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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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|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.                 |
+------------------------------------------------------------------------------+