Event Notification Report for July 15, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
07/14/1999 - 07/15/1999
** EVENT NUMBERS **
35915 35918 35919 35920
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|General Information or Other |Event Number: 35915 |
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| REP ORG: IDAHO NAT. ENG & ENVIRONMENTAL LAB |NOTIFICATION DATE: 07/12/1999|
|LICENSEE: IDAHO NAT. ENG & ENVIRONMENTAL LAB |NOTIFICATION TIME: 23:55[EDT]|
| CITY: REGION: 4 |EVENT DATE: 07/12/1999|
| COUNTY: STATE: ID |EVENT TIME: 21:33[MDT]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 07/14/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |BLAIR SPITZBERG R4 |
| |JOHN SURMEIER NMSS |
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| NRC NOTIFIED BY: BROWN | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NINF INFORMATION ONLY | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| THE IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY DECLARED AN ALERT |
| DUE TO LOSS OF OFF SITE POWER AND A DIESEL FAILURE. |
| |
| THE LABORATORY REPORTED THAT THEY HAD A LOSS OF COMMERCIAL POWER DUE TO A |
| FIRE IN THE ELECTRICAL SUBSTATION. THERE WAS ALSO A FAILURE OF THE DIESEL |
| GENERATOR. THIS CLASSIFICATION IS A DOE TYPE ALERT AND NOT A NRC TYPE |
| ALERT. THE LABORATORY DOES HAVE TMI FUEL ON SITE, BUT IT IS NOT AFFECTED BY |
| THIS ALERT. |
| |
| *** UPDATE ON 7/13/99 @ 0045 BY BROWN TO GOULD *** |
| |
| THEY UPGRADED TO A DOE TYPE SITE AREA EMERGENCY DUE TO THE LOSS OF POWER |
| WITH THE FAILURE TO START OF ONE STANDBY DIESEL GENERATOR AND THE FAILURE OF |
| ONE OPERATING STANDBY DIESEL GENERATOR. THIS SITE AREA IS ALSO A DOE |
| GENERATED CLASSIFICATION AND NOT A NRC GENERATED CLASSIFICATION. |
| |
| **** UPDATE ON 7/13/99 @ 0356 FROM GARCIA TO GOULD **** |
| |
| OFF SITE POWER RESTORED AT 0140 MDT AND EVENT WAS TERMINATED AT THAT TIME. |
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|Power Reactor |Event Number: 35918 |
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| FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 07/14/1999|
| UNIT: [1] [2] [] STATE: NJ |NOTIFICATION TIME: 12:25[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 07/13/1999|
+------------------------------------------------+EVENT TIME: 14:00[EDT]|
| NRC NOTIFIED BY: RUSS GUMBERT |LAST UPDATE DATE: 07/14/1999|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN WHITE R1 |
|10 CFR SECTION: | |
|NLTR LICENSEE 24 HR REPORT | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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 |
| | |
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EVENT TEXT
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| LICENSEE 24-HOUR REPORT DUE TO 10 CFR PART 50, APPENDIX R ISSUE |
| |
| "During on-going review of Salem Fire Protection Program and the post fire |
| safe shutdown analysis it was determined that cables associated with the |
| limit switches for both of the service water header valves (SW22) are routed |
| through the same fire protection area, in close proximity (mechanical |
| penetration area). This is not in conformance with the approved fire |
| protection program. In the event of fire in this area, hot shorts, although |
| highly unlikely, are required to be postulated per NRC guidance, in both of |
| these cables simultaneously. These shorts would result in the closure of |
| both of the header valves with the attendant loss of service water to safety |
| related equipment. Long term loss of service water would result in loss of |
| some equipment necessary to maintain safe shutdown, if left uncorrected. |
| |
| "The area in question has been subject to compensatory actions due to the |
| on-going fire wrap issues which had been previously identified. Based on |
| this, if a fire were to occur it would be detected and extinguished before |
| the postulated failure would occur. In the unlikely event that detection did |
| not occur simple non-heroic, straight forward operator action could easily |
| correct the resulting deficiency such that safe shutdown would be |
| maintained. |
| |
| "This is not an equipment operability concern because adequate compensatory |
| actions are in place and were in place prior to discovery. the likelihood of |
| the event is extremely low. No further immediate actions are necessary. |
| Current plans are to perform a design change which will eliminate the |
| concern. |
| |
| "This report is being made to the NRC in accordance with Section 2.1 of the |
| Salem Unit 2 Operating License as a condition found in violation of the: |
| requirements contained in Operating License Section 2.C.1O Fire Protection. |
| There is no significant impact on the public health and safety." |
| |
| The NRC resident inspector has been informed of this event notification by |
| the licensee. |
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|Power Reactor |Event Number: 35919 |
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| FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 07/14/1999|
| UNIT: [3] [] [] STATE: FL |NOTIFICATION TIME: 17:25[EDT]|
| RXTYPE: [3] B&W-L-LP |EVENT DATE: 07/14/1999|
+------------------------------------------------+EVENT TIME: 13:30[EDT]|
| NRC NOTIFIED BY: WILLIAM KISSNER |LAST UPDATE DATE: 07/14/1999|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ANN BOLAND R2 |
|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 |
| | |
| | |
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EVENT TEXT
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| OFFSITE NOTIFICATION DUE TO NPDS PERMIT VIOLATION |
| |
| The licensee notified the Florida Department of Environmental Protection |
| regarding the exceedance of the point of discharge (POD) temperature limit |
| specified in the NPDS permit. |
| |
| At 1145, all 'helper' cooling towers in the circulating water discharge |
| canal were unexpectedly lost due to maintenance activities. At that time, |
| the POD temperature was 95.5 degrees. The Unit 1&2 supervisor requested that |
| compensatory actions be taken to maintain the POD temperature less that the |
| NPDS limit of 96.5 degrees; however, the POD temperature continued to |
| increase. At 1310, the POD temperature exceeded the 96.5 degree limit. The |
| NPDS permit prohibits exceeding 96.5 degrees for greater than 3 hours. |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
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|Fuel Cycle Facility |Event Number: 35920 |
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| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 07/14/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 18:16[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 07/13/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 21:23[CDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 07/14/1999|
| CITY: PADUCAH REGION: 3 +-----------------------------+
| COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION |
|LICENSE#: GDP-1 AGREEMENT: Y |RONALD GARDNER R3 |
| DOCKET: 0707001 |JOHN GREEVES NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: THOMAS WHITE | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| 24-HOUR NRC BULLETIN 91-01 REPORT |
| |
| "At 2123 CDT on 7/13/99, the Plant Shift Superintendent was notified that a |
| product cylinder had been washed In the C-400 Cylinder Wash facility without |
| independent verification of cylinder heel weight, This is in violation of |
| NCSA.400.002. Product cylinders are required to be weighed prior to washing |
| as an independent verification of the Indicated heel weight. A weight ticket |
| is used to calculate the cylinder heel weight and this ticket was not |
| attached to the cylinder wash data sheet. The weight ticket has subsequently |
| been found and the heel weight shown to be acceptable. Although the cylinder |
| heel weight was within the maximum allowable weight, double contingency was |
| not maintained since the independent verification of the heel weight was not |
| performed at the time the cylinder was washed." |
| |
| The NRC resident inspector has been informed of this event. |
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Page Last Reviewed/Updated Thursday, March 25, 2021