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 |
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+------------------------------------------------------------------------------+
| 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
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| 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). |
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|General Information or Other |Event Number: 37354 |
+------------------------------------------------------------------------------+
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| 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
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| 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. |
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|Power Reactor |Event Number: 37355 |
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| 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. |
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|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
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| 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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Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021