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Event Notification Report for March 19, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           03/18/1999 - 03/19/1999

                              ** EVENT NUMBERS **

35383  35432  35483  35484  35485  35486  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   35383       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PERRY                    REGION:  3  |NOTIFICATION DATE: 02/18/1999|
|    UNIT:  [1] [] []                 STATE:  OH |NOTIFICATION TIME: 21:39[EST]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        02/18/1999|
+------------------------------------------------+EVENT TIME:        20:40[EST]|
| NRC NOTIFIED BY:  BRIAN STETSON                |LAST UPDATE DATE:  03/18/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MIKE JORDAN          R3      |
|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       97       Power Operation  |97       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LEAKAGE OUTSIDE CONTAINMENT EXCEEDED ITS 60 GPH LIMIT.                       |
|                                                                              |
| AT 2040 ON 02/18/99, RELIEF VALVE #1E12-F0036 ON THE LINE FROM THE RHR HEAT  |
| EXCHANGERS TO THE RCIC SYSTEM WAS DETERMINED TO BE LEAKING AT 75 GPH INTO    |
| THE AUXILIARY BUILDING EQUIPMENT DRAIN SUMP.  THE RCIC SYSTEM IS ALIGNED TO  |
| THE CONDENSATE STORAGE TANK, NOT TO THE SUPPRESSION POOL.  IN THE EVENT THAT |
| THE RCIC SYSTEM IS NEEDED IN AN ACCIDENT, IT COULD ALIGN TO THE SUPPRESSION  |
| POOL, RESULTING IN SUPPRESSION POOL WATER LEAKING OUT OF CONTAINMENT.  THE   |
| PLANT IS NOT IN ANY LCO ACTION STATEMENT AT THIS TIME, BUT WHEN REPAIRS TO   |
| THE VALVE COMMENCES, THE RCIC SYSTEM WILL BE DECLARED INOPERABLE AND THE     |
| LICENSEE WILL ENTER A 14 DAY LCO.  THE HPCS SYSTEM HAS BEEN VERIFIED TO BE   |
| OPERABLE.                                                                    |
|                                                                              |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED BY THE LICENSEE.                     |
|                                                                              |
| * * * RETRACTED AT 0806 EST ON 3/18/99 BY BRIAN STETSON TO FANGIE JONES * *  |
| *                                                                            |
|                                                                              |
| Upon further engineering review, the doses calculated with a leakage of 135  |
| gph were determined to be less that allowed by both 10CFR50 Appendix A and   |
| 10CFR100.  Since no regulatory limits would have been exceeded during an     |
| accident, a condition that was outside of the design basis did not exist.    |
| Therefore, the licensee has retracted this event notification.               |
|                                                                              |
| The licensee informed the NRC Resident Inspector of this retraction.  The    |
| Headquarters Operations Officer informed the R3DO (Geoffrey Wright).         |
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!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35432       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HADDAM NECK              REGION:  1  |NOTIFICATION DATE: 03/02/1999|
|    UNIT:  [1] [] []                 STATE:  CT |NOTIFICATION TIME: 17:24[EST]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        03/02/1999|
+------------------------------------------------+EVENT TIME:        17:17[EST]|
| NRC NOTIFIED BY:  PIONTKOWSKI                  |LAST UPDATE DATE:  03/18/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MICHAEL MODES        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          N       0        Decommissioned   |0        Decommissioned   |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| A POTENTIAL ERROR WITH THE DOSE TO CONTROL ROOM PERSONNEL WAS IDENTIFIED     |
|                                                                              |
| CR-99-0127 IDENTIFIES A POTENTIAL ERROR WITH THE DOSE TO CONTROL ROOM        |
| PERSONNEL DURING A POSTULATED RESIN FIRE ACCIDENT AS DESCRIBED IN THE        |
| LICENSEE'S UPDATED FINAL SAFETY ANALYSIS REPORT (UFSAR).  THE MAXIMUM ORGAN  |
| DOSE REPORTED IN THE UFSAR (SECTION 6.4.4.1) IS 3.83 REM FOR BONE.  USING    |
| THE SAME CONSERVATIVE SOURCE-TERM ASSUMPTIONS GIVEN IN THE UFSAR AND THE     |
| DOSE CONVERSION FACTORS FROM FEDERAL GUIDANCE REPORT 11, THE PRELIMINARY     |
| RECALCULATED DOSE IS 54 REM CDE (BONE) AND 3.2 REM CEDE.  THE 54 REM BONE    |
| DOSE EXCEEDS THE 50 REM LIMIT PRESCRIBED IN 10CFR50 APPENDIX A, GENERAL      |
| DESIGN CRITERION (GDC) 19, "CONTROL ROOM."                                   |
|                                                                              |
| THIS ERROR IS SPECIFIC TO THE CALCULATED CONTROL ROOM DOSE FROM THE RESIN    |
| FIRE ACCIDENT SCENARIO.  A SIMILAR ANALYSIS WAS PERFORMED FOR THE RESIN FIRE |
| ACCIDENT SCENARIO TO CALCULATE THE OFFSITE DOSE TO MEMBERS OF THE PUBLIC.    |
| THIS CALCULATION USED A DIFFERENT METHODOLOGY THAN THE CONTROL ROOM DOSE     |
| ANALYSIS AND HAS BEEN VERIFIED.                                              |
|                                                                              |
| IF THE PLANT OPERATED AS PRESENTLY ALLOWED, THE POTENTIAL EXPOSURE TO        |
| CONTROL ROOM OPERATORS COULD EXCEED THE DESIGN BASIS OF GDC 19 FOR THE       |
| LIMITING RADIOLOGICAL                                                        |
| EVENT, A SPENT RESIN FIRE.  IN ACTUAL PRACTICE, THE REQUIRED RADIOACTIVE     |
| CONTENT OF RESIN DOES NOT EXIST AT ANY ONE PLACE ON SITE, THEREFORE, AN      |
| ACTUAL EVENT EXCEEDING THE GDC 19 CRITERIA IS NOT CURRENTLY POSSIBLE.        |
|                                                                              |
| THE RESIDENT INSPECTOR WILL BE INFORMED.                                     |
|                                                                              |
| * * * UPDATE AT 1813 ON 3/18/99, BY BOWER, TAKEN BY WEAVER * * *             |
| The licensee is retracting this event based on a new calculation using the   |
| actual curie content of the contamination in the resin.  Best estimates put  |
| the bone dose due to a resin fire at slightly over 20 rem, well below the 50 |
| rem limit.  Hoo notified R1DO (McFadden).                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   35483       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 03/18/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 15:25[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        03/17/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        19:51[CST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  03/18/1999|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |GEOFFREY WRIGHT      R3      |
|  DOCKET:  0707001                              |LARRY CAMPER         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  W.G. HALICKS                 |                             |
|  HQ OPS OFFICER:  DOUG WEAVER                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|OCBA 76.120(c)(2)(i)     ACCID MT EQUIP FAILS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SAFETY EQUIPMENT FAILURE                                                     |
|                                                                              |
| "On 3/17/99, at 1951 CST, the C-315 Normetex pump UF6 release detection      |
| system failed.  120 Volt AC circuit breaker No. 5 in C-315 power panel CPD-1 |
| tripped which removed power from both channels of the Normetex UF6 release   |
| detection system.  The breaker trip was determined to be the result of a     |
| failure of the "A" power supply which, along with the (parallel) "B" power   |
| supply, supplies 200 Volt DC power to the Normetex pump UF6 release          |
| detection heads.  The breaker trip removed power from both the "A" and "B"   |
| power supplies, thus disabling the UF6 release detection system.  No other   |
| safety systems in the C-315 were affected by this loss of power.  The        |
| Normetex pump UF6 release detection system was declared inoperable and a     |
| continuous smoke watch was initiated in the affected area as required by TSR |
| 2.3.4.3.  Repairs were immediately initiated and the system was declared     |
| operable at 0138 on 3/18/99, and returned to service.                        |
|                                                                              |
| "This event report is submitted in accordance with Safety Analysis Report    |
| Table 6.9-1, Criteria J.1. And 10 CFR 76.120(c)(2) as a safety equipment     |
| failure.  The NRC Senior Resident Inspector has been notified."              |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35484       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT          REGION:  1  |NOTIFICATION DATE: 03/18/1999|
|    UNIT:  [] [2] []                 STATE:  NY |NOTIFICATION TIME: 16:48[EST]|
|   RXTYPE: [1] GE-2,[2] GE-5                    |EVENT DATE:        03/18/1999|
+------------------------------------------------+EVENT TIME:        16:27[EST]|
| NRC NOTIFIED BY:  ANTHONY PETRELLI             |LAST UPDATE DATE:  03/18/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JACK MCFADDEN        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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OUTSIDE DESIGN BASIS - FIRE PROTECTION PROGRAM                               |
|                                                                              |
| "As part of the corrective actions for LER 99-01, Niagara Mohawk Engineering |
| is performing a review of control circuits associated with the fire          |
| protection program needed during the control room fire scenario.  During     |
| this review engineering identified that the control circuits for the service |
| water intake bar rack heaters are not capable of isolation from the control  |
| room.  If a control room fire were to occur, these control circuits and      |
| associated heaters may not function.  The bar rack heaters are required to   |
| operate on each service water intake structure to prevent the formation of   |
| anchor ice which would cause a loss of service water flow required to        |
| support safe shutdown, when lake temperature is less than 39 degrees F.      |
|                                                                              |
| "As compensatory action for this deficiency, a roving fire patrol is being   |
| established once per 24 hours in the control room, relay room, and adjacent  |
| cable raceway areas.  Fire detection and suppression automatic systems are   |
| currently in service."                                                       |
|                                                                              |
| The licensee informed the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35485       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PEACH BOTTOM             REGION:  1  |NOTIFICATION DATE: 03/18/1999|
|    UNIT:  [2] [3] []                STATE:  PA |NOTIFICATION TIME: 17:33[EST]|
|   RXTYPE: [2] GE-4,[3] GE-4                    |EVENT DATE:        03/18/1999|
+------------------------------------------------+EVENT TIME:        17:00[EST]|
| NRC NOTIFIED BY:  PAT NAVIN                    |LAST UPDATE DATE:  03/18/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JACK MCFADDEN        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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       100      Power Operation  |100      Power Operation  |
|3     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| POTENTIAL FOR FIRE INDUCED FLOODING                                          |
|                                                                              |
| During a review of the Fire Safe Shutdown (FSSD) methodology, it was         |
| determined that potential damage from a postulated fire in Fire Areas 6N     |
| (Unit 2), 6S (Unit 2), 13N (Unit 3) and 13S (Unit 3) could result in         |
| spurious operation of high/low pressure interface MOVs and air operated      |
| valves in the RHR or Core Spray systems.  The sustained opening of these     |
| valves could result in pressure relief valve discharge and resultant         |
| unacceptable flooding of a sump pump room in the Unit 2 or Unit 3 Reactor    |
| Building.  These sump pump rooms contain instruments associated with the     |
| HPCI and RCIC systems.  Water damage to these instruments may result in loss |
| of these systems which are required for FSSD in the identified fire areas.   |
| RHR and Core Spray piping integrity would be maintained during the           |
| postulated event.                                                            |
|                                                                              |
| Previous analysis did not adequately consider potential effects of the       |
| flooding on other systems.  Hourly roving fire watch patrol inspections have |
| been established for the identified fire areas.  A temporary plant           |
| alteration is being pursued to remove power from one of the valves in the    |
| impacted high/low pressure interfaces which will be adequate to isolate the  |
| water flow paths.                                                            |
|                                                                              |
| This condition represents a failure to maintain the provisions of the Fire   |
| Protection Program (Appendix R to 10 CFR 50).                                |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   35486       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  U.S. STEEL                           |NOTIFICATION DATE: 03/18/1999|
|LICENSEE:  U.S. STEEL                           |NOTIFICATION TIME: 17:42[EST]|
|    CITY:  GARY                     REGION:  3  |EVENT DATE:        03/18/1999|
|  COUNTY:                            STATE:  IN |EVENT TIME:        12:00[CST]|
|LICENSE#:  13-07964-07           AGREEMENT:  N  |LAST UPDATE DATE:  03/18/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |GEOFFREY WRIGHT      R3      |
|                                                |JOSEPHINE PICCONE    NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  DEAN LARSON                  |                             |
|  HQ OPS OFFICER:  DOUG WEAVER                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NDAM                     DAMAGED GAUGE/DEVICE   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MOISTURE DENSITY GAUGE DAMAGED DURING MAINTENANCE                            |
|                                                                              |
| The licensee reported that a Texas Nuclear moisture density gauge, model     |
| number 5010A, serial number B153, was damaged by a cutting torch during      |
| maintenance activities.   The gauge contains a 1 Ci Am-241 source.  The      |
| torch cut a small hole in the outer case of the gauge.   The gauge was       |
| surveyed for both loose contamination and higher than normal radiation       |
| levels.  Both surveys indicated that the source had not been damaged and was |
| stowed in its shielded position.                                             |
|                                                                              |
| The gauge has been removed from service pending a review by the device       |
| manufacturer.  There were no personnel over exposures as a result of this    |
| event.                                                                       |
+------------------------------------------------------------------------------+