Event Notification Report for March 26, 2001
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
03/23/2001 - 03/26/2001
** EVENT NUMBERS **
37682 37684 37779 37799 37809 37844 37861 37862 37863 37864
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37682 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 01/24/2001|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 07:36[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 01/23/2001|
+------------------------------------------------+EVENT TIME: 07:25[EST]|
| NRC NOTIFIED BY: ABRAMSKI |LAST UPDATE DATE: 03/23/2001|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: |STEVEN DENNIS R1 |
|10 CFR SECTION: | |
|*INB 50.72(b)(3)(v)(B) POT RHR INOP | |
|*IND 50.72(b)(3)(v)(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
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION SYSTEM DECLARED INOPERABLE. |
| |
| The flow controller for the High Pressure Coolant Injection (HPCI) system is |
| indicating approximately 1400 gpm with the HPCI system in the standby |
| condition. Because the cause of this condition is not known at this time, |
| the HPCI system is considered inoperable. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
| |
| * * * RETRACTED AT 1528 EST ON 3/23/01 BY MARK ABRAMSKI TO FANGIE JONES * * |
| * |
| |
| "Engineering evaluation subsequent to this event has determined that the |
| HPCI system would have performed its' intended function as credited in the |
| LOCA analysis and therefore this 10 CFR 50.72 notification is retracted." |
| |
| The licensee notified the NRC Resident Inspector. The R1DO (Kenneth |
| Jenison) has been notified. |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37684 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 01/25/2001|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 06:53[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 01/25/2001|
+------------------------------------------------+EVENT TIME: 02:47[EST]|
| NRC NOTIFIED BY: M ADRAMSKI |LAST UPDATE DATE: 03/23/2001|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |STEVEN DENNIS R1 |
|10 CFR SECTION: | |
|*INB 50.72(b)(3)(v)(B) POT RHR INOP | |
|*IND 50.72(b)(3)(v)(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
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION (HPCI) DECLARED INOPERABLE. |
| |
| At 0247 ET on 01/25/01, the flow transmitter controller for HPCI system |
| spiked from zero to approximately 1500 gpm. The HPCI system was in standby |
| lineup at the time. The flow indication has been slowly drifting down. |
| |
| A similar event occurred on 01/23/01 at 0725ET. HPCI was declared |
| inoperable. The flow transmitter, 23FT-82, and flow switch, 23FS-78, were |
| vented and a small amount of air was noted. The flow indication returned to |
| zero (normal standby indication). After a HPCI operability surveillance |
| test, HPCI was declared operable at 1332 ET on 01/24/01. |
| |
| After the second flow indication perturbation on 01/25/01, HPCI was again |
| declared inoperable with an LCO start date of 01/23/01 at 0725 ET (7 days to |
| returned HPCI to operable status). The cause of this condition is still |
| under investigation. All other systems are operable. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
| |
| * * * RETRACTED AT 1528 EST ON 3/23/01 BY MARK ABRAMSKI TO FANGIE JONES * * |
| * |
| |
| "Engineering evaluation subsequent to this event has determined that the |
| HPCI system would have performed its' intended function as credited in the |
| LOCA analysis and therefore this 10 CFR 50.72 notification is retracted." |
| |
| The licensee notified the NRC Resident Inspector. The R1DO (Kenneth |
| Jenison) has been notified. |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37779 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 02/24/2001|
| UNIT: [] [] [3] STATE: CT |NOTIFICATION TIME: 03:24[EST]|
| RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 02/24/2001|
+------------------------------------------------+EVENT TIME: 03:06[EST]|
| NRC NOTIFIED BY: RAY MARTIN |LAST UPDATE DATE: 03/25/2001|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GLENN MEYER R1 |
|10 CFR SECTION: | |
|DDDD 73.71 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
| | |
|3 N N 0 Refueling |0 Refueling |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SAFEGUARDS DEGRADATION RELATED TO AREA BOUNDARY |
| |
| IMMEDIATE COMPENSATORY ACTIONS TAKEN UPON DISCOVERY |
| |
| THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. ADDITIONAL DETAILS MAY |
| BE OBTAINED FROM THE OPERATIONS CENTER. |
| |
| * * * RETRACTED AT 2121 EST ON 3/25/01 BY RAY MARTIN TO FANGIE JONES * * * |
| |
| The licensee is retracting this event based on reportability evaluation. |
| Additional details may be obtained from the operations center. |
| |
| The licensee intends to notify the NRC Resident Inspector. The R1DO |
| (Kenneth Jenison) was informed. |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37799 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 03/02/2001|
| UNIT: [1] [] [] STATE: MA |NOTIFICATION TIME: 10:10[EST]|
| RXTYPE: [1] GE-3 |EVENT DATE: 03/02/2001|
+------------------------------------------------+EVENT TIME: 05:30[EST]|
| NRC NOTIFIED BY: KENNEDY |LAST UPDATE DATE: 03/23/2001|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |RICHARD CONTE R1 |
|10 CFR SECTION: | |
|*IND 50.72(b)(3)(v)(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
+------------------------------------------------------------------------------+
| PLANT DECLARED RCIC INOPERABLE. |
| |
| During a panel walkdown, it was discovered that the RCIC flow controller |
| setpoint pointer was indicating erratically. Therefore, the flow controller |
| was declared inoperable resulting in RCIC being declared inoperable. |
| Troubleshooting is currently being performed on the controller. This |
| condition put the plant in a 14-day LCO action statement. |
| |
| The NRC Resident Inspector will be notified. |
| |
| * * * UPDATE 1055EST ON 3/23/2001 FROM ERIC OLSON TO S. SANDIN * * * |
| |
| The licensee is retracting this report based on the following: |
| |
| "During a control room tour on Friday, March 2, 2001, the output of the |
| reactor core isolation cooling system (RCIC) controller FIC-1340-1 was |
| observed oscillating between downscale (-value) up to approximately +2% as |
| indicated on the output demand meter. Initial testing measured voltages at |
| the input test terminals and found a steady flow signal applied to the |
| controller. Voltage measurements taken at the output test jacks found the |
| output oscillating between 9 to 11 milliamps, consistent with the |
| oscillation of 2% on the demand meter. In an effort to help pinpoint the |
| source of this problem, the set-point tape was adjusted down to the minimum |
| value allowing the deviation meter to come on scale (� 10% measuring the |
| signal error between flow input and set-point). In this mode, oscillation of |
| the deviation meter was observed, consistent with demand. The controller was |
| then taken to manual and the output demand meter became stable. These two |
| simple functional checks suggested the source of oscillation was limited to |
| the automatic control circuitry of the GEMAC controller, based on the stable |
| voltage measurement at the controllers input and the stable output when |
| placed in manual. The most probable cause for the oscillation would be |
| weak/aging power supply capacitors used in the controller's automatic |
| circuitry. |
| |
| "The RCIC system was declared inoperable and the NRC was notified at 1010 on |
| March 2, 2001 in accordance with 10CFR50.72(b)(3)(v) based on the belief |
| that the controller was not operable. |
| |
| "Troubleshooting was performed and it was decided to replace the controller |
| with the identical controller from the RCIC alternate shutdown panel (ASP). |
| RCIC was then tested using procedure 8.5.5.1 with satisfactory results. The |
| controller that had been removed from the RCIC panel was bench tested and |
| the results indicated that the controller would have allowed the RCIC system |
| to reach a stable rated 400 gpm flow control. |
| |
| "On Friday March 9, 2001, the controller from the alternate shutdown panel |
| was also noted to be oscillating about the '0' position, repeating the |
| condition described in PR01.9190. Problem report PR01.9210 was written to |
| describe this similar condition. It was concluded that the RCIC test could |
| be performed with the controller exhibiting some oscillation. The test |
| results demonstrated that the controller and therefore, RCIC was operable. |
| Further troubleshooting is in progress to determine the cause of the |
| oscillations. One possibility is that the source of the oscillations has to |
| do with equipment grounding and other equipment tests occurring on Fridays. |
| Further investigation is in progress. |
| |
| "The reporting criteria of 10 CFR 50.73 were evaluated as follows; |
| |
| "For (a)(2)(v); not reportable. The initial observation on Friday, March 2, |
| 2000, of oscillations on FIC-1340-1 indicated that the individual controller |
| was inoperable and needed maintenance. The controller was replaced with the |
| identical controller from the alternate shutdown panel (ASP). The newly |
| installed controller was tested and RCIC was verified to be operable. Bench |
| testing of the removed controller indicated that it would have performed its |
| safety function. A similar oscillation was noted on the new controller on |
| Friday March 9, 2001. RCIC was tested even though the controller appeared to |
| be oscillating. The testing verified the operability of the installed |
| controller and confirmed the conclusion that the original controller would |
| have been operable. Since the original controller would have been operable, |
| the observed oscillations could not have prevented the fulfillment of the |
| RCIC safety function and therefore, is not a reportable condition. |
| |
| "It is recommended that the 10 CFR 50.72 notification made on March 2, 2001 |
| be retracted." |
| |
| The licensee informed the NRC resident inspector. Notified R1DO(Jenison). |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37809 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 03/05/2001|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 17:56[EST]|
| RXTYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 03/05/2001|
+------------------------------------------------+EVENT TIME: 16:00[EST]|
| NRC NOTIFIED BY: K BELDEN |LAST UPDATE DATE: 03/23/2001|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |RICHARD CONTE R1 |
|10 CFR SECTION: | |
|*IND 50.72(b)(3)(v)(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
+------------------------------------------------------------------------------+
| CONTROL ROOM EMERGENCY VENTILATION DECLARED INOPERABLE. |
| |
| Control Room Emergency Ventilation was declared inoperable at 1600 hours. |
| This was a result of the Lab carbon sample analysis not meeting Technical |
| Specification 3.4.5.c of greater than 90% radioactive methyl iodine |
| removal capability when tested. This required entering into a 7 day |
| shutdown Limiting Condition for Operation. Carbon sample analysis is |
| required per Technical Specification to be performed once per cycle (2 |
| years). Licensee is in the process of replacing the carbon. |
| |
| The NRC Resident Inspector was notified of this event. |
| |
| * * * RETRACTED AT 1411 EST ON 3/23/01 BY JOHN PARRISH TO FANGIE JONES * * |
| * |
| |
| After further testing and calculations it was determined that the value was |
| above the technical specification requirements and the event was not |
| reportable and retracts the event notification. |
| |
| The licensee intends to notify the NRC Resident Inspector. The R1DO |
| (Kenneth Jenison) has been informed. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 37844 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 03/17/2001|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 10:55[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 03/16/2001|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 11:00[EST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 03/23/2001|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |GEOFFREY WRIGHT R3 |
| DOCKET: 0707002 |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: SPAETH | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 24 HOUR 91-01 BULLETIN - GEOMETRY VIOLATION |
| |
| At 1100 on 3/16/01, a seal test buggy was found without signs or tags as |
| required by NCSA-PLANT_031 (Potable Sampling/Test Buggies and Carts). Upon |
| investigation of the test buggy, the chemical trap was found to have a |
| nominal diameter of four inches and a length of twenty two inches. The four |
| inch diameter violates the passive design control 2(b) which requires a |
| three inch nominal diameter and a thirty three inch length. Nuclear |
| Criticality personnel have determined the maximum loading of the effected |
| trap to be 76 gram U-235 at 3% assay. 76 grams is lower than the 350 gram |
| safe mass limit. The NCSE contingency analysis considers credible, a |
| maximum five inch nominal diameter to remain subcritical. |
| |
| SAFETY SIGNIFICANCE OF EVENTS: |
| |
| Safety significance is considered very low. The NCSA requirement is three, |
| three inch nominal diameter chemical traps. However, the NCSE allows for |
| three, five inch nominal diameter chemical traps and remain subcritical, |
| |
| POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO[S] OF HOW |
| CRITICALITY COULD OCCUR): |
| |
| Based on the bounding calculations for five inch diameter chemical traps, |
| there no critical pathways involved |
| |
| CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.): |
| |
| Geometry is the controlled parameter that was violated |
| |
| ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS |
| LIMIT AND % WORST CASE OF CRITICAL MASS): |
| |
| The amount of uranium is unknown, however, it is not expected to be above |
| 350 grams U-235 due to the operation performed with this buggy and the fact |
| that the maximum loading of a 4" X 22" chemical trap is only 76 grams U-235 |
| at 3% assay. |
| |
| NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION |
| OF THE FAILURES OR DEFICIENCIES |
| |
| The control violated was the geometry control of the chemical trap. The |
| chemical trap was required to be three inch schedule 40 pipe, but it was |
| found to be a nominal four inch diameter pipe. |
| |
| CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN EACH WAS IMPLEMENTED; |
| |
| The test buggy was posted with temporary signs as required by |
| NCSA-PLANT_031. The buggy will remain in the anomalous condition boundary |
| until NDA results are obtained. Disposition of the buggy will be determined |
| based on the NDA results. |
| |
| The NRC Resident Inspector was notified. The DOE Representative will be |
| informed. |
| |
| * * * UPDATE AT 1346 EST ON 3/23/01 BY JIM McCLEARY TO FANGIE JONES * * * |
| |
| "NDA measurements show the chemical trap described above contains 1.6 +/- |
| 0.8 grams and the pump contains 1 gram of U-235. Total U-235 content |
| including error is 3.4 grams U-235. TSR 3.11.2 requires an NSCE for |
| operations with uranium enriched to 1 wt% and contains 15 grams or higher |
| U-235. Therefore this buggy is not a fissile material operation and not a |
| violation of NCSA-PLANT_031." |
| |
| The licensee notified the NRC Resident Inspector and the DOE representative. |
| The R3DO (Gary Shear) and NMSS EO (Brian Smith) were notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 37861 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: CALIFORNIA RADIATION CONTROL PRGM |NOTIFICATION DATE: 03/23/2001|
|LICENSEE: TWINING LABS |NOTIFICATION TIME: 19:02[EST]|
| CITY: FRESNO REGION: 4 |EVENT DATE: 03/16/2001|
| COUNTY: STATE: CA |EVENT TIME: 07:00[PST]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 03/23/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JOHN PELLET R4 |
| |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: ROBERT GREGGER | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| STOLEN MOISTURE DENSITY GAUGE |
| |
| The Twining Labs reported a stolen Troxler moisture density gauge, Model |
| 3430, serial # 20467. The sources are nominal 30 millicuries of Cs-137 and |
| 10 millicuries Am-241/Be. The local police were notified (police report # |
| 01-23615) and a reward was posted for the return. The theft occurred on |
| 3/16/01 about 0700 PST. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37862 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COLUMBIA GENERATING STATIREGION: 4 |NOTIFICATION DATE: 03/24/2001|
| UNIT: [2] [] [] STATE: WA |NOTIFICATION TIME: 08:35[EST]|
| RXTYPE: [2] GE-5 |EVENT DATE: 03/24/2001|
+------------------------------------------------+EVENT TIME: 03:08[PST]|
| NRC NOTIFIED BY: C. PERINO |LAST UPDATE DATE: 03/24/2001|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN PELLET R4 |
|10 CFR SECTION: | |
|*SHU 50.72(b)(2)(i) PLANT S/D REQD BY TS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 N Y 100 Power Operation |99 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PLANT SHUTDOWN REQUIRED BY TECHNICAL SPECIFICATIONS |
| |
| "This report is being made in accordance with 10 CFR 50.72(b)(2)(i). |
| |
| "Columbia Generating Station started a plant shutdown 03:08. At 23:15 |
| yesterday, a rise in drywell pressure was observed Coolant leakage was |
| confirmed by a rising trend in drywell particulate monitors. Upon |
| investigation, this leakage was confirmed to be due to cycling RCIC-V-63, |
| the RCIC steam supply inboard isolation valve, during the performance of a |
| Surveillance Procedure. |
| |
| "At 23:30, a rise in drywell unidentified leakage rate was observed. At |
| 01:56 an entry into Technical Specification 3.4.5.B for greater than a 2 gpm |
| rise in a 24 hour period was made. At 03:08, an entry into Technical |
| Specification 3.4.5 A was made for unidentified leakage greater than 5 gpm. |
| At this time, the decision to begin a controlled reactor shutdown was made. |
| |
| "RCIC-V-63 was backseated to terminate leakage at 03:55. At 03:58 it was |
| determined the backseating successfully stopped the leakage. The downpower |
| was terminated at 04:19. Indications of leakage are trending down. At 04:30, |
| the leakage had decreased below the Technical Specification limits and |
| reactor power was increased to 100%." |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37863 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 03/24/2001|
| UNIT: [1] [2] [] STATE: TX |NOTIFICATION TIME: 10:39[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/24/2001|
+------------------------------------------------+EVENT TIME: 00:30[CST]|
| NRC NOTIFIED BY: STEVEN SEWELL |LAST UPDATE DATE: 03/24/2001|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN PELLET R4 |
|10 CFR SECTION: | |
|*PRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 88 Power Operation |88 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION REGARDING DISCHARGE OF WATER OFFSITE |
| |
| "On 3/24/01, at 0845, a determination was made that a report to the TNRCC |
| [Texas Natural Resource Conservation Commission] is required for a discharge |
| of water to Squaw Creek Reservoir. An estimated 1000 gallons of fire |
| protection water was discharged due to a ruptured pipe in warehouse C. The |
| water contains no hazardous constituents that have assigned reportable |
| quantities; however, a report to the TNRCC will be made in accordance with |
| water quality regulations." |
| |
| The NRC resident inspector has been informed of this report by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37864 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 03/24/2001|
| UNIT: [1] [] [] STATE: AR |NOTIFICATION TIME: 19:24[EST]|
| RXTYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 03/24/2001|
+------------------------------------------------+EVENT TIME: 16:01[CST]|
| NRC NOTIFIED BY: FRED VANBUSKIRK |LAST UPDATE DATE: 03/24/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN PELLET R4 |
|10 CFR SECTION: | |
|*DEG 50.72(b)(3)(ii)(A) DEGRAD COND DURING OP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PRESSURE BOUNDARY DEGRADATION FOUND DURING TESTING AFTER SHUTDOWN |
| |
| "On March 18, 2001, following shutdown for a scheduled refueling outage, |
| Arkansas Nuclear One (ANO) Unit I performed a routine visual inspection of |
| the Reactor Vessel (RV) head area per NRC Generic Letter 88-05. This |
| inspection revealed an increase in the amount of boric acid crystals in the |
| area of one Control Rod Drive Mechanism (CRDM) nozzle over the amount that |
| had been present during the previous inspection. Results of the visual |
| inspection were inconclusive regarding the source of the leakage. No other |
| CRDM nozzle showed similar boron buildup. Prior to unit shutdown, on March |
| 16 the total unidentified Reactor Coolant System leak rate was determined to |
| be 0.087 gpm, significantly less than the 1 gpm allowed by Technical |
| Specifications. After the RV head was removed and placed on the storage |
| stand, additional inspections were conducted. At approximately 1601 on March |
| 24, 2001, eddy current and ultrasonic testing revealed an RCS pressure |
| boundary leak. Using ultrasonic test (UT) methods one crack was identified |
| in the wall of CRDM nozzle #56. The UT data indicates that the crack is on |
| the downhill side of the nozzle. It extends approximately 0.8 inches below |
| the weld and extends upward to approximately 1.0 inches above the weld. The |
| depth of the crack is approximately 0.2 inches. This crack is consistent |
| with industry experience associated with Primary Water Stress Corrosion |
| Cracking (PWSCC) in similar components that have been evaluated as part of |
| the NRC Genetic Letter 97-01 response. These cracks do not pose a |
| significant safety risk during plant operation. ANO plans to perform repairs |
| during the current outage. Since the crack resulted in leakage through the |
| Reactor Coolant System pressure boundary, this condition is being reported |
| as a non-emergency eight-hour report in accordance with 10 CFR |
| 50.72(b)(3)(ii), degradation of a principal safety barrier." |
| |
| The licensee notified the NRC Resident Inspector. |
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Page Last Reviewed/Updated Thursday, March 25, 2021