Event Notification Report for October 2, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
09/29/2000 - 10/02/2000
** EVENT NUMBERS **
37383 37386 37389 37390 37391 37392 37393 37394 37395
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 37383 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 09/26/2000|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 20:40[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 09/26/2000|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 17:30[EDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 10/01/2000|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |BRENT CLAYTON R3 |
| DOCKET: 0707002 |JOHN HICKEY NMSS |
+------------------------------------------------+FRANK CONGEL IRO |
| NRC NOTIFIED BY: JIM McCLEERY | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 4-HOUR NRC BULLETIN 91-01 REPORT INVOLVING THE X-705, DECON FACILITY, |
| COMPLEXING HANDTABLE DUCTWORK |
| |
| At 1730 during a review of Nuclear Criticality Safety Approval (NCSA) |
| Corrective Action Plan (CAP) with NCS it was noted that the X-705 Complexing |
| Handtable was not covered by an active NCSA. NCSA 705_014A00 had been |
| cancelled and the PORC approved 705_014A01 was not activated. Based on |
| security sweep data completed by Applied Nuclear Technology (ANT) personnel |
| it can be conservatively estimated that greater than 15 grams of U-235 exist |
| in the duct work associated with the handtable. TSR 3.11.2 Requires a NCSA |
| when operations involve uranium enriched to 1.0% or higher U-235 and 15 |
| grams or more U-235. |
| |
| The complexing handtable has not been in operation since NRC transition on |
| 03/03/97 and remains out of service. Upon notification of this issue the |
| Plant Staff Superintendent office directed the facility management to enter |
| an anomalous condition. This is reportable under UE2-RA-RE1030 (Event |
| Report Criteria) 3.C.1 as a 4 hour NRC Bulletin 91-01 event. |
| |
| SAFETY SIGNIFICANCE OF EVENT: |
| |
| The safety significance of this event is very low. No operation had taken |
| place on the complexing handtable since transition on 03/03/97. The small |
| amount of hold up may be greater than 15 grams of U-235, however, the |
| available data for the remainder of the handtable operation shows reading at |
| or near background levels. |
| |
| POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO OF HOW CRITICALITY , |
| ETC.): |
| |
| Since the handtable and associated piping are favorable geometry for any |
| enrichment, material would have to accumulate in the ductwork or pile up to |
| achieve a critical configuration. The operation is not currently being |
| performed and the ductwork is not connected to any system, therefore, a |
| criticality does not appear credible. |
| |
| CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.): |
| |
| The controlled parameter is geometry. The approved, but not implemented |
| NCSA establishes two controls based on geometry. |
| |
| ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS |
| LIMIT AND % WORST CASE OF CRITICAL MASS): |
| |
| The amount of U-235 is not more than 25 grams. Enrichment is not known, but |
| could be as high as 100%. The form of material is either uranyl fluoride or |
| uranyl nitrate. |
| |
| NUCLEAR CRITICALITY SAFETY CONTROL OR CONTROL SYSTEMS AND DESCRIPTION OF THE |
| FAILURES OR DEFICIENCIES |
| |
| The only deficiency is that the ductwork for the handtable potentially |
| contains more than 15 grams U-235 without an active NCSA to establish the |
| necessary controls to ensure double contingency. |
| |
| CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN EACH WAS IMPLEMENTED: |
| |
| Anomalous condition remains in effect until evaluations and testing are |
| completed. |
| |
| The NRC Resident Inspector was notified of this event by the certificate |
| holder. |
| |
| |
| * * * UPDATE ON 10/01/00 @ 1010 BY SPAETH TO GOULD * * * |
| |
| Non-Destructive Assay (NDA) analysis completed on 9/28/00 indicates less |
| than 15 grams of U-235 are present in the X-705 complexing handtable and |
| associated ductwork. The total U-235 identified in the and associated |
| ductwork is less than 6 grams including measurement uncertainties. An NCSA |
| is, therefore, not required for this equipment per TSR 3.11.2. |
| |
| The NRC Resident Inspector was notified. The DOE Representative will be |
| notified. |
| |
| The Reg 3 RDO(Clayton) and NMSS(Hickey) were notified. |
| |
| HOO Note: Portsmouth does not retract 91-01 Bulletins reports. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37386 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 09/28/2000|
| UNIT: [1] [2] [] STATE: MI |NOTIFICATION TIME: 01:23[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/28/2000|
+------------------------------------------------+EVENT TIME: 01:21[EDT]|
| NRC NOTIFIED BY: STEVE CHERBA |LAST UPDATE DATE: 10/01/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BRENT CLAYTON R3 |
|10 CFR SECTION: | |
|AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| ELECTRICAL BUS OUTAGE WILL AFFECT TSC VENTILATION SYSTEM |
| |
| "This event notification is for planned maintenance on Cook Unit 1's |
| electrical buses that remove power from a portion of the TSC ventilation |
| system. Contingencies are established to restore power to the TSC |
| ventilation fan (if needed) to support Emergency Plan execution. The fan |
| that will be unavailable boosts airflow through the TSC ventilation charcoal |
| clean-up filter subsystem. Ventilation flow will still pass through this |
| filter without the booster fan, but TSC pressure will not be boosted to |
| limit infiltration. Use of this fan is dependent on radiological conditions, |
| if radiological conditions warrant its use, and it is not available, the TSC |
| will relocate to the Unit 2 Control Room in accordance with plant |
| procedures. Reporting this event is consistent with NUREG-1022, Rev 1 |
| criteria for reporting loss of ERFs. |
| |
| "No adverse consequences are expected from this outage. The TSC ventilation |
| booster fan is expected to be unavailable for 48 hours, starting at 0121 |
| hours on 9-28-2000. Contingencies have been planned to restore power to the |
| booster fan in 8 to 10 hours if needed. Follow-up notification will be made |
| when the TSC is again fully available. The NRC Senior Site Resident |
| Inspector has been informed of this planned evolution." |
| |
| |
| * * * UPDATE ON 10/01/00 @ 0948 BY COBB TO GOULD * * * |
| |
| The onsite TSC emergency response facility has been restored as of 0515 and |
| it is fully available for use. |
| |
| The NRC Resident Inspector was notified. The Reg 3 RDO(Clayton) has been |
| notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 37389 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: NC DIVISION OF RADIATION PROTECTION |NOTIFICATION DATE: 09/29/2000|
|LICENSEE: UNION REGIONAL MEDICAL CENTER |NOTIFICATION TIME: 09:40[EDT]|
| CITY: MONROE REGION: 2 |EVENT DATE: 09/29/2000|
| COUNTY: STATE: NC |EVENT TIME: [EDT]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 09/29/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |CHARLES R. OGLE R2 |
| |FRITZ STURZ NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: S. JEFFRIES | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT |
| |
| An employee of the Union Regional Medical Center received an overexposure |
| based upon the results of dosimetery readings for the May-June 2000 |
| monitoring period. The individual's whole body TLD indicated the following |
| doses: 7762 mrem deep, 8168 mrem eye lens, and 8577 mrem shallow. In |
| addition, the individual's ring TLD indicated a dose of 11460 mrem. The |
| State of North Carolina is currently investigating this incident. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37390 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 09/29/2000|
| UNIT: [1] [] [] STATE: GA |NOTIFICATION TIME: 14:54[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 09/29/2000|
+------------------------------------------------+EVENT TIME: 13:57[EDT]|
| NRC NOTIFIED BY: PAUL UNDERWOOD |LAST UPDATE DATE: 09/29/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHARLES R. OGLE R2 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 M/R Y 55 Power Operation |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MANUAL REACTOR SCRAM FROM 55% POWER |
| |
| At 1357 on 09/29/00, while performing planned refueling outage shutdown |
| activities, a manual scram (RPS actuation) was actuated in response to |
| decreasing reactor water level due to both reactor feed pump turbines (RFPT) |
| being tripped. RFPT 'B' had been secured as per planned activities; RFPT |
| 'A' tripped on low suction pressure (cause unknown at this time). |
| |
| At the time of the manual scram, reactor water level was 22" and |
| decreasing. HPCI and RCIC both automatically actuated to recover reactor |
| water level. The lowest observed reactor water level was - 48". |
| |
| PCIV Groups 2 and 5, and Secondary Containment isolated as expected. SBGT |
| actuated as expected. |
| |
| Investigation is continuing. |
| |
| Recirculation pumps continued to run and decay heat is being removed by |
| steaming to the main condenser. The 'A' reactor feed pump has been |
| started. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37391 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 09/29/2000|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 17:40[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 09/29/2000|
+------------------------------------------------+EVENT TIME: 13:20[CDT]|
| NRC NOTIFIED BY: MARSHALL FUNKHOUSER |LAST UPDATE DATE: 09/29/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BRENT CLAYTON R3 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 99 Power Operation |99 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| HIGH PRESSURE CORE SPRAY DIESEL GENERATOR INOPERABLE |
| |
| At 1320 hours on 9/29/00, the seismic bolts of the Division 3 Diesel |
| Generator (DG) control panel door were discovered missing. At 1450, |
| Engineering determined that the seismic qualification of the control panel |
| was in question with these bolts missing. |
| |
| On 9/27/00, during the day shift, the Division 3 DG was tested per Clinton |
| Power Station (CPS) procedure 9080.02, DIESEL GENERATOR 1C OPERABILITY - |
| MANUAL AND QUICK START OPERABILITY. This procedure requires instrumentation |
| to be connected within the local control panel (1E22-S001B). The bolts to |
| this panel were discovered missing today at 1320. It is possible that they |
| had been missing since the performance of CPS 9080.02 but is unknown at this |
| time. The Division 3 DG is not analyzed for these missing bolts and is |
| considered inoperable while in this condition. |
| |
| This event is being reported pursuant to 10CFR50.72 (b)(2)(iii)(D) as a |
| condition that alone could have prevented the fulfillment of the High |
| Pressure Core Spray (HPCS) system, a single-train safety system needed to |
| mitigate the consequences of an accident, since the Division 3 DG is an |
| essential support system for the HPCS system needed to mitigate a small |
| break LOCA concurrent with a Loss of offsite power. |
| |
| The bolts were restored at 1442 today and the Division 3 DG is operable. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 37392 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 09/29/2000|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 22:46[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 09/29/2000|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 15:22[CDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 09/29/2000|
| CITY: PADUCAH REGION: 3 +-----------------------------+
| COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION |
|LICENSE#: GDP-1 AGREEMENT: Y |BRENT CLAYTON R3 |
| DOCKET: 0707001 |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: UNDERWOOD | |
| HQ OPS OFFICER: DOUG WEAVER | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NCFR NON CFR REPORT REQMNT | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SAFETY SYSTEM ACTUATION |
| |
| At 1522 on 09/29/00, the PSS office was notified that a secondary condensate |
| alarm was received on the C-360 position 3 autoclave Water Inventory Control |
| System (WICS). The WICS system is required to be operable while heating in |
| mode 5 according to TSR 2.1.4.3. The autoclave was checked according to the |
| alarm response procedure, removed from service and the WICS system was |
| declared inoperable by the Plant Shift Superintendent. Troubleshooting was |
| initiated and is continuing in order to determine the reason for the alarm. |
| |
| The safety system actuation is reportable to the NRC as required by Safety |
| Analysis Report section 6.9, table 1 criterion J.2 Safety System actuation |
| due to a valid signal as a 24-hour event notification |
| |
| The NRC Senior Resident has bean notified of this event. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37393 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 09/30/2000|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 05:14[EDT]|
| RXTYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 09/30/2000|
+------------------------------------------------+EVENT TIME: 01:10[CDT]|
| NRC NOTIFIED BY: HILL |LAST UPDATE DATE: 09/30/2000|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BRENT CLAYTON R3 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 85 Power Operation |85 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| HPCI DECLARED INOPERABLE AND THE UNIT ENTERED A 14 DAY LCO ACTION |
| STATEMENT. |
| |
| At 0110 hours on September 30, 2000, the Unit One High Pressure Cooling |
| Injection (HPCI) system was declared inoperable following failure to |
| successfully complete QCOS 2300-26, HPCI CCST Suction Check Valve Closure |
| Test. QCOS 2300-26 is an Inservice Testing surveillance used to verify |
| closure of the HPCI pump Contaminated Condensate Storage Tank (CCST) suction |
| check valve. The valve could not be verified to be closed by the |
| surveillance and the system was declared inoperable, as required by the |
| procedure. The time of the LCO entry was at 0048 hours when the system was |
| made inoperable for performance of the surveillance. Unit One is currently |
| in a 14 day LCO per Technical Specification 3.5.A.3. The HPCI system is |
| currently in the normal standby line-up, available for injection if |
| required, pending troubleshooting. |
| |
| The NRC Resident Inspector was notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37394 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 10/01/2000|
| UNIT: [1] [] [] STATE: LA |NOTIFICATION TIME: 03:56[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 09/30/2000|
+------------------------------------------------+EVENT TIME: 23:33[CDT]|
| NRC NOTIFIED BY: HUSTON |LAST UPDATE DATE: 10/01/2000|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHUCK CAIN R4 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PLANT ENTERED LCO ACTION STATEMENT WHEN BOTH PRIMARY CONTAINMENT UNIT |
| COOLERS WHERE DECLARED INOPERABLE. |
| |
| On 09130/00 at 2333, both Primary Containment Unit Coolers were declared |
| inoperable based on an apparent failure to fully meet required volumetric |
| flow rates. The Tech Spec SR 3.6.1.7.2 required values are greater than or |
| equal to 50,000 CFM. Actual calculated values were determined to be |
| approximately 45,000 CFM for Unit cooler A and 48,000 CFM for Unit cooler B. |
| This condition may impact the ability of these unit coolers to perform their |
| design safety functions. This report is being made pursuant to 10 CFR 50.72 |
| b.2.iii.D for loss of function required to mitigate an accident. |
| Activities to restore function include evaluation of test data and |
| methodology, cleaning of unit cooler coils, verification of calibration |
| data, and verification of system alignment. |
| The plant is in a 8 hour LCO to restore one of the coolers to operable |
| status or be in mode 3 within the following 12 hours. |
| |
| The NRC Resident Inspector was notified. |
| |
| * * * UPDATE ON 10/1/00 AT 2320 BY HUSTON, RECEIVED BY WEAVER * * * |
| |
| Both Primary Containment Unit Coolers A and B (Divisions I and II) have been |
| re-tested satisfactorily verifying both safety function and Tech Spec |
| operability. The station declared both Containment Unit Cooler A and B |
| operable and exited the LCO regarding Primary Containment Unit Coolers at |
| 1048 hours on 10/1/00 |
| |
| The station is evaluating information developed to determine whether a |
| retraction is warranted. |
| |
| The licensee will notify the NRC resident inspector. The Operations Center |
| notified the R4DO (Cain). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37395 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 10/01/2000|
| UNIT: [2] [3] [] STATE: NY |NOTIFICATION TIME: 10:40[EDT]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 10/01/2000|
+------------------------------------------------+EVENT TIME: [EDT]|
| NRC NOTIFIED BY: CALLER |LAST UPDATE DATE: 10/01/2000|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN KINNEMAN R1 |
|10 CFR SECTION: |AARON DANIS IAT |
|DDDD 73.71 UNSPECIFIED PARAGRAPH |FRANK CONGEL IRO |
| |RICHARD ROSANO IAT |
| |ELINOR ADENSAM NRR |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 N N 0 Refueling |0 Refueling |
|3 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| NONCREDIBLE BOMB THREAT RECEIVED BY HOO. FOR DETAILS SEE HOO LOG |
| BOOK/MISCELLANEOUS INFORMATION. |
| |
| NOTIFIED INDIAN POINT 2 (MONTROSS) AND INDIAN POINT 3 (MC ELROY). |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021