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 Entered dateEvent description
ENS 4802213 June 2012 16:27:00

While reviewing Maintenance Work Package 'Performance of the C-335 Annual CMS Surveillance' from April 28, 2012 an error was identified. Procedure 'C-335 CMS Maintenance And Testing' requires an audibility check if the as-found values for the regulator air pressure drift feeding the Criticality Accident Alarm System (CMS) air horns is >?12 psig. However, an audibility check was not performed as required at six locations all on the cell floor of the process building that were discovered to be out-of-tolerance. All air pressure regulators were adjusted to within acceptable-as-left tolerances prior to the system being made operable on April 28. Without the audibility testing being performed, the audibility of the C-335 CMS was questionable prior to the April testing. On June 13, 2012, a work package was developed to recreate the pressures encountered on April 28 and to test the audibility of the CMS. Subsequent testing has shown that three of the CMS horns fed by out-of-tolerance pressure regulators may not have provided the required sound levels necessary for audibility in those areas. This is failure of safety equipment required by TSR 2.4.4.2. This event is reportable as a 24 hour event in accordance with 10 CFR 76.120(c)(2), 'An event in which equipment is disabled or fails to function as designed when: (i) the equipment is required by a TSR to prevent releases, prevent exposures to radiation and radioactive materials exceeding specified limits, mitigate the consequences of an accident, or restore this facility to a pre-established safe condition after an accident; (ii) the equipment is required by a TSR to be available and operable and either should have been operating or should have operated on demand; and (iii) no redundant equipment is available and operable to perform the required safety function.' The NRC Resident Inspector has been notified of this event. PGDP Assessment and Tracking Report No. ATRC-12-1496; PGDP Event Report No. PAD-2012-03; Responsible Division: Operations

  • * * RETRACTION FROM BILLY WALLACE TO JOHN SHOEMAKER AT 1641 EDT ON 07/16/2012 * * *

Subsequently, the C-335 CAAS air horns have been tested in the as-found conditions from April 28, 2012. Using the original design audibility criteria in the most limiting condition, the CAAS horn audibility was found to be acceptable. Therefore, the system would have been able to perform its intended safety function in the April 28, 2012, as-found condition. Based on the testing and an engineering evaluation, the event notification is being retracted. The licensee has notified the NRC Resident Inspector. Notified R2DO (Calle) and NMSS (Silva).

ENS 4748328 November 2011 19:12:00

At 0930 CST on 11-28-11, during annual inspection of the C-400/C-409 floor drains and sumps according to procedure CP4-CU-CH6021, a chemical operator identified that an eye wash drain was no longer properly sealed around the concrete base and would not prevent solutions from entering the drain if challenged. NCSA (Nuclear Criticality Safety Assessment) CHM-001 requires specific drains to be sealed to prevent the accumulation of fissile material in the unsafe geometry drain system. In violation of NCSA CHM-001, the poured concrete base surrounding the eye wash drain #147 in C-400 was discovered to be broken loose from the floor so that it could no longer provide a seal against spilled uranium solution getting into the drain system. SAFETY SIGNIFICANCE OF EVENTS Although the concrete block has broken loose from the floor, only a small crack exists at the base of the concrete block which would present a torturous solution path to the drain. Therefore, a large release will be prevented from transporting a significant amount of solution to the drain system. While the Safety Related Item failed, no fissile material was released onto the C-400 building floor and no fissile material entered the drain system through this drain. POTENTIAL CRITICALITY PATHWAYS INVOLVED In order for a criticality to occur a release of greater than a safe mass of uranium onto the floor of C-400 would have to occur. A solution containing greater than a safe mass would then have to migrate to the drain, leak into the drain system, and accumulate in an unfavorable geometry. CONTROLLED PARAMETERS The two process conditions relied upon for double contingency for this scenario are mass and geometry. ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL Process is designed to handle uranium contaminated solutions with a maximum assay of 5.5 wt.% U235. NUCLEAR CRITICALITY SAFETY CONTROL AND DESCRIPTION OF THE FAILURES OR DEFICIENCIES The first leg of double contingency is based on the mass of uranium in solution form that leaks out of the system. The analysis credits both the integrity of the system and the fact that the tanks and piping are inspected for leakage. Small leaks will be identified and fixed before they have leaked enough uranium mass in solution to be a concern. Since no leakage has occurred, this control was not violated. The second leg of double contingency relies on the integrity of the floor drain seals to prevent uranium solution from getting into the unsafe geometry drain system. Since a pathway from the floor to the drain system exists, this control was violated and the parameter was not maintained. Because the parameter was not maintained double contingency was not maintained. Double contingency was not maintained because the geometry parameter was not maintained. CORRECTIVE ACTIONS 1. Stop fissile solution operations in the vicinity of the eyewash drain. This was completed at 1000 CST on

    11-28-11.
 2. Restore the seal to this drain. Pending
 3. Upon successful restoration of the seal for the eyewash drain #147, fissile solution operations may be 
     resumed. Pending

Since one leg of double contingency was lost, this is being reported to the NRC as a 24-hour Event Report in accordance with NRC BL 91-01 Supplement 1. The NRC Resident Inspector has been notified of this event. PGDP Problem Report No. ATRC-11-3171 and PGDP Event Report No. PAD-2011-20.

ENS 473101 October 2011 00:46:00Description: At 0854 CDT on 09-30-11, the Plant Shift Superintendent (PSS) was notified that water was observed in the #5 withdrawal position scale pit during the completion of the monthly test of the C-310 scale pit water detection system alarm module. The alarm module was being tested per procedure, when the module was found with the visual alarm (a red light) on at the local panel in the #5 withdrawal position room. In response to the alarm, the scale pit hatch was opened and the water detection sensor cable was observed to be at least partially submerged. Immediate investigation found the sump pump breaker to be tripped; when the breaker was reset the pump actuated and water was immediately removed. At the time of the occurrence, product withdrawal was in progress in the #3 and #4 withdrawal position room, and no cylinder was present in the #5 withdrawal position room. The source of the water was found to be a leaking steam condensate valve above the #5 withdrawal room ceiling. The water had drained to the concrete pad outside the building and then along the scale cart rails, eventually finding its way into the #5 scale cart pit where it gradually accumulated. Because the C-310 Scale Pit Water Detection Alarm did not function as credited, it is in violation of NCSE 032 (NCSA 310-004). Since one leg of double contingency was lost, this is being reported to the NRC as a 24-hour Event Report in accordance with NRC BL 91-01 Supplement 1. The NRC Senior Resident Inspector has been notified of this event. PGDP Problem Report No. ATRC-11-2610; PGDP Event Report No. PAD-2011-17 SAFETY SIGNIFICANCE OF EVENTS: The safety significance of this event is low, even though the event made it possible for the level of pre-existing water to exceed the safe geometry limit. Although it is normal case for overall PGDP operations to have assay up to 5.5 wt.% 235U, the actual assay of product withdrawal operations during the period in question remained no higher than 2.0 wt. % 235U. At that actual assay, the depth of water necessary to support a criticality would have been more than 7.21 inches, which might have been credible but in itself would have remained a very unlikely possibility due to the slow ingress rate and high probability of detection and mitigation by personnel performing routine activities in that area. POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO(S) OF HOW CRITICALITY COULD OCCUR): In order for a criticality to happen, a significant breach in the process system integrity would have to occur. After the breach, fissile UF6 and its reaction products would have to react with pre-existing water to form fissile solution. There would have to be a sufficient depth of water in the pit to support a criticality (e.g. more than 3.68 inches of water at 5.5 wt. % 235U). CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.): The two process conditions relied upon for double contingency are mass and geometry. ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS LIMIT AND % WORST CASE CRITICAL MASS): Product withdrawal assay at the time of the event was no higher than 2.0 wt% U235. However, no UF6 release occurred. NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION OF THE FAILURES OR DEFICIENCIES: Geometry is controlled in the second leg of double contingency by limiting the level of pre-existing water that might be present in the scale pit. Water accumulation is considered normal case in the NCSE by acute or by chronic sources. The NCSE credits the Scale Pit Water Detection Alarm to provide detection of chronic water accumulation in the scale pit. The alarm is set to actuate before the water level exceeds 2.5 inches in the pit. The geometry parameter limit is 3.68 inches assuming the worst-case possible enrichment of 5.5 wt.% 235U. The alarm is credited to provide early indication, and result in prompt mitigation, of water ingress to the pit before the NCS parameter limit is exceeded. Since the alarm was not functional, and the ingress rate was sufficiently slow that ingress was not easily detectable, there was no reliable means in place to detect and mitigate the ingress of water into the pit. The sensor and local panel light performed their intended function; however, it is the ACR audible and visible alarms that are controlled as AQ-NCS equipment and not the local panel light and buzzer. With the alarm out of service, continued ingress of water to the pit could have resulted in exceeding the geometry parameter limit for water depth before detection and mitigation. NCS entered the scale pit for inspection shortly after notification of the discovery and after the water had been drained. NCS observed that the water level at the lowest point in the pit may have reached 2.5 inches. Based on those inspections, it is likely that the water level remained below the 3.68-inch level, but there was no definitive way to prove the maximum height that might have occurred throughout the period of time when the alarm was not functional. Therefore, for conservatism it is assumed credible that the geometry parameter limit was violated during the lime the alarm was not functional. CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEMS AND WHEN EACH WAS IMPLEMENTED: The sump pump was immediately activated by resetting its breaker, which restored the water level in the pit below the 2.5 inch administrative limit, thus removing the hazard of this incident. The #5 withdrawal position scale pit will be checked twice per shift beginning on 9-30-11 in accordance with procedure due to the ACR alarm being out-of-service.
ENS 471111 August 2011 11:27:00
ENS 4530226 August 2009 16:19:00On 08-25-09, the Plant Shift Superintendent (PSS) was notified that C-360 (Toll Transfer & Sampling Building) Autoclave #4 had a failure in the autoclave pressure relief system. The autoclave pressure relief system utilizes a rupture disc in series with a relief valve. A pressure indicator is located between the rupture disc and the relief valve to verify that the pressure between the two devices is less than 5 psig per TSR 2.1.3.2 Condition A. This pressure is limited to prevent any significant bias to the actuation pressure of the rupture disc. TSR 2.1.3.2 requires that the actuation pressure of the autoclave pressure relief system shall not exceed 157.5 psig. On 08-25-09 at 2140 CDT, an operator was preparing to place the #4 autoclave into service, per the proper operating procedure, when the pressure between the rupture disc and the relief valve was found to be 5.5 psig, a pressure which indicated a failure in this required safety system. The autoclave was in a mode where this TSR system is required to be operable. There is low safety significance to this failure as the TSR does allow the current operating cycle to be completed under this condition. Since the operating cycle was just started and steam had not been applied to the autoclave, the operating evolution was abandoned and the autoclave was declared inoperable and taken out of service. This event is reportable as a 24 hour event in accordance with 10CFR 76.120(c)(2)(i). This is an event in which equipment is disabled or fails to function as designed when: a.) the equipment is required by a TSR to prevent releases, prevent exposures to radiation and radioactive materials exceeding specified limits, mitigate the consequences of an accident, or restore this facility to a pre-established safe condition after an accident; b.) the equipment is required by a TSR to be available and operable and either should have been operating or should have operated on demand, and c.) no redundant equipment is available and operable to perform the required safety function. The NRC Resident Inspector has been notified of this event. PGDP Assessment and Tracking Report No. ATRC-09-2084; PGDP Event Report No. PAD-2009-12; Worksheet No. Responsible Division: Operations
ENS 4481930 January 2009 19:33:00At 1217 CST, on 01-30-09 the Plant Shift Superintendent (PSS) was notified that C-310 (product withdrawal facility) had lost power due to an electrical fault. As a result of the power loss, the C-310 High Voltage Process Gas Leak Detection (PGLD) System was rendered inoperable. This PGLD System contains detectors that cover the C-310 UF6 condensers, accumulators, and piping heated housing. At the time of this loss of power, these areas were operating above atmospheric pressure. TSR 2.3.4.4 requires that all of detector heads in this system be operable during operations above atmospheric pressure. Power was restored to this PGLD System at 1240 hours, which is within the one hour required by TSR LCO 2.3.4.4.A.1 to enter a continuous smoke watch. This event is reportable as a 24 hour event in accordance with 10CFR 76.120(c)(2)(i). This is an event in which equipment is disabled or fails to function as designed when: a.) the equipment is required by a TSR to prevent releases, prevent exposures to radiation and radioactive materials exceeding specified limits, mitigate the consequences of an accident, or restore this facility to a pre-established safe condition after an accident; b.) the equipment is required by a TSR to be available and operable and either should have been operating or should have operated on demand, and c.) no redundant equipment is available and operable to perform the required safety function. Once the source of the fault was identified, power was restored to the C-310 the High Voltage PGLD System and the system was tested. Power was restored at 1240 hours and the system was tested at 1258 hours. The NRC Senior Resident Inspector has been notified of this event.
ENS 447058 December 2008 15:19:00At 0219 CST, on 12-08-08 the Plant Shift Superintendent (PSS) was notified that the C-333 Unit 6 Cell 5 UF6 Release Detection (PGLD) System would not test fire during routine testing. Operators found that the READY, MANUAL, and POWER lights for this system were properly illuminated. This PGLD System contains detectors that cover only C-333 Unit 6 Cell 5 which was operating above atmospheric pressure. TSR 2.4.4.1 requires that at least the minimum number of detector heads in the cell are operable during steady state operations above atmospheric pressure. With the Unit 6 Cell 5 PGLD system inoperable, none of the required cell heads were operable. This PGLD System was declared inoperable, TSR LCO 2.4.4.1.B.1 was entered and a continuous smoke watch was put in place within one hour. Engineering has determined, by analyzing the failed component, that the system would not have been able to perform its intended safety function when this condition was discovered. This event is reportable as a 24 hour event in accordance with 10CFR76.120(c)(2)(i). This is an event in which equipment is disabled or fails to function as designed when: a.) the equipment is required by a TSR to prevent releases, prevent exposures to radiation and radioactive materials exceeding specified limits, mitigate the consequences of an accident, or restore this facility to a pre-established safe condition after an accident; b.) the equipment is required by a TSR to be available and operable and either should have been operating or should have operated on demand, and c.) no redundant equipment is available and operable to perform the required safety function. The NRC Senior Resident Inspector has been notified of this event. As of the time of the report, the problem has been corrected and the system returned to service.
ENS 4455810 October 2008 14:20:00

The following information is provided without quotation for readability: DESCRIPTION: On 10/09/08 at 1537 hours it was determined that procedure CP4-CU-CH6430, "In Storage Fissile Cylinder Inspection", does not fully meet the periodic inspection requirements of NCSA GEN-003. GEN-003 requires inspection every four years of all thick wall cylinders that contained fissile material since they were last washed on the inside of the cylinder. Only cylinders that were filled with fissile material on their last fill have been identified for inspection. Cylinders filled with fissile material, emptied and subsequently filled with non-fissile material and emptied, have not been inspected as required. Approximately 73 Cylinders that have contained fissile material since their last washing have not been inspected in violation of the requirement of NCSA GEN-003, these cylinders could contain residual nonvolatile material referred to as heel. Potentially the residual heel could contain fissile material. Double contingency is maintained by implementing two independent controls on one parameter (moderation). The first leg of double contingency relies on the design of the cylinder to ensure moderation control. Cylinders are designed to the requirements of ANSI N14.1 and ensure that it is unlikely for the cylinder wall to breach and allow water intrusion. This control on moderation was not violated. The second leg of double contingency relied on inspections every 4 years of the cylinder wall, valve, and plug for abnormal corrosion. This control ensures that in the event of a cylinder breach, it is unlikely that sufficient moderation to cause a criticality will enter the cylinder before it is identified and mitigated. Since the cylinders were not inspected within the 4 year time frame as required, this control on moderation was violated. The NRC Resident Inspector has been notified of this event. PGDP Problem Report No. ATRC-08-2918; PGDP Event Report No. PAD-2008-31; NRC Worksheet No. 44558. SAFETY SIGNIFICANCE OF EVENTS: Although a control requiring inspection of the cylinders every 4 years was violated, no cylinder breaches occurred. Later inspections identified no cylinder integrity issues, moderation control was lost and double contingency was not maintained. POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO(S) OF HOW CRITICALITY COULD OCCUR): In order for a criticality to be possible, more than 10kgs of water would have to enter a breach in a cylinder which contains more than a critical mass of material enriched to greater than 1.0 wt% 235U. CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.): Moderation. ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS LIMIT AND % WORST CASE CRITICAL MASS) : There were 73 cylinders which were not inspected as required. These cylinders had at one time held fissile material. The cylinders were emptied except for a small residual heel and then filled with non-fissile material. The non-fissile material was then emptied leaving only the residual heel in the cylinder. Cylinder heels are typically less than 50 pounds. Assay is always less than 5.5% enrichment. NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION OF THE FAILURES OR DEFICIENCIES: NCSA GEN-003 requires cylinders containing material enriched to greater than or equal to 1.0 wt % 235U to be inspected every 4 years to identify significant signs of degraded cylinder wall, valve and plug. These cylinders were filled with fissile material, emptied and then subsequently filled with non-fissile material and then emptied again, but were not inspected within the four year requirement. CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEMS AND WHEN EACH WAS IMPLEMENTED : Cylinders have been inspected per the CP4-CU-CH6430 and the identified cylinders were found to comply with NCSA GEN-003.

  • * * UPDATE AT 1750 EDT ON 10/10/08 FROM BILLY WALLACE TO STEVE SANDIN VIA FAX * * *

On 10/10/08 at 1500 CDT, an additional 8 cylinders were discovered which had not been properly inspected. The additional cylinders were of a different size than the initial cylinders found, but fall under the same requirement. The additional cylinders have been inspected and all met the NCSA requirements. Notified R2DO (Shaeffer) and NMSS (McCartin).

ENS 4435620 July 2008 19:00:00At 1230 CDST, on 07-20-08 the Plant Shift Superintendent (PSS) was notified that C-315 had received an audible alarm with no visual indications. Moments later an alarm was received in C-331 for the C-315 High Voltage Process Gas Leak Detection System. Operators responded by contacting C-315 to inquire about the alarm. C-315 operators checked the system and found that the READY light for this system was not illuminated. This PGLD System contains detectors that cover the C-315 UF6 condensers, accumulators, and piping heated housing. At the time of this alarm, the areas were operating above atmospheric pressure. TSR 2.3.4.4 requires that all of detector heads in this system be operable during operations above atmospheric pressure. Operators responding to the system tried to test fire the system heads however the system would not respond and then they discovered the READY light to be off. This PGLD System was declared inoperable, TSR LCO 2.3.4.4.A.1 was entered and a continuous smoke watch was put in place within one hour. Engineering has determined that the system would not have been able to perform its intended safety function when this alarm came in. This event is reportable as a 24 hour event in accordance with 10CFR 76.120 (c)(2)(i). This is an event in which equipment is disabled or fails to function as designed when: a.) the equipment is required by a TSR to prevent releases, prevent exposures to radiation and radioactive materials exceeding specified limits, mitigate the consequences of an accident, or restore this facility to a pre-established safe condition after an accident; b.) the equipment is required by a TSR to be available and operable and either should have been operating or should have operated on demand, and c.) no redundant equipment is available and operable to perform the required safety function. The NRC Resident Inspector has been notified of this event.
ENS 4386423 December 2007 19:02:00On 12/23/2007 at 0358 the C-333 unit 3 cell 1 PGLD (process gas leak detection) head (YE-5) at stage 5 actuated. Along with the PGLD actuation a seal alarm and a vibration alarm on stage 7 were received. A nearby operator on the cell floor responded to the alarm and observed a small UF6 release from the stage 7A seal cavity. To stop the release the cell was immediately shut down from the ACR which lowered the cell's pressure to below atmospheric pressure. The exact amount of material released has not been determined. Checks by health physics personnel found the actual amount of UF6 released was not significant and resulted in a relatively small area of contamination on the end of the compressor near the seal that failed and on the floor immediately around the end of the compressor. The actuated PGLD head is a Q safety system component. At the time of the incident the cell was operating in a mode which required the system to be operational. This is being reported based on SAR 6.9 Table 1, J2 (unplanned actuation of a Q safety system) and 10 CFR 76.120(c)(1)(i) (unplanned contamination event). The NRC Resident Inspector has been notified of this event. PGLD Problem Report Nos. ATRC-07-3433; PGLD Event Report No. PAD-2007-022; NRC Event Number 43864
ENS 438297 December 2007 15:47:00On 12/06/2007 at 2042 (CST) C-337 unit 5 cell 5 was being charged and placed on stream and had just gone above atmospheric pressure. At 2044 hours two PGLD (process gas leak detection) heads in the C-337 unit 5 cell 5 actuated and would not clear indicating a potential UF6 release. To stop the release the cell was immediately taken back below atmospheric pressure. Investigation revealed that a UF6 release had occurred causing the PGLD actuation. The amount of material released has not yet been determined. The PGLD heads are Q safety system components. At the time of the incident the cell was operating in a mode which required the system to be operational. This is being reported based on SAR 6.9 Table 1, J2 (unplanned actuation of a Q safety system) and 10 CFR 76.120 (c) (1) (i) (unplanned contamination event). The NRC Resident Inspector has been notified of this event. There was no release to the environment and no personnel contaminations reported.
ENS 438287 December 2007 15:42:00On 12/06/2007 at 1550 (CST) the C-337 unit 5 cell 3 PGLD (process gas leak detection) head in the C-337 unit 5 cell 3 housing actuated and would not clear. Response to the alarm by operators revealed a haze above the cell indicating a UF6 release inside the cell housing. While the operators were responding to the unit 5 Cell 3 alarm, two other PGLD heads actuated in C-337 unit 5 cell 5. To stop the release both cells 3 and 5 were taken below atmospheric pressure. Investigation indicated that a UF6 release had occurred. The amount of material released has not been determined. The actuated PGLD heads are Q safety system components. At the time of the incident the cell was operating in a mode which required the system to be operational. This is being reported based on SAR 6.9 Table 1, J2 (unplanned actuation of a Q safety system) and 10 CFR 76.120 (c) (1) (i) (unplanned contamination event). The NRC Resident Inspector has been notified of this event. There was no release to the environment and no personnel contaminations reported.
ENS 4378716 November 2007 10:14:00On 11/15/2007 at 0915 instrument mechanics were performing a cell datum calibration in the C-333 Unit 4 Cell 2 cell panel when a strong odor assumed to be HF was noticed after the stage 1 high side pressure valve was opened. The 1/4" valve is on a manifold which accesses pressure taps in various locations in the cell. When the odor was detected a UF6 leak detection head located in the cell panel ducting also actuated. The mechanic opening the valve, immediately closed the valve when the odor was detected and they immediately left the area. HF samples taken a few minutes later in the area around the cell panel were all negative. Precautionary urine samples have been taken from the individuals involved and analysis are being run on the samples. It is believed a small incidental UF6 release occurred when the small high side valve was momentarily opened and actuated the UF6 detection system head which is a Q safety system component. At the time of the incident the cell was in operation in a mode which required the system to be operational. This is being reported based on SAR 6.9 Table 1, J2. The NRC Resident Inspector has been notified of this event.
ENS 4330517 April 2007 11:36:00At 1915, on 04/16/07, the Plant Shift Superintendent was notified of a large water leak on High Pressure Fire Water system. This system provides water for fire suppression to the plants process buildings. An alarm was received indicating a drop in the level of High Pressure Fire Water (HPFW) elevated tank. The buildings were contacted to look for a large water leak and the leak was quickly located inside the C-337 process building. The exact system leaking was not apparent as the leak was under the building concrete floor. To stop the leak the HPFW pumps supporting the system were shutdown and the sectional valves outside the building were closed. This action made the HPFW system for all process buildings inoperable. LCO actions 2.4.4.8 and 2.4.4.6 were entered. The leak was determined to be on C-337 system C-12 and this system and the two adjacent systems were isolated and all other previously isolated valves were reopened. The HPFW pumps were restarted and the HPFW elevated tank was refilled to the TSR required level. These actions restored HPFW operability to the other areas in the plant at 2101 hours. TSR required hourly fire patrols were initiated for the affected area in C-337. The leak is located on an underground eight inch header under the alarm and actuation controls for system C-12 inside the building. This is being reported as an event in which equipment is disabled or fail to function as designed when the equipment is required by a TSR to be available and operable and either should have been operating or should have operated on demand, and no redundant equipment is available. The licensee stated that this leak caused substantial damage to the concrete pad on the floor of the building. No structural damage is believe to have occurred but the concrete pad with have to be completely removed, the piping repaired, and eroded earth backfilled. A new concrete pad will then likely need to be poured. Nearly half a million gallons of water may have been lost through the break before it was isolated. The licensee has checked the site outfalls and no contamination was detected. The licensee notified the NRC Resident Inspector.
ENS 4286629 September 2006 14:41:00At 1802 CDT on 09/28/06, the Plant Shift-Superintendent (PSS) was notified of a failure of the C-333A Autoclave 3 South High Cylinder Pressure System (HCPS). During a normal cylinder heating cycle the operator noted that the cylinder pressure, as read on a local digital pressure indicator and on a digital recorder in the Operations Monitoring Room (OMR), unexpectedly fell from a steady 65 psia to a negative value on both instruments. A 14 ton cylinder containing 0.4019% U235 assay uranium hexafluoride had been heating (TSR Mode 5) for approximately 2.2 hours when the failure occurred. The PSS declared the HCPS inoperable and TSR LCO 2.2.4.14B actions were implemented to place the autoclave in Mode 2, 'Autoclave Open and Out-of-Service'. The HCPS is a TSR system designed to minimize the potential of primary system integrity failure (cylinder rupture) during a pressure increase event by tripping the steam supply to the autoclave prior to reaching the Maximum Allowable Working Pressure (MAWP) of the cylinder. This event is reportable as a 24 hour event in accordance with 10CFR 76.120(c)(2)(i). This is an event in which equipment is disabled or fails to function as designed when: a.) the equipment is required by a TSR to prevent releases, prevent exposures to radiation and radioactive materials exceeding specified limits, mitigate the consequences of an accident, or restore this facility to a pre-established safe condition after an accident, b.) the equipment is required by a TSR to be available and operable and either should have been operating or should have operated on demand, and c.) no redundant equipment is available and operable to perform the required safety function. There was no release of radioactive material. The licensee notified the NRC Resident Inspector.