Event Notification Report for June 30, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
06/29/1999 - 06/30/1999
** EVENT NUMBERS **
35793 35879
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 35793 |
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| FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 06/04/1999|
| UNIT: [1] [] [] STATE: VT |NOTIFICATION TIME: 12:35[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 06/04/1999|
+------------------------------------------------+EVENT TIME: 09:50[EDT]|
| NRC NOTIFIED BY: MITCH McCLUSKIE |LAST UPDATE DATE: 06/29/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |RONALD BELLAMY R1 |
|10 CFR SECTION: | |
|AINB 50.72(b)(2)(iii)(B) POT RHR 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 |
| | |
| | |
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EVENT TEXT
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| ALTERNATE COOLING SYSTEM DECLARED INOPERABLE |
| |
| "Following a question raised by an NRC Resident Inspector at VY, an Event |
| Report was submitted due to a lack of sufficient analysis to determine if |
| procedural guidance was adequate for operation of the Alternate Cooling |
| System (ACS). VY declared the ACS inoperable at 2110 on 6/3/99 and entered |
| a 7 day LCO [3.5.d.3] per the plant Technical Specifications. Based on |
| further evaluation, Operations and Engineering Personnel concluded that |
| current VY procedures may not provide the specific information necessary to |
| ensure that ACS Design Bases 1 & 2 above, would have been met. Engineering |
| and Licensing evaluations of ACS design and performance requirements |
| continue. |
| |
| "VY is currently developing procedural enhancements that will ensure that |
| the operating crews are provided with the guidance necessary to ensure that |
| ACS would be operated in the manner necessary to achieve its safety design |
| bases. It is expected that the necessary procedural guidance will be |
| developed and issued prior to the |
| expiration of the cited 7 day LCO." |
| |
| The licensee notified the NRC Resident Inspector and the State of Vermont. |
| |
| * * * RETRACTION 1635 6/29/1999 FROM BROOKS TAKEN BY STRANSKY * * * |
| |
| "Subsequent to [the original notification], Engineering and Licensing have |
| determined that the design basis criteria for the subject design basis event |
| is that the plant must be maintained in Hot Shutdown condition with a pool |
| temperature maintained with adequate margin to the boiling point. In |
| addition, adequate procedural guidance existed to assure that the design |
| objectives would have been satisfied. Thus the event was not reportable." |
| |
| The licensee will inform the NRC resident inspector of this retraction. |
| Notified R1DO (Doerflein). |
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|General Information or Other |Event Number: 35879 |
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| REP ORG: ABB COMBUSTION ENGINEERING |NOTIFICATION DATE: 06/29/1999|
|LICENSEE: ABB COMBUSTION ENGINEERING |NOTIFICATION TIME: 16:28[EDT]|
| CITY: WINDSOR REGION: 1 |EVENT DATE: 06/29/1999|
| COUNTY: STATE: CT |EVENT TIME: [EDT]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 06/29/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |LAWRENCE DOERFLEIN R1 |
| |JAMES CREED R3 |
+------------------------------------------------+LINDA SMITH R4 |
| NRC NOTIFIED BY: IAN RICKARD (VIA FAX) |VERN HODGE (via fax) NRR |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| 10 CFR PART 21 REPORT DUE TO DEFECTIVE OSCILLATION POWER RANGE MONITORS |
| |
| The following text has been excerpted from a letter submitted via facsimile |
| from the vendor: |
| |
| "The defect concerns the ABB Oscillation Power Range Monitor (OPRM) |
| delivered to Susquehanna 1 & 2, Clinton, Hope Creek, WNP-2, Perry, LaSalle 1 |
| & 2, Dresden 2 & 3 and Quad Cities 1 & 2. Specifically, the defect concerns |
| the Slave OPRM module randomly resetting, potentially causing the OPRM trip |
| channel to be out of service for a short period of time, typically under one |
| minute. The defect could lead to non-conservative failure of detecting and |
| suppressing thermo-hydraulic core oscillations during this time. |
| |
| "None of the OPRM systems are presently being used to detect and suppress |
| core oscillations. Installed OPRM systems are in the monitor mode with the |
| trip contacts disabled." |
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