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Event Notification Report for June 20, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           06/19/2000 - 06/20/2000

                              ** EVENT NUMBERS **

37016  37094  37095  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   37016       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK              REGION:  1  |NOTIFICATION DATE: 05/22/2000|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 13:42[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        05/22/2000|
+------------------------------------------------+EVENT TIME:        12:59[EDT]|
| NRC NOTIFIED BY:  ABRAMSKI                     |LAST UPDATE DATE:  06/19/2000|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DAN HOLODY           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                                   
+------------------------------------------------------------------------------+
| REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM MAY NOT BE PROTECTED BY STEAM   |
| LEAK DETECTION CIRCUITRY.                                                    |
|                                                                              |
| A LICENSEE ENGINEERING REVIEW IDENTIFIED A SECTION OF RCIC SYSTEM PIPING     |
| WHICH MAY NOT  BE PROTECTED BY THE STEAM LEAK DETECTION CIRCUITRY.           |
| SPECIFICALLY, THE STEAM SUPPLY ISOLATION SIGNAL MAY NOT ISOLATE A POSTULATED |
| CRACKED STEAM SUPPLY LINE PRIOR TO CRACK PROPAGATION AS IN THE DESIGN INTENT |
| OF THE STEAM LEAK DETECTION SYSTEM.  THE LICENSEE IS CONTINUING WITH ITS     |
| INVESTIGATION.  THE RCIC SYSTEM WAS NOT DECLARED INOPERABLE AND THE LICENSEE |
| HAS NOT ENTERED ANY LCO ACTION STATEMENTS.                                   |
|                                                                              |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED.                                     |
|                                                                              |
| * * * RETRACTED ON 6/19/00 AT 1254 EST BY MARK ABRAMSKI TO FANGIE JONES * *  |
| *                                                                            |
|                                                                              |
| "A review of plant design and licensing basis documentation has confirmed    |
| that the design and licensing basis requirements for the SLD system as       |
| defined in the UFSAR have not been properly maintained. It is therefore not  |
| clear that the ability to detect and isolate a leak prior to the leak        |
| propagating to a break in this section of pipe is in fact a design basis     |
| requirement.                                                                 |
|                                                                              |
| "LER 99-013 identified the condition where the SLD system was outside the    |
| design basis of the plant because the system could not reliably detect a 7   |
| GPM leak (but could detect a 25 GPM leak). The review of plant design and    |
| licensing basis documentation discussed above has identified the need to     |
| revise corrective actions identified in LER 99-013 to include a more         |
| comprehensive redefinition of the design and licensing basis requirements    |
| for the SLD system. The event reported in 10 CFR 50.72 notification log      |
| number 37016 is therefore an extent of the condition reported in LER 99-013  |
| and will therefore be discussed in the revision to LER 99-013.               |
|                                                                              |
| "On this basis 10 CFR 5072 notification log number 37016 is redundant to the |
| condition reported in LER 99-013 and 10 CFR 50.72 notification log number    |
| 37016 is therefore retracted."                                               |
|                                                                              |
| The licensee notified the NRC Resident Inspector.  The R1DO (Robert Summers) |
| was notified.                                                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37094       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  MA RADIATION CONTROL PROGRAM         |NOTIFICATION DATE: 06/19/2000|
|LICENSEE:  AEA TECHNOLOGY                       |NOTIFICATION TIME: 14:51[EDT]|
|    CITY:  BURLINGTON               REGION:  1  |EVENT DATE:        06/19/2000|
|  COUNTY:                            STATE:  MA |EVENT TIME:        11:30[EDT]|
|LICENSE#:  12-8361               AGREEMENT:  Y  |LAST UPDATE DATE:  06/19/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |ROBERT SUMMERS       R1      |
|                                                |DON COOL             NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  MICHEAL WHALEN               |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|BAE1 20.2202(b)(1)       PERS OVEREXPOSURE      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| POTENTIAL PERSONNEL OVEREXPOSURE                                             |
|                                                                              |
| A technician opened a "package" on the loading dock to check the contents    |
| after an apparent miscommunication.  The package contained 1650 curies of    |
| Co-60 in a shielded container.  The technician received an undetermined dose |
| to the head and shoulder areas of the body, possibly in excess of 5 rem.     |
| The dose will be determined but there is a good chance that it will be less  |
| than 5 rem.  Even after removal of the outer plug there was still 1.125      |
| inches of tungsten shielding.                                                |
|                                                                              |
| The Massachusetts Radiation Control Program plans to go to the site and      |
| conduct an investigation.                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37095       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DAVIS BESSE              REGION:  3  |NOTIFICATION DATE: 06/19/2000|
|    UNIT:  [1] [] []                 STATE:  OH |NOTIFICATION TIME: 16:22[EDT]|
|   RXTYPE: [1] B&W-R-LP                         |EVENT DATE:        06/19/2000|
+------------------------------------------------+EVENT TIME:        15:25[EDT]|
| NRC NOTIFIED BY:  CRAIG GILLIG                 |LAST UPDATE DATE:  06/19/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ROGER LANKSBURY      R3      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |98       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PLANT SHUTDOWN REQUIRED BY TECH SPEC 3.0.3 DUE TO FAILED VALVE TESTING       |
|                                                                              |
| The licensee was conducting Instrument and Control testing under DB-MI-03211 |
| which failed to produce the expected response for solenoid SP6A2 on valve    |
| SP6A, Steam Generator Main Feedwater Valve.  The problem is with the         |
| solenoid or associated limit switch.  Due to a lack of specific Technical    |
| Specification guidance, 3.0.3 has been entered which requires the plant to   |
| initiate action to place the plant in a mode in which the specification does |
| not apply.  It is expected that the plant will be able to repair and test    |
| prior to a full plant shutdown.                                              |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
|                                                                              |
| * * * UPDATE AT 1710 EST ON 6/19/00 BY CRAIG GILLIG TO FANGIE JONES * * *    |
|                                                                              |
| The licensee determined the problem was with the limit switch, has exited    |
| the tech spec required shutdown, and is returning to full power from 96%.    |
|                                                                              |
| The licensee intends to notify the NRC Resident Inspector.  The R3DO (Roger  |
| Lanksbury) has been notified.                                                |
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