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Event Notification Report for January 21, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           01/20/1999 - 01/21/1999

                              ** EVENT NUMBERS **

35269  35275  35284  35285  35286  35287  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   35269       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BROWNS FERRY             REGION:  2  |NOTIFICATION DATE: 01/15/1999|
|    UNIT:  [] [2] [3]                STATE:  AL |NOTIFICATION TIME: 11:12[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4,[3] GE-4           |EVENT DATE:        01/15/1999|
+------------------------------------------------+EVENT TIME:        06:30[CST]|
| NRC NOTIFIED BY:  CHRIS VAUGHN                 |LAST UPDATE DATE:  01/20/1999|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |AL BELISLE           R2      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|3     N          Y       100      Power Operation  |100      Power Operation  |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| BOTH CONTROL ROOM EMERGENCY VENTILATION TRAINS INOPERABLE FOR ABOUT 11       |
| HOURS                                                                        |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "EVENT DESCRIPTION:  On 01/14/99 at 1305 [CST,] the Control Room Emergency   |
| Ventilation (CREV) train 'B' was placed in service for flow rate testing     |
| following scheduled replacement of the charcoal trays.  At the time CREV     |
| train 'B' was started, CREV train 'A' was the only operable CREV train.      |
| When CREV 'B' was started, the CREV primary unit selector switch             |
| (0-XSW-31-7214) was placed in the 'B' position.  This in conjunction with    |
| CREV 'B' in service for testing, rendered CREV 'A' incapable of              |
| automatically starting on a valid initiation signal.  Thus, both CREV trains |
| were inoperable from 1305 hours on 01/14/99 until 0008 hours on 01/15/99.    |
|                                                                              |
| "REPORTABILITY LOGIC:  This condition is reportable per                      |
| 10CFR50.72(b)(2)(iii) as an event or condition that alone could have         |
| prevented the fulfillment of the safety function of systems or structures    |
| that are needed to mitigate the consequences of an accident.  [A licensee    |
| event report (LER)] is also required within 30 days per 10CFR50.73(a)(2)(v)  |
| and (vi).                                                                    |
|                                                                              |
| "Additionally, Unit 2 and 3 Technical Specifications Section 3.7.3.D         |
| requires [that Limiting Condition for Operation (LCO)] 3.0.3 be entered      |
| immediately with two CREV subsystems inoperable.  LCO 3.0.3 requires [that]  |
| action be initiated within 1 hour to place the affected units in MODE 2      |
| within 7 hours.  LCO 3.0.3 was not entered at the time both CREV subsystems  |
| were inoperable.  Therefore, this condition also requires submission of an   |
| LER within 30 days per 10CFR50.73(a)(2)(i)(B), any operation or condition    |
| prohibited by technical specifications."                                     |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
|                                                                              |
| * * * UPDATE AT 1701 ON 1/20/99, BY SWAFFORD TAKEN BY WEAVER * * *           |
|                                                                              |
| The licensee desires to retract this event.  The logic for the retraction    |
| follows:                                                                     |
|                                                                              |
| The initial report was categorized as an event or condition that alone could |
| have prevented the fulfillment of the safety function of systems or          |
| structures that are needed to mitigate the consequences of an accident. Both |
| CREV trains were considered inoperable due to Train B undergoing testing     |
| following charcoal tray replacement and Train A being incapable of           |
| automatically starting on a valid initiation signal due to the primary unit  |
| selector switch being in the B position.                                     |
|                                                                              |
| After further review and successful completion of post maintenance testing   |
| of the B train, it has been determined that the B train would have been able |
| to fulfill its safety function during the time it was being tested. The B    |
| train was in the required accident alignment during the time the selector    |
| switch was in the B position and post maintenance tests confirmed the        |
| operability of the train. As a consequence, TVA has concluded that this      |
| event does not meet the reporting requirements of 10 CFR 50.72.              |
|                                                                              |
| The licensee informed the NRC resident inspector.  Notified                  |
| R2DO(Christensen).                                                           |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   35275       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 01/15/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 18:08[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        01/15/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        14:10[EST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  01/20/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |JIM GAVULA           R3      |
|  DOCKET:  0707002                              |JOHN SURMEIER        NMSS    |
+------------------------------------------------+FRANK CONGEL         IRO     |
| NRC NOTIFIED BY:  RICHARD LARSON               |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 4-HOUR NRC 91-01 BULLETIN NOTIFICATION INVOLVING ABANDONED EQUIPMENT IN THE  |
| X-326 PROCESS BUILDING                                                       |
|                                                                              |
| ON JANUARY 15, 1999, AT 1410 EST IT WAS DISCOVERED THAT THE X-326 PROCESS    |
| BUILDING NUCLEAR CRITICALITY APPROVALS (NCSAs)  DO NOT DESCRIBE THE          |
| OPERATION/CONTROLS FOR THE FOLLOWING ABANDONED IN PLACE EQUIPMENT:  PRODUCT  |
| PURIFICATION DISTILLATION TOWER, OLD EVACUATION JETS, OLD SO2 REACTOR, OLD   |
| PW BOOSTER CONNECTED TO CELL 25-7-15,  AND [AN] OLD FREON DEGRADER.          |
|                                                                              |
| "THIS IS REPORTABLE DUE TO NOT HAVING ANY NCSA IN PLACE FOR THIS ABANDONED   |
| EQUIPMENT.                                                                   |
|                                                                              |
| "THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIAL OR                      |
| RADIOACTIVE/RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT."  |
|                                                                              |
| A PRIOR NRC NOTIFICATION (EVENT #33627) WAS MADE WHICH IDENTIFIED LEGACY     |
| EQUIPMENT IN THE X-326 PROCESS BUILDING, HOWEVER, THE ABOVE EQUIPMENT WAS    |
| INADVERTENTLY OMITTED.  THE EQUIPMENT IS IN GEOMETRICALLY FAVORABLE          |
| CONDITIONS AND CONTAINS URANIUM BELOW THE SAFE MASS LIMIT.  THIS CONDITION   |
| WAS DISCOVERED IN A REVIEW OF COMPLETED NCSAs.                               |
|                                                                              |
| THE LICENSEE WILL INFORM THE DOE SITE REPRESENTATIVE AND HAS INFORMED THE    |
| NRC RESIDENT INSPECTOR.                                                      |
|                                                                              |
| * * * UPDATE AT 1955 ON 1/18/99, BY LARSON, TAKEN BY WEAVER * * *            |
|                                                                              |
| "THIS IS REPORTABLE DUE TO NOT HAVING ANY NCSA IN PLACE FOR THIS ABANDONED   |
| EQUIPMENT.                                                                   |
|                                                                              |
| UPDATE: DUE TO THE PROBLEMS CONCERNING ABANDONED EQUIPMENT IN THE X-326      |
| BUILDING NOT COVERED BY NUCLEAR CRITICALITY SAFETY APPROVALS (NCSAs), A      |
| SEARCH PERFORMED IN THE X-705 & X-700 REVEALED ABANDONED EQUIPMENT THAT MAY  |
| NEED NCSAs. THE PLANT IS FOLLOWING IT'S PROCEDURE FOR ANOMALOUS NCSA         |
| CONDITIONS AND FURTHER EVALUATIONS ARE IN PROGRESS TO DETERMINE IF THIS      |
| ABANDONED EQUIPMENT MEETS THE FISSILE MATERIAL LIMITS. THE FISSILE MATERIAL  |
| LIMIT OF 15 GRAMS U235 BY PLANT PROCEDURES REQUIRES NCSAs."                  |
|                                                                              |
| THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIAL OR                       |
| RADIOACTIVE/RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT.   |
|                                                                              |
| The licensee informed the NRC resident inspector.  The Operations Officer    |
| notified the RDO (Gavula); EO (Surmeier); IRO (Congel).                      |
|                                                                              |
| * * * UPDATE AT 1643 ON 1/20/99, BY HALCOMB, TAKEN BY WEAVER * * *           |
|                                                                              |
| DUE TO PROBLEMS CONCERNING ABANDONED EQUIPMENT IDENTIFIED IN THE X-326       |
| BUILDING NOT COVERED BY AN NCSA, A PLANT WIDE SEARCH WAS INITIATED TO        |
| IDENTIFY ALL EQUIPMENT WHICH MAY MEET THE FISSILE MATERIAL LIMITS AND WOULD  |
| REQUIRE AN ACTIVE NCSA. THIS SEARCH HAS IDENTIFIED THAT THE X-344, X-333,    |
| AND THE X-330 BUILDINGS CONTAIN ABANDONED EQUIPMENT THAT WILL REQUIRE AN     |
| NCSA.  ALL IDENTIFIED EQUIPMENT HAS BEEN BOUNDARIED OFF AND AN ANOMALOUS NCS |
| CONDITION REPORT COMPLETED.                                                  |
|                                                                              |
| THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIAL OR                       |
| RADIOACTIVE/RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT.   |
|                                                                              |
| The licensee informed the NRC resident inspector.  The Operations Officer    |
| notified the RDO (Lanksbury); EO (BELL); IRO (Congel).                       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35284       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DUANE ARNOLD             REGION:  3  |NOTIFICATION DATE: 01/20/1999|
|    UNIT:  [1] [] []                 STATE:  IA |NOTIFICATION TIME: 05:58[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        01/20/1999|
+------------------------------------------------+EVENT TIME:        04:50[CST]|
| NRC NOTIFIED BY:  DAVE SCHUSSLER               |LAST UPDATE DATE:  01/20/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ROGER LANKSBURY      R3      |
|10 CFR SECTION:                                 |                             |
|ASHU 50.72(b)(1)(i)(A)   PLANT S/D REQD BY TS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PLANT SHUTDOWN REQUIRED BY TECHNICAL SPECIFICATIONS                          |
|                                                                              |
| The licensee commenced a unit shutdown in accordance with Technical          |
| Specification (TS) 3.8.1.7 after both standby diesel generators failed to    |
| reach required voltage and frequency within the required time (ten seconds)  |
| during a surveillance test.  The licensee stated that the methodology for    |
| the test has been changed, and this was the first test performed using the   |
| new methodology.                                                             |
|                                                                              |
| The old test procedure recorded the time for the diesel generators to start  |
| and reach required voltage and frequency, although the generators normally   |
| overshoot the targets slightly before reaching a steady state value. The     |
| revised test methodology records the time for the diesel generators to reach |
| steady state voltage and frequency. The licensee reported that one diesel    |
| generator reached steady state within 15 seconds, and the other reached      |
| steady state within 22 seconds.                                              |
|                                                                              |
| The NRC resident inspector has been informed of this event by the licensee.  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35285       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: TURKEY POINT             REGION:  2  |NOTIFICATION DATE: 01/20/1999|
|    UNIT:  [3] [] []                 STATE:  FL |NOTIFICATION TIME: 07:51[EST]|
|   RXTYPE: [3] W-3-LP,[4] W-3-LP                |EVENT DATE:        01/20/1999|
+------------------------------------------------+EVENT TIME:        07:51[EST]|
| NRC NOTIFIED BY:  ROBERT HANKE                 |LAST UPDATE DATE:  01/20/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHRIS CHRISTENSEN    R2      |
|10 CFR SECTION:                                 |                             |
|AARC 50.72(b)(1)(v)      OTHER ASMT/COMM INOP   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| ERDS UNAVAILABLE DUE TO TESTING                                              |
|                                                                              |
| The Turkey Point Emergency Response Data System (ERDS) link will be removed  |
| from service for approximately eight to ten hours in order to perform Year   |
| 2000 (Y2K) compliance testing of the plant Emergency Response Data           |
| Acquisition and Display System (ERDADS). The NRC resident inspector has been |
| informed of this notification by the licensee.                               |
|                                                                              |
| * * * UPDATE AT 1955 ON 1/20/99, BY HICKEY, TAKEN BY WEAVER * * *            |
|                                                                              |
| The licensee returned the ERDS link to service at 1830.  The NRC resident    |
| inspector will be informed.  The Operations Center notified the R2DO         |
| (Christensen).                                                               |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35286       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRAIDWOOD                REGION:  3  |NOTIFICATION DATE: 01/20/1999|
|    UNIT:  [1] [] []                 STATE:  IL |NOTIFICATION TIME: 13:00[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        01/20/1999|
+------------------------------------------------+EVENT TIME:        11:22[CST]|
| NRC NOTIFIED BY:  BOB NORK                     |LAST UPDATE DATE:  01/20/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          UNU                   |ROGER LANKSBURY      R3      |
|10 CFR SECTION:                                 |ED GOODWIN           NRR     |
|AAEC 50.72(a)(1)(i)      EMERGENCY DECLARED     |ROSEMARY HOGAN       IRO     |
|                                                |CANUPP               FEMA    |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNUSUAL EVENT - LOSS OF APPROXIMATELY 50% OF CONTROL ROOM ANNUNCIATORS       |
|                                                                              |
| "Loss of redundant Annunciator Power Supplies has rendered a substantial     |
| number of safety related annunciators inoperable.  This required a GSEP      |
| notification - Unusual Event, (MU-6 - Loss of Annunciators for >= 15         |
| minutes).  Backup indications are available and increased main control board |
| monitoring has been implemented."                                            |
|                                                                              |
| The licensee has notified the NRC resident inspector.                        |
|                                                                              |
| Event #35280 involved the same equipment.                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35287       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FERMI                    REGION:  3  |NOTIFICATION DATE: 01/20/1999|
|    UNIT:  [2] [] []                 STATE:  MI |NOTIFICATION TIME: 18:08[EST]|
|   RXTYPE: [2] GE-4                             |EVENT DATE:        01/20/1999|
+------------------------------------------------+EVENT TIME:        14:13[EST]|
| NRC NOTIFIED BY:  SANJEEV ARAB                 |LAST UPDATE DATE:  01/20/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ROGER LANKSBURY      R3      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       96       Power Operation  |96       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION (HPCI) INOPERABLE                            |
|                                                                              |
| At 1413 on 01/20/1999, the E4150-F022 "HPCI TURBINE EXHAUST DRAIN POT        |
| STOP/CHECK VALVE"  which drains to the suppression pool, failed to meet      |
| stroke time requirements (28.6 sec vs. <=27 sec required).                   |
|                                                                              |
| The valve was closed and locked per Technical Specifications 3.6.3  Primary  |
| Containment Isolation Valves  at 1600.   With the E4150-F022 valve closed,   |
| it has been determined that the HPCI system is inoperable.  This valve path  |
| provides a drain path for the drain pot during accident conditions.          |
|                                                                              |
| Repair efforts are in progress.                                              |
|                                                                              |
| The licensee informed the NRC resident inspector.                            |
+------------------------------------------------------------------------------+