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Event Notification Report for February 24, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           02/23/1999 - 02/24/1999

                              ** EVENT NUMBERS **

35239  35390  35394  35395  35396  

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|Power Reactor                                    |Event Number:   35239       |
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| FACILITY: RIVER BEND               REGION:  4  |NOTIFICATION DATE: 01/11/1999|
|    UNIT:  [1] [] []                 STATE:  LA |NOTIFICATION TIME: 16:56[EST]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        01/11/1999|
+------------------------------------------------+EVENT TIME:        15:20[CST]|
| NRC NOTIFIED BY:  RUSS GODWIN                  |LAST UPDATE DATE:  02/23/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BLAIR SPITZBERG      R4      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(vi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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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| NOTIFICATION TO STATE DEPARTMENT OF ENVIRONMENTAL QUALITY  (Refer the event  |
| #34815 for additional information.)                                          |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "On January 11, 1999, [River Bend Station (RBS)] personnel made a report to  |
| the Louisiana Department of Environmental Quality related to a potential     |
| defect in fuel cladding.  A previous report was made on September 21, 1998,  |
| and updated on October 22, 1998.  RBS personnel have continued to monitor    |
| plant conditions after the first two had been suppressed.  Chemistry         |
| sampling and power suppression results indicate a probable third fuel        |
| failure.  Indications could be caused by a previously identified fuel        |
| failure."                                                                    |
|                                                                              |
| "The plant is operating at 100% power with radioactive releases well below   |
| the limits of the Technical Requirements Manual and 10 CFR [Part] 20.  Plant |
| personnel continue to implement site procedures to address the issue and     |
| take appropriate actions."                                                   |
|                                                                              |
| The NRC resident inspector has been informed of this notification by the     |
| licensee.                                                                    |
|                                                                              |
| * * * UPDATE AT 1507 EST ON 01/26/99 FROM JOEY CLARK TO S.SANDIN * * *       |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "[At 1305 CST] on January 26, 1999, RBS personnel made a report to the       |
| Louisiana Department of Environmental Quality related to a potential defect  |
| in fuel cladding.  [Previous reports were] made on September 21, 1998,       |
| updated on October 22, 1998, and on January 11, 1999.  Plant instrumentation |
| and chemistry sampling indicates RBS has three (3) apparent fuel leakers and |
| a probable fourth fuel leaker adjacent to a previously identified and        |
| suppressed fuel leaker."                                                     |
|                                                                              |
| "The plant is operating at 94.5% power with radioactive releases well below  |
| the limits of the Technical Requirements Manual and 10 CFR [Part] 20.        |
| Plant personnel continue to implement site procedures to address this issue  |
| and take appropriate actions."                                               |
|                                                                              |
| The licensee informed the NRC resident inspector.  The NRC operations        |
| officer notified the R4DO (Marshall).                                        |
|                                                                              |
| * * * UPDATE AT 1435 EST ON 02/05/99 FROM DAN JERRELL TO JOLLIFFE * * *      |
|                                                                              |
| On 02/05/99, RBS personnel made a reports to the Louisiana Department of     |
| Environmental Quality related to a potential defect in fuel cladding.        |
| Previous report were made on 09/21/98 (updated on 10/22/98) and on 01/11/99  |
| (updated on 01/26/99).  During suppression testing for the 01/26/99 update,  |
| an additional probable fuel leaker was identified.  Plant instrumentation    |
| and chemistry sampling indicates RBS has three apparent fuel leakers and two |
| probable fuel leakers.  Currently, all apparent and probable fuel leakers    |
| are being suppressed.                                                        |
|                                                                              |
| The plant is operating at 94% power with radioactive releases well below the |
| limits of the Technical Requirements Manual and 10 CFR Part 20.  Plant       |
| personnel continue to implement site procedures to address this issue and    |
| take appropriate actions.                                                    |
|                                                                              |
| The licensee informed the NRC resident inspector.  The NRC operations        |
| officer notified the R4DO (Jeff Shackelford).                                |
|                                                                              |
| * * * UPDATE AT 1453 EST ON 02/23/99 FROM DONALD CHASE TO FANGIE JONES * *   |
| *                                                                            |
|                                                                              |
| On 02/23/99, RBS personnel made a report to the Louisiana Department of      |
| Environmental Quality related to a potential defect in fuel cladding.  On    |
| 02/15/99 at approximately 1200 CST, plant instrumentation indicated that RBS |
| experienced an additional probable fuel leaker.  Plant instrumentation and   |
| chemistry sampling indicates RBS has four apparent fuel leakers and two      |
| probable fuel leakers.  RBS is planning to perform suppression testing this  |
| weekend in an attempt to locate and suppress this additional fuel leaker.    |
|                                                                              |
| The plant is operating at 90% power with radioactive releases well below the |
| limits of the Technical Requirements Manual and 10 CFR Part 20.  Plant       |
| personnel continue to implement site procedures to address this issue and    |
| take appropriate actions.                                                    |
|                                                                              |
| The licensee informed the NRC resident inspector.  The NRC operations        |
| officer notified the R4DO (Elmo Collins).                                    |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35390       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SEABROOK                 REGION:  1  |NOTIFICATION DATE: 02/21/1999|
|    UNIT:  [1] [] []                 STATE:  NH |NOTIFICATION TIME: 11:28[EST]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        02/20/1999|
+------------------------------------------------+EVENT TIME:        21:00[EST]|
| NRC NOTIFIED BY:  STEVE MORRISSEY              |LAST UPDATE DATE:  02/23/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JIM TRAPP            R1      |
|10 CFR SECTION:                                 |                             |
|NLTR                     LICENSEE 24 HR REPORT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| DISCOVERY OF ELEVEN DEAD SEA DUCKS IN CIRCULATING WATER SCREEN WASH DEBRIS   |
|                                                                              |
| Eleven dead sea ducks were observed in Seabrook Station's circulating water  |
| screen wash debris on February 20, 1999, at approximately 2100 hours.  It is |
| not known at this time whether the ducks were alive or dead upon entering    |
| the offshore intake structure.  Sea ducks are diving birds which feed        |
| underwater.  This is a 24-hour notification in accordance with Section 4.1   |
| of the Environmental Protection Plan, Appendix B of the operating license.   |
|                                                                              |
| The NRC resident inspector was notified of this event report by the          |
| licensee.                                                                    |
|                                                                              |
| * * * UPDATE AT 1407 EST ON 02/22/99 FROM STEVE MORRISSEY TO FANGIE JONES *  |
| * *                                                                          |
|                                                                              |
| Two additional dead sea ducks were observed in Seabrook Station's            |
| circulating water screen wash debris on February 21, 1999, at approximately  |
| 2245 hours.  The licensee believes these additional dead sea ducks are part  |
| of the original group and were not picked up on the screen wash of the night |
| of February 20, 1999.                                                        |
|                                                                              |
| The licensee notified the NRC resident inspector.  The NRC operations        |
| officer notified the R1DO (Richard Barkley).                                 |
|                                                                              |
| * * * UPDATE AT 1402 ON 02/23/99 FROM STEVE MORRISSEY TO JOLLIFFE * * *      |
|                                                                              |
| Three additional dead sea ducks were observed in Seabrook Station's          |
| circulating water screen wash debris on February 23, 1999, at approximately  |
| 0100 hours.  The licensee believes that these additional dead sea ducks are  |
| part of the original group and were not picked up on the screen wash on      |
| February 21, 1999.                                                           |
|                                                                              |
| The licensee notified the NRC resident inspector.  The NRC operations        |
| officer notified the R1DO (Richard Barkley).                                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   35394       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 02/23/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 08:24[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        02/22/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        10:15[EST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  02/23/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |BRUCE JORGENSEN      R3      |
|  DOCKET:  0707002                              |FRED COMBS, EO       NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  R. LARSON                    |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| NRC BULLETIN 91-01 RESPONSE (24-HOUR NOTIFICATION)                           |
|                                                                              |
| Two condensers were found with their drain valves closed.  This is loss of   |
| moderation control and a violation of the NCSA requirements.                 |
|                                                                              |
| The following text is a portion of a facsimile received from Portsmouth:     |
|                                                                              |
| "On 02/22/99 at 1015 hours, X-333 operations personnel discovered that a     |
| Nuclear Criticality Safety Approval (NCSA) requirement was not being         |
| maintained on off-stream cell 33-5-7.  NCSA-0333_015.A03 requirement #10     |
| states in part, 'The condenser shall remain drained and vented to atmosphere |
| until after the R-114 is restored to the coolant system.'  On cell 33-5-7,   |
| the condenser drain valve was discovered closed; therefore, the condenser    |
| was not vented.  When the drain valve was opened, there was a small amount   |
| of water removed from the condenser.  Due to the above condition, the plant  |
| shift superintendent (PSS) directed the X-326, X-330, and the X-333          |
| operations personnel [to] conduct a walkdown of all off-stream cells to      |
| verify NCSA compliance.  As a result of this walkdown, off-stream cell       |
| 33-8-9 was discovered with the condenser drain valve closed thus violating   |
| the same NCSA requirement.  Requirement #10 was established immediately when |
| the drain valve was opened.  There was no water present on 33-8-9 when the   |
| drain valve was opened.  Both of these incidents violated requirement #10 of |
| the specified NCSA thus constituting a loss of control 'A' (moderation) in   |
| the double contingency matrix for contingency event A/B.6.b.3.  Control 'B'  |
| (mass) was maintained throughout this event.  A walkdown of all off-stream   |
| cells in all process buildings [was conducted and completed at 0600 EST on   |
| 02/23/99 without finding any drain valves closed]."                          |
|                                                                              |
| "SAFETY SIGNIFICANCE OF EVENTS:  Control 'A' (moderation) was lost when the  |
| condenser drain valve was found closed, and in one case, water [was]         |
| present.  For criticality to occur, a leak would have to develop and have    |
| greater than safe mass present and moderated."                               |
|                                                                              |
| "POTENTIAL CRITICALITY PATHWAY(S) INVOLVED ... :  If a deposit in the cell   |
| was greater than safe mass with optimum conditions, a criticality could      |
| occur if moderated."                                                         |
|                                                                              |
| "CONTROLLED PARAMETERS ... :  Control 'A' (moderation) was lost.  Control    |
| 'B' (mass) was maintained throughout this event."                            |
|                                                                              |
| "ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL ... :  Less than 3% |
| enrichment                                                                   |
| U-235.  Less than safe mass at optimum conditions."                          |
|                                                                              |
| "NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION  |
| OF THE FAILURES OR DEFICIENCIES:  Control 'A' (moderation) was lost when the |
| condenser drain valve was found closed, and in one case, water [was]         |
| present.  Control 'B' (mass) was maintained throughout this event."          |
|                                                                              |
| "CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN EACH WAS IMPLEMENTED:  |
| 33-5-7 condenser drain valve opened and [a] small amount of water [was]      |
| removed upon discovery.  33-8-9 condenser drain valve opened with no water   |
| present upon discovery.  [The] PSS directed operations personnel to walkdown |
| all off-stream cells to verify NCSA compliance."                             |
|                                                                              |
| The NRC resident inspector was notified of this event by the certificate     |
| holder.                                                                      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35395       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BIG ROCK POINT           REGION:  3  |NOTIFICATION DATE: 02/23/1999|
|    UNIT:  [1] [] []                 STATE:  MI |NOTIFICATION TIME: 11:35[EST]|
|   RXTYPE: [1] GE-1                             |EVENT DATE:        02/23/1999|
+------------------------------------------------+EVENT TIME:        09:51[EST]|
| NRC NOTIFIED BY:  MIKE BOURASSA                |LAST UPDATE DATE:  02/23/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BRUCE JORGENSEN      R3      |
|10 CFR SECTION:                                 |CHRIS GRIMES, EO     NRR     |
|AARC 50.72(b)(1)(v)      OTHER ASMT/COMM INOP   |FRANK CONGEL         IRO     |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOSS OF OFFSITE POWER DUE TO LOSS OF SUBSTATION.  TRYING TO REGAIN DOSE      |
| ASSESSMENT.  (Big Rock Point is permanently shut down with the core          |
| offloaded to the spent fuel pool.)                                           |
|                                                                              |
| At 0951 EST, the licensee lost power from its substation which caused a loss |
| of offsite power.  The main emergency diesel generator was started, and the  |
| licensee at this time is loading the emergency diesel generator.  A regional |
| crew is currently troubleshooting the substation and trying to restore       |
| offsite power to the site.  Spent fuel pool cooling was lost due to the loss |
| of offsite power.  The current temperature of the spent fuel pool is 60F.   |
| Spent fuel has been in the spent fuel pool for at least 540 days.  The       |
| licensee said that it would take 14 days for the spent fuel pool to heat up  |
| to 150F.  Per the technical specifications, the licensee has 24 hours to    |
| restore an alternate method of cooling the spent fuel pool.  The licensee    |
| said that they have a fire hose available to be used to supply cooling water |
| to the spent fuel pool.  The licensee said that the emergency diesel         |
| generator will be used to supply power so fire hose water can be supplied to |
| the spent fuel pool if needed.  The spent fuel pool temperature must heat up |
| to 140F before the licensee must declare an Unusual Event.  The licensee    |
| has standby diesel if it is needed.  The licensee said that they have lost   |
| power to their dose assessment equipment.  The licensee is running power     |
| lines so the dose assessment can be re-energized.                            |
|                                                                              |
| All emergency notification telephone lines are dead at this time.  The       |
| licensee called the event in on a commercial phone line.  The licensee can   |
| be called via commercial telephone numbers which were supplied to the NRC    |
| Headquarters Operation Center by the licensee.                               |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
|                                                                              |
| * * * UPDATE AT 1629 EST ON 02/23/99 FROM MIKE BOURASSA TO FANGIE JONES * *  |
| *                                                                            |
|                                                                              |
| Offsite power was restored at 1335 EST.  All emergency notification          |
| telephone lines have been restored to service.  Offsite power was out for    |
| about 3.5 hours.  It was lost due to a momentary undervoltage condition due  |
| to substation switching in the area.  All systems have been returned to      |
| normal operations.                                                           |
|                                                                              |
| The NRC operations officer notified the R3DO (Jorgensen), NRR EO (Hannon),   |
| and IRO (Congel).                                                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35396       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SURRY                    REGION:  2  |NOTIFICATION DATE: 02/23/1999|
|    UNIT:  [1] [2] []                STATE:  VA |NOTIFICATION TIME: 17:58[EST]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        02/23/1999|
+------------------------------------------------+EVENT TIME:        14:30[EST]|
| NRC NOTIFIED BY:  THOMAS SOWERS                |LAST UPDATE DATE:  02/23/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ROBERT HAAG          R2      |
|10 CFR SECTION:                                 |                             |
|HFIT 26.73               FITNESS FOR DUTY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| FITNESS-FOR-DUTY REPORT                                                      |
|                                                                              |
| A contract supervisor was determined to be in possession of a controlled     |
| substance.  The employee's access to the plant has been terminated.          |
| (Contact the NRC Operations Officer for additional details.)                 |
|                                                                              |
| The licensee informed the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+