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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37555 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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 |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 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 ½ 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). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 37556 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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 | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 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. |
+------------------------------------------------------------------------------+