Event Notification Report for April 22, 2002
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
04/19/2002 - 04/22/2002
** EVENT NUMBERS **
38762 38827 38860 38861 38864 38865 38866 38867 38868 38869 38870
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38762 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 03/12/2002|
| UNIT: [1] [2] [] STATE: WI |NOTIFICATION TIME: 20:51[EST]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 03/12/2002|
+------------------------------------------------+EVENT TIME: 14:30[CST]|
| NRC NOTIFIED BY: THOMAS JESSESSKY |LAST UPDATE DATE: 04/19/2002|
| HQ OPS OFFICER: GERRY WAIG +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MONTE PHILLIPS R3 |
|10 CFR SECTION: | |
|AUNA 50.72(b)(3)(ii)(B) UNANALYZED CONDITION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| UNANALYZED CONDITION, APPENDIX R VALVE UNABLE TO SATISFY DESIGN
FUNCTION |
| |
| "At 1430 on 3/12/02, an Appendix R credited valve was determined to be |
| unable to satisfy its design function of providing a flow path from the |
| Charging System to the Reactor Coolant System (RCS). The credited flow path |
| is necessary to control RCS inventory and maintain the plant in Mode 3 (Hot |
| Standby) during an Appendix R fire. The flow path is also utilized |
| procedurally in controlling RCS inventory while the RCS is cooled down and |
| depressurized from Mode 3 (Hot Standby) to Mode 5 (Cold Shutdown). |
| |
| "This issue places the plant in an unanalyzed condition and thus is |
| reportable under 50.73 (a)(2)(ii). |
| |
| "The specific valve is 1/2CV-1296 Auxiliary Charging Line Isolation valve. |
| The valve's design function is to open on a differential pressure of 200 |
| psid (with or without instrument air) between the discharge of the charging |
| pumps and the RCS. This line is not utilized during normal operations but is |
| an available charging path to the RCS and utilized during plant shutdown in |
| the event of an Appendix R fire. The valve is an air operated valve that is |
| assumed to have failed close due to a loss of instrument air. It has been |
| found that the valve will not open until a much higher differential pressure |
| is reached. If the RCS is at normal operating pressure (2235 psig), and the |
| actual lift pressure of the valve is greater than 500 psid, charging flow |
| will be unavailable to the RCS. A relief on the discharge of the outlet of |
| the charging pump will lift at 2735 and prevent flow to the RCS. The |
| charging pump maximum discharge pressure is 3000 psig. |
| |
| "Compensatory actions have been undertaken that establish plantwide fire |
| rounds. Fire rounds will be continued until the condition is corrected or a |
| suitable evaluation is completed that establishes other actions." |
| |
| The licensee notified the NRC Resident. |
| |
| ****RETRACTION 4/19/02 at 1821 from Mike Holzmann to Rich Laura**** |
| |
| "RETRACTION OF EVENT NOTIFICATION #38762 |
| |
| "At 2051 EST on March 12, 2002, ENS Event Notification # 38762 was made in |
| accordance with 10 CFR 50.72(b)(3)(ii)(B) for identification of an |
| unanalyzed condition that had the potential to significantly degrade plant |
| safety involving the Appendix R safe shutdown fire analysis. PBNP Unit 1 and |
| 2 valve CV-1296, 'Auxiliary Charging Line Isolation Valve,' are air-operated |
| valves. These valves, one in each unit, are credited with opening at 200 |
| psid to provide a charging system flow path to control RCS inventory and to |
| maintain the plant in Mode 3 (hot standby) during the Appendix R safe |
| shutdown fire with loss of instrument air. The notification was made when we |
| identified that the CV-1296 valves will not open until a much higher |
| differential pressure is reached and; therefore, the flow path through the |
| valve may not be capable of providing the Appendix R function of controlling |
| RCS inventory. At the time of this notification an evaluation of the |
| consequences of this Condition had not been assessed, and the report was |
| made because of the potential for the plant being in an unanalyzed condition |
| that significantly degrades plant safety. |
| |
| "We have subsequently completed an engineering evaluation which identified |
| the differential pressure necessary to permit charging flow through the |
| CV-1296 valve. This evaluation is based on the measured lifting force of the |
| valve stem with zero differential pressure across the valve. We have further |
| determined, based on engineering analysis supported by MAAP4 computer runs, |
| and using a more conservative RCS injection pressure then identified above, |
| that the RCS pressure would drop low enough to permit charging flow into the |
| RCS, before the RCS pressurizer level is lost. We have thus concluded that |
| the condition identified in our event notification would not result in a |
| significant degradation of plant safety. Therefore, this condition is not |
| reportable under 10 CFR 50.72 or 50.73, and we are hereby retracting this |
| event notification." |
| |
| The Senior Resident Inspector has been informed. The R3DO (J. Madera) has |
| been notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 38827 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE:
04/03/2002|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 15:54[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 04/03/2002|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 11:59[EST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 04/19/2002|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |DAVID HILLS R3 |
| DOCKET: 0707002 |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: RICK LARSON | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 24-HOUR NRC BULLETIN 91-01 (CRITICALITY CONTROLS) ISSUE AT PORTSMOUTH
|
| GASEOUS DIFFUSION PLANT |
| |
| "At 1159 hours today after Nuclear Materials Engineering completed a review |
| of their databases for batched items stored in 55 gal. drums, it was |
| discovered that 26 drums with questionable Segmented Gamma Scanner (SGS) |
| values were located in the XT-847. The concern about the SGS not correctly |
| counting the U-235 mass was identified earlier but at that time no drums |
| were identified in the United States Enrichment Corporation (USEC) leased |
| spaces. The mass counting error identified between the SCS and the Low |
| Density Waste Assay Monitor (LDWAM) was at times off by a factor of 10 or |
| more. Because of the questionable SGS measurements it could not be assured |
| the 350 gram U-235 limit per batched drum was maintained. The governing NSCA |
| X-0847_ 001. A04 Operation of the XT-847 Facility in it's NCSE accounted for |
| an error of a factor of two in mass calculations, as a bounding condition. |
| Thus with the loss of the bounding calculations and the potential error in |
| mass calculations, this resulted in the loss of both legs of the double |
| contingency basis (mass & the factor of two bounding error) for NCSA |
| X-847_001.A04. At the present time Waste Material handlers in the XT-847 |
| are moving all 26 drums from their storage area to another storage location |
| within the building to allow for remeasurement of the drums. The guidance |
| for moving and relocating these drums for remeasurement is covered by |
| existing procedures and NCSAs. |
| |
| "SAFETY SIGNIFICANCE OF EVENTS: The safety significance of this event is low |
| because the actual uranium mass content of the drums in question would not |
| be expected to contain more than a safe amount of uranium bearing material. |
| Other similar drums of trapping material batched during the same period |
| using LDWAM measurements contain considerably less than a safe mass of |
| U-235. The uranium mass limits assume optimum moderation and 100% |
| enrichment. The drums in question are known to contain less than 10% |
| enrichment (based upon process knowledge or sampling) and the material |
| stored in the XT-847 is dry trapping material (alumina, etc). Even with the |
| maximum potential error in the SGS measurements, the total mass in any drum |
| (or group) would be less than the safe mass of uranium at an H/U of 4 (wet |
| air moderation of approximately 7.9 kg of U-235 (100% enrichment) |
| |
| "POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO[S] OF HOW |
| CRITICALITY COULD OCCUR): |
| For a criticality to occur, the following events would be required: One or |
| more drums must contain greater than a minimum critical mass of uranium (at |
| this time, the measurement results are in question, but greater than a safe |
| mass has not actually been measured in any drum), the contents of the drums |
| would need to be moderated by water or oil (the material is dry trapping |
| material), and some amount of reflection would be required (for the drums, |
| or groups of drums, currently spaced 2 feet edge-to-edge apart). |
| |
| "CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY. CONCENTRATION,
ETC.): |
| The drums were filled by batching small diameter containers of trapping |
| material based upon NDA or sample measurements of the uranium mass present. |
| The batching limits are 43.5% of the minimum critical mass assuming optimum |
| moderation, concentration, geometry, reflection, etc. In the applicable |
| NCSE, credit is taken for a double batch scenario bounding potential uranium |
| mass upsets; however, the potential error in the SGS measurements may be |
| greater than a factor of two. Spacing is controlled for drums, or groups of |
| drums, unless categorized as containing less than 15 grams U-235. |
| |
| "ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE
PROCESS |
| LIMIT AND % WORST CASE OF CRITICAL MASS): The contents of the drums are dry |
| trapping material from the cascade buildings, and are known to be enriched |
| to 10% or less. At the time they were filled, the total mass was calculated |
| to be less than 350 grams U-235. However, the SGS used to measure source |
| containers has been questioned. The variability of the SGS results indicate |
| that the total uranium mass in containers batched into a drum could be |
| non-conservative by a factor of 10 or more. |
| |
| "NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND
DESCRIPTION |
| OF THE FAILURES OR DEFICIENCIES: Recent NDA measurements performed on the |
| Low Density Waste Assay Monitor (LDWAM) have identified discrepancies in the |
| gram quantity of U-235 when compared to the Segmented Gamma Scanner (SGS) |
| measured values (see PR-PTS-02-01398). The SGS values are biased low which |
| could have resulted in underestimatlng the total batch quantity for |
| previously batched drums. Until confirmatory measurements of the drums are |
| obtained, the potential mass content represents a loss of both legs of |
| double contingency as described in the applicable NCSE. |
| |
| "CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN EACH WAS
IMPLEMENTED: |
| These drums are not safety systems but corrective actions to regain |
| compliance was started at 1530 hours 4/2/02." |
| |
| The NRC Resident Inspector was notified by the certificate holder. |
| |
| ****UPDATE 4/19/02 at 1533, J. McCleery to R. Laura**** |
| |
| "Update 1: There is no safety significance for this event because all 21 |
| drums have now been confirmed to contain less than a safe mass for the |
| enrichment of material. While one drum was found to exceed the 350 grams |
| U-235 control limit. The actual U-235 mass is less than a safe mass and the |
| process conditions credited for double contingency were maintained. All |
| potential drum groups that could have exceeded 350 gram U-235 were examined, |
| the maximum mass for a drum group would have been approximately 620 grams |
| U-235, at a maximum of 5% enrichment. Therefore, all drum groups would have |
| been below safe mass at process conditions. Criticality was determined |
| noncredible given the new measurements for these drums." |
| |
| Notified R3DO (J. Madera) and NMSS (F. Brown) of this update. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 38860 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: NC DIV OF RADIATION PROTECTION |NOTIFICATION DATE: 04/17/2002|
|LICENSEE: UNKNOWN |NOTIFICATION TIME: 15:17[EDT]|
| CITY: ASHEVILLE REGION: 2 |EVENT DATE: 04/13/2002|
| COUNTY: STATE: NC |EVENT TIME: [EDT]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 04/17/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |BRIAN BONSER R2 |
| |JOHN HICKEY NMSS |
+------------------------------------------------+FEMA, DOE, USDA, HHS FAX |
| NRC NOTIFIED BY: GRANT MILLS |EPA, DOT(via NRC) FAX |
| HQ OPS OFFICER: LEIGH TROCINE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT/POSSIBLE RADIOACTIVE MATERIAL INCIDENT
INVOLVING |
| DISCOVERY AND DISPOSAL (AS TRASH) OF CONTAINERS WITH RADIOACTIVE LABELS
IN |
| NORTH CAROLINA |
| |
| The following text is a portion of a facsimile received from the North |
| Carolina Department of Environment and Natural Resources, Division of |
| Radiation Protection: |
| |
| "On April 17, 2002, the North Carolina Division of Radiation Protection, |
| Radioactive Material Section, was notified by the North Carolina Hazardous |
| Material staff of an ongoing event possibly involving radioactive material. |
| During the clean up of an unoccupied home (located in Asheville, NC) by a |
| church group, several containers with radioactive labels were discovered and |
| disposed of as trash (on April 13, 2002). The containers (approximately 10 |
| in number) were described as 3 inches in diameter (possibly lead), labeled |
| with the radiation symbol, and labeled 'TC'. Local authorities have |
| concluded the trash was deposited at the local landfill (Buncombe Co.) and |
| is currently under 1,500 tons of trash. Local authorities have performed |
| radiation exposure measurements at the landfill and home site[. They] |
| report no significant measurements above background levels. The North |
| Carolina Division of Radiation Protection is continuing to gather |
| information." |
| |
| Call the NRC operations officer for contact information. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 38861 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: LOUISIANA RADIATION PROTECTION DIV |NOTIFICATION DATE: 04/17/2002|
|LICENSEE: MEMORIAL MEDICAL CENTER-BAPTIST CAMPU|NOTIFICATION TIME:
16:30[EDT]|
| CITY: NEW ORLEANS REGION: 4 |EVENT DATE: 04/12/2002|
| COUNTY: STATE: LA |EVENT TIME: [CDT]|
|LICENSE#: LA-0349-L01 AGREEMENT: Y |LAST UPDATE DATE: 04/17/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |LINDA SMITH R4 |
| |DON COOL NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: SCOTT BLACKWELL | |
| HQ OPS OFFICER: LEIGH TROCINE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT/MEDICAL MISADMINISTRATIONS INVOLVING THREE
PATIENTS |
| AT MEMORIAL MEDICAL CENTER-BAPTIST CAMPUS IN NEW ORLEANS, LOUISIANA
|
| |
| The following text is a portion of a facsimile received from the Louisiana |
| Department of Environmental Quality: |
| |
| "Event Report ID No.: LA020007" |
| |
| "License No.: LA-0349-L01" |
| |
| "Licensee: Memorial Medical Center-Baptist Campus" |
| |
| "Event [Date] and Time: At the beginning of March 2002" |
| |
| "Event Location: [... New Orleans, LA ...]" |
| |
| "Event [Type]: Misadministration" |
| |
| "Notifications: Notified the patients and physician." |
| |
| "Event [Description]: On April 12, 2002, it was discovered that [three] |
| patients received a misadministration on a therapy procedure. All three |
| patients were to receive therapy doses to the prostate. While planning the |
| therapy, the Dosimetrist put Nucletron Source Positioning Simulator (Part |
| #111.094) together the wrong way. The design of the Simulator allows it to |
| be put together backwards. The correct distance for the dose was 1408 mm, |
| but the actual distance was 1117 mm. The dose the patient received was |
| calculated as 70 centigray to the knees, thighs, and scrotum of the three |
| patients. As of now, there appears to be no observable effects to the |
| patients. All three patients were notified and agreed to have the therapy |
| again for the correct site. This facility uses a Nucletron Vectrave HDR |
| with a 10-Ci source of Ir-192. The activity during the patient therapy was |
| 8.06 Ci for one patient, 5.45 Ci for another, and 4.8 Ci for the third |
| patient. The policy has been changed so that the physicist will check the |
| position simulator before use. Further details will be placed in the NMED |
| database as soon as the details are available." |
| |
| "Transport [Vehicle Description]: NA" |
| |
| "Media [Attention]: NA" |
| |
| Call the NRC operations officer for state contact information and event |
| location details. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38864 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 04/19/2002|
| UNIT: [] [2] [] STATE: CT |NOTIFICATION TIME: 14:25[EDT]|
| RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 04/19/2002|
+------------------------------------------------+EVENT TIME: 14:03[EDT]|
| NRC NOTIFIED BY: BRIAN KOSHMERAL |LAST UPDATE DATE: 04/19/2002|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |JOHN ROGGE R1 |
|10 CFR SECTION: |CHRIS GRIMES NRR |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 99 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR TRIP AT MILLSTONE UNIT 2 |
| |
| The licensee reported that all control rods inserted properly and all |
| systems functioned as designed. The reactor trip was initiated from a main |
| turbine protective trip which may be related to a stator cooling |
| malfunction. The plant is currently stable in Hot Standby. The licensee has |
| begun investigating the cause of the event. |
| |
| The Resident Inspector has been notified. Additionally, the licensee |
| notified the State and Local officials. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38865 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 04/19/2002|
| UNIT: [1] [] [] STATE: GA |NOTIFICATION TIME: 18:50[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/19/2002|
+------------------------------------------------+EVENT TIME: 16:54[EDT]|
| NRC NOTIFIED BY: EDWIN URQUHART |LAST UPDATE DATE: 04/19/2002|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |BRIAN BONSER R2 |
|10 CFR SECTION: |RICHARD WESSMAN IRO |
|ASHU 50.72(b)(2)(i) PLANT S/D REQD BY TS |SINGH BAJWA NRR |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 19 Power Operation |9 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PLANT SHUTDOWN REQUIRED BY TECHNICAL SPECIFICATIONS ON UNIDENTIFIED
DRYWELL |
| FLOOR LEAKAGE |
| |
| "This report is being made pursuant to 10 CFR 50.54(z); 50.72(a) (1) (ii) |
| and 50.72(b) (i) the initiation of a nuclear plant shutdown required by the |
| plant's Technical Specifications. Plant E. I. Hatch, unit one has commenced |
| a plant shutdown as required by Technical Specifications 3.4.4 A (RCS |
| Operational Leakage). The Reactor Coolant System unidentified leakage has |
| been calculated to be greater than the Technical Specification limit of 5 |
| GPM. The leakage has been calculated to be 6.85 GPM at 1647 Hrs. Eastern |
| Time, The plant was operating at 19% rated thermal power (RTP) and commenced |
| a power reduction at 1650 Hrs. Eastern Time. The current power is 9% RTP and |
| shutdown is in progress." |
| |
| The licensee notified the Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 38866 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 04/20/2002|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 01:27[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 04/19/2002|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 07:00[CDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 04/20/2002|
| CITY: PADUCAH REGION: 3 +-----------------------------+
| COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION |
|LICENSE#: GDP-1 AGREEMENT: Y |JOHN MADERA R3 |
| DOCKET: 0707001 |WAYNE HODGES NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: T. E. WHITE | |
| HQ OPS OFFICER: MIKE NORRIS | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| NRC BULLETIN 91-01 RESPONSE (24-Hour Report) |
| |
| "At 0700, on 04-19-02, the Plant Shift Superintendent (PSS) was notified |
| errors were found in historical data associated with three 30 gallon drums. |
| Research to support remediation activities associated with NCS-INC-01-025 |
| revealed that information used to characterize waste drums had been |
| incorrectly entered onto the Request For Waste Classification (RWC) sheets |
| for these three 30 gallon waste drums of NCS Spacing Exempt classified |
| waste, violating requirements of NCSA WM-03 and WMO.001. This violated the |
| Double Contingency principal. These drums were transitioned to storage under |
| WMO.001 upon deletion of WM-03. The purpose of the requirement is to ensure |
| the correct Information is available on the RWC for classification. |
| |
| "This Is a legacy issue; upon review of the correct data associated with |
| these drums, the classification status of NCS Spacing-Exempt is correct. The |
| drums are currently being properly controlled. |
| |
| "The NRC Senior Resident Inspector has been notified of this event. |
| |
| "SAFETY SIGNIFICANCE OF EVENTS: |
| |
| "Although the calculations were incorrectly performed and the independent |
| verification failed to catch the error, the correct data associated with |
| these drums was reviewed and the drums are still NCS Spacing-Exempt and |
| controlled properly. However, the paperwork needs to be updated to assure |
| downstream problems are avoided. |
| |
| "POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO(S) OF HOW |
| CRITICALITY COULD OCCUR |
| |
| In order for a criticality to be possible, the mass in multiple adjacent |
| waste drums stored as NCS Spacing Exempt would each have to be greater than |
| the safe mass determined for that container size and these waste drums would |
| have to be stored together or recontainerized into unfavorable geometry |
| containers. |
| |
| "CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION,
ETC) |
| |
| "The controlled parameter is mass. |
| |
| "ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE
PROCESS |
| LIMIT AND % WORST CASE CRITICAL MASS): |
| |
| "The correct data indicated that the mass of the drums was less than the |
| always safe mass of 120 grams of U-235. |
| |
| "NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND
DESCRIPTION |
| OF THE FAILURES OR DEFICIENCIES |
| |
| "Double contingency is maintained by implementing two controls to ensure the |
| uranium mass used for classification is correctly listed on the RWC. |
| |
| "The first leg of double contingency is based on correctly calculating and |
| transcribing the mass result onto the RWC. The wrong analytical result was |
| used for the calculation. This wrong calculational result was transcribed |
| onto the RWC. The control was violated. Since there are two controls on one |
| parameter, double contingency was not maintained, |
| |
| "The second leg of double contingency is based on independently verifying |
| the mass was correctly calculated and transcribed onto the RWC. The |
| incorrect calculation and transcription was not discovered during the |
| independent verification. The control was violated. Since there are two |
| controls on one parameter, double Contingency was not maintained. |
| |
| "Since double contingency is based on two controls on one parameter, double |
| contingency was not maintained. |
| |
| "CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEMS AND WHEN EACH WAS
|
| IMPLEMENTED: |
| |
| "Correct the RWCs." |
| |
| The NRC Resident Inspector has been notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38867 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 04/20/2002|
| UNIT: [1] [] [] STATE: GA |NOTIFICATION TIME: 06:52[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/20/2002|
+------------------------------------------------+EVENT TIME: 05:12[EDT]|
| NRC NOTIFIED BY: ROB DORMAN |LAST UPDATE DATE: 04/20/2002|
| HQ OPS OFFICER: MIKE NORRIS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |BRIAN BONSER R2 |
|10 CFR SECTION: | |
|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 30 Power Operation |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MANUAL RPS ACTIVATION DUE TO LOSS OF FEEDWATER |
| |
| "Unit 1 was at approximately 30% power and preparing to synchronize the Main |
| Generator to the grid. The A Main Feedwater Pump mini flow valve was |
| isolated per plant procedures. The isolation of the mini flow valve caused |
| the Steam Generator levels to rise. A Hi-Hi Steam Generator level occurred |
| in #4 Steam Generator. This resulted in a trip of the Main Feedwater Pump, a |
| Feedwater Isolation Signal, and the trip of the Main Turbine. The Reactor |
| was tripped due to having no Main Feedwater available to the Steam |
| Generators in anticipation of a low-low Steam Generator level trip at 38% |
| level. Both Motor Driven Auxiliary Feedwater pumps did start as a result of |
| the only running Main Feedwater pump being tripped." All rods fully |
| inserted into the core. |
| |
| The NRC Resident Inspector has been notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38868 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: YANKEE ROWE REGION: 1 |NOTIFICATION DATE: 04/20/2002|
| UNIT: [1] [] [] STATE: MA |NOTIFICATION TIME: 07:49[EDT]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 04/20/2002|
+------------------------------------------------+EVENT TIME: 06:51[EDT]|
| NRC NOTIFIED BY: DON MILLER |LAST UPDATE DATE: 04/20/2002|
| HQ OPS OFFICER: MIKE NORRIS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNUSUAL EVENT |JOHN ROGGE R1 |
|10 CFR SECTION: |DICK WESSMAN IRO |
|AAEC 50.72(a) (1) (i) EMERGENCY DECLARED |WAYNE HODGES NMSS |
| |S. BAYWA NRR |
| |R. ZAPATA FEMA |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Decommissioned |0 Decommissioned |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| USUAL EVENT DECLARED DUE TO SEISMIC ANOMOLY |
| |
| Licensee felt tremors in the control room lasting more than 5 seconds and |
| declared an Unusual Event at 0700 and immediately downgraded at 0701. |
| Walkdowns were performed and no damage was noted. Licensee has seismic |
| monitors which have a setpoint of .01 G and they did not alarm. Offsite |
| notifications have been made to the states of MA and VT. |
| |
| The NRC Resident Inspector will be notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38869 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 04/20/2002|
| UNIT: [] [4] [] STATE: FL |NOTIFICATION TIME: 20:34[EDT]|
| RXTYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 04/20/2002|
+------------------------------------------------+EVENT TIME: 16:57[EDT]|
| NRC NOTIFIED BY: JEFF DEAL |LAST UPDATE DATE: 04/20/2002|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |BRIAN BONSER R2 |
|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
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|4 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNPLANNED LOSS OF CONTROL ROOM ANNUNCIATORS LESS THAN 15 MINUTES
|
| |
| The licensee reported the loss of control room annunciators for 9 minutes |
| when the electrical supply breaker tripped free. The breaker was reset and |
| closed which restored the annunciators. However, later the same electrical |
| breaker tripped free again resulting in the loss of control annunciators |
| lasting for 14 minutes. The breaker was reset and closed for the second |
| time. Maintenance troubleshooting revealed that the breaker needed to be |
| replaced. The isolation for this corrective maintenance will result in a |
| planned loss of control room annunciators greater than 15 minutes. |
| Alternate plant monitoring will be utilized for the duration of the breaker |
| change out. |
| |
| The NRC Resident Inspector was notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38870 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 04/22/2002|
| UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 02:43[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/22/2002|
+------------------------------------------------+EVENT TIME: 01:15[EDT]|
| NRC NOTIFIED BY: ART FINCH |LAST UPDATE DATE: 04/22/2002|
| HQ OPS OFFICER: MIKE NORRIS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |JOHN ROGGE R1 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 M/R Y 16 Power Operation |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MANUAL RPS ACTUATION |
| |
| "Susquehanna Unit 1 was at 20% power and in the process of preparing to |
| further increase power following a Refueling and Inspection Outage. At 0016 |
| on 4/22/02, the B Reactor Recirculation Pump tripped for an unexplained |
| reason. During a review of the plant response to the transient, it was |
| discovered that the unit was operating to the left of the expected Power to |
| Flow curve. There was no indication of power flux oscillations from the |
| nuclear instrumentation, but no guidance was available on how to respond to |
| this condition. Reactor Engineering and Operations Management were contacted |
| and it was decided to manually scram the unit. At 0115 the Mode Switch was |
| taken to Shutdown and all control rods inserted. This was an unplanned RPS |
| Actuation and in accordance with 10 CFR 50.72(b)(2)(iv)(B) requires a |
| four-hour ENS Notification. Reactor water level dropped below level 3 which |
| is expected during a scram, feedwater level control responded to return |
| level to normal and all level 3 isolations went to completion. There were no |
| ECCS initiations, no challenges to containment, and no indication of |
| radiation releases. Operations is currently performing a controlled cooldown |
| to mode 4, an investigation into the cause of the recirc pump trip is |
| ongoing." |
| |
| The NRC Resident Inspector has been notified. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021