Event Notification Report for November 30, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           11/29/2000 - 11/30/2000

                              ** EVENT NUMBERS **

37555  37556  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   37555       |
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| FACILITY: MCGUIRE                  REGION:  2  |NOTIFICATION DATE: 11/28/2000|
|    UNIT:  [1] [2] []                STATE:  NC |NOTIFICATION TIME: 17:16[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        11/28/2000|
+------------------------------------------------+EVENT TIME:        16:25[EST]|
| NRC NOTIFIED BY:  JOHN SMALL                   |LAST UPDATE DATE:  11/29/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GEORGE BELISLE       R2      |
|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  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| BOTH UNITS OUTSIDE OF DESIGN BASIS DUE TO MOMENTARY LOSS OF BOTH TRAINS OF   |
| CONTROL ROOM VENTILATION                                                     |
|                                                                              |
| "Presently, 'A' Control Room Ventilation out of service for maintenance.     |
| 'B' Control Room Ventilation (VC/YC) inadvertently deenergized causing both  |
| trains of VC/YC to be inoperable. 'B' VC/YC restarted with no further        |
| complications.  Deenergized from 1625 until 1643 which places both units one |
| and two outside design basis.  With VC/YC inoperable for 'A' and 'B' trains, |
| entered [TS] 3.0.3 momentarily."                                             |
|                                                                              |
| The problem occurred when the technician performing maintenance on the "A"   |
| train went to the operating "B" train.  The "B" train Chiller was tripped in |
| error.  The licensee informed the NRC resident inspector.                    |
|                                                                              |
| * * * * UPDATE 1159EST ON 11/29/00 FROM JOHN JENKINS TO S. SANDIN * * * *    |
|                                                                              |
| The licensee is retracting this report based on the following:               |
|                                                                              |
| "On November 29, 2000, the above notification was made to the NRC under the  |
| requirements of 10 CFR 50.72 (b) (1) (ii) (B). Upon further evaluation, it   |
| has been determined that this condition did not place the plant outside of   |
| design basis.                                                                |
|                                                                              |
| "The ability to pressurize the Main Control Room was not affected in this    |
| condition. The pressurization fans would start and run if needed during an   |
| accident. The pressurization function mitigates dose to the control          |
| operators.                                                                   |
|                                                                              |
| "During the 18 minutes that the chiller was out of service the temperature   |
| in the Control Room increased from 70 degrees to approximately 72 � degrees. |
| The temperature rise was evaluated by the System Engineer. The temperature   |
| limit for the control room is listed as a maximum of 90 degrees in the       |
| Selected Licensee Commitments. This temperature is based on a continuous     |
| duty rating for equipment and instrumentation and for habitability of the    |
| Control Room. Annunciator alarms would alert the Operators of the increasing |
| temperature and existing procedures would direct actions to be taken to      |
| limit the temperature affects. The Engineering evaluation determined that    |
| the chiller would need to be out of service for 2 hours before this limit    |
| was challenged.                                                              |
|                                                                              |
| "This occurrence did not increase the probability of barrier failure or      |
| radiation releases. Remote shutdown capability outside the control room was  |
| not affected. For these reasons the plant remained within its design         |
| basis."                                                                      |
|                                                                              |
| The licensee will inform the NRC resident inspector.  Notified               |
| R2DO(Belisle).                                                               |
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+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   37556       |
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+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 11/29/2000|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 17:11[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        11/29/2000|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        11:35[EST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  11/29/2000|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |MICHAEL JORDAN       R3      |
|  DOCKET:  0707002                              |LARRY CAMPER         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  RICK LARSON                  |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NCFR                     NON CFR REPORT REQMNT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| REPORT INVOLVING ACTUATION OF A SAFETY SYSTEM                                |
|                                                                              |
| "AT 1135 HOURS ON 11/29/00 AUTOCLAVE #3 IN THE X-343, EXPERIENCED A HIGH     |
| CONDENSATE LEVEL SHUTOFF ACTUATION WHEN BOTH PROBES IN THE CONDENSATE DRAIN  |
| LINE FIRED. THIS ACTUATION OCCURRED DURING MODE II OPERATIONS (HEATING),     |
| RESULTING IN THE SHUTTING OF THE STEAM ISOLATION VALVE AND SHUTTING DOWN OF  |
| THE AUTOCLAVE.  OPERATORS FOLLOWING APPROVED RESPONSE PROCEDURES VERIFIED    |
| THE CYLINDERS STRUCTURAL INTEGRITY.  APPROXIMATELY TEN MINUTES AFTER THE     |
| STEAM VALVE SHUT THE HIGH CONDENSATE PROBE ALARMS CLEARED BASED ON THE       |
| ACTUATION OF BOTH CONDENSATE LEVEL PROBES. THIS IS BEING REPORTED AS A       |
| SAFETY SYSTEM ACTUATION. THE AUTOCLAVE WAS DECLARED INOPERABLE AND           |
| ENGINEERING IS EVALUATING THIS SYSTEM ACTUATION. THERE WAS NO RELEASE OF     |
| RADIOACTIVE MATERIAL FROM THIS EVENT."                                       |
|                                                                              |
| OPERATIONS PERSONNEL INFORMED BOTH THE DOE SITE REPRESENTATIVE AND THE NRC   |
| RESIDENT INSPECTOR.                                                          |
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