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Event Notification Report for January 27, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           01/26/1999 - 01/27/1999

                              ** EVENT NUMBERS **

35206  35239  35317  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   35206       |
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| FACILITY: PERRY                    REGION:  3  |NOTIFICATION DATE: 12/30/1998|
|    UNIT:  [1] [] []                 STATE:  OH |NOTIFICATION TIME: 19:03[EST]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        12/30/1998|
+------------------------------------------------+EVENT TIME:        16:00[EST]|
| NRC NOTIFIED BY:  HENRY KELLY                  |LAST UPDATE DATE:  01/26/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MONTE PHILLIPS       R3      |
|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  |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| 24-HOUR REPORT REQUIRED BY PLANT OPERATING LICENSE DUE TO VIOLATION OF       |
| TECHNICAL SPECIFICATIONS                                                     |
|                                                                              |
| The licensee has discovered that a solenoid-operated isolation valve on a    |
| 3/8" diameter sample line from the secondary containment was excluded from   |
| the plant technical specifications (TS), and, consequently, it was not       |
| subject to surveillances required by the TS.  The valve is located on a      |
| secondary containment atmosphere sample line which connects to the           |
| post-accident sampling system.  The licensee has verified that the valve is  |
| closed.                                                                      |
|                                                                              |
| The NRC resident inspector has been informed of this event by the licensee.  |
|                                                                              |
| * * * UPDATE AT 2117 EST ON 01/14/99 FROM BRIAN STETSON TO S. SANDIN * * *   |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "During the extent of condition investigation of Condition Report 98-2142,   |
| it was identified that instrument vent and drain valves associated with the  |
| reactor core isolation cooling system (E51) and the annulus exhaust gas      |
| treatment system (M15) could fit the definition of secondary containment     |
| isolation valves as discussed in Technical Specification Bases 3.6.4.2.      |
| However, these valves are not surveilled and checked closed every 31 days as |
| required by Surveillance Requirement 3.6.4.2.1.  There are 12 valves (3/8")  |
| associated with E51, and 8 valves (1/4") associated with M15."               |
|                                                                              |
| The licensee plans to continue its evaluation and has informed the NRC       |
| Resident Inspector.  The NRC Operations Officer notified the R3DO (Gavula).  |
|                                                                              |
| * * * UPDATE 1347 EST ON 1/26/99 FROM FRED SMITH TO S.SANDIN * * *           |
|                                                                              |
| "Update to notification ENF 35206. (Retraction)                              |
|                                                                              |
| "The event notification of 12/30/98 is being retracted based on an           |
| engineering determination that the 3/8" secondary containment atmosphere     |
| sample line that connects to the post accident sampling system is not a      |
| secondary containment isolation valve (SCIV).  Additionally, the sample      |
| valve is required to be opened post accident.  Surveillance requirement (SR) |
| 3.6.4.2.1 requires, in part, to verify each secondary containment isolation  |
| valve that is required to be closed during an accident condition is closed.  |
| The sample valve is not subject to the specification or the surveillance     |
| requirement and no report is required by the plant operating license due to  |
| a violation of TS.                                                           |
|                                                                              |
| "The event notification of 1/14/99 is also being retracted based on the      |
| engineering determination that the 12 valves (3/8") associated with reactor  |
| core isolation cooling and the 8 valves (1/4") associated with annulus       |
| exhaust gas treatment are also not secondary containment isolation valves.   |
| These valves are not subject to TS 3.6.4.2 and SR 3.6.4.2.1 and no report is |
| required by the plant operating license due to a violation of TS."           |
|                                                                              |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.  NOTIFIED R3DO(VEGEL).     |
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|Power Reactor                                    |Event Number:   35239       |
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| FACILITY: RIVER BEND               REGION:  4  |NOTIFICATION DATE: 01/11/1999|
|    UNIT:  [1] [] []                 STATE:  LA |NOTIFICATION TIME: 16:56[EST]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        01/11/1999|
+------------------------------------------------+EVENT TIME:        15:20[CST]|
| NRC NOTIFIED BY:  RUSS GODWIN                  |LAST UPDATE DATE:  01/26/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BLAIR SPITZBERG      R4      |
|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       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
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| NOTIFICATION TO STATE DEPARTMENT OF ENVIRONMENTAL QUALITY                    |
|                                                                              |
| "On January 11, 1999, RBS personnel made a report to the Louisiana           |
| Department of Environmental Quality related to a potential defect in fuel    |
| cladding. A previous report was made on September 21, 1998, and updated on   |
| October 22, 1998. RBS personnel have continued to monitor plant conditions   |
| after the first two had been suppressed. Chemistry sampling and power        |
| suppression results indicate a probable third fuel failure. Indications      |
| could be caused by a previously identified fuel failure.                     |
|                                                                              |
| "The plant is operating at 100% power with radioactive releases well below   |
| the limits of the Technical Requirements Manual and 10 CFR 20. Plant         |
| personnel continue to implement site procedures to address the issue, and    |
| take appropriate actions."                                                   |
|                                                                              |
| The NRC resident inspector has been informed of this notification by the     |
| licensee.                                                                    |
|                                                                              |
| * * * UPDATE 1507 EST ON 1/26/99 FROM JOEY CLARK TO S.SANDIN * * *           |
|                                                                              |
| "On January 26, 1999 [at 1305 CST], RBS personnel made a report to the       |
| Louisiana Department of Environmental Quality related to a potential defect  |
| in fuel cladding.  A previous report was made on September 21,1998, and      |
| updated on October 22, 1998, and on January 11,1999.  Plant instrumentation  |
| and chemistry sampling indicates RBS has three (3) apparent fuel leakers and |
| a probable fourth fuel leaker adjacent to a previously identified and        |
| suppressed fuel leaker.                                                      |
|                                                                              |
| "The plant is operating at 94.5% power with radioactive releases well below  |
| the limits of the Technical Requirements Manual and 10CFR20.   Plant         |
| personnel continue to implement site procedures to address this issue, and   |
| take appropriate actions."                                                   |
|                                                                              |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.  NOTIFIED R4DO(MARSCHALL). |
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+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   35317       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 01/26/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 15:25[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        01/26/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        09:15[CST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  01/26/1999|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |TONY VEGEL           R3      |
|  DOCKET:  0707001                              |JOSEY PICCONE        NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  TOM WHITE                    |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| 24-HOUR NRC 91-01 BULLETIN NOTIFICATION INVOLVING FAILURE TO MAINTAIN DOUBLE |
| CONTINGENCY                                                                  |
|                                                                              |
| "On 1/25/99 at 1430 CST, NCS [nuclear criticality safety] Incident report    |
| NCS-INC-99-001 was identified via ATR [problem report] as being incorrect.   |
| This NCS incident report was incorrectly classified on 1/12/99 and was       |
| subsequently not reported. The original NCS incident report concerned a pump |
| subassembly which had been removed and the Post NDA [non-destructive assay]  |
| had not been performed within 24 hours as required by TSR 2.5.4.2.  It       |
| incorrectly identified that this did not constitute a loss of a leg of the   |
| double contingency principle. Upon further review, NCS has determine that    |
| one of the legs of the double contingency principle is established by the    |
| independent verification of an always safe mass by post-removal NDA          |
| measurements performed within 24 hours of removal.  Since this did not occur |
| in the assumed time frame, double contingency was not maintained even though |
| the NDA results did confirm an always safe mass.                             |
|                                                                              |
| "Ropes/posting used to isolate personnel from area implemented on 1/12/99    |
| were removed that day when post-removal NDA results were obtained.           |
|                                                                              |
| "This event is being categorized as a 24-hour event in accordance with       |
| Safety Analysis Report Table 6.9-1, Criteria A.4.a and NRC Bulletin 91-01    |
| Supplement 1 report."                                                        |
|                                                                              |
| THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED AND THE DOE SITE REPRESENTATIVE |
| WILL BE INFORMED.                                                            |
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