Event Notification Report for February 8, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
02/05/1999 - 02/08/1999
** EVENT NUMBERS **
35239 35288 35345 35346 35347 35348 35349 35350 35351 35352
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35239 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 01/11/1999|
| UNIT: [1] [] [] STATE: LA |NOTIFICATION TIME: 16:56[EST]|
| RXTYPE: [1] GE-6 |EVENT DATE: 01/11/1999|
+------------------------------------------------+EVENT TIME: 15:20[CST]|
| NRC NOTIFIED BY: RUSS GODWIN |LAST UPDATE DATE: 02/05/1999|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BLAIR SPITZBERG R4 |
|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
+------------------------------------------------------------------------------+
| NOTIFICATION TO STATE DEPARTMENT OF ENVIRONMENTAL QUALITY (Refer the event |
| #34815 for additional information.) |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "On January 11, 1999, [River Bend Station (RBS)] personnel made a report to |
| the Louisiana Department of Environmental Quality related to a potential |
| defect in fuel cladding. A previous report was made on September 21, 1998, |
| and updated on October 22, 1998. RBS personnel have continued to monitor |
| plant conditions after the first two had been suppressed. Chemistry |
| sampling and power suppression results indicate a probable third fuel |
| failure. Indications could be caused by a previously identified fuel |
| failure. |
| |
| "The plant is operating at 100% power with radioactive releases well below |
| the limits of the Technical Requirements Manual and 10 CFR [Part] 20. Plant |
| personnel continue to implement site procedures to address the issue and |
| take appropriate actions." |
| |
| The NRC resident inspector has been informed of this notification by the |
| licensee. |
| |
| * * * UPDATE AT 1507 EST ON 01/26/99 FROM JOEY CLARK TO S.SANDIN * * * |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "[At 1305 CST] on January 26, 1999, RBS personnel made a report to the |
| Louisiana Department of Environmental Quality related to a potential defect |
| in fuel cladding. [Previous reports were] made on September 21, 1998, |
| updated on October 22, 1998, and on January 11, 1999. Plant instrumentation |
| and chemistry sampling indicates RBS has three (3) apparent fuel leakers and |
| a probable fourth fuel leaker adjacent to a previously identified and |
| suppressed fuel leaker. |
| |
| "The plant is operating at 94.5% power with radioactive releases well below |
| the limits of the Technical Requirements Manual and 10 CFR [Part] 20. |
| Plant personnel continue to implement site procedures to address this issue |
| and take appropriate actions." |
| |
| The licensee informed the NRC resident inspector. The NRC operations |
| officer notified the R4DO (Marshall). |
| |
| * * * UPDATE AT 1435 EST ON 02/05/99 FROM DAN JERRELL TO JOLLIFFE * * * |
| |
| On 02/05/99, RBS personnel made a reports to the Louisiana Department of |
| Environmental Quality related to a potential defect in fuel cladding. |
| Previous report were made on 09/21/98 (updated on 10/22/98) and on 01/11/99 |
| (updated on 01/26/99). During suppression testing for the 01/26/99 update, |
| an additional probable fuel leaker was identified. Plant instrumentation |
| and chemistry sampling indicates RBS has three apparent fuel leakers and two |
| probable fuel leakers. Currently, all apparent and probable fuel leakers |
| are being suppressed. |
| |
| The plant is operating at 94% power with radioactive releases well below the |
| limits of the Technical Requirements Manual and 10 CFR Part 20. Plant |
| personnel continue to implement site procedures to address this issue and |
| take appropriate actions. |
| |
| The licensee informed the NRC resident inspector. The NRC operations |
| officer notified the R4DO (Jeff Shackelford). |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35288 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 01/21/1999|
| UNIT: [2] [] [] STATE: PA |NOTIFICATION TIME: 09:00[EST]|
| RXTYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 01/21/1999|
+------------------------------------------------+EVENT TIME: 05:02[EST]|
| NRC NOTIFIED BY: TODD STRAYER |LAST UPDATE DATE: 02/05/1999|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN KINNEMAN R1 |
|10 CFR SECTION: | |
|AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| STANDBY GAS TREATMENT SYSTEM MAY NOT HAVE PERFORMED INTENDED FUNCTION DUE TO |
| DAMPER PROBLEM. |
| |
| While preparing to replace the solenoid valve for standby gas treatment |
| (SBGT) system damper PO-20466 (reactor building supply to SBGT), the damper |
| did not open when the control room hand switch was placed in the "open" |
| position. However, the damper did open when the pneumatic supply to the |
| solenoid valve was isolated. This damper opens automatically upon a SBGT |
| system initiation to provide a flow path from the Unit 2 reactor building. |
| The SBGT system would still have had a flow path from the Unit 2 refuel |
| floor and equipment cell exhaust areas upon an initiation. In addition, the |
| Unit 2 refuel floor currently has direct communication with the Unit 2 |
| reactor building because the refuel floor equipment hatch is removed. |
| |
| The licensee reported this event because the failure of the damper to open |
| could have prevented the SBGT system from performing its intended function. |
| The licensee is performing calculations to determine whether the failure |
| would have prevented the fulfillment of the safety function. The damper is |
| currently open, and the pneumatic supply to the solenoid valve has been |
| isolated. The licensee plans to continue activities to replace the solenoid |
| valve. |
| |
| The NRC resident inspector has been informed of this notification by the |
| licensee. |
| |
| * * * RETRACTION AT 1625 ON 02/05/99 FROM DENNIS BURGARD TO JOLLIFFE * * * |
| |
| Licensee engineering personnel have performed an evaluation to determine |
| whether the failure of the reactor building isolation damper would prevent |
| the SBGT system from performing its safety function. This evaluation |
| demonstrates that the failure of the damper for reactor building area |
| ventilation to open would not prevent the SBGT system from performing its |
| required safety function. Because the design basis function was not lost, |
| the licensee desires to retract this event notification. |
| |
| The licensee informed the NRC resident inspector. The NRC operations |
| officer notified the R1DO (Julian Williams). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 35345 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: TN DIV of RADIOLOGICAL HEALTH |NOTIFICATION DATE: 02/05/1999|
|LICENSEE: ALLIED TECHNOLOGY GROUP/MMT |NOTIFICATION TIME: 12:53[EST]|
| CITY: OAK RIDGE REGION: 2 |EVENT DATE: 02/05/1999|
| COUNTY: STATE: TN |EVENT TIME: 04:30[EST]|
|LICENSE#: R-73020 AGREEMENT: Y |LAST UPDATE DATE: 02/05/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |PAUL FREDRICKSON R2 |
| |FRED COMBS, NMSS EO |
+------------------------------------------------+JOSEPH GIITTER IRO |
| NRC NOTIFIED BY: DEBRA SHULTS | |
| HQ OPS OFFICER: DICK JOLLIFFE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - STYRENE RESIN SPILLED FROM RUPTURED LINE IN ALLIED TECHNOLOGY GROUP Q-CEP |
| BUILDING - |
| |
| AT 0430 ON 02/05/99, A STAINLESS STEEL ELBOW ON THE DE-INVENTORY LINE FROM |
| THE DYNAMIC AIR SYSTEM TO THE TOP OF THE 10-FOOT DIAMETER STORAGE TANK |
| (#T106A) IN THE RESIN PREPARATION AREA OF THE ALLIED TECHNOLOGY GROUP/MMT |
| QUANTUM CATALYTIC EXTRACTION PROCESS (Q-CEP) BUILDING RUPTURED AND |
| CONTAMINATED THE Q-CEP BUILDING. THE CONTAMINATION RESULTED IN A ONE-INCH |
| LAYER OF SOLID STYRENE RESINS IN PARTS OF THE Q-CEP BUILDING WITH |
| CONTAMINATION LEVELS BETWEEN 400,000 AND 600,000 dpm. THE ISOTOPES ARE |
| MIXED FISSION PRODUCTS INCLUDING Co-60, Cs-134, AND Cs-137. THE EXACT |
| ACTIVITY IS UNKNOWN, BUT IT EXCEEDS THE LIMITS OF THE "TN STATE REGULATIONS |
| FOR PROTECTION AGAINST RADIATION" [#1200-2-5-141(2)(c)1(ii)]. THE TN |
| INCIDENT FILE NUMBER IS #TN-99-017. |
| |
| THIS FACILITY PROCESSES SPENT RESIN FROM COMMERCIAL NUCLEAR POWER PLANTS. |
| |
| CURRENT PERSONNEL RADIATION EXPOSURE DATA INDICATES THAT NO PERSONNEL |
| RECEIVED AN INHALATION EXPOSURE, THAT NO PERSONNEL WERE OVEREXPOSED, AND |
| THAT THIS EVENT DOES NOT POSE AN IMMEDIATE THREAT TO PUBLIC HEALTH AND |
| SAFETY. |
| |
| (Call the NRC Operations Center for contact telephone numbers.) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 35346 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: MA RADIATION CONTROL PROGRAM |NOTIFICATION DATE: 02/05/1999|
|LICENSEE: DuPONT PHARMACEUTICALS, INC |NOTIFICATION TIME: 16:02[EST]|
| CITY: BILLERICA REGION: 1 |EVENT DATE: 02/05/1999|
| COUNTY: STATE: MA |EVENT TIME: 15:30[EST]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 02/05/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JULIAN WILLIAMS R1 |
| |PAUL FREDRICKSON R2 |
+------------------------------------------------+JOSIE PICCONE, NMSS EO |
| NRC NOTIFIED BY: DICK FAIRFULL |JOSEPH GIITTER IRO |
| HQ OPS OFFICER: DICK JOLLIFFE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - Damaged package containing two vials of Xe-133 (20 millicuries each) at |
| FEDEX facility in Memphis, TN - |
| |
| At 1530 on 02/05/99, DuPont Pharmaceuticals, Inc., notified the |
| Massachusetts Radiation Control Program that two vials containing 20 |
| millicuries each of Xe-133 had been lost in transit from their Billerica, |
| Massachusetts, facility to a licensee in Wichita, Kansas. The damaged |
| package was discovered at the Federal Express hub facility in Memphis, |
| Tennessee. At this time, the FEDEX health physicist and safety officer are |
| conducting a search at the hub facility. DuPont Pharmaceuticals expects to |
| submit a written report to the Radiation Control Program early next week. |
| |
| The licensee reports the dose rate from an unshielded vial to be |
| approximately 250 millirem per hour per millicurie. |
| |
| (Call the NRC Operations Center for a contact telephone number.) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 35347 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: POWER RESOURCES, INC |NOTIFICATION DATE: 02/05/1999|
|LICENSEE: POWER RESOURCES, INC |NOTIFICATION TIME: 16:29[EST]|
| CITY: GLENROCK REGION: 4 |EVENT DATE: 02/05/1999|
| COUNTY: STATE: WY |EVENT TIME: 14:00[MST]|
|LICENSE#: SUA-1511 AGREEMENT: N |LAST UPDATE DATE: 02/05/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JEFF SHACKELFORD R4 |
| |JOSIE PICCONE, NMSS EO |
+------------------------------------------------+JOSEPH GIITTER IRO |
| NRC NOTIFIED BY: BILL KEARNEY | |
| HQ OPS OFFICER: DICK JOLLIFFE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|EEEE 39.77 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - IN-SITU LEACH MINE MONITOR WELL PLACED IN EXCURSION STATUS - |
| |
| THE 'B' MONITOR WELL #M-64 AT THE IN-SITU LEACH MINE OPERATIONS AT THE |
| HIGHLAND URANIUM PROJECT, GLENROCK, WY, WAS PLACED IN EXCURSION STATUS |
| BECAUSE TWO OF THREE MONITORED PARAMETERS WERE ABOVE THEIR SPECIFIED LIMITS: |
| CHLORIDES - 9 MILLIGRAMS PER LITER (LIMIT IS 11); BICARBONATES - 413 |
| MILLIGRAMS PER LITER (LIMIT IS 281); CONDUCTIVITY - 749 MICROMHOS PER |
| CENTIMETER (LIMIT IS 735). THE LICENSEE FEELS THAT THIS IS A FALSE |
| EXCURSION THAT IS NOT A RESULT OF THE LEACH MINE OPERATION BUT IS DUE TO AN |
| OLD ABANDONED UNDERGROUND MINE LOCATED NEARBY. THIS SITUATION HAS OCCURRED |
| IN THE PAST. |
| |
| THE RESULTING RISK IS NIL, AND THERE IS NO ADVERSE IMPACT ON LOCAL PEOPLE, |
| LIVESTOCK, WILDLIFE, OR THE ENVIRONMENT AND NO THREAT TO PUBLIC HEALTH AND |
| SAFETY. THE LICENSEE PLANS TO COLLECT ADDITIONAL SAMPLES, NOTIFY STATE |
| AUTHORITIES, AND SUBMIT A WRITTEN REPORT TO THE NRC WITHIN 60 DAYS. |
| |
| |
| (Call the NRC Operations Center for a contact telephone number.) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Hospital |Event Number: 35348 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: RESEARCH MEDICAL CENTER |NOTIFICATION DATE: 02/05/1999|
|LICENSEE: RESEARCH MEDICAL CENTER |NOTIFICATION TIME: 17:02[EST]|
| CITY: KANSAS CITY REGION: 3 |EVENT DATE: 02/05/1999|
| COUNTY: STATE: MO |EVENT TIME: 08:30[CST]|
|LICENSE#: 24-17998-02 AGREEMENT: N |LAST UPDATE DATE: 02/05/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |THOMAS KOZAK R3 |
| |JOSIE PICCONE, NMSS EO |
+------------------------------------------------+JOSEPH GIITTER IRO |
| NRC NOTIFIED BY: ED CYTACKI | |
| HQ OPS OFFICER: DICK JOLLIFFE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|LADM 35.33(a) MED MISADMINISTRATION | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - 12.3% UNDER-DOSE DURING A CANCEROUS BRAIN TUMOR TREATMENT USING A GAMMA |
| KNIFE - |
| |
| AT 0830 CST ON 02/06/99, WHILE REVIEWING A PATIENT'S MEDICAL CHART, A |
| HOSPITAL SURGEON DETERMINED THAT DURING A CANCER TREATMENT FOR A BRAIN TUMOR |
| USING A GAMMA KNIFE (201 Co-60 SOURCES) ON 01/06/99, THE PATIENT WAS |
| ADMINISTERED AN UNDER-DOSE BY 12.3%. THERE WERE NO APPARENT ADVERSE EFFECTS |
| ON THE PATIENT. HOSPITAL PERSONNEL NOTIFIED THE PATIENT AND HIS PHYSICIAN. |
| |
| HOSPITAL PERSONNEL ARE PERFORMING AN INVESTIGATION TO DETERMINE ANY |
| ADDITIONAL TREATMENTS AND CORRECTIVE ACTIONS. HOSPITAL PERSONNEL PLAN TO |
| SUBMIT A WRITTEN REPORT TO NRC REGION 3 WITHIN 15 DAYS. |
| |
| (Call the NRC Operations Center for a contact telephone number.) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35349 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 02/05/1999|
| UNIT: [1] [] [] STATE: VT |NOTIFICATION TIME: 17:34[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 02/05/1999|
+------------------------------------------------+EVENT TIME: 17:25[EST]|
| NRC NOTIFIED BY: DENNIS MAY |LAST UPDATE DATE: 02/05/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JULIAN WILLIAMS R1 |
|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 |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - RHR & CS SYSTEMS FLOW INSTRUMENT POWER SUPPLY LINES ROUTED IN SAME CABLE |
| TRAY - |
| |
| AT 1725 ON 02/05/99, DURING A REVIEW FOR A DESIGN CHANGE, THE LICENSEE |
| DISCOVERED THAT THE 120-VAC POWER FEED TO POWER SUPPLY #PS10-100B IS ROUTED |
| IN THE SAME DIVISION II CABLE TRAY AS POWER SUPPLY #PS10-100A. THESE TWO |
| POWER SUPPLIES ARE INTENDED TO BE REDUNDANT TO EACH OTHER AND SUPPLY POWER |
| TO REDUNDANT TRAINS OF RESIDUAL HEAT REMOVAL (RHR) SYSTEM AND CORE SPRAY |
| (CS) SYSTEM FLOW INSTRUMENTATION. A LICENSEE OPERABILITY DETERMINATION |
| CONCLUDED THAT THE FLOW INSTRUMENTATION IS OPERABLE, AND THERE IS NO ADVERSE |
| IMPACT ON PRESENT PLANT OPERATIONS. THE LICENSEE IS DETERMINING CORRECTIVE |
| ACTIONS. |
| |
| THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35350 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 02/06/1999|
| UNIT: [] [2] [] STATE: MN |NOTIFICATION TIME: 07:24[EST]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 02/06/1999|
+------------------------------------------------+EVENT TIME: 05:44[CST]|
| NRC NOTIFIED BY: JOHNSON |LAST UPDATE DATE: 02/06/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |THOMAS KOZAK R3 |
|10 CFR SECTION: | |
|ADEV 50.72(b)(1)(i)(B) DEVIATION FROM T SPEC | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N N 0 Hot Shutdown |0 Hot Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MISSED TECHNICAL SPECIFICATION (TS) REQUIRED SURVEILLANCE |
| |
| Following a reactor shutdown for a planned outage, a TS required |
| surveillance was not met, and an evaluation is being made to determine the |
| reason. Following taking the unit to Hot Shutdown, technical specifications |
| require that procedure SP-2035D, Reactor Protection Logic Testing, be |
| completed prior to making the control rod drive system capable of rod |
| withdrawal. In this case, however, the shutdown reactor trip breakers were |
| closed and the shutdown rods withdrawn. Upon discovery of the missed TS |
| required surveillance, the shutdown rods were inserted, and the trip |
| breakers opened. The required surveillance will be completed prior to |
| re-closing the trip breakers. |
| |
| The NRC resident inspector will be informed by the licensee. |
| |
| *** RETRACTION AT 1350 EST ON 02/06/99 FROM W. ANDREWS TO TROCINE *** |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "At 0724 EST, on Saturday, February 6, 1999, Prairie Island Unit 2 made a |
| [1-]Hour non-emergency notification per 10 CFR 50.72 (b)(1)(i)(B) due to |
| identification of a missed technical specification required surveillance. |
| Upon further review, this event did not meet the conditions of reporting per |
| 10 CFR 50.72(b)(1)(i)(B), and the licensee |
| desires to retract this notification. The event will be reported under 10 |
| CFR 50.73(a)(2)(i)(B) with a 30-day Licensee Event Report." |
| |
| The licensee plans to notify the NRC resident inspector. The NRC operations |
| officer notified the R3DO (Kozak). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35351 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 02/07/1999|
| UNIT: [1] [] [] STATE: AZ |NOTIFICATION TIME: 04:19[EST]|
| RXTYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 02/06/1999|
+------------------------------------------------+EVENT TIME: 22:55[MST]|
| NRC NOTIFIED BY: MARKS |LAST UPDATE DATE: 02/07/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JEFF SHACKELFORD R4 |
|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
+------------------------------------------------------------------------------+
| EMERGENCY SIRENS WERE INADVERTENTLY ACTIVATED DURING TESTING. |
| |
| AT APPROXIMATELY 2226 MST ON 02/06/99, THE MARICOPA COUNTY SHERIFF'S OFFICE |
| REPORTED TO THE LICENSEE THAT THEIR WEEKLY SILENT TEST OF THE SIREN SYSTEM |
| SHOWED THE SIRENS NOT TO BE FUNCTIONAL. THE LICENSEE, THEREFORE, NOTIFIED |
| THE DEPARTMENT OF PUBLIC SAFETY TO REQUEST THAT THEY TEST THE SIREN SYSTEM |
| FROM THEIR ALTERNATE LOCATION. DUE TO A COMMUNICATIONS MISUNDERSTANDING, |
| THE DEPARTMENT OF PUBLIC SAFETY TESTED THE SIRENS BY ACTUALLY RUNNING THEM |
| FOR APPROXIMATELY 77 SECONDS. ALL 39 SIRENS WERE DEMONSTRATED TO BE |
| FUNCTIONAL. AS A RESULT OF THE SIREN ACTUATION, THE LICENSEE HAS HAD |
| FOLLOW-UP COMMUNICATIONS WITH MARICOPA COUNTY DEPARTMENT OF EMERGENCY |
| MANAGEMENT. ALTHOUGH THERE WERE SOME CONCERNS FROM RESIDENTS IN THE AREA, |
| NO PRESS RELEASE IS PLANNED. |
| |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED ALONG WITH STATE AND OTHER |
| GOVERNMENT AGENCIES. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35352 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 02/08/1999|
| UNIT: [1] [] [] STATE: MS |NOTIFICATION TIME: 00:34[EST]|
| RXTYPE: [1] GE-6 |EVENT DATE: 02/07/1999|
+------------------------------------------------+EVENT TIME: 22:38[CST]|
| NRC NOTIFIED BY: HANKS |LAST UPDATE DATE: 02/08/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JEFF SHACKELFORD R4 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| THE LICENSEE DECLARED RCIC INOPERABLE AND ENTERED A 14 DAY LCO ACTION |
| STATEMENT. |
| |
| RCIC WAS DECLARED INOPERABLE WHEN A DIVISION II ISOLATION OCCURRED DUE TO AN |
| INVALID SIGNAL DURING THE PERFORMANCE OF A SURVEILLANCE. THE CAUSE IS BEING |
| INVESTIGATED. HPCS WAS VERIFIED OPERABLE WITHIN ONE HOUR , AS REQUIRED BY |
| THE LCO ACTION STATEMENT, AT 2310 CST. RCIC IS REQUIRED TO BE RETURNED TO |
| SERVICE WITHIN 14 DAYS. THE ISOLATION SIGNAL HAS BEEN RESET, BUT THE VALVES |
| ARE STILL CLOSED AND WILL NOT BE REOPENED UNTIL THE CAUSE OF THE ISOLATION |
| HAS BEEN DETERMINED. |
| |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021