Event Notification Report for May 17, 2001
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
05/16/2001 - 05/17/2001
** EVENT NUMBERS **
37965 37993 37994 37995 37996 37997 37998 37999 38000
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 37965 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: NV DIV OF RAD HEALTH |NOTIFICATION DATE: 05/04/2001|
|LICENSEE: LAS VEGAS PAVING |NOTIFICATION TIME: 13:40[EDT]|
| CITY: NORTH LAS VEGAS REGION: 4 |EVENT DATE: 05/04/2001|
| COUNTY: STATE: NV |EVENT TIME: 06:15[PDT]|
|LICENSE#: 00-11-0255-01 AGREEMENT: Y |LAST UPDATE DATE: 05/16/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |GAIL GOOD R4 |
| |FRED BROWN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: STAN MARSHALL (fax) | |
| HQ OPS OFFICER: LEIGH TROCINE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| AGREEMENT STATE REPORT REGARDING A STOLEN TROXLER GAUGE |
| |
| The following text is a portion of a facsimile received from the Nevada |
| Health Division Radiological Health Section regarding a Significant Event |
| Report: |
| |
| "1. Event Report ID No. [-] NV-01-02" |
| |
| "2. License No. [-] 00-11-0255-01" |
| |
| "3. Licensee [-] Las Vegas Paving" |
| |
| "4. Event time, date, location [-] 6:15 a.m., May 4, 2001, 7/11 Convenience |
| Store, Losse & Cheyene Road, North Las Vegas, Nevada." |
| |
| "5. Event type (e.g., misadministration, lost source, overexposure, etc.) |
| [-] Theft of Troxler Model 4640B portable gauge." |
| |
| "6. Any notifications i.e., other agencies, patient, press release, FBI, |
| etc. [-] North Las Vegas Police Dept. notified by licensee." |
| |
| "7. Event description: release, isotope, activity, exposure(s), dose, |
| contamination level, equipment malfunction, model, serial No., etc. [-] |
| Chain securing Troxler Model 4640B gauge to pickup bed was cut, and gauge |
| was stolen from licensee's truck while gauge user was in [convenience] |
| store. Gauge is a Troxler Model 4640B, s/n 1658." |
| |
| "8. Transport vehicle description if known [-] Pickup truck." |
| |
| "9. Media attention [-] N/A" |
| |
| (Call the NRC operations officer for State contact information.) |
| |
| *** UPDATE (FAX) RECEIVED AT 1228 EDT ON 05/15/09 FROM LARRY BOSCHULT TO |
| LEIGH TROCINE *** |
| |
| The following text is a portion of a facsimile received from the Nevada |
| Health Division Radiological Health Section: |
| |
| "The licensee recovered the gauge May 10, 2001. The gauge was found by a |
| pedestrian. They saw the licensee's phone number on the gauge and called |
| them. The licensee immediately retrieved the gauge. The lock on the gauge |
| transport case was broken, but the gauge was still locked. The gauge has |
| been leak tested and placed in storage pending the outcome of the leak |
| test." |
| |
| The NRC operations officer notified the R4DO (Spitzberg) and NMSS EO |
| (Hickey). |
| |
| (Call the NRC operations officer for State contact information.) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37993 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BYRON REGION: 3 |NOTIFICATION DATE: 05/16/2001|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 05:38[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/15/2001|
+------------------------------------------------+EVENT TIME: 07:00[CDT]|
| NRC NOTIFIED BY: BRYAN HERRING |LAST UPDATE DATE: 05/16/2001|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MICHAEL PARKER R3 |
|10 CFR SECTION: | |
|NONR OTHER UNSPEC REQMNT | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 98 Power Operation |98 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PLANT MAY HAVE OPERATED ABOVE 100% POWER |
| |
| During power up-rate data verification, Byron Station identified that an |
| improper feedwater density factor and thermal expansion coefficient had been |
| used to calculate feedwater flow constants (referred to as AMAG constants) |
| on Units 1 and 2. The improper constants resulted in a non-conservative |
| determination of reactor power via the thermal power calorimetric |
| calculation. Thermal power was underestimated by 0.12 percent rated thermal |
| power. The improper AMAG constants have been utilized since AMAG was |
| implemented at Byron Station in May of 2000 (Unit 1 on 5/16/00 and Unit 2 on |
| 5/12/00). It is believed since May of 2000 either unit may have exceeded |
| 100 percent rated thermal power over an eight hour period based on the |
| non-conservative AMAG constants. There is no evidence that either unit ever |
| exceeded 102.0 percent rated thermal power. A formal review of past power |
| history for both units is in progress. The AMAG constants have been |
| corrected for Unit 2 and are in progress for Unit 1. Unit 1 is being |
| maintained at or below 99.88 percent rated thermal power until the AMAG |
| constants have been corrected. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37994 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 05/16/2001|
| UNIT: [] [2] [] STATE: NY |NOTIFICATION TIME: 12:25[EDT]|
| RXTYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 05/16/2001|
+------------------------------------------------+EVENT TIME: 10:18[EDT]|
| NRC NOTIFIED BY: DAN CIFONELLI |LAST UPDATE DATE: 05/16/2001|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN ROGGE R1 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 90 Power Operation |0 Hot Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TURBINE TRIP FOR UNKNOWN REASONS AND SUBSEQUENT REACTOR SCRAM |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "Nine Mile Point Unit 2 experienced a turbine trip and reactor scram |
| (Reactor Protection System (RPS) actuation) from approximately 90% power. |
| All control rods fully inserted. Reactor water level lowered to below Level |
| 3 (159.3 inches indicated, RPS actuation level) following the scram due to |
| high power scram. Level recovered to above Level 8. (203.8 inches |
| indicated, high level feed pump trip level). The operating feed pumps |
| tripped as designed, and the 'A' [feed pump] was restarted. Level was |
| restored to the normal band. Reactor pressure control continues to be |
| controlled using the main condenser and a normal cooldown is in progress. |
| Cause of the turbine trip is under investigation." |
| |
| The licensee stated that there were no related maintenance or surveillance |
| activities ongoing at the time of the turbine trip. None of the relief |
| valves lifted, and all containment parameters are currently normal. All |
| emergency core cooling systems (ECCS) are available, and no ECCS actuations |
| were required during this event. Other than the reactor scram, there were |
| no engineered safety features actuations, and none were required. There was |
| nothing unusual or misunderstood except for the cause of the turbine trip, |
| and all systems functioned as required in response to the turbine trip and |
| subsequent reactor scram. |
| |
| The licensee notified the NRC resident inspector and the State. The |
| licensee also plans to issue a press release. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 37995 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: FLORIDA BUREAU OF RADIATION CONTROL |NOTIFICATION DATE: 05/16/2001|
|LICENSEE: WINGERTER LABORATORIES, INC. |NOTIFICATION TIME: 16:12[EDT]|
| CITY: MIAMI REGION: 2 |EVENT DATE: 05/15/2001|
| COUNTY: DADE STATE: FL |EVENT TIME: 16:00[EDT]|
|LICENSE#: 0673-1 AGREEMENT: Y |LAST UPDATE DATE: 05/16/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |CHARLES R. OGLE R2 |
| |SUSAN FRANT NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JEAROLD EAKINS (fax) | |
| HQ OPS OFFICER: LEIGH TROCINE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT REGARDING THE THEFT OF A TROXLER GAUGE FROM THE |
| RESIDENCE OF A WINGERTER LABORATORIES, INC. EMPLOYEE IN MIAMI, FLORIDA |
| |
| The following text is a portion of a facsimile received from the Florida |
| Bureau of Radiation Control: |
| |
| "Incident Number[:] FL01-057" |
| |
| "Incident Date[:] 15-May-01" |
| |
| "Licensee or Owner[:] WINGERTER LABORATORIES, INC." |
| |
| "City, State, and Zip Code[:] Miami, FL 33181" |
| |
| "License #[:] 0673-1" |
| |
| "License Type; Category[:] Specific; 3L(1)" |
| |
| "Isotope(s)[:] Cs-137, Am-241" |
| |
| "Activity(s)[:] N/A" |
| |
| "Material Form; Chemical Form; Physical Form[:] N/A" |
| |
| "Portable Disposition of Material[:] Unknown" |
| |
| "Exposure? No" |
| |
| "Incident Category[:] Loss of Control - Lost , Abandoned, or Stolen |
| Materials" |
| |
| "Location Classification[:] Unrestricted Area" |
| |
| "Incident Description[: A licensee] operator[, ...,] was transporting [the] |
| gauge from [a] jobsite to [the] office and stopped off at [a] personal |
| residence (@ [approximately] 1600 hrs.). [The employee] left [the] truck |
| running while he went into [the] residence. When [the] employee returned, |
| [the] truck and gauge were missing. [The key] ring for [the] truck also |
| contained keys to [the] gauge[,] employees residence[,] and personal |
| vehicles. Company has issued [a] press release in the Miami Herald |
| newspaper offering $1,000 for information on [the] return of [the] |
| truck/gauge. [The truck] was reported recovered at 1500 on 16 May. [The |
| gauge] is still missing." |
| |
| "Device Type (Quantity)[:] Soil moisture/Density Gauge" |
| |
| "Manufacturer[:] Troxler" |
| |
| "Model Number[:] 3411-B" |
| |
| "Serial Number(s)[:] 7400" |
| |
| "Emergency Groups at Scene[:] USNRC, State Warning Point" |
| |
| "Organizations Notified[:] Metro Dade PD" |
| |
| "Media Contacted[:] None" |
| |
| (Call the NRC operations officer for state and licensee contact information, |
| the incident location, and licensee operator name.) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37996 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 05/16/2001|
| UNIT: [2] [] [] STATE: NY |NOTIFICATION TIME: 16:52[EDT]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 05/16/2001|
+------------------------------------------------+EVENT TIME: 16:06[EDT]|
| NRC NOTIFIED BY: FRANK KICH |LAST UPDATE DATE: 05/16/2001|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN ROGGE R1 |
|10 CFR SECTION: |MICHAEL PARKER R3 |
|*PRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION |JOHN GREEVES NMSS |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION/INFORMATION REGARDING A RECYCLE FACILITY SHIPMENT |
| CONTAINING RADIOACTIVE MATERIALS |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "Indian Point is making the following notification pursuant to |
| 10CFR50.72(b)(2)(xi) and in accordance with Station Administrative Order |
| 124, Item 47." |
| |
| "This report is being made pursuant to 10CFR50.72(b)(2)(xi), 'Any event or |
| situation, related to the health and safety of the public or on-site |
| personnel, or protection of the environment, for which a news release is |
| planned or notification to other government agencies has been or will be |
| made.'" |
| |
| "At approximately 1230 hours today[,] IP-2 was notified by KARTA Industries, |
| a recycle facility, that a shipment made by KARTA to Ohio was returned |
| because it contained radioactive material. KARTA plans to notify the New |
| York State Department of Environmental Conservation (DEC) of this event. |
| This report is being made for information only since the waste does not |
| appear to be associated with Indian Point operations. When notified by |
| KARTA, IP-2 dispatched radiation protection personnel to the KARTA facility |
| in Peekskill, NY. By 1330 [hours,] IP-2 RP personnel surveyed the returned |
| bale and determined it showed [approximately] 2.5 mrem/hr on contact. Since |
| IP-2 has expertise in radiation protection[,] it was decided to bring the |
| bale to the IP-2 site to ensure proper control and disposal. Isotopic |
| analysis of a sample of the bale material indicates mostly I-131[,] which |
| indicates a medical treatment, not material from a nuclear power plant. |
| KARTA does handle recyclable material from hospitals in the Peekskill |
| vicinity. IP-2 will assay the entire bale and ensure proper disposal. IP-2 |
| has been informed by KARTA that KARTA plans to notify the New York State |
| Department of Environmental Conservation (DEC)." |
| |
| The licensee plans to notify the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37997 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 05/16/2001|
| UNIT: [1] [2] [] STATE: VA |NOTIFICATION TIME: 18:26[EDT]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 05/16/2001|
+------------------------------------------------+EVENT TIME: 11:11[EDT]|
| NRC NOTIFIED BY: BRAD BROWN |LAST UPDATE DATE: 05/16/2001|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHARLES R. OGLE R2 |
|10 CFR SECTION: | |
|*IND 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 100 Power Operation |100 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| DISCOVERY THAT THE CONTROL ROOM HABITABILITY SYSTEM MAY NOT MEET DESIGN |
| REQUIREMENTS UNDER CERTAIN CONDITIONS |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "The control room habitability system may not meet design requirements under |
| certain conditions. Specifically, any design accident where the control |
| room bottled air pressurization system actuates and the exhaust fan of the |
| cable vault and tunnel area trips with the supply fan to the cable vault and |
| tunnel continuing to run, the minimum delta pressure between these areas may |
| not be maintained." |
| |
| "The control room bottled air systems of both Unit 1 and 2 have been |
| declared inoperable, and a 7-day [technical specification action statement |
| has] been entered." |
| |
| The licensee plans to notify the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37998 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 05/16/2001|
| UNIT: [1] [] [] STATE: MA |NOTIFICATION TIME: 19:16[EDT]|
| RXTYPE: [1] GE-3 |EVENT DATE: 05/16/2001|
+------------------------------------------------+EVENT TIME: 16:00[EDT]|
| NRC NOTIFIED BY: ERIC OLSON |LAST UPDATE DATE: 05/16/2001|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN ROGGE R1 |
|10 CFR SECTION: | |
|*ESF 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 N 0 Startup |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| REACTOR WATER CLEANUP SYSTEM ISOLATION DURING APPROACH TO CRITICALITY AND |
| MANUAL REACTOR SCRAM |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "During approach to criticality[,] the reactor water cleanup (RWCU) system |
| isolated on high temperature out of the non-[regenerative] heat exchanger. |
| The cause of the high temperature was due to air entering the system from an |
| ongoing local leak rate test. The RWCU system was providing the letdown |
| path to control [reactor] water level from control rod drive cooling [water] |
| flow. The control room was unable to recover the RWCU system and made the |
| decision to manually scram the [reactor]. A manual actuation of [the |
| reactor protection system] was inserted by placing the [reactor] mode switch |
| to shutdown. All rods [fully] inserted[,] and all systems responded as |
| expected." |
| |
| The NRC resident inspector was in the control room at the time of the event. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 37999 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 05/16/2001|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 23:53[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 05/16/2001|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 19:00[CDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 05/16/2001|
| CITY: PADUCAH REGION: 3 +-----------------------------+
| COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION |
|LICENSE#: GDP-1 AGREEMENT: Y |MICHAEL PARKER R3 |
| DOCKET: 0707001 |JOHN GREEVES NMSS |
+------------------------------------------------+NADER MAMISH IRO |
| NRC NOTIFIED BY: KEVIN BEASLEY | |
| HQ OPS OFFICER: DOUG WEAVER | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| NRC BULLETIN 91-01 RESPONSE - CRITICALITY CONTROL - (4-Hour Report) |
| |
| During the revision to NCSE 052 and 039 it was discovered that the condenser |
| could potentially be pressurized greater then 35.5 psia when the condenser |
| supply and return valve are both closed without a fluorinating environment |
| in the process gas system. NCSA CAS-002/001 allow both the supply and |
| return valves to be closed when draining the condenser without a |
| fluorinating environment. NCSEs 052 and 039 rely on the condenser supply |
| valve to be closed enough to prevent the condenser from being pressurized |
| above 35.5 psia during the time the return valve is closed and maintenance |
| personnel relieve the pressure on the condenser. Based on recent |
| discussions, it was discovered that closure of the supply valve may not |
| provide sufficient isolation to prevent the condenser from being pressurized |
| above 35.5 psia with the return valve closed because of potential seat |
| leakage of the supply valve. |
| |
| The licensee has stopped all maintenance activities which could create this |
| condition. Also, samples will be taken where this maintenance has occurred |
| to check that the freon still complies with the water content limits. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38000 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SURRY REGION: 2 |NOTIFICATION DATE: 05/17/2001|
| UNIT: [1] [2] [] STATE: VA |NOTIFICATION TIME: 01:38[EDT]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 05/16/2001|
+------------------------------------------------+EVENT TIME: 22:59[EDT]|
| NRC NOTIFIED BY: TIM WESPHALL |LAST UPDATE DATE: 05/17/2001|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHARLES R. OGLE R2 |
|10 CFR SECTION: | |
|*COM 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 100 Power Operation |100 Power Operation |
|2 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SAFETY PARAMETER DISPLAY SYSTEM (SPDS) INOPERABLE |
| |
| At 2259 hours on 5/16/01, the SPDS portion of the Emergency Response |
| Facilities Computer System (ERFCS) was noted to be inoperable because the |
| system time was not updating. The Technical Support Center (TSC) keyboard |
| is not available nor is the Control Room Unit keyboard available for either |
| Unit. Both Local Emergency Operations Facility (LEOF) and Central |
| Emergency Operations Facility (CEOF) SPDS data links were unavailable. |
| Initial indication of loss of ERFCS function was computer linkage failure at |
| 2159 hours on 5/16/01. The ERFCS was rebooted satisfactorily with a new |
| power supply. All portions of the system were noted to be functioning |
| correctly at 0120 hours on 5/17/01. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021