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Event Notification Report for March 22, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           03/19/1999 - 03/22/1999

                              ** EVENT NUMBERS **

35487  35488  35489  35490  35491  35492  35493  35494  35495  35496  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35487       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALO VERDE               REGION:  4  |NOTIFICATION DATE: 03/19/1999|
|    UNIT:  [] [2] []                 STATE:  AZ |NOTIFICATION TIME: 11:06[EST]|
|   RXTYPE: [1] CE,[2] CE,[3] CE                 |EVENT DATE:        03/19/1999|
+------------------------------------------------+EVENT TIME:        08:24[MST]|
| NRC NOTIFIED BY:  BRAD EKLUND                  |LAST UPDATE DATE:  03/19/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |PHIL HARRELL         R4      |
|10 CFR SECTION:                                 |                             |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |                             |
|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                                   
+------------------------------------------------------------------------------+
| TRAIN B OF CONTAINMENT SPRAY DECLARED INOPERABLE                             |
|                                                                              |
| "On March 19, 1999 at approximately 0824 MST, engineering personnel          |
| determined that a pipe support on the Unit 2 Train B containment spray       |
| recirc line piping would not perform its function to support the             |
| mini-recirculation piping and could result in a rupture of the pipe during a |
| Recirculation Actuation Signal following a loss of coolant accident.         |
|                                                                              |
| "Operations personnel have declared Train B containment spray system         |
| inoperable per Technical Specification 3.6.6.                                |
|                                                                              |
| "This condition is being reported because suitable redundancy for            |
| Containment Spray (two trains operable) was not maintained and is therefore  |
| considered outside design bases.                                             |
|                                                                              |
| "The event did not result in any challenges to the fission product barrier   |
| or result in any releases of radioactive materials.  There were no adverse   |
| safety consequences or implications as a result of this event.  The event    |
| did not adversely affect the safe operation of the plant or health and       |
| safety of the public.  An investigation is in progress to determine the      |
| cause of the event.                                                          |
|                                                                              |
| "Engineering personnel are preparing a change to the piping support design   |
| with expected completion within the Technical Specification allowed          |
| Completion Time of 72 hours.                                                 |
|                                                                              |
| "This condition does not apply to the other train of Unit 2 or Palo Verde    |
| Units 1 or 3."                                                               |
|                                                                              |
| The licensee informed the NRC Resident Inspector of this notification.       |
|                                                                              |
| * * * UPDATE AT 1635 ON 3/19/99 BY HAZELWOOD, TAKEN BY WEAVER  * * *         |
| The licensee desires to retract this event.  The design intent of the        |
| support is to restrain pipe motion in the vertical direction only.  The      |
| support is not intended to restrain pipe motion in the axial direction.      |
| Subsequent re-inspection of the subject pipe support determined the          |
| existence of a gap beneath the bottom end plate.  Given the existence of     |
| this gap, the pipe support will function as originally intended.             |
| Accordingly, there would be no overload condition and the pipe support is    |
| acceptable and in accordance with design.    Following racking in the pump   |
| breaker and performing a functional run, Operations declared the Train B     |
| Containment Spray System operable.                                           |
|                                                                              |
| The licensee informed the NRC resident inspector.  The HOO notified the R4DO |
| (Harrell).                                                                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35488       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUSQUEHANNA              REGION:  1  |NOTIFICATION DATE: 03/19/1999|
|    UNIT:  [] [2] []                 STATE:  PA |NOTIFICATION TIME: 11:51[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        03/19/1999|
+------------------------------------------------+EVENT TIME:        10:00[EST]|
| NRC NOTIFIED BY:  ROBERT M. PEAL               |LAST UPDATE DATE:  03/19/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JACK MCFADDEN        R1      |
|10 CFR SECTION:                                 |                             |
|ADAS 50.72(b)(2)(i)      DEG/UNANALYZED COND    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| Main Steam Isolation Valves Fail to meet Leakage Criteria                    |
|                                                                              |
| The following report is due to the Main Steam Isolation Valves failing the " |
| as found"  Maximum Combined Pathway Leakage criteria of 300 scfh. This       |
| failure requires a 4 Hr ENS notification under 10CFR50.72(b)(2)(i.). The     |
| overall Total Combined Maximum Pathway Leakage can not to be determined      |
| based on the inability to pressurize the 'C' Outboard and 'D' Inboard Main   |
| Steam Isolation Valves.  The 'as found' Minimum Combined Pathway Leakage is  |
| 255 scfh, which is below the 300 scfh used in the Offsite Dose Analysis. The |
| 'as left' leakage is to be determined following rework of the 'C' Outboard   |
| and 'D' Inboard Main Steam Isolation Valves.                                 |
|                                                                              |
| The licensee has notified the NRC resident inspector.                        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Hospital                                         |Event Number:   35489       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  FLOWER HOSPITAL                      |NOTIFICATION DATE: 03/19/1999|
|LICENSEE:  FLOWER HOSPITAL                      |NOTIFICATION TIME: 12:43[EST]|
|    CITY:  SYLVANIA                 REGION:  3  |EVENT DATE:        03/18/1999|
|  COUNTY:                            STATE:  OH |EVENT TIME:        16:45[EST]|
|LICENSE#:  34-15184-01           AGREEMENT:  N  |LAST UPDATE DATE:  03/19/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |GEOFFREY WRIGHT      R3      |
|                                                |DR. COOL             NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  DR. JUSTICE                  |                             |
|  HQ OPS OFFICER:  DOUG WEAVER                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|LADM 35.33(a)            MED MISADMINISTRATION  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MISADMINISTRATION                                                            |
|                                                                              |
| A Cs-137 BRACHYTHERAPY source was found in a patient's stool during a        |
| routine survey.  The survey was conducted prior to removal of the material   |
| from the patient's room.   The source was one of two being used to provide   |
| an intended dose to the patient of 65 Gray.  Each source had an activity of  |
| 11 mg Radium equivalent.  The other source remained in place during the      |
| treatment period.   The licensee is conducting an investigation to determine |
| how and when the source became dislodged.                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35490       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY            REGION:  1  |NOTIFICATION DATE: 03/19/1999|
|    UNIT:  [] [2] []                 STATE:  PA |NOTIFICATION TIME: 12:58[EST]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        03/12/1999|
+------------------------------------------------+EVENT TIME:        04:29[EST]|
| NRC NOTIFIED BY:  GEORGE STOTLOLIS             |LAST UPDATE DATE:  03/19/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JACK MCFADDEN        R1      |
|10 CFR SECTION:                                 |                             |
|AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| CONTAINMENT EQUIPMENT HATCH NOT PROPERLY SECURED                             |
|                                                                              |
| "On March 12, 1999, it was identified that air was being drawn into the      |
| Beaver Valley Power Station (BVPS) Unit No. 2 containment through the closed |
| equipment hatch while the reactor was being de-fueled. Fuel movement was     |
| halted until the equipment hatch bolts were re-tightened and the inleakage   |
| was terminated. The inleakage was caused by a pressure differential across   |
| the equipment hatch set up by the containment ventilation. The design basis  |
| fuel handling accident for BVPS Unit No. 2 assumes that there is no pressure |
| differential across the containment equipment hatch since the containment    |
| ventilation would be automatically secured upon a high radiation signal. It  |
| was originally believed that the door would have been able to contain any    |
| air transfer without the pressure differential across the door since it was  |
| closed with ten bolts in place versus the four required by Technical         |
| Specification 19.4 during fuel movement.                                     |
|                                                                              |
| "Information was obtained on March 19, 1999 that 1) the containment          |
| equipment hatch may have become ajar due to inadequate support during an     |
| equipment hatch chain hoist preventative maintenance and 2) there was a      |
| sufficient separation between the containment wall and the equipment hatch   |
| door to allow some light to be seen on the inside of containment coming from |
| the outside. Given this information, it could not be concluded that the      |
| containment capability of the equipment hatch would have been sufficient to  |
| have performed its safety function during a fuel handling accident if it     |
| were postulated to occur. Since the BVPS Unit No. 2 design basis fuel        |
| handling accident inside containment concludes that environmental release is |
| precluded, this condition violated the UFSAR safety analysis. Therefore this |
| indication of an air gap through the closed containment equipment hatch is   |
| being reported as a condition that alone could have prevented the            |
| fulfillment of the safety function of structures or systems that are needed  |
| to control the release of radioactive material pursuant to 10 CFR            |
| 50.72(b)(2)(iii)(C)."                                                        |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35491       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 03/19/1999|
|    UNIT:  [] [3] []                 STATE:  NY |NOTIFICATION TIME: 14:50[EST]|
|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        03/19/1999|
+------------------------------------------------+EVENT TIME:        14:10[EST]|
| NRC NOTIFIED BY:  TOM MCKEE                    |LAST UPDATE DATE:  03/19/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JACK MCFADDEN        R1      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|3     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION - FREON RELEASE                                         |
|                                                                              |
| The licensee notified the New York Department of Environmental Conservation  |
| of a freon leak.  More than one pound of freon is believed to have leaked    |
| from the air conditioning unit that supports the Technical Support Center.   |
|                                                                              |
| The licensee will inform the NRC resident inspector.                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35492       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK              REGION:  1  |NOTIFICATION DATE: 03/20/1999|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 04:08[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        03/20/1999|
+------------------------------------------------+EVENT TIME:        02:50[EST]|
| NRC NOTIFIED BY:  ALLEN                        |LAST UPDATE DATE:  03/20/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JACK MCFADDEN        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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THE "A" HPCI WAS DECLARED INOPERABLE, RESULTING IN A 7 DAY LCO ACTION        |
| STATEMENT.                                                                   |
|                                                                              |
| THE "A" HPCI ISOLATION LOGIC WAS DE-ENERGIZED, MAKING HPCI INOPERABLE, DUE   |
| TO A 130VDC BATTERY GROUND.  THIS CONDITION ALSO ACTUATED VALVES "23MOV-15"  |
| (INBOARD STEAM ISOLATION VALVE) AND "23MOV-58" (INBOARD TORUS SUCTION        |
| VALVE).  BOTH PENETRATIONS HAVE BEEN ISOLATED  AND DE-ENERGIZED WITHIN 1     |
| HOUR  AS REQUIRED BY TECH SPECS.  THE CAUSE OF THE GROUND IS UNKNOWN AND     |
| BEING INVESTIGATED.                                                          |
|                                                                              |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35493       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PERRY                    REGION:  3  |NOTIFICATION DATE: 03/20/1999|
|    UNIT:  [1] [] []                 STATE:  OH |NOTIFICATION TIME: 15:11[EST]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        03/20/1999|
+------------------------------------------------+EVENT TIME:        14:01[EST]|
| NRC NOTIFIED BY:  ROBERT SOCHIA                |LAST UPDATE DATE:  03/20/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GEOFFREY WRIGHT      R3      |
|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       90       Power Operation  |90       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION - SODIUM HYPOCHLORITE LEAK                              |
|                                                                              |
| A sodium hypochlorite leak was discovered emanating from the SW/ESW sodium   |
| hypochlorite tank into its surrounding dike.  The leak of about 1500 gallons |
| is completely contained within the dike.  The licensee notified the U.S.     |
| EPA, the Ohio EPA, the U.S. Coast Guard and Lake County.                     |
|                                                                              |
| The NRC resident inspector was informed.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35494       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM                  REGION:  1  |NOTIFICATION DATE: 03/20/1999|
|    UNIT:  [1] [] []                 STATE:  MA |NOTIFICATION TIME: 20:20[EST]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        03/20/1999|
+------------------------------------------------+EVENT TIME:        18:57[EST]|
| NRC NOTIFIED BY:  ERIC OLSON                   |LAST UPDATE DATE:  03/20/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JACK MCFADDEN        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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| RCIC INOPERABLE                                                              |
|                                                                              |
| The licensee declared Reactor Core Isolation Cooling (RCIC) inoperable       |
| because of a problem found during a surveillance.  Relay 13A-k30 contacts 1  |
| - 7 were found to have a high resistance.  These contacts close to provide   |
| the 'A' channel input to the RCIC high level shutdown.  A high resistance    |
| across these contacts may prevent the actuating relay (13A-k38) from         |
| energizing,  and thereby prevent a shutdown of RCIC on a high reactor vessel |
| water level.  The RCIC high water level shutdown requires both channels 'A'  |
| and 'B' signals be present to occur.                                         |
|                                                                              |
| The licensee entered a 14 day LCO because of this condition.   Repair        |
| efforts are in progress.  RCIC remains available for use in the event of an  |
| emergency.                                                                   |
|                                                                              |
| The licensee will inform the NRC resident inspector.                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35495       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DRESDEN                  REGION:  3  |NOTIFICATION DATE: 03/21/1999|
|    UNIT:  [] [2] []                 STATE:  IL |NOTIFICATION TIME: 05:18[EST]|
|   RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3           |EVENT DATE:        03/21/1999|
+------------------------------------------------+EVENT TIME:        03:30[CST]|
| NRC NOTIFIED BY:  MATTSON                      |LAST UPDATE DATE:  03/21/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GEOFFREY WRIGHT      R3      |
|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       99       Power Operation  |99       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| ROD BLOCK MONITORS 7&8 ARE OUT OF SERVICE AND THE PLANT ENTERED AN LCO.      |
|                                                                              |
| THE ROD BLOCK MONITORS (RBM) WERE FOUND TO HAVE INOPERABLE LPRM COUNT        |
| CIRCUITS.  DEPENDING ON THE CONTROL ROD SELECTED, BOTH RBM 7&8 DETECTED MORE |
| LPRM INPUTS THAN WERE ACTUALLY PRESENT.  WITH THIS CONDITION OCCURRING, THE  |
| RBM WOULD NOT PROVIDE THE REQUIRED "INOP" TRIP (ROD BLOCK DUE TO TOO FEW     |
| INPUTS).  THE HI ROD BLOCK TRIP WAS ALSO NON-CONSERVATIVE SINCE LPRM SIGNALS |
| NOT ASSOCIATED WITH THE SELECTED LPRM STRING ROD GROUP WERE BEING AVERAGED   |
| IN WITH THAT GROUP'S NORMAL INPUTS.  AS REQUIRED BY THE LCO ACTION           |
| STATEMENT, ONE (#8) OF THE RBM CHANNELS WAS TRIPPED AND TAKEN OUT OF         |
| SERVICE.                                                                     |
|                                                                              |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35496       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DRESDEN                  REGION:  3  |NOTIFICATION DATE: 03/21/1999|
|    UNIT:  [] [] [3]                 STATE:  IL |NOTIFICATION TIME: 12:43[EST]|
|   RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3           |EVENT DATE:        03/21/1999|
+------------------------------------------------+EVENT TIME:        11:38[CST]|
| NRC NOTIFIED BY:  HAL DODD                     |LAST UPDATE DATE:  03/21/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GEOFFREY WRIGHT      R3      |
|10 CFR SECTION:                                 |                             |
|ASHU 50.72(b)(1)(i)(A)   PLANT S/D REQD BY TS   |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|                                                   |                          |
|3     N          Y       38       Power Operation  |37       Power Operation  |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SHUTDOWN REQUIRED BY TECHNICAL SPECIFICATIONS                                |
|                                                                              |
| The licensee commenced a plant shutdown at 1138 CST because of non-isolable  |
| pressure boundary leakage in the 'B' recirculation loop.    A drywell entry  |
| was initiated due to an increase in the drywell activity reading.  A leak    |
| was discovered from flow element 3-261-9B tap at a tee in a welded fitting   |
| that attaches to the flow venturi.  The leak rate is estimated to be 0.25    |
| gpm.                                                                         |
|                                                                              |
| The licensee plans to bring the plant to cold shutdown to make repairs.  The |
| plant is expected to come off line at 1400 CST and be in cold shutdown by    |
| approximately 1800 CST.                                                      |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+