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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!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 |
| | |
| | |
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EVENT TEXT
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| 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. |
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+------------------------------------------------------------------------------+
|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 | |
| | |
| | |
| | |
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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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