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Event Notification Report for February 15, 2002

                         *** NOT FOR PUBLIC DISTRIBUTION ***
                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           02/14/2002 - 02/15/2002

                              ** EVENT NUMBERS **

38694  38695  38696  38697  38698  

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|Power Reactor                                    |Event Number:   38694       |
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| FACILITY: COLUMBIA GENERATING STATIREGION:  4  |NOTIFICATION DATE: 02/14/2002|
|    UNIT:  [2] [] []                 STATE:  WA |NOTIFICATION TIME: 04:18[EST]|
|   RXTYPE: [2] GE-5                             |EVENT DATE:        02/14/2002|
+------------------------------------------------+EVENT TIME:        01:03[PST]|
| NRC NOTIFIED BY:  BRIAN ADAMI                  |LAST UPDATE DATE:  02/14/2002|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |LINDA SMITH          R4      |
|10 CFR SECTION:                                 |                             |
|ASHU 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  |97       Power Operation  |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| TECHNICAL SPECIFICATION REQUIRED  SHUTDOWN                                   |
|                                                                              |
| "This ENS notification is made to report initiation of a plant shutdown      |
| required by the Columbia Generating Station Technical Specifications         |
| pursuant to 10 CFR 50.72(b)(2)(i). This plant shutdown is initiated due to   |
| the expected inability to restore the Division II Emergency Diesel Generator |
| (DG) to Operable status prior to exceeding the expiration of the Completion  |
| Time of Tech Spec LCO 3.8 1 Required Action B.4. The expected inability to   |
| restore the DG to operable status is due to a mechanical problem in the DG   |
| output breaker. The breaker is capable of closing and connecting the DG to   |
| its safety bus however, Mechanically Operated Contacts that are actuated by  |
| the breaker have failed to actuate, Although the Completion time of          |
| Technical Specification LCO 3 8.1 Required Acton B.4 expires at 0315,        |
| February 14, 2002, plant shutdown will commence prior to that time in order  |
| to fully evaluate the breaker anomaly."                                      |
|                                                                              |
| The NRC resident inspector has been informed of this notification by the     |
| licensee.                                                                    |
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|Other Nuclear Material                           |Event Number:   38695       |
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| REP ORG:  ENG. RESEARCH & DEVELOPMENT CENTER   |NOTIFICATION DATE: 02/14/2002|
|LICENSEE:  ENG. RESEARCH & DEVELOPMENT CENTER   |NOTIFICATION TIME: 13:52[EST]|
|    CITY:  HANOVER                  REGION:  1  |EVENT DATE:        02/14/2002|
|  COUNTY:  GRAFTON                   STATE:  NH |EVENT TIME:             [EST]|
|LICENSE#:  28-07946-06           AGREEMENT:  Y  |LAST UPDATE DATE:  02/14/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |JAMES TRAPP          R1      |
|                                                |DON COOL             NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  ALAN GREATOREX               |                             |
|  HQ OPS OFFICER:  LEIGH TROCINE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|BAE1 20.2202(b)(1)       PERS OVEREXPOSURE/TEDE |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| POTENTIAL OVEREXPOSURE AT ENGINEER RESEARCH & DEVELOPMENT CENTER IN HANOVER, |
| NEW HAMPSHIRE                                                                |
|                                                                              |
| On 02/04/02, the licensee received a telephone notification that an          |
| individual's badge had an exposure of 16 Rem during a 3-month period.  After |
| further investigation on 02/05/02, the licensee determined that the          |
| individual had lost the badge while packing a moisture density gauge for     |
| storage.  Approximately 4 weeks later, the badge was discovered when the     |
| device was being prepared to be sent for recalibration.                      |
|                                                                              |
| On 02/08/02, the licensee received a telex identifying what the exposures    |
| were in writing.  The licensee notified the NRC Region 1 office (Betsy       |
| Ullrich) on 02/14/02.                                                        |
|                                                                              |
| The licensee currently believes that the 16-Rem exposure was an exposure to  |
| the badge and not to the individual.                                         |
|                                                                              |
| NOTE:   The licensee stated that Engineer Research & Development Center is a |
| research portion of the Core of                                              |
| Engineers and that it was previously know as the U.S. Army Cold Regions      |
| Research & Engineering                                                       |
| Laboratory.                                                                  |
|                                                                              |
| (Call the NRC operations officer for a licensee contact telephone number.)   |
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|Other Nuclear Material                           |Event Number:   38696       |
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| REP ORG:  POWER RESOURCES                      |NOTIFICATION DATE: 02/14/2002|
|LICENSEE:  POWER RESOURCES                      |NOTIFICATION TIME: 18:19[EST]|
|    CITY:  DOUGLAS                  REGION:  4  |EVENT DATE:        02/14/2002|
|  COUNTY:  CONVERSE                  STATE:  WY |EVENT TIME:        13:30[MST]|
|LICENSE#:  15-SUA-1511           AGREEMENT:  N  |LAST UPDATE DATE:  02/14/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |MYRON FLIEGEL/MINING NMSS    |
|                                                |MIKE LAYTON/MINING   NMSS    |
+------------------------------------------------+LINDA SMITH          R4      |
| NRC NOTIFIED BY:  WILLIAM KEARNEY              |SUSAN FRANT          NMSS    |
|  HQ OPS OFFICER:  LEIGH TROCINE                |DWIGHT CHAMBERLAIN   R4      |
+------------------------------------------------+(via NRC) BROWN      EPA     |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NMIN                     MINING EVENT           |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| POWER RESOURCES HIGHLAND URANIUM PROJECT (AN IN-SITU URANIUM MINE LOCATED IN |
| A RURAL AREA APPROXIMATELY 30 MILES NORTH OF DOUGLAS, WYOMING) REPORTED A    |
| MINOR RELEASE OF RADIOACTIVE MATERIAL.                                       |
|                                                                              |
| At 1330 MST, while personnel were moving a trailer-mounted 1,000-gallon tank |
| full of water from a well, they forgot to close a valve, and approximately   |
| 20 to 25 gallons of water containing uranium drained onto a county road.     |
| The spill was cleaned up by approximately 1530 MST.  Original contamination  |
| levels were between 1,000 and 5,000 cpm, however, alpha scans of the area    |
| currently meet the NRC unrestricted release standard of 1,000 cpm.  A sample |
| of the water from the trailer is being analyzed to determine the actual      |
| activity levels.  There were no personnel contaminations or injuries         |
| associated with this event.                                                  |
|                                                                              |
| The licensee notified the Department of Transportation and plans to notify   |
| the local sheriff's office.  The NRC Region 4 office plans to notify the     |
| State of Wyoming.                                                            |
|                                                                              |
| The NRC mining experts assessed this event and stated that no adverse impact |
| is anticipated and no response is required.                                  |
|                                                                              |
| (Call the NRC operations officer for licensee contact telephone numbers.)    |
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|Power Reactor                                    |Event Number:   38697       |
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| FACILITY: DIABLO CANYON            REGION:  4  |NOTIFICATION DATE: 02/14/2002|
|    UNIT:  [1] [2] []                STATE:  CA |NOTIFICATION TIME: 20:30[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        02/14/2002|
+------------------------------------------------+EVENT TIME:        16:20[PST]|
| NRC NOTIFIED BY:  DOUGLAS DYE                  |LAST UPDATE DATE:  02/14/2002|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |LINDA SMITH          R4      |
|10 CFR SECTION:                                 |JAMES TRAPP          R1      |
|ASHU 50.72(b)(2)(i)      PLANT S/D REQD BY TS   |                             |
|AINA 50.72(b)(3)(v)(A)   POT UNABLE TO SAFE SD  |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |90       Power Operation  |
|2     N          Y       100      Power Operation  |89       Power Operation  |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| TECHNICAL SPECIFICATION REQUIRED SHUTDOWN OF BOTH UNITS BECAUSE STEAM        |
| GENERATOR WATER LEVEL INSTRUMENT CHANNELS ARE INOPERABLE DUE TO A            |
| NON-CONSERVATIVE WATER LEVEL-LOW LOW SETPOINT                                |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "During the investigation into the Unit 2 manual reactor trip on February 9, |
| 2002 (Event Number 38687), PG&E discovered a potentially unanalyzed          |
| condition.  The narrow range (NR) steam generator (SG) water level           |
| instrumentation did not respond as expected to initiate an automatic reactor |
| trip and auxiliary feedwater actuation on SG water level-low low."           |
|                                                                              |
| "The SG NR water level-low low setpoint is 7.2 percent.  This                |
| instrumentation is part of the Reactor Trip System (Technical Specification  |
| (TS) Table 3.3.1-1 Function 14.a), and Engineered Safety Feature Actuation   |
| System (ESFAS) (TS Table 3.3.2-1 Function 6.d), Auxiliary Feedwater (AFW)."  |
|                                                                              |
| "On February 9, 2002, main feedwater regulating valve (MFRV) FW-2-FCV-540    |
| failed closed, resulting in a rapid decrease in SG 2-4 water level.          |
| Indicated NR water level fell to approximately 7.5 percent and leveled out.  |
| Operators tripped the reactor within approximately one minute of the MFRV    |
| closing.  Based on investigations and conversations with Westinghouse today, |
| PG&E believes the actual SG 2-4 NR water level fell below the 7.2 percent    |
| setpoint before the reactor was tripped.  Westinghouse attributes this water |
| level discrepancy to a previously unaccounted for differential pressure (dP) |
| created by steam flow past the mid-deck plate (MDP) in the moisture          |
| separator section of the SG.  This dP phenomena will cause the SG NR to read |
| higher than actual at high steam flows (>60% power).  Thus, the SG NR water  |
| level-low low setpoint is believed to be non-conservative during certain     |
| transients."                                                                 |
|                                                                              |
| "In response, operators declared all SG NR water level-low low channels      |
| inoperable and entered TS Action 3.0.3.  At 1700 [PST], both units began     |
| reducing power to approximately 60 percent, where Westinghouse indicates     |
| this condition will no longer result in a non-conservative setpoint."        |
|                                                                              |
| "In accordance with 10 CFR 50.72(b)(2)(i), PG&E is reporting this as the     |
| initiation of a TS required shutdown.  It is also being reported under 10    |
| CFR 50.72(b)(3)(v)(A) as condition that at the time of discovery could have  |
| prevented the fulfillment of the safety function of structures or systems    |
| that are needed to shutdown the reactor and maintain it in a safe shutdown   |
| condition."                                                                  |
|                                                                              |
| The licensee notified the Salem facility and the NRC resident inspector.     |
| The licensee also plans to notify the local Advisory of the County.          |
|                                                                              |
| (Refer to event #38687 for additional information.)                          |
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|Power Reactor                                    |Event Number:   38698       |
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| FACILITY: FT CALHOUN               REGION:  4  |NOTIFICATION DATE: 02/15/2002|
|    UNIT:  [1] [] []                 STATE:  NE |NOTIFICATION TIME: 05:36[EST]|
|   RXTYPE: [1] CE                               |EVENT DATE:        02/15/2002|
+------------------------------------------------+EVENT TIME:        03:53[CST]|
| NRC NOTIFIED BY:  RANDY CADE                   |LAST UPDATE DATE:  02/15/2002|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          UNUSUAL EVENT         |LINDA SMITH          R4      |
|10 CFR SECTION:                                 |JOSE CALVO           NRR     |
|AAEC 50.72(a) (1) (i)    EMERGENCY DECLARED     |STEINDURF            FEMA    |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       98       Power Operation  |98       Power Operation  |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| DISCRETIONARY DECLARATION OF UNUSUAL EVENT DUE TO "INCREASED PLANT           |
| AWARENESS"                                                                   |
|                                                                              |
| During a dewatering evolution of the Spent Resin Storage Tank, some spent    |
| resin entered the tank vent header. This caused an elevated reading of 263   |
| mrem on a single area radiation monitor (RM-081). The licensee declared an   |
| Unusual Event in accordance with EAL 11.4, "Increased Plant Awareness."      |
| Additional personnel are being called in to the site to assist in devising a |
| plan to flush the resin from the affected piping. The licensee estimates     |
| that it will take two to three hours to complete this evolution. The NRC     |
| resident inspector and state and local government agencies have been         |
| informed of this event by the licensee.                                      |
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