Event Notification Report for August 22, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
08/21/2000 - 08/22/2000
** EVENT NUMBERS **
37208 37235 37241 37242 37243 37244 37245
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 37208 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 08/05/2000|
| UNIT: [] [2] [] STATE: NC |NOTIFICATION TIME: 08:07[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 08/05/2000|
+------------------------------------------------+EVENT TIME: 04:28[EDT]|
| NRC NOTIFIED BY: STUART BYRD |LAST UPDATE DATE: 08/21/2000|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GEORGE BELISLE R2 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| DISCOVERY OF A MINIMAL AMOUNT OF WATER IN THE REACTOR CORE ISOLATION COOLING |
| OIL SYSTEM |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "EVENT: The Unit 2 the Reactor Core Isolation Cooling (RCIC) system was |
| discovered to have a minimal amount of water in the oil system. Following |
| investigation of the event and replacement of the oil, the RCIC turbine was |
| successfully manually started and operated normally. During a subsequent |
| automatic start for post-maintenance test requirements, the turbine tripped |
| on high exhaust pressure apparently caused by the governor system's slow |
| response time. Investigation of the turbine control system is continuing." |
| |
| "CORRECTIVE ACTION(S): Continue the investigation to determine the root |
| cause of the water in the oil system and the response of the governor |
| control system." |
| |
| "INITIAL SAFETY SIGNIFICANCE EVALUATION: Minimal. The High Pressure |
| Coolant Injection System, Automatic [Depressurization] System, Low Pressure |
| Core Spray, and the Low Pressure Coolant Injection System were operable |
| throughout the event." |
| |
| The licensee stated that, as a result of this issue, the unit is currently |
| in a 14-day limiting condition for operation in accordance with Technical |
| Specification 3.5.2. The licensee also stated that all other systems |
| functioned as required. |
| |
| The licensee notified the NRC resident inspector. |
| |
| |
| * * * UPDATE ON 8/21/00 @ 1050 BY ELBERFELD TO GOULD * * * RETRACTION |
| |
| Upon further investigation, it has been determined that the condition |
| resulting in the RCIC turbine trip developed during the period of time that |
| the system was inoperable for maintenance, and that there was no loss of |
| safety function. |
| |
| After the notification was made it was determined that the trip of the RCIC |
| turbine was caused by the presence of air in the control system for the |
| governor valve positioning servo. The presence of air delayed the closing of |
| the governor valve during the RCIC turbine start sequence, allowing the |
| turbine speed to increase, thus increasing turbine exhaust pressure above |
| the trip setpoint. The presence of air was introduced by the maintenance |
| activities associated with changing the turbine lube oil. An acknowledged |
| industry expert was consulted and confirmed that one controlled manual start |
| would not be considered adequate to remove air from the governor control |
| system even with a substantial run duration. Experience has shown that |
| multiple starts, at least 2 to 3 governor valve strokes, may be needed to |
| remove the air that can cause abnormal turbine starts. |
| |
| Review of the "as found" condition of the RCIC system and the RCIC system |
| performance before and after the turbine trip indicates that the RCIC system |
| would have successfully performed its intended functions prior to being |
| taken out of service for maintenance on August 4, 2000. This is based on |
| the following. |
| |
| * The system quick started and ran successfully on August 2, 2000, prior to |
| the oil sample being taken that contained the water. |
| * The presence of water in the lube oil did not cause the turbine trip and |
| did not have an adverse impact on short-term system operability. |
| * Both turbine trips during the quick-starts were the result of minimal |
| governor valve stroking after the lube oil changes introduced air into the |
| governor valve control system. |
| * The RCIC turbine was able to achieve a quick-start without tripping, |
| during the performance of OPT-10.1.1 on August 7, 2000, after the governor |
| valve had been stroked twice (i.e., the controlled manual start and a failed |
| quick-start). |
| |
| This event is being retracted by the licensee. |
| |
| The NRC Resident Inspector was notified by the licensee. The R2DO (Paul |
| Fredrickson) was notified by the NRC Operations Officer. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37235 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 08/17/2000|
| UNIT: [1] [2] [] STATE: MN |NOTIFICATION TIME: 13:34[EDT]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 08/16/2000|
+------------------------------------------------+EVENT TIME: 11:15[CDT]|
| NRC NOTIFIED BY: BRAD ELLISON |LAST UPDATE DATE: 08/21/2000|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN JACOBSON R3 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION REGARDING A LARGE FISH KILL |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "[The] decision was made today (08/17/00) at 1130 [CDT] to notify offsite |
| agencies concerning a large fish kill at Prairie Island. This [was the] |
| result of the planned zebra mussel treatment that was taking place at the |
| plant." |
| |
| The licensee stated that the event occurred on 08/16/00 and that the fish |
| kill involved approximately 7,500 young fish (mainly catfish and minnows |
| approximately 2" to 5" in length). The majority of these fish were |
| discovered in the plant's recycle canal. However, a few dead fish were also |
| found in the Mississippi River. |
| |
| The licensee notified both the state and Goodhue County. The licensee also |
| plans to notify the NRC resident inspector. In addition, a press release |
| may be issued because this may be a media sensitive event. |
| |
| * * * UPDATE 1145EDT 8/21/00 FROM BILL MATHER TO S. SANDIN * * * |
| |
| The licensee is correcting this report to read that 75,000 young fish were |
| killed. The licensee informed the NRC resident inspector. Notified |
| R3DO(Hiland). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37241 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 08/21/2000|
| UNIT: [1] [] [] STATE: TX |NOTIFICATION TIME: 12:30[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/21/2000|
+------------------------------------------------+EVENT TIME: 06:45[CDT]|
| NRC NOTIFIED BY: MIKE SCHAEFER |LAST UPDATE DATE: 08/21/2000|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |LARRY YANDELL R4 |
|10 CFR SECTION: | |
|NLCO TECH SPEC LCO A/S | |
|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
+------------------------------------------------------------------------------+
| - 2 OF 3 TRAINS OF ESSENTIAL CHILLED WATER SYSTEM INOPERABLE; TECH SPEC |
| 3.0.3 ENTERED - |
| |
| At 0645 CDT on 08/21/00 with the 'C' train Essential Chilled Water System |
| inoperable for maintenance activities, the 'A' train Essential Chilled Water |
| System became inoperable due to an oil leak. This condition of two trains of |
| the Essential Chilled Water System being inoperable is not allowed by |
| Technical Specification 3.7.14 and required entry into Technical |
| Specification 3.0.3. No maintenance work had yet been performed on the 'C' |
| train Essential Chilled Water System. At 0754 CDT on 02/21/00, the licensee |
| released the equipment clearance tags and restored the 'C' train Essential |
| Chilled Water System to operable status and exited Technical Specification |
| 3.0.3. |
| |
| This event is reportable to the NRC in accordance with the requirements of |
| 2G of the South Texas Project's Operating License to notify the NRC within |
| 24 hours of any violation of Technical Specifications. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37242 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 08/21/2000|
| UNIT: [1] [2] [] STATE: MN |NOTIFICATION TIME: 14:54[EDT]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 08/21/2000|
+------------------------------------------------+EVENT TIME: 13:15[CDT]|
| NRC NOTIFIED BY: BILL MATHER |LAST UPDATE DATE: 08/21/2000|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |PATRICK HILAND 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
+------------------------------------------------------------------------------+
| - WESTINGHOUSE ANALYSIS OF UNBORATED SFP NOT WITHIN NRC APPROVED DESIGN |
| CRITERIA - |
| |
| Westinghouse has notified the Prairie Island Nuclear Plant that the analysis |
| for the Spent Fuel Pool (SFP) with zero boron concentration is not within |
| the NRC approved design criteria. The current NRC approved analysis for |
| unborated water in the SFP states that the Keff should be less than 1.0. |
| The Westinghouse analysis assumed a nominal fuel pellet density lower than |
| the as-fabricated density. This results in a Keff of 1.00086 in an |
| unborated SFP. |
| |
| Westinghouse reanalyzed the condition using a methodology that takes credit |
| for the effect of spacer grids and spacer sleeves. With this factor, the |
| analysis concludes that Keff in an unborated SFP would be less than 1.01; |
| however, this change to the methodology has not been approved by the NRC. |
| |
| The approved analysis includes a case that takes credit for 750 ppm borated |
| water. Westinghouse has reevaluated this case using higher density fuel |
| pellets and concluded the acceptance criteria (Keff < 0.95) is still met. |
| |
| Prairie Island Plant Technical Specifications require the SFP boron |
| concentration to be greater than 1800 ppm. Current SFP boron concentration |
| is 3210 ppm. Additional compensatory measures are being evaluated. |
| |
| Reference: Tech Specs 3.8.E.2.a and 5.6.A.1.b. |
| |
| The licensee notified state and local officials and the NRC Resident |
| Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37243 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: KEWAUNEE REGION: 3 |NOTIFICATION DATE: 08/21/2000|
| UNIT: [1] [] [] STATE: WI |NOTIFICATION TIME: 15:52[EDT]|
| RXTYPE: [1] W-2-LP |EVENT DATE: 08/21/2000|
+------------------------------------------------+EVENT TIME: 14:15[CDT]|
| NRC NOTIFIED BY: ROY SCOTT |LAST UPDATE DATE: 08/21/2000|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |PATRICK HILAND R3 |
|10 CFR SECTION: | |
|AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 96 Power Operation |96 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - 3 OF 3 AFW PUMPS INOPERABLE DUE TO UNDERSIZED PUMP SUCTION STRAINERS - |
| |
| During an inspection of the 'A' Auxiliary Feedwater (AFW) pump, the licensee |
| observed that the length and hole size of the pump suction strainer were |
| different than those assumed in a previous operability determination. The |
| installed pump strainer is approximately 10 inches long and has 1/16 inch |
| diameter holes. The operability determination assumed a 6 inch long |
| strainer with 1/8 inch diameter holes. The licensee could not determine |
| whether the smaller strainer would plug and therefore, declared the 'A' AFW |
| pump inoperable. The licensee inspected the suction strainers of the 'B' |
| and 'C' AFW pumps and determined that their suction strainers may be |
| identical to the 'A' AFW pump strainer and therefore, declared the 'B' and |
| 'C' AFW pumps inoperable. With 3 of 3 AFW pumps inoperable, plant tech |
| specs prohibit the licensee from changing plant operating modes. |
| |
| The licensee plans to remove the suction strainers from all 3 AFW pumps. |
| With the 'A' AFW pump strainer removed and the 'A' AFW pump declared |
| operable, the plant will be in a 4-hour shutdown LCO with the other AFW |
| pumps inoperable. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37244 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 08/21/2000|
| UNIT: [1] [] [] STATE: LA |NOTIFICATION TIME: 17:53[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 08/21/2000|
+------------------------------------------------+EVENT TIME: 15:31[CDT]|
| NRC NOTIFIED BY: MARK BROWNING |LAST UPDATE DATE: 08/21/2000|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |WILLIAM JOHNSON R4 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 M/R Y 100 Power Operation |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - MANUAL REACTOR SCRAM FROM 100% POWER DUE TO REDUCED MAIN CONDENSER VACUUM |
| - |
| |
| At 1531(CDT) on 08/21/00 with the plant in Operational Condition 1 at 100% |
| power, the operating crew inserted a manual reactor scram signal due to the |
| inability to maintain main condenser vacuum greater than 25 inches Hg. |
| Prior to this condition, the operating crew was responding to a low flow |
| condition in the in-service offgas system train in accordance with alarm |
| response procedures. While admitting air to the offgas system train as |
| directed, a low main condenser vacuum condition occurred, requiring the |
| operators to insert a manual reactor scram signal. All control rods |
| inserted completely. No safety/relief valves lifted. Steam is being dumped |
| to the main condenser. |
| |
| Subsequent to the reactor scram, a reactor vessel low water level 3 signal |
| was received, as expected, which resulted in an ESF isolation of the |
| suppression pool cooling system. The suppression pool cooling system was in |
| the suppression pool cooling mode at the time of the isolation. The reactor |
| vessel water level has been restored to its normal level. Following the |
| reactor scram, all systems functioned as expected. The plant is stable in |
| Operational Condition 3 (Hot Shutdown). |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37245 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 08/21/2000|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 19:33[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 08/21/2000|
+------------------------------------------------+EVENT TIME: 18:00[EDT]|
| NRC NOTIFIED BY: KERRY ALLEN |LAST UPDATE DATE: 08/22/2000|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHRISTOPHER CAHILL R1 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION REGARDING OIL SPILL ONSITE |
| |
| "Oil was discovered covering the gravel over an approximate 1 meter diameter |
| area. The area was located under vent pipe for the main turbine generator |
| air detraining tank on the turbine building roof." |
| |
| The NRC resident inspector will be notified by the licensee. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021