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Event Notification Report for March 9, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           03/08/1999 - 03/09/1999

                              ** EVENT NUMBERS **

35447  35448  35449  35450  35451  

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|Power Reactor                                    |Event Number:   35447       |
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| FACILITY: RIVER BEND               REGION:  4  |NOTIFICATION DATE: 03/08/1999|
|    UNIT:  [1] [] []                 STATE:  LA |NOTIFICATION TIME: 15:15[EST]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        03/08/1999|
+------------------------------------------------+EVENT TIME:        11:42[CST]|
| NRC NOTIFIED BY:  GEORGE TURNER                |LAST UPDATE DATE:  03/08/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GARY SANBORN         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       82       Power Operation  |82       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| INADVERTENT ACTUATION OF SINGLE OFFSITE SIREN DURING TESTING OF ACTUATION    |
| SYSTEM                                                                       |
|                                                                              |
| During Y2K testing of the offsite siren actuation system, a single siren     |
| actuated for about 5 seconds.  The test was terminated and the system        |
| returned to pretest conditions.  The licensee notified the Louisiana Office  |
| of Emergency Preparedness (LOEP) and informed them of the actuation.  The    |
| LOEP decided not to make a public announcement on the emergency alert system |
| as the siren was only actuated for a short period of time.                   |
|                                                                              |
| The licensee notified the local parishes and the NRC Resident Inspector.     |
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+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   35448       |
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| REP ORG:  FAIRBANKS MORSE ENGINE DIVISION      |NOTIFICATION DATE: 03/08/1999|
|LICENSEE:  FAIRBANKS MORSE ENGINE DIVISION      |NOTIFICATION TIME: 15:29[EST]|
|    CITY:  BELOIT                   REGION:  3  |EVENT DATE:        03/08/1999|
|  COUNTY:                            STATE:  WI |EVENT TIME:        14:20[CST]|
|LICENSE#:                        AGREEMENT:  N  |LAST UPDATE DATE:  03/08/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |TOM MOSLAK           R1      |
|                                                |VERN HODGE (FAX)     NRR     |
+------------------------------------------------+RONALD GARDNER       R3      |
| NRC NOTIFIED BY:  JAMES GOLDING                |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 10 CFR PART 21 REPORT REGARDING IMPROPER HEAT TREATMENT TO CAM ROLLERS       |
|                                                                              |
| On February 9, 1999, Coltec Industries, Fairbanks Morse Engine Division      |
| (FMED), became aware of a                                                    |
| potential safety hazard associated with the air and exhaust valve cam        |
| rollers for FM-ALCO 251 engines.  Final analysis was completed on March 8,   |
| 1999 by Engineering and Quality Assurance.  They determined the cause to be  |
| improper heat treatment of the cam rollers, which results in premature wear  |
| of the roller and possible damage to the camshaft lobe, roller pin, and push |
| rod.  The suspect rollers were induction hardened, which resulted in         |
| inadequate case depth hardness and surface hardness.                         |
|                                                                              |
| FMED had supplied the suspect rollers to Consolidated Edison Indian Point 2  |
| nuclear power station on November 14, 1997.  Based on a review of FMED       |
| records, Consolidated Edison is the only nuclear utility that is impacted.   |
|                                                                              |
| FMED has taken corrective action to prevent reoccurrence.  In addition, the  |
| tolerance used during the dedication process for the cam rollers has been    |
| changed. Other tolerances will be reviewed as parts are dedicated.           |
|                                                                              |
| It should be noted that FMED has not been notified, nor is it aware of any   |
| air and exhaust valve cam roller failures that have occurred at any nuclear  |
| facilities. The failures that have occurred have been in commercial          |
| applications after approximately 200 hours of operation.                     |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35449       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK                     REGION:  3  |NOTIFICATION DATE: 03/08/1999|
|    UNIT:  [1] [2] []                STATE:  MI |NOTIFICATION TIME: 16:53[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        03/08/1999|
+------------------------------------------------+EVENT TIME:        14:00[EST]|
| NRC NOTIFIED BY:  MARY BETH GREENDONNER        |LAST UPDATE DATE:  03/08/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |RONALD GARDNER       R3      |
|10 CFR SECTION:                                 |                             |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|2     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PLANT SECURITY REPORT                                                        |
|                                                                              |
| Safeguards system degradation related to potential unauthorized entry into a |
| vital area.  Immediate compensatory measures taken upon discovery.           |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
|                                                                              |
| Refer to the HOO Log for additional details.                                 |
|                                                                              |
| * * * UPDATE AT 1838 EST ON 3/8/99 BY MARY BETH GREENDONNER TO FANGIE JONES  |
| * * *                                                                        |
|                                                                              |
| Additional safeguards system degradation found during additional inspection  |
| after initial report.  Immediate compensatory measures taken upon            |
| discovery.                                                                   |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
|                                                                              |
| The NRC Operations Officer notified the R3DO (R. Gardner) and R3 IAT (James  |
| Creed).                                                                      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35450       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BROWNS FERRY             REGION:  2  |NOTIFICATION DATE: 03/08/1999|
|    UNIT:  [] [2] [3]                STATE:  AL |NOTIFICATION TIME: 23:39[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4,[3] GE-4           |EVENT DATE:        03/08/1999|
+------------------------------------------------+EVENT TIME:        21:42[CST]|
| NRC NOTIFIED BY:  RAYMOND SWAFFORD             |LAST UPDATE DATE:  03/09/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CAUDLE JULIAN        R2      |
|10 CFR SECTION:                                 |                             |
|ASHU 50.72(b)(1)(i)(A)   PLANT S/D REQD BY TS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       96       Power Operation  |94       Power Operation  |
|3     N          Y       100      Power Operation  |98       Power Operation  |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| Two Trains of Standby Gas Treatment (SBGT) Inoperable -  Shutdown Required   |
| by Technical Specifications                                                  |
|                                                                              |
| "At 2042, with both U2 & U3 in Mode 1, U2 coasting down at 3145 MWth, U3     |
| 100% 3458 MWth, U2 and U3 received alarms 'SBGT C RH [Relative Humidity]     |
| TEMP HIGH'  and 'SBGT C FLT [Filter] BANK HTR ELEM POWER LOST.'  The system  |
| engineer reported the supply breaker for C train SBGT tripped. C SBGT was    |
| declared inoperable.  B SBGT was already INOP due to scheduled maintenance.  |
| With two trains of SBGT INOP, this resulted in entering TS LCO 3.0.3 on both |
| units immediately.   At 2141, shutdown was initiated on both U2 and U3.      |
| This is reportable as a 1 hour report to the NRC under 10 CFR                |
| 50.72(b)(1)(i)(A), as 'The initiation of any nuclear plant shutdown required |
| by the plant's Technical Specification.'                                     |
|                                                                              |
| "Upon investigation by Engineering and Maintenance it was determined there   |
| was a problem with SBGT switch. Tech Spec Requirement 3.3.A.1 allows         |
| tripping of the logic of the inoperable flow switch and starting the         |
| affected SBGT C.  This action was completed and C SBGT was declared OPERABLE |
| and TS LCO 3.0.3 exited at 2237."                                            |
|                                                                              |
| The licensee informed the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35451       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LIMERICK                 REGION:  1  |NOTIFICATION DATE: 03/09/1999|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 05:55[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        03/09/1999|
+------------------------------------------------+EVENT TIME:        02:21[EST]|
| NRC NOTIFIED BY:  JOHN HUNTER                  |LAST UPDATE DATE:  03/09/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |TOM MOSLAK           R1      |
|10 CFR SECTION:                                 |                             |
|AINB 50.72(b)(2)(iii)(B) POT RHR 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  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| COMMON FAILURE EFFECTING BOTH TRAINS OF SHUTDOWN COOLING                     |
|                                                                              |
| "On 3/9/99, at 0221 it was discovered that the Unit 1 shutdown cooling       |
| valves HV-51-1F015A, HV-51-1F015B, and HV-51-1F08 could not be opened, if    |
| plant conditions required, due to a failure in the isolation logic circuit   |
| connectors.                                                                  |
|                                                                              |
| "This failure affected both shutdown cooling return valves and a common      |
| suction valve which results in one failure effecting both trains of shutdown |
| cooling.  The identified deficiency is being planned for repairs.  This      |
| condition, of a single failure disabling multiple trains of a system, is     |
| being reported pursuant to 50.72(b)(2)(iii)."                                |
|                                                                              |
| This deficiency was discovered during routine maintenance.  These valves     |
| could be opened manually using existing plant procedures if it were          |
| necessary to initiate shutdown cooling.                                      |
|                                                                              |
| The licensee will notify the NRC resident inspector.                         |
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