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. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021