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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    |
+------------------------------------------------+                             |
| 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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