Event Notification Report for November 4, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
11/03/1999 - 11/04/1999
** EVENT NUMBERS **
36303 36385 36390 36391 36392 36393
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36303 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 10/17/1999|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 14:24[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 10/17/1999|
+------------------------------------------------+EVENT TIME: 13:32[EDT]|
| NRC NOTIFIED BY: ED HYNE |LAST UPDATE DATE: 11/03/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES NOGGLE R1 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| INTEGRATED LEAK TEST FAILURE IN THE REACTOR BUILDING CLOSED COOLING WATER |
| SYSTEM |
| |
| "Failure of IST [Integrated System Test] testing for RBCLC [reactor building |
| closed loop cooling] containment isolation AOVs resulted in performance of |
| 'as-found' Type-C LLRT. Results of local leak test was 'gross' failure. |
| The failure was determined from inability to obtain test pressure and |
| quantify leakage. Based on these results, it is assumed Tech Spec allowable |
| containment leakage has been exceeded." |
| |
| The plant will remain shutdown until repairs are made. |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| * * * UPDATE AT 1422 ON 11/03/99 BY MARK ABRANSKI TO JOLLIFFE * * * |
| |
| The licensee desires to retract this event for the following rational: |
| |
| The RBCLC piping forms a closed loop inside containment which serves as a |
| redundant containment isolation barrier in the event an RBCLC containment |
| isolation valve fails. Therefore, it need not be assumed that Tech Spec |
| allowable leakage had been exceeded as reported above. |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| The NRC Operations Officer notified the R1DO Mohamed Shanbaky. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36385 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALISADES REGION: 3 |NOTIFICATION DATE: 11/02/1999|
| UNIT: [1] [] [] STATE: MI |NOTIFICATION TIME: 11:45[EST]|
| RXTYPE: [1] CE |EVENT DATE: 11/02/1999|
+------------------------------------------------+EVENT TIME: 09:00[EST]|
| NRC NOTIFIED BY: BOB VINCENT |LAST UPDATE DATE: 11/03/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES CREED 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - INDICATIONS DISCOVERED ON CONTROL ROD DRIVE SEAL HOUSINGS - |
| |
| At 0900 on 11/02/99, a dye penetrant (PT) examination of the control rod |
| drive seal housing for control rod #44 revealed a potential crack-like |
| indication in the Reactor Coolant System pressure boundary. The PT |
| examination was performed to investigate a boric acid deposit on the |
| exterior surface of the housing which was discovered during a previous |
| visual inspection. A small indication was also found on the seal housing |
| for control rod #30. The plant is in a refueling outage. An investigation |
| to characterize the indications and determine their cause and extent is in |
| progress. This situation will be resolved prior to plant restart. |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| * * * UPDATE AT 1432 ON 11/03/99 BY HUGH NIXON TO JOLLIFFE * * * |
| |
| At 1215 on 11/03/99, a PT examination revealed a circumferential indication |
| on the seal housing for control rod #26. |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| The NRC Operations Officer notified the R3DO Jim Creed. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36390 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 11/03/1999|
| UNIT: [2] [] [] STATE: NY |NOTIFICATION TIME: 13:10[EST]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 11/03/1999|
+------------------------------------------------+EVENT TIME: 13:00[EST]|
| NRC NOTIFIED BY: JOHN LAMB |LAST UPDATE DATE: 11/03/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MOHAMED SHANBAKY 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 N Y 99 Power Operation |99 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - FOUR OF SIXTEEN OFFSITE EMERGENCY SIRENS INOPERABLE AND BEING REPAIRED - |
| |
| Four of 16 offsite emergency sirens in Harriman State Park, Orange County, |
| NY, are inoperable due to the loss of an electrical line to the park during |
| a thunderstorm. The line is being repaired. |
| |
| The licensee plans to notify the NRC Resident Inspector. |
| |
| Refer to identical Event #36391 for Unit 3. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36391 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 11/03/1999|
| UNIT: [] [3] [] STATE: NY |NOTIFICATION TIME: 13:51[EST]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 11/03/1999|
+------------------------------------------------+EVENT TIME: 13:15[EST]|
| NRC NOTIFIED BY: STEVE DAVIS |LAST UPDATE DATE: 11/03/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MOHAMED SHANBAKY 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|3 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - FOUR OF SIXTEEN OFFSITE EMERGENCY SIRENS INOPERABLE AND BEING REPAIRED - |
| |
| Four of 16 offsite emergency sirens in Harriman State Park, Orange County, |
| NY, are inoperable due to the loss of an electrical line to the park during |
| a thunderstorm. The line is being repaired. |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| Refer to identical Event # 36390 for Unit 2. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36392 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 11/03/1999|
| UNIT: [] [] [3] STATE: SC |NOTIFICATION TIME: 15:09[EST]|
| RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-L|EVENT DATE: 11/03/1999|
+------------------------------------------------+EVENT TIME: 02:30[EST]|
| NRC NOTIFIED BY: RANDY TODD |LAST UPDATE DATE: 11/03/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |AL BELISLE R2 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| - Low Pressure Injection System removed from Engineered Safeguards alignment |
| due to erroneous procedure - |
| |
| At 0230 on 11/03/99, both trains of the Low Pressure Injection (LPI) System |
| were removed from their normal Engineered Safeguards (ES) alignment due to |
| an erroneous procedure. Approximately 20 minutes later, the proper ES |
| alignment was restored after the operators questioned the valve position |
| specified by the procedure. |
| |
| Although this event was terminated at approximately 0250 on 11/03/99, the |
| potential impact on system operability remained in question. Engineering |
| was notified and began evaluating operability. This included discussions |
| with Operations as to expected actions, alarm responses, etc. It was |
| concluded that operability could not be assured without a detailed analysis. |
| At 1330 on 11/03/99, Engineering and Operations concluded that there was no |
| longer "reasonable expectation" of past operability. Pending the results of |
| a full evaluation by Engineering, Duke Power decided that this was |
| potentially a "Condition that alone could have prevented the fulfillment of |
| the safety function...to...mitigate the consequences of an accident." |
| Therefore, this event is considered reportable. |
| |
| Impact on Postulated Accident: |
| The valves that were opened were #3LP-92 and #3LP-93, the train 'A' and 'B' |
| Decay Heat Cooler Bypass Valves. As a result of the alignment, flow |
| immediately after an accident could have been higher than expected. This |
| could affect the available NPSH to the LPI and Reactor Building Spray (RBS) |
| System pumps. Per the Emergency Operating Procedure, operators would have |
| throttled the cooler outlet valves to establish the desired total flow. |
| |
| Later in the scenario, the Borated Water Storage Tank inventory would be |
| depleted and operators would realign the LPI and RBS suctions to the Reactor |
| Building Emergency Sump. Also, Low Pressure Service Water would be aligned |
| to the decay heat coolers to cool the sump water. With #3LP-92 and #3LP-93 |
| open, a large portion of the LPI System flow would bypass the coolers, |
| resulting in cooling flow at higher temperatures than expected. Inadequate |
| core cooling might result until the inappropriate alignment could be |
| diagnosed and corrected. |
| |
| Cause: |
| Operators were performing a periodic procedure "Tech Spec Flow Path |
| Verification" which had recently been changed to include additional valves. |
| They repositioned two of the newly added valves to "OPEN" as directed by the |
| procedure. Subsequently, they questioned this action and verified from |
| other procedures that the proper position for these valves is "CLOSED". The |
| valves were reclosed within approximately 20 minutes. |
| |
| The root cause for the inaccurate procedure change will be investigated. |
| |
| Corrective action: |
| The proper positions of the valves were questioned and the valves were |
| returned to the original positions, thus ending the event. |
| |
| Because the impact on operability of the affected systems was not |
| immediately apparent, and it did not become apparent until well after the |
| termination of the event, no Tech Spec Action Statements were entered. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36393 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 11/03/1999|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 17:02[EST]|
| RXTYPE: [1] GE-3 |EVENT DATE: 10/19/1999|
+------------------------------------------------+EVENT TIME: 17:20[CDT]|
| NRC NOTIFIED BY: DUANE BISTODEAU |LAST UPDATE DATE: 11/03/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES CREED R3 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| - REACTOR CORE ISOLATION COOLING SYSTEM INOPERABLE FOR EIGHT DAYS - |
| |
| At 1720 CDT on 10/19/99, the Reactor Core Isolation Cooling (RCIC) System |
| was removed from service for a surveillance test and corrective maintenance. |
| During post maintenance testing following corrective maintenance, a problem |
| was identified that may have made the RCIC System inoperable. Subsequently, |
| the RCIC System was repaired, tested, returned to service and operable |
| status at 0135 CDT on 10/27/99. This event was originally determined to be |
| not reportable to the NRC. However, at 1500 CST on 11/03/99, plant |
| management decided to report this event to the NRC. |
| |
| The licensee notified the NRC Resident Inspector. |
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Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021