Event Notification Report for June 19, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
06/16/2000 - 06/19/2000
** EVENT NUMBERS **
36931 37089 37090 37091 37092 37093
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|Other Nuclear Material |Event Number: 36931 |
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| REP ORG: DRESSER EQUIPMENT GROUP |NOTIFICATION DATE: 04/26/2000|
|LICENSEE: DRESSER VALVE DIVISION |NOTIFICATION TIME: 14:40[EDT]|
| CITY: BURLINGTON REGION: |EVENT DATE: 04/25/2000|
| COUNTY: STATE: |EVENT TIME: 14:00[EST]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 06/16/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |PAUL FREDRICKSON R2 |
| |VERN HODGE NRR |
+------------------------------------------------+ |
| NRC NOTIFIED BY: L. H. WINDFIELD | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| DRESSER VALVES NAME PLATE AND CODE PLATE HAVE INCORRECT SET PRESSURE |
| INFORMATION AT HATCH. |
| |
| PART 21 FROM DRESSER EQUIPMENT GROUP, DRESSER VALVE DIVISION, BURLINGTON, |
| ONTARIO, CANADA. |
| |
| |
| The following noncompliance has been determined to be reportable within the |
| requirements of 10CFR Part 21. The noncompliance involves seven safety |
| relief valves that were purchased for the Hatch Electric Generating Plant by |
| the Georgia Power Company through its agent, Southern Nuclear Operating |
| Company, Inc. The valves are for use in a safely related service. |
| |
| The valves were purchased on Southern Nuclear Operating Company purchase |
| order #6040304 and produced on Dresser Valve Division sales order #119588N |
| and are further described as follows: |
| |
| Contract Item 002 Quantity 7 Part Number |
| 3990C-1-S4-MS-33-SC-SC-GS produced ASME Section |
| III Class 2 valves with the following serial numbers and |
| required set pressures: |
| |
| SERIAL NO. SET PRESSURE REQD |
| B119588-2-1 250 psig |
| B119588-2-2 250 psig |
| B119588-2-3 250 psig |
| B119588-2-4 250 psig |
| B119588-2-5 250 psig |
| |
| B119588-3-1 170 psig |
| B119588-3-2 170 psig |
| |
| NONCOMPLIANCE SITUATION AND BRIEF HISTORY |
| |
| On Tuesday April 25, 2000, the customer was performing receiving inspection |
| and noticed that the set pressure information on the Code Plates and the |
| Name Plates do not conform to the specification requirements or the history |
| docket testing information. The customer called the Quality Assurance |
| Department of Dresser Valve Division to discuss the finding. It appears |
| that the set pressure information on the plates has been interchanged. |
| |
| A summary of the information is as follows: |
| |
| SERIAL NO SET PRESSURE REQD CODE |
| PLATE NAME PLATE |
| B119588-2-1 250 psig |
| 170 psig 170 psig |
| B119588-2-2 250 psig |
| 170 psig 170 psig |
| B119588-2-3 250 psig |
| 170 psig 170 psig |
| B119588-2-4 250 psig |
| 170 psig 170 psig |
| B119588-2-5 250 psig |
| 170 psig 170 psig |
| |
| B119588-3-1 170 psig |
| 250 psig 250 psig |
| B119588-3-2 170 psig |
| 250 psig 250 psig |
| |
| Our investigation has begun and we have conducted a full review of our |
| records to confirm that the valves are set correctly to the contract |
| requirements. A notice has been given to the customer to return the |
| affected valves to Dresser Valve Division for confirmation of the plate |
| information and correction if required. The ANI will be involved in the |
| investigation and corrective actions as required. |
| |
| We have conducted a full review of our records and confirmed that these are |
| the only valves involved. A full review of our procedures regarding plate |
| preparation, inspection and installation will be completed. Corrective |
| actions will be initiated to address the internal issues, if warranted, and |
| details will be provided in our closure reports at the completion of our |
| investigation into the cause of this situation. |
| |
| * * * UPDATE 1415EDT ON 6/16/00 FROM WINFIELD TO S. SANDIN * * * |
| |
| The following information was received via fax: |
| |
| "This is a summary of the event dealing with the cause and the corrective |
| actions implemented to prevent recurrence. |
| |
| "The customer returned the valves and the set pressures were confirmed to be |
| correct to the General Arrangement Drawing (GA Dwg) requirements. New |
| nameplates were produced, verified to the approved GA Dwg., and installed on |
| the valves as witnessed by the ANI. |
| |
| "It was confirmed that the incorrect nameplate information was derived from |
| internal work order data. The approved GA Dwg was not used as required. |
| |
| "Revised internal operating procedures are being implemented to ensure that |
| engineering personnel complete nameplate forms, from data appearing only on |
| the approved GA Dwg. Only the approved GA Dwg will be used to verify the |
| correctness of the data." |
| |
| Notified R2DO(Bernhard) and NRR(Hodge). |
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|Power Reactor |Event Number: 37089 |
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| FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 06/16/2000|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 13:13[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 06/16/2000|
+------------------------------------------------+EVENT TIME: 11:20[CDT]|
| NRC NOTIFIED BY: LEROY KLINGER |LAST UPDATE DATE: 06/16/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DAVID HILLS R3 |
|10 CFR SECTION: | |
|DDDD 73.71 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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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| SECURITY REPORT INVOLVING VIOLATION OF PHYSICAL SECURITY PLAN |
| |
| MINIMUM SECURITY PERSONNEL STAFFING REQUIREMENTS NOT MET. IMMEDIATE |
| COMPENSATORY MEASURES TAKEN UPON DISCOVERY. THE LICENSEE WILL INFORM THE |
| NRC RESIDENT INSPECTOR. CONTACT THE HEADQUARTERS OPERATIONS CENTER FOR |
| ADDITIONAL DETAILS. |
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|General Information or Other |Event Number: 37090 |
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| REP ORG: YALE UNIVERSITY |NOTIFICATION DATE: 06/16/2000|
|LICENSEE: YALE UNIVERSITY |NOTIFICATION TIME: 16:01[EDT]|
| CITY: NEW HAVEN REGION: 1 |EVENT DATE: 06/15/2000|
| COUNTY: STATE: CT |EVENT TIME: 16:58[EDT]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 06/16/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MOHAMED SHANBAKY R1 |
| |SCOTT MOORE NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: TAMMY STEMEN | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NINF INFORMATION ONLY | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| POTENTIAL PERSONNEL OVEREXPOSURE |
| |
| A technician employed by Yale University in the Environmental Services Group |
| expressed a concern regarding ALARA during an inventory of both byproduct |
| and accelerator produced radioactive material. He noticed a vial containing |
| Na-22 (accelerator product) in the millicurie source range sitting on its |
| side in the "cave." The "cave" is a shielded storage location for both |
| waste and byproduct material. The technician's film was sent for an |
| emergency read. The results were received at 1658EDT on 6/15/00 and |
| indicated a whole body exposure of 6930 mRem. A thyroid scan and bioassays |
| were performed with negative results. Contamination surveys were performed, |
| again with negative results. The technician had taken his film badge with |
| him to Texas during the period of time the badge was used (May). The |
| University RSO has submitted the other technicians (between 30-35) film |
| badges for reading as part of the investigation. The University has |
| contacted the state of CT. |
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|Power Reactor |Event Number: 37091 |
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| FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 06/16/2000|
| UNIT: [] [2] [3] STATE: CA |NOTIFICATION TIME: 17:28[EDT]|
| RXTYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 06/11/2000|
+------------------------------------------------+EVENT TIME: 13:13[PDT]|
| NRC NOTIFIED BY: ANDY BOLYEN |LAST UPDATE DATE: 06/16/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: |LINDA SMITH R4 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
|3 N Y 100 Power Operation |100 Power Operation |
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EVENT TEXT
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| ACTUATION OF THE CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM DURING |
| RADIOGRAPHY |
| |
| "On June 11, 2000, at approximately 1313 PDT, SCE was performing radiography |
| on the 56' elevation of the Unit 2 Turbine Building when the Train B |
| radiation monitor (2/3RT7824) for the Control Room Isolation Signal (CRIS) |
| actuated. At approximately 1317 PDT, the Train A CRIS radiation monitor |
| (2/3RT7825) actuated. The Train A and B Control Room Emergency Air Cleanup |
| System (CREACUS) actuated as expected. |
| |
| "SCE was performing the radiography on the Unit 2 Main Steam Throttle Stop |
| Valves with an 82 Ci iridium-192 source. The unshielded beam emanating from |
| the collimated radiographic source was directed away from the CRIS radiation |
| monitors, which are about 150 feet away. The radiography was scheduled to |
| last approximately 3.5 minutes. |
| |
| "Because the actuation of the CRIS radiation monitors did not occur as a |
| result of airborne contamination or actual plant conditions or parameters |
| satisfying the requirements for initiation of the safety function of the |
| system, SCE did not consider this to be a valid actuation requiring a |
| report. However, if a 'valid signal' were to be defined as output from a |
| radiation monitor detecting any radiation source, then this event would be |
| reportable. Because questions have been raised regarding which definition of |
| 'valid signal' is applicable in this instance, SCE is conservatively |
| reporting this condition in accordance with 10CFR50.72(b2)(ii). |
| |
| "The trend data for the CRIS radiation monitors showed no readings above the |
| setpoint of 1E-5 �Ci/cc. Because no actual airborne radioactive |
| contamination was present, this event has no safety significance. |
| |
| "At the time of this occurrence, both Units 2 and 3 were operating at about |
| 100 percent power; Unit 1 remains permanently defueled. SCE will notify the |
| NRC resident inspectors about this notification and will provide them with a |
| copy of this report." |
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|General Information or Other |Event Number: 37092 |
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| REP ORG: UTAH DIVISION OF RADIATION CONTROL |NOTIFICATION DATE: 06/16/2000|
|LICENSEE: UTAH STATE UNIVERSITY |NOTIFICATION TIME: 18:07[EDT]|
| CITY: LOGAN REGION: 4 |EVENT DATE: 06/05/2000|
| COUNTY: STATE: UT |EVENT TIME: 15:30[MDT]|
|LICENSE#: UT0300159 AGREEMENT: Y |LAST UPDATE DATE: 06/16/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |LINDA SMITH R4 |
| |LINDA HOWELL R4 |
+------------------------------------------------+LARRY CAMPER NMSS |
| NRC NOTIFIED BY: JULIE FELICE | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| AGREEMENT STATE REPORT INVOLVING A LEAKING NI-63 SOURCE |
| |
| While performing a routine wipe test on 3/9/2000 of a Varian Gas |
| Chromatograph Detector Cell at the Utah State University in Logan, UT, |
| leakage from the 8 mCi Ni-63 source was detected. Accelerated leakage tests |
| were ordered to monitor the source. On 6/5/2000 the test results indicated |
| 0.02 �Ci which exceeded the reportability criteria of >0.005 �Ci. The room |
| and surrounding area was surveyed, with the results indicating no |
| contamination. The source was removed from service and will be returned to |
| the vendor for repair or replacement. The instrument is model # |
| 02001972-00, serial # A8615. Utah has assigned incident # UT-00-0003. |
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|Power Reactor |Event Number: 37093 |
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| FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 06/17/2000|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 13:00[EDT]|
| RXTYPE: [1] GE-3 |EVENT DATE: 06/17/2000|
+------------------------------------------------+EVENT TIME: 11:15[CDT]|
| NRC NOTIFIED BY: KEVIN PEDERSON |LAST UPDATE DATE: 06/17/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DAVID HILLS R3 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| UNIT ENTERED A TECH SPEC REQUIRED SHUTDOWN AFTER DECLARING BOTH CONTAINMENT |
| SPRAY TRAINS INOPERABLE |
| |
| "BOTH LOOPS OF RHRSW (RESIDUAL HEAT REMOVAL SERVICE WATER) WERE DECLARED |
| INOPERABLE DURING THE FILL PROCESS FOLLOWING MAINTENANCE ON '14' RHRSW PUMP |
| MOTOR. PER TECH 3.5.C.3, BOTH LOOPS OF CONTAINMENT SPRAY/COOLING WERE |
| DECLARED INOPERABLE REQUIRING A REACTOR SHUTDOWN AND TEMPERATURE LESS THAN |
| 212�F IN 24 HOURS. INITIAL INVESTIGATION ASSUMES THE DISCHARGE CHECK VALVE |
| ON THE '14 RHRSW PUMP DID NOT SEAT. AT THIS TIME THE 'A' LOOP OF RHRSW HAS |
| BEEN RESTORED AND THE PLANT IS IN A 7 DAY LCO." |
| |
| THE UNIT ENTERED AND EXITED THE SHUTDOWN ACTION STATEMENT AT 1115CDT AND |
| 1130CDT, RESPECTIVELY WITH NO POWER REDUCTION OCCURRING. |
| |
| THE LICENSEE WILL INFORM STATE/LOCAL AGENCIES AND THE NRC RESIDENT |
| INSPECTOR. |
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