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Event Notification Report for January 28, 2002

                         
                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           01/25/2002 - 01/28/2002

                              ** EVENT NUMBERS **

38649  38650  38651  38652  38653  38654  

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|Power Reactor                                    |Event Number:   38649       |
+------------------------------------------------------------------------------+
                         
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| FACILITY: SEABROOK                 REGION:  1  |NOTIFICATION DATE: 01/25/2002|
|    UNIT:  [1] [] []                 STATE:  NH |NOTIFICATION TIME: 13:06[EST]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        01/25/2002|
+------------------------------------------------+EVENT TIME:        08:54[EST]|
| NRC NOTIFIED BY:  DAMON RITTER                 |LAST UPDATE DATE:  01/25/2002|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |PETE ESELGROTH       R1      |
|10 CFR SECTION:                                 |                             |
|HFIT 26.73               FITNESS FOR DUTY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| FITNESS FOR DUTY REPORT                                                      |
|                                                                              |
| A non-licensed supervisor tested above the limit for blood alcohol content   |
| during a random test. The individual's site access has been suspended and    |
| the licensee is conducting a review of the individual's recent work. The NRC |
| resident inspector has been informed of this event by the licensee.          |
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|Power Reactor                                    |Event Number:   38650       |
+------------------------------------------------------------------------------+
                         
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| FACILITY: PILGRIM                  REGION:  1  |NOTIFICATION DATE: 01/25/2002|
|    UNIT:  [1] [] []                 STATE:  MA |NOTIFICATION TIME: 15:36[EST]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        12/28/2001|
+------------------------------------------------+EVENT TIME:        17:01[EST]|
| NRC NOTIFIED BY:  ERIC OLSON                   |LAST UPDATE DATE:  01/25/2002|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |PETE ESELGROTH       R1      |
|10 CFR SECTION:                                 |                             |
|AINV 50.73(a)(1)         INVALID SPECIF SYSTEM A|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| 60-DAY OPTIONAL REPORT PURSUANT TO 10CFR50.73(a)(1)                          |
|                                                                              |
| "On 12/28/01, the plant was in a cold shutdown condition with the RHR system |
| in the shutdown cooling mode. The reactor head vent valves were open.        |
|                                                                              |
| "At 1701 hours a reactor water level indication spike (notching) occurred on |
| the 'B' narrow range reactor water level instrumentation (e.g. instrument    |
| rack C-2206). The event occurred when Reactor Recirculation Pump 'B' was     |
| started. This resulted in Reactor Pressure Vessel pressure lowering due to   |
| condensing of vapor in the Reactor Vessel. The spiking was due to gasses     |
| coming out of solution in the reference leg associated with the 'B' narrow   |
| range instruments. The specific source of the gas is still under             |
| investigation. No spike was noted on the 'A' narrow range reactor water      |
| level instrumentation (e.g. instrument rack C-2205). The Group I isolation   |
| resulted in the closure of the Reactor Water Sample valves (AQ-44 and        |
| AQ-45). The Main Steam Isolation Valves (MSIV's) were already closed due to  |
| plant conditions.                                                            |
|                                                                              |
| "The Group I isolation was the result of a false high water level signal(s)  |
| from analog trip system trip units LS-263-58A-2 (to PCIS Channel A2) and     |
| LS-263-58B-2 (to PCIS Channel B2) while the reactor mode switch was in the   |
| REFUEL position (not RUN). A Group I isolation is designed to occur if a     |
| high water level condition occurs when the reactor mode switch is not in the |
| RUN position. These trip units receive signals from reactor water level      |
| transmitters LT-263-58A (instrument rack 2206A) and LT-263-58B (instrument   |
| rack 2206A) that are associated with condensing chamber 12B.                 |
|                                                                              |
| "The Group I isolation signal was not valid because a reactor water level    |
| increase of about 20" did not actually occur. Thus, even though the Group I  |
| isolation signal was not planned, the isolation signal was invalid."         |
|                                                                              |
| The NRC resident inspector has been informed of this report by the licensee. |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   38651       |
+------------------------------------------------------------------------------+
                         
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  AUTOMATIC VALVE                      |NOTIFICATION DATE: 01/25/2002|
|LICENSEE:  AUTOMATIC VALVE                      |NOTIFICATION TIME: 16:25[EST]|
|    CITY:  NOVI                     REGION:  3  |EVENT DATE:        01/25/2002|
|  COUNTY:                            STATE:  MI |EVENT TIME:             [EST]|
|LICENSE#:                        AGREEMENT:  N  |LAST UPDATE DATE:  01/25/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |PETE ESELGROTH       R1      |
|                                                |VERN HODGE           NRR     |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  KEVIN ARMSTRONG (fax)        |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PART 21 REPORT                                                               |
|                                                                              |
| "On 11-14-2001 [an employee] of Exelon Power Labs called and reported that   |
| (2) U0203FBBR-AA valves had been sent to their lab from Exelon - Limerick    |
| for evaluation with the complaint that the valves were leaking in the        |
| energized position. The valve is being used in the normally closed mode at   |
| an inlet pressure of 74 psig. Further, according to [the employee], there    |
| are additional U0203FBBR-AA valves at Limerick that are exhibiting the same  |
| problem.                                                                     |
|                                                                              |
| "On 11-29-2001 one valve was returned to Automatic Valve for further         |
| evaluation. At inlet pressures of 74 & 125 PSIG it was determined that the   |
| valve did not reset after the solenoid was de-energized. It did not reset    |
| until the inlet pressure was reduced to approximately 40 psig respectively.  |
|                                                                              |
| "When tested in the normally open mode - pressure to port 1 [...], there was |
| leakage at exhaust port 3 when the solenoid was energized but the valve      |
| immediately reset at its maximum rated inlet pressure of 125 psig when the   |
| solenoid was de-energized.                                                   |
|                                                                              |
| "When the valve was disassembled a permanent set in the rubber in the top    |
| plunger seal was found that conformed to the shape of the top seat in the    |
| solenoid plunger guide. This deformation is normal and is not a concern.     |
|                                                                              |
| "The plunger was then dissected for additional analysis. It was determined   |
| that the top seat was 0.020" below the top surface of the plunger or 0.007"  |
| below the maximum design standard of 0.013".                                 |
|                                                                              |
| "With the top seat 0.020 below the top surface of the plunger, the top seal  |
| was touching the top orifice but was not compressing the internal spring and |
| hence not creating a good seal. Consequently, there was severe leakage out   |
| of exhaust port 3 which is 0.125 in diameter. This severe leakage created a  |
| pressure differential across the top of the plunger, and thus a force        |
| tending to hold the plunger in place. This force could not be overcome by    |
| the external spring until the inlet pressure was reduced to approximately 40 |
| psig.                                                                        |
|                                                                              |
| "It was observed that all parts of the dissected plunger were present and in |
| their proper location. Further, it was noted that the tested leak rates and  |
| performance characteristics of the valve prior to the plunger being          |
| dissected did not match field reports from Exelon. Consequently, Exelon was  |
| contacted and additional samples were requested.                             |
|                                                                              |
| "On January 3, 2002 a second U0203FBBR-AA valve was returned to Automatic    |
| direct from Exelon - Limerick by [...]. This valve exhibited the same        |
| operational characteristics in the normally closed mode as did the valve     |
| returned on November 29, 2001. That is, it leaked excessively when           |
| energized. And, as with the previous valve examined by Automatic Valve, the  |
| inlet pressure at port 1 had to be reduced to approximately 54 psig after    |
| the solenoid was de-energized before the valve returned to its normally      |
| closed position.                                                             |
|                                                                              |
| "A second test was run on the valve returned on January 3, 2002. Previously  |
| both returned valves were tested 'cold.' That is, they had been at room      |
| temperature for a number of hours or days. When tested, pressurized air was  |
| plumbed to port 1 and the solenoid was energized only long enough to confirm |
| that there was leakage out of port 3. Then the solenoid was de-energized and |
| the inlet pressure reduced to a value that the plunger would return to its   |
| normally closed position. With the second valve, the solenoid was left       |
| energized with 125 psig of air to port 1.  After a period of approximately   |
| 60 minutes, the leak at port 3 greatly diminished and, when the solenoid was |
| de-energized, the valve immediately returned to its closed position. This    |
| test was repeated three (3) times with the same results.                     |
|                                                                              |
| "In summary, evaluation of the (2) valves resulted in the following symptoms |
| and concerns:                                                                |
|                                                                              |
| "1.   A faulty valve will leak out of port 3 when the valve is used in its   |
| normally closed mode [...] or leak out of port 1 when the valve is used in   |
| its normally open mode [...]                                                 |
| "2.   There is no concern that U0203FBBR-** valves used in the normally open |
| mode (pressure at port 3) will return to their de-actuated position (port 3  |
| open to port 2 and port 1 blocked) when the solenoid is do-energized. In     |
| this mode both the internal spring, the external spring, and inlet pressure  |
| at port 1 act to return the plunger to its normal do-actuated position.      |
| "3.  There does not seem to be a concern, based on field experience, that    |
| U0203FBBR-** valves used in the normally closed mode (pressure at port 1)    |
| will return to their de-actuated position (port 2 open to port 3 and port 1  |
| blocked) when the solenoid is de-energized provided the solenoid has been    |
| energized for an extended period of time. Test on the valve returned on      |
| January 3rd indicate that this period of time is approximately 15 minutes at |
| 80 psig inlet pressure and approximately 60 minutes at 125 psig. However,    |
| the impact of further degradation of the shell relative to the seal, when    |
| the valve has been energized over an extended period of time is unknown.     |
| "4.   There would not seem to be a concern in applications where the         |
| U0203FBBR-** valve is used in the normally closed mode (air at port 1) and   |
| the valve is normally de-energized provided that, when energized, it is not  |
| energized for a total period of time exceeding 6 months.                     |
| "5.   There is a concern that U0203FBBR-** valves used in the normally       |
| closed mode will not return to their de-actuated position if the valve has   |
| been in its de-energized position for a sufficient amount of time for the    |
| valve and the internal top seal to cool down. If the valve is energized then |
| is de-energized, within a period of approximately 60 minutes with 125 psig   |
| at port 1, or 15 minutes with 80 psig at port 1 there is a high probability  |
| that the valve will not return to its de-energized condition."               |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   38652       |
+------------------------------------------------------------------------------+
                         
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE:
01/25/2002|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 18:05[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        01/25/2002|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        12:00[EST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  01/25/2002|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |SONIA BURGESS        R3      |
|  DOCKET:  0707002                              |SUSAN FRANT          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JIM McCLEERY                 |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 24-HOUR NRC BULLETIN 91-01 REPORT                                            |
|                                                                              |
| "The Plant Shift Superintendent (PSS) was notified of an employee entering   |
| an inadvertent container area with a camera inside a plastic bag. During an  |
| investigation requiring pictures, the camera was removed from the plastic    |
| bag. When the employee was taking pictures the plastic bag was left          |
| unattended. This is a violation of NCSA-705076.A03 control #3 and #5. #3     |
| When unattended, all potential inadvertent containers shall be modified to   |
| prevent an unsafe accumulation in the container. #5 If flexible material is  |
| utilized, it shall be configured or secured such that it cannot be deformed  |
| into an inadvertent container with an unsafe accumulation potential.         |
|                                                                              |
| "The plastic bag was removed from the area.                                  |
|                                                                              |
| "SAFETY SIGNIFICANCE OF EVENTS:                                              |
|                                                                              |
| "LOW, There was no leak of uranium bearing material in the vicinity of the   |
| unattended plastic bag. The uranium recovery system was not in operation     |
| however solution was in the system.                                          |
|                                                                              |
| "POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO[S] OF HOW           |
| CRITICALITY COULD OCCUR):                                                    |
|                                                                              |
| "The recovery system would have to be in operation bearing solution with an  |
| unknown or high quantity of uranium. A leak from the system would occur such |
| that an unsafe amount of liquid would spray into the plastic bag. The liquid |
| would then have to collect 2.5 liters and deform the plastic bag to a depth  |
| of greater then 1.5 inches and an unsafe geometry.                           |
|                                                                              |
| "CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY. CONCENTRATION,
ETC.):    |
|                                                                              |
| "Volume 2.5 liters or Geometry 1.5 inches in depth or 4 inches in diameter   |
|                                                                              |
| "ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE
PROCESS    |
| LIMIT AND % WORST CASE OF CRITICAL MASS):                                    |
|                                                                              |
| "No uranium bearing material was involved in this event                      |
|                                                                              |
| "NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND
DESCRIPTION  |
| OF THE FAILURES OR DEFICIENCIES:                                             |
|                                                                              |
| "An unattended plastic bag in an inadvertent container area was not          |
| configured or secured such that it could not be filled or deformed into an   |
| inadvertent container with an unsafe accumulation potential.                 |
|                                                                              |
| "CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN EACH WAS
IMPLEMENTED:  |
|                                                                              |
| "The plastic bag was removed from the area."                                 |
|                                                                              |
| The NRC resident inspector has been informed.                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   38653       |
+------------------------------------------------------------------------------+
                         
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  TEXAS DEPARTMENT OF HEALTH           |NOTIFICATION DATE: 01/25/2002|
|LICENSEE:  QUALITY INDUSTRIAL X-RAY, INC.       |NOTIFICATION TIME: 18:15[EST]|
|    CITY:  SEAGRAVES                REGION:  4  |EVENT DATE:        11/07/2001|
|  COUNTY:                            STATE:  TX |EVENT TIME:             [CST]|
|LICENSE#:  L04079                AGREEMENT:  Y  |LAST UPDATE DATE:  01/25/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |GREG PICK            R4      |
|                                                |SUSAN FRANT          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  HELEN WATKINS (fax)          |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT                                                       |
|                                                                              |
| "A truck caught fire and burned. A S.P.E.C. camera, serial # 98, source      |
| serial # HS1210 containing Ir-192 was on board. The source remained intact   |
| and was not leaking. The device and source were returned to the              |
| manufacturer.                                                                |
|                                                                              |
| "We have no additional information. We have contacted the Licensee to obtain |
| more details."                                                               |
|                                                                              |
| Texas Incident No.:  I-7848                                                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38654       |
+------------------------------------------------------------------------------+
                         
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALVERT CLIFFS           REGION:  1  |NOTIFICATION DATE: 01/26/2002|
|    UNIT:  [] [2] []                 STATE:  MD |NOTIFICATION TIME: 18:03[EST]|
|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        01/26/2002|
+------------------------------------------------+EVENT TIME:        21:00[EST]|
| NRC NOTIFIED BY:  DAVE FRIED                   |LAST UPDATE DATE:  01/27/2002|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |PETE ESELGROTH       R1      |
|10 CFR SECTION:                                 |                             |
|ASHU 50.72(b)(2)(i)      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  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PLANT SHUTDOWN REQUIRED BY TECHNICAL SPECIFICATIONS                          |
|                                                                              |
| Unit 2 will be shut down in accordance with plant Technical Specifications   |
| because the 2A EDG has been declared inoperable due to worn engine drive     |
| gears and repairs cannot be completed within the 72 hour TS LCO time. The    |
| worn gears were discovered during a routine maintenance inspection.          |
|                                                                              |
| The licensee will commence the shutdown at 2100 EST. The licensee will       |
| inform the NRC resident inspector of this shutdown.                          |
|                                                                              |
| * * * UPDATE 0120EST ON 1/27/02 FROM DAVE LYNCH TO S. SANDIN * * *           |
|                                                                              |
| An NOED (Notice of Enforcement Discretion) conference call was held          |
| following which Unit 2 was granted a six day extension until shutdown is     |
| required, i.e., 0300EST on 2/2/02.                                           |
+------------------------------------------------------------------------------+