Event Notification Report for September 11, 2001
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
09/10/2001 - 09/11/2001
** EVENT NUMBERS **
37999 38247 38272 38273
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|Fuel Cycle Facility |Event Number: 37999 |
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| 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: 09/10/2001|
| 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: NON EMERGENCY | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| 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 than 35.5 psia when the |
| condenser supply and return valve are both closed without a fluorinating |
| environment in the process gas system. NCSA CAS-002/011 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. |
| |
| Paducah personnel notified the NRC resident inspector. |
| |
| ***** UPDATE RECEIVED AT 1500 EDT ON 06/21/01 FROM CALVIN PITTMAN TO LEIGH |
| TROCINE ***** |
| |
| The following text is a portion of a facsimile received from Paducah |
| personnel: |
| |
| "At 1900 [CDT] on [05/16/01], the Plant Shift Superintendent (PSS) was |
| notified of a deficient Nuclear Criticality Safety Evaluation. NCSAs CAS |
| 002 and CAS 011 allow both the Recirculating Cooling Water (RCW) supply and |
| return valves to be closed when draining the R-114 condenser without a |
| fluorinating environment. The NCS evaluations rely on the RCW supply valve |
| to be closed enough to prevent the condenser from being pressurized above |
| 35.5 psia during the time the RCW return valve is closed and maintenance |
| relieves the pressure on the condenser. Based on recent discussions between |
| NCS and maintenance personnel, it was discovered that closure of the RCW |
| supply valve might not provide sufficient isolation to prevent the condenser |
| from being pressurized above 35.5 psia with the return valve closed. The |
| RCW system provides cooling water to the R-114 condenser, which removes heat |
| from the freon system. The freon is used to remove the heat of compression |
| from the process gas system. The R-114 pressure is maintained above the RCW |
| pressure to form a barrier between the process gas and the RCW cooling |
| water, thus preventing moderation from occurring should a leak in the |
| condenser occur. If the RCW pressure is allowed to rise above 35.5 psia, |
| the potential exists that the RCW pressure could exceed that of the R-114 |
| pressure. At this point, an actual condition of RCW pressure greater than |
| 35.5 psia has not been identified." |
| |
| "UPDATE [on 06/20/01] ATRC 01-3248: During the Engineering review to |
| determine permanent corrective actions, additional immediate corrective |
| actions have become necessary. It has been determined that when the |
| condenser return valve is open, condenser pressure can also be affected when |
| the return header alignment is changed (i.e., closure of RCW loop isolation |
| valves, RCW building header valves, cooling tower riser valves, etc.). |
| Controls have been implemented to ensure that changes to the RCW system do |
| not impact our ability to maintain R-114 pressure above RCW pressure." |
| |
| "SAFETY SIGNIFICANCE OF EVENTS: The controls credited for the isolation of |
| the condenser to ensure the pressure at the condenser does not exceed 35.5 |
| psia do not meet the intent of the NCSE for isolation. Therefore, the NCSE |
| analysis is deficient and double contingency is not maintained. However, |
| the probability for a criticality is unlikely due to the number of |
| conditions that must be met in order for a criticality to be possible." |
| |
| "POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO(S) OF HOW |
| CRITICALITY COULD OCCUR): In order for a criticality to be possible, the |
| following conditions must exist. With the condenser supply and return |
| valves closed, the supply or return valve must be leaking to allow the |
| condenser pressure to exceed the minimum coolant pressure of 35.5 psia. |
| With the configuration of the supply valve closed and the return valve |
| opened, the RCW return system must be changed (i.e. closure of loop |
| isolation valves, RCW building header valves, cooling tower riser valves, |
| etc.) enough that the affected condenser pressure increased greater than |
| 35.5 psia. The process gas equipment must be at a UF6 negative and contain |
| a UO2F2 deposit greater than a critical mass. The condenser must have a |
| leak of sufficient rate and duration to allow enough water to overcome the |
| down comer allowing liquid water to enter the cooler. The cooler must also |
| have a simultaneous leak, which would allow wet coolant to leak into the |
| process gas side of the equipment at a location, which would allow |
| moderation of the deposit." |
| |
| "CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.): |
| Double contingency for this scenario is established by implementing two |
| controls for moderation." |
| |
| "ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS |
| LIMIT AND % WORST CASE CRITICAL MASS): Maximum assay of 5.5 wt. % U235" |
| |
| "NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION |
| OF THE FAILURES OR DEFICIENCIES: The first leg of [the] double contingency |
| is based on isolation of the RCW condenser by closing the supply valve to |
| maintain the condenser pressure less than 35.5 psia. Based on discussions |
| with maintenance personnel, the current leak rates of the supply valve may |
| be greater than the amount assumed to ensure the condenser pressure does not |
| exceed 35.5 psia when the return valve is closed. Also, when the return |
| valve is open, the RCW return system could be changed (i.e., closure of loop |
| isolation valve, RCW building header valves, cooling tower riser valves, |
| etc.). Therefore, the intent of this control has not been met, and this leg |
| of double contingency was not maintained." |
| |
| "The second leg of [the] double contingency is based on the independent |
| verification of the isolation of the supply valve and when the return valve |
| is required to be open, verification that the return valve is open. Since |
| adequate isolation of the supply valve cannot be ensured based on |
| verification of supply valve closure or return valve open, when required, |
| the intent of this independent verification control was not met. Therefore, |
| this leg of double contingency was not maintained." |
| |
| "Since isolation of the RCW condenser with the supply valve closed and the |
| return valve closed or opened may not meet the intent of the isolation |
| requirement to maintain the condenser pressure less than 35.5 psia, these |
| controls are deficient and double contingency has not been maintained." |
| |
| "CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEMS AND WHEN EACH WAS IMPLEMENTED: |
| Until the NCSEs and NCSAs can be revised and additional controls |
| established:" |
| |
| "Condenser Return Valve Closed" |
| |
| "1. All maintenance activities related to closing the condenser return |
| valve on a system, which is at a UF6 negative, have been stopped. This does |
| not apply to systems that are not connected to the supply line or the C-310 |
| TOPS Boosters." |
| |
| "2. The coolant systems for condensers, which had the return valve closed |
| without a fluorinating environment present, will be sampled in accordance |
| with NCSA CAS-002 to verify the CFC-114 still complies with the water |
| content limits." |
| |
| "3. The return [valves] on condensers, which currently have the return |
| valve closed, fluorinating environment removed (at a UF6 negative), and is |
| connected to the supply line, will be opened." |
| |
| "RCW Building Return System (based on ATRC-01-3248)" |
| |
| "4. The plant power level will be maintained below 400 MW until NCSE |
| changes are completed and/or necessary controls are implemented or specific |
| evolutions are evaluated by NCS and approval is given." |
| |
| "5. Both building RCW return header valves to a given header will not be |
| closed." |
| |
| "6. At least 3 cooling tower risers for every large pump and 2 risers for |
| every small pump will be kept in service." |
| |
| "7. Respective building RCW bypasses will be closed before isolating an RCW |
| system loop." |
| |
| "8. For any auxiliary systems not protected by a delta P alarm (i.e., A-310 |
| Booster, A-335 Booster, C-337 B Booster) except the C-310 TOPS Booster, any |
| activity that requires verification that the condenser return valve is open |
| will also verify other valves in the return path to the applicable RCW |
| return header are also open." |
| |
| Paducah personnel notified the NRC resident inspector. The NRC operations |
| officer notified the R3DO (Bruce Jorgensen) and NMSS EO (Patricia |
| Holahan).] |
| |
| * * * UPDATE 1705EDT ON 8/21/01 FROM CALVIN PITTMAN TO S. SANDIN * * * |
| |
| The following information was provided as an update: |
| |
| "The plant has completed and approved a USQD [Unreviewed Safety Question |
| Determination] to allow the plant power level to be increased to 850 MW." |
| |
| The NRC resident inspector has been informed. Notified R3DO(Gardner) and |
| NMSS(Essig). |
| |
| * * * UPDATE 1300 9/10/2001 FRIN BEASLEY TAKEN BY STRANSKY * * * |
| |
| "NCSE 039/NCSA CAS-011 and NCSE 052/NCSA CAS-002 have been revised, |
| approved, and implemented by the plant. These analyses are no longer |
| considered deficient. The analysis incorporates additional controls |
| associated with the cascade RCW system that are necessary for double |
| contingency above a power level of 850 MW." |
| |
| The NRC resident inspector has been informed. Notified R3DO (Burgess) & NMSS |
| (Wayne Hodges) |
+------------------------------------------------------------------------------+
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|Power Reactor |Event Number: 38247 |
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| FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 08/29/2001|
| UNIT: [] [] [3] STATE: CT |NOTIFICATION TIME: 11:02[EDT]|
| RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 08/29/2001|
+------------------------------------------------+EVENT TIME: 10:04[EDT]|
| NRC NOTIFIED BY: MIKE GOBELI |LAST UPDATE DATE: 09/10/2001|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |DAVID LEW R1 |
|10 CFR SECTION: |JOHN TAPPERT NRR |
|APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION |RICHARD ROSANO/NRR IAT |
|DDDD 73.71 UNSPECIFIED PARAGRAPH |AARON DANIS/NMSS IAT |
| |GREG SMITH/REGION 1 IAT |
| |NADER MAMISH IRO |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
| | |
|3 N Y 100 Power Operation |100 Power Operation |
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EVENT TEXT
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| OFFSITE NOTIFICATION REGARDING A 30-GALLON DIESEL OIL SPILL FROM A FREIGHT |
| TRAIN WHICH DERAILED AND BREACHED THE PROTECTED AREA BOUNDARY |
| |
| A freight train derailed and breached the protected area boundary. There |
| were no personnel injuries as a result of this event. However, 30 gallons |
| of diesel oil spilled from the train. The oil was contained by trap rocks |
| and did not reach receiving waters. |
| |
| Security personnel have been posted as a result of the protected area |
| boundary breach, and fire protection personnel are currently on scene |
| cleaning up the diesel oil spill. The licensee is in the process of |
| notifying the Connecticut Department of Environmental Protection of the oil |
| spill. The licensee also requested that local police investigate the cause |
| of the train derailment. |
| |
| In addition to the initial 4-hour event report for the offsite notification, |
| the licensee plans to call back with an update to include the reporting |
| criterion for the breach in the protected area boundary. |
| |
| The licensee notified the NRC resident inspector and plans to notify |
| applicable state and local officials. |
| |
| ***** UPDATE FROM MIKE GOBELI TO LEIGH TROCINE AT 1115 ON 08/29/01 ***** |
| |
| The licensee provided this update to include an additional 1-hour security |
| reporting criterion to the initial 4-hour event report for the offsite |
| notification. The licensee determined that this event was also reportable |
| in accordance with 10 CFR 73.71(b)(1), Appendix G, I(1)(c), for a |
| degradation or discovered vulnerability in a safeguards system that could |
| allow unauthorized or undetected access to a protected area, controlled |
| access area, or vital area. |
| |
| The NRC operations officer notified the R1DO (David Lew), NRR EO (John |
| Tappert), IRO (Nader Mamish), NRR IAT (Richard Rosano), NMSS IAT (Aaron |
| Danis), Region 1 IAT (Greg Smith), Region 1 (Curtis Cowgill), Headquarters |
| OPA (Beth Hayden), and Region 1 OPA (Neil Sheehan). |
| |
| * * * PARTIAL RETRACTION 1350 9/10/2001 FROM SMITH TAKEN BY STRANSKY * * * |
| |
| The licensee has determined that this incident is not reportable pursuant to |
| 10 CFR 73.71 (b)(1) as a one hour report. The NRC resident inspector has |
| been informed. Notified R1DO (Barr). |
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|Other Nuclear Material |Event Number: 38272 |
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| REP ORG: U.S. DEPARTMENT OF AGRICULTURE |NOTIFICATION DATE: 09/10/2001|
|LICENSEE: U.S. DEPARTMENT OF AGRICULTURE |NOTIFICATION TIME: 16:48[EDT]|
| CITY: PENDLETON REGION: 4 |EVENT DATE: 09/06/2001|
| COUNTY: STATE: OR |EVENT TIME: 11:00[PDT]|
|LICENSE#: 19-00915-03 AGREEMENT: Y |LAST UPDATE DATE: 09/10/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MARK SHAFFER R4 |
| |M. WAYNE HODGES NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JENSEN | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NONR OTHER UNSPEC REQMNT | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| STUCK SOURCE |
| |
| The licensee reported that a 15 mCi Am-241 source, used for soil moisture |
| measurements, had become stuck within a 6 foot length of tubing. Attempts to |
| retrieve it using the attached cable were unsuccessful. The source was |
| retrieved by digging up the tubing, cutting off the bottom portion and |
| pushing the source back up through the tube. The source was returned to its |
| shipping container. The dosimetry of the individual who performed the |
| retrieval has been sent to the vendor for analysis. |
| |
| An inspector from NRC Region I is currently performing a site visit to the |
| USDA office in Beltsville, MD, from where this report originated. |
+------------------------------------------------------------------------------+
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|Power Reactor |Event Number: 38273 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 09/10/2001|
| UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 23:13[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 09/07/2001|
+------------------------------------------------+EVENT TIME: 17:54[CDT]|
| NRC NOTIFIED BY: WILLIAM GREEN |LAST UPDATE DATE: 09/10/2001|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MARK SHAFFER R4 |
|10 CFR SECTION: | |
|AIND 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 |62 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOSS OF OFFSITE POWER SOURCES DUE TO LIGHTNING |
| |
| "On 9/7/01 at 1750 CDT the Startup Transformer was de-energized due to a |
| lightning strike on the transmission system. This deenergized one of the two |
| off-site circuits. This trip resulted in the trip of 'A' Recirculation M/G |
| set and subsequent single loop operations. Shortly after this at 1754 CDT |
| the Emergency Transformer was declared inoperable due to degraded voltage |
| and the plant entered the Limiting Condition for Operations for loss of both |
| off-site power circuits. Both Emergency Diesels remained available and the |
| unit remained on line. All plant equipment responded as expected. At 1932 |
| CDT the Emergency Transformer was returned to operable status. Two loop |
| operations were restored at 0521 CDT on 9/8/01. The Startup Transformer was |
| restored to operable at 1045 CDT on 9/8/01. Full power operation was |
| restored at 2100 CDT on 9/8/01. The NRC Senior Resident Inspector has been |
| notified. This event is reportable in accordance with NUREG 1022 Rev. 2 and |
| 10 CFR 50.72(b)(3)(v). Staff review of the event and NUREG 1022 Rev. 2 on |
| 9/10/01 identified the need to make a report under 10 CFR 50.72." |
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