Event Notification Report for August 7, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
08/04/2000 - 08/07/2000
** EVENT NUMBERS **
37197 37208 37209
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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: 08/04/2000|
| 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 | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| POTENTIALLY LEAKING SOURCE |
| |
| A 5mCi Sr-90 source in the form of a brachytherapy 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. |
| |
| * * * UPDATE ON 08/04/00 AT 1459 ET BY JIM O'REAR TAKEN BY MACKINNON * * * |
| |
| Up on further investigation it was determined that the brachytherapy seed |
| was damaged by NIST personnel during calibration work. The seed was |
| packaged up and returned to AEA Technologies located in Massachusetts. NRC |
| Region 1, John McGrath, was informed of this update by NIST. NRC R1DO (Jack |
| McFadden) and NMSS EO (John Hickey) notified. |
| |
| Correction To Initial Report: The brachytherapy seed was manufactured by |
| AEA Technologies for Novoste. |
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|Power Reactor |Event Number: 37208 |
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| FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 08/05/2000|
| UNIT: [] [2] [] STATE: NC |NOTIFICATION TIME: 08:07[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 08/05/2000|
+------------------------------------------------+EVENT TIME: 04:28[EDT]|
| NRC NOTIFIED BY: STUART BYRD |LAST UPDATE DATE: 08/05/2000|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GEORGE BELISLE R2 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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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| DISCOVERY OF A MINIMAL AMOUNT OF WATER IN THE REACTOR CORE ISOLATION COOLING |
| OIL SYSTEM |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "EVENT: The Unit 2 the Reactor Core Isolation Cooling (RCIC) system was |
| discovered to have a minimal amount of water in the oil system. Following |
| investigation of the event and replacement of the oil, the RCIC turbine was |
| successfully manually started and operated normally. During a subsequent |
| automatic start for post-maintenance test requirements, the turbine tripped |
| on high exhaust pressure apparently caused by the governor system's slow |
| response time. Investigation of the turbine control system is continuing." |
| |
| "CORRECTIVE ACTION(S): Continue the investigation to determine the root |
| cause of the water in the oil system and the response of the governor |
| control system." |
| |
| "INITIAL SAFETY SIGNIFICANCE EVALUATION: Minimal. The High Pressure |
| Coolant Injection System, Automatic [Depressurization] System, Low Pressure |
| Core Spray, and the Low Pressure Coolant Injection System were operable |
| throughout the event." |
| |
| The licensee stated that, as a result of this issue, the unit is currently |
| in a 14-day limiting condition for operation in accordance with Technical |
| Specification 3.5.2. The licensee also stated that all other systems |
| functioned as required. |
| |
| The licensee notified the NRC resident inspector. |
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|Power Reactor |Event Number: 37209 |
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| FACILITY: THREE MILE ISLAND REGION: 1 |NOTIFICATION DATE: 08/05/2000|
| UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 21:45[EDT]|
| RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP |EVENT DATE: 08/05/2000|
+------------------------------------------------+EVENT TIME: 20:54[EDT]|
| NRC NOTIFIED BY: J SCHORK |LAST UPDATE DATE: 08/05/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JACK MCFADDEN 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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| DURING TESTING ONE CUBICLE OF THE CONTROL BUILDING ENVELOPE, THE 1D 4160 |
| VOLT SWITCHGEAR ROOM WAS FOUND TO BE SLIGHTLY NEGATIVE IN PRESSURE. |
| |
| "At 2054 hours on Saturday, August 5, 2000-AmerGen identified a condition |
| that is outside the design basis at TMI Unit 1. Functional testing of the |
| TMI-1 Control Building Envelope {CBE} was in process to verify that the |
| design basis of the Control Building Emergency Ventilation System had been |
| maintained following plant |
| modifications to improve the reliability of the system. Results of the |
| Functional testing found that one cubicle of the Control Building Envelope, |
| the 1D 4160 Volt Switchgear room, located on the 338' elevation of the |
| Control Tower, 1 floor below the Control Room, was slightly negative in |
| regards to internal atmospheric pressure as compared to outside air |
| pressure. The TMI-1 UFSAR, Update 15 states in section 7.4.5.2.1 in part: |
| |
| " ....A positive pressure of > or equal to 0.10 inches w.g. {water gauge} is |
| not a criterion for the entire CBE. The pressure requirement in the cubicles |
| of the CBE, other than the Main Control Room, is that they are maintained at |
| a positive pressure with respect to the areas outside the CBE. |
| |
| "The functional testing found that the ID 4160 Switchgear room was |
| approximately 0.04 inches w.g. negative in regards to areas outside the CBE. |
| Subsequent adjustments to the Control Building Emergency Ventilation System |
| restored the area to a positive pressure in regards to areas outside the |
| CBE. Additional evaluation and testing is in progress to determine the root |
| cause of the event. |
| |
| "The potential consequences of the condition found are believed to be |
| minimal. No actual in-leakage pathway was identified and if the Control |
| Building Emergency Ventilation System been called upon to operate in the |
| re-circulation mode and had in-leakage occurred, the air in-leakage would |
| have been filtered by the CBEVS |
| charcoal filters prior to supply to the Control Room. Thus, the dose |
| consequences to the operators would have been very minimal due to the low |
| amount of in-leakage and filtration prior to supply to the control room." |
| |
| A follow up 30 day LER will be submitted. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
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