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Event Notification Report for July 30, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           07/29/1999 - 07/30/1999

                              ** EVENT NUMBERS **

35889  35958  35971  35972  35973  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   35889       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT          REGION:  1  |NOTIFICATION DATE: 07/02/1999|
|    UNIT:  [] [2] []                 STATE:  NY |NOTIFICATION TIME: 16:41[EDT]|
|   RXTYPE: [1] GE-2,[2] GE-5                    |EVENT DATE:        07/02/1999|
+------------------------------------------------+EVENT TIME:        13:30[EDT]|
| NRC NOTIFIED BY:  HANK STRAHLEY                |LAST UPDATE DATE:  07/29/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LAWRENCE DOERFLEIN   R1      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       15       Power Operation  |15       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - RCIC SYSTEM DECLARED INOPERABLE -                                          |
|                                                                              |
| While performing Reactor Core Isolation Cooling (RCIC) System injection      |
| testing, the licensee declared the RCIC System inoperable due to problems    |
| with the system injection testable check valves. Valve #2ICS*AOV157 did not  |
| indicate open with full flow to the reactor vessel and valve #2ICS*AOV156    |
| continued to indicate open following injection. The licensee declared these  |
| containment isolation valves inoperable and is taking actions to isolate the |
| containment penetration.  The RCIC System injected properly with the         |
| exception of the above noted problem.  Otherwise, the RCIC System operated   |
| properly.  Tech Spec 3.7.4 requires the licensee to restore the RCIC System  |
| to operable status within 14 days.  The High Pressure Core Spray System is   |
| operable.  The licensee will be troubleshooting these valves.                |
|                                                                              |
| The licensee informed the NRC Resident Inspector.                            |
|                                                                              |
| * * * UPDATE AT 1028 ON 7/29/99, BY PITTS RECEIVED BY WEAVER * * *           |
|                                                                              |
| At 1330 on 7/2/99, report was made associated with the Reactor Core          |
| Isolation Cooling (RCIC) inoperability in accordance with                    |
| 10CFR50.72(b)(2)(iii)(D).  RCIC was declared inoperable due to problems with |
| the injection testable check valves which are Primary Containment Isolation  |
| valves.  2ICS*AOV 156 continued to indicate open following injection and     |
| 2ICS*AOV 157 did not indicate open with full flow to the Reactor Vessel.     |
| These containment isolation valves were declared inoperable and actions were |
| taken to isolate the containment penetration.  RCIC injected properly when   |
| tested and injection capabilities were only effected by virtue of the        |
| necessity to comply with isolation requirements.                             |
|                                                                              |
| RCIC testable check valves 21CS*AOV156 and 2ICS*AOV157 failing to properly   |
| close or indicate position are independent of the ability of RCIC to operate |
| and perform its function.                                                    |
|                                                                              |
| Based on the above, RCIC would have operated under all design conditions and |
| was only incapacitated as a result of satisfying Primary Containment         |
| isolation functions.  Therefore this is a retraction of notification made    |
| under 10CFR50.72(b)(2)(iii)(D) (See event notification # 35889).             |
|                                                                              |
| The licensee notified the NRC resident inspector and the Operations Center   |
| notified the R1DO (Kinneman).                                                |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35958       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LASALLE                  REGION:  3  |NOTIFICATION DATE: 07/25/1999|
|    UNIT:  [1] [] []                 STATE:  IL |NOTIFICATION TIME: 22:32[EDT]|
|   RXTYPE: [1] GE-5,[2] GE-5                    |EVENT DATE:        07/25/1999|
+------------------------------------------------+EVENT TIME:        20:21[CDT]|
| NRC NOTIFIED BY:  WILLIAMS                     |LAST UPDATE DATE:  07/30/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |PATRICK HILAND       R3      |
|10 CFR SECTION:                                 |                             |
|AUNA 50.72(b)(1)(ii)(A)  UNANALYZED COND OP     |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       87       Power Operation  |87       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PLANT ENTERED TECH SPEC 3.2.3 LCO ACTION STATEMENT                           |
|                                                                              |
| AT 2021 CDT ON 07/25/99, THE "1B21-N500" PRESSURE TRANSMITTER INDICATION     |
| DROPPED FROM 1000 PSIG TO INDICATED 600 PSIG REACTOR PRESSURE.  THIS         |
| TRANSMITTER IS THE PRIMARY PRESSURE TRANSMITTER TO THE ELECTROHYDRAULIC      |
| SYSTEM (EHC).  DUE TO THIS CHANGE IN PRESSURE INDICATION, THE BACKUP         |
| TRANSMITTER TOOK CONTROL.  IN THIS LINEUP (BACKUP TRANSMITTER IN CONTROL OF  |
| THE EHC), THERE IS NO OTHER BACKUP TRANSMITTER AVAILABLE AND PROCEDURE       |
| "LOA-EH-101" STATES THAT THIS CONDITION IS AN UNANALYZED CONDITION AND THE   |
| PLANT IS TO ENTER TS 3.2.3.  TS 3.2.3 REQUIRES THE REACTOR TO BE <25% POWER  |
| WITHIN 4 HOURS.  THIS CONDITION WAS NOT DETERMINED TO BE AN UNANALYZED       |
| CONDITION UNTIL 2045 CDT ON 07/25/99 UTILIZING THE ABOVE PROCEDURE AND THE   |
| UFSAR.  THE PROBLEM WITH THE TRANSMITTER IS BEING INVESTIGATED TO DETERMINE  |
| WHY IT DOES NOT INDICATE 1000 PSIG.                                          |
|                                                                              |
| THE RESIDENT INSPECTOR WILL BE INFORMED.                                     |
|                                                                              |
| * * *RETRACTION 2253 7/29/99, FROM GRANWALD TAKEN BY STRANSKY * * *          |
| "It was subsequently determined from a detailed evaluation that was          |
| performed in May of 1999, which clearly shows that operation with a pressure |
| regulator out of service at LaSalle is bounded by the thermal limits         |
| calculated for the slow closure of one or more turbine control valves        |
| (TCVs).  The use of the thermal limits reported in the LaSalle Unit 1 Cycle  |
| 8 Core Operating Limits Report for the slow closure of one or more TCVs for  |
| operations with a pressure regulator out of service does not result in       |
| operation of the plant in an unanalyzed condition.  The thermal limits were  |
| adjusted to be in line with the TCV slow closure analysis and plant thermal  |
| limits were declared OPERABLE and Tech Spec 3.2.3 exited within 4 hours.     |
| Therefore, LaSalle Unit 1 was not in an unanalyzed condition as reported in  |
| Event No.35958."                                                             |
|                                                                              |
| The NRC resident inspector will be informed of this retraction by the        |
| licensee.                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Hospital                                         |Event Number:   35971       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  VA COMMONWEALTH UNIVERSITY           |NOTIFICATION DATE: 07/29/1999|
|LICENSEE:  VA COMMONWEALTH UNIVERSITY           |NOTIFICATION TIME: 13:51[EDT]|
|    CITY:  RICHMOND                 REGION:  2  |EVENT DATE:        07/23/1999|
|  COUNTY:                            STATE:  VA |EVENT TIME:             [EDT]|
|LICENSE#:  45-00048-17           AGREEMENT:  N  |LAST UPDATE DATE:  07/29/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |ROBERT HAAG          R2      |
|                                                |                             |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  MARY BETH TAORMINAL          |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|LADM 35.33(a)            MED MISADMINISTRATION  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MEDICAL MISADMINISTRATION                                                    |
|                                                                              |
| On 7/23/99, a medical misadministration occurred during a procedure          |
| involving a "Betacath" brachytherapy device with a strontium-90 source. Due  |
| to a problem with the catheter, a patient received only 2.26 Gy (226 rads)   |
| of the prescribed 14 Gy (1,400 rad) dose. The Betacath device is used during |
| cardiac catherization to prevent restenosis of blood vessels.                |
|                                                                              |
| This event was reported to the licensee's radiation safety office on         |
| 7/29/99. The licensee has contacted the NRC Region II office regarding this  |
| event.                                                                       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35972       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PRAIRIE ISLAND           REGION:  3  |NOTIFICATION DATE: 07/29/1999|
|    UNIT:  [1] [2] []                STATE:  MN |NOTIFICATION TIME: 17:59[EDT]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        07/29/1999|
+------------------------------------------------+EVENT TIME:        16:40[CDT]|
| NRC NOTIFIED BY:  PAT RYAN                     |LAST UPDATE DATE:  07/29/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GEOFFREY WRIGHT      R3      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| CONTROL ROOM SPECIAL VENTILATION SYSTEM DECLARED INOPERABLE                  |
|                                                                              |
| "At approximately 1640 on July 29, 1999, Plant Engineering discovered that a |
| condition existed with door 158 (entry door to 122 Control Room Chiller      |
| Room) on 7/27/99 similar to a condition that existed on 6/25/99 that         |
| resulted in a LER. Further investigation concluded that the condition of     |
| door 158 on 7/27/99 was almost exactly the same as that on 6/25/99. Door 158 |
| was identified as having a broken latch mechanism. The broken latch results  |
| in a breach of the Control Room Special Ventilation System, such that both   |
| trains are to be considered inoperable.                                      |
|                                                                              |
| "Interviews with duty people present during the 7/27/99 breach confirmed     |
| that the door latch was repaired well within an hour from its discovery and  |
| returned to service."                                                        |
|                                                                              |
| The NRC resident inspector has been informed of this event by the licensee.  |
|                                                                              |
| [HOO note: see related EN 35860]                                             |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35973       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT          REGION:  1  |NOTIFICATION DATE: 07/30/1999|
|    UNIT:  [] [2] []                 STATE:  NY |NOTIFICATION TIME: 00:02[EDT]|
|   RXTYPE: [1] GE-2,[2] GE-5                    |EVENT DATE:        07/29/1999|
+------------------------------------------------+EVENT TIME:        23:16[EDT]|
| NRC NOTIFIED BY:  ANTHONY PETRELLI             |LAST UPDATE DATE:  07/30/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN KINNEMAN        R1      |
|10 CFR SECTION:                                 |                             |
|AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD  |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HIGH PRESSURE CORE SPRAY INOPERABLE                                          |
|                                                                              |
| Check valve 2CSH*V16 on the High Pressure Core Spray pump suction from the   |
| suppression pool is not in the IST program plan for reverse flow testing.  A |
| preliminary review indicates that this check valve should be reverse flow    |
| tested.  The HPCS was declared inoperable and the plant entered a 14 day     |
| LCO.  Steps are being taken to retest the valve.                             |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+