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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!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 | |
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| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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 |
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| 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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