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 |
| | |
| | |
+------------------------------------------------------------------------------+
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). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|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
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| 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
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| 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 60�F. |
| 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 150�F. 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 140�F 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. |
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