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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).                                      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|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  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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.                                                          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37090       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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.                                                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37091       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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  |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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 ÁCi/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."                                                        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|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                                   
+------------------------------------------------------------------------------+
| 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 ÁCi which exceeded the reportability criteria of >0.005 ÁCi.  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.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37093       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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.                                                                   |
+------------------------------------------------------------------------------+