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Event Notification Report for June 29, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           06/28/1999 - 06/29/1999

                              ** EVENT NUMBERS **

35873  35874  35875  35876  35877  35878  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35873       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FARLEY                   REGION:  2  |NOTIFICATION DATE: 06/27/1999|
|    UNIT:  [1] [2] []                STATE:  AL |NOTIFICATION TIME: 18:21[EDT]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        06/27/1999|
+------------------------------------------------+EVENT TIME:        16:55[CDT]|
| NRC NOTIFIED BY:  VAUDY HOLLEY                 |LAST UPDATE DATE:  06/28/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |AL BELISLE           R2      |
|10 CFR SECTION:                                 |                             |
|AARC 50.72(b)(1)(v)      OTHER ASMT/COMM INOP   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOSS OF OFFSITE COMMUNICATION SYSTEM - TONE ALERT RADIO                      |
|                                                                              |
| After thunderstorms moved through the area of the plant, the licensee        |
| discovered that communications with the meteorological tower had been lost   |
| and the tone alert radio system was unavailable for greater than 15 minutes, |
| part of the public communication (warning) system.                           |
|                                                                              |
| Workers have been called in to investigate and repair the systems that have  |
| been lost.                                                                   |
|                                                                              |
| The licensee intends to notify the NRC Resident Inspector.                   |
|                                                                              |
| * * * RETRACTION 1759 6/28/1999 FROM HAWKINS TAKEN BY STRANSKY * * *         |
|                                                                              |
| The licensee has determined that, although the primary power supply was      |
| lost, the backup power supply remained available; therefore, the tone alert  |
| radio system remained operable. The NRC resident inspector has been informed |
| of this retraction by the licensee. Notified R2DO (Belisle).                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35874       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH                    REGION:  2  |NOTIFICATION DATE: 06/28/1999|
|    UNIT:  [] [2] []                 STATE:  GA |NOTIFICATION TIME: 03:55[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        06/28/1999|
+------------------------------------------------+EVENT TIME:        03:00[EDT]|
| NRC NOTIFIED BY:  FRANK GORLEY                 |LAST UPDATE DATE:  06/28/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |AL BELISLE           R2      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|ACCS 50.72(b)(1)(iv)     ECCS INJECTION         |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     A/R        Y       100      Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR SCRAM ON LOW REACTOR WATER LEVEL                           |
|                                                                              |
| The reactor automatically scrammed on low reactor vessel water level because |
| of maintenance activities on the 'B' level keep fill system.  Operators      |
| venting the keep fill system unintentionally vented the 'B' reference leg    |
| because the isolation valve between the two systems is apparently leaking.   |
| This venting caused level instruments using the 'B' reference leg to         |
| indicate high.  The mismatch on level indicators caused the feed system to   |
| switch to the 'B' leg (which happened to be the failed system).  This        |
| resulted in a decrease in feed flow and an actual decrease in reactor vessel |
| water level.                                                                 |
|                                                                              |
| The decrease in reactor water level caused a reactor scram and High Pressure |
| Coolant Injection (HPCI) initiation.  Reactor Core Isolation Cooling (RCIC)  |
| did not initiate because it uses the 'B' reference leg as an input.          |
| All control rods fully inserted.  The plant is stable in mode 3.  Water      |
| level has been restored to the normal band and is being maintained by the    |
| feed system.   The recirculating pumps are operating and no safety relief    |
| valves lifted.  The lowest indicated level was -45".                         |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   35875       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 06/28/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 14:52[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        06/28/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        01:05[EDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  06/28/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |MIKE JORDAN          R3      |
|  DOCKET:  0707002                              |DON COOL             NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JEFF CASTLE                  |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NLTR                     LICENSEE 24 HR REPORT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LICENSEE 24 HOUR REPORT - CRANE STOPPED WHILE MOVING UF6 CYLINDER            |
|                                                                              |
| "On June 28, 1999 at approximately 0105, the X-343 south crane movement      |
| stopped completely and would not operate in any direction. The crane failed  |
| while a full liquid UF6 cylinder was being removed from autoclave #6. The    |
| crane brakes functioned as designed to prevent further movement of the UF6   |
| cylinder. Following failure of the crane, the UF6 cylinder was suspended     |
| approximately two feet above the autoclave rollers. The exact cause of the   |
| crane movement failure is currently under investigation. The actuation of    |
| the crane brake is believed to have been necessary as a result of  the       |
| opening of the thermal overloads. Pending further investigation of the cause |
| for the brake actuation, the brake actuation is being considered a valid     |
| safety system actuation, and reportable in accordance with SAR Table 6.9,    |
| Criterion J2. As a precautionary measure, all liquid UF6 handling cranes     |
| have been tagged out of service pending the noted investigation. Support     |
| cradles have been positioned to support the suspended liquid UF6 cylinder."  |
|                                                                              |
| The NRC resident inspector has been informed of this event.                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   35876       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  WEST VIRGINIA UNIVERSITY             |NOTIFICATION DATE: 06/28/1999|
|LICENSEE:  WEST VIRGINIA UNIVERSITY             |NOTIFICATION TIME: 16:07[EDT]|
|    CITY:  MORGANTOWN               REGION:  2  |EVENT DATE:        06/25/1999|
|  COUNTY:                            STATE:  WV |EVENT TIME:             [EDT]|
|LICENSE#:  47-23035-01           AGREEMENT:  N  |LAST UPDATE DATE:  06/28/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |AL BELISLE           R2      |
|                                                |DON COOL             NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  KEN DOUGLAS                  |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB2 20.2201(a)(1)(ii)   LOST/STOLEN LNM>10X    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MISSING SHIPMENT OF SULFUR-35                                                |
|                                                                              |
| The licensee reported that 7 millicuries (mCi) of S-35 was missing from a    |
| shipment that arrived from ICN radiochemicals of California on the morning   |
| of 6/25/1999. Upon receipt, an individual inspected the package and reported |
| that the shipment was present; however, during the investigation, he         |
| admitted that he may not have properly checked it. The loss was discovered   |
| when the package was opened in the laboratory, and the researcher discovered |
| that the package contained only dry ice.                                     |
|                                                                              |
| The licensee has contacted the vendor, who indicated that the package went   |
| through a quality assurance inspection before shipment.  The licensee's      |
| investigation is continuing.                                                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35877       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WASHINGTON NUCLEAR       REGION:  4  |NOTIFICATION DATE: 06/28/1999|
|    UNIT:  [2] [] []                 STATE:  WA |NOTIFICATION TIME: 19:29[EDT]|
|   RXTYPE: [2] GE-5                             |EVENT DATE:        06/28/1999|
+------------------------------------------------+EVENT TIME:        12:44[PDT]|
| NRC NOTIFIED BY:  BRIAN GARDES                 |LAST UPDATE DATE:  06/28/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LINDA SMITH          R4      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC CLOSURE OF MSIVs                                                   |
|                                                                              |
| The licensee reported that the main steam isolation valves (MSIVs)           |
| automatically closed due to unknown reasons.; however, surveillance          |
| procedure ESP-RPS-X301 (Turbine Throttle Valves Channel Check) was being     |
| performed at the time. The unit is currently in Cold Shutdown for a fuel     |
| savings dispatch.                                                            |
|                                                                              |
| The NRC resident inspector has been informed of this notification by the     |
| licensee.                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35878       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK                REGION:  2  |NOTIFICATION DATE: 06/28/1999|
|    UNIT:  [] [2] []                 STATE:  NC |NOTIFICATION TIME: 21:43[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        06/28/1999|
+------------------------------------------------+EVENT TIME:        18:42[EDT]|
| NRC NOTIFIED BY:  DAVE JESTER                  |LAST UPDATE DATE:  06/28/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |AL BELISLE           R2      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     A/R        Y       70       Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC TURBINE TRIP/REACTOR SCRAM DUE TO LOSS OF CONDENSER VACUUM         |
|                                                                              |
| At 1842 EDT, an automatic turbine trip/reactor scram occurred due to low     |
| condenser vacuum after all four circulating water pumps tripped. All control |
| rods inserted following the scram, and the main steam isolation valves       |
| (MSIVs) remained open. No safety/relief valves lifted during the event. All  |
| systems functioned as expected with primary containment isolation system     |
| (PCIS) Group 2 (drywell floor and equipment drains), Group 6 (containment    |
| atmosphere cooling) and Group 8 (RHR shutdown cooling) isolations occurring  |
| due to low reactor vessel water level following the scram. The scram signal  |
| was reset at 1850 EDT.                                                       |
|                                                                              |
| The unit is currently stable in Hot Shutdown. Reactor vessel pressure is     |
| being controlled using the main turbine bypass valves. The licensee has      |
| restored circulating water system flow to the main condenser.                |
|                                                                              |
| The licensee reported that the circulating water pumps tripped as a result   |
| of excessive differential pressure across the intake screens caused by a     |
| fish run in the intake canal.  Operators had manually reduced power from     |
| 100% prior to the event in an attempt to stabilize condenser vacuum. Unit 1  |
| experienced similar increased differential pressure in the circulating water |
| system, but were able to stabilize condenser vacuum after reducing power to  |
| 70%. The fish run has subsided, and the licensee is currently returning Unit |
| 1 to 100% or rated power.                                                    |
|                                                                              |
| The NRC resident inspector has been informed of this event by the licensee.  |
+------------------------------------------------------------------------------+