United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated With Events > Event Notification Reports > 2000

Event Notification Report for July 21, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           07/20/2000 - 07/21/2000

                              ** EVENT NUMBERS **

35862  37178  37179  37180  

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   35862       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  ABB COMBUSTION ENGINEERING           |NOTIFICATION DATE: 06/25/1999|
|LICENSEE:  ABB COMBUSTION ENGINEERING           |NOTIFICATION TIME: 16:34[EDT]|
|    CITY:  WINDSOR                  REGION:  1  |EVENT DATE:        06/25/1999|
|  COUNTY:                            STATE:  CT |EVENT TIME:             [EDT]|
|LICENSE#:                        AGREEMENT:  N  |LAST UPDATE DATE:  07/20/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |GLENN MEYER          R1      |
|                                                |VERN HODGE (via fax) NRR     |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  IAN RICKARD                  |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 10CFR PART 21 REPORT REGARDING ABB COMBUSTION ENGINEERING 4KV VACUUM         |
| BREAKERS                                                                     |
|                                                                              |
| The following text is excerpted from a facsimile received in the NRC         |
| Operations Center:                                                           |
|                                                                              |
| "The defect concerns ABB 1200A 4KV Vacuum Breakers delivered to Baltimore    |
| Gas and Electric Company's (BG&E's) Calvert Cliffs Nuclear Power Plant       |
| (CCNPP).  Specifically, the defect concerns the breaker performing a trip    |
| free operation when a close signal is received by the breaker.  This defect  |
| results in the breaker failing to remain in the closed position.  The defect |
| could lead to non-conservative failure of not starting certain plant         |
| equipment upon demand such as an Emergency Core Cooling Pump."               |
|                                                                              |
| * * * UPDATE AT 1613 ON 06/30/99 BY VIRGIL PAGGEN TO JOLLIFFE * * *          |
|                                                                              |
| The above 10CFR Part 21 Report was submitted to the NRC via ABB Combustion   |
| Engineering Letter #LD-99-035, dated 06/25/99.  The following is an update   |
| to the above 10CFR Part 21 Report via ABB Combustion Engineering Letter      |
| #LD-99-039, dated 06/30/99, Same Subject.                                    |
|                                                                              |
| The activity for which this report is being filed is the use of ABB 1200A    |
| 4KV Vacuum Breakers in an application where the breaker is normally open and |
| must close on demand.  This defect applies only to BG&E's CCNPP.             |
|                                                                              |
| The defect identified is associated with the use of the ABB 1200A 4KV Vacuum |
| Breaker only in applications where the breaker must close on demand.  The    |
| defect was detected during site testing of the breaker during installation   |
| into CCNPP.  During this test, a close signal was applied to the breaker and |
| the breaker tripped free (i.e., failed to remain in the closed position).    |
|                                                                              |
| These breakers are intended for both normally open and normally closed       |
| operation.  In some applications, the breaker must close upon demand.  This  |
| may be for electrical distribution applications or component control         |
| applications (e.g., start an Emergency Core Cooling pump).  Demands can be   |
| automated (e.g., by ESFAS) or based on manual operator demands.  If the      |
| breaker does not remain closed when demanded (i.e., trips free), the safety  |
| function cannot be performed.  This breaker is intended for use in multiple  |
| redundant safety divisions. Multiple redundant divisions could be affected   |
| by this defect.                                                              |
|                                                                              |
| The defect applies only to ABB 1200A 4KV Vacuum Breakers delivered to CCNPP. |
| Thirty-seven (37) of these breakers were delivered to CCNPP.   ABB           |
| Combustion Engineering understands that several of these breakers have been  |
| installed at CCNPP, however, none are installed in any application that      |
| requires a close on demand function.                                         |
|                                                                              |
| The NRC Operations Officer notified the R1DO Larry Doerflein and NRR Vern    |
| Hodge (via fax).                                                             |
|                                                                              |
| * * *  UPDATE AT 1740 ON 7/20/00, BY PAGGEN VIA FAX RECEIVED BY WEAVER * *   |
| *                                                                            |
| An additional defect has been discovered.                                    |
|                                                                              |
| The defect concerns ABB 1200A 4KV Vacuum Breakers delivered to the Calvert   |
| Cliffs Nuclear Power Plant. Specifically, the defect reported herein         |
| concerns the potential for breaker stalling due to interference between an   |
| adjustment nut on the auxiliary switch extension rod and the mechanism top   |
| cover plate.  Such interference could result in failure of the auxiliary     |
| switch contacts to fully change state, which could prevent the breaker from  |
| being remotely opened on demand and could lead to failure of certain plant   |
| equipment to start on demand.  This defect could also potentially provide    |
| incorrect information to operators regarding the status of the breaker.      |
|                                                                              |
| The Operations Center notified the R1DO (Cranston) and NRR (Hodge) via fax.  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37178       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 07/20/2000|
|    UNIT:  [] [3] []                 STATE:  NY |NOTIFICATION TIME: 04:28[EDT]|
|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        07/20/2000|
+------------------------------------------------+EVENT TIME:        03:52[EDT]|
| NRC NOTIFIED BY:  TESORIERO                    |LAST UPDATE DATE:  07/20/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GREGORY CRANSTON     R1      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|3     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNIT OUTSIDE OF DESIGN BASIS                                                 |
|                                                                              |
| "On July 20, 2000 at 0352 hours a Reactor Coolant system leakrate of 0.30    |
| gpm was calculated. Currently the Charging and Letdown systems are isolated  |
| for maintenance. Investigation revealed the leakage being from the Excess    |
| Letdown system to the systems isolated for maintenance, which are located    |
| outside Containment. This leakrate exceeds the limit of 0.68 gph outside     |
| Containment and therefore is a condition outside the design basis of the     |
| plant. The Control Room Ventilation system is inoperable and a 72 hour       |
| limiting condition of operation has been entered."                           |
|                                                                              |
| The NRC resident inspector will be informed of this event by the licensee.   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37179       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM                  REGION:  1  |NOTIFICATION DATE: 07/20/2000|
|    UNIT:  [1] [] []                 STATE:  MA |NOTIFICATION TIME: 08:55[EDT]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        07/20/2000|
+------------------------------------------------+EVENT TIME:        08:15[EDT]|
| NRC NOTIFIED BY:  HAISLETT                     |LAST UPDATE DATE:  07/20/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GREGORY CRANSTON     R1      |
|10 CFR SECTION:                                 |                             |
|AESS 50.72(b)(1)(v)      EMERGENCY SIREN INOP   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| EMERGENCY SIRENS INOPERABLE                                                  |
|                                                                              |
| The licensee reported that offsite emergency sirens are inoperable due to a  |
| transmitter failure. The transmitter associated with one of the sirens has   |
| failed in the transmit mode, and radio interference from this siren is       |
| affecting the ability to activate all of the other sirens. The licensee is   |
| attempting to locate the failed siren and deenergize the transmitter. The    |
| NRC resident inspector has been informed of this event.                      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37180       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SOUTH TEXAS              REGION:  4  |NOTIFICATION DATE: 07/20/2000|
|    UNIT:  [1] [] []                 STATE:  TX |NOTIFICATION TIME: 13:54[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        07/20/2000|
+------------------------------------------------+EVENT TIME:        10:15[CDT]|
| NRC NOTIFIED BY:  BILL MOOKHOEK                |LAST UPDATE DATE:  07/20/2000|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MARK SHAFFER         R4      |
|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                                   
+------------------------------------------------------------------------------+
| INACTIVE LICENSED REACTOR OPERATOR STOOD WATCH FOR ONE HOUR                  |
|                                                                              |
| On July 20, 2000, at 0915 hours, it was determined that a violation of       |
| Technical Specification 6.2.2.b occurred.                                    |
| This notification is being made pursuant to Operating License NPF-76         |
| Condition 2.G for a condition prohibited by                                  |
| Technical Specifications.                                                    |
|                                                                              |
| On July 17, 2000, a licensed reactor operator with an inactive license stood |
| a watch for one hour to cover shift duties. The normal watchstander for day  |
| shift was late and a day staff reactor operator was requested to provide     |
| shift coverage. According to the posted active license list, the reactor     |
| operator's license was active. It was later determined that the active       |
| license list was in error and the license was not active. While on watch     |
| this individual performed no reactivity manipulations, and was supervised by |
| two licensed Senior Reactor Operators.                                       |
|                                                                              |
| Section 6.2.2.a of Technical Specifications requires specific staffing       |
| levels for the operating shift crew. The required shift staffing was not met |
| at all times and is therefore reportable as a violation of Technical         |
| Specifications.                                                              |
|                                                                              |
| This event presented no risk to the health and safety of the general         |
| public.                                                                      |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+