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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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