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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!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 |
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| 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 !!!!!!!
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|Power Reactor |Event Number: 35432 |
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| 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
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| 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). |
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+------------------------------------------------------------------------------+
|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." |
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|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. |
+------------------------------------------------------------------------------+
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|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. |
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