the pressurizer empty. |
| |
| "The pressurizer heater sleeve penetrations were inspected during 2R-13 |
| [between 1/9/99 and 2/25/99] as part of the routine I-600 inspections |
| performed each refueling outage. No indication of leakage was evident |
| during that inspection. |
| |
| "Pressurizer heater sleeve leakage is considered RCS pressure boundary |
| leakage." |
| |
| The licensee informed the NRC resident inspector. |
| |
| * * * UPDATE AT 0052 ON 07/31/00 BY LARRY McLERRAN TO JOLLIFFE * * * |
| |
| After removing insulation from the pressurizer and reactor coolant system |
| hot legs, the licensee discovered 9 or 10 additional pressurizer heater |
| sleeves that are leaking and also a hot leg temperature element that is |
| leaking. The licensee is continuing to inspect the hot leg penetrations for |
| evidence of leakage. |
| |
| The licensee notified the NRC Resident Inspector. The NRC Operations |
| Officer notified the R4DO Bill Jones. |
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