Event Notification Report for May 5, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
05/04/2000 - 05/05/2000
** EVENT NUMBERS **
36967 36969 36970 36971 36972 36973 36974 36975
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|Power Reactor |Event Number: 36967 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 05/03/2000|
| UNIT: [] [2] [] STATE: NY |NOTIFICATION TIME: 22:27[EDT]|
| RXTYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 05/03/2000|
+------------------------------------------------+EVENT TIME: 22:15[EDT]|
| NRC NOTIFIED BY: TONY PETRELLI |LAST UPDATE DATE: 05/04/2000|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |NIEL DELLA GRECA R1 |
|10 CFR SECTION: | |
|ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |96 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| UNIT 2 TECH SPEC REQD SHUTDOWN DUE TO 2 CONTAINMENT PURGE VALVES FAILING |
| THEIR LLRT- |
| |
| The licensee is shutting Unit 2 down from 100% power in accordance with Tech |
| Spec 3.6.3.A, 12 Hour Shutdown LCO, due to containment purge valves |
| #CPS*AOV-104 & 106 failing their local leak rate test #N2-ISP-CPS-Q001. |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| * * *UPDATE ON 05/04/00 AT 0002 ET BY M. ERON TAKEN BY MACKINNON * * * |
| |
| Licensee exited Technical Specification 3.6.3.A at 2350 ET after manual |
| Containment Purge Supply valve, 2CPS-V6, an upstream valve to #CPS*AOV-104 & |
| 106 was leak tested and verified closed. Lowest reactor power level reached |
| was 92%. R1DO (Della Greca) notified. |
| |
| The NRC Resident Inspector was notified of this update by the licensee. |
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|Fuel Cycle Facility |Event Number: 36969 |
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| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 05/04/2000|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 05:46[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 05/03/2000|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 08:00[EDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 05/04/2000|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |BRUCE BURGESS R3 |
| DOCKET: 0707002 |JOSEPHINE PICCONE NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: SISLER | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| POTENTIAL FOR ACCUMULATION OF SLUDGE CONTAINING HEAVY METALS ON/IN THE LID |
| OF TUB |
| |
| NRC BULLETIN 91-01 24 hour notification |
| |
| On 5/3/00 at 0800 hours it was discovered that a NCSA-0705_027.A003 control |
| was not in place. The sludge tub used for accumulating heavy metal |
| (including uranium) sludge had an unsafe/unfavorable geometry molded into |
| the design. The unfavorable dimensions created by the raised lip is 7.75" by |
| 37" by 2". This could have resulted in the potential accumulation, of an |
| unsafe volume on the sludge tub lid had a leak developed In a nearby system |
| containing uranium-bearing solution. |
| |
| NCSA-705_027.A003 requirement #17 states "Geometrically unfavorable |
| containers shall not be left uncovered while unattended in the heavy metals |
| precipitation process area or on the mezzanine in the area of the heavy |
| metals precipitation raffinate storage (HMPRS)". This was a loss of one |
| control (geometry/volume) in the double contingency principle for the afore |
| mentioned NCSA. The second control (physical integrity of nearby |
| uranium-bearing systems) was maintained throughout the event. |
| |
| At the direction of the Plant Shift Superintendent (PSS), the requirements |
| for the NCS anomalous condition were initiated. At 1015 hours compliance was |
| regained by covering the molded design |
| |
| SAFETY SIGNIFICANCE OF EVENTS: |
| |
| On May 3, 2000, it was discovered that the sludge tub used for accumulating |
| sludge containing heavy metals (including uranium) contains an accumulation |
| point on/in the lid. That accumulation point is created by a raised lip and |
| has unfavorable geometric dimensions (7.75" by 37" by 2"). This is a |
| violation of NCSA-0705_027 and NCSA-0705_076. This could have resulted in |
| the potential accumulation of an unsafe volume of solution on/in the sludge |
| tub lid had a leak developed in a nearby system which contain |
| uranium-bearing solution. No uranium-bearing material was involved in the |
| violation, since the remaining barrier to criticality (i.e., the physical |
| integrity of nearby uranium-bearing systems) was maintained. Therefore, the |
| safety significance of this event is low. |
| |
| POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO[S] OF HOW |
| CRITICALITY COULD OCCUR): |
| |
| If a leak had developed in a nearby uranium-bearing system such that the |
| solution could have accumulated on/in the sludge tub lid, an unsafe geometry |
| of solution could have resulted. If the leaking solution had contained a |
| sufficient amount of uranium, the resulting configuration could have been |
| sufficient for a criticality to occur. It should be noted that the allowed |
| safe geometry and volume limits established In NCSA-0705_076 are based on |
| potentially moderated, UO2F2 and water solution which contains uranium |
| enriched to 100 wt%. |
| |
| CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.): |
| |
| The parameter which was violated during this upset was the geometry of |
| potential accumulation present in the sludge tub lid (i.e., the volume in |
| which uranium-bearing solution could have accumulated in the event of a |
| leak). The physical integrity of the nearby systems containing |
| uranium-bearing material was maintained. |
| |
| ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS |
| LIMIT AND % WORST CASE OF CRITICAL MASS): |
| |
| No uranium bearing material was actually introduced into the lid of the |
| sludge tub. |
| |
| NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION |
| OF THE FAILURES OR DEFICIENCIES |
| |
| NCSA-0705_076.A00 and NCSA-0705_027 take credit for the physical integrity |
| of Systems which contain uranium-bearing material and that unsafe |
| volume/geometry containers are either modified, covered, or oriented to |
| prevent an unsafe configuration from resulting In the event of a leak. The |
| lid of the sludge tub observed was not protected from a potential |
| accumulation and it had been left unattended. |
| |
| CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN EACH WAS IMPLEMENTED: |
| |
| At 0800 hours, a NCS anomalous condition was initiated. |
| |
| At 1015 hours compliance was re-established |
| |
| The NRC Resident Inspector was notified of this event. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 36970 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: TENNESSEE DIV OF RAD HEALTH |NOTIFICATION DATE: 05/04/2000|
|LICENSEE: STUDSVICK PROCESSING FACILITY, LLC |NOTIFICATION TIME: 09:45[EDT]|
| CITY: ERWIN REGION: 2 |EVENT DATE: 04/30/2000|
| COUNTY: STATE: TN |EVENT TIME: 12:00[EDT]|
|LICENSE#: R-S1001 AGREEMENT: Y |LAST UPDATE DATE: 05/04/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |ROBERT HAAG R2 |
| |JOSEPHINE PICCONE NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: DEBRA SHULTS | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| 5000 SQUARE FOOT AREA CONTAMINATED WITH AN ESTIMATED 0.49 MILLICURIES OF |
| PRIMARILY COBALT-60. |
| |
| |
| On 05/01/2000, the licensee called to report a spill of residue inside their |
| processing building. A 5000 square foot area was affected/contaminated |
| with an estimated 0.49 millicuries of mixed fission/activation products |
| (primary Co-60) when the event occurred on 04/30/00. Gross maslin smears |
| revealed 30,000 dpm with a maximum small area smear of 6,600 dpm/100 square |
| centimeter. There was no release of radioactive material to the |
| environment. There were two minor personnel contamination incidents: one |
| involving an individual's shoes and one involving an individual's hair. |
| Both were easily decontaminated and released. There was no damage to |
| equipment. Decontamination had already begun when reported. This event |
| does not pose a risk to public health and safety but is reportable under |
| 1200-2-5-141 (2)(c)1 i, ii, and iii. It required restricted access for |
| greater than 24 hours, 0.49 millicuries is greater than 5 times the lowest |
| ALI for Co-60, and access was restricted to allow isotopes with less than 24 |
| half-lives to decay. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36971 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 05/04/2000|
| UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 16:36[EDT]|
| RXTYPE: [1] W-3-LP |EVENT DATE: 05/04/2000|
+------------------------------------------------+EVENT TIME: 13:24[EDT]|
| NRC NOTIFIED BY: CASPER JERNIGAN |LAST UPDATE DATE: 05/04/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ROBERT HAAG R2 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| INADVERTENT SAFETY INJECTION ACTUATION |
| |
| "Harris Nuclear Plant was in Mode-5 with Reactor Vessel level at -12 inches |
| following Mid-Loop operations. A Safety Injection Signal was actuated when |
| Instrument Bus S-III was de-energized to return it to its normal power |
| supply. Plant procedure MST-I0604 (Time Response Test for Channel 1 |
| Pressurizer Pressure) was in progress. This procedure had channel 1 |
| Pressurizer Pressure in test. When S-III was de-energized, the Low |
| Pressurizer Pressure SI and Low Steam Generator Pressure SI Block signal |
| (P-11) were unblocked due to Pressurizer channel III being de-energized |
| concurrent with Pressurizer channel 1 in test. The plant was in Mode-5 with |
| Pressurizer Pressure and Steam Generator Pressure at approximately 0 psig. |
| Pressurizer Low Pressure SI and Low Steam Generator Pressure SI actuated the |
| SI signal after P-11 was unblocked. Preparations to perform OST 1826 "Safety |
| Injection: ESF Response Time, Train B 18 Month Interval test" were in |
| progress. This test had the BIT injection valves closed with power off, |
| which prevented ECCS discharge to the RCS. Other equipment operated as |
| required in response to the Safety Injection Signal in these plant |
| conditions. This actuation did not have any negative impact on RCS |
| temperature or inventory control. The plant is currently stable in Mode-5." |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
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|Other Nuclear Material |Event Number: 36972 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: U.S. ARMY |NOTIFICATION DATE: 05/04/2000|
|LICENSEE: U.S. ARMY |NOTIFICATION TIME: 16:54[EDT]|
| CITY: REDSTONE ARSENAL REGION: 2 |EVENT DATE: 05/04/2000|
| COUNTY: STATE: AL |EVENT TIME: [CDT]|
|LICENSE#: SNM1998 AGREEMENT: Y |LAST UPDATE DATE: 05/04/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |ROBERT HAAG R2 |
| |JOSEPHINE PICCONE NMSS |
+------------------------------------------------+NIEL DELLA GRECA R1 |
| NRC NOTIFIED BY: JERRY GRAY |BRUCE BURGESS R3 |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| SOURCE SET LOST DURING SHIPPING |
| |
| Operations for US Army Communications Electronics Command at Fort Monmouth, |
| New Jersey shipped, via FedEx, an Amersham large area alpha calibration |
| source to US Army at Redstone Arsenal, Alabama on 3/15/2000. The |
| calibration set (serial # LAAS-003) contains 3 sources (serial #'s ES-927, |
| 928 and 929) with a total of about 18 microcuries of Pu-238. On 4/18/2000, |
| Redstone Arsenal contacted US Army Communications Electronics Command in New |
| Jersey to inquire about a leak test that was due on the calibration source, |
| who in turn informed them that it had been shipped to them in March. A |
| search was conducted at Redstone Arsenal without the calibration source set |
| being found. FedEx was contacted and a search of the sort center in New |
| Jersey, to which the shipment was traced, failed to locate the shipment. |
| The US Army is reporting that the source set is missing, assumed lost or |
| stolen. |
+------------------------------------------------------------------------------+
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|Power Reactor |Event Number: 36973 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 05/04/2000|
| UNIT: [] [3] [] STATE: NY |NOTIFICATION TIME: 18:00[EDT]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 05/04/2000|
+------------------------------------------------+EVENT TIME: 14:41[EDT]|
| NRC NOTIFIED BY: RUSSELL LONG |LAST UPDATE DATE: 05/04/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |NIEL DELLA GRECA R1 |
|10 CFR SECTION: | |
|NLTR LICENSEE 24 HR REPORT | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|3 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| ABOUT 25 DEAD FISH DISCOVERED IN DISCHARGE CANAL |
| |
| "On May 4, 2000, at approximately 1441 hours, plant personnel discovered |
| dead fish in the discharge canal. There were no plant events or occurrences |
| that appear to be causally related. The fish numbered about 25, had an |
| average length of about one foot and consisted of gizzard shad, not an |
| endangered species. The water in the discharge canal is river water used for |
| cooling plant equipment in both Indian Point 2 and 3 during plant operation. |
| The fish could not have traveled through the plant to the discharge canal |
| since the river water intake has screens to prevent this type of fish |
| intrusion. |
| |
| "This event is reported, within 24 hours, pursuant to Non-radiological |
| Environmental Technical Specification 4.1 as an unusual event, a fish kill. |
| The cause is being evaluated." |
| |
| The licensee intends to notify the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36974 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 05/04/2000|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 19:02[EDT]|
| RXTYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 05/04/2000|
+------------------------------------------------+EVENT TIME: 13:18[CDT]|
| NRC NOTIFIED BY: RICHARD CALVIN |LAST UPDATE DATE: 05/04/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BRUCE BURGESS R3 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| REACTOR WATER CLEANUP SYSTEM AUTOMATICALLY ISOLATED |
| |
| The reactor water cleanup system (RWCU) isolated due to ESF signal "high |
| flow isolation signal". Originally it was determined to be an invalid |
| signal caused by a pressure pulse induced by human error. Additional |
| information indicates that it cannot be proven that the isolation was not |
| caused by system flow, therefore it has been determined that the event is |
| reportable. The system isolated as designed and has been restored. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36975 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 05/04/2000|
| UNIT: [] [] [3] STATE: IL |NOTIFICATION TIME: 22:09[EDT]|
| RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 05/04/2000|
+------------------------------------------------+EVENT TIME: 20:18[CDT]|
| NRC NOTIFIED BY: DAVID SLAGER |LAST UPDATE DATE: 05/04/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BRUCE BURGESS R3 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
| | |
|3 M/R Y 44 Power Operation |0 Hot Standby |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| DECREASING CONDENSER VACUUM REQUIRED MANUAL REACTOR SCRAM |
| |
| "During unit startup from D3F30 forced outage, condenser vacuum was reducing |
| on 2 of 3 condenser hoods and condensate demin inlet temperatures were |
| rising. The abnormal operating procedure for loss of condenser vacuum was |
| entered and actions followed to scram at 135 �F condensate temp. All |
| systems responded as designed with no abnormalities noted. Investigation |
| into cause in progress." |
| |
| All rods fully inserted following the manual reactor scram. Group 2 and 3 |
| isolations were received as expected on reduced reactor vessel level. |
| |
| The licensee intends to notify the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
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Page Last Reviewed/Updated Wednesday, March 24, 2021