Event Notification Report for October 18, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
10/17/2000 - 10/18/2000
** EVENT NUMBERS **
37401 37429 37433 37434
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Fuel Cycle Facility |Event Number: 37401 |
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| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 10/02/2000|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 22:52[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 10/02/2000|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 15:41[EDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 10/17/2000|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |JOHN MADERA R3 |
| DOCKET: 0707002 |BRIAN SMITH NMSS |
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| NRC NOTIFIED BY: ERIC SPAETH | |
| HQ OPS OFFICER: LEIGH TROCINE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NCFR NON CFR REPORT REQMNT | |
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| | |
| | |
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EVENT TEXT
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| HISTORICAL INFORMATION REGARDING A FAILURE TO COMPLETE X-333 LOW ASSAY |
| WITHDRAWAL (LAW) COMPRESSOR PYROTRONIC SMOKE DETECTION SYSTEM ENGINEERING |
| MODIFICATIONS AS DESIGNED (24-hour report) |
| |
| The following text is a portion of a facsimile received from Portsmouth |
| personnel: |
| |
| "The engineering modifications to the X-333 LAW compressor Pyrotronic smoke |
| detection system were not completed as designed. The modifications were |
| intended to cause the safety system to alarm with only one smoke head firing |
| instead of requiring two smoke heads to activate the alarm. The |
| investigation into this matter was completed 10/02/00 at 1541 [hours]. The |
| investigation identified that on one occasion, a LAW station compressor was |
| in an applicable operating mode where the Pyrotronic smoke detection safety |
| system was required to be operable and one of the heads was in fact |
| inoperable making the system inoperable. Operations personnel did post an |
| immediate smoke watch to maintain [Technical Safety Requirement (TSR)] |
| compliance." |
| |
| "This finding is reportable to the NRC as a 24-hour event due to the fact |
| the equipment was required by the TSR to be available and operable and |
| should have been operating, and no redundant equipment was available to |
| provide the required safety function." |
| |
| "Note: The engineering modifications were completed 10/01/00, and |
| applicable [post-maintenance tests were completed satisfactorily]." |
| |
| It was reported that the inoperable head that was identified to be |
| inoperable on 10/01/99, but this issue was not identified until the |
| investigation was completed today (10/02/00) at 1541 hours. It was also |
| reported that there was nothing unusual or misunderstood and that all |
| systems functioned as required. |
| |
| NOTE: The X-333 building LAW station was reported to be a UF6 withdrawal |
| station. |
| |
| Portsmouth personnel have notified the NRC resident inspector and plan to |
| notify the Department of Energy site representative. |
| |
| * * * UPDATE 2125EDT ON 10/17/00 FROM KURT SISLER TO S. SANDIN * * * |
| |
| "NRA [Nuclear Regulatory Affairs] has reviewed the basis for the above NRC |
| event notification and determined that this event can be retracted. The |
| following provides the basis for this conclusion. |
| |
| "On October 2, 2000, the NRC was notified of a design problem which caused |
| the LAW UF6 Smoke Detection system to be inoperable at a time when the |
| system was required to be operable in accordance with TSR 2.5.3.3 (outside |
| each compressor housing one smoke detector must be operable in modes II or |
| III). The design problem resulted from the fact that Pyrotronics smoke |
| detectors were installed in series. In this configuration, the failure of |
| one detector could prevent the redundant detector from activating the alarm |
| contacts in the event of a UF6 release. |
| |
| "A review was conducted by engineering to determine if LAW had ever been in |
| Mode II or III with a failed outside compressor housing Pyrotronics |
| detector. The review identified one occasion in the past where this was the |
| case. As a result of the series configuration, the remaining Pyrotronics |
| detector would not have been able to perform its design function at that |
| time. Although there were CADP smoke detectors available for this area, |
| operating procedures did not recognize that CADP smoke detectors provided |
| backup to the Pyrotronics detectors. Based on the fact that the Pyrotronics |
| smoke detection system was inoperable and no redundant equipment was |
| available to perform the required safety function, the PSS notified the NRC |
| of this past safety system failure. This safety system failure was |
| documented on Problem Report PR-PTS-00-04649. |
| |
| "A followup evaluation by engineering confirmed that there was an outside |
| compressor housing CADP smoke detector available and operable at the time |
| the event occurred. The evaluation also confirmed that the SAR, Table |
| 3.2-4B, recognizes that CADP detectors provide smoke detection for outside |
| compressor enclosures. Engineering also confirmed that CADP detectors were |
| available and operable in all cases since March 3,1997, when any single |
| Pyrotronics head was inoperable. |
| |
| "Based on the above, redundant outside compressor housing CADP smoke |
| coverage was available at all times when the Pyrotronics heads were |
| inoperable and this event may be retracted." |
| |
| The NRC resident inspector was informed. Notified R3DO(Lanksbury) and |
| NMSS(Holonich). |
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|Power Reactor |Event Number: 37429 |
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| FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 10/14/2000|
| UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 05:14[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 10/14/2000|
+------------------------------------------------+EVENT TIME: 03:24[CDT]|
| NRC NOTIFIED BY: WILLIAM GREEN |LAST UPDATE DATE: 10/18/2000|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DAVE LOVELESS R4 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 A/R Y 100 Power Operation |0 Hot Shutdown |
| | |
| | |
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EVENT TEXT
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| AUTOMATIC REACTOR SCRAM DUE TO A MAIN GENERATOR TRIP FOR UNKNOWN REASONS |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "At 0324 [CDT], a reactor scram occurred due to a main generator trip. |
| Group isolations 2, 3[, and] 6 occurred due to low reactor water level. The |
| lowest [reactor water] level recorded was -20 inches on [the] wide range |
| level recorder. Reactor water level recovered, and both reactor [feedwater] |
| pumps tripped on high reactor water level. Group isolations have been |
| verified and reset. [The] 'A' reactor [feedwater] pump has been returned to |
| service and is being used to control water level. [High pressure coolant |
| injection] and [reactor core isolation cooling] did not inject and were not |
| needed to control reactor water level. The plant will be placed in Cold |
| Shutdown. The electrical grid is stable." |
| |
| The licensee stated that all control rods fully inserted and that all |
| systems functioned as required. The licensee also stated that alternate rod |
| insertion initiated as a result of high pressure due to the transient. The |
| highest pressure observed was 1,085 psi. None of the relief valves lifted, |
| and the main steam isolation valves remained open throughout the event. |
| Steam is currently being dumped to the condenser. |
| |
| In addition, the licensee stated that the cause of the main generator trip |
| is currently under investigation. There were no related surveillance or |
| maintenance activities ongoing at the time of the event. |
| |
| The licensee notified the NRC resident inspector. |
| |
| * * * UPDATE on 10/18/00 at 0428 ET by Myers taken by MacKinnon * * * |
| |
| A detailed review of the plant response to the scram has been conducted. |
| This review indicated the following clarification to the initial report are |
| needed: |
| |
| Alternate Rod Insertion initiated on low level, rather than high pressure. |
| The low level was not in long enough to trip the Recirculation pumps. The |
| pumps trip after a 9 second delay, and the low level signal was only in for |
| ~ 7 seconds. |
| |
| Initial indications were that reactor pressure had reached 1085 psig, based |
| on pressure recorder LRPR97, the highest reading of the pressure recorders. |
| Additional pressure recorders and the plant computer indicate pressure |
| reached a maximum of ~ 1068 psig. Evaluation of the recorder indicates it |
| is in calibration, and the "overshoot" of indicated pressure is due to |
| mechanical characteristics of the recorder linkage. NRC R4DO (John Pellet) |
| notified. |
| |
| The NRC Resident Inspector was informed of this update by the licensee. |
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|Power Reactor |Event Number: 37433 |
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| FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 10/17/2000|
| UNIT: [1] [2] [] STATE: IL |NOTIFICATION TIME: 12:13[EDT]|
| RXTYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 10/16/2000|
+------------------------------------------------+EVENT TIME: 18:30[CDT]|
| NRC NOTIFIED BY: DARYL NOHR |LAST UPDATE DATE: 10/17/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ROGER LANKSBURY R3 |
|10 CFR SECTION: | |
|HFIT 26.73 FITNESS FOR DUTY | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
|2 N Y 95 Power Operation |95 Power Operation |
| | |
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EVENT TEXT
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| 24-HOUR FITNESS-FOR-DUTY REPORT INVOLVING A CONTRACT SUPERVISOR |
| |
| A contract supervisor was determined to be under the influence of alcohol |
| during a test for cause. The individual's access to the plant has been |
| terminated. Contact the Headquarters Operations Officers for additional |
| details. |
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|Power Reactor |Event Number: 37434 |
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| FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 10/17/2000|
| UNIT: [3] [] [] STATE: LA |NOTIFICATION TIME: 22:15[EDT]|
| RXTYPE: [3] CE |EVENT DATE: 10/17/2000|
+------------------------------------------------+EVENT TIME: 19:53[CDT]|
| NRC NOTIFIED BY: BRUCE PROCTOR |LAST UPDATE DATE: 10/17/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN PELLET R4 |
|10 CFR SECTION: | |
|ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
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EVENT TEXT
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| INDICATION OF RCS PRESSURE BOUNDARY LEAKAGE DISCOVERED DURING INSPECTION OF |
| PRESSURIZER HEATER SLEEVE |
| |
| "A SMALL AMOUNT OF BORIC ACID WAS DISCOVERED IN THE AREA AROUND PRESSURIZER |
| HEATER SLEEVE NUMBER F4 DURING A BARE METAL INSPECTION PERFORMED ON |
| 10/17/00. THE BORIC ACID IS BELIEVED TO BE EVIDENCE OF PRIMARY STRESS |
| CORROSION CRACKING OF THE INCONEL ALLOY 600 HEATER SLEEVE. THE BORIC ACID |
| IS BELIEVED TO BE EVIDENCE OF REACTOR COOLANT SYSTEM (RCS) PRESSURE BOUNDARY |
| LEAKAGE, CONSTITUTING A DEGRADATION OF THE RCS PRESSURE BOUNDARY." |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021