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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.                                     |
+------------------------------------------------------------------------------+