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Event Notification Report for September 21, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           09/20/2000 - 09/21/2000

                              ** EVENT NUMBERS **

37346  37354  37355  37356  37357  37358  

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|Power Reactor                                    |Event Number:   37346       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DRESDEN                  REGION:  3  |NOTIFICATION DATE: 09/19/2000|
|    UNIT:  [] [] [3]                 STATE:  IL |NOTIFICATION TIME: 01:26[EDT]|
|   RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3           |EVENT DATE:        09/18/2000|
+------------------------------------------------+EVENT TIME:        22:30[CDT]|
| NRC NOTIFIED BY:  BRIAN GRANT                  |LAST UPDATE DATE:  09/20/2000|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BRUCE BURGESS        R3      |
|10 CFR SECTION:                                 |                             |
|ADAS 50.72(b)(2)(i)      DEG/UNANALYZED COND    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|                                                   |                          |
|3     N          N       0        Refueling        |0        Refueling        |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DEGRADED WHILE SHUTDOWN - FAILED CONTAINMENT LEAK RATE TEST                  |
|                                                                              |
| System Engineering reports the local leak rate test results for 3A Feedwater |
| Header Inboard and  Outboard Drywell Check Valves (3-0220-58A & 3-0220-62A)  |
| are indeterminate due to excessive leakage. This exceeds the containment     |
| pathway leakage values allowed by Technical Specifications Primary           |
| Containment Leakage Rate Testing Program.                                    |
|                                                                              |
| The licensee will notify the NRC resident inspector.                         |
|                                                                              |
| * * * UPDATE 2216 9/20/2000 FROM BRIAN GRANT TAKEN BY BOB STRANSKY * * *     |
|                                                                              |
| The "B" main steam inboard and outboard isolation valves also exceeded their |
| maximum allowable leakage. The NRC resident inspector has been informed by   |
| the licensee. Notified R3DO (Burgess).                                       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37354       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  SCIENTECH/NUSI                       |NOTIFICATION DATE: 09/20/2000|
|LICENSEE:  SCIENTECH/NUSI                       |NOTIFICATION TIME: 07:42[EDT]|
|    CITY:  GAITHERSBURG             REGION:  1  |EVENT DATE:        09/14/2000|
|  COUNTY:                            STATE:  MD |EVENT TIME:             [EDT]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  09/20/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |WILLIAM RULAND       R1      |
|                                                |VERN HODGE           NRR     |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  BOOSKA                       |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PART 21 RELATED TO DEFECTS IN DELTA T TIME DOMAIN MODULES SUPPLIED TO GINNA  |
| STATION                                                                      |
|                                                                              |
| SCIENTECH Inc.'s subsidiary NUS Instruments, Inc. (NUSI) has determined that |
| a Basic Component, supplied to Rochester Gas & Electric Ginna Station        |
| Nuclear Plant under RG&E purchase order NQ-l5877-A-JW, may contain a defect  |
| that is reportable under 10CFR21.  NUSI became aware of this potential       |
| defect September 14, 2000.  SCIENTECH, Inc. President was informed September |
| 19, 2000.  RG&E is aware of this problem and the affected components have    |
| been modified to remove any undesirable effects on their systems. A formal   |
| written report will be provided within 30 days of this notification.  The    |
| components, DELTA T Time Domain Modules, M/N: TMD500-08/08/08/08-15-08-01/2, |
| P/N: MBA-E062PA-l, Rev. 0 (4 ea.), were manufactured by NUSI.  These         |
| components have been supplied to no other utility for use in Safety Related  |
| Systems.  NUSI has opened a 10CFR21 file concerning this component and has   |
| numbered it as 21-00-01.                                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37355       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VOGTLE                   REGION:  2  |NOTIFICATION DATE: 09/20/2000|
|    UNIT:  [1] [2] []                STATE:  GA |NOTIFICATION TIME: 12:55[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        09/20/2000|
+------------------------------------------------+EVENT TIME:        12:15[EDT]|
| NRC NOTIFIED BY:  R. DORMAN                    |LAST UPDATE DATE:  09/20/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |THOMAS DECKER        R2      |
|10 CFR SECTION:                                 |                             |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SECURITY REPORT                                                              |
|                                                                              |
| Unescorted access granted inappropriately. Immediate compensatory measures   |
| taken upon discovery. Contact the NRC Operations Center for additional       |
| information. The NRC resident inspector will be informed of this             |
| notification.                                                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37356       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  TVA                                  |NOTIFICATION DATE: 09/11/2000|
|LICENSEE:  TVA                                  |NOTIFICATION TIME: 11:35[EDT]|
|    CITY:  CHATTANOOGA              REGION:  2  |EVENT DATE:        09/11/2000|
|  COUNTY:  HAMILTON                  STATE:  TN |EVENT TIME:             [EDT]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  09/20/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |LORI HAYES           R2      |
|                                                |BARRY MANILI         NRR     |
+------------------------------------------------+ROBERTA WARREN       NMSS    |
| NRC NOTIFIED BY:  MIKE HARDING                 |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNESCORTED ACCESS GRANTED INAPPROPRIATELY                                    |
|                                                                              |
| On September 11, 2000, TVA reported that inappropriate access may have been  |
| granted to some TVA employees based upon developed references utilized by    |
| RCM Power Services (formally Cataract Engineering, Inc.) in background       |
| investigations.  TVA-IG discovered five individuals may have been granted    |
| access based on incomplete information.  Workers at other licensees may be   |
| affected. Immediate compensatory measures were taken upon discovery.         |
|                                                                              |
| Refer to HOO log for additional details.                                     |
|                                                                              |
| Hoo Note:  This applies to the following reactor sites, as reported:  Browns |
| Ferry, Sequoyah, and Watts Bar.                                              |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37357       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH                    REGION:  2  |NOTIFICATION DATE: 09/20/2000|
|    UNIT:  [1] [] []                 STATE:  GA |NOTIFICATION TIME: 14:33[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        09/20/2000|
+------------------------------------------------+EVENT TIME:        12:15[EDT]|
| NRC NOTIFIED BY:  ED BURKETT                   |LAST UPDATE DATE:  09/20/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |THOMAS DECKER        R2      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       98       Power Operation  |98       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| RWCU ISOLATION VALVE FAILED TO CLOSE DURING TEST                             |
|                                                                              |
| During performance of a reactor water cleanup (RWCU) logic system functional |
| test, RWCU inboard isolation valve 1G31-F001 failed to close when a          |
| simulated high area temperature signal was applied. Subsequent testing       |
| indicates that a relay failed in the isolation circuitry. The licensee will  |
| replace the failed relay. The NRC resident inspector will be informed of     |
| this notification by the licensee.                                           |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37358       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH              REGION:  3  |NOTIFICATION DATE: 09/20/2000|
|    UNIT:  [1] [2] []                STATE:  WI |NOTIFICATION TIME: 17:51[EDT]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        09/20/2000|
+------------------------------------------------+EVENT TIME:        16:05[CDT]|
| NRC NOTIFIED BY:  RYAN RODE                    |LAST UPDATE DATE:  09/20/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BRUCE BURGESS        R3      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PLANT OUTSIDE 10 CFR PART 50 APPENDIX R DESIGN BASIS DUE TO PROCEDURAL       |
| ISSUES                                                                       |
|                                                                              |
| "During the final review of the new Appendix R rebaselining project, it was  |
| discovered that the refueling water storage tank (RWST) inventory could be   |
| lost if AOP 10A, 'Safe Shutdown-Local Control' and AOP 10B 'Safe to Cold     |
| Shutdown in Local Control' were performed as written. The postulated event   |
| occurs during an Appendix R fire where SI-851(RHR pump suction from          |
| containment sump B) encounters a spurious open signal, causing the RWST to   |
| drain via backflow into containment. The procedures do not address this      |
| potential failure early enough into the event to preclude a potential loss   |
| of RWST inventory. This puts Point Beach Nuclear Power Plant outside of its  |
| design basis because 10CFR50 Appendix R Section III.L.2.b performance goals  |
| might not be met for the above scenario."                                    |
|                                                                              |
| The NRC resident inspector will be informed of this notification by the      |
| licensee.                                                                    |
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