Event Notification Report for April 24, 2003
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
04/23/2003 - 04/24/2003
** EVENT NUMBERS **
39769 39784 39785 39786 39787 39788 39789 39790 39791
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|General Information or Other |Event Number: 39769 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: OHIO BUREAU OF RADIATION PROTECTION |NOTIFICATION DATE: 04/18/2003|
|LICENSEE: SOLAR TESTING LABORATORIES |NOTIFICATION TIME: 09:31[EDT]|
| CITY: BROOKLYN HEIGHTS REGION: 3 |EVENT DATE: 04/18/2003|
| COUNTY: STATE: OH |EVENT TIME: [EDT]|
|LICENSE#: OH31210180065 AGREEMENT: Y |LAST UPDATE DATE: 04/18/2003|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |THOMAS KOZAK R3 |
| |MATT KORMANN TAT |
+------------------------------------------------+FRED BROWN NMSS |
| NRC NOTIFIED BY: MIKE SNEE | |
| HQ OPS OFFICER: MIKE RIPLEY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| THEFT AND RECOVERY OF MOISTURE DENSITY GAUGE |
| |
| The following information was received via facsimile from the Ohio |
| Department of Health: |
| |
| The licensee reported the theft and recovery of a Humboldt Scientific |
| moisture/density gauge (model 5001, serial #750) containing a 44 millicurie |
| Am-Be source and a 11 millicurie Cs-137 source. The gauge was stolen during |
| the early hours of April 18, 2003 from the back of a truck parked at an |
| employee's residence in Brooklyn Heights, Ohio. The truck and gauge case was |
| broken into. The licensee notified police and the Ohio Department of |
| Health. At 8:45 AM on April 18, the employee discovered the gauge on the |
| side of the road a short distance from his residence where the theft |
| occurred. The gauge did not appear to be damaged. |
| |
| Notified R3DO (T. Kozak), NMSS (F. Brown), NSIR IAT (M. Kormann) |
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+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39784 |
+------------------------------------------------------------------------------+
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| FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 04/23/2003|
| UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 05:29[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/23/2003|
+------------------------------------------------+EVENT TIME: 02:07[EDT]|
| NRC NOTIFIED BY: TOM DOUGHERTY |LAST UPDATE DATE: 04/23/2003|
| HQ OPS OFFICER: ERIC THOMAS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |HAROLD GRAY R1 |
|10 CFR SECTION: | |
|ACCS 50.72(b)(2)(iv)(A) ECCS INJECTION | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
|AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 M/R Y 100 Power Operation |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| RPS ACTUATION WHILE CRITICAL |
| |
| "At 0207 EDT on April 23, 2003, a loss of feedwater occurred on Unit 1. |
| Operators initiated a manual reactor scram at 15 [inches] RPV level (auto |
| scram signal = 12.5 [inches]). The high pressure coolant injection (HPCI) |
| and reactor core isolation coolant (RCIC) systems initiated as designed at |
| -38 [inches], and injected into the RPV. RPV level was restored to the |
| normal band, HPCI and RCIC secured, and a reactor feed pump was returned to |
| service. The following isolation signals were received; Groups IB, IIA, |
| IIC, III, VIB, VIC, VIIB, VIIIB, and HVAC. RPV and containment parameters |
| are normal with an RPV cooldown in progress. |
| |
| "The loss of feed resulted from sequential trips of all 3 reactor feed pumps |
| on low suction pressure due to an apparent isolation of the condensate deep |
| bed demineralizers. The cause is under investigation." |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39785 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 04/23/2003|
| UNIT: [2] [3] [] STATE: PA |NOTIFICATION TIME: 10:23[EDT]|
| RXTYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 03/21/2003|
+------------------------------------------------+EVENT TIME: 12:19[EDT]|
| NRC NOTIFIED BY: DAVID J. FOSS |LAST UPDATE DATE: 04/23/2003|
| HQ OPS OFFICER: ERIC THOMAS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |HAROLD GRAY R1 |
|10 CFR SECTION: | |
|AINV 50.73(a)(1) INVALID SPECIF SYSTEM A| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 N Y 100 Power Operation |100 Power Operation |
|3 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| INVALID SPECIFIED SYSTEM ACTUATION |
| |
| "This 60-day optional report, as allowed by 10 CFR 50.73(a)(1), is being |
| made under the reporting requirement in 10 CFR 50.73(a)(iv)(A) to describe |
| an unplanned, invalid actuation of a specified system, specifically the E-2 |
| Emergency Diesel Generator (EDG). |
| |
| "On March 21, 2003, a momentary short was created during the installation of |
| test jacks, which resulted in an invalid start signal to the E-2 EDG. The |
| E-2 EDG started, however, the associated emergency buses remained energized |
| from their normal power supplies. |
| |
| "The affected emergency diesel generator responded as expected for the given |
| conditions and was subsequently returned to a normal configuration per plant |
| procedures. No deficiencies or abnormalities were noted during the event. |
| |
| "This event has been entered into the site-specific corrective action |
| program for resolution. |
| |
| "The NRC resident has been informed." |
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+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39786 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 04/23/2003|
| UNIT: [] [2] [] STATE: TN |NOTIFICATION TIME: 12:43[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/08/2003|
+------------------------------------------------+EVENT TIME: 12:11[EDT]|
| NRC NOTIFIED BY: M. HOWARD |LAST UPDATE DATE: 04/23/2003|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MIKE ERNSTES R2 |
|10 CFR SECTION: | |
|AINV 50.73(a)(1) INVALID SPECIF SYSTEM A| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| INVALID UNIT 2 TRAIN "B" CONTAINMENT VENT ISOLATION (CVI) . |
| |
| On 04/08/03 at 1211 an invalid Unit 2, Train "B", Containment Vent Isolation |
| (CVI) occurred. The actuation was caused by increased sensitivity of |
| radiation monitor 2-RM-90-131 as a result of small perforations in the |
| aluminum foil cover of the detector. |
| |
| The specific train actuated was Train "B", and the system which received the |
| isolation signal were Containment Ventilation Purge and EXHAUST (already |
| closed) and Radiation Monitoring isolation valves (went closed). |
| |
| Complete train actuation occurred. |
| |
| The Containment Ventilation Isolation function was successful. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39787 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 04/23/2003|
| UNIT: [1] [2] [] STATE: TN |NOTIFICATION TIME: 12:46[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/12/2003|
+------------------------------------------------+EVENT TIME: 12:54[EDT]|
| NRC NOTIFIED BY: M. HOWARD |LAST UPDATE DATE: 04/23/2003|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MIKE ERNSTES R2 |
|10 CFR SECTION: | |
|AINV 50.73(a)(1) INVALID SPECIF SYSTEM A| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| INVALID START OF THE FOUR EMERGENCY DIESEL GENERATORS. |
| |
| On 04/12/03 at 1254 an invalid start of the four emergency diesel generators |
| occurred. The actuation was caused by a loss of DC power to the 1BB |
| emergency diesel start circuit and a auto start signal to the remaining 3 |
| emergency diesel generators. Power loss was caused by poor terminal lug |
| contact on a space breaker during testing of a Vital Battery breaker. |
| |
| The specific train actuated were both Train "A" and "B" for both Units 1 and |
| 2. The system actuated was emergency AC electrical power (emergency diesel |
| generators). |
| |
| Complete train actuation occurred. |
| |
| The Emergency Diesel Generator start was successful. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39788 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 04/23/2003|
| UNIT: [1] [2] [] STATE: IL |NOTIFICATION TIME: 23:44[EDT]|
| RXTYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 04/23/2003|
+------------------------------------------------+EVENT TIME: 19:55[CDT]|
| NRC NOTIFIED BY: MARK OKOPNY |LAST UPDATE DATE: 04/23/2003|
| HQ OPS OFFICER: ERIC THOMAS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MONTE PHILLIPS R3 |
|10 CFR SECTION: | |
|ACOM 50.72(b)(3)(xiii) LOSS COMM/ASMT/RESPONSE| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 67 Power Operation |67 Power Operation |
|2 N Y 10 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOST OF EMERGENCY ASSESSMENT CAPABILITY |
| |
| "This report is being made pursuant to 10CFR50.72(b)(3)(xiii) Major loss of |
| emergency assessment capability. During the performance of routine |
| surveillance LOS-VG-M1 Standby Gas Treatment System Operability Test and |
| Inservice Test of 1VG001 and 1VG003, it was reported that the installed |
| preplanned monitoring system sample pump tripped. At 19:55 CDST on April |
| 23rd it was confirmed that the sample pump had tripped for the Preplanned |
| Alternate sampling system. This Preplanned Alternate sampling system had |
| been connected to comply with the Technical Requirements Manual (TRM) from |
| the inoperability of the installed Standby Gas Treatment Stack monitoring |
| system (Standby Gas Treatment system Wide Range Gas Monitoring system -SBGT |
| WRGM). Troubleshooting is in progress to restore the Preplanned Alternate |
| sample pump. The Standby Gas Treatment Train has been secured and placed in |
| standby configuration. The plant is stable and no abnormal or elevated |
| release occurred during this event." |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39789 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 04/24/2003|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 01:25[EDT]|
| RXTYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 04/23/2003|
+------------------------------------------------+EVENT TIME: 19:23[CDT]|
| NRC NOTIFIED BY: MARK OKOPNY |LAST UPDATE DATE: 04/24/2003|
| HQ OPS OFFICER: ERIC THOMAS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MONTE PHILLIPS R3 |
|10 CFR SECTION: | |
|AIND 50.72(b)(3)(v)(D) ACCIDENT MITIGATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 67 Power Operation |67 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| ACCIDENT MITIGATION |
| |
| "This report is being made pursuant to 10CFR50.72(b)(3)(v)(D), Event or |
| Condition that could have prevented fulfillment of a Safety Function needed |
| to Mitigate the Consequences of an Accident. On 04/23/03, at 18:15 CDST, the |
| 1A Diesel Generator was made inoperable for a scheduled surveillance. |
| Concurrent with this inoperability, the 0 Diesel Generator received a |
| spurious CO2 actuation signal. This spurious CO2 partial logic actuation did |
| not result in an actual CO2 injection into the 0 Diesel Generator Room. The |
| CO2 system partial actuation however resulted in several ventilation dampers |
| failing closed as designed. With these dampers closed, the ventilation |
| support system for the 0 Diesel Generator became inoperable, the 0 Diesel |
| Generator was declared inoperable at 1923 hours 04/23/03. This condition |
| resulted in both the 1A and 0 Diesel Generators concurrently being |
| inoperable. Actions were taken to terminate the 1A Diesel surveillance and |
| restore the 1A Diesel Generator to an operable status. This was accomplished |
| at 1952 hours 04/23/03. The 1A and 0 Diesel Generators were simultaneously |
| inoperable for 29 minutes. Due to the concurrent Diesel Generator |
| inoperabilities which affect redundant trains required to mitigate the |
| consequences of an accident, it has been determined that this event is |
| reportable as an 8 hour ENS notification. |
| |
| "Corrective actions have been initiated to address the 0 Diesel Generator |
| CO2 system and restore the ventilation dampers to an operable status. The |
| spurious actuation of the 0 Diesel Generator CO2 system was determined to be |
| due to a Non-Licensed Operator opening the fire detection panel for |
| inspection." |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39790 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 04/24/2003|
| UNIT: [1] [2] [] STATE: MI |NOTIFICATION TIME: 04:40[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/24/2003|
+------------------------------------------------+EVENT TIME: 03:48[EDT]|
| NRC NOTIFIED BY: STUART SCHUETTPELZ |LAST UPDATE DATE: 04/24/2003|
| HQ OPS OFFICER: ERIC THOMAS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: ALERT |MONTE PHILLIPS R3 |
|10 CFR SECTION: |JAMES LYONS NRR |
|AAEC 50.72(a) (1) (i) EMERGENCY DECLARED |MICHELE EVANS IRO |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA|CHUCK CAIN R4 |
| |CHARLIE BAGWELL FEMA |
| |JOHN FLACH NRC |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 M/R Y 100 Power Operation |0 Hot Standby |
|2 M/R Y 100 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| ALERT DECLARED |
| |
| At 0348 EDT on 4/24/03, the plant experienced an influx of fish on the |
| intake screens for the circwater and emergency service water (ESW) systems. |
| This resulted in a loss of vacuum to Units 1 and 2 main turbines, which led |
| operators to manually trip both reactors. Following the trip, operators |
| noted that ESW flow to all 4 emergency diesel generators (EDGs) was severely |
| degraded. This resulted in the licensee declaring all 4 EDG's inoperable. |
| An alert was declared at 0348 EDT, and the NRC entered Monitoring Mode at |
| 0506 EDT. |
| |
| * * * UPDATE AT 0600 FROM LICENSEE TO H. CROUCH * * * |
| |
| All EDG's have adequate flow to be used in an emergency, but remain |
| inoperable. |
| |
| The licensee is assessing damage to intake screens and strainers in the ESW |
| system, and manually backwashing ESW screens. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 39791 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 04/24/2003|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 05:42[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 04/24/2003|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: [CDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 04/24/2003|
| CITY: PADUCAH REGION: 3 +-----------------------------+
| COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION |
|LICENSE#: GDP-1 AGREEMENT: Y |MONTE PHILLIPS R3 |
| DOCKET: 0707001 |DANIEL GILLEN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: TOM WHITE | |
| HQ OPS OFFICER: HOWIE CROUCH | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| CRITICALITY CONTROL 24-HOUR REPORT (RESPONSE BULLETIN 91-01) |
| |
| The following information was obtained from the regulatee via facsimile: |
| |
| "At 1320 [CDT] on 4/23/03, the Plant Shift Superintendent (PSS) was notified |
| that the trap media replacement activities for C-337 #4 Seal Exhaust (SX) |
| trap were performed on 4/6/03 through 4/8/03 and the trap media and the |
| bottom screen were replaced. Contrary to the requirements of NCSA CAS-007, |
| 'independent verification of no trap media below the bottom screen' was not |
| performed prior to the bottom flange being removed. This requirement |
| ensures that an unanalyzed volume of media does not spill from the trap. |
| |
| "The NRC Resident Inspector has been notified of the event. |
| |
| "PDGP Assessment and Tracking Report No. ATR 03-1199 PGDP Event Report No. |
| PAD-2003-008 NRC Event Worksheet [39791]. |
| |
| "Responsible Division: Maintenance |
| |
| "SAFETY SIGNIFICANCE OF EVENTS: |
| |
| "Although the trap was not independently verified to be essentially empty of |
| accumulated trap mix, prior to in-place maintenance, no media was found when |
| the bottom flange was removed. |
| |
| "POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO(s) OF HOW C |
| RITICALITY COULD OCCUR): |
| |
| "In order for a criticality to be possible, a critical volume of trap mix |
| would have to be accumulated in an unsafe geometry. |
| |
| "CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION. ETC: |
| |
| "Double contingency is maintained by implementing two controls on volume. |
| |
| "ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS |
| LIMIT AND % WORST CASE CRITICAL MASS): |
| |
| "There was no media found when the bottom flange was removed. |
| |
| "NUCLEAR CRITICALITY SAFETY CONTROL (S) OR CONTROL SYSTEM(S) AND DESCRIPTION |
| OF THE FAILURES OR DEFICIENCES: |
| |
| "The first leg of double contingency relies on controlling the volume of |
| trap mix available to be spilled from the, trap after removal of media above |
| the bottom screen. NCSA CAS-007 requires the trap to be verified emptied of |
| trap media prior to in-place maintenance, thus ensuring that the trap does |
| not contain any accumulated trap mix in excess of a 5.5-gal drum. |
| Verification of the trap mix accumulated in the trap was not done, thus, |
| this control was violated. |
| |
| "The second leg of double contingency relies on controlling the volume of |
| trap mix available to be spilled from the trap after removal of media above |
| the bottom screen. NCSA CAS-007 requires the trap to be independently |
| verified emptied of trap media prior to in-place maintenance. Independent |
| verification of the trap mix accumulated in the trap was not performed. |
| therefore. this control was violated. Neither of the controls (verification |
| and independent verification) of the single parameter (volume) were |
| performed and double contingency was not maintained. |
| |
| "No trap media was spilled from the trap, thus maintaining the volume |
| parameter. |
| |
| "CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEMS AND WHEN EACH WAS IMPLEMENTED: |
| |
| |
| "None." |
| |
| Operations notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021