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Home > NRC Library > Document Collections > Reports Associated With Events > Event Notification Reports > 2001

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                                   
+------------------------------------------------------------------------------+
| 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.                            |
+------------------------------------------------------------------------------+